IR 05000313/1993032
| ML20059G282 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/11/1994 |
| From: | Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20059G279 | List: |
| References | |
| 50-313-93-32, 50-368-93-32, NUDOCS 9401240085 | |
| Download: ML20059G282 (194) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
Inspection Report: 50-313/93-32 ,
50-368/93-32 C
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Licenses: DPR-51 NPF-6 _;
Licensee: Entergy Operations, In Route 3, Box 137G Ru*.sellville, Arkansas .
Facility Name: Arkansas Nuclear One, Units 1 and 2 Inspection At: Russellville, Arkansas Inspection Conducted: December 6-17, 1993 Inspectors: R. E. Lantz, Chief Examiner, Operations Section Division of Reactor Safety '
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S. L. M'Crory, Examiner, Operations Section Division of Reactor Safety Accompanying Personnel: K. Faris, Examiner, Contractor Battelle Pacific NW Labs *
N. Maguire-Moffitt, Examiner, Contractor Battelle Pacific NW Labs
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T. Vehec, Examiner, Contractor Battelle Pacific NW Labs Approved: _
lh8 i di Pellet, Chief, Operations Section Date Division of Reactor Safety Inspection Summarv Areas inspected (Unit 2): Routine, announced inspection of the qualifications !
of applicants for operator licenses at the Arkansas Nuclear One, Unit 2, '
facility, which included an eligibility determination and administration of '
comprehensive written examinations and operating tests. The examination team also observed the performance of on-shift operators and plant conditions incident to the conduct of the applicant evaluations. The examiners used the guidance provided in NUREG-1021, " Operator Licensing Examiner Standards," '
Revision 7, Sections 201-203, 301-303, and 401-403, issued January 1993, 9401240085 940113 PDR ADDCK 05000313 O PDR,
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-2-Areas Inspected (Unit 1): No inspection of Unit I was performed.
Results (Unit 2):
- All nine of the applicants for reactor operator and all eight of the applicants for senior reactor operator licenses satisfied the requirements of 10 CFR 55.33(a)(2) (Section 1.6).
- The reference material provided by the training department for examination development was. adequate, with noted areas for improvement (Section 1.1).
- All applicants passed the written examinations, with scores ranging from >
a low of 82 percent to a high of 95 percent with averages of 87 percent for reactor operator applicants, 89 percent for senior reactor operator '
applicants, and 87.9 percent overall (Section Ic2).
- The examiners observed good communication practices from applicants during the conduct of the examinations and from control room operators during plant walkthr oughs (Section 1.3.1).
- In general, applicants did not conduct normal boration control in accordance with approved procedures during the operating test, resulting l from ineffective training (Section 1.3.1). !
- In one instance, component labeling was not as described in approved procedures and was noted to adversely affect operator performance during the walkthrough examinations (Section 1.3.2), j Results-(Unit 11: Not applicabl f Summary of Inspection Findinas:
- There were no findings that were assigned a tracking number identified during the course of this inspectio .
Attachments:
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- Attachment 1 - Persons Contacted and Exit Meeting i
- Attachment 2 - Simulation Facility Report ,
- Attachment 3 - Written Examination Keys !
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-3-DETAILS 1 LICENSED OPERATOR APPLICANT INITIAL QUALIFICATION EVALUATION (NUREG-1021)
During the inspection, the examiners evaluated the qualifications of 17 license applicants: 9 for reactor operator (RO), 4 for senior reactor operator (SRO) currently licensed as R0s, and 4 for instant SRO. The inspection assessed the eligibility and administrative and technical competency of the applicants to be issued licenses to opdrate and direct the operation of the reactivity controls of. a commercial nuclear power facility in a
REGION 4'
CANDIDATE'S NAME:
FACILITY: - ArkansqA Nuclear One-2'
REACTOR TYPE: PWR-CE DATE ADMINISTERED: 93/12/06-
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INSTRUCTIONS TO CANDIDATE:
Use~the answer sheets provided to document your answer Staple this' cover sheet on top _of the answer sheet Points for each-question are' indicated in parentheses after the question. The passing grade requires a final grade of at_least 80%. Examination papers will be picked up four (4)' hours after the examination start CANDIDATE *S TEST VALUE SCORE %
100.00 % ' TOTALS FINAL GRADE All work done on this examination is my ow I.have neither_given nor received ai :
Candidate's Signature
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l REACTOR OPERATOR Page 2-ANSWER SHEET-Multiple Choice- (Circle or X your choice) l l
If:you change your answer, write your selection in the blan MULTIPLE CHOICE 023 a b c d 001 a b' c d 024 a .b c d-002 a b c d 025 a b c 41 003 a b c d 026 a b- c d
'004 a li c d 027 b c d 005 a b c d 028 a b c d ;
006 a b c d 029 a b c d
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007 a b c d 030 a b c d 008 a b c d 031 a .b 1: d 009 a b c d 032 La b c d 010 a b c d 033 a b .c d 011 . b c d 034 a b c d ;
012 a b c d 035 b c d-013 a b c d 036 a b c' d 014 a b c d 037 a b 'c d r 015 a b c d 038 a b c d
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016 a b c d 039 a b c d '
'017 a b c d 040 a b c d j 018 a c d 041 a b c d 019 a .b c d 042 a b c d 020 a b c d 043 a b c d 021 a b c d 044 a b c d
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022 a b c d 045 a b c d ,
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ANSWER SHEET
~ Multiple Choice (Circle or X your choice)
If~you change your answer, write your selection in the blan a b c -d 069 a b c d 047 a b c d 070 a b c d
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-048 a b c d 071 a b c d .j 049 a b c d 072 a b c d
050 -a b c d 073 a b c d ,
051 a b c d 074 a b c d
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052' a b c d 075 a b c d
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053 a b c d 076 a b c d ^
i 054 ~a b c d 077 a b c d ;
055 a b c d 078 a b c d 056 a b c d 079 a b c d 057 a b c d 080 a b c d 058 a b c d 081- a b c d 059 a b c d 082 a b c d
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060 a b c d 083 a b c d
061 a b c d 084 a b c d 062 a b c d 085 a' b c d 063 a b c d 086 a b - d /;
-064: a b c d 087 a b c d-065 .a .b c d 088 a b c d !
066 a b c d 089 a b -c d
. i 067 a b c d 090 a b c d -)
068 a c d 091 a b c d
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REACTOR OPERATOR- Page' 4:
ANSWER S'H.E E T-
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-Multiple r aoiye (Circle or X'your choice)._
If-you change your answe'r, write your selection in the' blan '092 a b c d ,
093 a b c d ,
094 a b .c d 095 a b c d
-096 a b c d 097 a b c d 098 a b c d
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-099 a b- c d 100 a b c d t
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(********** END OF EXAMINATION **********)
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Page 5 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 Ims y done after you complete the examinatio ,
3. Restroom trips are to be limited and only one applicant at a time may leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil ONLY to facilitate legible reproduction ,
5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet and each answer shee . Mark your answers on the answer sheet provide USE ONLY THE PAPER PROVIDED AND DO MOT WRITE ON THE BACK SIDE OF THE PAG . Before you turn in your examination, consecutively number each answer sheet,
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including any additional pages inserted when writing your answers on-the examination question pag . Use abbreviations only if they are commonly used in facility literatur Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
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9. The point value for each question is indicated in parentheses after the questio ;
10. Show all calculations, methods, or assumptions used to obtain an answer to any short answer question ,
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11. Partial credit may be given except on multiple choice questions. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
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12. Proportional grading will be applied. Any additional wrong information that is provided may count against yo For example, if a question is j worth one point and asks for four responses, each of which is worth 0.25.
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points, and you give five responses, each of your responses will be worth O.20 point If one of your five responses is incorrect, 0.20 will b >
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deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answer ,
13. If the intent of a question is unclear, ask questions of the examiner only.
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i Page 6 14. When turning in your examination, assemble the completed examination with l examination questions, examination aids and answer sheets. In addition, I turn in all scrap pape !
15. Ensure all information you wish to have evaluated ~as part of your answer is on your answer sheet. Scrap paper will be disposed of immediately following the examinatio .
16. To pass the examination, you must achieve a grade of 80% or greater.
17. There is a time limit of four (4) hours for completion of the examinatio ,
18. When you are done and have turned in your examination,- leave the examination area (EXAMINER WILL DEFINE THE AREA). If you are found in this area while the examination is still in progress, your license may be denied or revoke ,
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REACTOR OPERATOR Page 7
QUESTION: 001 (1.00)
The'following plant conditions exist: '
' Unit 2 has tripped from 100% power due to a loss of offsite powe . Emergency Diesel Generator 2K4A has failed to star . RCS pressure is 2230 psi i Two (2) CEAs have failed to fully insert into the cor , RWT level is 70%. The Boric Acid flow transmitter down stream of the Boric Acid Makeup ;
pumps has just been discovered to be plugge ;
' Reactor operators are performing Emergency Operating Procedure 2202.001, " Standard Post Trip Actions". ,
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WHICH ONE (1) of the following methods is available for emergency boration given the above conditions? HPSI pump 2P-89A through High Pressure Isjection valve Gravity feed from RWT through 2CV-4950-2 to the Charging pump 2P36 Normal Emergency Boration flowpath through 2CV-4916-2 to the Charging pump 2P36 Gravity feed through 2CV-4921-1 to the Charging pump.2P36 ;
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QUESTION: 002 (1.00)
WHICH of the following actions should be performed if the Thot input to the
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Reactor Regulating System (RRS) fails HIGH? , Commence boratio Take letdown control to MANUA Commence dilutio ,
l Take backup heaters to OF j i
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-QUESTION: 003' (1.00)
WHICH ONE (1) of the following inputs to CEDMCS is provided by the Plant -
Protection System? , AWP (Automatic Withdrawal Prohibit) CWP (CEA Withdrawal Prohibit) AMI (Automatic Motion Inhibit) LGS (Lower Group Stop)
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QUESTION: 004 (1.00) ,
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WHICH ONE . (1) of the = following would be lost if the : feeder breaker to 480V Bus-2B-7 tripped OPEN? ;
- ' Reactor Pressurizer Proportional Heater Hydrogen Recombiner #2M-554 "A" Service Water Pump 2P-4A i
' Motor Generator (MG) Set'
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REACTOR OPERATOR Page 9 l
QUESTION: 005 (1.00)
WHICH ONE (1) of the following describes the CEDMCS Withdrawal Prohibit (CWP) !
alarm function? '
Initiated by the CEA Position Indication System in response to a PRETRIP condition on DNBR and prohibits ALL movement of. regulating CEA Initiated by the Plant Protection System (PPS) in response to a PRETRIP condition on DNBR and prohibits ALL OUTWARD group movement of CEA Initiated by the CEA Position Indication' System of the Plant Computer in response to OUT OF SEQUENCE / OVERLAP condition and prohibits ALL OUTWARD movement of CEA Initiated by the Plant Protection System (PPS) in response to OUT OF-
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SEQUENCE / OVERLAP condition and prohibits ALL movement of CEA QUESTION: 006 (1.00)
WHICH ONE (1) of the following conditions is ind.icated by'the BLUE light associated with Reactor Coolant pump (RCP) controls being LIT? The oil lift pump is runnin Oil pressure is NORMAL, An RCP motor over current condition exist RCP speed is zero (0) rpm.
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QUESTION: 007 (1.00)
WHICH ONE (1) of the following conditions exists if the RED indicating light for the RCP 2P32D is NOT lit? (Assume the bulb has been verified as good). The 2P32D RCP trip circuit has lost continuity and the ONLY means of tripping the pump is to open the breaker locall The 2P32D RCP trip circuit has lost continuity and the local handswitch must be used to trip the pum The 2P32D RCP start circuit has lost continuity and the ONLY means of starting the pump is to close the breaker locall The 2P32D RCP start circuit has lost continuity and the. local handswitch must be used to start the pum ,
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- Page 11 QUESTION: 008 (1.00)
1The following plant conditions exist: Unit 2 is in COLD SHUTDOW . SDC is in service with a solid Reactor Coolant Syste . RCS pressure is 300 psi . RCS temperature is 190 degrees F. and stabl . Steam Generator "2E24A" pressure is 20 psi . Reactor Coolant pump "2P32A" was started at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> and secured at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> to repair an oil lea . Reactor Coolant pump "2P32B" has been running for one (1) hou . At 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br /> Maintenance personnel report that the_ repairs to -
Reactor Coolant pump "2P32A" are complet WHICH ONE (1) of the following actions, per 2103.006, " Reactor Coolant' Pump Operations", should be taken (at 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br />) following a request from maintenance personnel to start RCP "2P32A"? (2103.006, Attachment A is attached). The RCP can be started after RCS pressure is increased to MINIMUM required per 2103.006, Attachment The RCP can be started with the present conditions at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> following a 30 minute rest period for the motor, The RCP can be started immediately after establishing a bubble in the pressurizer.
l The RCP can be started after reducing Steam Generator temperature to
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less than RCS cold leg temperatur QUESTION: 009 (1.00)
WHICH ONE (1) of the following conditions will AUTOMATICALLY close Letdown Line Stop valve 2CV-4820-2? Safety Injection Actuation Signal, Regenerative HX outlet temp. is 380 degrees Containment Isolation Signa Loss of power from 2B61-L _ _ _ _ _ _ _ _ - _ _ _ _ .
JREACTOR OPERATOR Page 12 l-QUESTION: 010 (1.00)
l WHICH ONE . (1). of the following methods is used to control . Shutdown. Cooling System (SDC) . purification flow? Manual control of CVCS Backpressure Regulators.2CV-4810/481 , Manual control of CVCS Letdown Flow ' Control valves 2CV-4816/481 Automatic control of SDC Flow Control valve 2CV-509 ' Automatic control of SDC Temperature . Control valve 2CV-509 ,
QUESTION: 011 (1.00) ,
The:following plant conditions exist'. ' Unit 2 is in COLD SHUTDOWN, RCS pressure is 400 psi . T-hot is 190 degrees .i
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WHICH ONE (1) of the following Engineered Safety Features Actuation' System (ESFAS) trip inputs is AUTOMATICALLY enabled when RCS pressure increases t
436 psia? Low RWT level, i High/ Low Steam Generator leve Low Steam Generator pressure, HI LOG Powe I I 1
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QUESTION: 012 (1.00)
WHICH ONE (1) of the following is actuated by LOW Pressurizer pressure signal? Containment Spray System (CSS) Penetration Room Ventilation System (PRVS) Main Steam Isolation System (MSIS) Containment Cooling System (CCS)
QUESTION: 013 (1.00)
WHICH ONE (1) of the following is used to designate Category 1 (Post LOCA Qualified) instrumentation? Red dots Green dots Red nameplates , Green nameplates
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REACTOR OPERATOR Page 14 QUESTION: 014 (1.00) ;
WHICH ONE (1) of the following is the reason thirty (30) degrees F. is chosen as the setpoint for the Margin To Saturation (MTS) alarm?
a. To ensure net positive suction pressure (NPSH) is maintained for the reactor coolant pumps (RCPs).
b. To ensure that RCS voiding is prevente c. To ensure that actual subcooling margin is maintained due to instrument errors, d. To ensure that actual subcooling margin is maintained when the RCPs are stoppe QUESTION: 015 (1.00)
WHICH ONE (1) of the following systems provides cooling to the Containment Cooling System following a design basis Loss Of Coolant Accident (LOCA)?
a. Chilled Water b. Component Cooling Water c. Service Water d. Auxiliary Cooling Water ,
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. REACTOR' OPERATOR Page.15-QUESTION: 016 (1.00)
WHICH ONE (1) of the following conditions will prevent starting Heater Drain Pump 2P8A at 40% reactor power? A Main Feed Pump running and 2CV0742 ope A Main Feed Pump running and 2CV0742 close B Main Feed Pump running and 2CV0742 ope B Main Feed Pump running and 2CV0742 close ,..
i QUESTION: 017 (1.00)
WHICH ONE (1) of the following conditions will AUTOMATICALLY close Feedwater to Steam Generator Isolation valve 2CV-1024-1? , LOW level in Steam Generator "A" HIGH level in Steam Generator "A" MSIS CIAS
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REA'CTOR OPERATOR Page 16 QUESTION: 018 (1.00)
The following condition exists: Unit 2 is at 5% powe . EFAS has actuate . EFW pump suction is aligned to the Startup and Blowdown Demineralizer effluen . Suction pressure for the Er.ergency Feedwater (EFW) pumps is.10 psig and DECREASIN WHICH ONE (1) of the following automatic actions will occur'if EFW pump suction pressure continues to DECREASE to 5 psig? CV-0789-1 and 2CV-0795-2 will automatically OPEN to supply water from the Condensate Storage Tan CV-0716-1 and 2CV .;-11-2 will automatically OPEN supply water from the Service Water Syste EFW-0706 will automatically OPEN to supply water from the Condensate Storage Tan EFW-16, Condensate Storage Tank Suction Bypass valve, will automatically OPEN to supply additional water from the Condensate-Storage Tan !
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' QUESTION: 019 (1.00)
The following conditions exist:
Steam Generator "A" Steam Generator "B" Level 25% & decreasing 20% & increasing Steam Pressure 725 psig 825 psig - Feedwater Pressure 1200 psig 1200 psig ;
WHICH ONE (1) of the following is the current status of the Emergency Feedwater System (EFS) given the above plant conditions? Assume all' plant ,
systems respond as designe >
- EFAS has not occurred but will AUTOMATICALLY actuate when Steam I Generator "A" level decreases to 23%. An EFAS trip condition exists and EFW is being supplied to BOTH steam generator An EFAS trip condition exists and EFW is being supplied to ONLY Steam Generator "B". 'r An EFAS trip condition exists and EFW is BLOCKED to BOTH steam generator I
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The following conditions exist: Unit 2 is in HOT STANDB . EFW is in MANUAL contro . EFW control valves 2CV-1025-1 and 2CV-1075-1 are throttled to BOTH Steam Generator . Simultaneous EFAS A#1 and MSIS #1 actuation signals are received'due to an I & C technician erro WHICH' ONE -(1) of the following is the affect of this error on EFW control valve 2CV-1025-1 and 2CV-1075-1 operation? Valves remain throttled because they are in MANUAL contro Valves remain throttled because EFAS A#1 and MSIS #1 have NO affect on these valve Valves go FULL open due to the EFAS A#1 signa Valves go FULL closed due to the MSIS #1 signa QUESTION: 021 (1.00)
WHICH ONE (1) of the following conditions.will result in AUTOMATICALLY closing:
Regenerative. Waste Discharge valve'2CV-4424 (2T-92 discharge to flume) ? Tank inlet valve ope Discharge line pH reading of Low instrument air pressure of 50 psi Waste Inlet Radiation Monitor 2RE-4447 HIGH alarm tri ... . . . . .. ., - - .-. .
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LREACTOR OPERATOR Page 19 QUESTION: 022 (1.00)
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WHICH~ONE (1) of the following discharges to the Drain Collection Header-(DCH)? Blowdown tank drain HPSI relief valve l LPSI relief valve t Containment sump drain .
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QUESTION: 023 (1.00)
WHICH ONE (1) of the following sets of Waste Gas Tank parameters.is acceptable? (2104.010, " Unit 2 Waste Gas Analyzer Operation", Attachment 1"A" 1 is attached.)
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pressure Hydrogen: Oxygen , .psig 401 12% psi % 5% psig 60% 3% , psig 6% 10%
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QUESTION: 024 (1.00)
WHICH ONE (1) of the following is the cause for an AREA Radiation Monitor to emit a LOW beeping sound? ' Monitor is placed in tes Monitor has failed LO , A valid HI radiation alar Battery backup is discharge i
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QUESTION: 025 (1.00)
WHICH ONE (1) of the following RCP discharge piping locations provide penetrations for normal pressurizer spray? RCPs 2P32A and 2P32 RCPs 2P32A and 2P32B, RCPs 2P32C and 2P32 ; RCPs 2P32B and 2P32 !
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WHICH ONE (1) of the following inputs is provided by Loop 2 hot leg temperature instrumentation? ESFAS bypass permissive for steam generator high/ low water level :
trip signals AWP (Automatic Withdrawal Prohibit) in CEDMCS LTOP isolation valve misalignment annunciation when valves'are OPEN-with temperature less than 240 degrees q Steam Dump and Bypass Control System Modulating Opening Signa :
F QUESTION: 027 (1.00)
To WHICH ONE (1) of the following locations are the Safety Injection Tanks
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(SIT) vented when lowering pressure in Mode 3? Containment atmosphere Reactor Drain Tank Quench Tank
' Holdup Tank l
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REACTOR OPERATOR- Page 22 l
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l QUESTION: 028 (1.00)
The following conditions exist:
l Unit 2 has tripped due to a small break loss of coolant accident l (LOCA). ; The event is ongoing and the Recirculation Actuation System (RAS)- ;
has initiate '
, .RCS pressure has increased to 1500 psi , BOTH High Head Safety Injection (HPSI) pumps continue to operate at full capacit .
WHICH ONE (1) of the following provides cooling for the HPSI_ pumps? Flow through the pumps to the RCS is sufficient to cool the pumps l under these condition Mini-Recirc flow to the RWT is sufficient to cool-the pumps under'
these condition i;
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t Mini-Mini-Recirc flow to the pump suction is sufficient to cool the i pumps for up to thirty eight (38) minutes, i Mini-Recirc flow to the containment sump is sufficient to cool the i pumps for up to thirty eight (38) minute !
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I REACTOR OPERATOR Page 23 !
QUESTION: 029 (1.00)
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The following conditions exist: Unit 2 is in COLD SHUTDOW . SDC is in servic WHICH ONE (1) of the following is the TOTAL affect of Pressurizer Pressure
. Channel-1 (2PI4823-1) failing to 500 psia?
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' SDC isolation valve 2CV-5084-1 close SDC isolation valve 2CV-5084-1 closes 100) SIT isolation valves .!
