ML20024B235
| ML20024B235 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/30/1979 |
| From: | METROPOLITAN EDISON CO. |
| To: | |
| References | |
| TASK-*, TASK-GB GPU-2308, NUDOCS 8307070426 | |
| Download: ML20024B235 (16) | |
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THREE MILE ISLA!!D !!UCLEAR STATIC:1 Af;;lUAL REQUALIFICATIO!! EXAM CYCLE 51978-1979 9 /
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APPLICANT I
FOR IDENite;;ATION
-/., /2 4 j
DATE BEftfAMIN
/
REPCRTERS.
LICEllSE TYPE R0/SRO (Circle One)
IllSTRUCTIO!!S TO APPLICA?{T:
Use separate paper for the answers.
Keep each Category separate and staple the question sheet on top of the. answer sheets.
Points for each question are indicated in parenthesis after the question.
Each Category question sheet contains directicns as to which questions are to be answered by an RO and/or SRO. A Category score of less tha'n 80% requires FSR makeup.
CATEGOP.Y
- --- % OF APPL-ICAtlT'S l %.0F VALUE TOTAL.
SCORE j CAT.'VALUE CATEGORY
~
R0 SR3 R0 SRO
~
~1.5 11.5 15.2 12.8 A.
Principles of Reactor Theory -(A, H) 11.0 11.0 14.5 12.2 B.
Features of Facility
~
'. Design;(,B) -
11.5 12.5
- 15.2 13.9
- C.
General & Specific Oper-ating Characteristics (C,J)
.10.0 10.0 13.2 11.1 D.
Instruments-& Controls
~
(D)
~~
11.0 11.0 14.5 12.2 E.
Safety & Emergency Systems (E)-
10.0 11.0 13.2 12.2 F.
Standard, Emergency &-
- Administrative. Procedures '.
Licits & Precautions (F,L).
~
10.75 11.5 14.2 12.8
~
G." Pidi5do~n Cl6n' trol &'
~
Safety (G,I) ft/ t-11.5 f t/A.
12.8 H.' Fuel' Handling & Core
~
Parameters (K) 75.7o 90.0 100%
100f.
TOTALS Final Grade Approved by:
8307070426 790730 PDR ADOCK 050002 9 V
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l CATEGORY A (A, H)
RO - 11.5 pts PRitiCIPLES OF REACTOR THEORY SRO - 11.5 pts 0 - RO Answers
.?
O 1.
a) tihat is meant by the tenn " delayed neutron fraction"?
(1.0) b) How and why does the delayed neutron fraction change over core lifetime?
(1.5) 0 2.
Assume Keff = 0.9.
Calculate the amount of reactivity addition required to attain criticality.
(1.0) 0*
3.
Explain how individual rod worth varies:
a) llith its radial position (1.0) b)
If another rod is placed next to it (1.0) c)
If coderator temperature increases (1.0) 0*
4.
a)
A reactor has a constant stable SUR of 0.5 DPM; h w lono will it take for power to rise from 10-10 amps to 5 x 10-0 amps?
Show all work.
(1.0) b) lihat is the value of the reactor period for.this transient?
(0.5) c) libat is the value~o'f Keff for this transient?
(1.0) 0*
5.
Samarium - 149 and Xenon - 135 are both reactor poisons.
~
a') !! rite 'the production' schemes for~ each starting 'with'the major fissicn' product.
Include half-life values.
(1.0) b) Explain why Xenon reactivity effects present a greater problem than that of Samarium.
(1.5) 6.
a) A shutdown reactor core has a Keff less than one, yet has an indicated constant count rate.
Explain why this can be true.
(1.0) b) Explain why the count rate will increase with control rod withdrawal while the reactor-is still -suberitical.
(1.0) 7.
a)
Explain in detail why the moderator temperature coefficient is nega-tive.
(1.0) b) Explain why the value of the noderator temperature coefficient changes over core life.
(0.5)
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C*.TEGORY B RO - 11.0 pts FEATUP.ES OF FACILITY DESIG'l SR0 - 11.0 pts 0*
R0 and SRO Answer All 0*
1.
Explainthepurposesofthefollowingplantdesignfeaturesi a) OTSG Aspirating Steam Ports (1.0) b) RCp Flywheel Assemblies (1.0) c) RCP Anti-Reverse Rotation Devices (1.0) 0*
2.
a) What is the purpose of the RC Drain Tank?
(0.5) b) How would the control room operator determine if a discharge into the t..ik was occurring?
(0,5) c) List three (3) indications of a leaking pressurizer, safety valve. (1.0) 0*
3.
'llhen the manual reactor trip pushbutton is depressed all CRD motors are deenergized, but only rod groups 1-7 drop into the core.
a) lihat featur'e of facility design prevents the rods in Group 8 from falling into the core? Be specific.
(0.5) b) Explain why this feature is necessary.
(1.0) 0*
4.
a) Briefly describe why the Emergency Feedwater System is put into opera-tion following loss of all four RCP's - even without a loss of main feedwater.
