ML20203B067
| ML20203B067 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/08/1986 |
| From: | Cooley R, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20203B063 | List: |
| References | |
| 50-482-OL-86-01, 50-482-OL-86-1, NUDOCS 8607170421 | |
| Download: ML20203B067 (84) | |
Text
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~ OPERATOR LICENSE EXAMINATION REPORT No. 50-482/0L 86-01 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Docket:
50-482 Operator License Examinations at Wolf Creek Generating Station (WCGS) 7/7!N Chief Examiner:
dhn E. Whi~tremore Date Signed i
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?!ff [6 Approved By:
I tit A./ Cooley' '
Date' Signed Summary Operator license examinations for seven (7) Reactor Operator candidates and four (4) Senior Reactor Operator candidates were administered at the WCGS facility during the week of June 3,1.986.
Six (6) of the seven (7) Reactor Operator candidates and three (3) of 'he four (4) Senior Reactor Operator candidates passed these examinations anJ have been issued the appropriate licenses.
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2 Report Details 1.
Examination Results Written and operating examinations were administered to seven Reactor Operator candidates. All candidates passed the operating examination and one (1) of the candidates failed the written examination.
Four Senior Reactor Operator candidates were administered written as well as operating examinations. All candidates passed the operating examination while one (1) failed the written examination.-
2 2.
Examiners
?
J. E. Whittemore (Chief Examiner)
R. L. Gruel '
S. L. McCrory 1
3.
Examination Report Performance results for individual candidates are not included in this report as it will be placed in the NRC Public Document Room. This Examination Report is composed of the sections listed below.
A.
Examination Review Comment Resolution In general, editorial comments or changes made during the examination or during subsequent grading reviews are not addressed by this resolution section. This section reflects comments and recommended changes'to examination answer keys by 4
the licensee. Examination key modifications resulting from these comments and recommendations are included in the master examination keys, which are provided elsewhere in this report.
Comments and resolutions are listed by examination section 4
question number.
1.05.a Delta flux or Delta I should also be an acceptable 5.03.a answer since it is used to help determine or limit KW/ft.
RESOLUTION:
Accept. Allowed partial credit for mention of any Power Distribution Limit.
1.13 Answer "e" could also be considered correct as it is not unusual to see little or no increase in temperature across a centrifugal pump.
RESOLUTION:
Not. accepted.
Increasing temperature without changing i
enthalpy of a compressed fluid is not possible.
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2.02.a Actual capacities are 500 + 30 GPM recirc. and 1000 + 60 GPH recirc.
2.02.b 2/4 Lo-Lo level in 2/4 S/G's UV on NB01 or N802 (station blackout) 2.02.c B&C S/G's supply the TD AFW PP RESOLUTION:
Accept.
Key modified.
2.04.a low pressurizer level only.
Loss of charging pumps does not cause letdown isolation.
RESOLUTION:
Accept.
Key modified.
2.05.b Either spray or surge line low temperature alarm should be an acceptable answer.
RESOLUTION:
Accept.
Key modified.
2.06.b UNIT-PARALLEL switch is spring returned to center which 6.03.b we call " NORMAL", but the mode of operation is called parallel.
" NORMAL" should be considered an additional correct answer if the mode of operation is explained.
RESOLUTION:
Accept.
Key modified.
2.06.d CCP breakers are not tripped.
They remain shut to start 6.03.d CCP's immediately on EDG breaker closure.
RESOLUTION:
Comment igr.ored.
Information was not solicited in the question.
2.07.a An additional correct answer would be "To provide RCS 6.04.a pressure control during solid plant operations."
RESOLUTION:
Accept.
Key modified 2.07.b The Excess Letdown Heat Exchanger can also discharge to 6.04.b the PRT.
RESOLUTION:
Accept.
Key modified.
2.08.a EMG ES-12 step 1 states " Ensure auto switchover has 6.05.a occurred" and the operator is led there from EMG E-1 step 14 which says to check RWST level < 36%.
CCW flow to RHR HX's is verified AFTER switchover has occurred and SI is reset, so there really are no preparatory actions required.
A frequently used answer is to check sump level.
RESOLUTION:
Accept.
Key modified.
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2.ll.a MS closes MCR outside air isolations.
2.'ll.g SIS (CIS-A) causes the RCP seal water return isolation valve'to shut.
' 2.11.h CCW valves for RHR HX's receive no signal.
RESOLUTION:
Accept. -Key modified.
3.02.a Low pressure SI may be blocked < 1970 psig, but procedure requires the operator to block both SI's when RCS pressure < 1950 psig.
3.02.c Second part of answer should read " low steamline pressure SI" vice_" low S/G pressure".
RESOLUTION:
Accept.
Key modified. Will accept either answer for.
both parts.
3.07 Both "a" and "c" are correct. CTMT Hi @ 3.5 psig causes SI and CTMT Hi 2 @ 17 psig causes MSLIS.
RESOLUTION:
Not accepted.
Question asks for one choice that will cause both actions.
4.01 Technical Specifications do not list the DBA's.
The actual reference is NPS-221.
Referring to T._S. as the may lead the students to inappropriate responses.
RESOLUTION:
Noted.
Question will be changed if used again.
4.04.b The wording of this question may lead to the T. S. limit of 583 deg's F.
GEN 00-002 merely requires requires logging use of spray with delta T > 320 deg's for determination of cycle limits.
RESOLUTION:
Noted.
Will further clarify question if used again.
4.05 The 3 point question in conjunction with the 2.5 points of question 4.04 means that 22% of this section is based i
on GEN 00-002.
This seems a little heavy.
See NUREG 1021, ES-107, Pg.- 1, Section C.5 RESOLUTION:
Not accepted.
GEN 00-002 is not considered to be a single, stand alone-topic.
4.06 Wolf Creek operators often speak of " carrying out the' required action of an 0FN" vice "taking the instrument out of service or out of the control circuit".
RESOLUTION:
Not accepted.
" Carrying out the required action" does-not state-the corrective action.
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4.07.a The attachments to EMG E-0 state the required position 7.07.a for safety related valves for various actuation states.
'These attachments do not however explain what will be seen on the ESFAS panel.
The only source of information on the appropriate indications on the ESFAS panels are
-the,, Tech. Manual and Logic diagrams.
RESOLUTION:
- Not'sccepted.
The Logic diagrams and Technical Manual
_ are not referenced in the procedure, but the procedural i
attachments are referenced.
4.07.b Second answer should be " Core exit TC's < 900 deg's and 7.07.b RVLIS natural circulation range < 40% with NO RCP's running.
RESOLUTION:
Accepted.
Key modified.
4.08 The term " faulted Steam Generator with a tube rupture" is misleading. A faulted SG has a secondary side break while a ruptured SG has a tube break.
i RESOLUTION:
Noted. Will synchronize terms with licensee's usage on future written examinations.
4.11 None of the answers is totally correct.
Initially both source ranges are selected to NR-45, a 2 pen recorder, and then after proper overlap is attained, one pen is switched to highest reading IR.
RESOLUTION:
Accept.
Key modified.
5.08.a A possible alternative answer is to explain that the formation of bubbles and the movement of those bubbles into the cooler areas of the flow channel both act to effectively increase the heat transfer area.
I RESOLUTION:
Accept.
Key accepts any viable answer alluding to more i
effective heat transfer.
5.10.2 Tavg will probably go through a transient and then return to near original value.
RESOLUTION:
Noted.
Any future use of question will require post transient steady state values.
6.01.b Other correct answers are:
- 1) CTMT HI RAD (GASE0US)
- 2) CTMT PURGE HI RAD.(GASE0US)
- 3) FUEL BLDG VENT ISOLATION SIGNAL RESOLUTION:
Accepted.
Key modified.
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6 6.06.a Additional function is to transfer steam dump control to plant trip ccntroller vice load reject controller.
6.06.b Turbine trip is due to P-9, not P-7.
Cited reference is incorrect.
RESOLUTION:
Accept.
Both answers modified on key.
6.07 Answer assumes that controlling channel fails low.
If channel were to fail high, opposite action would occur.
RESOLUTION:
Not accepted. Question specifically states that there is a loss of input.
6.08.a FWIS is also caused by P-4 & Tavg < 564 deg's F.
RESOLUTION:
Accept.
key modified 6.08.b FWIS is also provided in case of MSLB or MFLB for same reason as for LOCA.
RESOLUTION:
Not accepted.
Comment is undocumented.
7.02.c Pressurizer Safety valves also provide overpressure protection.
RESOLUTION:
Accepted.
Key modified.
7.04.b Excess letdown and seal return relief valves also go to the PRT.
RESOLUTION:
Accept.
Key modified.
8.02.b The only limitation on these devices is that they be in sight of the human tag.
8.02.c Jobs of short duration. (normally < 1 br.)
8.02.d Not required in new revision of ADM 02-100 RESOLUTION:
In light of recent revision, either old or new answer is acceptable for full credit and so indicated on key.
8.03.a Standing Order # 17 refers to P-10, not P-6.
By referring to wrong permissive, examinee may be led in the wrong direction.
i RESOLUTION:
Noted.
Question modified.
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-8.06.d Any plausible method of increasing SDM should be acceptable here.
I RESOLUTION:
cAccept.
Key modified.
j 8.09.a Licensee provides answer of " Duty Emergency Director".
RESOLUTION:
Answer acceptable.
8.11.b This question seems to say that a temporary modification j
is already in place and that it now becomes apparent that it will be left in permanently.
In this case a PMR must be completed IAW ADM 01-041.
1' RESOLUTION:
Interpretation is correct.
No changes made to question i
or answer key.
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June 5,1986 Exit Meeting Summary Near the conclusion of the site visit, the examiners met with licensee representatives to discuss the results of the examinations. the following personnel were present for the exit j
meeting.
t NRC LICENSEE J. E. Cummins H. K. Chernoff c
J. E. Whittemore C. M. Estes
- D. L. Fehr R. Guyer J. L. Houghton l
A. S. Mah J. Zell i
In accordance with NUREG 1021, no preliminary pass / fail results based on operating examination performance were provided to the licensee at this time.
It was explained to the licensee that i
region policy was to have the results finalized and licenses j
issued within 30 days.
C.
GENERIC COMMENTS The following apparent problems or areas of weakness were observed by the examiners and noted to the licensee.
1.
Several candidates did not understand how the Diesel j
Generator breaker, sequencer, and system functioned with the j
unit loaded and paralleled during the occurrence of Safety Injection or loss of off site power.
l 2.
Candidates experienced problems on the simulator during j
Nuclear Instrument failures. Problems noted were lack of l
familiarity with switches and removing wrong fuses.
3.
Candidates experienced problems controlling Turbine Generator i
load during transient conditions.
4.
Candidates would not reset steam dumps following failure of first stage pressure transmitter as required by procedure.
5.
Candidates did not routinely null out error before shifting instrument channels or controller modes as required by procedures.
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9 6.
Candidates experienced difficulty in estimating approximate RCS leak rates by failing to recognize seal injection and return contribution to charging and letdown flow rates.
7.
The examiners noted the following simulator problems and reported them to the licensee.
a.
RCS pressure was modeled extremely sensitive to Steam Generator feed, b.
At least 2 panel switches did not produce the desired effect on the first attempt to operate.
D.
EXAMINATION MASTER COPIES l
The SR0 and R0 master examination and answer keys follow.
I Changes resulting from licensee comments are reflected in these j
- keys, i
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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_WQLE_QBEEK REACTOR TYPE:
_EWB-MEQ4________________
DATE ADMINISTERED: _thlghlDQ________________
l EXAMINER:
_QQ1LEt_Ez_______________
APPLICANT:
1811890lIQNS_IQ_6EELIQaNIl Une separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at loast 80%.
Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY
% OF APPLICANT'S CATEGORY
__YoLUE_ _IQI6L
___1GQBE___
_VaLUE__ ______________Q8IEQQBl_____________
_25tQQ__ _25tDQ
________ l.
PRINCIPLES OF NUCLEAR. POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
_25tQQ__ _25zQQ
________ 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
_25tDQ__ _25tHQ
________ 3.
INSTRUMENTS AND CONTROLS
_25tQQ__ _25tQQ
________ 4.
PROCEDURES - NORMAL, ABNORMAL, i
EMERGENCY AND RADIOLOGICAL l
CONTROL i
lQQzQQ__ lQQzQQ
________ TOTALS FINAL GRADE _________________%
All work done on this. examination is my own. I have neither givon nor received aid.
APPLICANT'S SIGNATURE 1
Iz__EBINGIELES_QE_NMGLE68_EQWEB_EL8NI_QEEB811QNt PAGE 2
IMEBdQQ1Nad10St_ME61_IB6NSEEB_eNQ_ELUIQ_ELQW QUESTION 1.01 (1.50)
For the following definitions, give the term that is defined:
a.
The amount of reactivity that is needed to go from hot zero (0.5) power to hot full power.
b.
The fractional change in neutron population per generation.
(0.5) c.
The decay of a neutron into a proton with the simultaneous (0.5) ejection of an electron (and anti-neutrino) from the nucleus.
QUESTION 1.02 (2.50) a.
A variable speed ~ centrifugal pump is operating at 1/4 rated speed in a " CLOSED" system with the following parameters:
1)
Power 200KW
=
2)
Pump ' delta' P= 80 psid 3) flow = 500 gpm i
What are the new values for these parameters when the pump speed is increased to full rated?
(1.5) i b.
Choose the answer that most correctly completes the sentence.
l "In a closed system, two single stage centrifugal pumps l
operating in parallel will have ___(choose from below)___, as compared to the same system with one single stage centrifugal pump operating with one pump isolated."
1) a higher head and higher flow rate.
