IR 05000157/1986001

Exam Rept 50-157/86-01 on 861015-16.Exam Results:Candidate Passed Both Written & Oral Exams

ML20215C703
Person / Time
Site:	05000157
Issue date:	11/25/1986
From:	Coe D, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20215C666	List: IR 05000157/1986001 ML20215C664
References
50-157-86-01OL, 50-157-86-1OL, NUDOCS 8612150343
Download: ML20215C703 (51)

Text

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U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 86-01 (OL)

FACILITY DOCKET N0. 50-157 FACILITY LICENSE N0. R-80

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LICENSEE: Cornell University 241 Carpenter Hall Ithaca, New York 14853 FACILITY: Cornell TRIGA Reactor EXAMINATION DATE:

October 15-16 1986 CHIEF EXAMINER:

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D. Coe, Reactor Eddineer, Lead Examiner Date'

Reviewed By:

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I//z0/4Gf R. Keller, Chief, Projects Section IC Date APPROVED BY:

/// #

H.' Kister, hief, Projects Branch No. 1 Date

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SUMMARY: One R0 candidate was examined and passed both the written and oral examination.' Following up on Inspection 85-01, the examiner found that the facility is taking steps to perform its Emergency Plan drills, audit and requalification examinations on a timely (annual) basis.

The last drill and audit was performed in 6/86 with another drill and audit planned for late 10/86

,

(If an outside auditor is not available then the Safety Committee will appoint someone at Cornell to conduct the audit). All operators at the facility have taken a requalification examination or are scheduled to take one in 1986, except for the Reactor Supervisor who develops the examination.

Plans have

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been made to schedule the annual requalification examination in the fall of each year rather than scattered throughout the year.

8612150343 861209

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PDR ADOCK 05000157 V

PDR

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REPORT DETAILS TYPE OF EXAMS: Replacement X

EXAM RESULTS:

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CHIEF EXAMINER AT SITE:

D. Silk 1.

Summary of generic strengths or deficiencies noted on oral exams:

Candidate demonstrated good understanding of items on startup checklist 2.

Personnel Present at Exit Interview:

NRC Personnel D. Silk, Examiner Facility Personnel D. Clark, Director, Ward Laboratory of Nuclear Engineering H. Aderhold, Reactor Supervisor, Ward Laboratory

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3.

Summary of NRC Comments made at exit interview:

Candidate demonstrated good familiarity with the plant and its various systems.

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4.

Changes made to written exam from examination review:

A.05 Include equation To account for a form of answer mathematical approach to the solution B.04 Accept " Magnet Current On" Modify in place of " Rod Fully Inserted" answer key B.05 Core holds 85 fuel elements Correction to instead of 84 answer key B.07 Second part of answer is Correction to worth 1.0 point instead of 0.5.

answer key C.01 Final answer should be Mathematical error t = 196.84 seconds in answer key C.03 Maximum power initiation is Correction to 10kw not 10w answer key D.04 Also accept " Console Expand answer key Range Switch" in answer E.01 Two more possible answers are:

Expand answer key 1) Switch to pulse mode with Pulse-Mode key switch Off 2) Voltage sensitive device in the scram relay power supply F.04 Maximum power initiation Correction to is 10kw not 10w answer key G.03 Gas monitor above the reactor Modify answer key is considered portable.

Replace with "Ar-41 monitor" G.04 Replace answer to part b.

Modify answer key number 3 with "Close port beam vents" G.06 Replace answer with "Following Modify answer key a long run of full-licensed power, the cladding of fuel element fails during fuel handling (0.5). The results would be the release of fission products to the reactor bay area (0.5)"

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Attachments 1.

Written Examination and Answer Key (RO)

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Wrlte annwers on ene nide 001y.

Otaple Question sheet on too of the ancwer sheets.

Fotnts for each question are indicated in parentheses atter the question.

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

Examination pacern tv i l l be picked up siv (6) hours after the examination starts.

% OF CATEGORY

% OF CANDIDATE'S CAlEGCRY

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f_y O L U E __ _ _ __ _ _~_ _ _ _ _ _ _ _ _ _ C O I E G O S Y _ _ _. ___ _ _ ___ _ _ _,

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A.

PRINCIPLES OF REACTER OPERATION

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FEAIURES OF FACILIir ele IGi >

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GENE'RAL OPERAT[NG

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CHARACTERISIICS

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IN516UMENTS AND CONTRULa

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AFETY AND Er(ERGENC' Tv 5 FEr;G

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STANDARD AND EMERGENCY OF'ERATING t

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OUESTION A.08 (3.00)

DESCRIBE the heat flow path from the fuel to the ultimate heat sink stating sin (6) heat transfer barriers and the applicable heat transfer mechanisms.

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EXPLAIN.WHY potentially contaminated r'eactor ' pool water cannot m2.

with:the campus chilled we.'ter ' system 'shoul d' - a l e at: occur in t'h e

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to.'t: r tm (;

( I O 'l i. ter r a pul se.

3r, i;,.

t;ur cc1

'f i :

C.00 ( 1., 50 )

-

iraatl-D E _ L;::li~_ t te c:r o.. ;c; ci contr ol rod prrta caltbratloa D'-

..

(1"'>

t. h a Inhour Me t r' ad.

.,

~ ~ ~

QUEaT ) a.

C. 0 9'

(1.00)

, -c

Dr i c:f l y DESCRIDE !;nM true reactor power is determine;f ar!d WHAf influence I:h i s hat on nuclear instrumentation._

' l -> >

-

QUEj3T I Ot i ~ C.10 (1.00)

W H ',T i =, the 1 r.it on. r eat ter pool c o n d u c t. ' i ts, and !&4EPE s3 thic limit e c i f i a d c,

- 1 o)

s

-

,

ev

,

• d4%

e

-

-~.

.. ~

,

O l

,

d'

t (t**&4 E N! Ot2 CfiT EOGN'i C 444**/

{

r

-

. -

.

- -

-

.

D ___lBS.1BWiiN1S_.(Rg_.COUIBot.ii PAGE

t

.

,

QULB ' 1 D.01 i1.00)

to.

n :e ator 4ratnec hem c er t armr d startup and hm _ t 91

_ M the e

,

-

r e a r. t. e et apura :i matel v lp waffg.

Wim)n2 to a er + < r.

m i t m2 u2

.

k

-

Oe r at e.t u m m.

-f i t i n ie 1 h r.- Dul te "mcit 3 or

_.',

ni a W1th pulse 1 -~ * 1 t i S L I On.

E /. Pi.. O I.1 v 0' ir anG...

(i O!

>

prCCl-

'

OIE 5 ! 10 i D.O?

( 2. ',U )

NAME the five (5) r ancies of neutron level (power > Indicitloa

.

an c! STATE NHAT type of detector each 13 fed f r o m..

(2.5)

V1..,

CUESTION D.03 (.50)

When in the pulse modo of operation, WiiA i indication does the L O.)

N (O.5)

recorcer provide?

..

.

CUEbf10N 0.U4 (1.001 l' e vel 15. tT e i n g controlled edtematically. WHAT ilmitt the Nh rer i s einer love. ct,an x _. pascible in ' servo control ~

'.1. 01

OUES T 101.i D.Ob (2.00)

LIST r eauons for four (4) of the i n t er l oc i:v ?W= r oc i a ted w i t. h reactor (2.0)

operatton.

s t

e

'

em D.fEST 10.1 I <. 06 (i'. QO )

.

