Text

Exam Rept 50-160/OL-85-01 on 850710-11.Exam Results:One Senior Reactor Candidate Passed,Both Reactor Operator Candidates Failed & Two Reactor Operator Candidates Withdrew Applications
	ML20133N627
Person / Time
Site:	Neely Research Reactor
Issue date:	07/30/1985
From:	Rogers T, Wilson B; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20133N619	List: ML20133N617; ML20133N627;
References
	50-160-OL-85-01, 50-160-OL-85-1, NUDOCS 8508130555
	Download: ML20133N627 (5)
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ENCLOSURE 1 EXAMINATION REPORT 160/0L-85-01 Facility Licensee: Georgia Institute of Technology 225 North Avenue Atlanta, GA 30332 Facility Name: Georgia Tech Research Center Facility Docket No. 50-160 Written and operating examinations were administered at the Georgia Tech Research Reactor in Atlanta, Georgia.

Chief Examiner: ,usy e% 7 5 EA' Th'omas Rogers y Date Signed Approved by: An u < A TP f Br/ceA. Wilson,SectionChief Oate' Signed Summary:

Examinations on July 10 - 11, 1985 Written and operating examinations were administered to one senior reactor operator candidate who passed.

Written examinations were administered to two reactor operator candidates; both of whom failed. One reactor operator candidate. withdrew his application for a license prior to completion of the oral examination and the other withdrew his application prior to commencement of his oral examination.

8508130555 850002 PDR ADOCK 05000160 0 PDR

~

REPORT DETAILS

1. Facility Employees Contacted:

Dr. R. A. Karam, Director of Nuclear Research Center.

~* D. McDowell, Reactor Supervisor

Attended Exit Meeting

2. Examiners:

T. Rogers, USNRC

Chief Examiner

3. Examination Review Meeting At the conclusion of the written examinations, the examiners met with Dr..Karam, 'and Mr. Dean McDowell to review the written examination and answer key. The following comments were made by the facility reviewers:

a. SR0 Exam l

Question J.02 Facility Comment: The setpoint indicated for J.02.3(b) should be 137F instead of 125F. Reference material was' provided by the reviewers.

NRC Resolution: The answer key has been changed to 137F.

b. R0 Exam (1) Question B.03 Facility Comment:

The Bismuth gamma shield cooling medium has been changed to light water. Reference material was provided by the reviewers.

NRC Resolution: The answer key has been changed to light water.

$ (2) Question C.05 Facility Comment: The gasoline generator is now powered by natural gas. The reviewers agreed, however, that the fuel supply had no bearing on the answer or the validity of the question.

NRC Resolution: No change is required for this question.

i

Enclosure 1 2 (3) Question E.07 Facility Comment: The question is confusing because reactivity increases are not caused by steam void formation.

NRC Resolution: The question was incorrectly stated since it should have been directed to the collapsing of steam voids. The question has been deleted from the examination.

4. NRC Post Grading Review Following the review of graded examinations in accordance with NUREG-1021, ES-108, Quality Assurance Program for Review of Graded Examinations, the following changes were made to the answer key and the effected examinations were regraded accordingly:

SR0 Examination Quastion K.06 The responses listed below were also accepted as correct since they correctly answered the question in accordance with the GTRR Operating Procedure 1500.

CR-1 00 Area monitors Kanne air monitors Gas monitors Rod position Log N Scaler Count rate

5. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant <taff to discuss the results of the examination. Those individuals who clearly passed the operating examination were identified.

There were generic weaknesses noted during the oral examination. The areas of below normal performance were familiarity with the facility both in and outside of the control room and emergency and operating procedures.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

ENCLOSURE 3

. ~

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3. aU :1 04 REACTOR OPE :ATOR LICENEE EX An1N ATI0r; n.

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Un. .ie n D n _i rJ _n T _t F. E L . 3,. . .

ExAr.It!EF: 70n F O G E F. i M; I: ANT; __ ._-_. __ _________.-

INE RUCTIONE TD AP P L I C MJ ' :

Use s e ,:.s r s t e aspei for :. e snswers. wr.te snswer; cn one a t -i e anly.

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. g,, h g, & .g L

i A. PRINCIPLE 3 0F REACTOR OPERATION PAGE OUESTION A.01 (1.00)

Reactor buckling has the greatest effect sn the

s. neutron lockage from the ccre,

b. resonance escape probabilit .

c. fast fission factor,

d. thern.s1 ofilization facto .

GUESTION A.02 't.00i The unite of r.eut r on f iv:> ars

a. neutrons /sec,

b. ( n eu tr o n s -c m ) .'s c n. cubed-ser:.

c. neutrons /cm squared.

d. neutrons.'ca-sec).

QUEITION A.03 /1.00i A succritical rosctor with ! ncutron.scur:e stren3th of 20 c ;: s and I source tsnge count r s t r; rf 200 eps has 2 ieff if i: a s s un e a proportional-ttv ccn:ttnt of 1.05

s. 0.?5.

. . G . '; 0

. . n. . e. a

s. 0.20, r*:aa CATEGGPY A CONTINUEE CN r2 O T CAGE * *

s 's i

i A. PRINCIPLEE OF REACTOR OPERATION FACE 3 GUESTION A.04 (1.00)

Delayed neutrons allow sn operstcr more centrol cf the resctor because

a. there are more delayed neutrons than prompt neutrons.

b. delayed neutrons are born st a h13her energy level than prompt neutrons.

c. delsyed neutr ons decrosse the average neutrcn 3eneration time.

d. del a*, ed neut r ons increase the svera3e neutron generation t:mr.

GUE3 TION A,0I (1.001 During 3 power escalation on the Log N channel. it take 30 seconds to double reactor power level. Which cf the follouing is the stable reactor period that would cause this rate cf :hanget

a. 21 seconds

b. 30 seconds

c. 37 seconds

d. 43 acccnos 00ESTION A.0e :1.00.

4hich of the f:11: wing is the ccrrect definiti:n f micrcsco :: cc:ss se:tioni

s. Ths t r '. v a l tstgot are: cf tna nucleus.

b. The effective target s*es of the nucleul.

-: . The *otal :c

. si t s. r 3 c t srs: cf 311 nucle; . ' ,1 q f. h - c -: r ,_

1 The tots: 2'fe:tive tstgot sees of til n ._ _ i t h : r. the :: c.

CATEG0FY A CONTINUEC C 's O- 5 ACE ******

I l

i A. PRINCIPLES OF REACTOR OPERATION PAGE 4 GUESTION A.07 (1.00)

Which of the fcilcuing is definea 32 'the fracticnsi chan3e in neutron population per generation'?

s. F.eff o, Delts F.

c. Reactivity

d. Delte reactivit, GUESTION A.CG (1.00)

A 1/H curve that p r e d i c t-2 criticality estly is referred to as which of the following?

a. Useless

b. Conservative

c. Ncn-ccnservstive

d. Ideal GUE3 TIOri A.07 (1.^0' Which of *ne icilowing csn ce definco as 'the nuncer of neutrons c s.u a i n e f i s s i o r, thst were o r i g i n s 11 *, oorn delsyed divideo M tne total n u:a c e .' of neutrcns cau Inj /Isaicn?

a. Lanbas effective

b. Eho C. I C '. ; JifectiVG-

- ~.

d W S e

(***** CATE00Ei A C0riTINUED ON A/ T :< lE u422>

s A. PRINCIPLES OF REACTOR OPERATION FAGE 5 GUESTION A.10 (1.00)

Which of the fo110 win 3 terms is cefined as 'the energy eavivalent .: f the mass defe:t'7

3. Excitation energy

b. Binding energy

c. Fission energy

d. Critical ener33 GUESTION A.11 1.00)

Which of the following terms ci the six-fsctor fermuls has the highest value?

s. Fsst Fission Factcr

b. Pepr oduc t i or- Fstter

c. Therms 1 Utili:sticr. Fact r

6. Tner n.a l Nori-l e + L a ga Frcb25:1.*

OUE 3 TIC ri 4.12 it.0C' Liat the ctri slas : : c: :ted .4 i t ;- ::r..

harms. -

c hversulic gerformance 2003: MOT 0d 1 *. d e t e r :L i r.17 ~. t '* * ~~I*_*'- i. ! ih l t 2 Of

. TL: ' 39Pc; f 3r f o r ; g c,

': O *i v e C t i c r, f10w.

QUE3?ICN /, . ! 7 e 1 0 T' U;.-- .- 5.,c a e r ct!- ' - t i e r. : mus* -- < , t - - . c '; *: ,' atal -cu.

for SGI;ter POLOT i

l i C T l t 1

r' ~

/t11s CATECCFY .

0 H T D!'j E D C ri , - '- 7 *ME *a x L

9

A. PRINCIPLEE OF REACTOR OPERATION PAGE 6 GUEST ' ' " A.14 (1.00i The heat t r s r.s f e r mechanism from the fuel to the ccolsnt becomes iilm boilin3 at what D N E.R 7

a. 0.0 s.

d Ae E

. Le3 Ce e.,

s*sas E ,'j [ j f" CA'ECCC A att:

t a

1 T

0. FEATUREE OF FACILITY DE5IGGtJ PAGE 7 l

1 QUESTION E.01 (1.00' The atmosphere abo.e the moderstor i: nsintained free of wster . spor by a(n)

3. nitro 3en gas blanket.

b. helium 3a bisni.et,

c. hydtcjon Jas blanket,

d. a r ,J o n gas blant.et.

QUESTION 5. : '

'1.00)

List the fcur materials used to m s k e u r. t he b ic 1 c.31c a l shield surroundin3 the gr aphite reflector.

OUE37IJN B.03 '

't.00) what is the coolin3 medium for the bisn.uth 3sma.s shield for the bic-

~

medic 1 resen:b thielded icom GUESTIOrt 0.04 (1.c0'

. c -rn e d i c a l rat.+srea How is outron attenusticr. acccm,..shed for the Ihielded ic:m -

n. o g e. s . . n . .. ... s. . c c. ,

which ' / r< e of c c r, t r c '. rca h::

. . .e- t i: s1 t e t : c r. ',r:v3h the rz::t:r cere?

GUE? TION E.06 . 5 ':

W h i c i, * -

f :cnt , oo has t .- :3 host *e_ : *. i . . t . worth por sa?

(***** CATEGDP'i B CCHTINUEE CH HE/' OACE *****T

-"--- ac carTLIT) DE3IGCN FACE 8 GUE37 ION 5.07 (1.00)

What means of i n ,3 r e s s is svailable to the bio-medical 22esrch I .n t : 1ded room in the event of the shield door f s i! :r.3 shut ?

00ESTION 0.03 <1.00)

Explain how a :onstant aster level is T.strtained in the reactor vessel.

