IR 05000166/1987004
| ML20236M561 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 10/20/1987 |
| From: | Keller R, Norris B, Turner R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20236M541 | List: |
| References | |
| 50-166-87-04OL, 50-166-87-4OL, NUDOCS 8711130181 | |
| Download: ML20236M561 (89) | |
Text
{{#Wiki_filter:. - - - _ _ _ . _ _ _ _ _ -
.* ,
* i U.S. NUCLEAR REGULATORY COMMISSION REGION I
'
OPERATOR LICENSING EXAMINATION REPORT i i EXAMINATION REPORT N0.: 87-04. (OL) FACILITY DOCKET NO.: 50-166
!
FACILITY LICENSE N R-70 I LICENSEE: Maryland University Training Reactor Department of Chemical and Nuclear Engineering 1 University of Maryland ' College Park, Maryland 20742 I FACILITY: University of Maryland j-EXAMINATION DATES: September 8-11, 1987 CHIEF EXAMINER l% Robert L. Turner, Operations Engineer to //9 [M Dath REVIEWED BY: //MM ///e/ KP Bar'rg. Nor'ris, Senior Operations Date ngineer APPROVED BY: ld/~Lo /f17 kobert M. Keller, Chief, PWR Section
-
Date Operations Branch SUMMARY: Written examinations and operating tests were administered to four senior reactor operator (SRO) and two reactor operator (RO) candidates. All passed and received their license The facility reviewed the examinations on September 8, 1987 immediately after the written examinations were complete The facility comments are Attachment 3 and the NRC Resolution of those comments is documented in Attachment !
U Sb?lSEff8f, 1
'
PDh
.
p._h-s_.-_m_m-- _ _ _ _ _ _ _
. . *
l
!
!
6~ > i DETAILS TYPE OF EXAMINATIONS: Initial-EXAMINATION RESULTS: l RO l SRO l l Pass / Fail l Pass / Fail l l 1 I I I I . I I l Written l- 2/0 l 4/0 l l l l l l .I I I i l0perating l 2/0 1 .4/0 l
'
I I I I l l l l l0verall l 2/0 l 4/0 l l l l l l l l I CHIEF EXAMINER AT SITE: R. L. Turner, USNRC I OTHER EXAMINERS: D. J. Lange, USNRC The following is a summary of generic strengths and noted on the operating test This information is being provided to aid the licensee in upgrad-ing license and requalification training programs. No licensee response l is require STRENGTHS All of the candidates were proficient in taking the reactor to l power within the Operating Procedure envelope . Personnel Present at Exit Interviu: NRC Personnel David J. Lange, Senior Operations Engineer Robert L. Turner, Operations Engineer
.1 a
i
_ _ _ _ __ _ . --
. ,
p r L .- i
'
'
'3-
'
.
.-Facility Personnel Dr.'Marvin'Roush, Chairman - Department of Chemical & Nuclear
, Engineerin LDrc: Frank Munno, . Chairman ~ _ Nuclear Engineering Program ; Dr. David'Ebert, Reactor Director '
.i Dr.-l Ralph Belcher, Associate Reactor Director a Summary of"NRC comments made at' exit interview: ,
j The.f'cility a raised a question;as to the impact of the. equipment failure during the-first examination. The NRC responded that copies of the strip chart generated during that failure would ^ provide the additional informa-
'
tion.on which to. base a judgement. The facility agreed to supply sam l
.The NRC~ thanked the facility personnel for the cooperation extended throughout the examination proces i
' Summary of; facility comments and commitments made at' exit interview:
~
. ' . . -
In response _to-a' concern on radiation exposure control, the facility ; explained that-handling of high level radiation samples was limited to j their- experienced. people. and their record was good as' average -exposure .i for their people working at the reactor was less than 10 mrem / year on the averag ) Attachments-
' Written Examination and Answer Key (RO) l . Written-Examination and Answer Key'(SRO) i _ Facility Comments on Written Examinations after Facility Review l NRC Response to Facility Comments '
l
l
!
>
l ' l
.. .
I
, .. _ - -. . ..
. _ _ _ _
...
A774ChtrN7~_f i
~4 : . .4 U.' NUCLEAR REGULATORY COMMISSION . ,
REACTOR OPERATOR LICENSE EXAMINATION j J FACILITY: ' UNIVERSITY OF MARYLAND - l
..
I REACTOR TYPE: TRIGA l i DATE ADMINISTERED: _@7f99f@@________________ _ ) EXAMINER: _ TURNER 1 _R.______________ i CANDIDATE: _________________________ INSIBUCIlgNS_Ig_C86 Dip 61El-Una ' separate paper for the answer Write answers on one side onl ! Staplefquestion sheet on top of the answer sheet Points for each ! question are indicated in parentheses after the questio The passing grade requires at least 70%'in each categor Examinati on papers will
'be. picked up six (6) hours after the examination start % OF .. CATEGORY '% OF CANDIDATE'S . CATEGORY
__MBLyE_ _10166 ___SCOBE___ _y86UE__ ______________C81EGOBy_____________ _ldr 09__ _la,. I4 9 W ts? ,___________
,
________ PRINCIPLES OF.. REACTOR OPERATION l 4 . 4 !i F
._ _1 _4 _ _5 _0 _ _ _ 4_. 5_C
_ - ________ FEATURES OF FACILITY DESIGN 3 __________
.ild:E9-_ _1$1E9~,___ _______ .________ GENERAL' OPERATING j CHARACTERISTICS l l% o otid 12 37paM N .i M (d ._Js_99__ _13299 ___________ ________ INSTRUMENTS AND CONTROLS i i s. cod / 3 . V 0 2/
_1S29?__ 213199 ________ SAFETY AND EMERGENCY SYSTEMS
:4. G M___________ s 13 99__ _15299 ___________ ________ STANDARD AND EMERGENCY OPERATING PROCEDURES 14.Th
_19299__ __M r@@ __________ ________ RADIATION CONTROL AND SAFETY f J7. o o#
.imE299__ \ 00 00g ___________ ________ Totals Final Grade
;
.All work done on this examination is my ow I have neither given
.nor received ai i
___________________________________ , Candidate's Signature y l A f h & &$** W5 f Mc yat
%7%
C 3 + W .& M A. so-ac g7_ay '
'
_ __ 9"$7 \
-
V * ,:E ..- _. ,'Qf
._ ,
Wm 4w,
'
Ni;v0lL
' ' i .. , . ,
NRC 8ULES,AND1 GUIDELINES FOR LICENSE. EXAMINATIONS ! ; Dubing'theladministration'of<this examination'..the'following' rules applyh
'
i
'
1..' Cheating 1on1the examinat, ion"means an automatic' denial'of your' application:
-
E E and :could result in more severe penaltie ..<Restroom1t' rips'areEto be limited a'nd onlyEone candidate at a time'may-l eave. - You;mustlavoid'all. contacts wi,thianyone outside.the examination j
'roomito avoid'even the appearance or possibility of cheatin :;
3F ~
{
'
'3.?-Use black ink oridark pencil ggly- to f acilitate_ legible reproductions.' !
:\r 4. .' Print your name1in ' the bl ank providedLon the cover. sheet of the :
ex ami nat i on .
' . Fill in the date on the cover sh'eet ~ of the examination (if necessary).
.. Use only the paper.provided for answer . i
.l 7' . ' Print your name in the upper right-hand. corner of the first page ofeack z
'f c section of :thesanswer shee Consecutively number each answer sheet, write "End of Category __"Las appropriate,. : start each : category on .a gew page, write ggly gn goe side ~
,
Lof Lt he paper,,.and write."Last Page" on the'last answor shee l
..
9.- : Number-- each answer as to'categoryfand number, for example, 1.4, U
'
710.fSkip:at least.thgee;;1ines'between-each answe . Separateansher.sheetsfrompad and place finished answer sheets face
:down on your' desk or. tabl . Use abbreviations only if they are commonly used in facility litetatute, y
13. The point value forfeach question is indicated in parentheses after'the-question.and can be used as'a guide for the depth.of answer require ' 14. Show~all calculations, methods, or assumptions used to.obtain an answer to mathematical problems whether indicated'in the question or no . Partial credit may be give Therefore, AMSWER ALL PARTS OF THE
' QUESTION AND DO NOT LEAVE ANY ANSWER BLAN > . If_ parts of the examination are not clear as to intent, ask questions of the examinet onl '17.;You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examinatio This must be done after the examination has been complete J: ,
.t ;i ?- _ __ _____._____________U
'
%0
'
' '
'N & w <t . , , , .
ym +
'^ Q . . ,
,
"
{ '[: e ,; 1 i 'i ) .'Q i S.(
l j
.
, g. , >j
<
i i
' ' {.
an: ,p , ,.
' '
,
, ,
;
' '
,
SJ < N , ,
,
,
,
! M18M.Whengyou complete your? examination {Eyou.shall .m , .
.
-
.
--
.'l *., h, .,e .g ~
fi ,
,
' 4 A.ssemb1 e your Lex ami nati o' n : as - f ol 1 ows:
.
,
--
i
' 4 s , . ...
..
,. . . .
j i; ( 1 ) ExamL_questionsLonito '
: ' .
(2) Exam' aids - figures;itables,.et LR;:giv ,
. .
'
,
.'(3) .
:
Answer;pages including'f,igures'which are part of the~ answe b.: , ;Turhil'n .' your'i copy Tof .the exa' m i nation and all pages used to answer
,
the examination questions.
, n,< . Turn '. i n';- al l L scr ap paper and the balance of the paper-that'you-did
< inot:iuse : f or, answeri ng ' the. questi ons.
(l
.
p,
,.
..
.
,
. ., ..
. d b ' Leave. the examinat' ion area, ' as .daf ined by7the examine If after
'
leaving, you arrt'found i n..thi s area whi1 e. the ex aminati on i s sti11
;in progress,'y'our... license may..be denied or revoke . - % . ; j 'l -
J
,
f ns . r.
. 6
.} ' lf
>: l .
. <
!'
3 ,*
' , ' . - i e,;?
I! I
'
I
,
:I, 4
,, w:
'$,,' ,
- ,)
_ - - - - 7 ') ,
_ _ - _ - _ _ _ I f
-
f
.-8___EBINCJELES_gE_SE9CIg6_ggEB9IlgN PAGE 2 .
n. p. 9T 7" I [ , t LA
' QUESTION A.01 ( 2. CO),
Ncme four (4) of the variables that will cause the critical rod position j for the reactor to change from startup to startu l QUESTION A.02 (3.00) i How much reactivity has been added to a subtritical reactor if the count rate has increased from 100 cps to 150 cps and Keff was ini ti all y 0.95 ? Show All Work! j
. QUESTION A.03 (2.00)
i c) Assuming the reactor is at 125 watts and on a stable sustained period of 50 seconds, how long will it take to reach 250 KW? j Show your wor j
.
b) Assuming the reactor is at 125 watts and is placed on a 50 sec period, explain how the reactor will respond if no further operator actions are taken? l l QUESTION A.04 (2.00) After the reactor is critical on startup what affect will removal of the startup neutron s7urce have on: Detector indication Core reactivity j j j QUESTION A 05
) (1.50)
What affect, if any, will starting the primary coolant put . have 3 if the reactor is operating at 250 KW7 Explai l l QUESTION A.06 -(1.00) If 10,000 neutrons both prompt and delayed are emitted in one l gsneration and 70 of them are delayed what is the value of beta? l (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
- - _ = _ _ _ l _- _ - _ _ _ _ _ _ _ _ _ - , /l[) ' s' , . . j ' . , p;f.- ,
i , s ,
,.- r .
* '
y @ , h, , * '
w
, ,
j;91_!dIhi91PLE@298 8g@gIQ8 9EEB81]QN _ _ PAGE' '. 3
' ..
i fj , . ,: :
, , .
, . -
, , -QUESTION fA.07; ..( 2. 00 ) s Q:. ' ,..
'
W ? Gi;ve_ f our.' possi 61 e .f ates t for neuteons"prcduced'byEfissionLinside'of.th , t
. . '
., . . i
~
-
.j 2MUT ?- .j
,
,
,
,
. . ,;
'.]
r;. LQUESTION- A.08 J( 1. 00 ) : 4 . LWhy,:mightfit'be necessary to.make. fine adjustments to'the regulating
~
.
t
. 7
. red;following: a' decrease.in' power? -
- ( 1. 00) .
. ,
a
-!
.!
..
g,
. R.~-
.j no
.!~~
,
.i
:. y l
..
..j 9:
:1
:]
.1
!
'
,
, .):
.
r
'l
J
l i i
'
i (*****-END OF CATEGORY A *****) i
!
=L_-__ -_._.:_--__-_._. .- _ .b
, . . _ _ __ _ _ - _ _ _ _
L
, .. .
o
- e...
'i
}B:__EE91UBE@_gE_E9CJ6]Iy_DE@]@N PAGE ' 4- i
< QUEST 10N' B.0 '( 2. 0 0,) '
' Fill in the blanks <with the appropriate value:
La) LThe reactor shall.not be operated'unless the shutdown margin provided by the. control' rods, under the.most conservative con-
, ditions,.is greater than $____ b) The' excess reactivity. relative to the cold critical conditions, with' -.or without experiments in pl ace, shall not be greater than $____ :c)1The reactor shall not be operated unless each non-secured experiment hast a. reactivity value of'less'than'$____ d) TheJscram' time measured from the time a rod starts in motion to the time the' rod reaches a. f ully inserted position shall not exceed _____ seconds f or .the sl owest scramable ro ! ! QUESTION 'B.02 (2.00) -State how;the core diffuser system accomplishes its purpos L . QUESTION B.03 (2.00) I q What material is used and where is-it placed to provide enhanced neutron R reflection axially .f or the MUTR core? ' " QUESTION 'B.04- (3.00) 'a) :What are two design f eatures of the reactor tank cooling' piping that normally would li mi t the reduction in reactor tank level to 20 inches or less in the event there were a severe leak in the inlet or outlet piping?. (2.00) 'tt)- .What~would be the minimum thickness of water shielding above the )
reactor' core even after a cooling piping failure? (1.00)
' QUESTION 18.05 (3.00) l
!
g ' Sketch a simple schematic of the Reactor Coolant and Purification System i Primary loop. Show the fi ve maj or ' components, the five major valves, and the'five reactor console instruments associated with this syste ]
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
_ _ _ _ _ _ _ _ - _ - _
__ _ _ _ _
,
l e i
, .i B r_ ,, _EE @IQSE S_ _O E _E@g it= lIY _D E S IG N PAGE 5 ,
l i
,
i'
-. ..e
!
..
' QUESTION B.06 ( 2. 50,)
On the attached Figure 4.1.of the reactor cor e, show current positions of control rods, nuclear instrumentation detectors, source location'and the rabbit hol !
,
h
!
(***** END OF CATEGORY B *****)
!
I u
i
.
l
!
l l
<
l I O _ _ - - _ _ _ - - - _ - _ _ - . _ . _ _ - _ _ _ _ .--__-_-__-______-__-- - -
.
_ _ _
.
.
.
- .
