ML20137Q679

Exam Rept 50-054/OL-85-05 on 851009 & 10.Exam Results:One Reactor Operator Candidate Passed Both Written & Oral Exams

ML20137Q679
Person / Time
Site:	05000054
Issue date:	11/12/1985
From:	Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20137Q662	List: ML20137Q657 ML20137Q679
References
50-054-OL-85-05, 50-54-OL-85-5, NUDOCS 8512050334
Download: ML20137Q679 (52)

Text

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r U. S.. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 50-054/85-05 (OL)

FACILITY 00CKET NO.50-054 LICENSEE: Cintichem, Inc.

P. O. Box 326 Tuxedo, New York 10987 FACILITY: Cintichem, Inc.

EXAMINATION DATES: October 9 and'10, 1985' CHIEF EXAMINER: * , 8'7'I8 Noel Dudley, React ngineer Examiner . Date REVIEWED BY: If .

Robert M. Keller, Ciibf

//!/k/

Date Projects Section 1C APPROVED BY: /

Hadry B. K1'styr, Chief Dat Projects Bran & No.-.1 -

SUMMARY

A licensing examination was administered to one R0 candidate. He passed both the written and oral examinations.

8512o50334 851114 0 ADocM 050oo054 PDR

-m .

9 REPORT DETAILS TYPE OF EXAMS: Replacement EXAM RESULTS:

I R0 l l Pass / Fail l I I I I I I Written Exam l 1/0 l-1 I I I I I .

I Oral Exam i 1/0 l l l l l l l l Overall l 1/0 l l l l

1. CHIEF EXAMINER AT SITE: R. G. Clark, PNL-

2. OTHER EXAMINERS: None

3. Summary of generic strengths or deficiencies noted on oral exams:

Candidate demonstrated a weakness in knowledge of area monitors.

4. Summary of generic strengths or deficiencies noted from grading of written exams:

Candidate's knowledge of Principles of Reactor Power Operation was weak but acceptable.

Facility did not provide adequate or appropriate reference material for preparation of the examination.- The licensee. expended a-large portion of the examination review session attempting to find references to justify expansion of responses in the answer key. As a result, the examiner felt that, in some cases, the answers provided by the reviewers were less appropriate than the answers supplied by the candidate.

5. Personnel Present at Exit Interview:

NRC Contractor Personnel R. G. Clark,- PNL

. 3 Facility Personnel W. G. Ruzicka, Manager, Nuclear Operations S. E..Lupinski, Training Coordinator R. A. Strack, Reactor Supervisor

6. Summary of NRC Comments made at exit interview:

The candidate' clearly passed the oral examination.

Facility supplied questions and answers had not been received by the examiner.

7. CHANGES MADE TO WRITTEN EXAM:

The following changes were'made to the questions prior to the exam:

i Question B.5 p. 5 remove words by pass C.6 p. 9 or changed to on C.7 p. 9 insert word best in part b.

0.4 p. 10 change and to any G.6 p. 20 add and briefly tell why at end of question (answer expects this addition)

G.8 p. 21 change the word the to two. Give two.

limitations.

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. 4 Answers enlarged as a result of inadequate reference material submitted.

A.1 Add as an alternate Answer:

• photoneutron source I

02+ g- ------ n 1=1H 3 o A.2 Add ~as a factor:

^

• Relative short half-life as an option B.2 Add as an option:

• Due to press difference C.5 References provided by facility:

Tables on RM-04-2 or RM-03-2 0.1 For correctness, the last line of the answer should read:

a direction, thus overcoming the compensating current that is in excess of gamma current from the CIC.

D.2 Answer shall state:

Can cover ~a wide range of flux changes, without switching.

E.4 Answers should be:

For 3'-limit: To always assure NPSH for. primary pump.

For.7' limit: To assure adequate. volume in hold-up tank that r gravity flow of coolant-through the core occu~rs after primary pump t

lost.

Facility was unable to supply references.for these answers.

F.2 No change made. All suggested addition to answer were correct, but

insignificant.

Attachment:

.1. Written Examination and Answer Key (RO)

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U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Cintichem Reactor Type: Test Date Administered: October 9, 1985 Examiner: R. G. Clark Candidate:

, INSTRUCTIONS TO APPLICANT: -

Print your name on the line above marked " Candidate." The grade points available for each question are indicated within parentheses after each ques-tion. The passing grade is at least 70% in each of the seven (7) categories.

Use separate paper fo'r your answers and write on only one (1) side of the paper, unless a specific question instructs you otherwise. Staple this question package to your answer sheets. The examination questions and answers will be picked up six (6) hours after the examination was started. Read the statement at the bottom of this page. When you have finished this examination, affirm the gtatement by signing your name.

Category  % of Candidate's  % of Value -Total Score Cat. Value Category 17.5 17.5 A. Principles of Reactor Power Operation 12.0 12.0 B. Features of Facility Design 15.0 15.0 C. General Operating Characteristics 15.0 15.0 D. Instruments and Controls 16.0 16.0 E. Safety and Emergency Systems 11.5 11.5 F. Standard and Emergency

Operating Procedures 13.0 13.0 G. Radiation Control and Safety I

100.0 > TOTALS 1

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FlinalGrade  %

-  ! All work done on this: examination is my own; I have' neither given nor received I aid. , '

j .

t Candidate's Signature e

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• 1 CINTICHEM

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., OctobIr 9, 1985 A. PRINCIPLES OF REACTOR POWER OPERATION (17.5)

Points Available 00ESTION A.1 Give the nuclear reactions that produce neutrons from the source at the Cintichem Research Reactor. (1.0)

ANSWER A.1 '

9 Fd "

4 Be. + y ---+ Be8+ n l

(+1.0) '5 S # " "' ' #

o 4 0 y,, pp c,, f.esM jfl l" , ) : ' . , r' 12.r M7f~~

Reference (s)

._) j7,,,, ~ [$ a'((I% AV

1. Principles of Reactor Operation, p. A-7.

2, j\/ veu >,= E 4x .,..< /dosx fr m '"'7c" i7ss' y ' 3 ' '*"*

QUESTION A.2 Give two (2) reasons why Xe-135 has such a significant effect on reactor operation.

