ML20093D043
| ML20093D043 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/08/1984 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| KMLNRC-84-179, NUDOCS 8410110049 | |
| Download: ML20093D043 (30) | |
Text
a KANSAS GAS AND ELECTRIC COMPANY THei ELECT 54C COMPANY CLENN L MOESTER vice PatssotNT soucLean October 8, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 FMLNRC 84-179 Re:
Docket No. STF 50-482 Ref: 1) Letter dated 5/25/84 from DGEisenhut, NRC, to GLKoester, KG&E
- 2) Letter KMLNRC 84-094 dated 6/21/84 from GLKoester, KG&E, to HRDenton, NRC Subj: Operating Shift Staffing
Dear Mr. Denton:
Attached is further information about the Wolf Creek Generating Station shift conhulte.nt program that was requested by Reference
- 1), but was not available at the time of the Reference 2) transmittal.
Included are copies of the written and oral examinations given to the shift consultants, an answer key to the written exam, and test results. One individual failed to receive a passing grade on his written examination. He is presently taking an accelerated retraining program that is scheduled to be complete by November 1, 1984.
Yours very truly, f!!Y GLK:bb Attach xc:HThompson, w/a PO'Connor (2), w/a HBundy, w/a RDMartin, w/a r
8410110049 841008 i
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PDR ADOCK 05000482 V
PDR 201 N. Market -WIcNta, Kansas - Mail Address: RO. Box 208 I Wichita. Kansas 67201 - Telephone: Area Code (316) 261-6451
.a 6 l
l WOLF CREEK GENERATING STATION SHIFT ADVISOR EXAMINATION Date Administered Applicant INSTRUCTIONS TO APPLICANT:
Use separate Paper for the answers.
Write answers on one side ONLY.
Staple question sheet on top of the answer sheets.
Points for each auestion are indicated in parenthesis after the question.
The Passin9 9rade re9uires at least 70% in each cate9ers and a final 9eade of at least 80%.
The total duration of this exam will be four (4) hours.
Cate9ers
% of Applicant's
% of Value Total Score Cat. Value Cate9ers
- 6. Plant Swstems: Desi9n,-
15.35 33 Control and Instruments.
- 7. Procedures: Normal, Abnormal, Emer9encw and 14.50 71.__
Radiolo9fcal Control
- 8. Admin. Procedures, 16.7s 36 Conditions & Limitation.t 46.60 100 TOTALS FINAL GRADE:
All work done on this exam is mv own.
I have neither 9iven nor received aid.
Candidate Si9 nature ~
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,00'S AND DONT'S FOR EXAMS i
00'S
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1.
Read the questions carefully.
2.
Note the number of points allotted to each question.
3.
- Question the examiner if in doubt.
4 4.
- Pace yourself--don't spend hours drawing fancy sketches.
5.
Show all calculations.
6.
Look for any two-part questions which may not be labelled as such.
- 7 '.
' Recognize whether definition or explanation (discussion) is required.
8.
- List more than two reasons 1,f some or few are requested.
DON'T 1.
Leave any blanks.
2.
Read hidden meanings into the questions.
j.
3.
Show the examiner your answers for his concurrence.
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6.
Plant Systems: Design',' Control and Instrumentation 6.1 The reactor is operating at 100% power with all' control systems in automatic.. For.the following failures, what reactor protection signal will cause the reactor to trip? Assume no operator action and consider c,-
each failure independently. BRIEFLY EXPLAIN.
a.
CVCS flow rate drops to minimum of 47 gpm.
(1.0)
-b.
A cold leg temperature detector (controlling) fails high.
(1.0)
~6.2 Use Figure 6.2 to answer the following questions:
l l
'Give the flow path for the following modes of operation of the M/U
- system by indicating which valves are open and which are shut.
a.
Dilution
-(.25)
,?-
- b. -Manual
(.25) c.
Immediate borate
(.25)
.d.
Alternate dilute
(.25) 1 6.3 a.
Explain the operation of the source range detector.
(1.25) b.
Why is. gamma compensation not required in the power range? (Two reasons are required.)
(1.0)
-c 6.4
- a. 'What is the function of the seal oil system?
(.75) b.