_
% ' .
E . C ._ R U R O O S T C P E U T L E - T N D F B E O E E R U M R R L A T O T E E S L L H O T M E I T e R H I A L T P D D E E d r A B - B U O R A u F C G R P
][O G . h [s] n o
i t a
'/ r if u g
4 tl! i v f n o c _ e r - o
f
-
_ E c
. M B R - : U U T L T U O - - M C . .
H G 1 L U A - O 4 M . f IiI R e R - _ H r E u H T g T . i -
, l i F -
_ 7 - _
'/ _
<
- .
_ _ _ _ _
.
_
.
_ YN _ ll 1 ll
._ .
-_
.
_ _
. _ .
-
.
' " '
, . .i N% . "
. .. , . .
. .
-
"Ci__9ENE8@6_OEEB@l1Ng_CH86@CIEBl@IlG@ PAGEL 6-
" '
.
t or~
:
fN)Oilf it . ., m . . . .
. QUESTION;'C.~01 (2.50) , ; ? After;three"davs of continuousfoperationfat:200'KW,.the-reactor is1 shutdown: Ufor minor maintenance.- 'I t' i s. restarted 8-hours 11ate '(assume constant pool,. temperature) ,
a)' How;will'.the critical.~ rod' position on. restart? compare'to the-
'
critical: rod = position at.the: time'of1the. previous startup?: Give the: reasonRfor/changesfin the critical rod. position ! 26) 1Durin.g.the first:24' hours after startup,-describe the control' rod movements.that-would.be necessar to' raise.the power f rom just cri ticall uto:200:KWsEand maintain the power-constant after reaching 200.KW , Explain what~causes thelneed - for changes}in rod in/out motio 'N a
' :-QUESTION- C.02 (2.00)
Describelthe radialfand axial position"in the core where a one inch movement
'of a: control. rod.tip would have the maximum reactivity effect. Explain y your: answe QUESTION C.03 (2.00)
What are the reactivity values of the following: Ja)'MUTR core excess.re^ activity? b) Shim. Rods? c) Regulating Rod? d )- Shutdown Margin with highest Worth ~ Rod Withdrawn? QUESTION C.04 (1.00)
.During ' startup when the control rods are being withdrawn, the l' ' period meter indicates a positive period; when rods are stationary an infinite period is observed. What is the status of the reactor?
l
.
s (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
-
I I' L E_ -_-_ _1- 1_ ---_ - - _ _ _ . j
- ..
'
I 3; ,
'
'"
. HM fly. .; F
'
w-t .. .
,
'
j: ggg_iQENg8@g_DEEQ@l[NQ,qH@R@gIERISTlqS 'PAGE' 7.'
, -e
'
. 1
- . .
QUESTION: C.05i ( 1. 00), ' Dsscribeithe process / mechanism that pr.oduces flow throughzthe core during. reactor. operatio ,
' QUESTION C.06~ (2.00) '
If the reactor: was ' en1 automatic control = at' f ull power and it he 7through beamLtube began to be flooded, which direction would the-regulating' rod' move andlwhy?' QUESTION: C107 - ( 1. 00 ) . LFor, Reactor Pool Water Conductivity:
,
~
-a) why.is there a conductivity' limit?'
.b);how is the appropriate con'uctivit'y d maintained?
!
QUESTION C.08 -(3.00) Assume the plant was initially at 100% power, with al-1 rods in manual control, .and' cooling to the primary coolant heat exchangers is lost. If no
, operator' action is,taken:.
a) what'two major. plant parameters would change?
' b )- how will the two parameters change?
c) what alarms, if any , will be actuated? d) Will, or will not, a scram be actuated within an eight hour period? 1' It o
(***** END OF CATEGORY C *****) ,.
_ . _ - _ . _ - . _ - - _ _ _ . . - _ . . - _ . _ _ - - -
_ , .
-
. ,l; *
.,_) 4 .,, b' ' ' '
'
p 0:q NE
'
~. , '
'
r - _ :y ... a
. .
_[. M< iDi_i195IBUMgNI@_AND_QONI696@l - PAGE' 8 a '
<
' '
*
} g, g g,
.. g'jg,,
.
.
l. . ,
'
<
,
,
vf' [ . . . . . L ; QUESTION D.01 - ( 1. 50,), <
>TRUE'orJFALSE -
'a) -
The linear: Power' Channel provides a. control signal 1to the servo-controller for.automaticrcontrol of the regulating ro b). 'MoreLthan one control ~ rod,can~be' withdrawn at'the same time.. .
~c)? 'The regulating rodfautomatically inserts onia scramLsigna TOUESTION D.02' (2.50) .
A control rod' drive. assembly,has five switches. . What-is the' purpose'. '] n of s each: switch?. l
;!
QU'STION E D.03 -(3.00) a) How are water mass;and delta temperature measured when in7the process of -conducting' a -heat balance on: the MUTR? b)iAt what power. level'is a heat balance normally conducted? '
' ' c)"How 'is the indicated power level adjusted to agree wi.th the measured and calculated heat balance? : QUESTION D.04 (1.50)
a) : What will -happen to the indication of fuel temperature if the
' thermocouple develops an open circuit?
~
'b) What will happen to the ind'ication of fuel temperature if the
= thermocouple develops a short circuit?
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
I i hamm__.m..____.-.______-t __._i _
. -. _ _ _ _
l
.
>, 9 __JNgIBUMENIg_9NQ_CgNI69L@ PAGE 9
, ,
i
,
MASTER QUESTION .D.05 (1.50), If a shim rod had become disengaged from the, drive and was at the full in position and the drive was still full up , , vdt i c h shim rod indicating lights would be on and which would be off? QUESTION D.06 (1.00).
Explain how the' pool temperature is controlled during plant operations at 250 K ! OUESTION D.07 (2.00)
'
What instrumentation is provided at the MUTR to assure continuous indication of reactor power level f rom countrate level to full power? QUESTION D.08 -(1.00) What is the operating principle of the pool level monitor probe and what triggers the alarm? i I l (***** END OF CATEGORY D *****) L_ _
_ _ - _ -
* ,- ; 3)\ ,
_ i 4 L
.' ,.
1 01 ', - . .> "
.
.
+
l Ei;,_g8EgIy_8ND_EMgB@ENCyl@ysIgME L ,PAGE -10
, ,
.
.
.M
:
QUESTION'lE.017 ,
. ( 3. 5 0), .
List thel scram (s) which are: initiated by THE REACTOR . SAFETY CHANNELS. Lf ,'. LInclude'the number of channel (s) ' required E and the scram setpoint (s) . "
,
,
" QUESTION /E.02f (1.00)
y WhatJis the main. purpose of the control rod drop test?
. . l , ,0UESTIONj E.03' -( 3. 00 )
For eachi. of ithe f ollowing - interlocks indicate what conditions
~ -
prod'ucef the;' interlock and what action is prevented?' j a) Source Level-b): Beam Plug: Position
.c)' Control Rod: -QUESTION' E.04 (2.00)
Immediately,following a scram, how do you, as an operator, scheckithat the control rods have~ dropped fully into the core, t
< ' QUESTION E.05 (1.00) <
h k 6-i [ What built-in feature of the TRIGA control rod drive-system stops the rod at the desired position when the rod is withdrawn or inserted to a new position in the core? '{ I
<
!
- Q U E S T I O N' . E.06 (1.00) 4 What prevents exhausting radioactive gases from the reactor area through-the personnel entrance !
i (***** CATEGORY E CONTINUED ON NEXT PAGE *****) I
..
.- . . - -
,
e E:__ggggIy_2ND_gdggggNCy_gy@Igdg PAGE 11
.
..
L.i . , . * QUESTION E.07 (2.50).
What is the basis for the following conditions: a) Each non-secured experiment shall have a worth less than one dolla b) Explosive materials, such as gunpowder, etc. in quantities greater than 25 milligrams shall not be irradiated in the reactor or ex p er i raen t a l facilitie c) Experiments containing material corrosive to reactor components, compounds highly reactive with water, potentially explosive materials, and liquid fissionable materials shall be doubly encapsulate ~
>
>
I1
!:
l l l i
(***** END OF CATEGORY E *****)
_--__
. _ _ _ _ _ _ _ _ _ .
;
I
. >
!
.E.__gl@NQ@@Q_@NQ_EME5@ENCX_OEEQ@I[N@_PRQCEQURE@
_ PAGE 12 y pa - i ~: i + ? tiL W ;, m,,,1 i QUESTION F.01 (2.50). ( c) List four of the six categories of " Reportable Occurences" that are ! reportable per Technical Specification requirements, b) Is a reportable occurence report required when the reactor is shutdown? l i l QUESTION F.02 (3.00) i l' Assume a fuel bundle is to be moved from the core to a storage area:
,
a) what are the two purposes for the monitoring of the console instruments by the control room operator? i b) how does the bridge operator assure himself that the fuel handling ; tool is properly. latched before he moves the fuel bundle? i c) What items are recorded in the Control Room Log Book after the fuel , move is complete? !
- QUESTION F.03 (3.00) '
The following alarms are received simultaneously; water temperature high, exhaust radiation monitor high, water level lo c) Which one should be investigated first? Justify your answe b) What actions, if any, should be taken to control the situation L and determine the problem? l QUESTION F.04 (2.50)
During a standard startup: c) In what incremer ts are shim rods I and II pulled and what is the target position prior to withdrawal of the regulating rod? b) In what increments is the regulating rod withdrawn and what is the main concern at this point? c) When is it appropriate to remove the source from the core? ' l
'
l l I I l (***** CATEGORY F CONTINUED ON NEXT PAGE *****) ____
- - - .
l- i i f i - I F_z__@I@@Q@@Q,@NQ_EUE6@ENCY_Q@E8@TlNQ_PRQQEQURE@ PAGE 13 4' QUESTION- F.05 ( 1. 50). . vou are operating the reactor when an experimenter notifies you of.a large fire in the building. What immediate actions ] do you take? (assume SRO on site) - QUESTION F.06 (1.50) The reactor scrams, what are your next two immediate actions?
(***** END OF CATEGORY F *****)
_ _ _ _ _ _ _ _ _ _ _ _ J
_ - .-. _ -- _
- ._ _
.- . _- - - _ _ - .
',
'
py > >
<
q t' * t ! Y RADIATION' CONTROL;6ND SQF_gT1-
'
L PAGE' 14 7 .
]
!
.!
QUESTION- G.01 ( 3. 0 0,) - . ; . 'I
.
,
s i~:. .. .
' .!Lfst'the 6hree-(3)? l basic' VARIABLES which; affect an1 individual's dose Jinsa. radiation area AND describe how the dose.would~ change if-each , LVARIABLE was doubled (with the'other two variables 41 eld constant) . -c QUESTION G.02' -(1.00)
t' Where can irradiated fuelLbe stored'when it is.not in the reactor core at ' the MUTR?.ProvideLtwoElecation o-QUESTION HG.03 (2.00), .
:i A. reactor s sampl e ~ has a disintegration rate of ' 5 X 10E11. disintegrations j per secon Each disintegration emits. a .6 Mev gamm What1is the i'
dose rate ^ expected five (5) ' feet from.thelabove sample-(assume point-cource)? i
: QUESTION' G.04 (2.00)
Define or explain per-10 CFR 20:
.a) ' Radiation-Area ;b) Restricted Area-c)- High' Radiation Area d) Airborne Radioactivity Area ' QUESTION G.05 (2.00)
JIf,you were working in a radiation ~ zone where the general background was
.120 mrem /hr gamma. radiation, how long could you stay in that zone before .you would. exceed the - 10CFR 20 whole body quarterly limit?
i, a p u ll'8 )
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
w = __ _ . -
- _ _ - _ . . - _ _ . - . - - . _ _ _ _ - . _ _ _ _ _ _ - - _ - - -
_ __ _ ___--- _ _ _ - . - _ _ _ _ _ -._ .- - _ _ _ _ - - -
,
'- ^ 1
.m L ,;'* : ' o . .' . . . .
.
<
L-
-w ;
iGi_iE@D[@l[ON_CONIEQ(_@ND_S@EETY
,
~PAGE 15
.'i
-
y LQUESTION G.'06 (1.50) , Where Lare 'the three fixed position MUTR radiation monitors located? - .
,
,
's , .
J
'
QUESTION G.07- (1.00) l i
. What areithe" sources :of f the two radioactive . isotopes, Argon 41'and-Nitrogen 16,. produced by-the operati'on of research reactors?- ,
.i
.
' QUESTION: 'G.08' ( l'. 00 ) <
'
-
"
:If the reactor _was at:250-KW.and one central-fuel element failed,-would
:the tota 1Lactivity released from the fuel element be inJthe range- .
.of (Choosefone)
~
'
A) 0 - 100 millicuries
.
B). 101 - 1000 millicuries C)' greater than 1000. millicuries QUESTION- G.09 (1.00) Dur.ing reactor operation the bridge radiation monitor indicates 180 mrem /hr. What is the RO at the reactor console immediate response? i
!
.i
..
l
!
(***** END OF CATEGORY G *****)
_ _ _ _ _ _ _.- _ ~ ~ _ _ _
--, -
,
-
m,
, , ' . ,
y ,.6L__E81NQlE(ES_QE_BEBQ1QB_QEEBBIlgN -PAGE 16 -!
-ANSWERS --JUNIVERSITY.0F. MARYLAND .-87/09/08-TURNER, , i l , ..
- [ ANSWER A' . 01 ' (2.00)
l-
- .. . .
k , '1.. Power history'(Xenon).
- 2. Temperature.
b 13.l Experiments in'the. reacto i
' .4.-Fuel:burnu ,
L - 5.. Rod locatio .. Fuel locatio (Any 4 9.5 each'to max. 2.00) (2.00)
'. )
REFERENCE Nuclear Energy. Training, Units 6,9,10
.
ANSWER A.02 (3.00) crl-/cr2 = .(1-Keff2) / ( l'-Kef f 1 ) . (.9) 100/150 = -(1-Keff2) / (1-0.95)- (.5) , p 1-Keff2 = 10/15 x 0.05
'
Keff2 = 0.967 (.1) (1.50) Change in reactivity = (Kef(2-1)/Keff2 - (Keff1-1)/Keffl
= (Keff2 - Keff1) /:Keffi x Keff2 (.9) = 0.967 - 0.95 / G.95 x 0.967- (.5) = 1.85 % delta K/K (.1) (1.50)
REFERENCE Nuclear Energy: Training, pg 6.1-3, 12.1-3
,
JANSWER .A.03 -(2.00) a )' - P.= Po e(t/T) (0.4)- 250 KW = 0.125 e(t/50) (0.4) InC20003 =1nte (t/50)] 7.6"= t/50 t= 380 sec or 6.33 mi (0.2) (1.00) b) Power coefficient would lengthen period and would eventually stabilize power. (1.) (1.00)
>,
I
~ REFERENCE j .Nucleer Energy Training, Unit 6,pg 6.3-1 .
i
< !
>
'
.____ -___
- _ _ - _ __
,
, e
'
d'.
.'
