ML19220B455
| ML19220B455 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/17/1978 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | Withheld METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904260173 | |
| Download: ML19220B455 (45) | |
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7 U. S. NUC. EAR REGU1ATORY CD MISSICN RE.Cd CPE.uTCR LICINSE EX#2N.CICN Facility Three Mile island - Unit 2 Reacter Type w
g *,w Date Ad:~inistered at/91,7 Fxr iner J. J. Eurv Applicr.t' 17 /F I:.str.:cticns :: Applicr. :
Use separate paper for de r.s'.sers; staple questien sheet Feints for each questien are en tcp of the r. seer sheets.
An everall indicated in parendesis after de ques:icn.
sccre of 701 er greater is passin;;.
Cate;;crf
% cf Applicant's i of Value Tc 2_
<cere Cat. Value.
1 A.
Principles of Reac:cr Operatien 14 13.5 13.1 39_
'1.h 37 3.
Features of Facility Cesign l'
13.5 Ia:,D cQ C.
General Cperating Characteristics 17 15 D.
Inst:.r.ent.s and Centrols i9.(
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Saferf and 6.ergency Systers c
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15 15 Freceduns b.
G.
Radiaticn Centr:1 and So.ety 72 _
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A.
1.
- 3) What is meant by the term " del yed neutron fraction"'
(1.0) b) Mcw and why dces the delayed neutrcn fraction change during core lifetime?
(1.5)
A.
2.
The TMI procedure for approach to criticality recuires the ccerating staff to clot a One over M (1/M) during red withdrawal.
a) What data is required for the 1/M plot?
(0.5) b) Hcw is the data utiliced? Note:
a sketch may be used as cart of your answe.
(1.5)
A.
3.
Asstre ycur reactcr is,cn a stabis.S CFM startup rate as ;cwer level reaches 2 x 10-'
cn the intermediate range Tcnitor.
(Time is "0").
a) Plot the trace en Figure Al until the pcwer level reaches 10-o.
(1. 5 )
b) After a two-minute " hold" to take data at 10-8 the operatcr withdraws the control rods to obtain a 1 DEM startup rate.
Plot nis trace for 5 minutes;. include the period of red
.txclain any caanges during tn.e,1ve minutes.
(1.3) u mot 1cn.
c) Assume the reactor was at 10-6 at 3 minutes on figure Al and a reactcr trip cccurred. Plot and discuss the resulting trace for the remaining period or time on figure Al.
(1.0)
A.
4 Xencn conditicns include periods when xer.cn is at equilibrium and at peak conditicns.
a) What is meant by equilibrium xenon?
(1.0) b) Hcw does peak xencn develop?
(1.5) c) Assume a plant startup anc power escallation is in progress at tne tire of ceak xenen. Mcw dces this ciffer frcm a power esttilaticn after a cne-week shutdcwn? Note: a sketcn may ce used is cart of your answer.
It is not necessary tc include z2iues for xenen.
(1.5)
A.
5.
Water is used as a ccolait in vcur reactor.
List three other functicns of water in the reaciar.
(1.5) e cr1 t 1 A
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FEATLPE3 C: F2CILITY OES!Q,1 (la) 3.
1.
The nuclear services closed :: cling aater (NSCCW) system crovides
- cling water for ne nu: lear ::mecnents during nar al c:eration and also pr:vides cooling for ::: crents during a loss of ccolant accident.
- 3) List those c:mponents which use the NSCCW during normal cperaticn. List the c mpcnents (i) Inside and (ii) Cutside the reactor building.
(2.5) b) What c:=;cnents are supplied during a LCCA? Note:
if -
c:mpenents appear in part A, mark them with an asterisk *.
(1.0) 3.
2.
C ndensate and feedwater are Meated in a number of heat exchanges befcr e aa er enters the steam generat:rs.
Sketch a ene-line diagram of the ccm:ined systems fr:m the ::ndenser until it leaves the last heat exchanger.
- nclude all pumps and scurce of neat for each heat exchanger for cne string.
(2.5) 3.
3.
The fire protection system at ycur facility c nsists of a number of pumps located in unit one and two. The fire main sup lies a num:er of hydrants, hcsereel stations, a wet pipe sprinkler and a deluge system.
a) List all pumps wnich supply the fire main; incluce c2:acity and when each ptmp will start.
(2.0)
- ) Explain the difference between the wet pipe sprinkler and :he deluge water systems.
(1.0) 3.
4 One of the ccm:enents associated with the reactor coolant system is the R. C. crain tank.
a) List the equipment whicn discharges :: the drain tanks.
(1.0) b) What linits apply to the tank? :nclude :he reascns fcr :nese limits.
(1.5) c)
If the drain tank level is : o hign, anere may the 0; erat:rs discharge the excess liquid?
(0.5) 3.
5.
