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Examination Rept on Operator License Issued for TMI-2. Written Examination Encl.Operating Test Administered 770921
	ML19220B453
Person / Time
Site:	Crane
Issue date:	10/17/1977
From:	Collins P; Office of Nuclear Reactor Regulation
To:	Withheld; METROPOLITAN EDISON CO.
References
	NUDOCS 7904260155
	Download: ML19220B453 (59)
	v • d • e

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.J. J. Su:v Applican I 'l s V Instruc:icns to Anplicant: Use separate paper for the answers; staple questien sheet Poin:s for each questica are en tcp of the r.sser sheets. An everall indicated 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 tesign 14 13.5 I 1,9 kL C. Ceneral Cperating Ciaracteristics 17 16 16 15 I 3, '( E0 D. Instnnents and Centmis ) O' f E. Safety and Energency Systens l.'. < *1 s 10 1: / l. #1 F. Standard and Energency Operating 16 _ 15 Procedures C t-n3 /6 G. Radiatica Centrol and Safety ji 12 ~~ / luo ne r.r \\ e ranal,ra,e u .q c. t p

r~ c 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 during ccre lifetime? (1.5) A. 2. The Dil procedure for approach to criticality requires the operating 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 as cart of your answer. (1.5) A. 3. Assume ycur reactor is On a stable. 3 CPM startuo rate as pcwer level 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 reaches 10-d. (1.5) b) After a two-minute " hold" to take data at 10-8 the operator withdraws 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 Al and a reacter trip occurred. Plot and discuss the result ng i tr3ce for the remaining period of time en figure A1. (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 dces peak xenon deveico? (1.5) c) Assume a plant startup anu power escallation is in progress at the time of pe6k xencn. Mcw does this differ frca a ocwer escallation after a one-aeek shutdcwn? Note: a sketch may be used as part of your answer. It is not necessary to include values for xenen. (1.5) A. 5. Water is used as a ccolant in your reacter. List three othei functicns of water in the reactor. (1.5) o+n i t) . Erl

i a 3. FE?TlRESOFFACILIT' DESIGN (la) B. 1. The nuclaar ser, ices closec cooling aater (NSCCN) system cr; ides ccoling water for the nuclear campenents during normal cperaticn and also provides ccoling for ccmpcnents during a loss of coolant

accident, a) List those components which use the NSCCW durino normal operation.

List the components (i) Inside and (ii) Cutside the 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 exchanges before wate-enters the steam generators. Sketch a one-line diagram of the combined systems from the condenser until it leaves the last heat exchanger. Include all pumas and scurce of heat for each heat exchancer for one stranc. (2.5) B. 3. The fire protection system at your facility consists of a number of pumps located in unit cne and two. The fire main supplies a number of hydrants, hosereel stations, a wet pipe sprinkler and a deluge systen.. a) List all pumps which supply the fire main; include cacacity and when each pump will start. (2.0) b) Explain the difference between the wet pipe sprinkler and the deluge water systems. (1.0) B. 4 Cne of the ccmocnents 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 tne reascns for these limits. (1.5) c) If the drain tank le/el is tcc high, where may the operatcrs discnarge the excess liquid? (0.5) E. 5. Cne of the Limits and Preventions require that systems ccntaining liquids shculd be free of air before they are ogerated to prevent water hammer.

) ahat is water hammer and why shculd plant coerators be concerned about wcr hammer?

(i.0) b) Oces water harrer cccur only aith systems containing licuid and air? Explain your answer. (1.0) 9.~_. r g

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i m e C. GENEM L OPERATING CPARACTERISTICS (17) C. 1. The ence-through steam generators (OTSG) at your facility will procuce superheated steam curing pcwer 0:eration. a) With the aid of a simple sketch, explain hcw superheat is accceplished in the OTSG. (1.5) b) Hati does su;erheat vary frca 15 to 100% power? A sketch may be 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 of the limitations, a) Co not attempt to start a reactor coolant pump when ;ower is greater than (2.0) b) During startuo and shutdown 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 positioned 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 drives c:ncern 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.? (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 in the RCS during pcwer operatient -x;iain your answer. (1.0) d) The tem;erature of ccoling water to the CRCM may vary frem 25 - 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:r coolant cump, a) Previce the initial steady state values for parameters listec in figure CS. (1,0) b) Shcw the res:cnse to inese :arameters until canditicns stacil!:e. Assume the reactor dces no cria-(2.3) r ,w ~~ f g

