ML20056D406

Exam Rept 50-116/OL-93-01 on 930623.Exam Results:All Three Candidates Passed Their Respective Portion of Exams & Issued Appropriate License

ML20056D406
Person / Time
Site:	University of Iowa
Issue date:	07/08/1993
From:	Caldwell J, Isaac P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056D295	List: ML20056D294 ML20056D406
References
50-116-OL-93-01, 50-116-OL-93-1, NUDOCS 9308130173
Download: ML20056D406 (43)

Text

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.f Iowa State University Docket No. 50-116 CC:

Mayor Larry Curtis City Hall 515 Clark Avenue Ames, Iowa 50010 Director, Office for Planning and Programming 523 East 12th Street Des Moines, Iowa 50319

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PDR ADOCK 0500 6 i  :

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i ENCLOSURE I 'i U. S. NUCLEAR REGULATORY COMMISSION  :

OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-116/0L-93-01 FACILITY DOCKET NO.: 50-116 FACILITY LICENSE NO.: R-59 l FACILITY: Iowa State University EXAMINATION DATES: June 23, 1993 EXAMINER: Patrick I aac, Chief Examiner SUBMITTED BY: ,t[ ~ 6-80'f8 '

Patri : Isatt/JE f Examiner Date APPROVED BY: ,, ), 7 73 Janies' L. C~alpdelf, C)flef Date Non-Power R(act6r Section Operator Licensing Branch Division of Reactor Controls and Human Factors -

Office of Nuclear Reactor Regulation

SUMMARY

A retake of section A of the written examination was administered to one Senior Reactor Operator (SROI) candidate. A retake of section C of the- '

I written examination was administered to one Reactor Operator (RO) candidate.

A retake of the operating test was administered to another RO candidate. _ All  !

Three applicants passed their respective portion of the examinations and have been issued the appropriate license.

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i REPORT DETAILS  ;

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1. Examiners:

Patrick Isaac, Chief Examiner i

2. Results:  ;

i R0 SR0 - Total (Pass / Fail) (Pass / Fail) (Pass / Fail) 'i

i NRC Grading: 2/0 1/0 3/0  ;

3. Written Examination: a Section A of the written examination was administered to one Senior i Reactor Operator candidate. Section C was administered to.one Reactor.

Operator candidate. A copy.of the master "as given" examinations with  !

answer key was given to the Reactor Manager for his formal review. ,

At the conclusion of the examination, the Reactor Manager expressed in .'

writing that he had no. comments concerning the written examinations.  !

Both candidates passed their respective portion of the examination. .

4. Operating Tests:

j Operating tests were somicistered to one Reactor Operator candidate.  !

There were no _ generic defi:iercies identified by the examiner. .

The candidate passed the 9pr. rating tests.

5. Exit Meeting:  ;

An exit meeting was held, on June 23, 1993, between Mr. John Adams, Reactor Manager, and Mr. Patrick Isaac. Mr. Adams commented on what he-thought was an excellently prepared examination. There were no generic concerns raised by the examiner.

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NRC Official Use Only - ENCLOSURE 2 1

Nuclear Regulatory Commission Operator Licensing Examination 7

This document is removed from Official Use Only category on date of examination.  ;

i NRC Official Use Only i

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I o r U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION ,

FACILITY: IOWA STATE UNIVERSITY REACTOR TYPE: UTR-10 DATE ADMINISTERED: 1993/06/21

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REGION: 1 CANDIDATE:

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1NSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheet to  :

the examination. Each question is worth one (I) point. A 70% is required to pass the )

examination. The examination will be picked up one (1) hour after the examination starts. -

% OF CATEGORY % OF CANDIDATE'S CATEGORY  !

VALUE TOTAL SCORE VALUE CATEGORY 20.00 100.0n A. REACTOR THEORY, THERMODYNAMICS AND .

FACILITY OPERATING CHARACTERISTICS i

% TOTALS 4 FINAL GRADE  :

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

i Candidate's Signature i

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

1. Cheating on the examination means an automatic denial of your application l 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 l done after you complete the examination. L

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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

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

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

7. Print your name in the upper right-hand corner of the first page of each '

section of your answer sheets.

