ML20043G325

Exam Rept 50-285/OL-90-01 on 900529-30.Exam Results:All Applicants Passed All Portions of Exams & Issued Licenses

ML20043G325
Person / Time
Site:	Fort Calhoun
Issue date:	06/08/1990
From:	Keeton J, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20043G316	List: LIC-90-0489, Advises That Personnel at Util Reviewed Reactor Operator Licensing Exam Administered on 900529.Comments on Exam Encl ML20043G315 ML20043G325
References
50-285-OL-90-01, 50-285-OL-90-1, NUDOCS 9006200155
Download: ML20043G325 (74)

Text

{{#Wiki_filter:- i i i APPENDIX U.S. NUCLEAR REGULATORY COMMISSION REGION IV NRC Inspection Report: 50-285/0L 90-01 Operating License: DPR-40 Docket: 50-285 L kensce: Omaha Public Power District 444 South 16th Street Mall i Omaha, Nebraska 68102-2247 Facility Name: FortCalhounStation(FCS) Examination at: FCS b Chief Examiner: F. Keeton, Chief Examiner, Dperator Licensing Date Section, Divisio of Rea r Safety Approved: M s1 /e d 8 [d ell , chie q operator Licensing Dite / ' ion Division of Reactor Safety Summary ] NRC Administered Examinations Conducted During the Week of May 29, 1990 IRIC Report 50-285/0L 90-01) NRC administered examinations to three reactor operator (RO) applicants. All of the applicants passed all portions of.the examination and have been issued the appropriate licenses. l 9006200155 900611 PDR ADOCK 05000285 PNU

-2 4 DETAILS 1. PERSONS EXAMINED i. SRO TOTAL Licensee Examinations: Pass - 3 0 0 i Fail - 0 0 0 2. EAMINERS I - J. Keeton, Chief Examiner J. Whittemore M. Satorius 3. EXAMINATION REPORT Performance results for individual candidates are not included in this report L because examination reports are placed in the NRC Public Document Room. Individual performance results are not subject to public disclosure. 3.1 Examination Review Comment / Resolution -In general, editorial comments or changes made as a resu t of facility reviews l prior to the examination, during the examination, or subsequent grading reviews are not addressed by this resolution section. The facility licensee post-examination comments, less the supporting documentation, are included in the report immediately following the master examination key. All facility licensee comments were incorporated into the answer key. 3.2 Site Visit Sumary The facility licensee was provided a copy of the examination and answer key J l for, the pu" pose of commenting on the examination content validity. The l-facility licensee was informed that examination results could be expected the b week of.'one 4,1990, if comments on the written examination could be l provideJ by the end of the examination visit. An 'nformal meeting was held May 31, 1990, with the following persons in attendance: l-HP.C FACILITY J. Whittemore M. Lazar l7 T. Reis J. Herman M. Satorius L 1 t

o i, NRC expressed appreciation for the cooperation and professionalism exhibited by the control room staff during the walkthrough portion of the examination. Also, the personnel responsible for dosimetry and body counting were very cooperative in arranging their schedule to help the examiners meet the desired schedule. The focus of the meeting was directed to future examinations with the newly installed simulator facility. The facility training staff determined that a formal exit meeting was unnecessary. 3.3 General Comments Performance on both the written and operating examinations was satisfactory. The written examination consisted entirely of multiple choice and matching test items. The average grade on the examination was 83.5 with only four questions being missed by all candidates. Facility reviewers and candidates remarked that this examination was the most difficult they had seen, but that the examination was fair and valid in all respects. Because of the small number of epplicants examined, :ic specific training weaknesses were identified; however, the fac M ity licensee is encouraged to continue evaluating training effecM yeness and operator performance. During the walkthrough portion of the examination, two items that were identified by the examiners were bought to the attention of facility training personnel. One item involved boration. The candidates appeared to be unaware that a procedure existed for metering boric acid into the reactor cooling system continuously for a gradual power decrease. Instead, they preferred to batch feed boric acio, which reflects operational practice. Second, the candidates referred to the radiation protection procedure and could not find the radiation limit for visitors. They were not aware that the limit is stated in the radiation protection plan procedure. The training staff was reminded that prior to the examination scheduled for October 1990, the NRC will require the new simulator reference material that has been developed and updated prior to the examination. Also, the facility will need to provide updated plant reference material for development of that examination. 3.4 Master Examination and Answer Key j A master copy of the FCS license examination and answer key is attached. The facility licensee comments were accepted and are incorporated into the answer L key.

