ML20236G107

Exam Rept 50-150/OLS-87-01 on 871007-08.Exam Results: Two Reactor Operator Candidates Passed

ML20236G107
Person / Time
Site:	Ohio State University
Issue date:	10/22/1987
From:	Burdick T, Hare E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20236G100	List: ML20236G097 ML20236G107
References
50-150-OLS-87, 50-150-OLS-87-0, NUDOCS 8711020421
Download: ML20236G107 (46)

Text

- _ _ _ - _ _ - _ _

a.

U.S. N' CLEAR REGULATORY COMMISSION U

REGION III

. Report No'. 50-150/0LS-87-01(DRS)

Docke't No. 50-150 License No. R-75 i

.Licenseei Ohio State University i

Nuclear Reactor Laboratory

'1298 Kinnear Road Columbus, OH 43212 7.

Facility Name:

Nuclear Reactor Laboratory, UTR-10 Examination Administered'At: Ohio State University, Columbus, Ohio 1

- Examination Conducted: October 7-8, 1987

-Examiner:

Elizabeth A. Har [ '

W h M b

Date Approved By: [ mt ief

/

2 ~2-/O >

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Operating Licensing Section Date

/

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Examination Summary Examination administered on October 7-8, 1987 (Report No. 50-150/0LS-87-01(DRS))

to two reactor operator candidates.

Results: Both candidates passed.

2

f 8711020421 071027 PDR ADOCK 05000150 V

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E REPORT DETAILS

1. --

Examiners lE.'A. Hare, Chief Examiner L

.2.

Exit Meeting

!~

I' 0n October 8, 1987 at the conclusion of the examination, a meeting was L

held to discuss generic findings made during the course of.the L

' examination. ~The following personnel attended the meeting:

Facility Representative l'

.R. Myser, Plant Supervisor NRC Representatives 1

E. A. Hare, Chief ~ Examiner-T.

M.' Burdick,: Chief, 0perating Licensing Section

-The items discussed during this mee' ting are listed in the following.

paragraphs.

o a.

Three-instances were observed where facility personnel placed their-ungic"ed hands into the reactor pool. The examiner noted that

placing one's hand into the reactor pool without a glove was not a L

good radiation practice since the water is.potentially contaminated.

This practice. should be observed and revised'as appropriate.

b-The OSURR training material did not contain substantial information on the normal A.C. power system,. action to be taken on loss of A.C. power or backup power supply.

'This should be reviewed and revised as necessary.

c.

The procedures used at OSURR do~not clearly state what is the

. (.

responsibility of the R0/SRO. This should be clearly defined in each procedure or in a " conduct of operations" procedure.

1 3.

Examination Review Refer to the Attachment.

1 1

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ATTACHMENT 4

A.02 c.

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Facility l Comment:

Incorrect answer is'given in answer key-(0.736' delta K/K):

K-1

~~

=.

1.0795-1 L=

0.0736. delta K/K K

1.0795 is the correct answer.

NRC_ Response:

' Agree with. comment; answer key.will be change to 0.0736

. delta K/K.

TA.04'a.b.

Facility Comment:

This question is not appropriate for an R.0. exam.

I recommend that it be deleted. -It tests: knowledge and. understanding of 1/V. behavior' that an R.0.' does not need...The intent of' assigning.this material to our R.0. candidates to read was for them to gain j

~

a general' understanding of fuel and moderatorL coefficients of reactivity. ;This questionLfrom-

Section 5.81.of Nuclear Reactor Operations, p. 259,.

is too specific.

.NRC. Response::

Disagree with comment..The answer did not~ require knowledge of 1/V behavior for' credit; The question only required basic knowledge of mo'derator temperature coefficient not-specific knowledge such as 1/V. The answer key will'not be changed.

B.01

. Facility Comment:

This question is too' vague even though you. told the examinees which section (6.0) of the Technical Specifications to consider in their answer. Also, the expected answer lists items that an SR0 reviews as a part of approval of a request form (see procedure AP-4 II)..

An R.0. does not choose or approve experiment location.

I would recommend that this question be weighted less.

(perhaps'1.5 points ir.3tead of 3).

NRC. Response:

Disagree with comment.

It is unclear from reading AP-4 II, what is the responsibility of.the RO or SRO.

It is not clea rly ~ stated.1 A R0 should be cognizant of experiment Lin and around the core, and_how they could effect reactor l

operations. The answer key and question value will not be changed.

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C.03 Facility Comment:

Since this question does not specify to exclude poison section differences, the following answers are also correct:

R.R.

Shim Safety (SS) 1.

Different Lengths 24" 26" 2.

Different Reactivities 1/4 of S.S.

4 x:R.R.

3.

Grooved vs. Smooth Smooth Grooved Surface 4.

' Boron vs.1 Stainless Steel Stainless 1.5% Natural Boron

-1 Ref. Question and Answer from'1985 equal exam'B7.

'Also Sections 1.8.1 and 1.8.2 of the HSR indicate the following:

I R.R.

Shim Safety (SS)

H l '.

Solid vs. Hollow-Hollow Solid NRC Response:

Agree with comment. Answer key will be change to reflect all possible answers.

C.05 i

Facility Comment:

During training, we discussed and/or demonstrated what happens if:

1.

Blower motor is turned off at the switch away from j

the Rabbit control panel - rabbit stays in.

2.

Fuse is removed from the Rabbit control panel - wind gates are reversed so the rabbit'is returned to the receiving terminal.

l 3.

Rabbit permit' off in the control room - rabbit cannot be sent.

4 Although it was not covered in training, if the rabbit permit is turned off while the rabbit is in, the rabbit is returned.

I would recommend credit for either answer 2 or 4 above.

NRC Response:

Disagree with comment. No reference material was sent to substantiate facility comment.

The question dealt with operation of the solenoids. Answer key will not be changed, i

2

= 2 -__-__.__

L' '

+:

}

I D.05 a.

Facility-Comment:

Since we do not 'use the _ fission chamber (start-up-channel)-

as ar absolute power level monitor, a better indication of

'its range is simply the recorder and/or meter scales which-go from 1-- 10,000 cps.

I recommend this as an acceptable answer.

l NRC' Response:

' Agree with comment.

. ill accept either answer for full W

l credit. Answer key will be changed.

(-

E.01 I

Facility Comment:

'A revised answer for fast vs. slow scram was-sent just i

prior to'the exam.

This same information is enclosed again.

~

NRC Response:

Agree with comment. The answer key will be changed to the revised answer.

E.07 i

Facility Comment:

A revised _ scram list was. included in information. sent-just.

prior to the e~am.

It is enclosed again.

Please grade x

using new information.

NRC Response:

Agree with comment. Answer key will be changed to the revised answer.

