ML19220B448

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Examination Rept on Senior Operator License Issued for TMI-2.Written Examination Encl.Operating Test Administered 770915
ML19220B448
Person / Time
Site: Crane Constellation icon.png
Issue date: 10/17/1977
From: Collins P
Office of Nuclear Reactor Regulation
To:
METROPOLITAN EDISON CO.
References
NUDOCS 7904260135
Download: ML19220B448 (74)
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Text

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= _ ] U. S. NUCLEAR REGULATCC 7C?!SSICN SENIOR REACTCR CPERATOR LICIkif. :Xa.MINATICN Facility: Threejlile Island - Unit 2 Reactor Type: o r "c' -. "? Cate Administerec: c/ / C/ ' ' Exa.T :ne r: .1. J. auzy

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/.97o INSTRUCTICNS TO APPLICANT: Use separate paper for the answers. Staple questien sheet On top of the answer s.'ests. Points for each questien are indicated in pare.n:hesis after the questien. Cate;c ry % of Applicant's

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'/alue Total Score Ca t. 'h l',j Catecory 14 20 Il. b kh5 d. Reactor Theory la 20 l 1,$ br#T I. Radicactive. aterials Handling, M Disposal and Hazards I). J. Specific Operating la 20 Cha racteri s t' cs k l). Y Ib K. Fuel Handling & Core Para. meters la 79 / I 3. $ C)g (s L. Administrative Precedures, Cen-la 20 ditiens and Limitations 7n ),b Totals Final Grade: ., w <> s., . ~ - -

} n H. REACTCR THECRY (14) H. 1. Tao minutes after a reactor trip from full ;cwer, a large number of neutrons are still present in the care. List these neutrons and give their crigin. (1.5) H. 2. Assume your reactor is en a 1 DPM startup rate at 5 X 10-9, group 5/7 is at 15" withdrawn. a) What should be the red position when the Operator levels off at lO-C? Shcw all work, include any assumptions _. (2.0) b) With maximum r0d speed, how long should the cperatcr move the rods to level off at 10-3? Explain how you arrived at your answer. (1.5) c) If pcwer.<ere allcwed to increase, hcw far do ycu ex;'ect the pcwer level to rise? Include any assumptions. (1.0) d) Will the same reactivity addition produce the same S.U.R. during core lifetime? Ixplain. (1. 5 ) ' H. 3. Refer to figure 29. Control red groups 5-7 reactivity worth at 5320F. a) Sketch the approxi ate reactivity worth of group 5-7 when tne temcerature is 5320F. (0.5) b) Explain why the curve will change. (2.0) H. 4 Refer to tuestien K3. Assume the individual responsible for taking the count rate reads and records the data imediately af ter the fuel element is inserted into the core. Would the resulting plot be more er less conservative? Explain your a n s..e r. (2.0) H. 5. Cne of the limiting conditicns for cceration at ycur station is the value of the =cderator temperature coefficient. Is this value of concern early or at the end of c:re lifetime? Explain the reasen(s) for your answer. (2.0) r acq s t.r . s so

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( i e..- ) si. ,ericc1:al,.y, caring ;;wer operation, it is necessary to i. purge the reactor building. Cescribe the proccdures and limitations that you, as snift superviscr, are res; nsible for during tne purge. Include the fc!1cwing: a) Accinistrative require:.ents, including individuals who L approve the release. (1.0) b) What monitors are required to be in service? (1.0) ~ .) 'a'hy' i. s '. '... =..=.e.= ry- '.. r *..*.=. '.4.,=. - - o '. s. *. 4.. a. s y s. =.... ". a. 2. y. ' n.. s' ) c e - a. *.. n = 1 " ".. i.....". a. - =. 'i a..= s e '. s r. 3 d) Maximu.T react:r building pressure ; rice :: release. (0.3) A smear is taken en a ca,ilarated pressure c.auc.e wnich was i. c. used in the waste disposal area. i Scear Area - 100 CM' Background - 15 cpm 5 minute count - gCO Scaler efficiency - 15" a) Determine if the gauge can be returned to the ins rument shcp. (1.:- b) Discuss new vou would take a smear /s) for this cauce. (I.0) 6 Assume a reacter c:clant leak develops in the reactor building. 2. a) What are limits en reactor c clant system leakage as a function of locaticn or identity of the leakage? (l.5) b) Assume tne leakage collects in the reactor buildinc sur. ..= n... ~... a -,,. r. a.- .u..e a.2.r :..;.w. 2 s.. j e <. . 2... 2 s s,...,..,4... ,u i. 4. _..,., .1 s-c s a,s, tl.:) s .a c) pricr to entering the r2act:r building to sear:h for the leak, wnat installed monitoring system (s) can :e used by the inspect 1cn team :: evaluate tne levels of radiation? (1.,) _-.-..a-I. 4 An Opef ator has dr:pped a set of keys en ::p of a s:ent fuel ~ element.in the storage pccl. He wants to fabricate a tool t ..~, s. e o :...,