2) the same head and a higher flow rate.
3) the same head and the same flow rate.
4) a higher head and the same flow rate.
(0.5) c.
How is the available NPSH affected by an increase in system flowrate?
(0.5) i l
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IMEBdQQIN651G1t_HE81_IB6NSEEB_eNQ_ELVID_ELQW 4
S
' QUESTION 1.03 (2.50)
Compare the Estimated Critical Position (ECP) calculated for a startup to be performed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100% power, to the Actual Critical Position (ACP) if the following events /
conditions occured.
Consider each independently.
Limit your 4
answer to ECP is (HIGHER, LOWER, or THE SAME.AS) the actual critical position.
4 a.
The fourth coolant pump is started two minutes prior to criticality (0.5) i b.
The startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip.
(0.5)
}
c.
The steam dump pressure setopint is increased to a value j
just below the Steam Generator PORV setpoint.
(0.5) d.
Condenser Vacuum is reduced be 4 inches of mercury.
(0.5) 1 e.
All Steam Generator levels are rapidly being raised by 5% as criticality is reached.
(0.5) i i
QUESTION 1.04 (1.50)
During a natural circulation cooldown, it is notice that pressurizer level suddenly increases soon after spray flow is initiated to the pressurizer.
Explain what has occurred?.
-(1.5)
QUESTION 1.05 (2.50) a.
Since fuel temperature cannot be measured,.what power distribu-tion limit is observed at Wolf Creek to prevent exceeding the fuel temperature limit.
(0.5) b.
If the fuel temperature limit is 4700'deg F and the cladding temperature is 2200 deg F, what limit must be observed to prevent exceeding the cladding temperature limit when the-1 fuel temperature is~above 2200 deg F?
-(0.5) i c.
Why will the fuel rod surface temperature peak towards the top of the core rather than the location of-the' peak heat flux?
(1.5)
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11__EBINCIELE1_QE_ NUCLE 68_EQWEB_ELoNI_QEE8611QN PAGE 4
i IBEBUQQ1Ned1CSz_BEeI_IB88SEEB_eNQ_ELy10_ELQW QUESTION 1.06 (3.00)
The reactor is at 100% power with equilibrium xenon and all rods out when the boron concentration is reduced, causing a deep insertion of control rod bank D to maintain Tave constant.
Describe how the axial core power distribution will change WITH TIME as a result of this action.
Be complete in your answer.
Assume no further rod motion.
(3.0)
QUESTION 1.07 (2.50)
How will the following affect the Moderator Temperature Coefficient?
BRIEFLY EXPLAIN your answer.
c.
The charging pump suction inadvertently switches to the Refueling Water Storage Tank.
(1.0) b.
The core ages from BOL to EOL.
(0.5) c.
The RCS is cooled down from 550 F to 450 F.
(1.0)
QUESTION 1.08 (3.00)
Indicate the basic problem encountered and the inadequacy of the result obtained (under or overpredicting criticality) for a refueling 1/M plot obtained with the following conditions.
a.
The core is loaded toward the detector.
(0.75) b.
The detector is initially too far from the CORE.
(0.75) c.
The detector is too close to the SOURCE.
(0.75) d.
The detector is too far from the SOURCE.
(0.75)
QUESTION 1.09 (1.50)
Describe how the pressurizer thermodynamica11y attempts to maintain RCS pressure during transient (insurge,outeurge) conditions.
Ignore the operation of heaters and spray in your explanation.
(1.5)
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li__EBINQIELE1_QE_NuQLEeB_EQWEB_ELaNI_QEE86IIQNi PAGE 5
IBEBdQQ1Nad10ft_BE8I_IB8NSEEB_860_ELVIQ_ELQW 4
QUESTION 1.10 (1.50)
J If reactor power increases from 1000 cps to 5000 cps in 30 seconds, i
what is the SUR?
(1.5) a QUESTION 1.11 (1.00)
Both Pu-239 and Pu-240 concentrations increase over core life.
Which of the following statements concerning the effects of these increases is correct?
a.
The buildup of Pu-240 increases the average delayed neutron fraction.
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The buildup of Pu-239 decreases the core Reproduction factor.
c.
The buildup of Pu-239 causes the MTC to become more negative.
d.
The buildup of Pu-240 causes the Doppler Coef. to become more negative.
l QUESTION 1.12 (1.00)
Which of the following will cause plant efficiency to increase?
I a.
Total S/G blowdown is changed from 30 gpm to 40 gom.
I b.
Steam quality changes from 99.7% to 99.9%.
c.
Level increase to higher than normal in a feedwater heater d.
Absolute condenser pressure changes from 1.0 psia to 1.5 psia, i
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IBEBdQQ1NedIQSt_BE81_IB8HSEEB_8NQ_ELu1R_ELQW 4
QUESTION 1.13 (1.00) l Which of the following best describes the parameter changes that occur coross a centrifugal pump in a closed system?
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c.
Temperature INCREASES, Enthalpy INCREASES.
b.
Temperature INCREASES, Enthalpy DECREASES.
c.
Temperature INCREASES, Enthalpy CONSTANT.
d.
Temperature CONSTANT, Enthalpy CONSTANT.
I o.
Temperature CONSTANT, Enthalpy INCREASES.
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l 21__EL8HI_QE11GN_INGLUDINE_16EEIX_8NQ_EMEBGENGX_111IEd1 PAGE 7
i QUESTION 2.01 (1.00)
Concerning the cold leg accumulators (CLA's), pick the following state-ment that is true; a.
The CLA reliefs discharge to the PRT.
I b.
An orifice is provided to extend the blowdown time of the CLA during a LOCA.
I c.
The accumulator isolation valves fail as is.
d.
Accumulator check valves are not considered pressure boundary valves.
QUESTION 2.02 (3.00) a.
State the rated flow of each type of auxiliary feedwater pump below:
i
- 1. Motor-driven 2.
Turbine driven (1.0) 4 l
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b.
State FOUR signals that will automatically start the TURBINE i
driven auxiliary feedwater pump.
(Include coincidences)
(1.0) i c.
Which S/G's can supply steam to the turbine driven auxiliary feedwater pump?
(1.0) 4 l
QUESTION 2.03 (2.50)
)
a.
The flowrate through the RCP #1 seal is not constant for all plant conditions.
Explain WHEN and WHY the flow rate will be at it's j
highest and lowest value.
Consider only normal conditions and not failure.
(1.0) i b.
What is/are the flowpath(s) for RCP #1 seal leekoff during Safety i
Inj ect ion?
(1,0) c.
What parameters determine the differential pressure across the
- 1 seal?
(0.5) 4 i
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CATEGORY 02 CONTINUED ON NEXT PAGE *****)
2:__ELeNI_DE11EN_INCLUQ1NE_18EEI1_aNQ_EMEBGENC1_S111EUS PAGE 8
QUESTION 2.04 (2.50) a.
What will cause the letdown orifice isolation valves to auto-matically close with no operator action?
(control switch for the valves in the auto /open position). Ignore loss of power or air. (1.0) b.
What is the function AND purpose of the letdown pressure control valve during each of the following?
1.
Normal operations 2.
Solid plant operations (1.5) i i
QUESTION 2.05 (2.50) a.
List TWO reasons for maintaining a minimum pressurizer spray line flow during normal "at power" operations.
(1.0) b.
What indication or annunciation is av'ailable to alert the operator that minimum spray flow is not being maintained?
(0.75) c.
What creates the motive force for pressurizer spray flow?
(0.75) i QUESTION 2.06 (3.00) l c.
What additional purpose is served by Diesel Engine Starting i
Air?
(0.5) l 1
b.
During load test surveillance, what is the position of the UNIT -
l PARALLEL switch and WHY?
(0.75) i c.
How is starting air blocked if the diesel should receive a start signal with the unit already running?
(0.75) 4 d.
Describe the sequence of events that occur if the EDG is paralleled 1
and loaded and a LOCA and loss of power occurs.
Discuss only those events related to the EDG or electrical system.
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QUESTION 2.07 (3.00) c.
What are 2 specific instances where the operator may be required to initiate flow flow through the RHR System Letdown Control Valve (HCV-128)?
(1.0) b.
How does system design assure that the Positive Displacement Charging Pump is started unloaded?
(0.5) c.
Explain the effect on Seal Return flow, should the Seal Water Heat Exchanger become plugged or restricted on the seal water side?
(0.5) d.
What are 2 possible outlets from:
1.
Seal Water Heat Exchanger?
2.
Excess Letdown Heat Exchanger?
(1.0)
QUESTION 2.08 (2.50) c.
What is the only preparatory action required of the operator prior to automatic switchover to RHR Cold Leg recirculation?
(0.5) b.
Explain why manual switchover requires the RHR pumps be stopped?(1.0)
'c.
How can the operator prevent "AUT0" switchover from occurring?
(0.5) d.
How is continued flow assured during manual switchover?
(0,5)
QUESTION 2.09 (1.00)
Listed below are the four bypass flow paths which occur within the reactor vessel.
c.
Baffle Bypass b.
Cold Leg to Hot Leg c.
Control Rod and Instrument Thimble d.
Upper Head Cooling Which of the previously named choices has the highest percentage of core bypass flow?
(1.0)
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2t__ELeNI_QE11EH_INGLMQ1NE_E8EEIl_8NQ_EMEBEENQ1_EXEIEd1 PAGE 10 QUESTION 2.10 (1.00)
When the Reactor Makeup system is in AUTOMATIC, how does it know what otrength boric acid to provide?
e.
The automatic controller has an input from the boronmeter, b.
The latest analysis from Chemistry is automatically inputted j
into the controller.
c.
The controller uses the setting on the manual / automatic potentiometer.
d.
The controller uses the integrated charging header flow signal.
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QUESTION 2.11 (3.00)
For the following components, indicate whether they will receive an OPEN, CLOSE, or N0 signal upon a manual safety inj ection initiation.
a.
Control Room outside air isolation valves (0.3) b.
Main Feedwater bypass valves (0.3) c.
Cold Leg Accumulator isolation valves (0.3) d.
Charging header isolation valves (0.3) e.
Main steam isolation valves (0.3) f.
RWST to centrifugal charging pumps suction valves (0.3) g.
RCP seal water return isolation valve (0.3) h.
CCW isolation valve from RHR heat exchanger (0.3) i.
CCW isolation valve from letdown heat exchanger (0.3) j.
Steam supply valves to turbine-driven AFW pump (0.3) 1 I
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2z__IN11BudENIH_8NQ_QQNIBQLg PAGE 11 i
I QUESTION 3.01 (2.00)
The plant has been cooled down using the atmospheric dumps and steam pressure is steady at 900 psig.
What control is adj usted to produce further cooldown and why.should caution be exercised in operating this control?
(2.0)
QUESTION 3.02 (2.00)
I c.
At what pressure is SI blocked during a controlled cooldown?
(0.5) b.
How does the operator know that the block permissive is activated?
(0.5) c.
How does the operator block SI?
(1.0)
'l QUESTION 3.03 (3.00) i For each case below EXPLAIN the resulting method of reactor coolant i
system temperature control AND indicate the approximate final RCS Tavg.
Assume all systems normal except as stated, no operator oction.
CONSIDER EACH CASE SEPARATELY s.
The normal steam pressure setpoint is reduced by 92 psi while l
in Hot Standby awaiting reactor startup.
(1.0) b.
The train A Steam Dump Selector Switch is placed in the "off" position while at 5% power awaiting turbine startup.
(1.0)
)
c.
The train B reactor trip breaker fails to open upon a trip signal while at 78% power.
NOTE:
The train A breaker opened.
(1.0) 3
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
2t__INSIBudENI1_6NQ_QQNIBQL1 PAGE 12 i
QUESTION 3.04 (1.00) l Which of the following is NOT a function of the P-4 permissive (trip cnd bypass breakers open)?
a.
Allows bypassing of steam dump cooldown interlock.
b.
Allows operator block of SI signal.
c.
Causes feedwater isolation if low Tavg is also present.
d.
Causes a turbine trip.
i QUESTION 3.05 (2.50) i Match the following symptoms or causes in column "B" to the specific Rod Control System failure or error in column "A".
"A" "B"
I e.
Power Cabinet Urger.t Failure 1.
Caused by simultaneous zero i
current to stationary and l
movable ~ grippers.
b.
Regulation failure 2.
Unselected rod (s) having current flow in movable or lift coils.
3 c.
Phase failure 3.
Caused by failure of redundant
]
power supply modules, i
d.
Logic error 4.
Caused by pulser or slave cycler i
failure.
o.
Multiplex error 5.
Caused by full current being applied for' excessive time.
I (There is only 1 correct numerical 6.
Can be caused by regulation.or l
answer for each lettered error or phase failure as well as logic failure 4 0.5 each) or multiplex errors.
j 7.
Occurs when voltage to coils has excessive ripple.
(2.5) 1 i
i 1
l
(***** CATEGORY 03_ CONTINUED ON NEXT PAGE *****)
21__INSIBudENIS_6NQ_GQUIBQLS PAGE 13 QUESTION 3.06 (2.50) c.
Fully explain how a trip is avoided when testing the Source or Intermediate ranges of nuclear instrumentation and the reactor is critical at any power level.
(1.0) b.
Explain the function of the " BYPASS" switches on the Nuclear Instrument Miscellaneous Control and Indication Panel.
(1.5) l QUESTION 3.07 (1.00)
Which of the following signals cause BOTH a safety inj ection and a main steamline isolation?
c.
Low Steamline Pressure b.
High Steam Pressure Rate c.
High Containment Pressure d.
Low Pressurizer Pressure QUESTION 3.08 (1.50)
Indicate whether the following statements concerning a resistance temperature detector (RTO) are TRUE or FALSE.
o.
