ML19220B476

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Examination Rept on Senior Operator License Issued for TMI-2.Written Examination & 18 Encl.Operating Test Administered 770914
ML19220B476
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/29/1977
From: Collins P
Office of Nuclear Reactor Regulation
To:
METROPOLITAN EDISON CO.
References
NUDOCS 7904260288
Download: ML19220B476 (69)


Text

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\\ i 3,, 1 .m O. U. S. NUCLEAR REGULATCRY CC.v!SSICN SENICR REACTCR CFE?ATCR LICENSE EXAMINATION Three Mile Island - Unit 2 Facility: Reactor Type: _;"a ra^ Cate Administered: '/ ' / Examiner: J. J. ury Applicant: /Go INSTRUCTICNS TO APPLICANT: Use separate paper for the answers. Staple questien sheet on tcp of the answer sheets. Points for each questien are indicat.ed in paren-hesis af ter the questicn. Category

of Applicant's
of Value Total Sccre Cat. Value Catecory 14 20 lk h bb H.

Reactor Theory 10.7 76 I. Radioactive saterials Handling, 14 20 Dispcsal and Hazards e1 J. Specific Cperating la 20 Characteri s tics .N K. Fuel Handling & Core Parameters la gn 14 20 [h b ]N L. Administrative Procedures, Con-ditiens and Limitations 70 b/, l Totals Final Grace: ?.T C43 e 5

4 , _,, -,j 2 i. e A i s H. REACTCR THEORY (14) H. 1. Two minuces after a reactor trip from full pcwer, a large number of neutrons are still present in the core. List these neutrons and give their origin. (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 Assume your reactor is en a 1 DPM startup rate at 5 X 10-9, group 5/7 is at 15" withdrawn.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) Whatshoulg?be the rod position when the c;erator levels off at 10-Shcw all work, include any assumptions. (2.0) b) With maximum red sceed, hcw long should the cperator move the rods to level off at 10-8? Explain how ycu arrived at your answer. (1.5) c) If pcwer were allcwed to increase, hcw f ar do ycu expect the ;cwer level to rise? Include any assumptions. (1,0) d) Will the same reactivity addition produce the same S.U.R. during care lifetime? Explain. (1.5) H. 3. Refer to figure 28. Centrol rod groups 5-7 reactivity worth at $32cF. a) Sketch the approxi. mate reactivity aorth of grcup 5-7 when the temperature is $820F. (0,5) b) Explain why the curve will change. (2.0) H. 4 Refer to question K3. Assume the individual responsible,ar taking the count rate reads and records the data irr.ediately after the fuel element is inserted into the core. Would the resulting plot be more cr less conservative? Explain your answer. (2.0) H. 5. One of the limiting conditions for cceration at your station is the value of the cederator temperature coefficient. Is this value of concern early or at the end of core lifetime? Explain the reason (s) for ycur answer. (2.0) 7.9.044 e O

1 8 E. 4 9 ~ ~ _ .r. -. n I ~.-,., ,,c, -.,. L e.... n. i. r e - ,.- r.e.._s,s r,.,.-n5 .0 ~ c-x_ ns si r o .aa, v 3 i. 1. r eri e d:. ca.ly, during : wer c:eraticn, it is necessary to t 4.

urge the react:r building. Describe ne pr:cecures and limitations tha: you, as shift su;ervisce, are responsible for during the purge.

!nclude the f licwing: a) Administrative requirements, including individuals who approve the release. (1.0) I b) What menitors are required to be in service? (1.0) = c) Why is it necessary fcr the # ire pre:ecticn system :: be

pera:icnal during the release?