2CV-5003-1 / 2CV-5023-1 ope .l SDC isolation valve 2CV-5086-2 close SDC isolation valves 2CV-5086-2 closes AND'EIT isolation valves j 2CV-5043-2 / 2CV-5063-2 ope ;
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i REACTOR OPERATOR Page 24
'l QUESTION: 030 (1.00)
l The following plant conditions exist:
] RCS pressure is 2250 psi . Pressurizer Pressure Control System (PPCS) setpoint is 2250 psi . RCS boron concentration is 500 ppm boro . Pressurizer boron concentration is 350 ppm boro WHICH ONE (1) of the following is the correct method to equalize RCS boron concentration per 2103.005, " Pressurizer Operation"? ENERGIZE all Pressurizer Backup Heaters and place "A" RCP spray valve in MANUAL and OPEN to maintain RCS pressure within + 10 psia of desired setpoin ~
b. ENERGIZE all Pressui .er Proportional Heaters and place "A" RCP
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spray valve in MANUAL and OPEN to maintain RCS pressure within + 10 psia of desired setpoin C. RAISE Pressurizer Pressure Control System'setpoint to 2300 psia.AND energize Pressurizer Proportional Heaters to maintain Pressurizer Spray flo ,
d. DECREASE Pressurizer Pressure Control System setpoint to 2220 psia AND energize Pressurizer Backup Heaters to maintain Pressurizer Spray flo QUESTION: 031 (1.00)
Pressurizer level indication on the Remote Shutdown Panel may differ from that of Level Channel 1 as indicated on Panel 2C04. This is because-the Remote Shutdown Panel receives its signal from ?
a. Level Channel 2 and is NOT temperature compensate b. Level Channel 2 and is temperature compensate c. SPDS which is temperature compensate d. SPDS which is NOT temperature compensate r n y y y e e m.+- n , . , - - -
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REACTOR OPERATOR Page 25-l QUESTION: 032 (1.00) ;
WHICH ONE (1) of the following signals is used DIRECTLY to generate the-pressurizer level control setpoint? T-cold T-ho , Tref Tavg i
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QUESTION: 033 (1.00)
WHICH ONE (1) of the following would result from depressing ONE (1)- Manual Reactor Trip pushbutton on panel 2CO3? > TCBs 2 and 6 open and the reactor trip : TCBs 2 and 6 open but the reactor does NOT tri TCBs 2 and'3 open and the reactor trip TCBs 2 and 3 open but the reactor does NOT tri >
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REACTOR. OPERATO Page 26
. QUESTION: 034 - (1.00)
The following plant conditions exist: Unit 2 is at 100% powe . RCS pressure is 2405 psi . The Reactor Protection System (RPS) has NOT actuate . . All Reactor Protection System setpoints have been calibrated to >
plant design specification WHICH ONE (1) of the following results-from RCS pressure INCREASING to 2450 psia? Assume no additional failures occu The HIGH Pressurizer pressure setpoint of the RPS is reached'and Reactor Trip Breakers will OPEN to DE-ENERGIZE the control element ,
assembly (CEA) holding coils, The HIGH Pressurizer pressure setpoint of the Diverse Scram System :
(DSS) is reached DE-ENERGIZING the trip coil to open a contact' '
interrupting output power from both Motor Generator (M3) set The HIGH Pressurizer pressure setpoint of the RPS is reached and the MG set 480 VAC output breakers will OPEN to DE-ENERGIZE the control element assembly (CEA) holding coil The HIGH Pressurizer pressure setpoint of the Diverse Scram System (DSS) is reached ENERGIZING the trip coil to open a contact ,
interrupting output power'from both Motor Generator (M3) sets, t:
QUESTION: 035 (1.00)
WHICH ONE (1) of the following CEA position alarms is generated by Reed Switch Position Transmitters? CEA GROUP OUT OF SEQUENCE DROPPED CEA LOWER GROUP STOP CEA POWER DEPENDENT INSERTION i
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REACTOR OPERATOR- Page.27 J
- QUESTION
- 036 .( 1. 0 0 )
'WHICH ONE (1) of the following is the reason for a FLASHING indication on the '
Saturation' Margin Monitor (SMM) ? I Indicated value is below the saturation margin alarm setpoin Indicated value is below 30 degrees F' saturation margi Indicated value is erroneou j Indicated value is superheate ;
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.i QUESTION: 037 (1.00)
i WHICH ONE (1) of the following will result in the loss of Containment Spray- ;
Pump'2P-35A? l Loss of 6900 VAC Buses 2H q Loss of 6900 VAC Buses 2H ;
e Loss of 4160 VAC Buses 2A Loss of 4160 VAC Buses 2A i
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. QUESTION: 038 (1.00) !
WHICH ONE (1) of the following is the MINIMUM condition that will INITIATE j actuation of the Containment Spray System? '
! CIAS actuation, CIAS and SIAS actuatio !
' Containment pressure at 24.0 psia and:CIAS actuatio I ' Containment pressure at 24.0 psia and SIAS actuatio ;
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. REACTOR OPERATOR -Page 38 QUESTION: 039 (1.00) ;
WHICH.ONE (1) of the following AUTOMATIC actions take place-following a trip ~
of the Containment Purge Exhaust fan to prevent overpressurization of the containment?
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- Exhaust dampers go'100% open to relieve pressur Supply dampers throttle to control pressur i Supply' fan trips after a ten'(10) second time dela ,
' Purge isolation valve 2CV-8284 close !
QUESTION: 040 (1.00)
The following conditions exist: Unit 2 has tripped from 100% power one (1) minute ag . Steam Generator "A" level is 95%. Steam Generator "B" level is 40%.
. High Level Override Level Selector switch is selected to the BOTH '
positio WHICH ONE (1) of the following is the expected status of-the Feedwater Control-System (FWCS)? (Assume NO operator action.)
~ Feedwater is isolated to Steam Generator "A" and at 5% flow demand ,
to-Steam Generator "B". Feedwater is isolated to BOTH Steam Generators "A" and "B". ! Feedwater is at 5% flow demand to BOTH. Steam Generators "A" and "B". l
, Feedwater is at 5% flow demand to Steam Generator "A" and at' 100%
flow demand to "B" Steam Generato !
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QUESTION: 041. '(1.00)
The following conditions exist: Unit 2 is operating at 100% powe . Steam Generator Level selector switch is selected to BOT WHICH ONE (1) of the following will cause the "B" Steam Generator Flow Demand -
Signal to DECREASE? "B" Steam Generator Level transmitter fails HIG "B" Steam Generator Steam Flow transmitter fails HIG "B" Steam Generator Feedwater Flow transmitter fails LO "B" Steam Generator Pressure transmitter fails LO >
QUESTION: 042 (1.00)
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The following conditions exist: Unit 2 is operating at 100% powe . Operators are performing the "MSIV Quarterly Partial Stroke Test". .
WHICH ONE (1) of the following will result from holding the EXERCISE switch in the CLOSE position'for one (1) minute? The valve will stroke closed until the GREEN closed light is illuminated, then re-open automatically, The valve will stroke closed until it is 10% closed, then re-open automaticall The valve will stroke closed until it is 10% closed,' then remain'in l that position until re-opened manuall , The valve will continue to stroke closed until the EXERCISE switch is placed in the OPEN positio ,
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i QUESTION: 043 (1.00)
WHICH ONE (1) of the following is NOT an AUTOMATIC action which results from a' ,
HIGH alarm trip of Unit 2 Control Room Ventilation Radiation Monitor 2RE-8750-1? Unit 1 Control Room Isolation dampers clos L Unit 1 Supply fan VSF-8 stop , Control Room Emergency Supply fan 2VSF-9 start ' Control Room Recirculation dampers ope QUESTION: 044 (1.00)
The following conditions exist: !
- Unit 2 is in HOT SHUTDOW ! Operators are placing SDC in servic . SDC Heat Exchanger Cross-tie valves 2SI-5A and 2SI-5B are OPE . Containment Spray Header MOVs 2CV-5612-1/2CV-5613-2 are OPEN for testin WHICH ONE (1) of the following will occur when LPSI pump 2P60A is started? BOTH 2CV-5612-1 AND 2CV-5613-2 will close AUTOMATICALL CV-5612-1 will close AUTOMATICALLY but 2CV-5613-2 will remain ope LPSI Header Isolation valve 2SI-6 will close AUTOMATICALLY but 2SI-SB will remain ope SI-5A will close AUTOMATICALL ,
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REACTOR OPERATOR Page.31 ,
. QUESTION: 045 (1.00)
iWHICH ONE (1). of .the following is a possible source of inventory for the Quench' Tank? Reactor Drain Tank discharge SIT drain lines Service Water System makeup
' RCP Controlled Bleedoff
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QUESTION: 046 (1.00)
The'following conditions exist: Unit 2 has tripped due to a large steam break inside containmen . CSAS has been actuated for one (1) minut . Sodium Hydroxide pump 2P136A has NOT starte ,
WHICH ONE (1) of the following could be a reason the 2P136A pump:is NOT
. running? (Assume all systems are performing as designed.) The pump start time delay has not timed ou ,
b '. Sodium Hydroxide pump 2P136A discharge valve'is close ' Sodium Hydroxide tank outlet valve.is only 75% ope Sodium Hydroxide tank level is 50%. ,
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QUESTION: 047 (1.00)
Hydrogen Analyzers must be placed in service within fifteen (15) minutes following a Loss Of Coolant Accident-(LOCA)? This is based on NUREG 1.97
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which requires a hydrogen sample within .?
~! thirty (30) minutes of a LOCA and it takes fifteen (15) minutes for the analyzers to warmu thirty (30) minutes of a LOCA and'it takes approximately 11 minutes-to transport the gas'to the analyzers, one (1) hour of a LOCA and it takes forty five (45) minutes-for the analyzers to warmu one (1) hour of a'LOCA and it takes thirty (30) minutes for the analyzers'to warmup and analyze a sample and approximately 11:
minutes to transports.ae gas to the analyzer QUESTION: 048 (1.00)
WHICH ONE (1) of the following conditions will PREVENT movement of the Refueling Machine? Spreader is NOT extended.
. Fuel assembly is in the full up positio Suspended ad is at setpoint,
, Fuel Hoist is operatin ,
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REACTOR OPERATOR Page 33
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QUESTION: 049 (1.00)
WHICH ONE (1) of the following Steam Bypass Control System signals /permissives is INOPERABLE should steam line pressure transmitter 2PT-0301 fail LOW? Quick Opening Block signal Automatic Modulation permissive Automatic Motion Inhibit signal Quick opening permissive
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QUESTION: 050 (1.00) is WHICH ONE (1) of the following conditions renders the Service Water System INOPERABLE per Technical Specification 3.7.3, " Service Water System"? The' Red ESF bus supplies power to both Service Water pump 2P4B and the Auxiliary Cooling Water System (ACW) . Service Water pump discharge filter delta pressure is 11 psi The Green ESF bus supplies power to both the Service Water pump 2P4B and the 2P4B sluice gat Service Water pump suction pressure is 11 psi f
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A major Turbine Building Instrument Air header rupture has occurred on Unit ,
WHICH ONE (1) of the following is expected to provide Instrument Air to Unit 2
,from Unit I?
a. Unit 1 Crosstie valve 2SV-3015 AUTOMATICALLY open b. Unit 1 Crosstie valve 2CV-3004 AUTOMATICALLY close [
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c. MANUALLY open IA TO UNIT 1 CROSS CONNECT. valve IA-5 d. MANUALLY open Unit 1 to Unit 2 Crosstie valves 2CV-3015 and 2CV- ,
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QUESTION: 052 (1.00)
The following Reactor Coolant Pump conditions exist:
"A" RCP "B" RCP 1. RCP Vapor Seal Pressure 1600 psia 1250 psia 2. Pump Shaft Vibration 12 mils 14 mils
3. Pump Frame Vibratica 2 mils 1 mil 4. RCP Controlled Bleedoff 1 gpm 4 gpm WHICH ONE (1) of the following actions is required per 2203.025, "RCP Emergencies"? ASSUNE the reactor has been trippe ,
a. Secure "A" RCP due to HIGH RCP Vapor. Seal Pressur b. Secure'"B" RCP due to HIGH Pump' Shaft Vibratio c. Secure "A" RCP due to HIGH Pump Frame Vibratio d. Secure "B" RCP due to HIGH Controlled Bleedoff flo .
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QUESTION: 053 (1.00)
WHICH ONE (1) of the following is the MAXIMUM time allowed for operation'of a Unit 2 Reactor Coolant pump following loss of_ Component Cooling Water while in POWER OPERATION per 2203.025, "RCP Emergencies"? minute [ minutes minutes minutes QUESTION: 054 (1.00)
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The following conditions exist: Unit 2 is at 100% powe . Total Component Cooling Water flow is 250 gpm to RCP 2P32 . RCP 2P32A upper seal cavity pressure is 1125 psi . RCP 2P32A middle seal cavity pressure is 1125 psi . Pressurizer pressure is 2250 psi WHICH ONE (1) of the following describes the condition of RCP 2P32A?
' Low Component Cooling Water (CCW) flow exist ' Upper seal failure has occurre ' Middle seal failure has occurre Lower seal failure has occurre i t
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REACTOR OPERATOR Page 36 QUESTION: 055 (1.00)
The following conditions exist: Unit 2 has tripped from 100% power and reactor power is DECREASIN . Emergency Boration was initiated at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> when CEAs #40 and #41 failed to fully inser .
' A Pressurizer level control malfunction has resulted in a Pressurizer level of 95% and INCREASIN . Tavg is 565 degrees F. and DECREASING slowl . Pressurizer pressure is 2400 psia and INCREASIN . Operators are SLOWLY inserting CEA #40 manually and it will be fully 1 inserted at 0815 hour0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> . CEA #41 remains fully withdrawn and immovabl . Operators desire to terminate RCS makeup to prevent RCS overpressurizatio WHICH ONE (1) of the following conditions will allow termination of-RCS makeup? CEA #40 is fully inserte Thirty (30) minutes of Emergency Boration has been complete Pressurizer level reaches 100%. Pressurizer pressure reaches 2450 psi ,
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REACTOR. OPERATOR 'Page 37 QUESTION: 056 (1.00)
The following conditions exist:
, P33A is is in PTL for maintenanc . 2P33B is supplying loop I CC . 2P33C is supplying loop II CC '
' A rupture occurs in loop II CCW, causing pressure to. decrease to less than 80 psi WHICH ONE (1) of the following AUTOMATIC actions will result from the above-conditions? CCW Loop I Crossover valves 2CV-5220 and 2CV-5230 clos CCW Loop II Crossover valves 2CV-5221 and 2CV-5232 close, CCW Loop II Crossover valves 2CV-5221 and 2Cp-5232 ope i An IMMEDIATE reactor trip on loss of CCW flow to the Reactor. Coolant-pumps.
QUESTION: 057 (1.00)
The following conditions exist: Unit 2 is at 100% powe . Pressurizer spray valve 2CV-4651 has' failed to close on deman . Operators are taking actions per 2203.028, "PZR Systems Malfunctions", Step ,
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WHICH ONE (1) of the following is the reason the. control switch for 2CV-4651 is placed to OPEN for one (1) second then to CLOSE.for five (5) seconds?. This action OVERRIDES the Master Controller and allows the valve to be closed MANUALL This action. activates the mechanical hammer' mechanism which> assists in seating.the valv i
! This action activates the QUICK CLOSE circuitry for the. valve.' This action opens additional CLOSE solenoids which provide greater i air pressure to seat the valv ,
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REACTOR OPERATOR Page 38'
-QUESTION: 058 (1.00)
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The following conditions exist:
1. Unit 2 has tripped from an Excess Steam Demand Accident (ESD).
2. Operators have gone to 2202.005, " Excess Steam Demand". .
WHICH ONE (1) of the following is the reason for tripping one (1) RCP if RCS Tcold is less than 510 degrees F?
a. To decrease heat removal from tre affected loo b. To prevent core uplift with four (4) pumps runnin c. To decrease affect from pressurized thermal shock (PTS).
d. To prevent Steam Generator tube stres s
,t QUESTION: 059 (1.00)
The following conditions exist:
1. A steam line break exists upstream of the "A" Steam Generator MSIV on Unit . MSIS has automatically initiate WHICH ONE (1) of the following conditions could result if a steaming flowpath from the unaffected steam generator is NOT established immediately following dryout of the affected steam generator?
a. Rapid repressurization of the RCS and subsequent Pressurized Thermal Shock (PTS) conditions, b. Inability to open "B" S/G MSIV due to pressure difference created when affected steam generator reaches dryout. condition i c. A rapid INCREASE in T-cold of the UNAFFECTED loop resulting in an interruption of natural circulatio d. A INCREASE in.the core exit ~ temperatures resulting in an interruption of natural' circulatio . . . . _ - _ -- . .. . . .
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. QUESTION: 060 (1.00)
WHICH ONE (1) of the following discriminates between a steam line break inside-containment and a small break LOCA? Containment pressure RCS pressure . Containment temperature ! RCS temperature
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QUESTION: 061 (1.00) -
The following conditions exist: . Turbine roll is in progres . 1800 rpm is selecte . Turbine speed is 1700 rpm and increasing rapidl WHICH ONE (1) of the following actions should be performed? ; Select'800 rpm on the speed set-rpm selecto Select Close Valves on the speed set-rpm selector, i i Break vacuum and verify turbine is trippe l Trip the reactor and verify the turbine is trippe ,
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REACTOR OPERATOR Page 40
. QUESTION: 062 (1.00)
WHICH ONE (1) . of the following is an indication that natural circulation exists following a. loss of electrical power? (All temperatures are degrees F.)
RCS Subcooling Thot Tcold CETs .
QUESTION: 063 (1.00)
P-The following conditions exist: Unit 2 has tripped from 100% power due to.a Loss of Offsite powe . Diesel generators are running with NO Service Water (SW) coolin q
- WHICH ONE (1) of the following is the MAXIMUM time period that the diesels can run with NO.SW cooling WITHOUT suffering. damage? ' Three (3) minutes Ten (10) minutes Fifteen (15) minutes Diesels can run indefinitely since they. provide theirLown cooling; I flo i
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REACTOR OPERATOR Page 41
QUESTION: 064 (1.00)
The following conditions exist: The control room operator has received a report of a small-fire in the 317' elevation of the Auxiliary Building. , The individual reports the fire is contained in the corner of the 2T20B room where oily rags have been stored incorrectl . The same individual reports there is no smoke, the area is well ventilated, and he has an ABC Dry Chemical Extinguishe . The individual has requested permission to extinguish the fir WHICH ONE (1) of the following conditions prevent this authorization? The fire is caused by a hazardous chemica The potential for smoke exists and the individual has no respiratory equipmen The extinguisher is incorrect for this type of fir The fire is in a radiological control area (RCA).
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f QUESTION: 065 (1.00)
WHICH ONE (1) of the following is an indication that is required by Technical Specifications to be displayed at the Remote Shutdown Panel (2C80) ?
a. Reactor Trip Breaker Indication b. Steam Generator Pressure c. RCS Subcooled/Superheat Monitor d. Refueling Water Tank Level
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' QUESTION: 066 (1.00) ,
WHICH ONE (1) of the following operator actions is required during an evacuation of the Unit 2 control room due to a fire in the cable spreading room per 2203.014,_ " Alternate Shutdown"? l
' Trip two (2) Reactor Coolant pumps (one in each loop) and leave two (2) running, Trip ALL four (4) Reactor Coolant pump l Trip the "B" Loop Reactor Coolant pump , Leave ALL Reactor Coolant pumps running if seal water can be established within five (5) minute l
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i QUESTION: 067 (1.00)
The following conditions exist: Unit 2 has tripped due to a loss of Feedwate . Operators have entered Functional Recovery Guideline WHICH ONE (1) of the following is the criteria for going to HR-4, "Once Through Cooling" to provide core cooling? RCS Thot is increasing uncontrollabl ; RCS pressure is increasing uncontrollably, BOTH Steam Generator levels decrease to less than 70 inche '
, RVLMS LVL 03 indicates voidin ;
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i REACTOR OPERATOR Page 43 QUESTION: 068 (1.00)
The following conditions exist: Unit 2 is at 30% power and increasing at 3% per hou . CEAs are in MANUAL SEQUENTIA . GROUP 5 CEAs were withdrawn from 50 to 60 inche . At 60 inches Group 5 CEAs continued stepping ou ,
WHICH ONE (1) of the following actions are required to be performed FIRST per 2203.003, "CEA Malfunction"? Initiate' emergency boration per 2203.032, " Emergency Boration". Attempt to stop CEA movement by placing MODE SELECTOR switch.to th OFF positio TRIP the reactor and %; "to 2202.001, "
Standard Post Trip Actions". De-Energize both MG sets by opening breakers 2B712 and 2B81 ,
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QUESTION: 069 (1.00)
-The following plant conditions exist:
Mode 3, Trip from 100% power occurred 5 minutes ag ~ . CEAs #40 and #41 are fully withdraw . Charging pump suction piping has rupture WHICH ONE (1) of the following operator actions should be performed under *
these conditions? Use auxiliary spray and emergency borat Emergency borate via HPSI by opening 2CVC-11 Lower RCS temperature and commence a normal boration, Lower RCS pressure and emergency borate via HPS ,
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' QUESTION: 070 (1.00) '
-The'following conditions exist:
4 Unit 2 tripped from 100% powe . 2202.001, " Standard Post Trip Actions", has been entere l The Main Turbine did NOT trip as expecte WHICH ONE (1) of the following actions should be immediately performed per 2202.001, " Standard Post Trip Actions", to trip /stop the turbine? Manually close MSIV ,
' Manually-open Generator output breaker Manually trip the generator exciter field breaker,
' Locally trip the Turbine from the front standar r
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QUESTION: 071 (1.00)
Considering Procedure 2202.009, " Functional Recovery Procedure", WHICH ONE (1)
of the following Safety Functions has the HIGHEST order.of priority?- RCS Inventory Vital Auxiliaries i Core Heat Removal , Containment Integrity '
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QUESTION: 072 (1.00) !