An RTO is connected across one leg of a bridge circuit.
As temperature that is sensed by the RTO changes, a proportional change in the output voltage (current) across the bridge occurs.
(0.5) b.
When an RTO fails due to an open, it always indicates a downscale Clow) reading on its meter.
(0.5) c.
If an RTO is completely submerged, its ability to accurately monitor temperature is unaffected by flow rate.
(0.5)
(*****
CATEGORY 03 CONTINUED ON NEXT PAGE *****)
i f
l 2t__INSIBUMENIS_6NQ_QQNIBQLS PAGE 14 1
I QUESTION 3.09 (2.00) j For the following radiation detector types, indicate whether the j
output intensity (current or pulse height) is proportional to the incident radiation energy, i.e.,
if the incident energy increases, 4
}
will the output intensity increase? (Answer YES or N0 to each).
a.
Ion Chamber (0.5) 1 b.
GM (0.5) c.
Proportional Counter (0.5) d.
Scintillation (0.5) i j
1 QUESTION 3.10 (1.50)
Indicate whether the following statements concerning operation of the 3
1 reactor trip (RT) and bypass (BY) breakers are TRUE or FALSE.
1 i
I a.
If one train is placed in test while the other train's bypass j
breaker is closed, then both reactor trip breakers and both j
bypass breakers will trip.
(0.5)
(
l b.
If it is attempted to close both bypass breakers.at the same 4
time, then both bypass breakers will trip but the reactor I
j trip breakers will remain closed.
(0.5)
I c.
A solid state protection system (SSPS) train A reactor trip I
j signal will trip RTA and BYA breakers.
(0.5)
I QUESTION 3.11 (1.50) 1 Match the NIS detectors in Column A with the area on the gas-filled detector characteristic curve which they operate in, listed in Column B.
j (answers may be used more than once) j Column A Column B 9
a) power range detector
- 1) Limited Proportional i
b) inner volume of IR detector
- 2) Geiger-Mueller i
c) source range instrument
- 3) Recombination j
- 4) Ionization l
- 5) Proportional i
l i
i
(*****
CATEGORY 03 CONTINUED ON NEXT PAGE *****)
i
21__INSIBudENIS_eNQ_QQUIBQLS PAGE 15 QUESTION 3.12 (2.50)
Match the following reactor protection and control signals in Column A to their associated logic coincidence in Column B.
COLUMN A COLUMN 8 e.
2 loop loss of flow trip (per loop) 1.
1/2 2.
2/2 b.
P-6 (SRM turn-on on power decrease) 3.
1/3 4.
2/3 c.
P-12 (Lo-Lo Tavg on temperature decrease) 5.
1/4 6.
2/4 d.
Pzr high pressure trip (p essure increase) 7.
3/4 e.
PRM high power rod stop (power increase)
QUESTION 3.13 (2.00) c.
What are the containment parameters available to the operator as post accident monitoring indication?
(1.5) b.
What is the secondary purpose of the Post Accident Monitoring system?
(0.5)
[
l
(*****
END OF CATEGORY 03 *****)
)
4 __EBQQEQUBES_:_NQBdakt_8BNQBU8Lt_EMEBGENQ1 6NQ PAGE 16 x
i 86DIQLQQ108L_QQNIBQL 1,
i QUESTION 4.01 (1.50) l There are four ' Design Basis Accidents' for which the ECCS systems l
are designed to limit or mitigate the consequences of.
Give three of the four.
(1.5) l t
QUESTION 4.02 (3.00) l 10 CFR 20 provides federal regulations for the control of radiation j
oxposure for radiation workers.
Answer the following questions in l
l eccordance with 10 CFR 20.
l a
a.
What is your QUARTERLY Whole Body exposure limit?
(0.75) i i
j b.
What THREE criteria must be satisfied in order to exceed this limit under NON-EMERGENCY conditions?
(2.25)
I i
1 i
QUESTION 4.03 (1.00) i j
If the following critical safety functions were all displayed orange, j
which one has priority?
i l
a.
Suberiticality.
I l
b.
Heat Sink.
1 4
i c.
Integrity.
i d.
Inventory.
1 i
i t
1 i
i 1
3 i
i I
)
I 1
l i
(***** CATEGORY 04 CONTINUE 0 ON NEXT PAGE *****)
i i
l
}
di__EBQQEQUBE1_ _NQBdekt_6BNQBdekt_EMEBQENQ1_6NQ PAGE 17 BeQ10LQQ10eL_QQNIBQL 1
i I
3 QUESTION 4.04 (2.50) 3
)
Complete the following statements utilizing information found in the Plant Heatup procedure (GEN 00-002).
i c.
For normal heatup of the pressurizer, a rate of
_______F/ hour (0.5)
{
will not be exceeded.
i b.
Spray flow into the pressurizer will NOT be initiated if the temperature difference between the Pzr and Spray fluid exceeds 4
_______F.
(0.5) j c.
At least one Reactor Coolant Pump should be in operation before RCS tmperature exceeds ________ deg's.
F.
(0.5) d.
Heat-up must be terminated or spray initiated if pressurizer l
boron concentration approaches ________ ppm less than RCS loop 1
concentration.
(0. 5).
i j
o.
When RCS temperature narrow range indication is off-scale, RCS temperature is determined by the _________ reading wide range i
temperature indication.
(0.5) l QUESTION 4.05 (3.00) s.
During the performance of GEN 00-002 (Cold Shutdown to Hot Standhy),
what are two (2) specific actions taken by the control room operator to i
improve secondary chemistry or purity.
State how each action serveg to improve chemistry or purity.
(1.0)
I b.
At what RCS temperature is Operating Mode 3 entered, and what sig-nificant step related to plant safety is taken at this time?
(1.0) 7 1
c.
Briefly describe how RCS is overpressure protected from Mode 5 until f
startup is complete.
(1,0)
I
\\
1 i
f
)
1 l
i
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE *****)
~_
J c,
dz__E8QQEQUBEl_:_NQBd8Lt_8ENQBd8kt_EME8QENQ1_8NQ PAGE 18 86DIQLQQ10eL_QQNIBQL d
f."
QUESTION 4.06 (3.00) 2 ^
Assume that a hot leg RTD has failed in the upward direction and the i
following systems are in automatic control.
Explain the expected system response OR lack of response AND state in general terms any action the operator must take to continue operating.
Assume 75 % power.
I a.
Rod Control System (1.0) b.
Steam Dump Control (1.0) c.
Pressurizer Level Control (1.0)
QUESTION 4.07 (1.50) a.
Various steps in EMG E-0 tell the operator to verifyscorrect response
~
to isolation signals by checking ESFAS status panels.
Where can he
}
obtain information as to what the panels should indicate?
(1.0) b.
State a RED PATH Summary for CORE COOLING.
(0.5) i I
QUESTION 4.08 (1.50)
Describe the three methods available to cool and depressurize a Steam Generator with a tube rupture.
(1.5)
I 1
QUESTION 4.09 (2.00) l OFN 00-015 (Loss of RHR Cooling) instructs the oper-ator to establish
)
alternate decay heat removal if the RHR system should fail under use.
Briefly describe the alternate decay heat removal method for' e.
Normal conditions.
(1.0) 2 b.
Vessel head removed.
(1.0) l
}
J l
i l
j
(*****
CATEGORY 04 CONTINUED ON NEXT PAGE *****)
3
4z__EBQQEQUBES_:_NQBdeL&_oRNQBdekt_EdEBGENQ1.6NQ PAGE 19 B6QIQLQQ1QoL_CQUIBQL QUESTION 4.10 (1.00)
In the process of determining if S1 can be terminated, it is determined that the secondary heat sink is available.
In which of the following cituations could SI be terminated?
PZR LVL SUBC00 LING PRESSURE c.
4%
60 degrees stable b.
25%
25 degrees increasing c.
20%
65 degrees decreasing d.
10%
55 degrees stable QUESTION 4.11 (1.00)
Which of the following statements is correct concerning the status of the Nuclear Instrumentation Recorder during control bank rod withdrawal for a reactor startup?
O.
Both source range channels and the highest reading intermediate intermediate range channel are selected.
b.
The highest reading source range and intermediate range channels are selected.
c.
Either source range and the lowest reading intermediate range are selected.
d.
With proper overlap, the highest reading intermediate range is placed on the recorder.
QUESTION 4.12 (1.00)
For a dropped control rod, Tave/ Tref mismatch is initially maitained by which of the following?
a.
Controlling turbine load.
b.
Taking manual control of individual control rod banks.
c.
Taking manual control of individual control rod groups.
d.
Boration and dilution of the reactor coolant system.
(***** CATEGOR'I 04 CONTINUED ON NEXT PAGE *****)
8t__EBQQEQMBE1_:_NQBd8(t_8BNQBd8(t_EdEBGENQ1_8NQ PAGE 20 88DIQLQQ1Q8L_QQNIBQL QUESTION 4.13 (1.00)
Which of the following radiation exposures would inflict the greatest biological damage?
c.
1 Rem of ALPHA.
b.
1 Red of NEUTRON c.
1 Roentgen of BETA d.
1 Red of GAMMA QUESTION 4.14 (2.00)
It has been decided to evacuate the control room with the reactor et power.
o.
What action is required of the RO prior to leaving the control room?
(0.5) b.
How does the RO obtain guidance for immediate and followup action to be performed after leaving the control room?
(0.75) c.
What items must the RO have in his possession when he leaves the control room?
(0.75) 4 i
i l
l
(***** END OF CATEGORY 04 *****)
( * * * * * * * * * * * *
- E N D O F E X A M I N A T I O N * * * * * * * * * * * * * * * ])
It__EBINGIELE1_QE_NVQLEeB_EQWEB_EL6NI_QEEBaIIQNt PAGE 21 IHEBdQQ1NedlG1t_BE61_IB8NSEEB_8NQ_ELu1D_ELQW ANSWERS -- WOLF CREEK
_86/06/03-00YLE, P.
ANSWER 1.01 (1.50) e c.
Power Defect (0.5) b.
Reactivity (0.5) c.
Beta decay (0.5) j REFERENCE WC Reector Theory Pp.39, 150, 219 i
ANSWER 1.02 (2.50) a.
Power (2)
Power (1) * (N2/N1)**3 = 200 * (4)**3 = 12.8 Mw (0.5)
=
Delta P(2)
Delta P(1) * (N2/N1)**2 = 80 * (4)**2 = 1280 psid (0.5)
=
FlowC2) = Flow (1) * (N2/N1) 500
- 4 = 2000 gpm (0.5)
=
i b.
- 1 (0.5) c.
Decreases (0.5)
REFERENCE WC Thermal-Hydraulic Chapt. 10, P.
36.
ANSWER 1.03 (2.50) e.
REFERENCE WC Rx. Theory, Pp. 238-241
=
Iz__EBING1ELES_QE_NVGLEeB_EQWEB_ELeNI_QEEBeIIQNt PAGE 22 IBEBdQQ1Ned1 cst _BEeI_IBeBSEEB_eNQ_ELulD_ELQW 4
ANSWERS -- WOLF CREEK
-86/06/03-D0YLE, P.
1 ANSWER 1.04 (1.50)
The initiation of spray flow to the pressurizer caused temperature and pressure to decrease (0.5].
A higher temperature in the core is causing the formation of a new steam bubble (0.5] and thereby forcing water into the pressurizer (0.53 (1.5)
REFERENCE WC Exam. Question Bank 4
ANSWER 1.05 (2.50) n.
Local Power Density-KW/FT. (Allow full credit for description of how operator maintains non-observable limits in specification and 1/2 credit for any power distribution limit.)
(0.5) b.
DNB or DNBR (accept either answer)
(0.5) c.
Fuel surface temperature is a function of both heat flux (0.5] and
)
coolant temperature.[0.53 Moderator temperature is higher at the top of the core.[0.53 (1.5)
REFERENCE WC Thermal-Hydraulics Ch. 13, Pp. 8,9,20,27 ANSWER 1.06 (3.00)
Rod insertion causes flux shift towards botton of core. [0.5]
With time, xenon buildup in top of core due to less burnout and xenon reduction in bottom of core due to increased burnout causes flux to shift towards the bottom of the core even more (1.0]
Later, xenon buildup in bottom of the core due to increased production and xenon reduction i
in top of the core due to xenon decay causes a flux swing towards the top of the core. [1.0)
These feedback effects between xenon and power result in an axial power oscillation. [0.5]
(3.0) i REFERENCE WC Rx. Theory Pp. 272,273 i
_r___,,
Iz__EBINQIELES_QE_NUQLEoB_EQWEB_ELeNI_QEEBoI1QNt PAGE 23 IBEBdQQ1Ned191t_BE61_IB8NSEEB_eND_ELu1D_ELQW ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
ANSWER 1.07 (2.50]
c.
LESS NEGATIVE [0.5] More boron to leave core area per degree temperature change. [0.53 (Or equivalent answer]
(1.0) b.
MORE NEGATIVE [0.25] Less boron, opposite result as above.[0.25)(0.5) c.
LESS NEGATIVE {0.5] Water density changes are less as temperature is reduced.[0.5]
(1.0)
REFERENCE UC Reactor Theory, Pp 177-180 ANSWER 1.08 (3.00) n.
There are less neutrons absorbed in the moderator and the detector becomes more sensitive as the core moves closer. [0.25]
Criticality is over predicted.
[0.5]
b.
The detector will not see neutrons until there are a great number.
[0.25]
Criticality is over predicted. [0.5]
c.
The initial count rate is too high and the detector is insensitive to core changes. [0.25]
Criticality is over predicted. [0.5) d.