8. Each question is worth one (1) point. Partial credit will NOT be given.  :

9. If the intent of a question is unclear, ask que.ntions of the examiner only.

10. When you are done and have turned in your examination, leave the examin-atior, area as defined by the examiner. If you are found in this area  !

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while the examination is still in progress, your license may be denied or revoked.

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EQUATION SHEET t

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~ 6 - E cp AT MTC - 0.0054 $/'F 6 - 5 di SCR - S/(1-Keff) 6-UAAT CR (1-Keff)3 - CR2 (1-Keff)2 3

26.06 (A.,,p) g, (1-Keff)n SUR (B-p) (1-Keff),

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

P=P a 10*"" SDM - (1-Keff)/Keff P - Po e"'" Pwr - W, m P- ~#I f* - 1 x 104 seconds P,

7 - (f*/p) + [(if-p)/A,,,p] r - f*/(p-[)

p - (Keff-1)/Keff A,,, = 0.1 seconds

p = AKeff/Keff 0.693 I1/2 " A 0

E - 0.0065 DR3 Di z - DR 22 D DR = DR,e* j l

l DR - _6 E(n) 1

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1 Curie - 3.7x10'" dps 1 kg - 2.21 lbm I hp - 2.54x10 3BTU /hr 6 1 Mw = 3.41x10 BTU /hr 1 BTU = 778 ft-lbf *F = 9/5*C + 32 l

1 gal H2O = 8 lbm 'C - 5/9 ("F - 32)  ;

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' A. RX THEORY, THERM 0 & FAC OP CHARS Page- 2 l

-*- ANSWER SHEET

-Multiple Choice (Circle or X your choice)

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

MULTIPLE CH0 ICE 001 a b c d 002 a b c d 003 a b c d  :

004 a b c d .

005 a b c d ,

006 a b c d 007 a b c d  ;

008 a b c d  !

009 a b c d ,

i 010 a b c d >

011 a b c d i

012 a b c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 017 a b c d 018 a b c d 019 a b c d 1

020 a b c d

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

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' Sectipn A _ BuThqqry. Thermo & Fac. Operatino Characteristics' Page.6 i

oQUESTION (A.1)

The. regulating rod has been withdrawn to increase power.

SELECT the reactivity coefficient that provides the most significant negative reactivity insertion-to turn power following completion of rod motion. (Assume no i

.other operator actions are taken.)

a. Moderator temperature coefficient

b. Fuel temperature coefficient i

c. Pressure coefficient

d. Void coefficient oQUESTION (A.2) t Which ONE of the following is true concerning the differences between prompt and delayed neutrons?

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a. Prompt neutrons account for less than one percent of the neutron population while delayed neutrons account for approximately ninety-nine ,

percent of the neutron population '

b. Prompt neutrons are released during fast fissions while dTlayed neutrons are released during thermal fissions

c. Prompt neutrons are released during the fission process while delayed neutrons are released during the decay process

d. Prompt neutrons are the dominating factor in determining the reactor period while delayed neutrons have little effect on the reactor period E

Section A RrTheory. Thermo & Fac. Operatino Characteristics Page 7 '

oQUESTION (A.3) i Given the following:

The reactor is at low power with T(out) at 75 deg F ,

The shim-safety rod was initially positioned at 30%

Coolant temperature was allowed to _ increase at constant power until the shim was at 60%

Approximate shim-safety rod reactivity worths are:  !

25% ---

0.124$ 55% ---

0.600$

30% ---

0.2015 60% ---

0.6695 35% ---

0.257$ 75% ---

0.834$ ,

45% ---

0.4575 100% ---

1.1235 .

CALCULATE the final value of T(out) for the above conditions. (Note: All choices ,

rounded to nearest degree.) '

a. 162 degrees F

b. 158 degrees F

c. 137 degrees F

d. 112 degrees F l

l oQUESTION (A.4)

SELECT the reason why a UTR-10 reactor requires a moderator. ,

A moderator is required to: f

a. absorb excess high-energy neutrons.

b. reduce the amount of excess core reactivity.

c. allow for a lower fuel enrichment. .

d. provide the media for the slowing-down of neutrons.

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int _ ion. A_ fLIbppty. Thermo & Fac. Ooeratina Characteristics Page 8 ,

. i 0 QUESTION (A.5) ,

Which ONE of the following would be the most efficient neutron moderator?