I The following plant conditions exist: Unit 2 has tripped from 100% powe . SIAS has actuate . RCS pressure is 1300 psia and DECREASING slowl . Pressurizer level is 100 . RCS Thot (Th) is 557 degrees l
' Containment pressure is 16 psia and INCREASING slowl WHICH ONE (1) of the following events has occurred? Main Steam line break inside Containment ;
' Inadvertent SIAS RCS cold leg break
- Pressurizer vapor space break ,
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QUESTION: 073 (1.00) !
WHICH ONE (1) of the following parameters is used to determine if adequate !
core cooling exists following a small break loss of coolant accident (SBLOCA) '
.per 2202.003, " Loss Of Coolant Accident, Safety Function Status Check"? ; RCS Thot and average CET temperatures are less than superheate ! Loop delta T is less than ten (10) degrees l 1 CET temperatures less than 1000 degrees d .. RCS Tcold is less than ten (10) degrees F. superheate ~!
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REACTOR OPERATOR Page 46
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QUESTION: 074 (1.00) -l l
The following conditions exist: i i
1. A large break LOCA condition exist ! RCS pressure is 140 psia, j CETs indicate 267 degrees l LPSI pump 2P-60A is injecting into the RC i HPSI pumps 2P-89A and 2P-89B are injecting into the RC I WHICH ONE (1) of the following indicates the lowest acceptable total Emergency Core Cooling System flow per 2202.010, " Standard Attachments"? (References ',
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attached.) gp ! gpm gpm gpm
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QUESTION: 075 (1.00) ;
The following conditions exist after a Unit 2 reactor trip from 100% power: .
- Pressurizer pressure is 450 psia and DECREASIN [ Pressurizer level is O . CETs indicate 370 degrees . All ESFAS Actuations required have actuate WHICH ONE (1) of the following is the MINIMUM operator action for the above conditions per 2202 001, " Standard Post Trip Actions"? (References are provided.)
' Trip RCPs 2P32A and 2P32 Trip RCPs 2P32C and 2P32 : Trip RCPs 2P32A and 2P32C ;
' Trip ALL RCP l l
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QUESTION: 076 (1.00) I WHICH ONE (1) _of the following is the MINIMUM condition that defines a " Harsh" '
containment? Containment temperature is 200 degrees Containment temperature is 150 degrees F. and pressure is greater .;
than 8.5 psi Containment humidity is saturate Containment humidity is saturated and Containment radiation. levels indicate 1 X 10E3 R/h i
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QUESTION: 077 (1.00)
WHICH ONE (1) of the following temperature indications is preferred.for monitoring RCS temperature following a loss of Shutdown Cooling flow? LPSI pump discharge monitor (T5096) >
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REACTOR OPERATOR Page 48
QUESTION: 078 -(1.00)
WHICH ONE (1) of the following-is the reason MG set supply breakers 2B712 and 2B812 are opened for a minimum of ten (10)_ seconds before re-closing when responding to an Anticipated Transient Without Scram (.ATWS) ? To assure all CEAs have sufficient time to fall into the cor l
' To allow sufficient time for the TCBs to ope To allow sufficient time for the MG sets to coast down and overcome the flywheel devic To prevent overcurrent trips when breakers are re-close ,
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QUESTION: 079 (1.00) .
The following plant conditions exist:
- Unit 2 is in REFUELIN . Start-up channel "A" is out of servic l Start-up channel "B" is OPERABL ' Core alterations.are in progres WHICH ONE (1) of the following MINIMUM Technical' Specification Action Statements should be implemented? Suspend all operations involving positive reactivity change Determine the RCS boron concentration at least every twelve (12) )
hour Immediately evacuate containment until the audible alarm from ,
Channel "A" is returned to servic ,
Perform CHANNEL FUNCTIONAL TEST on Channel
- "B" within one (1) hou i
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REACTOR OPERATOR Page 49 LQUESTION: 080 (1. 0 0 )-
The following conditions exist: Unit 2 has reduced power to 15% due to a Steam Generator tube lea . Letdown has been isolate . One (1) charging pump is runnin . Pressurizer level is DECREASING slowl WHICH ONE (1) of the following is a valid method to determine the amount of primary to secondary leakage? Use Charging flow and Letdown flow mismatc Use SG Tube Leak N-16 monitor Use Charging flow minus Controlled Bleedoff flo f Use Main Steam Line Radiation monitor '
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QUESTION: 081 (1.00)
The following conditions exist: Unit 2 has tripped from 100% power due to a Steam Generator tube rupture on the "B" Steam Generato . Operators have throttled HPSI flow to assist in recovery operation . RCS pressure is 1800 psi WHICH ONE (1) of the following conditions will require operators to restore FULL HPSI flow? Margin to saturation is 40 degrees Pressurizer level is 25%.
, RVLMS sensor four (LVL 03) indicates WE Steam Generator "A" level is 5% and increasing with EFW flow of 500-
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REACTOR OPERATOR Page 50 QUESTION: 082 (1.00)
The following conditions exist:
' Unit 2 has been manually tripped due to a loss of ALL Feedwate . Operators are initiating step 3 of 2202.006, " Loss.of Feedwater" and >
.are tripping ALL RCP WHICH ONE (1) of the following is the basis for tripping all Reactor Coolant j
'
Pumps as per this step in the procedure?
i To reduce heat input into the reactor coolant syste l To reduce Reactor Coolant System pressur To reduce thermal stress to steam generator To reduce tube to shell delta pressure in the steam generators.
QUESTION: 083 (1.00)
WHICH ONE (1) of the following is the MAXIMUM time'that-the Vital 125 VDC
' batteries 2D-11 and 2D-12 can be expected to carry the vital loads following a loss of the battery chargers? hours ,
i hours hours hours i
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.. . ... . . . .
.
..
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l REACTOR OPERATOR Page 51 QUESTION: 084 (1.00)
-The following conditions exist: Unit 2 is at 100% powe . Pressurizer level control is selected to Channel "A". Proportional Heater Bank handswitch is in AUTOMATI WHICH ONE (1) of the following is the affect of a loss of power supply 2Y1 on the Pressurizer Level Control System? Channel "B" instruments FAI . Proportional and Backup Pressurizer heaters are ENERGIZE Proportional and Backup Pressurizer heaters are DE-ENERGIZE Pressurizer level in; cation at the Remote Shutdown Panel is LOS ^ QUESTION: 085 (1.00)
WHICH ONE (1) of the following is the MINIMUM level required in the Steam Generators in order to sustain Natural Circulation Cooling (NC) ? inches inches inches inches
_--_____ _-_______ - _- - _
- REACTOR OPERATOR Page 52
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QUESTION: 086 (1.00)
- WHICH ONE (1) of the following valves will fail CLOSED on a loss of Instrument-Air pressure? CV-0634, Hotwell Makeup valve CV-1051, Steam Generator "B" Upstream Dump valve CV-0740, FW Loop "B" Main Reg valve- CV-5091, SDC HX Flow Control valve i
.-
-
QUESTION: 087 (1.00)
-!
The following conditions exist: i An operator has been assigned to operate the Refueling Machine from 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on Monday, 12-06-199 . Dose rate for the area is 25 mR/ hou . The operator's exposure for the previous seven days is as follows:
- Monday, 11-29-1993........... 25 mR
- Tuesday, 11-30-1993.......... 30 mR
- Wednesday, 12-01-1993........ 50 mR
- Thursday, 12-02-1993.......... 0 mR ,
- Friday, 12-03-1993........... 25 mR WHICH ONE (1) of the following is the expected accumulated WEEKLY dose for th operator following his present work assignment? mR mR
- mR i mR
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. REACTOR OPERATOR Page 53 QUESTION: 088 (1.00)
WHICH ONE (1) of the following is the MINIMUM frequency for, reading-your:Self ,
Reading Dosimeter' (SRD) while working in a HIGH RADIATION Area? Every sixty (60) minutes Every thirty (30) minutes Every twenty (20) minutes
. Every ten (10) minutes
'
QUESTION: 009 (1.00)
'
WHICH ONE (1) of the following boundaries is challenged the most by.a' chloride excursion in the RCS?
- ' Fuel cladding RCS' letdown piping RCS cold leg piping
' Containment liner
,
S
$
, . . . . - . . . .. - . - .-. .
. - _- . . .._
,
REACTOR OPERATOR 'Page 54 QUESTION: 090 (1.00)
The following conditions exist: Unit 2 is at 100% powe . An operator is conducting his routine rounds when he discovers a fire door OPEN with scaffolding blocking closur ' NO fire watch is presen WHICH ONE (1) of the following MINIMUM actions must the operator perform due-to these conditions? , Return to his duty station and fill out a Condition Repor , Report the condition to the Superintendent, Shift Operations.and remain in the area as a fire watch until receiving further instruction Perform hourly firewatch patrols until a continuous fire watch is .
poste I Notify Maintenance Supervisor to remove the scaffolding and remain in the area as a fire watch until the door is close QUESTION: 091 (1.00) ;
WHICH ONE (1) of the following is an IMPROPER handling of a HIGH pressure gas cylinder? A thirty five (35) pound oxygen cylinder is moved by rolling it on it's bottom edge.
, An acetylene cylinder is transported in an OPEN vehicl Grease is applied to a sticky valve on an oxygen. cylinde An acetylene cylinder is used in a radiological are ,
I
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. - . . . -
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. REACTOR OPERATOR: Page 55
' QUESTION: 092 (1.00) i WHICH ONE (1) of the following represents a NON-INTENT Change in a' procedure? ' A change in initial condition A modification to setpoints, s Deleting a hold poin Correction to step sequenc ,
QUESTION: 093 (1.00)
WHICH ONE (1) of the following controls is placed on keys to the Reactor Building? Controlled by the Superintendent, Shift Operation Controlled by the Supervisor, Health Physic Controlled by the Manager, Health Physic ' Controlled by the Plant Manage ;
i N
I k
f i
,
a v --e o e = e-- w w
_ _ _ _ . . _ _ _ . _ . . - - . ._ . . _ . . -
REACTOR OPERATOR Page 56 i j
QUESTION: 094 (1.00) I l
The-following conditions exist:
I A crew is preparing to conduct MOV testin . They find a HOLD CARD tagging the breaker OPEN for-the valve they are to tes WHICH ONE (1) of the following actions should be.taken next? Install the MOV TEST CARD over the HOLD CARD and proceed with MOV '
testin ;
' Proceed with MOV testing under protection of the HOLD C1UU) and a MOV TEST card is not neede Install the MOV TEST CARD but contact the Shift Supervisor for further instructions, Contact the Shift Supervisor for authorization to remove the HOLD CARD prior to installing the MOV TEST CARD.
QUESTION: 095 (1.00)
WHICH ONE (1) of the following is the PREFERRED method of verifying the correct position of a THROTTLED valve?
. Close and re-open the valve the prescribed number of turn , Observe the original operator position the valv Open and re-close the valve the prescribed number of turn Observe control room position indication ligh .
t
-,,# - -
, __ -
n -
- .. - = - . . .. -
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REACT R OPERATOR Page 57 l l
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QUESTION: 096 (1.00) l
- WHICH ONE (1) of the following methods is used to identify an INACCESSIBLE valve? By placing a Hold Card on the valve breake By installing bright orange tywrap on the valv By painting the valve bright orang By installing a special placard on the_ valve breake l QUESTION
- 097 (1.00)
WHICH ONE (1) of the following is the MINIMUM frequency for reading your Self Reading Dosimeter (SRD) while working in a RADIATION Area? Every sixty (60) minutes Every thirty (30) minutes Every fifteen (15) minutes a Every ten (10) minutes i
l l
j QUESTION: 098 (1.00)
WHICH ONE (1) of the following designates a FLOATING STEP in an Emergency Procedure? .
1 An asterisk precedes the ste I An solid square precedes the step, i Step number is in brackets, Step number is BOL l l
I f I V , - + - - y-- (w w -,w-: w-my g vy er--vw-- =&-N*'* M D"fTb' I8
~ .. . . . .. - - - - . .
,
' REACTOR OPERATOR Page 58-QUESTION: 099- (1.00)
.WHICH ONE (1) of the following is the MINIMUM level of approval:needed-to-remove a' NUISANCE. annunciator from service?' Two (2) Licensed Reactor Operators Two (2) Licensed Senior Reactor Operators Shift Engineer AND. Control Room Supervisor Shift Superintendent
.
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i QUESTION: 100 (1.00)
~WHICH ONE (1) of the'following activities does NOT require the use of.anL Japproved operating procedure?
- Trouble shooting the erratic operation of a EFW valve, Service connection to Service Air Syste , Blowdown of a Safety Injection Tank (SIT).
i Addition of Lithium Hydroxide to the Spent Fuel Pool,
~;
1-
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Li l
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(********** END OF EXAMINATION **********)-
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. REACTOR [ OPERATOR Page 59 r
001 (1.00)
'
'i ANSWER: [+1.0)
REFERENCE:
,
. .032, " Emergency Boration", page . AA52102-003, " Chemical & Volume Control System", . Obj ective. . KA 004000K205 (2.7/2.9) 004010A207 (3.8/3.9) 004010A403 (3.9/3.7)
004010A403 004010A207 004000K205 ..(KA's)
,
ANSWER: 002 (1.00) [+1.0)
,
REFERENCE: , AA52002-014, "Excore Nuclear Instrumentation", Objective 14.3f, page'2 . KA 015000K106 ( 3 .1/ 3 . 4 )
015000K106 ..(KA's)
.
'
ANSWER: ~003 (1.00) [+1.0) ,
,
REFERENCE: AA-52002-012, " Control Element Drive Control", Objective 12.6, page-1 l KA 001000K105 (4.5/4.4) ,
-001000K105 ..(KA's) -i
,
ANSWER: 004 (1.00)
[+1.0)
'
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REACTOR _ OPERATOR 'Page-601 REFERENCE:
1 AA-52002-012, " Control Element Drive Control", Objective 12.3, page ,
! KA 001050K202 ( 3 .1/ 3 ~. 5 )
,
001050K202 ..(KA's)
,
. ANSWER: 005 (1.00) (+1.0)
REFERENCE: AA-52002-012, " Control Element Drive Control", Objective 12.6,'page-1 .2 . KA 001000K105 (4.5/4.4)
001000K105 ..(KA's) ,
3:
ANSWER: .006 (1.00) [+1.0) t REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.6, page 39, KA 003000A304 (3.6/3.6)
,
1003000A304 ..(KA's)
,
ANSWER: 007 (1.00) [+1.0)
i
' !
REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.6, page 4 . KA 003000A402 (2.9/2.9)
003000A402 ..(KA's)
'l I
- -. ,
. - . - . . . -
'!
REACTOR-, OPERATOR Page'61 l
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' ANSWER: 008 (1.00)
a :. . [+1.0) l REFERENCE: i
' .006, " Reactor Coolant Pump Operations", Attachment A, page 1 . AA52002-001, " Reactor Coolant System", Objective 1.7, page 4 , KA 003000G005 (3.4/3.8), 003000G010 (3.3/3.6), 003000G013 (3. 6/3. 7) ;
003000G013 003000G010 003000G005 ..(KA's)
ANSWER: 009 (1.00)
, [+1.0] ;
REFERENCE: i
- AA42002-003, " Chemical and Volume Control", Objective 3.3, page 1 ~ KA 004000G007 (3.3/3.3), 004010K403 ( 3.1/3. 6 )
.
<
004000G007 004010K403 ..(KA's)
ANSWER: 010 (1.00) [+1.0]
REFERENCE: AA42002-003, " Chemical And Volume Control", Objective 3.3h, page 1 . KA 004010K101- (3.4/3.9)
004010K101 ..(KA's)
'
ANSWER: -011 (1.00) [+1.0)
.
'
.- .
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-
REACTOR-OPERATOR .Page 6 REFERENCE: AA-52002-013, " Engineered Safety' Features Actuation System", Objective 1 13.1F, page 1 . KA 013000A101 (4.0/4.2)
013000A101 ..(KA's) ,
,
ANSWER: 012 (1.00) (+1.0)
REFERENCE: AA-52002-013, " Engineered Safety Features Actuation System", Obj ective -
13.2B, page 1 . KA 013000A301 (3.7/3.9) ,
013000A301 ..(KA's)
,
,
RNSWER: 013 (1.00) (+1.0)
.
REFERENCE: AA52002-014, "Excore Nuclear Instrumentation", Objective 14.2D, page 1 . 101 015000G004 (3.4/3.4)
015000G004 ..(KA's)
ANSWER: 014 (1.00) ' (+1.0)
.
>
>
, , , ~
, -
- . . -
1 REACTOR OPERATOR Page-63
, i
~
e REFERENCE:
L I' - AA52002-037, " Saturation Margin Monitor", Objective 37.8, page ~. KA 017000G010 (2.6/2.9)
'
017000G010 ..(KA's)
~ ANSWER: 015 (1.00) [+1 0)
' REFERENCE: STM-2-09, " Containment Cooling and Purge' System",-'page' . AA52002-027, " Service Water System", . Objective 27.2 . KA 022000K101 (3.5/3.7)
t 022000K101 ..(KA's)
.
- ANSWER: 016 (1.00)' _ [ + 1.' 0 ]
REFERENCE:
, , AA32003-021, " Condensate and Feedwater System", Objective 21.6, page 4 . KA 059000G010 (2.9/2.9)
,
059000G010 ..(KA's)
ANSWER: 017 (1.00) [ +1. 0]
I
.-
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3 - ,- , . . ~, -
. - - . .
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REACTOR OPERATO Page'64
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REFERENCE: AA32003-021, " Condensate and Feedwater System", Objective 21.3h, page 3 . }Ui 059 000K419 (3.2/3.4)
'
- 2 . >
059000K419 ..(KA's)'
ANSWER: 018 (1.00) [+1.0]
REFERENCE:
1.- AA-42002-021, " Emergency Feedwater System", Objective 21.2B, page . KA 061000K401 (3.9/4.2) ,
-
061000K401 ..(KA's)
ANSWER: 019 (1.00)
c .. [+1.0]
REFERENCE: AA-52002-013, " Engineered Safety Features Actuation System", Objective '
13.2D, page 2 . KA 061000K414 (3.5/3.7)
061000K414 ..(KA's)
.
ANSWER: 020 (1.00)
> [+1.0]
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REACTOR' OPERATOR- 'Page 65
..
' REFERENCE: AA42002-021, " Emergency'Feedwater System", Objective 21.3C, page 1 .. KA 061000A303 (3.9/3.9)
061000A303 ..(KA's)
ANSWER: 021 (1.00) (+1.0)
' REFERENCE:
1, AA-52002-033, "Radwaste System", Objective 33.4, page 2 . KA 068000A302 (3.6/3.6)
068000A302 ..(KA's)
ANSWER: 022 (1.00) [+1.0]
- REFERENCE: - STM-2-52, " Liquid Waste System", page . AA-52002-033, "Radwaste System", Objective 3 . KA 068000K107 (2.7/2.9)
068000K107 ..(KA's)
ANSWER: 023 (1.00) [+1.0)
.
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REACTOR OPERATOR .Page 66
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REFERENCE:
1.- 2104.010, " Unit 2 Waste Gas Analyzer Operation", Attachment "A", page 2 . AA-52002-033, "Radwaste System", Objective.33.4, page 3 ; KA' 071000K504 (2. 5/3.1) ,. 071000A429 '(3. 0/3. 6)
071000A429 071000K504 ..(KA's)
ANSWER: 024 (1.00) [+1.01 REFERENCE: AA-52002-018, " Radiation Monitoring System", Objective 18.5, page- . KA 072000G010 (2.8/3.0) ,
072000G010 ..(KA's)
- ANSWER: 025 (1.00) [+1.0]
'
REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.1,-page . KA 002000K109 (4.1/4.1) .
002000K109 ..(KA's)
ANSWER: 026 (1.00) [+1.0]
>
,
REFERENCE:
' AA52002-001, " Reactor Coolant System", Objective 1.2, page 1 . KA 002000K108 (4.5/4.6)
002000K108 ..(KA's)
_ _ _ _ ._ ,
. _ . . . _ _ . _ . _ . . . _ _ . ~
'1
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REACTOR-OPERATOR- 'Page 6 ,
1 ANSWER: - 027 (1.00) (+1.0)
REFERENCE: l l .AA52002-004, " Emergency Core System", Objective 4.9A, page 1 ~- 2 . KA 006020A107 (3.5/3.7)
006020A107 ..(KA's)
,
- ANSWER: 028 (1.00) [+1.0) .
>
..
REFERENCE: AA52002-004, " Emergency Core System", Objective 4.4, page . KA 006000K603 (3.6/3.9) -
006000K603 ..(KA's)
ANSWER: 029- (1.00) ' [+1.0]
REFERENCE:
' AA52002-001, " Reactor Coolant System", Objective 1.11, pages 56-5 KA 010000K403 (3.8/4.1)
'
. .
010000K403 ..(KA's)
.
ANSWER: 030 (1.00)
-, [+1.0}
,
4 t -. r -- , -
e
. _ . . _ . ~ . . _ . . _ . . . _ . . . . . . .~ _
. . - . . . _ . . _ . . . _ . _ . . . . .
!
REACTOR OPERATOR Page168-REFERENCE: *
! .005, " Pressurizer Operation", page ' 2 '.
-
AA52102-002, STG2A, Objective 1.1, Attachment A, page 32 of 45,
' AA52002-001, " Reactor Coolant System", Objective 1.11,.page 6 . KA 010000A402 (3.6/3.4), 010000A101 (2.8/2.9)
010000A101 010000A402 ..(KA's)
!
.
