examination rept on operator license issued for tmi-2
TRANSCRIPT
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. NRC FC AM 157 v.S. NUCLE A6 43U tCENSE APPL;ED A-(10-75)
RO SRO C,
URRENTLY A LICENSEC CPER ATOR HERE7
gEXAMIN ATION REPORT yEs C NO
i APor ir s o''t N AME REACTCR LOCATICN
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WRITTEN EXAMINATION
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CPER ATING AND ORAL EX AulN ATION SUT,iARY R EPORT
EV aLa AT1CN11an SRC a:cucant <s .r at stactory at t"e SRO Levet, comorere :he RC ccAur n to evaluate wencant's
'' ' Ewe:axv at :*e R C Levet. NuveER
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ansar s '.ocicev r* worses are erotaoned.
1. CPER ATING CEYCNSTR ATICNs
)1.1 P14tartvo and instrument Checus
1.2 Conscie Cceration
h '' e/ i@ga. Vaniowatrcns,
b. Undentanding
2. FAC:LITY ECUtPVENT
a. Vaior _
b. Au xii.ary._
Eagmeered Sak . rds Svstemsc.
3. INSTRL"C ';T A . ' CN_
(3 %c| ear s
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b. Process
4. REACTCR PROTECTICN
5. PRCCECUR ES
a. N o r m.a t
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c. c me rge ncy
6 RE ACTIVITY E F E ECTS (Exce t Conscie Operetron)
7. ACMINISTR ADVE RECUIREVENTS
8. EVERG ENCY PL.AN
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U. S. NLC.EA?. FIGLurRY C2?SSSICN-
FIACICR CPERATCR LICSE EIOC.WICN,
/Facility Three Mile Isl a"d _ Uni: ?
Reactcr Type ;';p - ;$d
*aDate Adninisteret. _ , ; /77
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Exriner .J. J. Su:v
ApplicanI 'l s V
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Instruc:icns to Anplicant:
Use separate paper for the answers; staple questien sheetPoin:s for each questica areen tcp of the r.sser sheets. An everallindicated in parenc:vsis after the questien.score of 70% cr greater is passing.
Categ:ry 1 of Applicant's % of
Value _ Total _ Score _ _Ca+.. Value
14 13.5 ! ),9 h1 A. Principles of Reactor Cperatien_ m
/s'O 1.j 3. Features of Facility tesign14 13.5 ,.
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I 1,9 kL C. Ceneral Cperating Ciaracteristics_
17 16
16 15 I 3, '( E0 D. Instnnents and Centmis
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10 1:
/ l. #1 F. Standard and Energency Operating16 _ 15 Procedures
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A. PRI6CIPLES OF REACTCR OPERAT!g (14)4
A. 1. a) 'What is meant by the ter "delaye neutrcn fraction"? (1.0)
b) How and why does the delayed neutrcn fraction change duringccre lifetime? (1.5)
A. 2. The Dil procedure for approach to criticality requires theoperating staff to plot a cne over F. (1/M) during red withdrawal.
a) 'What data is required 'cr the 1/M plot?, _
(0.5) -
b) how is the data utili:ed? " ate: a sketch may be used ascart of your answer. (1.5)
A. 3. Assume ycur reactor is On a stable. 3 CPM startuo rate as pcwerlevel reaches 2 x 10-8I on the interteciate range cnitor.(Time is "0").
a) Plot the trace on Figure Al ur.til the pcwer level reaches10-d. (1.5)
b) After a two-minute " hold" to take data at 10-8 the operatorwithdraws the control rods to obtain a 1 CPM startup rate.Plot this trace for 5 minutes; inciude the period of rod
,motion. Explain any changes during the five minutes. (1.5)
c) Assume the reactor was at 10-6 at 3 minutes on figure Aland a reacter trip occurred. Plot and discuss the result ngi
tr3ce for the remaining period of time en figure A1. (1.0)
