ML20234E829

Exam Rept 50-116/OLS-87-01 on 870602-04.Exam Results:Two of Three Reactor Operator Candidates Passed.Exam Encl

ML20234E829
Person / Time
Site:	University of Iowa
Issue date:	06/26/1987
From:	Burdick T, Hare E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20234E826	List: ML20234E822 ML20234E829
References
50-116-OLS-87, 50-116-OLS-87-0, NUDOCS 8707080011
Download: ML20234E829 (42)

Text

,

U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-116/0LS-87-01(DRS)

Docket No. 50-116 License No. R-59 Licensee:

Iowa State University Nuclear Engineering Department 261 Sweeney Hall Ames, IA 50011 Facility Name:

Iowa State University UTR-10 Examination Administered At:

Iowa State University, Ames, Iowa Examination Conducted:

June 2-4, 1987 1

Examiner:

M O'

06 - 95~- Yr ~7 Elizabbth A. Hare Date d7 Approved By:

( & [f,

[O 2 52 Thomas M. Burdick Date Examination Summary Examination administered on June 2-4, 1987 (Report No 50-116/0LS-87-01(DRS))

To three reactor operator candidates.

Results:

Two candidates passed.

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DETAILS 1.

Examiner Elizabeth A. Hare, Chief Examiner 2.

Examination Review Meeting Refer to the Attachment 3.

Exit Meeting On June 4,1987, at the conclusion of the examinations, a meeting was held to discuss generic findings made during the course of the examinations.

The following personnel attended the meeting:

Facility Representatives:

R. Hendrickson, Reactor Manager-R. Williams, Reactor Supervisor NRC Representative:

Elizabeth Hare The items discussed during this meeting are listed below:

The examiner noted that the general condition of the facility appeared to be uncluttered and neat.

I The examiner noted that overall the candidates did not know much about the maintenance and upkeep of the 13 volt batteries.

The examiner l

acknowledged that it is not the R0s responsibility for maintenance.

However, the examiner felt it would be useful if the operators understood concepts like specific gravity.

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ATTACHMENT Facility Comment A.02 Control re ' worths are certainly affected by temperature if there are large temperature changes.

There are no large temperature changes in the UTR-10 and we do not use this information in our training program.

(Please withdraw this question from our question pool.)

NRC Response

{

Disagree.

The question is valid and will not be deleted.

The UTR-10 has the capability of achieving higher temperatures than the normal operating I

temperature of 80 F.

Your facility Safety Analysis Report states the following:

I "The temperature set point may be adjusted to accommodate various experimental conditions, but the maximum setting may not exceed 140 F.

A bypass valve may be operated to achieve higher temperatures, but the upper temperature limit of 180 F for the process system must not be exceeded."

Since the UTR-10 has the capability to have large temperature changes, the operators should be aware of how this could change control rod worth.

Facility Comment A.04 Claim:

1.

Reactivity and Ak are assumed to be equal in the solution of the problem.

If k dkthen k -k 1

2 1

Ap =

not k -k 2

i kk 2 1 If ki =

.8, then Cr3 = 57 cps if Ap is the same rather than 40 cps if Ak is the same.

Claim:

2.

This question is more of an algebra test than an indicator of knowledge of reactor physics.

NRC Response 1.

Partially agree.

If a k value is assumed to solve for count rate then 1

a different answer will be obtained.

However, the problem can be solved without that assumption.

2.

Disagree.

This is not an algebra test but a functional operational synthesis of parameters.

Facility Response 8.03 The components could also be labeled by detector type:

(1) is a compensated Ion Chamber, (4) and (5) are fission chambers.

1 a

e Also, the arrows to the control rods appear to terminate at the drives, not the rods.

NRC Response Agree.

The answer key will reflect both answers.

Facility Comment C.03 1.

It is not clear that there will be a loss of reactivity as water spreads through the graphite.

2.

If the thickness of water between the fuel and the CIC were to decrease as a result of the leak, the count rate in the CIC would increase (just the opposite of the drop in the CIC output as we approach N0L).

This effect would appear to be an increasing power level and would drive the reg rod into the core.

(We request that this question be removed from our test bank.)

NRC Response The question will be modified in the exam bank.

However, the facility did not provide any documentation to provide validity to their assumptions.

Facility Comment C.06 The students will surely state that T.

= 80 F as per the table of normal operatingprocedures,ratherthan90$"anoutdatedvaluefromtheSAR.

NRC Response Agree.

The answer key will reflect both answers.

The facility is requested to update the SAR and training material prior to next scheduled exam.

Facility Comment E.02 The DOWN lights on the console are actually orange or peach color, rather than white, as stated in the SAR.

NRC Response Partially agree.

When console is lit the DOWN lights are not illuminated

" white" but a pink / peach color.

However, when they are not lit they appear white.

The facility is requested to update the SAR and training material prior to the next scheduled examination.

Facility Comment F.08 The phrase " exact seqbence" implies operator actions are required.

Note that if the console is energized, the coolant pump is energized.

The minimum count rate is required to withdraw control rods, but not to close the DV (so three and four are in the reverse order).

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NRC Response Disagree. Your Safety Analysis Report states the following:

"If the scram circuit is continuous, the calibrate and test controls in their " operate" positions, the minimum power (count rate) is above the setpoint, then the dump valve control is activated and the dump valve can be closed."

This infers that the dump valve can not be closed until the minimum count rate is above setpoint.

From a safety standpoint, the operator would want to ensure that the nuclear instrumentation was working prior to closing the dump valve and allowing the reactor core tanks to fill up with water.

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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION ot FACILITY:

_IQW9_ST@T(_ UNIVERSITY ___

REACTOR TYPE:

_ U_ _T R _ _1 0_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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DATE ADMINISTERED: _@7/gp/92________________

EXAMINER:

_ HARE 1_E.A.______________

CANDIDATE:

IN518U[IJONg_IO_C9NDJDOIE1 Use separate paper for the answers.

Write answers on one si de onl y.

3 Staple question sheet on top of the answer sheets.

Points f or each l

question are indicated in parentheses after the question.

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

Ex ami na t i on papers will be picked up six (6) hours after the ex ami nati on starts.

3

)

% OF i

)

(

CATEGORY

% OF CANDIDATE'S CATEGORY i

VALUE TOTAL SCORE VALUE CATEGORY l

l

_19:59__ _15:29 A.

PRINCIPLES OF REACTOR OPEPATION

)

_13:09__ _1219s

________ B.

FEATURES Or rACILITY DEEIGN 13:29__ _11 @h C.

GENERAL CPERATING CHARACTERISTICS

_15199__ _12:9h

________ D.

INSTRUMENTS AND CONTROLS

_13199__ _13._;b

________ E.

SAFETY AND EMERGENCY SYSTEMS

_19199__ _13:95

________ F.

STANDARD AND EMERGENCY OPERATING PROCEDURES

_13 99__

12:@p

________ G.

RADIATION CONTROL AND SAFETY 101.00 Totals Final Grade AlI war I.

done on this e x a rr. i n a t i en is my own.

I have neither given nor received aid.

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Candidate's Gignature i

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NRC R'dLES AND GUIDELINES FOR LICENSE EXAMINATIONS Dur irg the e deii ni s tr a t i on of thi n ex ami nat i on the i ol1owing rulcs app)v:

9 2.

Ctm ot a rm ca, the ex em:iscti on means ra n au t on.at i c denial of your applitulaen m uJ

.t r i ! rl r t. L u i t lii me e se em e penalties.