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~. _. _....i I. 5. The maximum activity contained in cne gas decay tank is limited to a) What is the limit and who is res;:cnsible to assure this limit is not exceeded? (1.0) (1.0) ! b) What is the reason for this limit? s A,

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'!2.'-.'..----- ~~ ~ J. SPEC:FIC CPERATING CHARACTERISTICS (14) J. 1. Li th itm hydrcxide and hydracine are two chemicals that are added to tne reactor coolant system. a) Discuss when it may be necessary to add these chemicals. (1.5) b) What precautions must be cbserved when handling these chemicals? (1.0) J. 2. Curing the unit heatup, one of the steps requires a hard ~ bubble degasification when the coolar;t temperature reaches 3500F. a) Cutline hcw this step is performed. (1.0 ) b) What wculd be the consequences if this step was not performed? Assume pcwer ocerations with steady state and transient conditicns. (1.5) J. 3. Abcut two years ago, TMI Unit Cne went critical during a plant heatup, while the PC temperature was 5050F. a) What procedural steps were mcdified to. prevent a repeat incident? (1.5) b) What is the L.C.0. for minimum R.C. temperature for criticality and what is the basis fcr this L.C.O.? (1.5) J. 4 When operating frcm 50 to 1C0% rated power with 4 RC pumps running, the staff is required to maintain cold leg differential temperatures to less than 50F. a) How does the cperating staff comply with this limitaticn? Include controls the staff must manipulate. (1.5)

) Why is this conditicn req'F red?

(1. 0 ) J. 5. Assume a reactor startue is in crogress and within 5% of red pcsition for criticality. At the same time, an I.C.S. recresentative is " fine tuning" the control system.

Suddenly, all turbine bypass valves go full valves ccen. Assume (i) cne main feed pump in service and (ii) R.C. temperature decreases at 3CcF/ min.

a) What protective device (s) shculd rescend to trip the reactor if no action is taken? (0.3) b) What immediate acticn is recuired by :ne operating staff' (0.7) ! action J ccntinued en next cage 2 >", [O y., (;

~ J. 5. c) Assume 3 action by the c::erating staff. '. shat systems will res:cnd if tne tur:ine by-cass valves cannet be snut. Attempt to show if the plant systems wiii oT-RTT not terminate this transient without cperator action. (2.5) ? I J s 6 e