I F.07 b.

Facility Comment:

There is.now a key bypass as described in Section 1.7.7 of the revised information in the HSR.

It is enclosed again for review.

Please grade according to latest information.

NRC Response; Agree with comment. Answer key will be changed to the revised answer.-

i G.03-Il Facility Comment:

This seems to be an administrative question more appropriate for an SRO. Also, the reference for the answer is incorrect.

It should be 20.101, not 20.201.

I would recommend that this question be weighted less (1.5 points instead of 3).

NRC' Response:

Disagree with comment. This question is appropriate for R0 and SRO level of knowledge. The answer key will not be changed.

The reference will be changed to be 10 CFR 20.101.

i 3

i

l l

G.06 Facility Comment:

The correct answer is 75 mr, not 75 mr/hr.

45 min.

x 100 mr/hr. = 75 mr 60 min./hr.

NRC Response:

Agree with comment. The answer key will be changed to 75 mr.

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CL LATO C

I O

J REACTOR OPERATOR LICENSE EXAMINATION FACILITY:

_ OHIO STATE ITMTVERATTY REACTOR TYPE:

POOL-MTR DATE ADMINISTERED:

87/10/07 EXAMINER:

HARE. E. I'.

Il' CANDIDATE INSTBU_91LQMS TO CANDIDAIEL Use separate paper for the answers.

Write answers on one side only.

Staple question sheet on top of the answer sheets.

Points for each

. question are indicated in parentheses after the question.

The passing grade requires at least 70% in each category.

Examination papers will be picked up six (6) hours after che examination starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY VALUE_

TOTAL SCORE VALUE CATEGORY

_14.25' 14.21 A.

PRINCIPLES OF REACTOR OPERATION

_14.00

_13,97 B.

FEATURES OF FACILITY DESIGN 14.00 13.97 C.

GENERAL OPERATING CHARACTERISTICS 13.50 13.47 D.

INSTRUMENTS AND CONTROLS 15.00

_l4,96 E.

SAFETY AND EMERGENCY SYSTEMS' 14.75 14.71 F.

STANDARD AND. EMERGENCY OPERATING PROCEDURES 14.75 14.71 G.

RADIATION CONTROL AND SAFETY 100.2 Totals Final Grade All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature j

s-NRC' RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Du' ring 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.

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.

3.

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

4.

Print your name in the blank provided on the cover sheet of the i

l examination.

S.

Fill in the dat,e on the cover sheet of the examination (if necessary).

6.

Use only the paper provided for answers.

7.

Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8.

Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

9.

Number each answer as to category and number, for example, 1.4, 6.3.

1 Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility literature.

1. 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

j

14. Show all calculations, methods, or assumptions used to obtain an answer l

to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed.

E g7, d

18.When you complete your examination, you shall:

p i-l a.

-Assemble-your examination as follows:

i (1)' Exam questions on top.

(2)

Exam aids - figures, tables, etc.

L (3)

Answer pages including figures which are-part of the answer.-

b.

Turn in your copy of the examination and all pages used to answer L

the-examination questions.

' Turn in all scrap paper and the balance of the paper that you did-j c.

i not use for answering the questions.

l d.

Leave the examination area, as defined by the examiner.

If after leaving, you are found in this area while the examination is still.

in progress, your license may be denied or revoked.

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99"3 L PRINCIPLES OF' REACTOR OPERATIONc

Paga 4-4.";

V QUESTION

_A.01:

(2.00) t Briefly EXPLAIN the difference between:

Ja.,

Fast and prompt neutrons.

(1.0)

Lb.

Slow and' delayed neutrons.

(1,0) ei

_ QUESTION A,02 (2.00) y t

' a '..

Expl'ain the1 difference between K-infinite and K-effective.

(1.0) ii.:

xK-effective.of a reactor is given as.1.0795 delta k/k.

What K-excess i

does,the. reactor have?

(0.5).

i

'What reactivity is associated with thisLK-effective?

(0.5) c.

l i

QUESTION!

A.03;

.(2.00) e..

Define reactor' period.

(1.0) ib.

JExplain thel term prompt critical.

~(1.0) a 4

i

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QUESTION A.' 0 4 -

(2.00) l How'does highly' enriched uranium fuel (U-235) ef f ect the modeeM I

b a.

temperature coefficient over' lifetime ~of fuel?

(1.0)

' * ~

b.-

'HowLwill this change if low enriched fuel is used in. future core loads?

(1.0)

,-)

.1

~

QUESTION A.05 (1.50)

What is the purpose of the " moderator" in the reactor?

(1.0) a.

l b.-

' Indicate which one of the following is considered an important l

aspect of a good moderator.

(0.5)

.1.

Low mass number 2.

-Large absorption cross section

'3.

Small scattering cross section l..

!~

(*****

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

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u Para-5 Af. PRINCIPLES OF REACTOR OPERATION i;.

te'4 ur

.a QUESTION-A.06:

(1,00)

Reactor power is;100 watts and increasing on a 30 second period.

How long.

will it.'take for the. reactor power to reach 10 kilowatts?- (Neglect; heating effects)

Show your work.

(1.0) 71 Yf t

. QUESTION.

.A 07

-(0.75):

How much excess reactivity is permitted by the OSU. Technical

' Specifications?, (.75)

-QUESTION ~

A.08 (1.00).

-t.

DEFINE the term Shutdown Margin.

(1.0)

QUESTION

.A.09 (2.00)

a.

.A step. insertion.ofja small amount of positive reactivity is made-to'a' reactor while critical in the very low-power range.

Describe

' the changes in neutron flux and why the changes' occur after the reactivity addition.

(Neglect heating effects.)

(1.0)

.b.

Describe the changes in neutron flux and'why the changes occur following a reactor scram from full power operation.

(1.0) 4 j

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

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B.,

FEATUREE-OF FACILITY DESIGg Pcgo' 6 9

y QUESTION-B.01 (3.00)

When an-experiment is being installed in the reactor, in:accordance with

~ OSURR Technical Specifications there are THREE (3) considerations the operator must keep in mind whe choosing a location.

STATE the THREE considerations.

g QUESTION B.02 (3.00)

From Figure 1, OSU Reactor Core Layout, LIST the components that are marked 1 through 8.

i 1

QUESTION B.03

.(1.50)

What is:the determining factor of fuel element lifetime and what is it dependent upon?

QUESTION-B.04' (1.50)

. Fill in the blanks of the following statements.

1.

The control system shall have a shutdown margin of at least in reactivity.

2.

-The regulating rod shall be worth less than

% in reactivity.

1 i

3.

The reactor shall be suberitical by a minimum margin of in reactivity when the maximum worth shim-safety rod and the regulating rod are fully withdrawn from the core.