(0.7) d) Maximum rea:::r building pressure ;rior :: release. (0.3) 2. A smear is taken on a calibrated pressure gauge which was used in the waste disposal ar?a. A Smear Area - 100 CM2 Eackground - 16 CPM i 5 minute c:un: - gCO Scaler eff'ciency - 15% t a) Cetermine if the gauge can be returned to the instr. ment shop. (1.5) l i i b) Discus Scw you wculd take a smes -(s) for this gauge. (1.0) I. 2. Assume a reac:Or coolant leak develc;s in :ne reactor building. a) What are limits en reac:Or c:clant system leakate as a ~ function of iccation or identity of ;he leakage? (l.5) b) Assume the leakage collects in :ne reac cr :uilding sume. Describe in secuence what ha:; ens :: the wa:er from the sumo :o i ts ul:imate dis:csal. (1.5) c) ? rice :: entering the react:r :uilbing :: search f r ne leak, una: installed moni:Oring system (s) can be used by tne ins:ection team to evaluate :ne levels of radia:icn? (1.5) I. 4. An ope?at:r' has dro;;ed a set of keys en : p of a spent fuel element.in the s:Orage ; col. He wants to fabricate a tool t made of ten fco: Icng, One inch diameter secticns of electrical \\ c:nduit joined by couclings. !n additicn, he has had a heck i aelced to a Oi:e ca :: join witn the end of :ne c:nduit sections wnich will be used :: pick u the key -ing. Shculd you ali:w nin

= assertie ne 2:01 and use it? Ex: lain wnv cr wnv net.

(2.0) 5ecti:n ! ::n:inuec rex: : ace I t "O I t1-

i, '.t j ~ e 1-I. 5. The aximum accivity contained in ene gas decay tank is limited to a) What is the limit and who is responsible to assure this limit is not exceeded? (1.0) b) What is the reisen for this limit? (1.0) O

,2 ri j I. -s J. SPECIF!C CpERAT:';G CHARACTER:ST:CS (14) J. 1. Li th j um hydroxide and hydrazine are two chemicals that are added to the reactor coolant system. a) Discuss when it may be necessary to add these chemicals. (1.5) b) What precautions must be observed when handling these chemicals? (1.0) J. 2. Curing the unit heatup, cne of the steps requires a hard bubble degasificaticn when the ccolant temperature reaches

3500F, a) Outline hcw this steo is performed.

(1.0) b) What would be the censecuences if this step was not performed? Assume pcwer operations with steady state and transient conditicns. (1.5) J. 3. About two years ago, TMI Unit Cne went critical during a plant heatup, while the RC temperatu e was SC50F, a) What precedural steps were modified to, prevent a repeat incident? (1.5) b) What is the L.C.O. for minimum R.C. temperature for criticality and what is the basis for this L.C.O.? (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) Mcw dces the operating staff ccmply with this limi. ation? Include centrols the staff must manipulate. (1.5) b) Why is this condition required? (1.0) J. 5. Assume a reactor startup is in pregress and within 5% of rod position for criticality. At the same ;ime, an I.C.S. recresentative is " fine tur.ing" the contrcl system. Suddenly, all turbine bypass valves go full valves cpen. Assume (i) one main feed pump in service and (ii) R.C. temperature decreases 0 at 20 F/ min. a) What protective device (s) shculd respond to trip the reactor if no action is taken? [0.3) b) What immediate action is recuired by the c erating staff? (0. 7 ) Secticn J continued on next cace i3 047 m 9 S

~, ,1 . _. _.. _ _ ~.. -. .j e ,a J. 5. c) Assume no acticn by the c:erating staff. ' shat systems will res;cnd if the turbine by-pass valves cannot be -,u,t. Attempt to shcw if t.Me plant systems alli oF-sh w1:i not terminate tn..is transient without cpera:or action. (2.2) f '6d Y.S ():1