91__E81NCJELES_gE_BE@CJg8_ GEE 69IlgN 'PAGE 17 1*. , E ANSWERS - UNIVERSITY OF MARYLAND -87/09/08-TURNER, ' ?.
..
t ANSWER A.04 (2.00) L l a'. L a) Slight reduction in count rate'(.5) due'to~ removal of - J neutron source-which was positioned near detector. (.5)- j
'
b ) :, Reduce core reacti vi ty4 4 ,-54--due--to-removal-of-a-source n4 n oute on s .-.-LS)- (2.00) O**')qLJ4ttdjil l REFERENCE i OP 103 ; Nuclear Energy Training,' Unit 11 ANSWER A.05- ( '1. 50 ) 6 IR2 actor power will increase (.6) due to the addition of cold water.and MTC feedback. (.9) (1.50) REFERENCE OP 104, pg 1 a ANGWER- A.06 (1.00)
. <
Bata = 70/10000 = .007
<
REFERENCE
'
Nuclear-Training Manual, 5. F e i
' ' /.' ( ANSWE A.07 (2.00)
Thermal absorption-in fuel of Thermal absorption in non fuel Cause f dst . fission
. 7 ,. . Epithermal resonance capture ; ' .Lf est.: leakage P '. thermal leakage (any four 9 .5 each) (2.00) ', s )
', '
REFERENCE.' j fg" ' Nuclear Energy , Tr aini ng, Unit 1 i
!
'I ,4
)
b
_ - _ _ _ _ _ ._ _
,
f.
, . I i... 6t- EBINQlE6ES.,QE_REQQ1Q6_QPE[89TlQN PAGE 18 ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, }j'W'a
'J n iij .
ANSWE A.08 (1.00) To maintain the reactor critical at a steady state level (.5) due to the delayed neutron effect.4(.5) .( 1. 00) ov D u.< liter . C.wijc . l'Mi[D(Pl j . REFERENCE MUTR OP-104, pg 3
\
l d
+,,
i i l
,
_ _ _ _ _ _ _ _ _ _ _
x, . ,- - - -
<
' ' 1,. . ie Be__EEQlyRE@_OE_EQC[611Y_ DESIGN PAGE' 19 i
*
l ANSWERS -- UNIVERSITY OF' MARYLAND -87/09/08-TURNER, e I i l
!
ANSWER B.03 (2.00) a) $0.50 4 b) 53.50 c) 51.00 i d) one (.5 each) (2.00) j
!
REFERENCE MUTR TRIGA TS, pg. 7,8,13 i ANSWER B.02 (2.003 A pump takes a suction from the bottom of the pool (.5) und discharges through a nozzle above the core (.5) and causes a circulation pattern (.5) shich allows time for the N16 to decay prior to reaching the pool water surface t.5). (2.00) ;
!
REFERENCE ; MUTR SAR, pg 8-4 ANSWER B.03 (2.00) ;
;
Graphite slugs (1.) pl ac ed top and bottom within the fuel rod ensembly (1.). (2.00) I i REFERENCE MUTR FSAR pg 4-2
.l
'l l.
. J l i E 1___ _ _ _ _ _ _ _ _ . _ $
' ;
Q,
'
e .- ,
.
.,
l
'
--'4 $
'
',
. .:
,
,
3 . ' '. . Es,.
- EE,,,@lyR_ES, _QE_EQQ16111_QE_Sl@N' .PAGE '20 .f; w -
s L ANSWERS -- UNIVERSITY : OF MARYLAND ' :-87/09/08-TURNER,- l
'
'
.
,
.
ANSWERl B.04- '(3.00)
;a) '1)'Thefpool. water,. inlet pipe.is equipped with a siphon break. cat-the s'uef ace of. ~ the pool l.' ( 1. )' .2) Thelpool water, return (outlet) . pipe. i s not ' morei than 20 incihes below the' overflow outlet: pipe.~(1.)
y lb) Fifteen [ feet (1.) ( 3. 00 )-
. .. REFERENCE .. .
rMUTR:TS.pg 18'-&119 .
,
'
.
'
'
.;!i ANSWER B.05: (3.00)
';
.
;Sne figure 5.1, MUTR.FSAR pg'5-8
,
(.2'for'each component requested.in the: question to'a. max'of.3.00) .(3.00) .
'
'
B REFERENCE h-MUTR FSAR pgf5-8
~
.,
i
'
)
i ANSWER B.06 (2.50)
, MUTR SER Figure 4.1 , three control' rods, fission chamber,'cic-chamber, ion chamber,' source, and rabbit hole
'
, (.3125 for each of the above components correctly located to a
'
maximum of 2.50 points) (2.50) y
'
', REFERENCE
.MUTR SER' Figure 4 1
!
s I J
{;
'
l 6, _ _ _ _ . - - _ - _ _ - _ _ _ - _ _ _ _ - - - _ _ _ - _ -
l i
.
-
-
s
. .', .r )
- _ . .
,
o - t t - c, ol l e . _
, on API V ,
,
,
-
-
P UR
'
mo EE KT AA v g
'
,
O t M ,
,
, g l
~ te
, ot
[';
l
' j pO
, ou
'
0, '~ . f bI
/ \
-
;
'
/ -
I] 4. ,.
)
\ (
r '
-
-
M)%
. e n ' b)(. -
MU
!
1 n- a II
-
oxh II
-
I E c T ~ v I C C R it ll m AE '{\ e Y\V lI _t
,
D/ N s
. - O y C s
_ - E S gM k )
>
t g ,-
/ n n / )/,-
j a
'/
,),
i j'
/
/
-
, _
l
/
.
o j/',
.
/ 2 - _
clYb, o
'
2 c nv
\ 3 -
' X H
/ ) }- y r
(l, / y
, ( .
a m i l f' I . r 1R P
)
A3 J
-
I .
$ D 1 N
O P . C E M 5 - Sy -
~
(l ~l{
I T
-
.!
n
&P%_'g Vg U c
_
( e r
u g f]'x _ g2 i
/
\
- F
_ ( t , MG V _
._
-
s me f &
' jij I
F
,I _
l \ [' i
.
-
-
,lI < E I
C m[1 Y . l *
.DI
_ I F . _ . T M * FI R
*
*-.
O _ . _
. . '\
_ _ Y
.
_ _ Y R n h R
.
A A a D D N N m
' -
O C E
$ O C
E - S all
.
S y, A I _ fk
-
-
s 3- : eEc3
.
:.
!> k 6 F o} L0 ye --
-
. .
..- 9
: - 4 ,.
x '; f .
,\
i
')
O
= ' .-
-w a i s 'h = g Z- O d e w 3 w a= .s'
ww
=. a = I F
l a ws w .. g' K < z- >
. "w -
o
= 3: o w .aw sz.- o.< Ei m., <- ,
e
.g m I fga o e . @ @ @ 7ib E .! ,
sw
-
f4 1 o 5 :f C-!
\\ - -
@ . .F H
)
_ OnO OnO 0,0 0,0 j 3 O'O O*O OO O"O "f l
'2* -
1 0,00,0 00, :g;ltjo,0 g l 2 O'o g*O O*6 6::a O*C y ; } OO O.O Oc0 ' I- t;
*
b' O'O O*O OO O"O ,_ x 1
.N
_
"- OO O.O O.O *
g [. ; .i
:$ O"O O*O OO O"O & / @ . 1 E O,0 eO s O,0 0,0 g g E
5 $ O'O O*O OO O"O l 6 0.0 0.0 03 ! O'O O*O OO O*O xx @ b
- , . N w w o S W N H l
] E 3 E h <
!,! :
ll
'
>Z @ '
- Bo_x o 5 . o h - ; EISVR 1__ _ - - - _ _ _ - m- _ ._ ;
ygg ; ..
,
.
- - - - - - - - - --- - -
]
-., T: .
' 1 1C - g kEt__@gNERQy_QEEQ@l[N@_Qd@@@QlE61SI[Q 'PAGE '21
:
> .
>
; CANSWERS.'-- UNIVERSITY _OF MARYLAND
-
~ -87/09/08-TURNER, '
>,
' ANSWER: . C'. 01 (2.50)
'
a )~ The criti,calJr~.. neignt on restart would be higher (0.5) ~due to' , u theLincriase in' Xenon ~during shutdown (0.5). (which.would have'added' ) negat've . reactivity).
- i _b) 'ani ti all'y, rods must be wi thdrawn to. increase power : to' 200 : KW - (0.5) . - 4 As Xe.is burned out from i ts parak value, rods must be1 inserted (0.5). ) Eventually,-_Xe will reach a minimum value and will'begin to. increas ' to its: equilibrium'value for the: steady state power level. At this i Ttime, rods will have'to be moved out.to. keep-power constant' -( 0. 5 ) .
-REFERENCE Nuclear. Engineer Training,- pg' 10.3-1,2,3
.
.
" -
l ANSWER C.02 (2.00)
'In.theiregion of highest flux .( 1. ) i .Normally in the center radially (.5) and the middle ax i al l y (.5) (2.00)
REFERENCE Basic' Reactor Theor CAF f
I
'l ' ANSWER C.03 (2.00) .
I J a) 1.21% dk/k.($1.73) (.5)
!
b) ~ $5.80 -(.5) l
"
c)-$2.42 '(.5) d)'$3.49 (.5) (2.00)
(Will accept + or - 10%)
REFERENCE i; 'UM'SER pg 4-5
'
l
'
.-
,
i i__..._____ ._ _ _ _ _ _ _ _ __ .._______________.__a
----
, ,
,,.
i n'a,n *l
.s
!
'
9: ' f J ' o
'
j Ei._@ENE8@(_OEEg@l[N@_Qd@@@QIE6[QIlg@: e -PAGE ~ 22 -l i
"" ANSWERS -- UNIVERSITY OF MARYLANDi - 8 7 / 0 9 /.0 5 - T U R N E R , ' R '.
I i
" .. .. ,
j ANSWER :C.04 (1.00)
,
y iThe reactorLis.not.'et/ critical. . (The. longer it takes for
. period to-die;off the closer you'are to critical.) (1.00)
REFERENCE
? Nuclear: Energy Training. pg112.1-4 1
.i1
^
-
: ANSWER /C.05~ ( 1.' 00 )
, Water' flow 1through-the core is by natural convection. (1. ) -(As the I water in.the. core is-heated, its density decreases 1cnd it tends
- -to rise.JIt.^is replaced'by cooler ~. water, which heats.and i also; rises.) '
(1'.0 0 ' 'd j
.
'IREFERENCE MUTR SER,-pg'4-3
h- Il - ANSWER C.06 (2.00) !
'The regulating rod would move in (1.) to compensate for the increase in reactivity' caused tnr.the enhanced reflection of-neutrons back to ?the core as the . gas was replaced with water (1. ) . (2.00)
f U .E "! 'PEFERENCE
^
INuclear Energy Training, Unit 1
+ ; : ANSWER C.07 (1.00) "
a) To minimize system corrosion (.5)
.b)IMaintained by operation of'the demineralized (.5) (1.00)
!'
. REFERENCE UMLSER pg 5-1, TS' i j
. _ _ _ - _ _ _ _ _ _ .. i
__-
.
C:.__GENEQQ(_OPEQ@I{NG_Qt!@B@gIES{SI{GS PAGE 23
,
ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, l ANSWER C.08 (3.00) c) Pool temperature (.5) and reactor power (.5) b) Pool Temperature increase (.5), reactor power decrease (.5) c) High temperature pool alarm (.5) d) No (.5) REFERENCE MUTR SP 202 , pg 1
;
l f i f l l
_ _ _ _ _ _ _ -
. _ .
-
-_
.
U > <
. . .
^
!' ; i , .
, , l ,
' .
t
' !
p, -d D y 4 (_21N@TRUMENIQ_ANQ_CONIR06S PAGE' 24
~
ANSWERS)- " UNIVERSITY OF; MARYLAND -87/09/08-TURNER, ,
:-
t'
..MASIB 1 (. : ANSWER ~ D.01' -( 1. 50 )
a)q True.(.5).
'
. b ) -- ~'Fal se ' ( . 5) .
c ), 'True.(.5) - ( 1 ?50 ) -
, , . '
REFERENCE-i ' MUTR1TRIGA SER,-pgJ4.7, & 7-1,7-2
' . ANSWE '. D. 02 (2.50) $[ i d .ThreeJindications of' rod position (.5 each):
'
.Up (f ully withdrawn)
Down (f ull y -inserted)- Down position of . the rod
'
p -Indicates;whether magnet current is on (.5) Indicates whether1the magnet is in contact with the rod (.5) (2.50) REFERENCE
.MUTR SER-pg.4-6,4-7
ANSWER D.03 '(3.00) a) The mass of the-water is'a' constant (22,680 kg) when the pool water
,
level is adjusted to the 23 foot mark.(.5) The pool temperature is , measured with'a thermister over a period of time when the reactor' power ' 11 s . constant ( . 5) i i b)'At[100 or 200 KW (1.)
c)nThe. height of. neutron detector is adjusted.(1.) (3.00) (: . . REFERENCE , MUTR SP.202 l L I-i
'
I m, i-L .L :._L- - _ - .
.. .
-
=-- ~ , - - - - - - - - - - - - - - ---- - ----- - -- - - - - - - - - - - - - - - - - - - - - -
)f 4yi ,
;/-
,
';
* i ,
,. ,
'
'
, } y ;. - r 5-j
-
.. ; ,
.
>
D['__INgIRU_M_E_N_IS,,,AN_D,,C_ON1R,017
" '
.PAGEI.25 j te : .
'
ANSWERS -- UNIVERSITY-OF-MARYLAND' -87/09/08-TURNER, ;
' MAS:IR .i V, "' -ANSWER' - - D. 04 : ; (1.EO) ,
i
1
,a). . Indication' roads off: scale high. (.75)
.. .
~
l- s l b)' Indication reads" temperature at short.(.75) '( 1. 50 ) L ll REFERENCE Bas.ic Thermocouple Operation - CAF
., !
ANSWER D.05- ( l '. 5 0 ) - L '
*di
, ROD--DOWN L IGHTl f DV%{9t Thh O
"s
&y E-OkN - rd\'
+ ') -@,
MACNCT--UP--4.1.GHT - ON ' _me M AGNE-T--DCWN L I CMT-NPr ' . 5) .. > ' . l 3 W\ hb-O' ('1. 50 ) N b -N REFERENCE
.MUTR, Safety Evaluation Report pg'4-6-
,
i ( , 3-) g ,j tj
. ANSWER' D.06 (1.00)
Pool, temperature-is controlled by operation of.the primary cooling system (.5)', with heat exbhangers in service as required'(.5' (1.00)
,MUTR SER Section'5 ANSWER D.07 (2.00) . . Al%W '154lM[5l Sse Figure MUTR SER, pg 7-5 FissionLCham er (.001 watts to 0 watts) (.5)
y l Compensats Ion Chamber (.1 Watts to ull power) (.5) l
. Log-n.reco der (spare)
Compensated lon Chamber (.01 Watts,o full power) (.5) Linear rjkcorder
.
