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Examination Rept on Senior Operator License Issued for TMI-2.Written Examination -18 Encl.Operating Test Administered 780606
	ML19220B451
Person / Time
Site:	Crane
Issue date:	06/13/1978
From:	Collins P; Office of Nuclear Reactor Regulation
To:	; METROPOLITAN EDISON CO.
References
	NUDOCS 7904260146
	Download: ML19220B451 (97)
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U. S. NUC.EG REGJLAIRY C2 tCSSICN RSACTCR CPERATCR LICENSS EQC.WICN Facility Three Mile Island - U,it 2 Reactor Type ow _ ow Date Ad.v.inistered of n /77 Ex=iner _ J. J. Bu rv Applicant Il N Instn:cticns to. applicant:

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Principles of Reactor Cperatien 14 13.5.l_ A. 14 13.5 II. ( $1 B. Features of Facility Design n 17 16 l 'l. 7 \\_ C. Gen'.ral Cperating C aracteristics I 16 15 14.l Y) D. Instr =ents and Centrols 16 15 l 9. (~ Cl[ E. Safen s'.d E+ergency Syste.5 St,andard and S::er2ency Operating 16 15 lU.3 k#1 F. rroce;ures 11.0 b G. Radiatien Centrol and Safety 13 12 106 ,\\ Final Grcae e - ,,,,) 1%< ~ ~,,

..=_---._-=m.. 2, ,-~ 'A. PRINCIPLES OF REACTCR OPERATICN (14) A. 1. a) What is meant by the term " delayed neutron fraction"? (1.0) b) Mcw and why dces the delayed neutren fraction change during care lifetime? (1.5) A. 2. The TMI procedure for apprcach to criticality requires the operating staff to plot a one over M (1/M) during red withdrawal. a) What data is required for the 1/M plot? (0.5) b) How is the. data utilized? Note: a sketch may be usea as cart of your answer. (1.5) A. 3. Assume ycur reacter is)cn a stabla.S OPM startuo rate as power level reaches 2 x 10-' cn the intermeciate range monitor. (Time is "0"). a) Plot the trace en Figure Al untii the power level reaches 10-0 (1. 5 ) b) After a two-minute " hold" to take data at 10-8 the acerator withdraws the control rods to obtain a 1 OPM startup rate. Plot this trace for 5 minutes;: include the period of red motion. Exclain any chances during the five. minutes. (1.5) c) Assume the reactor was at 10-6 at 3 minutes an figure Al and a reactor trip occurred. Plot and discuss the resulting trace for the remaining pericd of time on figure Al. (1.0) A. 4 Xenon conditions include periods when xenen is at equ1iibrium and at peak c:nditions. a) What is meant by equilibrium xer.cn? (1.0) b) Mcw does peak xencn deveicp? (1.5) c) Assume a plant startup and ;cwer e;callation is in progress at the time of peak xenen. Hcw does this differ frca a power escaFlation after a one-week shutdown? Note: a sketch may be used as cart of your answer. It,is not necessary to include values for xenen. (1.5) A. 5. Water is used as a coolant in your reactor. List three other functicns of water in the reactor. (1.5) r ,3 ,gs ab <- r1 e em

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~ ~ B___ FEATURES OF FACILITY DESIGN (14) x 5. 1. The nuclear services closed cooling water (NSCCW) system crovides c oling water for the nuclear components during normal operaticn and also provices cooling for components during a loss of c:olant accident. a) List those ccmpenents which use the NSCCW during ncrmal operation. List the ccmpenents (i) !nside and (ii) Outside the reactor building. (2.5) b )- What ccmpenents are supplied during a LCCA? Note:. if compcnents appear in part A, mark them with an asterisk *. (1.0) 3. 2. Candensate and feecwater are heated in a num:er of heat exchanges before water enters the steam generators. Sketch a cne-line diagram of the c:cbined systems from the condenser until it leaves the last heat exchanger. Include all pumps and source of heat for each heat exchanger for one string. (2.5) 3. 3., The fire protection system at your facility consists of a number of pumps located in unit one and two. The fire main supplies a ms number of hydrants, hcsereel staticns, a wet pipe sprinkler and a deluge system. a) List all pumps which supply the fire main; include ca:acity and when eacn pump will start. (2.0) b) Explain the difference between the wet pipe sprinkler and the deluge water systems. (1.0) 3. 4. Or.e of the compcnents associated with the reactor coolant system is the R. C. drain tank. a) List the equipment which discharges co the drain tanks. (1.0) b) What limits a: ply :: the tank? Include the reascns for these limits. (1.5) c) If the drain tank level 's too high, where may the operators discharge the excess lis. d? (0.5) 3. 5. Cne of the Limits and Preventions recuire tnat systems containing licuids should be free of air before they are cperated to prevent water hammer. a) What is water ha.mer and why shculd plant 0:erators be concerned abcut eater hammer? (1.0) b) Oces water hammer occur only aitn systems containing licuid and air? Exclain your answer. (l.C) tt. ,.1$ r3~ i

