ML20059K029
| ML20059K029 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 08/01/1990 |
| From: | Mcconnell T DUKE POWER CO. |
| To: | Casto C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20059K006 | List: |
| References | |
| NUDOCS 9009210117 | |
| Download: ML20059K029 (11) | |
Text
{{#Wiki_filter:.. s ' *' \ WRC' Official Use Only ENCL 0sVRE 2 SRO
$go g,,do, l
l l Nuclear Regulatory Commission l Operator Licensing l Examination l troNud: s z.y 446 MGT l #G9 Pos' Er< m : Hy 4167 tl 99 l l This document is removed from l Official Use Only category on date of examination. NRC Official Use Only l 9009210117 900903 PDR ADOCK 05000369 p V PDC l L. -J
( , U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 2 FACILITY: McGuire 1 & 2 REACTOR TYPE: PWR WEC4 DATE ADMINISTERED: 90/07/30 CANDIDATE: INSTRUCTIONS TO CANDIDATE: Points for each question are indicated in parentheses after the question. To pass this examination, you must achieve an overall grade of at least 80%. Examination papers will be picked up four and one half (41/2) hours after-the examination starts. NUMBER TOTAL CANDIDATE'S CANDIDATE'S QUESTIONS POINTS POINTS OVERALL GRADE (%) 100 100.00 All work done on this examination is my o*:a. I have neither given nor received aid. 1 Candidate's Signature I y l i l a a
. . l NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination. :
- 3. Restroom trips are to be limited and only one candidate at a time may .
leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. 4.. Use black ink or dark pencil only to facilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (if necessary).
- 7. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT. WRITE ON THE BACK SIDE OF THE PAGE.
- 8. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 9. Print your name in the upper right-hand corner of the first page of answer sheets whether you use the examination question pages or separate sheets of paper. Initial each of the following answer pages.
- 10. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
- 11. If you are using separate sheets, number each answer and skip at least 3 lines between answers to allow space for grading.
- 12. Write "Last Page" on the last answer sheet.
- 13. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols.such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out. i l L L j
. . 1
- 14. The point value for each question is indicated in parentheses after the !
question. The amount of blank space on an examination question page is l NOT an indication'of the depth of answer required. i
- 15. Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: partial credit will NOT be :
given on multiple choice questions. !
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is ,
worth one point and asks for four responses, each of which is worth 0.25 ! points, and you give five responses, each of your responses will be worth O.20 points. If one of your five responses is incorrect, 0.20 will be i deducted and your total credit for that question will be 0.80 instead of , 1.00 even though you got the four correct answers. ,
- 18. If the intent of a question is unclear, ask questions of the examiner only.
i
- 19. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80% or greater. ,
- 21. There is a time limit of (4 1/2) hours for completion of the examination.
(or some other time if less than the full examination is taken.)
- 22. When you are done and have turned in your examination, leave the examin- t ation area as defined by the examiner. If you are found in this area while the examination is still in progress, your license may be denied or revoked.
I l l l l
I' . . SENIOR REACTOR OPERATOR Page 4 QUESTION: 001 (1.00) Given the following conditions: NC pump start in progress. il seal leakoff flow is 0.1 gpm. WHICH ONE (1) of the following actions needs to be performed before starting the pump per OP/1/A/6150/02A,
- Reactor Coolant Pump Operation?"
- a. Raise VCT pressure.
- b. Decrease NO. I seal differential pressure,
- c. Close the seal return line vent.
- d. Rotate the NC pump shaft.
QUESTION: 002 (1.00) Given the following conditions: Reactor power is 100%.
-Pressurizer level control selector switch in the 12 position.
Pressurizer level channel 1 fails LOW.
-Pressurizer level control is in AUTO.
WHICH ONE (1) of the following describes the plant response to the pressurizer level channel failure? ASSUME N0 operator action is taken,
- a. Charging flow decreases, actual level decreases, letdown isolates, and the level stabilizes at setpoint.
- b. Charging flow remains the same, letdown flow temperatures increase, l and backup heaters turn on.
- c. Charging flow increases, letdown isolates, actual level increases, and .
the reactor trips on high pressurizer level,
- d. Charging flow remains the same, letdown isolates, heaters turn off, ,
and the reactor trips on low pressurizer pressure. I i l
SENIOR REACTOR OPERATOR Page 5 l l l QUESTION: 003 (1.00) ] l WHICH ONE (1) of the following sets of plant conditions is used as the basis i for the minimum shutdown margin in MODES 14 as specified in Technical i Specifications 3.1.1.1, " Shutdown Margin Tave>200F?* )
- a. End of core life, NCS temperature 557 degreer, steam line break .
- b. End of core life, NCS temperature 588.1 degrees, a stuck open PZR i PORV.
- c. Beginning of core life, NCS temperature 588.1 degrees, steam line break,
- d. Beginning of core life, NCS temperature 557 degrees, a stuck open PZR ;
PORV.
)
QUESTION: 004 (1.00) WHICH ONE (1) of the following plant conditions will result in a main ) feedwater isolation? ;
- a. Doghouse level 10.5 inches
- b. Steam line pressure 575 psig l c. Steam generator level 80.5% ,
- d. Reactor trip and Tave 558 F l
~ l i l i
i l SENIOR REACTOR OPERATOR Page 6 i l l 1 l l I E QUESTION: 005 (1.00) i Given the following plant condition:
~
)
! -Performance of OP/1/A/6100/01, " Controlling Procedure for Unit Startup." ; \ l WHICH ONE (1) of the following would cause the CLA discharge j isolation valves to receive an open signal? 4
- a. P 4 actuation
- b. Pressurizer low level l c. Steam generator low level
- d. P ll setpoint l
i l I QUESTION: 006 (1.00) WHICH ONE (1) of the following will result in clearing the ' ROD AT BOTTOM" annunciator as the control banks are withdrawn?
- a. Bank A reaches 7 steps. 1 l b. Bank B reaches 7 steps,
- c. Bank C reaches 7 steps.
- d. Bank D reaches 7 steps. ,
1 1' I t QUESTION: 007 (1.00) WHICH ONE (1) of the following is an input to the ROD BANK LOW LOW alarm? L
- a. Auctioneered high Tave . ,
l I b. Auctioneered high Tref u : l c. Auctioneered high NI power level 1^
- d. Auctioneered high delta T t , - ~ ~ - ..w-
y e SENIOR REACTOR OPERATOR Page 7 l QUESTION: 008 (1.00) Given the following conditions:
- Reactor power is 75%.
- Channel N41 is the highest reading Power Range Channel.
- Rod control is in AUTOMATIC.
- Channel N42 instantaneously fails LOW.
- N0 operator action is taken.
WHICH ONE (1) of the followir,g describes the resultant control rod system response?
- a. Control rods will drive in at maximum rate.
- b. Control rods will drive in at minimum rate,
- c. Control rods will drive out,
- d. Control rods will not move.
QUESTION: 009 (1.0f WHICH ONE (1) c) 1 following statements describes one of the purposes of the Nuclear Insh maent Channel Comparator? 1
- a. Detects axial flux tilts.
1
- b. ' Detects faulty PR channels,
- c. Compares upper vs. lower detectors.
- d. Alarms on 1% deviations.
i i l l l l l l
SENIOR REACTOR OPERATOR Page 8 QUESTlor. 010 (1.00) , Given the following conditions: Reactor is in MODE 5. Source range instrument N31 has read 80 cps for several hours Boron concentration is 1300 ppm
-Electronic noise from a welder caused N31 to reach 3000 cps for 30 seconds.
WHICH ONE (1) of the following describes plant response?
- a. Suction of the centrifugal charging pumps switches from VCT to FWST.
- b. Containment purge supply and exhaust dampers close.
- c. Containment evacuation alarm sounds,
- d. A containment ventilation isolation actuates.
QUESTION: 011 (1.00) WHICH ONE (1) of the following describes the response of the VUL system if containment pressure increases to 0.5 psig?
- a. VU AHUs and RA fans go to maximum cool
- b. VL AHUs shift to hi speed
- c. VL AHUs RV flow goes to maximum
- d. Pressurizer booster fans alternate fan auto starts L
I .
)
SENIOR REACTOR OPERATOR Page 9 h ( QUESTION: 012 (1.00) WHICH ONE (1) of the following systems supplies cooling water for the VUL j system AHUs? ! l
- a. RC system
- b. KC system
- c. RL system ,
e
- d. RV systen ;
QUESTION: 013 (1.00) WHICH ONE (1) of the following causes the steam to flow up through the ice condenser following a LOCA?
- a. Lower inlet doors opening to the turning vanes.
-b. Containment fans in the bottom of the ice condenser blowing steam up through the ice condenser.
- c. Impingement plates directing steam flow upward from the lower plenum,
- d. Containment fans in upper containment drawing the steam flow upward. >
SENIOR REACTOR OPERATOR Page 10 QUESTION: 014 (1.00) WHICH ONE (1) of the following statements contains logic that would result in containment spray actuation? ASSUME Containment Spray / Phase B has actuated,
- a. Manual actuation with Containment Spray / Phase B actuation signal CPCS at 0.0 psig
- b. Manual actuation with Containment Spray / Phase B reset CPCS at 0.40 psig
- c. Auto actuation with i Containment Spray / Phase B ectuation signal l CPCS at 0.28 psig
! d. Auto actuation with l Containment Spray / Phase B reset i CPCS at 0.40 psig I i QUESTION: 015 (1.00) WHICH ONE (1) of the following would cause "A" FWPT to trip? l
- a. Pump suction pressure is at 200 psig.
l l 1
- b. FWPT oil pressure is at 12.5 psig.
- c. FWP discharge pressure is 1325 psig.
- d. Water level in outer doghouse is at 10.5 inches.
t l' l l
l , i t . . k- SENIOR REACTOR OPERATOR Page 11 - t
; QUESTION: 016 (1.00)
Given the following list of plant actions: ,
- 1. TD CA pump trip. 1
- 2. CF isolation. ;
- 3. Turbine trip.
- 4. CF pumps trip. .
WHICH ONE (1) of the following selections will result if a steam generator level INCREASES to 82%?
- a. 1, 2, 3
- b. 1, 2, 4
- c. 1, 3, 4
- d. 2,3,4 QUESTION: 017 (1.00) l Given the following list of valves:
l- '
- 1. CF to CA nozzle isolation valve (CF 129)
- 2. S/G CF control valve (CF-20)
- 3. S/G CF tempering isolation valve (CF-153)
- 4. FWP isolation valve (CF-5) ,
WHICH ONE (1) of the following combinations of valves will close from a manual feedwater isolation signal?
- a. 1, 2, 3
- b. 1, 2, 4
- c. 1, 3, 4
- d. 2,3,4 f
T
. SENIOR REACTOR OPERATOR Page 12
, QUESTION: 018 (1.00) WHICH ONE (1) of the following describes the rate of heat transfer from the NC system to the steam generators following a reactor trip?
- a. Decrease at higher NC system temperatures.
- b. Decrease at higher CA flow rates.
- c. Increase at higher NC system flow rates.
- d. Increase at higher CA temperatures.
QUESTION: 019 (1.00) WHICH ONE (1) of the following statements describe a power cabinet NON URGENT FAILURE in the rod control system?
- a. Coil current does not match the ordered current.
- b. Zero current ordered simultaneously to moveable and stationary coil,
- c. Zero current from a DC power supply in a power cabinet,
- d. Current is present to non selected rod or rod groups moveable and lift coils.
QUESTION: 020 (1.00) WHICH ONE (1) of the following items will AUTOMATICALLY terminate a waste gas discharge? i
- a. High radiation alarm on EMF-36 UNIT VENT GAS (Low Range).
- b. EMF-50 WASTE GAS (High Range) fails low.
- c. Waste gas analyzer high oxygen in discharge line,
- d. Waste gas decay tank high pressure.
I j
SENIOR REACTOR OPERATOR Page 13 QUEST 10N: _021 (i.00) Given the folicwing conditions:
-Reactor power is 60%.
-Loop 10 Delta T indicates LOW.
Loop IC Tave indicates HIGH. WHICH ONE (1) of the following RTD failures cause these indications?
- a. Thot failed high.
- b. Thot failed low,
- c. Tcold failed high.
- d. Teold failed low. ,
i b QUESTION: 022 (1.00) WHICH ONE (1) of the following sources discharges into the NCDT? ,
- a. Reactor vessel 0 Ring leakoff,
- b. NV letdown relief valve downstream of letdown orifice (NV-6),
- c. NV letdown relief valve downstream of letdown heat exchanger (NV-156),
- d. NI pump suction relief valves, e P
I I
SENIOR REACTOR OPERATOR Page 14 QUESTION: 023 (1.00)
- At WHICH ONE (1) of the following NC system pressures would a CLA tank level decrease first be noted following a large break LOCA?
- a. 780 psig
- b. 680 psig
- c. 580 psig
- d. 480 psig l
l QUESTION: 024 (1.00) t- , WHICH ONE (1) of the following conditions describes the Techni:a1 Specification 3.5.5, " Refueling Water Storage Tank," requirement for an operable RWST in MODE I? Borated Water Boron Solution Volume Concentration Temperature l a. 3'/s,000 gallons 2050 ppm 95 F 1
- b. 375,000 gallons 1950 ppm 95 F
- c. 395,000 gallons 2050 ppm 65 F
- d. 395,000 gallons 1950 ppm 65 F L QUESTION: 025 (1.00)
- 1. WHICH ONE (1) of the following sets of conditions is indicative of pump runout?
I a., High discharge pressure, high flow, and high power requirements.
- b. High discharge pressure, low flow, and low power requirements.
- c. Low discharge pressure, high flow, and low power requirements. !
- d. Low discharge pressure, high flow, and high power requirements.
l z- .!
, w -
SENIOR REACTOR OPERATOR Page 15 QUESTION: 026 (1.00) WHICH ONE (1) of the following is the set of pressures that will energize the "C" (proportional) and backup heaters, respectively? ASSUME pressurizer pressure control is set for normal operation.