QUESTION B;05 (3.00)

From Figure 14, Flow diagram for the water process system, LIST the

[

l components that are marked 1 through 10.

QUESTION B.06 (2.00)

STATE.the primary'and secondary functions of the water process system.

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

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[QL_^ GENERAL 10PERATING_ CHARACTERISTICS Pagd)7; g,

q.s J

i QUESTIONi FC.01' (1.00)'

.The.biologiballshield'.at-OSURR consists of light water and. concrete.

What-tare the radiation: levels.at 1 m above the' pool surface and outer lateral-

surface;when operating at~10.Kw?

1

[

}

.(2 00).

' QUESTION C.02 For the:following' items, STATE'the nominal: values'for each:

J a.

Recirculating / Flow Rate l

.. ]

+-

1 ib..

. Conductivity-J

'c.

Heat Exchanger (Chiller) Cooling rate i

d.

Pool Water: Heater heating rate

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.. QUESTION C.03-

-(3.00) ~

1, The regulating rod'..is identical to the shim-safety rods with the exception: I

~

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.of THREE features.-. LIST TWO of.the three features.

LQUESTION C. 0 4.

(1.50)

A a.

.How often'is conductivity monitored?' (O.5) b b.

How and'where is it monitored?

(1.0)

~

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' QUESTION ~

C.05 (1.00)

LIST'TWOL(2) ways to operate the solenoids that return the rabbit to the receiving terminal..

t i

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(*****

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

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- t Paga :8 j

h \\E,,_ qEtiERAL OPERATING _ CHARACTERISTICS 1

.. m l

l

. QUESTION Cf06

'(2.50) l

Explain why reactor startup cannot be accomplished without the Pu-Be, 1

.a.

1 source'.

.(1.0)

I b.

How is the source position indicated?

(1.5) i

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QUESTION C.07 (3.00) i

'What is the difference between the standard fuel elements'and the a.

.. control rod fuel elements?' (2.0) i b.

,What/is the reason for having the special fuel elements?

Consider i

all types.

(1.0) s 1

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

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D,,

INSTRUMENTS AND CONTROLS Paga 9

s QUESTION D.01 (2'00) a What is the dif ference 1etweer.t an uncompensated and a compensated ion chamber?

i i

QUESTION D.02 (2,50)

LIST the FOUR (4) monitored locations in the area radiation monitoring system and STATE their trip level, i

QUESTION D.03 (2.00) l a.

How many shim-safety rods can be withdrawn at a time (upward movement)?

(0.5)

I b.

What position does-the manual drive toggle switch end up in when released?

(0,5) c.

Choose correct answer.

A (LOWER / RAISE) signal to any shim-safety control rod overrides a (LOWER / RAISE) signal to any other shim-safety rod.

(1.0)

I QUESTION D.04 (1.00)

When is,the building exhaust air monitored?

(0.5) a.

b.

What type of detector is it?

(0.5) i l

QUESTION D.05 (3.00) j For the following instrumentation, STATE what type cf detector it is and its range.

I l

I a.

Startup Channel (Log Count Rate)

(1.0) l b.

Level Safety (1.0)

}

)

c.

Period Safety (1.0) l l

(*****

CATEGORY D CONTINUED ON NEXT PAGE *****)

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h;..INSTRUMENTSAND' CONTROLS' Page 10 3

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' QUEST' ION--

D.06 (2.00)

With' respect.to shim-safety control-rod assembly:

Where is theidash pot cylinder located and what.is the purpose a.

of this cylinder.

(1.5)

-l

?-

b.

What is conta'ined in the, poison section of these rods 7: -(0,5)

QUESTION-D,07.

(1.00) l Concerning the startup channel; Briefly discuss how neutrons nre l

a' re Distinguished from alpha, beta, and gamma radiation.

(1.0).

1 4

1 1

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(***** END OF CATEGORY D *****)

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, (1,1. SAEETY AND EMERQENCY'SYETEMS Page 11 f

~a

]

QUESTION E.01 (2.00) l EXPLAIN the difference between a fast scram and a slow scram.

]

~

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QUESTION:.E.02 (1.00)'

WHICHLTWO (2)Linterlocks prevent the operator from obtaining magnet i

current if they are'notfsatisfied?

4 QUESTION.

E.03 (3.00) l cFor the following lights provided for each shim safety rod, STATE what

each one indicates and its lamp color.

1.

Jam 2.

Down 3.

Engage QUESTION E.04 (1.50)

Concerning Emergency Power, answer.the following:

a.

Upon: loss of building power, what emergency power is supplied?

(0.5) 3, d

b.

~What TWO:(2) ways can you confirm the rods were on the bottom and the lp reactor safety shut down if building power is lost?

(1.0) m.

' QUESTION E.05,

~(2.00)

LIST TWO (2) ways the evacuation alarm can be sounded.

-QUESTION E.06-(1.50)

What are the' Safety System design criteria for the possibility of single l

electrical. fault disabling a scram function?

(1.5) j 1

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

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SAFETY AND' EMERGENCY SYSTEdii Paga'12-0

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' QUESTION-E.07 (3.00)-

LIST-15 items or conditions that-will~cause a scram.

,1 I#

'i

.. QUESTION E.08 (1.00)

Which.TWO-(2)' control room recorders do~not'have' scram functions associated with their operation?

(1.0) j d

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(***** END OF CATEGORY E *****)

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.y.

i

QUESTION F.01

.(2.50)

LIST FIVE:(5) of the six special. considerations an SRO should'be made

' aware ofrand initial per OM-08,' Reactor Operation Logbook Records.

5 !,

/

- QUESTION F.02 (1.50)

~

LIST.theLTHREE (3). times:or conditions, a complete set of readings shallt

.be made.

QUESTION F.~ 0 3 (1.00)

When a' stable reactor period has been reached in a reactor startup,. WHAT 1

'TWO (2)Lpieces of information shall be noted in the logbook?

1 4

QUESTION F.04

'(3.00).

'j

' LIST-the' minimum staffing requirements for the following operational conditions:-

l a.

Normal reactor op6 ration (1.0) b.

First startup of-the day (1.0) c.

FuelLhandling (1.0) lQ y

QUESTION F.05 (1.75)

LIST the reactor operator's responsibilities when a nuclear emergency is' 1

U declared.

j

)

QUESTION.

F.06 (2.00) g j

i J

Section 9.0, Surveillance Requirements of the OSURR Technical Specifications, states that-a reactor check-out shall be performed prior 1to1each~ day's operation (unless the operation is for more than~one' full day).

STATE the minimum check-out requirements.

