ML20058Q305
| ML20058Q305 | |
| Person / Time | |
|---|---|
| Site: | Neely Research Reactor |
| Issue date: | 07/24/1990 |
| From: | Casto C, Curtis Rapp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058Q304 | List: |
| References | |
| 50-160-OL-90-02, 50-160-OL-90-2, NUDOCS 9008220028 | |
| Download: ML20058Q305 (38) | |
Text
{{#Wiki_filter:^ 'l UNITED STATES ~ ja* R8?p4'o, . c. NUCLEAR REGULATORY COMMISslON p ~[ . REGION 11 -g' 101 MARIETTA STREET,N.W. ' ATLANTA,GEORot A 30323 (*****/ ENCLOSURE I a EXAMINATION REPORT 1 -Facility Licensee: Georgia Instituts of Technology' Neeley Nuclear Research' Center " 900 Atlantic Drive, N. W. Atlant6, GA 30332-0425 Facility Docket No.:. 50-160 . Facility License No.: R-97 + An examination was ' administered'at the Region II office in Atlanta, Georgia. Chief Examiner: / beM a, # //7 V/96 ^ Curtis W. Rapp / Date Signed . Approved By:
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f Charles A. Casto, Chief ~Date Signed t Operator. Licensing Section 2 . Summary: - 7 An examination was administered on May 7, 1990. A written-re-examination was administered to.one R0 applicant who did not pass. I i 4 5 1 n. V
p x f o is l t REPORT DETAILS 1. Facility Employees Contacted: R. 'Karam, Directorf-Neeley Nuclear Research Center. l 2. Examiners:
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Rapp M. Morgan;
- Chief Examiner 3.
Exit Meeting: At the conclusion:of the examination, the examiners provided R.. Karam with a copy of the-examination and-answer key for review. No comments were made by the facility following this review. t tThe written examination was also pre-reviewed by R. Karem at the Region 11 office. Few changes to the written examination.were required because of i this pre-review.- ( The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.- ? i 1 l. A
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(***** CATEGORY A CONTINUED ON NEXT PAGE *****). j, w _ lik.U-M_i Yg _Q'lS; ? - - !' \\ 'y "l &XP' W 4 2 f d&n'.,Mp+t& R . h W$$f;ty - JV-a 22:w& p+%p e "?.c Vn m peg ..ne-- h ) k( j ' [-, s f N '-- [ i. . m my? E~$.V sd$h:~_L .m' ' l I..{p xe_x m y' O-- i 's i ~ ' l y,
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!i. U.; PRINCIPLES'OFiREACTOR.0PERATION. .P ag e ' 4 A p 07 4.. i; ' ANSWER: .004._(i.00) 'a)
REFERENCE:
Reactor Operator Training Chap 10 GUEST 10N: 005 (1.00) Which one of the f ollowing correc tly describes the order of heat transfer' from the-fuel to the bulk-coolant'? a) Convection, Radiation, Conduction ' b ). Rad ia tior), Conduction, Convection 'c ) - Conduction, Convection, Radiation d) Conduction,. Radiation, Convection ANSWER: DOS (1.00) d )-
REFERENCE:
Reactor Operator Training Chap li (***** CATEGORY A CONTINUED ON NEXT PAGE *****) 0, ' ' )
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A. PRINCIPLES'OF REACTOR OPERATION Page 6 l-OUESTION: 007 (1.00) Whic h one o't the following is NOT a function of installed neutron sources? a) Provide en initial neutron population to start the fission p r oc es t.. b) Provide reliable source of neutrons during an approach to critical. c) Provide a visible indication to the operator the neutron instrumentation is f unctioning pr operly. d) Provide.* means for the operator to see changes in neutron flux as reactor conditions change. ANSWER 007 (1.00) a)