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b U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4 FACILITY: FT. Calhoun REACTOR TYPE: PWR-CE DATE ADMINISTERED: 90/05/29 CANDIDATE: i INSTRUCTIONS TO CANDIDATE: . Points for each question are indicated in parentheses after the question. To pass this examination, you must achievo an overall grade of at least 80%. Examination papers will be picked up four and one half (4 1/2) hours after the examination starts. NUMBER TOTAL CANDIDATE'S CANDIDATE'S QUESTIONS POINTS POINTS OVERALL GRADE (%) 95

98. t -

L ll work done on this examination is my own. I have neither given A nor received aid. j g, t i Candidate's Signature 1 L i

P o NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During tha 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 penalties. 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of l cheating. 3. To pass *.he examination, you must achieve an overall grade of 80%. 4. There is a time limit of 4 hours for completion of the examination. 5. The point value for each question is indicated in parentheses after the question. 6. Partial credit will NOT be given on multiple choice questions. 7. Multiple choice questions may contain one or more choices which are correct IP certain assumptions are made. However, the correct answer +:111 not need assumptions or qualifiers. Therefore, when i more chan one choice seems to be correct, select the choice which BECT answers or completes the question or statement for the conditions given in the question. 8. If the intent of a question is unclear, ask questions of the examiner only. ( 9. Use only black ink or dark pencil to allow legible reproductions, l 10. Print your name in the blank provjded in the upper right-hand corner of the examination cover shset. Print your initials in the L upper right-hand corner of each answer page. 11. ONLY the answers marked on the examination specific answer sheet will be considered for examination arading. Information or answers marked on scratch paper or on the examination will NOT be credited during examination grading. 12. After you complete your cxamination, you mest sign the statement on the cover sheet indicating that the work is your own and that you have not received nor given assistance in completing the o examination. 13. When turning in your examination, assemble the signed cover sheet followed by the examination specific answer sheets. The examination and any scratch paper will be collected separately. 14. When you are done and have turned in your examination, leave the examination area as defined by the examiner. If you are found in this area while tne examination is still in progress, your license may be denied or revoked.

REACTOR OPERATOR-Paga 4 'i -QUESTION: 001 (1.00) Which one of the following personnel's INITIAL response to a fire in the -RCA-does NOT require use of respiratory gear per S0-G-28? a. Water Plant Operator b. Licensed Operator c. LEquipment/ Auxiliary Operators-d.- Radiation Protection personnel l . QUESTION: 002 (1.00) Who maintains administrative control of the key (s) to locked radiation -areas in which the intensity of radiation is greater than 1000 mrem / hour in cocordance with Technical Specifications? a. Supervisor - Radiation Protection b. . Shift Supervisor on duty c. Supervisor - Operations d.- Manager - Fort Calhoun Station, or designee

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REACTOR OPERATOR Paga 5-t

. QUESTION: 003 (1.00) 'Which of the following is the correct statement regarding access margin as r0 corded on a Radiation Work Permit (RWP) (FC-RP-201-1)? a. Access margin'is the maximum available doce a person is permitted to receive when using the RWP and is normally. greater for a special RWP than for a routine RWP. b. Access margin is the difference between estimated job exposure and administrative whole body limits and is normally-greater for a special RWP than for a routine RWP. c. Access margin is the maximum available dose a person is permitted to receive when using the RWP and is normally greater for a L routine RWP than for a special RWP. i d. Access margin is the difference between estimated job exposure and administrative whole body limits and is normally greater for a routine RWP than for a special RWP. 4 . QUESTION: 004 (1.00) Which tagout sequence is required for. removing charging pump 1B from csrvice;for seal replacement? The attached figure may be used for .roference. a. CH-192, CH-173, CH 1B breaker, CH 1B handswitch b. CH 1B handswitch, CH-192, CH-173, CH 1B breaker c. CH 1B breaker, CH-192, CH-173, CH 1B handswitch -d. CH 1B handswitch, CH 1B breaker, CH-192, CH-173 )

REACTOR OPERATOR Pagn 6

'a QUESTION: 005 (1.00) Ucing the attached copy of OP-3 as a guide, which of the following is the guidance on whether sequence of procedural steps is. required? a. Precautions and procedure steps must be satisfied or completed in sequence unless the procedure specifically states otherwise, b. Precautions must be satisfied in sequence but procedure steps are not required to be completed in. sequence unless specified in the procedure, c. Precautions and procedure steps are not required to be satisfied or. completed in sequence unless specified in the procedure, d. Precautions are not required to be satisfied in sequence but procedure steps must be completed in sequence unless the procedure states otherwise. -QUESTION: 006 (1.00) Using the cycle 12 curves and the completed Estimated Critical Position Work Sheet (TDB-V.1) attached, which of the lines listed below represents 1 an INCORRECT graph interpretation.for a reactor startup? The reactor power history prior to shutdown was steady state at 80% for.14 daysa a. C.1. on TDB-V.1-2 (Total. Power Defect) b. C.2.b. on TDB-V.1-2 (Inverse-Boron Worth) c. C.3.b. on TDB-V.1-3 (Startup Xenon Worth) d. C.3.e. on TDB-V.1-3 (Startup Samarium Worth)

.= REACTOR-OPERATOR Page 7 QUESTION: 007 (1.00) =Which of the'following describes.how the three rod positions for criticality given in sections D and E of the completed Estimated Critical Position (ECP) Work Sheet (TDB-V.1) attached satisfy the power dependent insertion limit at-zero power? ECP-1%- ECP ECP+1% a. Not satisfied Not satisfied Satisfied. b. Satisfied Satisfied .Not satisfied c. Satisfied Not satisfied Not satisfied d. Not satisfied Satisfied Satisfied