I
[ i
_ Ion Cha)mber (100 KW to full powerl ( . 5) (2.00)
'
CMP :d 7e pM e Ldi d.t b ct. q g L in e m C. l od
,
f _ = _ _ _ _ . _ _ _ i
'
l , 92__JN@ISUMENI@_9NQ_CgNIS96@ PAGE 26 ) ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, R.' [ t REFERENCE MUTR SER PG 7-5 I
' ' ' ANSWER D.08 (1.00)
Operates on the principle of a conductivity "onitor (.5) Difference in reading in air as compared to reading in water (.5) (1.00) 4 REFERENCE MUTR FSAR pg 7-27 j i
,
-
l
- - - - - . - - - - - -
- , .
E;__S@EEIy_@ND_EMERGENC1_SYSIEMS PAGE 27
. ' ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, l - I ANSWER E.01 (3.50) !
i Safety Channel No. Required Trip Setting ; g) Raattor Power Level - two required - set at 120% of full licensed power
#
a) 7 G D.\ c Q O U ? dd{fEC y Fuel Element Tem one - Not hdexceed 400 degrees C j
/ :
'
Rcattor Power C two - loss of power supply voltage l y) Datector Power Supply to chamber ' ohC c) (LR nD(g 40 ks e a u e o Tf L'y^[ ' 6) Hinuaf Scram - one - n/a
&
7) Consol e El ectri c al
' -
one - loss of electrical power 53pply to the control console j
$ ~5ybrCat b REQoxG fe lt f uul. Ctsh r '
'
- 4,-1% 4 - nach-corr-eet-r esponse4-y ypyp p / (3.50)
,/
REFERENCE ,
'
MUTR TRIGA TS, pg 9. M e,o L'(m were A sce reN7h ,
/
/
I T'1 1 ANSWER E.02 (1.00)
$W[
To demonstrate compliance with Technical Specification control rod drop time (< 1 second) (1.00)
!
REFERENCE MUTR TS 3.2. (1) ; MP 304 pg 1
) - ANSWER E.03 (3.00)
a) Source countrate less than setpoi nt ( . 5) ; Prevents any rod withdrawal (.5) b) A plug from the beam tubes or through tube is removed (.5) Prevents any rod withdrawal (.5) (unless special bypass key is used).
c) Attempt to withdraw second control rod when one rod is being l withdrawn (.5) Prevents more than one control rod being withdrawn at a time (.5). (3.00) 1 l i i l l
!
!
m_._______.___.__ ]
_
,4 , @ *._ _S 9F_EIY_@N D _E ME R @E NC Y _S YSIE MS PAGE' 28 ..
ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, i Yi , REFERENCE ! MUTR.SER pg 4-7 ANSWER E.04 (2.00) f Check: I nuclear instrumentation for immediate drop in power (.5) for - 80 sec period (.5)
'
rod down lights (.5) CR drive position - visual check (.5) REFERENCE-MUTR SER pg 4-6,4-7 )
-ANSWER E.05 (1.00) ] g gp-7 Q ; -An electronic braking mechanism on the drive (1.)
(permits a lock at .24 inch' increments over the 24 inch rod travel) ( 1. 00 ).
'
REFERENCE MUTR FSAR pg 4-8 ANSWER E.06 (1.00) Nrgative pressure maintained in reactor room ventilation system ( 5) z(.5) by
.
gg gg (1.00) REFERENCE MUTR SER pg 6-1 . I i
! . - - _ - _ - - . _-
. _ _ - .
l
4
. l l < i E __g8EE11_@ND_EMERQENC1_SY@TEMS PAGE 29 ,,
ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, j ESTER 1 ANSWER E.07 (2.50) a) Intended'to prevent exceeding the safety limit (.5) if sudden removal of the experiment should occur (.5).
b) ' intended to prevent damage to reactor components (.5) from accidental detonation of ex p l osi ves (.5) l
c) Intended to prevent damage to reactor components (.5) (2.50) REFERENCE MUTR TS pg 13 & 14 a
!
l l l , I L_____ -- 1
. .. ' t!# e ,4:. . . . ' ,
e 1
,
t
- ESTANDARD'AND:EMERGENCYIOPERATING' PROCEDURES' PAGE='305 > L: in .l i
O fANSWERS:-- UNIVERSIT.Y OF. MARYLAND -87/09/08-TURNER, ' ' s . . .
,
. .
~-e
.ae -,. ;
> y; .
.
'
LANSWER F.01 (2.50)
'
. a)l'Anyffour=of'.the.six.11sted.in TS 1. 21.1 ~ the ough -1.'21. 6 : (at .5 points
,
. each . .f or a max. of:2.00 points).
.b)f:No -(.5) '
(2.50)
' ^ REFERENC aMUTR SER pg 6-1
'
ANSWER- F.02- '(3.00) :i
!
a) The purposes are to be. aware of the radiation levels at the. bridge (.5)
,and=that~the ccre power level'is not rising (.5).
b) ; By f shaking /the f f uel handling tool to assure that it is latched onto th Ltop handle of'the; fuel bundle.(.5)
'.c)1 Record the time ('.'.5), grid and location number from which the fuel Li bundle was' removed (.5) and the storage-bin number to which'the bundle was moved (.5) (3. 00) .
; REFERENCE
=MUTR MP 303- i
o ANSWER F 03 (3.00) l
.1 a) Water level (.5) results in loss of shielding and high radiation level (.5)
b) Scram the reactor (.5) Restrict Access to the bridge (.5)
~
;
Notify the Director (.5) ' Attemp to control leak (add water) (.5) (3.00) ) REFERENCE (MUTR EP 402 , I l- ' i
; > .
m-----_______-. - _ - . - - R
_ - - -_ ____- _ -_ -
,c
' EL-_Q1@NQ@@Q_@NQ_EMEgqENCY_ OPE 8@I[NQ_PRQCEQUREE PAGE 31 l ' *
i
' ANSWERS -- UNIVERSITY OFEMARYLAND -87/09/08-TURNER, l i y- ,
A
. AU . ~ .
'
;
.
ANSWER F.04 (2.50)
!
a) 10% increments (.5); banked at 80% (.5) I r b) 1-5% increments (.5); avoiding 1 reactor period trip (.5) c) Just before or just after the reactor is critical- (.5) REFERENCE MUTR OP 103, PG,1 i ANSWER- F.05 (1.50) Scram reactor (.5)
!
Manually trip the ventilation system (.5) 1 Notify the reactor supervisor (.5) { REFERENCE i MUTR EPP 7. l ANSWER F.06~ (1.50) a) turn off key and secure reactor (.75) b) Notify Reactor Director of the event (.75) REFERENCE MUTR AP 500
,
s
I
<
____: __ z _. - - - _ -
,
-. _
_ _ ,
.. lGe__50918IlQN_QQNIBQ6_@NQ_S@EEIY PAGE 32- l ANSWERS -- UNIVERSITY OF MARYLAN /09/08-TURNER, R.
V inh 8TG i
;
ANSWER G.01 (3.00) i Time (.5). Time doubl es, dose doubles (.5) l
\ Distance (.5). Distance doubles, dose rate decreases by 4 (.5) (inverse square law) Shielding (.5). Dose decreases exponential y wi th thickness (.5) (3.00)
J REFERENCE Basic Radiation Protection J.R. Lamarsh, Introduction to Nuclear Engineering,pg 480 ;
ANSWER G.02 (1.00) In the fuel racks (13 positions) in the reactor pool . ( . 5) 2, In the fuel pit , north floor of reactor building.(.5) (1.00) ! REFERENCE MUTR SER, pg 9-1; SAR, Chapter 8 q i ANSWER G.03 (2.00)
-(5 x 10E11 dps)/3.7 X 10E10 dps per Ci = 13.5 Ci (1.00)
DR = (6 X Ci X E)/dE2 = (6 X 13.5 X .6)/25 = 1.9 R/Hr (1.00) ! REFERENCE Glasstone, Principles of Nuclear Engineering pg 545, MUTR SP 205, pg 1 i i l
;
;
I
;
l
;
_ - _ _ _ _ _ _ _ _ _
.-. ._____ __- --___ - ____ -
s f , S'G u
[: Nn - , ' .i
, 'GA- : RADIATION' CONTROL'AND SAFETY PAGE 33 ' " ~*;
ANSWERSE- -UNIVERSITY OF MARYLAN /09/08-TURNER, R .- ) l ISSIB
- ' ANSWER -
G.04 (2. 00): 1 j
'
a) Any. area i rt whi ch there exists' radiation at a. level.such that"a 1 major portion'of the body coul d recei ve 5 : mrem ~ i n one -hour- or 100 :
.
mrem in'5. days (.5).
b)' EArea of' controlled: access-for. protection of i ndi vi dual s. f rom-exposure.to' radiation-(.5).
c)L lAny: area'in'which thereLexists radiation at a l'evel such~thatEa } , mayor portion of;the. body could receive 100 mrem in one i hour-(.5).
Ld)
. .. .. .
Area in which concentrations of airborne radioactivity exceed-
.
]
.!
amounts specified infl0 CFR 20,. Appendix B (.5). (2;00) j
' REFERENCE 10.CFR 20,-part 20.202 IANSWER: G.05' (2.00) , l'. .101CFR 20 whole body quarterly limit for gamma radiation is 1250 . mrem ( l'. ) -2.11250/120L= 1'.42 O hrs: stay time (1.) (2.00) . REFERENCE'
E10 CFR 20 < i ,
< ANSWE G.06 (1.50) j a)!ane on bridge above the reactor ( .7 g s = n ~ ~ e.r - .u - em .
. =,r c).one near the reactor room air exhaust fan M (, ")$ (1.50)
a REFERENCE MUTR SER 12-2 l n
, .. - -
.,
, - .
, ,
p7 , , r.., !D G
'
j G.,,, _B@Q.I,@llON_CONIBOL__QNQ,,S@F.ETE PAGEf'34.
V.s.-e., CANSWERS ---:: UNIVERSI TY .OF..' MARYLAND --87/09/08-TURNER,'R.- g- .
'
L .
-'.. -
. -[[n,,;; ;,_d1i
..
..
l
>
,, ..
.
' ANSWER- -G.07- -- ( l '. 0 0 ) . !
-Rsdioactiv'e. argon.-is produced'by the radiation by.: neutrons.of the. argon in
; air ( . 5) and ni trogen 16 is produced by the radiation.-of oxygen in' water'by<
L ,
,nauteon . REFERENCE . .
MUTR SER_12.3, SAR 8.5' l
.o a ANSWER- ' G '. 0 8 (1.00) , ' A) 01- - 100 millicuries' -(1.00)
in REFERENCE i MUTR FSAR 11.2. o ,,V l r
', f
!' ) ANSWE 'C,09 (1.00)
,,.
.
'I
.
. ';The RO: shutdowns (.5)'and secures the reactor (.5)
.- -( 1. 00) - i l- ' REFER'ENCE
: Emergency Preparedness Plan,Lpq 3-3 is - ;i ,
i i E * L;1 y:-
,
p.
c l l.
'
.,.
b 1 _ . .. . _ J
. . . . , ,
x < q; '
. TEST = CROSS REFERENCE PAGE 1 . : QUESTION -VALUE' REFERENC ' .________ _--_-- _----_--- .
A 01- 72.00 'TRLOOOO554I * jf
.A.02- 3.00 TRL0000355- . A. 03 ' ,2.00 TRLOOOO556 A.04 2.00 1TRL0000557 .A.05 .1. 5 TRL0000558 A.06' 1.00- 'TRL0000559 JA.07: ' ~2.00' "TRL0000560: .A.08 ~1.00 .TRL0000561
_____- l' 14.50' B.014 L 2. 0 TRL0000563
*
iB.02 :2.00 TRL0000564'
~ B. 03' 2.0 TRL0000581 -
'
'B.04 3.00 TRL0000582 B.05 '3.00' TRLOOOO586
]
B.06' 2.50 TRL0000587 '
.______
-14.50 C.01; 2.50' TRL0000562 7
: C. 02 - 2.00 .TRL000056 >C.03 :2.00 TRL0000583-
'C.04 1.00: TRL000058 C. 05 ': 1.00 TRL0000589 xi . C.06 2.00- TRL0000590-q- ;C.07 1.00- -TRLOOOO593 '
.
1C.08 -3.00 TRL0000594
, .._____
1 . 14.50- .! i I u.'fD.01
-
1.50- TRL000056 TRL0000568
' -D.02' 2.'50 , D.03- 3.00 .TRLOOOO579-D.04 1.50 TRL0000595 l ,D.05 1.50 TRL0000596 , D.06 1.00 THLOOOO597
[^ , D.0 .00 TRL0000598 3
'D 0 't.00 TRL0000599 '
______
] ,
14.00 l E.01 3.50 TRL0000565 L E.02 1.00 TRL0000585 1 l- .E.0 .00' TRL0000600 I }. - (E.04 2.00 TRL0000601 ' IE.05 1.00 .TRL0000602
' E . 06' 1.00 TRL0000603 'E.07 2.50 TRL0000604
______ 14.00 l
, .F.01- 2.50 TRL0000569 i
_.___.____________a
- - - -- - - - --
: -- --. - . - .
*
p.:' . {-l , ,. ... '
. -
s
.i
* *
. . . . . ,
' '-
.
TEST-CROSS REFERENCE- ' PAGE 2 l at si ' b , _ GUEST ION ? . ______ VALUE- : REFERENCE'
'
-
.
___ __1 -- ________ -
,
, F.02; ' 3. 00' . TRL0000584
. F.03 3.00- .TRLOOOO605
: F.04' .- 2 . 5 0 , TRL0000606 ;
F 05
-
- .
'1.50' TRL0000607- 4 - F.06- 1.50- LTRL0000608 1 . _ _ _ _ _ . '14'.00 :
G.01~ 3.00 ~.TRL0000570 G ; 0 .00- TRL0000572 . G.0 .0 .TRL0000573= Gs04 2.00 lTRLOOOO574_ ,
*
'
; G.05- :2.00 'TRL0000575 G.06' ~ 1.50 TRL000057 G.07 l'.00 TRL0000577 G.08 1.00- -TRL0000578-
-
- G.09- l'.00 :TRL0000580
_ _ _ _ _ _ . . ;
.14.50
___ __
- _ _ _ _ _ . ' 100.00'
i il
..
- _ - _ - - _ _ _ -
.. . - . - - - ~_ -- A 77s9C drif W 2- . ' , ,
L ~e; U. S.' NUCLEAR REGULATORY. COMMISSION SENIOR REACTOR' OPERATOR LICENSE EXAMINATION FACILITY: _UNIygRSI_TY_gF_M9RYL@NQ _
;
REACTOR n TYPE: _ _T _R _I G._A _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ n,
'
l, DATE ADMINISTERED: _@Zf@9f9@___ _ _ __ __ _ _
.~ EXAMINER: _TURNgR2 _R1 ___________
L ' CANDIDATES - _ _,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ '.INDIBUGII9NS_Ig_Ceyp1peIE1 iUsa separate . paper'.for.the answer Write answers on one side.onl ,, Stapl D. questi on sheet .. . c.,n top of the. answer sheet Points'for each '; qusation are -indicated in parentheses after the questio The passing
: grads requires at:least.'70%.in'each. categor Examination papers will bo picked..up six (6) hours. .after the examination start ,
.I
:
% OF-
@TEGORY % OF CANDIDATE'S CATEGORY L.YBLut_ _Igl@g ___SCQRE___. _y@6U_E _ _ _ _ _ _ _ _ _C@lEGQRY_____________, zo.sprl 39:.99__ _29_L ___________ ________ REACTOR THEORY
'. 2 o .s tyr .