2.

Destecom trips are to be limited and on]y one candidate at a ti me may Ieave.

You must avoi d alI contacts with anyone outsi de the exami nat2 on room to svoid even thc appearance or possibility of cheating.

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PrlNC1"LES-Or REACTO7 OPERATION PACE

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QUESTION A.C5

( 00) c.

E" plain &ch at the c'iffcrerca iT betwcen ' -1 mf i r; te and I-ef'ective.

2,0) b.

K - tif ccti ve Of a reactor is given-as 1.0775 delta k/k.

What

-excets does the reacto-have"?

(0,5) c.

What reactivity is associated with this I-effective 7 10,5)

DUCCTICN A. 06 (1.50) a.

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

( 1. 0.'

b.

Indicate which one of the f oll owi ng is considered an important aspect of e good moderator.

(0,5)

(1) low mass number (25 2a ge abscrption cross section

(!)

small scatterirg tu r ce s secticr DUECT!DN A.07 (2.00) a.

Describe hcw sr ope at - ccn determine when the re6ctor, o cr] t i c.3'.

c' u r i n g a startup.

'!.05 l

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A person being trained on the reactcc has d evel op e d a system fo' reactcr t, t a r t u p s,.

He noted thct the last time he dic a startup the reactor was critical at 5000 cps.

He reasons that for his next startup (sore months later) when he reaches 5000 cps the reactor will be critical.

It this persor*s system valid?

E p2cin ycur ansse.

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DUEST CP A.GG (2.00' Dces U'R-10 r eed a neutron scece in the reactor" Explain.

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Li: t 4 cf tr e 5 use-c for t h e b ri d ;;e ' c r ar.e.

OL'ECT!ON D.02 (2.00) l The inlet ccclant tem;;cr a t ur e ccntrol system was designed with an appe-

-end loner temperature lim;t.

What are the derign resspns 3 o5-t h e E ta

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u CUEETION D.03 (7. 00)

From figure 1 (drawing-of UTR-10 cere), list the components that are ms-ted 2 th u S.

DUEET*DN E,04

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Fill in tSe t)cnEs.

1.

The masimum allrwable tocras resetivity dar:mg. cold, cleon

(;3:1 s.o n - f r e e ) c;eration c4 th e r eactor is 2.

The minimum s h u t d o <. 7 margin, wi t h the bcast safety type rod a s su m :? d.

t navcil able, it geester thah I

CUESTION D.05 (1.00)

What pi eces of equipment a s. 5.J e e s t h e posi tive posi ti oning of fuel c pent 6 3 's e T,b l i e t h3 thin the core tanks?

(1.0)

DUE ST I CP '

3.06 f2.OO)

Why cust a ri,imum level of C inches (65 gellone) re ms:ntal,ed ;n 'hc I

dung t 3 r ' "'

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QUESTION C.01 (1.00)

Gi ce two desi gn features of the.rebbit tube that serve to limit the radiaticn h a:: a r d during use.

OUECTICN C.02

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- at the UTR-lO reacter and brie f l y descri t e Fow each.is veed 4cr.

DUCSTION C.Q!

(2.00)

You art oper ot i ng at 10 liW end the primary Icop springs a l ea :- at tSe top of the core tank and begins to wet the cf ap hi t e re f l er: tor.. Wha t ' wOul d the. r eac tor contro! 2,yste1 do if it wer :e i n ciuto?

Why?

(2.0)

DUC2 TION C.04

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t Ib9 in1Ct and Oiit1Cl p i~ i 116 r 'i C C;il Gn t tC:T p Q r O t u t' 0 7, drC mOaGured b y 0 + I t yp o' d e '. c : t e r '

Whc!

J u n c t i c.n o arc p r c v;. d e d by t h ern' n..

r-i. T Cu.e q r.

(

...r-s. 3 s nw 4

w.

en

' ', C t is t h e, djf'E"En e b e t.;E C'-

1.

UnC C T; E'

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iC'

- bir.bgr^

ry er e T T -

s.'

D. O. '

( ~e..'M.. )

evwa s-L a.

List the area mcnitors and #a t they mor. i t c r feediation and *parific plant areas).

f l. 5) b.

Provide the norme! a: a m setps:nta.

( C. 5 '.

t, W"e7 cre they operabic" (1.5) m, e r r -e

• C. e, i n.

,%. ~e

,.r..s s*

u..-.

1 s

w t

• s i

l I

9 I

'T' b a3

=1 4

1*-

-O i.e a.- mi

&a V.C e. b. 4 4

.- 4 4

.- 9 f

V a...

4-4 g"

M C....g4 f

p., p &.

.I.

hI-.Ts p $. m.;

6 4

w [J t 1e n.,t

,a.) 4. k.

v J,, I, 4 p

fi s6

/

i "if G e C C. d i '. I c T,

3rG 3dt2If: Od.

L.i ? t thess THMCC c c n d i t.i o n s.

n, m e 7 i nn.

r.. p. c

-... q s,

, 4 L%

4v -

w

~..- i n q a tcr.stic ade of Ope-st:cn, xhich rcd.does the autexstic centroller c c n t r ol

m m e + v r, e :

r. e s /

(; -

w

..w s

4.'

-.- '==

e.

I b

4 se t

L h

N i E f3 y J-3 L.E d d '

I *. C '.

m,,--,y r..

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e 3

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vs l[.

(

rI

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(' ih 4, hu h h h [f'i

,h f(

bh([

3 f, 7

e, 4 e I

1

1

{:.

.O

{

{*

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2,2. 2 2..:;. _._ = :.

d 3

s f

• f f. e *m**

• T f.1.e

{'

1. N1 1 M g*. D} '

I on '*

a 6'

w a

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E.x p 1 a i n t ", c dignifi;anca c' t"e f a i1 - ;a / e' pr iaciple of the r c' a l

., ; s,

=%

i L' 4 4 e

% 4 a w' r h'

(

- + '

t I

g i

1 m j a-f y i m o 7

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t.,s 6 - s A _

w a.

A e

{/' p. 4.

B.1

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)

4.

W%.

e**.. e pe.

b. m r

e L. h e

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e. em -

g.

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c.. _

3p p

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r.

um.

.a aw

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s.,. r

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r a 6 -.

m m

3.

rcd 2 c.11' c in t h Ca i r D 6 x i %.Ti o i i h d F ;1h'61 DOS;tiOr d.

t'E 1 1.J.s

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Drd; ca r e in their ma<: mum : n;cr te d pot;t cn c.

Ereer

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e Lf L

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L La s.

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r. 1 r r y

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r.. v.*.

t ".. m., e i e

m sw-i.

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n.. e. t

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r. a

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A. s.

w.

w r

p.a s, 3.

t+,g

&. o-.. m> w,, p g<r_,

e. m. r_

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6. 5 n..

a _8.

A e, s

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~.

+

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s a..

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e r, -

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QUESTION. E.05 (2.00)

' I' c r ' the (cIlowing ccndit;ans, stat e whet her a.CCRAM, ALARM, ' or ' !N~E7LC""'

i CN MOD WITHDGANL i.s re ejved.

4 f

4.r.

~

3*

.E.

g r.e.

",. m. w= 1, M. n 4 f4 v

4 1.

6b pd. O w. D-a 4 tr:g :.

-- e 5

'I 4

qs.

L,_.,

" m....s g.. ~ 4.

.. } n.. p '. i

. e. e h o. q-4 *' j r, H a,c.,

4

... o 5

j c.