~. _m _.c:- j -~ K. FUEL HANCLING 1 CCRE P ARA. METERS (14) K. 1. Listed below are several fuel handling devices and maneuvers. List and explain the curcose of the interlock (s) during each maneuver. a) Control rod handling mechanism anile inserting and withdrawing control rods. (1.0) b) Rotation of the fuel transfer baskets and the main fuel or spent fuel storage handling bridge. (1.0) c) Fuel grapple mechanism and hoists when inserting or removing fuel in the core. (1.0) K. 2. Assume a malfunction en one of the safety rods in group 2 results in a dropped red. The reactor is at rated pcwer and the reactor demand station is in manual. a) What immediate action is required by the operator? (1.0) b) Why is the above action necessary? (1.0) c) Assume trouble shcoting cannot begin for several hours, would the axial pcwer imbalence and/or the luadrant pcwer tilt b.eccce the limiting ccndition for cperation? Explain your answer. (1.5) K. 3. Initial fuel Icading at most FWRs develc'ps as a " slab. The source is located in the center and the fuel is loaded outward (see figure K-3). Temporary chambers (A13) are located in the vessel and succritical multiplication plots are made for each section of the slab loading. a) Sketch the expected plet of subcritical cultiplication for each chamber. (1.5) b) Explain any difference in the picts. (2.0) K. 4. Curing the initial pcwer escallation and immediately folicwing a control red interchange, the rate of power increase is limited to 3%/hr. between 75 to 90% power; also, a 5 hour hold is required at 90% pcwer. a) What are the normal maneuvering rates between 75 to 90% pcwer? Provice transient and ccntrolled ccnditions. (0.5) b) Why is it necessary to perform a control rcd interchange ard uhy are pcwer increases reduced to 3%/hr? (2.0) K. 5. Attached is figure IA, Core Excess Reactivity, for ycur facility. Exclain the shape of tne curve during ne first 100 EF?D. (1.5) ,c e e e

n L. A:MINISTRATI'/E PROCECURES, CONDITICNS AND LIMITATIONS (14) L.

1. If ' any safety limit is exceeded, the shift supervisor is required to notify the station / unit superintendent and rave the reactor in not standby conditions within one hour, a) What parameters and limits are considered in the safety limits for ycur station?

(1.5) b) What instrumentation in the reactor protecting system should 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, Operatcrs Licenses, defines an operator as any individual who manipulates a control of a facility.

a) Cefine centrol as it applies to this definition and give two examples. (1.0) b) Is it necessary to be a licensed operator to manipulate a control? Expl ain. (0.5) c) Assume an operator was injured during a motorcycle accident. He is disabled for 5 months. When can he return to normal duties? (1.0) L.

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

a) What shift records are maintained? (1.5) b) What co7ditions are required in order for an entire shift to be relieved? (1.0) c) List the shift organization required by the technical specifications durir.g (i) fuel leading and (ii) plant s ta rtuo. (1. 5 ) L.

4. Assume you are the shift supervisor in charge of your shift.

For each condition below provide (i) immediate and subsequent action and (ii) the reasen for your action, including any administrative limits. a) The unit is shutdcwn for 0TSG tube inspecticr.. You are informed that the scdium hydroxide tank was inadvertantly lined uo to the decay heat pumps. Abcut half of the tank volume is left. (1.5) b) The plant is at ra:ed :cwer during the ainter. The auxiliary Ocera:Or informs you that :he vent (s) On the SWST tank seem to have frc:en due to ccndensation and ice formation. (1.0) Sectt n L continued on 9 ext age A m t) v:6 .. r1 g ww=

= p ~ L. 4 c) During a test of the containment isolaticn valves, one of the valves begins to leak at tne packing gland. The test engineer suggests he can "back seat" the valve ::y holding in the c;:en relay with an insulated screwdriver at the matar control center. (1.5) =. 8 e 1.. p =

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Wo - E W Date Administered a / /7/ 77 Ex::.iner J. J. Bu:'v Applicant lf[O _

Instr.:c:icns to Applicant: Use separate paper fcr the ans.sers; s aple questien sheet Points :or eacn questien are en :cp of the answer sheets. An overall indicated in parenthesis af ter the questien. score of 70% or greater is passing. Category 1 of Applicant's % of Valm Total _ Score Cat. Value 14 13.5 R,l N A. Princiales of Reactor Operatica e 14 13.5 9,( $b B. Features of Facility Design 17 16 l2.I 7) C. General Cperating Characteristics 16 15 i4 I W D. Instr.=ents and Centrols 1W.D 91 E. Safety and Energency Systens 16 15 I). 7 '[ F. Standard and Emergency Operating 16 i5 Precedures G. Raciatien Centrol and Safety \\ )- 13 _ 12 __ b 1C6 o .inal crade X t e. fc '~ ~~~ ~ -- 6 t> .. % 'i) __ _ _ _ _.