~ e - ^ =.... ' ~ = ~ -= 3 e ~ (s K. FUEL PANDLIN3 L CCRE P:RAMETERS (14) K. 1. Listed belcw are several fuel handling devices and maneuvers. List and explain the curcose of the interlock (s) during each maneuver. a) Centrol rod handling mechanism while inserting and withdrawing control reds. (1.0) b) R0tatice 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 on one of the safety rcds in grcup 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 trcuble shooting cannot begin for several hcurs, would the axial pcwer imbalance and/or the quadrant pcwer tilt beccme the limiting condition for operation? Explain your answer. (1.5) K. 3. Initial fuel icading at most pWRs develops as a " slab". The source is located in the center and the fuel is leaded cutward (see figure K-3). Temporary chambers (A&B) are located in the vessel and subcritical multiplication plots are made for each secticn of the slab loading. a) Sketch the expected plot of subcritical multiplication for each chamber. (1.5) b) Explain any difference in tne plots. (2.0) K. 4 During the initial power escailation and immediately folicwing a control rad interchange, the rate of pcwer 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 cransient and centrolled conditions. (0.5) b) Why is it necessary to perform a control red interchange and why are pcwer increases reduced to 3%/hr? (2.0) K. 5. Attached is figure 1A, Core Excess Reactivity, for your facility. E<clain the shape of the curve during the first 100 E?PD. (1.5)

2, i, e. .m L. ACMINISTRATIVE PROCEDURES. CONDITIONS AND LIMITATIONS (14) L.

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

a) What parameters and limits are considered in the safety limits for your station? (1.5) b) What instrumertation in the reactor protecting system shculd prevent reaching a safety limit? (1.5) c) What are the plant conditicns for hot stancby? (0.5) L.

2. Title 10 CFR Part 55, Operators Licenses, defines an cperator as any individual wno manipulates a control of a facility.

a) Cefine control 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? Explain. (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 completed.

a) What shift records are maintained? (1.5) b) What conditicns are required in order for an entire shift to be relieved? (1.0) c) List the shift organization required by the technical specificatiens during (i) fuel leading and (ii) plant s ta rtup. (1.5) L.

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

For each condition belcw provide (i) imediate and subsequent action and (ii) the reason for your action, ir.cluding any administrative limits. a) The unit is shutdown for OTSG tube inspection. You are informed that the sodium hydroxide tank was inadvertantly lined up to the decay heat pumps. Abcut half of the tank volume is left. (1.5) b) The plant is at rated ccwer during the winter. The auxiliary operator informs ycu that the vent (s) cn the 5WST tank seem to have frozen due to condensation and ice for ation. (1.0) Section L continued cn next cace 79 050 3

i 4 3 .m 6 L. 4 c) During a test of the containment isolaticn alves, one of the valves begins t leak at the packing gland. The test engineer suggests he can "back seat the valve by holding in the ocen relay with an insulated screwdriver at the motor control center. (1.5) 79 051 m O M S

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,. a Material Half-Li fe disinterraticn ac/cl ue/ 1 u e /:1-' c/=1 -6 -0 A-41 1.33 h 13 2xlo 9 Exlo I Co-6o 53 y 25 3xio-I lxio-3 ll 1210-8 5x10-5 ' I-131 8.1 d o.36 9xio" ,6x10-5 l 1xio-lo 3xio-T rr-85 10.8 y o.ch 1xio-5 l 3xio-7 Ni-65 l 25 h o.59 9xio Exlo.3 3xlo_6 i -7 -4 1x10 4 -4 -14 -6 I, 6x10 5x10 Pu-239 2.hx10 y 0.cc8 2x10-12 1x10 -9 i .5 l -1] I 6 sr-90 28 y 1x10 l 1x10 ' j 3xlo 3x10 -O Xe-135 92 h o.25 hx10 1xio -9 -5 -lo -6 Any sic.gle radiccuclide with T > 2 hr 3x10 9xlo 1xio 3x10 g which dces not decay by a er spentanecus fissics ieutrens per e-f Average flux to deliver Neutren Enerry("ZV) I ecuivalent to 1 rem 100 rze= in ho he-as 6 'O:er._si 970xio 670 0.02 LCox106 260 05 43xic6 30 lo 2hx10D 17 LIITA? AISCF.F"'ICN CO:. e ACEC (c=-1) Energy UG'/)I eter l Cencrete l Iren l Lead 05 o.c90 0.21 0.63 17 1.0 o.C67 0.15 o.kh o.77 15 0.c57 0.13 o.ko c.57 2.o 0.0k3 0.11 0 33 0 51 25 o.CL2 o.C97 o.31 o.49 3.o 0.035 0.C58 o.30 0.h7 NFML'U S AtiD CCN7E?sICNS h/hr = 6CI I, = I,e-/'* I, = I. N= N,e d2 d2 T= 4e I = 0.693 p= E#V M T x 3x1010 g=1 + g 3: T= 1 T 's - 1-A T e-q 43 1 cal = 3 78 liters 1 kg = 2.21bs N[=6.c?x10 A. 4e 1 in = 2 54 es 1 ge/c=3 = 62.h lbc/ft3 1% =3 14 + q x ' 1 yr = 3 15xioIsec. 1 ft) = 7.k3 Esl e =2 72 t