E 't F L A I N W H Y and HOW comma compensatico

+1 ac n i ovetJ on lac N anc(

l i n C J t'eCOrde C h-(nn e l ', and WH) i t-12 not no 232 3rv ( t VR.-

(2)

F C aG. r t C ' On thO [u:f r c el ) t.

p o ;*J e r C I i ? "i n e S.:. ')

('

(4*it& C AT EGOf<Y D CONIINUCD UN iEii P AliL

• +*1)

t

-

s

~e -

P90iE

!h ___INMI6MdErjIE_GlitLGOdlBQW

.

..

Oy ( i.; );

Cr.Ai r ; r,c.;

.

1)ur ) : t.

r armal nhu t do'in, thc r> actor oca-ator ia inctriated to LOplGV.

U!i4[ ' 1G thO 919 i n i ' I r.

1n Or) - : r,-

.e 1 } < e gr D oh'i F F '_' - =.? r d i

'-

'no chov:

t n o t r m '_ t c:c i ulven-

,1,0)

w c.

, t t. a c, n+

- h t d o in,

ind W

OUE5T10N 1:. :u (. ty >.>

WHAT t,

tho i l m t i r,o saf ety nyutem si+t p oi n t for the ccram settin.1 on the i n s t r u eriei.t e d Fuel element temperature channel"-

(0.5)

-

QUESTION D.09 (1.50)

is the range of your period meter sufficient to alled accurate indication of the constant negative period that occurs after a r c-a c t o r scram?

EX. PLAIN.

(1.5)

OtJE(.iT l ui 4

'.10 ( 1

'5 0 !

WHr3 r thrne (3) r; 1 o n al s are' input to the servo amelfiier circuit to

~

(1.5)

au tom.c i i c al l y contral reactor p o i;3r.'

v

.

.

4'

(t*+*A END I!F t:0 I t'bu!W

!*

4**tii

.

ht ___.56EETX_ AND_EtgByENCylf'51NJ5 PAGE

.

OUESf1ud E.01 (2.bu)

A ' c i a n-r at i be initiat.?o bv +1m methods.

Nal id tor.

(2.b)

.

QUESTION E.02 (3.00)

a.

WHAT provician is made f or nicaitaring gaceous c flu'it from the (0.S)

1. acility?

b.

WHAT nuc11ae in it cal)brstcd to mua<ur.L (0.5)

c.

At WHAT LEVEL does it alarm?

(0.5)

d.

WHAT three (3) aut ornat i c actions occur on reaching the alarm (1.5)

setpoint?

,

OUEST 'I ON.E.03 (2.00)

WHEFE and WHAT' type of detector is vaca in area ractation mor1 tor:

located in the reacter b ay'

Wl ! A T are the c et c,o i n t s a n.j thr (Z.O)

result of eacn?

,

DUESTION E.v4 (1.50)

An undergraduate ntudent, hurr yi ng to t i r. i e n t.i s ex c er l man t, tript while riinning across the reactor b2v and the shielded tla3k containing 0.5 Ci of radioactive liquid that he was carrying runs into the floor drain.

WHERE does the l i c!u l d go trom there, and NHAT uetection and hold-up barriers lie between the epill and its celeaco rom the

.1. c- )

facility?

DUEGTION E.OS s 3. '< 0 )

LIBF and FRIEFLi E XPL AI!1 i n.: f ous-

c_1 c.

v o n w e m u a.. n c i..c.

cS,0c 4'

.

(t****

CAIE00FY E CONTINUED ON ME4 T F W '.E v*4**>

h C

?

n,-.

-

-.

--.

. -.

~_

' hk0E

$

-

.

dk IE~ ' [ } b! $

k..'IN ( 2. Of_' I WHI N iu the emeroencv

!~

t 3 :d (4M A T.10ee i t contain'-

(2.0)

-

%

%.

4'

am$ un, m enic._;o v t.

+,m.,

-

.

E:___ e !O!M6fiQ_OUQJigf@EUQX__Qt@[j@j I.Mj._iBQGQQOEp PAG:E

.

UaLETitoa I v1 (1.00)

' V tli t 4 -if t ! t oUn'

("!

cGncitiGhn O O e i. ( -7 P t Oc h n ) /~ a l cpeci 1C3C1'3h Of minimo.

stu itco on marain 9's. SU eupi'

(2.0)

~*

Xi

_

.

....,

.

QUE5 T IUil F. O.

(1.00)

%.

or t' r o n n a. en t re a removal. He! is thn chutdowa reactivity eGUlreJ

'r and Hold is it achieved.'

(1.0/

QUESTION F.03 (1.00)

(1.0)

DEF I Ni-operable (per Technical Specifications).

_

OUESTION F.04

.22.00)

...

di s ti r:c t spec i f ii at i o:it.,pply unlouelv to pulce mcde WH4T tuc

.<

-

(2a O}'

operations and WHY7 OUn9 TION

'. 0 ",

(i.003 You are oper atino the r. 2 : tor in et e ady--Ot at e made at ap p r ol l F a t e l ',

80"/. power when. over the course af th i r' y seconds 3 you obseive the percent p o w c.ir an t er and the linear o p>er recorder drift down tu approximately 50*. and 4 0 T. respectively While the lcq N channel remain:

stable.

Wil A I ac t i ons do /ou take and Wi n' -

'. 1. s.) )

'N

• D'* DVD3I1ON I, U(.

( 1. O' i l

>

(n: i ti,v e been ce ratino t r u.

r eat. t or o'

10 6 pow m tor !u:

tvv t! ire >

(~'

hour in a u t o m *.t i t ant r.il

. "1 sol u t -

y u >thina ani ' w. + 1

.

h 45 (T.:r t ir t' ed sj W A sia th1-n.

1 +,o

<' vet t ' l -.' i di ' t c'

'~ t " + ' ' ' ' !

'd'*-

'+'a.

'

.

-

Witlo watc h t ivi lie <_ 'i iw l

>i *

'a

iI**

• '

'

?'

"'

!

hi

'

.

!I O=

perm)

1 bl(a f'FlalN, La u m. t+

t.*****

C A T EGOln t CUNiIHUEU UN 1 t:_ ( i NUE

1. +4*#'

• a E1_EilbIdI2600_Ofdh._I DE8QEUUU OEE6611.UQ._E60GE.QUBES PAGE

L

.

,

UUES t lor)

l.U/

'5.00)

LlST

a > itemT outside ci routine startups, power chanec, ;. n u sh u t d owi t s which irust be noted in the fecac tor Operailona tog;>co!

( c.. O.

.

QUEbTION F.US (1.00)

WHAT is tne pool temperature limit and CAN the reactor ne operated continuously wi t hoi t t exceeding it?

EXPLAIN.

(1.0)

QUESTIGN F. O'i (1.SU)

HOW LONG may the reactor be operated with the ventilation Systen

. inoperable, and WHAT two

.( 2 ) restrictions apply durino the LCO (1.5)

peri.ed?

..

w-

.

,

s.

QUC3TIUH F.10

.1.00)

WH4T iS 'the minimum al1owable pool depth, and WiinT musi De'done li the level t e; i et tnd ta be tec lowc s. l. 0 )

'

he m '~

~

.O'

4'

!

(444A4 [ !.!!) Oi L fD E OUfi'Y t-4444&)

-

[

l

_

.

c FAGE

9 -_. BOD 1OT1019_ cot _ilGOL._Ot@_iiGEtiT y

,

.

UUt. S l i UN b.91 ( 2. S.9 )

Wi n ;

i.v (n) :)or t a b l e c ac11 at ? O i curvey inst,umeatc ei r _> at t i l ab 1,'

in the vs. actor ww and UHAi ao thcy detect:

(2.5)

QUESTItM u.02 (1.09)

WHE R.1 1c tne air that in puracd tram the t il er m a l column and beam portr exhau=^o> tc. and WHAT icotope is of principal concerni (1.0)

OUESTION G.02 (1.00)

_

GIVE the location of four (4) of the fixed pocition radiation (1.0)

monitors in the TRIGA facility.