ANSWER: 031 (1.00) [+1.0}
REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.9, page 5 '
- I KA 011000K605 ( 3 .1/ 3 . 7 ) '
011000K605 ..(KA's)
ANSWER: 032 (1.00) [+1.0]
REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.9, page 5 . KA 011000K404 (3.0/3.3)
011000K404 ..(KA's)
ANSWER: 033 (1.00) [+1.0) j
.1 REFERENCE: -l l AA52002-006, " Reactor Protection System", Objective , page 16 ' KA 012000A401 (4.5/4.5)
012000A401 ..(KA's)
. . - - . _ - - - ..
. - , _ .. . - . . _-.
t REACTOR. OPERATOR Page 6 .
.
.' ANSWER: 034 (1.00)
[+1.0]
'
' :
.
REFERENCE: AA-52002-043, " Diverse Scram System", Objective 43.10,- page . KA 012000K201 (3. 3/3. 7) , . 012000K107 (3.2/3.2) !
012000K103 (3.7/3.8) 012000A407 (3.9/3.9)
.
012000A407 012000K103 012000K107 012000K201 ..(KA's) 1
ANSWER: 035 (1.00) , [41.0) .
' REFERENCE: STM-2-02, " Control' Element Driv 6 Control", page . AA-52002-012, " Control Element Drive Control", Objective 1 . KA 014000K101 (3.2/3.6)
014000K101 ..(KA's)
i ANSWER: 036 (1.00) , [+1.0) ,
'
REFERENCE:
AA52002-037, " Saturation Margin Monitor", Objective 37.6, page . KA 016000A302 (2.9/2.9) ,
.
016000A302 ..(KA's) 1
!
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ANSWER:- 037 (1.00)
- [ + 1. 0)
!
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_ _ . . . . .
__ -
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.-- _-_ . . _ _ _
.;
- REACTOR OPERATOR ~ Page 70-REFERENCE:
- AA42002-007, " Containment Spray System", Objective ^ STM 2-08, " Containment Spray System", page ,
= KA 026000K201 (3.4/3.6) 4
,
026000K201 ..(KA's)
ANSWER: 038 (1.00) [+1.0)
REFERENCE:
I 1. - AA-52002-013, " Engineered Safety Features Actuation System", Objective; -
13.2D , page 1 .
I KA 026000A301 (4.3/4.5), 026000K101 (4.2/4.2)
026000A301 026000K101 ..(KA's)
ANSWER: 039 (1.00) .
! [+1.0]
REFERENCE: ' STM-2-09, " Containment Cooling and Purge System", page ; KA 029000K104 (3.0/3.1)
029000K104 ..(KA's) i i
' ANSWER: 040 (1.00) ,.
. [+1.0] :
.
l
?
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. , , . ,.- . , -. ... . -. - . . . - - . ~ . .
,
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. REACTOR' OPERATOR Page 71 REFERENCE: ; AA52102-015, "Feedwater Control System", Objet ive 4, page 1 . KA 035010A301 (4.0/3.9)
,
035010A301 ..(KA's)
ANSWER: 041 (1.00) ,
. [+1.0)
'
REFERENCE: AA52102-015, "Feedwater Control System", Objective 7, page 2 . KA 035010A203 (3.4/3.6)
035010A203 ..(KA's)
(1.00)
'
ANSWER: 042 [+1.0) :
REFERENCE: STM-2-15, " Main Steam", page . 2106.016,. " Condensate and Feedwater Operation",~ Supplement 1, page 11 . KA 039000K408 (3.3/3.4)
039000K408 ..(KA's)
ANSWER: 043 (1.00)
' [+1.0) .
s
,
(
,- _
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- REACTOR' OPERATOR- Page=72
,
JREFERENCE:
fl . AA52002-032, " Control-Room and'ESF. Equipment Ventilation. System",
'
Objective 32.2,Lpage' '
- .KA 073000G007 (2.9/3.0)-
073000G007 ..(KA's) ]
D
,
ANSWER: 044 (1.00) [+1.0) !
-REFERENCE:
, AA52002-044, "
Shutdown Cooling System", Objective 44.2, page . KA 005000K110 (3.2/3.4)
.005000K110- . .(KA's)
,
ANSWER: 045 (1.00)- [+1.0]' ,
P REFERENCE: '
~
1.- AA52002-001, " Reactor Coolant System" , Objective 1.8, page 6 . KA 007000A301 -(2.7/2.9)
007000A301 ..(KA's)
ANSWER: 046 (1.00) [+1.0) :
!
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P
.m - -. , . . - _ - .. _ -. .;~ _ . . _ . - . _ . _,
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REACTOR-OPERATOR Page 73- 1 I
-REFERENCE:
2?. AA42002-007, " Containment Spray System", Objective 7.6, page 20, KA 027000G007 (3.2/3.4)
I
'
.027000G007 ..(KA's)
,
ANSWER: 047 (1.00) , [+1.0) !
REFERENCE:
L AA52002-050, " Containment Combustible Gas Control", Objective 50.7,:page .
,
.2 * KA 028000G010 (3.0/3.2)
028000G010 ..(KA's)
' ANSWER: 048 (1.00)
s [+1.0)
.
REFERENCE: AA-52002-006, " Fuel Handling Equipment",. Objective 26.3, Attachment A, page .
, KA 034000K402 (2.5/3.3) ,
.
034000K402 ..(KA's)
.
ANSWER: 049 (1.00) [+1.0)
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REACTOR OPERATOR Page 74
~ REFERENCE:
' AA52002-011,'" Steam Dump &. Bypass Control System",- Objective'1 . SDBCS, pages 7 & ' KA 041020A102 . (3.1/3.2)
041020A102 ..(KA's) .
ANSWER: 050 (1.00) [+1.0)
i'
REFERENCE:
i AA-52002-027, " Service Water", Objective 27.6, ,page 2 . KA 076000G005 (2.8/3.2), 076000G010 (2.7/2.9) ,- ;
' i 076000G010 076000G005 ..(KA's)
ANSWER: 051 (1.00) [+1.0]
REFERENCE: .021, " Loss of Instrument Air", page . STM-2-48, " Instrument Air System", page . KA 078000K303 (3.0/3.4)
078000K303 ..(KA's)
ANSWER: 052 (1.00) {+1.0)
REFERENCE: .025, "RCP Emergencies" Attachment D, page 1 . KA 000015G010 (3.4/3.4)
000015G010 ..(KA's)
_
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REACTOR OPERATOR Page 75 :
,
-ANSWER: 053' (1.00) ,
- [+1.0]
REFERENCE: .025, "RCP Emergencies", Attachment D, page 1 . KA 000015A210 (3.7/3.7)
000015A210 ..(KA's)
'
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ANSWER: 054 (1.00) t [+1.0]
-
-
I REFERENCE: .025, "RCP Emergencies", page ' KA 000015A122 (4.0/4.2) ,
000015A122 ..(KA's)
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ANSWER: 055 (1.00) [+1.0)
REFERENCE: j AA52002-014, " Reactor Trip Recovery", Objective 14.5, page 6 i KA 000024K302 (4.2/4.4)
l 000024K302 ..(KA's)
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ANSWER: 056 (1.00) ,
i [+1.0)
l
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REACTOR OPERATOR Page 76-REFERENCE:
L ' .028,-" Component Cooling Water System Operation", page . AA52002-030, " Cooling Water System", Obj ective .30.2H,.pages 15-1 . KA 000026A201 (2.9/3.5) 000026K301 (3.2/3.5) , 000026A102 (3.2/3.3)
000026A102 000026K301 000026A201 ..(KA's)-
ANSWER: 057 (1.00) [+1.0]
REFERENCE:
. AA42102-002, " Pressurizer Pressure and Level Control System", Q10.,.page ~ KA 000027K303 (3.7/4.1) .
000027K303 ..(KA's)
ANSWER: 058 (1.00) [+1.0]
REFERENCE: AA52003-009, " Excess Steam Demand", Objective 09.2, page 15 KA 000040K304 (4.5/4.7)
000040K304 ..(KA's)
. ANSWER: 059 (1.00)
-' [+1.0)
i
- REACTOR OPERATOR 'Page 77
~ REFERENCE:
2. . - AA52003-009, " Excess. Steam Demand", pag . KA 000040K106 (3.7/3.8).
000040K106 ..(KA's)
-ANSWER: 060 (1.00) [+1.0]
REFERENCE: .010, " Standard Attachments", Attachment 20, page 6 . KA 000040A203 (4.6/4.7)
000040A203 ..(KA's)
- (NSWER: 061 (1.00) [+1.0) E REFERENCE:
1, 2203.019, " Loss Of Condenser Vacuum", page . KA 000051A202 (3.9/4.1)
-000051A202 ..(KA's)
. ANSWER: 062 (1.00) {+1.0)
'
REFERENCE: AA52003-011, " Loss of Offsite Power", Objective 11.6, pages 20-2 :2 . KA 000055A202 (4.4/4.6)'
000055A202 ..(KA's)
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w - n<w.
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REACTOR' OPERATOR Page 78 l i
IANSWER: 063 (1.00) [+1.0) ,
.
REFERENCE: -
. 'AA52003-012, " Station Blackout", Objective 12.5', page 1 . KA 000055G007' (3. 6/3. 7)
000055G007 ..(KA's)
.
ANSWER: 064 (1.00) [ +1. 0)
' REFERENCE: 'I .034, " Fire Or Explosion", page i
, }UL 000067K102 (3.1/3.9)
000067K102 ..(KA's) ;
i
.I ANSWER: 065 (1.00) ;
,
l [+1.0) -j
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REFERENCE:
!
' T/S.3.3.3.5, Table 3.3-9, p. 3/4 3-3 '
' .L4 000068K201 (3.9/4.0)
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000068K201 ..(KA's) I
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' ANSWER: 066- (1.00) J [+1.0) l
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i REACTOR OPERATOR Page 79-i
. REFERENCE: .014, " Alternate Shutdown", page . KA 000068G010 ( 4 .1/ 4 . 2 )
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000068G010 ..(KA's) ,
i
.RNSWER: 067 (1.00) * [+1.0]
REFERENCE: .009, " Heat Removal Decision Tree", page I KA 000074G011 (4.5/4.6) .i
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000074G011 ..(KA's)
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ANSWER: 068 (1.00) (+1.0]
REFERENCE:
1 2203.003,."CEA Malfunction", page .i AA-52002-012, " Control Element Drive Control", Terminal Objective, page
~ ; ;
. KA 000001G010 (3.9/4.0) I 000001G010 ..(KA's) !
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. ANSWER: 069 (1.00): e d.- [+1.0] 2 a
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. REACTOR. OPERATOR .Page 80
' REFERENCE: l
.- j .003, "CEA Malfunction", page j AA-52002-012, " Control Element Drive Control", Terminal Objective, page l .j KA 000003G011 (4.0/4.1)
000003G011 ..(KA's)
,
i ANSWER: 070 (1.00) [+1.0) -
REFERENCE: , .2202.001, " Standard Post Trip Actions", pag . KA 000007K301 (4.0/4.6) i 000007K301 ..(KA's)
.
(1.00)
'
ANSWER: 071 [+1.0]
REFERENCE: .009, " Functional Recovery Procedure", page 1 * KA 000007G012 (3.8/3.9)
000007G012 ..(KA's)
ANSWER: 072 (1.00) [+1.0)
'T
'
REFERENCE: AA52002-015, " Loss of Coolant Accident EOP", Objective 15.4, page 1 . KA 000008G011 ( 4 . 0 / 4 .1 ) +
000008G011 ..(KA's)
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REACTOR OPERATOR Page-81 j ANSWER: 073 (1.00) .
I [+1.0]
-l
REFERENCE: .003, " Loss Of Coolant Accident, Safety Function Status Check", pag !
7 . KA 000009A239 (4.3/4.7).
000009A239 ..(KA's)
!
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-ANSWER: 074 (1.00) , [+1.0)
.
i REFERENCE: .019, " Standard Attachments", Exhibits 2 & 3, pages 90 & 9 . AA52002-015, " Loss Of Coolant Accident EOP", Objective 15.15, page 42, KA 000011A210 (4.5/4.7) ,
000011A210 ..(KA's) i
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ANSWER: 075 '(1.00) '
[+1.0)
REFERENCR-
' ,1'01, " Standard Post Trip Actions", page . RFe 2 . 010, " Standard Attachments", Attachment 1 and 2,.pages 3 and . Zh 000011G010 _(4.5/4.5), 000011A103 (4.0/4.0)
.,
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000011A103 000011G010 (KA's)
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ANSWER: 076 (1. 0 0 )-
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REACTOR: OPERATOR Page,82
' REFERENCE:
~ .2202.003, " Loss Olf Coolant Accidentsa , page . KA 000011G007 (3.7/3.9)
000011G007 ..(KA's)
ANSWER: 077 (1.00) [+1.0]
REFERENCE: .029, " Loss of Shutdown Cooling", page ~ KA 000025A112 (3.6/3.5)
,..
i 000025A112 ..(KA's)
ANSWER: 078 (1.00)
- [+1.0)
' REFERENCE:
- STM-2-02, " Control' Element Drive Control",-page . KA 000029K312 (4.4/4.7)
000029K312 ..(KA's)
'
. ANSWER: 079 '(1. 00 ) . [+1.0) ,
,
r REFERENCE: -;
- Unit 1 TechnicalcSpecifications_3.9.2, " Refueling Operations",-page-3/4 '! KA b00032G008 - (2.'8/3 -. 3 ) .
000032G008 ..(KA's) 'l
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A RSACTOR-OPERATOR Page 83
' ANSWER: 080 (1.00) [ + 1.'0 ] -
' REFERENCE: .038, " Primary To Secondary Tube Leakage", page . KA 000037A212 ( 3 . 3 /4 .1)
000037A212 ..(KA's) ..,
.
ANSWER': 081 (1.00) ;
L
! [+1.0)
. ,
REFERENCE: , AA52003-008, " Steam Generator Tube Rupture", Objective-08.8, pages 19-2 . KA 000038G011 (4.2/4.3)
000038G011 ..(KA's)
ANSWER: 082 (1.00)
2 [+1.0}
REFERENCE:
1, 2202.006, " Loss of Feedwater", page *
_
2.- AA52003-010, " loss Of Feedwater", page 1 .i 3'. KA 000054K304 (4.4/4.6)
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000054K304 ..(KA's) !
ANSWER: 08 (1. 00) . . . [ + 1. 0 ) -
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REACTOR' OPERATOR
- :Page:84 REFERENCE:
- AA52002-007, " Electrical Distribution", page 3 . KA 000058A203 (3.5/3.9)
.000058A203 ..(KA's)
ANSWER: 084 -(1. 0 0 ) [+1.0]
' REFERENCE: AA42102-002, " Pressurizer Pressure and Level Control System", Objective 5, pages 43-4 _
'""
- KA 000028A212 (3.1/3.5) l 000028A212 ..(KA's)
ANSWER: 085 (1.00) [+1.0) ,
REFERENCE:
- AA52003-011, " Loss of Offsite Power", Objective 11.6, page 2 . KA 000056A288 (4.1/4.2)
000056A288 ..(KA's)
-i ANSWER: 086 (1.00) :
a -. [ +1'. 0] ,
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. . _ . . . - - - . __ . ._. . . . : REACTOR OPERATOR Page 8 REFERENCE: .021, " Loss Of: Instrument Air", Attachment E, page 4 . 1 KA.000065A208 (2.9/3.3).
000065A208 ..(KA's)
.
ANSWER: 087 (1.00) (+1.0]
. REFERENCE: , .021, " Exposure Limits and Controls", page . KA 194001K103 (2.8/3.4)
194001K103 ..(KA's) ..;
RNSWER: 088 (1.00) * [+1.0]
REFERENCE:
- .021, " Exposure-Limits and Controls", page 1 ' KA 194001K103 (2.8/3.4)
194001K103 ..(KA's)
ANSWER: 089 -(1.00) (+1.0] .,
> REFERENCE: 'T/S BASES 3/4 . .
2 '. KA 194001A114 (2.5/2.9)
194001A114 ..(KA's)
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. REACTOR' OPERATOR Page 86 )
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ANSWER: 090 (1.00) [+1.0] ;
I REFERENCE: -
- .120, "ANO Fire Barrier Watch Program", page . KA 194001K116 (3.5/4.2)
194001K116 ..(KA's)
,
ANSWER: 091 (1.00) [+1.0]
REFERENCE:
! .128, " Industrial Safety and Occupational Health", page 2 . KA 194001K109 (3.4/3.4) ,
,
k 194001K109 ..(KA's)
ANSWER: 092 (1.00) [+1.01 REFERENCE:
, .006, " Procedure Control", page . KA 194001A101 (3.3/3.4)
194001A10 ..(KA's)
e ANSWER: 093 (1.00) [+1.0)
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' REACTOR OPERATOR Page~87 REFERENCE: .019, " Station' Security Requirements", page 1 . KA 194001K105 '(3.1/3.4)
~
-194001K105
~
..(KA's) ,
ANSWER: 094 (1.00) [+1.0) .,
-REFERENCE: ; .027, " Hold and Caution Card Control", page 3 . KA 194001K102 (3.7/4.1) 1
194001K102 ..(KA's)
,
ANSWER: 095 (1.00) 1
- [+1.0]
,
. REFERENCE: .001, " Conduct Of Operations, page 4 . KA 194001K101 (3.6/3.7)
194001K101 ..(KA's)
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- ANSWER: 096 (1.00)
[+1.0)
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REFERENCE: ,
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. .011, " Conduct Of Operation"', page 51 ,
}Ut 194001K101 (3.6/3.7)
' K101 ..(KA's)
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. REACTOR' OPERATOR' Page 88 ,
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. ANSWER: 097- (1.00)
- (+1.0)
' REFERENCE: .021, " Exposure Limits and Concrols", page 1 l KA 194001K103 (2.8/3.4)
194001K103 ..(KA's) ,
ANSWER: 098 (1.00) j
- (+1.0)
i
REFERENCE: ! .002, " Reactor Trip Recovery", page . KA 194001A102 (4.1/3.9) :
194001A102 ..(KA's) i ANSWER: 099 (1.00) - (+1.0)
,
REFERENCE: .028, " Operations Annunciator Control", page > KA 194001A109 (2.7/3.9)
194001A109- ..(KA's) !
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ANSWER:- 100 (1.00) ; [+1.0) 1
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REACTOR' OPERATOR Page 09 REFERENCE: .032, " OPS Procedure Users Guide", page . KA 194001A102 - (4.1/3,9)
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194001A102 ..(KA's)
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3 REACTOR OPERATOR Page 1
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ANSWER KEY
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l MULTIPLE CHOICE 023 c 001- c 024 d 00 b 025 o 003 b 026 a ,
004 d 027 b 028 c 006 d 029 a ,
007 a 030 a
!
008- a 031 a 009 a 032 i 010 a 033 b a-011 a 034- d ,
012 d 035 b- ,
013 'b 036 c 014 c 037 .c
015 c 038 d 016 'd- 039 c 017 c 040 a 018 -b 041 a 019 c- 1042 d i 020 c 043 d ;
, 021 d 044 b 022 a 045 d ;
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6,- es-., e,-... . ., ,-
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' REACTOR OPERATOR' Page 2'
ANSWER KEY '
,
046 c~ 069 d
'047 b 070 a-048 d 071 b r- ;
049 b 072 d 050 b- 073 a ,
051 d 074 c 'i 052 a- 075 c 053 b 076 a .
054 c 077 d
055 a 078 c l 056 c 079 a g 057 b 080 c
058 b 081 b-
-059 a 082 a 060 d 083 b )
~061, b 084 c
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062 c 085 a 063 -a 086- a
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-064 d 087' a 065 b 088 d-
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066 b 089 - c .
067 -c- 090 b 068 -b 091 c
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- . REACTOR OPERATOR Page.- 3 l ANSWER KEY I
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l 092 d ,
093 a
094 d
- 095 b 096 h-097 b 098 b ci 099 d 100 b
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U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION SENIOR OPERATOR LICENSE REGION 4 CANDIDATE'S NAME:
FACILITY: Arkansas Nuclear One-2 REACTOR TYPE: .PWR-CE
'
DATE ADMINISTERED:- 93/12/06 INSTRUCTIONS TO CANDIDATE:
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheet Points for each question are indicated in parentheses after the question. The passing grade requires a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination start CANDIDATE'S TEST VALUE SCORE %
100.00 % TOTALS FINAL GRADE All work done on this examination is my ow I have neither given nor received ai Candidate's Signature I
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- SENIOR' REACTOR OPERATOR Page 2 ANSWER- S H E.E T
'
Multiple Choice (Circle or X your choice)
If you. change your answer, write your selection in the blank, ,
,
?
MULTIPLE CHOICE 023 a b 'c d
~
'001- a b c d 024 a b c d
002 a b c d 025 a b c d ;
003 a b c d 026 a b c d-004 a b c d 027 b .c d 005 a b c d 028 a b c d 006 a b c d 029 a b c +
'
007 a b c d 030 a b c d 008 a b c d 031 a b' d .
00 a b c d 032 a b- c d 010 a b c d 033 a b c d
,
.011 a b c d 034 a b c d [
012- a b c d 035- a -b c' id 013 b c d 036 a b ~c d 014 a b c d 037 a b c ,
i 015 a b c d 038 a b~ c d ,
016 a b~ c d 039 a b c d 017- a b c d 040 a b c d 018- a b c d 041 a b c d 019 a c d 042 a c d t
020 a b c d 043 a b c d
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02 b c d- 044 a b c d 022 a b c d 045 a b c d ;
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-SENIOR REACTOR OPERATOR Page= 3L ,
ANSWER SHEET
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Multiple Choice (Circle or X your choice)
If.you change your answer, write your selection in the blan !
'046 a b c d 069 a b c d !
047 a b- c d 070 a b c .d
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048 a b c d 071 a b- c d -
049 a b c d 072 a b c d
. . .