QUESTION

008 (1.00)

According to S0-0-01, which of the following describes the correct use of communications systems during a site emergency causing activation of the Emergency Plan? a. The GAI-TRONICS is the preferred alternative but portable radios may be used by operations on channels 1, 2, or 3. b. -Portable radio' channel 1 is the preferred alternative but the GAI-TRONICS or radio channel 3 may be used. Radio channel 2 is reserved for security use only. c. The GAI-TRONICS is the preferred alternative but radio channels 1 or 3 may be used. Radio channel 2 is reserved.for security. d. Portable radio is the preferred alternative using channels 1, 2, ore 3, For areas where radio frequency interference is a concern the GAI-TRONICS may be used. i

..T L- - REACTOR OPERATOR Page 8 i -QUESTION: 009 (1.00) Which-of the following describes the use of the Procedure Verification Stamp placed on the front of procedures? a. The stamp contains the Plant Manager's signature and date signed to indicate-that the revision is official. b. The stamp indicates that a revision verification signature step is contained in the procedure, c. The stamp provides a place for the procedure user to document that the revision is current. c. The stamp establishes the revision history with a signature block for the PC Clerk. QUESTION: 010 (1.00) Fort Calhoun Station (FCS) Technical Specifications allow the operator one hour to implement action required for a control element assembly.(CEA) 1 misaligned by 16 inches. The one hour time limit will: -a. Preclude a decrease of available shutdown margin-(SDM). b. Minimize the effects of Xenon redistribution. c. Preventfpeaking factor degradation. d. Preserve 23sumed worth of an ejected rod. QUESTION: 011 (1.00) According to FCS OI-RC-9, which of the following conditions require the operator to shutdown a Reactor Coolant Pump (RCP)? a. Motor stator temperature is 120 degrees C. b. Motor stator temperature is 195 degrees F. c. Motor radial bearing 75 degrees C. d. Motor radial bearing temperature 215 degrees F.

j . REACTOR OPERATOR Paga 9 1 QUESTION: 012 (1. 00)- Given an uncontrolled heat extraction event-ongoing due to a steam.Line break outside of containment, which condition resulting from the evant will L torminate the event without operator action? l l, a. RCS pressure is at 1455 psig. j l b. Steam Generator levels are 31 and 32 inches wide range. c. Steam generator pressures are 484 and 485 psig. L d.- Containment pressure reaches 5 psig. n QUESTION: 013 (1.00) Which instrument combination can be used to make a valid determination of RCS sub-cooled margin WITHOUT ANY OTHER INPUT such as conversion tables, eteam tables, or a Mollier diagram? a. Alternate Shutdown Panel (AI-185) cold leg temperature and AI-1 185 Pressurizer Temperature. b. Auxiliary Feedwater Shutdown Panel (AI-179) Wide range steam l generator pressure and AI-179 Narrow range RCS pressure. c. AI-179 steam generator temperature and AI-185 Hot leg temperature. l d. AI-179 wide range steam generator pressure and AI-185 Hot leg temperature. 1 I

~ t REACTOR OPERATOR P go 10 (QUESTION: 014 (1.00) LWhich of the following satisfies the RCS Heat Removal post trip safety-

function but does NOT satify the RCS Inventory post trip safety function?

a. RCS subcooling is 19 degrees F and RCS Tc is 555 degrees F. b. Pressurizer level is 30% and S/G pressure is 845 psia, c. RVLMS indicates 95% and S/G narrow range level is 70%. d.- Charging System is not operating and S/G levels are 66% and 73% WR respectively. i J UESTION: 015 (1.00) Q .Following an uncontrolled heat extraction'(UHE) event that is terminated by 'SGIS, the specific action necessary to control cooldown or minimize the possibility of pressurized thermal shock resulting from the initiation of auxiliary feedwater is to' control Shu addition of-auxiliary feedwater by: a. Closing and fully reopening HCV-1107A & 1108A. b. Throttling HCV-1107A & 1108A. c. Throttling HCV-1107B & 1108B. d. Closing and fully reopening HCV-1107B & 1108B. QUESTION:.016 (l'. 0 0) During a loss of off-site power and all S/G feedwater, the Atmospheric Dump Valve'(ADV).will not be used for INITIAL heat removal because: 'a. The MSIVs have shut. b.. = MSS 291/292 have a higher capacity. c. The ADV is isolated. d. Using the safety valves preserves S/G inventory. (I

.t. REACTOR OPERATOR' Paga 11 . QUESTION: 017-(1.00) ) Which ofLthe=following is the-normal method of placing a single. bistable ~ n trip. unit inithe tripped condition?-

a..