.

.

CUCG'IION U.04 (1.50)

( 0. 0 a.

WHnl dced AL.nRA st and f ot - ~

..

.*

b.

GIVE two (2) e:-: a mp l es of Cornell University's efforts to comply (1.0; with vtMA.

~ g.

QUESTICN O. O'.5 (1.001 An a mi rii n.um. HOW >%NY people most tm oresent to move reactor fuel and WHaT aual1Fications n.u s t they possesW (1.0)

i e

i OUr '.s i 10N 6.JS ( ?. 007

-

-

I

= (

h h

) ()

l k h,' -, I ft }

l h ()(t {

[-)

h([( { j (l[]

,].I_

}Q lj'.] t *

rcactat and (2H R ) } :

.3 d 1 a;,i t t s i f. V h,_..'.3 r ri WOuld rUSUlt ( 1. O ;,

-

,

)

('

I i

)

'

(**i**

L 41 E GOI. 'y

CONfINULD ON NE X '[

POEn 44&t*

l i

. _ _ _. -

J

s e,

G, R4DIATION CONTROL AND SAFETY PAGE

• e OUE.5T I UN G.

(.'. M O cobzit c ot o-c e emi ts a radiatlan Le ?1 o,

t i e o./ I'

a t.

A c. mall

'1:

'

a distance or 1S tt.

it _, n aperator r equ1 r m

.o.

s: > ': > r:' t t e ta c. i i t t a valve locatud

t, cm this, c m.tr c

h +i -

ic or

.

.n arc operate the valve befror.

nc' r e :: el veu a c a t, a in cc ;;

c.

Ui2 10 Gn 20 quarterly whole body e::.N s ur e 11 mi t

E.t ttA i nli e:ar L

'nd (2.5)

assumptions.

QUESTION G. 98 (1.00)

GIVE en exomple at the f011owina:

( 1. O )

a.

Penetrating ionizing radiation b.

Norgen et r at i n g ionizing radietion

,,

.

.

,.

QUESTION G.09 (3.00)

.

D$1INE or EXPLAIN j3.O)

- a.

. Radiation area t).

Restricted area c.

High radiation area d.

_ Rem e.

Rad f.

Curie

..

.

.

4'

(*4A**

ENI) OF CATEGORY O

• • • 44'>

(****t45******

END OF EXAMINATIuu

• • tavt4*4.+6&t**/

--

c

.

G, RA01 RATION CONTROL AND SAFETY PAGE

e

,

s

...,

,

UUESTlON G.07 (2. 50)

I.m A11 ]

.t i :: ed cobalt nouece emits a radiation level e1 i f he receives a dose in excess of the 10 CFfi 20 ciuarterly whole body e>:posure l i m i t

SHOW all work and assumis t i ans.

(2.5)

DUESTION G.OB (1.00)

GIVE an example of the following:

(1.0)

A.

Penetrating ionizing radiation

,

-

,w b.

Non penetrating i oni:r i ng radi ati on

-

DUESTION G.09 (3.00)

DEFINE or EXPLAIN (3.0)

a.

Radiation area

,

b.

Restricted area c.

High radiation area d.

Rem

,

e.

Rad f.

Curie

--

.

('

(***t*

END OF C A T EGOR'.' G

• • • • $)

(************* END OF EXAMINATInN

• • • • • • • • • • • • • • • )

.

,

.

$

-

5 E

-

e

E t

1<

b#

$

n :/ 1~ g < s / / ' : s t <e e t n(

"

fp seit8

-

a u,~. u d, s. :5 :- H }< > s! !5-I $!$ ~ E8 E6 58

.

$m!5,52!

.

$

$

!

5

!

r r

r r

F F

E Y

-

,

(n h

N

'

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~

l

/

3

[

I E

xD b

r

'

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S5

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d

j m M m,v gs s.

l

~

w

. u._ _ v.p.~g

.

-. _.,

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.

.

.

.

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.

.

.

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-. _ _ -

, _. _ _, -, _ _ -. -. _ - - -.,. _ _.

- _, _. _.. _,,, -, _

_ _, _ _ _ _ __ _ _ _ _ _._

..

~

EQUATION SHEET

'

,f = ma v o s/t Cycle efficicncy a (Mstworx

.

out)/(Energy in)

-

s = V c + 1/2 at w = ag o

E = ac KE = 1/2 av a = (Vf - V,)/t A = AN A = A,e" PE = agn

..

t=

an2/t1/2 = 0.693/t1/2 Vf = V, + at w = e/t.y 1/2'## * EItin)I*b l I

'

t

-

,

y

,

((t1/2) * (*b)3

~

"/ 'N -

d = 931 am

-

I'= I,e'**

Q = mCpat d=UAat

I=Ie"#

'

~

g I = I,10-*/U L Pwr = W ah f

TVL = 1.3/u P = P 10 "#I*)

HVL = -0.693/u

-

p=Pe/I t

-

o.-

'UR = 26.06/T SCR = S/(1 - K,g)

S

~

CR

= S/(1 - K,ffx)

x SUR = 2So/t* + (a

.o)T CR)(1 - K,g)) = CR (1 - keff2}

-

-

'

g

.

l T = ( t*/o ) + [(a - o )/lo]

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

T = 1/(o - 8)

M = (1 - K,g,)/(1 - K,ff))

T = (a - o)/(lo)

SDM = (1 - K,g)/K,ff a = (K,g-1)/K,g = 4K,g/K,g t* = 10-6 seconds T = 0.1 seconds ~I o = ((1*/(T K,g)] + [f,g/(1 +$T)]

I d) 2,2 2

=Id l

P = (r+V)/(3 x 1010)

Id gd jj

2 I = oN R/hr = (0.5 CE)/d (meters)

R/hr = 6 CE/d2 (feet)

'

l Water Parameters Miscellaneous Conversions 1 gal. = 8.345 lbm.-

1 curie = 3.7 x 1010dps

1 ga. = 3.78 liters 1 kg = 2.21 lbm

3

,

)

I ft* = 7.48 gal.

I hp = 2.54 x 10 Stu/hr l

Density = 62.4 lbm/ft3 1 ane = 3.41 x 106 Stu/hr l

Density = 1 gm/cm3 lin = 2.54 cm Heat of vapori:tation = 970 Stu/lom

• F = 9/5*C + 32 l

Heat of fusion = 144 Stu/lbe

• C = 5/9 (*F-32)

i 1 Atm = 14.7 psi = 29.9 in. Hg.

1 BTU = 778 ft-lbf 1 ft. H 0 = 0.4335 lbf/in.2

_ _ _ _

_

p

e

.,

A.

PRINCIPLES CF REACTOR OPERAFION PHGE

-

.

ON%ERS - CORNELL UNIVERSITY-86/10/14-JARRLLL.

D.

,

Ar P:A ;O *.

4.O1 (2.v01

.t e l v rn. c ot - * t ~ 1 -. n t 'elpha l) --

F-4 deli k/h iec L4 /*. j

,

tamp effect o r.

r e ar: t i v i t y talphw-11.. tdelta temps

<

20.4 E-4 delta k/k L+0.5J

- 1. z E -4)

X ('f 2. 0 )

=

$0.35 L+1.OJ 26.4 E -- 4 diviaed by 0.00/5 reactivity in f-

=

=

kJ_f EF E NCE.

c.,

1, C orriel l Univercity: Final Saf eguar ch: f4 ep or t.

p.

'-7.

AN3WER A.U2 ( 1. r.50 )

Filling the voided central thimble volume with Water resultc in a positive (+; reactivity insertion (of 0.047. or approximatoly $0.0e).

f+0.53 A large par 1tivo ( c. l ow ) perl.od would ~ result C +0. 51 followed by-a high 41ux scram if not ~ controlled by'the operator.

