ML19220B461
| ML19220B461 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/17/1977 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | Withheld METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904260208 | |
| Download: ML19220B461 (65) | |
Text
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Fxr.iner J. J. Bu:v
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Use separate paper for the answers; s:xple questien shee:
Peints for each questica are cn :cp cf 9.e ans er sheets.
An everall indicated in parenthesis after the ques:icn.
score cf 70% er grea:er is pc.ssing.
t, cf Categc y
\\ ef
);plicen:'s Cat. Value Score Principles of Reac:cr Cperatica Valm _
Tc:al_
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1.
1;
.eansres o: rac h.rf aesign i -
3.
r i-.
W C.
General Cperating C aracteristics
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D.
Inst:.: ents a.d Centrol.s C
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E.
Safety and E.mergenef Syste s id 15
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F.
Standard and E.mergency Operatin;;
i 15 15 Procedures G.
Fadiatica Centr:1 and Safety 13 12 c- '
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1.
a) What is meant by tne term " delayed neutr:n fracti:n' ?
(1.0) m.
t) How and whv does the delayed neutron fracticn change :urir.g core life:1me?
1.5 he oli procecure,,or approach to critica,ilty recuires t.u.e n.
4.
i cperating staff to plot a One over M (1/M) during r:d withdrawal.
- 3) 'What data is required for the 1/M pict?
(0.5)
,I b) How is the data utilized? Note:
a sketch may te used as cart of your answer.
(1.5)
A.
3.
Assume ycur reacter is.:n a sta:1e. 3 0FM startu: rate a: ;cwer level reaches, 2 x 10-' A on the intermediate range moni;or.
?-:
=- 1 s,, v,, J.
si -
e a) ? lot the : race en rigure Al until the ;caer level reaches 10-c.
(1.5) b) After a two-minute "hcid" to take data at 10-8 the operator withdraws the control rods to cctain a 1 GPM star uo rate.
Flo: this trace fer 5 minutes;. include ne perice c# rod motion.
-xclain any changes during the,.1ve minutes.
(1.0) c) Assume the reactor was at 10-6 at 3 minutes en figure Al and a reactor trip cccurred.
Dict and discuss tre resul:ing trace for the remaining pericd of time en figure Al.
(1.0 )
U A.
Xencn c:nditions include periods when xenon is at ecuilibrium
{
anc at peak c;nditions.
F a) What is meant by epuilibriu.1 xenen?
(1.0) t' b) Mcw d:es peak xenon develop?
(1.5)
I
- ) Assume a plant startu; anu pcwer escallaticn is in progress i
at the time of :eak xencn.
Hca dces this differ frcm a cwer escallaticn after a cne-week shutd wn? Note:
a sketch may be used as : art of your answer.
It is not necessary t: include vaiues for xenen.
(1.5)
A.
5.
'ater is used as a c clant in your reactor. List three c her functions of water in the reac cr.
(1.5)78-018
..,. Y,r a, u.,i.
(,i. )
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i 5.
1.
The nuclear services closec cccling sa:er (NSCCW) system cravides cccling water for the nuclear ccmper.ents during normal c;eraticn anc also provides ccoling for comocnents during a 1:ss of cc:lan:
accicent.
r j
a) List those ccmpenents wnicn use the NSC"W durin-normal c eration.
List the compcnents (i) Inside and fii) Outside
'..".a. r a..= c+.. r *. i. l d i. n g.
2.:
. if b)
'n' hat components are supplied during a LOCA? Note:
com;cnents a;; ear in : art A, cark them with an asterisk'.
(1.0)
E.
2.
Ccndensate and feedwater are heated in a number of heat exchanges
. k = *..h.=.-.. a. - l i. n e
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3.
The fire protecticn system at your facility c:nsists of a number of ; umps Iccatec in unit one anc two.
The fire main sup; lies a number of hydrants, hosereel staticns, a wet pipe s:rinkler and a del uc.e s.ystem.
l a) List all pumps which su; ply the fire main; include ca:acity and when each pumo will start.
(2.0) e.x. ' a i n *.". e d i #. #. =. - a.. ~- = " e *.w =. a. r * ". a. w a.. -i.ee s rinkler. 2 ~d
.a.
a..
e deluge water systems.
(1.0) 2 s w c d. a..a s. w i.5
- ..*.e r a..s c..-.
- c..- ^v 'i = n
- s y s =_..
c.
cm.
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m..
is One R. C. drain tank.
2,i
- 4. 3.
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, a. s *..* *... a.
d.r.a i a. *=nks.
(1. 0 )
b)
What limits acoly to :ne tank?
Include One eascns for these I ' m.i ts.
(1.5) c)
'f the drain tank level is ::c high, where may the ::eratcrs
. e. 2... a., e.. ~a
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3 liquics snculd be free of air :efore they are c; era:ed : preven u>.ar.
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(1.5) l b) H:w d:es superheat vary from 15 to 100% pcwer? A sketch may be used as cart of your answer.