Peried icss than'5 te::nds

' j d.

C001 sr t o.J t l E t t 0;'Q (T ;" a t U:70 g r E d t C " thSte I de C ' d E O P O D E I e

l'edc ator leve; g estcr than 55 irches f.

Di cni-er Moni t or grerter t he 5t normal ' f tal l power background; 5$

S, u w

,,, a a 6i + 5 a

W' 6

+.. -

Wh y i s c oc'. i n g of the fue: -not.rea;2 ed to:lmging a strae" r.s a 14/

e. n...-

4. n_ r.. s m e...

/

9.

, e n >* ' ? '4 w [

l b., (4

.I - ',S.i b

3 b,

1

' M y.p 4, h b "

4. I 1.

- 6 1W

' k-we

r.

• t p

la 72 4 a.I e6 g. $ r.., e +

L. ~i

r..

1. a, (m.

- s. )

m

^<

,y w

a NJPT

t. h d U d yI'D I'. W C 1 C S ~' i

• T I' # C 7 t 3 I "I C*'e Ch.3*in(iI L that {,EnCrnt9

t. [ p 's Of th !

E0f Ct) L'j2t9m CL i GQJi"Ed by IC I6ble C-1.

4 l

l ti eu 4 CND Cr c,T:CCRy E 4: ****.

r*

r' r' ' m LP" A "1 t.v e r.-r N C Y d""= rmT.1' t:=9 "P ^h = t"

!. = "

raat-sO n

'~

^ ' ' ' " * ~

.-,x

':.:=,

LW w

-2

..=

e=----

j W

.l j

1 I

I I

1 1

l mJ re

,-,n..

r.r"

( * ' "i. a.

r u --

4_.

Under what two canditions can the atorage ga:es for special nuclear w

]

mat er l a! (CNPS b e u n l c c i e d

]

n.,iir e.,ns.J

e.. n..

(4,. r: U~ s List th? ts: Ren:ter Operat ~- At: Ob dLring fJO! trankfOr.

( *. 5 )

i l

gi i. r a 7nn r - w-( ~.. e u, v s u-v List the four Emergenty. Action L e v e :;, at Iowc Ot at e 'Jn! vor si ty T r om l e a r *-

1 we ver e t o act.t severe, Ci t r e ? Y. LW

,, 6 A

e. 1. c. q s I

_s Whe9 a e pe*; men'

n.

bei".g inste!Ied,

1. , a t.

i r F ce m a t 2. c n shal1 t %c R e s '. c r

n. r.. t t~. 4. c..

1.

r. u_....., - u

,m

.m 1

n., -., -

r.

p.,e

.. e c.

s

_u.

What is t h e c,i m i rnu m s t s f f i n ;;

epvired ')

ibe I C L' T5 #c-t ". e rcec'c- :n ot s e c.: r n ? *'

l I

D i i r e. v,

• C.p~i r. n.../

( ~.. (.i n. )

Other tFs>

p r c : r e d su i n s t r u t t e t' by GFC", describe the r equi red operstcr at t10.c upt-rc:cipt of t e f:11cw ng alarm;:

a.

Lc. rodc e ator fIc%

t, Lcw naderctor tempersta e 1

c.

Lr. nater le va: an rt.e d tuH 1

l 1

.-r-,

.m..

1 s'

[/ ? [)C.-2 d L. e i n Or d o --- tL

,c3'.

<;3 :. 6 I *s C I.LM 3 I E e%.L ' a * 'y I,i i V i.3 '. 2 *1

'c

~.'*i

.4 a'

t.

tb C.; c ; ( i,3 cr yr.usge.'

.. - c.'s

t a n t e g "

1 l

/., p q g t r' O *< w"" e n. p s,i t

c ne t 1 r,!, - - -'r m m.y k 'r y v

• t * ** 44ty :i s

- 1 w

e

-u s

-t

.~

F.

CTANDARD-AND EM

--..--------------- ERCCNCY CPERATING PR

- - - - - - - - -.- - - - - - - - - -.O C E D U R E.C.

PAGE 11 c.

DOECTIDN r.ee

-(c.503 Lirst the excet sequence which mrt b 2.- f o l l o ws*c' in a reactor startup i n-ortler to :st i sf y the startup logic' (2,3) 1 I

i j

i

}

1 i

I i

l

(+4*+4 END O~ CoTEOCRV r

• 4***)

i

E.,

R AD I AT I OfJ-CO!.'T70L AND Sr,rETY

.PA3E 1.?

q QUEETICN

'E.01 (1.501-i

.,)

A materi.31 decars at a rate of 40-pe :ent pe-day.

What is i t c h el ' -1. f 75

( 1. e..

a

- i 1

l l

ni er-,1 C t r. o.

... n. r. )

a 2 a

A leak has cc c'_:r ed in the pr i mar y coci an t' s.y st em.

Describe where the viater ir collected at, where it will go and what nast be done befc're it can be discharged.

QUESTICN C.05 (1.00)

Fill i r, the blant.E.

If srear survey rusa'.tn e> ceed dpm per __,___._ _ cnG, a d d i t i c r,a !

mess.p eme te will 6e porfarmed tc identify the scurce of contamincticm,...

f 4.. m.,

-. i C e., t m,

r..-),.

<,...ess vu

+w w

a.

W5: l e working in an s%e mer ked "Cautico, Pe,d i 3 t i :n Ares.P (1.51 an cperstcr dis:cvers his dosi met cr i t, off scolc and leaver the area.

If he had been cric.ng i r; the are6 for AS tirutEE, what it the nsv m _; r. dare he s h o u ', d have received?

I n i, r e.,. u,,,,

v.rc

,. o.. r.. >

e-va_

~

Dur i ng reactor operatic,s, Argco-41 is produced.

piw..

i w_..__,,..a.._.,

.., s,. _...r _

-, _ a.,

,).et a..,

u s-a.

b.

W ere 3L ;t p r od.s c c d

l1.5) l 1

ev.'r._e. t.*

r. N. _.

( _m. n. o. t

.u~

1 Why doetn"t t"e bi:1cgir.c1 eIfcci ai irO Ren depe"d Or whether it :I :-

i r r: t r on o-qaw a d o s e ~'

E p ! e, i n.

4

($44t4 " f T r.. w". "_'!C V v"'

" "'Q T i t l' : {. n.

'E V T P 4 *- ".

.t y 4. w g $

I w

4 --.

w

u. -i s

--__U

C, RAD:cTICfJ CO!JTRCL AND E'AFETY PAGE

.12 '

-4 t

QUESTIDN G.07 (7. 00)

Acccrding to 10 CFR [0, an a rdi vi dua! 'i n a restricted area may bc s ! '. c h e d to receive a.whol? b orJ y dose of radiatien creater-than 1.25 Rem per qucrter when t hree cendi ti ons are ene t.