s. . = - ::... : -. -. = - =- - = -.. =..-- =.-- --._. 4. PRINC:PLES OF REACTCR OPERAT!ON (14) A. 1. a) What is eant by the term " delayed neutron fraction"? (1.0) b) How and whv does the delayed neutron fraction change during core lifecime? (1.5) A. 2. The TMI procedure for approach to criticality requires the operating staff to clot a one over M (1/M) during red withdrawal. a) What data is required for the 1/M plot? (0.5) ,l b) Mcw is the data utilized? Note: a sketch may be used as rart of ycur answer. (1. 5 ) A. 3. Assumeycurreactorigenastable..S0;Mstartuprateas;cwer level reaches 2 x 10-en the intermediate range monitor. (Tice is "0"). a) Plot the trace en Figure Al until the pcwer level reaches 10-c. (1.5) b) After a two-minute " hold" to take data at 10-8 the operator withdraws the control rods to obtain a 1 D;M startup rate. Plot this trace for 5 minutes;. include the period of rod motion. Exclain any changes during the five minutes. (1.5) c) Assume the reactor was at 10-6 at 3 minutes en figure Al and a reactor trip occurred. Plot and discuss the resulting trace for the remaining period of time en figure Al. (1.0) A. 4. Xenon conditions include periods when xenon is at ecuilibrium and at peak conditions. a) What is meant by equilibrium xenen? (1,0) b) Mcw does peak xenon develop? (1.5) c) Assume a plant startup and power escallaticn is in progress at the time of peak xenen. Mcw dces thi s differ fecm a pcwer escallation after a one-week shutdown? Note: a sketch may be used as cart of your answer. It is not necessary to include values for xenon. (1.5) A. 5. Water is used as a cociant in your reactor. List three other functicns of water in the reactor. (1.5) r n,m 0 f e.-

1 '3. FEATLRES OF FAC'LITY CESIGN (14) 5. 1. The nuclear services closed c cling water (NSCCW) system provides cooling water for the nuclear c mpenents during normal c eration and also pr vides c cling for c:mponents during a loss of caolant accident. a) List those components which use the NSCCW during normal aceration. List the c:mpenents (i) Inside and (ii) Cutsida the reactor building. (2.5) b) What components are supplied during a LCCA? Note:. if. c:cpenents 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 genera ces. Sketen a one-line diagram of the c cbined systems fr:m the condenser until it leaves the last heat exchanger. !ncluce all pumps and scurce of heat for each heat excharger -far One string. (2.5) 3. 3. The fire protection system at your facility censists of a number of pumps located in unit one and two. The fire main supplies a number of hydrants, hosereel stations, a wet pipe sprinkler and a deluge system. a) List all pumps which supply the fire main; include ca acity and when each pump will start. (2.0) b) Explain the difference between the wet pipe sprinkler and the deluge water systems. (1.0) 3. 4 Cne of the ccm;cnents associated with the reactor coolant system is the R. C. drain tank, a) List the equipment wnich discharges to the drain tanks. (1.0) b) What linits apply to the tank? :nclude the reasons for these limits. (1.5) c) If the drain tank level is too high, where may the Operators discharge the excess liquid? (0.5) 3. 5. One of the Limits and Freventicns require that systems centaining liquids shculd be free of air before they are operated to prevent water hammer. a) What is water hammer and wny shculd piant cperators be concerned abcut water hammer? (1.0) b) Cces water nammer occur only witn systems containing li. quid and air? Explain ycur answer. (1.0) r - ,,f.

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^^L -_.__. ~. _ - - ~ i, ' ~ ~ ~ ~ ' ' ~ ~ 'E. $AFETY AND E"ER3ENCY SYSTEMS (16) E. 1. The pcwer distribution system at TMI-2 contains two DC buses, 2-1:C and 2-20C. a) Use a one-line disgram to shcw what ccmponents sucaly these busses and their source (s) of pcwer. Include any crcss ties between these busses and supplies. (2.0) b) If a station blackout cccurs, what leads are supplied by the D.C. bus until the emergency diesel generatcrs begio to Jupply power? (1.5) E. 2. List the conditions that will cause a reactcr trip with fcur R.C. pumos in service. Include present set points. (2.5) E. 3. Assume

  • less of ccolant accident (uCCA) occurs. The LCCA increases reactcr cu11 ding cressure at 2 PSI / minute and doubles each minute (2, 4, 8, etc.).