QUEETION E:.09 (: .00' What i s the purpose of the reactcr vessei cunp line QUE5 TION E.10 (1.00' Wh-/ does the sateld coolin3 sv:tcm have tuc sets of ::rs11c1 cccling tubo ?

GUEiTION E,11 (1.00i How : s criticslity orevented from ac c:: t ; in the spent fuel eccl ~

QUEST!0H E.,i: (;.00~

What is the a:nimum numcer :f shim-isic's alscc that 9.u s t :. e serted tc

. nsure re::tir t.. t c r i t i c r l i ' , '

00E37 ION E.13 ' 1 . '> '

Thc i- t r.1 u n 'uel in the GTFF has been erit a :nc t-

9 3, ... .

s. .

S M 88$...

~

. --t ..

i a

re CATECOPY E 7)i1 T Ii UJ E E ? ZfT CACE *'***

i b

1 B. FEATURES OF FACILITY DESIGGN PAGE :

GUESTION B.14 (1.00)

The neutron 3bsor birn3 ma ter ial of the shim-ssicts bisdes i s

a. ' boron.

b. hafnium,

c. indium.

4 d. c2dnium.

QUESTION E.15 (1.00)

What is the ncrmal opersting prassure cf the GTRR?

a. 15 pais.

b. 15 psij. .,

c.. 25 pair,

d. 25 r2i3

><s** E:10 0F ATE;0RY B atts I

I 6

-- , ,+y.n . _ - . - . - _- , . . . . ,n._, _.-.--,,,v._r ,n- ,.- - -- - - - - - , . , , , , , , -

o C. GENERAL OPERATING CHARACTERI5TICT FAGE 10 GUESTION C.01 (1.00';

Ir a scram did not occur d i r ec t 1;- fron the nn-c:ct sir pressurc :13nsi during ? los: of zir p r e i s t.r c - u '. 3 t woul d ev s r.t s:11. shut r; 3 w r. th:

resctor? Assume no cperstc- scticn and no fsultv i n s t r u rrie n t : .r: . : 2 t i c n .

0UE:.,*.T.un. r . = T.

(*.. . e. .

uh:t will happen 'c t tM ' c il ,u t r , ; < s t e n. s . ' c c n. 3 : r , e .:

. n s icsz cf ower;

s. F? quieting r a rj .

c. Tcp refle:tcr.

c. Containnent ventilst:2n.

n_ u.,r a T 't n.,N L* . r. ~_1 ' '_ . ~. '

A. GLe three irdic i 't:r.s in thn control r:cm 6. h a ' - loss of subststion 5

.a s oc:ured. '1.Si E. What indi.stion in the contr:1 rocm is assilacle for a Icss of vbststi:r, A' 'O.5?

, . o. r - r. .c rr

. .. . .s. a . . , * .,

a f c u r.d in c "0 :e ten uh;t . . : ' r, p e wculo 's :n-. c: tin 3 s D ' C $ 2. 0

,e:t e r char y r le al 7 A : vr:- c - 1 : -j le ri s .

2 Ce t m 135.

D 7

i i 1 O lt .

c. !cdine !2!.

~_.

D i, E,1.

-.: r.n.e,

c. .. =.. .=.. s

r. r .- . .. c. e- -.-

. n. u e . 6: .-

- . 1 '. n .s. .

v., r c - . - ' , - - . i l. - + - - -- .>

'.'.- .+--+

u', ; s +,

.31 1 : :. t sopolv pous' to t r. e c o r, t r o l : ef tre r----' ' o c 1 : r.g

!-tn c ntrcls. TsuE cr FAL2 '

,,,,, e. r1 i c. .; .2 -

. c. . , i. n. . ..

. . p..tr. m- . .; . - - . -

ai . . r .- 3. , , 1 O

C. . GENERAL OPERATING CHARACTERISTICS PAGE 11 GUESTION C.06 (3.00>

For each of tne fcllowing indeper. cent condittanti :escr;ce the r e s r>o n s e of the regulating red. Ir.c l u d e in your a r c. w e - the resson f oi the ststed response.

s. The reactor has c'een :perating in s, toms +tc centrcl at : M4 with equilibrium conditions established when a decrc:se in the H2O inlet temperature occurs for t c. e C20.'H2O hest 9:: ha nge r ,

b. The resctor is oFerating in a u t o a.a t i c control set at : MW two nourt sfter a cold starte:3

c. The rasctor is cpersting in sutomst: 4-ccntrol set it : MW when the instrument supplying the reference power to tro sutomatic contril system fails 1cu.

00ESTICU C.07 (1.00)

Whst is the maximum 'usi centerline temperature under ncrmal operation of the GTRF.;

3. 211F,

s. 1,; r .

u.

u4-e, r .

2 ec...-

m r .

. GUE3 TION C.^3 1.'

Tne s ne s 11 0:0 :1: :visting pump

. murt c: un in osrsliel with the ,n s i n 0:0 pump to increase .s c w e r tc 5 MW~

~

2. :: tc be used o r.1 - cel:w 50 9 tc .n t n t m i n e rs u m p sc r t cddec to the r.. o rie r a t o r .

. . t be v:co in the event :f 'he msin 0 :0

. .> m r- #: i l i r. g sod t:, sn c r. 2 for reduc.2d pouer operrtion.

d. is sn emer3ency system powered fr:n aa ince ene:,t m er cuppl' to allow forced flow during s lacs ti not.r1 power.

(4asaa ATECGRY C CHTINUED Or E 'T ~ J- :E oa

\.

8 0

C. GENERAL OPERATING CHARACTERISTICS PAGE 12 GUESTION C.09 (1.00; What is the normal (Icw rate of tae D20 purificsticn s y s t. e m '

a. 1 spm.

b. ~ 3pm.

c. 15 g?m.

d. 30 jpm.

GUESTION C.1C :1.00' What is the enpocted life of s D:0 purificaticn resin ced?

s. days,

b. 30 davs.

c. I montn;.

d. 1 year.

OUE5TIOu :.:) 11.c:

The pneumatic trar.ncrt tvatem 311cuq samples *c ce recovered at the e c n t i:i n n.s n t building casement st tion within (select the minimum schieveble sn3e)

a. I to sc;onds.

.b. 20 to 30 seconds.

-0. I tc : ;i i n u t e s .

2

d. 11" t: 20 minute .

( s.< * *

ENC 0F CATEGOEY C *****;

D. INSTRUMENTS AND CONTROL 5 PAGE 12 OUESTION D.01 (2.00i How many shim safety bisdes srs cropped by one electronic scrsm :trcuit?

How are the remaining shin safety bisdes relessedi 00ESTION D.02 /1.00' Which cf the (clicwing zlerm c:nditicns is interlocked to prevent a reactor startup;

a. Em e r 3 e n c a. Cooling TsrJ Low.

b. Regulating Rod Low Limit.

c. Cutside Automstic Controller Servo ~Ran3e.

d. D20 Leak.

QUESTION D.03 c i 0 :

State tuc different ways to verify that emergency cooling circulstion exists in the cor e tard.

GUE3 TION D.04 '1 ~}~

Which systea will pr wice the ftrst 'n tcsticn - 3 fuel e l e a. e n t failure?

GUEITION O.05 ! :Ci Phat sr+ ths tw: 513ns1 2 Jr ' e; for the ECCE 21:rm?

GUE3TI;a 0.0c t1.00)

List tuo r:ssons for the Icw ion enamber v o l . -s 3 e I : t s rn ,

(as*** CATEGOFi 0 CONTINUEC ON NE'<T PAGE **t**

D. INSTRunENTE AND CONTROL 5 PAGE 14 GUESTION D.07 (1.00.)

What operster aid is available to help prevent a ' cold ecolant slug' accident when starting a reactor coolant pump other than procedures?

QUESTION D.03 (1.00)

What indication o' rod insertien is svailable during : Ic:s cf Primary Switchgear?

GUESTI]H D.0? (1.00)

The D20 uster purity is constantly monitored in the Purification 5vstem bs

s. salinity cells,

b. pH meters.

c.-conductivity cells.

d. Particulate cells.

GUESTION 0.10 /1.00)

The signals 3enerateo by the Nuclest Instruments :re pulses jonersted by I. n.wtrans s t r i t. 2 n g t h e -z e n s i n g e l e nie n t .

b. r,c u t r e n s snd 3smma rsys strit.ing the sensins alement.

c. chst ged par ticles. c s u s e r_ bs neutron intersctions- striking the sensin3 elen.ent.

c. I o n i r s t i o r. . csused by charged particles. striking the sensing element.

QUEI' OI: D,11 (1.00' tJ h t t s r .: the 0 'O proportional detectors v s :- c for in the Nuclasr Iris t r ument a t i on System?

(***** CATEGORY D CONTINUED ON N .I FACE *****)

a .

D. ItiSTRUMEt1TE At1D C0tJTROL5 PAGE 15 GUESTI0t1 D.12 ( .50)

The indicated power ss detected t, an overcompenssted ion chamber will be lower than actual reactor power. TRUE or FALSET

-00E3TI0tl D.13 (1.00)

The detector used for senerstin3 the period trip is

3. 2 compensated ion chamber.

b. an uncompensated ion c h a n.b e r .

c. s E F-2 de +.ec t o r .

d. s GH tube.

QUE 57I0ti 0.14 it.00)

A major difference ostween sn inn chamber snd 3 GM detector is

s. the GM detector has s photo-multip'ier tube to increzze it's sensitivity

b. the ion chsmbcr is rressur:rea with gas snd the GM dectector operates-under r cc:uum.

c.-thc icP ch3mber Operst0s s' sVCh Icw VCit: 9 t_ th3t s sijnificsnt fiUmbCr Of iOr p3iri 3re IOst Dt r e c oliab i n B t i o n

thefObs decreEsing if s densitiVit/_

3 'hd C ri d e t d '; t c r 0 ;L .2 r .E t e t E' . E s? ch htgher < Cit,cg4 csy21ng ;, ; 3 mUltipli 5 tion t :- incrErse 4 50 Ch3rge Collected tO s islue Ind? pendent O f' *be FC Cf .< : article intt:: ting it (f**Yt Ell [ O ' C f.T E C O i' ' [ *af4*

] '

L-

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i 1

E. 5AFETY AND EMERGENCY SYSTEMS F. GE is ,

OtJES TIO N E.01 (1.00)

What c o n d i t,i o n s presi'e a 'fsst' scram cf all four snim s a f c t- :1:ces?

GUESTION E.02 ' .00: ,

The Ec.er3ency Cooling S y s + e c. 13 c s e- .- s b i c ct p r c e i d i n a. -_.-_- ,ct:1 #1% +:

+

the fool elements fer :

ceriod of at less- ______ . without :; er=tsi acti n.

s. 13 gpm. 15 w i ., t.: tes

b. c: ,"l P fle a OU P,a 1 D '.' l e E

~#

C, [~. 3 p Th .* .% i n *> +, e E Qo . }:Dr

'- 9 hDUT a

3 'g 0 -

. O , '

e egy LiI IO S i I *' ? T e n f. COOditi*.Ci :

'1J

Ll' -

" , ., 0 C t ; C tid C h : 2 ,.