' Pull the-trip unit out of its drawer. b.- Turn the Trip / Bypass key switch to the' Tripped position. f c. Open the RPS channel power supply breaker. d. Depress the Pretrip/ Trip button located on the trip unit. f i - QUESTION: 018 (1.00) l-During a loss of off-site power (both-161 KV and 345 KV), bus 1A4 becomes-faulted and-Emergency Diesel Generator (EDG) D-1 will not start. To icnergize a 4160'VAC vital bus with this equipment failed, the operator must follow procedural steps in: a. System Operating Instruction EE-1. l-b. Emergency Operating Procedure EOP-02. =j c. Emergency' Operating ~ Procedure EOP-07. d.- Abnormal Operating Procedure AOP-31. t l l l L a e L N' s t t

c.. J+ i REACTORiOPERATOR Pcgo 12 ,.. QUESTION:.019 (1.00) !.The reactor has-tripped and EOP-00, Standard Post Trip Actions are complete. The1following plant' conditions exist: Pressurizer Lavel: 50% and decreasing Steam Generator Pressures: 850 psia and slowly decreasing 4160 VAC bu'J 1A3: Energized '4160 buses 1A1, 1A2, and 1A4: Deenergized Containmant Pressure: 1.0-psig Choose the correct EOP to enter. a. EOP-02, Loss of off-site power. b. EOP-03, Loss of coolant accident. c.- EOP-05, Uncontrolled heat-extraction.- d. 'EOP-20, Functional recovery procedure. QUESTION: 020 (1.00) During'the performance of steps 3.4, 3.5, and 3.6 of=EOP-00 with.161 KV available', the operator recognizes that buses 1A1, 1A2, and 1A3 are 'deenergized'and EDG D-1.is running. The operator is required to: a. Attempt to manually start EDG D-2 and manually-energize -1Al' and 1A2 from 161 KV. b. Enter EOP-02 and perform concurrently with EOP-00, c.- Enter EOP-00 Safety Function Acceptance Criteria Checklist for Maintenance of Vital Auxiliaries (MVA). d. Establish a success path for MVA in EOP-20. w T

..a I REACTOR OPERATOR Pcgo 13 QUESTION: 021 (2.00) 'During preparations forfstartup, the following conditions exist: RCS Pressure Control: Manual heaters & spray RCS Temperature: 340 degrees F RCS Pressure: 1250 psia RCS Flow: 2 RCPs If it becomes necessary_to reduce RCS pressure the operator: a. Is prohibited.from using spray because of thermal shock considerations. b. Is encouraged to use any available method to vent the pressurizer-for-pressure reduction. c. Is allowed to use normal spray. d. should use auxiliary spray. QUESTION: 022 (1.00) Which of the follov,-g describes the events that occur if Pressurizer Pressure Sigma Mets PIC-103X fails low? Assume X is the controlling channel and no operator action is taken. a. Backup heaters energize, pressure increases, spray valves open, and-pressure stabilizes at a higher value. b. Backup h'saters deenergize, pressure decreases, proportional heaters energize, and pressure stabilizes at a lower value. c. Backup heaters deenergize, spray valves open, pressure decreases until a-Thermal Margin / Low Pressure Trip (TM/LP) Occurs. d. Proportional heaters energize, spray valves open, and pressure decreases until a TM/LP Trip occurs. I

4 REACTOR OPERATOR-Paga 14 -QUESTION:-023 (1.00) Given the.following initial plant = conditions: l Pzr level: '100% (solid) Pzr temperature: 380 degrees F RCS temperature: 350-degrees F RCS pressure: 475 psia' i 2 RCPs running j Pzr heaters off/ min Spray valves shut i Which action will result in a significant decrease in RCS pressure? j a. Start third RCP-1 b. Open SIT MOVs c.- Deenergize Pzr heaters d. Open letdown valves l QUESTION: 024 (1.00) The operator needs--to determine 1the CCW outlet temperature of the RW/CCW l hOat-exchanger.- The PREFERRED.way to; acquire this information is to: a. Dispatch an operator to. read the temperature locally. b. Utilize the control room common outlet temperature indication. c. Utilize the computer point for that temperature indication. d. Read the temperature directly on CB-1.

v, 4 ,4 PREACTOR OPERATOR Pcgs 15: y. L QUESTION: 025 (1.00) During a loss of off-site power complicated by a loss of Component. cooling Water (CCW)~ during the winter months, the operator attempts'to admit Raw L Water (RW) to both control room air conditioners. He is not successful in p = obtaining-RW cooling for one air conditioner because: a. RW will not function in the economizer mode. b. Valves will not open unless unit is selected to run. c.