(2.0) 4 ANSWER A.2 Because of its high fission product yield (+1.0).

Because of its very large thermal cross-section (+1.0).

g/c h uA >St n 'Th G c ) s r i v>:1. v s >> r, f J ,o,1; r t o cf Reference (s)_

1. NUS, Vol . 3, p. 10, 2-1.

j. pn Ers:: $  !.', /*//-*T!" $ f ' 2- 4

- Section A continued on next page -

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2 CINTICHEM

, Octob:r 9, 1985 Points Available 00ESTION A.3 Answer TRUE or FALSE and briefly justify your answer.

a. The time it takes to achieve peak Xe conditions following a shutdown is independent of the equilibrium power level 4 prior to shutdown. (1.0)

b. The equilibrium Xe-135 concentration at 50% (2.5 MW) .

power is about half the Xe-135 concentration at 100% power. (1.0)

ANSWER A.3 .

a. FALSE - The lower the equilibrium power, the earlier the Xenon peaks.

b. FALSE - It is about 70% as high as at 100% due to higher burn-out factor of Xe-135 at 100% power.

(+1.0 each)  :

Reference (s)

1. NUS, Vol . 3, pp.10.2-2,10.2-3 and 10.2-4.

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- Sedtion A con,tinued on next page - *

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3 CINTICHEM

. _,' Octobtr 9, 1985

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Points  !

Available

'00EST10N A.4 .

Why,is excess reactivity added to a reactor greater than that necessary for a critical mass? Give three (3) reasons. (3.0)

ANSWER A.4 (Any three (3)]

1. To overcome' negative power coefficients. '

2 .~ To overcome neutron losses due to poisons and leakage.

3. To give operating flexibility 1.e., increase to power at a reasonable rate.

i 4. To compensate for fuel burnup, i r s' 5. To accommodate negative reactivity of experiments.

(+1.0 each, +3.0 maximum)

• Reference (s)

1. Training Manual (TM), Section J, Specific Operating Characteristics, pp. 10, 11.

4 j 2. NUS, Vol . 3, Section 11. , p.11.1-3.

Section A continued on next page -

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7.* .. 4 CINTICHEM

, Octcb;r 9, 1985 Points Available QUESTION A.5 Given the following, KS = multiplication factor for delayed neutrons X(1-6) = multiplication factor for prompt neutrons 8,ff = 0.008 for Cintichem Research Reactor Give the maximum safe multiplication factor that can be tolerated in this reactor, and briefly explain why. (2.0)

ANSWER A.5 ,

Less than 1.008. (+1.0) s Because at these multiplication factors the rate of increase is controlled only by the rate of emission of delayed neutrons. (+1.0) i j Reference (s)

1. Training Manual (TM), Section H, p. H-7 e

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- Section A continued on next page - I i

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5 CINTICHEM October 9, 1985 Points Available QUESTION A.6 How does 8 differ from 6,ff (larger / smaller) in the Cintichem Research Reactor and briefly explain why? (2.5)

ANSWER A.6 Seft is larger (+1.0). The essence of this statement. Delayed neutrons are born with lower energies (hence, fewer fast fissions), greater thermalization, less fast neutron escape. '

Resulting in more thermal neutrons present. Hence 8,gg is larger. (+1.5)

Reference (s)

1. NUS, Vol. 3, p. 5.3-3.

2. Console Exercise #1, p. N-1, Par. 2.

3. Console Exercise #3, p. N-4, Par. 4.

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- Section A continued on next page -

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.j. n - u - - + a -. - -.n .

. . 6 CINTICHEM OctobIr 9, 1985 l- Points Available 00ESTIONS A.7 What reactivity-(e) is associated with the following values of k,ff?

a. keff = 1

> e=? (0.5)

b. k,ff = 1.001 e = ?- (0.5)

c. k,ff = 0.995 e=? (0.5) j ANSWER A.7

a. e=0 1 b. le = 0.001

, c. e = -0.005

(+0.5 each) i Reference (s)

1. Training Manual (TM), Section H, p. H-7.

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Section A continued on next page -

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, .,' ,, Octob:r 9, 1985

. 1 Points Available 00ESTION A.8 Select the best answer (a. , b., c. , or d.)

' FroMthe initial count until- the reactor is critical during a startIup, how many doublings of the count usually occur u,ntil criticality is achieved? (0.5)

(a.) , 3_ -

(b.) .5 ' 4 (c.) 7

, (d.) 10 t

~

ANSWER A.8 3

(b.) (+0.5) ,

, N Reference (s)

1. Training Manual (TM), Section N, Console Exerc,ises, p. N-2.

N QUESTION A.9 The effectiveness of a control rod (disregarding its material or construction) depends largely upon what factors? Name two (2). ,

(2.0) 9 ANSWER A.9 e a. Position in the core. (+1.0)

b. Neutron flux at the location of the rod. (+1.0)

Reference (s) ',

1 i ,

~1.- Training Manual (TM),.Section N, Console Exercises, p. N-5.

i.