C+0.5]

wEFEFolNCL

~-11.

, 1.

Cornell Unilve city: Final Sai oquards heport,

p.

/

2.

Cornell Uniwarasti F1 al Safeauard_. Report, p.

5 -- 2.

AMiWLR A.03 (1.50's Samarium i c unecl as a burnable poiscn to mi n i r,u z e ticcion product reac t-i v t ty e 4 - ac t and c omp an -n a t e tar tual burnup.

E+1.O]

The Worth monotonicaliv decrease, with burnup (trom approximatalv

$1.M at 13OL to approninately %.15 after 100 kW years of operation

[ 4 c., 5 i fi E f 7 }-' fi i N C L 1.

';or nel l I Jn t '/er = t t v: Fi rwl E.f oque r d '__ Repor*

p.

b-1

.,

'ia W d 5

IO?por i fl. I?

.lly!

tm.lal 9aE s

'O Pfli.$1 i ! !' i l 7

_:

.

.

.

.

O z

_.B R l.N g i f 1 E 5 R _ FiEi l+C T Q S _ D E E R M 1 0 bi PAGE

cA N 5 W Efr.i -- CONNELL L441 VE RS I T (

-86/10/14-JARRELL.

D.

• At v>iE ;..

4.04

. 00

.

Fr. 10 ling a ~apid re.stisitv 1r'ert1cn, tit ' t1

,1 r. ! r

-

.

b-r~r cn sier at;itiQ additie

.il prompt n'Jtrans. :in d u au i ri in_ r

_;1ti i rate to begin to r!1vecae Ori prompt n r'u t t er.G aluno

" (nue tne nn: o 13 actually sul'cr i t 1 Cal Cn prompt r.eutt on 3.

It must Natt ict the delayed neutt00 Groupa to Contribute their noctn z ar v-t r at t10n to centtitue (lic po,ec r 2 se Lt2.OJ FCFFRENCE 1.

Gona]] Unis.'r r i t y: Floal E M eguards Repy t, p.

t -1 !.

2.

Lit n er i c.

L.: m a r s h,

J.H..

"Introductten to uoc l o wr h:o e c t or ih or y, '

p.

427.

MENE R A.05

'1.00)

Two. feet of water is appro:< 1 ma tel y 3-tenth thicknescon of epithermal neutron attenuation ( 4 0. 5.J reaulting in a reduction of 4 W'

in the inc1dont flu-on thc ' i i er or npor o;:inatol v b E 5 n/cm-a 0 L+0.D1

.

. RLFiu ENJ.il

" i t i.11 cwtequarde F r'p o - t.,

3, 5 - L.,.

J.

Lor oci1 Unav r,1t

-

2.

Oanertc Radiological H o-a l t n lian d L] ack,

p.

144 ftNi>1& R A. ( th (2.00)

1.

Spectrum h a r d en i n ta propertlec nt Zr-H tuel niature ceu w a rapid increa<5o in ledage out of the tuel with increastnq t ar.p s.r a t. i m e L+1.03

>

I I mp r.1 r r o r o a.J er i i n..i, a. w i nt..r e mea :eithe v 1 neret

.r,

.c -

.

.

] llc r s2d'5Lnq t U(9 0t i l 8. ; f'

L + l. '.31 REFEi,FNM i

~

s il,'

[),

!

}

i (,' bL (i !.'s ' / ) '/I, J1 P e 6 (_

f

- I i. 4c t i Ofi fs U;)

l h

i

,

c

..

PAGE

Dr._ _ERINCIELES_OE _REGCIOB_OEEROIIOlj fiNSWERS - CORNELL UNIVERSI TY N 86/10/14-JARRELL.

D.

--

.

ANSWin A.07 (1.00)

It cbearbs neutrons principally in the thermal region f. + 0. 5 3 It varies inversely with neutron energy (typical 1/v absorber for thermal neutrons)

[+0.5]

REFERI:NCE 1.

Cornell University: Final Safeguards Report, p.

1-6.

ANSWER A.08 (3.00)

Heat generated in the fuel is transmitted to the environment by:

1.

conduction through the fuel 2.

natural convection through the fuel-clad gap 3.

conduction through the fuel cladding 4.

natural convection from the fuel clad to the pool water

.

5.

fcrced convectico through the pool heat exchanger to chilled water system 6.

forced convection from the chilled water svatem heat e< changer to the atmosphere All parts worth

[+0.5].

REFERENCE 1.

Cornell University: Final Saf eguardo Report, p.

S-1.

2.

NUREG-0984, " Safety Ev a l u '.t i on Report,"

p.

5-1.

..

('

. _ _ _....

_ _ _ _ _ _.

._

b z__EEOlUEE S _OE_EQC I'g lI y _ D E S IGN PAGE

.

. ANSWERS -- CORNELL UNIVERSITY-86/10/14-JARRELL, D.

.

ANSWEh D.01 (.50)

.

--

Maximum rate is 0.04% delta-k/k/s.

E+0.5]

REFERENCE 1.

Cornell University: Final Safequards Report.

ANSWER B.02 (.50)

To prevent streaming which could occur through a continuous wall-plug interface. E+0.51

-

,

REFERENCE 1.

Cornell University: Final Safeguards Report, p.

5-10.

ANSWER B.03 (1.00)

Radial - water and an aluminum clad graphite cylinder E+0.53

,

Axial - water and plugs of graphite in the fuel can above and below the active fuel region E+0.53 REFERENCE 1.

Cornell University: Final Safeguards Report, p.

5-- I and U-8.

ANSWER B.04 (1.00)

1.

magnet full'up E+0.25]

2.

magnet full down E+0.25]

3.

rod fully inserted C+0.253 4.

magnet in contact with rod L+0.25]

REFERENCE

~

1.

NUREG-09B4, " Final Safequard Report,"

p.

5- *

a PAGE

U.._._EE81UfigitO EEOC RIT LLES,IUb!

_

.

.4f lSWER S -- CORNEL.L UNIVERSITY

--Oo /10 /1 &-J.4RRE.LL.

D.

"

n.N itJE R O.e5 (1.001 4n11e a

.:',

-tc for

"at.

NO t+'

'.;

cach well, holdc

< _.

' } ' ' e' i C i l.

t. i ' '.. '. s t-U I } r Or C' adV C on t -M i n U3 LG d1

S EF riHENL'E 1.

t !Llid Ei--(.Fi t< 4

"Sa+aty ;valt ation Report, n.

4-2.

~4

N39LH B

o^

( 1., 5 0 )

-y

'y aluminum urid platep.

1,.

HCRIZCNTAL LOCATION top and bottou i c.

.

Elements are fixed at the tcp by tr i angul ar spacert, arid at tne

~

bottom by cuide pins.

C+0.51

'

VERTICAL LOCATION in via the lower grid plate supporting the fuel element bottom end fixture.

C+0.5J WEIGHT TRANSFER proceeds from the elem3nt. bottom end f i :: tur'e

?.

-

to the l ow.'r grid plate.

The orld plate is in turn supported by the graphite reflector housit.0, the reflac. tor woport structurt., and the pool floor. C4u.SJ

,

REFERENCE ( '.or n e l l Univorcity: Fi n al Eateouardr R >p(

t, u

b -I cuta

'.1, b.2, and S.10.

'.

• iqures i

AMWER U.O/

(1.50)

Ihe

"r abbi t"

-vetem irrac ation location is in the oi t t er ring (ttuth)

l,5xto 4 /gn.ge, of tharnal f l i.c M

a E+0.5] and provide appr o - t matel v

'. + 0. S.I.