-? -m J. I'iSiEME:iTS AND 1 TROL (16) 2. 1. Refer to the transient in cuestion C.5. Discuss -he acticn of the 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 principle of 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><eceby C' A n 4 c) Car :: p: rat 4w.. ...c.,e the ", overlap" requirements between the other channels? Explain. (1.0) D. 3. The pressurizer electrcmati; celiet value (RC-2) may be operated in the manual or autcratic mcde. Discuss how the. valve may be operated in eacn moce. A simple sketch may be used as part of your answer. (2.0) (c.u. u : 1 D. 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) motor rotation 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 for each alarm? (1.5) t..r ....a h 9

_g e e-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 these busses and their source (s) of pcwer. Include any cross ties between these busses and supplies. (2.0) b) If a station blackout occurs, what Icads are supplied by the D.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 increases reactor 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 initial 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 prcvided with a feedwater latching system. a) List the instrumentation associated with this system and explain the icgic that will actuate the system. (1.5) b) List the autcmatic action that will occur when this system is actuated. 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 co arrarge them in order of increasing leak rate. (1.0) b) When the operators have identified the leaking GT5G, should they trip the reactor or begin an cederly shutdcwn? Explain the reascn for your answer. (1.5) v . -, ~, [4 J

e~ F. STAbARD A 40 E'!ERGE ICY CPERAT:,G ?CCECURES (16) F. l. Assume ycur unit is at the pcwer level cutoff point and waiting Oc meet the requirements before increasing power. All systems are in autcmatic. A malfunction cccurs in the circulating water system and vacuum begins tc decrease at 1" Fg/ min. a) What is the pcwer level cutoff point and when may pcuar be increased 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 (assume vacuum continues to decrease)? (1.0) d) List the heat sink (s) available if corrective action can not restore 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 and inadequate cooling." a) What are the abcve ficw rates? (0.5) b) What is pump runcut and what are the consequences if the pump continues tc cperate :n this condition? (1. 5 ) c) What is cavitation and how would the operator obse ve this ccndition on the D.H./ Injection pumps? (1.5) F. 3. Curing reactor startup, limits are imposed cn the amcunt of reactivity which may be added acc.e and below the estimated critical

positien, a) What 'are these limits and hcw does the operatcr convert enem to 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 by the 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) ag i, ' "' G 1 e

t 3. PADI'ATION CCNTROL AND SAFETY (13) G. 1. Assume you have been working in a contamina:ed area. After y:u remove your pr:tective clothing you mcnitor yourself before leaving 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 is off scale and ycu leave the area. A survey indicates a hot sect en a drain line reads 1200 mr/hr gamma at two feet. Ycur cistance frcm the 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 exposure limits may have been exceeded? (1.0) c) With the aid of a imple sketch, explain the operating principle of a pocket dosimeter. (1.0) G. 3. Three of the classified are: 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) 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 rules apply? (2.0) G. 5. During a refueling cu: age you are in the reacter building cn the main fuel handling bridge. A spent fuel element drops into the core. a) What instrumentation will aler: the personnel in the reactor building of any release of fissicn pecducts? (1.0) b) What autcmatic action (s) may cccur if radiation levels exceed preset limits? (1.0) c) What acticns are required by tne c:n:rol rcca staff? (0.5) 9 4 m