A. 4 Xenon conditions include periods when xenon is at ecuilibriumand at peak conditions.
a) 'What is meant by equilibrium xenen? (1.0)
b) Mcw dces peak xenon deveico? (1.5)
c) Assume a plant startup anu power escallation is in progressat the time of pe6k xencn. Mcw does this differ frca aocwer escallation after a one-aeek shutdcwn? Note: asketch may be used as part of your answer. It is notnecessary to include values for xenen. (1.5)
A. 5. Water is used as a ccolant in your reacter. List three otheifuncticns of water in the reactor. (1.5)
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3. FE?TlRESOFFACILIT' DESIGN (la)*
B. 1. The nuclaar ser, ices closec cooling aater (NSCCN) system cr; idesccoling water for the nuclear campenents during normal cperaticnand also provides ccoling for ccmpcnents during a loss of coolantaccident,
a) List those components which use the NSCCW durino normaloperation. List the components (i) Inside and (ii) Cutsidethe reactor building. (2.5)
b) What ccmpenents are supplied during a LOCA? Note: . if ..
compcnents appear in part A, mark them wit! an asterisk *. (1.0)
E. 2. Ccndensate and feedwater ar2 heated in a number of heat exchangesbefore wate- enters the steam generators. Sketch a one-linediagram of the combined systems from the condenser until itleaves the last heat exchanger. Include all pumas and scurceof heat for each heat exchancer for one stranc. (2.5)
B. 3. The fire protection system at your facility consists of a numberof pumps located in unit cne and two. The fire main supplies anumber of hydrants, hosereel stations, a wet pipe sprinkler and adeluge systen..
a) List all pumps which supply the fire main; include cacacityand when each pump will start. (2.0)
b) Explain the difference between the wet pipe sprinkler and thedeluge water systems. (1.0)
B. 4 Cne of the ccmocnents associated with the reactor coolant systemis the R. C. drain tank.
a) List the equipment which discharges to the drain tanks. (1.0)
b) What limits apply to the tank? Include tne reascns for theselimits. (1.5)
c) If the drain tank le/el is tcc high, where may the operatcrsdiscnarge the excess liquid? (0.5).
E. 5. Cne of the Limits and Preventions require that systems ccntainingliquids shculd be free of air before they are ogerated to preventwater hammer.
:) ahat is water hammer and why shculd plant coerators beconcerned about wc''r hammer? (i.0)
b) Oces water harrer cccur only aith systems containing licuidand air? Explain your answer. (1.0)
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C. GENEM L OPERATING CPARACTERISTICS (17)
C. 1. The ence-through steam generators (OTSG) at your facility willprocuce superheated steam curing pcwer 0:eration.
a) With the aid of a simple sketch, explain hcw superheat isaccceplished in the OTSG. (1.5)
b) Hati does su;erheat vary frca 15 to 100% power? A sketch maybe used as cart of your answer. (1.0)
C. 2. The following are two of the limitations and precautions in the -
Unit Startup procedure. Provide the value and reason for each ofthe limitations,
a) Co not attempt to start a reactor coolant pump when ;ower isgreater than (2.0).
b) During startuo and shutdown when reactor power is less thanpercent, the OTSG water level shall be maintained
between and (2.0).
C. 3. Unless scecified by the reactor engineer, group 8 (APSR) will bepositioned about 32% withdrawn prior to an appr.cach to criticality,
a) With the aid of a sketch, indicate how the APSRs worth varies' between 0 1CO*, withdrawn. (Include approximate reactivity
values) (1.5)
b) Explain when it is necessary to move the APSRs (i) in and(ii) out. (2.0)
C. 4 Two of the limits and precauticns for the control rod drivesc:ncern the gas concentration in the RCS and the cooling water tothe mechanism.
a) 'What are the sources of gas in the R.C.S.? (1,0 )
b) Why is gas concentratien a fact:r for t.5 CRCMs? (1.0).