g C. GENERAL CPERATING CHARACTERISTICS (ll) C. 1. The ence-througn steam generatcrs (OTSG) at ycur facility will produce superneated steam during power operation, a) With the aid of a simple sketch, explain hcw superhett is acccmplished in the OTSG. (1.5) b) Mcw does superheat vary fecn 15 to 100% pcwer? A sketch may be used as :nct cf your answer. (1.0) C. 2. The folicwing are two of the limitations and precautiens in the Unit Startup procedure. Provide the value and reason for each of the limitations. a) Co not attempt to start a reacter coolant pume when power is greater than (2.0) b) Curing startuo and shutdcwn when reactor pcwer is less than __ percent, the OTSG water level shall be maintained between and (2.0) C. 3. Unless specified by the reactor engineer, group 8 (APSR) will be positiered about 32% withdrawn prior to an apprcach to criticality, a) ' lith the aid of a sketch, indicate how the APSRs worth varies between 0 'C0% withdrawn. (Include approximate reactivity values) (1.5) b) Explain when it is recessary to move the APSRs (i) in and (ii) cut. (2.0) C. 4. Two of the limits and precautiens for the control rod drives concern the gas concentration in the RCS and the cooling water to the mechanism. a) What are the sources of gas in the R.C.S.? (.l. 0 ) b) Why is gas ccncentration a factor for the CRCMs? (1.0) c) Is it necessary to maintain a minimum concentration of gas the RCS during pcwer operation? Expiain ycur answer. (1.0) d) The temcerature of ccoling water to the CRCM may vary frcm 85 - ICScF. Is there a preferred temperature range? Explain. (1.0) C. 5. Assume rated pcwer ccnditicns and a trip occurs to a reactor ccolant pump. a) Provide the initial steady state values fcr parameters listed in figure CS. (1.0) b) Shcw the respcnse to tnese carame:ers until ::nditicns stabilize. Assume :he reactor dces ret trip. (2.0) ,y 9 ,t

= __ -..r _= - ~ ~ D. I'iSTR'JE'iTS ZD CCNTRCL (15) D. 1. Refer to the trar.sient in cuestien C.5. Discuss One acticn of the centrol systam(s) fcc each cf the folicwing parameters: a) Lead MWe (1.5) b) Fressurizer level (1.5) c) Feedwater ficw A 5 3 (2. 0 ) D. 2. The intermediata channel utilizes a compensated icn chamber'(CIC). a) With the aid of a simple sketch, explain the c;erating princicle of a CIC. (1.0) b) Is ccmpensation required at 100%,15%, or lower pcwer levels?. Explain ycur answer. (1.0) m u *v w u C" Aw ( (.%% r,*,, W t e r.o b:,M i c N h *. O M ~ c) C ^ :: ;;n..t.;r.. 3: the "cverlap" requirements between the other channels? Explain. (1.0) D. 3. The pressurizer clectrcmatic celief value (RC-2) may be cperated in the manual or autc-atic mcde. Discuss hcw the valve may be operated A simple sketch. a,1 e used as part of your answer. (2.0) in eacn mode. 3 b g.,3r esw e s D. 4 Unit 2 of TMI utilizes a coron feed 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) When is the centroller utilized? (0.5) D. 5. Two cf the alarms en ene Diamend Centro! panel are the (i) motor rotation fault and the (ii) asyrretric mcniter. a) Discuss the purpose of each alarm. (1.5) b) What immediate action is recuired by the operating staf# for each alarm? (1.5) r- -. ,y r : q ._ g I, ...,As