What is the function of the steam seal system?
(.75) c.
State the sources of steam to the steam seal. system.
(1.25) 6.5 a. What are the TWO conditions that will cause automatic startup of The Emergency Diesel Generators?
(0.6) b.
What are FIVE conditions that will cause automatic trip of the Emergency Diesel ENGINES when running in the Emergency Mode?
(1.5)
What are the TWO conditions that will cause automatic trip of
- c..
-the Emergency Diesel Generator BREAKERS when running in the Emergency Mode?
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Plant Systems: Design, Control and Instrumentation 6.6 a.
What two conditions will initiate Phase B Containment Isolation.
Include logic and setpoints.
(1.0)'
b.
How does Phase B Containment Isolation affect the Component Cooling Water System? Be specific.
(1.5) 6.7 Utilizing the attached CVCS drawing, (Figure 6.1), answer the following questions.
a.
Where does this valve divert to?
(.25) b.
What are the TWO purposes of this valve?
(.5) c.
To which position will this valve fail on loss of control air?
(.25) d.
In which positions on the Reactor Makeup Control System Mode selector switch is this valve (FCV-1108) enabled to open?
(0.4) f.
What are TWO signals that will result in AUTOMATIC closure of these valves (LCV-1128 and C)? (No setpoints required).
(0.5) g.. Where does this valve divert to?
(.25)
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Procedures: Normal, Abnormal, Emergency and Radiological Control 7.1 The following questions concern Precautions and Limitations in
" Hot Standby to Minimum Load" (GEN-00-003).
-a.
What control action should be taken by the operator before.
adjusting RCS boron concentration? EXPLAIN WHY.
(1,0) b.
While diluting to the Estimated Critical Boron Concentration, one source range channel changes from 8 counts to 17 counts and the other channel changes from 6 to 9 counts. What action (1.0) is required?
c.
Tave is lowered to 548 F with the reactor at 2% power due to excessive steam removal. What action is required by Technical Specifications?
(0.5) d.
What " Precautions and Limitations" are being challenged if you were performing the following operations?
1.
Diluting to the Estimated Critical Boron Concentration with the reactor slightly subcritical?
(0.5) 2.
Increasing power from P-6 to P-10 with control bank D with-drawal while slowly diluting because control bank D rods
~
are nearly all the way out.
(0.5) 7.2 List the Critical safety Functions (CSF)'in the order that the Status Trees for the CSFs are to be checked to evaluate the safety state of the plant in accordance with " Critical Safety Function Status Trees (CSFST)", EMG F-0.
(1.5) 7.3 Indicate the lowest emergency event classification that requires activation of the following Emergency Centers:
a.
Emergency Operation Facility (EOF)
(0.5) b.
Technical Support Center (TSC)
(0.5) 7.4 Match the trends from Column B that'would be indicative of conditions for Column A malfunctions prior to any protective funciton actuations.
There may be more than one answer. Place answers on answer sheet (e.g.,c-7,8,9)
COLUMN A COLUMN B a.
Small Breaker LOCA Inside 1.
Decreasing Pressurizer Level Containment 2.
Decreasing Steam Pressure b.
Steam Leak Inside Containment 3.
Increasing Containment Pressure 4.
Decreasing Tave
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Increasing Containment Radiation 6.
Decreasing Pressurizer Pressure (3.0) sh
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Page 4
- 7. Procedures: Normal, Abnormal Emergency and Radiological
~ Control 7.5 What are the minimum required' AC electrical sources which must be operable in Mode 3?
(2.5) 7.6. Define the following:
- a.: ~ Controlled leakage
(.75) b '. Axial. flux difference'
(.75) c.
Dose equivalent I-131
(.75)
- d.
Mode 5: Cold Shutdown
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Page-5 8.
Administrative Procedures, Conditions and Limitations 8.1 As shift supervisor / supervising operator you have the responsibility
'of ensuring the request of equipment to be removed from service is accurate and complete.
- a. ' What information must be on a Danger - DO NOT OPERATE (DN0) Tag? '(1.4)
-b..When is it permissible to use a human DN0 tag?