What are there conditions' (Assume non energency conditicrt) l

'i (4i4t* E'T 9I Cb*(([IY [

4 & t.* i )

fa49 4 $ 1 > $ V. / 4 9

[','O Or [X/'P]N!!T!CN s' A t *. i A A A y S +tpp15 i

EQUATION SHEET i

~

Cycle efficiency = Ret Work (out) j 2

w = ag a = v,t + %at b

W E = aC a = (vg

.v,)/t A = AN g = v, + at A = A,e KE = lony v

PE = agh a = 8/t A = 1m 2/tg = 0.693/tg W = vAP t (eff) = (t )(t )

q t

AE = 931 A:n g

(

)

[}=$ CAT

-IX

~

I.Ie P

o

-UX Q = UALT I=Ie Pwr = Wg*

I=I 10 *

~

o (t)

P=P 10 TVL = 1.3/p i

e /T EVL = 0.693/p t

P=P o

i SUR = 26.06/T T = 1.44 DT SCR = S/(1 - Edf)'

/1*ff )

p SUR = 26 1 CR, = S/(1 - E

)

\\ g,,J 1(

eff}1 "

2(

eff)2

~

T = (1*/p )+

[(f

• p)/1 p]

T = 1*/ (p'- T)

M = 1/(1 - K,gg) = CR /CR g

O T = (3 - 0)/ 1,ggo g, (3 ~ gdf)0 II ~ Eeff)1 P"I eff"I) eff eff *ff gDM ~ (l ~ Keff)/Esff

~#

/K

[L*/TK,gg ] + @/(1 + 1,gg )]

1* = 1 x 10 ' seconds

~

T p=

P = I(V/(3 x 10 0) 1,gg = 0.1 secnods~I z=u Id =Id 33 2y WATER PARAMETERS Id =1d g

2 1 gal. = 8.345 lba R/hr = (0.5 CE)/d (meters)

I gal. = 3.78 liters R/hr = 6 CE/d (feet)-

3 1 ft = 7.48 gal.

MISCELLANEOUS CONFESSIONS 10 Density = 62.4 lbalft 1 Curie = 3.7 x 10 g,

p 3

Density = 1 gm/cm 1 kg = 2.21 1ho 3

Heat of va;orizatiou = 970 reu/lba 1 hp = 2.54 s 10 BTU /hr Heat of fusica = 144 Stu/lba 1 W = 3.41 x 10 Btu /hr k.

1 Atm = 14,7 psi = 29.9 in. I's.

1 Stu = 778 f t-lbf 1 f t. H o = 0,433~, Ib f /in 1 inch = 2.54 en y

F = 9/5 C + 32

j

~ C_4.' _ _P_R_ _I N_C_ _I D L E_E _D_C R_E_ A_C T O_C_ _O_SE_R_ A_T_ _I D_N_

M"E 14 GNEWEf?S

- ID'WA OT' ATE UN!VERCITY

- 07 / 06/ 02-! M.RE.

E.A.

i ANE WE P' A.01 (0.00) a.

art cutrar tf er to those at h2;h e n e r ;,_ levels.

(0.51 C

P r o.i p t rcutrens -efer to tsare r e l e n t-e d at the time

r fi c si c..

(0. T )

b.

51 a.+

n e.a t e c t e are euter t o'

oo emergy levcis.

f 0. 5 :>

Deityrd nt% t r on s a r e t h e s e wh : r',

appea' at scme ti me e f t e-thc. fiction event due to f i s s.i c n product decay.

(0.53

)

1

{

r, Act:vity refe 2 to the rate c r esdioac ti ve decay.

70.55 Gesuti.ity c:.p r e : 3 e : the deviaticn of a r e c c l. c r from the critical c aridi t i on.

( 0. 5 )

REFERCtJCE Reactor Operation P r o.i e c t for ISU UTP-10 p u e. m. _ n,-

ps o +-.

z~.. m<>

-a.

e s s

3.

Core rea;ti+1ty

.E dsr>essed.

The temperature in:rcare j

e OiskCC 0 C' L-9 : i, CFC E :E L O c' th; c.ac cr E t cr.

TherC i s I

] S.r. r.

T, " de r.;

• i r "-

• n[

.- J *

.n. n r.

+ l- ^ ~-.' n. g h

.J *,

r" 3.,

s y.

k ',f E.

4._.

.f4, 4

i' 8

tt v'c i

4

. n 4.- s.e..') *.

e e r4 n - p== 4 b=

b p, s

. 4-4

~ J m..e au, pa., e

,eu r.i m = e s,=. c a.d e,

a.

r.re, - e3 c m...

3 wnu u.

a_,.

6 'j lhe p r.. b o b.: 1 j t y cf ; c :,', p g e ;rto k control. rcd in;ridLe3, t h t-c4fcctivercIs of t"e c Opti Ol ; rds i f' C f OGE0.

Q el' V Q ~? f ?_ V_

w _

De3cto-O p e r s t..:- P-rtext t o

! CU UM 1.^

1

[,s t. e s., r r i

/,.

(< ~

g..e I

es

.s NC, cb N P f 'f Qet$ C 1 o L E :'" (C

.),

Ihe f " 3 C. I ; c ' I d 1 C b O "a j E IC n E _' ( r U n po;2131;On per gener:.ticr i 3 ;F,c ) ; er f gr e rp31 re :ti vi ty a :.' d i t i on s.

Therefore, i t t:Ecc mere gene ct; n tu J_ t c r r '; cs!

C+

!h? nur Eubr ? 8. ; 01 CCU-t r4te, i1.0 t r F.. p r._ '., ** r p $9

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1 t ru i r-i g. e,.

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s a v e,

r. rgwr,, pw a. r q r, e n,

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s. pp e,

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(

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t4.. i

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wrr~s o<<

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<. o. n s,i i r e.

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v u. t.7.

1 f.r, r

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1.

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1..a. f4 _

s. /.- 4

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I.,

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s

-n.

r. y. ~ e,

n, c f.r., _ ( ~..,, v g4. i..

m.m

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c'/c)<,.

I m_ e. t 4 3, n

v r e.,

., e. ? f g *, ( + _

p e, s.4 ) f r,., fc),4.

_ i: n. f

e. )

r r

l n g,. ~. - *'.m r

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A g g e

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ut

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a c

c.,en j

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c. r,- v. e r a._

o-n _,m.

o.,

m.r

L.m 1..,,

I s.J

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i

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s..

4 s_m-r -_

f4n... r,,.. r-

• I..

m...

( ~_. e.,, r t.6m i

s s.

V -i n f i n i t e 2s

t. h e ultiplicatica comitart T.' r a t h e or e t i c.n l r e r. : t e r s it' terr : t s: 0;2.

1 o f f e t. ' i ve taket jnto acccurt n o., t r r m L Inst da to 21:w and fort lockage (1: - rf f k-inf *

=

Li ra cmd f.as t no -2e4 sge pr ob spi ' i t y. >

(1.O)

L-2ffcct:ve 1 1.0795 1 b.

D-c"c Is =

0.0795 d21ta k

( '.'. 5 )

=

t.

PeatL2v: ty' (1 -ef f cet i vc 1) /k - e rfective (1.0795-1)/1.&'95

=

O. 07 3L. :"c1 t a } /1:

(O.5)

.',,.e.,'.--

t

• L I L..

L rj m. 4.

& w r. 3.-

e.

r

= -..

f.

r., p

• c.i

.c-

• n f

.J A

w 4

.a 1

1 agp,.*

A er

, ~'

f

,,.4g,,;

-(

9_,,..,,. -.

4., 1

._g g

p.

L.,

.f.4

_i_.,.9.4.,

d.,.,f o

c a.

6 yb

,,,gg g

.s..,.,

s I*'"'"

'*l t*C 4.. O M!!'

N9L' ' * " ' *:

2.i C t [. EI h i i] h G f'l O r i.} ';/

,..j.'.4, 3 w.

~s s...:.

A. L. r.

...r.

[**.*,'

's C *s. p 1

( 'a O'

c.