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~ 4 t U. S. b'JC1. EAR REGJ1ATCRY C2lCSSICff RE.GR CFERATCR LICENSE EX#CSATICN hacility Three Mile Isivd - Unit 2 Reactor Type

Np. g y,1 Date Adninistered c/ / 7 /77 Exr.iner J. J. Surv Applican:

/g 30 Instructicns to Applicant: Use separate paper for the e ssers; staple questien sheet en top cf the r.swer sheets. Points for each questien are An everall indicated in jarenthesis after the questien. score of 70% or greater is passing. Categcry % of Applicant's % of Valm Total Score Cat. Value 14 13.5 I2.Y hl_ A. Principles of Reactor Opera:ica 14 13.5 } 0, la T B. Features of Facility Cesign o 17 16 l).[ lt/ C. General Cperating Characteristics 16 15 O.F EO D. Instr ents and Centrois 16 15 I f, [ b $1 E. Safety and Faer;ency Systens I I, Y ) F. Standard and Energency Cperating 16 15 Procedures 3.7 G. Radiatien Centrol and Safety 13 12 6 $'M r-1C6 C. Final Grade G t 78 074

3 4 2 "A. PRINCIPLES OF REACTCR CPERATICN (14) A. 1. a) What is meant by the term " delayed neutron fraction"? (1.0) b) How and why does the delayed neutron fraction change during core lifetime? (1. 5) A. 2. The TMI procedure for approach to criticality requires the operating staff to plot a cne 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 used as cart of your answer. (1.5) A. 3. AssumeycurreactorifIcn a stable. 3 DPM startup rate as ::cwer level reacnes 2 x 10-en the intermediate range monitor. (Time is "0"). a) Plot the trace en Figure Al until the power level reaches 10-c. (1.5) b) Af ter a two-ainute " hold" to take data at 10-8 the operator withdraws the control reds to obtain a 1 DPM 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 on figure Al and a reactor trip cccurred. Plot and discuss the resulting trace for the remaining period of time on figure Al. (1.0) A. 4. Xenon conditions include periods when xenen is at equilibrium and at peak conditions, a) What is meant by equilibrium xenen? (1.0) b) How dces peak xencn develop? (1.5) c) Assume a plant startup and power escallation is in progress at the tice of peak xenen. Mcw does this differ frcm a power escallation after a one-week shutdown? Note: a sketch may be used as :: art of your answer. It is not necessary to include values for xenon. (1.5) A. 5. Water is used as a ccolant in your reactor. List three other functions of water in the react:r. (1.5) 7E C75 J

= 2 ..-4 1 S. FEATURES OF FACILITY DESIGN (14) B. 1. The nuclear services closed cooling water (NSCCW) system provides cooling water for the nuclear ccmpenents during nor al operation ar.d also provides cooling for components during a loss of ccolant accident. a) List those c:mponents which use the NSCCW durino normal operation. Listthecompcnents(i)Insideand(ii)Outside the reactor building. (2.5) b) What ccmponents.are supplied during a LOCA? Note: ' if ' ~ components appear in part A, mark them with an asterisk *. (1.0) 3. 2. Condensate and feedwater are heated in a number of Feat exchanges before water enters the steam generators. Sketch a one-line diagram of the ccmcined systems from the condenser until it leaves the last heat exchanger. Include all pumos and source of heat for each heat exchanper for one string. (2.5) 8. 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 number of hydrants, hosereel stations, 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) c) Explain the difference between the wet pipe sprinkler and the deluge water systems. (1.0) B. 4 One of the ccmpcnents associated with the reactor 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, where may the operators discharge the exccss liquid? (0.5) 3. 5. One of the Limits and Preventions require that systems containing liquids should be free of air refore they are operated to prevent water ha=er. a) What is water hacer and why shculd plant cperators be concerned about water ha m er? (1.0) b) Coes water hammer cccur only with systems containing licuid and air? Explain ycur answer. (1.0) e m> p'., t u s b