(1.0) 8.2 Under the RP manual each WCGS supervisor is responsible to aid Health Physics in maintaining ALARA. State four (4) responsibilities you as a supervisor and held accountable.
(1.6) 8.3 In accordance with Administrative Procedure ADM 02-001 " Operations",
what are the minimum duty shift manning requirements for the follow-ing during power operations?
Do not consider the two hour exceptions.
1.
Licensed Senior Operator.
Include the titles for positions held.
2.
Reactor Operators.
Include license requirements.
3.
Nuclear Station Operators.
(1.95) b.- What is the minimum number of Fire Brigade members required onsite at all times AND how many of the minimum shift crew are NOT to be included as members of the Fire Brigade?
(0.8) 8.4 For each of the following leak locations, give the maximum allow-able leak rate AND the basis for~each:
a.
Unknown location b.
Through a pressurizer code safcty valve to the Pressurizer Relief Tank.
Through the wall of the line between the pressurizer relief c.
valves and the pressurizer.
d.
Total flow to Reactor Coolant Pump seals.
~
TOTAL Steam Generator tube leakage.
(4.0) e.
8.5 During refueling operations involving core alterations:
a.
What are the minimum neutron flux monitoring requirements as required by Technical Specifications?
Include the monitoring locations and method of monitoring.
(0.8) b.
What are the minimum Technical Specification requirments in
. regard to:
1.
Containment Building equipment door?
2.
Containment Building airlocks?
3.
Each Containment penetration providing access to the out-side environment?
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- 8.~
Administrative Procedures, Conditions, and Limitations
. 8.6~ What action must be taken if the Reactor Coolant System Pressure Safety Limit-is exceeded, in accordance with Technical' Specifications?
. Consider all MODES.
,(1.5) 8'.7 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. 'Initally assumes the responsibilities of the Operations Emergency Coordinator?
(0.5) d.
Is the normal relief for the Operations Emergency Coordinator?
(0.5) a l
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b KEY Page 1 6.1 a) Letdown flow is greater than charging flow which will lead to letdown isolation at 17% level. After this the pressurizer will refill and cause a Reactor Trip due to high Pressurizer level.
(1.0) b) The plant will trip on low Pressurizer Pressure. Tc Failing _
high will cause Tave to Fall high driving rods in the reduce
.Tave. This will cause Pressure to decrease faster than Press-urizer heaters can make up for the decrease REF: NPS-217-6 (1.0) 6.2 a)
IIIA & IIIB open 110A & 110B shut
(.25) b)
111A & 110A open 1118 & 1108 shut
(.25) c) HV810A open 110A & B, 111A & B shut
(.25) d)
111A & B, 110B open 110A shut
(.25)
REF: SNP-21 Rx M/U sys 6.3 a) A neutron enters the detector and interacts with the boron.
This reaction causes an alpha to be emitted which causes ioniza-tion of the gas. The ion pairs are then collected and utilized as an output pulse to indicate neutron level.
(1.25) b)
1.
Gamma flux is proportional to power.
2.
Neutron flux is much greater than gamma flux.
(1.0)
REF: SNP-36 6.4 a) Prevents air leakage in the H leakage out of the generator.
(.75) 2 b) Prevents air leakage in the steam leakage out of.the main turbine.
(.75)'
c) 1.
Main steam 2.
Aux steam 3.
LP turbine 9th stage extraction 4.
HP turbine glands 5.
Turbine stop and control valve leak offs REF: SNP-27 (1.25) 6.5 a)- Safety Injection (0.3)
(0.3)
- Undervoltage on NB bus b)- Overspeed (0.3)
- low lube oil pressure (0.3)
- high crankcase pressure (0.3)
- high Jacket water temperature (0.3)
- failure to start (0.3) i,,,_o
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KEY Page 2 6.5 CONT.
c)- Neutral ground overcurrent (0.3)'
- differental overcurrent (0.3)
-REF:
NPS-213-5 6.6 a)~- Containment Hi 27 psig 2/4
~
(0.5)
- Manual 2/2 (0.5) b) The phase B signal shuts the CCW supplies (2) and returns (4).
-This will isolate CCW;to the following components:
- RCP motors
- RCP thermal barrier Hx
- Excess letdown-Hx
- RCDT Hx.