L wur -

.u

.1 s.

u w

er n.

u,

.) % (,.

p 4

A c-e.

s -

a

.e

A.-

PRINCIPLEC'Or D OPERhTION PAGE. 6l

---

.CACTOR l

r ANONE.RE.-- IOWA CTATE UL:IVEPCITY

- 0 * / OL/ OCil lARC',

E. A.

i t

i a

q e

.-r 1_

t l

Dr:cter Operatien rcject for ICU UTR 19 o

i fr.c.. w.. p

+,. e. 7 g. c. m..

r v

2.

Obser.c period s n ;' f l u; I c v r.31 ;r:t cTentaticn.

Whtm paver ;cvt1

.c.tinuc to i nc rcre end p e-i ;.' re-a:ns p it:ve s'ter rd withdravs', the res tt- :s super r 1 t1:5,1.

? t ' e e x a c t. c - i '. i c e l positi n iE di!Iituii ta d ficrertic e from s ub r e i t i t. s l mul ti pl i: at; cn.

(1.'

b.

Nct vclid (0.51

- The ourt este at :r;tica! it a functi;r c#

clarting c c in t.

rate t scu r c ta and the shutdc.4n mergin.

Al oc sever al months latt.,

b'.2 r r u p, poisons, and sny changes in cuperimentt wi!

have some offett.

(0.5)

P. r F r n. E e.. r_

m i4atto-Operation Pr oj ec t for !CU'UT9-10 WSWER A. 00 rr.oc>

4 ow

,g.

, e.>. c, )

ns -.

un.

_m.

)

t: have e m _ r i me cur + ;evc2

,.15 c < c bo:Fgrou-d to

'O.C) i r c.y r s I r: y l e n e : t. a

• j o n iu wo-rinq c o r r ry c t } y,

-.g

_a,

c. u-...4 a

+ _. r ub

• .4' ' : '4

'=v'.. *w 4 c.'

--'a-l..-

v c".. s u _ +% i.t.' '7

( 6. m, m-r awo m

et20tigE ir the C C r Er.

pa r.p rN. F.

Peac t or C'p e-a t : c P.cjcct rr ICU UTR-10 e

L i'

i l-1 i

L_

E _, F_ _E. A_i u7 E _S_- O_r _ _F.A. _C.I. _L.I. T _Y_D E..S_! G _N PAGE 17

-87/06/02-HARE, E. A.

)

I,NEWEDD -

. I EWA. CT AT E UNI'1ERO TY' i

k i

ANSWER' B 01 (2 CO)

L: fling reactor shi el d closure 2.

Fuel transfe cock i

r O.

Iv03 Storiage pit C C i e '~ G00 plUQV 4

P e cc e. s t. pit covers 5.

Der vi c e en p er i men.t needt (4 0 0.5 pts cach 2.0)

Will accept other c or e:t answers r

REFEFENCE e A. F-Tc,

.sw s

s ANCWEP D.02

( 2. 00) i i

j Upper Li mi t :

the design 1.mit cf the dump tank (1000 F)

(1.0) mcwer Liait:

e -t 61. sh t d by e.<

cLs reactiv:ty and c i ri mu n :5utdro, e qui - e:nen t.

( 1. 9 l

!!EFERENCE IEU SAP pg. 4-40 i

- q 1

ANGWER D.O!

(3.00)

Date:ter f @ Mb 1.

Multirange Linear, Neutron j h g g,or 2.

Cafety Rod, 3.

Shim Safety - Rod, P

. h, e 4.

Lc; & L i n t> s - Neutron Dc.ctor, 5.

Log t-L i n e e r Neutrcr C et ec t a;

• CA1W ben ~

6.

Cefety Fod, hn p_

7 9 g u l 6 t i n g

"!c. t',

pg g g O.

Neutrt, Cour ce d

pr e _ R r.e r r.

6 vw6 f_- ' I F f., f f.+ s -. a -

[.[

I' p

3.

FEATUDES-OF FACILITY DECION PAGE.. 10 ANSWE.RC !- - IOV4'G~~ ATE UNIVERSITY.

.-07/06/02-HARE, E. 4.

A'JGUER

.D.04 f1.00) 1.

0. 5'4 delta I./ t* cc O. 7 0':.

(0.5) 2.

O. 4 *'. de;tc t /t e t-O.62t.

Io.5)

PIFERENCE

)

2Eu EAn pg.

4-+

ANOWER D.05 (1.DO)

Ey the end-pcsitionin; d e vi : e s, located'on the loarr belted spacer assemb1y.

( 2. O :-

' REFERENCE 1

IEU SAR 4.2.2 ANCWER B.06 (2.00)

A minimum level ~ murt te m:intaited in orde-to protect the stect hrater c ti1.

1.01 a n tf tC prtv:de a net post ti ve cactien head to.the pumps. [1,C].

REFERENCE ICU CAR 4.

v ANEWER S.07

! 3. 0 0 'e IEU SOR 4.5-3 PEFEPENCE I';U C AP 4.!-9 i

i

m Eg I

l'g I

lll i.

h

).

t:

l' Ii

[

,fb I

I

! "ls

^

i l!

y

}..

h g';

o OI i t k

N I; k m k

{

E s>l y

1 Q

h L

1

'X II h

<J G

/

I g

d la

lh H

w m

o I

M' p

g

$s 1

= n@

\\

• i u,,

lll h

b Figure 4.3-0.

Reactor cooling system t!

4-26 4

h C.----- NERAL ODERATING CHARACTERISTICS PACE 19

,GE- - ----------

ANSWEDG -'- IDWA ST'TE UNIVERSITV G7 /06/02-HARE, E.A.

A ANCWED C.01 (1.00)

Uces filtered compretted a,ir (0.5' E>5aust i s f i l t erer' 'th u HEPA filters to.5)

PErERENCE ISU SAR 4.2.7 fe)

ANSWER'

.C.02 (7.00)

Experimental facilities most frequently used and examples of experimental apparatus emp1oyed.are:

~

--Pneumatic irr&diatior' facility (rabbit tLbe):

This fac!!aty 10 used tc irradiste small vol u t:#e sampite in all fo'ms.

.e.,

so!!d, l i qui d, cr gas.

(1.C)

--Vcrtica; central st-ince-fi nter nci -ef l ec t cr ' :

With this stri,ger encscd, spene e vidietett iet6ven cccc t ent.s-bc ce s s sveilabic for i n;e-tic-of e g ; i p,m e n t a ging from

v ge s:;re meutron detecto : te a rusctc-oscil; stet cnd t;,ilar +p;&retas ts:ed r s i 'a r s t i n g c-otstir; neutrcn absorbi-g e4 pterials.

' 2.0'

--Hcri antal centrat stringer fthe mal column):

W;th this e

stringer removed, Epace in line with one ccFe tar k io available tc a c c on tr od s t e equipment ranging from neutrtn detectors tc a cc111 mating tube for eatectting a neutron beam 4or d i f f r a c t.i on mea sur etten t s.

( 1. 9)

Rr_FrRre.r ICU SAR 4.2.7 l

l

^.1 P* t er m s ve Q

. f. *Ta

/M. ^%q' \\

e

- u 1

s b.. t h d e a vs r egul ating rcd to compr Late for loLo of reactiv;ty vs ' i i c h occurs as tvcter spreads through the gr opSi te.

r e-r*n " r "w 1 L e.,.'

• r,,,

• e U ".,f< C

4. ".. "-

1 l

C.