- 4. 2280 psig, 2010 psig
- b. 2250 psig, 2210 psig
- c. 2280 psig. 2250 psig
- d. 2250 psig, 2240 psig QUESTION: 027 (1.00)
Given the following conditions:
-Reactor power is 100%.
-Pressurizer spray control is in AUTO.
-Pressurizer. spray valves open.
WHICH ONE (1) of the following is the response of the PORVs and spray valves if pressurizer master controller setpoint is inadvertently changed to ??70 psig? ASSUME a step change in the setpoint and that pressurizer pressure control remains in automatic. pu & w t kw I
.The automatic responses of the PORVs and spray valves,will be:
- a. PORY NC 34 opens, spray valves remain open,
- b. PORVs NC 32, 34, and 36 remain closed, spray valves remain open.
- c. PORVs NC 32, 34, and 36 remain closed, spray valves close,
- d. PORVs NC 32 and NC 36 open, spray valves close.
I
SENIOR 8 FACTOR OPERATOR Page 16 QUESTION: 028 (1.00) WHICH ONE (1) of the following describes the reason for the pressurizer program level changes?
- a. Provides an adequate margin between the program level and the high level reactor trip.
- b. Maintains a constant mass in the reactor coolant system reducing the need to increase and decrease charging and letdown for changing reactor power levels,
- c. Provides an adequate margin between program level and low level heater shutoff and letdown isolation,
- d. Designed to permit the pressuriter system to properly function and maintain a constant pressure at full power.
QUESTION: 029 (1.00) WHICH ONE (1) of the following statements describes a trip associated with the P-8 permissive?
- a. Source range reactor trip
- b. Pressurizer Iigh pressure trip
- c. Single loop low coolant flow trip
- d. NC pump bus undervoltage trip QUESTION: 030 (1.00)
WHICH ONE (1) of the following is the time delay for the automatic start of i the hydrogen skimmer fans on a phase "B" actuation?
- a. 10 seconds
- b. 30 seconds
- c. 7 minutes
- d. 10 minutes
SENIOR REACTOR OPERATOR Page 17 i
- QUESTION: 031 (1.00)
WHICH ONE (1) of the following sets of signals are used to control the i feedwater bypass flow control valve when in AUTOMATIC 7 =i
- a. Steam header pressure, feed pump discharge pressure, steam flow, j
- b. Steam generator level, programmed steam generator level, auctioneered 3 high nuclear power. i
- c. Steam generator level, feed pump discharge pressure, steam flow.
.]
- d. Steam hea' der pressure, programmed steam generator level, auctioneered i high nuclear power. 3 q
QUESTION: 032 (1.00) WHICH ONE (1) of the following states the effects on reactivity due to changes in secondary plant pararneters? ASSUME the moderator temperature-coefficient is negative.
- a. An increase in feedwater temperature results in a positive reactivity addition,
- b. An increase in feedwater' flow results in a negative reactivity addition.
'l
- c. A decrease in steam flow results in a negative reactivity addition, i
- d. A decrease in condensate temperature results in a negative reactivity addition,
..( i
- 'l i
1 J
SENIOR REACTOR OPERATOR Page 18 QUESTION:- 033-(1.00) WHICH ONE (1) of-'the following describes the conditions which will cause a rapid transfer on the IATB 6.9 KV bus supply breakers? l
- a. - 1A, IB, and ID NCPs in operation,-and 1ATA and'1ATB out of synchronism,
- b. lA, 10, and ID NCPs in operation, and 1ATA and 1ATB out of synchronism,
- c. IA, 10, and ID NCPs in operation, and 1ATA and 1ATB in synchronism, d.- 1A, IB, and ID NCPs in operation, and 1ATA and 1ATB in synchronism.
' QUESTION: 034 (1.00) l l
When manually synchronizing the generator to the grid, OP/1/A/6300/01, .i
" Turbine Generator Operation," directs the operator to adjust the generator
-l
- speed until the hand on the synchroscope moves slowly in the " fast" .
direction. !
- WHICH ONE (1) of the following parameters are indicated by the synchroscope? I
- a. Current and voltage differences. ;
- b. Frequency and current differences.
- c. Frequency and phase differences.
- d. Current and #erences. ,
i i i
> SENIOR REACTOR,0PERATOR Page 19-l QUESTION:- 035-(1.00) -i i; WHICH ONE-(1) of the following is _the MINIMUM voltage' and frequency _which -
will-allow the diesel generator to accept the loads assigned by the sequencer during an AUTOMATIC start? a.--75% voltage and 75% frequency
- b. 75% voltage and 95% frequency
- c. 95% voltage and 75% frequency
- d. 95% voltage and 95% frequency QUESTION: 036 (1._00)
WHICH OE (1) of the following completes the statement? The diesel generator must be able to start and attain rated sped within:
- a. 5 seconds i
- b. 11 seconds '
- c. 20 seconds
- d. 30-seconds l
l l
.0 VEST 10N: 037 (1.00) l WHICH ONE (1)= of the following will AUTOMATICALLY isolate containment ' j ventilation?
l
.a. Phase "B" isolation l
- b. 1 EMF 36, unit vent gas low range trip 'l 1
- c. 2 EMF 37, unit vent iodine high range trip' I
- d. Safety injection
- 1. l l
D- "E .. . SENIOR REACTOR OPERATOR Page.20-l QUESTION: 038 (1,00) l WHICH ONE-(1) of the following-discharges into the pressurizer relief tank?
- a. Alternate flowpath for excess letdown p b. PORY INC36B valve packing leakoff
- c. NS pump suction relief valve
- d. NC pump seal #2 leakoff ..,
o QUESTION: 039 (1.00) WHICH ONE (1) of the following loads is supplied by the KC system?
- a. Waste gas compressors.
- b. Diesel Generator cooling water heat exchanger
- c. VC chillers ;
I
- d. Containment. ventilation units
'I h
p ,
, SENIOR REACTOR OPERATOR Page 21-
. QUESTION: 040' (1.00)
Given the following conditions:
-Reactor power is 100%.
-KC pumps B1 and B2 are supplying system loads.
-Safety injection signal is received.
l WHICH ONE (1) _of the following statements describe' tLa response of the KC system? r
- a. KC pumps B1 and B2 will continue to run, KC-pumps Al and A2 will auto
. start.
.b. KC pumps B1 and B2 will be shed from their busses, then the LOCA early_
sequencer will start KC pumps A1, A2, B1, and B2.
- c. KC pumps B1 and B2 will be shed from their busses, then the LOCA accelerated sequencer will start KC pumps Al and A2.
- d. KC pumps B1 and 82 will continue to run, KC pumps Al and A2 will not start.
I i 1 1 QUESTION: 041 (1.00) WHICH ONE (1) of the-following describes the Immediate Actions to be taken
- per AP/1/A/5500/14, " Rod Control Malfunctions, Case 11 Continuous Insertion / Withdrawal Of A Control Rod Bank?"
p
- a. Initiate emergency boration to counteract the positive reactivity addition,
- b. Place rods in Bank D Select and drive rods in until Tavg and. Tref are
, matched.
- c. Place rod bank selector switch in manual and verify rod motion has stopped.
- d. Manually initiate SI and perform EP/1/A/5000/01, " Reactor Trip or Safety Injection."
l
- SENIOR REACTOR OPERATOR' Page 22' ' '
t-QUESTION: 042 (1.00) :
.WHICH ONE (1)- of the following' selections is.NOT an indication of continuous ~ ' , rod withdrawal?
a- P/R OVER POWER R0D STOP .
- b. Reactor Power - Turbine Power Mismatch ,
'c, ROD CONTROL URGENT FAILURE- [
l' d. Tave Deviation j 4 P QUESTION: 043 (1.00) 'i
.i
,Given.the following conditions:
i
- Reactor power is 35%.
- Raising power during startup.
- RPI AT BOTTOM ROD DROP alarms.
- Rod bottom light-for rod C-5 lights.
WHICH OME (1) of the following is an Immediate Action? ' a- Manually adjust. control bank D to maintain power. j f l- b. Decrease turbine load to below the P-7 reactor trip. < l s
- c. Place the control rod. bank selector switch' in manual. .i l
J d. Trip the reactor if-Tave and Tref deviate by more than 8 F. DI l 1 l l
-J l
I e -
SENIOR REACTOR OPERATOR Page 23 QUESTION: 044 (1.00) Given the following conditions:
-Reactor power is 35%.
-One rod is misaligned below its group by 15 steps.
WHICH ONE-(l) of the following actions would, per AP/1/A/5500/14, " Control Rod Malfunctions, Case IV Control Rod Misalignment" provide indication that the rod will move if required?
- a. Tave Tref mismatch within 1 degree F with the Bank Selector switch in auto,
- b. Check the indicator fuses for the affected rod at the rod control cabinets.
- c. Drive-the affected bank inward ten steps observing that the affected rod moves.
- d. Verify that no URGENT FAILURE alarm exists for the affected bank and that lift coils are connected.
QUESTION: 045 (1.00) Given the following conditions:
-NCS Pressure-Decreasing
-NCS Temp-Decreasing
-Secondary Radiation-Normal
-Cont. Humidity-Increasing
-cont. Pressure-Increasing
-S/G Pressure-Decreasing
-Cont. Radiation levels-Normal WHICH ONE (1) of the following events has occurred?
- a. Small Break Loss Of Coolant Accident.
l b. Large Break Loss Of Coolant Accident, c.- Steam Generator Tube Rupture.
- d. Faulted Steam Generator.
- o. s SENIOR REACTOR OPERATOR Page 24-I
. QUESTION: 046. (1.00)
T, e,~ , b GinAusr WHICH ONE (1) of the following is isolated by a +afety-inject-ton?
- a. Auxiliary building non-essential service water,
- b. Component cooling water to the NC Pumps,
- c. Main feedwater tempering flow to steam generators.
- d. ND flow to containnent spray.
/
QUESTION: 047 (1.00) i WHICH ONE (1) of the following is sequence of the AUTOMATIC LOCA sequencer l actions? l l 1. Starts diesel
- 2. Verifies Bus Voltage
- 3. Loads a safety injection pump
- a. 1, 2, 3 i
- b. 2, 's , 1 l L c. 3, 1, 2 !
- d. 2, 1, 3 ;
;l 1
i i f I
..- . 1 SENIOR REACTOR OPERATOR Page 25 l l
QUESTION: 048 (1,00) WHICH ONE (1) of the following describes the reason for ensuring control of !
. steam-generator levels for natural circulation?.
- a. To prevent unnecessary positive or nagative reactivity additions due to varying cooldown rates,
- b. To prevent a Technical Specification violation due to an excessive cooldown rate. ;
- c. To provide continuous flow to the steam generators to ensure steam generator tube integrity,
- d. To provide a stable heat sink for decay heat removal at the steam ,
generator no load level, i QUESTION: 049 (1.00) WHICH ONE (1) of the following groups of parameters indicater the existence of adequate natural circulation?
- a. -Steam pressures - stable or decreasing. .
-Core exit T/C's - stable or increasing ..
-NCS cold leg temperatures - near saturation temperature for steam.
pressure. >
- b. . -Steam pressures - stable or increasing. ..
-NCS subcooling - more subcooled than instrument error.
-NCS hot leg temperatures . stable or decreasing.
- c. -Steam pressures stable or increasing.
-NCS pressure - stable or decreasing.
-NCS cold leg s temperatures - near saturation temperature for NCS pressure.
c d. -Steam pressures - stable or decreasing.
-NCS subcooling - more subcooled than instrument error.
-NCS cold leg temperatures - near saturation for steam pressure.
l
SEN OR REACTOR OPERATOR Page 26 : QUESTION: 050 (1.00) : WHICH ONE (1) of the .following describes a condition that requires emergency i boration according to AP/1/A/5500/38, " Emergency Boration?"
- a. Less than 2000 ppm boron in MODE 5. >
- b. CONTROL R0D BANK LO-LO LIMIT alarm in MODE 1.
t
- c. Three out of four loop Tavgs reach 540 F after reactor trip.
- d. Failure of a single control rod to drop following reactor trip. [
l. QUESTION: 051 (1.00) Given the following conditions: ,
-A normal plant cooldown is in progress.
-The computer alarm for the KC surge tank indicates a need for makeup !
from the makeup demineralized water system. ,
-Locally, there is no cause for the problem. !
-The water level in the surge tank compartment 1A is slowly DECREASING.
-The associated makeup valve to the surge tank compartment 1A is fully ,
open.
? i i
WHICH ONE (1). of the following is the cause of the problem?
- a. There is a leak in an NCP thermal barrier heat exchanger. -!
- b. A leak is present in a KC heat exchanger.
l c. A leak is present in the letdown heat exchanger. !. d. The plant is being cooled down at an excessively fast rate. l l i i
' ; ,, . m
. SENIOR REACTOR OPERATOR Page 27 j p.
Y QUESTION': 052./(1.00).
- WHICH ONE (1)'of the following describes AMSAC automatic actions upon .;
- actuation?
~a.. Trips turbine- '
Closes S/G sample valves. Starts MD CA pumps. ,
- b. Trips turbine. ' '
C1oses S/G' blowdown lines. o, Starts TO CA pumps. i
.t
- c. Trips MSIV and bypass valves.
Closes .S/G sample valves. Starts TD CA pump,
- d. Trips MSIV and bypass valves. -
l Closes S/G blowdown valves. . Starts MD CA pumps. i
-i QUESTION: 053 (1.00)~
WHICH ONE (1) of the following is the basis for NOT manually initiating a safety-injection during an anticipated transient without scram? -
=a. It would result in loss of heat sink due to a 'feedwater isolation with- ,
l the unit at power. I
- b. -It would trip the NC pumps, causing a loss -of NC system flow.
- c. It would automatically trip the turbine and cause a. reduction in heat ~
sink. p- d. It would result in MD CA pump starts which could lead to overcooling [ of the NC system. L T d e,
SENIOR REACTOR OPERATOR Page 28 l 1 1 QUESTION: 054 (1.00) The following_ plant conditions exist:
-A valid reactor trip signal has been received.