3h.99__._2LES _ 3________ ______ . RADIOACTIVE MATERIALS HANDLING
.
DISPOSAL AND HAZARDS Fl?. Og.;d,9N(f L 7
:2@r@@p .J. . SPECIFIC OPERATING
$9 9 ________ __ ______ CHARACTERISTICS 3 2.0.5*18 9 l2@r.9@ 3@_'r@@ __ _______ ________ FUEL HANDLING AND CORE ! PARAMETERS l 2o .5 /+f - i Eh.99__ _ & @@l.___ __ __ . _ _____ ADMINISTRATIVE PROCEDURES, l CONDITIONS AND LIMITATIONS j N 97.5 W ELET__ /0#74___________ ________% Totals 1 Final Grade ' I All work done on this examination is my ow I have neither given j nor. received ai l
:
_ _ _________________.____.__________ Candidate's Signature 2.1 M4 M 8M gW N sp - wm 3 N
. s.a_< W ivo , co -m,&r7-og ZA7f,494r7
,,, . ,- r - - <
a :
'
{, l/ u
- i f iNRC' RULES,AND GUIDELINES FOR LICENSE EXAMI' NATIONS Q3 uring ).the administration of this examination the following rules 1 apply -
t .
,
Ji: Cheatingfonethe examination means-an' automatic' denial oflyour. application '
-and:could resultEinJmore severe penaltie '
h .Restroom trips are to~be li5ited and only'one candidate at a. time may.
p' leav You.must avoid allLcontacts.with anyone outside the. examination troomito avoid even1the appearance or possibility of cheating.
E} 'Uss; black' ink or-_ dark pencil gnly to facilitate legible reproductions.
O Print'your name inLthe blank provided on the cover sheet of the
.~ ax ami n at i on .
b; Fill in the date on the cover sheet of the examination (if necessary).
, Use only'the paper provided for answer ! i
'
.s - P.' Print.your name in the upper,right-hand corner of the first page of=eac 'section of the answer. sheet.
D. : Consecutively number each answer sheet, write "End of Category __" as , ' appropriate, start each category on a ngw page, write gnly 90 goe sidg l l of-- the - paper , and write "Last Page" on the last answer shee j ! l Number each answer as to' category and number, for example, 1.4, , -
.
i 30,LSkip at-least:thagg lines between each answe ! II. SzparateLanswer sheets from pad and place finished answer sheets face
'down on your desk or table.
)2. :Use abbreviations only if they are commonly used in facility l_i_tecatut . y L3. The, point value for-each question is indicated in parentheses after the i question and can be used as a guide for the depth of answer required.
[4.JShow all calculations, methods, or assumptions used to obtain an answer i to mathematical problems whether indicated in the question or not.
L5. Partial credit may be give Therefore, ANSWER ALL PARTS OF THE-QUESTION AND DO NOT~ LEAVE ANY ANSWER BLANK.
16. If' parts of the examination are not clear as to intent, ask questions of
:the examinet onl l I7.?You must sign the statement on the cover sheet that indicates that the
' j work is your own and you have not received or been given assistance in
. completing the examinatio This must be done after the examination has been completed.
L i ' r ! r I L _ - _ _ _ - _ -
m ,
,
.\
,
< - ,&,;; >.,," '
, ; , -1 g 4? 4 ,
4, ; 4- .j
'- '
. , , ,' . .. - -
*g : )
%t W' hen?-you complete your examination, you.shal1:t .
.
. .
- q' . l p- j w , _- __ '~ms ;
3k;eAssemble yourgexamination;as fallows: , j
-- . ,.
.
.
,.
:(1) ExamEquestions onjtop.:
l(2) Exam. aids -l figures,: tables,-et ' 2'( 3 ) ; 'Answerfpages!. including' figures which.are'part oflthe answe '
.
~
i UL b . .
'
iT urn in.your. copy of. the examination.'and all- pages used to answer ) the examination. question j I c:.; MTurn i n : al'1 scrap : paper fandl the bal ance of, the paper' that - you did -
.
.
-
j
' *
:not-use.for. answering the question 'i Leavethe examinationLarea, as..ddfined by the examine '
.6ed.- If after leaving, you are found in this area while the examination is :still-
.in-progress, your license maylbe denied or. revoke .
.3- .
!
i
.
.
,
.I i
a
I' l
.1 L i t
-
!
~
o 3 i
!
I I l l
, i S..1 ;
-
,
_ _ - _ _ - - _ c - , . . a: f h '. , 2 ,~
.
[be.e_BgecIOS_IggOgv -> <
'
7, PAGE- w n
! '
_') !4 <
, ,
CQUESTION'g.H.01 '< 2. 00 ) - n Nsmi'f ourI; ( 4 ) .I ofi thefvariables that 15.) hlcause the critical rod positio ' , for'the reactorjto-change'fr6m startup to:startu Li ' i liQUESTION;[Hj02: 3 ( 2. 00 ) - ,
(MatchT tihe[l abeled : areas of the chart: below . showing'.J countrate :as .a"f unction ;of' time)duringLa: reactor startup with the appropriate description.
t
'(NOTE::iSever al areas have.the sameLlabel.)
,
:: . .
l *- Lin :: b *
" ,4 .! * : : TIME; ! *
l c- *
' .. *******
1 * 'I I
..!- d*' .)
l:
'
* l
:.1 *
'i < * l
!. * 1 l, Final countrat 'l l' * Initial-countrat 'l ***** ' 3. - Equilibrium value of
!; '* - subcri ti cal . multiplication q l
r
'
.'d* Equilibrium value of' a
! c * final" critical'countrate' ]
***~
i
:- *
5 .'~ Premptfjump Critica1J reactor ] - i c '* Point of adding heat j i ** 0 - 1: - * . a-* _____,,______________________________________________
'
[ ! i i ! l ) ,000 10,000 100,000
'
'l,
-
i
JDUESTION 'H!03 (3.00) l '
@ow'much' reactivity.has been added to a subcritical reactor if i
!
'the count' rate has increased from 100 cps to 150 cps and Keff was t j_ ini'tially.0.95? Show All' Work!
_ j l i- < . .; $ l (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
.:
u s
.--- - _ _ _ - - - - - _ _ -
. _ - - - _ - ., . > .g w l
$ Hic _6E891Q8_IHEOBXf PAGE 3-l W
'
a
6 )+ [ :
,
t '
'
NQUESTIONI H.'04' (( 2. 50) -.
,
LNamithe differentj' modes lof' heat itransfer by.'which the . heat..of. .f i ssi on
'ia' removed fromLthe fue ' Include maj or ' components iinvolved. in the heat-
*romoval' process startingcwith the fuel and'ending at'the~ ultimate heat
-
']
'
.
siin .
'
.1 l;
:. QUESTION; H.05 '(2.00)
-
.
\'
ra ) . . Assuming the reactor is atc125 watts and afperiod of 50 . seconds
=1s, maintained,.how long.will it take'to reach 250 KW?
Sho@ your. work'.
:bF ' Assuming'the reactor.is' ate 125 watts and a 1%3 second period is-initially established, explain how and why the. reactor will :
respondJif no further. operator actions are take t
'! i
:l
~
QUESTION H.06 (2.000- ,
'j : Explain the;two properties'of Zirconium Hydride fuel that account for the .larga, prompt,.and' negative-temperature coefficien '
QUESTION'~H.0 . (2.00) ! a i Mc After the reactor is critical on startup what affect will remova { loftthe startup-neutron-source have ont (justify-your responses) i a) . Detector indication
!
.b)' Core reactivity I
!
QUESTION 14.08 (2.00) r e)Tunder steady-state operation, would there be any significant difference between the control rod positions at 100 watts and
>L200. watts? Explai :b)[Under steady-state operation, would there be any significant difference between the control 1 rod positions at 100 KW and ;200 ,
KW? Explai i (***** CATEGORY H CONTINUED ON NEXT PAGE *****) L_ L- . _ ._
_ __ -_ _ _ .,
! '
i i
;
2d_LjBE8gIgB_IBEgBY PAGE 4 ; l ., - - - , , . j
.
. . v.* , i, .i a l' QUESTION H.09 (1.50)
r i g
'Whdt affect, if any, Will starting the prima'ry. coolant pump have
, '
"
if the reactor is operating st 250 KW? Explai I s, QUESTION H.10 (1.00) J If 10,000 neutrons both prompt and delayed are emitted in one i q:ncration and 70 of them are delayed what is the value of beta? i
.!
i t I
!
i
!
,
i l
(***** END OF CATEGORY H *****) l
_ _ . _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ -
_ _ _ _ _ _ -
,
Itt_geplg8CIlyE_M9IE6186S_b8NQ6]NG_plgEgS86_8NQ_d9188Q@ PAGE 5
!
l- a
'5'*
'
%)
c' QUESTION 1.'01 -(3.00) Lidt the thr'ee (3) basic VARIABLES which affect an individual's dose tin a radiation a'rea AND descFibe how much the dose would change if each
' VARIABLE was doubled (with the other two variables held constant).
, t s
' QUESTION I.02 (1.50)
What are the three (3)' principle sources of low' level radioactive liquid waste at the MUTR? ' QUESTION I.03 (1.00) Whnre can irradiated fuel be stored when it is not in the reactor core'at tha MUTR? Provide two location QUESTION I.04 (2.00) A reactor sample has a disintegration rate of 5X 10E11 disintegrations p:;r secon Each disintegration emits a .6 Mev gamma. What is the , dos rate expected five (5) feet from the above sample (assume point ] cource)? l OUESTION I.05 (2.00) 1 Define or explain per 10 CFR 20: e a) Radiation Area b) Restricted Area c) High Radiation Area d) Airborne Radioactivity Area QUESTION I.06 (2.00) l If you were working in a radiation zone where the general background was 130 mrem /hr gamma radiation, how long could you stay in that zone before l you would exceed the 10CFR 20 whole body quarterly limit? l (***** CATEGORY I CONTINUED ON NEXT PAGE *****) _ _ _ - _ _ _ _ _ - -
. . _ - _ _ - - _ _ _ _ . __-
7 , . 9; >
~ .x -- - .. - . . . - .
lldC;88QlO@QIlyE_d@lE81@(S_d@NQL{NG_DlSPOSQ(_6NQ_d@[@8QS "~ PAG ;
' ' . ,
f( . "
-QUESTION ^ h 07 (3.00) J What;are::thnee purposes.of a " radiation. safetyLand personnel protection d program"?:
'
-
. .
,
.QUESTIONL.I.08 . ( 1. 50)'
IWharo,are-the three fixed position MUTR radiation monitors located? i
' QUESTION
~
I.09 (1.00) What are the~ sources'of the two radioactive -isotopes,. Argon 41 and 1
. -
j Nitrogen 16, produced by the :operati on of research reactors?
-QUESTION I.10- '(3.00)
9- .
..
If the-reactor was.at 250 KW and one central fuel element failed:
- a) what f our radioactive ga ses would escape? - 1 b) would the total activity released from the fuel element'be in:the' range of:-(Choose one) :
~l A) 0- 100 millicuries 1
-!
B) 101 - 1000 millicuries C) greater than 1000 millicuries k i
1 J l
:
i (***** END OF CATEGORY I *****)
'[
. _ . _ _ _ _ _ . _ _ _ _ . _ -
. _ - _ __ __ , >
o -- I
'
id
-
K, , . ~Qy[f ( _SP/ ClElC_OPER@llNG g @8@CIE81STICS; ;
'PAGE; 7x ., >
1 , i
,fL , ,
Q' .
'*;
. .t .j
. .
.1 JOUESTION . ' J. .. 0 . ( 2. 50)- '
,;
[Aftselthree? days of(continuous operation.at.200 KW, the.-reactor is' shutdown ^
fforEminor; maintenanc Itfis restarted 8 hours later, , j Ka) ~How will the criticalErod position on restart. compare,to the
-
~
criticel rod position atLthe time of the previous startho? Give the- z
;. reason;fornchanges[in the critical rod p osi t i on s,.
"
'
,
~b ) Duringltheifir'stf24 hours'after startup, describefthe control rod .
'
: movements that would be necessary to raise the power from Just critical
;to'200>KW and maintain the power constant.after reaching 200 KW- 7 Explainfwhat causes.the need for changes in rod in/out motio 'j-i
<
:l
!
, IQUESTIONi.J.02 (2.00)
' ' '
LFill inithe blanks with the appropriate value: 'q 4 a) The-reactor ~shall not beloperated unless the-shutdown margin
'p,*ovided,by the control rods, under the most conservative conditions',
=isigreater than'$____ [
.
-b):1 T he excess reactivity relative to the cold critical condition %, with or- I
#
without experiments in' place, shall not be greater than $_____.-
;
c) 'The1 reactor'shall.not be operated unless each non-secured experiment has a reactivity value of less than $____ !
'd)EThe' scram time measured from the time a rod starts in motion to the time the rod reaches a fully inserted position shall not- a exceed _____ seconds for'the slowest scramable ro I (QUESTION J.03 (2.00)
,
-l State how the core diffuser system accomplishes its purpos ;
.F
. QUESTION J.04 (3.50) i List.the scram (s) which are initiated by THE REACTOR SAFETY CHANNEL l
: Incl'ude the number of channel (s) required and the scram setpoint(s),
i i
(***** CATEGORY J CONTINUED ON NEXT PAGE *****) 3 . -_ -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
-
3pc -; , . . , ,
'Ti O Gh i TdbciEEEg1E}g_OEE68IJNG_QShB89]E51gIlgg' ,
,PAGEL BL i
,
[s
,q .'
pt N../.:
,
<
..., a-
'
. >
,
,
, ,
>
,s - , v .g l ' .4
.
, un A iQbESTION'LJS05 ~(1.00)
;4 ,
:n t . .
MWhat~.are:the. components o'f the fuel.' temperature' monitor?
.
: Fu -
.
f a.? y 3 ?
" QUESTION 'iM EMr .. (2. 00 ) 1
~ '
[Demeribelthe radialLand~ axial position in the-core.where a one inch a movement of.a control" rod tip;would have the. maximum effect.'Expl~ain .
;
your: answe L
, : : QUESTION JJ.07 (1.50) l TRUE or FALS f a)bkhe' linear power Echannel providest a. control signal to the servo '
IE- : controller for_ automatic control of the regulating ro b ') ' More than1one control' rod can be withdrawn at the same tim , c). The regulating rod automatically inserts on a scram signal.
l
.<
QUESTION 'J.'08- -(2.50)g g
:A control rod drive assembly _has five switches. . What is the purpose ,
[ Cof?each. switch?; ; !- I
! ' QUESTION J.09 (3.00) ]
i ( -a) Why is the ventilation system considered an engineered safety system?