3 ii+

r

' w! b .'.. . !!^

, _ke . .e .'V.-

Li** f . 's 2 3 I f f O

d I". i *

1 3 C '- "ei J '4I ~ ). - - _" 5 Ti - I

~ . , r- . .- .

u - -.

mi,L .!." % a

? . " ' '

".t ,. ,

*; ~

a' 'ls ; ~ - 1 '. i*iil' [ ,h i T G s i: ' :* " ~*

,,162 -

a

-. 4 m >< a-M 43 4. W f _ W

- . - * * . Ei;. 1 JTt1 i . 1 T4 , _

s

.;,4 , 22 .. _~'

l V

T I

t 7

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

h er"e.

W9 afgiu..r W 9

I i

b a

i I

I m n-, , ,.,wn,e,e-r-,- mrwm-.,-wmm,-,.----- --,-.v. - - - - - - - - - --w, - - - - - --

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

i 4 ,

i i !

4.

I

I 1 l 4: . . BAFETY AND ENERGENCY EY3TEME PAGE 17 !

r i

l,. l J !

1 I OUESTION E.07 (1.00i ;

3 1-

iow is the GTRR sutomatically protected f r o n. reactivitv incresses csused !

by the formation of steam voids within the coolant channals of the fuel (

,' assemblies? -

.I ,

i l t !

GUESTION E.0S (1.00~ '

1 i

uhat sutomatic sctions will occur .<pcn e.;ceedin 3 the gsseous activity -

t j s.etpoint.In the exhaust systeni i t

1 d ,

f i OUESTIGH E.07 (1.00 :

4 i What automatic actions occur o r. ECCE i n i t i a t i o r. '

4 1

.]

GUESTIGH E.10 (1.00) i 4

An overpressure ccndition in the resctor cessel is relieved b, ,

i :

, 2 motor operatsd rclief calve l a

b. sn sir cpersted relief v :s i v e , ,

f e. a pilot operat<d relief vs1v', ;

I l d. a ceptere diaphraga. ,

t 1

l QUESTI0r! E,11 s1.00i !

1 i

Wh2t ts thC intarCIl dGIiin c * .? I : u r i cf the '^ >::t--

...i t f i n t.. .N ' 2011dinq3 -

i l

4 i

s. _

. i I; 3.

i l

S. IE p;.J.

c. "' A :. s : . .

i

3. 5) :!!J.

i

' II I ee est , ed .

r i

I 5

i l

i r

I p

i h

i I

~ - , - . . _ . - - . _ . . , . . _ _ _ . . . _ _ , , _ . _ . . - . __. __.___ _ __ _ J

E. 5AFETY AtID EMERCEtJCY E Y 5TEtG PAGE 12 QUESTI0t1 E.12 (1.00'-

Wher: c:e: t:1e 0< err <re : :c Feli f S v s t 2 a, dischs 32 t::

"? e ** Er'*-

L Or ,/~~~Oy- E t

g .s

O F. 37ANDARD Aric Er1ERGENCY OPERATING PROCEDUFES PAGE 19

'iUESTION F.01 (2.00)

List the immediate acticns for performin3 Code AELE, Include sny remediel actions where applicable.

QUESTION F.02 (2.00)

List the immeciste operator action for perf:rmin3 Code EAVEF, OUESTION r.CI (1.00'-

What i: the appecpriste cperster :: tion t: secire emergency ccolin3 flow when it is i r. a d v e r t a n t l y initiated GUESTION F.M (1.00)

'4 h a t is t h c- hsckup emer3ency ecelant sucol, and 'cw ,

is it inittstec7

n. . yt : .e v. ta p

. r .ws ?<.p M c .4 12 :sent / vel pool w: tar vicpl:ed t th' ? pray System in en ener 3ency?

s. A r, opor ate- .s1ves in the s p e r, t fuel pool allowin3 3ravitv drsin to the 5.crav 3' tes, b , . An c r- e r s t e r . 1ves in the E p m *. f cel cci snd then start 3 p i; m p in the t r :r ? #er Fi Fin 3

. An '9erE!C~ :OnneCt3 3 t e ~i? C r I r V ' C E i~ ': 511Cw 70iVit*. Or3in tO the E P ' *. E . i t 411

d. ',

L; #. r 3 t e t' CCnne:tI 3 tet90r3r h0Ie 15d - temOO"Er< " U fb r- tC 4 - ' c. ; f e t !. h c y>' 3Y t: ihe Sprav 3 v s t e l'.

011!'?T70N F.'4 1.50*

Uhat -

'h-

. : " cod e?errt.;r a c +. i c n f:r :

. :::1: + : ng r:d '. : . . : :. : '

' l ', ' P - : Or. . t ; n3 (11T*Y CATEGORY F C G a' T IN 'J E O 0 ?- 4E'" :-AGE *ie27i

.. . _ _ _ . . _ _ . _ _ _ _ _ . _ _ . _ ~ _ . . . . _ . . _ . _ _ . _ _ _ _ _ _ . - . . _ . _ . . _ . _ . _ _ _ __

l 1

i .

e I

F. ST AND ARD Afl0 EMERGEtlCY OPERATItJC FPDCEDURES r. A G E 20 4

I i

j 00ESTION F.0~ (1.00s i i

What in the 14 :: i m u n, allowsble de/istion between +iw highest snd Icwest .

thin- bisdes during notn.a1 opersti:n: a b :iv + 50 I;u r j l'- ,

i s. 2 de3r es. l l b. 5 degrooi.

c. - Segrec:. .

t i f d. 10 dey ces. :

i l r q.u.e.c.T7.0H 1.i'.^.i.

r F.A.G i i ~h- T: i n i n.u n. 311cumble r e s.: t o r e3 t:d ivrina : r :ter =t:rturs ::

( !

l

s. 5 t e: ond s .

n

(

' . , . . 10 seconds. !

I I

! . :. 15 2:rondt. .

s - r

d. '

, 30cCnd'. I i

i i

I OUE.FT09 r ':'

' 1 . ~ >-

f

f. Uh0D plt (p7 t, h ,1 e 3 * :! - [ *, ;Jt;nj'i- .! c a , tral. t' _

c .,,, q '- ;g,;3[ ,; n ,;py ; t '3

. [

[ i. c. . .. 4y:.

.-.. . ,._..,t . . . . .,. : 13 1. .-, ,}.

I 4 3

a. ..

j l

l, f 1 3 ',

h l

,;,.-t 2 .. f g e-i' g y. - > .. .

e. i,.,

7 .. ,. ,. , . . , .

c. r - 5. . ,- - _ .. . . .. . : >-

... .. . - c - . * . - ,

4 .

. .. a g, cs .- u. r_

.- .... _ . , p 1_. .i ,. -

1 1

i

.*

t1% " A I E C C I I C)fl*[NUEO '* ? ' i[i ~

.[ E

8

1 ;*

5 1 h,

j I.

i f

I E

i

- i i

3 i

i k

1, 1

i 4

i !

I 6

4 s.,,._ . . - _ _ . - - , , _

t

=

r. diAt4DARD AND EMERGENCY OPERATING PROCEDUPEF PAGE 21 QUESTION F.11 (1.00)

In the event of s icw 0:0 tempcr3ture slarar 'he t:mper:ture shculd be increased by

2. starting the stindby 0:0 pump.

5. r ep o s i tioning t he- shin. blade = Ind/or reguistirc3 roc. z necess ry,

c. increasing the 900 (Icu t: the C20/H 0 heat eachsnger.

d. id f usting the Cooling Tower Suten s t- necestsr..

QUESTION F.1 't.00)

The 320 low tempersture Iinit i? imposed becauss

s. cf the .nocr noderating sbilit. of D20 st icw temperstures.

b4 -of the f a i r l i. high freering tenperstore of D20,

c. the DIO circulatin3 pumps aill everhest from reunp in 3 wa ter with a higher d e r. s i t y then the c ;ng dcsign limit:-

d. cf the uncertaint. of the f st (1+ in the er eriment penett: tion:

C?vFed bV a rt incre3EE in neJtron b!:I ? : ' t O' in j .

r**** ENE CF CATE005' r x2 -

G. RADIATION CONTF:0L AND S AFETY PAGE :

f a

G.01 GUESTION (1.00)

> What isotope is formed in the resctor's grsphite regicn

hat is a pctential .

o rsdistion har.ardi

'00ESTION G.02 't.00)

Given 23 jrams of Al-28 with sn setivity of 1.36 E23 dis / min and a decay constant of .309/ min, what would be the setivity sfter 10 minutes?

, s. 4.23 E : dis / min

b. S.46 E21 dis / min

. 4.23 E21 dis / min

. d. 9 46 E20 dis / min GUESTION G.03 (1.00i What-i: the required thickness of lesd to reduce-s i hev gamns flux from E? Nev/(em squared-se:) dour. to 2 hev/icm squared-se )-

Fofer to the equsticn shcot fcr tenth snd hsif thicknesses.

a. 3.45 in hes. .

.3 . 3 inc..1 e s .

O, .

c. 4.11 in:7e:-

d. J . -: 0 inches.

i

.0UESTION G.04 (1.00)

I f -s point tcorce af gamma rsdistien 31.es sa espasure rsts of 10 m r .'h r at i noter. wh,t -ould be the e::po sur e ' r s t e st 5 meters

s. 5.0 mr.Mr.

I~

'b. 2.5 mr/Pr.

c. 2.0 mr..ir.

6, 0.4 mr/hr.

* * * *

CATEG0FY G CON'INUED GN d E X T F .', G E *****i.

t-i k

a

G. RADIATION CONTROL AND SAFETY PAGE Z3 OUESTION 0.05 (1.50)

How is environmentsl monitcrin3 serformed srounc the G T F. F. 0 QUESTION G.06 ( .50)

Where are the arcs survev records asintained' OUESTIOtl G.07 (1.00'-

Match the following isotopes with the princips1 tvpe of radistien e::p e s u r e hazard. The choices rro s , bc used morc th:t once.

1. Ar-41 s. 3smma 2 tritium ':i . alphs

2. N-16 c. neutrcn

4. Co-60 d. bete

e. proton GUE3TTON G.0E (1.50' rt gie three w rf -: thst #resh fuel is contrclied in order tc

event cr.1ti: 1it, O f.!E 3 T ! .? M C."c 'l.:O' How .s an open fool s c - i '. i c n :t 'h7 t e r. of the rc:ctor : cntrclied to F~eVer.t Fer3Onnel f r D IT. 1" L','e r t a n t l y D 9 i '. 9 O '. * * ! EMF OsOd O '. tn?