REFERENCE:
Ra - Operator Training Chap 10. GUEST 10N: 000 (1.00) Which one of the following factors has the LEAST effect on rod worth? a) Number and location of adjacent control rode b) Temperature of the moderator c) Temperature of the fuel d) Core age (**44* CATEGORY A CONTINUED ON NEX7 FAGE 4****)
y y 4,y-m y ny-y .;r-pp -mp .+ .r ~7, s.c ~ PRINCIPLES OF REACTOR OPERAT. ION) l' age E7. l, { 's <} ANSWERS.- 000; - ( 1. 00 ). 8 ge c)- .{.. (i - J
REFERENCE:
h, 4: . Reactor Operator TrainingfChap 10 y ;-. r,i f C ^ QUESTION: '009l.(1.00) o ,y P 'Which-one of'the.fol. low 3ng is-the maximum reactivity worth of'an-'unsecuredM L experiment:-in'accordance with' Procedure 3101, Definition of Experiment ~~ Categories?. 'T, Q q. ' a ') : 'O.0025 delta,k/k 'y
- t b) 0.00.4' delta k/k t) 0.015.idelta.h/k
-0~.01'I elta k/h d) d .a n
- ANSWER 009. (1.00) b)'
y
REFERENCE:
Procedure 3101' R L (***** CATEGORY A CONTINUED ON NEXT PAGE *****) f du, ' J
'A-PRINCIPLES OF REACTOR OPERATION Pg O i3 I QUESTION: 010 (1.00) Mhich one of the following corrr'ctly explains why an DVERCOMPENSATED lon l chamber detector will have a lower indicated count rate? a) Fewer neutrons are counted b) Fewer gammas are counted c) Fewt+r betas are counted d) Fewer alphas are counted s { ANCWER: 010 (1.00) n a)
REFERENCE:
tb l Reactor Operator Training Chap 14 f I-l QUESTION: L111 (1.00) Which one of the following is most affected by the regulating control rod? a) Fast Fission Factor b)
- rmal Utilization Factor
[- c) Thermai Non-Leckage Probability d) Renonance Escape Probability ANSWER: 011 (1.00) b) (***** CATEGORY A CONTINUED ON NEXT PAGE *****) y. f-e
PRINCIPL ES OF REACTDR OPE ~ff ION P 9 l REFERENCEt Reactor Operator Training Chap 10 GUESTION: 012 (1.00) During a reactor startup, equal reactivity additions are made. The source range count rate is allowed to stabill:e after each addition. Which one of the following correctly describes the response of the r,ource range to each reactivity addition? e) The change in stable count rate im larger and the time to stabilire 15. Shorter, b) 1 he change in stable count rate is larger and the time to stabilire is lonp' c) The change in st ale count rate in smaller and the time to stabill:n in shorter. d) The change in stable count rate Js smaller and the time to stabill e is longer, ANSWER: 012 (1.00) d)
REFERENCE:
Reactor Operator Training Chap 10 (***84 CATEGORY A CONTINUED ON NEXT PAGE *****) -o
my r l PRINCIPLES OF REAC10R OPERE. TION Pg 1 j r { 1. ] t.j .g GUEST 10N 013 (1.C0) j \\ Which one of the.following correctly explains why failure to replace the f 4 graphite plugs in idle experimental facilities could result in a sudden l f? addit 2on of positive reactivity? Ik ~ I a) Decreases moderator void volume t ( b) Decreasen moderator density h 1 jb c) Decreases moderator temperature ] d) Decreases moderator level i 5 ,f ' [ c o h j 1 rl-t ANSWER: 013 (1.00) j 1 r i I e a) i i V 1 [.
REFERENCE:
I [k - GAR 2.3 pg 11 r i l ( F i i \\ DUESTION: 014 (1.50) I j State-the five (5) parametern crucial to reactor safety for 5 MW operation. \\ b o l f.tJSWER: 014 (1.50) I I .(0.bD cacht I 1)' Reactor power L
- 2) Reactor period
.i 3)'D2D temperature f
- 4) D20 flow f) D20 level i
h I RETERENCE: p [ S$R 2.3 pg 12 p I (****4 CATEGORY A CONTINUED ON NEXT PAGE
- 4**)
-, r s.