(*****

CATEGORY F CONTINUED ON NEXT PAGE *****)

t 2--L-_-__--

m v..y

.c.=

..m.

,s 3:,,

({." BTANDARD'AND EMERGENCY OPERATING PROCEDURES Page 14 l]

-I

.o

'l

, QUESTION F,07-

.-(3,00)'

1 When would an operator want to. bypass a low level source scram?

f a.

- (1. 5 ) L c '..

d j

i:

b.

How is'.this accomplished (i.e., bypassed)?-

$y

'(1.5) i

' i i

b

.)

t e

i

- I i

t A

M 4

i

\\

l k.

l 1

1

(***** END OF CATEGORY F *****)

J f

L_._ _ _

m 7, m - #:. p

.g.m

~ _, _ _ _ _ _. _. _. _.. _. _, _ _ _ _. _

t.

Pags 15 jgc RADIATION CONTROL AND SAFETY' c

,q ;,.

p l'!

' QUESTION- :G.01

,(1'00.).~

Fill in the blanks:of the following. questions'.

~

's -

'a.

Ifl storing at sample'that'has greater than mr/hr contact dose: rate,.: place the sample.in a lead pig prior to storage.

I-

.b..

-Radiation: levels outside=of a radioactive materials storage facility; 2

mr/hr.

- should not exceed.

~

' QUESTION

'G,02:

(1.50)

'A material. decays at'~a rate of 40 percent per day.

Whatcis its half-life?-.

J y

QUESTION G.03 (3.00)

-According to 10fCFR 20,1anEindividual in a: restricted area.may be allowed

'to receive a'whole bodyEdose of radiation greater-than 1.25 rem per quarter when:THREE conditions are met..What are these conditions?-

~

l(Assume non-emergency conditions.)

QUESTION G.04 (2.25)

'During. reactor operations, Argon 41 is produced.

a.

What is its' source,. half-life and decay mode?

(1.5) 3L.

'[

'b.

Where is it produced?

_ (.75).

~

QUESTION

.G.05 (2.00) i.

Does-the; biological effect of 100 rem depend on whether it is a neutron or

. gamma dose?- EXPLAIN.

i I

e 6

1:

(*****

CATEGORY G CONTINUED ON NEXT PAGE *****)

h____m.-_._.

.2._.

m=wp=w.=..=-u;-_~__-_..._-...-._...............

?

i

" Q.

RADIATION CONTROLLAHD~ SAFETY

,Pegp'16 l

j

~ QUESTION-G,06

-(l'.50).

While working 'in an area narked " Caution,- Radiation Area," an operator.

-)

? discovers his~ dosimeter is off scale and leaves the area.' Assuming he'had been working in.the area or 45. minutes, what is the maximum dose he wouldi have received?

(Showallwork.and-stateanyassumptionsjyouhave~made.)

i n

QUESTION.

G.07 (2.00)

-STATE-the qurirterly occupational dose limit for whole body, hands a.-

and feet, and skin of whole bcdy.

(1.5) b.

What is:the dose limit for individuals under the age of 187

(,5)

QUESTION G.08 (l.'50)

'If the dose rate f rom a radiation source is 100 mrem /hr at 1 meter, what is the dose rate at 25 cm?

Show work.

(1.5).

1 i

.+q. -

Y i

k

(***** END OF CATEGORY G *****)

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

i

c _;.

w--

=-,===.aa uw -

m ;-_.;.x; EQUATIONSHEET I,

= ma'

'y a s/t Cycle officiene o (Network-

.) w = ag s m'Vot + 5 at2

• • )/I W I" E s'sc2 L

KE = 5 av2 a = (Vf - Vo)/t A = AN A = A e-At g

i

' PE = agh '

Vf = Va + at

.w = e/t x = An2/tg = 0.693/tg f

Wu d tgeff = [(t ) (t )

t b

[(ty) + (t )3 l

b AE = 931 am 3,jo,xx Q" = m"Cpat 6=UAst-I = Io *

• e

.Pwr = Wrah.

I = Io 10-x/TR TVL = 1.3h P = Po10sur(t)

HVL = -0.693h P = P et/T o

SUR = 26.06/T SCR = S/(1 -'Keff)

CRx = S/(1 - Keffx)

SUR = 26p/s* + ( s-p )T CRj (1 - Keffg) = CR (1 - keff2)

~

2

, T = (a*/p) + [(s - p)/ip)

M = 1/(1. - Keff) = CRt/CRo

' T = A/(p

's)

M = (1 - K,ffo)/(1 - Keffi)

. T = (8 - p)/(Ap)

SDM = (1 - Keff)/Keff p = (Keff-1)/Keff = AKeff/Keff A* = 10-5 seconds I = 0.1 seconds-1 I

p = [(1/(T Keff)] + [s ff /(1 + IT)]

e

'Ijdt=1d22 2

i 2

J P = (reV)/(3 x 1010)

Ildt 5 1d22 2

I = eN R/hr = (0.5 CE)/d (meters) w/hr = 6 CE/d2 (feet)

Water Parameters Miscellaneous Conversions

l' gal. = 8.345 lbm.

1 curie = 3.7 x 1010dps 1 gal. = 3.78 liters 1 kg = 2.21 lba 3 Btu /hr 1 ft3 = 7.48 galt.'

1 hp = 2.54 x 10 Density = 62.4 lbm/ft 1 aw = 3.41 x 106 Btu /hr Density = 1 gm/cm3 1 in = 2.54 cm Heat of vaporization = 970 Btu /1bm

'F = 9/5'c +'32 Heat of fusion = 144 Btu /1bm

'C = 5/9 ('F-32) 1 Ata = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-Ibf t ft H O = 0.433 1bf/in2 2

hm S-

]

~

~

lf "AIMPRIRQ1fjJS OF REACTOR OPERATIONl '

Pagei17>

h J

L'j.,,,

'o

.c 4

g,. ANSWER; A.01.

,(2.00)

.)

o.;

y 9 a..

.Fastineutrons are of.high energy. levels _and prompt' neutrons-areithose 4

rel' eased:atithe timeLof fission.

.. ( 1. 0 ) -

1 i b.-

Slow.neutronscare of low-' energy levels:and delayed neutrons. appear at.

some' time after the fission event due to fission' fragments.

( 1. 0 )-.

's c

REFERENCE N p

y

" Nuclear' Reactor! Engineering, pgs. 11,-90 n

.a'

.1

ANSWER-A.02-

-( 2. 00 ),

3

'r a.

- K-infinite"isithe. multiplication constant for a-theoretical reactor?

iwithano leakage.

K-effective-takas into account neutrons lost due-to slow ~and fast leakage (K-eff =,K-inf

• slow and fast non-leakage.

probability).