Section A

• continued 9n next page -t

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.- 8 CINTICHEM Octobtr 9, 1985 Points Available i QUESTION A.10- , j If reactor power steadily increases from 1 MW to about 2.72 MW in 100 seconds, what is the approximate period? (1.0)

P.= Po et /T, 1 ANSWER A.10 100 sec (+1.0)

Reference (s)

1. NUS, Vol.~3, p. 6.3-1. >

- End,of Section A -

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., . ', . 9 CINTICHEM-Octob r 9, 1985 B. FEATURES OF FACILITY DESIGN (12.0)

Points Available OVESTION B.1

,- a. In the reactor cooling system, rank in' order of elevation, the following components, i.e., which is highest, next highest, etc. (2.0)

1. Heat Exchanger (bottom)

2. Reactor Stall (pool surface)

3. Hold-up Tank (bottom) ,

4. Storage Tank (bottom)

b. Briefly explain why a difference (if any) exists in eleva-tion and size of the above. (1.0)

ANSWER B.1

a. 4. Storage Tank (highest)

2. Reactor Surface

1. Heat Exchanger

3. Hold-up Tank (lowest)

(+0.5 each)

b. To provide an adequate supply of coolant under all conditions

(+0.5) and to assure that the pool cannot be drained inadvertently to drop the pool level below the core (+0.5).

Reference (s)

1. Drawing 101586A - Flow Diagram-Reactor Cooling.

2. Training Manual, Section B, p. B-8 i

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i Section B-continued on next page - .

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10 CINTICHEM

• Octobsr 9, 1985 1

I Points Available j OVESTION B.2 t

l If a tube leak develops in the heat exchanger, state in j.whichdirectiontheleakageoccursandwhy. (1.5)

• ANSWER B.2  !

From the tube to the shell (+0.5); to prevent the primary water from contaminating the secondary (+1.0). 73 k__fppoptb

$0F 70 /D r.CL ' D i !-F l r ? "' ~ ^ O 'M ' O *#

Reference (s) [/ P) NM,

1. Training Manual (TM), Features of Facility Design, p. B-8.

- Section 8 continued on next page -

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. 11 CINTICHEM

, .,. Octob;r 9, 1985 j Points Available OUESTION B.3 i Give (a) the important design feature and (b) the important components that result in the ability of the ventilation $ystem to maintain a negative pressure t'n the reactor building, con-sidering that the supply capacity:is 19,000 CFM, the hot Tab '

fancapacityis30,000CFM,andthereactorbuildingexhatist fan capacity is 20,000 CFM.

(2.0)

ANSWER B.3 For credit, the answers must contain the essence of the following:

a. The hot lab exhausts directly to the stack, which doesn't affect the reactor building. (+0.5) - #4 S o v5? JW 7E " ( 4# '7 V l} b.

S<ccros .Su??Lf Sysilm c 4 4s?'A Ventilation supply valves (+0.5), ventillation exhaust valves

(+0.5), and a negative pressure control valve (+0.5) can be adjusted to result in the reactor building pressure being less than atmospheric.

Reference (s)

1. Training Manual (TM), Features of Facility Design, Figure B-11.

). l eis 1: y }4pona A  ?>,, FM 74- c7 l

- Section 8 continued on next page -

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12 CINTICHEM

=

. OctobIr 9, 1985

, ,' P51nts i

Available 00ESTION B.4 The continuous overflow gutter located on both sides of the pool is a gravity drain system open to the atmosphere.

a. How is most of this air prevented from saturating -

the reactor primary water? (1.0)

b. Why is this important? (1.0) .

ANSWER B.4

a. The overflow drains into the hold-up tank, which is vented releasing the air. (+1.0)

b. Excessive quantities of Ar41 from air-saturated primary cooling water are eliminated reducing the requirements for exhaust ventilation. (+1.0)

Reference (s)

1. Training Manual (TM), Features of Facility Design, B-3.

- Section B continued on next page -

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. 13 CINTICHEM

, Octcb:r 9, 1985 i '

I i Points

. Available QUESTION B".5' I .

Select theibest answer (a., b., or c.). (0.5)

When'the _y past puri'fication system of (a.) filter, (b.) lon-exchanger er, and (c.) ion-exchanger are all arranged in series, the maximum rhcommended flow through this alignment is:

a. 50 gpm

b. 200 gpm

c. 100 gpm ANSWER B.5

c. 100 gpm (+0.5)

Reference (s)

1. Training Manual (TM), Features,of Facility Design, p. B-9.

QUESTION B.6 The total worth of the five shim safety rods is closest to (0.5)

a. 9.35% ak/k

b. 7.85% ak/k

c. 10.9% ak/k ANSWER B.6

a. (+0.5)

Reference (s)_ .

1. Training Manual (TM), Features of Facility Design, p. B-10.

- Section 8 continued on next page -

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'. 14 CINTICHEM Octcber 9, 1985 -

Points -

. Available I '

OUESTION B.7 l

i

a. What is the purpose of the hinged, flapper plate (valve) t ,

attached to the side of the plenum? (1.0) i

b. How is it designed to operate? (1.5)  :

ANSWER B.7

a. The valve, when open, provides a path for thermal connection -

cooling of the. core. (+1.0)

b. It is closed initially with a push rod from the bridge

(+0.5), and drops open by gravity provided by counter-weights when pressure from forced primary flow is lost (loss of primary pump) (+1.0).

Reference (s)

1. Training Manual (TM), Features of Facility Design, Section B, p. B-7.

- End of Section 8 -

15 CINTICHEM October 9, 1985 C. A GENERAL OPERATING CHAR'CTERISTICS (15.0)

Points QUESTION C.1 Identify three (3) contributors to the power coefficient in order of significance, with the most significant (greatest in magnitude) first. (1.5)

ANSWER C.1 First Fuel Temperature (Doppler)

Second Tliird Moderator Temperature l Void Coefficient or Pressure Coefficient

(+0.5 each)

Reference (s)

1. Training Manual (TM), General Operating Characteristics, Section C,

p. C-3.

- Section C continued on next page -

16

• - . . CINTICHEM Oct:ber 9, 1985 Points OVESTION C.2

• Available I

Answer TRUE or FALSE and briefly justify (explain) your choice.

1. At Cintichem the CIC on the log N is gerierally kept in a slightly over compensated condition. t

, (1.0)

2. The two strongest rods at Cintichem are and 4. (1.0)

ANSWER C.2 i 1. FALSE (+0.5). Slightly under-compensated condition to bring the instrument on scale at startup and to avoid spurious i periods (+0.5).

i

'2. FALSE (+0.5). Rods 2 and 5 are the strongest (+0.5).