) t.a PRINCIPLES OF REACTOR OPERATION P g-11 4 1 -- r, 9 QUESTION: 01S (1.00) Which one of the following is the design pressure t the reactor vesse)? a) S psig b)- .7 psig -c) .9 psig d) 12 psig 'd ANSWER: 015 (1.00) c)
REFERENCE:
SAR Table 2.1 pg 8 ll OUESTION: 016 (1.00) Which one of the following-is the reason graphite is inctalled around tho reactor 7 a)' Provide reduced neutron leakage b) Provide additional moderation ~ (- 'l c) Provide reduced gamma radiation i d) Provide heat sink during emergency conditions 1 ANSWER: 016 (1.00)
- I
.4 l i (i**** CATEGORY A CONTINUED ON NEXT PAGE *****) i l a
p. ) PRINCIPLES.OF REACTOR OPERAT!ON P g~ 12 )
REFERENCE:
SAR 2.1 pg 2 1 i f OUESTION: 017 (1.00) State the pu" pose of the thermal shield. l ANSWER: 017 (.1.00) Reduce heating (0.50)(of the concrete portions) of the biological shield I (0.50). l
REFERENCE:
l GAR 4.4.5 pg 55 l l QUESTION: 018- (2.00) State all penetrations cealed by a building isolation signal. I ANSWER: 010 (2.00) 1 l (0.50) each l l
- 1) building ventilation inlet
- 2) building ventilation outlet
- 3) pneumatic irradiation facility remote terminals
{
- 4) building vacuum line l
REFERENCE:
,f SAR 4.3.2 pg 40 l I I i i (***** CATEGORY A CONTINLIED ON NEXT PAGE *****)
s -,)i A.- PRINCIPLES OF REACTOR OPERATION Pg 13 i l QUESTION: 019 (1.00) Which'one of the following is the radioisotope of concern if air'is. allowed into the reactor? a) N-16 b) .0-16 c) Ar-41 l' d) H-3 .j { ANSWER: 019 (1.00) J c)
REFERENCE:
BAR B.5.4 pg 157 f DUESTION '020 (1.00) Which one of the following will result in a DECREASE in regulating control rod worth? l. .b I a) Withdrawal of all safety-shim blades b) Insertion of regulating control rod c) Decrease in moderator temperature d) Increase in void percent .j ( ( ANSWER: 020 (1.00) l t d) l t I (***** CATEGORY A CONTINUED ON NEXT PAGE
- 4*)
) "J
.y, yg 'pi [ . PRINCIPLES OF REACTOR OPERfTION P9 14 (r; ~
REFERENCE:
Reactor Operator Traitiirig Chap 12 l 1 E 1 l { t i { t 1 I t (
- }
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- 1a113to completely',closi during automatic. operation ~.
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4 me t J. 1 m 1 + m-1 L.. 'y;Q y-p;p y "' ' QUESTION: 002- (1.00). .. = v. s :n. s man <+ v x~ %a. JState;theJthreen(3) factional. caused by;theiBloymedical%Facil.itygemergencys ( + @ <intop1pushbuttonlinfectordan'ce!withlProcedure 3105)LBio-medicaliFacilit @X.!"d &' 7 ) ,n 1 $. tOperation.. ,. a,a n: m am ,o i
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- 2).l De-energizen : the. : timer
%, Wg?k!q i' ' II)]StopsJmoving'the door l--(andtled esli'tianjis)J 4 ,m o a ~ ' '
- 3) Closes,the'collimator' w w@$
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- 4)
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\\ \\ i 1f D, FEATURES OF FACILITY DEGIGN P I l OLIEST ION : 003 (1.00) l An experiment is inserted into the reactor using Horizontal beam Port H4. r l The regulating rod ine.urts four (4) inchen to compennate for the increase l in reactor power. Which one of the following 15 the correct reactor operator action? l a) Place the Automatic Reactor Power Control System in manual l b) Wi t hd r r.w regulating four (4) inches l l c) Immediate1,' remove the experiment I f l' d) Shut down the reatter l l l ANGWER: 003 (1.00) l d) l l l
REFERENCE:
-{ Procedure 3103 l l l l i l i ] (44*** CATEGDRY D CONTINLIED UN NEXT PAGE *****) e a i
(t-i-
- A A
D; FEETUREC OF F AC it.I TY DESI. N P~g 1 k GUEST 10N: 004 (2.50) ( tia tc h the procedural limits in Column A with the value in Column B. Column A Column D 4 a) The maximum angle between highest
- 1) 30 second and lowttct blade positions may be l
exceeded for special tests if
- 2) 20 second l
reactor power is less than b) With less than deviation,
- 3) 50 kw place the mode colector switch to
' AUTO'.
- 4) 10%
k e) When changing power do not go below a period except for
- 5) 5%
specially written and approved tests, j
- 6) 3%
l d) When changing power in the automatic l modn, do not exceed a __ deviation
- 7) $ degrees on the servo deviation meter.