c) Is it nc:essary to :aintain a minir.cn concentration of gas inthe RCS during pcwer operatient -x;iain your answer. (1.0)
d) The tem;erature of ccoling water to the CRCM may vary frem25 - IC5cF. Is there a preferred temperature range? Expl a i n. (1.0)
C. 5. Assume rated ;cwer conditicns and a trip cc:urs to a react:rcoolant cump,
a) Previce the initial steady state values for parameters listecin figure CS. (1,0)
b) Shcw the res:cnse to inese :arameters until canditicns stacil!:e.Assume the reactor dces no cria- (2.3)
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J. I'iSiEME:iTS AND 1 TROL (16)
2. 1. Refer to the transient in cuestion C.5. Discuss -he acticn ofthe control system (s) for each cf the folicwing parameters:
a) Load MWe (1.5)
b) Pressurizer level (1.5)
c) Feedwater ficw A & 3 (2.0)
D. 2. TL.e intermediate channel utilizes a ccmpensated icn chamber'(CIC)..
a) With the aid of a simple sketch, explain the operating principleof a CIC. (1.0)
b) Is ccacensation required at iC0%,15%, or icwer power levels?.Explain vcur answer. (1.0)dbnye ti huyw:s% /esuliine><ecebyC' A n 4
c) Car :: p: rat 4w.. ...c.,e the ", overlap" requirements between theother channels? Explain. (1.0)
D. 3. The pressurizer electrcmati; celiet value (RC-2) may be operated inthe manual or autcratic mcde. Discuss how the. valve may be operatedin eacn moce. A simple sketch may be used as part of your answer. (2.0)
(c.u . u : 1D. 4 Unit 2 of E4I utilizes a bcron feed and bleed' controller,
a) What are the input signals to the centroller? (1.0 )
b) What are the cutput signals of the centroller? (1.5)
c) When is the centroller utilized? (0,5)
D. 5. Two of the alarms on the Diamond Control panel are the (i) motorrotation fault and the (ii) asymmetric moniter.
a) Discuss the purpose of each alarm. (1.5)
b) What immediate action is required by the ccerating staff foreach alarm? (1.5)
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E. SAFETY A:;0 E."E:GE ICY SYSTEMS (16)
E. 1. The power distribution system at T!!!-2 contains two DC buses,2-lCC and 2-20C.
a) Use a one-line diagram to show what ccmcenents sucoly thesebusses and their source (s) of pcwer. Include any cross tiesbetween these busses and supplies. (2.0)
b) If a station blackout occurs, what Icads are supplied by theD.C. bus until the emergency diesel generators begic tc supply -
pcwer? (1.5)
E. 2. List the conditions that will cause a reactor trin with four R.C.pumps in service. Include present set points. (2.5)
E. 3. Assume a less of coolant accident (LCCA) cccurs. The LOCA increasesreactor building cressure at 2.:SUninute and doubles each minuce(2, 4, 3, etc.). Utill:e this rate fcr tne fclicwing:
a) What autcmatic action (s) occur during the first fcur minutes? (1.0)
b) What instruments will the operatcr obsarve to assure initialand continuing operation of equipment? (2.5)
c) What is the postulated peak reactor building pressure in thedesign basis LOCA? (0.5)
E. 4. Three Mile Island Unit 2 is prcvided with a feedwater latchingsystem.
a) List the instrumentation associated with this system and explainthe icgic that will actuate the system. (1.5)
b) List the autcmatic action that will occur when this system isactuated. Assume rated pcwer cperation. (2.0)
ssume a primary to secondary leak develocs in cne of the OTSG. The. :.
leak begins at one GFM and dcubles every 5_ minutes (1, 2, 4, 3, etc.)
a) List the systems that will alert the aceratcr. At.emot coarrarge them in order of increasing leak rate. (1.0)
b) When the operators have identified the leaking GT5G, should theytrip the reactor or begin an cederly shutdcwn? Explain thereascn for your answer. (1.5)
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F. STAbARD A 40 E'!ERGE ICY CPERAT: ,G ?CCECURES (16)
F. l. Assume ycur unit is at the pcwer level cutoff point and waitingOc meet the requirements before increasing power. All systemsare in autcmatic. A malfunction cccurs in the circulating watersystem and vacuum begins tc decrease at 1" Fg/ min.
a) What is the pcwer level cutoff point and when may pcuar beincreased above this level? (1.5)
b) How will the ICS respcnd as vacuum decreases? . _ (1.0) -
c) What immediate acticn is required by the cperator (assumevacuum continues to decrease)? (1.0)
d) List the heat sink (s) available if corrective action can notrestore vacuum. (1.0)
F. 2. Cne of the Limits and Precauticns of the Decay Heat / Injection Fumps- states "When operating in the E5 mode with suction en the building
sump, pump discharge must be throtied to GFM to limit runcut.Oc not throttle below GP!1 as this may result in cavitation andinadequate cooling."