Initial flux level is low so that ICRR is low. [0.25]
Criticality is under predicted. [0.51 (3.0)
REFERENCE WC Theory, Pp.299,300 ANSWER 1.09 (1.50)
When reactor coolant expands into the pressurizer the vapor volume is compressed and the pressure of the steam increases.
This causes steam to condense until the new set of eqailibruim conditions is reached.
[0.75] During an outsurge the level decreases and the steam volume increases resulting in a system pressure decrease.
This results in increased boiling, generating more steam to stop the pressure decrease a r.d establish new equilibrium conditions. [0.75)
(1.5)
It__EBINCIELE1_QE_ NUCLE 88_EQWEB_EL8NI_QEEB811QNt PAGE 24 IHEBBQQ18601 Cit _BE81_IB6NSEEB_6NQ_ELUIQ_ELQW ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
REFERENCE WC HT&FF, Ch.
4, Pp.69,70 ANSWER 1.10 (1.50)
P= Po x 10(0.5 SUR)
(0.5)
" log P/Po = 0.5 SUR (0.5)
SUR = 0.7/0.5 s 1.4 (0.5]
(1.5)
REFERENCE Reactor Theory Handout, pp. 316 & 317.
ANSWER 1.11 (1.00)
--d.--
REFERENCE Reactor Theory Handout, p.
199 ANSWER 1.12 (1.00)
--b.--
REFERENCE WC Thermal-Hydraulics Ch.
7, Pp.66-69 ANSWER 1.13 (1.00)
--a.--
REFERENCE WC Thermal-Hydraulics Ch.10
2t__ELeNI_QE11EN_INGLVQ1NE_SeEEI1_eNQ_EMEBEENQ1_SYSIEd1 PAGE 25 ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
ANSWER 2.01 (1.00) i
--c.--
REFERENCE WC SD ECCS, Pp. 116-118 ANSWER 2.02 (3.00) n.
Motor Driven -
500 gpm (plus 30 GPM recirc.)
Turbine Driven-1000 gpm (plus 60 GPM recirc.)
[0.5 es.)
(1.0) b.
2/4 low-low levels in 2/4 S/G's 2/4 low voltage on NB01 or NB02
[0.5 ea.)
(1.0) c.
B and C.
(1.0)
REFERENCE WC SD AFW, Pp. 1,2,11 ANSWER 2.03 (2.50) u.
As the plant pressure changes so will the delta-P across the
- 1 seal, thus changing the seal flowrate.[0.5)
Flow is high at high pressures and low at low pressures.[0.5)
(1.0) b.
Through #2 seal to the-RCDT and the #1' seal return line relief valve to the PRT.
(1.0) c.
RCS-pressure compared to the backpressure created by the VCT.
(0.5)
REFERENCE WC SD RCP, Pp. 4-8 THRU 4-15
Zz__ELoNI_ DESIGN _INCLUDINQ_SeEEIl_oNQ_EdEBQENGl_SYSIEd3 PAGE 26 ANSWERS ---WOLF CREEK
-86/06/03-00YLE, P.
ANSWER 2.04 (2.50) a.
Pzr. levea 17% or less.
Clow Pzr. level)
(1.0)
=
b.
1.
Controls pressure downstream of the letdown orifices to eliminate flashing and two phase flow. (0.75]
2.
Controls flowrate out of the RCS via RHR to control system pressure. (0.75]
(1.5)
REFERENCE WC SD CVCS, Pp.1,7,13 ANSWER 2.05 (2.50) n.
1.
To reduce thermal stress to the spray line and spray nozzle.
2.
To maintain Pzr. chemistry uniform with the RCS. (0.5 ea.]
(1.0) b.
Spray or surge line low temperature alarms. (one required)
(0.75) c.
Differential pressure across the reactor vessel (will also RCP dP)
(0.75)
REFERENCE WC SD RCS, Pp. 12,18 ANSWER 2.06 (3.00) a.
Used to shutdown the diesel.
(0.5) b.
Parallel or Normal.
(0.25]
Used to provide the speed control governor with a droop characteristic for stability of parallel operation. (0.51 (0.75) c.
When the EDG is sensed to be above a certain speed, the air start solenoid valve receives a shut signal.
(0.75) d.
A load shed signal will trip all feeder and load breakers. (0.25]
i When proper speed and voltage is sensed, (0.25] the DG output breaker.
will close on to the bus. (0.25]
Vital loads are sequenced on to the bus.
(0.25]
(1.0) 1 i
_ ~. _.,. _. _ - _ _ _. _ - _. _. -. _
f.
21__EL8NI_QE11GN_INQLVQ1NG_18EEI1_6NQ_EMEBEENQ1_111IEMS PAGE 27 ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
REFERENCE WC EXAM QUES. BK.
ANSWER 2.07 (3.00) n.
1.
To purify coolant when on RHR cooling.
2.
Provide additional letdown during heatup or bubble formation.
3.
RCS solid plant pressure control. (Any 2, 0.5 es.)
(1.0) b.
The pump is interlocked to prevent starting unless a bypass valve is open which closes ~ 2 minutes after starting.
(0.5) c.
Continued flow is assured by a relief valve which directs flow to the VCT.
(0.5) d.
SW HX:
1.
Chg. pump suct.
i 2.
VCT (0.25 ea.)
Ex. LD HX:
1.
RCDT 3.
PRT (Any 2, 0.25 ea.)
(1.0)
REFERENCE WC NPS 219 Ch.1, Pp.11,21,26,27 ANSWER 2.08 (2.50) a.
Accept any one of the following:
1.
2.
Check RWST level.
3.
Check Sump level.
(0.5) b.
An interlock (0.5) prevents opening the containment sump valve with the same side RWST valve open. (0.53 (1.0) c.
Depress the RWST SIS reset button.
(0.5) d.
By switching over only one train at a time.
(0.5)
REFERENCE WC ECCS, Pp.43,44 i
._,--,m
2t__EL8NI_DESIEN_INGLMQ1NG_S8EEI1_8NQ_EMEBEENQ1_11SIEd3 PAGE 28 ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
ANSWER 2.09 (1.00) c.
Control Rod and Instrument Thimble.
REFERENCE Reactor Vessel, Internals, Core Components, and Rod Drive Mechanisms p.
29.
ANSWER 2.10 (1.00)
--c.--
REFERENCE WC SYS BG 200, P.
2 ANSWER 2.11 (3.00)
(0.2 pts each) e.
CLOSE b.
CLOSE c.
OPEN d.
CLOSE e.
N0 f.
OPEN g.
CLOSE h.
NO i.
NO j.
NO REFERENCE WC SD ESF CThroughout)
2___INSIBudENI1_6ND_QQNIBQLS PAGE 29 ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
i ANSWER 3.01 (2.00)
The Cooldown Steam Dump Controller or Atmospheric Dump Controller [0.75) should be adj usted slowly [0.251 to avoid an inadvertant Safety Injection
[0.51 due to rate sensitive sensors. [0.5]
(2.0)
REFERENCE WC SD MAIN STEAM, Pp.21,26 ANSWER 3.02 (2.00) u.
1950 or 1970 psig.
b.
The P-11 status light illuminates (0.5) c.
Place BOTH A and B train switches for low pressurizer pressure SI to BLOCK [0.53 and BOTH switces for low Steam line pressure SI to BLOCK.
[0.5]
(1.0)
REFERENCE WC GEN 00-006, Step 4.16 ANSWER 3.03 (3.00) c.
The normal steam pressure setpoint of 1092 psig maintains Tavg at ~557 F.
a decrease in the setpoint to 1000 psig would cause the dumps to open and cool Tavg to ~550 F
[0.5] where the P-12 interlock whould close all steam dumps.
[0.53 (1.0) b.
Secondary pressure would rise to the setpoint of the secondary atmospheric relief valves [0.5] which would maintain pressure at 1125 psig [0.25) and primary temperature 560 +/- 1 F [0.253 (1.0) c.
A signal by the Load Rej ection controller [0.53 would control primary temperature at "No Load" Tref (+2 F deviation [ dead band, 559 F1)
[0.53 (1.0)
REFERENCE WC SD MN. STM, Pp. 31,32.
.i i
i
2t__INSIEMdENIS_8NQ_QQN18QL3 PAGE 30 ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
ANSWER 3.04 (1.00)
--a.--
REFERENCE WC SD RPS, P.28 ANSWER 3.05 (2.50) a.-----------------6.
b.-----------------5.
c.-----------------7.
d.-----------------1.
e.-----------------2.
(0.5 EA.]
(2.5)
REFERENCE WC Rod Control, Pp.21-22 ANSWER 3.06 (2.50) a.
Each channel has a bypass switch to prevent a trip at low power levels due to 1/2 trip logic.
(0.53 At higher levels, the trips are blocked by the P-6 or P-10 permissives.
(0.5]
(1.0) i b.
1.
The " Rod Stop Bypass Switch" (0.5] removes the overpower rod stop function for the selected channel to allow rod motion.
(0.25]
2.
The " Power Mismatch Bypass Switches"-(0.53 remove the selected channel from the rod control system auctioneer circuit.(0.25)(1.5) l REFERENCE WC NI, Pp.15,28,40 l
ANSWER 3.07 (1.00) l
--a.--
l
2t__IN11BudENI1_8NQ_QQNIBQLS PAGE 31 ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
4 REFERENCE Precautions, Limitations, and Setpoints, P.
9 i
ANSWER 3.08 (1.50) a.
TRUE b.
FALSE c.
FALSE (0.5 each)
(1.5) i REFERENCE WC SD RCS TEMP. IND., Pp.5,9 ANSWER 3.09 (2.00) n.
YES (0.5) b.
NO (0.5) c.
YES (0.5) d.
YES CO.5)
REFERENCE WC RAD. PROT. MAN., Pp.
9.6--9.8 a
i ANSWER 3.10 (1.50) a.
TRUE b.
FALSE c.
FALSE (0.5 each)
(1.5)
- 2t__IN118MMEN11_8NQ_QQN18QLS PAGE 32
' ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
i r
ANSWER 3.11 (1.50) e) 4 b) 3-c) 5 REFERENCE Wolf Creek "Excore NIS", pp 5 and 22.
4 ANSWER 3.12 (2.50) n.
4
-(0.5) b.
2 (0.5) c.
6 (0.5) d.
6 (0.5) o.
5 (0.5) i REFERENCE WC SD RPS TABLES SB-1,2,3 ANSWER 3.13 (2.00) j o.
1.
Pressure 2.
Radiation 3.
Sump Level 4.
H2 5.
Temperature (0.3 en.)
(1.5) b.
To provide a record for subsequent analys is..
(0.5)
REFERENCE WC SD PAMS, Pp. 2,4 i
4 m
$A__EBQQEQUBEl_:_NQBU8L'i_8BNQBualt_EMEBGENQ1_88Q PAGE 33 86DIQLQQIQaL_QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
1 ANSWER 4.01 (1.50)
(Any 3 of 4, 0.5 each) 1.
Rod Ejection 2.
Loss of Secondary Coolant Accident 3.
Steam Generator Tube Rupture 4.
Loss of Coolant Accident (LOCA) which results in a coolant leak greater than the capability of the normal charging system.
(1.5)
REFERENCE
-WC SD ECCS P.9 ANSWER 4.02 (3.00)
I a.
1.25 Rem /Qtr.
(0.75) b.
Three (3) REM /Qtr is not exceeded [0.75)
Total accumulated lifetime dose does not exceed 5(N-18)-(0.75)
Accumulated-Exposure on record (NRC-4).
(0.75)
(2.25)
REFERENCE j
a.
10 CFR 20.101 Ca) (b)
(1), (2), & (3)
.i i
ANSWER 4.03 (1.00)
^
--a.--
REFERENCE 4
EMG E-0, Foldout Page I
i l
4
it__EBQQEQUEER_:_NQBd8Lt_aRNQBdekt_EMEBGENQ1_6NQ PAGE 34 88DIQLQGlQ6L_QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-D0YLE, P.
ANSWER 4.04 (2.50) a.
100' b.
320 c.
160 d.
50 e.
highest
[0.5 each]
(2.5) i REFERENCE GEN 00-002, Pp.1-3 ANSWER 4.05 (3.00) a.
- 1. Place condensate demineralizers in service [0.25] to remove impurities. [0.25]
2.
Start S/G blowdown (0.25] to remove impurities. [0.25]
- 3. Establish main condenser vacuum [0.25]
which reduces oxygen [0.25]
(Allow 1/2 credit for actions performed outside MCR)
[Any 2, 0.5 each]
(1.0) b.
350 deg's,
[0.51 Previously inoperable ECCS Pumps are made operable at this time. [0.5]
(1.0) c.
Initially protection is provided by RHR relief valve. [0.25]
When RHR is isolated, Cold Over pressure protection actuation of PORV's provides protection [0.5] until temperature increases (above 310 deg's) and normal actuation of PORV's is available. [0.25]
(1.0) 1 REFERENCE WC GEN 00-002, Pp. 9,10,13
SA__EB29EQU8ES_:_NQBd8Lt_8BUQBd8(t_EME8GENQY_8NQ PAGE 35 S6019LQGIQ8L_QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-D0YLE, P.
ANSWER 4.06 (3.00) c.
There will be rapid control rod insertion due to Tavg./ Tref. mismatch.
[0.5)
The operator must place system in manual control, stabilize plant, and take the instrument out of the control circuit.[0.5] (1.0) b.
There should be no actuation unless the " Loss of Load" interlock (C-7) is armed
[0.5)
Regain manual control, close valves, and reset interlock. [0.5]
(1.0) c Pressurizer level would start increasing to maximum program level.
[0.5)
The operator should take the instrument out of the control circuit. [0.5]
(1.0)
REFERENCE WC OFN 00-008, P.15 ANSWER 4.07 (1.50) a.