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[- D'- = - ~ ~ _. ~ ,n,. ~ -__-__.'~;- - -_ _~ __LT.'q ] ^ -'- -M _.-+ -e g__ b_- _h _e_ _~_,_.= - = _ +. - -__ = = _ -. _ _.- .._j.-h -e-.-..e.. ,e_ _-e*- e e.-- -e. . -. - _ y-... - - _ . _._. - _.. _ _ _.. ~- -.-s-C-- .=, __,g,_ ~~ . ~ _, _. - _. ~ ~ ~. ' ^. ~~~~~~'?'- '^ . -. _ _. ' ~ -^ - ' _.. - _ - -. ~ ^ ^ ~~~- ' ~ ^_ _1.~~M ~ m.,7,,, me--._ 4 + - -. =. .em.N_ a h,._ e _%e _-mm. ~ ~ _. _..r_ .b ~ - - - - -. ) C.-. J.~_.___ ~. _. _ - ^ ^ ~ ~. -._ _. _~. ~~~ I I 7-.. - '"__.---~7__ ^~ Y~ ~ _' ~ _. 2~^Y--~."C-~-. "-~- EE$ (J . ' ' ' ' ^ ~ ' ~~~ -.'7.,'C ~ ~ - ___,.1"'"' -.__.'_-_ __-_ "~-_ _,, ~- - - ~2__ ^ -_17.^*~'^.'~~'~~' 4 .*'*e ~~' ^ ~ C'~ [ _ _ ~ -. ~ ~ -. ~. --.E.- ~. '~ w .___._O"_.'.-~~.'"___. '~=__~.I~1_~CY.".__- __"CC.~.._ - -. _ _ _ _ - ~. ~"~ _ _ _ _ = _. 7 1 r- -. _._---- ___,__~ _. - _^ ' ~ _._ -. ~ ^. - ~ ^ ',. ' ~ _. _-- ~~. ^^'"- _ _. ~ ~ ' _ - e '.T._.'-~_-$I'l~_-'.~_I""_-~*~I L _C._ ~ _ _. _ ~ _ *. _. _. _ - _____-__~_.~~_-'~L-~~_~_^- - _. - -. - - _ _ ._~_!._-._J~;-~~-_ ' - -"""._. ~~:.Z*~~~~__"" -~ e

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4

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TW1e 1. u.IS"I'.l.A iECUS 10 CFR 20 Appendix B f T.ble 1 1 ble II ~ e Ener,y Col 1 Cai II Cat 1 Cul II j e FE7 per A ir Vater Air Water sta t e.-i si - alf-life disinteerstien ac/nl u e /-J. ue/- ue/1 l -6 -8 . A kl l.83 h 13 2x10 9 hx10. co-60 5a y 25 3.c10-I (1x10~3 h 1 10~0 -5 5x10 I-131 8.1 d 0 36 9x10' 6x10~5 l 1x10-10 3x10-I c Kr-85 l 10.8 y l 0.04 lx10~5 3x10-I -7 i -8 -k lii-65 I 25 h 0 59 9x10 'l Ex10-3 3x10 - lx10 i 4 -a i Pu-239 2.kx10 y 0.cc8 2x10 w-l 1x10 j 1 -o 6x10 4 l5x10 I -9 I -2 t - 11 l -6 Sr-90 i. 20 y lx10 lx10 3x10 I 3x10 -O Xe-135 92 h 0.25 Ex10 1x10 Any single rad!.cn_:lide with T > 2 h-3x10 9x10 lx10~ 3x10 i which d:es act deca:- by x cr sp:ntaneous fissi:=> lieutrons per .2 Average flux to deliver I

e + -- r qy ( yE7 )

ecuivalent to 1 re: 100 -.~e: in 10 heu : I 6 Thernal 970x10 670 0.C2 kC0x10h 230 05 h3x109 30 10 2kx10D 17 a::- --.= ( c =-H L. .,. 3 1_1. _,. _..,, C., u. zner D'E7) I veter I C:ncrete i Iren I lead l 05 0.c90 0.21 0.63 17 1.0 0.067 0.15 c.kh 0 77 15 s. 0.057 0.13 0.ko 0 57 2.0 '~ 0.Ca5 0.11 0 33 0 51 25 0.C42 0.C97 0 31 0.L9 30 0.035 i

0. C-58 0 30 C.kT

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2 5h :

1 ::l::3 = 62.i it /^t3 .a 3*? 1 in <[ =3 14 != 4 + i: _, xq , y- =3._x,.. sec. ..~.- =.. - .a-e =2., e o ... 3 etr ee -=une +=w e

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= soa fee s_ n y au c nt c/e b Iora /m Am a f & y ec e~e

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f. ',$

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A

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0 \\\\\\\\\\x p //, @?~ ', k g '.b' - f',, j%9,, ~g/, i v gy/,4,y* fjjjj%iV,'e-+g /// V 4 x , _ E e _1,. TEST TARGET (MT-3) I.O ??11 3h li;? !!g2 e ?ii g=2n I.I L = lll' 8 1.25 1.4 __ 'li I.6 l + 6" + %' //p ll?, N// &+X//h ~, '(; 'I S h' g ,y ;, gv

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