ML19220B446
| ML19220B446 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 10/17/1977 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904260123 | |
| Download: ML19220B446 (66) | |
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U. S. NUC. EAR REGULCKY CMCSS10; REACICR CFEMZR LICENSE EMCN,CICN Three '4ile Isl and - Unit 2 Facility _
Reactor 7ype
- wq _ aw a / /7 /77 Date Adninistered __
E.xa iner J. J. Buzy 4plicant
~ /
/'ila Instr.:::ic.s to 4plicant:
Use separa:e paper for the ar_r. vers; s::ple questien sheet Points for each questien are en :cp of the r.swer sheets.
An everall indicated in parenthesis after the questien.
score of 70% or greater is passing.
Categerf
% ef 4plicant's
% of Value Total Secre Cat. Value A.
Principles of Reac:cr Operatien
/ 3, b h[
14 13.5
_ 14 13.5
//, Y S}
B.
Features of Facility resign
/
17 16
/d 5 MD C.
General Cperating Characteristics 16 15
/3, %
I3 D
Instruaents and Centrols C
Sa:ety and c.nergency Systems l L/, '7 oG n
io l e-
/ 3. '/
t F.
Standard and Emergency Operating ib 16 15 FrcCedures 6.
G.
Radiatien Centrel and Safety 13 12 lC6
\\
Fi;:a1 Grade Y,
e m
= _ _ _ _ _ _
c A.
FRI:;C!PLES CF REACTCR 0? ERAT!C!i (14)
A.
1.
a) What is meant by the term " delayed aeutren fraction"?
(1.0) b) How and why does the delayed neutron fraction change during core lifet;me?
(1.5)
A.
2.
The DII procedure for approach to criticality requires the operating staff to plot a one over M (1/M) during rod withdrawal.
a) What data is required for the 1/M plot?
(0.5) b) Hcw is the data utilized? ?;ote: a sketch may be used as cart of ycur answer.
(1.5)
A.
3.
Assume ycur reactor is en a s acle. 3 ON startua r te as :cwer level reaches 2 x 10-'I on the intermediate range monitor.
(Tire 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 operator withdraws the centrol rods to obtain a 1 CEM startup rate.
Plot this trace for 5 minutes;. include the period of rod motion.
Exclag any changes during the five minutes.
(i.5) c) Assume the reactor was at 10-6 at 3 minutes en figure Al and a reactor trip occurred.
Plot and discuss the resulting trace for the remaining pericd of time on figure Al.
(1.0)
A.
4.
Xenon ccnditions include pericds when xeron is at ecuilibrium and at peak ccnditions.
a) What is meant by equilibrium xenon?
(1.0) b) Ecw dces peak xencn develep?
(1.5) c) Assume a plant startup and ;cwer escallaticn is in prcgress at the time of peak xenen. Ecw dces this differ fr:m a pcwer escaliation after a one-week shutdcwn? Note:
a sketch mav be used as cart of vcur answer.
It is not necessary"to include values fo'r xenon.
(1.5)
A.
5.
Water is used as a ccolant in ycur reacter.
List three cther functi:ns of water in ::e reacter.
(1.5)
I ki
- 14. %
m a
3.
EATURES OF FACILITY DESIGN (la) 3.
1.
The nuclear services closed cooling water (NSCCW) system ::rovides cooling water for the nuclear concenents curing ncr~al cceration and also provides ccoling for ccmponents during a loss of coolant accident.
a) List those ccm;cnents which use the NSCCW during nor al operaticn. List the ccmpenents (i) Inside and (ii) Cutside the reactor building.
(2.5) b) What ccmpcnents are supplied during a LOCA? Note:. if ccmpenents appear in part A, mark them with an asterisk *.
(1.0) 3.
2.
Ccndensate and feedwater are heated in a number of heat exchanges before water enters the stesm genera:ces.
Sketch a one-line diagram of the cc=bined systems frca the condenser until it leaves the last heat exchanger.
Include all pumps and scurce of heat for each heat exchancer for one string.
(2.5) 3.
3.
The fire protection system at ycur facility consists of a number of pumps located in unit one and two. The fire main supplies a number o hydrants, hosereel stations, a wet pipe sprinkler and a deluge s istem, 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) 3.
4 Cne of the camponents ascociated with the reactor ccolant system is the R. C. drain tank.
a) List the ecuipment which discharges :: the drain tanks.
(1.0) b) What'linits acply c the :ank?
Include the reascns for these limits.
