ML19220B465
| ML19220B465 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/17/1977 |
| From: | Collins P Office of Nuclear Reactor Regulation |
| To: | Withheld METROPOLITAN EDISON CO. |
| References | |
| NUDOCS 7904260245 | |
| Download: ML19220B465 (45) | |
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CPE? ATING CEYCa.STR ATICN 1.1 P emartuo and irstrument Checks 1.2 Conscie Cperation
- a. Vanicwations
- b. Unde,tancrrig
- 2. F AC:LITY ECUIPMENT C
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- b. Process 4 REACTCR PRCTECTICN 5.PACCECURES I
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- 6. AE ACTIVITY EF F ECTS (E xcept Consc+e Coarmon)
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U. S. NUCl.EG F21MTCRY QBCSSIW FIACTCR CFER.CCR LICENSE EXAMINATICN Facility Th-ee Mile Isl wd - Uni: 2 Ecactor Tfpe O'.,o 9 y.1 II/77 Date Adninistered c/
E.xminer
/J. J. Ed:v Applic2nt ISK Instr:cticns :: Applicant:
Use separate paper for the a-s.-rs; stacle questien sheet Feints for each questica are en *.cp cf the ars.er sheets.
An everall indica:-d in parenthesis af ter ti.e questica.
secre cf 7C1 cr greater is passing.
Category
% of Applicant's
% of Va.lue Total Score Cat. Value_
lS.(
hlo A.
Principles of Reac:cr Cperaticn 14 13.5 14 13.5
- 10. k 3.
Features of Facility Design 17 16 13, 1 M_
C.
Ceneral Cperating Curacte-istics 16 15
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D.
Instr.cnents and Centrols 16 15
/k#1 93_
E.
Safety and E ergency Systens Ill O
F.
Standard and Sergencf Operating 16 _
15 Precedures l I, 6
G.
Fadiatien Centrol and Safety 13 _
12 IY 1C6 O
Final Grade
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A.
PRI"CI LES OF REACTCR CPERATIo.'i (14)
A.
1.
a) What is meant cy the term "delayec neutron fraction"?
(1.0) b) Mcw and ahy dces the delayed neutron fraction change during core lifea me?
(1.5)
A.
2.
The TMI procedure for aparcach to criticali:y 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) How is the data utiliced? "ote: a s, ketch ray be used as
- art of your answer.
(1. 5 )
A.
3.
Assume ycur reactor is)cn a stable.S OFM startup rate as ;cwer level reaches 2 x 10-'
cn the intermediate range monitor.
(Time is "0').
a) Flot the trace en Figure Al until the pcwer level reaches 10-c.
(1.5) b) After a two-minute " hold" to take data at 10-c the operator si:ndraws the control rods to obtain a i FM startup rate.
Plot this trace for 5 minutes;. include the period of red motion.
Exclain any chances during the five minutes.
(1.5) c) Assume the reactor was at 10-6 at 3 minutes on figure Al and a reactor trip cccurred.
Plot and discuss the resulting trace for the remaining pericd of time en fijUre Al.
(1.0)
A.
4 Xenon ccnditions include periods when xenen is at equilibrium and at peak ccnditions.
a) What is meant by equilibrium xencn?
(1.0) b) Mcw dces peak xenon develop?
(1.5)
) Assume a plant startuc and cower escallaticn is i, ;r gress a One time of peak xenon. Fcw dces this ciffer frca a
- cwer escallaticn after a one-week shutdcwn? No;e
- a sketch may be used as carc of your answer.
It is not necessary to include vaiues for xenon.
(1.5)
A.
5.
Jater is used as a ccclant in your reactor. List three other functions of water in the reactor.
(l..)
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FEATURES OF FACILITY DESIGN (la)
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3.
1.
The nuclear services closed cooling water (NSCCW) syste. Orovides cooling water for the nuclear ccm crents during normai operation and also provides c cling for compcnents during a loss of coolant accident.
a) List those c:mponents which use the NSCCW during normal operation. List the c:mpenents (i) Inside and (ii) Outside the reactor building.
(2.5) b) What components are supplied during a LCLc? Note:. if -
c mpenents appear in part A, tark them wit., an asterisk *,
(1.0) 3.
2.
Condensate and feedwater are heated in a numcer of heat exchanges before water enters the steam generators.
Sketch a :ne-line diagram of the combined systems from tne condenser until it leaves the last heat exchanger.
Include all ; umps and scur:e of heat for each heat ex:hanper for one string.
(2.5) 3.
3.
The fire :rctection system at your facility consists of a numcer of pumps located in unit one and two. The fire main supplies a number of hydrants, hcsereel staticns, a wet pipe sprinkler and a deluge system.
e) List all pumps which supply the fire main; include cacacity and when each pump will start.