T3ci: tic- be3m dij n i t', g r e #'J O ! ing ?

l') g t. :.'. T *i n. p

~. . . A. . 1 , S. r.

N :w .: Od13k1CF '~03@ln] S T e 'i e n k O d # RCD

k~ . 5' ~ 4 T [ S e I. f I [ dC1e3 5

3. ,.\...: ; ~ ~.JFr 1 n.

ie e i. ...r..~,-

N C t- di the A n t r I f c .I i fi t 0 the pir9 t '.' O n e l del: u f'C '_?ctcr : n * ? C !. l '3 c .,

Ofd9' t0 p r ever,t O V t> T eMLGsVPC tO pe*sOfsrGII

( 8181 't C A I E G O F. ' I. COf)TINUED CN 3I'* ~ ,) :~ E 8 8 S 't 2

G. RADIATI0t1 CONTROL MJC EAFETY PAGE 24 OUEETIO! G.12 (1.00' Hcw much radistian e::p o s u r e is 3 r, undergrscusta -tudent nc t m 211 - limited to7

3. 107; cf the 10 CFF 20 1 -

t. 257, of the 10 CFF 20 linit.

c, 50 ?; of the 10 CFR 20 112 6

-; . 1 T; a-' t t.c 10 C F F. 20 1 : ra i * .

u pm.e T r r r!.

C . .* 4 i. t. ..

,^,.,

uhich of the fallowing i; e 1C CFF 20 emesure limit?

2. 5 remi> ear-whcle bod',.

h 1 em/ou a r te r -whol e b,d,

. 15. 5 em/ quarter-hands.

i, - r e m ' _1 e r i n - 31 i n rf whol- b:c.

(1 s t r . ~, . p y

... i[ . r.

'~

o.- :-- i r. - tC mP-t' ,:ur , cmma field fr tinutes- what :. 7 vcur dose

"~

ir n.F: E H af*er ninute:~

'i s I $

4 i

e.4

'. ~ * ..y

> - - =

peog ya' ' - t ,*,ei L ; e, n ! i; 8*? a E i t * * * *.*. *.* *

t. t t Ef:[ !F [ X ,'i r* I ,1 ;. '- ~ t*

seat **r e s

-- . ~

A. PRINCIPLES OF r.dACTOR OPERATION DAGE I5 ANSWERS -- GEORGIA INSTITUTE OF TECH . -35 '07 /10-TOM F OCEPS 4

ANSWEF A.01 (1.00' 1

I REFERENCE hMS OF -riC -if I C T-NhF . c.15.

a tiuHt t-n.,-- .-

, n,. .

b

~ -r rFrtwpre w-n d 3 0 F '- H C - 5 F S ~ ' - F P . p.10.

ANSWER A.02 (1.00>

b PEFEREr!CE 1 . .. . . , ,

flil _; u r^ - f* L... I': n. .G.P.Ai .

n' i. j 0., Uwr

~I n.\32

^

6

. i,t i M

em.

f" N 5 0 ? - f1 C - 3 F 3 - 5 I - ? * ;.'2, .

.3. a p : - - ,

rt6 w H + (, =a . 4 . .. s

. a'* 33 * .L **'. . s 'l b ,-

' 4 s 5

'. -C.;V :t.-..-'. .. s.

i s !. ' .' ? ' ' . ~. 3 : *. , *...T.<<.. "

- . ?. L f i j . 5 (* .

?*,,. . ) E.- t- . . . './

o l __ _.. _ . . _ . . _ . -

""dcTFLE3 UF REACTOR OPERATION PAGE ::

ANSWERS -- GEORGIA INSTITUTE OF T E C H . 3 5 / 0,- ' i G - T G ri FOGER5 REFERENCE C.: A L , n.; clear Reactcc Theory, p. 5-2 ANSWER A.07 (1.00>

c REFERENCE NO3, Reactor Thecrv ANSWER A.05 ,1.00>

b REFERENCE NUS, Reactor Theor.

ANSWEF A.0? (1.001 C

EEFERE:!CE N1) S , Reactcr I h c a r '.

AdSHER A.10 (1.v0+

.O PEFERENCE CP!,L. rioc le r s .: .: tar Thear . -. -15 l4 . ; )W, q $, f_.

4 .

M6 A 4

,4 .-,,.

d f r u,P 4 . ,r_.e -. v r B J m 4 $ .I',

a #

t I

r

'oTNGIPLES OF EEACTOR OPERATION PAGE 27 ANSWERS - GEORGIA INSTITUTE OF TECH.-95.'07'10-T0h PCGEP5 ANSWER A.12 (1.00)

For 0.2~ pcints esch:

1. Reactor Pcuer -

. .Peacter coclant ficw.

3. Reacter coolsnt ten per atur e.

4. Mooerstor level.

PEFEPENCE U T R. F.

i ar u .,. 4 t .

ANSWER A.13 (1.30' G ) .5 ma t.,t s sach:

1 D20 coolant.

2. Shield coolant.

T e_ r rPw

1. J~L -r

. r f.

G7RR. OP 2015, c.3.

- ,s' t1 I*. !, kl _ _L P. M.4 -f4 k ,& . (, .

b.

.....s- .-.

.9 9 $ M

4 f! ( .s4: L 1Pc t e r f 0."!Ted A c 0

a;.[ 6J.

9

R- FEATURE 3 0F FACILITY DESIGGN PAGE 23 ANSWERS -- GEORGIA INSTITUTE OF T E C H . - S L ~. ' 10 - T 0 h ROCERS ANEVER 0.01 '1.00 6

REFERENCE

. a .s. n. F , r . 4 a-.

L. _

b.v_-

nN:,Wtt t,.vu 9 I) 23 ,~.Cinti OCCd

1. borII

.. S t .i e l 9 4

. se -

. o*

4. concreta REFEPEN:E u, -.F.

r.

r . e;.-.

tj e i.. u E r. E . , .5 4

. .,s M SO r.: t L t.L d L L u ,, : n t- - .-

nr.- ~c.- c. .. .

a-.

.J 3 t s i , i r. t -

F EF~ TrME

- I .

e 4

^ =}\'1 . :. j ;G,

,:. ; .- . i ;_* ,,m

j ;- .

,. 3.. , ,. ,

s t r91 9 .-..:-r

'O e B. FEATURES OF FACILITY DESIGCN PAGE ?

ANSWERS -- GEORGIA INSTITUTE OF TECH . -85/07 e'10-TOM F0GERS ANSWEF E.06 .50' Shim ssfety blade, REFERENCE GT 5AR, p.52.

ANSWER D.07 ~1.00?

'li s minway in ceiling cf - o :::. .

REFEREHCE GT SAR, e.64.

ANSWER B.05 (1.00i 000 it withdr:wn frem 'ho : t c r :: g : tan!' vis purific: tion pump and injected into ths mzir: cire p u rt.: su ' ion piping CO.5]. E;:ces= w?ter will be diverted back to the stcrsje tani. v12 c, r#1cww l i r. e CO.52.

4 REFEFENCE GT SAEr -s. -?.

r1-,< j e. u 6r. er e. e . -

r. e 1.,...-.

se r. . eA imr -

3c I Ie b 9 '$ . I J I 'E + 'L *E 5b5 -.! o b) < 5s .U 'I3 .,

9

ese es . r .-

s J V W*WW Y*

e L P * ~ L el fm Y; J%. ... )MI .. s ..ht

~ '* *

ii es 5j 'I. Q. w.".

$ . .. .s <

g I, a.f5 * **{,-el + IA * * * ' "1 e 1-j*-D

s i

d .. E.**- , r.! T y . 9 fI1*'a 9 ,*,,". ; ..,", "

a t * ..

p % 5 .; *3 .-' ;4 ;*

[ j ** 's Pg s.

t t - -

k 'J D $ ' ;5 k C. E N E r ~ a;* E p ., .,. . .

O i 3 N .w + G.5 i

er m- n a.-- r ,,e . - eo n. a v- - -- .-e- , --,-wa2-.w.,w--w. r

O E. FEATURES OF FACILITY DESIGGN PAGE 20 4

AN5WERS -- GEORGIA IllSTITUTE Or TECH.-9E/07'10-T0h POGEFS i

ANEWEF E. 11 (1,00' Mininium distance be+. ween ' : e 1 elements.

R EFEF:E N C E GT 2AF- p.130.

A tl E M E F E.12 (1.00)

PEFERENCE CT SARr p.137, A N 5 H E F, E: .1.7 (1.00:

C REFERENCE

'J5 N F C :.eSe3ren E c 2 c t. c r s r ,0 35.

A tJ 5 WE R E. 11 t i 0 ':

== age _em -* , n T,L f L A L IJ L L'S s 3i; E LI R e 5 0 3 T C .'I 5. 2 i C

C l' i r ' e'- 5 ".~. .

s

'l qk . . .-- . . r . , , -

ash I e id T h b r .h .s 9-4

._r. . ,. ,

J 4 l'\ 4'. )d %f 6 9

C. OENERAL OPERATINC CHARACTERISTICS PAGE 31 ANSWER 5 -- GEORGIA INSTITUTE OF TECH.-95/07/10-TOM ROGERS ANSWEP E. 01 (1.00)

Reflector drain valves would openCO.53 reactor would snutdown on loss of reflector iea:tivity or on a 1cas of overflow trip CO.53 (either way is accepted )

REFERENCE.

GT EOF 5024, p.2, AN S WEF: C.02 (1.50)

Ce 0.5 points c. cn.

3. Reg roc cecomes inoperable it position when LOF occured.

b. Drains.

c, I2 secured =nd containment botiding isolstes.

R EF EF:EN C E GT SAR. p.13,~.

AN5WEF C.0I (2.00-Anv 3 ? O,5 ooints e s i, :

A. 1. 5 : r a n. .

E. :ss of IdC scuer.

3. Loss c., f r..= * : u r y Ism;i 4 Emergere. li3 hts ccme :.

E: . T,o r c i nanc. Ca.52 CEF~KTMC"

TFE OF 5 : '. ! : .

ANSWO- C.:' 1.0Ci b

FEFERENCE GirF OF 5120- p.1.

y-

C. GENERAL OPERATIllG CHARACTERISTIC 5 FACE 32 ANSWERS -- GEORGIA INSTITUTE OF TEC H . -8 5 /0 7 '10-TO'r F00EE3 ANSWER C.05 i .50' TRUE.

AN5WER C.06 '3.0C)

a. Fe 3 rac will th c < e i r: C :' , 51 to .ss*.sblisc r e s : *. c r scwer at s -int The i n c t e r 3 t -j : colin 3 c suseo 3 power inctc21e from tne tit C :C.53

b. Peg rod will move out CO.51 t: o ,t p e n t : t a f .: r tenon b';il h ::.52.

c. Peg trd will not mo.e C5.5] becsuse the :cuer control 2,Itcm sutonat:cally switched to wanusi on +he - 10 *. se+:cint t:

reset:r power dev:sti:n [C.51.