Utli1ce this rate for the felicwing: i a) What autcmatic actien(s) cccur during the first fcur minutes? (1.0) b) What instruments will the cperatcr ccserve to assure initial and ccntinuing operation of equipment? (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 prcvided with a feedwater latching system. a) List the instrumentatien asscciated with this system and explain the logic that will actuate the system. (1.5) b) List the autcmatic acticn that will occur when this system is a ctua_ted. Assume rated pcwer cperation. (2.0) E. 5. Assume a primary to seccndary leak develocs in ene of the OT5G. The leak begins at cne 3FM and dcubles every 5, minutes (1, 2, 4, S, etc.) a) List the systems that will alert the cceratcr. Attempt to arrange them in ceder of increasing leak rate. (1.0) b) When the operatcrs have identified the leaking OTSG, should they tri? the reacter er begin an orderly shutdcwn? Exclain the reason fcr ycur answer. (1.5) e <- <~g e t.s e. s; 7 -w- - + - - - - - - -e = ,-e_-

e _ p ~ ' D. INSTRUMEriT3 40 CCllTROL (16) D. 1. Refer to the transient in questien C.5. Discuss ne action of the control system (s) for each of the following parameters: a) Lcad MWe (1.5) b) Pressurizer level (1.5) c) Feedwater ficw A & 3 (2.0) D. 2. The intermediate channel utilizes a compensated icn chamber'(CIC). a) With the aid of a simple sketch, explain the ccerating principle of a CIC. (1,0) b) Is ccm::ensation required at 100%,15%, or lower pcwer leveis?. (1.0) Explain your answer. 4 G E M "/ C d% c)Q_yj gwf M 6y;N4n.the " overlap" requiremedts between the --p: other channels? Explain. (1.0) D. 3. ine pressurl:er electrcmatic relief value (RC-2) may be cperated 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 ycur answer. (2.0) fgyiti54: D. 4 Unit 2 of TMI utilizes a bcron feed and bleed controller, h a) What are the input signals to :he controller? (1.0) b) What are the output signals of the controller? .(1.5) c) When is the controller utilized? (0,5) D. 5. Two of the alarms en the Diamond Centrol panel are :he (i) motor rotation fault and the (ii) asymetric monitor. a) Discuss the purpose of each alarm. (1.5) b) What i=ediate action is required by the operating staff for each alarm? (1.5) G.?10 .e +N* r em --e a e o ee ee m*w 6ee -- w em e,W -ee e-m e, _g h--+ e -==--- -w-- e--

  • --+%

C. GENERAL CPERATING C4aRACTERISTICS (17) C. 1. The once-through steam generat:rs (OTSG) at ycur facility will pecduce superheated steam during pcwer operation, a) With the aid of a simple sketch, explain hcw superheat is acccmplished in the OTSG. (1.5) b) How does superheat vary frem 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 limitaticns. a) Ca not attempt to start a reactor ccolant pump when power is greater than (2.0) b) During startuo and shutdewn when reactor pcwer is less than percent, the OT5G water level shall be maintained between and (2.0) C. 3. Unless specified by the reactor engineer, group 3 (APSR) will be positioned about 32% withdrawn prior to an approach to criticality. a) With the aid of a sketch, indicate how the APSRs worth varies between 0 - 1C0% withdrawa. (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 Two of the limits and precautions for the control rod drives concern the gas c ncentration in the RCS and the ccoling water to the mechanism. a) What-are the sources of gas in the R.C.S.? (1.0) b) Why is gas concentraticn a factor for the CRCMs? (1.0 ) c) Is it necessary to maintain a minimum concentration of gas in the RCS during pcwer operation? Explain your answer. (1.0) d) The tem erature of cooling water to the CRCM may vary from 25 - IC50F. Is there a preferred temperature range? Expl a i n. (1.0) C. 5. Assume rated ;cwer conditions and a trip occurs to a reac:cr c:alant pumo. a) Provide the initial steady state values f:r parameters listed in figure C5. (1.0) b) Shcw the res:cnse :: these parameters until conditions stabilize. Assume the reac:Or d:es no : rip. (2.0) < x; <>