G) 7 anches t n) 9eive shim blades in until the bank l position is or less at which ( ti me the clutchen may be deenergized. i l ANSWER: 004 (2,50) l l. (0.50) each: a) 3 i b) 6 + l C) 2 d) S y e) 7 f l 1
REFERENCE:
l Procedure 2000 r j ) i (44**$ CATEGORY D CONTINUED ON NEXT PAGE
- )
--a-~
) l D FEATURES OF FACILITY DELIGN Pg 18 QUESTION: 005 (3.00) Define the following terrns in accordance with Procedure 2001,-Two Operator 7 Operations. a) Ofir> ra tor b) Senior Operator c) Reactor Shutdown } l I ANSWER: 005 (3.00) l a) Any individual who manipulatus the con trols of the facility f i l b) Any individual licensed by the NRC to direct the licensed activities t of licensed operatorn { l. f c) The nhim-naf ety bladen are fully inserted and the control rod power 1s) L l off.
REFERENCE:
Procedure 2001 1 i QUESTION: 006 (1.00) l< State the correct response if the ECCS override switch is pressed when the 1 spray block valves are closed. i l ANSWER: 006 (1.00) The remctor isolation valvec (0.50) will open (0.50). i i i I (**$$$ CATEGORY B CONTINUED ON NEXT PAGE *$$4*) k.;
3 k D. FCATURES OF' FACILITY' DESIGN Pg 19f I ( e i \\
REFERENCE:
Procedure 2160 QUESTION: 007 (1.00) Which once of the f ollowing is the rninimum length of time a CO2 purge of the pneumatic tube transport system must be perforrnted if a purge was NOT .) performed prior to reactor startup? a) 5 minutes b) 10 minutes c) 15 minuten d) 20 minuten ANSWER: 007 (1.00) c)
REFERENCE:
Procedure 3104 l l QUESTION: 000 (1.00) .in accordance with Procedure S000, Objec tives and Code for Emergency Procedures, state the basis for opening the drain valves.if f l u >t is not decreasing. -ANSWER: 000 (1.00) Remove (upper) reflector ($4*** CATEGORY B CONTINUED UN NEXT PAGE *****) -l
NNElM$h!$hDk M%'..i... ~ y. ' +,*~r b # c %!N),P E.W N' f N ~ ihign %yi4%p @nm$yi;: % '. # ! %. u n 6, L '"f'" $r = w w ' < gfC.' l yel u ^> A:nMMW DN FEATUFEDJ OFJ FACILITYL DE31GN;" < ?" %.zP M 2SL W Dn
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3', igm 1 b). -~ ,.,, 7 .2)j[ Low,D20 Flow M Delay,,[7 %dA9ini = saf etyi system ;. net work l,9 m 3: ( M9s /? \\ ~ ' Insure' adequate; reactor core v O m s. J' h!$j '.c cooling :ati all? timen 4 i3h i MagnetCA.ctuatorMmp1Tflerh wNA c % w. w ~ ..a e y 3 q s r_. . e s4 <m q%u o$s !c)3. Protect lagainst arloss.ofLcoolant? E4 V, Low (Ion; ChambernVoltage Q-q , n. 1 m :- e. _nm t _.g. p ~.. , (,7,$ " d )5 Linsure:adequatefheat'removalifrom> '5)'=ReacternTank, Low $ s.evel, p kF ifrom/th.eaD20.1 system,i Reactor,il501aticrh alVeN Yi ..., -. s o# @dv a.ngg.p, ' 1 -4); e
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we, FE TURES OF FACILITY DE 1GN Pg 21 QUESTION 010 (1.00) Which one of the iallowing in the correct classification of an accessible area with a radiation level of 150 mR/hr in accordance with the Radiation Safety Manual? a) Controlled Area b) Radiation Area c) High Radiation Area d) Airborne Radioactivity Area ANSWER: 010 (2.00) c)
REFERENCE:
Radiation Gaf ety Manual l GUESTION: 011 (1.00) List two (2) DIRECT indications available to the operator to verify the shim-nafety blades have scrammed. ANSWER: Oli (1.00) l. Any two (2) at (0.50) each Ghlm blade down light Position indication of shim blade Indication of deenergdmed clutch (***** CATEGORY ft CONllNUED ON NEXT PAGE *****)
~~ B.- FEATURES'OF FACILITY DESIGN P 22 }
REFERENCE:
SAR pages 50-52 l OUESTION: 012 (1.00) used to attuate a containment building Stato three- (3) channels that can be i r.ol a ti on in accordance with Proceduro 7220, Containment Building Isolationj) { Tust. t l ANSWER: 012 (1.50) l Any three (3) at (0.50) each l_ Kanne Chamber MAP-1 j Gas Monitor } l Filter Bank Monitor j l D20 Leak i l l
REFERENCE:
t Procedure 7220 f I QUESTION: 013 (1.50) Technical Specification 3.1.d requires each shim-safety blade withdrawn above full insertion be positioned no that free fall of the blade will i result in a reactor scram. State the basis of th2s Technical Specification requirement. .t i ANSWER 013 (1.50) Aboures 'the chi #n blade pansing through its normal insertion limit (0.50) toJ l a position which results in a positive reactivity addition (0.50) will cause a negative period scram by the first 100 of insertion (0.50). l (***** CATEGORY B CONTINUED ON NEXT PAGE *****) l ~ 6
w .) +- r i 3 q B: FEATURES OF FACILITY DESIGN P19: 23 , REFERENCES-t. Technical' Specification 3.1 l OUESTION: 014 '(1.00) State thu ono (1) exception when instrument "As Found" measurements'.are NOT, required in accordance'with Procedure,9059,'"As Found" Calibration Check. . ANSWER: 034 (1.00)' When.the instrumtentfin taken from the Out'of Service shelf-
REFERENCE:
Procedure 9059 c ll ]' GUESTION: 015 (2,50) l In accordance with Proceduro 9306, Preparation & Maintenance of RWPsh state five (S). specific activities that req" ire the'unu of,an'RWP.. is ANSWER ' 015 (2.50) )
- 1
[ (0.DO) eath: i')1 Entry into a high radiation area 1 2)-Entry;into an airborne radiation area i
- 3) Modification biological nhielding around.the reactor f
- 4) Penetration of any port hole in tho biological' chield b
5)' Entry into the hot call l 6).Manipuistion (raising and lowering) of sources it, thefhot cell O
- 7) Entry into a contaminated area where removable contamination of D0,000:
ff, dpm/100 tm2 in present th i f t: b (**$$* CATEGORY B CONTINUED ON NEXT PAGE
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..Q, ~~ r R, d;. .t e s D: lFE'TURES OF. FACILITY DESIGN P 91 24- .. i, e + r
REFERENCE:
l> [a/ Proceduro 9306 y,.,.
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- ANSWER s : '.- 00AM(1!.00)l
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~1 W '% TQUEST10NiE00211(1-.00); r o .. e ; -+ = p 1 u m ' W Which oneToffhhe71ollowingsallowsc forimaintenance cM cordtanthador[mkAU6th vn s sa r [e, y: i / 7 % 'ileveFd #inginohmalkoperations?~ g M ',s f _ T % I ~ . ~...I(([.s ~ s, -. b h.I* '~ .M4 4 q;./ i;I [ . s w.-. - ) 43, ,r-, ' m' 2 .. - (;., ,g g-s a m., > 20 ; s s _ a)M yThrottlingethe reactor _'dumpf11oefdischargcRyalvertoithei @ j ' ',*, -g D K.W 9,# iM. >m V ystorago Ltank-1 w my j< :g < w v ,g g, m 9 s 1.. e E, v a.l v. e j, 4; M = ; g<.. 4 2 - yt - 3., 4 34 ~ . b.)". -zThrottli,ng.the main circulating:pbmp;dischprg. P m.L ,3 s vs q ;.e.., s c, .g 4 Q - c ); Additional water supp19 to'theEmainicircul'ating7pumpffrcim[theky x g y l ,t y!( @ Ty
- reactori return s and ? purification ' pumpfdisic harge ' ; '
.x 'k l '. ~i g ) ...I 3 e' A ? ~ C~ 1 gg w; y; . d )T 'C'onsfantimak'e'up from7T D2 by gr~aOity?dr'ain- .-7
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- V**-)'~
, n .,~ + h; Q_y y;-A : g' . y. A r S N@Q% l Ni((s: ', ' A 4.. m. g y
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- C-GENERAL OPER TING' CHARACTERISTICS P ge 26' ANSWER:
002 (1.00) c)
REFERENCE:
5AR pg 70 l hj l 1 l [ QUCSTION: 003 (1.00) l. Which one of the f ollowarig will enuse the Automatic Reactor Power Control l System to swi tch to manual control mod e"? } a) Servo deviation greater than S% b) Ert or voltoge greater than 10% l c) Reactor period less than 20 secondu l' d) Regulating rod speed greater than 0.2 inches per second i l ANSWER: 003 (1.00) 1 l-b) t 1
REFERENCE:
.SAR pg 69 ii -DUESTION: 004 (1.00) State the method available for isolating TD-2 1ollowing a lous'of electrical power and no need for emergency cooling exists. i, s .l (***** CATEGORY C CONTINUED ON NEXT PAGE *****) i m__
wy -m OENERAL DPERATING EHARACTERISTIES P 27 ANSWER: 004 (1.00) Manually close the locked-open stop valve
REFERENCE:
SAR pg 01 QUESTION: 005 (1.00) Which one of the following in the correct response of the regulating control rod to a loss of electrical power 7 a) Remain at current position b) Drive in at ma>timum speed c) The automatic control system will switch to manual d) The magnetic clutch will deenergire and ucram the control rod ANSWER: ODS ( 1. 41 0 ) a )-
REFERENCE:
SAR pg 137 QUESTION: 006 (1.50) Technical Specification 3.6.c requiren all grid por,itions contain fuel elements, grid plugs, or experimental facilities for operation in the forced convection mode. State the basis for this Technical Specification ( requirement. 4 i (***** CATEGDRY C CONTINtJED ON NEXT PAGE
- )
- C.
GENERAL OPERATING CHARACTERISTICS Page 20 o ANSWER: 006 (1.50) Prevent the degradation of calculated flow rates (0.50) due to bypesruing the active fueled region (0.50) through an unoccupied grid plate location (0.50).
REFERENCE:
Technicel Specification 3.6 GUEST 10N: 007 (1.00) Whic h ont, of the following conditions is an interloth that will prevent r t?ac tor startup? a) Outcide Automatic Controller Servo Range i b) Low Helium Flow c) Lew Chield Coolant Flow I d) Law D20 Temperature ANSWER: 007 (1.00) c)
REFERENCE:
) i 1 SAR Table 4.3 DUESTION: 000 (1.00) In accordance with Procedure 2004, Shift Supervisor Startup Approval, state : the one (1) condition when the low D20 flow channel is not required during a reactor startup, i (***4* CATEGORY C CONTINUED ON NEXT PAGE *****) j i
C GENERAL OPERATING CHARACTER 1GTICS' P ge 29 ANSWER: 008 (1.00) Natural convection (circulation) operations
REFERENCE:
Procedure 2004 OUESTION: 009 (1.00) In accordance with Procedure 2015, Reactor Power Calibration, state the allowable range between indicated reactor power and calculated heat balance which may result in adjuotment of the power trip and picommmeter channels. ANSWER: 009 (1.00) >2%-but <=6.5% l'
REFERENCE:
Procedure 2015 l-l- l I QUESTION: 010 (2.00) l 1 t [- Match the nuclear instrument in Column A to its full range in Column D. l Column A Column B l a). Fission chamber detectors
- 1) ikw to St1H i
b) mirco-micro ammeter channels
- 2) Ikw to IMw l
c) log-N amplifier channels
- 3) Iw to SMw d) power level trip channele
- 4) iw tc 1kw
.) S) Critical to SMw i
- 6) Startup to critical (14***
CATEGORY C CONTINUED ON NEXT PAGE *****) 1 W ) _ 9J h-
,q 4 e1 10ENERAL' OPERATING CHARACTERIS11CS 'P~_ 30. ~ 5 ' ANSWER: ~010 (2.00)
- ANSWER-(0.50) each a) 6' b) S c) 3 p
d) 1
REFERENCE:
j;p SAR 4.4.7'.1.pg.66 lr 1; I . QUESTIONS Oli '(1.00) , l 1.. Which one of the following are the signals which initiate a " fast" scram:of 1 'al l' f our,. ( 4 ) safety-shim blades? 1 a)- power and D20 13ow b) D20 flow and D20 temperature c) 'puried'and D20 level ~ d )- power and period l' g 1 1 ANSWER - 011 (1.00) i r. d) a REFERENCES-L [ .SAR 4.4.7.2 pg 67-DUESTION: 012. (1.00) A'.Iow D20 flow scram condition in detected lectronic scram circuit 1 only. State how safety-shim blades.for ele. nic scram circuit 2.are -scrammed. I (44*** CATEGORY C CONTINUED ON NEXT PAGE *****) O L i