Units will'not operate in-this power configuration.

d. RW temperature will be less than 70 degrees. F. QUESTION: 020. (1.00). During Shutdtwn Cooling (SDC) operation with the RCS intact, offsite power is lost.and regained in 6 minutes. SDC controls are NOT touched during the transient. .Chcose the system response: a.. With-the busses being supplied by offsite power after the transient, the SDC pump (a) did not restart. [ Eb. The pumps restarted when the EDGs picked up the buses, but not when offsite power.was restored to the buses. c. The pumps never restarted after the initial loss of power, i ad. The pumps stopped during the loss of offsite power-but restarted when the buses were picked up by offsite, i s p' yt. i

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3REACTORLOPERATOR; Pcga 16 j c i 1 QUESTION::027 -(1.00)

During.a-recovery from loss of. shutdown. cooking,.the following. conditions cxist:

1 J L EC system:- NOT intact RC level:: Bottom of loops-SIRWT level: 14 inches Containment Sump level: 50' inches 1 Refueling' Canal: Not available R \\; = Choose the preferred: source of RCS makeup: I a. Charging pumps'from SIRWT. u b. .LPSI/HPSI-from Containment sump. p c. LPSI/HPSI from SIRWT. l 7 d. Charging:. Pumps from BAST. [ v e 1 QUESTION: 028 (1.00); i h

The operator: suspects that an open-Pressurizer-PORV is-the cause of ongoing L

RCS pressure reduction. Prior to shutting a PORV block valve, his most ral'iable set of' indication oft an open PORV would be: L a. PORV position' indicator, increasing quench tank level. l-L b. Tail pipe temperature, PORV. position indicator. ic.. Acoustic: monitor, Tail Pipe temperature.- [ d. Quench tank: temperature, Acoustic monitor. L 3 ..Y! ^ i

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i i REACTOR OPERATOR Page 17-h QUESTION:-029 (1.00) While two charging pumps are out of-service, an.RCS leak occurs-at a rate greater than. charging capacity..-The reactor is shutdown and RCS inventory in recovered using HPSI_ pumps. Which condition below will preclude the operator from-stopping or throttling HPSI pumps to control inventory, in accordance with AOP-227 a. RCS subcooling is 20 degrees F. b. Pressurizer level is 40%~, increasing slowly. c. OnlyJone Steam-Generator is available.

d.

RVLMS indicates 46%. QUESTION: 030 (l'. 0 0 ) 1 ,For the same situation as the previous question, which set of conditions swill. ALLOW the operator to throttle or stop the LPSI pumps in-accordance iwith AOP-22? a. RCS pressure 205' psia,. natural circulation vcrified. b.- Both S/Gs available. c.

RVLMS. indicates 80% at.165, psia RCS' pressure d.

RCS pressure 195 psia, pressurizer level 50%, increasing. -QUESTION: 031 (1.00) In order to withdraw a group of regulating rods in manual sequent.'al, each . shutdown rod must display-core mimic lights that are: a. Red / Blue b. Blue / Green c. Green / White d. White / Amber i

LREACTOR OPERATOR Paga 18. 4 QUESTION:-032 (1.00) i

During steady state-operation,1.the, operator observes that RCS cold leg.

t mperature is 2 degrees low:and Axial-Shape Index is approaching =a n:gative limit. To restore both, he must: a. Insert CEAs. 1 b. Insert CEAs and dilute.

i 1

} .c. Withdraw CEAs and Borate. L L:. d. Withdraw CEAS. ] p QUESTION: 033 (1.00) I: .A. grid perturbation results in the following conditions after ctabilization: [ The reactor is tripped. -~ ~ All offsite power has been lost. EDG #1 did not start, 1A3 is not energized. 3

1. 1'DC bus is;deenergized due to a dead short.

l i: u L Theircason'for.the'EDG' failure to start has been corrected. To start and h load the EDG,-one action the, operator must perform is: _a. Start the dieselflocally, at AI-133. o b. Place the' diesel back in AUTO. u .c. Regain a source of 12b VDC power. 9 1'. d.- Start the diesc1 inanually, remotely. l-1 ?. [ '1 l L

nf. y ;.. : p REACTOR: OPERATOR Paga 19 l l QUESTION: 0.14 (1.00) During the execution of EOP-00,< Standard Post Trip actions,.one-125 DC bus

io'deenergizad.

To which document is the operator directed for specific 'information on the. impact on plant instrumentation due to the lack of the effected DC bus. ,a. EOP Maintenance of Vital Auxiliaries b. Technical'l'ata Book.section V o c. .OI-EE-3, Operation of 125 VDC System d. Figure 8.1-1, One Line Diagram, Plant Electrical System- . QUESTION: 033. (1.00) 'At the start of a transient, the loss of one DC bus requires that~the operetor follow the:- .a. Functional recovery where two energized DC buses meet the functional requirements. b. . Optimal recovery for the particular event in progress where-only. one bus is required. c.. There.is no' contingency action for loss of one DC bus so no-procedure-transition is required. d. Functional. recovery where one energized bus meets the functional-requirements.

.s- . REACTOR OPERATOR Paga 20 l QUESTION: 036 (1.00) During blackout conditions a fire has grounded the DC battery charger and bus supplying power to FW-10. The PREFERRED method to start and feed the steam generat. ors with FW-10 is: Mtnually open the pump steam supply valve, a. 4 b. Select the Alternate DC power supply, c. Manually open the AFW supply valve to the feed header (FW-1384). d. Locally jack open.the steam admission valve so the shaft driven oil pump will supply control pressure.

