ML19220B467
| ML19220B467 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/17/1977 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | Withheld METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904260252 | |
| Download: ML19220B467 (44) | |
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1 U. S. S*J' EG RECUlaKRY CnC55ICri RECR CFE.UTCR 1.lCENSE EX.VENCICli Facility Three Mile Is13rd - Unit 2 Reactor 7,ge
- wo - 9W Date Ac.-d.nistered 9// 7 /77 Exx-lner _
J. J. Surv
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/f90 Instr.:cti:ns to.irplicant:
Use separa:e paper fer de ar.s..ers; starle questien sheet ca ::p of d e a-r.er sheets. Feints for each questien are An everall indicated in pareneesis after de question.
score of 70% or greater is passing.
Category 1 of 4plicant's
% of Vedm Tc:31 Score Cat. Value C
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/l A.
Principles of Reactor Cpera:ica la 13.5 14 13.5 ll.1
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Features of Facility Cesign 17 16 i (, O m[(
C.
General Cperating C;aracteristics 15 15 13, O
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Instreents and Centrols IbL 9
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Safety and Z: ergency Systems 15 15 16 15 l3. 0 hl F.
Standard and E.:ergency Cperating Procedures 13 12
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Fadiation Centrol and Safety lC
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1.
a) What is meant by the term " delayed eutrcn fraction"?
(1.0) b) Ecw and why does the delayed neutrcn fraction change during ccre 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) Mcw is the data utilized? Note: a sketch may be used as cart of your answer.
~
(1.5)
A.
3.
Assume jcur reac:ce is en a s:able..a JPM startuo rate as pcwer le;el reaches 2 x 10-'I cn :ne intermediate range moni:Or.
(Tire is "0").
a) Plot the trace en Figure Al until the pcaer level reaches 10-c.
(1.5) b) After a two-minute "hcid" to take data at 10-3 the operator withdraws the control rods to obtain a 1 0FM startup rate.
Plot this trace for 5 minutes;. include the pericd of rod motion.
Exclain any chan;es during the five minutes.
(1.5) c) Assume the reactor was at 10-6 at 3 minutes on ficure Al and a reactor trip cccurred.
Plot and discuss the esulting trace for the remaining period of time en figure A1.
(1. 0 )
A.
4 Xenon canditions include periods when xenon is at ecuilibrium and at peak ccnditions, a) What is mean by equilibrium xenen?
(1.0) b) Mcw dces ;eak xencn develoc?
(1.5) c) Assume a plant startup anu pcwer escallation is in crogress at the time of peak xenen. Mcw dces inis differ frcm a sewer escallaticn arter a one-aeek shutccwn? Note: a sketch may be used as : art 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 other functions of water in the reactor.
(1.5)
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1.
The nuclear services cicsed cooline water (NSCCW) system provides
- cling water for the nuclear c: :: rent: during ncreal c:eraticn and also provides cooling for ::m:enents during a loss of ::clant accident.
a) List those compcnents which use the NSCCW durine normal operation. Listthe::mponents(i)Inrideand{ii)Outside the react:r building.
(2.5)
- 5) What c mponents are supplied during a LOCA? "cte:. if.
cccccnents appear in part A, mark them with an asterisk *.
(1.0) 5.
2.
Condensate and feedwater are be..! '
a num:er o'
-o=*
s t:t a'r c e c bef:re water enters the.
Sket:n 2......:
diagram or the combir.ed sja.;-a.r:m tne c:nde ler until it u
leaves the last " eat exchanger.
!nclude all pumps anc scurce of heat for each heat exchanger for one string.
(2.5) 3.
3.
The fire protection system at ycur facility consists of a number of pumps lccated in unit cne and two. The fire main su;clies a number of hydrants, hosereel stations, a wet pipe sprinkler and a deluge system.
a) List all pumps which supply the fire main; includa u
_it.
~_~
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 ccmpcnents associated with the reactor c:clant system is the R. C. drain tank.
a) List the equipment which discharges to tne drain tanks.
(1.0) b) What' limits apply to the tank? Include the reascns for these limits.
(1.5) c)
If the drain tank level is :o high, wnere may the c:erators discharge the excess licuid?
(0.5) 3.
5.
Cne of the Limits and preventions retuire that systems cen:sining liquids should be free of air before they are c;erated to prevent water hammer.
a) What is water hammer and ~hy shculd plant ::erators be
- ncerned abcut water hammer?