(1.0) 4 nz b.

- K-excess =-K-effective -1 = 1.0795 -1 =.0795 delta'k' (0~.5) _

j

~

(K-effective.-1)/K-effective.

(0.5)

.I c.

Reactivity-=

(1.0795 -1)/1.0795

=-0.~00 delta k/k;

=

~ REFERENCE-Nuclear. Reactor' Engineering, pgs. 152, 234

[

EANSWER

,A.03

'(2.00) a.

- The. time required for the neutron' density (or flux) to change by a.

~

factor e.

.(1.0)

- b.'

When a reactor is critical on prompt neutrons alone (i.e., a reactor

~

- became-promptferitical when the reactivity is equal to the fraction

^

of delay neutrons.

(1.0) q i

REFERENCE '

\\

i Nuc1' ear Reactor Engineering, pgs. 236 and 248 I

i

-i

-)

(*****

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

a[

j fu _. -.

=: ;. z u _ _...

A.

PRIHCIPLES OF REACTOR OPERATION Page 18 ANSWER A.04 (2.00) a.

By using highly enriched U-235, sufficient U-235 will be present toiprevent the moderator temperature coefficient from becoming positive.

(1.0) b.

.With slightly enriched fuel (both U-235 and U-238)'Pu-239'is l

produced, having a positive reactivity effect.

This can allow the l

moderator temperature coefficient to become positive after a period of operation.

(1.0)

REFERENCE Nuclear Reactor Operations, pg. 259 ANSWER A.05 (1.50)

Neutrons of low energy have the highest probability of causing a.

fission in the fuel.

Most neutrons are born at high energy levels.

The moderator reduces the neutron energy level.

(1.0) b.

1.

Low mass number (0,5)

REFERENCE Nuclear Reactor Operations, pgs. 438, 445 ANSWER A.06 (1.00)

.P = Po*exp (t/T) 10,000 = 100*exp (t/30) in 100 = t/30 t = 30*4.6 = 138 seconds

= 2.3 minutes (1.0)

REFERENCE OSURR Requal Test 1985 Question A.2 ANSEER A.07 (0.75) 1.5% delta k/h (.75)

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

{

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&- -.. - - --. - -...~ _.,... -.._ _

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A

~PRIEIELES OF REACTOR OEERATION' Paga 19-e.;;

. l-ll t

> REFERENCE-OSURR. Technical Specification4~1.3' y.

4. <

p:

' (1.00)

']

ANSWER' A.08L

'Shutdownmargin.isthe; amount'ofnegativereactivity'insdrtedbelow'the.-

minimum. critical height'.

REFERENCE-OSURR Requal Exam 1985, Question <3;a.

-Q LANSWER

. A.09-

. (2.00);

.I tThere'is a " prompt. Jump". increase-.in neutron flux due to the

a.

-immediate~effectsJof prompt neuttons.

(O.5)

Power then increases on' l a stableiperiod the value of which is determined by theDamount of.

. reactivity? inserted and the delayed neutron generation time..

-(0,5)-

b.

Following.an seram there is a prompt drop-in neutron flux as prompt.

neutron. generation is stopped.

(0,5)- Flux then gradually decreases as delayed. neutrons continue to be generated from the decay of the precursor groups.

(O.5)

REFERENCE C'j.

Nuclear Reactor Engineering, pgs. 90-93 l

,.i i

l 4

f c

.i l

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

I.

r, mn iB.

? FEATURES OF FACILITY DESIGN

.Pago 20'

~ ANSWER

B. 01' (3 00) i

.No-experiment shallibe installed in the reactor-inssuchEa'imanner t' hat:

bonitors.

l.

.It could shadow the nuclear instrumentation system i

2.

Failure of the experiment could interfere with the. insertion of a control' rod.

3.

Failure of the experiment could credibly result in fuel element

damage.

T

.(3o@ 1.0 pt each = 3.0) l 1 REFERENCE j.,.

LOSURRl Technical Specifications pg. 5 Suhm 4 3.00):

(

ANSWER.

B.02 1.

Regulating Rod 2.

Uncompensated ion chamber 3.

Compensated ion chamber (#2) 4.

Compensated ion chamber (#1) 5.

. Uncompensated ion chamber.

i J

6.-

-Fission chamber.

4 7.

Shim Safety Contrc'l Rod (#2) 8.

Neutron source (Pu-Be).

'(8 @.375 pts each = 3.0)

. REFERENCE OSURR Reactor Description and Hazard Summary Section 1.2

-l l

(*****

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

j

?

i

m ;;x;;9-,.:w ;a;a.s u-a.,-

.w.

FEATURES OF FACILITY DESIQB Pego 21 g

w e

a

-l f

.r l.-

aANSWER

.B.03 (1.50)'

-l L

~

Corrosion of-cladding is the limiting factor.[0.75]'..

It:is' dependent =on water purity [0.753 REFERENCE

'il -

f' l

.OSURR Reactor Description'and Hazard Summary Section 1.3.1.

l ANSWER B.04

( l'. 50 )

l 1.

6%

2.-

0.7%;

3.

1%

I(3'@.0.5 pts:each =~.1,5)

J

~ REFERENCE i

OSURR Technical' Specifications 4.2.3 j

i s

p ANSWER

'B.05

.(3.00) 1 1.

. Chiller 4

1 2.

Water Heater 1

J 3.

Ion Exchanger k.

-4.

Cuno Filter I

5..

Centrifugal-Pump 6.

Mixed Bed Resin Exchanger

~7.

Centrifugal Pump 8.

Cuno Filter 9.

. Ion Exchanger 10.

Flow Meter i

l

(*****

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

1 l

l

a-

a:..w.

c a;

.w

.,, ;;,... :::;,.. ;. a. u-- =.;..= u = ;.. ; a :.=:-.. ::-------------

.g.

1B.

FEATURES OF FACILIT DESIGN Pago 22 m.

REFERENCE Figure 14 of OSURR Reactor ~ Description and Hazards Summary 1

ANSWER-B.06 (2.00)

.r s:

l The primary purpose is water purification [1.0] (to retard fuel cladding j

corrosion) and secondary function is cooling and/or heating [1.0].

. REFERENCE

-OSURR Reactor' Description and Hazards Summary, Section 1.9 i

i i

l i

s a

i i

s i

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

.2 tz;w _ a a z --. _ _ a- _.. _

a____

j;

<4..