QUESTION: 037 (1.00)

While. executing EOP-00 after a scram that resulted from a loss of feed water, an Auxiliary Feed Actuation Signal (AFAS) initiates feedwater injection. To throttle auxiliary feedwater flow, the operator must: a. Open HCV-1384 on CB-10/11 and 1107/1108B on AI-66A/B then throttle at CB-10/11. b. Open HCV-1107/1108A at AI-66A/B and 1107/1108B on AI-66A/B then-throttle at CB-10/11. c. Close_HCV-1384 on-CB-10/11 and 1107/1108A on AI-66A/B, and open HCV-1107/1108B on AI-66A/B~then throttle at CB-10/11. d. Close HCV-1384 on CB-10/11 and 1107/1108B on AI-66A/B, open 1107/1108A on'AI-66A/B then throttle at CB-10/11. l m m-.._______________._-_____--_-_______.__________----_.__.___.____-_m.m.___.___:._ .m__.. _ _-_-__--____-_ mms-.mm-____-m -m_.m_

y 4.' Ip l REACTOR' OPERATOR Page 21 1 u QUESTION: 038 (1.00) .The operating crew Pas just entered EOP-06 due.to a loss of all feedwater E when it becomes kneen that the loss of feed was due to a break that-is not isolable from the 3/G. To recover, the crew should: a. Continuo with the execution of EOP-06. b.- Leave EDP-06 and enter EOP-05 for uncontrolled heat extraction. c. Return to EOP-00 Diagnostic Actions. Leave-EOP-06 and enter EOP-20 to initiate functional recovery. d. x pm u. ' QUESTION: 039. (1.00) .During a-reactor startup, power level is 5x10(E-5)%, when a Wide Range " channel fails. The operator is required to: m a. 'Re-insert all CEAs that have been withdrawn. b.- Trip all trip units on the failed channel and continue startup. c. Execute entire Sect. II, AOP-15, Loss of Flux Indication. d. Bypass the failed channel and continue with:the reactor startup. QUESTION: 040 (1.00) 'A Group 4 control rod is dropped at full power. The reactor is taken to 69% power and the control rod is realigned within 45 minutes. Core power should remain at 69%: a. Until any desired change is authorized by the system dispatcher. b. One hour or until Shutdown Margin is calculated. O c.- Until Plant Manager's approval to increase is obtained, d. One hour to assess power distribution, u [\\ '. ! f t ~~ 3,

90, [.. 1 fin REACTOR OPL'RATOR ' Pago 22 [ QUESTION: 041 . (1. 0 0) JWhich; detection method.can NOT.be.used to identify / confirm themaffected- =oteam? generator with a S/G tube leak, a. LS/G blowdown rad monitor i b. Steam line rad monitor -c. Direct' sample

d.

Condenser off-gas rad monitor QUESTION: 042L- (1.00) 'After a steam generator-tube rupture occurs, all RCPs are tripped.- After etabilization, 2 RCPs are restarted. Subsequently, SI is terminated after aneting criteria and the plant stabilizes with the following conditions: Pressurizer Level: 48% Pressurizer-Pressure: 450 psia-Tcold:- 435 degrees F. -S/G Pressure: 365 psia What is-the next' action that should be taken by the operator? Figures 5-l' 'through.-5-3 from the EOPs-are. attached-for reference if required. a. Trip the Reactor Coolant Pumps. b.; , Commence cooldown on the unaffected S/G. Ec. Restart Safety Injection. d. . Reduce RCS/SG psid to 0. 1 -k f

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, l s $ REACTOR OPERATOR-Paga 23 .;it ' '

il' n" " QUESTION

-043 (1.00)

' h. During a fuel handling accident in the. containment, the operator = notices ithe following conditions: 1 -: An authorized gas release-is in progress. J D ' Containment filtering units are isolated. ' Control Room ventilation is in the Normal Mode. The action required of the operator is to: 1 ? a.- Manually. initiate CIAS. b. Terminate waste gas release. c. Manually initiate VIAS. ( o. Transfer. control room ventilation to RECIRC Mode. 4 4 ' QUESTION: : 04 4 -(1.00) o C :The~ annunciator on' panel AI-44, AREA RADIATION TROUBLE, would be caused by: -a.- A failed detector only. L b. 'A failed-detector.or reaching the alarm high setpoint only.: l' 'c. A. failed detector or reaching the alert level setpoint only. d. Reaching the alarm high setpoint only. g -l QUESTION:1045 (1.00) h jFollowing a reactor trip from full power due to a loss of all offsite p l power, the.RCS Tave will be controlled: a. Automatically by the steam Dump Valves, b. Manually by the Turbine Bypass Valve. c. Automatically by the Secondary Safety Valves. [ di Manually by the air operated Safety Valves L p 1l' 1 l-g s

,m NREACTOR OPERATOR: Page;24 OUESTION: 046 (0.00) ~ If a waste gas-release must-be momentarily: interrupted duringeanzauthorized . release, shutting which one of the following' valves will result in reset-of 'the flow totalizer?- a. FCV-532A b. FCV-532B c. FCV-532C d.- FCV-532D, 3 QUESTION: 047 (1.00) If any relief. valve on the waste gas decay tanks or-the compressor

discharge header fails open with no release in progress, which one of the following is-correct concerning detection and isolation?

a. Detectable on flow recorder FR-532 and isolated by shutting ~FCV-532C. b. Detectable on containment air gas monitor RM-051 and isolated by shutting VA-285. c. Detectable:on flow instrument FI-530 and isolated ~by shutting. FCV-532C. d. Detectable on ventilation duct gas monitor RM-062 and isolated by. shutting VA-285.