KFFEhEN::E

_itv.

F2nal bs.4eir rdu H>.

.i r p.

i-1.

ar 3

--- 1 1,

'

lotnoll Unive

'

n

,

and.ciqure

.11.

('

.

h_ _EEO [URE5_OE._EOG I LJIY _ DES.[Gtl PAGE

.

dTNbWERO --- CORNELL UNIVERBIT Y-G6/10/14-JARRELL, D.

_

ANSWER tu v8 (1.50!

1.

The n av in ot r'nnic-c*d cencrtic con t '; r uc t i on H1t, v., p o r 21. L1O.bl barrier m<-

2.

There are no windows, and limited access doors with oacketed

e e l s. L + > 5.1

.

.;.

fil 1 wa() penetration; are caulkoa or otherwi ce ceal e:1 E -t O. 5 J REFERENCE 1.

Cornell Un i ver r.i t v : Final Saiequards Report, p.

2-9.

.

~-

(1.,001 (\\NSWtiR B.09

,

The pool water is maintained.at a lower prescure so any l eal: age would be i n t'o the pool.

[+1.O]

REFERENCE

.

1.

NUREG-0904

" Safety Lvaluation Report "

a.

b ~- 1.

.

10 f 1., 00 ;

AN% E-R Ihe water temperature c,

.he reactor pool t l i c.i t ed by the resin s.t s e d in the mt::ce bod dt+ -i on l c er

. +1.01 REFERENCE 1.

Cornell Univercity-I'acility License No. R-W, Afi-END I X O,

T(ichnical Spectrications.

p.

1;.

A N'S<lE R D.I1 (1.001 a.

It is built t r.to tiie i.ir e in tho +0rm of a l un,i n a r s t w ait r at fuel r oil l ot !.

L 4 d 's j]

t:na t h e n rP O f t hi s ac(IV

lir,r.39i g

.c h iei..

6ia,5i

.

[

EEI U REIICE

-!.

1.

Lconell ! !r. :.cr 1t.

i,in 1 a t a u ar -i

'

'

p.

u.

t

<

,

.,

Bo____EEGIt)fjES_ gE _F AC I LIIL, DES I Gti PAGE

cANSWERS - CORNELL UNIVERSITY,

-86/10/14-JARRELL, D.

...

ANEWER 13 12 (3.00)

-

1 of 32

/

^

.

.m..

'd

,

$

2b

_

_

[+0.51 each for listed components REFERENCE 1.

NURED-0904, " Final Gaf quards Report," Figure b.0.

ANSWER Li. 1 3 (1.00)

,,,

2b') 1:W c on t i t u tou t-removal

[+1.03 4'

-

.

,

.

SHOCK ABSORBER VENT HOLES

's i

,

EXTERNALLY THREADED CYLINDER PlSTON SUPPORT C

%

PT

"

-.

..

I I

-'

~~

_]

'I I

l-

'

L, Y

,d

.

.,s e.'

~~

BEARIN35

WORM WORM GEAR

'

..

?

.

_

HOUSING

-

'

c' r

-

PISTON ROD

=

VENT 2 SUPPLY AIR SUPPLY

'

, HOSE

,

SOLENOID VALVE-b

.

'

BOTTOM LIMIT

=

.

CONTROL ROD ('

>

Fig. 5.8.

Schematic of Transient-Rod Drive Assembly

- - _. _ -

. _ _ _ _ _ _,. -..... _ - _.. -.

. _.

_.__

..

_

..

-. -

. - -

.

.

15.

FEATURES OF FOCILITY DESIGN PAGE

_. ANSWERS - - - CORNELL UNIVERSITY

--86/10/14-J ARblLL.,

D.

"

PEF E F4.NC E 1.

Fernel1 O il v e r n i t '. - iOP ho a :l.or I col Looting

_fct.

.

I 4'

l

'

o C-GENERAL OPERATING CHARACTERISTICS PAGE

ANSWER 3 - CORNELL UNIVERSIT Y-86/10/14-JARRELL.

D.

• ANOWER C.01

-

(2.00)

100% power corresponds to 500 kW l+0.53 EXP(t/ f)

L+0.5]

P = Po EXP(t/T) or P/Po

=

15s C+0.5]

T

=

taking the natural log of both sides :

= t/T E40.5]

In(SOO/1)

(6.21) X 15s = 93.2s C+0.5]

t

=

REFERENCE 1.

NUREG-0984, " Safety Evaluation Report,"

p.

4-4.

ANSWER C.02 (1.00)

Decrease.

[+0.5]

The core has a negative void reactivity coefficient.

C+0.5]

.

REFERENCE 1.

Cornell University: Final Safeauards Report, p.

5-11.

ANSWER C.03 (2.00)

-%.

S3.OO C+0.5]

max i mu<n transi ent worth

=

10w E40.S]

maximum power initiatinn

=

basis => 1imit manimum fuel temperature to 1000 deq C L41.O]

'

REFERENCE 1.

Cornell University:

Facility License No.

R-94, Append 1:'

A, Technical Specifications, p.

7.

('

'

o G r.._ _ l M S 8 % _ O.f 5 8 0 l l. @ 4.C O O!! B C P5 B l p I.Il h PAGE

.ANEWERS -- CORNELL UNIVEPSITY

- 86/10 /14-J ARRt:LL,

I>.

ANbWE f :

C.04 ( 1. W )

Th.

I m t-e n t:.u r e s thit t n i.

t u.- i e1 < imrn t s t" 1 1 1 m u,>tain

. i na r Inwm I ty

-

.n c!

t. h a t no ciadaln4 ruoag e wil1 occur.

L<v.5j The concern is encocc c.t r e s s ta ul l d u p in t'ur c l a'.Jd i ng becausa:gt; dis.uclation of 2 1 r c e n i '..M, hydrida L + 0, -h j FEFEPENCE 1.

NUREG-09G4, "Sarety L:voluation beoor t. "

p.

4-4.

ANSWt.R C.05 (2.00)

Power would show a prompt dron L+0.5] followed by an appro:timate 80-second negative period L+0.53.

' Prompt drop" results from'the laroe negative reactivity i n c e.r t i on ab'2erbing fast (prior to slowinq down) neutronn with a resultant repid decline (on the order of several promat n.ut.ran 11fetimec) in flun level 140.S]

Tha OO-occand p r "* l od corrn:poncc to t 'v. ' half

-

} i -f e Ot tho }ongent-lI'vt'd delM ed n O' tt r O n eTai t t o-group.

L+0.U3

,

F* E FE R E Nf:E Cur n. r l 1,, U n i v e r, ty: rc i n a l _ oi e quords Report, ;.i.

L.- 1 t.

<.

.

.'.

L3 0 : t e r 1 C *

l._ _UT. v s h.

J.R..

I N T h0 03 '._ ! 101 ' TO nut:'.Ei f < F-E A L Ti W I HEOF f.

p.

HN5tJER i:.00 (1.50)

a.

400 deq C LFO.

'- ]

r s. ;

i b l.3 l.

I ec atme in t rie e v i: > n i ai

<utomat..

.a v e t. w 4 a t lin e

-

-

u nC On L r e Jl 119d JdjLtiOn *3f DO31i U r e. (: fIt I./

' J U U l il i' O ': 'l t

t ht? t(te l t e m p *> r ' a t. Lt t f; rj + q r s' a :. i t

! l u. /1 }

.

'<Lif. R dill:

1.

IPIf o, F.tl.trd M ahi tipi

.ition'

(h i o1c i s t >

-.

,

.

hiUht.b -tr? 9,

;ovi u.-

.,:. u m d, l e. : o.r'.'

o;.

n!