(1.0) b) Describe the response of the main feedwater system (valves and pumps) upon loss of all four RCP's.
Assume main feedwater pumps do not trip.
(1.0) 0*
5.
Part of the fire protection system at this station consists of a number of pumps located in each unit. The fire main supplies hydrants, hose reels, wet pipe sprinklers and deluge systems.
a) List all the pumps which supply water to the fire main, their capacity, and pressure setpoint for automatic start.
(1.0) b) Explain the operation of a deluge valve as applied on the flatural
-. Draft Cooling Towers, (1.0) c) How do you manually actuate a natural draft cooling tower deluge valve?
(0.5) 0
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CATEGOP.Y C (C/J)
RO - 11.5 pts GEriEiW. AilD SPECIFIC OPEPATIllG CHARACTERISTICS SR0 - 12.5 pts 0 - R0 Answers
1.
A regulating control rod adds negative reactivity as it is inserted.
Explain how an Axial Power Shaping Rod (APSR) can add positive reactivity when it is inserted. (1.0) 0 2.
Following a Steam Line Break Accident the possibility exists to excessively repressurize the reactor coolant system.
a)
Explain why this condition exists.
(1.0) b) What operator actions will prevent this from occurring?
(1.0) 0*
3.
Assume that the plant is operating at 100% FP, all ICS stations are in autonatic.
On the attached figure C-1:
a) Show the initial conditions for each parameter.
(1.0) b) Assuming a reactor trip occurs, plot the response of the parameters for five (5) minutes.
(2.0) 0*
4.
The fiakeup and Purification system uses the following chemicals during operation.
Explain why they are used and when they are used during plant operation:
a) Lithium Hydroxide (1.0) b) Hydrazine (1.0) c) Hydrogen (1.0) 0*
5.
The regulating control rod groups are withdrawn with a normal amount of overlap.
a) Uhat is the value for normal overlap?
(0.5) b) How is this overlap verified?
(1.0) c) What characteristics of the reactor and the control rods make it desirable to operate with overlap?
(1.0) 6.
If an excessive Quadrant Power Tilt condition exists a minimum re-quirement is that power must be reduced below the power level cutoff.
a) Define Quadrant Power Tilt.
(0.5) b) What is the value of Power Level Cutoff?
(0.5) c) During normal operations what conditions must be met prior to exceeding the power level cutoff? Uny?
(1.0)
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7.
On the attached figure C-2:
(Unit 1 (A) and Unit 2 (B))
a) Mark with an X the lights that are lit for 100% FP operation.
(1.0) b) fiark with a circle the lights that are lit assuning a, dropped rod in Group 4.
(1.0) 9 I
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_CATEG3RY D RO - 10.0 pts It:5iRU: lit.TATI0tl A!!D C0:lTROL SRO - 10.0 pts 0* - R0 and SRO Answer All 0*
1.
liith the aid of a sketch, explain how the Cross Limit circuits are develop-ed within the ICS.
(2.0) 0*
2.
Describe the development for each type of control rod position' indication used at this station.
(2.0) 0*
3.
a) libat is the purpose for the ICS STU Limits?
(0.5) b) lihat parameters are monitored in the development of the BTU Limit?
(1.0) c) Which direction (increase, decrease) must each of the individual parameters go to lower the BTU Limit. Assume reference conditions at 100% power.
(1.0) 0*
4.
Consider a turbine trip from 100% power with feedwater and reactor in automatic.
Reactor power and feedwater flow are reduced by the ICS -
the plant stabilizes at 15% reactor power.
a) What terminates the reactor plant runback at 15%?
(0.5) b) !!hy is this setpoint desirable? For instance, why don't we run the plant back to 5% F.P.? Be specific.
(1.0) 0*
5.
a) Describe why the source range 00C nuclear instruments are deenergized on a plant startup.
(0.5) b) Describe the logic (normal and backup) utilized to automatically de-energize these detectors.
Include setpoints.
(1.5) l i
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Cate orv E (E)
R0 - 11.0 pts Safe:y anc Emergency Systems SRO - 11.0 pts 0* - RO and SRO Answers 0*
1.
List the conditions which will automatically trip an Emergency Diesel Generator after an automatic E.S. start signal is received.
(2.0) 0*
2.
a) Describe how the main steam line rupture detection system (feedwater latch) is actuated.
(1.25) b) Uhat protective action is automatically initiated by its actuation?
(0.75) 0*
3.
List all the reactor protection system trips, for 100% FP, include the Technical Specification setpoint for each trip.
(2.0) 0*
4.
flake a simple sketch showing the flowpath of water during the infection phase of safety injection for:
a) Highpressureinjection(1.5) b) Low pressure injection (1.5) 0-5.
Certain substances will cause a charcoal filter to be degraded a) Uhat are the general classifications for these substances?
(1.0) 4 b) Give an example (substance) for each general classification given in part "a".