REF:. NPS-221-3, 217-5 (1.5)
~ 6.7 a) Pressurizer Reilief Tank (0.25) b)
.1. Prevents steam flashing across orifices (0.25)
- 2. RCSL pressure control during RHR operations (0.25) c) to bypass the deminerlizer (0.25)_
d) Alt. Dilute, Dilute, and Manual (0.3) e) : Automatic, Alt. dilute, Borate, and Manual (0.4) f) Lo-Lo VCT level and safety injection (0.5) g) RCDT (0.25)
REF: NPS-217-1 t
A Y Y N.
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'7.1 a) When changin'g the Reactor Coolant System Boron Concentration, Pressurizer. sprays should be utilized to minimize the differential between the Pressurizer and the Loop Boron Concentration to
< 50 ppm by placing one group of Pressurizer Backup Heaters in Manual-0n and leaving Pressurizer Spray Control in Auto.
(1.0) b)
If, during any step involving boron dilution, the source range
. count rate. increases by a factor of two, dilution shall be stopped immediately and suspended until core reactivity has been evaluated.
(1.0) c) When the reactor is critical the_ lowest operating, coolant loop
-Tave must be maintained > 551 F.
If temperature decreases to 551 F, restore to > 55T F within 15 minutes or be in hot standby within the next 15 minutes to satisfy technical spec-ification 3.1.1.4.
(0.5) d)
1.
Criticality shall not be achieved by boron dilution with the exception of initial criticality and initial-criticality after refueling.
(0.5) 2.
Do not add positive reactivity by more than one controlled method at a time.
(0.5)
REF: GEN-00 7.2- - Subcriticality
. Core Cooling
- Heat Sink Integrity
--Containment
- Inventory REF:
EMG FR-0 (1.5) 7.3 a) Site Emergency (0.5) b) Alert (0.5)
REF: WCGS E-Plan 7.4 a) 1,3,5,6 (1.5) b) 1,2,3,4,6 (1.5)
REF: EMG E-0
'7.5 -1. To physically independent circuits between the offsite trans-mission network and the Onsite Class IE Distribution System,
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. 2. Two separate and: independent diesel generators, each with:
'a.
A separate day containing a miniumu volume of 390 gallons of fuel, b.
A spearate Fuel Oil Storage System containing a minimum
^
volume of 85,300 gallons of fuel, and c.
A separate fuel transfer pump.
.REF: Tech.' Spec. 3.8.1 (2.5) 7.6 a) That seal water flow from RCP seals.
(.75)-
b) Difference in normalized flux signal between the top and bottom halves of a two section excore neutron detector.
(.75) c) Dose equivalent I-131 is that concentration of I-131 which.
alone would produce.the same thyroid dose as the quantity and isotopic mixture of I-131, 132, 133, 134, 135 actually present. (.75) d) When Keff 4.99; 0% rated power; Tave f.200 F.
(.75)
REF: Tech.-Spec. Sec. 1.0 w
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KEY Page 5 8.1 a)
- 1.. Clearance order number
- 2. ~Date/ Time 3.
Component tagged 4.
Component Position 5.
Issued by (S.S. name) 6.
Tagged by 7.
Verified by (1.4) b) Jobs of a trouble shooting or adjusting nature that required that a component by isolated or deenErgized, then restored several times over a short period of time to allow for work and then test.
(1.0)
'REF: 'ADM 02-100 8.2 1.
All work is performed in accordance with station procedures, rules, and Radiation Work Permits.
2.-'All personnel receive training and are knowledgable in radio-
-logical protection.
- 3. 'Adminstrative dose limits are not exceeded by personnel under his supervision.
4.
The Health Physics Group is advised of any changes in work procedures, or unusual occurences or incidents where radio-logical conditions may be influenced.
~
NOTE: Other responsibilities will be considered at the graders'
' discretion.
REF: RP Manual Pg. 4-5 (1.6) 8.3 a) 1.
Shift Supervisor and Supervising Operator 2.
2 Reactor Operators-one must be at the controls during-power operations 3.
Station Operators - 4 (1.95)
- b) ' Minimum'of 5 brigade' members. 3 of minimum shift crew may not be included.