-Rod bottom lights are NOT lit and flux is NOT decreasing.
-The turbine is tripped.
-The.CF pumps are running and NC loop temperature is stable. -
-Emergency boration is in progress.
-NC system pressure is 2350 psig. >
WHICH ONE (1) of the following represents the action to be taken and the basis.for those actions to reduce NC system' pressure per EP/a/A/5000/ll.1,
" Response to Nuclear Power Generation /ATWS"?
- a. Depressurize the NC system with pressurizer PORVs to allow enough
borated water flow to insure addition of negative reactivity to the Core.
- b. Depressurize the NC system with pressurizer PORVs to prevent a rapid overpressurization transient and begin a controlled cooldown,
- c. . Depressurize the NC system with pressurizer sprays to allow enough borated water flow to insure addition of negative reactivity to the Core.
d.- Depressurize the NC system with pressurizer sprays to prevent a rapid overpressurization transient and begin a controlled cooldown. QUESTION: 055 (1.00)
.WHICH-0NE (1)- of the following represents a red path for core cooling.per EP-
-12.1." Response to inadequate Core Cooling," if subcooling is -10 F?.
NCPs 'RVLIS Running Core Exit Temperature Vessel Level STEADY AT
.a. None 750 F 40 %
- b. None 850 F 60 %
- c. lA 750 F 40 %
- d. IB 850 F 60 %
l l 1'
l SENh0RREACTOR' OPERATOR Page 29 l 1 1 1 QUESTION: 056 (1.00)- Given the following conditions:
- A' steam line break has occurred.
- EP/1/A/5000/14.1, " Response to Imminent Pressurized Thermal Shock Conditions," step 11 has been completed.
- The CAUTION above step 12 states, " Steps 12-17 provide for a rapid SI termination for pressurized thermal.. shock events . .. ." and directs terminating SI when the criteria is met.
WHICH ONE (1) of the following is NOT,a reason for terminating SI? L a. SI may be mtributing to the cooldown.
- b. Inventory needs to be made up faster than SI_can,
- c. Poor mixing of S1 will increase thermal stress.
~
- d. SI.may cause the plant to repressurize.
QUESTION: 057- (1.00) WHICH ONE'-(l) of the following is the basis for isolating all feedwater _to a faulted' steam-generator per EP/1/A/5000/03, " Steam Line Break Outside Containment" step 37. -; I i
~
- a. To reduce the probability of occurrence of a steam generator tube rupture in the faulted steam generator.
'b. To limit the cooldown by limiting the blowdown of the faulted steam
- generator.
L c. To prevent all feedwater flow from entering the faulted steam 4
. generator and filling the generator, causing the PORV's to lift, i l d. To allow. raising the faulted steam generator PORV setpoint to reduce ,
environmental releases. L i' Y
s -
,b ,
SENIOR REACTOR OPERATOR Page 30
' QUESTION: 058 (1.00)
Given the following conditions:
-The plant has experienced a main steamline rupture and the operators have entered EP/1/A/5000/14.1, " Response to Imminent Pressurized Thermal Shock Conditions."
WHICH ONE (1) of the following reflects the major actions of the above procedure?
- a. Maintain NC system cooldown rate Maintain NC system pressure >
- b. Maintain NC system cooldown rate Depressurize NC system
- c. Stop NC system cooldown Maintain NC system pressure
- d. Stop-NC system cooldown Depressurize NC system
. QUESTION: 059 (1.00)
Which ONE (1) of the following is the pressure at which containment' conditions are considered adverse per EP/1/A/5000/12, " Core Cool'ng?"
.a. 0.35 psig
- b. 1.0 psig
- c. 1.5 psig
- d. 3.0 psig t
i
1 SENkORREACTOROPERATOR Page 31 QUESTION: 060 (1.00) j Given the following plant conditions: ,
- Reactor / Turbine power 39%.
CONDENSER LO VACUUM (PRE TRIP) lit.-
- - Condenser vacuum - 18 inches.
WHICH ONE (1) the following describes the Immediate Actions for the above conditions?
- a. Manually trip the reactor and turbine and refer to EP/1/A/5000/01, neactor Trip of Safety Injection."
- b. Verify air ejectors operating properly, add more air ejectors if needed. Dispatch operator to locally align and start mtin vacuum pumps "A" and "B".
- c. Make paging announcement, reduce turbine load, start more NC pumps, '
verify air ejectors ~ operating properly, and add more air ejectors,
- d. Ensure proper number of circulating pumps are operating, and manually 1 trip the turbine if generator load decreases to less than 35% of rated
~
load. I QUESTION: 061 (1.00) WHICH ONE (1) of the following is an .Immediate Action for EP/1/A/5000/09,
" Loss of All AC Power"?
- a. Place KC pump switches in pullout position.
- b. Check if letdown isolation valves are closed,
- c. Send an operator to locally start DG.
- d. Send an operator to' standby shutdown facility to start NC pump seal injection,
, - SENh0RRFACTOROPERATOR Page 32 1-g :!
QUESTION: 062 .(1.00) j 1 WHICH ONE (1) of the following is the MINIMUM time limit battery EVCD (for vital instrument and control power) is sized to carry all its DC loads? i
- a. 12 minutes -
- b. 30 minutes
- c. 45 minutes
- d. 60 minutes !
3- 1 QUESTION: 063 (1.00) ; L- In the RVLIS differential pressure range (Dynamic Head) and with the reactor L at full power, the Unit I normal differential pressure -(DP) reads low. , L .1 WHICH 0NE~(1) of the following statements is the reason for this condition? M
- a. Some of the core exit thermocouples are reading cold leg temperatures. !
L Under accident conditions requiring RVLIS, the hot leg.and-cold leg
~'
E- temperatures are nearly the same.
- b. The thermocouple reference junction boxes are controlled to 160 F.
T/C correction factors are determined by calibration and can be
=
manually adjusted. '
- c. The OAC makes an additional correction for this-inconsis'tency'during i an inadequate core cooling condition.
1 a
'- d. The capillary RTDs measure containment temperature instead of NCS temperature. The correction factors are incorrecti for the colder a containment temperatures. ,
-i 1
l' [ -
\
\(
i
.I[ '
e r a' I, !, r
~\ -I
i
' ~ SENIOR REACTOR OPERATOR: -Page 33' i
_UESTION:1064 Q '(1.00) ; WHICH-ONE (1) of the following is the basis' for reducing Tave to less than 500 F with the specific activity of the NC' system greater than 100/E
- i microCuries per gram of gross radioactivity?:
- a. Elimination of CRUD bursts. i t ~b. Elimination of the iodine spiking phenomenon.
'1
- c. Allows faster cleanup by-the NV system mixed bed:demineralizer '
- d. Prevents a release of activity in the event of a steam generator tube '
f rupture.
\
l- i I ! QUESTION: 065 (1.00) l -The Computer is out of service and you are directed to determine the- < 1 l- subcooling margin for these NCS parameters:
-Low range pressure is 440 psig.
-Thot is 450 F.
-Tcold.is 430 F.
-Tave is 440'F.
The subcooling margin is: I
- a. ~MdegreesF A-
- b. af degrees F y,y
- c. hdegreesF
- d. hdegreesF-o r
i 4
/ x- .
' SENIOR REACTOR _ OPERATOR 1 Page 34' 1
'. QUESTION: 066 '(1.00). ;
WHICH ONE (1) of the following indications has an alternate limit during adverse containment?
- a. Core exit thermocouples
- b. NCS wide range RTDs
- c. NCS pressures
- d. Pressurizer levels j QUESTION: 067 (1.00) l Given the following conditions:
-A pressurizer PORY-is. leaking 21 gpm to.the PRT
-All other system components:are normal ;
WHICH ONE (1) of the following conditions exist per Technical Specification
, 3.4.6.2, " Operational Leakage?" q
- a. IDENTIFIED LEAKAGE limit has been exceeded and a shutdown is required.
- b. IDENTIFIED LEAKAGE is less than the shutdown limit. 4
- c. Reactor Coolant System Pressure Isolation Valve leakage limit has been- 3 exceeded and a shutdown is required. .
J d.- Reactor Coolant -System Pressure Isolation Valve leakage is.less than. the shutdown limit.
'b s
-w, , w
si4' .
- e. ... , ;
SENIOR REACTOR OPERATOR: 'Page 35 1
.i
~;
QUESTION: 068 (1.00)-
-The following is a list of loads sequenced on by the LOCA sequencer ;
h l'lNV pump
- 2. NS pump q -- 3. CA pump WHICH 0NE (1) of the following is the correct order-for loading the sequencer- !
loads during a LOCA? :
- a. 1,2,3
- b. 2, 1, 3 f
- c. 2, 3,1
- d. 1, 3,'2 ipi QUESTION: 069 (1.00) ..
Given the following' conditions::
, - Reactor power is 100%
- Pressurizer level is DECREASING
- Back-up. heaters are energized
- Charging flow INCREASING
- VCT-level is 12% "
- PRT level is 88%
- Containment sump pump has started j The CVCS letdown isolation valves have just CLOSED due to LOW.
pressurizer level and pressurizer level is now' steady. WHICH ONE. (1) of the following identifies the location of the lea?
- a. Letdown oiping
.b., Charging piping c.. Regenerative heat exchanger hk le. A y c
- q
- d. Seal water return header relief valve stuck open I
4 l 1 1 l
SENIORREACTOROPERATOR Page 36. QUESTION: 070 (1.00) , Wrl!CH ONE (1) of the following describes the conditions required to permit opening NI-1848 (RB Sump to ND) to transfer to cold leg recirculation?
- a. NS 1B (B NS Pmp Suct from Cont Sump)' closed ND-19A (ND Pmp Suct From FWST or NC) closed
- b. ND-4B (ND Pmp Suct From FWST or NC) closed S' latched bypass depressed
- c. NS 1B (B NS Pmp Suct From Cont Sump) closed S' latched bypass depressed
- d. ND 4B (ND Pmp Suct From FWST or NC) closed S' latched contacts are closed QUESTION: 071-(1.00)
WHICH ONE'(1) of the following describes an Immediate Action and a Response Not Obtained (RNO) required for AP/1/A/5500/19, " Loss of Residual Heat Removal System," during refueling?
- a. Verify IND-1B (Loop C Hot' Leg to ND pumps) CLOSED. RN0 Start ND pump (s). I
- b. . Verify IND-2A (Loop C Hot Leg to ND Pumps) OPEN. ' RNO-Start ND '
pump (s).
- c. Verify IND-1B (Loop C H;,t Leg to ND. Pumps) OPEN. RNO-Stop ND pump (s). '
- d. Verify IND-2A (Loor C Hot Leg to ND Pumps) CLOSED.: RNO-Stop ND pump (s).
l + l l l l l l l l
l 4 1 4
- SENIOR REACTOR OPERATOR Page 37 f
i t b - QUESTION: '072 (1.00). WHICH ONE (1) of the following describes an RNO of the Immediate Action > required in AP/1/A/5500/11, " Pressurizer Pressure Anomalies" if pressurizer . pressure is DECREASING and a pressurizer spray valve will NOI close?
- a. Trip' reactor.
b.- Decrease reactor power to less than P-7. i
- c. Decrease reactor _ power to less than P-8. 4
- d. Initiate SI.
L. H ; l l - QUESTION: 073 (1.00) l WHICH ONE (1) of the following actions are required per Technical l Specification 3.3.1, " Reactor Trip system Instrumentation," for a single SRNI ! failure with the reactor below P-67 ASSUME the reactor is in MODE 2.
- a. Raise power until P-6 is reached and IRFNs are on scale. . ,
1, 1 b, Verify compliance with shutdown margin. c.- Restore the inor,erable channel to operable status with in 48 hours or ll open thelreacter trip breakers within the next hour.
'd, Suspend all operations involving positive reactivity' changes.
QUESTION: 074 (1.00) - WHICH ONE (1) of the following conditions indicates an intermediate , range channel detector which has had a loss of compensating voltage? 4
- a. Some neutron flux and all gamma flux signals are being subtracted from-the outer-detector output,
- b. Detector output will read less than actual neutron flux level,
- c. Detector output will read higher than actual neutron flux level.
- d. Source range detectors may be automatically re-energized too early.
. SENIOR REACTOR OPERATOR Page 38 l
p QUESTION: 075 (1.00) The following plant conditions exist:
-Reactor power is IX10E-6 amps. .
-N 35 Intermediate Range channel has failed LOW.
-A reactor startup is in progress.
WHICH ONE (1) of the following actions is correct per Technical-Specification 3.3.1, " Reactor Trip System Instrumentation"?
- a. Restore inoperable channel prior to exceeding P-6. i
- b. Restore inoperable: channel prior to exceeding 5% power, f
- c. Restore inoperable channel prior to exceeding 10% power.
- d. Bypass the inoperable channel and continue with reactor startup.
t t QUESTION: 076 (l'00) l The first Immediate Action of AP/1/A/5500/10, "NC System Leakage Within Capacity of Both NV. Pumps," is to " Check pzr level - AT OR INCREASING TO PROGRAMMED LEVEL." " WHICH ONE (1) of the following lists the first four Response Not Obtaineds?
- a. Verify pressurizer spray flow at a minimum Open seal injection flow control valve Start NV pump ,
Raduce letdown- t
- b. Verify charging line flow control valve opening Open seal injection flow control valve o Start NV pump Reduce letdown ,
-)
- c. Verify charging line flow control valve opening Start-NV pump Open seal injection flow control valve Verify pressurizer spray flow at a minimum .
a
- d. Verify charging line flow control valve opening Verify pressurizer spray flow at a minimum Open seal injection flow control valve '
Reduce letdown i 4
' SENIOR REACTOR OPERATOR Page 39 QUESTION: 077 (1.00)
WHICH ONE (1) of the following conditions REQUIRES tripping the reactor per AP/1/A/5500/10, "NC System Leakage Within capacity of Both NV Pumps," Case 1, Steam Generator Tube Leak?