CC"EPAL DrERATINC CH

---

cnACTCPI'37.:.CD CADE 20 l

A. NSR'E.r' c - - I og g OTATc UNIvtp;;TY

-C'/ O L/ 02 4 ' A7E, C. A.

ANCWER C.04 r;,CO)

Co v t a n t-l e 15 are c c i r o.' ' c.'t b7 e f i n e c' ca er f i c, pipe in each t er tanL.

Lese: va ice E ; '. 7 t ? y vith flow, fl.0)

-.- - r ;...

'JLc f

I C L1 EA7 t. 5. ~ ( t, 1

I r_vt. r-c. e... e_.

c.,.

c

s..

It wet c h a E *.i n tc r' i n : m. c s the l o c '_' t, f restron signa! [:.0: due to c: tcEs nater act2n; as

.2 neuteon ad gamma shic1d []. O: (after hasIng e,.cccdc-d iPo 1 Gi El c c r c sp an d i n;; tc the.nfinits ref1cctor t h i c k n e s t. ).

1 ptrERO;CE T Ci t r

• F>

n"'. C. "."

s

. a A N ~,1 J E P C.06

( 2. 0 0

c,,c,g(,gygg

,6/

gog 7

1.

W

• C ee ;r cs s F l

2.

I h.LrOrhCE / C '" f Ci

) F IC l

l 7 4 / - {

T

., a 4 /- 5 de3reus F,{@-$ f

&$ p(DM 4

I '. C c9

,o.

n.. e,

&e. s L:-

s i

1 I'EIER[NCE v e./ ed c *- r, e.~n E a J ' ' '

5 -3 %m. A C

• e

%)

l l

t I

9-q y

a

.m e_. e.,

eeuu.

y_.._..

g_

.3..;.

m

,c-

.n r r; g r~ ~.._5 s -

,r,,

_ -. 7

• ?

4 d.

e e

A

_ _ _-_ _ A

i-CCNERAL OPERATING CHARACTE

'C.

---

RISTICS PAGE 21 et4Cis'EF S - ~ I Cl4 A SThTE'UNIVERCITV

-87 /06/02-IIARE,

E.A.

l l

A N S.'tr!

C.OC (2.00) g 1.

Full-load fuel plate 2.

Ifal f l oad f uel plate 3.

Duartei -I cad fuel ristr 4

Durrmy pl o t es (4 0 0.5 pts ca:S =

". 0 5 1

l R E p c ni.,,

t-s-

ISU SAR Ecction 4.2.2 1

l 1

I

D_ _. _ _ _I N_ S_T_R_U_M_ E_N_T_ S_ _ A_N_D_ _ C_ C_ N_T_P_ O_L_ S_

PAGE 22' ST'TE UNIVERSITY-

-97/06/02-H.ARE, C.A.

ANSWEGO

-' IOWA A

AN0lJEO D.01 12.50)

Retistance temperature device, RTD (0.5)

(INLET t e:rp e r a t u r e, TIC-3,) Los tenperstu e c1 arm, a u t orna t i e contrc1 of secondary w a t er f l oa, and dump va:ve clceure inttrltch if minican inlet temperature is not sa ti sf i ed

( *.. U )

w

( C _(t ; e t te ps e t,.; r c',

T I -;. ) high teTqeraturc a l a r r.

C O. 3)

REFEPCNCE i

ICU SAR 4.4.T ANSWER D.02 (1.50)

An uri c c rp en s s t e d 2on charter detect; gsema rays as wcll as routrons.

A compensated ;on charbcr is constructed sc that gamma ray induced cu"rcmtc are outcmatically sAtracted fram the total current reading; thus.19c recult2n; ret currcet r epresents or; y neut on 1 oter cc t a en, (1. 5) i 1

p%r r e r, r,.~. E.

Reacter Cpcret. cme Project; f;r ISU, UTn

.10, pg. 2 6 ~' 7 ANCWCQ D.03 f3.50) a.

Couth and west perimeter of reactor [0.25], detect abnormal gamma ray intensity [0.25], including the fuel pit (0.253. Ncrth and east perimeter cf reactor [0.25] detect abrermal gamma rcy-I nt ersi t y (0.25].

NDeth monitor also checks f cr acequate shield tank l evel e '- - c.,J.

6 A

]

b.

5 :- r ; m / h r.

( 0. 5 )

c.

Sauth and oest operatie at all t i mes :0.75].

- Nor t h and east cps 7.ble i

ahen t"c - cactcr cencol e in e n c=r g i t e c CO.753.

n e _ r.. e r. - r.

w*ww

't (~ t !

C.' HQ

,P+ e c8'e e

• aw.6~

M e C 4 4 ti:

A k4 r

1

,1 M

4 ww

-a s

i

D.

--.NGTRUMENTC. A ND CONTPCLC..

PAGE 23

.I l

l.

?NOWr_BC --. I C"CA GT'AT E UN I VE RD I T Y 07 /06/ 024'ARE, C. A.

, m r e,

,,c. s

.n... 4 g..., r.>.-

The r: ram circuit i; t c m t i n.; c s :

-2.

The m: r a r r. rNc r eto-t r.m p e r a t u r v r e q.r i e c P.en t i. met.

l

~

The ecol art pump circLat b r e c..c e r 2 c;cred.

1 C.O 1.0 pt each 3.O'

=

P< r rE R r_*.' r e-3ri. s.r',,- w. 1

~.~n

<- a av A. h..i O. !g...if f8 u. f~E f 1. O.,r.%

D The regulating rod.

1 e1. r b I%'e r.

t-t ICU SAR 4.5.1 H..r g -

n. r.. L -

. 3.. se e) s.

.*w.v w

k [ l'il t 5-Witch Ei O h I D 3 D 1 VC pCL: . ' 2 *t a f*1 C G.N t [ r.Q U, S h & 9 ( p2DD} }jght,

.(*,"'

-., r m,, k....

• Lf i%

e' i

's a'.I U.iC< I..

f,. 4.

• O l

i j

l n.r.-r r,s/

e-.,

c,,) % g i

3r

• 1 * % g b w' f'

W

\\. e 1

Idh6 u' 2 C

. ' E.'

E. [2 I I ()

C i^

• I (' O (fI C )

@f (f)Q [ (.)l". ( 8'O

(.' (

82 [ 9 e

.,, s..

L <

a-Ls. cJ. e

\\ s.t. a

. ; ~. c: t e,

ssC s -

t 1

- e.~ - e r.., v..s e r'L L';L,prL

• P 'k r

r e-i u., a t '

• s e s a es

a n

- r. _ _e, ce_. _ y mm rMrnC"NCY cVcT"MG P A r m.

?4

=_

. _ : __.____:._=_____:._::.=__

r* v. As "r' E I et,, s 9 t 'r fs.ar., T, y *.#

.. n *T / S t / (s _. L { r,g r'*

f_".^,.

(.ri e c._~i e r *m **.

4 m.p.

• no,

_.A s

ss.4 -

v,-

.~

m,

+s,... e_. mir n E, n4

(. Ors, m.

m c.

T5c ' I s i l -- n a f e " principl:= requi-es thct the relays coils bc -- :~ ; i : M to hol d the re::av :entacts tIceet :n the scism c: rcuit. ( 1. D b.

".c r a m.

( Ce ~ 5 )

m, t r r n.. r e. i r C w

..n

1. a,,

r o,,

-1. L. _

we.

l i

fu.e_ t.,r q t. n. _-

(.4. s. n. ) -

i e

1 L

a.

\\

j av

~

2,.