(0.8)
REF: ADM 02-001 8.4 a) 1 gpm - Sufficiently low to ensure early detection of additional leakage b) 10 gpm - provides allowance for a limited amount of leakage from known sources and will not interfere with the detection of unidentified leakage.
c) 0 gpm - may be indicative of an impending gross failure of the pressure boundary.
d) 8 gpm per RCP - ensures that SI flow will not be less than assumed in accident analyses.
- e) 1~gpm - ensures dose less than 10 CFR 100 limit.
(4.0)
REF: Tech. Spec. Bases 3/4 4.7.2
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KEY Page 6 8.5 a) Two source range detectors with indication in the control' room. One of which provides audible indication of count rate in containment and in the Control room.
(0.8) b)
1.
Must be_ closed w/ minimum of 4 bolts (0.4) 2.
At least one airlock door closed (0.4) 3.- Access to atmosphere must be locked closed by blank flangh or by manual valve or capable of closed by an automatic isolation signal (0.4)
REF: Tech. Spec. 3/4 Sec. 9 8.6 Modes 1 & 2 - Hot standby within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Modes 3,4 & 5 - Restore pressure to within limit within 5 minutes All - Notify NRC within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> -
- V.P. Nuclear and PSRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- Evaluate and prepare report for PSRC review
- Submitt report to NRC, V.P. Nuclear, and NSRC within 14 days
- Criticality requires NRC approval
= REF: Tech. Spec. Sec. 6 (1.5) 8.7 a) Shift Supervisor (0.5) b) Plant Manager or Duty Call Superintendent (1.0) c) Supervising Operator (0.5) d) Operations Superintendent (0.5)
REF: Tech. Spec. Sec. 6 O
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FORM 1977 REY.1 47 INTEROFFICE CO R RESPON D E NC E To,-
Paul Turner non : -
Dale Moses oir e, July 27, 1984 suancr. Shift Advisor Exam Results The following are the results of Shift Advisor Training program:
QUIZZES:
- 1
- 2
- 3 Armstrong 86.2 81.5 92.6 Cade 67.8 79.5 86.6 Jurrus 88.5 92.1 90.6 Molpus 86.2 70.0 98.6 Ochs 85.1 75.2 98.6 Rathbone-81.6 88.9 92.6 WRITTEN EXAM:
Sec.6 Sec.7 Sec.8 OVERALL
'Armstrong 87.0 92.8 89.9 89.8 Cade 73.3 97.2 94.0 88.2 Jurrus 84.0 91.0 76.1 83.4 Molpus 91.5 89.7 76.4 85.5 Ochs 83.7 71.7 92.8 83.3 Rathbone 58.3*
77.2 85.7 74.0**
SIMULATOR:
ORAL:
OPERATIONS:
Armstrong Pass Pass Cade Pass Pass
~Jurrus Pass Pass Molpus Pass Pass 0chs Pass-Pass Rathbone Pass Pass
- Does not meet 70% passing requirement for category.
- - Does not meet 80% overall passing requirement.
The quizzes, written exams, and simulator exam reports are available upon request for your review and for training record update.
. h New E. Dale Moses EDM/ mis.
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w WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE: Bob Jurrus Page 1 - of 2
GRADE OUESTION S-Why take Rx power to 2% on plant startup?
S Limitations on rod motion during startup?
5 When is SR turned off?
S Why is 0 TDT setpoint so high?
S Why letdown Regen HX high T alarm?
U~
Discussion of CB."D" rod drop effects.
S' Effects of, low Tavg due rod drop?
U How do you know keff 1, now.
S' Why IR indication different.
S What are effects of CB "D" position on CR mode switch?
S B0P panel Tech Spec related equipment?
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1 WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE:
Bob Jurrus Page 2 of 2
' GRADE 0VESTION t
S How raise TG power output?
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S What is the expected response of FW reg. system to power increase?
S What area radiation monitors in Tech Specs.
S Explain precautions for power increase? (Gen Oper. Curve)
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-g t he WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE:
Shannon Armstrong Page 1
of 2 GRADE 00ESTION S
Discuss purpose and use of L/D pressure CV?
S Use of power defect curves and nomographs for power ramp?