- a. Pressurizer level at 17% and decreasing rapidly with 1 NV pump on,
- b. Pressurizer level at 4% with 1 NV pump on and stable,
- c. Pressurizer pressure at 1965 psig with all heaters on.
- d. Pressurizer pressure at 2000 psig with backup heaters 0FF.
QUESTION: 078 (1.00) WHICH ONE (1) of the following contains TWO (2) DISADVANTAGES of SGTR cooldown using the backfill method?
- a. Increases waste processing.
Dilutes NC system boron.
- b. Increases waste processing.
High potential for radioactive release.
- c. Difficult to control pressure and-level in NC. system..
High potential for radioactive release,
- d. Difficult to control pressure and level in NC system.
Dilutes NC system boron, t 3
SENIOR REACTOR OPERATOR Page 40 s QUEST 10N:.079 (1.00) WHICH ONE (1) of the following describes the result of feeding a hot, dry steam generator after a loss of all feedwater? I a. Steam generator failure due to thermal stresses,
- b. Steam generator failure due to intergranular stress corrosion cracking.
- c. Overcooling event due to excessive feeding of the steam generator.
- d. Overcooling event due to excessive steaming of the steam generator. 3 QUESTION: 080 (1.00) i WHICH ONE_(1) of the following statements describes the automatic actions of the Process Radiation Monitor EMF-468, Component Cooling B, HIGH radiation I al arm.
I i l
- a. The KC surge tank vent is automatically closed.
- b. The regenerative heat exchanger is isolated,
- c. The excess letdown heat exchanger is isolated.
- d. The letdown heat exchanger is isolated.
f t
. SENIOR REACTOR OPERATOR Page 41 l
l QUESTION: 081 (1.00) If pressurizer level control select switch is in the 3-2 position when the. reference leg for level III develops a leak, WHICH ONE (1) of the following describes plant response? ( Level 11 Level Ill VCT LEVEL l PZR LVL INDICATION PZR LVL INDICATION ! a. INCREASING DECREASING INCREASING
-1 l
I. b. DECREASING INCREASING INCREASING l
- c. INCREASING DECREASING DECREASING I
- d. DECREASING INCREASING DECREASING l
? ! l QUESTION: 082 (1.00) Civen the following conditions. -- ! -SPENT FUEL POOL LEVEL LOW is lit. 'I l- -SPENT FUEL P0OL BUILDING BRIDGE EMF-17 is lit. i
-Level-is decreasing in refueling canal.
WHICH ONE (1) of the following is the final required position for each piece l of equipment according to AP/1/A/5500/40, " Loss of Refueling Canal Level," l
'Immediate Actions? ASSUME a fuel assembly is in each piece of equipment.
Upender in Reactor Spent New l Spent Building Fuel Fuel -i Fuel Manipulator- Manipulator Elevator Pool Crane Crane l
- a. as is fully down fully down fully down
- b. fully down as is fully down fully down j1
- c. fully down fully down as is fully down l: 3 L d. fully down fully down fully down as is l
1
l ..
- SENIOR REACTORiOPERATOR - Page 42-1 1
L > QUESTION: 0831 (1.00)_ Given the-fo11 ewing conditions: .
- Reactor power is 100%. l'
- Control rod drive selector in MANUAL.
- Bus Line IB is lost.
t WHICH ONE (1) of the following describes an immediate action for this load ! rejection case?
- a. Verify turbine speed decreases to 1800 RPM. If turbine has NOT l decreased to 1800 RPM, control turbine at 1800 RPM. ,
- b. Verify turbine impulse pressure DECREASES to 410 psig. -If impulse pressure has NOT decreased to 410 psig, control turbine at 410 psig. ;
- c. Verify TAVE DECREASING. If Tave has NOT decreased, MANUALLY control turbine AND decrease load.
- d. Verify control rod drive selector in MANUAL. Verify turbine load is decreasing.- If turbine load is NOT decreasing, MANUALLY decrease' turbine.
QUESTION:1084 (1.00)- ! WHICH ONE (1):of the following statements describe when a tag sticker is- : REQUIRED due to the safety tag obscuring otherfindications or controls? '
- a. Red tag;on the-local diesel generator alarm panel,
- b. Yellow tag on control room switches,
- c. Yellow tag on local diesel generator local-remote control panel.
- d. White tag on control room panel.
1 I t
i SENIOR REACTOR OPERATOR Page 43 . l I l QUESTION: 085- (1.00) II Given the following conditions: ! l
-Motor. driven (MD) CA pump has been removed from service for repair. -l
-Maintenance has- completed repairs. i
-Prior to returning the CA pump to service, the CA pump fails testing with
'the same symptoms. ,
WHICH ONE (1) of the following statements' describes the handling of the safety _ tags removed and their stubs?
- a. The tags and stubs should be marked " VOID" and filed.
- b. Tags and stubs should be retained for six months and then discarded as the work' supervisor- sees fit. >
- c. The tags should be replaced on the components and the stub re-used.
- d. Tags and stubs should be matched and filed in the Tag Lifted for Testing File-(TLTF).
- QUESTION
- 086. (1.00) 1.
L When; replacing a Human Red Tag, WHICH ONE (1) of the following lists of L individuals must agree upon the' replacement Human Red Tag?
- 1. Shift supervisor / assistant' shift supervisor
- 2. Work supervisor
- 3. Person performing work
- 4. Supervisor _ with operational responsibility for the component
- a. 1, 2, and 3
- b. 2, 3, and 4 *
- c. 1, 3, and 4
- d. 1, 2, and 4 I
l
-SENIOR REACTOR OPERATOR _ Page 44 QUESTION: 087 (1.00)
-Given the following plant conditions:
-The' system dispatcher called a control room operator and requested that safety tags be issued on a portion of the plant.
--In the subsequent discussion between the control room operator 3nd the assistant shift supervisor it became clear that there was confusion as to exactly what was to be tagged.
WHICH ONE (1) of the following individuals .should contact the system dispatcher for clarification? !
- a. Control. room operator' taking call. !
- b. Compliance manager,
- c. Assistant shift supervisor,
- d. Shift supervisor. l i
QUESTION::088 (1.00) l 1 WHICH of the following selections reflect those individual responsible for j identifying UNQUALIFIED personnel to do independent verification on valves ' essential to safety according to OMP 1-6, " Independent Verification"? ;
- 1. Shift supervisor ;
- 2. Unit supervisor
-3. McGuire station training manager
- 4. Nuclear equipment operator j
- a. 1; 2, 3
]
- b. 2,3,4 i
- c. 1, 2, 4
- d. '1, 3, 4 'I l
i i
SENIOR REACTOR OPERATOR Page 45 QUESTION: 089 (1.00) WHICH ONE (1) of the following describes how an independent verification of position for a manually operated valve in the THROTTLED position is done?
- a. Move the valve slightly in the closed direction and then return it to its original position,
- b. Inspect the last valve lineup sheet for verification signature and compare recorded valve position with the required position,
- c. Observe the operator initially place the valve in the position that the valve is to be throttled to,
- d. Compare visual observation of stem or indicator position with the required position.
QUESTION: 090 (1.00) WHICH ONE (1) of the following describes the relationship between the Unit Supervisor log, PT log, and the Tech Spec Action Hem log books?
- a. The Unit Supervisor log should contain nearly all the information in the Tech Spec Action Item log book. The PT log is independent of the other two,
- b. The Tech Spec Action item log is the controlling log book. The PT log is for specific tests and the Unit Supervisors log is for general infe mation,
- c. The PT log it for recording Tech Spec CAllBRATIONS, TESTS, and CHECKS.
Most significant information from this log should be reported in either the Tech Spec Action item log or the Unit Supervisor log,
- d. The Unit Supervisor log is the controlling log. The other two logs are for the convenience of the Unit Supervisor log and duplication of information in either the PT log or the Tech Spec Action item log is not necessary.
1
,(
SENIOR REACTOR OPERATOR Page 46 I i QUESTION: 091 (1.00) I Given the following conditions: Startup is in progress. Heatup rate was 60 F for the last hour. ) 0P/1/A/6100/01 ' Controlling Procedure for Unit Startup," has a 50 F/ hour j heatup rate limit, i WHICH ONE (1) of the following describes required operator actions?
- a. If the Technical Specification LCO is not exceeded, the heatup rate will be logged in the Unit Supervisor log. If Tech Spec heatup rate is exceeded, the reactor is to be in at least HOT STANDBY within 6 hours. ,
- b. Immediately shut the reactor down. Get NRC permission before restart. ]
- c. Hold power while a calometric is completed to verify that the limit 1 was exceeded, if the limit was not exceeded, continue startup. If the limit was exceeded, return to the limit within one hour or terminate startup. l L l
- d. Note that the procedural limit was exceeded in the procedure. Report i exceeding the limit to the Control Room SRO. l 1
QUESTION: 092 (1.00) An R0 has the Duke Power Company radiation limit for the qt.arter approved for 1000 mrem for Job 1 on Unit 1. Job 1 is cancelled with no exposure taken. However the same job is to be done on Unit 2. ASSUME the R0's previous radiation for the quarter was zero (0). WHICH ONE (1) of the following is the R0's exposure limit for the same job on Unit 27 ]
- a. 150 mrem l
- b. 200 mrem l
- c. 500 mrem j i
- d. 1000 mrem )
\ l..
1
\ $ENIOR REACTOR OPERATOR Page 47 ,
1 QUESTION: 093 (1.00) i WHICH ONE (1) of the following definitions of the ALARA term " reasonably ; achievable" are in the Radiation Protection Manual?
- 4. Judgement based on costs and conditions under which the job must be performed. ,
- b. Calculated 10% reduction based on previous performances of the same l job.
- c. Evaluated at $1,000 per REM. l i
- d. Reduction which can be attained by adding up to a maximum of 3 inches of lead shielding. ;
l 1 QUESTION: 094 (1.00) An item has a yellow " Caution Radioactive Material" tag and has been conditionally released by Healtis Physics (HP). WHICH ONE (1) of the following contamination classifications is the LEAST contaminated area that the item may be moved into? ASSUME no additional . packaging has taken place and the material has an HP escort. l
- a. Off-site
- b. On site
- c. Restricted area
- d. Radiation controlled area v
. l SENIOR REACTOR OPERATOR Page 48 i QUESTION: 095 (1.00)
WH3CH ONE (1) of the following responses completes the following sentence and ! identifies fuel handling equipment key requirements during refueling? l 1 The fuel handling supervisor is required to . . .
- a. return keys and check out keys again at the end of each shift.
- b. may carry keys off site as long as keys are not checked out for more than 48 hours, j
- c. may delegate use of the keys to an RO for up to one hour. '
- d. may keep keys checked out until an activity is completed. f QUtSTION: 096 (1.00) :
WHICH ONE (1) of the following is the MINIMUM number of escorts required in ! each respective area for a group of 16 visitors? Protected Area Vital Area
- a. I 2 :
- b. 2 2
- c. 2 4
- d. 4 4 i
QUESTION: 097 (1.00) WHICH ONE _(1) of the following is the LOWEST emergency classification that REQUIRES activation of the Technical Support Center?
- a. Unusual event
- b. A*,ert
-c. Site area emergency
- d. General emergency
SENIOR REACTOR OPERATOR Page 49 , QUESTION: 098 (1.00) The following plant conditions exist: At 0300 hours a bomb threat was phoned to the control room. The caller stated that the bomb was an incendiary device. .
-The location of the device was not specified.
WHICH ONE (1) of the following individuals is responsible for determining if the conditions are of significant severity to require a control room evacuation?
- a. Shift Supervisor ,
- b. Operating Superintendent .
4
- c. Fire Brigade Leader
- d. Station Manager QUESTION: 099 (1.00)
WHICH ONE (1 of the following statements apply to the use of critical safety function (CS ) status trees? i
- a. CSF status trees must be monitored continuously if any condition other '
than GREEN exists; otherwise, monitoring frequency may be reduced to 10 20 minutes,
- b. During functional restoration of a Heat Sink RED path, a Core Cooling .t ORANGE path develops. The correct operator action is to continue with the function restoration of the Heat Sink RED path,
- c. During functional restoration of a Containment ORANGE path, an !
Integrity ORANGE path develops. The correct operator action is to continue with the functional restoration of the Containment ORANGE path,
- d. A YELLOW path must always be restored prior to a ORANGE flow path unless permission has been obtained from senior operations management.
l
$Eh!ORREACTOROPERATOR Page 50 QUESTION: 100 (1.00) i WHICH ONE (1) of the following individuals may authorize defeating the interlocks on the refueling machine?
- a. The shift technical advisor
- b. The fuel handling supervisor
- c. The maintenance department supervisor in charge of refueling
- d. The reactor engineer l
l t-l l l l l l L (********** END OF EXAMINATION **********)
SENIOR REAC10R OPERATOR Page 1 i ANSWER SHEET ! Multiple Choice ' (Circle or X your choice) { If you change your answer, write your selection in the blank. i 001 a b c d i 002 a b r; d 003 a b c d , t 004 a b c d . 005 a b c d , 006 a b c d _ 007 a b c d L 008 a b c d 009 a b c d l 010 a b c d i 011 a b c d 012 a b c d 013 a b c d L : l 014 a b c d 015 a b c d 016 a b c d i 1 017 a b c d l 018 a b c d 019 a b c d l 020 a b c d 1 021 a b c d 022 a b c d 023- a b c d i 024 a b c d i 1 025 a b c d l
SENIOR AEACTOR OPERATOR Page 2 ANSWER SHEE1 Multiple Choice (CircleorXyourchoice) ! If you change your answer, write your selection in the blank. l l , 026 a b c d l 027 a b c d : 028 a b c d 029 a b c d , t 030 a b c d ,
-031 a b c d 032 a b c d 033 a b. c d 034 a b c d 035 a b c d 036 a b c d
( 037 a b c d 038 a b c d i 039 a b c d l 040 a b c d i i
- l. 041 a b c d 042. .a b c d 043 a b c d !
l l 044 a b c d 045 a b c d i-046 a b c d 047 a b c d 048 a b c d _ 049 a b c d > 050 a b c d ;
' SENIOR REACTOR OPERATOR Page 3 ANSWER SHEET l Multiple Choice (Circle or X your choice) .