-
q
. .
!
c) In what two ways is the safety function of the the ventilation l system: actuated?' d i
~
l? i l t (***** END OF CATEGORY J *****) , i L - l. , l . d_ . '
_ _ _ _ - _ - - -- -
- - - _ _ - - ~ : ,
f[KALfEggylb@NDLING_8ND_COBE_E869MEIEBS: ,; PAGE 9
.
l
'
l , t tQUESTION. K.01 (1.50) , aWhatfisitheLlength, number', and percent U235 enrichment of'the E-fuel-rods inLthe MUTR core? "
-QUESTION.. K.02- ( 1.' 00 )
JD2 fine'"Re'ctor a Shutdown".
[ QUESTION: KLO3 (3.00) e In'accordance with MPL303, what are the licensed personnel:
" requirements to perf orm f uel': movements in the reactor pool . tank?
_
,
'
(Include. type of license, number required, and location of personnel)
-QUESTION K.04 (2.00) 14
'f
)
:What material is.used and where is it placed- to provide enhanced neutron
.. reflection axially for;the-MUTR core? QUESTION K.05 J(1.00)
.In.accordance with; Technical Specifications. fuel el'ement cladding cetross will be less than the ultimate stress if the fuel temperature-LisflessLthan _______ and the fuel-cladding i s _________c ool ed . .(f il1~-~ i n the bl anks)
L-QUESTION' K.06 (3.00) a) What are two design features of the reactor tank cooling piping that normally would limit the reduction in reactor tank level to 20 inches or less in the event there were a severe leak in the inlet or outlet piping? (2.00) 1b') What would be the minimum thickness of water shielding above the rasctor: core even after a cooling piping failure? (1.00) . l l a-
'l (***** CATEGORY K CONTINUED ON NEXT PAGE *****) :
i _ _ _ _ _ _ _ . _ _ . - ___ __
K2__E9E6_H9NQLINQ_9ND_COBE_B8BBMEIEB@ PAGE 10
'
l QUESTION K.07- (2.00) Whct are the reactivity values of the following: a) MUTR core excess reactivity? i b) Shim Rods? c) Regulating Rod? I d) Shutdown Margin with highest Worth Rod Withdrawn? QUESTION K.08 (3.00) Assume a fuel bundle is to be moved from the core to a storage areas a) what are the two purposes for the monitoring of the console instruments by the control room operator? b) how does the bridge operator assure himself that the fuel handling tool is properly latched before he moves the fuel bundle? c) What items are recorded in the Control Room Log Book after the fuel move is complete? QUESTION K.09 (1.00) What are the two purposes of the rod drop test after maintenance or replacement of a control rod? i CUESTION K.10 (2.50)
{
l How are the following TE objectives accomplished: i a) prevent criticality in stored fuel?
'
..
b) prevent attainment of unsafe temperatures in stored fuel?
!
I I
l l
!
(***** END OF CATEGORY K *****)
)
- ____ _____ __ _
- - _ --
,
'\,
11_lB901NigIB8IJyg_8BgggpUBEg3_ggNp1IJgNg_@ND_yld]I@IlgNS- PAGE 11-
" ,
<
,
.
4 14 , QUESTION : L. 01' (2.00).
' rIn compli ance wi thiMUTR ' Techni cal ~ Speci.f i cati'ons,. What four operati'ons - must : Lb@~ supervised by a licensed / senior-reactor operator? o
< ,q
!
.. i
" QUESTION ! 1 bO2 : _ '(l.00) ,
In,accordance.with MUTR Technical ~ Specifications, if a safety limit is: ! oxceeded-what~must: happen.before'the reactor operation'is resumed?
.
i i QUESTION L.0 (3.00) i ua ) How~'areEwater mass.and delta temperature measured when in the. process of conducting a heat. balance on the MUTR? b)7At-what power-level'is a heat balance normally conducted?-
. !
'
c) How is the indicated power level adjusted to agree with the measured - and calculated heat-balance?
~
' QUESTION - L .' 0 4 ' (3.00)
'What is the' approval: level required.for the fol' lowing:
.a)[Special' Experiments !
)
b)' Routine Experiments j
.c) Modified Routine Experiments I q
)
. QUESTION L.05 (1.50)
Based'on EP 404, what are three major objectives in the event there is
.a major radioactive spill?
o ll QUESTION L.06 (1.00) I [i Why is there'a specification on the maximum conductivity of the pool water? .
.
,
I l
! .
I (***** CATEGORY L CONTINUED DN NEXT PAGE *****) w _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ - ..
, , .
,u
, ---
.
..
.
.
'
?. . . ..
1Li_iBDylNISIR@lly@_P8QQEDySESt_QQNDlIlQNS_QND_61dlI@IlONS: lPAGE; 12' a
*
.
' '
s :
;
.l-QUESTION'LL'0 (3.50) <
,
'
)
o I
' 'During' reactor operation t h e.; b r i tig e; r ad i a t i on ; monitor indicates.100 1 q
mram/hr.LWhat isJthe'RO at'..the' reactor-consoleLimmediate response.-and what'
' l is the-Duty SRD's responsibilities? !
l p> QUESTION -L.08 ,2.50);
( 'i 'In the event of a civil disturbance, what three officesishould be -
notified and what two protective' actions-shculd be taken per
-
,
'
:EP14057 '
!
,
'1 QUESTION L.09 (2.50). <
!
a) ListEfour of the six categories of " Reportable Occurrences" that are l L 1 reportable per Technical Specification requirement b) Is.a reportable occurrence report required when the reactor is shutdown? i i-l l
.i i
:q i
'f i
,
i i I (***** END OF CATEGORY L *****) I (************* END OF EXAMINATION ***************) I a
. . - . .a . - - - - -
z . .. i5/s_ + p g n' ; ~',,_c
'
y- g '
. >,. . .
, ,
.
Af2BE09I982ItJE,98Y s
> '
;
.; PAGE 13 s
'itI,,
; <.' [' .
,.-.<.>.
'f' - . . - .
,l[ ANSWERSf--~~'UNIVERSI TY' OF --MARYLAND-. -87/09/08-TURNER,fR.-
~ n ,
.; p _. y
'I
<f] _
+
' ANSWER' H.01 _ (2.00) ,..
i .l1f.qPower hi story ( X en on ) ~.
' 2. M Tamp er at ur e . -
' J3. :. Exper i ments in'the' reacto .4.- - Fuel' bur nup .- 5. - Rod . l ocati o L 6.: Fuel location.- -(Any.4 0.5 each to max. 2.00) -(2.00) !
'
, , .)-
'
iREFERENCE
.: Nu c l ea r Energy - Tr aini ng, Uni ts 8,9,10 I
< ANSWER- H.02
-
(2.00)
,
'
'
-a.-23i ~6;< ; (.5.each to a' max of 2.00) . ('2. 00) ]
j, , REFERENCE: i-Basic' Nuclear-Theory & Reactor _ Operations
' ANSWER H.'03' '(3.00) _ l
!
~
L' - c ) .- crl'/cr2 ~= = ' (1-Keff2) / (1-Keff1) (.9) 1
--100/150- '(1-Keff2) / (1-0.95)
.
(.5) i 1.-Kef f 2 = 10/15'x 0.05' i Keff2 = ,0.967 (.1) (1.50)
l- -
.
, sb). Change ~in, Reactivity = (Keff2 - 1 ) '/ Ke f f 2 , .- (Keffl
'
1)/Keffi ) ..
'
=-(Keff2 -Keff1)/Keff2*Keff1 '(.9)
-
'1 l
!. =-(O.967-0.95)/0.967*0.95 (.5)
= 1.85 */. delta K/K (.1) (1.50)
REFERENCE '
- ' Nuclear Energy Training, pg 6.1-3,12.1-3
, i l
'
< ,
' '.
.L ,
-.
_ _ - _ _ _ t -
,
y $ '. ) ; n
'
( H k." R E A C T O R' T H E O R'Y
-
':PAGE ::1 .
': ANSWERS 0- ' UNIVERSITY OF MARYLAND: '-87/09/08-TURNER, R. : __
,j
-
C <
*
'I
!.. f- e
<j t- ' 1 G
l
;
:- A N S W E R '--. J H.~ 04
..
(2.50) - ,
.i-
;' Conduction through' fuel. '(Radiation.across fuel gap) .i in Conduction' transfer'from' fuel to coolan I Forced convection to heat' exchange .
l Conduction across' heat' exchanger'. tube ; Convection of cooling waterin' heat exchanger -(0.5' pts each)' '(2.50)
' -REFERENCE Introduction to-Nuclear Engineering, chapter 8;,J R Lamarsh j
iy '1 , ANSWER, H.05 (2.00). ,
. .
'I a)~ P = Po e(t/T) (0.4) !
'250.KW'= 0.'125 e(t/50) (O.4) .j inC2000] =1nte . (t/50) 3
' 7.6 = t/50 t= 380'se or 6.33Jmi (0.2) .(1.00) j b) ' Power coefficient would lengthen period (.5) and would .i eventually stabilize power. (.5) (1.00) j REFERENC . Nuclear Energy Training', Unit-6,.pg 6.3-1 ANSWE H.06 (2.00)
I
'ZrHxishifts the neutron spectrum at elevated temperature -(0.5) which . -l '. increases the.' leakage ofl slow neutrons from the fuel bearing region.4(0.5)
or (tec.r e%e hs f de acassscenq( j Doppler broadening ( . 5) which causes more absorption in the U238 'd @ ! Trononance absorption region at elevated temperature (.5) (2.00)- '! REFERENCE .j .
.SER,,p 4-4 _ 4
i i E 1
' i I e ,
:
I !
' ' -
i
.. .'-l' ) .:__ . . - _ -
'
g$i ,.,
-
- .
;[ . ;~ _ .
-
' ' - ..
. >. . t
,
H,,;;,,,6(6Q1Q6,,,THE_Q8Y,._
.
'
. :4-
>
lPAGE',15- [ NSWERS'--?UN'IVERSITY.-OF MARYLAND . ,-87/09/08-TURNER, R.-- 4
-
, il [
'
. ..c -
,
U ANSWER H.07- l(2.00) , '
, ,
7, o .
'j-
~ a)'_ S1.i ght s reducti ori,i n counti rate l('.5)Ldue'to removal-of-. '
~
_ j neutron j source ? whi ch ;was' posi ti oned near ~ detector. : ( . 5)'
.
-l
'b ) : Rnduce core --reac t i vi ty - (M5Ldde__tn_ removal--of-a-sourcel Apa t r-onC- ( ML . M _
N (2.00) d
.
3 ) g y ; REFERENCE'
-OP 103H;; Nuclear: Energy Training, Unit -11 i
ANSWER H.08 . (2.00)-
-f a)'!-No di.f f erence ~ '( .9) .because.the reactor i s below. heat range and .. ::the power coefficient'does-not: add.any negative reactivity..(.5)-
b)1 Rods would.be further withdrawn at 200 KW (.5) to compensate'for/th ) inegative.. reactivity added by the power. coefficien (.5) (2.00) 1
't
: REFERENC .. Nuclear. Energy Training,' Unit 13 I
.j -
j
'l q , ANSWER H.09 -( 1. 50 ) '
yRsactorlpower.will increase'(.'6)'due to the_ addition of cold
: water and MTC' feedbac (.9) ,(1.50)
' REFERENCE dl-OP(104, p 1- 'I
-{
t
.]
FANSWER .H.10 (1.00) ! iBata =.70/10000 = .007 ! l REFERENCE-iNuclear" Training. Manual, 5. l le; ...
.
o
'
,
. .
il p. . 4 a
, _
\
LleC_E8D198Gl[ME_M@IERL@(S_d@ND(LNG _DLSPQS@(_@ND_d@{@SDS- PAGE 16 q
.)
ANSWERSL - UNIVERSITY OF MARYLAND -87/09/08iTURNER, .- t r u n * *' -
!
I.;7.0 : .a I
-
s ANSWER, I.01 (3.00) ,
- Time (.5). Time .doubl es, dose doubles (. 5) i
)
' Distance t.5). Distance doubles, dose rate decreases by 4 (.5) 1 (inverse square law) )
.!
l 3. . Shielding (.5). Dose decreases exponentially with thickness (.5) (5.00) ;
'1
.]
REFERENCE 1 Basic Radiation Protection I J.R. Lamarsh, Introduction to Nuclear Engineering,pg 480 i ANSWER I.02 (1.50) . J Drainage from grill work at the base of the reacto '2.,
- (Two) . sinks located in the West Balcony Laboratorie . Pool overflow (.5 each) (1.50) ] ' REFERENCE j ' '3 AR , Chapter 9 ANSWER I.0 (1.00)
fi..In the fuel racks (13 positions) in the reactor pool . ( . 5) 2. In the fuel pit , north floor of reactor building.(.5) (1.00) REFERENCE MUTR SER, pg 9-1; SAR, Chapter 8 j l l
?
ANSWER I.04 (2.00)
(5 X 10E11 dps)/3.7 X 10E10 dps per Ci = 13.5 Ci (1.00)
DR~= (6 X Ci X E)/dE2 = (6 X 13.5 X .6)/25 = 1.9 R/Hr (1.00) l I
I I _--_ _a
, . . _ _ -- -. -
- - - . . - - - -
.,, _ , , .
..
~
or & * o st:Bie l
[PAGEi;1['
'
[ B@DlQA IlM@[d@l@8[Qh@_h@NQLINQ_QL@PQ$@QA9NQiS9[@RQQ: '
;g.- NSNERS -~~ UNIVERSITYf0F.'ARYLAND: .M :- 87/09 /08-TURNER, .
-l ' -. REFERENCE *
r (Glasstonep Principles of.' No:: lear Engineering pg- 545, MUTR<SP 205, pg ' l' -
~
'
,
i s a i
'
,
..
iANSWERJ I.05 -(2.00)
.e! .
"
.
' l{
Y ' la)j -. AnyjareaEinfwhich there exists' radiation at.a'. level such that a
, major. portion of'theLbodyfcould'recieve 5 mrem in one hour or.100 meemfint5 days (.5). . ] (b). : Area-of'contro11ed i access for protection of . individuals from jj : exposure to' radiation"(.5).
'
'
.
.
,
.I'
c )'. 'Any area-in whichithere exists radiation at a level such that'a'
' mayor portion ;of:~the body could receive ? 100 mrem in one- ,. hour. (.5). j i
d)-- Area in which concentrations of airborne radioactivity exceed i
amounts specified.in 10 CFR 20, Appendix-B.(.5). . .(2.00)
< 'REhERENCE~ l .10'CFR 20.,:part"20.202- . .
j
.
i ANSWERT I.06 (2.00)- ; L- : 1.'10JCFR 20Lwhole body-quarterly limit'for gamma radiation is 1250 1
. mr em ( 1.' )
'
-2.=1250/120 =-10.42 hrs stay' time (1.)- (2.00)-
!