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..... -. ~--. 2 - ~ : _ : ^ ~~ ~ ~2* E. SAFETY AND E"EOGE.' ICY SYSTEMS (15) E. 1. The ocwer distribution system at T'1I-2 contains two CC buses, 2-lDC and 2-2CC. a) Use a one-line diagram to shcw what ccmconents sucoly these busses and their scurce(s) of pcwer. !nclude any cross ties between these busses and supplies. (2.0) b) If a station blackcut cccurs, what leads are sucplied by the D.C. bus until the emergency diesel generatcrs begic to ;upply power? (1.5) E. 2. List ne ccnditions that will cause a reactor trip witn fcur R.C. pumps in service. ' Include present set points. (2.5) E. 3. Assume a loss of coolant accident (LCCA) cccurs. The LOCA increases reactor building cressure at 20SI/ minute and doubles each minute (2, 4, 3, etc.). Utilice this rate for the followITg: a) What automatic actien(s) cccur during the first four minutes? (1.0) b) 'What instruments will the operatcr observe to assure initial and continuing operation of equipment? ~ (2.5) c) 'What is the postulated peak reactor building pressure in the desiga' basis LCCA? (0.5) E. 4 Three Mile Island Unit 2 is provided with a feedwater latching system. a) List tne instrumentation associated with this system and explain the logic that will actuate the system. (1.5) b) List the aute:atic action that will occur when this system is actuated. Assume rated scwer operation. (2.0) Assume a primary to seccndary leak deveicos in ene of the GTSG. The E. a. leak begins at cne GpM and doubles every 5_ minutes (1, 2, 4, 5, etc.) a) List the systems that will alert the operator. Attempt to arrange them in order of increasing leak rate. (1.0) b) '4 hen the c::eratcrs have identified the leaking OTSG, should they trip the reactor or tegin an orderly shutdown? Explain the reascn for ycur answer. (1. 5 ) e t, .'t,'; 'l 0 = = = - e -

~ F. STA:, CARD At.D E"EFGE:;CY CPERATI';G : CCECURES (15) B F. 1. Assume ycur unit is at the pcwer level cutof# point and waiting to meet the requi 'ments before increasing pcwer. All systems are in automatic. A malfunction occurs in the circulating water system and vacuum begins to decreasa at 1" Hg/ min. a) What is the pcwer level cutoff point and when may pcwer be increased above this level? (1.5) b) Mcw will the ICS respcnd as vacuum decreases? (1.0) c) What immediate action is recuired by the c;erator (assume vacuum continues to decrease)? (1.0) d) List the heat sink (s) available if corrective acti:n can not restore vacuum. (1.0) F. 2. Cne of the Limits and Precautions of the Cecay Heat / Injection Pumps states "When cperating in the E5 mcde with suction en the building sump, pump discharge must be throtled to GFM to limit runout. Do not thrott'le beicw GFfi as this may result in cavitaticn and inadequate cooli1g." a) What are the above flew rates? (0,5) b) What is pump runcut and what are the consequences if the pump continues to cperate in this condition? (1.5) c) What is cavitation and how would the operator observe *his condition on the D.H./ Injection pumps? (1. 5 ) F. 3. During reactor startup, limits are imposed on the amcunt of reactivity which may be added above and belcw the estimated critical

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a) What'are these limits and hcw does the cperator c;nvert them to rod positicn? Assume an ECP of 500 cn Gr:up 5/7. (1.5) b) What action (s) are required if these limits are exceeded? (1.5) F. 4 In the event of a reactor trip, list the manual acticns required by tne TMI-2 emergency peccedure. (3.0) F. 5. In the event of an unanticipated criticality: a; What symptons wculd alert the operating staff? (1.0) b) What immediate acticn is recuired :y the :perator? (1.0) -.w g( e.rs