If you change your answer, write your selection in the blank. ; 051 a b c d 052 a b c d { 053 a b c d , 054 a b c d ; 055 a b c d 056 a b c d 057 a b c d - 058 a b c d 059 a b c d 060 a b c d 061 a b c d , 062 a b c d 063 a b c d 064 a b c d 065 a b c d 066 a b c d 067 a b c d 068 a b c d , 069 a b c d : 070 a b c d 071 a b c d 072 a b c d t 073 a b c d __ 074 a b c d 075 a b c d l
r-o ~9
,-. 5ENIOR REACTOR OPERATOR' Page 4 AN5WER SHEET Multiple Chuice (Circle or X your choice)
If you change your answer, write your selection in the blank. I 076 a b c' d 077 a b c d 078 a b c d 079 a b c d 080 a b c d 081 a b c d 082 a b c d 083 a b c d l l 084 a b- c d 085 a b c d 086 a b c d l 087 a b c d 088 a b c d 089 a b c d l 090 a b c d l 091 a b c d 092 a b c d i. 093 a b c d 094 a b c d ! 095 a b c d 4
- l. 096 a b c d 097 a b c d l l 098 a b c d 099 a b c d 100 a b c d ,
l (********** END OF EXAMINATION **********) i
s Ig, n . i l 1! I OF/1/A/6100/ ENCLOSURE 4.3 ; Curve 1.10A l { McGU1RE NUCLEAR STATION* UNIT 1 ! SUBCOOLED MARGIN MONITOR Saturation Curve Adjusted For Instrument Error i Low Range NC Pressure Sensor A i Saturation Temp. Adjusted For NC Pressure Instrument Error 4 (FSIG) (Deg F) . 0.0 200.00 ; 35.3 041.22
- 85.3 297.82 135.3 335.33 105.3 362.00 235.3 382.97 285.3 400.65 !
335.3 415.83 ' 385.3 409.30 435.3 441.38 485.3 452.51 535.3 462.74 585.3 472.00
- 635.3 481.09 685.3 489.48 >
735.3 497.34 785.3 504.81 l J Prepered Byfp M _. Date g24T7 I t
OP/1/A/6100/22
- Enclosure 4.3 Curve 1.iOA .
Seturation Curve Adjusted For Instrument Error Low Range F4C Pressure Sensor LRJIT 1 800
....j....
. .. .... .g.).g,g 4
. p. ...a.
4.i.g.I . . g ,t. g g a. g.
..g.g.g . g .;.g..g
. u...
. p. l r . p. . e,
.i..
...... ........I
. ..... . ......o..
. .ti... 4; , ....
. i.
....o ..
.....!lt....., g.
...,t... .,... e ..
,oo . . . . . . ........ ... .
.t.....t
.......I..... I
. . ........s.. . .... . ..... ... .
fi'~
*****g SOO - '
... . .. 4...... ...
.l. . ..
.., . I4 i . . . . .. .. . .. .
- -~ . . . . . . . . ... .. . . ..... t c3 500 - * ** * ***
- w . . ... .. . . .. .... . . ..... .....
tn *
~ -
_OL, ts . . .. . . .. . . .... .. . . ..
~~~1*
- t. 400 .. .. .....
3 . .. W3 .. . . . . .. . . . . . ... . ..... . g3 . .. .. . . .. . . . . . ... . ... ......... ........ gy c, . . 0L 300 . . . - .
. :SUBCOOLIO - - .- .--.-. SATURATED - * .-
f... ....... (3 .. .. . .. . . . . ... ....... . .. . ... It . . . .. .. . . .i.. .. ... .. .
. s... . .......
...I...
*l,..,.., ...
. . . . . ... ......... ....* .... ...g..s.;.....I .
.I. .
'g......g.g...
200 ~ ** * - * * * ** *
.....,.I.' ~
l .1 , .,.. .., 4. 6 l ., .4
. , 4, 1, . . .
i.'.l.....
.I...
.... 94.
........ .:. ..s. , .g,.,-., .......
5,...,g.
.. . .,... . ,,..,.,.. . . ~ . ,. .......
.,,,.I
. II.4.a.
. .g,g, 4
s4. .
.e.,,.
. {......
.I &,..
...). 'g.;4,... .I. .........
........ ... .. ... .4 .. . ,,3,, ... ... . . .
.geg ~, .4 ...,.t...
~~**-~ * - * * * * **** ** . - ' ***t' fff' "- t "* *!"** ******~**
100 ....
.... ... . .. . . ... . ..... es.6.t... ;6.i...;. . .
,4i..t.ii.
.5,66.,.){.i.~. ~.
. .i...
...t.,..,....
O
-?- . > ' i. -
- r. :t r- . . - r- :::t::::: : : :t:t-t: - t r:' - t- : tr:
100 150 200 250 300 350 '400 450 500 550 Temperature (Degrees F) _ _ . - . _ _ . _ _ _ _ . _ _ _ _ . _ _ a
. Nl[ . . 9RO f o cfv/ i
^ SENIOR REACTOR OPERATOR Page 51 i
' ANSWER: 001 (1.00) i 1
- d. [+1.0) t
REFERENCE:
- 1. McGuire: OP/1/A/6150/02A, page 1. {
- 3. KA 003000A201 (3.5/3.9) 003000A201 ..(KA's) j ANSWER: 002 (1.00)
- c. (+1.0)
REFERENCE:
-1. McGuire: Lesson Plan, Topic 15, OP-MC-PS-ILE handout MC-IC-ILE-3.
- 2. KA 004000A202 (3.9/4.2) ,
004000A202 ..(KA's) . f
' ANSWER: 003 (1.00)
- a. (+1.0) l
REFERENCE:
- 1. McGuire: Tech. Spec Bases 3/4.1.1.1 and 3/4.1.1.2
- 2. KA'004000K519 (3.5/3.9) ,
004000K519 ..(KA's) l ANSWER: 004 (1.00)
- b. [+1.0)
P
7 .. , j , . l SENIOR REACTOR OPERATOR Page 52 i
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 17, OP MC ECC-ISE, pages 26 and 27.-
- 2. McGuire: Lesson Objective OP MC ECC-ISE 1.1. ,
- 3. KA 013000K413 (3.7/3.9) ,
013000K413 ..(KA's) l 1 I ANSWER: 005 (1.00)
- d. [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 17, OP-MC ECC-CLA, Objective 6.
- 2. McCuire: Lesson Plan, Topic 17, OP MC ECC-CLA, pages 9 and 10,
- 3. KA 013000K106 (4.2/4.4) ,
013000K106 ..(KA's) ANSWER: 006 (1.00) ,
- a. [+1.0)
REFERENCE:
- 1. McGuire: OP/1/A/6100/100, Panel l AD2 - D - 9. .)
- 2. McGuire: Lesson Plan, Topic 16, OP-MC IC-IRE, objective 12. ,
- 3. McGuire: Lesson Plan, Topic 16, OP-MC IC-EDA page 18. :
- 4. KA 014000K403 (3.2/3.4) 014000G007 (2.8/3.0) ,
014000G007 014000K403 ..(KA's) l ANSWER: 007 (1.00)
- d. [+1.0) l
s t . SENIOR REACTOR OPERATOR Page 53 ; i i
REFERENCE:
- 1. McGuire: Annunciator / Alarm Procedure, " Control Rod Bank LO LO Limit.* l
- 2. KA 014000A103 (3.6/3.8) 014000G007 (2.8/3.0) 014000A103 014000G007 ..(KA's) !
l ANSWER: 008 (1.00) ,
'd. [+1.0) f
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 16, OP MC-IC IRX, page 19.
- 2. KA 015000K302 (3.3/3.5) 015000K302 ..(KA's) !
ANSWER: 009 (1.00)
- b. [+1.0)
REFERENCE:
f
- 1. McGuire: Lesson Plan, Topic 13, OP MC IC CHB, page 31. .,
- 2. KA 015000G007 (3.3/3.4). ,
015000G007 ..(KA's) - f ANSWER: 010 (1.00)
- c. [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 16, OP NC-IC-ENB, page 26.
- 2. KA 015000K604 (3.1/3.2) 015000K604 ..(KA's) i 1
l
- u. _ _ _
( SENIOR REACTOR OPERATOR Page 54 f
%> i ANSWER: 011 '(1.00)
- b. [+1.0) !
REFERENCE:
t
- 1. McGuire: Lesson Plan, Topic 14, OP MC-CNT-VUL page 20.. (
- 2. McGuire: Lesson Plan OP MC CNT-VUL objective 3.
- 3. KA 022000K402 (3.1/3.4) i 022000K402 ..(KA's) ,
i ANSWER: 012 (1.00)
- d. [+1.0) .
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 14, OP MC CNT VUL page 17.
- 2. KA 022000K101 (3.5/3.7) 022000K101 ..(KA's)
ANSWER: 013 (1.00)
- a. [+1.0) ,
i
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 14, OP-MC-CNT-NF page 16,
- 2. KA 022000A301 (4.1/4.3) 022000A101 (3.6/3.7)
'l 022000A301 022000A10.' ..(KA's) >
H i ANSWER: 014 (1.00)-
- b. [+1.0) _;
l 1 I t
r SENIOR REACTOR OPERATOR Page 55 f
REFERENCE:
i
- 1. McGuire: Lesscn Plan, Topic 17, OP-MC-ECC NS, pages ll,12, and 13. !
- 2. McGuire: Lesson Plan, Topic 17, OP MC-ECC-ISC, pages 16 and 17. j
- 3. KA 026000A401 (4.5/4.3) i 026000A401 ..(KA's) :
ANSWER: 015 (1.00) ]
- a. [+1.0)
REFERENCE:
l
- 1. McGuire: Lesson Plan, Topic 10, OP-MC-CF-CF, page 26.
- 2. KA 059000K416 (3.1/3.2) 059000K416 ..(KA's)
II ANSWER: 016 (1.00)
- d. [+1.0) i
REFERENCE:
i
- 1. McGuire: Lesson Plan, Topic 10, OP HC CF CF, pages 14 and 26. .
- 2. McGuire: Lesson Plan, Topic 17, OP-MC-ECC-ISE, page 20,
- 3. KA 059000A203 (2.7/3.1) 059000K104 (3.4/3.4) i 059000K104 059000A203 ..(KA's) ,
s ANSWER: 017 (1.00)
- a. [+1.0)
SENIOR REACTOR OPERATOR Page 56 I
REFERENCE:
j
- 1. McGuire: Lesson Plan, Topic 10, OP-MC CF-CF, page 21. ;
- 2. McGuire: Lesson Plan, Topic 17, OP MC ECC ISE, page 21. !
- 3. KA 059000A412 (3.4/3.5) l t
059000A412 ..(KA's) l ANSWER: 018 (1.00)
- c. [+1.0) i
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 10, OP MC CF CA. !
- 2. KA 061000K50) (3.6/3.9) 061000K501 ..(KA's)
ANSWER: 019 (1.00) i
- c. [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 16, OP MC IC IRE page 22. ;
- 2. McGuire: Lesson Plan, Topic 16, OP MC IC-IRE, Objective 9 and 10. 1
- 3. KA 063000K302 (3.5/3.7) 063000K302 ..(KA's) l l
l ANSWER: 020 (1.00)
- a. [+1.0) )
i
)
1
~ SENIOR REACTOR OPERATOR Page 57 j l
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 22, OP MC WE-EMF, page 14. ;
- 2. McGuire: Lesson Plan, Topic 22, OP MC WE EMF, objective 3. ;
- 3. KA 071000A303 (3.6/3.8).
- 071000A303 ..(KA's) {
ANSWER: 021 (1.00) ;
- c. [+1.0) i
REFERENCE:
- 1. McGuire: ' Lesson Plan, Topic 15, OP-MC PS NC. ,
- 2. KA 002020K509.(3.6/3.9) ,
002020K509 ..(KA's)
' ANSWER: 022 (1.00)
- a. [+1.0) j
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 22, OP MC WE-WL, handout MC WE WL 3,
- 2. McGuire: MC-1553 2.1
- 3. KA 002000K110 (2.8/3.1) i 002000K110 ..(KA's)
ANSWER: 023 (1.00)
- c. [+1.0) !
l r i.
t e. . SENIOR REACTOR OPERATOR Page 58 j
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 14, OP-MC ECC-CLA page 11. '
- 2. KA 006020K603 (3.0/3.2) 006000K602 (3.4/3.9) 006000A301 (4.0/3.9) .
006000A301 006000K602 006020K603 ..(KA's) ANSWER: 024 (1.00) , a.-[+1.0)
REFERENCE:
- 1. McGuire: Technical Specification 3.5.5.
- 2. KA 006000A102 (3.0/3.6) 006000A102 ..(KA's) .
ANSWER: 025 (1.00)
- d. [+1.0) i
REFERENCE:
- 1. McGuire: System Description, MC 1223.04 page 5.
- 2. KA 006000K613 (2.6/2.9) ;
006000K613 ..(KA's) ANSWER: 026 (1.00)
- b. [+1.0) -
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 15, OP MC PS IPE, handout MC IC-IPE-13. l
- 2. KA 010000A402 (3.6/3.4) l 010000A402 ..(KA's)
I l q
F F , . SENIOR REACTOR OPERATOR' Page 59 ANSWER: 027 (1.00) d.' [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 15, OP MC-PS IPE pages 20 and 37,
- 2. KA 010000K603 (3.2/3.6) 010000A403 (4.0/3.8) 010000A403 010000K603 ..(KA's)
ANSWER: 028 (1.00)
- b. [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 15, OP MC-PS ILE, page 5. -
- 2. McGuire: Lesson Plan, Topic 15, OP MC-PS ILE objective 1.B.