There are attachments at the end of the procedure that can be used to verify proper isolation.
(1.0) b.
Core Exit 7C's > 1200 deg's without RVLIS; OR Core Exit TC's > 900 deg's AND RVLIS natural circulation range less than 40% with no RCP's running. (Only one required)
(0.5)
REFERENCE WC EMG E-0 & EMG ES-01 ANSWER 4.08 (1.50) o.
Blow it down to the blowdown system.
[0.5) b.
Blow it down to (backfill) the RCS.
[0.5) c.
Cooldown to steam dumps.
[0.5]
(1.5)
REFERENCE EMG ES-31, 32, a 33 m-.
m
dz__EBQQEQUBER_:_NQBd8Lt_6BNQBMAlt_EdEBQENQ1_8NQ PAGE 36 86DIQLQQ1QaL_QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-D0YLE, P.
4 1
ANSWER 4.09 (2.00) a.
Use AFW [0.25] and stcem to S/G PORV's. 03.25] TD AFW pump, [0.25]
or steam dumps. [0.25]
(1.0) b.
Maximize charging /letoown flow [0.53 and place spent fuel pool cooling system in operation. [0.5]
(1.0)
REFERENCE WC OFN 00-015, Steps 6,8 ANSWER 4.10 (1.00)
__d.__
REFERENCE EMG E-1, Step 6 t
ANSWER 4.11 (1.00) 1
--d.--
REFERENCE WC GEN 00-003, P.9 I
ANSWER 4.12 (1.00)
--a.--
REFERENCE WC OFN 00-011,P.1 ANSWER 4.13 (1.00)
J
--b.--
REFERENCE 10CFR20 4
3 4
,,,.r.
, -, -,., -,. ~, +,...., - -,,, -,.,, -,,, -. -,.,, -. - -.,,.
St__EBQQEQUEEl_:_NQBd8Lt_8ENQBM8(t_EMEBGENQ1_8NQ PAGE 37 B8DIQLQQIQ8L_QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-00YLE, P.
068/000-K5.04. (3.2/3.5)
ANSWER 4.14 (2.00) e.
Trip the reactor and fast close the MSIV's (0.5) b.
He is directed to perform an attachment to the procedure.
(0.75) c.
Keys for the emergency locker and security doors.
(0.75)
REFERENCE WC OFN 00-017, P.
3 & ATT C.
t 1
4 i
TEST CROSS REFERENCE PAGE 1
QUESTION VALUE REFERENCE 01.01 1.50 WJE0000602 01.02 2.50 WJE0000604 01.03 2.50 WJE0000605 01.04 1.50 WJE0000606 01.05 2.50 WJE0000607 01.06 3.00 WJE0000645 01.07-2.50 WJE0000646 01.08 3.00 WJE0000647 01.09 1.50 WJE0000648 01.10 1.50 WJE0000614 01.11 1.00 WJE0000615 01.12 1.00 WJE0000616 01.13 1.00 WJE0000617 25.00 02.01 1.00 WJE0000612 02.02 3.00 WJE0000639 02.03 2.50 WJE0000640 02.04 2.50 WJE0000641 02.05 2.50 WJE0000642 02.06 3.00 WJE0000649 02.07 3.00 WJE0000650 02.08 2.50 WJE0000651 02.09 1.00 WJE0000620 02.10 1.00 WJE0000621 02.11 3.00 WJE0000622 25.00 03.01 2.00 WJE0000608 03.02 2.00 WJE0000610 03.03 3.00 WJE0000611 03.04 1.00 WJE0000623 03.05 2.50 WJE0000652 03.06 2.50 WJE0000653 03.07 1.00 WJE0000624 03.08 1.50 WJE0000626 03.09 2.00 WJE0000627 03.10 1.50 WJE0000628 03.11-1.50 WJE0000618 03.12 2.50 WJE0000629 03.13 2.00 WJE0000619 25.00 04.01 1.50 WJE0000603 04.02 3.00 - WJE0000613 04.03 1.00 WJE0000630 04.04 2.50 WJE0000643
TEST CROSS REFERENCE PAGE 2
QUESTION-VALUE REFERENCE 04.05 3.00 WJE0000655 04.06 3.00 WJE0000656
' 04.07 1.50 WJE0000657 04.08 1.50 WJE0000631 04.09 2.00 WJE0000632 04.10 1.00 WJE0000633 04.11 1.00 WJE0000634 04.12 1.00 WJE0000635 04.'13 1.00 WJE0000636
- 104.14 2.00 WJE0000638 25.00 i
100.00
+
4 m
E
U.
S.
NUCLEAR REGULATORY COMMISSION 4
SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY:
_WQLE_QBEEK REACTOR TYPE:
_EWB-WEQ4________________
i DATE ADMINISTERED:_Q64QhlQQ________________
EXAMINER:
_WB1IIEUQBEt_JA__________
APPLICANT:
INSIBUQIIQNS_IQ_aEELIQaNIl Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question. The passing gr' a requires at least 70% in each category and a final grade of at least 80%.
Examination papers will be picked up six (6) hours after the examination' starts.
i
% OF CATEGORY
% OF APPLICANT'S CATEGORY
__V8LUE_ _IQIaL
___1QQBE___
_VaLUE__ ______________QaIEQQBl_____________
_25ADQ__ _25100 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS l
_25tDQ__ _25tQQ
________ 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION i
l
_25tDQ__ _2EAQQ
________ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
_25ADQ__ _25tHQ
________ 8.
ADMINISTRATIVE PROCEDURES,
]
CONDITIONS, AND LIMITATIONS 10010Q__ 100t09
________ TOTALS FINAL GRADE _________________%
4 All work done on this examination is my own. I have neither given nor received aid.
i i
j APPLICANT'S SIGNATURE 1
i
-a
,,,n..-
--v~--
e,,..
r.
,--e,
Et__IBEQBY_QE_NUQLE88_EQWEB_ELeNI_QEE86110Nt_ELU10st_6ND PAGE 2
IBEBdQQ1N6010S QUESTION 5.01 (2.50) a.
During RCS cooldown, the operator may be required to have shutdown rods withdrawn.
When do procedures require this action?
(1.0) b.
During cooldown, what concept can be used by the operator to anticipate inadvertent criticality?
(0.75) c.
Which of the factors below will NOT affect rod height at crit-icality?
1.
RCS Temperature.
2.
Boron Concentration.
3.
Boron concentration rate of change.
4.
Count rate.
5.
Samarium concentration.
6.
Control rod speed.
(0.75)
QUESTION 5.02 (3.00)
The reactor is at 100% powet with equilibrium xenon and all rods out when the boron concentration is reduced, causing a deep insertion of control rod bank D to maintain Teve constant.
Describe how the axial core power distribution will change WITH TIME as a result of this action.
Be complete in your answer.
Assume no further rod motion.
(3.0)
QUESTION 5.03 (3.00) o.
Since fuel temperature cannot be measured, what power distribut-ion limit is observed at Wolf Creek to prevent exceeding the fuel temperature limit?
(0.8) b.
If fuel temperature limit is 4700 deg's and cladding limit is 2200 deg's.,
what limit must be observed to prevent exceeding the clad limit when fuel temperature is above 2200 deg's?
(0.8) c.
Why will the fuel rod surface temperature peak towards the top of the core rather than the location of peak actual heat flux?
(1.4)
(*****
CATEGORY 05 CONTINUED ON NEXT PAGE *****)
5t__IBEQBl_QE_ NUCLE 6B_EQWEB_ELeNI_QEEBoIIQNt_ELu1 dst _6NQ PAGE 3
IBEBdQQ1N6dlG3 QUESTION 5.04 (1.50)
A reactor is critical at 10 -8 amps in the intermediate range.
An inadvertent boron dilution puts the reactor on a 0.5 DPM startup rata.
Calulate the change in boron concentration caused by this dilution.
STATE any assumptions you make and assume 80L conditions.
QUESTION 5.05 (2.50)
How will the following affect the Moderator Temperature Coefficient?
BRIEFLY EXPLAIN your answer.
c.
The charging pump suction inadvertently switches to the Refueling Water Storage Tank.
(1.0) i b.
The core ages from BOL to EOL.
(0.5) c.
The RCS is cooled down from 550 F to 450 F.
(1.0)
QUESTION 5.06 (2.50) a.
Explain how, why, and when fuel densification occurs and it's effect on the Doppler Coefficient.
(1.5) b.
Provide 2 reasons that the Doppler Coefficient is of great importance to reactor safety.
(1.0)
QUESTION 5.07 (3.00)
Indicate the basic problem encountered and the inadequacy of the result obtained (under or overprediction of criticality) for a refueling 1/M plot obtained with the following conditions.
a.
The core is loaded toward the detector.
(0.75) b.
The detector is initially too far from the CORE.
(0.75) c.
The detector is too close to the SOURCE.
(0.75) d.
The detector is too far from the SOURCE.
(0.75)
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
52__IBEQBl_QE_NUGLE68_EQWEB_ELeNI_QEEBellQN _ELylQSz_8NQ PAGE 4
t IBEBdQQ1NedigS QUESTION 5.08 (2.00) s.
Why does nucleate boiling heat transfer remove more heat than non-boiling heat transfer?
(1.0) b.
Why does film boiling remove less heat than nucleate boiling?
(1.0)
QUESTION 5.09 (2.50) a.
Describe how the pressurizer thermodynamically attempts to maintain RCS pressure during transient (insurge,outsurge) conditions.
Ignore the operation of heaters and spray in your explanation.
(1.5) 4 b.
Answer the following TRUE or FALSE 1
1.
The pressurizer can be thermodynamically evaluated as a non-steady flow. closed system.
2.
The pressurizer steam space is ideally a little hotter than the liquid space.
1 4
3.
The primary consideration for spray flow being COLD leg rather than HOT leg is to provide better pressure reduction because of the i
colder fluid.
(1.0)
}
QUESTION 5.10 (2.50) a a
Consider only post transient stable conditions and explain why
{
the following statements are true:
i If a Reactor Coolant Pump is stopped at 30 % power AND no protective or operator action occurs:
4 1.
The entire affected loop temperature will go to T cold conditions.
2.
Average temperature will remain constant.
3.
Total RCS flow will be greater than 75 %.
i 4.
Flow rate through the core may be less than 75 %.
j 5.
Steam pressure at the throttles will decrease.
(***** END OF CATEGORY 05 *****)
1 Ez__ELaNI_SISIEUS_DE11ENt_QQNIBQLt_6NQ_INSIBudENI6Il0N PAGE 5
J QUESTION 6.01 (2.50) c.
There are more than one group of ventilation fans located within Containment.
Which.TWO (2) groups of Containment fans are automatically shifted to slow speed upon receipt of a Safety Injection Signal (SIS) AND WHY are they shifted to slow speed?
(1.5) b.
List TWO unrelated signals other than a SIS or MANUAL signal that will automatically isolate the Control Room Ventilation System from outside air.
(1.0)
QUESTION 6.02 (2.50) c.
List four signals (non-similar/ unique) which will initiate a motor driven Auxiliary Feedwatar Actuation Signal (AFAS).
(2.0) b.
With an AFAS signal initiated, what signal (s) will cause an automatic shift of the Auxiliary Feed pump water supply from the Condensate Storage Tank to the Essential Service Water System? Include logic.
(0.5) 1 I
QUESTION 6.03 (3.00) n.
What additional purpose is served by Diesel Engine Starting i
Air?
(0.5) b.
During load test surveillance, what is the position of the UNIT -
PARALLEL switch and WHY?
(0.75) c.
How is starting air blocked if the diesel should receive a start signal with the unit already running ?
(0.75)
]
d.
Describe the sequence of events that occur if the EDG is paralleled and loaded and a LOCA and loss of power occurs.
Limit your response to the events occurring to the EDG and electrical system.
(1.0)
I l
4 1
I i
4
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
,si
\\'
1 Ez__EL8NI_11SIEd1_DE11ENt_QQUIBQLt_8NQ_INSIBudENI6IIQN PdGE 6
QUESTION 6.04 (3.50)
~
e.
What are 2 specific instances where the operator may be required.to 4
initiate flow through the RHR System Letdown Control Valve CHCV-128)?
(1.0)<
1 b.
How does system design assure that the Positive Displacement Charging i
Pump is started unloaded?
(0.5) c.
Explain the effect of a containment isolation signal on RCP seal water return flow.
(0.5) i d.
Explain the effect on Seal Return flow, should the Seal Water Heat Exchanger become plugged or restricted on the seal water side?
(0.5) l e.
What are 2 possible outlets from:
1.
Seal Water Heat Exchanger?
2.
Excess Letdown Heat Exchanger?
(1.0) i i
QUESTION 6.05 (2.50) l a.
What is the only preparatory action required of the operator prior to automatic switchover to RHR Cold Leg recirculation?
(0.5) b.
Explain why manual switchover requires the RHR pumps be stopped?(1.0) c.
How can the operator prevent "AUT0" switchover from occurring?
(0.5) d.
How is continued flow assured during manual switchover?
(0.5)
I.
a
?
)
QUESTION 6.06 (2.50) i i
n.
What generates AND what are the functions of the P-4 permissive?(1.0) l b.
What are the specific Reector Protection system trips are affected by the P-7 permissive?
(1.5)
~
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE'*****)
+
s ht__ELaNI_SISIEDS_QERIGNt_QQNIBQLt_8NQ_INSIBudENI6Il0N PAGE 7
QUESTION 6.07 (2.00)
List the parameter inputs to the Pressurizer Level Master Controller and briefly describe the controller response for a loss of each specific parameter input.
Assume full power and no operator action.