C3.. GENERAL OPERATING'CARACTERIGTICS. Paga 23 fk l J. ANSWER C.01 .(1.00) .i o, - E ' Pool Surface: < 5 mrem /hr @ 1m (0.5)3, j ' Outer Lateral Surface: ' < 0.25 mrem /hr (0.5) REFERENCE g. OSURR Reactor. Description and Hasards Summary Section 1.4 -l l l -~ ANSWER C.02 J2.00) a. 10 gpm t/- 1 gpm i b ', 0.1 - 1.5~mhos/cm + 2'mhos/cm i c. 0.5 degrees F/hr +/ .1 I d. .3-4' degrees F/hr i (4 @ 0.5 pts each = 2'.0) l i REFERENCE i OSURR Reactor Description and Hazards Summary Section 1.1 x ANSWER. C.03 .(3.00) 1.. TheLpoison section is attached directly to the drive screw without a magnet and hence does not fall into the core when magnet current is cut off or reduced. 4 I '2. There is no magnet engaged indicating light associated with this control rod since there is no magnet. + 3. There is a 10-turn potentiometer included in the drive train to 'i provide a signal to the servo control systen..

• b i n Ln 1.5 pts each.= 3.0) y' @ @ dggu

= Ob h k (2 of'S required @ 5.h.'dhwd M REFERENCE g, V_ ilqss SS = 4 x RR q OSURR Reactor Description and Hazard Summary Section 1.8.2 b'.Q'R, is W W s 5 5 h y tcve q, gg.3 p.bo 6Uu), 55 io /Wo M M g'0" g.Rgis h/k,5 a W \\ (***** CATEGORY C CONTINUED ON NEXT PAGE *****) { g

7,. ., _t, *.

s

>[ if i GENERAL OPERATING CHARACTERISTICS Page 241 1 lw l li ' C.04: (1.50) sANSWER a. . Monitored each operating 1 day. (0.5) b. =By using a remote-reading conductivity probe [0.5] ocated in the water process: system piping [0.5]. (l'.0)

REFERENCE 0SURR Reactor Description and Hazards Summary Section 1.9.2 ANSWER C.05 (1.00) 1.

Manual pushbutton (0.5) 2. -Automatic mechanism. actuated by a timer. (0.5) j -REFERENCE OSURR Reactor Description and hazards Summary, Section 1.5.5 ANSWER C.06 (2.50) The react'or cannot be started up due to the low source level scram. a. (1.0) .b. .At the control console on a single dial indicator [0.75] and upper and lower limit lights [0.75]. (1.5) i b REFERENCE OSURR Reactor Description and Hazards Summary, Section 1.7.10 ) (***** CATEGORY C CONTINUED ON NEXT PAGE *****) 1 I

ywmy qv :,.;~x ~ - - - y. 5- [ [ C,. IGENERAL OPEEATING CHARACTERISTICS- .Paga-'25^ ":.:e 1 i u _ 3.00).

i, ANSWER

, C.07: ( n v - aC, 'Standardifuel elements consist of'10 fuel' plates (and each contains 'f e Ea"nominalT1401 grams'of U-235)'. (1.0)~ Control / rod : fuel elements are modified standard fue$ elements with - H the~centralifour fuel plates removed.- The central two; fuel plates are absent 3to provide: a channel:through which the poison.section. -moves.. The' adjacent fuelfplate position'on each side;is fitting with anCaluminimum' plate which-acts as:a constraining guide for'the? poison

section.

(Each element contains a nominal 84 gramslof U-235 distributed equally.amongLthe-remaining'six1 fuel plates.) . ( 1. 0 ) ~ 1 ' bD Four partial fuel elements were originally planned for the reactor to l provide. reactivity and/or flux _ shimming for the' core. -(0. 5 ) : 'Exce'as reactivity for experiments could be obtained only if a'more heavily loadedLelement was acquired. (A ten-plate element containing-a_ nominal-178 grams of.U-235 is used.) (0.5) L ' REFERENCE .OSURR Reactor: Description and Hazards Summary Section 1.3: x ..s J \\ ~<- 1 ? l L W l (***** END OF CATEGORY C *****) l [ 5 : h-L

gx.x x:., -.. _ :2. u m u _ ax _ _ __ _ _ _...m m _ _ _ _.... _ _.,_ _. _ _,_, m a jh. INSTRUMENTS ~AND DQNTROLS 'Pags 26 t NSWER-D.01 '(2.00) -An uncompensated ion chamber ~ detects gamma rays as'well as. neutrons. A compensated ion chamber:is constructed so that gamma ray induced currents-are automatically' subtracted from.the total current reading; thus the resulting net current represents only neutron interaction (2.0) -REFERENCE Nuclear. Reactor Engineering, pg. 313 i

LNSWER D.02 (2.50) 1.

Pool Top 2. Thermal-Column 3. Beam Port-Area 4. Process System (4 @.0.5 pts each = 2.0) . Trip Level: 10 mr/hr. (0.5) REFERENCE OSURR Reactor Description and Hazards Summary Section 1.7.9 j ANSWER D.03 (2.00) [. a. One .(0.5) b. Neutral (0.5) c. Lower (0.5) Raise (0.5) ~ REFERENCE OSURR Reactor Description and Hazards Summary, Secticn 1.8 (***** CATEGORY D CONTINUED ON NEXT PAGE *****) l i n, -l__._--.

p p. .c.y .:y a.z: u. ;.. w :,; =;...; u _.... _ ;- _.. h 'g.: o b. -INSTRUESTji_AHD ' CONTROLS: Page 27L .f i >r. 4 a

ANSWER.

~D.04 (1.00) JWhenever reactor is in operation. (0.5) .a. b '. GM detector. (0.5) y REFERENCE 1 0SURR Reactor Description and-Hasards Summary, Section 1.7.11 l ANSWER D.05 (3.00)- ] a. Fission: Chamber 1 (0.5) Shutdown approximately 1.nne with startup source in place und fission chamber @-lower limit to nominal 10 Kw with fission chamber raised approximately 72 cm. 4(0.5) oR O -10,o00 eps b. Uncompensated Ion Chamber (0. 5) - ' 4 Shutdown.to 150% of full power (0.5) c.- Compensated. Ion Chamber (0.5) Infinity to +1 sec over full power range (0.5) f i-REFERENCE -OSURR Reactor Description and Hazards Summary, Sect' ion 1.1 l 9 ~ LD.06 (2.00) ANSWER a. Located at the base of the guide tube. (0.5) The purpose is to slow down speed of rod after a scram as it l reaches its lower limit. (1.0) .b. Boron-stainless steel (0.5) REFERENCE-0SU React'or Description and Hazards Summary, Section 1.8.1 and Figure 1.3 l (***** CATEGORY D CONTINUED ON NEXT PAGE *****) . -t d_Em___.._ __.

y m m--7; = .=__.;.;s_______ h. D. INSTBUEENTS AND CQNTROLS Page 28 ':<:'g, n., I 1.