A material that has a:

a. low density and large atomic mass.

b. high density and small atomic mass.

c. low density and small atomic mass.

d. high density and large atomic mass.

f oQUESTION (A.6)

Which ONE of the following does NOT affect the Effective Multiplication factor (Keff)?

a. The moderator-to-fuel ratio. <

b. The physical dimensions of the core.

c. The strength of installed neutron sources.

d. The current time in core life.

Os as,..-

Scction A- R Theory. Thermo & Fac. Doeratina Characteristics Page 9

• QUESTION (A.7)

.Given the.following conditions:

The reactor is operating at a power level of 155 watts  !

The regulating control rod is inserted 4 The rod insertion results in a stable, negative 25-second period SELECT the expected reactor power 30 seconds after the rod insertion. (NOTE: Choices ,

are rounded to the nearest watt.)

a. 32 watts ,

b. 47 watts 9

c. 67 watts ,

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d. 151 watts

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• QUESTION (A.8)  !

Which ONE of'the following describes " Excess Reactivity"7 i

Excess reactivity is:

a. a measure of the additional fuel loaded to overcome fission product poisoning. {

b. a measure of remaining control rod worth with the reactor exactly critical.

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c. the combined control rod negative reactivity worth required to keep the

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reactor shutdown.

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d. The maximum reactivity by which the reactor can be shutdown with one "

control rod fully withdrawn.

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Section A R Theory. Thermo & Fac. Operatina Characteristics Page 10' oQUESTION (A.9)

Siven the following conditions:

The reactor is suberitical -

Keff has been increased from 0.861 to 0.946.

What is the amount of reactivity that has been added to the core?

a. 0.220 delta-K/K '

b. 0.125 delta-K/K

c. 0.104 delta-K/K

d. 0.085 delta-K/K '

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• QUESTION (A.10) i During a fuel loading, as the reactor approaches criticality, the value of 1/M is.

plotted. Which ONE of the following describes the progress of the 1/M curve?

a. decreases toward zero '

b. decreases toward one

c. increases toward infinity

d. increases toward one t

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[SectionAl&_Ttteory.Thermo&Fac.OoeratinaCharacteristics Page Il l

'OQUESTION (A.ll)

Which ONE of the following is the cause for the constant rate of power change (decrease) 10 minutes following a reactor scram from full power?

The constant rate of power change is due to the:

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a. mean average decay rate of ALL neutron sources.

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

c. decay rate of the LONGEST-lived delayed neutron precursor. i

d. decay rate of the MOST PROBABLE delayed neutron precursor.

oQUESTION (A.12) tihich ONE of the following causes indicated power to STABILIZE several hours after a reactor scram? (Assume a high power history, all systems and components operating as '

designed, no change in reactor experiments and no removal of fuel from the reactor.)

Indicated reactor power will stabilize due to:

a. continuing decay of the shortest-lived delayed neutron precursor. i 1

b. the decay of instrumentation compensation voltage at low power levels. -l

c. the subcritical multiplication of source neutrons,

d. dropping below the instrumentation minimum detectable level.

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Section A R Theory. Thermo & Fac. Operatino Characteristics Page 22

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oQUESTION (A.13) i l

' SELECT the factor that will NOT affect the shim-safety control rod estimated critical ,

position as calculated prior to a reactor startup. J

a. Installed experiment location and type a

b. Installed startup neutron source strength

c. Time since reactor shutdown

d. Core tank water level '

cQUESTION (A.14) ,

SELECT the reason why a neutron source is installed in the core until power is 50 mW during a startup.  !

The neutron source:

a. provides the source neutrons to maintain reactor period above the 5 second period scram setpoint.

b. increases the power level to greater than the I watt reactor scram -

setpoint.

c. increases the power level by a factor of 1/M -(M - Subtritical Multiplication Factor).

d. provides a neutron level high enough to be monitored by wide range nuclear instrumentation.

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['SectionA R Theory. Thermo & Fac. Operatino Characteristics Page 13-u

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• QUESTION (A.15)

Which ONE of the following is a correct statement concerning the factors affecting

. control rod worth?

a. Fuel burn up causes the rod worth for periphery rods to decrease,

b. Fuel burn up causes the rod worth to increase in the center of the core.

c. The withdrawal of a rod causes the rod worth of the remaining inserted rods to change.

d. As Rx power increases rod worth increases.