- e

-

C$

GENERAL OPERATIJJG_GHARACTERISTIGS

\\

PAGE

B inNSWERS -- CORNELL UNIVERSITY-86/10/14-J4RRELL, D.

.

ANSWER C.O/

(1.00)

1.

Direct reading from the transient-rod reactivity worth curve L+0.E]

2, Balancing the transient-rod against other control rod worth curves at low power (approximately 10w).

L+0.53 REFERENCE 1,

.

1.

TRIGA Pulsed-Mode Operationn (handout) dated 11/9/83.

ANSWER C.08 (1.50)

Method entails withdrawal of a control rod at very low power to achieve a slow (long) period, and measuring the time required to traverse a ten-fold increase in power.

[+1.03 The amount of rod withdrawal and time increment aio used to infer reactivity worth

-

through the " Reactivity in Dollers versus Reactor Period in Seconds" curve supplied by the reactor vendor.

[+0.5]

REFERENCE

,

1.

Cornell University:

Training handout, " Control Red CTlibration by the Inhour Method Procedure".

ANSWER C.09 (1.00)

Power calibration or true reactor power, is measured by determining the rate of rise of pool water temperature.

E+0.5]

The height of the detector ( i on chamber) is adjusted relative to riie core centerline until the channel indicates true power.

[+0.5]

REFERENCE 1.

Cornell University:

Training handout, "TRIGA Power Calibration by the Calortmetric Method."

.

'-

'e.

PAGE

C2__

6CliE60l _QFJROlINQ_Gij0Rf)g.TEfM STICS ONOLJERS - CORN;iLL tin 1VERSITV-86/ l u/14 -MtRRELL,

D.

(>rit3t9,is -

t.,

(1.001 l i rr,t

at en in the The eneratino 1 c>1 t is b cu' m h a ' r.

'

L+O 53 ti-

'

LFO.sj Technical Lpecificattanx : ap p eru.n

,5

• a ti a - to_111tt 11ornt

>

_

.

REFERENCE

?m, Append 1: %

p.

12.

~-

1.

Cornell Un i v.?r 31 1. v :

iacility '_icence No.

s

--

,

%

ht

,

~~

4'

-

,

PAGE

s 01_ _.3 NpibU%NJ',:3__O[fp._ CONJ [4(S (Nr. EWERS -- CMRNELL lJNIVERSI TY-86/10/14--3 ARRELL.

D.

• t. t.KO ANMiti v D. O i e

'Jo,

'*n.bl furnitio thc c cce cwitch t o p u l u: ut taoist a ir :t t.trainq the Ny Icck viltch on, rasvit 2n a r e.3 c t.c r scram.

L'U.b]

REFERENCE 1.

N!!HE B-O YG 4,

Sai e t y Evalunttoi Repor t "

p.

L.

-

ANSWER D.02 ( 2. St.O 1.

Start-up Channel - iicuion chamber 2.

Log N recorder - compensated ion chamber

~

~.

3.

Power level Ch it 1 - comp (.nnated ion chamber 4.

Power, level.Ch it 2 - unc'ompensated ion c.h a m b e r 5.

Feak power - uncompencated lo'n chamber L i- 0. 5 _ each

.

REFU.RENCE 1.

Cornoll Un i ver ci t y:

Inol Safeguards Repart, c.

a~z anJ 3-8.

...

AN'J WER D. O J.

(.bO)

Fuel e1cment temperature L + 0. b:1 REFERENCE

_

1.

Cornel 1 Uni ver si ty: iInal Saiequardt Report, h c.

a.4 and p.

5 O.

-

's. _.

ANENEh D.va ( 1.00)

Within the l i eu t, cf the t eq u l at i n.:, rod worth.

[ * i. 0 :1 REFERENCE 1.

C e r nt?1 1 Lin i v er 1 t y : F 1nal Eai. quar d - fepert, p.

t.

.

O PAGE

Dr...lF.ilHyljEl1Jj_ OND _CutJJ 6ULS cMIS'nE R b

- CORNELt. UNIVERS1'iY-86 /10 /14 -J 4n REl.L.

D.

.

.

i,. a w.f-D. u '.

( 2. 0 f-1.

i..

..n r <re lii at

,c o -,i L1 9 e nt'*tm 7 i t. d t c.s t i c n is a v e i ' i S t.'

f..

+, t u p

/,

'T o preve rit wi t hdr awal of two cuntrol rods c l inul t aneousl y durinq

.n c i tu a l cc:otrol *

In prevent s t N d y - rit a t e moac tranni t nt -rott w i t h dr c.w a l unlow

.

the sh t 9 and naiety tad? are fully inserted

To v: :s u r e that a pulse cannot be initiated without cenicr extor operatar concurrence D.

To encure that only the trannient rod can ne moved in pul st r m. 3 J o h

- (4n y four ( 41.-t F O. 5 ] each.

2. 0 %M.

REFERENCE

~

1.

NUREG-0984, " Safety Evaluation Report,"

p.

4-7.

,

.ANSWEE 1>. 0 6 ( _'. 0 01 AHY-- At low power levels, cagni+1 cant e r tr in n c u t r.,-

l e w;l cro Lt Introduwd by intease gamma radiation causina iaaizing eventu 1, i the detector.

L+0.5]

n **s.

,

=

UGJ-Compensation voi tage crcated in a non-neutt'on interactina v o l u rr e is used to subtract the gamma produccd fraction of the s i g n a.1.

leo.UJ At high power levels, this is not necoenary tiecauce-1.

the neutron stonal it now much laraer than the camna ' 1.a n al,

-

an ci

[*0.5]

2.

4the gamma signal becomes a p p r o.,1,v e t e l - propor ti ar.a1 to power in this rectco

[40.53 PEfERENCE 1.

Cornell Ui11 ver s i t y : f: I n al Latoaucrd-Rep. [r !,

L.

'r. and Floure 5.*.

4'

__

_

_ _ _

s, Q __ l tgdf ljtjEij jj3_OND., CONT ROL_O PAGE

.

$

.A N C W l. R b --- CONNELL UNIVf RSIT Y-86 /10/ l d -J r)RRE L L. 1:.

..

.ViSWER U.v7 ( l, 00 :*

twer u squi det,n la os Inc.ertino mar.u c t ;rr m.

is

.J

.

Fower is followers to c h ec t: for proper-innrum.m*; functico and indication overl y.

L+0.53 f>ElERENCE 1.

Cornel 1 thii vei s2 ty:

Training handou*

,' 1 S A Docrationc".

p.

7.

"

'

AN3 WEN D.00 (.50)

The LSDG for-f uel element high temperature scram ic 600 deg C.

[ + 0. S 'J REFtiRENCE

..

1.

NUREb-OyB4, "Sof et y E_ val uati on Report,"

p.

4-b.

,

~

AH5 web D.09 (1.50)

>

YES. NO.S]

The chartent obcervable period on the meter 1-

~10

.

accanda.

The lonaact lived delayed neutron or ecut var <_ V o' a half-

'

I life of 56 seconds, which recults in e -- 8 0... e *. period ano it s

j tin" ef oro easily secut on the meter.

[+1.03

-

+

,_

RF.FERENCE

l w

1.

Cornell University: Final Satequards Report, p.

b-2.

ANSWER D.10 (1.50's

! +0. S J 1.

power demand from tha power demand potention.

>+

power lovel bom the pow-2r-channel it 1 (1 t ner reco~dorJ L *-0. 5 J

..

derivat2ve of th* period nional C+0.SJ

~~

-s

..-

fi [~k !k.I ! I[

-

p 1.

'or r tel l Un1ver.Itv: Final Saiequards hepor L.

o.

_-

.

I l

l

-

- - - -.