REFERENCE GTPF SAF. p.69.

ANCWER C.07 1. f 0 :

=

.-r r F.F E.. N e.r f- t ri [ O a,* tO g s'- .I.

..se -+* 5t- . p t -

rse r. . r. c_ .

O e

r Tr e : AF . - ~5

,nc ;rc :,o: , .:

._ _ ....$.[.

. .. _m . . g I. ._.

9

C. GENERAL OPERATING CHARACTERISTICS PAGE 33 ANSWERS -- GEORGIA INSTITUTE OF TECH.-95/07/10-T0H PSGEF.I ANSWER C.10 (1.00) d PEFERENCE GTRR 3AF., p.93.

ANSWER C.11 ( 1. 0 ) :-

3 REFERENCE GTRR SARr p.t17.

i .

l i

l 1

i

f D. INSTFUMENTS AND CONTROL? PAGE 34 ANSWERS -- GEORGIA INSTITUTE OF T E C H . -- 5 5 / 0 ~ ' l ~; ~ M : 0GEEE ANSWER E.01 ( 2 . 0 0 :'

2C1.03r B. electromechanical : i r c r> i t fcr a sc* m ;r.it :'ed e- . sr-instromont ch annc i [1.03.

FEFERENCE 1

4 CT 3 /J . p.i~.

,dl t*sp p p.. F,*>*_

u ' f. . n. o *.

E REFEFENCE

-v .- - - --

bI .' N b ' e- _p- . 4e

a

, r j e2Wrr. Re r, . A. *., /1.,;n.-

ficw f. am

1. Ecreiccpe '

: :':1d tc a m e r g e n.: v coc1:nt nrt:; CO.53,

. C o o 13 r. 4 u: : 4 t h e t ne o c :r. : ?c- CO.53.

p e r E .t...p !. ". -

~

4

GT IAF. 1.9' O -

c.. Il .. . .-

g

. _ [ l , i. .

4 -

y

% w 4

4 EF~ ENCE h' C Ii 0 5 ..g

.,*! s-

. .c . .u.c. - n.-e .L,

? [. ' 4

1. a'c-.;r,

-1 117 ' : ;it.- *cr /21.s ' * '. ', - --

f.*.,,

(n, * -_ w., i 3.,+1

t. ..c 4

?u ? ?u0 ? h. u h,1,. C.

\ r,. p. . r w. r. ene a < . -y.,-

f

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

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

e . .

D. INSTRUMENTS AND CONTROLI PAGE 25 ANSWERS.-- GEORGIA INSTITUTE OF TECH.-95/07/10-TOM FOGERS AN5'JEP D.06 (1.00 0 0.5 points esch.

1. Erroneous si3nal to. # 1u, monitorin3 ssfe* . channels.

2. Power icvel triF a n. : 'scif-theti c e n r.e t ce sstisfs:tcris caccleted.

REFEREbCE GTRR- EOF 3005- ,c . i

/.N34ER D.07 1.00 A low + s m .2 .

rstore interlock. Produces an 31 s r n. [0,53 if Icu cecisnt tons limit of SOF is resched E0.53 REFERENCE GTRR SAR. p.120.

AN99EF O.09 1.M' V: Us1 check of ccch dr: ts m e : n stit : n..

GEFE-ENCE -

.. . .r r . c.J r e,,..

a . .. .

.c..

ANCHCF D.07 '1.00 cEFERENCE G T F/ F 5 A T. - :.33.

ANSWER 0.!' '1.i' i

RE EFENCE I!E Tech han ;;1 W=t. P tJ R , -.E.1-3'

g D. INSTRUMENTS AND CONTROLE RACE 2c f.NSWERS -- GEORGIA INSTITUTE Or TECH.-85/07 : n - 7 3 r; : 0 2 E F. ?

ANSWER D.11 / 1. 0 0

P r ov i c;c s indetendent cro=s r. e c t e ,f NI: during i r t : r t o :. .

F ErEF Et1CE GTPF' CAP- p.6:

MJGWER D.1: .50)

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e 9

ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: GEORGIA INSTITUTE OF TECg.

REACTOR TYPE: TEST DATE ADMINISTERED: 85/07/10 EXAMINER: TOM ROGERS APPLICANT: ___@biEf_6_______________

INSTRUCTIONS TO APPLICANT: ,

Uco separate paper for the answers. Write answers on one side only.

Stcple question sheet on top of the answer sheets. Points for each quastion are indicated in parentheses after the question. The passing grcde requires at least 70% in each category and a final grade of at 1sost 80%. Examination papers will be picked up six (6) hours after th2 examination starts.

% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20 0 20 0

___I__0__ ___I_0 _ ___________ ________ H. REACTOR THEORY 20 0 20.00 RADI0 ACTIVE MATERIALS HANDLING

___1_0 ___ ______ ___________ ________ I.

DISPOSAL AND HAZARDS 20 0 20 0 SPECIFIC OPERATING

___1_0 ___ ___1_0_ ___________ ________ J.

CHARACTERISTICS 20.00 20.00 FUEL HANDLING AND CORE

________ ______ ___________ ________ K.

20 0 20 0 ADMINISTRATIVE PROCEDURESr

___I_0 ___ ___I_0_ ___________ ________ L.

CONDITIONS AND LIMITATIONS 100.00 100.00 TOTALS FINAL GRADE _________________%

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

5PPL5C5UTI 5 555UdiUR5~~~~~~~~~~~~~~

r s

H. REACTOR THEORY PAGE 2 QUESTION H.01 (1.00)

A constant subcritical multiplication count rate does not meet the d3finition of criticality (Keff=1 0) because

o. there are no delayed neutrons when soberitical.

b. there is a decrease in neutron population that is not detected by the source ranSe detectors.

c. it has no effect on the reactor period indication.

d. the definition of criticality excludes source neutrons.

QUESTION H.02 (1.00)

The inhour equation discribes the relationship between reactivity and

o. reactor period,

b. moderator temperature.

c. fuel temperature.

d. shutdown margin.

QUESTION H.03 (1.00)

A suberitical reactor with a neutron source strenSth of 20 cps and o source ranse count rate of 200 ces has a keff of (assume a proportional-ity constant of 1.0)

o. 0.85.

'b. 0.90.

c. 0.95.

d. 0.99.

(***** CATEGORY H CONTINUED ON NEXT PAGE *****)

e 1

H. REACTOR THEORY PAGE 3 QUESTION H.04 (1.00)

Delayed neutrons allow an operator more control or.the reactor because o there are more delayed neutrons than prompt neutrons,

b. delayed neutrons arc born at a hi 3h er energy Icvel than prompt neutrons,

c. delayed neutrons decrease the average neutron generation time.

d. delayed neutrons increase the average neutron Soneration time.

(file STION H.05 (1.00)

During a reactor startup, the first reactivity addition caused count rate to increase from 10 cps to 16 cps. The second reac-tivity addition caused count rate to increase from 16 cps to 32 cps. Which of the following statements describing the rela-tionship between the reactivity values of the first and second reactivity additions is correct?

o. The first reactivity addition was larger,

b. The second reactivity was larger.

c. Both reactivity additions were equal.

d. There is not enough data given for anyone to determine the relationship between the two reactivity additions.

QUESTION H.06 (1 00)

Th notation Be-9(alpha, neutron)C-12 means

o. A Be-9 atom absorbs an alpha particle, resulting in the production of a C-12 atom and a neutron.

b. A Be-9 atom releases an alpha particle and a neutron, resulting in the production of a C-12 atom.

c. A Be-9 atom absorbs an alpha particle and a neutron, resulting in the production a C-12 atom,

d. A Be-9 atom absorbs a neutron, resulting in the production of an alpha particle and a C-12 atom.

(xxxxx CATEGORY H CONTINUED ON NEXT PAGE *****)

H. REACTOR THEORY PAGE 4 QUESTION H.07 (1.00)

Which of the followin3 is a correct statement concernin3 radioactive docay?

a. When a nuclide decays by beta emission, the new nuclide will have increased in atomic number by one and the mass number will be the came as the original nuclide.

b. When a nuclide decays by alpha emission, the new nuclide will have decreased in atomic number and mass number by two, from the original nuclide,

c. When a nuclide decays by neutron emission, the new nuclide will have increased in atomic number by one and decreased in mass number by nne, from the ori 3 i nal nuclide.

d. When an element decays by gamma emission, the new nuclide will have increased in atomic number by one and the mass number will remain the same as the original nuclide.

QUESTION H.08 (1.00)

Which of the following is a fissile nuclide?

a. Th-232.

b. U-235.

c. U-238.

d. Pu-240.

If 0ESTION H.09 (1 00)

Which of the following materials would require the highest number of neutron collisions to reduce the neutron's energy from 2Mev to lev?

a. H-1.

t b. H2.

I

c. H20.

d. D20.

(***** CATEGORY H CONTINUED ON NEXT PAGE xxxxx) l 9

e i

H. REACTOR THEORY PAGE 5 QUESTION H.10 (1.00)

A good neutron reflector will have

c. a low logarithmic energy decrement.

b. a high macroscopic scattering cross section.

c. a high macroscopic absorption cross section.

d. a high Fermi Age.

QUESTION H.11 (1.00)

The neutron flux in a reactor with a neutron density of 1.36 E8 neutrons por em cubed and an average neutron speed of 2.20 E5 cm per second is

o. 6.18 E2 n/(cm squared-sec)

b. 1.62 E3 n/(cm squared-sec)

c. 8.40 E12 n/(cm squared-sec) d._2.99 E13 n/(cm squared-sec)

QUESTION H.12 (1.00)

During a power escalation on the Los N channel, it takes 30 seconds to double reactor power level. Which of the followins is the stable reactor period that would cause this rate of change?

a. 21 seconds

b. 30 seconds

c. 39 seconds

d. 43 seconds l

l (**xxx CATEGORY H CONTINUED ON NEXT PAGE xxxxx) i l

L

s H. REACTOR THEORY PAGE 6 QUESTION H.13 (1.00)

Which of the following is NOT a samma ray interaction?

o. Photoelectric interaction.

b. Compton collision.

c. Inelastic scatterin3'

d. Pair production.