~ ^- -- = G. P30!AT*CN CCNTROL AND SAFETY (13) G. 1. Assume ycu have been working in a contaminated area. Af ter ycu remove ycur protective cictning ycu mcnitcr ycurself before leaving the area, a) Should an icnization or GM device be used? Expl a i n. (1.0) b) What tjpe of radiat']n will the instrument detect? (0.7) c) What is the criteria for determining if a persen is. cont:minated? (0.8) G. 2. After wcrking in area for twc Mcurs, you disccver ycur dosimeter is off scale and ycu leave the area. A survey indicates a het spot en a drain line reads 1200 'r/hr gamma at two feet. Ycur distance frca the line was abcut five ree:. a) Estimate the dose w' > fcc may have received. (1.5) r b) If your previous expcsure to the quarter was 9C0 mr, what exposure limits may have been exceeded? (1.0) c) dith the aid of a simple :1atch, explain the operating principle of a pocket dosimeter. (1.0) G. 3. Three of the classified areas in the Radiaticn Prctection Manual at TMI are (i) contrciled area (ii) radiaticn area and (iii) high radiation area. a) Define each area; include any limits. (1.5) b) May the NRC examiner enter each area? Explain your answer. (1.0) G. 4 In the event of a radioactive spill, one of tne basic rules is tc administer aid to anycne wnc is injured. What other basic rules accly? (2.0) G. 5. Curing a refueling cutage.ycu are in the reactor building en the main fuel handling bridge. A scent fuel element drops into the ccre. a) What instrumentatien will alert the ;ersennel in the reactor building of any release of fission products? (1.0) b) What autcmatic actien(s) may cccur if radiation levels exceed preset limits? (l.0) c) What acticns are requirec by the centrcl ecem staff? (0.5) e ts ::.; a

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.3,.,..r .s Ener.y Col 1 C 1 II p Col 1 Cal Il EV per AL: 'n'a t e r d Air 'da t e: Katerial E31f-Life disinterr2:1:n u:/ 1 ne/-l lI ue/-12 g:/n1 I -6 -8 . A-41 1.33 h 13 i 2x10 9 Ex10 I Co-60 53 y 25 3x10-I lx10-3 fl 1x10 x10 I-131 8.1 d 0 36 9x10' 6x10-5 l lx10-10 l 3x10-I c Kr-S5 l 10.8 y 0.04 llx10-5 ll 3x10 8' t lii-65 l 25 h 0 59 9x10 Ex10 1 3x10 _o 1x10 -7 l i -4 E -4 I -lk .c Pu-239 2.Lx10 y 0.CC3 2x10 lo 1x10 l 6x10 5x10 Sr-90 l 23 y l llx10~ 1x10 -0 l 3x10'- l3x10 .a Xe-135 92 h 0.25 4x10 1x10"' -5 -10 -6 ^ Any single radienuelide vith T > 2 hr 3x10' 9x10 1x10 3x10 g which d:es not decay byx er spontaneous fissionj Neutr:ns per c:2 l Average flux to deliver l Neutr:n Ere: y('27) ecuivalent to 1 ret i 100 -. e: in k0 heu a 1 -D ner:al 97Cx10 670 0.02 LCOx106 280 0.,- h3x100 30 10 2kx10b 1'T ..-. >--.. -a= - : w : ~ C - _. _.. .~. ~. = ( - -. - l L -. -.s, Ener v U-27) I 'J e t e r l Concrete l Iren l Lead 05 0.090 0.21 0.63 17 1.0 0.C67 0.15 0.kh 0 77 15 0.057 0.13 0.ho 0 57 2.0

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_______n_..__ m U. S. NUCLEAR RESULAT:RY C PFISSICN SENICR REACTOR CPERATCR LICENSE EXAMINATICN Facility: Threeyilejsland-Unit 2 Reactor Type: ran - u., Oate Administered: cu o te< Examine r: J. J. cu:y . Applicant k.D INSTRUCTICNS TO APPL! CANT: Use separate pacer for the answers. Staple questien sheet en top of the answer sheets. Points for each questien are indicated in parenthesis after tne question. Category

of Applicant's

" of Value Total Sco re Cat. Value Category 14 20 l}.9 I9 H. Reactor Theory 14 20 IO,I I. Radioactive Materials Handling, Disposal and Hazards J. Specific Cperating 14 20 Characteristics 11. O g. Fue1 Haneling 3 Care p3r3eeters la gg la 20 k l. %k L. Administrativa Procedures, Con-ditions and Limitations Totals

n Ts LL Final Grade

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s .. -. R,f f,s. ) .u. 9.....2 nw. r H. 1. Tac ninutes af:er ; reac Or tri frcm full ;;wer, a lar;e num er of neutr:ns are still ; resent in the ccre. List these neutrons and give their origin. (1.5) H. 2. Assume your reac:ce is :n a 1 CFM startup rate at 5 X 10-9, grcup 6/7 is at 15% withdrawn. a) 'dhat shculd be the r:d positicn when the opera:Or levels off at 'C-5? Shcw all wecs, include any assumptions _. (2.0)