(2.0) b) Exclain the difference between the wet pipe serinkler and the deluge water systems.
(1.0)
B.
4 One of the comecnents 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 the reasons fcr these
, limits.
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c)
If the crain tank level is ::o high, where may the o;erators discnarge the excess lipuid?
(0.5) 3.
5.
One of the Limits and preventions require that systems containing licuids shculd be free of air before they are operated to prevent water hammer.
a) What is water hammer and why shculd plant operators be concerned about water nammer?
(1.0) n f)\\ Oces water hammer cccur only with systems containinc licuid k- ')
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(1.0) and air? Explain your ansoer.
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C.
GENERAL C? ERAT!NG CHARACTERISTICS (17)
C.
1.
The ence-through steam generators (CTSG) at ycur facility will produce su:erneated steam during pcwer Operation, a) Witn the aid of a simple sketch, explain hcs superheat is accomplished in the OTSG.
(1.5) b) H;w dces superheat vary from 15 to 1C0% pcwer? A sketch may be used as : art of your answer.
(1.0)
C.
2.
The following are two of the limitations and precauticns in the Unit Startup procedure. Provide the value and reason for each of the limitaticns.
a) Co not attempt to start a reactor c;clant pamo when pcwer is greater than (2.0) 5J Curing startuo and shutd:wn when reactor :cwer is less than percent, the 0753 water level shall :e maintained Cetween arc c.0 C.
3.
Unless specified by the reactor engineer, grcup 8 (AFSR) will be positioned about 32% withdrawn prior to an appr ach to criticality.
a) With the aid of a sketch, indicate hcw the AFSRs worth varies between 0 - ICC% withdrawn.
(Include apprcximate reactivity values)
(1.5) b) Explain when it is necessary to move the APSRs (i) in and (ii) cut.
(2.0)
C.
A.
Two of the limits and precautions for the c:ntrol rod drives ccncern the gas ccncentration in the RCS and the c oling water ;a the mechanism.
a) What are the scur:es of gas in the R.C.S.?
(1.0)
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b) Why is gas concentraticn a factor for tne CRCMs?
(1.0) c)
Is it necessary to maintain a minimum concentration of gas in ne RCS during pcwer Operaticn? Expiain ycur answer.
(1.0) d) The tem:erature of cooling water to the CRCM may vary frca S5 - 1C5CF.
Is there a preferred tem;erature range? Expl a i n.
(1.0)
C.
5.
Assume rated :cwer conditiens and a trip cccurs to a reactor c clant pum.
a) Provide the initial steady state values for :arameters listed in figure C5.
(1.0) b) Shcw the rescanse to these :arameters an-il cancit'cns stati'ize.
Assume.he react:r dces not tri;.
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4 D.
INSTR'.ME.4TS AND ::MTRCL (15)
C.
1.
Refer to the transient in cuestion C.5.
Discuss the action of One centrol syscem(s) for each of tr.e fcilcwing parameters:
a) Lead MWe (1.5) b) Pressuri:er level (1.5) c) Feedwater ficw A & 3 (2.0)
D.
2.
The intermediate channel utilizes a ccmpensated icn chabber'(CIC).
a) With the aid of a simple sketch, explain the operating principle of a CIC.
(1.0) b) Is ccmpensation required at ICCP., 15%, or icwer power levels?.
Explain your answer.
(1.0) c) J;E...__ _.._ ;.i;.- f^ _. ;; the a verl ap" requi remen ts between the other channels? Explain.
(1.0)
D.
3.
ine pressurl:er electrcmatic relief value (RC-2) may be operated in the manual or autcmatic acde. Discuss hcw the' valve may be ccerated in eacn mcde. A simple sketch may be used as part cf your answer.
(2.0)
C. a.
Unit 2 of TMI utilizes a boren feed and bleed, controller.
D s
a) What are the input signals to the centrc11er?
(1. 0) b) What are the output signals of the controller?
(1.5) c) When is the controller utilized?
(0,5)
D.
5.
Two of :ne alarms on the Diamond Centrol panel are the (i) motor rc:aticn. f ault and the (ii) asyr. metric monitor.
a) Discuss the purgese of each alarm.
(1.5) b) What immediate acticn is recuired by the ccerating staf ~ for each alarm?
(1.5)
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SAFETY AND E"ERGENCY SYSTEMS (15)
E.
1.
The :cwer distributicn system at T:1!-2 c:ntains two DC buses, 2-lCC and 2-2CC.
a) Use a one-line diagram to shcw what ccmconents succly these busses and their scurce(s) of pcwer.
Include any cross ties between these busses and supplies.
(2.0) b) If a station blackcut cccurs, what leads are supplied by the O.C. bus until the emergency diesel generators begia to supply pcwer?