Reference (s)

1. Training Manual, Section C, p. C-5.

2. Training Manual, Section C, p. C-4.

- Section C continued on next page -

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. , CINTICHEM Octcber 9, 1985 .

,' 4  !

i Points 00ESTION C.3 ,

Available-If the reactor is shutdown after extended operation with an estimated 2% ak/k remaining in the gang at time of shutdown,

, a. .

how much time is available for a reactor restart?

Assume 0.02% Ak/k/ min Xenon buildup.

(1.0) ,

b. .w hat are the options available for a restart if the reactor is not restarted within the time as determined in a.?

(2.0)

ANSWER C.3

a. 100 minutes; 2% ok/k

• 0.02% ak/k/ min = 100 minutes.

(+1.0) b.

Must wait for some fraction of the reactor dead time to elapse (+1.0) OR must perform an Xenon reloid. (+1.0)

Reference (s) 1.

Training

p. J-9. Manual (TM), Specific Operating Characteristics, Section J,

- Section C continued on next page -

. 18 CINTICHEM

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.  ; Octob;r 9, 1985 i

8

Points QpESTION C.4 Available i C'o mplete the following.

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h. At Cintichem, the reactivity worth of any single experiment i shall not exceed n

(0.5)

b. The combined worth of all experiments that can add

! positive reactivity to the core upon withdrawal or malfunction shall not exceed .

(0.5)

c. During critical operation, no samples removed or loaded shall exceed .

(0.5) ,

1 E

ANSWER C.4

a. 0.5% ak

b. 2.0% ak

c. 10.25% ak

(+0.5 each)

Reference (s) 1.

Training Manual (TM), General Operating Characteristics, Section C,

p. C-4.

- Section C continued on next page -

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19

• . CINTICHEM l

- Octcber 9, 1985 i .

Points

)

i QUESTION C.5

! Available l

Complete the following table for the selected safety ' ,

channels below. For example, the table is completed j i

for the power level channel.

, (2.0) t i

Operating ',

Channel Function -

Mode l

1. Power Level (normal) Scram at 7.5 MW Start-up

2. Pool Temperature *

3. Coolant Flow 4 Flapper Valve

, 5. Bridge Excursion l Monitor l

l l ANSWER C.5

1. Power Level (normal) given given

2. Pool Temperature Alarm 9 115'F all

3. Coolant Flow Scram <2000 gpm at forced circula-tion above 250 kw

4. Flapper Valve Scram above M "

i 250 kw with valve open

5. Bridge Excursion Detect high Start-up radiation alarm and isolate at 5 R/hr

( (+0.25each)

_Re ference(s )_

1. Regulation Manual RM-03 2 l

- Section C continued on next page -

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• 20 - CINTICHEM.

',. --.o. *;. - .

Octcbir 9,.1985- -

j Points 00EST10N C.6 Explain why-that during a long shutdown, there is a constant decrease in the CR trace ort the log count rate (LCR) channel. (1.0)

ANSWER C.6 -

l This is 'due to fission product decay - fewer gamas with fewer

[ photo-neutrons produced. (+1.0) ,

!  ; Reference (s) 1 *

.1. Training Manual, Section C, p. C.S.

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- Section C continued on next page -

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' 21 CINTICHEM October 9, 1985

> ~

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' Points

, Available -

00ESTION C.7

• g Given these two expressions, ,

l T

2 I T=g ,

0 '.

T= ,

] .10 where T is reactor period.

a. ' Define T2 and T10 (1.0)

b. Identify which channel is used to measure each. (1.0)

ANSWER C.7

a. T2 is the time required for reactor power to double (+0.5) as j

measured on the linear N channel (+0.5).

b. T 10 is the time required.for the reactor power to increase by a factor of 10 (+0.5) as measured on the Log N channel

(+0.5).

Reference (s) b'

1. Training Manual, Section J, p. 2.

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- Section C continued on next page -

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22 CINTICHEM Octcb:r 9, 1985 i Points

Available -

QUESTION C.8 How is the Integral Worth of a rod expressed, and what does Integral Worth of a rod mean? (2.0)

ANSWER C.8 Integral Worth is expressed in % ak/k (+1.0) and is the total -

value of the reactivity change the rod is capable of effecting for its full-length of travel (+1.0).

Reference (s)

1. Training Manual Section J, p.1.

- End of Section C - ,

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23

• ' CINTICHEM October 9, 1985 D. INSTRUMENTS AND CONTROLS j . (15.0. )

Points

' Available 00ESTION D.1  :

Briefly describe what the buck,ing current on the Log N amplifier accomplishes.  ; (1.0)

ANSWER'D.1 The bucking in the Log-N amplifier eliminates false scrams where compensated ion chamber (CIC) over-compensation is suspected, i.e., bucking brings Log-N recorder just on scale during start-up preventing the input capacitor from being charged in the wrong a direction, thus overcoming the gamma current from the CIC. 1.0)

Reference (s) Nsc N 9 e s e.rr t. ') Y(+/[U ' *

1. Training Manual (TM), Instruments and Control, Section D, p. 0.20 y .. .. ,. o- -

p, y y ,

QUESTION D.2 Give two (2) distinct advantages of a Log-N amplifier over a linear amplifier. (2.0)

ANSWER D.2

/

a. Can cover a widef range of flux changes < io 50u- J w e rN"w . 44

b. Its percentage reading accuracy is the same at all points on the chart.

c. Exponential flux changes appear as straight lines on the recorder.

(+1.0 each, +2.0 maximum)

Reference (s) 1.