050~ a b c d .073 'a' .b- c d l b
051 a b c d 074 a b c d __
052 a b c d 075 a b c d 053 a b c d 076 a b c d'
054 a b c d 077 a b c d ;
i 055 a b c d 078 a .- b c' .d i 056 b c d 079 'a b c d j 057 a b d 080 a b c d .i 058 a' b c d 081 a b c d'
059 a b c d '082- a b c d
060 a b c d 083- a b c' d '!
061 a b c d 084 'a' b c d 1 i
062 a- b c d 085 a b' c d' ;i
-
063 a b c 'd 086- a 'b c -d'
064 a b c d 087- a b c d ;
J 06 b c d- 088- a .b c d .j 066 a b c d 089 a b d :!
i 067 a b c 'd 090 a b c d- l 068 a b c d 091 a b c d
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-SENIOR REACTOR' OPERATOR Page 4 ANGWER SHEET Multiple Choice (Circle or X your choice)
If.you change your answer, write your selection in the blan '092 a b c d 093 a b c d .;
'094 a b c d 095 a b c d
'
096 'a b 'c d
,
097 a b c d .
.
098 a b c d
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099 a b c d '
100 a b c d
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(********** END OF EXAMINATION **********) l, v 1 , y ~
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Page 5 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
1. Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 examinatio , Restroom trips are to be limited and only one applicant at a time ma '
leav You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheatin . Use black ink or dark pencil ONLY to facilitate legible reproduction l
<
5. Print your name in the blank provided in the upper right-hand corner'of the examination cover sheet and each answer shee .
6. Mark your answers on the answer sheet provide USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAG . Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question pag . Use abbreviations only if they are commonly used in facility literatur Avoid using symbols such as < or > signs to avoid a simple transposition J
error resulting in an incorrect answer. Write it ou . The point value for each question is indicated in parentheses after the questio . Show all calculations, methods, or assumptions used to obtain an answer to- -
any short answer question ,
11. Partial credit may be given except on multiple choice questions. Therefore,
. ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER-BLAN . 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 0.20 point If one of your five responses is incorrect, 0.20 will be deducted and your total. credit for that question will be 0.80 instead of 1.00 even though you got~the four correct answer . If the intent of a-question is unclear, ask questions of the examiner onl :
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f Page 6 14. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheet In addition, turn in all scrap pape . Ensure all information you-wish to have evaluated as part of your answer is on your answer sheet. Scrap paper will be disposed of immediately following the examinatio . To pass the examination, you must achieve a grade of 80% or greate . There is a time limit of four (4) hours for completion of the examinatio *
18. When you are done and have turned in your examination, leave the examination area (EXAMINER WILL DEFINE THE AREA). If you are found in this area while the_ examination is still in progress, your license may be denied or revoke ,
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SENIOR REACTOR OPERATOR Page 7 *
QUESTION: 001 (1.00) -
The following plant conditions exist: Unit 2 has tripped from 100% power due to a loss of offsite powe . Emergency Diesel Generator 2K4A has failed to star i RCS pressure is 2230 psi . Two (2).CEAs have failed to fully insert into the cor . RWT level is 70%.
' The Boric Acid flow transmitter down stream of the Boric Acid' Makeup pumps has just been discovered to be plugge . Reactor operators are performing Emergency Operating Procedure-2202.001, " Standard Post Trip Actions".
WHICH ONE (1) of the following mechods is available for emergency boration given the above conditions? HPSI pump 2P-89A through High Pressure Injection valve Gravity feed from RWT through 2CV-4950-2 to the Charging pump 2P36 Normal Emergency Boration flowpath through 2CV-4916-2 to the Charging pump 2P36 Gravity feed through 2CV 4921-1 to the Charging pump 2P36 QUESTION: 002 (1.00)
WHICH of the following actions should bo performed if the Thot input to the Reactor Regulating System (RRS) fails HIGH?
E Commence boratio Take letdown control to MANUA Commence dilutio Take backup heaters to OF ,
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SENIOR REACTOR OPERATO t i
QUESTION: 003 (1.00)
WHICH ONE (1) of the following describes the CEDMCS Withdrawal Prohibit (CWP)
alarm function? Initiated by the CEA Position Indication System in response to a PRETRIP condition on DNBR and prohibits ALL movement of regulating ,
CEAs.
' Initiated by the Plant Protection System (PPS) in response to a PRETRIP condition on DNBR and prohibits ALL OUTWARD group movement of CEA Initiated by the CEA Position Indication System of the Plant *
Computer in response to OUT OF SEQUENCE / OVERLAP condition and prohibits ALL OUTWARD movement of CEA . Initiated by the Plant Protection System (PPS) in response to OUT OF SEQUENCE / OVERLAP condition and prohibits ALL movement of CEA !
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QUESTION: 004 (1.00)
i WHICH ONE (1) of the following conditions exists if the RED indicating light for the RCP 2P32D is NOT lit? (Assume the bulb has been verified as good). 1
' The 2P32D RCP trip circuit has lost continuity and the ONLY means of tripping the pump is to open the breaker locall ; Thel 2P32D RCP trip circuit has lost continuity and the local handswitch must be used to trip the pum The 2P32D RCP start circuit has lost continuity and the ONLY means of starting the pump is to close the breaker locall The 2P32D RCP start circuit has lost continuity and the local handswitch must be used to start the pum 'I
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SENIOR REACTOR OPERATOR Page: 9- I i
QUESTION: 005 (1.00)
WHICH ONE (1) of the following is the basis for NOT starting the fourth- J Reactor Coolant Pump for Unit 2 until RCS temperature is greater than 500 ;
degrees F.? !
, To prevent exceeding RCS heatup rate limit ,
r To minimize excessive RCP starting current > To limit Steam Generator tube stresse , To limit core uplif ,
,
)
QUESTION: 006 (1.00) .,
WHICH ONE (1) of the following is actuated by LOW Pressurizer pressure. signal?
- Containment Spray System (CSS)
' Penetration-Room Ventilation System (PRVS) Main Steam Isolation System (MSIS) Containment Cooling System (CCS)
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SENIOR REACTOR OPERATOR Page 1 QUESTION: 007 (1.00)
.WHICH ONE (1) of the following is the reason thirty (30) degrees F. is chosen as the setpoint for the Margin To Saturation (IfDS) alarm?- To ensure net positive suction pressure (NPSH) is maintained for the reactor coolant pumps (RCPs).
' To ensure that RCS voiding is prevente ' To ensure that actual subcooling margin is maintained due to instrument error To ensure that actual subcooling margin is maintained when the'RCPs are stoppe QUESTION: 008 (1.00)
WHICH ONE (1) of the following systems provides cooling to the~ Containment Cooling System following a design basis Loss Of Coolant Accident (LOCA)? Chilled Water Component Cooling Water ) Service Water i Auxiliary Cooling Water i
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' QUESTION: 009 (1.00)
.VGIICH ONE (1) of the following conditions will prevent starting. Heater Drain
' Pump 2P8A at 40% reactor power? A Main Feed Pump running and 2CV0742 ope '
b. .A Main Feed Pump running and 2CV0742 close B Main Feed Pump running'and 2CV0742 ope B Main Feed Pump ' running and 2CV0742 ' close ,
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' QUESTION: 010 (1.00)
WHICH ONE (1) of the following conditions will AUTOMATICALLY close Feedwater ,
to Steam Generator Isolation valve 2CV-1024-1? LOW level in Steam Generator "A" HIGH level in Steam Generator "A" MSIS CIAS
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-SENIOR REACTOR OPERATOR Page 12
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QUESTION: 011 (1.00)
The'following. condition exists: Unit 2 is at 5% powe , EFAS has actuate . EFW pump suction is aligned to the Startup and Blowdown Demineralizer effluen r Suction pressure for the Emergency Feedwater (EFW) pumps is'10 psigt and DECREASIN WHICH ONE (1)-of the following automatic actions will occurfif EFW pump suction pressure continues to DECREASE to 5 psig? CV-0789-1 and 2CV-0795-2 will automatically OPEN to supply _ water from the Condensate Storage Tan CV-0716-1 and 2CV-O ril-2 will automatically OPEN supply water f rom the Service Water Syste EFW-0706 will automatically OPEN to supply water.from the
Condensate Storage Tan EFW-16, Condensate Storage Tank Suction Bypass valve, will automatically OPEN to supply additional water from the Condensate Storage Tan ,
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SENIOR REACTOR OPERATOR Page 13 ,
QUESTION: 012 (1. 0 0 ) .
The following conditions exist:
Steam Generator "A" Steam Generator "B"
- Level 25% & decreasing 20% & increasing Steam Pressure 725 psig '825 psig Feedwater Pressure 1200 psig 1200 psi WHICH ONE (1) of the following is the current status.of the Emergency '
Feedwater System (EFS) given the above plant conditions? Assume all plant systems respond as designe ,
' EFAS has not ocu red but will AUTOMATICALLY actuate when Steam Generator "A" level decreases to 23%. , An EFAS trip condition exists and EFW is being supplied to BOTH steam generator ; An EFAS trip condition exists and EFW is being supplied-to.ONLY Steam Generator "B". An EFAS trip' condition exists and EFW is BLOCKED to BOTH steam generator >
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- The following conditions exist: Unit 2 is in HOT STANDB . EFW is-in MANUAL contro . EFW control valves '2CV-1025-1 and 2CV-1075-1 are throttled to BOTH Steam Generator . Simultaneous EFAS A#1 and MSIS #1 actuation signals are received due to an I & C technician erro WHICH ONE (1) of the following is the affect of this-error on EFW control valve 2CV-1025-1 and 2CV-1075-1 operation?
. Valves remain throttled because they are in MANUAL contro Valves remain throttled because EFAS A#1 and MSIS #1 have NO affect'
on these valve Valves go FULL open due to the EFAS A#1 signa Valves go FULL closed due to the MSIS #1 signa QUESTION: 014 (1.00)
WHICH ONE (1) of the following conditions will result in AUTOMATICALLY closing Regenerative Waste Discharge valve 2CV-4424 (2T-92 discharge to flume) ? Tank inlet valve ope Discharge line pH reading of Low instrument air pressure of 50 psi Waste Inlet Radiation Monitor 2RE-4447 HIGH alarm tri .
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SENIOR REACTOR OPERATOR Page 15 t-QUESTION: 015 (1.00) l WHICH ONE (1) of the following discharges to the Drain Collection Heade (DCH) ? Blowdown tank drain l HPSI relief valve LPSI relief valve ;
. Containment sump drains, i
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QUESTION: 016 (1.00)
WHICH ONE (1) of the following sets of Waste Gas Tank parameters is acceptable? (2104.010, " Unit 2 Waste Gas Analyzer Operation", Attachment: "A" is attached.) '
pressure Hydrogen Oxygen psig 40%- 12%
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, psig 20% 5% psig 60% 3% ! psig 6% 10%
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SEMIOR REACTOR OPERATOR LPage 16' H I
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. QUESTION: 017 (1.00)
WHICH ONE (1) of.the.following is the cause for an AREA Radiation Monitor to Lemit a' LOW beeping sound?- , Monitor is.placed in tes . Monitor has-failed LO A valid HI radiation alar Battery backup is discharged, t
QUESTION: 018 (1.00)
WHICH ONE (1) of the following inputs is provided by Loop 2 hot. leg temperature instrumentation? ESFAS bypass permissive for steam generator high/ low water level trip signals .; AWP (Automatic Withdrawal Prohibit) in CEDMCS LTOP isolation valve misalignment annunciation when valves are'OPEN with temperature less than 240. degrees Steam Dump and Bypass. Control System Modulating Opening Signal- ;
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QUESTION: 019 (1.00)
The following conditions exist: The plant is operating at 75% power and the latest leak rate data indicates: ,
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- 11.5-GPM - Total RCS leakage rate
- 2.5 GPM - Leakage into the Quench Tank
- 2.2 GPM - Leakage into the Reactor Drain Tank
- 3.5 GPM - Leakage past check valves from RCS to SI system
- 1.2 GPM - Total primary to secondary leakage (Assume distributed over all S/Gs)
WHICH ONE (1) of the following is the current RCS leakage status per Technical Specifications 3.4.6.2, " Reactor Coolant System Leakage"?
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a. PRESSURE BOUNDARY LEAKAGE that requires shutdow b. UNIDENTIFIED LEAKAGE that requires shutdow c. IDENTIFIED LEAKAGE that does NOT require shutdow d. PRIMARY to SECONDARY LEAKAGE that does NOT require shutdow QUESTION: 020 (1.00)
T To WHICH ONE (1) of the following locations are the Safety Injection. Tanks (SIT) vented when lowering pressure in Mode 3? Containment atmosphere Reactor Drain Tank < Quench Tank Holdup Tank
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QUESTION: 021, (1.00) ,
The following conditions exist: Unit 2 has tripped due to a small break loss of coolant accident >
(LOCA). i The event is ongoing and the Recirculation Actuation System (RAS)
has initiate . RCS pressure has increased to 1500 psi . BOTH High Head Safety Injection (HPSI) pumps continue to operate at:
full capacit WHICH ONE (1) of the following provides cooling for the HPSI pumps? Flow through the pumps to the RCS is sufficient to cool the pumps under these condition Mini-Recirc flow to the RWT is sufficient to cool the-pumps under these condition Mini-Mini-Recirc flow to the pump suction is sufficient to cool the pumps for up to thirty eight (38) minute Mini-Recirc flow to the containment sump is sufficient to' cool the pumps for up to thirty eight (38) minute '
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QUESTION: 022 (1.00)
The following p1' ant conditions exist: RCS pressure.is 2250 pal . Pressurizer Pressure Control System (PPCS) setpoint is 2250. psi . RCS boron' concentration is 500 ppm boro . Pressurizer boron concentration is-350 ppm boron.
-WHICH ONE (1) of the following is the correct method to equalize RCS boron concentration per 2103.005, " Pressurizer Operation"? ENERGIZE all Pressurizer Backup Heaters and place-"A" RCP spra valve in MANUAL and OPEN to maintain RCS pressure within + 10 psia
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of desired setpoin , ENERGIZE all Pressurizer Proportional Heaters and place "A" RCP spray valve'in MANUAL and OPEN to maintain RCS pressure within +'10 psia of desired setpoin RAISE Pressurizer-Pressure Control System setpoint to 2300Lpsia AND' ,
energize Pressurizer Proportional Heaters to maintain Pressurizer Spray flo DECREASE Pressurizer Pressure Control System setpoint to 2220 psia AND energize Pressurizer Backup Heaters to maintain Pressurizer Spray flow.
QUESTION: 023 (1.00) ,
Pressurizer level indication on the Remote Shutdown Panel may differ from that of Level Channel 1 as indicated on Panel 2C04. This is because'the Remote Shutdown Panel receives its signal from' ? Level Channel 2 and is NOT temperature compensate . Level Channel 2 and is temperature compensate SPDS which is temperature compensate SPDS which-is NOT temperature compensate .
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QUESTION: 024 (1.00) ,
The following plant conditions exist: Unit 2 is at 100% powe . RCS pressure is 2405 psi . The Reactor Protection System (RPS) has NOT actuate . All Reactor Protection System setpoints have been calibrated to plant design specification WHICH ONE (1) of the following results from RCS pressure INCREASING to 2450 psia? Assume no additional failures occu i The HIGH Pressurizer pressure setpoint of the RPS is reached and Reactor Trip Breakers will OPEN to DE-ENERGIZE the control element assembly (CEA) holding coil The HIGH Pressurizer pressure setpoint of the Diverse Scram System (DSS) is reached DE-ENERGIZING the trip coil to open a contact interrupting output power from both Motor Generator (:MG) set The HIGH Pressurizer pressure setpoint of the RPS is reached and the MG set 480 VAC output breakers will OPEN to DE-ENERGIZE the control >
element assembly (CEA) holding coils, The HIGH Pressurizer pressure setpoint of the Diverse Scram System (DSS) is reached ENERGIZING the trip coil to open a contact r interrupting output power from both Motor Generator (MG) set QUESTION: 025 (1.00)
WHICH ONE (1) of the following is the reason for a FLASHING indication on the 1
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Saturation Margin Monitor (SMM) ?
I Indicated value is below the saturation margin alarm setpoin Indicated value is below 30 degrees F saturation margi l l Indicated value is erroneou l i Indicated value is superheate l i
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QUESTIONi 026 (1.00) l WHICH ONE (1) of the following will result in the loss of Containment Spray i Pump 2P-35A?'
i Loss of 6900 VAC Buses 2H .
- Loss of 6900 VAC Buses 2H t Loss of 4160 VAC Buses 2A , Loss of 4160 VAC Buses 2A +
QUESTION: 027 (1.00) .
WHICH ONE (1) of the following is the MINIMUM condition that will INITIATE- .
actuation of the Containment Spray System? CIAS actuatio l CIAS and SIAS actuatio Containment pressure at 24.0 psia and CIAS actuatio Containment pressure at 24.0 psia and SIAS actuatio .
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- QUESTION: 028_ (1.00)
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WHICH ONE (1) of the following AUTOMATIC actions-take place following a trip of the' Containment Purge Exhaust fan to prevent:overpressurization of the containment? Exhaust dampers go 100% open to relieve pressur i Supply dampers throttle to control pressur ' Supply fan trips after a ten (10) second time dela , Purge isolation valve 2CV-8284 close QUESTION: 029 (1.00)
WHICH ONE (1) of the following conditions could prevent the Spent Fuel [ Poo Cooling System from maintaining pool temperature below the' design-limit.of 150 degrees F.? Component Cooling water.(CCW) flow to the Spent. Fuel Pool' heat exchanger is 1500 gp The reactor has been shutdown for 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> when spent fueluis transferred to the Spent Fuel Poo Only one (1) Spent Fuel Pool pump'is OPERABL Spent Fuel Pool level is reduced to 410 feet 2 inche ,
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The following conditions exist: Unit 2 has. tripped from 100% power one (1) minute ag . Steam Generator "A" level is 95%. Steam Generator "B" level is 40%. High Level Override Level Selector switch is selected to the BOT positio WHICH ONE (1) of the following is the expected status of the Feedwater Control'
System (FWCS)? (Assume NO operator action.) Feedwater is isolated to Steam Generator "A" and at St~ flow demand to Steam Generator "B". Feedwater is isolated to BOTH Steam Generators "A" and "B". Feedwater is at 5% flow demand to BOTH Steam Generators "A" and "B". Feedwater is at 5% flow demand to Steam Generator "A" and at 100%
flow demand to "B" Steam Generato QUESTION: 031 (1.00)
The following-conditions exist: Unit 2 is operating at 100% powe ,
' Steam Generator Level selector switch is selected to BOT WHICH ONE (1) of the following will cause the "B" Steam Generator Flow Demand l Signal to DECREASE? "B" Steam Generator Level transmitter fails HIG l l
' "B" Steam Generator Steam Flow transmitter fails HIGH, "B" Steam Generator Feedwater Flow transmitter fails LO "B" Steam Generator Pressure transmitter-fails LO .. -. .-. , , - _ - - . _ _ - ~ -. . .. . . . - . . - -~ ._
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SENIOR REACTOR OPERATOR Page 24
QUESTION: 032 (1.00) .;
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The following conditions exist: Unit 2 is operating at.100% powe . Operators are performing:the *MSIV Quarterly Partial Stroke Test".
WHICH ONE (1) of the following will result from holding the EXERCISE switch in the CLOSE position for one (1) minute? The valve will stroke closed until the. GREEN closed light is ,
illuminated, then re-open automaticall The valve will stroke closed until'it is 10% closed, then re-open automaticall The valve will stroke closed until it is 10% closed, then remain in 3 that position until re-opened manually, , The valve will continue to stroke closed until the EXERCISE switch is placed in the OPEN position.
QUESTION: 033 (1.00)
WHICH ONE (1) of the following is NOT an AUTOMATIC action which'results from a HIGH alarm trip of Unit 2 Control Room Ventilation Radiation Monitor 2RE-8750- '
1? Unit 1 Control Room Isolation dampers clos l Unit 1 Supply fan VSF-8 stop Control Room Emergency Supply fan 2VSF-9 start Control Room R.ecirculation dampers ope i l
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QUESTION: 034 (1.00)
The~following conditions exist:
' Unit 2 is in HOT SHUTDOW . Operators are placing SDC in servic . SDC Heat' Exchanger Cross-tie valves 2SI-5A and 2SI-5B are OPE . Containment Spray Header MOVs 2CV-5612-1/2CV-5613-2 are OPEN for testin '
WHICH ONE (1) of the following will occur when LPSI pump 2P60A is started? BOTH 2CV-5612-1 AND 2CV-5613-2 will close AUTOMATICALL CV-5612-1 will close AUTOMATICALLY but 2CV-5613-2 will remain ope 'i LPSI Header Isolation valve 2SI-6 will close AUTOMATICALLY but 2SI-5B will remain ope , SI-5A will close AUTOMATICALL !
QUESTION: 035 (1.00) '
WHICH ONE (1) of the following is a possible source of inventory for the :
Quench Tank? Reactor Drain Tank discharge SIT drain lines . Service Water System makeup RCP Controlled Bleedoff i
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QUESTION: 036 (1.00)
The following conditions exist: Unit.2 has tripped due to a large steam break inside containmen
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.WHICH ONE (1) of the following could be a reason the-2P136A pump is NOT running? (Assume all systems are performing as designed.)
- The pump start time delay has-not timed ou Sodium Hydroxide pump 2P136A discharge valve is close Sodium Hydroxide tank outlet valve is only-75% ope > Sodium Hydroxide tank. level is 50%.