(1.5)
E.
2.
List the ccnditiens that will cause a reactor trio with fcur R.C.
pumps in service.
Include present set points.
(2.5)
E.
3.
Assume a less of ccolant accident (LCCA) occurs. The LCCA increases reac ce building cressure at 2?SI/ minute and dcubles each minute (2, 4, 3, etc.).
Unlil:e this rate for the fciicwing:
a) What automatic action (s) occur during the first four minutes?
(1.0) b) What instruments will the c erator cbserve to assure initial and centinuing operatien of equipment?
(2.5) c) What is the postulated peak reactor building pressure in the design basis LCCA?
(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 system.
(1.5) b) List the autcmatic action that will cccur ahen this system is actuated. Assume rated pcwer cperation.
(2.0) mssume a primary to secondary leak develocs in ene of the OTSG. The leak begins at cne GFM and dcubles every i minutes (1, 2, 4, 3, etc.)
a) List tne systems that will alert tne operator. Attemot to arrange them in crder of increasing leak rate.
(1.0) b) When the acerators have identified the leaking OTSG, shculd they trio the reactor tr tecin an crderly shutdcwn? Ex; lain the reascn for your answer.
(1.5)
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STANCARD AND EMERGENCY CPERATING FRCCECURES (15)
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F.
1.
Assume ycur unit is at the pcwer level cutoff point and waiting to meet the requirenents before increasing pcwer. All syst:ms are in automatic. A malfuncticn occurs in the circulating water system and vacuum begins to decrease at 1" Hg/ min.
a) What is the pcwer level cutoff point and when may pcwer be increased abcve this level?
(1.5) b) How will the ICS respcnd as vacuum decreases?
(1.0) c) What immediate action is recuired by the operatcr (assume vacuum continues to decrease)?
(1.0) d) List the heat sink (s) available if cor ective action can not restore vacuum.
(1.0)
F.
2.
Cne of the Limits and Precautiens of the ecay Heat /Injecti:n Pumps scates "When cperating in the ES mcde with succion on the building sump, pump discnarge must be throtled to GPM to limit runout.
Oc not thrcttle belcw GPM as this may result in cavitation and inadecuate cooling."
a) What are the above ficw rates?
(0,5) b) What is pump runcut and what are the consecuences if the pump c:ntinues to operate in this condition?
(1.5) c) What is cavitation and hcw would the acerator cbserve this ccndition on the D.H./ Injection pumps?
(1.5)
F.
3.
During reacc:r startup, limits are imposed cn the amount of reactivity which may be added above and below the estimated critical
- positien, a) 'ahat are these limits and how dces the cperatar convert them t0 rod positicn? Assume an ECP cf 50% cn Grcup 5/7.
(1.5) b) What actien(s) are recuired if these limits are exceeced?
(l.5)
F.
4 In the event of a reactor trip, list tne manual actions required ay the TMI-2 emergency prccedure.
(3.0)
F.
5.
In the event of an unanticipated criticality; a) What symptons wculd alert the cperating staff?
(1.0 )
b) What 4 mediate action is recuirec by the Operator?
(1.0)
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RAJIATICN CONTROL AND SAFETY (13)
G.
1.
Assume you have been working in a centaminated area. Af ter you remove your prctective clothing ycu renitor jcurself before leaving the area.
a) Should an icnication er GM device be used? Expl ai n.
(1.0) b) What type of radiation will the instrumer.t detect?
(0.7) c) What is the criteria for determining if a person is. contaminated?
(0.8)
G.
C.
After working in area for two hours, ycu discover your dosimeter is off scale and ycu leave the area. A survey indicates a het spot en a drain line reads 1200 mr/hr gamma at two feet.
Your distance frca tne line was accut five feet.
- 3) Estimate the dcse which ycu may have received.
(1.5) b)
If ycur previcus exposure to the quarter was 900 mr, anat exposure limits may have been exceeded?
(1.0) c) With the aid of a simple sketch, explain the operating principle of a pocket dcsimeter.
(1.0)
G.
3.
Three of the classified areas in the Radiation Protection Manual at TMI are (i) contrciled 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 ycur answer.
(1,0)
G.
4 In the event of a radicactive spill, cne of the basic rules is to acminister aid to anycne wno is injured. What other basic rules apply?
(2.0)
G.
5.
Juring a refueling cutage jcu are in the reac:cr building on the main fuel handling bridge. A scent fuel element drops into tne core.
a) What instrumentation will alert tne perscnnel in the reactcr building of any release of fissicn products?
(1.0) b) What autcmatic action (s) may occur if radiaticn levels exceed preset limits?
(1.0) c) What acticns are required by the contrei rcca staff?
(0.5) p[,r,f.
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