(1,0) 1 O
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CATEGORY F (F.L)
R0 - 10.0 pts STA:;DM.D, EMERGENCY, A"D AD:1INISTP.ATIVE PROCEDURES SR0 - 11.0 pts LIf1ITS AND PRECAUTIONS 0 - R0 Answers
- - SRO Answers 0* - R0 and SR0 Answers 0
1.
List the allowable steady state quadrant power tilt limits.for the following methods of measurement:
a) Sy=etrical (full) incore system.
(0.25) b) liinimum incore system (0.25) c) Power range channels (0.25) 0 2.
For the following emergency conditions, list the unique indication (s) of each, as given in the emergency procedure:
a) Loss of reactor coolant inside centainment (0.75) b) OTSG tube rupture (0.75) c) Steam line break inside containment (0.75) 0" 3.
a) List the conditions, as given in the emergency procedure, which would warrant small break LOCA response.
(1.0) b) How much time, by procedure, does the CR0 have to recognize that a small break LOCA condition exists?
(0.5) c) How long, by procedure, does the Small Break LOCA team have to get the leg flows balanced at 125 Sp=?
(0.5) 0*
4.
The control rod drive emergency procedure states that in the event of an asyr=etric rod condition to verify plant runbach.
a) Uhat conditions must be satisfied to get the automatic runback? (2.0) b) Does the ICS runback for an asy=etric rod condition always satisfy Technical Specification requirements? Explain (2.0) 0*
5.
Briefly explain the purpose of " Caution Tags". (1.0) 6.
List the emergency procedure symptoms for a "High Activity in Reactor Coolant" condition.
(1.5) 7.
The control room for the purpose of defining the area for the
" Operator-at-the-Controls" is divided into the routine operations i
area and nonroutine operations area.
1 a) List three (3) conditions which warrant the " Operator-at-the-Controls" entering the nonroutine operations area.
(1.5) b) On the attached Figure F-1 (Unit I (A) or Unit II (B) Control Room as applicable) mark the routine operations area for the
" Ope rator-a t-the-Control s".
(1.0)
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CATEG03.Y G (G. I)
RO - 10.75 pts RADI AT10:. CO:JROL AMO SAFETY SRO - 11.5 pts 0 - R0 Answers
1.
You've been working two hours next to a hot spot which has a field intensity of 1200 mrem at one foot.
You note that youf dosimeter has pegged high and you leave the controlled access..Yotr-were working two feet from the hot spot.
i- -
a) What was your exposure? (1.5) b)
If you've already received 900 mrem this quarter, what is your total quarterly dose?
(0.25)
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c) What Administrative and/or flRC linits have you exceeded?.; (0._5.)...:'
, n..r.,.o.y 0
2.
What are the TMI entry requirements for areas with greater than 100 mrem /hr doserate?
(1.0) 0*
3.
For each of the following list:
i) Activity monitor (s) that would sense the problem ii) Automatic actions associated with the monitor (s) iii) !!onitor locations iv) Type of detector used a) High level liquid radwaste release. (1.0)
Y b) Spent Fuel Element failure.
(1.0) c) High level waste gas decay tank release.
(1.0)
'- ) '. Q
'E 0*
4.
a) Define " Radiation Area" (1.0)
.\\,
1 b) Define " Contaminated Area" (1.0)
~-
You're exiting the controlled access area and you discove[ the' I Ie'of * "
- 0*
5.
your shoe is contaminated.
A buddy hands you a piece of tape and you remove the contanination. What further actions should you take before
~ ^ ' '
u leaving the access area entrance?
(1.5) 0*
6.
What is the difference between a RAD and a REM?
(1. 0),...
- q. t
.a List the criteria for declaration of a Local Radiation Emergency'.Ei (2.0)'.'"'t.,!
T 7.
s 8.
a) List the three major sources of Tritium at TMI.
(1.5)
I b) Describe the hazards associated with Tritium.
(1.0)
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SRO - 11.5 pts luel Hanclin0 and Core Parameters SRO Answers 4
1.
a) Briefly explain.why an installed artificial neutron source is used.
(1.0) b) Uhat type of artificial neutron source is installed in the core?
(0.5) c) Uhat are the core locations for the installed artificial neutron sources? (0,5) 2.
a) What is the reason for the mechanical caneuvering rates limit on the rate of reactor power increase below 20% FP? (1.0) b) What is the rate of increase allowed by the mechanical maneuver-ing rates below 20% FP? (0.5) 3.
Define the following:
a) FQ (1.0)
H b) F4 H (1.0) 4.
What prevents the fuel grapple from engaging or disengaging at the wrong time.
(2.0) 5.
a) What is the formula for subcritical multiplication? (0.5) b) Assume Keff = 0.9 when the countrate is 10 cps.
Sometime later during the fuel loading the countrate has increased to 20 cps.
Show calculations for the following:
1.
What is the new Keff of the reactor?
(1.0) 2.
What would be the status of the reactor if the same amrunt of reactivity was added to the reactor as was added to in-I crease the countrate from 10 cps to 20 cps? (1.0) 6.
flane the Refueling Technical Specification for the following:
a)
Flux Monitoring (0.75) b) Communications (0.75) 3
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