4 t e + ~C. GENERAL OPERATING CHARACTERISTICS (17) C. 1. The ance-through steam generators (OTSG) at your facility will produce superneated steam during power operaticn. a) With the aid of a simple sketch, expiain hcw superheat is accceplished in the OTSG. (1.5 ) b) How does superheat vary frem 15 to 100% power? A sketch may be used as cart of your answer. (1.0) C. 2. The follcwing are two of the limitations and precautiens in 11:e ~ Unit Startup procedure. Provide the value and reascn for each of the limitations. a) Do not attempt to start a reactor ::olant pump wnen pcwer is greater than (2.0) b) During startuo and shutdcwn when reactor power is less than percent, the OTSG water level shall be maintained between and (2.0) C. 3. Unless scecified by the reactor engineer, group 8 (APSR) will be positicned about 32% withdrawn prior to an approach to criticality. a) With the aid of a sketch, indicate how the APSRs worth varies between 0 - 100% withdrawn. (Include approximate reactivity values) (1. 5 ) b) Explain when it is necessary to mcve 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 concentration in the RCS and the cooling water to the r.echanism. a) What 3-e the sources of gas in the R.C.S.? (1.0) b) Why is gas concentration 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 temcerature of cooling water to the CRCM may vary frcm 85 - 1050F. Is there a preferred tem:erature range? Expl ai n. (1.0) C. 5. Assume rated pcwer canditions and a trip occurs to a reactor coolant pump, a) Provide the initial steady state values for parameters listad in figure C5. (1.0) b) Show the res:cnse to these parameters until conditiens stabilize. Assume the reacter dces not trip. (2.0) i

3 .-4 1 D. INSTRUMENTS AND CCliTROL (16) D. 1. Refer to the transient in cuestien C.5. Discuss the action of the control system (s) for each of the folicwing parameters: a) Load MWe (1.5) b) Pressurizer level (1.5) c) Feedwater ficw A & B (2.0) D. 2. The intermediate channel utilizes a ccmpensated ion cha.h.ber'(CIC). a) With the aid of a simple sketch, explain the operating principle of a CIC. (1.0) b) Is compensation required at 1C0?.,15%, or icwer pcwer levels 1 Explain your answer. (1. 0 ) , cyspc,.e iu c o +,e-s>ns usar i~ s v ar&n c) C2" : per at :- k r.;;,ithe " overlap" requirements between the i other channels? Explain. (1.0) D. 3. The pressurizer electrcmatic relief value (RC-2) may be operated in the manual or autcmatic mode. Discuss hcw the-valve may be operated in eacn =cde. A simple sketch may be used as part of your answer. (2.0) Pelta 3:9/ /E D. 4 Unit 2 of TMI utilizes a baron feed ard bleeddcontroller, a) What are the input signals to the controller? (1.0) b) What are the output signals of the controller? .(1.5) c) When is the centroller utilized? (0,5) D. 5. Two of the alarms on the Diamond Control panel are the (i) motor rotation fault and the (ii) asymmetric monitor, a) Discuss the purpose of each alarm. (1.5) b) What immediate action is required by the cperating staff for each alarm? (1.5) a _. c >C ~2 ,~ i u