- 3. KA 011000K512 (2.7/3.3) 011000K512 ..(KA's) :
ANSWER: 029 (1.00)
- c. [+1.0)
REFERENCE:
- 1. McGuire: Technical Specifications 2.2.1 and bases page B 2-8.
- 2. KA 012000K406 (3.2/3.5) 012000K406 ..(KA's)
ANSWER: 030 (1.00) l I d .' [+1e) l l 1
~
F , , SENIOR REACTOR OPERATOR Page 60
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 14, OP-MC-CNT-VX, page 19.
- 2. KA 028000A401 (4.0/4.0) 028000A401 ..(KA's)
ANSWER: 031 (1.00)
- b. [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 10, OP-MC CF-IFE handouts OP-MC-IFE-1A and R
- 2. 35 kbl(3.6/3.8) ;
035010A101 ..(KA's) . ANSWER:- 032 (1.00) ;
- c. [+1.0)
REFERENCE:
l 1._McGuire: Lesson M:.n, Topic 8, OP-MC-STM SG.
- 2. KA 035010K501 (3.4/3.9) ]
035010K501 ..(KA's) .] ANSWER: 033 (1.00)
- d. [+1.0) 1
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 6, OP-MC-EL-EP, page 25. .
2.-McGuire: Lesson Plan, Topic 6, OP-MC-EL EP, handout OP MC-SLYS-EP 1.
- 3. KA 062000K201 (3.3/3.4) 4 062000K201 ,,(KA's)
y -_ _ - . F ~ SENIOR REACTOR OPERATOR Page 61 : L i ANSWER: 034 (1.00) c.. (+1.0)
REFERENCE:
- 1. McGuire: OP/1/A/6300/01, ENCLOSURE 4.2, page 8.
- 2. KA 062000A403 (2.8/2.9) !
062000A403 ..(KA's) ANSWER: 035 (1.00)
- b. (+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 12, OP-MC-DG DG, page 10.
- 2. McGuire: Lesson Plan, Topic 12. OP-MC DG DG, Objective 3.
- 3. KA 064000A103 (3.2/3.3) 064000A103 ..(KA's) i ANSWER: 036 (1.00)
- b. (+1.0)
REFERENCE:
- 1. McGuire: Question bank, Q DG-DG-06,
- 2. McGuire: Lesson Plan, OP-MC-DG-DG, page 10.
- 3. KA 064000A302 (3.4/3.7) +
064000A302 ..(KA's) - ANSWER:- 037 (1.00) i i
- d. [+1.0) l i
l l
SENIOR REACTOR OPERATOR Page 62
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 17, OP-MC-ECC-ISE, objective 1.C, page 14.
- 2. KA 103000K406 (3.1/3.7).
l 103000K406 ..(KA's) ANSWER: 038 (1.00) l c. [+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 15, OP-MC-PS NV page 11.
- 2. McGuire: Drawing MC-1553.and MC-1554.
- 3. KA 007000K103 (3.0/3.2) 007000A301 (2.7/2.9) 007000A301 007000K103 ..(KA's) ,
ANSWER: 039 (1.00) .
- a. (+1.0)
REFERENCE:
j
- 1. McGuire: Lesson Plan, Topic 10, OP-MC-PSS KC-2.
- 2. McGuire: System Description RN, Table 1. i
- 3. KA 008000K102 (3.3/3.4) .,
008000K102 ..(KA's) l ANSWER: 040 (1.00)
- a. (+1.0) )
1 1 l l l l
.l l
l l
7 ..,
)
{ <
\
i SENIOR REACTOR OPERATOR Page 63 l I
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 17, OP-MC-ECC-ISE, page 14. '
- 2. McGuire: Lesson Plan, Topic 13, OP-MC PSS-KC, pages 7,18, and 29. l
- 3. McGuire: Lesson Plan Topic 12, OP MC-DG-EQB, page 11. !
- 4. KA 008030A304 (3.6/3.7) l I
008030A304 ..(KA's) l ANSWER: 041 (1.00) !
- c. [+1.0)
REFERENCE:
- 1. McGuire: AP/1/A/5500/14, page 4.
- 2. KA 000001A205 (4.4/4.6) 00000lG010 (3.9/4.0) 000001G010 000001A205 ..(KA's) ;
l ANSWER: 042 (1.00)
- c. [+1.0) ,
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 16, OP MC-IC IRE. >
- 2. KA 000001A205 (4.4/4.6) 000001A205 ..(KA's)
ANSWER: 043 (1.00)
- c. [+1.0)-
i
REFERENCE:
- 1. McGuire: OP/1/A/5500/14, page 6,
- 2. KA 000003G010 (3.9/3.8) 000003G010 ..(KA's)
. t e
... .+
l SENIOR REACTOR OPERATOR Page 64 l l- n.; l ANSWER: 044 (1.00)
- c. [+1.0) ,
REFERENCE:
- 1. McGuire: AP/1/A/5500/14, page 16. l 2._KA 000003K205 (2.5/2.8) 000003K308 (3.1/4.2) i 000003K205 000003K308 ..(KA's)
L ANSWEx: 045 (1.00) ,
- d. [+1.0) .
REFERENCE:
.l. McGuire: Lesson Plan, Topic 21, OP MC-EP EP2.
2.-McGuire: Lesson Plan, Topic 21, OP-MC EP-EPl. .
-3. KA 0000llA213 (3.7/3.7) !
0000llA213 ..(KA's) , ANSWER: 046 (1.00) f (+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 17, OP-MC-ECC-ISE, pages 14 and 21.
2.'McGuire: Lesson Plan, Topic 17, OP MC ECC ISE, LPRO and LPS0 1.c. ,
- 3. McGuire: Lesson Plan, Topic 13, OP-MC-PSS-RN, page 20.
- 4. McGuire: Lesson Plan, Topic 13, OP-MC PSS-RN, ISS objective 8.
- 5. KA 0000llA112 (4.1/4.2) 000011K302 (3.5/3.7) 000011All2 000011K302 ..(KA's)
. ANSWER: 047 (1.00)
- a. [+ 1. 0) .
- n. -, , . .
. l SENIOR REACTOR OPERATOR Page 65
REFERENCE:
l
- 1. McGuire: Question bank, Q-DG EQS 6.
- 2. McGuire: Lesson Plan, Topic 12, OP MC DG E48, page 11. "
- 3. KA 000011All3 (4.1/4.2) 0000llA113 ..(KA's)
ANSWER: 048 (1.00)
- d. [+1.01
REFERENCE:
1
- 1. McGuire: Lesson Plan, Topic 20, OP MC-TA AM, page 26. )
- 2. WOG ES 0.2, page 28. l
- 3. McGuire: EP/1/A/5000/1.1, page 5. l
- 4. KA 000015K307 (4.1/4.2) 000015K307 ..(KA's) i ANSWER: 049 .(1.00)
- d. (+1.0) i
REFERENCE:
- 1. McGuire: EP/1/A/5000/1.1, Foldout.
- 2. KA 000015K101 (4.4/4.6) :
000015K301 ..(KA's) ANSWER: 050 (1.00)
- b. (+1.0) i
REFERENCE:
- 1. McGuire: AP/1/A/5500/38, " Emergency Boration," page 2.
- 2. KA 000024G011 (3.8/3.9) 000024K301 (4.1/4.4) 000024K301 000024G0ll ..(KA's) [
W . $ SENIOR REACTOR OPERATOR- Page 66 l. ANSWER: 051 (1.00)
- b. [+1.0)
REFERENCE:
- 1. McGuire: System Description 1223.23, pages 9 and 22.
- 2. KA 000026A105 (3.1/3.1) 000026A105 ..(KA's)
ANSWER: 052 (1.00)
- a. (+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 10, OP MC CF-CF, page 16,
- 2. McGuire: EP/1/A/5000/ll.1, " Response to Nuclear Power Generation /ATWS."
- 3. KA 000029All5-(4.1/3.9) 000029K312 (4.4/4.7) 000029K312 000029All5 ..(KA's)
ANSWER: 053 (1.00)
- a. (+1.0)
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 21, OP MC EP FP6, page 6.
- 2. WOG FR-S.1, pages 23.and 24.
- 3. KA 000029K312 (4.4/4.7) 000029K312 ..(KA's)
ANSWER: 054 (1.00)
- a. [+1.0) i I
h
g
'SEN10s : REACTOR OPERATOR Page 67
REFERENCE:
hh 5 4
- 1. McGuire: ' Lesson Plan, Topic 21, .'0P-MC-EP-EP6 page 7.
2.- McGuire:' Lesson = Plan,- Topic 21=, OP MC-EP-EP6, objective B.3. k0 '
- 3. McGuire: EP/1/A/5000/ll.1 page 2.
E 14.-KA 000029K312 (4.4/4.7)- 000029K312 ..(KA's)
-ANSWER: 055.(1.00)
- a. [+1.0) 5
REFERENCE:
g 1. McGuire: EP 12.1, . " Response to Inadequate Core Cooling." i 2. McGuire: Status Trees. - 3. McGuire:- OP-MC EP-EP7, Objective B. 4..KA 000074G011 (4.5/4.6) L-000074G011 ..(KA's) y
' AN'.lER: 056 (1.00)
- b. (+1.0)
REFERENCE:
1.-McGuire: OP-MC-EP-EP9, Objective B.2., p. 7.
- 2.-McGuire: EP/1/A/5000/14.1, " Response to Imminen iicssurized Thermal Shock Conditions."
. 3. KA 000040K101.(4.1/4.4) 5 000040K101 ..(KA's)
.e ' ANSWER:- 057 (1.00)
, b ;[+1.0)
_ -r ,
, m ..- , a
.Page 68 if
- SENIOR REACTOR OPERATOR l
l l
REFERENCE:
a 1.-_McGuire:~ EP/1/A/5000/03, page 3.
'2. McGuire: Lesson Plan, Topi; 21, OP-MC-EP-EP3, page 5.
- 3. McGuire: Lesson Objective 2b.
.4~KA3000040K304-(4.5/4.7) 1, 000040K304 ....(KA's) i d
ANSWER: 058'(1.00)
- d. [+1.0)- j
!. a l-
REFERENCE:
I l
- 1. McGuire: Lesson Plan, Topic 21, OP-MC-EP-EP9, page 6. I
- 2. McGuire: . EP/1/A/5000/14.1, pages 1 and 2. .I l
- 3. KA 000040K101 (4.1/4.4).KA 000040K304 (4.5/4.7) l O'00040K101 000040K304' ...(KA's) l l
l- l ANSWER: 059 (1.00) )
.d. (+1.0) 1 1,
l
REFERENCE:
- 1. McGuire: Lesson Plan, Topic 21, OP-MC-EP-EPF, page 25. .
2..McGuire: Eril/A/5000/12, 12.1, 12.2, and 12.3. 1
- 3. KA 000040K306 (3.4/3.9) .l l.
000040K306 ..(KA's) i
'l l
,1 ANSWER:. 060 (1.00) -
- a. (+1.0) l u
I li l l . 1
p .- '. LSENIOR REACTOR OPERATOR.. Page 69 . l .I t
REFERENCE:
- l. McGuire: AP/1/A/5500/23,-pages 2 and 3.-
;2. KA 000051A202i(3.9/4.1) 000051G0ll (2.7/2.9) ,
000051A202 000051G011' ..(KA's) .3 l .
- ANSWER:. 061 ('.00)
- d. -[4: 9]
REFERENCE:
lMcGuire: EP/1/A/5000/09, " Loss of All AC Power".
- 2. McGuire: Lesson Plan, Topic 21, OP-MC-EP-EPS. y
- 3. KA 000055G010 (4.1/4.3) 000055K302 (4.3/4.6) 000055K302. 000055G010 ..(VA's)
ANSWER: 062 -(1.00)
- d. (+1.0]
i
REFERENCE:
- 1. McGuire: OP-MC-EL-EPL, page ll. '
- 2. McGuire: Question Bank, Q DG EPQ-01.
3.-KA 000055K301 (2.7/3.4)
'000055K301 ..(KA's) t ANSWER: 063 (1.00)~
- a. (+1.0]
i
REFERENCE:
i
- 1. McGuire: Lesson Plan, Topic 13, OP-MC-IC-ICH pages 17 and 18.
- 2. KA 000074A116 (4.4/4.6) 000074A101'(4.2/4.4) 000074A101 000074All6 ..(KA's)
'f
SENIOR REACTOR OPERATOR- Page 70
'1
,( 1 1
- ANSWER:' 064 (1.00) i
- d. [+1.0)
REFERENCE:
- 1. McGuire: Technical Specifications, 3.4.8 and Bases, p. B 3/4 4-7.
- 2. KA 000076K305 (2.9/3.6) KA 000076G004 (2.1/3.7) 000076K305 000076G004 ..(KA's) q q
- ANSWER: 065 (1.00) -
- b. [+1.0] [
REFERENCE:
i
- 1. McGuire: Steam Tables, j
- 2. KA 000007A103 (4.2/4.1) l t
000007A103 ..(KA's) i 1
. ANSWER:- 066 (1.00)
'd .' [+1.0)
REFERENCE:
l.'McGuire: 1.esson Plan, Topic 17, OP-MC TA-AM, page 53.
- 2. McGuire: 1.esson Plan, Topic 21, OP-P EF-EP9, page 6.
- 3. KA= 000008K202 (2.7/2.7) ],
j 000008K202 ..(KA's) ANSWER: 067-(1.00)- I a.- [+1.0] f
.o .-
SENIOR REACTOR 0PERATOR. , Pag ( 11 7 H ;
REFERENCE:
p ; s 1. McGuire: Technical Specifications 3.4.6.2 and Definitions. ; 2..KA 000009G003 (3.5/4.1)- 000009G003 ..(KA's)
. ANSWER: 068 (1.00)
- a. - [+1.0) (W +
REFERENCE:
l.-McGuire: OP-MC-DG-EQB . Handouts at end of lesson.