(2.0)
QUESTION 6.08 (2.50) a.
List the signals that will cause feedwater line and steam line isolation signals.
Ignore manual actuation signals (1.5) b.
What are the specific events that steam and feedwater isolation provide protection for?
(1.0)
. QUESTION 6.09 (2.00)
~,
Match the following symptoms or causes in column "B" to the specific Rod Control System failure or error in column "A".
"A" "B"
a.
Power Cabinet Urgent Failure 1.
Caused by simultaneous zero current to stationary and movable grippers.
b.
Regulation failure 2.
Unselected rod (s) having current.
flow in movable or lift coils.
c.
Phase failure 3.
Caused by failure of redundant power supply modules, d.
Logic error 4.
Caused by pulser-or slave cycler failure.
o.
Multiplex error 5.
Caused by full current being applied for excessive time.
.(There is only 1 correct numerical 6.
Can be caused by regulation or answer for each lettered error or phase failure as well as logic failure 0 0.4 each) or multiplex errors.
l 7.
Occurs when voltage to coils has j
excessive ripple.
(2.0)
(*****
CATEGORY 06 CONTINUED ON NEXT PAGE *****)
l ht__EL6NI_111IEdi_QE110Nt_CQNIBQLt_eNQ_IN11BudENI611QN PAGE 8
i QUESTION 6.10 (2.00)c a.
Fully explain how a trip is avoided when testing the Source or Intermediate sanges of riuc le a r instrumentation and the/ reactor is critical at any power level.
(1.0) i b.
Explain the function of the " BYPASS" switches on the Nuclear Instrument Miscellaneous Control and Indication Panel.
(1.0) i
.\\
i 1
i r
i I
1 4
d
(***** END OF CATEGORY 06 *****)
Zz__BBQQEDVBEl_ _NQBd6Lt_8BNQBd6Lt_EME8QENQY_6NQ PAGE 9
8801QLQQIQaL_QQNIBQL QUESTION 7.01 (2.50) c.
The design rate of power change for the Wolf Creek Plant is 5%/ min. or a 10% step change in power.
Power is usually changed much slower due to impositions of GEN 00-004.
What are the two most common reasons for limiting the rate of power increase to less than design?
(1.0) b.
Why does GEN 00-004 as well as other procedures prohibit the starting of a Reactor Coolant Pump in Mode 17 (0.5) c.
Notes throughout GEN 00-004 instruct the operator to borate or dilute as necessary to maintain the control rod position in the maneuvering band.
What is the maneuvering band?
(1.0)
QUESTION 7.02 (2.50) a.
During the performance of GEN 00-002 (Cold Shutdown to Hot Standby),
what are two (2) specific actions taken by the control room operator to improve secondary chemistry or purity.
State how each action serves to improve chemistry or purity.
(1.0) b.
At what RCS temperature is Operating Mode 3 entered, and what sig-nificant step related to plant safety is taken at this time?
(0.75) c.
Briefly describe how RCS is overpressure protected from Mode 5 until startup is complete.
(0.75)
QUESTION 7.03 (2.50) o.
For the Component Cooling Water (CCW) system, briefly describe the automatic action that can occur as a result of a leak into AND out of the system.
Consider each case separately.
(1.25) b.
Briefly describe the INITIAL action necessary to LOCATE a leak out of the CCW system.
(1.25)
(*****
CATEGORY 07 CONTINUED ON NEXT PAGE *****)
Zi__EBQQEQUBEl_:_NQBdakt_aBUQBdakt_EdEBGENGI_aNQ PAGE 10 BaQ10LQQ1QaL_QQNIBQL i
QUESTION 7.04 (3.00) o.
While executing the Off-Normal procedure fcr RCS leakage (OFN 00-007),
the leak rate is noted to be slowly increasing.
At what point is the the operator required to enter the Emergency procedure ?
(0.5) b.
While attempting to locate an RCS leak, it'is noticed that the Pressurizer Relief Tank level is increasing.
What are four systems or components likely to be the source of leakage ?
(1.0) c.
For the specific type of RCS leakage in column "A",
match the appropriate symptoms (s) in column "B".
(Place appropriate letters next to numbers on your answer sheet.)
(1.5)
"A" "B"
l.
All RCS leakage A.
Aux. Bldg. sump levels increasing 2.
S/G Tube leakage B.
Condenser Vacuum Pump Red.
3.
Leakage to Aux. Bldg.
monitor increasing.
1 C.
Liquid Waste Holdup Tank level increasing.
D.
Increase in VCT make up rate.
E.
Decreasing pressurizer level with chg. and letdown flow balanced.
F.
Increasing S/G blowdown activity monitor.
(1.5) l l
l l
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
I Zz__EBQQEQuBEE_:_NQB58L&_8BNQBdekt_EbEBGENQ1_6NQ PAGE 11 88Q10LQQIQ8L_QQNIBQL QUESTION 7.05 (2.50)
Assume that a hot leg RTD has failed in the upward direction and the i
following systems are in automatic control.
Explain the expected system response OR lack of response AND state in general terms any action the operator must take to continue operating.
Assume 75 % power.
I a.
Rod Control System (1.0) b.
Steam Dump Control (0.75) c.
Pressurizer Level Control (0.75)
QUESTION 7.06 (2.50) a.
What are 3 of the general items the operator is told to check to
" Verify ECCS Flow" during the performance of EMG E-07 (1.0) b.
During the performance of EMG E-0, the operator is instructed to " Check if ECCS flow should be reduced".
What are 3 of the items, parameters, or values that should be checked to make this determination?
(1.0) i c.
During the recovery in EMG E-0, the operator is instructed to maintain Steam Generator level between 4% and 50%.
What instruction does the i
procedure provide under " Response not Obtained" if level can NOT be controlled at less than 50 %?
(0.5) l QUESTION 7.07 (2.00) n.
Various steps in EMG E-0 tell the operator to verify correct response to isolation signals by checking ESFAS status panels.
Where can he obtain information as to what the panels should indicate?
(0.5) b.
State a RED PATH Summary for CORE COOLING.
(0.5) c.
What is the purpose of AND the entry conditions for EMG ES-Ol?
(1.0)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
Zt__P8QQEQQBEg_ _NQ808(t_AgNQBd8Lt_EMEBGENQY_88Q PAGE 12 88Q10LQQ1Q8L_CONIBQL QUESTION 7.08 (2.50)
Assume that during refueling there is an element in transit over the open Reactor Vessel when an element already installed falls over and causes obvious damage to another irradiated element.
a.
Who has overall and at the scene responsibility for instituting corrective or recovery action?
(0.75) b.
How would responsibility assignment differ if a similar type of accident occurred in the spent fuel pool?
(0.5) c.
Who is responsible for verifying to the individual with overall responsibility that spaces are evacuated?
(0.5) d.
What should be done with the element in transit?
(0.75)
QUESTION 7.09 (2.50)
Safety Inj ection termination criteria in " Loss of Reactor or Secondary Coolant" (EMG E-1) are specified for normal and ADVERSE containment conditions.
WHICH criteria / parameters are different, WHY are they affected, and HOW is each specific criteria adj usted f or Adverse Containment conditions?
QUESTION 7.10 (2.50) a.
During start up, why must the operator observe limits on RCS and VCT pressure prior to starting a Reactor Coolant Pump (RCP) ?
(1.5) b.
What are 5 conditions that require the operator to stop an RCP ?(1,0) i
(***** END OF CATEGORY 07 *****)
I
l.
At__8QUINISIB811VE_PBQQEQUBESt_QQNQlIlQNSt_8NQ_(IdlI611QNS PAGE 13 QUESTION 8.01 (2.50)
In the event of a plant emergency requiring implementing the Emergency Plan, who, by title:
a.
Initially assumes the duties of the Duty Emergency Director?
(0.5) b.
Can relieve the Duty Emergency Director (Both Titles)?
(1.0) c.
Initially ass mes the responsibilities of the Operations Emergency Coordinator?
(0.5) d.
Is the normal relief for the Operations Emergency Coordinator?
(0.5)
L QUESTION 8.02 (2.50) 1 a.
What provides the tagout function for a live breaker which must be cycled several times while trouble shooting under a " Clearance Without DNO Tag"?
(0.75) b.
How many components can be controlled by a single " Clearance Without DNO Tag"?
(0.75) c.
What is the maximum time that a " Clearance Without DNO Tag" may remain open?
(0.5) d.
When filling out the clearance order for a " Clearance Without DNO Tag",
what information is supplied in the blank for Tag Number?
(0.5)
QUESTION 8.03 (2.50) a.
According to Standing Order # 17, a Nuclear Instrument System Power Range failure and subsequent inoperability may negate the protective actions provided by Permissive P-10.
Explain the cause for concern and how protection may be affected.
(1.0) b.
What action is required of the operator if this concern should actually occur?
(0.75) c.
Explain how it is possible to be in compliance with the Technical Specifications and start up the reactor in violation of Standing Order # 17.
(0.75)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
az__aQUINISIBaIIVE_EBQCEQMBESt_QQNQlIlQNEt_6HQ_LidlI611QNS PAGE 14 QUESTION 8.04 (2,50) a.
While escorting an NRC inspector on a tour of the Radiologically Controlled Area (RCA), the-inspector informs the escort that his pocket dosimeter is off scale.
What is the required initial and follow up action?
(0.75) b.
An individual with a current quarter exposure of 250 mrem receives en additional 300 mrem in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Explain any K.
G.
& E.
OR NRC limits or guidelines that have been violated or exceeded for any 1
individual that may be considered.
(1.0) 1 c.
How can administrative controls to control personnel exposure be circumvented when emergency conditions preclude taking the time to fill out paperwork to satisfy administrative requirements?
(0.75)
QUESTION 8.05 (2.50)
Concerning the Wolf Creek Emergency Procedures, c.
Why are some procedure step subtasks designated by letters while others are designated by bullets (o)?
(0.75) b.
1.
What should the operator do if a RED Terminus is encountered in a Critical Safety Function Status Tree (CSFST)?
(0.5) 2.
What should the operator do if a second RED terminus is acquired while he/she is attending to the first condition?
(0.5) c.
What is the purpose of the INTEGRITY Critical Safety Function Status Tree (CSFST)?
(0.75)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
Sz__eQUINISIB611YE_EBQQEQUBESt_QQUD1I1QNSt_8NQ_LIU1IaI1QNS PAGE 15 QUESTION 8.06 (2.50)
While passing into Mode 5 from Mode 4 a control room operator runs the SOM program on the reactivity computer and obtains a value of 1.23 for Shutdown margin.
a.
Explain any problem with the obtained value.
(0.75) b.
State any action that may be required (0.5) c.
Would corrective action have been required if the plant had remained in Mode 5?
Explain.
(0.5) d.
What is a viable alternative if the operator is prevented from taking the required action due to equipment malfunction?
(0.75)
QUESTION 8."7 (2.50)
At 75% reactor power it is noted that AFD is outside the allowable band for this power level and power is reduced to 50% immediately.
c.
Explain why it was necessary to reduce power.
(1.0) b.
Explain any action that may be necessary subsequent to reducing reactor power.
(0.75) c.
When can power be increased back to 75%?
(0.75)
QUESTION 8.08 (1.00)
During the shift the Reactor Operator manually calculetes Quadrant Power Tilt Ratio and submits to the SRO a result of 0.99.
Explain why this number should or should not be accepted as a valid result.
(1.0)
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
{
i az__8DdINISIgallyg_EBQGEQUBESt_GQNQ1110NSt_8NQ_L1611oI1QNS PAGE 16 I
1 QUESTION 8.09 (2.50)
Answer the following questions assuming that there is a Site Area Emergency declared and that the Emergency Plan has been placed in effect with full r
augmentation complete.
The NRC response team is not on site.
c.
A disagreement has arisen among personnel in the Control Room, Techni-cal Support Center, and the Emergency Operations Center about whether 4
or not a specific action (start an RCP) should be taken.
Who (by title) is the K.
G.
& E.
person having final authority?
C0.5) b.
Explain the admin ist r at ive relationship of the Radiological Assessment Coordinator, Dose Assessment Coordinator, and the Radiological I
Emergency Coordinator.
(0.75) 1
~
c.
When do the Emergency Plan Implementing Procedures require verification call back?
(0.5) d.
How does the Emergency Directory denote personnel to call first:
l 1.
To staff on site emergency positions?
I
]
2.
To notify personnel in Wichita?
(0.75)
QUESTION 8.10 (1.50) i What is the general responsibility of the Shift Supervisor for Technical Specification Surveillance Testing in the below listed specific areas?
a.
Pre-test responsibility.
(0.75) b.
Post -test with unsatisfactory results.
(0.75) l 1
i i
4 4
l
(*****
CATEGORY 08 CONTINUED ON NEXT PAGE *****)
~
At__6DdlN11186IIVE_EBQQEQUBEnt_CQNQ1Il0N1t_6NQ_L1011611QUE PAGE 17 QUESTION 8.11 (2.50) a.
What action must be taken when an approved procedure that authorizes the installation of a temporary modification is suspended for an indefinite period with the modification in place AND who is responsible for initiating this action?
(0.75) b.
What administrative action is to be taken if it becomes clear that a temporary modification is to become permanent?
(0.75) c.
What are 4 separate types of operation or modifica, tion covered by the 1
Temporary Modification Procedure?
(1.0) i 4
i 4
4 I
i
(***** END OF CATEGORY 08 *****)
__,C.**********.***-_END OF EXAMINA TION ***************)
St__IBEQBl_QE_NUQLE68_EQWEB_ELaHI_QEEB6110Nt_ELUIDSt_8HQ PAGE 18 IBEBdQQ1Ned10S ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANSWER 5.01 (2.50) a.
