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Examination Rept on Senior Operator License Issued for TMI-2.Written Examination & 18 Encl.Operating Test Administered 770920
	ML19220B472
Person / Time
Site:	Crane
Issue date:	10/17/1977
From:	Collins P; Office of Nuclear Reactor Regulation
To:	; METROPOLITAN EDISON CO.
References
	NUDOCS 7904260267
	Download: ML19220B472 (66)
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C551CN R:/CCR CFERATCR LIOSE Elt'ES.CICli Facility Three U1e Isl ard - JJnit 2 Reactor Type _rx:. n ', y Date Ad.tinistered c//7 /77 Exr.iner J. J. Surv

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IC2 0 Ir.structicns to 'gplicant: Use separate paper for the ars.<ers, s:sple cuestica sheet Feints for each questica are en tcp cf the ars.er sheets. An everall indicated in parenthesis af ter the questien. sc re of 70% or greater is passing. Categc:y 1 ef 4plicant's % of Valte To:21 Score Cat. Value_ 14 13.5 ll,4 k[ A. Principles of Reactor Operatien 14 13.5 id,9 lb 3. Features of Facility Design 17 16 \\ I, '( bT C. General Operatin5-Characte:istics a 16 15 19 7 71 D. Instrxents and Controls 16 15 IU.7 2 E. 5-fety and E.mergency Syste=s Q 16 15 I #.0 $I F. Standard and E.mergencf Cperatin; Frocedures i O.3 7.

c. Radiatica Centrol and Safe:y 13 12 m

1C6 0/Q v Final Grade 4 'jg.y-x, e)- -- J ,a N ~ A. PU.'.C'PLES 'F REACTCR CPERATICri (14) A. 1. a) 4 hat is maant by the tem " delayed neutron fraction"? (1.0) b) Mcw and why does the delayed neutron fraction change during core lifet;me? (1.5) A. 2. The D1I procedure for approach to criticality requires the operating staff to p!ct a one over M (1/M) during red withdrawal. a) What data is required for the 1/M pict? (0.5) b) How is the data utilized? f;c ta: a sketch may be used as cart of ycur answer. (1.5) A. 3. Assume ycur reactor is)cn a stable. 3 CFM star uc rate as ccuer level reacnes 2 x 10-' cn :ne intermediate range monitor. (Time is "0"). a) Plot the trace on Figure Al until the pcwer level reaches 10-c. ('. 5) b) After a two-minute "hcid" to take data at '.0-8 the operatar withdraws the control rods ta obtain a 1 DFM startup rate. Plot this trace for 5 minutes;. include the period of rod action. Exclain any change ( during the five minutes. (1. 5 ) c) Assume the reactor was at 10-6 at 3 minutes on figure Al and a reactor trip occurred. Plot and discuss the resulting trace for the remaining pericd of time on figure A1. (1. 0 ) A. 4 Xenon condicians include periods when xencn is at equilibrium and at peak conditions. a) What is meant by etuilibrium xenen? (1. 0 ) b) Mcw dces,:eak xenon develop? (1.5) c) Assume a plant startup and pcwer escallation is in progress at the time of peak xenen. Mcw does this differ fece a pcwer escallation after a one-week shutdown? Note: a sketch may be used as car: of ycur answer. It is not necessary to include values for xencn. (1. 5 ) A. 5. Water is used as a coolant in your reactor. List three otner functicns of water in the reacter. (1.5) Y S ' (( 1 G - -.. ) 2 T e 3 ~ B. FEATURES OF F CILITY DESIGN (14) 5. 1. The nuclear services ci sed c;oling wa:er (15CCW) system provides c:aling water for the nuclear c:mpcnents during normal c:eraticn and also provides cooling for ::mocnents during a loss of coolant accident. a) List those c mpcnents which use the NSCCW durina normal oceration. Listthecompcnents(i)!nsideand(ii)Cutside the reacter building. (2.5) b) What c;mponents are supplied during a LCCA? Note: if.. ccmpenents appear in part A, mark them with an asterisk *. (1.0) 3. 2. Condensate and feedwater are heated in a number of heat exchanges before water enters the steam generators. Sketch a one-line diagram of the c:mbined systems frcm the condenser until it leaves the last heat exchanger. Include all pumps and scurce of heat for each heat exchanger for cne string. (2.5) 3. 3. The fire protecticn system at your facility consists of a numter of pumps located in unit one and two. The fire main supplies a number of hydrants, hosereel staticns, a wet pipe sprinkler and a deluge system. a) List all pumps which supply the fire main; include cacacity and when each pump will start. (2.0) b) Exclain the difference between the wet pipe sprinkler and the deluge water systems. (1.0) 3. 4 One of the components associated with the reacter coolant system is 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 the reasons for these limits. (1.5) c) If the drain tank level is too high, ahere may the ccerat rs discharge the excess li:uid? (0.5) 3. 5. Cne of the Limits and preventions require that systems containing liquids should be free of air before they are opera ed to prevent water hancer. a) What is water hamrer and why shculd plant 0;erator. be concerned a: cut aater hammer? (1.0) b) Oces water nemmer occur only with systems : ntaining licuid and air? Exclain your answer. (1.0) 4N. u9 9 r,