Training Manual (TM), Instrument and Control, Section 0,pp. 0-23. p.pg

- Section D continued on next page -

. 24 CINTICHEM -

Octobpr9,1985 s

Points

, Available -

OUESTION 0.3 Give two (2) reasons why a malfunction of'the autocontrol '

system cannot increase reactivity sufficiently to take the reactor to prompt' critical. .

(2.0)

ANSWER 0.3

a. The total worth of the regulatory rod is much less than the amount necessary (0.81% ak/k) to make the reactor prompt critical. (+1.0)

b. The regulatory . rod is driven by a constant speed motor that Ilmits its rate of travel to 24 in per minute, making it impossible to make sudden changes (short periods) in reactivity. (+1.0)

Reference (s)

1. Training Manual (TM), Instruments and Control, Section D, p. 0-43.

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... 25 CINTICHEM ,

', , _ . , . . Octcb;r 9. 1985 '

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Points

! l- Available 1 00ESTION 0.4 l Give af two (2) of the the four (4) con' trol actions j (inhibits) performed by the Log-N channel. (2.0) .

ANSWER D.4 i Any two of the following.

a. Prohibits shim and regulating rod withdrawal for periods less than 30 sec.

b. Bypassing count rate (start-up) channel inhibits above 0.001 Ng (0.001 of 50 kw).

c. Reverses shim-rods at periods less than 10 sec or neutron fluxes greater than 1251, OR when neutron flux is greater than 2 NL (-100 kw) with any shim rod less than 50%

withdrawn.

d. Bypasses process system scrams (primary pump, flapper, and flow) below 2 S/L (-100 kw)

(+1.0 each, +2.0 maximum)

Reference (s)

1. Training Manual,(TM), Instruments and Control, Section 0, p. 0-35.

- Section 0 continued on next page -

. 26 CINTICHEM OctcbIr 9, 1985 j Points

," Available OUESTION D.5 '

W' hat are the consequences, if any, if readtor operat, ion is in auto when the neutron flux at the ion chamber loc'ation of the linear-N channel is reduced by some purely loc' al means (some absorber being placed in front of the chamber)' 4 or by a change in flux distributions over the reactor (shim rods repositioned)? , (2.0)

ANSWER D.5 The change will be interpreted by the auto system as a power change (+1.0). The system will try to restore power, raise it unnecessarily (+1.0).

Reference (s)

1. Training Manual (TM), Instruments and Control, Section D, p. D-43.

- Section D continued on next page -

' ~

• 27 CINTICHEM Octcb2r 9, 1985 l l l Points 00ESTION 0.6 Explain why the flux monitoring instruments at Cintichem are only roughly proportional to power. (1.0)

ANSWER D.6 The neutron flux monitors "see" only leakage neutron flux because . ,

of their locations outside the reactor core and are incapable of monitoring the internal neutron flux within the core, measurement of which would correctly determine power. (+1.0) -

Reference (s)

1. Training Manual (TM), Instruments and Control, Section D, p. D-27.

- Section D continued on next page -

~ *

. \

.- 28 CINTICHEM Octcbtr 9, 1985 j i Points Available

. 00 STION D.7i I

! l Answer TRUE or FALSE. i

a. In an iohization chamber, operating in the ionization 2

region, the saturation current is in strict proportion to the radiation field. (0.5)

b. Operating an ionization cha;nber in its plateau region means that its output is sensitive to small changes in col-

-lector voltage. (0.5)

c. The length of a plateau in an ionization chamber is not affected by the strength of the radiation field. (0,5)

d. If the CIC is under compensated, the Log N will remain on scale even though the power level in the core is nil. (0.5)

ANSWER D.7 ,

a. TRUE

b. FALSE c.- FALSE

d. TRUE

(+0.5 each)

Reference (s)

1. Training Manual (TM), Instruments and Controls, Section D, pp. D-13, D-14,

2. Training Manual (TM), General Operating Characteristics, pp. C-4, C-5.

- Section D continued on next page -

i 9

~-

• 29 CINTICHEM

Octcher.9. 1985 iPoints

. Available QUESTION D.8 i Give the three (3) control actions performed by the count  :

rate (CR) channel. l(3.0) t ANSWER 0.8 ',

Prevention of shim and regulatory rod withdrawal when

a. the CR recorder is turned off (+1.0) OR ,

b. the counting rate is not in the 2 - 9800 cps range (+1.0) OR

'c. the period is less than 30 seconds (+1.0).

Reference (s)_

1. Training Manual (TM), Instruments and Controls, Section 0, p. 0-33.

4

- End of Section U -

i e f

i-

,. x.

30 .CINTICHEM ,

. - Octtb:r 9, 1985

'L.  ; .

E. SAFETY AND EMERGENCY SYSTEMS (16.0)

Points Available 00ESTION E.1 Answer TRUE or FALSE.

i

a. 'The automatic transfer switch will transfer power to emergency bus upon failure of utility power, but not

, , back to normal power when utility power is firmly restored. (0.5)

b. Stringer tubes may be removed fran the reactor while it is critical. .

(0.5) l

, c. Unexplained alarm of 2 area monitors requires an immediate reactor shutdown. (0.5) l

. ANSWER E.1 l a. FALSE (+0.5)

b. FALSE (+0.5)

c. 'TRUE (+0.5)

Reference (s) l .

l 1. a. Regulations Manual, RM-08-3.

l 2. b. Regulations Manual, RM-09-7.

l 3. c. Emergency Procedures EP-03-03. ,

l .

(

I s

i-l l ' - Section E continued on next page -

l l

S

31 CINTICHEM October 9, 1985

.. i .

r Points f I

Available  ; ,

QUESTION E.2_ I Give the primary reason why the primafy pump shall not be operated unless the secondary pump is toperating. (1.0)

ANSWER E.2 5 To prevent leakage of primary water into the secondary side in ,

case of a heat exchanger tube leak. (+1.0) '

Reference (s)

1. Regulations Manual, RM-06-01, RM-06-03.

QUESTION E.3 ,

L Give the reason why mercury bearing instruments and equipment shall not be allowed in areas where accidental spillage could introduce mercury into the primary. (1.0)

ANSWER E.3 8ecause of the use of aluminum in the primary system, which the mercury will chemically attack. (+1.0)

Reference (s)

1. Regulations Manual RM-06-2.

2. CAF.

- Section E continued on next page -

., . i

, 32 CINTICHEM October 9, 1985

Points' Available 00EST10N E.4 .