C ti? O.5 pt: each 1.5)

=

rv r_ P_ e c.

e I t'

". Mi 4. #. t-c.,,. r....i c. c..

(.'.e....-

t 1.

The elapsed tima b e t n ee r, r e c c h i r.g s 1; mi ta rq I,c T e t y system atsi it

&~d the ;nitial rr ove m en t O f a EsfEty typC rod.

( 1. 0 )

2.

Those systems,

( i n c. l u d i n g their sonociated ;-

har re; r), W,2 r k o-e desi gn ed to i nitiate e ut o.wt i c eectcr p r o t e t t i c.n [0.C]

c-pro,;dt infc maticn (cr initiation of manual protective action 00.52.

A measuring or protective c hannel in the rccctor scfety uybtcr.

(C.5:

n.-

rEr.b L L

m

• r,i

,,_.i8 r-

...e E,.

3 h.r'e= b k e -...

6.

d one es I

4.5 kw I 4 h ee' Wp' h.s h

e e em b'

I O

.t.t_s. t" e..* *'" (,

L,.r,.

. /* !

a rS b=g. h h gie e

she b

6.E OO k ges' W h 9

h 4

--_~T

'--r., -

t

- L L. i

• c'J

• • '..^D 4. f. f,

.w

. Cortiv-A C.----------- tc EMERCCtJCV - EvCTEMO Pr,C E ' 25-ANSWE.DT

-- -IOWA SThTC'UNIVERCITY

-87 / 06 / 02-l ! ARE,

C. A.

t I

.1 1

1

- s s. < e_ r r. r. =,

<.. o. n- )

m ru s

1 1

a.

Alarn t.

Interic L c.

Scram d.

A l a r r.

e,

'Ctrcm Alorn is C,. n.

L.

-m

.. -.. o. s aw.

p. r. y,r..- r

_ t

.. ~

i.

I n., n,. T o..s. 1._,

~..6...,

p,y.

m-.

4 s,

I ANOWER E.06 (I.00)

Deccuse the f i ssi on product inventory it not.Lafficient to provide a h '2 a t courte or any cc, sequence, f. O)

I REFERENCE ICU CAP, pg. fr 33 s.; r_,e.ir 7_

r.,,,

m

. e_,s. s s 4 T9e : n t e r l a c ic s y:: t er presentt tha dsvv opeent of poteitie:13 h er r-t :s 3 condit.'o 1 by :nFibiting :cetoin_operationc cttempted by the operttcr during the st ar tup nede of op c r a t i on.

';.5)

- r c of,r i

• w %

+t-r 75 L..

4. e l l r

yg.

~.O.M w-av r

e a

u.,l, _ kIr

[.Dr

$.. f.. ( L

%h vu Twc 1 ;.,- p t.s e r tr:ps ( f. c a r c e o;t',

1-.5)

• ..e h i ;t. powvr tr:pc

( 0, 5 )

Two fast p er-i od tript

( 0, 5 '

Ti.o h,gh.oltagt l ow tc r.-detectorE

'O.5)

,r-

.\\i,:

L. a

,r

'iLf 46 9 -1

• • r'*

'P 01 4"'1 A $

'es' hU N&

4 4

i a

J

r : _ _C T_ Ak'D_ A_P*'

AM D_ _~=M_E_9_C c t.:Y_ _O_P E_R_ A_T, :T t.:q:: _nnn-rn ince n r'.c' r-n

• a 2_

2 J=

_x:r c=

0 NCh'E.RC --

Oh'A ST' ATE UtJI VECC l'Y

- 07 / C l.,.' 02 -- HArc, c. A.

1 1

4 t., e_..ir D F

n.,

f.,.er.-

.m v

1.

Curing m.c.t er i s,1 revements into er out of the cor tainer.

'( 0. ' 5 )

2.

During a,

viut5cri ed invente.

y.

(0.75) f2 C O.75 pts e a r. h 1.5)

RcrERENCE I EU Oper n i n;; Procedure T.. d. t ! )

m iei,rR

)

,a--

(... e: r s.

co m_

1.

Monitor reactor : n s t rumer t a t i on.

?.

heep.the f uel r e c t r c':.

(2 7 0.75 pts cach -

1.5)

P r e n.r_.-c_ _r F el Tra tr e-Opc gt; q, rrg;.cd_rc, r ;;,

(+*.t r. '.t r. p p. p '..t.

(

. e. c.. s Personnt! Emerger.cy 2.

Unusuel Event Alcet 1

4 Site Area Emergency (0.5 pts.rcr co rect c r c' e -

(0.5 ptr fcr cac'. c o r e t '. artwer = ?. 0:

n _repr,N w

<- r w s

' I lp.=

4 h f

• h.

I4 2

4 a,

g 1

)

l 1

j 1

l I

F

~

....._ _0_" A_N.D. _CC_ D_ _C.N. D _ _E. F E F. _C.E N _C _Y _ _0_" E _D AT _I N_G. _.P. _R.C. _C.E. _D UR E _C '

P'ADE 27-ANEkCDC

" IDW4 EThTC UNIVEDCITY

-D 7 / OL,/ C 2-HAPE,

E. A.

9 AiC'viEn -

F.On

( *. 50 ) -

Ct prri e-t i d e r;t ; ( : :ction a -' c' i c :.a t i o r..

a 3.:

4 r

a..: _)s._a

..c.s.

p m....

4 u.

o.

_g m.

(2 ? O.'S pts each

1. 51

=

.q p g p.,., _

EU Cperatirms P ccedu c E.C

x. - puer 7. ta

,.. e.v..m

-e

~

.. j 1.

A no in the conteel r :'om.

( 0. 5)

j 2.

A SPD readil y avr il abl e om cs!'.

(0.5) s Health Physic,-qual: 4 i ec : ndi v: due cad:1y a '. a i l a b l e e--

call.

(O.51 p.

p r.e r_ n+.. r_

.rs, 3 c.,.

L.,.,. f, s aw a

2.

ANSWER r. '!,

'!.N>

J 6.

2.

Lo~er power tt 1 Kw rse less (0,5) em,,

o. _rf

-i m a_ r ", c,c'

. +.,~. a. p

'^. c. '

s..

b.

1.

Ee:ett V.'4NUAL ODEncT CN Macc-f or in: et tenp er s t.;re c c.n t r ol l er.

(n.5) g s ~.,

c-w

t. p. c.

,a. m. *r

.r.

< r.,. e 1 a J

w..

. w w

w e

i

)

,e m..

.c.

2.t.

v.-....L._,e.

.._....,., ns.

.s

,.-22 s....

a 7

s 9

r.

4 -. } :...

_....,,.8_6_.

i e. r- )

c ma su us y

s-m e r e.,.. r. e s. s e r ti

+.

u ibU CL'aIrdt[C7'O E!* C C C C.' *.i t' O b O b b " 2 r l' 6 I O ^I N E !I F y. ' C p' C OM d $ k i CIIb O

3 pydJ s

e 69d L'

r.

1 r_ _. _ _ S_._T A_!_c_ A R_S_ _ r_N_ D_ _E_M_E_R_O_C N C_ Y_ _O_ P_ E_R_ A_T_ _I N_3_ _P_ R_C_ C. E_ D_U_R_E_ S_P AGE - '00 SNEWEpS ' --. I DWA ' ST* ATE UNI VERS IT.V

-97/06/02-HARE,.E.4 AtJCWER F.07 (1.00)

On-Duty 990.