) '!ith ma.a :um rod speed, how long should the operator move the rods to level off at 10-c? Explain hcw ycu arrived at

.,a yCur answer. (1.J) c) If ;cwer were alicwed c increase, hcw far do ycu expect the pcwer level :: rise? Include any asst =ctions. (1.0) d) Will the same reacti,ity addition produce the same S.U.R. during core lifetime? Explain. (1.5) H. 3. Refer to figure 23. Control red groups 5-7 reactivity worth at 532cF. a) Sketch the accroximate reactivity wortn of grcup 5-7 when the temperature is 582cF. (0.5) b) Explain why the curve will change. (2.0) H. 4 Refer to ;uestion K3. Assume the individual responsible for taking the count rate reads and records the data irrediately af ter the fuel element is inserted into the care. Would the resulting plot be mora or less conservative? Explain your answer. (2.0) H. 5. Cne of the limiting ::nditicns for ::erition at your station is the value of the acde-ator tem era:ure c ef#icient. Is tnis value of concern early c- =- -"= snd of c:re lifetime? Explain :ne reascn(s) far ycur ansaer. (2.0) ' t1 .( pa-ac ;y r. t

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m _ I. 5. The maximt.m activity c:ntained in cne ;as cecay tank is limited tc a) 'What is the limi* and wna is responsible tc assure this limit is not exceeded? (1.0) b) 'What is the reascn fcr this limit? (1.0) I f

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n .e p e.c. t : c. c..o e:... ;r, c.u.. :. r.. ::.-..e. ~.a ( 4, 4 ) v a. J. 1. Li th j um 'r.ydroxide and hydrazine are two chemicals that are added to tne react:r c:alant system. a) Discuss when it may be necessary tc add these chemicals. (1. 5 ) b) What precautions must be observed when handling these chemicals? (1.0) J. 2. During the unit heatup, cne of the steps requires a hard bubble degasificati:n when the coolant temperature reaches 3500F. a) Outline hcw this s:ep is pcrformed. (1.0) b) What wculd be the ::nsequences if this s ep was not perfor ed? Assume pcwer c;eraticns with steady state and transient conditicns. (1.5) J. 3. Abcut two years ago, TMI Unit One went critical cuo ng a plant heatup, while the RC tgmperature was 5C50F. a) What procedural steps were modified to prevent a repeat incident? (1.5) b) What is the L.C.0. fur minimum R.C. temperature for criticality and what is the basis for this L.C.0.? (1.5) J. 4 When operating from 50 to 100% rated pcwer with 4 RC pumps running, the staff is required to maintain cold leg differential temperatures to less than 50F. a) Ecw does the operating staff comply with this limitation? Include centrols the staff must manipulate. (1. 5 ) b) Why is this ::ndition recuired? (1.0) J. 5. Assume a reactor startup is in progress anu uithin 5" cf red posi tic.i for cri ticality. At the same time, an I.C.S. representative is " fine tuning" the centrol system.

Suddenly, all turoine bypass valves go full vtives cpen. Assume (i) ene main feed pump in service and (ii) R.C. tem;:erature c'ecreases 0

at 20 F/ min. a) What protective device (s) shculd respcnd tc trip the reacter if no acticn is taken? (0.3) ) What imediate action is required by the c;erating. afD (0.7) Section J ::ntinued on next : age r ,. y 5 $rj

~ e i J. 5. c) Assume g action Oy the ccerating staff. hat systems will res:cnd if cne tur:inr: ::y-pass valves cannet be --,u,t Atter0t to shcw if the plant systems alil cr-sh W1:1 not terminate Onis transient without operator action. (2.0) h I I) (,

m F'.'EL HANCLIN3 & CCRE :tRAMETERS (la) K. 1.9 Listed below are several fuel handling devices and maneuvers. List and explain the curecce Of tne interlock (s) during eacn

maneuver, a) Centrol roc handling mechanism while inserting and withdrawing centrol rods.