a. g y

3 ~ C. SENERAL CpERAT!NG CHARACTERISTICS (17) C. 1. The once-througn steam generaters (OT5G) a ycur facility will pecduce sucerheated steam during power operation. a) With the aid of a simale sketch, explain hcw superheat is acccmplished in the OTSG. (1. 5 ) b) Mcu dces superheat vary from 15 to 100% pcwer? A sketch may be used as cart of ycur answer. (1.0) C. 2. The folicwing are two of the limitations and precauticns in the ~ Unit Startup precedure. provide the value and reason for each of the limitations. a) Do not attemot to s art a reactor coolant pump when ocwer is greater tnan (2.0) b) Curing startuc and shutd:.,n when reactor scwer is less than percent, the UTSG water level shall be maintained ce: ween and (2.0) C. 3. Unless s:ecified by the reactor engineer, group 3 (ApSR) will be positiened about 32% withdrann prior to an apprcacn to criticality. a) With the aid of a sketch, indicate hcw the ApSRs worth varies between 0 - 1C0% withdrawn. (Include approximate reactivity values) (1. 5 ) b) Explain when it is necessary to move the ApSRs (i) in and (ii) cut. (2.0) C. 4 Tao of the limits and precautions for the control rod drives concern the gas concentratien in the RCS and the cooling water to the mechanism. a) What.are the scurces of gas in the R.C.S.? (1.0 ) b) Why is gas c:ncantraticn a factor for the CRCMs? (1.0) c) Is it necessary to maintain a minimum concentration of gas in the RCS during pcwer Operaticn? Explain ycur answer. (1.0) d) The temperature of ccoling water to tne CRCM may vary frca 35 - IC5cF. Is there a preferred temperature range? Expl a i n. (1.0 ) C. 5. Assume rated pcwer c:nditiens and a trio cccurs to a reac ar cociant ;umo. a) Er0 Vide the initial steady state values f:r Carameters listec in figure C5. (1.0) b) Show the res:cnse ta :nese :arameters until conditions stabi'ize. assure ne reac:Or dces nc ri ?. (2.0) i b. t.21. 9 =e - - - -... = - .sm.,, .m= a -=*u m p 1 I 1 /}g' ' tie

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't 7. ' C I'*.n n " $ p 7 0. s /%w l. }. i 6. 4 3 1. - lw.J.. '4' 1 w tw .wat ( wj D. 1. Refer to ne transient in questien C.5. Discuss :he acticn of the centrol systam(s) fcr each cf the folicwing parameters: a) Load MWe (1.5) b) Pressuri:er level (1.5) c) Feecwater ficw A & 3 (2. 0) D. 2. The intermediate channel utilizes a ccmpensated icn chamber'(CIC).

3) With the aid of a simple sketch, explain the ccerating principle of a CIC.

(1.0) b) Is ccm;ensaticn required at 100%, 15%, or icwer pcwer levels 3 Explain ycur answer. (1.0) o,., 1 ::,n 3< N u~psssen a r as 'r i ~' u c

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c) {a.,

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the " overlap" requirements between the other channels? Explain.

(1.0) D. 3. The pretsurizer electrcratic relief value (RC-2) may be Operated in the manual or autcratic mcde. Discuss hcw the valve may be operated in eacn mode. A simple sketch may be used as part of your answer. (2.0) .,r ui S 5' ' C D. 4 Unit 2 of TMI utilizes a bcron fced and bleed [ controller, a) What are the input signals to the controller? (1.0) b) What are the cutput signals of the controller? (1.5) c) Jhen is the controllar utilized? (0,5) D. 5. Tao of the alarms en the Diamcnd Centrol panel are the (i) motor rctaticn fault and the (ii) asyrretric rcnitcr. a) Discuss the ;urpose of each alarm. (1.5) t) What immecla:e acticn is required by the operating staff for each alarm? (1.5) lW~319 d } = E. SAFETY AND E."ERGENCY SYSTEMS (15) E. 1. The ;cwer distributicn system a: E!!-2 :entains two CC buses, 2-lCC and 2-2CC. a) Use a cne-line diagram to shcw what ccmponents sucaly these busses and their source (s) of ;cwer. Include any cross ties between these cusses and supplies. (2.0) b) If a station blackout occurs, what leads are supplied by the D.C. bus until the emergency diesel generatcrs begin to Jupply pcwer? (1. 5 ) E. 2. List the ccnditiuns that will cause a reac:cr trip with fcur R.C. pumps in service. Include presen set points. (2.5) E. 3. Assume a less of ccolant accident (LCCA) occurs. The LCCA increases reactor buildic.g cressure at 2pS!/ minute and dcubles eacn minute (2, 4, a, etc.). d:li::e this rate far the foiicwing: a) 'ihat autcmatic action (s) occur during the first four minutes? (1.0) b) What ;nstruments will the operator cbserve to assure initial and continu'ng operaticn of ecuipment? (2.5) c) What is the postulated peak reactor building pressure in the design basis LOCA? (0.5) E. 4. Three Mile Island Unit 2 is provided with a feedwater latching system. a) List the instrumentation asscciated with this system and exclain tne logic that will actuace the system. (1.5) b) List the au cmatic action that will occur when this system is actuated. Assume rated pcwer operation. (2.0) E. 5. Assume a primary to seccndary leak develcos in one of the OTSG. The leak begins at ene 3F.l4 and dcubles every j, minutes (1, 2, A, 3, etc.) a) List the systems that will alert tne coerator. Attemot to arrange :nem in Order of increasing leak rate. (1. 0)