• QUESTION (A.16)

The shutdown margin (SDM), upon full insertion of all control rods following a reactor scram from full power, is the SDM immediately prior to the scram.

a. Equal to

b. Less than

c. Greater than

d. Independent of f

a e v a

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Section A Pr Theory. Thermo & Fac. Operatina Characteristics Page 14  ;

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• QUESTION (A.17)

Which ONE of the following will be the resulting stable reactor period when a $0.25 i reactivity insertion is made into an exactly critical reactor' core?  ;

a. 48 seconds j

b. 30 seconds

c. 18 seconds

d. 10 seconds

• QUESTION (A.18)

' IDENTIFY the reason why it is necessary to have " excess reactivity" in the ISU reactor. ,

! Excess reactivity is required to make up for the reactivity loss associated with:

a. the reduction in remaining core life. f

b. fission product poison burnout or decay. I

c. moderator temperature reductions. f u  !

d. decreased core voiding. ,

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'Section A R Theory. Thermo & Fac. Operatino Characteristics Page 15

• QUESTION (A.19) 1 Which ONE of the following describes the response of the reactor to equal amounts of i reactivity insertion as Keff approaches 1.07 '

a. The change in neutron population per reactivity insertion is smaller, and it takes more time to reach a new equilibrium count rate

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b. The change in neutron population per reactivity insertion is larger, and it takes more time to reach a new equilibrium count rate

c. The change in neutron population per reactivity insertion is larger, and it '

takes less time to reach a new equilibrium count rate-i

d. The change in neutron population per reactivity insertion is smaller, and it takes less time to reach a'new equilibrium count rate

• QUESTION (A.20)

With the reactor on a constant positive period, select the power transient that will i take the LONGEST time.

a. 5% power -- going from 1% to 6% of rated power

b. 10% power -- going from 10% to 20% of rated power

c. 15% power -- going from 20% to 35% of rated power

d. 20% power --

going from 40% to 60% of rated power  !

(*** End of Section A ***)  !

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'Section A R Theory, Thermo & Fac. Operatina Characteristics Page 1 l OANSWER (A.1) t a.

• REFERENCE (A.1) >

ISU Reactor Operator Training Manual, " Reactivity Coefficients",

Pages 32 & 33  :

UTR-10 Reactor Training Manual, " Reactivity Coefficients II", ,

Figure 10-1, Pages I-189 & I-190 t

OANSWER (A.2) c.

OREFERENCE (A.2)

ISU Reactor Operator Training Manual, " Reactor Startup", Page 11 0 ANSWER (A.3)

a. >

OREFERENCE (A.3) .

RO/SRO Exam 1984, Question C.4, Examiner Modified l

((0.669 - 0.201)/0.0054) + 75 = 161.667 degrees F 5

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OANSWER (A.4) d.

• REFERENCE (A.4)  !

-ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Page 1 ,

" Introduction to Nuclear Engineering", J.R. Lamarsh, 1975, Pages 180-182 .

t UTR-10 Reactor Training Manual, " Neutron Travel and Neutron Sources", Pages I-71 & I-72 i

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• Section A R Theory. Thermo & Fac. Operatina Characteristics Page 2  !

• ANSWER (.A 5) ,

b.  ;

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• REFERENCE (A.5)

UTR-10 Reactor Training Manual, " Neutron Travel and Neutron Sources", Pages I-71 & I-72 l

• ANSWER (A.6) l C.  !

• REFERENCE (A.6) l UTR-10 Reactor Training Manual, " Reactivity, Shutdown Margin and i Excess Reactivity", Page I-102 & I-103 r

• ANSWER (A.7)

I b.

• REFERENCE (A.7)

UTR-10' Reactor Training Manual, " Reactor Period I", Figure 10-1, ,

Pages I-150 & I-155 j P = 155 [e (30/-25)] = 46.7 watts i

• ANSWER (A.8)  ;

b.

• REFERENCE (A.8)

ISU Reactor Operator Training Manual, " Technical Specifications",  !