(1.5) c)
If the drain tank level is tco high, snere may the cceraccrs discharge the excess liquid?
(0.5) 3.
5.
One of the Limits and Preventions require that systems containing liquids shculd :e free of air before they are cperated to prevent water ha:mer.
a) What is water hammer and wny shculd plant ccera:ces ':e ccncerned abcut uatar ha.rer?
(1.0) b) Oces water narrer cccur only ei:n systems containing licuid and air? Exclain ycur answer.
(1.0) sI
' ' '.Q,
C.
SENERAL CPERATING CFARACTERISTICS (17)
C.
1.
The ence-through steam genera:ces (OTSG) at your facility will produce sucerneated steam during pcwer c:eraticn.
a) With the aid of a simple sketch, exclain how superheat is acccmplished in the 0753.
(1.5) b) Mcw dces superheat vary from 15 to 1C0% pcwer? A sketch may be used as cart of your answer.
(1.0)
C.
2.
The felicwing are two of the limitaticns and precautiens in the Unit Startup precedure. Provide the value and reason for each of the limitations.
a) Cc not attemot to start a reactor c:clant pump when pcwer is greater than (2.0) b) Curing startuo and shutdowr. when reac:Or ;cwer is less than percent, the DT53 water level shall be maintained ce: ween and (2.0)
C.
3.
Unless specified by the reactor engineer, grcup 8 (APSR) will be
- csitioned abcut 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 Oc mcve the APSRs (i) in anc (ii) cut.
(2.0)
C.
4 Two of the limits and precautiens for the control rod drives concern the gas concentration in the RCS and the ccoling water to the mechanism.
a) What.are the scurces of gas in the R.C.S.?
(1.0) b) Why is gas c;ncentraticn a factor for the CRCMs?
(1.0)
- )
Is it necessary to maintain a minimum :0ncentration of gas in
- ne RCS during pcwer operaticn? Ex;iain your answer.
(1.0) d) The tcm;erature of cooling water to the CRCM may vary fecm 25 - IC5cF.
Is there a preferred temperature range? Excl a i n.
(1.0)
C.
5.
Assume rated :cwer c:nditi:ns and a trip occurs :0 a reac:ce c: clan: : cmc.
a) Previde the initial steady sta:e values for parameters listed in igure C5.
(1.0) b) Shcw the res:cnse ta these ;arame:ers un:il c:nditicns stabilire.
Assume the reaccer dce no: tric.
(2.0) g (,
8
e
";37q, v.. :.mi
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s.
1 D.
l.
Refer :: the transient in question C.5.
Discuss the action of tne centrol system (s) for each cf the fcllcwing parameters:
a) Lead MWe (1.5) b) Pressuri:er level (1.5) c) Feedwater ficw A a 3 (2. 0 )
D.
2.
The intermediate channel utilizes a ccmpensated icn chamber (CIC).
a) With the aid of a simpie sketch, exclain the cperating principle of a CIC.
.(1.0) b)
Is ccmcensation required at 100",15", or icwer pcwer levels 1 Explain ycur answer, (1.0)
[y,,,a ay 5 us Gjmf!LUA7*'oro ALS'uc 7~ /NJ &rc 2&g.'4f c)
-?t- -- r: ::t :
- : ;; the "ovarlap" recuirements between the other channels? Expl a i n.
(1.0)
D.
3.
The pressuri:er electrcma-ic relief value (RC-2) may be cperated in tne zanual or autcratic mode. Discuss how the. valve may be operated in eaca mode. A simple sketch may be used as part of your answer.
(2.0) f##
D.
4 Unit 2 cf TMI utilizes a bcron feed and bleed controller.
a) What are the input signals to the controller?
(1.0) b) 'ihat are the cutput signals of the centroller?
.(1.5) c) When is the centralier utilized?
(0.5) 3.
5.
Two cf the alarms en the Dia cnd Centrol panel are the (i) mc cr rota:icn fault anc the (ii) asymmetric monitcr.
a) Discuss the curpose of each alarm.
(1.5) b) What immediate action is required by the aperating staf# for each alarm?
(1.5) 4 n
}
mm
E.
SApETY ONO E.'1ERGE.NCY SYSTEMS (15)
E.
1.
The pcwer distribution system at TMI-2 contains two :C buses, 2-1CC and 2-20C.
a) Use a ene-line diagram to shcw what cccconents succly these busses and their source (s) of pcwer.
Include any cross ties between these busses and supplies.
(2.0) b) If a station blackout cccurs, what leads are supplied by the D.C. bus until the emergency diesel generatcrs begin to supply pcwer?