QUESTION H.14 (1.00)

The heat transfer mechanism from the fuel to the coolant becomes film boilin3 at what DNBR7

c. 0.0

b. 1.0

c. 1.3

d. 1.7 QUESTION H.15 (1.00)

The thermal power to the D20 coolant is ______ with a core flow of 1800gpm, en inlet temperature of 114F and an outlet temperature of 125F.

o. 2891 kw

b. 2914 kw

c. 3208 kw

d. 3492 kw l

l

(**mmm CATEGORY H CONTINUED ON NEXT PAGE um***)

1 i

i i

l i

l l

t_

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H. REACTOR THEORY PAGE 7 QUESTION H.16 (1.00)

Which of the following correctly sequences the heat transfer mechanism for an increasing fuel cladding temperature from 110F to 2000F?

o. Single phase convection, nucleate boilin3' Partial film boiling, film boiling.

b. Nucleate boiling, single phase convection, partial film boiling, film boiling.

c. Single phase convection, partial film boilins, nucleate boilin3' film boiling.

d. Single phase convection, partial film boiling, film boilin3' nucleate boilin3*

QUESTION H.17 (1.00)

Which of the followins is an INCORRECT statement concerning heat oxchangers?

a. Heat transfer is by both the conductive and convective methods of heat transfer.

b. The heat transfer rate for a parallel flow heat exchanger is hi3her than that of a counter flow heat exchanger if the inlet temperatures are the same.

c. The heat transfer rate is directly proportional to the heat transfer coefficient associated with the material the tubes are made of.

d. Higher thermal stresses across the tubes will accompany a hiSher tube thickness.

QUESTION H.18 (1.00)

Which of the following conditions, by itself, will reduce the margin to DNB when operating at 5MW?

o. The moderator level increasins.

b. The loss of the reactor coolant pump.

c. Increasing the H2O flow through the D20/H2O heat exchanger.

d. Placing an experiment in the core.

(xxxxx CATEGORY H CONTINUED ON NEXT PAGE *****)

s H. REACTOR THEORY PAGE 8 QUESTION H.19 (1.00)

The mode of heat transfer across the fuel claddin3.i's

c. conduction.

b. convection.

c. black body radiation.

d. white body radiation.

QUESTION H.20 (1.00)

The heat transfer rate through an ale.inum slab is inversely proportional to

c. the temperature difference across the slab.

b. the thermal conductivity of aluminum.

c. the thickness of the slab.

d. the area of the slab.

(xxxxx END OF CATEGORY H xxxxx)

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 9 QUESTION I.01 (1.00) c What isotope is formed in the reactor's graphite region that is a potential radiation hazard?

GUESTION I.02 (1.00)

What is the required thickness of lead to reduce a 1 Mev gamma flux from 2 E3 Mev/(cm squared-sec) down to 1 Nev/(cm squared-sec)? Refer to the eqdation sheet for tenth and half thicknesses.

a. 3.45 inches.

b. 3.78 inches.

c. 4.11 inches.

d. 4.60 inches.

QUESTION I.03 (1.00)

Given 28 grams of Al-28 with an activity of 1.86 E23 dis / min and a decay constant of .309/ min, what would be the activity after 10 minutes?

o. 4.23 E22 dis / min

b. 8.46 E21 dis / min

c. 4.23 E21 dis / min

d. 8.46 E20 dis / min UUESTION I.04 (1.00)

An experienced operator is assigned to you. He is 28 years old. His NRC Form 4 indicates a 60 rem accumulation lifetime dose. His quarterly whole body dose is 1300 mr. Knowing this, would you allow him to work in a radiation area? Explain why or why not.

HUESTION I.05 (1.50)

List the normal permissible dose limts specified in 10 CFR 20 for whole body, hands,'and skin.

(xxxxx CATEGORY I CONTINUED ON NEXT PAGE ***xx)

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 10 QUESTION I.06 (1.00)

What is done with liquid wastes that cannot be si3nificantly reduced in activity by radioactive decay to allow discharge to the sewerage cystem?

00ESTION I.07 (1.50)

Describe the procedure for allowin3 a discharge of the waste storage tanks to the city sanitary sewerage system.

QUESTION I.08 ( .50)

Who maintains liquid waste discharge records?

OUESTION I.09 (1.50)

How is environmental monitoring performed around the GTRR?

UUESTION I.10 ( .50)

Where are the area survey records maintained?

QUESTION I.11 (1.00)

Match the following isotopes with the principal type of. radiation exposure hazard. The choices may be used more that once.

1. Ar-41 a. samma

2. tritium b. alpha

3. N-16 c. neutron

4. Co-60 d. beta

e. proton

(***** CATEGORY I CONTINUED ON NEXT PAGE *****)

e I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 11 QUESTION I.12 (1.00)

What is the activity of 10 grams of Sr-90' S i ven the decay constant for Sr-90 is 7 E-10/see?

o. 6.02 E23 dis /sec.

b. 6.69 E22 dis /sec.

c. 4.68 E13 dis /sec.

d. 3.79 E13 dis /sec.

QUESTION I.13 (1.00)

Co-58 has a radioactive half-life of 72 days and a biological total body half-life of 9.5 days. What is the total body effective half-life?

c. 0.1 days.

b. 4.75 days.

c. 7.6 days.

d. 8.4 days.

QUESTION I.14 (1.00)

Hw are samples placed in the vertical incore positions (V21-V28) without overexposing personnel?

UUESTION I.15 (1.00)

How are you supposed to determine if a person is authorized to perform radiation surveys if he/she is not from Health Physics?

UUESTION I.16 (1.00)

List the four classifications of liquid wastes.

(xxxxx CATEGORY I CONTINUED ON NEXT PAGE 1xxxx)

a I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 12 QUESTIL.v I.17 (1.00)

If a person requires prompt professional medical attention due to a hi3h level of skin contamination, he should be sent to

a. the GT infirmary.

b. Grady Hospital.

c. Georgia Baptist Hospital.

d. Emory.

QUESTION I.18 (1.00)

If you discover an uncontrolled spread of radioactive contamination, whom cre you required to notify?

UUESTION I.19 (1.00)

If you are in a 100 mrad / hour samma field for 45 minutes, what is your dose in MREM after 45 minutes?

a. 45

b. 75

c. 450

d. 750 QUESTION I.20 ( .50)

'The goal of ALARA can be achieved by allowing more personnel be exposed for shorter times than one person being exposed for a longer time provided the total time of exposure is the same. TRUE or FALSE?

(xxxxx END OF CATEGORY I *****)

e J. SPECIFIC OPERATING CHARACTERISTICS PAGE 13 GllESTION J.01 (1.00)

If a scram did not occur directly from the service. air pressure signal during a loss of air pressurer what would eventually shut down the reactor? Assume no operator action and no faulty instrument indication.

QUESTION J.02 (3.00)

Provide the trip setpoints for the following instruments for (a) Mode 1 cnd (b) Mode 2.

1. HiS h level flux.

2. Low primary coolant flow channel 1.

3. Primary coolant hi 3h temperature channel 2.

QUESTION J.03 (1 00)

What is the minimum D20 level in the reactor vessel allowing an operator to start MD-2A?

o. 42 inches.

b. 48 inches.

c. 52 inches.

d. 58 inches.

QUESTION J.04 ( .50)

The primary coolant purification pumps are normally operated with their primin3 valves opened. TRUE or FALSE?

UUESTION J.05 (1.00)

How is control power restored to MD-3 and MD-4 (reactor isolation valves) to allow openin3 them in order to refill the reflector when it is at dump level?

(***** CATEGORY J CONTINUED ON NEXT PAGE *****)

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 14 QUESTION J.06 (1.50)

What will happen to the followins systems / components on a loss of power?

o. Re301 sting rod.

b. Top reflector.

c. Containment ventilation.

OllESTION J.07 (2.00)

List five different conditions that will cause a delayed scram. .

QUESTION J.08 (3.00)

For each of the followin3 independent conditions, describe the response of the regulating rod. Include in your answer the reason for the stated response.

c. The reactor has been operatin3 in automatic control at 2 MW with equilibrium conditions established when a decrease in the H2O inlet temperature occurs for the D20/H2O heat exchanser,

b. The reactor is operating in automatic control set at 2 MW two hours after a cold startup.

c. The reactor is operatins in automatic control set at 2 MW when the instrument supplying the reference power to the automatic control system fails low.

QUESTION J.09 (1.00)

What automatic actions occur on ECCS initiation?

(xxxxx CATEGORY J CONTINUED ON NEXT PAGE xxxxx)

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 15 QUESTION J.10 (1.00)

Peak xenon followins a shutdown from 5 MW equilibrium operations adds cpproximately ______ negative reactivity.

c. 9%

b. 6%

c. 4%

d. 1%

(tuESTION J.11 (1.00)

The shim-safety blade calibration curves given as Figure J.11 shows the differential rod worth to be the highest at about

c. 5 degrees.

b. 15 degrees.

c. 30 degrees.

d. 55 degrees.

(!UESTION J.12 (1.00)

The reactor should NOT be started or left unattended when the blanket gas system level indicator is outside the

c. 0-30% limits.

b. 30-60% limits.

c. 60-90% limits,

d. 90-100% limits.

(xxxxx CATEGORY J CONTINUED ON NEXT PAGE xxxxx)

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 16 QUESTION J.13 (1.00)

What is the maximum allowable deviation between the highest and lowest chin blades during normal operations above 50 KH?

o. 2 degrees.

b. 5 degrees.

c. 7 degrees.

d. 10 degrees.

(IUESTION J.14 (1.00)

The minimum allowable reactor period durin3 a reactor startup is

o. 5 seconds.

b. 10 seconds.

c. 15 seconds.

d. 20 seconds.

QUESTION J.15 (1.00)

When placing the reactor in automatic controit the power deviation must be less than (select minimum value)

c. 1%.

b. 3%.

c. 5%.

d. 10%.

(***** END OF CATEGORY J *****)

K. FUEL HANDLING AND CORE PARAMETERS PAGE 17 QUESTION K.01 (1.50)

Name three ways that fresh fuel is controlled in order to prevent criticality.

QUESTION K.02 (1.00)

How is criticality prevented from occurin3 in the spent fuel pool?

QUESTION K.03 (1.00)

How is an open fuel position at the top of the reactor controlled to prevent personnel from inadvertantly beins over exposed by the radiation beam during refueling?

QUESTION K.04 (1.50)

Name three components that must be removed or disconnected in order to gain access and remove a fuel element.

QUESTION K.05 (1.00)

Why must the reactor be shutdown for at least 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months before a fuel olement can be removed?

OUESTION K.06 (1.50)

List three instruments that must be operable durin3 fuel handlins in the core.

l

(**xxx CATEGORY K CONTINUED ON NEXT PAGE xxxxx)

K. FUEL HANDLING AND CORE PARAMETERS PAGE 18 QUESTION K.07 (1.00)

If the signal from the neutron monitorin3 channel (s) increases by a factor of ______ durin3 fuel movement, the operation must be terminated.

(Select the minimum value for which it is applicable)

o. 2

b. 4

c. 5

d. 10 QUESTION K.08 (1.00)

If a fuel handlin3 Operation is secured due to a high neutron count rater who must authorize the operation to continue?