One of the Limits and Preventions recuire that systems centaining licuids snculd be free of air before they are cperated :: ;revent water hamm.er.
a) What is wa:er hammer and any should 013nt :erators be concernec accut water hammer?
(1.0) b) Oces water mammer occur :nly aith systems : ntaining liquic and air? Explain jour answer.
(1.3) er%
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3ENE AL CPE:ATIN3 CPARACTEUST!CS (17)
C.
1.
The ence-through steam genera: Ors (CTSG) at fcur facility will
- r
- duce su;erneated steam during pcwer 0;'eration.
a) With the aid of a simole sket:h, explain new superheat is accceplished in the OT5G.
(1.5 )
b) Hcw does superheat vary fr:m 15 to 1C0% pcwer? A sketch may be used as cart of ycur answer.
(1.0)
C.
2.
The foll: wing are two of the limitations and precautions in ihe Unit Startup procedure. Frevide the value and reasen fcr each of the limitaticns.
a) Co not attemot to start a reactor c:clant pumo when pcwer is greater : nan (2.0)
- ) Curing startue and shutdcan ahen reac Or ::cwer is less than percent, the UT55 water level snall be maintainec
- etween and (2.0)
C.
3.
Unless s::ecified by the reactor engineer, grcup 3 (APSR) will be positioned about 32% withdrawn prior to an apprcach to criticality.
- 3) With the aid of a sketch, indicate hcw the APSRs worth varies between 0 - IC0% withdrawn.
(Include approximate reactivity values)
(1.5) b) Exclain when it is necessary to move the Ap5Rs (i) in and (ii) cut.
(C.0)
C.
4 Too of the limits and precauticns fer the control red drives concern the gas concentra:icn in the RCS and the cooling water to the mechanism.
a) 'What.are the scur:es of gas in the R.C.S.?
(1.0) b) 'Why is gas c:ncentration a factor for the CRCMs?
(1.0) c)
Is it necessary to maintain a minimum car. cec: ration of gas in the RCS during pcwer :peration? Ex;:iain your answer.
(1.0) d) The tem;erature of c:oling water to the CRCM may vary from 85 - IC50F.
Is there a preferred tem;;erature range? Explain.
(1.0)
C.
5.
Assume rated :cwer c:ncitions and a trip occurs to a reactor c: clan: ;um::.
a)
?- vice One initial steady state values for :arametert listed in figure C5.
(1.0) b) Show the res:cnse :: :hese :arameters until ::nditions stacilize.
Assume ne reac::r d:es no: tria.
(2.0) d ' l' f ;
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INSTOL7ENT5 ED CCf! TROL (15) 2.
1.
Defer :: the transie
- in cuestian C.5.
Discuss ne action of
- ne con:r:1 system (s) for eacn of the folicwing parame:ers:
a) Load PWe (1.5) b) Fressuri:er level (1.5) c) Feedwater ficw A & B (2.0)
D.
2.
The intermediate channel utilizes a ccmpensatec icn chamber (CIC).
a) With the aid of a simple sketch, explain the c;erating principle of a CIC.
(1.0) b) Is ccm:ensation required at iCC",15",, or icwer ;caer levels?.
Explain vcur answer.
(1.0)
Cw L p <m w"r-uJ % w dm c),e m...
a the Overlap" recuirements betwee.( the other cnanneis? Explain.
(1,0 )
D.
3.
The pressurizer electromatic relief value (RC-2) may be c;erated in the manual or aut: atic mcde. Discuss how the valve may be c;erated in eacn cde. A simple ske:ch may be used as part of your answer.
(2.0)
D.
4 Unit 2 cf T:il utilizes a bcren feed and bleec cENIN a) What are the input signals to the ccntroller?
(1.0) b) What are the cutput signals of the c:ntroller?
(1.5) c) When is the controller utilized?
(0.5)
O.
5.
Two of :ne alar.s en the Diamend Centrol panel are the (i) motor rotaticn fault and the (ii) ary=etric mcnitor.
a) Discuss the purpose of each alarm.
(1. 5 )
b) What i=ediate acticn is recuired by the c;erating scaff for each alarm?
(I.5) cr; g
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E.
SAFETY AND O'E9.GENCY SYSTEMS (15)
E.
1.
The :caer distributicn system at TMI-2 c ntains two CC buses, 2-lCC and 2-2CC.
a) Use a one-line diagram to shcw wnat components succly these busses and their source (s) of ;cwer.
Include any cross ties between these busses and supplies.
(2.0) b)
If a staticn blackcut occurs, what leads are supplied by the D.C. bus until the emergency diesel generators begin to su ply
- cwer?
(1.5)
E.
2.
List the conditions that will cause 3 eacter trip witn four R.C.
pumos in service.
Include present set ;cints.
(2.5)
E.
3.
Assume a loss of ::clant accident (L2CA) cccurs. The LCCA increases reacter building cressure at 2?S:/ minute and doubles eacn mir.ute (2, 4, 5, etc.).
utli1:e this rate for tne fcilcwing:
a)
'.ihat autcmatic action (s) cccur during the first f ur minutes?