(1.0) b) Oces aater hammer occur Only wi n systems :0ntaining licuid and air? Exclain ycur answer.
(1.0) 4% ur;
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1.
The ence-:hrcugh steam generat:rs (OTSG) a ycur facility will produce su:erneated staam during ;cwer ::eration, a) With the aid of a simole sket:h, explain hcw su erheat is accomplished in :he OTSG.
(1. 5 )
b) Hcw does sucernea vary fr:m 15 to ILC% pcwer? A sketch may be used as : art of your ana er.
(1.0)
C.
2.
The folicwing are two of the limitaticns and precautions in the
~
Unit Startup prccedure. Provide the value and reason for each of ne limitaticns.
a) Co not attempt to start a reac:Or c:clant :tro wnen power is greater than (2.0) b) Curing startuo and shut:an anen reactor ocwer is less than percent, the OTSG water level snall :e maintained
- etween and (2.0)
C.
3.
Unless specified by the reactor engineer, group 8 (APSR) will be positicned about 32% withdrawn prior to an approach to criticality.
a) !!ith the aid of a sketch, indicate hcw the APSRs worth varies between 0 - ICC% withdrawn.
(Include apprcximate reactivity valuer (1.5) b) Exclain when it is necessary to move the APSRs (i) in and (ii) out.
(2.0)
C.
4 Two of the li lits and precau:icns for the control red drives concer; the gas concentraticq in the RCS and the cooling water to the mechanism.
a) What.are the scurces of gas in the R.C.S.?
u.0) b) Why is gas c:ncentration a factor for the CRCMs?
(1.0) c)
Is i necessary to maintain a minimum concentration of gas in the RCS during pcwer cperation? Explain your answer.
(1.0) d) The temcerature of cooling water to the CRCM may vary frcm 85 - IC5cF.
Is there a preferred temcerature range? Explain.
(1.0)
C.
5.
Assume rated pcwer c nditions and a trip cc:urs to a reactor 2001an: ;tmo.
a) Pr vide One initial staady state values f:r parameters listed in figure C5.
(1.0) b) Show tne res:ense to these ;arame:ers until c:nditiers s:2:ilize.
Assume the reac: r does r.o tric.
(2.0)
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D.
1.
Refer to the transient in cuestien C.5.
Discuss tne action of the ccntrol systam(s) for each of :ne folicwing 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 ccccensated icn cha.m:er'(CIC).
- 3) With the aid of a simale sketch, explain the c:erating crinciple of a CIC.
(1.0) b) Is compens'ation recuired at iCC",15%, cr icwer pcwer levels 3 Explain,ycur answer.
c,4 (1.0)
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c c) W-m2- -
m " overlap" repuirements between the other channels? Explain.
(1.0)
D.
3.
The pressuri:er electromatic relief value (RC-2) may be operated in the anual or autc atic mcde.
Discuss how the talve may be cperated in eacn mcde. A simple sketch may be used as part of your answer.
(2.0)
D.
4.
Unit 2 of TMI utilizes a bcron feed and bleed ccntroller, 41_ d.v>, m _.
a) What are the incut-signals to the ccntroller?
(1.0) b) What are the cutput signals of the controller?
(1.5) c) When is tne controller utilized?
(0,5)
D.
5.
Two of the alarms on the Diamond Centrol panel are the (i) motor rotation fault and the (ii) asyrretric monitor.
a) Discuss the purgese of each alarm.
(1.5) b) What immediate action is required by the operating staff for each alarm?
(1.5) e b, 4 q t
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E.
1.
The ;cwer distributicn system a: T:1!-Z c:n ains :.,o DC buses, 2-lCC and 2-20C.
a) Use a cne-line diagram to shcw what c meonents sue:1y these busses and their source (s) of ;cwer.
Include any cross ties between these busses and supplies.
(2.0) b) If a station blackcut cc:urs, what leads are supplied by the D.C. bus until the emergency diesel generators begin to supply pcwer?
(1.5)
E.
2.
List the conditions that will cause a reactor trip witn four R.C.
- um
- s in service.
Include : resent se: points.
(2.5)
E.
3.
Assume a less of c:clant accident (LCCA) cc:urs.
The LOCA increases reac:;r building ressure at 2?SI/ minute and dcubles each minute (2, 4, 3, etc.).