UUESTION K.09 (1.00)

What is the minimum number of shim-cafety blades that must be inserted to Gnsure reactor suberiticality?

HUESTION K.10 , (1.00)

The reactivity worth of the regulating rod is about

a. 0.01%.

b. 0.4%.

c. 2.3%.

d. 4.2%.

(xxxxx CATEGORY K CONTINUED ON NEXT PAGE xxxxx) i

K. FUEL HANDLING AND CORE PARAMETERS PAGE 19 QUESTION K.11 (1.00)

Followins a week of 5 MW power operations, a reactor scram occurs. What is the expected decay heat immediately followins the scram in percent of full power?

o. 8 to 9%

b. 5 to 6%

c. 3 to 4 %

d. 1 to 2%

GUESTION K.12 (1.00)

Which of the following correctly describes the two group flux shapes (fast and thermal)in the GTRR?

a. Fast and thermal flux is higher in the fuel than in the moderator.

b. Fast and thermal flux is lower in the fuel than in the moderator.

c. Fast flux is lower in the fuel than in the moderator and thermal flux is higher in the fuel than in the moderator.

d. Fast flux is higher in the fuel than in the moderator and thermal flux is lower in the fuel than in the moderator.

QUESTION K.13 (1.00)

What is the minimum number of fuel assemblies necessary to have a critical mass in the reactor core?

e. 11

b. 14

c. 16 i d. 19 i

l (xxxxx CATEGORY K CONTINUED ON NEXT PAGE **xxx)

L_

K. FUEL HANDLING AND CORE PARAMETERS PAGE 20 QUESTION K.14 (1.00)

Which of the following is NOT a major reactivity coefficient in the GTRR due to the high enrichment of the fuel?

o. Void coefficient.

b. Moderator temperature coefficient.

c. Doppler coefficient.

d. Power coefficient.

QUESTION K.15 ( .50)

The magnitude of the void coefficient will decrease for a given coderator channel if measured from the core center to the core edge.

TRUE or FALSE?

QUESTION K.16 (1.00)

The reactivity calibration of the re3ulatins rod is done by taking

e. doubling time data.

b. 1/M plot data.

c. shim blade motion data,

d. temperature change data.

QUESTION K.17 (1.00)

The standard fuel element is made up of

a. aluminum-uranium alloy plates cladded with an aluminum alloy.

b. aluminum-uranium alloy plates cladded with a circonium alloy.

c. =irconium-uranium alloy plates cladded with an aluminum alloy.

d. =irconium-uranium allo 9 plates cladded with a =irconium alloy.

(xxxxx CATEGORY K CONTINUED ON NEXT PAGE **xxx)

K. FUEL HANDLING AND CORE PARAMETERS PAGE 21 QilESTION K.18 (1.00)

A moderator temperature increase from 22C to 45C will add approximately

e. 0.5% positive reactivity.

b. 0.5% negative reactivity.

c. 1.5% positive reactivity.

d. 1 5% negative reactivity.

QUESTION K.19 (1.00)

What is the reactivity worth of equilibrium xenon and samarium?

o. 1.3%

b. 2.2%

c. 3.4%

d. 5.2%

o (***** END'0F CATEGORY K xxxxx)

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 22 GUESTION L.01 (1.00)

How is the entrance into the pipe tunnel below the. reactor controlled in crder to prevent over exposure to personnel?

OUESTION L.02 (1.00)

The process of determining an instruments accuracy by visually comparing the indication to other independent instrument channels measuring the e.ame parameter is defined in Tech Specs as a

e. Channel Calibration.

b. Channel Check.

c. Channel Functional Test.

d. Channel Source Check.

QUESTION L.03 (1.00)

' Reactor Shutdown' as defined in Tech Specs is

a. when all shim-safety blades are fully inserted.

b. when all shim-safety blades and the regulating rod is fully inserted.

c. when all shim-safety blades are fully inserted and the control rod power is off.

d. when all shim-safety blades are fully inserted and the required shutdown margin is satisfied.

GUESTION L.04 (1.50)

List the requirements to meet Containment Integrity.

QUESTION L.05 (2.00)

What are the Safety Limits when in (a) the forced convection Mode and (b) when in the natural convection Mode?

(*xxxx CATECORY L CONTINUED ON NEXT PAGE xxxxx)

~

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS - PAGE 23 QUESTION L.06 (1.50)

According to Tech Specs, the shutdown margin relative to the cold xenon free critical condition shall be at least (a) ___

delta k per k with the cost reactive shim-safety blade and the regulating rod fully withdrawn.

The reactor shall be subcritical by more than (b) ___ delta k per k during loading changes.

And the excess reactivity of the core shall be limited to (c) ___ delta k por k.

QUESTION L.07 (2.00)

List four different conditions that Tech Specs requires Containment Integrity to be in affect.

QUESTION L.08 (1.50) .

What are the Tech Spec sampling requirements for a release of liquid radioactive effluents?

UUESTION L.09 (1.00)

Which radiation monitors does Tech Specs require to be operable to perform a gaseous waste release?

UUESTION L.10 (1.00)

What is the basis for the Tech Spec limit for tritium released?

(xxxxx CATEGORY L CONTINUED ON NEXT PAGE xxxxx)

'L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 24 GUESTION L.11 (1.00)

To take the reactor criticale Tech Specs requires the primary coolant pH to be between

o. 3.5 and 7.5.

b. 4.0 and 7.0.

c. 4.5 and 7.5.

d. 5.5 and 8.5.

QUESTION L.12 (1.00)

The reactor _______ with the D20 Emergency Coolant System inoperable.

a. must be shutdown

b. can be operated up to a maximum of 1 kw

c. can be operated up to a maximum of 1 MW

d. can be operated at 5 MW for up to one hour GUESTION L.13 (1.00)

What is the minimum crew required whenever the reactor is not secured.

Include any eligibilty requirements.

QUESTION L.14 (1.00)

List two levels of approval required by Tech Specs to perform an experiment.

QUESTION L.15 (1.00)

List four of the five categories of experiments as grouped by the Ovality Assurance Program.

(xxxxx CATEGORY L CONTINUED ON NEXT PAGE xxxxx)

F l

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L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 25 QUESTION L.16 (1.00)

When conducting an inventory of Special Nuclear Materiale (a) what is beins inventoried and (b) how is it identified?

RUESTION L.17 ( .50)

What must the Shift Supervisor do to satisfactorily verify the status Cf electrical jumpers to meet the requirement of the Shift Supervisor Startup Approval Checksheet?

(xxxxx END OF CATEGORY L **xxx)

(xxxxxxxxxxxxx END OF EXAMINATION xx*xxxxxxxxxxxx) 4

H. REACTOR THEORY PAGE 26 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER H.01 (1.00) d REFERENCE MNS OP-MC-SPS-RT-NMF, p.8.

ANSWER H.02 (1.00) a REFERENCE NUS, NET, Vol. 3, 6.6-1.

ANSWER H.03 (1.00) b REFERENCE MNS OP-NC-SPS-RT-RKr p.12.

ANSWER H.04 (1.00) d REFERENCE MNS OP-MC-SPS-RT-RK, p.12.

ANSWER H.05 (1.00) a REFERENCE HDR, Reactor Theory, Sessions 41 and 42 ANSWER H.06 (1.00)

H. REACTOR THEORY PAGE 27 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS REFERENCE NUS, NET, Vol. 2, p. 11.3-1.

ANSWER H.07 (1.00) a REFERENCE Nuclear Reactor Analysis, Duderstadt & Hamilton, 1976r p.13.

ANSWER H.08 (1.00) b REFERENCE NUS, NET, Vol. 2, 12.2-2.

ANSWER H.09 (1.00) d REFERENCE NUS, NET, Vol 2r 16.1-3.

ANSWER H.10 (1.00) b REFERENCE NUS, NET, Vol 2, p. 16.5-1.

ANSWER H.11 (1.00) d 0=NV=(1.36 E8)(2.2 E5)=2.99 E13.

REFERENCE Nils , NET, Vol 2, 14.5-4.

H. REACTOR THEORY PAGE 28 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER H.12 (1.00) d (period = 1.443 x doublins time)

REFERENCE NCSUr Reactor Operator Trainin3r Exp. 3, p. 3 ANSWER H.13 (1.00) c REFERENCE Nuclear Rad. Detect., Pricer pp. 25-29.

ANSWER H.14 (1.00) b REFERENCE HNS Core Performancer pp.12-13.

ANSWER H.15 (1.00)

C p=F(To-Ti)Cp

=1800(125-114)(.162)=3207.6kw.

REFERENCE GRTTr OP 2015, p.1.

ANSWER H.16 (1.00)

B REFERENCE Nuclear Reactor Analysis, Duderstadt & Hamiltor, p.491.

l

H. REACTOR THEORY PAGE 29 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER H.17 (1.00) b REFERENCE General Physics, HTT&FF.

ANSWER H.18 (1.00) b REFERENCE GTRR, TS 2.1.1.

ANSWER H.19 (1.00) a REFERENCE General Physics, HTT&FF, p.99.

ANSWER H.20 (1.00) e REFERENCE General Physics, HTT&FF, p.107.

l l

1 l

l I

L l

l l

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O I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 30 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS i

ANSWER I.01 (1.00)

Argon 41.

REFERENCE GT SAR, p.44.

ANSWER I.02 (1.00) b.

3 tenth thicknesses will reduce it to 2, so then you need 1 half thickness to reduce it to 1.

3(1.15)-+ 1(0.33)=3.78 inches.

REFERENCE NUS, NET, VOL 2, Shielding.

ANSWER I.03 (1.00)

A=Aoe( ^t)

A=(1.86E23)e-(.309)(10)=8.46E21.

b.

REFERENCE NUS, NET, VOL 2, p.10.3-4.

ANSWER I.04 (1.00)

NoEO.53 He has exceeded 5(N-18) requirement.CO.53 5(28-18)=50 rem, he has 60.

REFERENCE 10 CFR 20.102

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 31 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER I.05 (1.50) 0 0.5 points each wb-1.25 ren/qtr hands-18.75 rem /qtr ckin-7.5 rem /qtt REFERENCE 10 CFR 20.101.

ANSWER I.06 (1.00)

It is solidified and handled as solid waste.

REFERENCE GT SAR p. 132.

1 ANSWER I.07 (1.50) 0 0.5 points each

1. Isolate tanks.

2. A3itate contents.

3. Verify activity is within limits by samplin3+

REFERENCE GT SAR, p.107.

ANSWER I.08 ( .50)

Health Physics.

REFERENCE GT SAR, p.107.

J i--..,

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 32 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS 1

ANSWER I.09 (1.50)

@ 0.5 points each

1. (50) film badges'outsite perimeter checked monthly.

2. (7) neutron plus beta samma detecting film badges check biweekly.

3. (2) fixed particulate air samplers.

REFERENCE GT SAR, p.109-110.