4' REACTOR OPERATORt .Paga 25 i QUESTION:: 048 (1.00) zWhich radiation. monitor alarm-williALWAYS'be accompaniedt.by a control' 1-cignal that'will automatically secure a normal waste gas release?- a.- Containment Radiation High b. Main Stack Gross Rad / Iodine High-Radiation c.. Containment / Stack Gas High Radiation d. Process Radiation High or Trouble QUESTION: 049 (1.00) Which-of the following correctly completes the statement below? The presence of a. alarm along with indicates a possible-- liquid:radwaste_ release via the normal release path above release permit limits. a. Waste Disposal System Malfunction, HCV-691 only shut and pump WD-23A running, b.- Process Radiation High or Trouble, HCV-692 only open and pump' WD-23B running c. Panel AI-33C Radiation Monitor' Trouble, HCV-691 only open and pump WD-23A' running d. Area Radiation _ Trouble, HCV-692 only open and pump WD-23B running-

u . ?': ~ REACTOR OPERATOR Pngs 26 -QUESTION: 050 (1.00) -Which-system parameter error, when used in a heat. balance, will have:the d0 scribed effect on adjusted.NI power.for a Power Range Safety Channel Adjustment? a. If indicated main steam pressure is less than actual pressure, adjusted NI power will be too high. b. If indicated RCS T-cold.is less than actual temperature,Jadjusted NI power will be too low, i c. If indicated feed water flow rate is greater than actual flow rate, adjusted NI power will be too low. d. If indicated RCS-flow rate is greater than actual flow-rate, adjusted NI power will be too high. t QUESTION: 051 -(1.00) Which nuclear instrument channel is used to calculate Quadrant Azimuthal- . Tilt? a. Power Range Safety b. Power Range Control c.- Wide Range Log d. Incore i

p... REACTOR OPERATOR. Pags 27 ' QUESTION: 052 (1.00) Which statement. describes the use of containment and. spent. fuel storage p -screa installed area radiation monitors (ARMS) during refueling operations? L a. No area. radiation monitoring-is required in containment as long as the stack monitors are operable, b. Fuel handling must stop if less than two ARMS are operable in both containment and the spent fuel storage area. E c. Fuel handling may proceed as long as some form of continuous area radiation monitoring is in progress in affected areas. i l d. Low range portable area radiation monitors must be used in lieu of installed ARMS when moving spent fuel. 1 I LQUESTION: 053 (1.00) l Salect the answer that completes the following-statement. 1 Upon' generation ol' a , the containment air cooling and j L filtering system responds by opening the dampers, shutting L the dampers, and shifting the number of running fans from 3 J j to I 1 ll a. VIAS, bypass, face, 4 1. E b. CSAS, face, bypass, 4 l l c. CPHS, face, bypass, 2-d. PPLS, bypass, face, 2 1 1 l l-

x. ,14 L,. : 2 REACTOR-OPERATOR Pags 28-l i QUESTION: 054 .(1.00) ,a Which'of the following monitoring instruments of the waste:-gas disposal 3. Jcystem is located in.the control room? 1 a. Flow recorder FR-532, which monitors waste gas discharged. 1[ b. Automatic gas analyzer AI-110, which monitors tanks using nitrogen or hydrogen gas, i t 4 c. Pressure indicator PI-532,.which monitors waste gas discharge ~ g pressure. y -\\ p, d. Radiation monitor RM-052, which monitors stack gas. p ti [ i t QUESTION: 055 (1.00) 1 Which of the following describes:the way' rate-of-change-of-power'(SUR) yo -oignals are derived from power range safety (PR) channels and~ wide range (WR) log channels when the' reactor is operating in the source and power ranges? ~ 1 .\\4 a. Source and power range SUR are derived-from the WR channels. d. -b. Source range SUR is derived from WR channels and power range SUR ]. -is-derived from PR channels. l m: d c. Source range SUR'is derived from the WR channels and SUR is 3 {: bypassed once operating in the power range. ] i d. Source and power range SUR are derived from the PR channels. v1 ) 4 .l r 1-a ,{ d <4 1 +. i-r n M - r n .j m