(1.0) b) What instruments will the cperat:r cbserve to assure initial-~~
(2.5) and continuing operation of equipment?
c) What is tre pcstulated peak reactor building pressure in the design basis LCCA?
(0.5)
E.
4 Three Mile Island Unit 2 is provid2d with a feedwater latchirg system.
a) List tne instrumentaticn associated with this system and explain ne icgic :nat will actuate the system.
(1.5) b) List the aut:matic action that will :ccur when this system is actuated. Assume rated power operaticn.
(2.0)
E.
5.
Assume a primary to secondary leak develcos in cne of the CTSG.
The leak begins at cne GPM and doubles every i minutes (1, 2, 4, 3, etc.)
a) List the systems that will alert the coerator. Attem:t to arrange them in order of increasing leak rate.
(1.0) b) When the operators have identified the leaking OT5G, should they trip the reactor er begin an orderly shutdown?
Ex: lain the reason for your answer.
(1.5)
.- a, c,a f 1
2 R
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. D.
..D
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- sa:a rs
.s 1.
Assume your unit is at tne pcwer level :utoff coint and.saitir.g to mee: :ne requirements before in:reasing :cwer. All systems are in aut:matic. A malfanction cccurs in the circulating water system and vacuum begins to decrease a: 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 acticn is required by the operator (assume vacuum continues to decrease)?
(1.0) d) List the heat sink (s) available if : rrective acticn can not restore vacuum.
(1.0)
F.
2.
Cne of the Limits and Precauticns of the Cecay Heat /!njection Purcs states "When operating in the ES mcde with suction en the building sumo, pump discharge must be throtled to GPM to limit runcut.
Do not thro:tle below GPfi as this may result in cavitaticn and inadequate cooling."
a) What are the abcve ficw ratas?
(0,5) b) What is pump runcut and what are the consequences if the ;umo continues tc cperate in this ccndition?
(1.51 c) What is cavitaticn and hcw would the operator cbserve this condition on the D.n./Injecticn pumps?
(1.5)
F.
3.
During reactor startuo, limits are imccsea en the arcunt of reactivity which may be added above and belcw the estimated critical ccsiticn.
a) What'are these limits and hcw dces the c; erat r convert them to red positicn? Assume an ECP of 50% cn Grouc 5/7.
(1.5) b) What action (s) are recuired if tnese limits are exceedec?
(1.5)
F.
4.
In the event of a reac:cr trip, list the manual actions required by the TMI-2 emergency procedure.
(3.0)
F.
5.
In the event of an ur.anticipa:ed criticality:
a) What symotors would aler; the ccerating staff?
(1.0)
- ) Wha: 7:ediate acticn is recuired :y the c: era::r?
(1.0) 4
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G.
1.
Assure you have been werking in a ccntaminated area. Af ter ycu re cve ycur prctective cic:hing you scniter ycurself before leaving the area.
a) Shculd an icnization er GM device be used? ~xplain.
(1.0) b) What type of radiation will the instrument detect?
(0.7) c) What is the criteria for determining if a perscn is.:entaminated?
(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 hat spct en a drain line reads 1200 mr/hr gamma at two feet. Your distance fecm
- ne line was abcut five feet.
- 3) 5 stimate the dose wnicn ycu ay have received.
(1.5) b)
If your previcus exposure to the quarter was 900 mr, what exposure limits may have been exceeded?
(1.0) c) With the aid of a simple sketch, explain the Operating principle of 2 :::ket dosimeter.
(1.0)
G.
3.
Three of the classified areas in the Raciition Protection Manual at TMI are (i) centrc11ed area (ii) radiation area and (iii) high radiation area, a) :efine each area; include any limits.
(1.5) b) May the NRC examiner enter each area? Ixclain your answer.
(1.0)
G.
4 In the event of a radioactive spill, cne of the basic rules is to administer aid to anycne who is injured.
What etner basic rules apcly?
(2.0)
G.
5.
During a refueling cutage ycu are in the reacter cuilding cn the main fuel handling bridge. A spent fuel element drc;s in c the ccre.
a) What instrurentaticn will alert the perscnnel in the reacter building of any release of fission products?
(1.0) b) What auccmatic acticn(s) may occur if radiation levels exceed
- rese: limits?
(1.0) c) What acticns are recuired cy the centrol recm staff' (0.5) c e r)
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Table '-
Inerg Col 1 COL 11
[
col 1 Cal II
- 'at e r MEV ;er A Lr
';a t e r Air disinte-2ti:n a /:1 ue/-l u c / l'
- / 1
a t e r i al S1f-l' fe l
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A 2.1 i
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l l 5x10
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10.S y l
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0 59 9x10 Ex10-3 l
-7
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25 h k
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]
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1
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y l
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Neutr:ns per c:'
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Ener U27)I
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