_ - _ -..,

,,,,,., - - _. _ - _. _ _. -. _

_., _ _, _..,,

_

__

i-

a

-

O E.

5AFE1Y AND EMERGENCY SYS'lEMS PAGE

c '.N'!.W E R S -- CORNELL iJNIVERSI l Y-06/10/14-JARRELL, D.

-

.01 ( 2. '.0 )

() f t' Q r

11, :6. p ot.or cn eith.'r Sowcr l e /e.

h r u W

..

no etil (chort) period J.

an chamber pcwer supply f all aire

4.

cperating power failure

'.5.

manual E -+ 0. ?. ] eech, Nat3 mum 2.5 points.

RE F l.REf 'C E 1.

N URE G-O'/0 4, " Safety Evaluation Report."

o.

7-1.

ANGWER E.02 (3.00)

a.

A G.N.

type E x h t;u s t Stack f1onitor issdecated in the reactor boy exaaust air duct.

[+0.52., x ::

..

a b.

A-41 radiation.

[+0.5]

.

c.

n high-level alarm ia zet'at voi c pin.

T. + 0. 5 ]

,

d.

Un reaching the setpoint, the system:

1.

rinou an :aud i b l e a: arm f+0.b-2.

deenergizec the reactor Day /cntilation i nne L+0.bJ

'

shuts the re actor b a'/ 1solatlan va)ved E +0. S 3 REFERENCE 1.

Cornell University: Site-cpecitic training handout.

(;N3WER E.03 (2.00)

I O N I Z.A T I O N tvpo ar ea monitura aru loceted or, f r.e LG's ~f (tND WEE f WALL

,

'

of thc r t.Gt-t c7 Dav.

C+1.0)

The f ol l c.wi ng act)ons result fra, reachina the eetpoint_. -

Resi l t li.a Actico 5etpoint i

1 mWhr t 1 n h l,' q f.M l o w aiert I a cW '

L9O.D.

100 mR/ht light plus aud1 hic al mm L + '.'s

i

)

i

>

f

-

.-

--

-

_ _ -

_ __

.. c E,__ _,50EE.1X _ ON D _EOhi$iE,N C L iY EME M S tAGE

3 ANSWEPS - C Dh MEL.L UNIVER'JITY-96 /10 /1 si.i ORREL L.

D.

'

REFl+-NCE

.

~~

'Jor nel : Un i ver :.i t v-Elto-orecl+1c tr ai n i n.; nandout

.

ANSWER E.04 (; t.50)

4 1 :. qu i d entering the bay tloor drain ir routed tc a drain cu.op in the reactor equipment room.

C+0,53 At leact two carriers trand tietween the liquid an:1 itu panni bi c release:

1, tha reactor equipment rump is sampled bef or e being pumpeu to the warte holdup storage tank. C+0.53 2.

the waste storage tank i s also sampled prior to being transferred to the newer system,

-f ac i l i t y waste sump, or to a tank truck for off site disposal.

[+0.53 REFERENCE 1.

Cornell Univercity: Training handout, VEC drawing 1256-M-1 dated 12/59.

-

t 2.

NUREG-O'r64, " Safety. Evaluation Report."

p.

6-2.

..

-.

4'

a.

PAGE

En_50F ET L AND_EMEf3GEUCL SYSIEl;jS e4MSWERS -- CORNELL UNIVERSITY-86/lO/14-JARRELL D.

• tWSWER L.05 ( 7. U > >

Th, +our c)ames of emeraenciec. detined in the crier enc

_1.nn n a 1.

Personnel Enero crigy

- accidents to persons withn.

o unaae to the f ac 1. ] i t y (i ncl udes boc'l l y injury, radgation Locure, a,3

<'

contamination, or a combination)

.?.

Emergency Alcrt -- potential hazard evident - time <,va11able to tM:e protecti ve action.

(ex. civil disturbance, tnreat, natural dinat,ter, n e ar tly fire or explosion)

3.

Peactor Emergency - actual or threatened, TRIGA or ZPH radiation hazard within the l aborat or y (unexplained hich r ad i a t i on., fire or explosion, major spill of radioactive material. pool water leakage)

)

4.

Facili ty Emert ency - Threat or actual release of gaseous ficsion products. (Gudden failure of a reactor fuel el en.on t !

^

~

[40.75] each.for-c1 ass AND explanation (may'be ward or excmp1e suplanation), Maximum'3.0. points.

REFERE(ICE

'

l.

Cornell Un i ver s~i t y : Emergency Pihn d a t e'd June 1984.

p.

c.

ANSWER E. :%

(2.00)

The emergency kit. is located near the laboratory loboy [+1.03 and contains survey Instruments, protective clothing and equipment, and personnel monitoring devices.

[+1.0]

REFERENCE 1.

Cornell University: Emergency Plan dated June 1904.

('

I o

PAGE

F_.,,_Js.T ANDOBD_OMQ_ EL1!iBGEUCE_OtEBOIIN'j__EBUGEDLJRL?

e'"

c;N:MER

- CORNELL UNIVERSIlY

- --86/19/1h1 AF4 RELA _,

D.

O Ath,! t *,

f.01 (2.00)

'u min S/L m z4ro i n applies wien the reect *-

g...thn

.

1.

lu in a cold, <enon free condition

[+0.53

-

2.

has its highest worth control red fully withdrawn L -+ 0. 5 3 P

>.

the higlest worth nonnecured e:periment is in itc mast reactive i

p o s i '; 100 E+0.5!

4.

c. cured experiments with movable parts ar-in their mort reactive

.

ccnfiguration C+v.53 TiEFERENCE 1.

Cornell University:

Facility License No.

R-92, Appendiv A --

~Iechnical Specifications, p.

6.

ANSWER'

F.02 (1.00)

The roactor muct be shown to be aubcritical Uv at least 50 centu/ ult!-

-

all control rods removed.

Eto.51 2 a acnieved

[ + 0. ti _t Feel element; are removed until thir condittoo REFEF.ENCE 1.

Ecrnell University; TRIG 4 SOP TFANEIENT HUu REMOVAL, 0.1.

AN5WEli F. O _'.

(1.Ov)

A Svc.

'm or compcnent i s, operable w ten it in c e p s.b l e of performine its intended function I r. a normal manner.

[41.6 3 RErEfd NCE

t.ornell Unisercity:

Faciltty Licenw No.

f~ - 9 2, Appe.d1 A,

p.

..

r ('

q

PAGE

E.1__310dPOBD._QUtLElipjGENCf OEfilj0IIUJ_CBOCEDUGES ONSUERS

- CORililLL UNIVEFSITY-86/10/14

.J AREELL,

D.

b ANEWEN F. < !4 ( ;. *>.- )

1.

f h e renc t i v:= t y wor t.,

ei t. h e trancient roc s ec t not _. c e >ed I

$3.00.

C+0.51 To 11mtt fuel tempurate~es to

~.10 A dea C.

C + 0 _ 'a J 2.

The stcacy utate power level of the teactor must not e: ceed 10w E40.5J fo limit the final peal t e.np er a t ur e to below the soiety limit (600 deu C in D-ring).

C+0.5J REFERENCE 1.

Cor ncil University:

Facility Li cenc3e r!o. 7 -- 4 ;, appendin A,

p.

7.

ANSWER F.05 (1.00)

Insert a manual.ucram.

L+0.D]

Tech Opecs require that two operable channels showing' reacto,r power be displayed during steady-state mode.

The fact tha.t. the. log N channel remained-stable,. whil e the

,

to.'iffering values tants serious doubts on their

.other's shiftdd d

op er ab i l i' t v.

EtO.53 REFERENCE

.

1.

Cornel 1 Lin i ver si t":

Faci 1ity License No.

R-92, Append 1; A.

pp.