QUESTION: 037 (1.00)
Hydrogen Analyzers must be placed in service within fifteen (15) minutes
'following a Loss.Of Coolant Accident'(LOCA)? This is based on NUREG 1.9 .'
which-requires a hydrogen sample within .? thirty (30) minutes of a LOCA and it takes fifteen (15) minutes for the analyzers to warmu thirty (30) minutes of a'LOCA and it takes approximately 11 minutes to transport the gas to the analyzer one (1) hour of a LOCA and it takes forty five (45) minutes for th analyzers to warmup, one (1) hour of a LOCA. and it takes thirty (30) . minutes for' the analyzers to warmup and analyze a sample and approximately 11 minutes to transport the gas to the analyzer ;
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SENIOR REACTOR. OPERATOR Page. ; 27-QUESTION: 038 (1.00)
WHICH ONE (1) of the following conditions will PREVENT movementfof the Refueling Machine?- Spreader is NOT extende Fuel assembly is in the full up positio Suspended load is at setpoin ' Fuel Hoist is operatin QUESTION: 039 (1.00)
WHICH ONE (1) of the following conditions renders the Service Water System IMOPERABLE per Technical Specification 3.7.3, " Service Water System"? 6 The Red ESF bus supplies power to both' Service Water pump 2P4B and' '
the Auxiliary Cooling. Water System-(ACW). Service Water pump discharge filter. delta pressure-is 11 pai The Green ESF bus supplies power to both the Service-Water pump 2P4B and the 2P4B sluice gat Service Water pump suction pressure is 11'psi ,
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.. QUESTION: . 040
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(1.00) ;
j A' major Turbine' Building _ Instrument Air. header rupture has occurred on_ Unit 2.-
l WHICH ONE (1) of the following is expected to provide-Instrument Air to Unit 2 from Unit 1? ; Unit 1 Crosstie valve 2SV-3015 AUTOMATICALLY open ! Unit 1 Crosstie valve 2CV-3004 AUTOMATICALLY close , MANUALLY open IA TO UNIT 1 CROSS CONNECT valve IA-5 MANUALLY open Unit 1 to Unit 2 Crosstie valves 2CV-3015 and 2CV- ,
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QUESTION: 041 (1.00) ,
J WHICH ONE (1) of the following describes the reason for the Transient CEA !
Insertion Limits?
' Ensures a MAXIMUM shutdown margin assuming an excess' steam demand accident at the beginning of core lif ;
t Ensures a MAXIMUM shutdown margin assuming the failure of'the highest reactivity worth single CE ; Ensures axial peaking factors are within acceptable level ;
' Ensures the potential effects of'a CEA ejection accident are limited to acceptable level .i
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QUESTION: 042 (1.00)
The following Reactor Coolant Pump conditions exist:
"A" RCP "B" RCP 1. RCP Vapor Seal Pressure 1600 psia 1250 psia 2. Pump Shaft Vibration 12 mils 14 mils 3. Pump Frame Vibration 2 mils 1 mil 4. RCP Controlled Bleedoff 1 gpm 4 gpm WHICH ONE (1) of the following actions is. required per 2203.025, "RCP ,
-Emergencies"?- ASSUME the reactor has been tripped. ~ ,
a. Secure "A" RCP due to HIGH RCP' Vapor Seal Pressur I RCP due to HIGH Pump Shaft Vibratio ~
b. Secure "B" c. Secure "A" RCP due to.HIGH Pump Frame Vibratio ,
d. Secure "B" RCP~due to'HIGH Controlled Bleedoff flo L l
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l SENIOR REACTOR OPERATOR Page.30-QUESTION: .043 (1.004
The~following conditions exist: Unit 2 is at 100% powe l Total Component Cooling Water flow is 250 gpm to RCP 2P32 . RCP 2P32A upper. seal cavity pressure is 1125 psi . RCP 2P32A middle seal cavity pressure is'1125 psi . Pressurizer pressure is 2250 psi WHICH ONE (1) of.the following describes the condition of RCP 2P32A?- ; Low Component Cooling : Water (CCW) flow exist Upper seal failure has occurre Middle seal failure has occurre Lower seal failure has occurre !
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QUESTION: 044 (1.00) {
The following conditions exist: , Unit 2 has tripped from 100% power and reactor power is DECREASIN + Emergency Boration was initiated at.0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> when CEAs #40 and #41 failed to fully inser . A Pressurizer' level control malfunction has resulted in a i
Pressurizer level of 95% and INCREASIN . Tavg is 565 degrees F. and DECREASING slowl . Pressurizer pressure is 2400 psia and INCREASIN .
, Operators are SLOWLY inserting CEA #40 manually and it will'be fully {
inserted at 0815 hour0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> . CEA #41 remains fully withdrawn and immovabl ; Operators desire to terminate RCS makeup to prevent RCS ,
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overpressurizatio i WHICH ONE (1) of the following conditions will allow termination of RCS makeup? < CEA #40 is fully inserte , Thirty (30) minutes of Emergency Boration has been completed, Pressurizer level reaches 100%.
t Pressurizer pressure reaches 2450 psi i f
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QUESTION: 045 (1.00)
WHICH ONE (1) of the following is the basis'for'the limit on boron concentration and temperature in the RWT according to Technical Specification: ,
3.5.4, " Refueling Water Tank"? j Prevents corrosive attack of system piping during maximum flow ;
conditions such as a boration even :; Ensures integrity of CVCS pump suction piping by presanting thermalj shock conditions during a boration even Prevents excessive motor current for the Charging pumps during a maximum flow condition such as a'boration even Ensures reactor will remain subcritical in the cold condition I
following mixing of the RWT and RCS water volumes during a boration'
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-QUESTION: 046 (1. 0 0 ) -
The following conditions exist: '
, P33A is is in PTL for maintenanc . 2P33B is supplying loop I CC , 2P33C is supplying loop II CC . A rupture occurs in loop II CCW, causing pressure to decrease to less than 80 psi WHICH ONE (1) of the following AUTOMATIC actions will result from the above conditions? CCW Loop I Crossover valves 2CV-5220 and 2CV-5230 clos ;
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~ CCW Loop II Crossover valves 2CV-5221 and 2CV-5232 clos CCW Loop II Crossover valves 2CV-5221 and 2CV 4232 ope ;
< ; An IMMEDIATE reactor trip on loss of CCW flow to the Reactor Coolant pump ,
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t-QUESTION: 047 (1.00)
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The following conditions exist: -
e 1. Unit 2 is at 100% powe l
' Pressurizer spray valve 2CV-4651 has failed to close on' deman . Operators are taking actions per 2203.028, "PZR Systems- i Malfunctions", Step WHICH ONE (1) of the following is the reason the control switch ~for 2CV-4651 ,
.is placed to OPEN for one (1) second then to CLOSE for five (5)' seconds? i This action OVERRIDES the Master Controller and allows the valve to be closed MANUALL I This action activates the mechanical hammer mechanism which assists )
in seating the valv This action activates the QUICK CLOSE circuitry for the valv This action opens additional CLOSE solenoids which provide greater air pressure to seat the valv .,
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SENIOR'REACTORLOPERATOR Page 34-QUESTION: 048 (1.00)
The following conditions exist: A steam line break exists upstream of the "A" Steam Generator MSIV-on Unit 2, MSIS has automatically initiate ,
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WHICH ONE (1) of the following conditions could result if a steaming flowpath from the unaffected steam generator is NOT established immediately following dryout of the affected steam generator? Rapid repressurization of the RCS and subsequent Pressurized. Thermal Shock (PTS) condition Inability to open "B" S/G MSIV due to pressure' difference created when affected steam generator reaches dryout condition A rapid INCREASE in T-cold of the UNAFFECTED loop resulting in an interruption of natural circulatio i A INCREASE in the core exit temperatures resulting in an interruption of natural circulation.
QUESTION: 049 (1.00)
WHICH ONE (1) of the following discriminates between a steam line break inside containment and a small break LOCA? Containment pressure RCS pressure Containment temperature RCS temperature ,
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i QUESTION: 050 (1.00)
The.following conditions exist: , brbine roll is in progres . 1800 rpm is selecte . Turbine speed is 1700 rpm and increasing rapidl WHICII ONE (1) of the following actions should be performed? Select 800 rpm on- the speed set-rpm selector, Select Close Valves on the speed set-rpm selector, Break vacuum and verify turbine is trippe Trip the reactor and verify the turbine is ti:1ppe ; ,
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. QUESTION: 051 (1.00)
TGIICH ONE (1) of.the'following is an indication that natural circulation exists following a '.oss of electrical power? (All temperatures are degrees JP. )
RCS Subcooling Thot Tcold CETs 4 *
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QUESTION: 052 (1.00)
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The.following conditions exist: Unit 2 has tripped from 100% power due to a. Loss of Offsite powe . Diesel generators are running with NO' Service Water (SW) coolin t
.WHICH ONE (1) of the following is the MAXIMUM time period that-the diesels can !'
run with NO SW cooling.WITHOUT suffering damage? Three (3) minutes !
o Ten (10) minutes , Fifteen (15) minutes Diesels can run indeflyiral.y since they provide their own cooling *
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1-QUESTION: 053 (1.00) '
The following conditions exist:
, The control room operator has received a report of'a small-fire in- l the 317' elevation of the Auxiliary Buildin .
. The individual reports the fire is contained in the corner.of the .
2T20B room where oily rags have been stored incorrectl ! The same individual reports there is no. smoke, the area is well
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ventilated, and he has an ABC Dry Chemical Extinguishe . The individual has requested permission to extinguish theLfir E WHICH ONE (1) of the following conditions prevent this authorization? The fire is caused by a hazardous chemica !
I The potential for smoke exists and the individual has no respiratoryf '
equipmen j The extinguisher is incorrect for this type of fir !
' The fire is in a radiological control area (RCA).
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SENIOR' REACTOR' OPERATOR 'Page 37~
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QUESTION: 054 (1.00) a-WHICH ONE (1) of the following is an indication that is required by. Technical'
Specifications to be displayed at the Remote. Shutdown Panel (2C80) ? {
a. Reactor Trip Breaker Indication b. Steam Generator Pressure c. RCS Subcooled/Superheat Monitor
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d. Refueling Water Tank Level j
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QUESTION: 055 (1.00) i
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WHICH ONE (1) of the following operator actions is required during an ,
evacuation of the Unit 2 control room due to a fire in the cable spreading room per 2203.014, " Alternate Shutdown"? ; Trip two (2) Reactor Coolant pumps (one in each loop) and leave two l (2) runnin Trip ALL f our (4) ' Reactor Coolant pump l ~
Trip the "B" Loop Reactor Coolant pump Leave ALL R? actor Coolant' pumps running if seal water can be established within five (5) minute .
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QUESTION: 056 (1.00) .;
WHICH ONE (1) of the following conditions. represents a LOSS of Unit 2 i Containment Integrity? Unit 2 is in REFUELING Mode, Equipment Hatch closed with ONLY four (4) bolts., d
- One (1) Air Lock door is OPE , Containment Purge is in progres _l An electrical penetration's seals are removed for repair !
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ISENIOR REACTOR OPERATOR Page 38- e i
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QUESTION: 057 (1.00)- .!
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The following conditions exist: Unit 2 has tripped due to a loss of Feedwate f Operators have entered Functional Recovery Guideline WHICH ONE (1) of the following is the criteria for going to HR-4, "Once :
Through Cooling" to provide core cooling? RCS Thot is increasing uncontrollabl ;
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' RCS pressure is increasing uncontrollabl BOTH Steam Generator levels decrease to less than 70 inche f
' ' RVLMS LVL 03 indicates voiding.
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QUESTION: 058 (1.00)
WHICH ONE (1) of the following is the Technical Specification basis for the-requirement to cooldown Unit 2 to below 500 degrees F within six (6) hours :
when specific activity of the coolant exceeds 1.0 microcurie / gram DOSE l EQUIVALENT I-131 for greater than'48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />? ;
! Reduces the dissolution of fission products in the reactor. coolan Increases reliability of the data collected for actual' iodine (
determinatio ! Reduces the rate of release if a steam generator tube rupture should l occu , Increases coolant density sufficiently to enable self shielding thereby reducing on-site exposur l j
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SENIOR REACTOR OPERATOR 'Page 39'
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QUESTION: 059 (1.00)
The following conditions exist: Unit 2 is at 30% power and increasing at 3% per hou . CEAs are in MANUAL SEQUEN'I'IA . GROUP 5 CEAs were withdrawn from 50 to 60 inche . At 60 inches Group 5 CEAs continued stepping ou i WHICH ONE (1) of the following actions are required to be performed FIRST per !
2203.003, "CEA Malfunction"'r ! Initiate emergency boration per 2203.032, " Emergency Boration".
- Attempt to stop CEA movement by placing MODE SELECTOR switch to the .
OFF positio ! TRIP the reactor and go to 2202.001, " Standard Post Trip Actions". De-Energize both MG sets by opening breakers 2B712 and 2B81 >
QUESTION: 060 (1.00) ,
The following plant conditions exist: [
' Mode 3, Trip from 100% power occurred 5 minutes ag i CEAs #40 and #41 are fully withdraw . Charging pump suction piping has rupture WHICH ONE (1) of the following operator actions should be performed under- !
these conditions?
, Use auxiliary spray and emergency borat Emergency borate via HPSI by opening 2CVC-11 j Lower RCS temperature and commence a normal boratio Lower RCS pressure and emergency borate via HPS !
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SENIOR REACTOR OPERATOR Page 40 .
QUESTION: 061 -(1.00)
Considering Procedure 2202.009, " Functional Recovery Procedure", _ WHICH ONE - (1) !
of the following Safety Functions has the HIGHEST order of priority? RCS Inventory Vital Auxiliaries Core Heat Removal Containment Integrity i>
QUESTION: 062 (1.00) ,
The following plant conditions exist: +
' Unit 2 has tripped from 100% powe . SIAS has actuate . RCS pressure is 1300 psia and DECREASING slowl ~ Pressurizer level 1s 100%. ' RCS Thot-(Th) is 557 degrees _ . Containment pressure is 16 psia and' INCREASING slowl WHICH ONE (1) of the following events has occurred?
- Main Steam'line break inside Containment Inadvertent SIAS
, RCS cold leg break ; Pressurizer vapor space break f
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SENIOR REACTOR OPERATOR Page 41'
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QUESTION: 063 (1.00)
WHICH ONE'(1) of tne following'provides MAXIMUM cooling to the core for.the
- first twelve-(12) hours during a SMALL BREAK'(300 gpm with RCS pressure ;
falling below 1250 psi) Loss Of Coolant Accident'(SBLOCA)?_
+
-! Reflux boiling l Break flow' cooling Natural Circulation Forced Circulation ,
3 QUESTION: 064 (1.00)
WHICH ONE (1) of the following parameters is used to determine if adequate _
core cooling exists following a small break loes of coolant accident-(SBLOCA)'
per 2202.003; " Loss Of Coolant Accident, Safety Function Status Check"?. RCS Thot and average CET temperatures are less than superheate ! Loop delta T is less than ten (10) . degrees ,
, CET temperatures less than 1000 degrees' RCS Tcold is less than' ten (10) degrees F. superheate i a
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I SEWIOR REACTOR OPERATOR Page 42-
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QUESTION: 065 (1.00)
WHICH ONE (1) of the following is the reason simultaneous Hot and. Cold Leg I
' Injection is NOT established prior to two (2) hours following a' loss of l
. coolant accident - (LOCA) ? To avoid possible entrainment of SI flow in the Hot Leg due to steam 1 flow which is substantial prior to two . (2) hour Boron precipitation is not a problem prior to two -(2) hours due'to-the large steam flow through the Hot-Leg out the brea Maximum Cold Leg flow is needed-to cool the core due to the high amount of decay heat _ prior to-two (2) hour To allow time for vessel head cooling to prevent the possibility for _
void formation in the vessel head which would substantially reduce-core cooling.
QUESTION: 066 (1.00)
The following conditions exist: A large break LOCA condition exist . RCS pressure is 140' psi ' CETs indicate 267 degrees . LPSI pump 2P-60A is injecting into the RC . HPSI pumps 2P-89A and 2P-89B are injecting into the RC :WHICH ONE-(1) of the following indicates the lowest acceptable total Emergency ,
Core Cooling System flow per 2202.010, " Standard Attachments"? (References attached.) gp ' gpm gpm 3 gpm
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SENIOR REACTOR OPERATOR Page 43 ,
.f QUESTION: 067 (1.00)
.The following conditions exist after a Unit 2 reactor trip from 100% power:
1. Pressurizer pressure is 450 psia and DECREASIN . Pressurizer level is 0%.
3. CETs indicate 370 degrees . All ESFAS Actuations required have actuate WHICH ONE (1) of the following is the MINIMUM operator action for the above conditions per 2202.001, " Standard Post Trip Actions"? (References are provided.)
a. Trip RCPs 2P32A and 2P32 b. Trip RCPs 2P32C and 2P32 .
c. Trip RCPs 2P32A and 2P32C :
d. Trip ALL RCP .
A QUESTION: 068 (1.00)
WHICH ONE (1) of the following is the MINIMUM condition that defines' a " Harsh" ;
containment?
a. Containment temperature is 200 degrees b. Containment temperature is 150 degrees F. and pressure is greater than 8.5 psi c. Containment humidity is saturate i l
d. Containment humidity is saturated and Containment radiation ~ levels i indicate 1 X 10E3 R/h '
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SENIOR REACTOR OPERATOR Page144 ej QUESTION: 069 ( 1. 0 0 )'-
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WHICH ONE (1) of the following temperature indications-is preferred for ,
t monitoring RCS temperature following a loss of Shutdown-Cooling. flow? LPSI pump discharge monitor (T5096) >
' RVLMS ATS
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QUESTION: 070 (1.00)
LThe'following conditions exist: Unit 2 is in REFUELIN . Shutdown Cooling System is in servic ! One LPSI pump is operatin . Unit 2 is drained down for nozzle dam. installatio WHICH ONE (1) of the following Shutdown Cooling (SDC) parameters is an indication of a loss of adequate core heat removal per 2203.029, " Loss of-Shutdown Cooling"?
^ Shutdown cooling flow is 1500 gp ..
I Component Cooling Water (CCW) flow to the shutdown cooling 7 heat ,
exchangers is 1000 gp ~
RCS Local Level indicator indicates 36 inches from the bottom of the- '
hot le ! RVLMS' indicates sensors 04 through 08 are WE ,
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SENIOR REACTOR OPERATOR Page 45 *
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t QUESTION: 071 (1.00)
WHICH ONE (1) of the following is the reason MG set supply breakers 2B712 and 2B812 are opened for a minimum of ten (10) seconds before re-closing when responding to an Anticipated Transient Without Scram (ATWS)?
t To assure all CEAs have sufficient time to fall into the core, To allow sufficient time for the TCBs to ope To allow sufficient time for the MG sets to coast down and overcome the flywheel devic To prevent overcurrent trips when breakers are re-close QUESTION: 072 (1.00)
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The following plant conditions exist: Unit 2 is in REFUELIN I Start-up channel "A" is out of servic . Start-up channel "B" is OPERABL ;
i Core alterations are in progres i
! WHICH ONE (1) of the following MINIMUM Technical Specification Action
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. Statements should be implemented? i Suspend all operations involving positive reactivity changes, Determine the RCS boron concentration at least every twelve (12)
hour Immediately evacuate containment until the audible alarm from Channel "A" is returned to servic Perform CHANNEL FUNCTIONAL TEST on Channel "B" within one (1) hou j
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' SENIOR REACTOR OPERATOR Page 46 ,
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- QUESTION: 073 (1.00)
The following conditions exist: Unit 2 has reduced power to 15% due to a Steam Generator tube lea . Letdown has been isolate . One (1) charging pump is runnin . Pressurizer level is DECREASING slowl ~
WHICH ONE (1) of the following is a valid method to determine the amount of primary to secondary leakage? Use Charging flow and Letdown flow mismatch, Use SG Tube Leak N-16 monitor Use Charging flow minus Controlled Bleedoff flo , Use Main Steam Line' Radiation monitor QUESTION: 074 (1.00)
Unit 2 is being shutdown to HOT STANDBY due to a steam generator tube lea WHICH ONE (1) of the following indicates the MINIMUM conditions necessary for-a manual reactor trip per 2203.038, " Primary to Secondary Leakage."? When all available charging pumps are running, letdown has been i isolated, and pressurizer level can no longer be controlled at setpoin ! When all available charging pumps are running and letdown has- i reached minimum flo l
..) When letdown flow combined with the tube rupture flow exceeds 132 !'
GPM with three (3) charging pumps runnin When charging flow reaches 132 GP j
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SENIOR REACTOR. OPERATOR Page 47
. QUESTION: 075 (1.00)
The following conditions exist:
~ Unit 2 has tripped from 100% power due to a Steam Generator tube' ,
rupture on the "B" Steam Generato . Operators have throttled HPSI flow to. assist in' recovery operation . RCS pressure is 1800 psi WHICH ONE .(1) of the following conditions will require operators tx) restore FULL HPSI flow?
- Margin to saturation is 40 degrees Pressurizer level is 25%. RVLMS sensor four (LVL 03) indicates WE Steam Generator "A" level is 5% and increasing with EFW flow of 500 gp :
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SENIOR REACTOR OPERATOR Page 48 QUESTION: 076 (1.00)
The following conditions exist: Unit 2 has been MANUALLY tripped following a rupture of Steam Generator "B". SIAS has automatically actuate . All RCPs are secure . RCS pressure is 1000. psi . CETs indicate 450 degrees . Pressurizer level indicates 26%. RVLMS LVL 01 indicates WE WHICH ONE (1) of the following actions must be performed prior to resuming RCP 2P32C operation per 2202.004, " Steam Generator Tube Rupture"? Seal injection must be supplied to RCP 2P32 t RCP 2P32B must be started first to establish Pressurizer Spray flo RCS subcooling must be increased to within allowable RCP restart'
limits, Pressurizer level must be increased to within allowable RCP restart limit l l
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SENIOR REACTOR OPERATOR Page 49 QUESTION: 077 (1.00)
The following conditions exist: Unit 2 has tripped from 100% power when ALL Feedwater is los ; The Turbine Driven Emergency Feedwater pump 2P7A can be returned to '
servic . Steam Generator "A" level indicates 20%. l Steam Generator "B" level indicates 46%.