S Boration flow paths?
S T.S. misaligned rods, RIL, AFD?
'S-PR Flux deviation alarm, causes, set points?
S TS on Min. temp for criticality.?.
S Demineralizer-operation S ~
Actions on rod control failure?
S M.T. turning gear indication, ECC, Sp, Valve Pos. Ind.
S Runbacks, Setbacks signals?
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o WOLF CREEK GENERATING STATION, Simulator Oral Exam Report CANDIDATE:
Walt Molpus Page 1
of 2
GRADE OUESTION
.S Capacity of start up.MFP?
S Aux feed pump auto start on loss of MFP. How is signal defeated during S.U?
S Min. temp. for criticality? Why?
.S What is adverse containment?
S When can you throttle aux fee,d?
S Required chem sampling freq?
S Dilution required for ramp?
M Tech. procedure for loss of NB0-1?
-S Why use alt. dilute instead of dilute?
S Load limit with loss of Circ pump?
M What programs T-Ref which IMP?
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WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE:
Randy Cade Page 1
of 2 i
GRADE OVESTION MS Reasons for RIL's - bases for T/S on RIL?
S Who maintains the various plant logs?
S T/S on AFD and actions required >90% and 490? 50%
S What are your actions on the CCW High Surge tank level & how are you diagnosing the leak?
S What methods of Imm. Boration are available?
S What causes the PR upper detector flux dev. alarm and why.it was in?
S What are the different modes of operation for the Steam dumps?
S What SI Signals are there? Can any of these be blocked and where?
5 Extraction Steam Sources and uses-Heating of feedwater and why we heat feedwater and cold reheat steam.
S Use of S/G PORV's with a loss of air-what is the supply-and what else is the supply used for?
S Precautions when starting a MFP - how many are required at full power-where do the heater drains tie in to the system?
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- o.3 WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE:
Walt Molpus Page ' 2 of 2
i GRADE OUESTION S
What is program signal for pzr. level?
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What controls P.D.P. speed?
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Rx trip circuitry?
S Turbine supervisory inst.
S Full Arc - Partial arc admission i
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AFW TS, S/U feed system?
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WOLF CREEK GENERATING STATION Simula'.or Oral Exam Report CANDIDATE:
Randy Cade Page 2 of 2 GRADE OVESTION S
Interlocks associateo w/ letdown isolation and orifice iso'lation valves-excess letdown path?
5 CCP operation and mini-flow operation - flow control and inputs from PZR level control?
S Why are rods banks overlapped?
S What are the inputs to the rod control system? Discussed Rod control interlocks?
S What are the effects of various NR RTD failures-What are the indications of these failures-What is Auct Hioh Tava used for?
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'.0chs-A CANDIDATE:
Page 1 - of 2 GRADE OUESTION S
Are + VARS going in or out?
M What happens to volt as you increase load?
U First stage pressure feedback. control-What does it do?
S What would happen to load if one Gen bkr. opened?
U What happens if you loose Cirq pump at 100%?
S Steam dump arming circuits?
S What is feed pump program DP?
S What does Lolo limit mean? What is the T/S?
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-How do you verify feed water isol?
S How much dilution is required for 20 - 50% power change?
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Program T-Ref?
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WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE:
A. Ochs Page 2 of 2
l GRADE OUESTION S
Pzr. level program inputs?
S Pzr. master level controller inputs?
S-What do you do if you violate a tech spec. safety limit?
S Is the PDP safety related?
S Reason for partial trip?
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'6 WOLF CREEK GENERATING STATION Simulator Oral Exam Report CANDIDATE: Bob Rathbone Page 1 of 1 GRADE OUESTION M
Alarm recognition, Why is the Gen of alarm in? How can we clear it?
U Where do we read eccentricity when on TG?
M Discuss turning gear ops & ind?
S Explain shrink & swell?
S Describe indications of droppe,d Rod?
M Discuss T.S. on Min. temp. for criticality?
M Discuss MW, MVARS, PF?
S-Explain use of L/D pressure control valve?
S Discuss BKR indications?
S Discussed feed / condensate, HTR drain pump lineups?
4 S
TS on electrical busses?
S Reason for L/D divert?
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