7 a:id 2.

Cornell University: SOP TRIG /) Operations.

p.

6.

Section V.b._.

ANSWER F.06 (1.00)

NO.

C+0.53 A licensed operatcr muut be present at the console at all times.

E40.SJ (Other Justifiable answer - such as relief operator -

is acceptable.)

FEFERENCE 1.

Cornel 1 Un i v er si t.y : TRIGA SDP Operations, p.

2, Bect1on D.1.

('

a -

F.

STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE

s)NSWERS

- CORNELL UN I VEI G I TY-86/10/14-JARRELL, D.

.

Af 6WE',

F.U/

.00)

1.

iny fro:li-s i cat i one to reactor equipment which will effect reactor operatinq ch r ac teri st i cs 2.

A reactor scram 3.

Elianges in core configuration (written in ed in!:)

4.

Chances in control rod position for stable operating conditions 5.

Insertion or removal of e(perimental apparatus 6.

Intentional production of radioisotopes 7.

Changes in beamport condition 8.

Any equipment malfunction c/.

Operating " crew'

(Senior Operator, Operator, " Fec on d Person".

Experimenter)

-

.

10.

Equipment surveillance acti vi ti es

, 1 1.

Reportable occurrence-2 E+0.5J each Mm: 1 mum 3.O coinie

REFERENCE

"

1.

Cornell University: EOP Operations, p.

7.

2.

NUREG-0984. " Safety Evaluation Repo-t,"

p.

26.

ANSWER F.08 ( 1. OCo 130 degrees F E+0.51 No.

Continuous cocration at 500 kW woule result in er.ceed i ng the allowable temperature.

C+0.5]

f(EFERENCE 1.

Cornell Univercitv: b b F' Heactor F'oo l Cooling S/ ste.

T PAGE

E __S10dOOBO_OHQ EjdESGEUGy__OBESO_ IU!j._SBOGE.DUBES

'

ON3WER5

- CURNELL UNI'/ERSITY-a6/10/14-JARRELL, D.

ANC.hEF t '. (.W

!1.50)

Re ac t c operat:en is allowed for two days to permit reonirs. L40.bJ Durir ) tlio tim 2 that the LCU exists, the -f ol l owi ng restrictions apply:

1.

no pulse mode cperation

[+0.53 2.

rio experiments in place which could release radioactive gasses or aerocolu.

C+0.53 REFEREiICE 1.

Lorneli Univernity: Facility License No. R -- 9 2, Appendix A,

p.

10.

-

.

ANSWER F.10 (1.00)

Minimum level is 18.5 ft.

[+0.53 Scram the react.or -(or d. o not start up)

C+0.53

-

.

REFERENCE 1.

Cornell. University: Facility License rio. R-92 Oppend1:

A, p.

12.

,

l

.

4'

-

-

_60DIGIlgN_CQUIGQL_AhpJOFEIY

~

FAGE

G

'

>

iANSWERS - CORNELL UNIVERSITY-U6/10/14-JARRELL.

D.

ANBWER G.01 (2.5J)

1.

G.

survey meters: alpha, beta, gamma 2.

Cutie Pie: alpha, beta, gamma 3.

Ionization chambers: beta, gamma 4.

Rem Counter: neutrone 5.

Alpha probe: alpha only

--

[+0.53 each REFERENCE

.

1.

Cornell University: Site-specitic training handout.

%

ANSWER G.02 ( l'. 00 )

Air ic continuously diccharged from bcam room through the laborstory exhaust s t a c k:. [ + 0. 5 'J

,

The principal isotope of concern is Ar-41.

[+0.53 REFERENCE 1.

Cornell University: Facility icense No.

R-5'2, ( pp endi :s A,

p.

11-2.

-

.

,.

.,,

-

ANSWER G.03

. (1.00)

.

1.

experimental area,* 1

,-.

2.

experimental area tt 2 3.

on the reactor bridge 4.

gas monitor above the reacter

[40.253 each REFERENCE 1.

NUREG-Ood4, " S a f e t_ y Evaluation Report,"

p-12-.

-

FAGE

i G _,_B6DIGIlON_CONIBQL._OND_SOEEIY n

ANSWERS - CORNELL UNIVERSITY-86/10/14-JARRELL, D.

ANSWER G.04 (1.50)

a.

As Low As Reasonably Achievable

[+0.53 b.

1.

procedure:s tg minimize exposures 2.

a check valve to 61nimize A-41 from pneumatic transier 11ne 3.

change in ZPR ventilation to require manual restart after re.nctor operations Any two (2)

[+0.5J each,

+1.0 maximum (other answers may be appropriate)

.

.e. - FK.FERENCE.

..

i

~

-

1.

NUREG-0984, " Safety Evaluation Report,"

p.

11-1.

w ANSWER 6.05 ( 1.' 00 )

Two. [40.5]

,One each, SRO and RO qualified.

[+0.U3 R F_.F E R E N C E 1.

Cornell University: SDP Fuel Handling and Transfer, p.

1.

ANSWER G.06 (1.00)

The occurrence of a defect in the fuel clad simultaneously with a 1.5%

delta k/k or larger transient

[+0.5].

The result would be the release of a small quantity of fission products to the reactor bay atmosphere E+0.5].

REFERENCE 1.

Cornel 1 thi versi ty: Final Safequards Report.

p.

7 - 1 :_.

-

.-

- - - -

e.

. - ____

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

._

P

~

.,50D I /3T I OtLCONTRI.L_ AND_SOFETY.

-i==en; PAGE

1

'

MN5WERE; -- CORNELL UNIVERSITY-86/10/14-JARRELL, D.

ANSWER G.07 (2.50)

A s mi.oT o t t o n s are as fol1ous:

1.

The quarterly whole body dose in 1.25 Rem 2.

IL can be considered a point source 3.

Only gamma radiation is considered 4this assumption can be impiicit)

The doce rate at 5 ft will be -

2 1 Rem /hr X 1 hr/60 min X (D ) /(D )

2 or

2 150 mR/ min 1000 mR/hr X 1 hr/60 min X 15 /5

=

since it requireu one minute to manipulate the valve, the ma::imum number of operations to reach the quarterly limit is:

1250 mR/150 mR = 8.3 or '? operations wi11 cause hi m to ~ e:< cec'd hie ciuarter1y 1imit.

[+2.53

~

REFERENCE

,

1.

Cornell University: Training hendout.

.

s-g 2.

Generic: Radiological Health Handbook, p.

32.

ANSWER G.09 (1.00)

-

a.

gamma, beta, _ neutron i

.53 (any one)

b.

alpha

[+0.53 REFERENCE 1.

Cornell University: Radiat1-fnntrol handou F

- e ;,

PAGE

r, ' G, RADIATION CONTROL AND_ SAFETY

'

o

$NSWERS -- CORNELL UNIVERSITY-86 /10/14 --J ARRLLL.

D.

-

r/

i ANSWER G.09 (3.00)

a.

Any area in which there e::ists radiation at a level such that_

a major portion of the body could receive 5 MREM in one hour.

b.

Area of controlled access for protection of individuals from exposure to radiation.

c.

Any area in which there exists radiation at a level such that a major portion...of the body could receive 100 MREM in one hour.

.~~

d.

REM - dose of ionizing radiation such that the body receives the biological equivalent of one roentgen (r) of X-rays.

e.

RAD - done of ionizing radiation such that the body absorbs 100 ergs of energy per gram of tissue.

3. 7 :

10**10 disintegrations per second.

f.

Curie

=

C+0.5] each REFERENCE 1.

10 CFR 20.

Standards for Protection Against Radiation.

.

2.

Cornell supplied quiz material question (Radiation Control and Safety-question #1).

.

e-

.

.