! g should the hold-up tank contain a water depth o' f at least 3 feet but no more than 7 fe,et? (2.0) .

ANSWER E.4 l -To assure a minimum amount of ~ primary coolant to covif'thrtore-

• during core cooling-by natural connection-(+1.0) hat-=^t ?"~r?. d ' e water

-as-to over-f-low-the-bes tn-et-these-t1,., . tel3) <

R'f'r'"C'(S)

N.9) l

</

', L p, , y- A/4# /'t'B

1. 1. 1. 1. (gst pt -) / 'P ' '

1. Regulations Manual, RM-06-01. A/> ///M/

! 2.

CAF. 7 7' g p j g y i;- e c ny ')> urn G A> / Is'? V fjsw 7p n c;p c re.r M7EA QUESTION E.5 j g py /h i p a n y /)uW NY

' ~

Give the limits of the control rod drive mechanisms for MUI'# '

,4,p t, i;;i j Y/LWWE N' the length of travel (0.5) [/,4) l a. '

b. drive speed //p/ //# ## (0.5) i

c. simultaneous withdrawal (ganging) (0.5)

_ ANSWER E.5

a. 24 inches

b. 5 inches / min

c. 2 drives (rods)

(+0.5each)

Reference (s)

1. Regulations Manual. RM-09.

- Section E continued on next page .

. 33 CINTICHEM .

. October 9, 1985 i Points I' .

~

Available -

QdESTION E.6 . .

a, . How is the " evacuation sequence" in the errergency I ventilation system initiated? (1.0)

. b'. Below are most of the events in the " evacuation sequence."

', supply the three (3) key events that are missing in the *-

sequence and indicate when in the sequence they would occur. (3.0)

Sequences

~

e All supply dampers close. .

e Pool sweep dampers close.

! e Hold-up tank vent Itne and air purge valves close.

l e Beam tube exhaust fan shuts down.

After seven (7) seconds or when reactor butiding pressure -

reaches 1-inch negative pressure. .

. e Emergency exhaust fan starts.

l e Emergency exhaust fan's damper opens. '~ '

l l

ANSWER E.6

a. Initiated by Excurston Monitor (Bridge Monitor) (+0.5), or manually by console operator (+0.5).

i

b. 1. Immediately (+0.5), reactor building supply fan shuts down(+0.5).

2. Af ter 7 seconds (+0.5), main exhaust damper closes 'T

(+0.5),and

3. Af ter 7 seconds (e4.5), exhaust fan shuts down (+0.5).

i Reference (s)_

l 1. Regulations Manual, RM-07, pp. 3 and 4.

l

- Section E continued on next page -

e

E e' 34 CINTICHEM

October 9. 1985 l .. 4 Po,ints

s. . ,  ; Available OUESTION E.7 .

I

. I

! When the yellow bulb at the entrance to the transformer' room  :

Hghts and starts flashing, it indicates that the overload i

~

' protectors on the emergency generator have tripped. l

~.-

i r

m' a. What is=the significance of this? (1.0)

b. WhatZtwo (2) actions must the reactor operator do?' (1.0) l s l '.

ANSWERED ~

+ ,- 'a. The emergency generator may not start. (+1.0)

b. ,The rsactor operator must shutdown the reactor (+0.5)

' y, , and thg' reactor operator notify a senior operator (+0.5).

l gference(s)

1. RehJ14tions Manual. RM-08, p. 3.

,e ,

,w q.

00ESTION E.8  %

a e s l What is the condition that ' requires the einergency core spray to i

be t:irned, on? (1,0)

ANSWEP. E.,n .

J l

When The condition results ih the core being uncovered. (+1.0)

N*

• t s <

l ,

~.

_Referendals)_ ,

n.'

d ,1. Regulations Manual, RM-06-3.

,. w ,

i

.i *~

f 1 <

/ -

. . y -

Section E continued on next page -

,, .e b

+

\ ,

A '+.,,_ #

l' ,

, *, f

? r-

/

,j' j

3

. = *

~'

i:

1 35 CINTICHEM Octob:r 9, 1985 I

j Points . ,I Available- i A' QUESTION E.9' Answer TRUE or FALSE. '

a. The worth of the regulating rod shall not exceed 0.6% ak. (0.5) [

b. The emergency generator should NOT start when the power outage lasts less than 15 seconds. (0.5)

c. High-level radiation incidentj are those requiring evacuation acco? ding to the Regulations (4anual. (0.5)

d. Hourly CAM rate meter readings, entered into the reactor I log book, may be substituted for a failed CAM recorder. (0,5)

~ ANSWER E.9

a. TRUE

b. FALSE

c. TRUE

d. TRUE

(+0.5each)

Reference (s) t 1. a. Regulations Manual, RM-09-5.

" 2. b. Regulations Manual, RM-08-2.

n '

3. c. Emergency Procedures, EP-02-01.

4. d. Emergency Procedures, EP-03-05.

m N

End of Section E i 5

.O, r ,W L t  ?

e k -

' 36 CINTICHEM.

- . Octcbzr 9, 1985-

. i -

I F. STANDARD AND EMERGENCY OPERATING PROCEDURES (11.5)i.

,. e i  : .

Points Available l

00ESTION F.1  :

l

. Answer TRUE or FALSE. ,

i The foll'owing conditions warrant.immediate shutdown of the-reactor. .,

(2.0)

a. The reactor critical with the control rods more than 50%

withdrawn from the core.

b. Loss of the water seal in the canal.

c. Failure of the auto transfer switch.

d. Inadvertent initiation of the evacuation sequence.