a) What are the abcve ficw rates? (0.5)
b) What is pump runcut and what are the consequences if the pumpcontinues tc cperate :n this condition? (1. 5 )
c) What is cavitation and how would the operator obse ve thisccndition on the D.H./ Injection pumps? (1.5)
F. 3. Curing reactor startup, limits are imposed cn the amcunt ofreactivity which may be added acc.e and below the estimated criticalpositien,
a) What 'are these limits and hcw does the operatcr convert enemto rod position? Assume an ECF of 50% cn 3rcup 6/7. (1.5)
b) What action (s) are required if these limits are exceeded? (1.5)
F. 4 In the event of a reacter trip, list the manual actions required bythe TMI-2 emergency procedure. (3.0)
F. 5. :n the eva t of an unanticipated criticality:
a) -45a symctens wculd alert the operating staff? (1.0)
b) What immediate acticn is recuired by the cceratce? (1.0)
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3. PADI'ATION CCNTROL AND SAFETY (13),
G. 1. Assume you have been working in a contamina:ed area. After y:uremove your pr:tective clothing you mcnitor yourself beforeleaving the area.
a) Should an ionization or GM device be used? Expl a i n. (1.0)
b) What type of radiation will the instrument detect? (0.7)
c) What is the criteria for determining if a persen is. contaminated? (0.8) -
G. 2. After working in area for two hcurs, you discover your dosimeter isoff scale and ycu leave the area. A survey indicates a hot sect ena drain line reads 1200 mr/hr gamma at two feet. Ycur cistance frcmthe line was abcut five feet.
a) Estimate the dose which ycu may have received. (1.5)
b) If your previous exposure to the quarter was 900 mr, what exposurelimits may have been exceeded? (1.0)
c) With the aid of a imple sketch, explain the operating principleof a pocket dosimeter. (1.0)
G. 3. Three of the classified are: in the Radiation Protection Manual atTMI are (i) controlled area (ii) radiation area and (iii) highradiation area,
a) Define each area; include any limits. (1. 5 )
b) May the NRC examiner enter each area? Explain your answer. (1.0)
3. 4 In the event of a radicactive spill, one of the basic rules is to. administer aid to anycne who is injured. What other basic rulesapply? (2.0)
G. 5. During a refueling cu: age you are in the reacter building cn themain fuel handling bridge. A spent fuel element drops into thecore.
a) What instrumentation will aler: the personnel in the reactorbuilding of any release of fissicn pecducts? (1.0)
b) What autcmatic action (s) may cccur if radiation levels exceedpreset limits? (1.0)
c) What acticns are required by tne c:n:rol rcca staff? (0.5)
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TW1e 1. u.IS"I'.l.A iECUS 10 CFR 20 Appendix B f- .
T.ble 1 1 ble II~
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Ener ,y Col 1 Cai II Cat 1 Cul IIjeFE7 per A ir Vater : Air Water
sta t e.-i si - alf-life disinteerstien ac/nl u e /-J. ue/-'' ue/1 |'
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ap o fu 2 a s76 /de '
m& emee- ac7 m clykk -
b[ 2 2r, 7e e a'c M !eewq
f a A-[B)s/L ,a v ;= soa fees_ n y au c nt& c/e b Iora /m Ama f & y ec
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/6oc/%~ = 6 c%) + q_ C@ + 1 g%%L%~ = Goo &(Pb Qwh@b
O 00 69 f , 00 /*ggee .
S ea me = 6069
/E~OL!,
O =dcae U 2X~ u"** 4 "9
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ccn e =
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I.O ??11 3h- |i;? !!g2
e ?ii g=2nI.I L =
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1.25 1.4__ 'li I.6l
+ 6" >
+ %' //p||? , N// &+X//h~,''(; 'I ''S h'
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1.0 :f a ?H33 n22- r
a g u==
b ga gg2.0y| L "=..
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' l.0 if M M$ $ EM
i u [f UM' M
l.25 1.4 :| 1.611
4 6" >
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