ANSWER D.07; (1.00) i' The pulses generated-from ionizations caused by fission fragments are much.

-larger than those?of' alphas, betas, and gammas. Therefore, byLsetting . disc. only pulses.above alpha cutoff are detected. (1.0)1 l i 'I -REFERENCE .OSURR Requal'1985, Question 2.a., Section D 1 i 1 4 l l k a l i I i m f ( l ( I i l l l I I 1 1 l l 'l (***** END OF CATEGORY D *****) i l l .) 1

v,....n X ; -n;a_,_..._..;._.;_,.,____2____,__,,,__,.,___,,__._.__ I. SAEEIl AHD_EMEBQENCY SYSTEMS Pege 29 i LANSWER E.01 (2.00) h ).% h hd M: ' ~T M agnet control amplifierp thr uf,th: cig. bus - j/ fast scr m._ _g ca the shim-safety con ol rods W h h l., & rn f) ) /' l(y55 N & rom the magnet pc=:r cu;;11::. % N A slow scram rermoves power % b M M % % % M C.in.A OSU Reactor Description and Hazards Summary, Section 1.7.6 ANSWER E.02 (1.00) 1. Control and Instrument Power 2. Key Switch (2 @ 0.5 pts each = 1.0) REFERENCE OSU Reactor Description and Hazard Summary, Section 1.7.6 ANSWER E.03 (3.00) 1. Indicates control rod malfunction [0.75] Lamp Color: Red -[0.25] i i 2. Indicates control rod lead screw at lower limit of travel [0.75] Lamp Color: Green [0.25] 3. Indicates control rod engaged to the electromagnet assembly [0.75] Lamp Color: White [0.25] REFERENCE i d OSURR Reactor Description and Hazards Summary Section 1.8.1. l I \\ (***** CATEGORY E CONTINUED ON NEXT PAGE *****) l

mxmumyy_ va.s# s - -...- - u - - - _wm. -. - - _ _ m _ _ m --. _ - y ,,f /

Paga 30-

, S K. -SAFETY AND Edgi;BGEHQY: SYSTEMS-o q.m ?' .~n-L 1 b -, L YANSWER E.04 1.50)' ( i L' a. (None.:.toicontrol room instrumentation)'; only. emergency. lamps and -(0.5) .. security: system have backup' batteries. I ~ 1 b.- - Either by. sound'or by visual if a flashlight is available

j to' observe that the rods.have dropped-(when 'p, control rod and u

connection to: connecting rod are visible. When down, connecting { rod and connettion top surface only are. visible). -(1.0). l !j REFERENCEz Wl OSURR Requal: Exam 1985,. Question E.2. %l, O

ANSWER E.05 (2.00) g Can.b~e operated from the control console by a manual switch.

(1.0)J - 1. ,'2. Will sound automatically:if the annunciator acknowledge. button ~ is-not pushed-within 12 secondsiafter trouble; signal is received. (1.0) REFERENCE .i -OSURR'.ReactorLDescription and Hazards Summary, Section'1.7.8 1 q 4.- , ANSWER E.06-(1.50) j it. i The safety system shall be' designed such that.no single electrical fault which' partially or' completely disables the automatic scram function,'can,. 1 cif: any manner, impair or disable the manual scram function, and vice i ,4 -versa. (1~5) REFERENCE ~OSURR Technical Specification 5.2 \\ I '\\ (***** CATEGORY E CONTINUED ON NEXT PAGE *****) 4 i -_----l-__--_-_--..l-L__

EZM '. U.. :. z _ a.. _ _ _ _._ _ ..T ~ ~ - ~ $g, SAFETY AND_EMEB9EECY' SYSTEMS' Pega 31 j

l..

AMSWER E.07 (3.00) 1 j, l Safety System Continuity '.L = s. Bulk Shielding Facility Area Manual Switch 7 Control Rod. Area Manual Switch 't Thermal Column Area Manual Switch 2 Rabbit' Area Manual Switch Control Console Manual Pushbutton CIC Power Supply #1, Loss of High Voltage Relay CIC Power Supply #2, Loss-of High Voltage Relay l ' Servo System Error.. Relay (> +/- 8% of setpoint) Period Recorder Microswitch, 5 Second Period Linear Level Recorder Microswitch, 120% on 150% Scale ~ WI;) l (r:lfunctic.f

"- t; Srplifi^ 0) %.

4-S2f Ot, Ti;dlO \\orga , Leu 4 ~ Low Nn e4 Vg-w " u. u,. r & % Y f h ( " ~ N3 ~ gw \\] @ ',% Low Source Level (the LCR recorder must be indica ng greater than two counts per second) 'Startup Channel Use' Switch (must be f.n the "use" position) T . Log-N-Period Operate Switch (must be'in the " operate" position) i ~ Power,to Linear Recorder ~~ ~ Power to Period Recorder 4 Power to LCR Recorder 2_.._. n..,, a _ _ i m,,. %n %_n m HV Failure from Safety Power Supply Period Generator Off Switch (must be in the "off" position) L Ie,.^.rp FSult 'A short period signal (*****' CATEGORY E CONTINUED ON NEXT PAGE *****)

. : sa w. .a.-..._-......,_-.......___.. 3 s- ~ >>'d A highlpowar:'_lovalf -(15 required ~@ 0.2 pts each =-3.0) H. 1 4 REFERENCE-OSURR Reactor Description and Hazards Summary, Section 1.7.6 i[ j 0 ANSWER E.08 (1.00) Log-N -Effluent- --(2 @ 0.5 pts each : 1.0) REFERENCE-s OSURR.Requal Exam 1985, Question E.6 1 - +; s , l' 1 i l i b ( -1 ) i i I i t i 1 i l i i l l i i L j (***** END OF CATEGORY E *****) l l 1

s e. F; SIAEDARD AND EMERGENCY OPERATING PROCEDURES Pego'33- ' lia. } u i l ANSWER F.01, . (2. 50 ) ' 1.. Anyfunplanned scram fi; ) 2. B.E. after loss of building power /u i di l '3. Adjustment of compensation voltage .j 4. Using the' low source' bypass 5. ' Installing and removing the RY-4 jumper 6. Using less than a nominal 30 second period j (Any 5 of the above @ 0.5 pts.each = 2.5) REFERENCE OM-08, Reactor Operation Logbook Records, pg.'5 ,~- ANSWER' F.02 (1.50)

1. -

Every. hour 2. 'Every operator change l 3. Every power change if the reactor is then leveled se+ REFERENCE I, OH-08 Reactor Operation Logbook Records, pg. 1 -i ' i ANSWER F.03 (1.00) 1. Control rod positions l 2. ' Period produced 1 l -(2 @ 0.5-pts each = 1.0) REFERENCE n OH-1, Reactor Power Changes, pg. 3 (***** CATEGORY F CONTINUED ON NEXT PAGE *****) j l t__ -

o c (BTANDARD ANy EMERGENCY OPERATING' PROCEDURES / Page~34-T J 1h 'n*n, h;. wm ? ANSWER F.04[ '(3i00) 1Two ortmorenpersonnel','at least one:of'which is/a licensed j a. reactorfoperator, shall'be in the building at.the timeJof reactor j i u operation. za

• b.