Page 1-1 UTR-10 Reactor Training Manual, " Reactivity, Shutdown Margin and Excess Reactivity", Page I-103 j i

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Section A R' Theory. Thermo'& Fac. Ooeratina Characteristics Page.3 OANSWER (A.9) l

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OREFERENCE (A.9)

UTR-10 Reactor Training Manual, " Reactivity, Shutdown Margin and '

Excess Reactivity", Pages I-102 & I-108 i CANSWER (A.10) l a.

OREFERENCE (A.10) '

UTR-10 Reactor Training Manual Vol. II, "The Approach-to-  ;

Criticality-Experiment", Pages 38 & 39  ;

cANSWER (A.11)  ;

c. ,

CREFERENCE (A.11) j UTR-10 Reactor Training Manual, " Prompt and Delayed Neutron i Fractions", Pages I-138 - I-140 [

0 ANSWER (A.12)  !

c.

OREFERENCE (A.12) i UTR-10 Reactor Training Manual, "Subcritical Multiplication", Pages I-112 - I-115  :

OANSWER (A.13) t

b. l CREFERENCE (A.13) ,

UTR-10 Reactor Training Manual, "Subcritical Multiplications",-  !

Pages I-116 - I-118 l c

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'gection A R Theory. Thermo & Fac. Operatina Characteristics Page 4 ,

1 OANSWER (A.14)

d. ,

i oREFERENCE (A.14) ,

ISU Reactor Operator Training Manual, " Reactor Operations Projects-  ;

Startup", Page 10 UTR-10 Reactor Training Manual, " Neutron Travel and Neutron i Sources", Page I-73 j I

i cANSWER (A.15) j E

c.

OREFERENCE (A.15) "

l Training Manual pg. 46 & 47 " Rod Shadowing" CANSWER (A.16) l

a. j CREFERENCE (A.16)

Trng Manual figure 1 pg 47. " Shutdown Margin" 0 ANSWER (A.17)

b. [

r OREFERENCE (A.17)  !

T= (0.fr P) / (P A) T!

T= (.0065 .001625)/(.1 x .001625)

T = 30 seconds

• ANSWER (A.18) a.

• REFERENCE (A.18) '

UTR-10 Reactor Training Manual, " Reactivity, Shutdown Margin and Excess Reactivity", Page I-103 -

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'Section A R Theory. Thermo & Fac. Ooeratina Characteristics Page 5 OANSWER (A.19) b.

OREFERENCE (A.19)

IS,U Reactor Operation Project  :

- OANSWER (A.20)

a. ,

OREFERENCE (A.20)  !

UTR-10 Trng Manual, " Reactor Period I", Fig. 10-1

• P f= P o e") => t= (In Pf/Po)

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In(6/1) > In(20/10) > In(35/20) > In(60/40)  ;

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NRC Official Use Only P

b Nuclear Regulatory Commission Operator Licensing Examination This document is removed from Official Use-Only category on date of examination.  !

NRC Official Use Only  :

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i U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: IOWA STATE UNIVERSITY REACTOR TYPE: UTR-10 -

DATE ADMINISTERED: 1993/06/21 REGION: 1 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheet-to the examination. Each question is worth one (1) point. A 70% is '

required to pass the examination. The examination will be picked up one (I) hour after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY '

VALUE TOTAL SCORE VALUE CATEGORY 2I.00 100.00 C. PLANT AND RAD MONITORING SYSTEMS

% TOTALS ,

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

~~~

Candidate's Signature  !

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

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

i

2. After the examination has been completed, you must sign the statement on I 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.  ;

i

3. Restroom trips are to be limited and only one candidate at a time may 1 leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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

5. Print your name in the blank provided in the upper right-hand corner of-  !

the examination cover sheet. ,

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

7. Print y'our name in the upper right-hand corner of the first page of each section of your answer sheets. ,

8. Each question is worth one (I) point. Partial credit will NOT be given.

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

only.

10. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.

C. PLANT AND RAD MONITORING SYSTEMS Page 2 r ANSWER SHEET-Multiple Choice' (Circle or X your choice) 2 If you change your answer, write your selection in the blank.

MULTIPLE CH0 ICE 001 a b c d 002 a b c d 003 a b c d 004 a b c d 1 005 a b c d 006 a b c d 007 a b c d O' 3 a b c d 009 a b c d e.

010 a b c d 011 a b c d ___.

012 a b c d 013 a b c d J14 a b c d 015 a b c d 016 a b c d 017 a b c d 018 a b c d 019 a b c d ,

020 a b c d ___

021 a b c- d

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

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

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• Section C Plant and Rad MonitorinoSystems Page 5 r

• QUESTION (C.1) .

SELECT the plant condition that will PREVENT control rod withdrawal.

a. Coolant outlet temperature is 165 degrees F. ,

b. Moderator level is 39.5 inches.

c. Power is stable at 0.9 watts.

d. Coolant flow rate is 3.75 gpm.

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• QUESTION '(C.2) -l The facility has experienced a loss of all site AC electrical power.

IDENTIFY the system / component that will still be available. (As>ume all systems are operating as designed.)

a. The Nuclear Instrumentation System (Linear Power Channels) ,

b .~ The Reactor Protection System (Reactor Safety portion) ,

c. The Ccre Tank Dump Valve ,

d. Tho Fac. ;!ty Evacuation Bell h

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Section C Plant and Rad MonitorinaSystems Page 6

• QUESTION (C.3)

Given the following conditions:

The reactor is operating at 10 KW The Dump Tank has developed a leak and level is lowering rapidly How will these conditions impact continued reactor operation?

a. The reactor will automatically scram at the low Dump Tank level setpoint.

b. There will be disruptions and/or reductions in primary coolant flow rate. '

c. Power will decrease as Reactor Core Tank water is lost due to the Dump Tank leak.

d. . The Dump Valve will automatically open to restore Dump Tank water level.

• QUESTION (C.4)  !

SELECT the method by which the area radiation monitoring instruments are ,

checked for proper operation.

.. The area radiation monitors:

a. are checked by applying a known value signal through their circuitry. i

b. individual detectors are exposed to a known strength beta particle source.

c. are checked automatically by the holding current circuitry signal.

d. individual detectors are exposed to a known strength gamma source.

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Section C Plant and Rad MonitorinoSystems Page 7

• QUESTION (C.5)

IDENTIFY the interlock that must be met to allow the operator to close the Dump Valve prior to a reactor startup.

a. The Primary Circulating Pump circuit breaker must be closed.

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b. Primary coolant flow must be greater than 5 gpm.

c. Moderator temperature must be less than 160 degrees F.

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d. Power Level Control must be in " Manual".

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• QUESTION (C.6) l SELECT the source of the reactor power signal to the Automatic Power Level Control Circuit. I The reactor power signal is:

a. an average of the two log power channels.  ;

b. an average of the two linear power safety channels.

c. operator selectable between the two linear safety channels. I

d. direct from the Multirange linear power channel.

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Section C Plant and Rad MonitorinaSystems Page 8

• QUESTION (C.7)

SELECT the REASON why a compensated ion chamber is used for monitoring neutron flux levels on the Multirange Linear Power channel.

A compensated ion chamber:

a. increases the accuracy of neutron flux indication at lower power levels.