Shutdown rods must be withdrawn whenever positive reactivity is being added [0.5) unless the RCS has been borated to cold shutdown condi-tions. [0.5)
(1.0) b.
Counts doubling. If the counts have doubled, adding the same amount of reactivity will cause criticality.
(0.75) c.
3, 4,
6
[0.25 for ea.)
(0.75)
REFERENCE WC Rx. Theory, Pp. 230-236 ANSWER 5.02
[3.00)
Rod insertion causes flux shift towards botton of core. (0.5)
With time, xenon buildup in top of core due to less burnout and xenon reduction in bottom of core due to increased burnout causes flux to shift towards the bottom of the core even more
[1.0)
Later, xenon buildup in bottom of the core due to increased production and xenon reduction in top of the core due to xenon decay causes a flux swing towards the top of the core. [1.0)
These feedback effects between xenon and power result in an axial power oscillation. [0.5)
(3.0)
REFERENCE WC Rx. Theory Pp. 272,273 ANSWER 5.03 (3.00) a.
Local power density-KW/FT. (Full credit for description of how operator maintains non-observable limits in specification and 1/2 credit for any power distribution limit.)
(0.8) b.
DNB or DNBR (accept either answer)
(0.8) c.
Fuel surf ace temperature is a function of heat flux and moder-ator temperature. [0.7) Modersture temperature is higher at the top of the core. [0.7)
(1.4)
]
Et__IBEQBl_QE_NUQLE68_EQWEB_EL8NI_QEEB8IIQNt_ELVIQEt_8NQ PAGE 19 IBEBMQQ1N8dlQS ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
E REFERENCE WC Heat Transfer Review, Pp.140,142 i
ANSWER 5.04 (1.50) 4 Assume:
boron worth 10 pcm/ ppm (Allow full credit for
=
Beta bar eff.
= 0.007 any reasonable assumption lambda eff.
0.08 sec of these values)
=
g The stable period is given by:
T=
26/SUR 26/.5 = 52 Sec's
[0.5)
=
The reactivity associated with the stable period:
p = beff/1+ lambda T
.007/ 1+(.08)(52)
=
0.001357 dk/k = 135.7 PCM
[0.5)
=
The change in boron concentration:
d CB = 135.7 pcm/-10 pcm/ ppm 13.6 ppm (0.53 (1.5)
=
REFERENCE WC QUEST.BK.RT-H17 i
ANSWER 5.05 (2.50) c.
LESS NEGATIVE [0.5) More boron to leave core area per degree temperature change. [0.53 (Or equivalent answer)
(1.0) b.
MORE NEGATIVE [0.25] Less boron, opposite result as above.[0.25 (0.5) c.
LESS NEGATIVE [0.5) Water density changes are less as temperature is reduced. [0.53 (1.0)
REFERENCE WC Reactor Theory, Pp 177-180 I
l 4
I i
~.
Et__IBEQBl_QE_N90LE68_EQWEB_EL8NI_QEEB8I1QNt_EL91QSt_6NQ PAGE 20 IBEBdQQ1NedIQS ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANSWER 5.06
[2.50) a.
Occurs early in the fuel cycle [0.3] when fuel pellets shrink as small bubbles within them collapse. [0.3]
This causes the gap between the pellets and clad to increase [0.3] resulting in a lower rate of heat transfer. [0.31 The resultant higher fuel temperature for a given power results in a less negative coefficient. [0.3]
[1.5) b.
1.
Fast acting.
2.
Always negative
[0.5 es.]
[1.0)
REFERENCE WC Rx. Theory, Pp. 199,199a ANSWER 5.07
[3.00) a.
There are less neutrons absorbed in the moderator and the detector becomes more sensitive as the core moves closer. [0.25]
Criticality is over predicted.
[0.51 b.
The detector will not see neutrons until there are a great number.
[0.25]
Criticality is over predicted. [0.5]
c.
The initial count rate is too high and the detector is insensitive to core changes. [0.25]
Criticality is over predicted. [0.5]
d.
Initial flux level is low so that ICRR is low. [0.25]
Criticality is under predicted. [0.5)
[3.0)
REFERENCE WC Theory, Pp.299,300
St__IBEQBl_QE_NVQLE88_EQWEB_EL8NI_QEEB8110Nt_ELVIQ5t_6NQ PAGE 21 IBEBdQQ1Ned10S ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANSWER 5.08 (2.00) n.
Nucleate boiling creates turbulent flow which promotes more mixing.
[0.5)
The coolant picks up latent heat of vaporization and carries it to cooler parts of the channel. [0.53 (Accept similar viable explanation)
(1.0)
,b.
In film boiling, a film of steam coats the clad surface and forms an insulating layer [0.5) which greatly reduces the heat transfer coefficient. [0.53 (1.0)
REFERENCE WC HT & FF, Ch.
3, P.72 ANSWER 5.09 (2.50) a.
- 1. When reactor coolant expands into the pressurizer the vapor volume is compressed and the pressure of the steam increases.
This causes steam to condense until the new set of equilibruim conditions is reached.
[0.75) 2.
During an outsurge the level decreases and the steam volume increases resulting in a system pressure decrease.
This results in increased boilin, generating more steam to stop the pressure decrease and establish new equilibrium conditions. [0.75)
(1.5) b.
1.
FALSE 2.
FALSE 3.
FALSE
[0.33 es.)
(1.0)
REFERENCE WC HT&FF, Ch.
4, Pp.69,70
St__IBEQBY_QE_NVGLE88_EQWEB_ELeNI_QEEB6Il0Nt_ELVIDS&_eNQ PAGE 22 IBEB5001NadlGS ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANSWER 5.10 (2.50) 1.
Flow in the affected loop is reversed and is supplied from the core inlet plenum.
2.
Does not change as steam demand remains constant.
3.
Stopping one RCP decreases the head that operating RCP's must pump i
against and their individual output increases.
4.
A large amount of operating flow bypasses the core through the cold leg of the affected loop.
a 5.
The equivalent heat transfer must occur through 75% of the area previously available.
Therefore S/G temp. and press must decrease to i
increase dT and provide the same energy flow rate.
[0.5 ea.]
(2.5) l i
REFERENCE j
WC HT7FF, Ch.12, Pp. 15-17 l
l l
4 l
f
.I i
l l
i 1
I
Ez__PL8SI_1111gd1_QE11GNt_QQNIBQLt_8NQ_IN11BQUENI611QN PAGE 23 ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANSWER 6.01 (2.50) a.
The Hydrogen Mixing fans (four)
[0.5) and the Containment Fan Cooler fans (four).
[0.5)
'They are shifted to slow speed to prevent overload in a high pressure (high humidity) environment.
[0.53 (1.5) b.
-High Radiation (at Control Room Supply).
High Chlorine (at Control Room Supply).
Cont. Hi Rad (Gas)
Cont. Purge Hi Red (Gas)
Fuel Bldg. isolation signal (Any 2, 0.5 ca.]
(1.0)
REFERENCE W.C.
NPS 221, Chapter 4, pp. 43 ANSWER 6.02 (2.50) a.
1.
Manual.
2.
S/G low-low level.
3.
Safety Injection.
4.
Trip of both Main Feed Pumps.
5.
Undervoltage on both NB01 & NB02 busses. (Class 1E Busses.]
[Any 4, 0.5 es.)
(2.0) b.
Low suction pressure.
(0.5)
REFERENCE WC NPS 223, Chapter 5, pp.12,13
r J
6t__EL8NI_SISIEdi_QE11GNt_CQUIBQLt_8NQ_INSIBubENI8Il0N PAGE 24 ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
1 ANSWER 6.03 (3.00) c.
Used to shutdown the diesel.
(0.5) i b.
Parallel or Normal.
(0.25]
Used to provide the speed control governor with a droop characteristic for stability of parallel operation.
(0.5]
(0.75)
J c.
When the EDG is sensed to be above a certain speed, the air start solenoid valve receives a shut signal.
(0.75) l d.
A load shed signal will trip all feeder and load breakers. (0.25]
When proper speed and voltage is sensed, (0.25] the DG output breaker will close on to the bus. (0.25]
Vital loads are sequenced on to the bus.
(0.25]
(1.0) l REFERENCE WC EXAM QUES. BK.
1 ANSWER 6.04 (3.50) a.
1.
To purify coolant when on RHR cooling.
2.
Provide additional letdown during heatup or bubble formation.
3.
RCS Solid plant pressure control. (Any 2, 0.25 es.]
(1.0) 1
~
b.
The pump is interlocked to prevent starting unless a bypass valve is open which closes ~ 2 minutes after starting.
(0.5) c.
Continued flow is assured by a relief valve which directs flow to the
)
PRT.
(0.5) d.
Continued flow is assured by a relief valve which directs flow to the VCT.
(0,5) e.
SW HX:
1.
Chg. pump suct.
i
- 2. VCT (0.25 ea.)
Ex. LD HX:
1.
]
3.
[Any 2, 0.25 es.]
(1.0) i I
REFERENCE j
WC NPS 219 Ch.1, Pp.11,21,26,27 I
i
kt__EleNI_111IEd1_DESIGNt_GQNIBQLt_6NQ_IN11BudENIeIlQN PAGE 25 ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
1 ANSWER 6.05 (2.50) a.
Accept any one of the following:
1.
2.
Check RWST level.
1 3.
Check sump level.
(0.5) b.
An interlock (0.5) prevents opening the containment sump valve with the same side RWST valve open. [0.5)
(1.0) i l
c.
Depress the RWST SIS reset button.
(0.5) d.
By switching over only one train at a time.
(0.5)
REFERENCE WC ECCS, Pp.43,44 ANSWER 6.06 (2.50) n.
Generated by: The reactor trip and bypass breakers being open.-[0.25)
Functions: Causes Turbine trip / Reactor trip Isolates feedwater < 564 deg's Tavg.
1 Allows operator to block S.I.
signal after a (60 second) time delay.
Transfers Steam dump from load reject to plant trip mode (Any 3, 0.25 es.)
(0.75) b.
1.
Two loop low flow 2.
RCP bus undervoltage 3.
RCP bus underfrequency 4.
Turbine trip 5.
High pressurizer water level 6.
Low pressurizer pressure (0.25 ea)
(1.5)
REFERENCE WC NPS 227, Pp. 5,28 i
I e
i
.i kz__ELANI_EX1IEMS_DESIGNt_QQNIBQLt_6NQ_INSIBudENIeIIQN PAGE 26 ANSWERS -- WOLF CREEK 86/06/03-WHITTEMORE, J.
I h
ANSWER 6.07 (2.00)
Programmed level. [0.51 Loss of the program level signal would cause the controller to see a 25% minimum desired programmed level signal, and level would control at 25%
[0.5]
Actual level. [0.51 The system would indicate zero or minimum level and the controller would attempt to increase level in the pressurizer until cuch time as protective action occurred due to high level. [0.51 (2.0)
REFERENCE i
WC PZR LEVEL CNTRL, P.8 ANSWER 6.08 (2.50) a.
MSIS:
i 1.
Low steam line pressure j
2.
High steam pressure rate i
3.
Containment pressure HI-2 j
FLIS:
t 1.
Safety inj ect ion 2.
HI - HI S/G water level 4
3.
P With Lo Tavg.
[0.25 es.]
(1.5) j b.
Feed line isolation is provided in the event of a Primary or Secondary LOCA. [0.33]
Steam line isolation for a LOCA [0.33]
{
and MSLB (0.33]
(1.0) i i
REFERENCE NPS 21, Ch.1, Pp.20,21 4
i i
3 l
d
m,-my--,--
,,,,,,<-,,--.,------.,,.-_-,-.-,.-m,4.
-.,---,..,.,_,,~s...
m
,--v
,. - - - ~, _ _ -, -,---,
y%.
..,,,,,.,.vy
1
.i r
hi__ELeNI_111IEUS-QE11ENi_QQUIBQLi_eND_IN1IBUMENIeIIQN PAGE 27 ANSWERS ---WOLF CREEK
-86/06/03-WHITTEMORE,
~J.
~
A l
ANSWER 6.09 (2.00) j e.-----------------6.
j b.-----------------5.
i
{
c.--~~-------------7.
I d.-----------------1.
e.-----------------2.
REFERENCE WC Rod Control, Pp.21-22 l
5 ANSWER 6.10 (2.00) s.
Each channel has a bypass switch to prevent a trip at low power levels i
due to 1/2 trip logic. (1.0) (At higher levels, the trips are blocked r
I by the P-6 or P-10 permissives.)
(1.0) i b.
1.
The " Rod Stop Bypass Switch" removes the overpower rod stop function
{
for the selected channel to allow rod motion.
(0.5) 2.
The " Power Mismatch Bypass Switches" remove the. selected channel i
from the rod control system auctioneer circuit.
(0.5)
(1.0) a i
i REFERENCE
{
WC NI, Pp.15,28,40 i
i.
i i
i a
o
}
l l=
W
Zi__EBQQEQuBE1_ _NQBdelt_eRNQBdekt_EMEBGENGl_eNQ PAGE 28 BeQ10LQQ1 gel _QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
l 1
ANSWER 7.01 (2.50) i a.
Limits are imposed by power history (fuel conditioning) [0.53 or by Turbine Generator loading capabilities.
[0.51 (1.0) b.
Prevent unwarranted power excursions.
(0.5) c.
Rods must be maintained above RIL [0.51 and positioned to maintain axial flux difference in specification. [0.5]
CAF (1.0) l i
i REFERENCE j
WC GEN 00-004,Pp. 1,5 i
1 ANSWER 7.02 (2.50) 4 n.
1.