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p 'F. STANCARD AND EMERGENCY C?ERATING PRCCEDURES (16) F. 1. Assume your unit is at the pcwer level cut ff point and waiting to meet the requirements before increasing pcwer. All systems are in autcmatic. A malfunction occurs in the circulating water system and vacuum begins to decrease at 1" Hg/ min. a) What is the pcwer level cutoff point and when may pcwer be increased above this level? (1.5) b) Hcw will the ICS respcnd as vacuum decreases? (1.0) c) What immediate action is required by the cperater (assume vacuum centinues te decrease)? (1.0) d) List the heat sink (s) available if corrective acticn can nct restcre vacuua. (1.0) F. 2. One of the Limits and Precautions of the Cecay Heat /Injecticn Pumps states "When cperating in the E3 mode with suction on the building sump, pump discharge must be throtled to GFM to limit runcut. Do not tnrottle belcw GFft as this may result in cavitation and inadequate 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 ccndition? (1.5) c) What is cavitation and hcw would the operator cbserve this condition on the D.H./ Injection pumps? (1.5) F. 3. During reac:ce startup, limits are imposed on the amount of reactivity which may be added abcve and belcw the estimated critical positicn. a) What are these limits and hcw dces the cceratcr ccnvert them to red pcsition? Assume an ECP of 50% cn Group 6/7. (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 actions recuired by the TMI-2 emergency precedure. (3.0) F. 5.

n the event of an unanticipated criticality:

a) What symatens would alert the Operating staff' (1.0) b) What inmediace action is recuired by the :cerator? (1.0) 's u ',) ^ ~.'..C.).

I_. ._._;__.._._. =.- - -i .u c 'G. RACIATICN CONTROL AND SAFETY (13) G. 1. Assume you have been working in a contaminated area. After you remove your protective clothing you mcnitor ycurself before leaving the area. a) Should an icnization or GM device be used? Expl a in. (1.0) b) What type of radiation will the instrument detect? (0.7) c) What is the criteria for determining if a person is. contaminated? (0.8) G. 2. After working in area for two hcurs, ycu discover ycur desimeter is off scale and you leave the area. A survey indicates a het spot en a drain line reads 1200 mr/hr gamma at two feet. Ycur distance frcn tne line was about five feet. a) Estimate the dose which you may have received (1.5) b) If your previous exposure to the quarter was gCO mr, what exposure limits may have been exceeded? (1.0) c) With the aid of a simple sketch, explain the operating principle of a pocket dosimeter. (1.0) G. 3. Three of the classified areas in the Radiaticn Protection Manual at TMI are (i) centrolled area (ii) radiation area and (iii) high radiation area. a) Cefine each area; 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 anyone who is injured. What c her basic rules apply? (2.0) G. 5. Curing a refueling cutage you are in the reac:Or building on the main fuel handling bricge. A spent fuel element drops into the c;re. a) What instrumentation will alert the persenrel in the reactor building of any release of fissicn products? (1.0) b) What automatic acticn(s) may occur if radiatien levels exceed. preset limits? (1.0) c) What actions are recuired by the control recm staff? (0.5) v $ k.F r, o ag aj

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l -9 -5 1 -10 -o Any single radi:nucli:ie with O > 2 h 3x10 9x10 1 1x10 3x10 g which does not decay by.x cr spontaneous l fis sica ! Neutrens per crd Averese flux : deliver l Neutron Enerry(!T'/) ecuivalent to i re: 100 r. en in h0 heu s 1 6 Ther al

97Cx10, 670 0.02 hC0x10D 280 05 h3xlCO 30 10 24xlCO 17

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