WHICH ONE (1) of the following is the correct method for re-establishing feedwater flow to the Steam Generators? Initiate feedwater to the "A" Steam Generator at the maximum flow rate possible for the first five (5) minute Initiate feedwater to'BOTH "A" and "B" Steam Generators at the naximum flow rate possible for the first five (5) minute , Initiate feedwater slowly to "B" Steam Generator at a maximum flow rate of 150 gpm for the first five (5) minute , Initiate feedwater slowly to BOTH "A" and "B" Steam Generators at a maximum flow rate of 150 gpm for the first five (5) minute l
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QUESTION: 078 (1.00)
The following conditions exist: 1 Unit 2 has been manually tripped due to a loss of ALL Feedwate . Operators are initiating step 3 of 2202.006, " Loss of Feedwater" and are tripping ALL RCP S WHICH ONE (1) of the following is the basis for tripping all Reactor Coolant-Pumps as per this step in the procedure? To reduce heat input into the reactor coolant syste To reduce Reactor Coolant System pressur I To reduce thermal stress to steam generator To reduce-tube to shell delta pressure.in the steam generators.-- !
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- SENIOR REACTOR OPERATOR Page:50
'1 QUESTION: 079 (1.00)
LWHICH ONE (1) of the following is the MAXIMUM time that the Vital 125 VDC-batteries 2D-11 and 2D-12 can be expected to carry.the vital loads following ~1oss of the battery chargers? hours hours hours ,
i hours P
QUESTION: 080 (1.00)
The following conditions exist: Unit 2 is at 100% powe . Pressurizer level control is selected to Channel "A". Proportional Heater Bank handswitch is in AUTOMATI j l WHICH ONE (1) of the following is the affect of a loss of power supply 2Y1 on-the' Pressurizer Level Control System? Channel "B" instrumente FAI Proportional and Backup Pressurizer heaters are ENERGIZE . Proportional and Backup-Pressurizer heaters are DE-ENERGIZE Pressurizer level indication at the Remote Shutdown Panel is' LOST.
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SENIOR REACTOR-OPERATOR Page 51 QUESTION: 081 (1.00) !
The following plant conditions exist: Core alterations are in progress on Unit . A spent fuel assembly is in the hoist box on the Main Refueling bridge, withdrawn 30 inches from the cor . A Station Blackout then occur WHICH ONE (1) of the following actions should be performed? Leave the fuel assembly and evacuate containment immediatel ,
l Hand jack the fuel assembly back into-the core, j Hand jack the fuel assembly into a storage rac Hand jack the fuel assembly completely in[o the hoist box,.then hand:
jack to the spent fuel poo l l
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l QUESTION: 082 (1.00)
WHICH ONE (1) of the following is the MINIMUM level required in the Steam Generators in order to sustain Natural Circulation Cooling (NC) ? , inches inches inches inches ~;
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-SENIOR REACTOR OPERATOR' Page.52 l QUESTION: 083 (1.00)
WHICH ONE_(1) of the following valves will fail CLOSED on a loss'of Instrument Air pressure? CV-0634,-Hotwell Makeup valve CV-1051, Steam Generator "B" Upstream Dump valve c, 2CV-0740, FW Loop "B" Main Reg valve CV-5091, SDC HX Flow Control valve
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i-QUESTION: 084 (1.00)
WHICH ONE (1) of the following jobs can be performed under an Operations Standing Radiation Work Permit (RWP)? An entry into a High Rad.iation Area where accumulated dose is expected to be 75 mre An entry into a High Contamination Area where accumulated dose is expected to be 10 mre A job which requires opening- a potentially contaminated steam lin A job which requires use of respiratory protection'due to loose' :
contaminatio 't
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SENIORfREACTOR OPERATOR 'Page 53
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- QUESTION: 085 (1.00)
WHICH ONE-(1) of the'following atmospheric conditions defines an acutely disabling atmosphere? Oxygen concentration is 20%. Ammonia concentration is 5 PP Chlorine concentration is 5-PP Hydrazine concentration is .05 PP re QUESTION: 086 (1.00)
The following conditions exist: A planned job is being conducted in a Confined Spac i Several crews are working the job on a rotating basis approximately
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every two (2) hour . The job is to last around the clock for two (2) day ,
WHICH ONE (1) of the following is the MINIMUM frequency required for issuing a' ,
Confined Space Entry Permit? The permit is issued once by Planning and Scheduling prior.to.the- ' :
start of the jo The permit is issued once when the first crew enters the -job sit . A new permit is issued every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if ventilation'is maintained, A new permit is issued-each time a crew enters the job' site, a
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. SENIOR. REACTOR OPERATOR Page 54
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I QUESTION: 087 (1.00)
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WHICH ONE (1) of the following is designated to perform an emergency rescue o an individual in a Confined Space?
- Any individual who has received training as an ATTENDAN Any individual who has received training to make confined' space-entrie Any member of the Bechtel Emergency Tea Any member of the Pope County Rescue Tea ,
QUESTION: 088 (1.00)
The following conditions exist: Unit 2 is operating at 100% powe . The latest Chemistry sample indicates that the RCS has a dissolved Oxygen concentration of 1500 pp WHICH ONE (1) of the following MINIMUM actions is applicable for these conditions? The Action Level 1 limit has been exceeded which requires Oxyge concentration to be reduced to less than five (5) ppb within seven (7) days, The Action Level 2 limit has been exceeded which. requires Oxygen concentration to be reduced to less than five (5) ppb within twenty four (24) hour The Action Level 3 limit has been exceeded which requires' Oxygen concentration to be reduced to less than one hundred (100) pp within twenty four (24) hours, The Action Level 3 limit has been exceeded which requires th reactor be shutdown immediately and RCS temperature reduced to less-than 250 degrees F. as soon as possibl .
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SEMIOR REACTOR OPERATOR Page 55
' QUESTION: 089 (1.00)
WHICH ONE (1)'of the following boundaries is challenged the mostLby a chloride-excursion in the RCS? Fuel cladding
, RCS letdown piping RCS cold leg piping 4 Containment liner -
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QUESTION: 090 (1.00)
WHICH ONE (1) of the following is an indication that an electrical _ hand tool issued from the toolroom on 12-13-1993 was recently inspected and is safe for-use? ANY piece of equipment issued from the toolroom is assumed to be safe for us The tool will be' tagged with a orange tag, The tool's cord will be marked-with a continuous ring of orange electrical tape behind the plu The tool will have an orange inspection sticker affixed to it's ,
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1, SENIOR-REACTOR OPERATOR' Page 56 .
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QUESTION: 091 (1.00)
'WHICH ONE (1) of the following designates a CONTINUOUS ACTION STEP in'an Emergency Procedure? An asterisk precedes the ste .
' ' An solid square precedes the ste ' Step number is in bracket Step number is BOL ,
QUESTION: 092 (1.00) -
WHICH ONE (1) of the following is the MAXIMUM time-allowed'to report an -
UPGRADE in an event classification to the NRC? five (5) minutes fifteen (15) minutes iq thirty (30) minutes t sixty (60) minutes-I Y
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SENIOR REACTOR OPERATOR Page 57 QUESTION: 093 (1.00)
The following conditions exist:
" Hold Cards are being removed from equipment in the Auxiliary Buildin . A Licensed Control Room Operator is in contact with the crew in the Auxiliary building by telephon WHICH ONE (1) of the following is the MINIMUM amount of documentation needed on the Hold Card Record Sheet if the tag removal is being documented PER-TELECON? The Licensed Operator needs only to initial the sheet with his own initials and enter Telecon into the Remarks Section of the Hold Card Record Sheet, The Licensed Operator needs only to initial the sheet with the initials of the person removing the tag The Licensed Operator needs to initial the sheet with his own initials and those of the person removing the tags and enter Telecon into the Remarks Section of the Hold Card Record Shee The Licensed Operator needs to initial the sheet with his own initials and the Shift Supervisor must initial those of the person removing the tag l l
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SENIOR REACTOR OPERATOR Page 58 ,
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QUESTION: 094 (1.00)
The following conditions exist: , A crew is preparing to conduct MOV testin . They find a HOLD CARD tagging the breaker OPEN for the valve they are to tes WHICH ONE (1) of the following actions should be taken next? Install the MOV TEST CARD over the HOLD CARD and proceed with MOV testin , Proceed with MOV testing under protection of the HOLD CARD and a-MOV TEST card is not neede Install the MOV TEST CARD but contact the Shift Supervisor for-further instruction Contact the Shift Supervisor for authorization to remove the HOLD CARD prior to installing the MOV TEST CAR QUESTION: 095 (1.00)
WHICH ONE (1) of the following represents an INTENT Change in a procedure? Deleting a step that closes a valve that has been removed by a Design Chang Correction to a typographical error in an AC ,
' Deleting a step that requires a hold-poin Modification to step sequence.
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A SENIOR REACTOR' OPERATOR Page 59
QUESTION: 096 (1.00)
The following crew members are present-to assume control of the shift while the Unit is operating at 100% power: , One (1) SRO Three (3) ROs One (1) Waste Control Operator One (1) AO ' One (1) STA WHICH ONE (1) of the following additional crew members is needed to complete' MINIMUM Shift Complement per 1015.001, " Conduct of_ Operations"? ; One (1) SRO One (1) RO .
i One (1) Waste Control Operator One (1) AO
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QUESTION: 097 (1.00)
WHICH ONE (1) of the following is the MINIMUM level of approval'needed to
"N/A" a procedure step in an approved operating procedure? Two (2 ) Licensed Reactor Operators Two (2) Licensed. Senior Reactor Operators Shift Engineer AND Control Room Superviso Shift Superintendent
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SENIOR' REACTOR. OPERATOR Page 260 QUESTION: 098 (1.00)
WHICH of the following individuals may be issued a key to the Containment Personnel Hatch? A qualified Reactor Operator A Security Officer A qualified Senior Reactor Operator The Health Physics Supervisor
QUESTION: 099 (1.00)
The following conditions exist:
1. Unit 2 is performing Refueling Operation . The Shift Supervisor needs a control room operator for the upcoming evening shift on a Saturday night to replace an 111~ crew' membe .
WHICH ONE (1) of the following is the PREFERRED operator to fill this vacancy ,
per 1015.001, " Conduct Of Operations"?
! Operator "A", who has worked his normal dayshift, is willing to hold over on to the evening shift but he states that he came in one hour-early to relieve an operator for a doctors appointmen Operator "B", who has' worked his normal dayshift (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />), is willing to hold over on to the evening shift but he states that he
. worked eight (8) hours on the evening shift the day before after ,
'
working day shif Operator "C", who works relief dayshift, is willing to work the
-
evening shift but states that he worked an overtime shift.two (2)
' days ago and it would be his third overtime shift this weeki Operator "D", who works the midnight shift, is willing to cnme'in and. work the evening shift, but states he held over from his previous shift for a'one (1) hour training clas ;
,
, , - -
r -.
.
' SENIOR REACTOR ONERATOR Page 61
'
-QUESTION: 100 (l'. 0 0 ) .
WHICH ONE (1) of the following will meet the MINIMUM number of Fire Brigade Trained personnel that are required to respond to a fire.on Unit 2 per Administrative Procedure 1015.007, " Fire Brigade Organization and-Responsibilities", (including Brigade Leader) ? , Two (2) operations-personnel from Unit 2 and one (1) security representative Two (2) operations personnel from Unit 2, one (1) security representative, and one (1) operations representative from Unit 1 Two (2) operations personnel from Unit 2, Two (2) security-representatives, and one (1) operation's representative from Unit 1 Two (2) operations personnel from Unit 2, Two (2) securit representatives, and two (2) operation's representatives-frbm Unit 1 l
,
l i
l l
l l
.]
!
(*******,, END-OF EXAMINATION ******,,,,)
l I
l
- _ . . . - - - - - --_- -. ... .- -. _ .
, ._ _ .__ ._ . . - . . . . . - _ . . _ _ . - . . . _ _ . . _ . . . . . _ - . _ . . . _ _ . . .-
&
- SENIOR REACTOR OPERATOR Page 62
.
. ANSWER: 001 (1.00) , (+1.0] ;
REFERENCE: +
1.
2203.032, " Emergency Boration", page . AA52102-003, " Chemical & Volume Control System", Objective i KA 004000K205 (2.7/2.9) 004010A207 (3.8/3.9) 004010A403 (3.9/3.7)
004010A403 004010A207 004000K205 ..(KA's) ;
,
ANSWER: 002 (1.00)
b'. [+1.0)
- REFERENCE: AA52002-014, "Excore Nuclear Instrumentation", Objective 14.3f, page 29, KA 015000K106 (3.1/3.4)
015000K106 ..(KA's)
i ANSWER: 003 (1.00) l
, [+1.0)
'
= REFERENCE: AA-52002-012, " Control Element Drive' Control", Objective 12,6_,-page 1 . KA 001000K105 (4.5/4.4)
001000K105 ..(KA's) '
- ANSWER:
-
004 (1.00)
. [ + 1. 0 ) - ,
,
-l i
, ,, ... ,
.. . . . - . , . .. - - . _ - ~ . - . - . ~ .
.. . ~ . - . . . . - . - .-.
-
sSENIOR REACTOR' OPERATOR Page 63 l
l-REFERENCE: l 'AA52002-001, " Reactor Coolant System", Objective 1.6, page.4 . KA 003000A402 (2.9/2.9)
'
l
-)
003000A402 ..(KA's)
l
. ANSWER: 005 (1.00)
, (+1.0)
i-REFERENCE: t AA52002-001, " Reactor Coolant System", Objective 1.7, page 41, KA 003000G013 ' (3. 6/3. 7) , 003000G010 (3.3/3.6)
003000G010 003000G013 ..(KA's) l J
r (1.00)
'
ANSWER: 006 d' . (+1.0)
i REFERENCE: l .AA-52002-013, " Engineered Safety Features Actuation System", Objective 13.2B, page 1 . KA 013000A301 (3.7/3.9)
013000A301 ..(KA's)
.
.
ANSWER: 007 (1.00)
P [+1.0]
REFERENCE: g 1.- AA520021037, " Saturation Margin Monitor", Objective 37.8, page . KA 017000G010 (2.6/2.9)
.i 017000G010 ..(KA's)
r
, . . .- - . . . . . . . . . .- ., . - _ - .. _
SENIOR 2 REACTOR OPERATOR Page 64 i
ANSWER: 008 (1. 0 0 ) ' [+1.0)
.. REFERENCE: STM-2-09, " Containment' Cooling and Purge System", page ii AA52002-027, " Service Water System", Objective 27.2 . .KA 022000K101 (3.5/3.7) -
-022000K101 ..(KA's)
,
ANSWER: 009 (1.00) ' [+1.0) '
REFERENCE: i AA32003-021, " Condensate and Feedwater System", Objective 21.6,.page 4 * KA 059000G010 (2. 9/2. 9 )
059000G010 ..(KA's)
f ANSWER: 010 (1. 0 0) ' [+1.0)
,
'
REFERENCE: AA32003-021, " Condensate and Feedwater. System", Objective 21.3h,.page
_ 31.'.
.2.- KA 059000K419 (3.2/3.4)
.!
t 059000K419 ..(KA's)
.
<'
_ , . . - . _ , - . . _ - --. _ .__..._.______________________z______z___'
, . . - . . - ~ . .. , . - .- . - - . - . - - . . - . . . . . .. .. . - _ . - ... - .... .
i
!
.
.
I
. SENIOR REACTOR OPERATOR Page 65
' ANSWER: 011' (1.00)- -l l [+1.0) i REFERENCE:
AA 42002-021, " Emergency'Feedwater System", Objective ~21.2B,-page ' . KA 061000K401 (3.9/4.2)
061000K401 ..(KA's)
i
'
ANSWER: 012 (1.00) [+1.0)
-
REFERENCE: ]
-i
,
' AA-520022013, " Engineered Safety Features Actuation System", Objective 13.2D, page 2 . KA 061000K414 (3.5/3.7)
061000K414 ..(KA's)
,
. ANSWER: 013 (1.00) [+1.0)
REFERENCE: AA42002-021, " Emergency Feedwater System", Objective 21.3C, page 1 .: 101 061000A303 (3.9/3.9) '
'
061000A303 ..(KA's)
. ANSWER: 014 (1.00) [+1.0)
, , . - - _ . - . . -_. - -. __ - . - ,. _ --
. . .. _. . _ m ._ .. _. . . _ i
- SENIOR REACTOR OPERATOR - Page 6 '
,
REFERENCE:
' AA-52002-033, "Radwaste System", Objective 33.4, page 2 . KA 068000A302 (3.6/3.6) !
068000A302 ..(KA's)
,
-!
ANSWER: 015 (1.00)
i [+1.0)
,
REFERENCE: '
.i
~ STM-2-52, " Liquid Waste System", page . AA-52002-033, "Radwaste System", Objective 3 . KA 068000K107 (2.7/2.9)
068000K107 ..(KA's)
i
ANSWER: 016 (1.00) ; [+1.0)
-
REFERENCE: .010, " Unit 2 Waste Gas Analyzer. Operation", Attachment "A",.page 2 . AA-52002-033, "Radwaste System", Objective 33.4, page 3 . KA 071000K504 (2.5/3.1) , 071000A429 (3.0/3.6) i
,
,
071000A429 071000K504 . . (KA's)
ANSWER: 017- (1.00) [+1.0} *
,
s
REFERENCE: AA-52002-018, " Radiation' Monitoring System", Obj ective: 18.5, page . KA 072000G010 (2.8/3.0) 4 072000G010- ..(KA's)
R-e , - + . . ~ . . .- , - - ,c .. +.v., ,
. . _ _ . ._ .. . _ _ _ . . _ _. . . _ . _ .. _
'
SEMIOR REACTOR OPERATOR Page 67 i
ANSWER: 018 (1.00) [+1.0)
REFERENCE: AA52002-001, " Reactor Coolant System",. Objective 1.2, page 1 . KA 002000K108 (4.5/4.6)
002000K108 ..(KA's)
ANSWER: 019 (1.00)
. '
[+1.01 s
-
4 REFERENCE: Technical Specifications 3.4.6.2, " Reactor Coolant System' Leakage", page 3/4 4-1 . AA52002-001, " Reactor Coolant System", Obj ective 1.1 . KA 002000G011 (3.3/4.0)
NOTE: Answer 10. 5 - ( 2 . 5 +2 . 2 +2 . 5 + 1. 2 ) - 2.1 gpm unidentified which is.> .
'
1.0 gpm unidentified limi !
002000G011
'
..(KA's)
,
,
(1.00)
'
ANSWER: 020 [+1.0)
REFERENCE: , AA52002-004, " Emergency Core System", Objective 4.9A, page-1 .
,
KA 006020A107 ( 3 ~. 5 /3 . 7 ) !
006020A107 ..(KA's) f
1 r
, . . - , , . - . , _. - . , . . , ..n , .
. - . . --, , , ,
. . . . ,. . . . _ . . . _ . - ._ . . - ....-.~.......___.__ .. . ... .,
'
' SENIOR-REACTOR.OPERATO'R Page 60'
ANSWER: -021 (1.00) [+1.0]
I
REFERENCE: ,
l'. -AA52002-004, " Emergency Core System", Objective 4.4,.page' '2. . KA 006000K603 (3.6/3.9)
006000K603 ..(KA's)
i
,
< ANSWER: 022 (1.00) [ + 1.' 0 ] .
.
REFERENCE:
, .005, " Pressurizer Operat. don", page . AA52102-002, ~STG2A, Objective 1.1, Attachment A, page 32 of 45, AA52002-001, " Reactor Coolant System", Objective 1.11, page 6 . KA 010000A402 (3. 6/3.4) , 010000A101 (2. 8/2. 9 )
+
010000A101 010000A402 ..(KA's)
,
!
ANSWER: 023 (1. 0 0 )' .[+1.0)
,
. REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.9, page 5 . KA 011000K605 -l(3.1/3.7)
011000K605 ..(KA's)
,
ANSWER: 024 (1.00) , [+1.0)
,
e n , , , w w- ,w. .,, -,. -m, .e -, , e n .-e>,
<
,
i 1 SENIOR REACTOR OPERATO .Page 69 REFERENCE: AA-52002-043, " Diverse Scram System", Objective 43.10, page . I 2.- KA 012000K201 (3.3/3.7), 012000K107 (3.2/3.2) )
'
012000K103 (3.7/3.8) 012000A407 (3.9/3.9)
012000A407 012000K103 012000K107 012000K201 ..(KA's).
ANSWER: 025 (1.00)
c.- [+1.0] ,
!
REFERENCE: AA52002-037, " Saturation Margin Monitor", Objective 37.6, page 8, KA 016000A302 (2.9/2.9) ,#
.
,
,
016000A302 ..(KA's)
ANSWER: 026 (1.00)
c '. [+1.0]
!
REFERENCE: ,
. AA42002-007, " Containment Spray System", Objective . STM 2-08, " Containment Spray System", page . KA 026000K201 (3.4/3.6) .;
026000K201 ..(KA's)
ANSWER: 027 (1.00) .
. I+1.0)
,
i
.
+
,
B
.. ._ ., - . ... - -
.-. < . ..
f
.-
'
SENIOR REACTOR OPERATOR Page 70
,
LREFERENCE:
,
'
' AA-52002-013, " Engineered Safety Features Actuation System", Objective
'13.2D , page.1 .
.
! KA 026000A301 (4. 3/4. 5) , 026000K101 ( 4 . 2 /4 .'2 )
026000A301- 026000K101 ..(KA's) .
t
" ANSWER: 028 (1.00) , [+1.0)
REFERENCE:
.