m } C. GENERAL OPERATING CHARACTERISTICS Pg 31 ANSWER: 012 (1.00) I 11y the elettromechanical circuit l-
REFERENCE:
SAR 4.4.7.2 pg 67 1 l l l' GUESTION: 013 (1.00) Wh.ich one of the following in the r>econdary emergency coolant supply to the emergency coolant storage tank? l a) T-D1 I b) Deionized H2O system c) Storage Pool d) City water -l k 1 ANSWER: 0.13 (1.00) l l_ d)- l~
REFERENCE:
t GAR 4.4.G.3 pg Di QUESTION: 014 (1.00) l State the reason exhaust air for the Reactor Ventilation System is drawn y primarily from around the upper reactor face. ANSWER: 014 (1.00) Remove any gaseous and particulate radioactivity 'j (***** CATEGORY C CONTINUED ON NEXT PAGE *****) e fke-mm-. . - ~. 1
e,,p 0F v r GENERAL' OPERATING CHARACTER ETICS P D 32 s 1
REFERENCE:
a' s SAR-4.4.9.5 pg G6 GUESTION :015 (1.00), Which one of the following is the reason both sections of the secondary-cooling towers must.be operated? t1 a). Prevent, overheating of the primary coolant b) -Prevent necondary cooling pump cavitation c) Prevent flooding of the sections d) Prevent' heat exchanger vibration ' ANSWER: 015 (1.00) c)
REFERENCE:
. Procedure 2200 DLIECT ION : 016 (1.00) l -1 I'1' excessive meinture.-lu observed _from the gas separator during operation of the Gas Recombiner System valve 214 may.be closed.. Ftate=the effect of= 1 closing this valve. . I r i l . ANSWER: 016 (1.00) i Gas:binnket withdrawn only from D20 storage tank l REFERENCEt Procedure 8400' (***1t CATEGORY C CONTINUED ON NEXT PAGE ***** ). L e
@yes s' o i f-r . P ~ g ; ; 33 ; .e GENERAL OPE ~LATING CHARACTERISTICS - k; _ .9-o_kp ifi Q ;, f, ',, / ,0UESTION: 017- (1.00)' n 1 E State the concern associated with operating the Secondary Cooling System 11; -cooling tower water temperature is low.
- k o
[ g ANSWER: 017-(1 00)_ 1 Freezing'of-D20 y
REFERENCE:
,j Procedure 8300 j '0UESTION:s010 ~ ( 1. 00 ) -Jn.accordance with Procedure 2160,I Emergency Core Cooling =SystemK stateithe? two.(2)' conditions which require the use of epent funi pool'as the supply. 3' to ECCS. y JANSWERt. 018 (1.00)'- v s = City water, pressure (0.25) < 21 psig (0.25)- City water flow (0.25)~< G gpm (0.25). s,
REFERENCE:
} Procedure,2160 .u n } .:t;_ .,' f - --'i ,n: 1 A j r ) 'I E, ~ "(***** CATEGORY C CONTINLIED ON NEXT PAGE $****) o a m.' s i) Aba. u_-21
.w
- cCi,1 GENERAL OPERATING CHARACTERISTICS-
.Page 34 L gj>::,-* }+ L ^ OUESTIONs.019 (1;00) Which one of the-following is.used to monitor D20 purity:in-the. W,,
- Purification System?
.a) salinity cell b) pH cell c) = conductivity cell d) particulate cell e. AN9WER: 019 (1.00) c)
REFERENCE:
GAR.4.4'.9.3 pg 83 OUESTION: 020 (1.00) Which one of the following detector types is used to generate the period ( ceram? a) lon chamber- .b) scintillation detector y ; c) BF-3 detector =d) GM tube .g. o ANSWER 020 .(l'.00). < ia ) (***** CATEGORY C CONTINUED ON NEXT PAGE *****)
7. l ,,'. " C, GENER L' OPERATING CHARACTERIST1CS
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~ J. ll l6 L
REFERENCE:
~ Pr.i c e. fj f E N l r i I h t ): !:) -i ~ i s f ': I -l r I'**** END OF CATEGORY C.*****) (****- /*** END OF EXAMINATION
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