b. increases.the accuracy of neutron flux indication at higher power levels.

c. provides a more rapid power change response input for reactor period indication.

d. provides a linear power change input signal for reactor period indication.

• QUESTION (C.8)

Given the following conditions:

A valid reactor scram signal has just been received All control rods have inserted as designed The Moderator Dump Valve did not automatically open and will_not open from the Control Room e

SELECT the MINIMUM reactivity by which the reactor is expected to be shutdown.

a. 0.72$

b. 0.65$

c. 0.46$

d. 0.225

p Section C Plant and Rad MonitorinoSystems Page 9 i

• QUESTION (C.9) l IDENTIFY the control rod assembly component that provides the "Stop" signal to '

the drive subassemblies at either end of rod travel.

a. Drive shaft worm gear

b. Motor limit switch

c. Helical potentiometer

d. Electromagnetic clutch

?

• QUESTION (C.10)

Given the following conditions:

The reactor is operating at 100% power  !

The Power Level Control system is in " Automatic" A valid reactor scram signal has just been received SELECT the method by which the regulating control rod will be inserted into  !

the core reflector.

t The regulating control rod: i i

will scram with the other control rods.

a.

b. must be manually inserted by the operator.

c. must be manually scrammed after the Power Level Control system is placed in " Manual".

d. will be driven into the core reflector automatically at normal. f speed following the scram. i i

e i

k i

<s,r s .=, ~~w+'w-- t. % - ,+ -.e-i. - . . .

.w.e.e-+ - ~=wn. es.

Section C Plant and Rad Monitorina Systems Page 10

.i

• QUESTION (C.11)

The TOP pushbutton for the control circuitry of Safety Control Rod #2 is illuminated (yellow).

IDENTIFY the condition of that control rod. (Note: Evaluate each choice separately from the others.)

Safety Control Rod #2:

a. is at its MAXIMUM withdrawn position ,

b. is fully inserted. j

c. has power applied to its clutch.

d. ' on" pushbutton has been depressed. l k

• QUESTION (C.12)

Identify the type of detectors used in the area and equipment radiation j monitoring assemblies throughout the ISU facility.  ;

i

a. Geiger-Mueller tubes -

b. Scintillation detectors

c. Gamma sensitive ion chambers

d. Fission chambers i f

i i

i i

1 A

.i i

l Section C Plant and Rad MonitorinoSystems Page'll )

• QUESTION (C.13)  :

Given the following conditions:

A reactor startup is in progress

~

The reactor is critical with power increasing The operator does NOT direct the startup neutron source be pulled ~

to its storage location  ;

If the startup continues, SELECT the expected AUTOMATIC action.  ;

i

a. Reactor scram as power increases. '

b. Reactor scram on short reactor period.

c. Control rod withdrawal interlock as power increases. ,

t

d. Control rod withdrawal interlock on short reactor period. .

l

• QUESTION (C.14)

SELECT the MAXIMUM allowed temperature of the primary coolant flowing through l the deionizer. ,

a. 120 degrees F l

b. 140 degrees F

c. 150 degrees F

d. 180 degrees F .j I

d. [

+

.Section C Plant and Rad MonitorinoSystems Page 12

• QUESTION (C.15)

SELECT the NORMAL method of regulating the inlet coolant temperature during reactor operation at power. >

Inlet coolant temperature is regulated by: #

a. manual control of the steam flow rate through the dump tank steam heating coils.

b. automatically varying the amount of primary coolant flow through the heat exchanger.

c. manual diversion of coolant flow to the dump tank or core tanks as necessary.

d. automatically varying the amount of secondary coolant flow through the heat exchanger.

3

• QUESTION (C.16)

SELECT the condition required for power to be applied to the Regulating

.. Control Rod "Up" switch. (Note: Consider each choice separately from the others.)

a. Safety Control Rod #1 must be at its upper limit.

b. Safety Control Rod #2 must be at its upper limit.

c. Safety Control Rods #1 AND #2 must be at their upper limits.

d. Shim-Safety Control Rod must be at its upper limit.  ;

Section C Plant and Rad MonitorinoSystems Page 13

• QUESTION (C.17)

SELECT the area radiation monitor that will automatically sound the evacuation alarm when the preset limits are exceeded and the reactor console is NOT energized.

The radiation monitor that monitors the:

a. east perimeter of the reactor.

b. area of the shield tank.

c. deionizer column.

d. fuel pit area.

• QUESTION (C.18)

IDENTIFY the condition allowing the reactor to continue operation without the Primary Circulating Pump in operation.

Operation may continue if'-.

a. the Power Level Control is left in " Manual".

b. natural convection mode is used less than 1 (one) hour.

c. reactor power is held at 570 watts.

d. the moderator temperature increases no more than 10 degrees'F.

i s

l

. I Section C Plant and Rad Monitorina Systems .Page 14 l l