' STM-2-09, " Containment Cooling and Purge. System", page . KA 029000K104 ( 3 . 0 / 3.1)
029000K104 ..(KA's)
- ANSWER: 029 (1.00) ,
. {+1.0)
REFERENCE: , "Spes '- Fuel System", page .' - .2001-008, L! 'tive . Ka 033000G010 , 2/2.5)
033000G010 ..(KA's) ,
ANSWERi 030 (1.00) i [+1.0)
4 :
i
.
h
..
- . . . -
. . . ,
^
..,
l l SENIOR REACTOR OPERATOR Page 71
,
!
1 REFERENCE: -1 i
1 AA52102-015, "Feedwater' Control System", Objective 4, page.1 .
l l KA 035010A301 (4.0/3.9) J 035010A301 ..(KA's)
.,
' ANSWER: 031 (1.00) [+1.0)
. REFERENCE:
' AA52102-015, "Feedwater Control System", Objective 7, page 2 . KA 035010A203 (3.4/3.6) -1 035010A203
>
..(KA's)
!
'
ANSWER: 032 (1.00) [41.0)
i
'
REFERENCE: STM-2-15, " Main; Steam", page .
+
2.- 2106.016, " Condensate and Feedwater Operation", Supplement 1,-page 116, KA 039000K408-(3.3/3.4) j a
039000K408 . (KA's) ,
t ANSWER: 033 (1.00)
.i [+1.0)
i
.1
'f P
!
1-4 i
. - . . - - - . -
- *
. . . - . . .. .. - . . . - . - - . . . . . ~ ~ . , , - . . - .- - .- .
-
..-.-.....-n .
+
.
' SENIOR REACTOR OPERATOR -Page 72 l, i
<
_. REFERENCE:
1~. AA52002-032, " Control Room and ESF Equipment Ventilation System", >
Objective 32.2, page . .KA 073000G007 (2.9/3.0)
073000G007 ..(KA's) .;
ANSWER: 034 (1.00) [+1.0] .
REFERENCE:
i AA52002-044, " Shutdown Cooling System", Objective 44.2', page '; KA 005000K110 (3.2/3.4) {
005000K110 ..(KA's) ;
,
ANSWER: 035 (1.00) [+1.01 REFERENCE: AA52002-001, " Reactor Coolant System", Objective 1.8, page 62'. KA 007000A301 (2.7/2.9)
007000A301 ..(KA's)
ANSWER: 036 (1.00) [+1.0)
?
.
..
.
I i
.
i
.
.
,
t ,
- -_ _ ... .,. , . . . _.
s
. SENIOR: REACTOR OPERATOR Page 73-
'l
REFERENCE: : AA42002-007, " Containment Spray System", Objective 7.6, page 2 . KA 027000G007 (3.2/3.4)
027000G007 ..(KA's)
ANSWER: 037 (1.00) [+1.0) '
REFERENCE:
1 AA52002-050, " Containment Combustible Gas Control", Objective 50.7,-page ,
2 '. KA 020000G010 (3.0/3.2) '
~028000G010 ..(KA's)
',
- ANSWER: '038 (1.00)- [+1.0) '
- REFERENCE:
' AA-52002-006, " Fuel Handling Equipment", Objective 26.3, Attachment A, page . KA 034000K402 (2.5/3.3) -;
~
034000K402 ..(KA's) l ANSWER: 039 (1.00) [+1.0]
,
f
'-
, - - . . .
_ _ _ _ _
! SENIOR REACTOR' OPERATO Page 74- -
,
' REFERENCE: AA-52002-027, " Service Water", Objective 27.6, page 2 :
'
2 ~. - .KA 076000G005 (2. 8/3.2) , 076000G010 (2.7/2.9)
076000G010- 076000G005 ..(KA's)
.
ANSVF (1.00)
d.- (+1.0) ,
,
REFERENCE: ; '22r3.021, " Loss of Instrument Air", page '2. . STM-2-48, " Instrument Air System", page '. KA 078000K303 (3.0/3.4) !
078000K303 ..(KA's)
ANSWER:- 041 (1.00) [+1.0)
_
REFERENCE: ,
, Technical Specification Bases-3/4.1.3, " Movable Control Assemblies", page-B 3/4 1- . KA 000005K302'(3.6/4.2)
000005K302 ..(KA's)
-ANSWER: 042 (1.00)
a .. (+1.0] '
000015G010 ..(KA's) ,
,
,
__m _ _ . _ . -
.
-
_
SENIOR. REACTOR' OPERATOR' Page 75-ANSWER: 043' '(1. 0 0 )
. [+1.0}
' REFERENCE:
- 1, 2203.025,'"RCP Emergencies", page . ~KA 000015A122 (4. 0/4.2 ) .
000015A122 ..(KA's)
ANSWER: 044 (1.00) [+1.0}
...
,
REFERENCE:
'1 AA52002-014, " Reactor Trip Recovery", Objective 14.5, page 6
' KA 000024K302 (4.2/4.4)
'000024K302 ..(KA's)
ANSWER: 045 (1.00)
' [+1.0]
REFERENCE: Technical' Specifications Bases 3.5.4,." Refueling Water Storage", page'B 3/4'5-2, KA 000024K104 (2.8/3.6), 000024G004 :(2.9/3.8).
000024G004 000024K104 ..(KA's)
e L ANSWER: 046. (1.00) [+1.0)
o
_ _ . , _ - _ +i SENIOR-:REA:iOR_ OPERATOR 'Page 76
' '
- REFERENCE:
-1. . 2104.028, " Component Cooling Water System Operation", page
7 AA52002-030, " Cooling Water System", Objective 3'.2H,.pages O 15-1 . KA 000026A201 (2.9/3.5) 000026K301 (3.2/3.5), 000026A102 (3.2/3.3) '
000026A102 000026K301 000026A201 . . - ( KA ' s ) ,
ANSWER: 047 (1.00) , [+1.0)
.;
REFERENCE: .
- AA42102-002, " Pressurizer Pressure and Level Control System", Q10.,.page . KA 000027K303 (3.7/4.1)y -
i 000027K303 ..(KA's)
'
ANSWER: 048 (1.00) *
[+1.0)
n REFERENCE: -j AAS2003-009, " Excess Steam Demand", page ' KA 000040K106 (3.7/3.8).
000040K106 ..(KA's)
ANSWER: 049 (1.00) [+1.0) !
i REFERENCE:
1. : 2202.010, " Standard Attachments", Attachment 20, page 6 . KA 000040A203 (4.6/4,7)
000040A203 ..(KA's)
- .- .
. _ , . _ _ - . _ . . _._.m- - - - _
..
SENIOR REACTOR OPERATOR Page 77
.
cANSWER: 05 (1.00) ( + 1. 0)
REFERENCE: .019, " Loss Of Condenser Vacuum", page . .KA 000051A202 (3.9/4.1)
000051A202 ..(KA's)
.
ANSWER: 051 (1.00) [+1.0)
e,,--
REFERENCE: AA52003-011, " Loss of Offsite Power", Objective ~11.6, pages 20-2 .- KA 000055A202 (4.4/4.6)
000055A202 ..(KA's).
ANSWER: 052 (1.00) [+1.0)
REFERENCE: AA52003-012, " Station Blackout", Objective 12.5, page 1 . KA 000055G007 (3.6/3.7)
.000055G007 ..(KA's)
>
ANSWER: 053 (1.00)
v
' {+1.0)
. . -
. . . . . -_ .. .. - - _ . . - ~ . -. . _ ..
,
SENIOR REACTOR OPERATOR Pagen78 UREFERENCE: .034, " Fire Or Explosion", pag . KA 000067K102 (3.1/3.9)
000067K102 ..(KA's) .
ANSWER: 054 (1.00) [+1.0]
REFERENCE: T/S 3.3.3.5, Table 3.3-9, p. 3/4 3-3 . KA '000068K201 (3.9/4.0)
000068K201 ..(KA's)- ,
ANSWER: 055 (1.00)
' {+1.0) .
?
'
REFERENCE: .014, " Alternate Shutdown", page . KA 000068G010 ( 4 .' 1/ 4 . 2 )
000068G010 ..(KA's)
i ANSWER: 056 (1.00) [+1.0) ;
i i
REFERENCE: .005, " Loss of Containraent Integrity", page ,l KA 000069A201 (3.7/4.3)
- .
000069A201 ..(KA's) i
'
i
- ..
!
. . . . . .
. , , ~ . - ~ - ~ . .. . . . . - . - . . . . . . . . - . - . - . . . . . . - ~ . . . . . ~ . - . ...
-
-
'
SEWIOR REACT SPERATOR Page 79 ;
i
' ANSWER: 057 (1.00)
.c . (+1.0) ,
!
- REFERENCE:
. .009, " Heat Removal Decision Tree", page . KA 000074G011 (4. 5/4. 6)
>
000074G011 ..(KA's)
t
'
ANSWER: 058 (1.00) {+1.0)
REFERENCE:
1. - Technical Specification Section B3.4.8, " Specific Activity", page B 3/4 l KA bOOO76K306 (3.2/3.8),'000076G004 (2.1/3. 7) . [
t 000076G004 000076K306 . .(KA's)
ANSWER: 059 (1.00) i (+1.0]
-;
'
- REFERENCE:
1, 2203.003, " CEA Malfunction", page ! AA-S2002-012, " Control Element Drive Control", Terminal' Objective, page * KA 000001G010 (3.9/4.0) ;
000001G010 ..(KA's)
.
r
. ANSWER: 060 (1.00) l
' [41.0]-
-
,
..
P epq g V uw s y
. - _ -
.-
t
[ SENIOR REACTOR OPERATOR Page 80 REFERENCE: .003, "CEA-Malfunction", page .- 'AA-52002-012, " Control Element Drive Control", Terminal Objective, page-
_2 . KA 000003G011 ( 4 . 0/4 .1)
000003G011 ..(KA's)
ANSWER: 061 (1.00) [+1.0)
REFERENCE: .009, " Functional Recovery Procedure", page 1 . KA 000007G012 (3.8/3.9)
-000007G012 ..(KA's)
ANSWER: 062 (1.00)
. [+1.0)
REFERENCE: AA52002-015, " Loss of Coolant' Accident EOP", Objective 15 4, page 1 . KA 000008G011 (4.0/4.1)
000008G011 ..(KA's)
ANSWER: 063 (1.00) -- [+1.01
'
REFERENCE: AA52003-015, " Loss of Coolant Accident", Objective:15.3, page 1 . KA 000009K101 (4.2/4.7)
000009K101 ..(KA's)
. _ _ _ _ _ _
- - SENIOR. REACTOR OPERATOR Page 81
!
.,
ANSWER: 064 (1.00) ! [ + 1. 0 ]- l (
REFERENCE: .003, " Loss Of Coolant Accident, Safety Function Status Check", page--i 7 ' KA 000009A239 (4.3/4.7)
'
,
000009A239 ..(KA's)
ANSWER: 065 (1.00)
- [+1.0]
REFERENCE: 'AA52003-015, " Loss of Coolant Accident", Objective 15.3, page 1 . KA 000011K313 ( 3 . 8 /4 '. 2 )
000011K313 ..(KA's)
.
ANSWER: 066 (1.00) [+1.0)
REFERENCE: .019,'" Standard Attachments", Exhibits.2 &;3, pages 90 & 9 . AA52002-015, " Loss Of Coolant Accident EOP", Objective 15.15, page 42'. KA 000011A210 (4. 5/4. 7)
000011A210 ..(KA's)
- ANSWER: 067 (1.00)
' (+1.0)
.]
l
..
's I
-
r
- ,. .+ a. -.
- . - . - . . . - . . - - - . ,
>. .
G
[S'EN10R REACTOR OPERATOR Page 82--
~
REFERENCE:
' .001, " Standard Post' Trip Actions", page 8, 2.- 2202.010, " Standard Attachments", Attachment 1 and 2, pages 3 andi . KA 000011G010 -(4. 5/4. 5) ,. 000011A103 (4.0/4.0)
>
000011A103 000011G010 ..(KA's) ,
,
. ANSWER: 068 (1.00)
. [+1.0)
REFERENCE:
l '. 2202.003, " Loss Of Coolant Accidents", page . KA 000011G007. (3.7/3.9)
000011G007 ..(KA's)
ANSWER: 069 (1.00)
d.- .[41.0)
REFERENCE:
~ .029, " Loss - of Shutdown Cooling, page . KA 000025A112 (3.6/3.5)
000025A112 ..(KA's)
-
ANSWER: 070 (1.00) [+1.0] I
.
-REFERENCE: 1 .029, " Loss of Shutdown Cooling", page . .
] KA 000025A102 (3. 8 /3.9 ) , 000025A207 (3.4/3.7), 000025A101-(3.6/3.7) *
-000025A101 000025A207 000025A102- ..(KA's)
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.' l
.-
.
. .
' SENIOR REACTORLOPERATOR Page 03 ANSWER: 071 -(1. 0 0 ) (+1.0)
REFERENCE: STM-2-02, " Control Element Drive Control", page . KA 000029K312 '(4.4/4.7)
000029K312 ..(KA's)
-ANSWER: 072 (1.00) . [+1.0)
REFERENCE:
- Unit 1 Technical Specifications 3.9.2, " Refueling Operations",- page 3/4 l 9-2.
l KA 000032G000 (2.8/3.3)
'
000032G008 ..(KA's)
ANSWER: 073 (1.00)
c.- [+1.0]'
REFERENCE: .038, " Primary To Secondary Tube Leakage", page . KA 000037A212 (3.3/4.1)
000037A212 ..(KA's)
,
ANSWER: 074 (1.00) [+1.0)
.,
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'[ SENIOR'REACTOROPERATOR' Page 84 -
A+
'
REFERENCE:
h 2'203.038, " Primary To Secondary Leakage", page . AA52003-008,." Steam Generator. Tube Rupture", Objective 08.2, page .- KA'000037A206 (4.3/4.5)
000037A206 ..(KA's) ;
ANSWER: 075 (1.00)
, [+1.0) ..
REFERENCE:
' AA52003-008, " Steam Generator Tube Rupture", Objective 08.8, pages 19-2 . KA 000038G011 (4.2/4.3)
,
000038G011 ..(KA's) *
,
ANSWER: 076 (1.00) [ +1. 0].
REFERENCE: .004, " Steam Generator Tube. Rupture", page 3 . AA52003-008, " Steam' Generator Tube Rupture", Objective 08.12,'page 2 . KA 000038A217 (3.8/4.4)
000038A217 ..(KA's)
ANSWER: 077 (1.00)
' { + 1. 0)
i REFERENCE: AA52003-010, " Loss Of Feedwater", pages 8 & 1 . 2202.006, " Loss Of Feedwater".
!, KA 000054A203 (4.2/4. 3 ) , 000054K102 (3.6/4.2)
000054K102
_
000054 A203 ..(KA's)-
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. SENIOR' REACTOR OPERATOR Page.85
'
ANSWER: 078 (1.00)
- [+1.0) '
REFERENCE: .006, " Loss of Feedwater", page . AA52003 010, " loss Of Feedwater", page 11. . KA 000054K304 (4.4/4.6) ,
'
000054K304 ..(KA's)
,
,
ANSWER: 079 (1.00) , [+1.0)
'
REFERENCE:
.;
' AA52002-007, " Electrical Distribution", page 3 . KA 000058A203 (3.5/3.9)
000058A203 ..(KA's)
f ^
ANSWER: 080 (1.00) {+1.0]
REFERENCE: AA42102-002, " Pressurizer Pressure and Level Control System", Objective 5, pages 43-4 . KA 000028A212 (3.1/3.5) e t
000028A212 ..(KA's)
ANSWER: 081 (1.00) [+1.0)
..
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-i i-SENIOR REACTOR OPERATOR- Page 86~
~
TREFERENCE: .2502.001,." Refueling Shuffle", Attachment J, page 3 . KA 000036G010 (3.7/3.8)
000036G010 ..(KA's)
S l ANSWER: 082 (1.00) (+1.0] e
.
-REFERENCE: AA52003-011, " Loss of Offsite Power", Objective 11.6, page 2 . KA 000056A288 ( 4 .1/ 4 . 2 )
000056A288 ..(KA's)'
'
ANSWER: 083 (1.00)
'
a.- -[+1.0)
REFERENCE: -
1, 2203.021, " Loss Of Instrument Air", Attachmen't E, page 41'.
- KA 000065A208 (2.9/3.3) > -
.
000065A208 ..(KA's)
s l
ANSWER: 084 (1.00)
"
. . [ + 1.' 0 ]
'
REFERENCE::
'
l'012.019, " Radiological Work Permits",-page '
.1 . -i
. KA 194001K104 (3.3/3.5), 194000K103 (2.8/3.4) -I
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.
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194000K103 194001K104 . . '( KA ' s )
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LSENIOR' REACTOR OPERATOR Page 87-
. ,
~ ANSWER: 085 (1.00)
c; [+1.0]
L REFERENCE: .005, " Confined Space Entry Program", page . KA 194001K111 (3.4/3.5) ,
194001K111 . . (KA's)
ANSWER: 086 (1.00)
d .- [+1.0)
,
REFERENCE:
' .005, " Confined Space Entry Program", page . KA 194001K114 (3.3/3.6)
194001K114 . . (KA's) ;
,
ANSWER: 087 (1.00) [+1.0) '
'
REFERENCE: .005, " Confined Space Entry Program", page 1 . KA 194001K114 (3.3/3.6) ,
194001K114 . .(KA's)
.
ANSWER: 088 (1.00) [ + 1. 0] -
.
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.
. SENIOR REACTOR' OPERATOR Page 88 :
REFERENCE:
1. - 1000.106, " Primary Chemistry Monitoring Program", page , KA 194001A114 (2.5/2.9)
194001A114 ..(KA's)
-ANSWER: 089 (1.00) [+1.0]
' REFERENCE: T/S BASES 3/4. . KA 194001A114 (2.5/2.9)
194001A114 ..(KA's) .
.
t-ANSWER: 090 (1.00) [+1.0) x
'
i REFERENCE: .128, " Industrial Safety and Occupational Health", page 4 . KA 194001K107 (3.6/3.7)
194001K107 ..(KA's)
ANSWER: 091 (1.00) ,
'- [+1,0)
REFERENCE: .002, " Reactor Trip Recovery", page 2, KA 194001A102 ( 4 .1/ 3 . 9 )
194001A102 ..(KA's)
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SENIOR REACTOR' OPERATOR Page 89 A
PANSWER: 092 (1.00)
i [+1.0]
.
REFERENCE:
' .001, " bud: Reporting", page 2 . KA 194001A116 (3.1/4.4)
194001A116 ..(KA's)
ANSWER: 093 (1.00) [+1.0]
REFERENCE:
' .027, " Hold and Caution Card Control", page 3 . KA 194001K102 (3.7/4.1)
194001K102 ..(KA's)
ANSWER: 094 (1.00) [+1.01 REFERENCE: .027, " Hold and Caution Card Control", page 3 . KA 194001K102 (3.7/4.1)
,
194001K102 ..(KA's)
ANSWER: 095 (1.00) [+1.0]
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'
SENIOR' REACTOR OPERATOR Page 90 -
REFERENCE:
+ .006, " Procedure Control", page . KA'194001A101 ( 3 . 3 / 3 . 4 ') '
194001A101 ..(KA's) l
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ANSWER: 096 (1.00)
.
' [+1.0]
r REFERENCE:
~ .001, "
Conduct o2 Operations", Attachment 1, page 5 . KA 194001A103 (2.5/3.4)
.
L
'
194001A103 ..(KA's) !
,
.
ANSWER: 097 (1.00) {+1.0]
j REFERENCE: l .032, " Operations-Procedure Users Guide .
, page- . KA 194001A101 ( 3 '. 3 / 3 . 4 ) -
194001A101 ..(KA's)
,
ANSWER: 098 (1.00) (+1.0] '
REFERENCE: .005, " Operations Key Control", page . KA 194001K105 (3.1/3.4)
194001K105 ..(KA's)
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. SENIOR REACTOR OPERATOR Page 91
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= ANSWER: 099 (1.00) .t [+1.0)
l
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REFERENCE: .001, " Conduct Of Operations", page 3 . KA 194001A103- (2. 5/3.4) '
-
194001A103 ..(KA's) 1 l
ANSWER: _100 (1.00) [+1.0)
.-
REFERENCE: ,
' .007, " Fire Brigade Organization and Responsibilities", pag . KA 194001K116 (3.5/4.2)
-!
194001K116 ..(KA's)
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b ('*********
- END OF EXAMINATION **********) ,
,
-
y- 1 SENIOR REACTOR OPERATOR Page 1 f
ANSWER KEY ,
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MULTIPLE CHOICE 023 a 001 c 024 d
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002 b 025 c
,
003 b 026 c ,
004 a 027 d -
005 d 028 c
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006 d 029 b [
00 c 030 a y
~000 c 031 j 009 d 032 d .
010 c 033 d 011' t 034 ,
012 c 035 d 013 c 036 c
.
.014 d 037 b
'015 a 038 d-016 c 039 b 017 -d 040 d
>
1018 a 041 d'
019 b 042 a 020 a 043 c 021 c 044 a .
,
'022 a 045 d' .,
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.- . . . . . - . . - .
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SENIOR REACTOR-OPERATOR Page 2 AN'SWER KEY
!
046 c 069 d 047 b 070 a I
048 a 071 c 049' d 072 a 050 b 073 c 051- c 074 a
'
052 a 075 b 053 d 076 d 054 b 077 d
"
055 b 078 a 056- d 079 b ,
, 057 c 080 c 058- c 081 b 059 b - 082 a 060 d 083 .a
-
,
061 b 084 a 062 d -085 c 063 c 086 d 064 a 087 d 065 a' 1088 d
066~ c 089 Lc 090 c 068 a 091 a
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.
-
Page 3 SENIOR REACTOR OPERATOR ANSWER KEY 092 d 093 c 094 d 095 c 096 a 097 d 098 b 099 c 200 d
+
i (********** END OF EXAMINATION **********)
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