- 2. KA 000009All3 (4.4/4.4)-
000009A113 ..(KA's)
' ANSWER: 069 (1.00)' i
- a. [+1.0)
REFERENCE:
- 1. McGuire: . Lesson Plan, Topic'15, OP-MC-PS-NV, pages 31-35. !
2.-McGuire: Malfunction Description, NV-18,
- 3. KA 000022A201 (3.2/3.8) 000022A2011 ..(KA's) i ANSWER:. 070 (1.00) c._[+1.0)
REFERENCE:
1
- 1. McGuire. EP/1/A/5000/2.3, pages 3, 5, and 6.
2.'McGuire: Lesson Plan, Topic 15, OP-MC-PS-ND, page 21. 3; KA 000025K301 (3.1/3.4) 000025K301 ..(KA's) [
,1
; SENIOR. REACTOR OPERATOR Page 72 4
' ANSWER: ' 071_ (1.00)= ;
i
- c. (+1.0]_ ;
REFERENCE:
. f
- 1. McGuire: 'AP/1/A/5500/19,.page 17. '
- 2. KA-000025A103 (3.4/3.3) 000025K303 (3.9/4.1) 000025K101 (3.9/4.3) ;
000025K303 000025K101 000025A103 ..(KA's) 1
' ANSWER: - 072 (1.00) :
c._ (+1.0]
REFERENCE:
1, McGuire: AP/1/A/5500/11, page 2.- ,
- 2. KA 000027A101 (4.0/3.9) l I
000027A101 ..(KA's) ANSWER: 073- (1.00)
- d. [+1.0) ,
i REFERENCE. ,
- 1. McGuire: Technical Specifications 3.3.1. !'
,2. McGuire: AP/1/A/5500/16, page 2.
-3. KA' 000032G003 (2.6/3.3)
L- 000032G003 ...(KA's) ANSWER: 074 (1.00) c.. (+1.0) i I
i 1
. .. i
' SENIOR REACTOR 0 ,JR _Page 73-
REFERENCE:
~
- l. McGuire: AP/1/A/5500/16, page 5.
-2. KA 000033A211 (3.1/3.4) 000033A211 ..(KA's) i i
ANSWER: 075 _(1.00) lc. (+1.0) ,
REFERENCE:
l'. McGuire: Technical Specification 3.3.1.
- 2. KA 000033A209 (3.4/3.7) KA 000033G008 (2.8/3.4) 000033A209 000033G008 ..(KA's)
ANSWER: 076 (1.00) b.- [+1.0] 4 i
REFERENCE:
- 1. McGuire: AP/1/A/5500/10, page 2.
- 2. KA 000037K307 (4.2/4.4) 4 000037K307 ...(KA's)
ANSWER: 077 (1.00)
.b (+1.0) -
REFERENCE:
- 11. McGuire: AP/1/A/5500/10, page 2.
L ,
.2; KA 000037Alll (3.'4/3.3) c h~
000037A111 ..(KA's) i
1' o , LSENIOR' REACTOR OPERATOR Page 74-ANSWER: 078 -(1.00)- o d.. [+ 1 '. 0)
REFERENCE:
t 1.'McGuire: Lesson Plan, Topic 21, OP-MC-EP-EP 4, pages 28 and 29, i 2.KA000038K306(4.2/4.5) 00003BK306 ..(KA's)
\
ANSWER: 079 (1.00)
- a. [+1.0)
REFERENCE:
s
- 1. McGuire: Lesson Plan, Topic 20, OP-MC TA-SA. -
.2.KA000054K102(3.6/4.2) >
000054K102 ..(KA's)
=l i
IANSWER: 080 (1.00)
- a. .[+1.0) l
REFERENCE:
i
'l l'. McGuire: Lesson Plan, Topic 22,0P-MC-WE-EMF, page '22.
- 2. KA 000061A101 (3.6/3.6) l l
000061A101 ..(KA's)- ANSWER: 081 (1.00)
- b. [+1.0)
-)
i
I SENIOR REACTOR OPERATOR- Page 75
REFERENCE:
f
- 1. McGuire: Lesson Plan, Topic 15, OP-MC PS ILE, handout MC-IC-ILE-2,3. l
- 2. McGuire: Lesson Plan, Topic 15, OP-MC PS ILE, pages 8, 9. '
+
'3. KA 000028K202 (2.6/2.7) 000028K101 (2.8/3.1) ,
000028K101 000028K202 ..(KA's) ; il ' ANSWER:' 082 (1.00) i
- d. [+1.0) ,
1 r. l
REFERENCE:
-l
- 1. McGuire: AP/1/A/5500/40, page 2. l
- 2. McGuire: Lesson Plan, Topic 23, OP-MC-FH-FC, objective 13. l
- 3. KA 000036K201 (2.9/3.7) 000036G010 (3.7/3.8)
-000036K201 000036G010 ..(KA's) J ANSWER: 083 (1.00)
J
- b. [+1.0)
REFERENCE:
- 1. McGuire: AP/1/A/5500/03,.pages 2, 9, and 16.
- 2. KA 000056K302 (4.4/4.7)-
000056K302. ..(KA's) l
- ANSWER: 084 (1.00)
+.
- d. -[+1.0)
RE5ERENCE:
- 1. McGuire: S.D.,3.1.19, page 11.
-2. KA 19400lK102 (3.7/4.1)'
194001K102 ..(KA's) m i
- e.
- y ML SENIOR REACTOR'0PERATOR Page 76-a bc v1
- ANSWER:- 085 (1.00)~-
c.. [+1.0)
REFERENCE:
- 1. McGuire: S.D. 3.1.19, page 20.
- 2. KA 194001K101 (3.6/3s7) 19400lK101 ..(KA's) ,
.I I
ANSWER: 086 (1.00)
- b. [+1.0]'
REFERENCE:
l
- 1. McGuire: S.D. 3.1.19, page 30,
- 2. KA 194001K102 (3.7/4.1) .
194001K102 ..(KA's) ANSWER: 087 (1.00) d.. [+1.0)
REFERENCE:
- 1. McGuire: S.D. 3.1.19, page 35.
- 2. KA 194001A105 (3.6/3.8) .i 1
194001A105 ..(KA's) 'l 1 J ANSWER: 088 (1.00) .i c .L (+1.0]' o ~ .
i n ;; ,5 ,
?
. SENIOR REACTOR OPERATOR. Page 77 ;
i
REFERENCE:
- 1. -' McGui re : OPM l-6 page 2.
~
- 2. KA 194001A110 (2.9/3.9)-
_p 194001A110 ..(KA's)
.I ANSWER:: 089 (1.00)
, c. ' [+1.0) Fv ( .
REFERENCE:
- 1. McGuire: OPM l-6, page 5, 2..KA 194001K101 (3.6/3.7) i 19400lK101 ..(KA's) ,
1 ANSWER: 090 (l'.00) d- [+1.0) f, f
REFERENCE:
- 1. McGuire: OMP-2-4, page 3. !
- 2. KA 194001A105.(3.4/3.4) 194001A106 ..(KA's) ;
. l
' ANSWER: 091 (1.00) .
- d. [+1 0).- l
REFERENCE:
- l. McGuire: OMP l-2, page 3.
2; KA 194001A102 (4.1/3.9). 194001A102 ..(KA's) i r-
^ -
e r
-SENIOR REACTOR OPERATOR- Page.78 i
IL ANSWER:l 092 (1.00) h
. i
'c; [+1.0) i
REFERENCE:
- 1. McGuire: Radiation Physics Manual, section 2.1, pages 3 to 6.
2.' KA_19400lK103 (2.8/3.4) , 19400lK103 ..(KA's) ! ANSWER: 093 (1.00) ;
- a. -[+1.0]
REFERENCE:
- 1. McGuire: Radiation Protection Manual, section 3.1.4.
- 2. KA 19400lK104.(3.3/3.5) q 19400lK104 ..(KA's)
~ ANSWER: 094 (1.00)
((+1.0) C is o nIy CDc d Ai M M"r ("%' Ab ' / (nm m ciiIL
- 1. McGuire: Radiation Protection Manual section 6.1.4. c
- 2. KA 19400lK103 (2.8/3.4) 194001K103 ..(KA's)
ANSWER: 095 (1.00)
- d. .[+1.0) 1 L H i
I: L j
g . . .
- SENIOR-REACTOR OPERATOR. Page 79
REFERENCE:
Ll 'McGuire: OMP 2-16,'page 2.-
- 2. KA 194001All2-(3.1/4.1) ,
L 194001A112 ..(KA's)
#NSWER: 096 -(l'.00)- .
c.=[+1.0)
REFERENCE:
- 1. McGuire: SD 3.7.1,.section 5.1.2.2. t
- 2. KA.19400lK105 (3.1/3.4) :
19400lK105 ..(KA's) , ANSWER:' 097 (1.00).
- b. [+1.0) r
REFERENCE:
'l.-McGuire: RP/0/A/5700/02, section 2.1.3, page 1.
-2.:KA 194001A116 (3.1/4.4) 194001A116'- ..(KA's)
ANSWER: 098 (1.00)
.a. [+1.0) ;
REFERENCE:
l l'. McGuire: S.D. 3.1.4 pages 1, 2, and 3.
~2.'KA 194001A109 (2.7/3.9) l l
194001A109 ..(XA's) 1 l l l e -
= SENIOR. REACTOR OPERATOR PAge 80-4
, ANSWER: 099 (1.00)'
b.. [+1.0)-
REFERENCE:
- l. McGuire: Lesson Plan, Topic 21,- OP-MC-EP-EPF.
2.-KA 194001A102 (4.1/3.9) 194001A102 ..(KA's) ANSWER: 100 (1.00)
- b. [+1.0)
REFERENCE:
=1. McGuire: OP/0/A/6550/22 page 1.
2.-KA 194001A112 (3.1/4.1) 194001A112 ..(KA's) 1 1 l
) ,ia j i
i l l (********** END OF EXAMINATION **********) :
.i n
3 s ~. .- w
]- -
g 1 SENIOR' REACTOR OPERATOR Page 1 ! ANSWER KEY r i 001- d-002 c' 003 a 004 b 005 d 006 a ; 007- d ' 008 d ! 009 b 010 c. 011 b-012 d 013 a
. 014 b-015 a
, -016- d i
-017 a <
018 c 019: c - v- : 020: a 021' c. 022- a 023- c. l 024 a i :. 025 d I:i. ..
= SENIOR REACTOR OPERATOR Page 2 ANSWER' K'E Y
+ C i. t
-)
026: b J
!" 027- d i
028 b 029 c 030 d 031 b ! 032 c 033 d l [ 034. c-035 b El 036 b I 037 d 'i 1
;038. c '
1 039 a 040 a 4 s 041 c
-042 c I
043 e~
-t
-044 c -
l 045' d
-l l
046- / CL - l 047 a
'048 d I
)
049 d l 1 050 b :l' 3
4. o '7 y. , i SENIOR REACTOR OPERATOR- Page '3f -j A N'S W E R KEY' l 051 b 052 a 053- a i
.t
'054 a 1 l
055 a ; 056 b' l 057 b= , 058 d. -l 059 d 060- a
'061 d
.062 'd :
~
.l 063- a .,
.064. d.
065 b 066 .d 067' .a j 068 a :c* (/- l
~069' a- .!
- 070 .c 071- c-
-e 072 c
.1
-073 d 074 c
<,. 075L c
L . ,
- MCGUIRE.SRO .. .
7/26/90 Page 92
; SENIOR _ REACTOR OPERA 70R' Page 4 ANSWER KEY 076 'b-077 b 078 d 079' a 080 a 081 b
.082 d
-083 .b 084. d 085 c 086 b l
087 d 088 c 089 cevd 090 d >
-091 d L092 c i 093'- a. .a 094 ,/ C-095 .d 096- .c
('y 097 b I 098. a 1099 t 'I v 100 b i (********** END OF EXAMINATION **********)
TEST CROSS REFERENCE Page 1 QUESTION VALVE' REFERENCE 001 1.00- 9000001 ; 002 1.00 9000015
.003 1.00 9000061 004 1.00 9000016 005 1.00 9000025 006 1.00- 9000017 -
007 1.00 9000046 008 1.00 9000002 , 009- 1.00 9000008 010 1.00 9000023 011 1.00 9000041 . 012 1.00 9000042 , 013 1.00 9000043 014 1.00 9000086 i
~
015 1.00 9000029 016 1.00 9000030-017 1.00 9000031 018 1.00 9000084 019 1.00 9000053 020- 1.00 -9000010 021 1.00' 9000068 022 1.00 9000074' 023 1.00 9000006 024 1.00 9000034 , 025 1.00 9000065 026 1.00 9000014 027 1.00 9000066 028- 1.00 9000091 3 029 1.00 9000045 030' 1.00 9000072 g 031 1.00 9000073 032 1.00 9000085 033 1.00- 9000022 H ' 034 1.00 9000069 035 1.00 9000024 1 036 1.00 9000052 ; 037- 1.00 9000011 l
-038 1.00 .9000040 i
~039 1.00 9000007-040 1.00 90000711 041 l'.00 9000048-042: 1.00 9000089 l 043 1.00 9000018- j 044 1.00: 9000092 l 045 1.00 9000036
'046 1.00. 9000082 047 1.00 9000096 048: 1.00 9000075 049 '1.00 9000077 050 1.00 9000019 ,
051 1.00 9000093 l 052- 1.00 9000028 053 1.00 9000049 054 1.00 9000078
. m TEST CROSS REFERENCE Page 2
-QUESTION VALUE REFERENCE l
055 1.00 9000026 056 1.00 9000027 057 1.00 9000044' ; 058 1.00 9000081 i 059 1.00 9000083 ' 060 1.00 9000088 1 061 1.00 9000037 1 062 1.00 9000094 063 1.00 9000067 064 1.00 9000080 065 1.00 9000064 066 1.00 9000062 l 067 1.00 9000063 068 1.00 9000095 069 1.00 9000013 070 1.00 9000055 ' 071 1.00 9000056 072 1.00 9000057 073 1.00 9000051 074 1.00 9000059 . 075 1.00 900C079 , 076 1.00 9000039 077 1.00 9000050 : 078 1.00 9000058 079 1.00 9000076 080 1.00 9000060 081 1.00- 9000070 082 1.00 9000090 083 1.00 9000012 084 1.00 9000098 085 1.00 9000099 086 1.00 9000100 > 087 1.00 9000101 088- 'l.00 9000102 089 1.00 9000103 090 1.00 9000104 091: 1.00 9000105 092 1.00 9000107 093 1.00 9000108 094 1.00 9000110 095 1.00 9000111 096 1.00 9000112- ; 097 1.00 9000113 098 1.00 9000114 099 1.00 9000115 100 1.00 9000116 lbb$bb 100.00 I i (= 'l
11 1 '
- sy . ENCLOSURE 3 ,
l' DukeItnwr Company huddlion Support ikpartment (70418TS 50C9 7 mining & Technologv center - ID39 dagm kny Rwd Huntmeil:e, NC28018 DUKEPOWER
- August 1, 1990 Mr. Chuck Casto-Operator Licensing Section U.S. Nuclear Regulatory. Commission Region II 101 Marietta Street N.W. .