-ANSWER F.1

a. FALSE b.- TRUE-

c. TRUE

d. FALSE

(+0.5 each)

Reference (s)

1. Regulations Manual, RM-04.

- Section F continued on next page -

1

37 CINTICHEM Octcb:;r 9,1985 Points Availdble QUESTION F.2~ l i  !

Give two (2) reasons why'the reactor operator is instructed t to keep the control rods within 110% of their mean. position

~

i during all rod manipulations when reactor power is above ',

500 kw. (1,0)

ANSWER F.2  : ,

To assure that hot spots in the core (fuel degradation or excessive burnup) are avoided (+0.5) and that experiments receive ~their expected radiation (+0.5), 4/ c Reference (s)-

1. Regulations Manual, RM-04-7  ;

2. CAF i

l

- Section F continued on next page -

I l

i I

I. l i, ,_ .__ . . . . . . - . . . . . - , .

. 38 CINTICHEM l Octobtr 9, 1985 i

j Points

Available OVESTION F.3 Complete the following with the required words so that Cintichem Regulation is properly stated. (2.5)

a. When radiation alarms occur, without waiting for approval of emergency director may initiate the evacuation. sequence or shutdown the reactor,

b. The core should be loaded with a minimum of fuel elements with each control element in place being considered as a element,

c. The unexpected absence of a second reactor ope:ator at a facility for hours is acceptable .roeided immediate action is taken,

d. The Console Checklist (RS-01), Process Equipment Checklist, (RS-02), and the Electronic Equipment Checklist (RS-03) need not be completed where a restart is intended within hours after any shutdown. ,

ANSWER F.3

a. Reactor operation personnel (+0.5) b .- 30 (+0.5), half (+0.5)

c. 2 (+0.5)

d. 8 (+0.5)

Reference (s)

1. a. Emergency Procedures EP-03-02.

2. b. Regulations Manual, RM-10-6.

3. c. Regulations Manual, RM-03-4.

4. d. Regulations Manual, RM-03-7.

- Section F continued on next page -

,z- .,

, - .. 39 CINTICHEM

, October 9, 1985 e

i

Points

• Available QUESTION F.4 l Immediate shutdown of the reactor end initia(ion of the

.evacuationsequencewithevacuationofbuildingpersonnel is required for one combination of the following alarm conditions. Select the one (1) correct combination. (0.5)

a. 1. All three stack recorders going of f', scale.

2. UnexplainedalarmofbothreactorbbildingCAMsinany combination (recorder or rate meter, alert or high level). .

-3. Unexplaine,d alarm of one or more building or canal radiation alarms simultaneously, or consecutively with a stack alarm,

b. 1. Unexplained alarm of two or more area monitors.

2. Unexplained alarm of both reactor building CAMS in any combination'(recorder or rate meter, alert or high l evel ).

3. Unexplained alarm of one or more building or canal radiation alarms simultaneously or consecutively with a stack alarm,

c. 1. Unexplained alarm of one or more area monitors.

2. -- All three stack recorders going off scale.

3.. Unexplained alarm of one or more building or canal radiation alarms simultaneously, or consecutively with a stack alarm.

' ANSWER F.4 The answer is b. (The only answer above that does not include the

' incorrect statement "all three stack recorders going off scale.")- -(+0.5)

Reference (s)

1. Emergency' Procedures, EP-03-03.

- Section F continued on next page -

i n , ~ , -r

9

~

40 CINTICHEM October 9, 1985 [

' l i

Points Available 00ESTION F.5 -

a. Give the only reason for a reactor operator to activate the stress alarm. .

(1.0) ,

b. How may a reactor operator cancel a stress alarm? (1.0)

ANSWER F.5 -

a. If law enforcement personnel are required in the reactor building. (+1.0)

b. By making two (2) calls to the boiler house requesting that the a.lert be canceled. (+1.0)

Reference (s)

1. Emergency Procedures, EP-09.

QUESTION F.6

' Briefly describe the procedures the roving operator is to complete following an intrusion alarm.

(1.5)

ANSWER F.6

1. Interrogate the four (4) intrusion alarm buttons 4

2. Investigate the areas

3. Report to control room every ten (10) minutes

(+0.5 each)

Reference (s)

1. Emergency _ Procedures EP-10.

- Section F continued on next page -

l l

1 4

4 41 .CINTICHEM Octcber 9, 1985

,' j Points j '

i

,'  ; Available ,

00ESTION F.7 i 4

' Complete the following statements with the proper terms.

I

a. D'uring reactor operation, the safety of the facility

1) the direct responsibility of . (1.0)

b. Loading or removal of samples from the core shall be done only by or under the direction of . (1,0) 1 ANSWER F.7

a. the licensed operator at the console. (+1.0)

b. a licensed operator. (+1.0)

Reference (s)

1. Regulations Manual, RM-04.

- End of Section F -

3 - +-~ , - -

y-,,-

_f 42 CINTICHEM

, Octobir 9, 1985 o i -

G.- RADIATION CONTROL AND SAFETY -

13.0)

Points

. Available OUESTION G.1 t i.