(1.0)
C.
s precautions in i.u.e ine 70,tewing are two er. :ne,simi:2:icns ano Unit startup rocedure. Provide the value and reascn f:r each of
.w.
l4..2. 2 4.uns.
a)
"--.c*.2...=~.~-.
s..= r..=. c..= c.. r.- ^ 1 m= r '
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percent, ne UTSG aa er level snali :e maintained
- e: ween and (2.2' I
C.
3.
Unless specified by the reacter engineer, c.rcup 3 (APSRi will be positioned about 32% withdrawn prior to an approach to criticality.
a)
'.!ith tne aid of a sketch, indicate how the ApSR's worth varies between 0 - ICC% withdrawn.
('nclude apprcximate reactivity values)
(1.5)
_-x;,iain when it is necessarv : :ve the
- n. S,.s i
in and s
rr
( e.1 9.0 C.
4 Two of the limits and precautions f:r the centrol red drives c:ncern the gas ccncentr ation in the RCS and the c0 cling water to
. + e
..a. c..u a. a. s....
a) ' Wha; are the sources of gas in the R.C.S.?
(1.0) b) '. ".. v
- 4. 2
..= s c n - c.a....= *. 4. v...=
'.'.*..r#..-
'..".a. F. 7. ~" u.s ?.
(1.0) e.
- c. )
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..a4n.2.4i n.,. e.. 5......- co.....e.w,
- e. -,s 'n a j..
i
....... r tne RCS during pcwer operaticn? Expiain ycur answer.
(1.0) s '.
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- c. :. r..j ~, 7 ac...
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1.
0efer :c the transient in question C.5.
Dis.uss :ne ac:icn cf
- ne cen:rol system (s) for eacn of the follcwing carare:ers:
a) Load P!de (1.5) b) Pressurizer level (1.5) c) Feedwater ficw A & B (2.0)
D.
2.
The intecediate channel utilizes a ccmpensatet' icncnabber'(CIC).
a) 'With the aid of a simple sketch, explain the coerating crinciple of a CIC.
(1.0) b)
Is ccc::ensation recuired at 1:0%,15",, or iceer ;cwer levelst Explain ycur answer.
(1.t-)
4,,a d w ;
- <,, y ~ n. - u. : ' - ~ v :<%
c ) e.
.-%.+...._
- e-
- he,' aver, tap" requ;remen:s ::etween tne
.s other channels? Expla i n.
(1.0)
D.
3.
The pressurizer electrcmatic relief value (RC-2) may be c::erated in the manual or autc~atic rede. Discuss hcw the valve may be c;erated in eacn acde. A sic;1e sketch may be used as part of your answer.
(2.0) p m.. (
D.
4 Unit 2 of Ti4I utili:es a bcren feed and bleec>centrciler.
~
a) What are the input signals to the cen:rclier?
(1.0) b) 'What are the cu:;ut signais of the centroller?
(1.5) c) 'When is the centroller utili:ed?
(0,5)
- ne a sams en :ne Diamen; Centrol panei are tne (1, mc:cr
.ac c.
e rc:ation fault and the (ii) asy=etric monitor.
a) Discuss the ;ur;cse of each alarm.
(1.5) b) 'What i=ediate ac:icn is recuired by the c::erating staff for each alarm?
(l.5) c._ m n i
U hl-e
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=
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so
- - wu and :-c,n..c.
l a) Use a cne-line diagram to shew what ::mecnents sucoly these busses and their source (s) Of ;cwer.
Incluce any crcss ties between these busses and supplies.
(2.0) b)
If a station blackcut occurs, what icads are supplied by the D.C. bus until tne emergency ciesel genera:ces begin to Jupply pcwer?
(1.5)
E.
2.
List the c nditions that will cause a reac'.cr trip with fcur R.C.
pum s in service.
- nclude present set points.
(2.5)
E.
3.
Assume a less of : clan accident (LCCA) Occurs.
The LCCA increases cc,...r ui'i....
,s_ee".-c.
- 3..Oc'.,"..'.."m.=.
2 ~- " ~.* l a_.c e2..
.4".=.
m
(.,.,.,
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n....,
.- o..,.
.2.=..
r
...a.
. s i e ~en1 n 3.-
v a) What automatic action (s) cccur during the first fcur minutes?
(1.0)
U b) What instruments will the cperator c:sc-ve to assure initial and centinuinc :;eration of epuipment?
(2.5)
I t
t-c) What is the pcstulated peak react:r building pressure in the design basis LCCA?
(0,5) l t
E.
a.
Three Mile Island Unit 2 is provided with a feedwater latching system.
a) List the instrumentation asscciated with this system and exclain the icgic that will actuate the system.
(1.5) b) List the automatic action that will cccur when this system is l-actuated. Assume rated pcwer cperation.
(2.0)
[
i:
.ssume a crimarv to se::ncary. tea < deve. ices in one ci 'ne J ou.