( 1. O)

DEFEREtJCE -

ISU Technical Operi fic ati on 6. C.

ANCWCD F.CO (2.50?

1.

Turn en ecntole p m e,c r.

2.

Start e col an t ci r c ul ati on pump.

3.

Minimum count rate is above rctpoint.

4 DOmp v a) ve c1 med.

5.

Safety Rod #1 w: thdraur.

6.

Osfet' Rcd #2 w; t hde an, 7,

G.h i ec s ;. I e t; ; ar ;

r e g g ; g. t 1 g rcj

, ( $ d e g. p,, t

r i *- i C a l p rd ; l'i C r,

n.

p.o.

c%._h i-w (0.4 pts fcr ccerent orcer)

PCFERENCE

i. c_' U C A P p'

. c ".>_.

________________._.____m.___________

.G.--- RADIATICN CONTROL AND SAFET.Y PAGE..

29 ANCW"o.R5--- IOWA CT'ATC UNIVEROITY

- D7 /06/02-HARC, C. A.

i 1

l 1

ANSWEP G. 01 (1.50)

N=

Not[-1pmbd3 tt]

'O.5)

I 100-40/100 ' GE-1ambda

• 1J l

in.6I= lan.bda

.51 lambde

=

t-1/2 = In 2/1.ambds t o. St t-1/2:= 0.69!/O.5; 1.36 dayt

( C. 5~)

=

R..,e r. c. uc e-

,1 t

.. m

~ 'c di t. c ;;i ca l Safety Exsm. Quest;;n 14 J

i ANCWER G.02

( 2. Or0 1

The water is collected in the suTp in the process pit [C.SJ.

A f t e *'

assessment that concentrattort of the r adi oi cotcpes pr esent in the sur:p are below 10 CFR 20 limits E O. 5 3, tr ae u s l l y energize a pump to nove 1:7.id to the basement sump [0.5] for further d i l u t i or-and di schar ge t o t,ani t ar y rewer CO.50.

RErEn NCE t e.sLi c - - m. m. /,-

a we w

ANCWED C.03

( 1. OCO 250 dpm, 100 cm2 (2 O O.5 occh 1.C)

=

REFEPE%CE

SU SAR N. ".;. 4 s

1 GN5u:CR C.0L t:.?v' A r adi e t 2 ti aret is greeie-t F.s n C MP/ Pour.

c Migh raddattcn e es is ; cater

'ho.

10? MR/ hour.

Ths ms:inur c o s_. e rate in a prcgerly marked rcdictitn 3res :t.

therefore 100 P~i/ hour.

!:2 I m a. 2 r.:., n. dale 250uld be:

45 / L O.- 100 7D MP.

(".5)

=

m.r. t r r T ~-

t

~

s-usw 4O

• ? ' **)

Rf A L.

• t-

's

(-

1

G _. _. R_ A_ D.-.I A T_..: C.. 'J._ C_ O.N_T_ R_ O_ L, _- A_N_ D_ S A_F_C T_ Y_

PACC

'C A, NSW r" C -- l CWA GTCC L"C 'MiiSI TY

-87/06/02-PAGE, E.A.

(i.. r..,,.. r. >

e. c,e f -.-.w>

n..

w s

a.

D 40 (n,

s mw a ' A 21; ha!f--life.1.93 h gro-decay by beta emiscipn.

,li

' enact 5s1f 1 fe

r. c t required, must be within 20% of r, c t u a l i b.

t it ;:roduc ed.i n. a v r - 4 i : l e d sp ac es. adj acent to t he r eartur c o" e

O.752 End in the air dissolved in the cro. lent Dousing t hr o;.Jh the c ar e Cn.75 RE",CRCNCE 1a. e,n., n. e-a.4 e

o a e ANSWER G.06 (2.00)

Cecause the ur,i t Rem'a1.eady censiders the different'eifects. ( 1. 0 ).

Ram it a bi ol ogi c al unit th;s different rad 2ation causing the sa n'e dost in Pcam s h ou l ci have the same ofrett.

!1.0) e, :.. -. n w. ~- -

w

. ~;

c 4n -. r. ri.

n.

m.. :...q

... n. -

r.. n n. s 1.

iie dees not enceed 3 W.? per caceter.

2.

His radistic, hi.,tc y is ' r.? w and re:crded o-

!J7 C +~ p r m

t..

3.

The dote att r ecei ved Jr r, added to his r adiati cn hi rtery coes ne'.

exceed D'N-10).

(3.?

1.0 pts each 3.0) r R r r C o r >Jer rw -

In r r.. r..en, v.

is i

TEST CROSS REFC~CNCE T' A E E -

1-

'CUESTION VALUE.

REFERENCE

__,o-_.,

A.01 3.00

. EAliOOO1160 A.02 2.00 EA!!OOO1169

-A.07 1.OO CAHOOO1170 l

A.04 2.00 EAHOOO1171 i

A.05 2.00 EAHOOD1172 A.06 1.50 EAHOOO1173 A.07 2.00 C AllOOO: 17 c A.00 2.00 EAHOOO!175

. r.

4a.en l

D.01 2.00 E At !C 001176

)

E.02 2.00 CW!OOO1177

)

D.O?

2.00 EAH^OO1170

?

E.04 1.00 EA'tOcc1179 E.05 1.OC E Al lOOO11 CC E. 06 2.00 E A!! OOC 1101 D.07 3.00 EAHOOO11E2 I

14.00 C.01 1.00 EAHOOO1103 E.02

?. 00 EAH0001104

]

C. 03 2.C0 CAHOOO1~03 E.04

.CO EAT 100011D0 C.C5 2.00 EAHOOO1107 a

E.06 2.00 E Al1000: 1 CD l

C. 07 1.00 E nl l OOC 1100 E.DC-2.00 E AHr.001 : CC 14.00 4

D.01 2.50 EAHOOO!191

')

D.02 1.50 EA40001192 D. O!

3.50 E A1:OOO1192 D.04 3.00 EAHOOO1194 D.05 1.00 EAWO.'$01195 2.06 1.00 EGHOOO.'.196 D. 07 1.50 EAMOOO1197 i

1 4. n

1 1

C.01 2.00 En OOOu eE 1

E.02 1.50 EA!ICOO1199 i

E.OT

. 5 0 EAHOOO12OO

.. es.~.

r_ e+u,n. e.n.. s

n.,.

d

. n. c.

s

-. c.r_,

~_. c e g nnno. :, 4 O_m.

E. O.'.

',. M,.

r_ A H. ^ O ^, -.'."..

E. O ~'

1.50 E A H O O O 1 : n ',

c..3,

w-r a pi u, n. s,.. n. c--

e

'L M

I

'TEC'T CRDSS REFERENCE RACE 2

'DUESTION VALUE REFERENCE

.. -... a e4 I

14.50 i

F. 01 1.50 EAHOOO1200 F.02 1.50 EAMOOO1207 r,o; 2.50 EAi10001209 F.04 1.50 E4MOOO1207 F,05 1.30 CAHOOO121O

".06

!. "; O C At lOOO 1211 F.07 1.00 E Al 19001212

. n. C

.r,

q u.. e... n. n...v_ i s 15.00 G.01 1,50 CAHOOO1214 G.02 2.00 EAHOOO1213 G.03 1.CO C4HOOO1216 G. 04 1.50 EAHOOO1217 G.05 3.00 EAHOOr.'218 2.06 2.00 E AHOOO 121 r/

G.07 3.00 EAHOOO1220 14.00

%MM'6-101.00

?