What three (3) principles (parameters, factors);are used ',

to control radiation ' exposure? I(0.9)

ANSWER G.1 ' -

time distance sheilding -

(+0.3 each)

Reference (s)

1. Training Manual (TM), Radiation Control and Safety, Section G, p. G-23.

00ESTION G.2 ,

Assume that eight (8) centimeters of a particular lead glass will reduce the gamma radiation from 150 nr/hr to 75 mr/hr.

a. How many ' centimeters of this lead glass will be required to reduce similar gamma radiation from 400 mr/hr to 200 mr/hr? . (0.4)

b. How many centimeters of'this glass will be required to reduce a gamma radiation level from 80 mr/hr to 10 mr/hr? (0 '.7 )

ANSWER G.2 a.- 8 cm (by inspection)- (+0.4) b '. 24 cm .80/10 = 8 = (1/2)3 a 3 half-value layers (HVL)'

1 HVL = 8 cm, 3 HVL = 24 cm. (+0.7)

Reference (s)

1. Training Manual (TM), Radiation Control and _ Safety, _Section G, p. G-14.

- Section G continued on next_page -

, + 43 CINTICHEM Octobsr 9, 1985 0 *

[ Points Available 00ESTION G.3 ,

Briefly explain the permissible whole-body dose for persons employed at Cintichem facility, giving (1) the permissible whole-body limits and (2) the allowable whole-body limits *

(10 CFR limits). (2.0)

ANSWER G.3 The permissible whole-body dose is 1-1/4 rem per calendar quarter at Cintichem facility (+1.0).

The 10 CFR limits is 3 rem per quarte.' for an individual whose radiation history is complete and their lifetime dose does not exceed 5 (N-18) (+1.0).

Reference (s)

1. Training Manual (TM), Radiation -Control and Safety, Section G, p. G-12.

QUESTION G.4 State how a real iodine release would be characterized in the stack monitoring system. (1.0)

ANSWER G.4 A real iodine release would be characterized by a high iodine level'on the chart AND that it persists after the gas monitor has -1 dropped to a low level. (+1.0)

Reference (s)

1. Training Manual (TM), Radiation Control and Safety, Section G, p. G-10.

i - Section G continued on next page -

l

, - - , , .. l

• 44 CINTICHEM October 9, 1985 o  : .

4 Points  !

Available !

-OUESTION G'.5 -

l A recently, recovered irradiated saniple, as a radioactive source, may require two roped-off direas around it with differenthostingsforeach. Brieflly explain how this may happen. ',

(2.0)

i ANSWER G.5 .

One roped-off area will be at the boundary where the radiation level (dose rate) is 5 millirem /hr and posted as a " Radiation -

Area" (+1.0) and an . inner roped-off area will be required at the boundary where the dose rate is 100 millirem /hr and posted as 'a "High Radiation Area" (+1.0).

Reference (s)

1. Training Manual (TN), Radiation Control and Safety, Section G, p. G-12.

QUESTION G.6 Assume a radiation field from gamma radiation is expected to 4

be at least 4 R/hr. What kind of portable radiation instru-ment is required',and what. portable gamma sensitive instrument is not acceptable heret, hwny Tme>'4 Gon vex v'"Y-/~ t~d pw/g (1.0)

ANSWER G.6 0.2. C A portable ionization chamber (+0.5) A Geiger Counter (GM)Awould saturate in moderate to high radiation fields giving an unacceptable reading) and is not an acceptable alternative (+t8).

Reference (s)

1. Radiation Control and Safety, Section G, p. G-7.

, - Section G continued on next page -

.y

~

45 CINTICHEM Octcbar 9, 1985 .

.o

• t

Points Available QUESTION G.7

, Answer TRUE or FALSE. (2.0)

a. The maximum range in air 'of a beta particle ranges from '

28 inches to 6 feet.

b. The only units of dose that can be added to give total dose from different types of radiation (i.e., alpha, beta, gamma) are units expressed in rad.

c. The only radiation that the CAM units do NOT respond to is-j that due to alpha.

d. The reading of a pocket dosimeter is a dose rate.

ANSWER G.7

a. FALSE (6 inches to 28 feet)

b. FALSE (rem)

c. TRUE

d. FALSE (dose)

(+0.5 each)

Reference (s)

1. Training Manual (TM), Radiation Control and Safety, Section G, p. G-19, 15,11, 8, and 6, respectively.

- Section G continued on next page -

l l

.)

- .. --. .~ .. -

[ .* ' 46 CINTICHEM o-Octobtr 9, 1985

'n, '

I '

[ .

Points

, '). _ , _

l Available

-QUESTION G.8' '

-Ao .

, Give~the limitations of thA Cutie Pie as a survey instrument. (1.0) i 1.

ANSWER G'.8

. 1. 'Does not __ detect low energy radiation.

2. Does not~ detect _ neutrons.-

3. Has an upper limit of 55 rads /hr.

(+0.5 each,. +1.0 maximum)

Reference (s)

'1. Training Manual (TM), Radiation Control and Safety, Section G.

l Section G' continued on next page -

1

.,m._,

i = ,

c. -r' 47 . CINTICHEM 6- >

'Octob:r 9, 1985 g .  :

Points I Available 00ESTION G.9 '

I

• A Select the best answer and show all calculations. t

, (2.0) i An encapsulated Co-60 source hanging on the wall in the pool is to { -

be removed and placed in a cask for transfer. Assume the average  :

gamma energy is 1.25 Mev and that HP has appr.oved the transfer, ',

having measured the dose rate at 3. feet from -the source at 100 mr/hr. The amount of Co-60 activity in the capsule could be  ! -

no more than about

a. 1 Ci b .- 1/8 Ci

c. 1/2 Ci

. .d. 2 Ci Hint: Dose rate in R/Hr at 1 ft. = 6 CiE R/Hr Ci = curies E = gamma energy i

ANSWER G.9 The answer is value b. (1/8 Ci). (+1.0)

Calculation Method.

Dose rate at 1 ft., = 900 mr/Hr = 0.9 R/Hr Dose rate at 3 ft. = 100 mr/Hr nose rate at 1 ft. = (3 2f12) . 100 mr/Hr

= 9

• 100 mr/Hr

= 900 mr/Hr '

O.9 =.6 CiE = Ci (1.25)(6) s Ci = 0.12 -1/8 Ci' (+1.0)

Reference (s)

1. Training Manual.(TM). Radiation Control and Safety, Section G, p. G-15.

- Section G continued on next page -

- END OF EXAM -

. _ . _ _ - - _ . . _ _