Atlanta,. Georgia.
Subject:
McGuire Nuclear Station Review of Written License Examinations
Dear Sir:
-Attached are our: specific comments on the Reactor Operator and Senior Reactor Operator, written examinations administered July 30,.1990 at
.McGuire Nuclear Station.
i Inhaddition,-McGuire would like to commend the NRC for allowing a ' pre-exam review and'the openness with which they received.our t comments. ' Very truly yours, ! LA? T.L. McConnell Plant. Manager . McGuire' Nuclear Station
. CAM /wms cc: R.B. Travis L.E. Weaver i
~D.A. Baxter D.M. McGinnis P;F.: 9.2 t i
=l t
=l 1
(... ' -
..)
+
31I + 4
'\ 31 j '
,~
- -i E RO --N/Al SRO-68: *
' QUESTION:
l
' PROBLEM:- Two potentially correct-answers,
- a. Is' correct if > 3.0 PSIG Containment Pressure'when-LOCA Seq Actuated.
d.- Is correct if < 3.0 PSIG Containment Pressure wheni
.LOCA seq Actuated and pressure increases to 3.0-o!
, PSIG later.
*iJTE: LOCA Seq doesn't actually start NS Pump, it only provides an -
enabling signal to allow "Hi-H1' Containment Pressure" (>"3.0L ,
# .PSIG) to start pump. l y
REFERENCE:
OP-MC-ECC-NS (page 11) : 1 RECOOGENDED ACTION: ., No action is recommend for.this exam, however please modify-question as shown below'if the exam question is.to be..used again. The following is a list of loads sequenced cn1 by the LOCA sequencer:
- 1. NV Pump
- 2. NS Pump
- 3. CA Pump ,
WHICH ONE(1)'of the following is the correct order for loading'.the sequencer loads during a LOCA with > 3.0;PSIG in Containmett?-
.i
- a. 1 , 2 , 3-4 b.- 2, 1, 3
- c. 2, 3, 1 1 d.-- 1, 3, 2' 1
h
,- 'i OP-MC-ECC-NS Juno 5,11983 DWA/
Page 11'of 18 i
+
r B. Abnormal and Emergency Operation-
- 1. +--AutorAc,tuationi+.a:4
. , ,uu u
- a. ?Hi1Hi' Containment?Presisurej
- 1) Setpoint of 3 psig
- 2) Logic 2 of.4 detectors
- b. . CPCS > .35 psig i
- 1) 5370 permissive for NS-32 and 29 -
- 2) 5360 permissive for NS-15 and 12
- 3) 5520 permissive for NS .Pwnp A *
- 4) 3510 permissive for NS Pump'B
- 2. Manual Actuation
- a. Containment Spray / Phase B. initiation pushbutton train.A or B-depressed
- b. .CPCS > .35 psig i
- 3. ISystem:Acguation@
a.- NS pump discharge containment isolation: valves open Ng b .e j NS ipump's Ostartj[
- 4. Discuss EP/ lor 2/A/5000/2.3 " Transfer to CLR"Lin
' relation to'the NS System.
- 5. Discuss when ND spray would be used EP/ lor 2/A/500/15.1 " Response to High Containment' ;
Pressure" ) Rev. 06/11-28-89/WGH i
v ~ 1
+
QUESTION- RO-90 SRO-89' PROBLEM: J Question has two correct answers.- <- c. Is potentially correct per OMP l-6 that states - to restore throttled valves to the: correct position the operators-shall work _together.
} ,
'd. Can also be correct per OMP 1-8 that allows using l
. stem position to verify a throttled valve position i' if valve is not being moved
REFERENCE:
OMP 1-6 OMP 1-8 RECOMMENDED ACTION: No' action recommended for this exam, however please modify '" r question as shown below if the exam question is to berused again.- i WHICH ONE(1) of the following describes how an independent-
. verification of; position for.a manually operated valve ~to be placed11n- i the THROTTLED ~ position is done?-
- a. Move the valve'slightly in'the closed directionland then
~
return 1t to its original position. b.- InspectLthe-last valve: lineup sheetifor verification-4 ' signature and compare recorded valve position with the required position.
- c. Observe the operator initially _ place the valve in'the 1 position that the valve is to be throttled to. .I 1
- d. Compare visuai observation of stem or indicator position 1 with the required position.
l 1 l l 1
.i
, ,l
pra,tiorisT Manages $sif PQfed'un;${}Q : Page.5 of 6 K.- Switches that disable components that are " Essential'to Safety":must be independently verified. L. Other components as determined by the Superintendent of i
, Opertions or his designee. '
i a 7.0 PERFORMANCE OF INDEPENDENT VERIFICATION 7.1 Independent verification consists of two (2) distinct evolutions: (1) First - the correct component is identified and (2) Second - the proper position of that component is verified. Independent 1 verification shall be performed by two (2) different qualified personnel determining the position of valves, breakers or completion of procedure steps. A. A qualified person is an individual who has: ',
- 1. A current license on the applicable unit; or l: ,
- 2. Been qualified in accordance with the Non-NRC Licensed Personnel Training Program. ';
B. The person designated to perform the independent'(second) verification will have.to be qualified to T&Q Guides MO-1001 l- thru 1006, 1008, 2001 and 2002. 7.2 "When[ independent l verification i'sirequiredffor; eqiiipe'edt[tdtMii3
' ^ " ~
re, _4 moved,fr,om: service., the two.per,
, , '_ s e _ ..
sons performing:.the, v. ..,taskpshalltw l-ywork together p f Whenf the) equipmentLis - .- .~ . J returned 9to: serv, ice: ori,umwhent 4 -, , e s < .a ,; l , sperformingDa:vslve,ichecklistTthe
._ .m ., ,.
3
. _ m.g . . , , . g persons?may"workLtogetherb
; ;. _. ; g # .. , . . .-
- l. FAdditional.lypifma --
= valve?is ctoTbe:placed in a " throttled'!!
. _ , , - ~
lipositiorf,{thefpersons shall 2workitogether.; V l ! l
- l l' l l-1 1;-
' o
~"
"Operat.
~ . - - ions.Nanagementi9eoc,edure71$s.
-n i Page 3 of 12- l
- n ,a. - 1 g.. '
+ ;
1 h '
- 3. To' verify-valves in.the." Locked Open" or " Locked Closed" r position, rsmove the lock and physically verify correct' :
y[ position, then replace lock. If valve is " Locked Closed" II and opening is undesirable, apply pressure-in the closed direction to verify.. valve is already closed. Fire protection post indicator valves that have a local I indication of valve position do not have to-be unlocked to verify proper p'osition. 4
- 4. To verify valves in the " Locked Throttled" position verify that the lock, tamper proof locking device, or-
' tamper seal is properly installed. " Locked Throttled" - l
. valve positions are normally set by Performance during testing and require retesting if the positions are changed. l l
- 5. To verify valves in the " Throttled" position:
- a. The operator should physically move the valve-through its stroke to ensure.the correct position.
- b. (When]ticisjundesirable[(due(to system}operatingj
~
istatus)f E n n ~~ to move .~1ad"+-Throttled".! valve.i - to# verify l~its.o
~ --
;positionfusentheifo11owing;considerationslin{ l (determiningjtheval%posi. tion':f
$1) jValvefappeararicag
)
- 2) Flow indications
- 3) Presence of locks
- 4) Consider changing system status in order to-q check valve position '
4 5) Consider impact on plant operation if the valve is misaligned l l
- ,,a
)
> i
<"- a
- QUESTIOtf: RO~ N/A'- SRO-94 PROBLEN: Answer Key is incorrect !
1 b'. Onsite is correct answer on key, but-.this is'not: 1 allowed per RP Manual. s J
- c. Restricted Area is the. correct answer per RP-Manual.
n. 1
REFERENCE:
RP Manual'6.1.4 1 i RECONNENDED-ACTION: Change-answer key to "C" l l 1 1 1
)
i l l I 11 ll l d 1 3 i 1 1 l l 1 I l l l l l- . l l: s.i:
q' ;: ,_
=, ..! b.
p Total '(combination of smearable and fixed contamination) Beta / Gamma - 5000'DPM/100 cm8 measured by a thin window (2 a mg/cm ) pancake GM detector at one-half inch f rom the-surface. This is 150 cepm measured by an Eberline HP-210 or 260 probe with a window area of 16 cma and a window t thickness of 2 mg/cm8 connected to an RM-14 equivalent.- ! Alpha - no net observable' counts above background. NOTE: Monitoring for alpha contamination shall be performed only as conditions require it.
- 3) The System Radiation Protection Manual' allows exception- to the l above limits.in Section I.J.2, i.e., conditional release of items from the RCA. These exceptions are provided to allow .
flexibility in the contamination control program and are not to i be used routinely. 4 1;
-a. Beta-Gamma - (amearable) 15,000 dpm/100 cm2 .
- b. Beta-Gamma - (fixed) 10 mrad /hr at one foot.
t I 6.1.4 TAGS i i.
- 1) A Green " Released" Tag indicates that an item is free of i
significant contamination and/or radiation and'the. items may be' { removed from the Radiation Control Area.and the Restricted Area ' and/or removed f rom the site. i
.{
1-{ NOTE: It is-not intended that this process be used to separate ' fi clean items from contaminated waste or scrape. It'is 1 generally intended for personnel items or occasional I 4
. pieces of equipment. i t
- 2) A Yellow "Ctution Radioactive Material" Tag indicates that i.
caution shall be used in handling an item because residual i contamination remains on the item. 3). 7 Items mayjbelcond1Edon'alk released l2f rorENhe"R'a'diatibn"C$ntEoli E lAreaO(butinot?f rom the: Res trihted 'Areaf that 'd'o[not-L$ thew meet
.m
~
- - ~ ~ ~ ' ~ ~~~-~ ~
a;: , , .$. < e' ireq' uiremental for unconditional
=
( releasej at the discretton of
.m .
Radiation Protection if conditions in Section 6.1.3(3) are met. Such items shall be securely wrapped and tagged with a completed / Yellow - " Temporary Conditional Release" Tag and shall be maintained under positive control.while outside the Radiation Control Area. These items shall be returned to Radiation 5- Protection within the time limit noted n the Yellow -
" Temporary Conditional Release Tag".
6.1.5 HOT TOOL CRIB Items to be released (for storage attd reuse) to the Hot Tool Crib that meet specifications (< 2 mR/hr and < 5,000 dpm/100 cmr get . Gamma) may be released to that area provided all items are painted L i red or scribed to indicate " Radiation Control Area Use Only" and the additional controls described in Section 6.7 are employed. Items in transport to and from the Hot Tool Crib shall be properly wrapped or bagged if necessary, unless a green tag is attached. 6.1.6 Exhibits 6.1-1 Decontamination Planning Worksteet 6.1-2 Radiation protection Tags t 6.1-3 Item Decontamination Lossheet M M b m-P m , -4 b _ _ _ _ _ _ . . . ..
n- . q, -- q p 4 . i Y ' ?, l
'i i
I . . F , ENCLOSURE 4- '{
^
i,g - NRC RESOLUTION OF FACILITY COMMENTS g i i .- R0/SR0 Examination: .! Question 090/089:-
' Facility comment noted. -
Since two correct answers exist, the answer key 'will : be changed to accept either a. or b. for' full credit. i t SRO Examination: l
~
b Question 068: : Facility comment noted. Since two correct answers' exist, the answer key will ! be changed to accept either a, or d. for full credit. ]
. Question 094: . .
Facility comment accepted. . The answer key will be. changed to required c.'for ,
- - -full. credit. "This answer was changed to from c. to b as a result of facility l comments--during the preexamination. review.
- ;
r i [ i ih 1 ; I t 1; t
-h
~!
i 5' . I
.I
,1 t .E
-sk~a
_ . - - . - - ~- _
ENCLOSURE 5 0 ' SIMULATION FACILITY FIDELITY REPORT l Facility Licensee: McGuire Nuclear Station Facility Licensee Docket No.: 50-369, 50-370 Operating Tests Administe;.d on: July 31 - August 2, 1990 This form is to be used only to report observations. These observations do not
'consititue audit or inspection findings and are not, without further verification and review, . indicative of nor.-compliance _ with 10 CFR 55.45(b).
These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations. During the conduct of the simulator portion of the operating examination,'.the
-following items were observed:
- 1) Letdown line flashing does not occur if the letdown pressure control valve is opened fully. Letdown line flashing does occur if charging flow is-reduced.
- 2) Malfunction for NC Hot Leg Leak is non-1Inear with malfunction severity.
- 3) With both pressurizer spray valves failed closed, RCS pressure increased rapidly when the backup heaters energized. When the backup heaters were removed, RCS pressure decreased and controlled at 2235 with no spray flow.
I
. . , - . , _ , v}}