Place condensate domineralizers in service (0.25] to remove impurities. [0.25]
2.
Start S/G blowdown [0.251 to remove impurities. [0.25]
- 3. Establish main condenser vacuum (0.25] to remove 02. (0.25]
i
[Any 2, 0.5 es.] (Allow 1/2 credit for actions that are not l
performed in the MCR)
(1.0) 1 i
j b.
350 deg's. [0.25]
Previously inoperable ECCS systems are made i
operable at this time. [0.5]
(0.75) c.
Initially protection is provided by RHR reliefs. [0.25] When RHR is isolated, Cold over pressure actuation of the PORV's provides protection [0.251 until temperature increases (above 310 deg's) l i
and normal actuation of PORV's/ Safeties offer protection.[0.25) (0.75) i
+
REFERENCE WC GEN 00-002, Pp. 9,10,13 1
i l
i
Zt__EBQGEQUBE1_:_UQBdekt_eBNQBdeLt_EdEBGENGl_eUQ PAGE 29 BeQ19LQQ1 gel _QQUIBQL ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANFWER 7.03
[2.50) c.
IN:
1.
Auto closure of surge tk. vent.
[0.25]
OUT:
1.
Auto make up.
[0.25]
2.
Stand by pump start on low pressure.
[0.25]
3.
Auto isolation of Radioactive Weste bldg. [0.25) and Post Accident sampling System. [0.251
[1.25) b.
Shift to other safety loop and observe surge tk. level. [0.5]
If level i
stabilizes, leak was in the train initially in service
[0.25]
If level decrease continues, isolate service loop and observe level.
[0.25]
If level decrease stops, then leak is in the service loop.
[0.251 (1.25)
REFERENCE WC OFN 00-004, Pp. 1,2 ANSWER 7.04 (3.00) c.
When leakage exceeds the capacity of 2 chg. pumps.
[0.5) b.
1.
PORV's 2.
Pzr. Safeties 3.
RHR suction relief 4.
Letdown reliefs 5.
Excess Letdown Relief 6.
Seal Return relief
[Any 4, 0.25 es.1 (1.0) c.
1.
0,E 2.
B,F 3.
A,C
[0.25 for each correct letter.]
[1.5)
REFERENCE WC OFN 00-007, Pp. 1,2
Zi__EBQQEQWBE1_ _NQBdebt 8BNQBdelt_EMEBGENQ1_8NQ PAGE 30 BeQ10LQQ1 gel _QQNIBQL ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
ANSWER 7.05 (2.50) a.-
There will be rapid control rod insertion due to Tavg./ Tref. mismatch.
[0.5)
The operator must place system in manual control, stabilize plant, and take the instrument out of the control circuit.[0.53 (1.0) b.
There should be no actuation unless the " Loss of Load" interlock (C-7) is armed
[0.5)
Regain manual control, close valves, and reset interlock. [0.25]
(0.75) c Pressurizer level would start increasing to maximum program level.
[0.5)
The operator should take the instrument out of the control circuit. [0.25]
(0.75)
REFERENCE WC OFN 00-008, P.15 l
ANSWER 7.06 (2.50) e.
1.
BIT flow indicator 2.
RCS pressure 3.
SI pump flow indicator 4.
RHR pump flow indicator
[any 3, 0.33 es.)
(1.0) b.
1.
RCS subcooling 2.
Secondary heat sink 3.
RCS pressure 4.
Pzr. level (any 3, 0.33 each)
(1.0) c.
He is directed to the " Tube Rupture" procedure.
(0.5)
REFERENCE WC EMG E-0, Pp.8,12,13 ANSWER 7.07 (2.00)
REFERENCE WC EMG E-0 % EMG ES-01 l
Zi__EBQGEQUBES_:_NQBd8Lt_8BUQBUalt_EMEBQEUQ1_6NQ PAGE 31 BBQ19LQQ196L_CQUlBQL ANSWERS -- WOLF CREEK
-86/06/03-WHITTEMORE, J.
l l
ANSWER 7.08 (2.50) l l
e.
The SRO in the control room has overall responsibility [0.5] while the l
SRO in charge of refueling has control at the scene.[0.25]
(0.75) l l
b.
The spent fuel pool crane operator is in charge at the scene [0.25]
l l
unless the SRO in charge of refueling is present. [0.25]
(0.5) c.
Security.
(0.5) d.
Remove from over the open vessel (0.51 and move it to a safe storage location. [0.25)
(0.75)
REFERENCE l
OFN 00-018, Pp. 1-3 l
l l
ANSWER 7.09 (2.50)
-RCS subcooling (0.51 Required to be greater for adverse containment due to potential error in pressure indication [0.51
-S/G 1evel (0.5].
Required to be greater for adverse containment due to potential reference leg heatup (0.25].
-Pzr level [0.5).
Required to be greater for adverse containment due to potential reference leg heatup [0.25]
(2.5)
REFERENCE EMG E-1, P. 6 i
i
Zt__EBQQEQUBE1_:_NQBdekt_8BNQBd8Lt_EMEBGENC1_6NQ PAGE 32 B&Q10LQQ106L_QQNIBQL ANSWERS -- WOLF CREEK
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i ANSWER 7.10 (2.50) l a.
A minimum RCS pressure (0.25] must be observed to ensure that a i
sufficient NPSH is available for the pump. (0.25]
and to maintain a minimum dp across #1 seal. (0.25]
A minimum VCT pressure (0.251 must be observed to provide sufficient i
backpressure to ensure #2 seal flow.
[0.53 (1.5) b.
1.
- 1 seal dp < 200 psid.
2.
Leakoff from #1 seal < 0.2 GPM.
3.
- 1 seal backpressure < 15 psig.
1 4.
< 6 GPM seal inj ect ion flow.
5.
CCW lost.
1 6.
Bearing temp. > 200 deg's.
7 7.
Frame vibration, 5 mils 8.
Shaft vibration, 20 mils (Any 5, 0.2 es.]
(1.0)
REFERENCE WC Quest. Bk.
I i
f i
)
l l
t T
i a
1 l
Bi__eQUINISIBel1VE_EBQQEQUBEft_QQNQ1Il0N1t_6NQ_LidlI8Il0NS PAGE 33 ANSWERS -- WOLF CREEK
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ANSWER 8.01 (2.50) o.
The Shift Supervisor (0.5) b.
1.
The Plant Manager 2.
The Call Superintendent (0.5 each)
(1.0) c.
The Supervising Operator (0.5) d.
The Superintendent of Operations (or his designee)
(0.5)
REFERENCE EPIP, AOM 12-1.2, pp 1,3 GLJ 120 ANSWER 8.02 (2.50) a.
A human tag maintaining continuous monitoring of the component. (0.75) b.
Can be issued only if affects a single component OR, All components must be within sight of the human tag.
(0.75) c.
May not remain open beyond the authorizing Shift Supervisor's shift OR, One hour.
(0.5) d.
The name of the person performing the " Human Tag" function OR, No clearance order filled out.
(0.5)
REFERENCE WC Quest. Bk.
ANSWER 8.03 (2.50) o.
If an additional channel should fail, and power is lowered below the setpoint, protective system functions can become disabled or fail to enable.
(1.0) b.
If the operator determines that the P-10 permissive cannot be placed in the appropriate status, trip the reactor.
(0.75) c.
Tech. Spec's require that 3 of 4 channels be operable for startup while Standing Order # 17 requires all 4 be operable.
(0.75) d
St__eQMIN1HIB8IIVE_EBQQEQWBEnt_QQNQ1Il0 Nit _8NQ_LidlI8IIQN1 PAGE 34 ANSWERS -- WOLF CREEK
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/
REFERENCE WC Standing Order # 17 ANSWER 8.04 (2.50) a.
Immediately exit the RCA and report to Health Physics. [0.25)
Deter-mine total exposure by processing TLD before allowing re-entry back into the controlled area. [0.5)
(0.75) b.
- 1. No limits have been violated.
[0.5) 2.
The guide line for keeping exposure under 100 mrem /wk has been exceeded.
[0.25) 3.
In the event that the individual was.a pregnant female the 500 mrem recommended dose guideline for the entire gestation period has been exceeded.
[0.25)
(1.0) c.
When quick action is necessary, continuous escort or coverage by an HP substituted for an RWP.
(0.75)
REFERENCE WC Red. Prot. Man. Pp. 8,21,28 ANSWER 8.05 (2.50) e.
The subtasks are designated by letters or numbers if the sequence of performance is important.
(0.75) b.
1.
Immediately stop the performance of any other guideline and initiate guidelines to correct the RED Terminus.
(0.5) 2.
Determine which RED Terminus has priority and initiate guidelines to correct the higher priority nroblem.
(0.5) c.
Allows the operator to identify a potential thermal shock problem and implement the proper guidelines to mitigate the problem.
(0.75)
REFERENCE WEC ERG Executive Volume
)
i
's-Bi__8QMIN11188I1YE_EBQQEQUBEli_QQNQ1Il0 Nit _6NQ_LIMII6IIQNS PAGE 35 ANSWERS -- WOLF CREEK
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ANSWER 8.06 (2.50) e.
SOM requirement for Mode 4 is 1.3%
(0.75) b.
Emergency borate.
(0,5)
.,c.
No.
SOM requirement for Mode 5 is 1.0%.
(0.5) d.
The operator could immediately stop any heatup and cool the plant down below 200 deg's so that the requirement reverts to 1%, OR increase SOM using any boration method possible.
(0.75)
REFERENCE WC TS 3/4.1.1 STS RE-004 4
ANSWER 8.07 (2.50) e.
The limits on AFD assure that the Heat Flux Hot Channel Factor is not exceeded.
(1.0) b.
If AFD remains outside the 50 % power limits, it is required that Power Range Trip setpoints be reduced OR, adj ust boron to position rods to eleminate axial offset..(Either action is full credit)
(0.75) l l
c.
Power can be increased as soon as AFD is within limits for greater than
}
50% power.
(0.75) i i
REFERENCE WC TS 3/4.2.1 ANSWER 8.08 (1.00)
Should not be accepted (0.5) as the calculation is the highest value 4
divided by the average value and should be 1 or greater. (0.5)
(1.0) 1 REFERENCE WC TS 3/4.2.4 l
l
o At__8Dd1NISIBaIIVE_EBQQEQUBESt_QQNDIIIQNSt_8NQ lid 1I6110NS PAGE 36 ANSWERS -- WOLF CREEK
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ANSWER 8.09 (2.50) c.
Duty Emergency Director (0.5) j b.
Both assessment coordinators report directly to the Radiological Emergency Coordinator.
(0.73) c.
During emergency paging of personnel.
(0.5) d.
1.
Denoted by "P".
[0.51 2.
Denoted by "*"
[0.25]
(0.75)
REFERENCE WC EPP 01-1.1, Pp.3,4 & EPP 01-3.5,P.1 ANSWER 8.10 (1.50) a.
1.
Determine and attain proper plant conditions.
[0.5]
2.
Ensure performance is safe.
[0.25]
(0.75) 1 b.
Document results (0.251 and determine equipment operability [0.25] and reportability.
[0.25]
(0.75)
REFERENCE WC ADM 02-300, Pp.5,13 i
1 ANSWER 8.11 (2.50) e.
The work group responsible for the suspension [0.25] initiates a l
Temporary Modification Form. [0.53 (0.75) 1 b.
A work request (PMR) must be generated.
(0.75) j c.
1.
Electrical j umper.
2.
Mechanical j umper.
3.
Disable an annunciator.
i 4.
Pulled circuit card.
5.
Lifted lead.
6.
Blank flange installation.
[any 4, 0.25 ea.]
(1.0) a
+
o' 1
Az__8DMIN11188IIVE_EBQGEQUBEft_CQNQ1IIONit_6NQ_L151IAIlQN1 PAGE 37 ANSWERS -- WOLF CREEK
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REFERENCE WC ADM 02-121, Pp. 4,6 J
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t b
4 t
4 f
n l
l k
e 1
1 l
4 J
t
^
i 1
4 i
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- _ _,,_ _.. = _,.. - -....
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TEST CROSS REFERENCE PAGE 1
QUESTION VALUE REFERENCE
~05.01 2.50 WJE0000561 05.02 3.00 WJE0000562 05.03 3.00 WJE0000563 05.04 1.50 WJE0000564 05.05 2.50 WJE0000565 05.06 2.50 WJE0000566 05.07 3.00 WJE0000567 05.08 2.00 WJE0000568 05.09 2.50 WJE0000569 05.10 2.50 WJE0000570 25.00 06.01 2.50 WJE0000571 06.02 2.50 WJE0000572 06.03 3.00 WJE0000573 06.04 3.50 WJE0000574 06.05 2.50 WJE0000575 06.06 2.50 WJE0000576 06.07 2.00 WJE0000577 06.08 2.50 WJE0000578 06.09 2.00 WJE0000579 06.10 2.00 WJE0000580 25.00 07.01 2.50 WJE0000581 07.02 2.50 WJE0000582 07.03 2.50 WJE0000583 07.04 3.00 WJE0000584 07.05 2.50 WJE0000585 07.06 2.50 WJE0000586 07.07 2.00 WJE0000587 07.08 2.50 WJE0000588 07.09 2.50 WJE0000589 07.10 2.50 WJE0000590 25.00 08.01 2.50 WJE0000591 08.02 2.50 WJE0000592 08.03 2.50 WJE0000593 08.04 2.50 WJE0000594 08.05 2.50
'WJ1 100059 5 08.06 2.50 WJE0000596 03.07 2.50 WJE0000597 08.08 1.00 WJE0000598 08.09 2.50 WJE0000599 08.10 1.50 WJE0000600 08.11 2.50 WJE0000601 25.00 100.00 L-