(1.0) b) Rotaticn of the fuel transfer baskets and the main fuel or spent fuel storage handling bridge. (1.0) c) Fuel grapple mechanism and hoists when insert'ng or removing fuel in the core. (1.0) K. 2. Assume a malfunction on ne of the safety reds in group 2 results in a dropped rad. he reactor is a: rated pcwer and the react:r demand staticn is in manual, a) What ictediate action is required by the operator? (1.0) b) Why is the abcve action necessary? (1.0) c) Assume trouble shooting cannot begin for several hcurs, would the axial ;cwer im:alance and/or the quadrant scwer tilt bec me the limiting condition for cperation? Explain ycur answer. (1.5) K. 3. !nitial fuel leading at most FWRs develops as a " slab. The source is located in the center and the fuel is leaded outward (see figure K-3). Temporary cham:ers (A&B) are located in the vessel and subcritical multiplication plots are made for each section of the slab ioading. a) Sketch the expected plot of su: critical multiplication f:r each cham:er. (1. 5 ) b) ~ Explain any difference in :ne plots. (2.0) K. 4 During tne initial pcwer escallati:n and immediately follcwing a centrol rod interchange, the rate of power increase is limited to 3%/hr. bet..een 75 to 90% pcwer; also, a 5 hcur hold i5 required at 90! pcwer. a) What are the nereal maneuvering rates between 75 to 90% power? provice transient and controlled annditicns. (0.5) b) Why is it necessary to :erf:rr. a ::ntrol red 'ntarcharge and wny are ;cwer increases reduced to 3%/hr? (2.0) K. 5. At acned is figure IA, Core Excess Reactivity, f:r ycur f acili ty. Ex; lain the shape of :ne curve during :he first 1:0 EFpD. (1.5) "*"'*-+h e +- w -

E O. L. ACMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS (14) L.

1. If any safety lini is exceeded, the shift supervisor is required to notify tne station / unit superintendent and have the reactor in hot standby conditions within one hcur.

a) What parameters and limits are considered in the safety limits for ycur station? (1.5) b) '. shat instrumentation in the reactor protecting system shuld prevent reaching a safety limit? (1.5) c) What are the plant conditions for hot standby? (0.5) L.

2. Title 10 CFR Part 55, C;erators Licenses, defines an cperator as any individual aho manipulates a control of a f acility.

a) Define centrol as it applies to this definiticn and give two examples. (1.0) b) Is it necessary to be a licensed operator to manipulate a control? Explain. (0.5) c) Assume an operator was injured during a motorcycle accident. He is disabled for 5 months. When can he return to nor al duties? (1.0) L.

3. When a shift is relieved, a number of items must be ccmoleted.

a) What shift records are maintained? (1. 5 ) o) What conditions are required in crder for an entire shift to be relieved? (1.0) t) List the shift organizaticn required by tne technical s::ecificaticns during (i) fuel leading and (ii) plant s ta rtup. (1.5) L.

1. Assume you are the shift sucerviscr in charge of your shift.

For eacn condition below provide (i) irrediate and subsecuent action and (ii) tne reason for ycur acticn, including any administrative limits. a) The unit is shutdcwn for OT3G tube inspection. You are informed that the sodium hydroxide tank was inadvertantly lined up to the decay heat ;t.mos. Abcut half of the tank volume is left. (1.5) b) The plant is at rated ccwer during the ainter. The auxiliary operator informs you :nat the vent (s) On tne 3'aST tank seem Oc have frcren cue J concensaticn and ice formation. (i.0) Secticn L conti ued on next cage. I ^ t t.>

A. L. 4 c) During a test of the ccntainment isolaticn va'ves, cne of the valves begins to leak at the ;;acking <, land. The test engineer suggests he can "back seat" :ne /alve by holding in the c;:en relay w;th an insulated screwdriver at the motor control center. (1.5) e p,.. I)) g$)

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970x10, 670 0.C2 LCOx10D 280 05 h3x10 30 10 24x106 17 9*

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