l

• QUESTION (C.19)

SELECT the reason why 49.5 inches was selected as the normal operating core tank water level. i This water level:

a. provides the maximum shielding for controlling radiation levels in areas outside the reactor.

b. ensures the nuclear instrumentation detectors are measuring an accurate reactor neutron flux.

c. ensures an adequate net positive suction head for the Primary Circulating Pump.

P

d. provides the design amount of negative reactivity for insertion when the dump valve is opened.

i

• QUESTION (C.20)

Which ONE of the following describes how the deionizer functions to minimize corrosion of the reactor components?

t ,

The deionizer:

]

a. maintains the coolant pH at a slightly basic value.  !

I

b. removes soluble radioactive impurities from the coolant. i l

c. removes suspended particles from the coolant. l

d. maintains primary coolant at a low conductivity.

i

_ _ _ _ _ _ _ _ _ . _ _ _ . . _ . _ _ _ _ __. ____ _ . , . _ ._ _ _. _. I

7 Section C Plant and Rad MonitorinaSystems Page 15 3

• QUESTION (C.21)

SELECT the method by which gamma-ray compensation is accomplished in the nuclear instrumentation compensated ion chambers.

Gamma-ray compensation is accomplished by: '

a. a pulse height discriminator that eliminates (or discriminates) the pulses from the low energy gammas and allows only the higher '

energy neutron signals through.

b. the comparison of the currents generated in two concentric chambers in the detector, one sensitive only to gammas and one sensitive to neutrons and gammas.

c. varying the amount and concentration of the boron trifluoride gas '

in the compensated ion chamber thus reducing the detector's sensitivity to gamma induced ionizations.

d. varying the pressure of the detector Argon charge gas in conjunction with a low boron concentration coating the inside walls of the outer chamber.

i 5

i

(*** End of Section C ***)  !

(***** End of Examination *****)

I

~

Section C Plant and Rad Monitoring Systems- -Page 1

• ANSWER (C.1) b.

• REFERENCE (C.1)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility", Table 3.6-1, Page 61

• ANSWER (C.2) d.

• REFERENCE (C.2)

ISU Reactor Operator Training Manual, "UTR-10 Standby Power Supply", Figure 1

• ANSWER (C.3) b.

• REFERENCE (C.3)

ISU Reactor Operator Training Manual, " Introduction and General i Description of Facility", Page 25

• ANSWER (C.4) b.

• REFERENCE (C.4)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility", Pages 35 & 40

Section C Plant and Rad Monitoring Systems Page 2

• ANSWER (C.5) a.

• REFERENCE (C.5)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility", Page 42 >

• ANSWER (C.6) d.

• REFERENCE (C.6)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility", Pages 30 & 31

• ANSWER (C.7) ,

a.

• REFERENCE (C.7) ,

ISU Reactor Operator Training Manual, " Reactor Power Indication",

Pages 25-28 i

• ANSWER (C.8)

c. ,

• REFERENCE (C.8) ,

ISU Reactor Operator Training Manual, " Introduction and General i Description of Facility", Page 12  :

ISU Reactor Operator Training Manual, " Technical Specifications", Page 3-1

Section C Plant and Rad Monitoring Systems Page 3

• ANSWER (C.9) b.

• REFERENCE (C.9)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility", Page 44

• ANSWER (C.10) d.

• REFERENCE (C.10)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility", PaDes 56 & 60

• ANSWER (C.11) c.

• REFERENCE (C.11)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Page 59

• ANSWER (C.12) a.

• REFERENCE (C.12)

ISU Reactor Operator Training Manual, " Introduction and General

. Description of Facility ", Pages 34 & 35

.-m - .. , .-..

r Section C Plant and Rad Mon'toring Systems Page 4

• ANSWER (C.13) a.

• REFERENCE (C.13)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Table 3.5-1, Page 61

• ANSWER (C.14) .

b.

• REFERENCE (C.14)

ISU Reactor Operator Training Manual, " Introduction and General  ;

Description of Facility ", Page 28 and Table 3.5-3 Page 47 i

• ANSWER (C.15) d.

• REFERENCE (C.15)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Pages 46-48

• ANSWER (C.16) c.

• REFERENCE (C.16)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Pages 59 & 60

Section C Plant and Rad Monitoring Systems Page 5

• ANSWER -(C.17) d.

• REFERENCE (C.17)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Pages 40 & 53

• ANSWER (C.18) c.

• REFERENCE (C.18)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Page 25

• ANSWER (C.19)

b. ,

• REFERENCE (C.19)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Page 49 c.

• ANSWER (C.20)

)

d. l

• REFERENCE (C.20)

ISU Reactor Operator Training Manual, " Introduction and General Description of Facility ", Pages 28 & 48 l

• ANSWER (C.21)

b. I

• REFERENCE (C.21)

ISU-Reactor Operator Training Manual, " Reactor Operations Projects-Reactor Power Instrumentation", Page 27 i I