2 .-4 5 -~ ~ E. SAFETY AND EMERGENCY SYSTEMS (15) E. 1. The pcwer distribution system at TMI-2 contains two DC buses, 2-1DC and 2-20C. a) Use a one-line diagram to shcw what compcnents sucoly these busses and their source (s) of power. Include any cross ties between these burses and supplies. (2.0) b) If a station blackcut occurs, what leads are supplied by the D.C. bus until the emergency diesel generators begio to supply pcwer? (1.5) E. 2. List the cor.diticns that will cause a reactor trip with four R.C. pumps in service. Include present set points. (2.5) E. 3. Assume a loss of coolant acci. dant (LOCA) occurs. The LCCA increases reactor building pressure at 2 PSI / minute and doubles each minute (2, 4, 8, etc.). Utill:e this rate for the following: a) What automatic action (s) occur during the first four minutes? (1.0) b) hhatinstrumentswilltheoperatorobservetoassureinitial and continuing 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 provided with a feedwater latching system. a) List the instrumentation associated with this system and explain the logic that will actuate the system. (1.5) b) List the autcmatic action that will occur when this system is actuated. Assume rated ;cwer operation. (2.0) E. 5. Assume a primary to secrndary leak develcas in ene of the OTSG. The leak begins at one GPM and doubles eveer 5 minutes (1, 2, 4, 8, etc.) a) List the systems that will alert the operator. Attempt to arrange them in order of increasing leak rate. (1.0) b) When the cperators have identified the laaking GTSG, should they trip the reactor or begin an orderly shutdown? Explain the reascn for your answer. (1.5) r'o- (s rn d./ u6J

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-s s F. STANDARD AND EMERGENCY CPERATING PRCCECURES (15) F. 1. Assume your unit is at the pcwer level cutoff point and waiting to meet the requirements before increasing power. All systems are in autcmatic. A malfunction cccurs in the circulating water system and vacuum begins to decrease at 1" Mg/ min. a) What is the power level cutoff point and when may pcwer be increased abcve this level? (1. 5 ) b) How will the ICS respond as vacuum decreuses? (1.0) c) What immediate action is required by the cperatcr (assume vacuum continues to cecrease)? (1.0) d) List the 5 eat sink (s) available if ccrrective action can not restore vacuum. (1.0) F. 2. One of the Limits and Precautions of the Decay Heat /Injecticn Pumps states "When operating in the ES mode with suction on the building sump, pump discharge must be throtled to GPM to limit runout. Do not throttle below GRi as this may result in cavitation and inadequate cooling." a) What are the above ficw rates? (0,5) b) What is pump runout 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 this condition on the 0.H./ Injection pumps? (1.5) F. 3. During reactor startup, limits are imposed on the amount of reactivity which may be added above and below the estimated critical positicn. a) What are these limits and hcw does the operator convert them ~ to rod position? Assume an ECP of 50f. cn Group 6/7. (1.5) b) What action (s) are required if these limits are exceeded? (1.5) F. J. In the event of a reactor trip, list the manual act;cns required by the TMI-2 emergency precedure. (3.0) F. 5. In the event of an unanticipated criticality: a) What sycotons would alert the operating staff? (1.0) b) What immediate acticn is recuired by the operater? (1.0) r,:c3 f_t C0 S

J b -t e -s G. RADIATICN CONTROL AND SAFETY (13) G. I. Assume you have been working in a contaminated area. After you remove your protective clothing you monitor ycurself :efore leaving the area, a) Should an ionization or GM device be used? Explain. (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 hours, you discover your dosimeter is off scale and ycu leave the area. A survey indicates a hot spot on a drain line reads 1200 mr/hr samma at two feet. Your distance from the line was accut five feet.

3) Estimate the dose which you may have received.

(1.5) b) If your previous exposure to the quarter was 900 mr, what exposure limits may have been exceeded? (1.0) c) With the aid of a simale sketch, explain the operating principle of a pocket dosimeter. (1.0) G. 3. Three of the classified areas in the Radiation protection Manual at TMI are (i) controlled area (ii) radiation 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 radicactive spill, one of the basic rules is to administer aid to anyone who is injured. What other basic rules apply? (2.0) G. 5. During 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 instrumentation will alert the perscnnel in the reactor building of any release of fissicn products? (1.0) b) What autcmatic action (s) may occur if radiation levels exceed preset limits? (1.0) c; What acticns are required by the centrol r cm staff? (0.5) G}} 0%4 S

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