Ut111:e this rate fcr the foiicwing:
a)
'! hat aut:matic action (s) occur during the first fcur minutes?
(1,0) b) What instruments will the operator ceserve to assure initial and c:ntinuing c;eration of equipment?
(2.5) c) What is the postulated peak react:r building pressure in the design basis LOCA?
(0.5)
E.
a.
Three Mile Island Unit 2 is provided with a feedwater latching system.
a) List the instrumentation asscciated with this system and explain
- ne logic that will actuate the system.
(1.5) b) List the automatic action that will occur when this sys:em is actuated. Assume rated ;;wer c;eraticn.
(2.0)
- . nssume a primary to secon,ary leak c. eve,icts in ne or :ne 0...6:u.
...ne leak begins at cne GPM and dcubles every minutes (1, 2, a, 3, etc.)
a) Lis the systems that will alert the ::erator. Attempt to arrange them in order of increasing leak rate.
(1.0) b) When the operaters have icentified the leaking OTSG, should they trip the reactor cr begin an orderly snutdcwn? Explain the reason 70r your answer.
(1.3)
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F.
l.
Assume ycur unit is at the pcwer level cut:ff point and waiting to meet the recuirement; before increasing pcwer. All systems are in automatic. A malfunction cc:urs in the circulating water system and vacuum begins to decrease at 1" Hg/ min.
a) What is the power 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 acticn is repuired by the operator (assume vacuum continues to decrease)?
(1.0) c) List tne heat sink (s) availa:le if corrective action 3-rest:re vacuum.
(1.0)
F.
2.
Cne of the Limits and Precautions of the Decay Heat /:njecti:n Fucos states "When cperating in the E3 mcde with suction cn the building sump, pump discharge must be throtled to GFM to limit runcut.
Co not throttle belcw GFM as this may result in cavitation and ir.adecuate cooling."
a) What are the above ficw rates?
(0.5) b) What is pumo runcut and what are the consecuences if the pumo c ntinues to operate in this condition?
(1.5) c) What is cavitation and hcw would the operator abserve this condition en the D.H./ Injection pumps?
(1.5)
F.
3.
Curing reactor startuo, limits are imposed on the amcunt of reactivity wnich may te added above and below the estimated critical positicn.
a) What are these limits and 50w dces tne cperator c:nvert them to red position? Assume an ECP of 50% cn Grouc 6/7.
(1.5) b) What action (s) are required if these limits are e.xceeded?
(1.5)
F.
4 In the event of a reactor trip, list the manual actions required by the TMI-2 emergency procedure.
(3.0)
F.
5.
In the event of an unanticipated criticality; a) What symptons aculd alert the Operating staff?
O.0) a)
What immediate acticn is recuired by the coerator?
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G.
1.
assume ycu have been wcrking in a ::ntaminated area.
After you remove ycur protective clothing you rcnitar ycurself before leaving the area, a) Shculd an icnization or GM device be used? Expl a i n.
(1.0) b) What type of radiaticn will the instrument detect?
(0.7) c) What is the criteria for determining if a person is. contaminated?
(0.3)
G.
2.
After working in area for two ncurs, y:u discover your desimeter is off scale and ycu leave the area. A survey indica es a hot spot on a drain line reads 1200 mr/hr gamma at :wo feet.
Ycur distance fr:m
~
the line was abcut five feet.
a) Estimate the dose wnich ycu may have received.
(1.5) b)
If ycur previous exposure to the quarter was 900 mr, what exposure limits may have been exceedec?
(1.0) c) With the aid of a simple sketch, explain the operating principle of a pccket dosimeter.
(1.0)
G.
3.
Three of the classified areas in the Radiaticn Protection Manual at TMI are (i) controlled 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 your answer.
(1.0)
G.
4 In the event of a radicactive spill, cne of tre basic rules is to administer aid to anycne who is injured. What other basic rules apply?
(2.0) 3.
5.
During a refuel'ng Outace you are in the reactor building on the main fuel handling bridge. A scent fuel element drops into the core.
a) What instrumentation will alert the perscnnel in the reactor building of any release of fissicn pr ducts?
(1.0) b) What autcmatic action (s) may cccur if radiation levels exceed preset limits?
(1.0)
- ) What actions are recuired :y the ::n:rol r:cm staf '
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