5) When the operators have identified the leaking OTSG, should they trio the reacter er begin an orderly shutdcwn? Explain the reason for your answer.

(1.5) 78 3'do " " ' ~

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..em 2 ) .y W F. STANDARD AND E"EcGENCY ope:ATING ::CCOSES (15) F. l. Assume your unit is at the pcwer level cutof# ceint and waiting to meet the requirements before increasing pcwer. All systems are in autcmatic. A malfuncticn occurs in the circulating water systam and vacuum begins to decrease at I" Hg/ min. a) What is the power level cutoff ;cirt and when may pcwer be increased above this level? (1.5) b) Mcw will the ICS respond as vacuum decreases? (1.0) c) What immediate action is required by the ocerator (assume vacuum continues to decrease)? (1.0) d) List the heat sink (s) available if ccrrective action can not restore vacuum. (1.0) F. 2. Cne of the Limits and Precautions of the Cecay Heat /Injecticn Pumps states "When ocerating in the E5 mode with suctio.1 c-the building sump, pumo discharge must be throtled to GFri to limit runcut. Do not throttle belcw GFfi as this may result in cavitation and inadecuate ccoling." a) What are the abcve ficw rates? (0,5) b) What is pump runcut and what are the consequences if the pump continues to ccerate in this condition? (1.5) c) What is cavitation and hcw would the operator observe this condition on the D.H./ Injection pumps? (1. 5 ) F. 3. During reactor startup, limits are imposed en the amount of reactivity which may be added above and belcw the estimated critical positicn.

3) 'ihat 'are these limits and hcw dces the c;eratcr convert them to red position? Assume an ECP of 50% cn Gecup 5/7.

(1.5) b) What acticn(s) are required if nese limits are exceeced? (1.5) F. t. In the event of a reactcr trip, list the manual actions required by the TMI-2 emergency peccedure. (3.0) F. 5. In the event of an unanticipated criticality: a) What symctens wculd alert -. e cperating staff? O.0) b) What immediate acticn is recuired cy the ccerator? (1.0) M 321 e N -w ww -. k __}

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.s ~ G. RADIATICN CCNTRCL AND SAFETY (13) 3. 1. Assume jou have been.4crking in a contaminated area. After you remove your protective clothing ycu reni:cr yourself before leaving the area. a) Should an icnization or GM device te used? Expl a in. (1.0) b) What type of radiaticn will the instrument detect? (0.7) c) What is the criteria for determining if a persen is.contamina:ed? (0.8) G. 2. After working in area for two hours, you discover your dosimeter is off scale and ycu leave the area. A survey indicates a hot sect on a drain line reads i200 cr/hr gammc a: twc feet. Your dis:ance from

ne line was abcut five feet.

a) Estimate the dose which you may have received. (1.5) b) If ycur previous exposure to the quarter was 9CO mr, what exposure limits may have been exceeded? (1.0) c) With the aid of a simple sketch, explain the operating princ.icle of a pcc<et dosimeter. (1.0) G. 3. Three of the classified areas in the Radiation Protection Manual at Ril are (i) centrolled area (ii) radiation area and (iii) high radiation area, a) Define each ?rea; include any limits. (1.5) b) May the NRC examiner enter each area? Explain ycur answer. -(1. 0 ) G. 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 rules a; ply? (2.0) G. 5. Curing a refueling cutage you are in the reactor building on the main fuel handling bridge. A spent fuel element drops into the core. a) What instrumenta icn will aler: :ne perscnnel in the reactor building of any release of fisaicn products? (1.0) b) dhat automa:ic acticn(s) may occur i' radiatien levele eed preset limits? (1 0) c) What ac: cns are recuired by the con:rci -ccm staf#? (0.5) 4 fd M2

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ML19220B472

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