ANSWER I.10 ( .50)

Office of Radiological Safety.

REFERENCE GT SAR, p.109.

ANSWER I.11 (1.00) 0 0.25 points each.

1-a.

2-d.

3-a.

4-a.

REFERENCE Rad Health Handbook,USDHEW, Table VI.

ANSWER I.12 (1.00) c.

A=YN, Y= 7 E-10 N= mass / mass /GAW X Na Atoas/GAW N= 10/90 X 6.02 E23= 6.69 E22 A= (7 E-10)(6.69 E22)= 4.68 E13.

Io RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 33 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS REFERENCE NUS, NET, Vol 2, p.478.

ANSWER I.13 (1.00) d (9.5)(72)/(9.5+72)=8.4 REFERENCE CRC Rad. Nuclides, p.194.

ANSWER I.14 (1.00)

Via a fishing rod with a multi prong hook and mirrors.

REFERENCE GTRR, OP 3103, p.4.

ANSWER I.15 (1.00)

By verifying the person is on the Form RS-25, Self Monitoring Approval list ,

REFERENCE GTRR, HP Procedures, p.11.

't ANSWER I.16 (1.00) 0 0.25 points each

1. Clean waste.

2. Low level waste.

3. Suspect waste.

4. High level waste.

REFERENCE GTRR, HP Manual, p.14.

S

. - _ _ , - _ _ __-r ----- . . . - --_ _- _ . _- _., -----------r_m - --,

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 34 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER I.17 (1.00) b REFERENCE GTRR, HP Manual, p.22.

ANSWER I.18 (1.00) 0 0.333 Points each!

1. GT Police.

7. ED.

3. HP.

REFERENCE HP Manual, p.20.

ANSWER I.19 (1.00) b o

GF=1 for samma 100(45/60)(1)=75 REFERENCE 10 CFR 20.

ANSWER I.20 ( .50)

FALSE- (ALARA is based on a total annual reduction)

REFERENCE 10 CFR 50, App. I.

i

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 35 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER J.01 (1.00)

Reflector drain valves would open[0.53 reactor would shutdown on loss of reflector reactivity or on a loss of overflow trip E0.53 (either way is accepted )

REFERENCE GT E0P 5024, p.2.

ANSWER J.02 (3.00)

For 0.5 points each

1. (a) 125% with 1000kw being 100% meter.

(b) 110% with 5000kw being 100% meter.

2. (a) 1000 spm (or 1625 spm).

(b) 1625 spm.

3. (a) 123F.

( b ) -i z ,r .- /37 p: falh Crecld v4.<_ u 3d hc !

W u%.

REFERENCE GTRR, OP 7250, pp.1-2.

ANSWER J.03 (1.00) b REFERENCE GTRR, OP 2150.

ANSWER J.04 ( .50)

FALSE.

REFERENCE GTRR, OP 2050.

A v ,__ ,, , _ _ . _ _ _ , , . , . . _ . . ,

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 36 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER J.05 (1.00)

Push ECCS OVERRIDE button.

REFERENCE GTRR, OP 2050, p.2.

ANSWER J.06 (1.50) 0 0.5 points each.

a. Reg rod becomes inoperable at positio:- when LOP occured.

b. Drains.

c. Is secured and containment building isolates.

REFERENCE GT SAR, p.137.

ANSWER J.07 (2.00)

Any 5 0 0.4 points each.

1. Low H2O flow.

2. Control air low pressure.

3. Low shield. coolant flow.

4. High shield coolant temp.

5. High bismuth coolant temp.

6. Low bismuth coolant flow.

REFERENCE GT SAR, p.72.

ANSWER J.08 (3.00)

o. Reg rod will move in [0.53 to establish reactor power at setpoint.

The increased coolin3 caused a power increase from the MTC [0.53

b. Reg rod will move out CO.53 to compensate for xenon buildup [0.53.

c. Reg rod will not move E0.53 because the power control system automatically switched to manual on the >10% setpoint to reactor power deviation E0.53.

e on J. SPECIFIC OPERATING CHARACTERISTICS PAGE 37 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS REFERENCE CTRR SAR, p.69.

ANSWER J.09 (1.00) 9 0.5 points each!

1. Reactor isolation valves close.

7. Spray valves open.

REFERENCE GTRRr OP 2160, p.2.

ANSWER J.10 (1.00)

D REFERENCE GTRR SARr p.92.

ANSWER J.11 (1.00) b REFERENCE GTRR SAR, p.53.

ANSWER J.12 (1.00) b REFERENCE GTRR, OP 8350, p.2.

ANSWER J.13 (1.00) b REFERENCE GTRR OP2000, p.1.

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J. SPECIFIC OPERATING CHARACTERISTICS PAGE 38 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER J.14 (1.00) d REFERENCE GTRR OP~2000, p.1.

ANSWER J.15 (1.00) b

-REFERENCE

GTRR, OP 2000, p.2.

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 39 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER K.01 (1.50)

Any 3 9 0.5 points each.

1. Locked access.

7. Special storage boxes.

3. Criticality monitors.

4. Limit number of elements is same area.

REFERENCE GT SAR, p.130.

ANSWER K.02 (1.00)

Minimum distance between fuel elements.

REFERENCE GT SAR, p.130.

ANSWER K.03 (1.00)

By use of barricadesCO.53 and stationed personne1CO.5].

REFERENCE GT SAR , p.129.

ANSWER K.04 (1.50) 0 0.5 points each-any 3.

1. Lead cover removed.

?. Upper top-shield port plus removed.

3. Thermocouples disconnected.

4. Top reflector drained.

REFERENCE GT SAR, p.128. .

e K. FUEL HANDLING AND CORE PARAMETERS PAGE 40 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER K.05 (1.00)

Allows decay time to limit temperature (below 450 C) before transferring to dry coffin.

ANSWER K.06 (1.50) 0 0.5 points each.

(g- t % Mu Au Sc W

?

1. Startup channel. pg/ml ggQ

2. Picoa.mmeter channel 1.

d "" * * *.b o /.h. fS.(gS

3. Picoammeter channel 2.

REFERENCE I6) d GTRR OP 1502, p.2. y op ffco p, f ANSWER K.07 (1.00) e REFERENCE GTRR, OP 1502, p.2.

ANSWER K.08 (1.00)

Reactor Supervisor.

REFERENCE GTRR, OP 1502, P.2.

ANSWER K.09 (1.00) 2 REFERENCE GT SAR, p.137.

K. FUEL HANDLING AND CORE PARAMETERS PAGE 41 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER K.10 (1.00) b REFERENCE GT SAR, p.52.

ANSWER K.11 (1.00) b REFERENCE GTRR SAR, p.80.

ANSWER K.12 (1.00) d REFERENCE GTRR SAR, p.95.

ANSWER K.13 (1.00) a REFERENCE GTRR SAR, p.93.

ANSWER K.14 (1.00) c REFERENCE i GTRR SAR, p.10.

l ANSWER K.15 ( .50) i i TRUE.

l m - - - . . _ _ - , , , - - - . . ,_y- _ - . _ . _ - ._ .

K. FUEL HANDLING AND CORE PARAMETERS PAGE 42 ANSWERS ---GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS REFERENCE GTRR SAR, p.98.

ANSWER K.16 (1.00)

G REFERENCE GTRR, OP 7246, p.1.

ANSWER K.17 (1.00)

D REFERENCE GTRR SAR, p.48.

ANSWER K.18 (1.00) b REFERENCE GTRR SAR, p.102.

ANSWER K.19 (1.00) c REFERENCE GTRR SAR, p.102.

o

o.* . \

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 43 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER L.01 (1.00) 0 0.25 points each.

1. Locked access door.

2. HP approval for entering.

3. HP must monitor area.

4. Minimum time after shutdown required prior to entering.

REFERENCE GT SAR, p.56.

ANSWER L.02 (1.00) b REFERENCE GTRR, TSr 1.5.

ANSWER L.03 (1.00)

C REFERENCE GTRR, TS, 1.9.

ANSHER L.04 (1.50) 0 0.5 points.

1. 1 door on each personnel airlock is closed and sealed.

2. The truck door is closed and sealed.

3. Containment capable of being isolated automatically or inoperable paths are isolated.

REFERENCE GTRR, TS, 1.26.

o.* ,

e L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 44 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER L.05 (2.00) 0 0.5 points per item Forced convection:

1. Power within Fis II-1.

2. Reactor coolant inlet temperature < or = to 123F.

3. Moderator level within 12 inches of overflow.

Natural convection:

1. Power < or = to 2kw.

REFERENCE GTRR TS, 2.2.2, 2.2.2.

ANSWER L.06 (1.50) 0 0.5 points each.

(a) 0.01.

(b) 0.0275.

(c) 11.9 %.

REFERENCE GTRR TSr 3.1.

ANSWER L.07 (2.00) 0 0.5 points each.

1. Reactor operatins.

2. Whenever an operation is bein3 Performed that could change core reactivity.

3. During rovement of irradiated fuel.

4. Reactor shutdown from power level operation ebove 1 MW, for less than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

REFERENCE GTRR TSr 3.3.

F.

o* .

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 45 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TON ROGERS ANSWER L.08 (1.50)

1. 2 independent samplesEO.53.

2. 1 prior and 1 during release CO.53.

3. 1 must be done from the dischar3e line during the release E 0.53.

REFERENCE GTRR TS , 3.5.

ANSWER L.09 (1.00)

Gross radioactivity monitor CO.53 charcoal filter cartridge and particulate monitor E0.53.

REFERENCE GTRR TS, 3.5.b.

ANSWER L.10 (1.00)

To be within the 10 CFR 20 limit.

REFERENCE GTRR TS 3.5.

ANSWER L.11 (1.00)

C REFERENCE GTRR TS 3.6.

ANSWER L.12 (1.00) c REFERENCE GTRR TS, 3.7.

o...

L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 46 ANSWERS -- GEORGIA INSTITUTE OF TECH.-85/07/10-TOM ROGERS ANSWER L.13 (1.00) 2 persons E0.5], at least 1 SRO licensed CO.5].

ANSWER L.14 (1.00)

Nuclear Safeguards Committee E0.5].

Licensed SRO in charge of reactor operations E 0 '. 5 ] .

REFERENCE GTRR TS, 6.3.a.

ANSWER L.15 (1.00)

Any 4 0 0.25 points each.

1. Rabbit.

2. Guppy.

3. External.

4. Internal.

5. General.

REFERENCE' GTRR, OP 3102.

ANSWER L.16 (1.00)

(a) U-235 CO.5].

(b) By serial number E0.5].

REFERENCE GTRR, OP 3600, p.1.

ANSWER L.17 ( .50)

Verify all jumpers are on the jumper board.

REFERENCE GTRR, OP 2004, p.1.

.

ML20133N627

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