. . -l
' REFERENCE'
i
:10 CFR 20 .
J d
! ' ANSWER I.07 ~ (3.00) J .1.tTo. prevent, internal contamination'n ( :.
2..T'o minimize exposure to external radiation ij j L3;:: To guard 'against damage to property or injury to personnel from the use s of ' radi oi sotopes. or. ra>Ji ati on produci ng equi pment . )
(1 point each) (3.00) I
< , I
:
i
-
!
.
..I
__-- - ---
, , , ;;?,7c... i ' u '
CAM , _ L .
,
p , . .m ' ,VIh ' RADIOACTIVE MATERIALS' HANDLING" DISPOSAL'AND,HR EDS' PAGE'l18 < r>
'
fANSbERS D dNIVERSITY OFLMARYLAND -87/09/06-TURNER,; ' s by , . . REFERENCE' gMUTR Procedures, EP404.- .. , ' Jt iANSWE I.08- ( 1. 50 )"- - , -
. . .. .
t ,7[ZW
<a) One on bridge..above.the. reactor-(.5 .
... .. . .. .
.
.
g r- , Ja-.One-nea r-th e-waterp uri+1 c a ti ort-system-.4. 5 ),Y yj (' *? 5*/ a
: .c) tone.near' the-reactor' room exhaust air fan J.'5P.S!Jl -(1.50) (REFERENCE- :; M U T R ; S E R ,- pg 12.2~ . 'I.09' -(1.00)
tfNSWERS
: Radioactive ' argon--is produced by'the radiation by' neutrons of'the. argon in - ' ai r ( .- 5) .- anoini trogen 16 is produced by'the radiation of oxygen'in water by -
i
'nsutron j iREFERENCE-MUTR;.SER 12.3,.SAR 8.~5 cANSWE LI .' 10 ( 3. 00 )-
m :.
'
a)LBromine, Iodine, Krypton, Xenon'(.5 each) (2.00)' b) A) 0 .100 millicuries (1.00) i,REFEREt:CE 9 MUTR FSAR 1 1 . 2 . 2 .' 1 a
* <
j i-i j
'
-i
<
t + 1 l l i 3 L - . _ _--_ _- .
-- _ - l
-
", '. , > . ,. t f.yf y 4,
.'
'
,
"'
.
,
.
7 ',
,
d2d SPECIFIC OPERATIN'G' S
'
CHARACTERISTICS -PAGE'.19 %
' .Qa 7 , .
r
/Q ANS14ERS';;--T UNIVERSITY ' OF! MARYLAND - 287/09/08-TURNER, w *.
-
,-
.
' .. .i,
, ,
,
-p 3,,.
.
y' - :l
,
'
. .m -
j@tj i
.
W:. . . .
.
.
'
,
" ANSWER: '. J . 01 ( 2. 50 ) ' ' , )
,
,
L a') The'ceilical! rod'. height.on, restart would'be high'er4(0,5) 'due.to , the increase,in Xenon'during shutdown (0.5) which.would have added-
,
negatives reactivit = b )' = . Initially, rods must'be withdrawn tofincrease. power: to.200'KW (045);
~
LAsJ Xe i s burned out f rom .i ts peak value,~ rods.must be inserted (0.5).
- Eventual l y, Xe ;-wi l'1 reach a fnii ni mum , val ue _ and will 'begin to l'ncrease
;
to its equilibrium value forjrhe; steady state power level'. At~this 4 time 7 rods will1have to be' moved out'to keepfpower constant (0.5). .. j ( 2. 50 )' i
,
REFERENCE
:lNuc1 ear .Engi neer. 'Tr ai ni ng , Pg : '10.3-1,2,3
:l LAN,5WER' JJ.02- (2.00) , '
a)J80.50 !
.b)'$3.50 - c ) M 01 '.~ 00 -
d)L on (.5 each)L (2.00) ] REFERENCE MUTR:TRIGA TS, pg. 7,B,13
-ANSWER: J.03 (2.00) l
!
[AIpump takes.a: suction.from the bottom of the pool (.5) _and. discharges through<a nozzle.above the core (.5) and causes a circulation pattern'(.5)
Lwhich'w. lows' time for the N16'to decay prior to reaching the
' pool! water:surfcce (.5). (2.00)
? REFERENCE iMUTR SAR, pg 8-4-
-!
i
. _ _ - _ _ .
_ -
-_ _ _ _ _ _ _ _ - .
Se__EPEQlElq_DEE8811NG_Od@@@QIE81EllqE PAGE 20 ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, '
,
t . ii . j, *
\
f-ANSWER ~ J.04- (3.50)
' '
Safety channel No. Required Trip Setting
/
o Reactor Power Level - two required - set at 120% of full licensed power ,
'
..
7) -ituc i CD .- ~, E $ Ec ' , f.l) Fuel Element Tem ,
-
one - Not to exceed 400 degrees C
/
[ '
/
4) Reactor Power C two - 1 css of power supply voltage /
' Detector Power Supply to chamber /
M Manual Scram T) 6lGerConio>r 2o.it enna
-
ex:E one - n/a Q[gy
*y d) Console Electrical -
one - loss of electrical power , l' Supply to the control console l 3 :i>'s;% n 2Epuucib fal 3 u Lic EW ! ' L A-25-for-each -cor_r ne t e osaI2nse4 (3.50)
/
REFERENCE ' - MUTR TRIGA TS, pg 9, /g a j 6 f L'_& (#/M MP l s ANSWER J.05 (1.00)
.
l 'The fuel temperature monitor is a meter-operated optical relay (.5)
=that derives its signal directly from a thermocouple imbedded in an instrumented fuel assembly (.5). (1.00)
\
REFERENCE \ MUTR TRIGA SER, pg 7-3
,
.'\
,
ANSWER J.06 (2.00) In the region of the highest flux (1) Normally in the center radially (.5) and the middle axially (.5) (2.00) REFERENCE Basic Reactor Theory CAF
?
I k - - _ - - - _ _ - _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ __ _ _ - _ _ _ _ _ _ _ _ _ _ __ ._ _ . _ _
_ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . 4 tu _S EE g [F lq _D EE B@l[N G _Qd@B@gIE 8 [SIlqS PAGE 21 ANSWERS'-- UNIVERSITY OF MARYLAND -87/09/08-TURNER, sl ' ANSWER J.07 (1.50) a) TRUE (.5) b) FALSE (.5)
. L1-
c) TRUE (.5) (1.50) LREFERENCE MUTR TRIGA SER, pg 4.7, & 7-1,7-2 I ANSWER J.08 (2.50) _.-
'
-
w oo
Three indications of rod position (.5 each): Up (f ully wi thdrawn) , Down (f ull y inserted) l Down position of the rod
Indicates whether magnet current is on (.5)
. Indicates whether the magnet is in contact with the rod ( . 5) (2.50)
REFERENCE MUTR SER pg 4-6,4-7 ANSWER J.09 (3.00) O5)($1f)51 a) Controls release of radioacti ve gase(s, during normal operation (.5) Prevents release during abnormal or accident condit6ns(.5).
b) 1) Emergency Manual Shutdown (from four locations in the reactor ! other locations in the reactor building (.5) s 2) All reactor scrams (1.) (3.00) REFERENCE MUTR SER pg 6-1
"
- _ __ _ _ _ -
. _ .
,
,
',
,
-,
*~a '
g, s " g ,s
;. ,. ; ,
j n
--
.
,
Nk F_QE,,(jf@N_QL_[N@,@N_Q.,COBE EQR_@t!E,T.ESQ ; 4 PAGE' l:22-
,
3.;[AhSWERS N .lONIVERSITY.OF MARYLAN
:-87/09/08-TURNER, ,
ni
'
,
*-- <
.h r u, , n a];p(lj37 _,
o y ,j 7fANSWE K.01 ..
(1.50)-
L t .. s . . .
..
.
.,
K .; Length - .9' meters-(.5) '; E' ,
.i d c~ . .> '
-.
, , . . Number ' . , 93 ~.( . 5 ) :, -
.7 Psrcent U235 enri chment : -4 20*/. (.5) ,
'(1.50)
n 1 P ERkFERENC ' MUTR 1 SER : , pg . 4-1,.4-2, . Fi g . f 4.' 1:
.
-!
ANSWEP' - K.02 '(1.00) 1 , J.Th[reac'torl i s'. i n a. shutdown condition when sufficient control rods are i
' inserted..to assure that the: reactor is subcritical by.~at least $1.00 of- .
LreactiVity ( . 5) ', ' wi th : the: f uel'.and moderator at. ambient temperature (.5).;
'
.
,
'
x
.
-(1.00):
~
+
iREFERENCE-
: MUTR TS, -: pg. 4
'
, )
\'E ANSWER .K.03: (3.00)
3One (.5) SRO (.5) on the reactor bridge (.5) (supervises the f uel move)
.OneL(.5) . RO. ( . 5) at the: reactor- consol e ( . 5) (3.00)-
UREFERENCE-MUTR'MP303,.pg 1 ANSWE ' K .' 0 4 '. '(2. 00) Graphite slugs ( 1. ) ~ p l aced -. top and bottom within the fuel rod musemb 1 y" .'( 1. ) ~. -
(2.00) ,
q
) REFERENCE
, 'MUTR .FSAR pg 4-2
-
- _m.- _ - - - - _ _ _ _ - -
_ _ _ - _ _ _ _ _ _ _ - _
'
K_ ta _Egh_d@yDL.,1,NQ_A_ND__C.,OBE _,E@B@M_ET_E,,RS PAGE 23 ANSWERS -- UNIVERSITY ~OF MARYLAND -87/09/08-TURNER, e a
\' . i s
ANSWER K.05 (1.00) 1 1000 degrees Centigrade (.5) water cooled (.5) (1.00)
.;
REFERENCE MUTR TS pg 6 _ ANSWER K.06 ( 3.' 00 ) a) 1) The pool water inlet pipe is equipped with a siphon break at the \1' surface of the pool . (1. ) 2) The pool water return (outlet) pipe i s not more than 20 inches below the overflow outlet pipe.(1.)
b) Fifteen feet (1.) (3.00) REFERENCE MUTR TS pg 18 & 19 u ANSWER K.07 (2.00) a) 1.21% dk/k ($1.73) (.5) b) $5.80 (.5) c) $2.42 (.5) d) 53.49 (.5) (2.00)
(Will accept + or - 10%)
REFERENCE UM SER pg 4-5 I ..
=
i
.
_m _ mm- - - _ _ _ . _ _ . _ _ - . . _ --._____.._._m___-_.m.-. _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _ _ _ . _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ___-_________m __ -
_-_ - - _ _ _ _ _ _ _ _ I.
! Mu__FUEy;dQNQ({GQ,QNQ,ggRE_ PARAMETERS PAGE 24 ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, "" i AN3WER K.08 (3.00) a) The purposes are to be aware of the radiation levels at the bridge (.5) and that the core power level is not rising (.5).
b) By sh'aking the' fuel handling tool to assure that it is latched onto the top handle of the fuel bundle.(.5) i c) Record the time (.5), grid and location number from which the fuel bundle was removed (.5) and the storage bin number to which the bundle was moved (.5) (3.00) REFERENCE MUTR MP 303 ANSWER K.0 (1.00) a) To demonstrate compliance with Technical Specification control rod drop time.(.5) (< 1 second)
.b) To' assure that the rod is properly aligned.(.5) (1.00)
REFERENCE MUTR TS 3.2.(1); MP 304 pg 1 ANSWER K.10 (2.50)
, a) Store in a geometrical array (.5) where the keff is less than 0.8 (.5) l for all conditions of moderation (.5) b) Store in an array which will permit sufficient natural convection (.25) in water (.25) or air (.25) so design temperature values are not exceeded (.25). (2.50) l REFERENCE MUTR TS 5.3, pg 19 & 20 l l _ _ - _ - _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ . - _ _ - _ _ _ - _ _ _ _ - . - - _ _ _
,,___- ,-----_-
;
i I i ltc_89 MIN [S1881[VE _EBQCEQU8ESt_QQNQ[IlQNS_QNQ_([M[IQI[QNS PAGE 25
ANSWERS --- UNIVERSITY OF MARYLAND -87/09/08-TURNER, j IL . . _ 1 . i
!
l~ ANSWER- L.01 (2.00) } l- - c) Fuel manipulations in the core.(.5) )
.b)- When experiments are being manipulated in the care that have an cutimated worth greater than 570p0c (.5)
i L ev .< Yi c) Rsmoval of control rod (s) (.5) ?,C Go u ps '-
" ..d)'Rrsumption of operation following an unscheduled shutdown (.5) (2.00)
REFERENCE MUTR' Technical Specifications, pg 20 & 23 l ANSWER L.02- (1.00) LTha.NRC must authorize restart. (1.0) (1.00) REFERENCE MUTR TS pg 26 ANSWER L.03 (3.00) c) The mass of the water is a constant (22,680 kg) when the pool water lovel is adjusted to the 23 foot mark.(.5) The pool temperature is j maasured with a thermister over a period of time when the reactor power is constant (.5) b) At 100 or 200 KW (1.) l c) The height of neutron detector is adjusted.(1.) (3.00) i u REFERENCE -l
'MUTR SP 202 j i
!
_ _ _ _ _ _ _ _ _ _ _ _
_ ._ -. _ . _ _ _ _
.
b.;_00dlN[
- SIS 811ME_P6QQEQQSESt _QQNQll[QNS_@NQ_(ldlI@IlQNQ PAGE 26 ]
ANSWERS --' UNIVERSITY OF. MARYLAND 5-87/09/08-TURNER, ! l,
; , , . . ,. _ ,
l> . . . .i{
, : ANSWER L.04 '(3.00)
s)oReactor' Safety Committee (.75) and the Facility Di rector ( 75) t
~
b). Duty Senior. Reactor Operator (.75).
c) Facility Director-(.75) (3.00) ,
'
i
'REFEREWCE ,5 MUTR OP 105 ANSWER L.05 (1.50)
Protect personnel ( .15 ) ; isolate spill (.5) and notify necessairy parsonnel to remedy !si tuation (.5) (Radiation Safety Officer) (1.50) REFERENCE
'MUTR EP 404, p .
i l' ANSWER L.06 (1.00) I
, Conductivity is specified to minimize the degree of fuel eldment cladding corrosion (.5) and tne subsequent consequences of dissolved 4 metals in the
'
rocctor pool (.5) (exact wording not required) (1.00) REFERENCE MUTR TS pg 11 i i ' l l t
. _ _ _ _ _ _ _ _ _ _ - .
_ _ _ .
-_ , - - _ - - _ - _ - _
N5ADMINISTRATIVEEPROCEDURESt_QQNQ{TlQNS _ANQ_L,'{M[T AT iQNS i PAGE 27'
;t ' ANSWERS --l UNIVERSITY 0F: MARYLAND -87/09/08-TURNER,- R.
o
, ..l( '
a18ifit-ANSWER' 'L.07 (3.50) T_Tho' RO : shutdowns '('. 5) and secures the reactor (.5) The SRO becomes'the acting emergency director and L i s' responsible: f or t .