[First startup;of the: day'- 2 persons shall beLin the' building, r' one of'which-shall-be a licensed senior reactor operator;) ~'c. 'A minimum:of three staff shall be'present during fuel. handling.. z { , One'must?be.a'licensedfsenior reactor operator.and'one must be"a' 1 licensed reactor operator. MREFERENCE q

OSU AP213,1 Personnel: Required for Reactor Operations, pgs. 1 and 2

'I _ ANSWER. F D05' (1.75) i The Reactor Operator is. responsible for performing-the following:

Depress lthe~manu'l scram button on the Control Console [0.-25],.

a a. 'announce over the intercom that the building is to'be-evacuated [0.25]',Jand assure that'the buildingievacuation' horn is sounded [0.25]. b.: Turn off,the. building fans as he/she leaves the Control Room. '(0.25). LPick.up both-a neut'ron-sensitive and gamma-sensitive survey c. 4E instrument [0.25], as well as the'NRL sign-in logbook'[0.25), an'd 50 proceed to the Van de Graff-Laboratory.[0,25].

c

• 4 REFERENCE

-OSU, EP-01, pg. 2 1 .I i \\ 1 i i i i I (***** CATEGORY F CONTINUED ON NEXT PAGE *****) $s . te w ____un _ i_z_ __ __ _ _ n___ _ __ .j

l es t STANDABD AND EMERGENCY OPERATING PROCEDURES Pega 35 <w . e -- i ANSWER F.06 (2.00) The check-out shall include, as a minimum, the following: l' A visual inspection of the core and experimental facilities. (0.5) a. b. A functional' check on pool water temperature and co5ductivity devices. (0.5) l c. A functional check on operation of the annunciator system. (0.5) i d. A front ppnel calibration of the instrumentation and~ area radiation monitoring systems. (0.5) REFERENCE OSU IM-03, OSURR Pre-Start Checkout, pg. 1, OSURR Technical Specification Section 9.0 ANSWER F.07 (3.00) a. This is used on1 during a core unload - loading operation when i conducting approach to c,riticality tests. (1.5) Mb a Mn _etk_ _Q M M( reen the _nr 3., b, This is accomplished by gun;;ru.g m..: i nn "A") eNLY11 1-n th; esfety r"4 +~ 'The jux;;r is installed :n d the bn:h ' th

1-u :: a concela.)

1.5) 6M-REFERENCE 1 l I OSU IM-6, Use of Low Level Bource Bypass, pg. 1 .s 2$1 i i I (***** END OF CATEGORY F *****) .l

mn. ww.w :., a a a;.:.. a. :.a. :a......a... - - a -- - - - - -.. - -. - a. ~46' L, LTh RADIATION CONTBQL AND SAFETY Piga 36 ~t.gj r. D ) 1 ' ANSWER G.01 (1.00) ~ a.. 100 'i' l b, 5 a,. REFERENCE. / 'l l Labelling and Storage of Radioactive Materials, RS 1, pg. 1 ANSWER G.02-(1,50) l

N=Noe [ - lambda *t)

(0.5) (100-40)/100 = e [ - lambda *1)- In.0.6 = lambda-l .51.= lambda 'T 1/2 = In 2/ lambda (0.5) T.1/2 = 0.693/.51- =-1.36 days (0.5) REFERENCE Nuclear Reactor Engineering,-Glasstone and.Sesonske, pgs. 31 and 32 ANSWER G.03 (3.00) q ( 1. -Does not exceed 3 Rem / quarter. I y 3 't;;. 2. Radiation history is known and recorded on NRC Form 4. l i [1^ 3. The dose rate received when added to his radiation history does .not exceed.5(N-18). (3 @ 1.0 pts each = 3.0) REFERENCE 10CFR20,/01 I j l l' l l (***** CATEGORY G CONTINUED ON NEXT PAGE *****) l

g'.. M,. 'Paga 37' ,g ;77 a-r C ~ s_ O;u 4 RADIATION CONTBQL AND SAFETY pp. isg e.., p y. .si JANSWER G.04- '(2.25). -. a..

Half-life 1.83 hrs.;-

/. 'Ar-40 ' (n,.. gamma) jar-41; f ' ~,. ' Decay.by beta emission f(f -(l'5) a. M (Half-life:must:be within 20%) .i -. b. : =Ituis produced in air in the experimental facilities. -('.75) -REFERENCE- .OSURR Reactor Description and Hazards Summary Report, Section 1.5.5 ~ I LANSWER' G.05' (2.00)' No,[0.5]. The unit remcalready. considers the different effects. Rem is'a' biological-unit,' thus different radiation causing the same, dose'in rem 'should have the:.'same offect [1.5).

REFERENCE l10:CFR 20.

ANSWER 'G.06 '.(l'.50) i 9 O 'A radiation area is >:5 mr/hr. '1 N 'A"high radiation areaLis > 100 mr/hr. { q; I ~ ~ iThe maximum dose rate'in a properly marked radiation area is 100 mr/hr. J

The maximum dose'is calculated as follows

4'5/60'x 100 = 75 mr h (1.5) REFERENCE \\ 10;CFR 20 '(***** CATEGORY G CONTINUED ON NEXT PAGE *****) l v... --.-l-.__

rp .x. m.r, vg_n:; a au __7_.._w__..;___2.___c;..__.________ 1: y. F [ q ti. RADIATION CONTROL AND EAFETY Paga 38 1 7., - Q l an

ANSWER-G.07 (2.00).

1.25 rem / quarter '9-a. Whole Body 1 c 18.75 rem / quarter f,(: l I' c. Hands and feet' L .if. Skin-7.50 rem / quarter b. 10~ percent'of.the above limits. ' REFERENCE-1 10 CFR'20.101, 104 m '1 ANSWER G 08 (1.50) 1 I1D12 = I2D22 .(100 mrem /hr (1 m)2 = 12 (.25 m)2 1600' mrem /hr : I2 (1.5) l REFERENCE OSURR.Requal Exam 1985, Question G.1 i % Y 'h. y; t. +, 4 j.- . s., 1, g (***** END OF CATEGORY G *****) (********** END OF EXAMINATION **********) &_--_-}}