.. ice leak bec. ins at One G.;M and doucles everv.5. minutes (1, 2, 1, 8,etc.)
i t.
t.
a) List the systems tha uill alert tne c erator. Attemot to arrange them in Order of increasing leak rate.
(1.0) b) When the c:eraters ave identified the leaking CT53, should
- hey trip the reactor :r begin an orderly shutdcwn? Explain the reascn for your answer.
(1.5) 7g.-022
i Dam.r"4
., "',, ;-.% J ;.,. y L P O N9 3 itb
--.m,.,,
-s
-,,c;,LLM;3
(,10 )
I F *s L v w.
1.
Assume your uni: is at the ;cwer level cutoff :cin: and waiting to mee :ne requirements before increasing ;cwer. All systems are in au :matic. A malfunction occurs in the circulating water
~
system anc vacuum begins to decrease at 1" Hg/ min.
a) What is the pcwer level cutoff point and when may power be increased above this level?
(1.5) b) Ecw will the ICS respond as vacu.m decreases?
(1.0) c) What immediate acticn is required by the :;erator (assume vacuum centinues to decrease)?
(1.0) c) List the heat sink (s) availacle if ::rrective action can not res: Ore vacuum.
(1.0) o.
- c.. 3, #.
- . a. I. '.. d. ' s.' n d :. a. r..' ". '. '. c a. s o #.
..". e, e r..' y' '.a. 2 + ' i. n.; >.+. i r n ".... s F
states "When cperating in the E5 mcde with suction on the build:ng sum;, pump discharge must be t rctled to GPM to limit runcut.
6 Uc not throttle below C'M as this may result in cavitation and inadequate cooling."
a) What are the abcve ficw rates?
(0.5) b) What is pum; runcut and what are the c nsecuences if the 0u 0 c ntinues :: cperate in this condition?
(1.5) l w.,i c) ' nat is cavitation and hcw wculd the cpera:Or observe this i-a conditicn on the D.H./ Injection ; umps?
(1.5) r
- t..
F.
3.
Curing reac: r startuo, limits are imposed en the amount of reactivity wnich may be added above and below the estimated critical
.. n.- a.. a.....
a).ihat are tnere limits and how dces the 0;eratcr convert..ien
- rod :csiticn? Assume an ECF cf 5C% cn Group 5/7.
(1.5) b).ihat a::icn(s) are recuirec if tnese limits are exceeded?
(1.5)
F.
- n :ne event cf a reae.tcr trip, list :ne manual actions recuired by
- ne TM:-2 emergency procedure.
(3.0)
F.
5.
- n the even: cf an unanticipated criticality:
fl.0) s S.-
- e. v~. *.. n s u.. d _' 'i _ r '.
2, a..c.
o.
'... =..-. o. r =. '... 3 m
b) ana: im ecia:e ac:icn is ce:uiree by the ::er3:;r7 (1.:)
W 023 9%
3 I
+
i.
I t
- r e; T. r a wy i :~ _ : qn q::r. s y
- n. )
m G.
1.
Assume ycu have been working in a ccntaminated area. After you
~
i remcve ycur ;rctective cic:hing you mcnitor yourself before
. a s v.,. 3e.-
., a. o __.
--a I
i a) Shculd an icnication or Gi1 device be used? Expl a i n.
(1.0) b) What type of radiation will tne instrument detect?
(0.7) c) What is the criteria for determining if a person is. contaminated?
(0.8)
G.
2.
After wcrking in area for two hcurs, you disccver your ccsimeter is off scale and ycu leave the area. A survey indicates a het spo: en a drain line reads 1200 mr/hr gamma at :wa feet.
Your distance frcm the line was abcut five feet.
a) Estimate the dcse which ycu may have -eceived.
(1.5) b)
If ycur previous exposure :c the cuarter was.;CO mr,..nac exposure limits may have been exceeded?
(1.0) c) With the aid cf a simple sketch, explain the operating principle of a pccket dosimeter.
(1.0) 3.
3.
Three cf the classified areas in the Radia:icn Protection A nual at T:iI are (i) centrolled area (ii) raciaticn area and (iii) high radiaticn area.
a) Define eaca area; include any limits.
(1.5) l b) May the NRC examiner enter each area? Exclain your answer.
(1.0)
G.
4 In the event of a radicactive spill, cne of tne basic rules is to administer aid to anycne who is injured.
What otner basic rules l
apply?
(2.0) i G.
5.
Curing a refueling cutage you are in the reactor building en the Tain fuel handling bridge. A spent fuel element crccs into the Core.
a'
'iha: instrumentation will alert :ne perscnnel in the reacter cuildinc. cf any release of fissicn -recuc s?
(1.0) b) Lihat au:cmatic actien(s) may cccur if radiaticn levels exceed crese limits?
(1.0) c) What acticns are recuired by :ne cen:rci ecem s:a?
(0.5) 98 024 i
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