.
1) placing;the reactor in a ~ saf e fshutdown condi tion (.5)
.
. .
.' .
ti 2) Terminating or minimizing releases of radioactive material (.5)
' .3)' protecting facil-ity personnel and visitors (.5).
.] i
'
d assessingiseverity'ofLthe event, and(.5)
5)anotifying the. Reactor Director (.5) (3.50) '[ REFERENCE
- . 'Emurgency Preparedness' Plan, pg 3-3 !, ,. .
ANSWER L.08 (2.50) i
!
! L a') Notify the-Division of Publi'cfSafety Office (.5)
, Lb)nNotifyfthe Reactor Director (.5)
c) . Notify the Radiation Safet.y Office (.5)
.
d)LSecure all: door- $4 rea-tor building and containment area (.5)- o'C Acti vate the i ntrusion al arm system.-( . 5)' (2.50) L . REFERENCE. _
.MUTR EP,405 lJANSWER' .L.09 (2.50)
Ka)iAny four of'the six: listed in TS 1.21.1 through 1.21.6 at .5 points inach.forLa max of 2.00 point ! b)LNo.(.5): (2.50) D n
-
'
i L L_________--_________m_____ _ >
_ _ - _ _ _ _ _ _ _ _ _ _ i
>
h _090lNigIB@l]Vg_889QgpW85}2_QQNQJIlgd@_@NQ_61DlI@Ilgd@ PAGE 28
.' ANSWERS -- UNIVERSITY OF MARYLAND -87/09/08-TURNER, '
iMS"iR REFERENCE MUTR Technical Specification 1.21.1-1.21.6 dated August 17, 1984 i
:
l l l l l
'
l l l
i l _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ - _ _ _ - _ -
_ _ __ -- _ -- __ -
,
^ , i
,
, t-
,. TEST CROSS REFERENCE PAGE 1[
'
$ESTION' VALUE-- . REFERENCE 4 g ___. ______ .-. __________ m ! H.01 2.00- TRL0000504
.
'
) ]
.j p,H.02 2.00 TRL0000505 '
H.0 .00- 'TRL0000506
-
H.0 .50 TRL0000507
'
l H.05 2.00 TRL0000508 ; i H.06 2.00 TRL0000509: ' j
' H. 07- 2.00 TRL0000510'
H . 00 - 2.00 TRLOOOO5111 H.09- '1.50 TRL0000512 H.10 1.00 TRL0000522
- ______
20.00 1.01- 3.00 TRL0000513 I
:I.02 1.50 =TRL0000514
, 'I.03 .1.00 TRL0000515' .j
'I.04 2.00 TRL0000516'.
I.05 2.00 :TRL0000517-I.06 2.00' TRL0000518: I;07 3.00 :TRL0000519 I.08 1.50 TRL0000520
. I . 09 - 1.00 TRL0000521 ,
I'.10J 3.00 TRL0000523 J ______ 20.0 J.01 2.50 TRL0000524 '
'J.02 2.00 TRL0000525 J.03 -2.00 TRL0000526 S J 04- 3.50 TRL0000527 J.0 .00' TRLOOOCS28 J.06- 2.00 'TRL0000329'
J.07 1.50- TRL000053 J.08 2.50 'TRL0000531 J.09' 3.00 ~TRL0000532
.______- y '20.00 K.01 1.50 TRL0000533 K.02' 1.00 .TRL0000534 K.03 '3.00- 'TRL0000535 'K.041 2.00 -TRLOOOO536-K.05 1.00' TRL0000537 K.06' 3.00 TRLOOOO538 K.07 ' :2. 00 TRL0000539 l K;08 _3.00 TRLOOOO540 )
, f K,0 .00 TRL0000543 ) [.K.10 ______ 2.50 .T RL.0000544 L 20.00
' L.01' 2.00 TRL0000545 i
w _ -_--
a... .y"'
- - -
x ;- .
'7,,
gg E m , t ... ,
2- . _7
-
, .
<
-
w.
i , ef,ue
.
u ,
.Oo.',',
,
..
.
q (.,
,
, . TEST:-CROSS REFERENCE'
.g.-
' PAGE-h2l
'-
=j l
- -
. ,.
.,
UESTION VALUE' -REFERENCE-g yp.;___ j_r
. . -
.
-
p 'J ' L.'Oit _______.___
-1',00 i LTRL00005461
'
,
'
,'
(
-
I g-(/[.:(L. 03I L3)00f'iTRL0000347.- . y ' % L. 04 .3.00b >TRL000054 l .L05 ' s . 1. 50 lTRL0000549: ~ L ~. 06 " 1.0 ,TRL000055 , a iL.0 :TRL0000551< \ ' 3.50i 1
>
d LT08' '.2;50'.3 TRL0000552- <-
'
3 L.09 J 2.50$ TRL2000553 D '- s
~
'9
, . d, ,
: .._ _ _ _ _ _ 4, 4 y; ' -!
@ nc
'yg;gg '
:
e: G: _ . . . _ i
, ,,
'
.'a
'
100i00l .
:), '
3 4 i
.:s
",.. T- l
'
[h . . ,
. . . ,
!
. 'y ,,1. , r y ,
'
..
.)
.-
;e
'
t
,
. , ,
.5-
l
- .,
<pf
., ( t .j .) M92 . -
- .
'
.
_ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
? 1 ..
Q ' kf]~l}(hg{Qf _3
'
Q jQ y j
~1y y by3
> :_ 1 t= *dt"x o
- v6 ic A - % g. ,
seo
'
? -tya m ,sf 9/Cf93
~ b O T>. & - +
Rodn t>6eln.
b g. oi - pd km 4 g a m dn. p).gf M k
% Pag-2/hcI . ,
l: Y 3 u [)^h~ I u t& Hcl a& L ,ea . s A '. D Z - D. K, , h h 03 ~ c. , r Um % ) 'u s h no-d 'm> %~ 6 Scoc. . Y k. o <. g A.o1 - a.o L6 M ,p 4.hLw1 c- -a gpo.M eMe o.s - S- u s- L A A cd & Ahp 1 w e. WM
.
a m a ww W ~Ad d C 8 rt' Ak mm a "L _ _ . . gi M m &. . _._.A.D4- 0 K-L y_
~ '
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ -
L
.i
, ;.
; :
, A .01 - O.K.
\ y A .0B - %S y I e M g 'uv[ w k y nA u g-- l ' 3, o \ - D. K . i i
' : 6. O 1. -- c . K' . '6 . 0 3 - c . &G Zjd , a f;, ; '
a, t.of o. K . B. or c. .O b ~ O. !( , ; c.at - wr JE mJn m
& Ka- p'f N ~ e a ms%' a d )
6 Ava +6 2.9o kW M fou~
% s. k b,4 A % k l - u y 4: ~ T DA bVid J+f~ A . ;
C . D 2. - O. d . I c . o 't - C.;> ?Ml kW m fny a0kw N %A
+ as 1"1 a 'W is . C of - o, K .
LC .o S - 0 Mr M Mk r eg n o - n - 4 , - - - _ _ - _ _ _ _ _ _ _ _
.
.
c.oe - FSd q n nd
,e++dl fro bI ' - +%W'/% o. (a (), M-4, +d c . o, ~ ce . AA at ap ./ Jsw W. v.p c.us - ca. 2 s JJ & , Q fd
)
'
M
'
+ %es .&d
/ L') .
.
'
o Ii['y
// 2
./
~
5j' j /2f Yd
.,i
'"'#^3[\.f+
trrc Q) . g M.
L p.ot - e Mhw h A4c A M4 4 a a A e J.
' s emb A
'
D.ot - % ,6 A .
% %hdk k
g4n g Am & z d M< %acx ' A
,
L q ~ av mLn ~ d~E% &a . t _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
" , .
g
'g \
vnr C"I-w _w kll sw d' ' df \ '
(,,~ k k acI L
& m & L eS . Pm %s <alp $n
<tak % t~o d I d e u . .
(p . c LO . o n .
~
b.oK - 0. 4 . 3 h am wa ptR
& N & J & & % o f g .@ ~
9.07 - ue o -
,
cel.; fL;f'[ n eV - 4 d e+ L t : off - N.7. % p[ = on l b.Ob - p, K . D.o1 - L.oy % q m &k X % Rssi m d cevat4e% . k h, nE Me cIc M A b d A /te d p W - at n
%
rv-en g s f nyi .
~f
'
'
w .ot - FM S d, 2 &
- 1:1
.
9 f #79 s am [Fv . i
. .
-
_ a__-_____-__--__-_-_____ . _ _ _ - _ _ _ _-- _____-__-__ _ ___ _ _ _ _ _ _ _ - . _ , - _ . _ -- --
- - - -
q I . a i l' ,
'1 .
l
X .0 i 7 p. K . ';
-
;
'
y , c 2. - p . g. . l
E.D3- o; K . 'l E , o W - bp $1 dp ' c4w-9 W
^' M cu - .A & dn (~ t~id 1 n GPL coar + .p o w D cm n .
l 3. or - p w ,w a a,s sA2
% J hs~42c) h- % 0 3 l c. o c. - g L.mf % e NT ( 4Ad, ~
,
%
M ndky0' h 6
-
cy j +W Amy .
. S. e , - '
o.<.
'
y. o \ ' ~ , _T' . D t - O. d . J, o 3 - O. .e*- .#+3 4
'
8 . _ V.of - - . _ _ . _ V. 0 4 - . 0 . _
,
_ . _ _ _ _ _ _ _ _ _ _ _ _
~ ~- ! ,. _T1 , .
i-l E.;', 4 ,-
. k- , .'y- . -c, , o g -- : p. K ,
, >1
' G.0L -
0. M . L
' '
l: 4. ,O
'
3 - ' [ O.K . _ TG.:o) - o. k;. G . o s' ~ oK- i
' '
G..O -
* :(a d y mi- Pt g ,
t.. o1 - . ' G O2 -- Lc. o ,-
*v-TL pn oJn J m k Jo d .,
*
* r am m4h i ,r i
_ _ . . _ _ _ _ _ _ . _ _ _ _ _ _
::L . ,.. - - - a 8 hk.D l e M i
14 . 0 1 - 0. A M MM . N Md k x s es (JJ ? l-l . o 3 - a t N. C 4 ' rV W & 1 % a ef I0 6i AV%~ n 4 mL/c.h e l 4' lk . O T ' .M 4.O G ' N o ~s . 's % y -Lo 4mm m Y~M ~ My d-4.07 - 5 d .o S - O. K . 14. m - e R .w s o
-
g I.ot -
+ p.<. ~.L . o 3 - 4 ] . O '4 - N 1 . D 5' - -#
m - , . , - - - ---,.,----zm - -
,s, .. g , :.,
I.DG +
. .07 - c. l 1 08 - p ; - 1 . o Cf ' - -
y j
-M M
'
I.lo- 4). TLew w & '{ , , . N (M . < .
' .I
'f t.
L 7, ot - +- ; 4. o z .N
. T. o 3 - W-Z.bn- -1 E. o 5' ~ - Idu k m g. YD $ r n b. ce2I j wk'W gt - II hld .W %M M % av A' s en&&A :
1e7A A% , .
1 J. 04 - -# l I A. o 1 ~ t _ 'T. 0 8 - + J. cet - 6. t( .
-._
g. . _
~ --
_ _ _ _ _ _ _
_ _ - _ - . . _ _ _ _ _ _ _ _ _ _ _
. O . .
K pI - d. k . - p 7 AO -
/
. k.D1 ~ O <. o3 - o. k . ! (,o9 - t . K. o S - 0. V .
< . _ . .
"
K. o 7 - 4 K.03 - 4 K.Ot- 0.K . K.io - o,<. ' L.o t - o. K .
-
L . t) t - e.K, t 07 - -y
.
L . ot - . o .K . L . 05 - c. K . . _ L. o G - N _ _
.
L . 07 - 0. K .
. _ . . - . _ . - _ - , . _ _ _ . . . . . . ~ . . _
.. , i G 3
.- ' , -L.08 -
A c>, k h[ A :c A -4 xuss S,
'
J4m%_ MMM $ . e s-[ & f -l
> ~ n! Vo->fa ra a 6
'
%, . d: D .
an 1
.
>
>
L.09 - + i i __ ! l l
- - - -
i I
. .. .
n e=
'-
m _ _:11 _ _
- . _ _ _ . _ - . e b Attachment 4 NRC Response to Facility Comments The Facility Comments on the written R0 and SRO examinations given on September 8; 1987 are part of this exam report as Attachment 3. This response addresses those comments where a response was requested as indicated by the "R" in front of specific questions of Attachment R0 Written Examination: A.04 b Same as H.07 on SRO Examination Full credit (one point) will be given for a decrease in or reduction of reactivity respons A 08 One half point for either a delayed neutron or a fuel temperature change respons C.01 Same as J.01 on SR0 Examination The question is based on the training material submitted and is applicable to reactor operation. The fact that very little xenon is generated in the MUTR will be considered during grading, C,05 The fact that the cooling and or diffuser pump operation will enhance core cooling will be considered during gradin D.02 Same as J.08 on SRO examination The question will be deleted from this examination. Section value total will be appropriately adjuste D.05 Answer will be modified to the following response: Up Light on l Contact Light off Down Light off l l Magnet Current Light on (.375 points each) { l Section total value and question value will be appropriately adjusted.
! l L- --
r , i' ' i
-
.( s 1 <
,
t, 9 2 '
&a cchment 4 0.07-The intent of the question was to solicit the coraplete nuds ar instrumentation provided at the MUTR. Wiil accept for full credit either p m rumentation system that provides full range coverage, i.e., log w rcent power; instrumentation or Wide Range Linear CI '
E.05 This question will be deleted from this examination as training material did not address this information. The section value will be appropriately l adjusted, i l E 01 Same as J.04 on SRO Examination i The answer'.las modified based on informatio6 gained at the facility so th n a ' listing of five of the systems that initiate scrams including number required and setpoints will be adequate for full credit, . .e. , .7 points per system.
l (Also includes systems not listed in TS page 9) E.06 Double-door system will be an-acceptable alternate answer for full credit of one poin G.06 Same as I.08 on SR0 Examination Full credit will be given if only the monitors in service are liste G.09 Full credit will be given for " secure the reactor" respons SRO Written Examination: H.06 Will accept " decrease in fission cross-section" as an alternate response corresponding tc increase in leakag H.07 Full credit will be given for a decrease or reduction of reactivity respons I.08 Full credit will be given if only the monitors in service are liste Training material did not indicate the water room monitor was not in servic y
-
-
,. ,
.,
o ! o .
.j
- 4 .- 3 Attachment 4
'
! i ! J.08 , i i This question will be deleted from this examination. .Section value total will ' be appropriately change !
!
Questions noted as being the same as those addressed for'the'R0 Examination ! l will be treated in the same manner as the R0 resolutio i l
!
!
I o i l I
!
{'
'!
!
, !
!
i i t i
!
!
<
l
)
?
i i
:
i f l
/ l
. ___-_ _ _ a
}}