(1.5)
E.
2.
List the canditions that will cause a reactor trip with four R.C.
pumps in service.
Include present set points.
(2.5)
E.
2.
Assume a icss of ccolant accident (LCCA) occurs. The LCCA increases reactcr building cressure at 2 PSI / minute and doubles eacn minute (2, a, 3, etc.).
Utill:e this rate for the fcilcwing:
a) What automatic action (s) occur during the first four minutes?
(1.0) b) What instruments will the operatcr observe tc assure initial and centinuing cperation of equipment?
(2.5) c) What is the postulated peak reactcr 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 asscciated with this system and explain the logic that will actuate the aystem.
(1.5) b) List the autcmatic action that will occur when this system is actuated. Assume rated pcwer operation.
(2.0)
E.
5.
Assume a primary to secondary leak develops in cne of the OTSG. The leak cegins at cne GpM and dcubles every i minutes (1, 2, a, 8, etc.)
s a) List the systems that will alert the cperatcr. Attem.: to arrange them in crder of increasing leak rate.
(1.0) b) When the cceratcrs have identified the leaking OTSG, should they trip the reactor cr begin an cederly shutdcwn? Exclain the reascn for your answer.
(1.5)
- Pff,
-8
- 15)
I t.s
. e. n,
y F.
STANDARD AND EMERGENCY OPERATING PROCECURES (15)
F.
1.
Assume your unit is at tne power level cutoff point and aaiting to meet the requirements before increasing pcwer. All systems are in automatic. A malfunction occurs in the circulating water system and va:uum 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) Mcw will the ICS respcnd as vacuum decreases?
(1.0) c) What immediate action is required by the operator (assume vacuum continues to decrease)?
(1.0) d) List the heat sink (s) available if corrective acticn can not restore vacuum.
(1.0)
F.
2.
One of the Limits and Frecautions of the Decay Heat / Injection Pumos states "When c:erating in the ES mcde with suction on the building sumn, puma discharge must be throtled to GPM to limit runcut.
Co not throttle belcw GFri as tnis may result in cavitation and inadequate cooling."
a) What are the above flow rates?
(0,5) b) What is pump runcut and what are the consequences if the pump continues to operate in this ccndition?
(1.5) c) What is cavitation and hcw would the operator observe this condition en the 0.H./ Injection pumas?
(1.5)
F.
3.
During reactor startuo, ifmits are imposed on the a= cunt of reactivity which nay be added above and below the estimated critical positien.
a) What are these limits and hcw does the operator ::nvert them to rod ;csition? Assume an EC? cf 50% cn Grouc 5/7.
(1.5) b) What acticn(s) are requirec if these limits are exceeded?
(1.5)
F.
4 In the event of a reactor trip, list the manual actions recuired by the TMI-2 emergency procedure.
(3.0)
F.
5.
n the e'/ent of an unantici;ated criticality:
a) What sym:::ns wculd alert tne ::erating staff' (1.0) b) What ir. mediate acti:n is recuired :y the 2:erator?
(1.0)
) sJ '..'.1.R,t
- ~- L -- ~
.... -.. =
.-i p
G.
- )DIATICN CONTROL AND SAFETY (13)
G.
l.
Assume you have :een working in a contaminated area. After you remove your protective clothing you mcnitcr yourself before leaving the area.
a) Should an icnization 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.contami.nated?
(0.8)
G.
2.
After acrking in area for two hcurs, you discover your dosimeter is off scale and you leave the area. A survey indicates a hot scot rn a drain line reads I200 mr/hr gamma at two feet.
Ycur distance feca the line was abcut five feet.
a) Estimate tne dose which you may have received.
(1.5) b)
If your previous exposure to the guarter was 900 mr, what exposure limits may have been exceeced?
(1.0) c) '$'ith the aid of a simple sketch, explain the operating princicle of a pocket dosimeter.
(1.0)
G.
3.
[nree of the classified areas in the Radiation 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, one of the basic rules is t0 administer aid to anycne who is injured. What other basic rules apply?
(2.0)
G.
5.
During a refueling cutage you are in the reactcr building on the main fuel handling cridge. A spent fuel element drops into the core.
a) 'What instrumentation will alert the perscnnel in the reactcr building of any release of fissicn products?
(1.0) b) What autcmatic acticn(s) may cccur if radiation levels exceed creset limits?
(1.0) c) What acticns are recuired cy tne :cntral rc : staff' (0.5) 5L ?M
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