,s

,s REACTOR OPERATOR Paga 29 1 QUESTION: 056' (1.00)~ After what period of time following.a. reactor.. trip fromm100%. power.would -the extended range. circuit be expected'to be energized, and approximately. whhc count rate would it be expected to. initially indicate? a. 6Lainutes, 10 counts per second b. 12 minutes, 100 counts per second b c.- 24-minutes, 1,000 counts per second. d. 48' minutes, 10,000 counts per second-t 1.' 1 QUESTION: 057 (1.00) Which of the radiation monitors would.be expected to FIRST initiate a Vantilation Actuation Isolation Signal (VIAS)'as a result of dropping:and cdamaging a spent fuel assembly in the Auxiliary Building while removing it p from the core-during refueling operations? l L a. RM-050 - Containment-Air Particulate- -b. 'RM-060 - Stack Iodine Gas l L c. RM-082 - Auxiliary Building elevation-1007', zone D-2 d. RM-089 - Auxiliary Building elevation 1025", zone C-4 i QUESTION:.058' -(1.00) o Which of the following describes power supplies to the CEDM clutch power -supplies? Instrument bus-A or B feeds clutch power supplies 1 and 3. a. b.. i Instrument bus B or C feeds clutch power supplies 2 and 3. c. Instrument bus C or D feeds clutch power supplies 3 and 4. d. Instrument bus D or A feeds clutch power supplies 2 and 4. 1

~ REACTOR: OPERATOR-Page 30 b-i ' QUESTION:-059- (1.00) "Which of the following= describes the location of the CEDM clutch power -supply. transfer switches? a. Panel-AI-57 near the. northeast corner of the Control Room. b. Panel AI-3 near.the southwest corner-of'the Control Room. c. Panel AI-3 near the northeast corner of the: Control Room. d '.. Panel AI-57 near.the southwest corner of the Control Room.

QUESTION

060 (1.00)

"Which of the following completes the paragraph below with regard to reactor coolant pump (RCP) startup? ~The oil lift pump should be in operation for at least minutes at the. time of RCP startup. The RCP breaker close circuitry is interlocked so it will not close if the oil lift pressure is 'below-psig. -When the RCP achieves 90% speed, a speed sensing . switch deenergizes the pressure-oil lift pump. a. 2', =1 5 0, high b. 5, 120, low c. 2, 120, low 4 d. 5, 150, high +.-' ac l,

a.{ b

o

. REACTOR OPERATOR Page 31 -QU3STION: 061 (1.00) Which of the following-describes =why the: charging pumps shouldsbershifted to the SIRWT within-30 minutes after initiation of SIAS? a. The VCT level will be very low and the automatic swap of suction valves is disabled by a SIAS. o b. The increased boron concentration in the SIRWT compared to the VCT will assure adequate shutdown margin. c. The Boric Acid Tank-(BAT) level will be very low and there is no automatic swap to the SIRWT. d. The decreased boron concentration in the SIRWT compared to the BAT will reduce the risk of boron precipitation. QUESTION: 062 (1.00) Which' containment parameter does NOT have a direct indication in the Control Room? a. Humidity b. Sump level c. Particulate radiation d. Dew point QUESTION: 063 (1.00) Which component failure would rcquire entry into a Limiting Condition for Operation per Technical Specifications section 2.2 on the Chemical and Volume Control System (copy of section 2.2 is attached for reference)? a. FCV-269Y, Boric Acid Flow Control valve-b. LCV-218-2, Volume Control Tank Outlet valve c. FCV-269, Makeup Stop valve d. LCV-218-3, SIRWT to Charging Pump Suction valve

REACTbROPERATOR Page 32 -QUESTION: 064 (1.00) Which of the following is NOT a correct response of the Component Cooling Water (CCW) system to SIAS/CIAS actuation signals? a. All CCW containment isolation valves are closed. b. CCW flow to spent fuel pool heat exchangers is isolated. c. CCW valves to the safety injection pump coolers are opened. d. CCW valves to the containment spray pump coolers are opened. QUESTION: 065 (0.00) Which source of makeup water to the Emergency Feedwater Storage Tank is the closest to the normal chemistry of emergency feedwater? a. Condenser hotwell b. Condensate storage tank c. Fire water header d. North Omaha Station QUESTION: 066 (1.00) 1 What is the PREFERRED method for avoiding thermal shock or water hammer damage to the steam generators when using Auxiliary feedwater to maintain steam generator levels during reactor startup? a. Use the main feed nozzles and maintain steam generator level at least 55% narrow range. b. Use the auxiliary feedwater nozzles and maintain steam generator level at least 80% narrow range, c. Use the main feed nozzles and maintain steam generator level at least 80% narrow range.. d. Use the auxiliary feedwater nozzles and maintain steam generator level at least 55% narrow range.

i REACTOR OPERATOR Pcg3 33 QUESTION: L67 (1.00) Which transient is the Pressurizer. Code Safety Valves sited and: set for? a. Loss of all feedwater flow at 100% power. b. Complete loss of full load without direct reactor trip. c. Turbine trip from 100% power. d. Continuous CEA withdrawal from 10 (E-5)% power. QUESTION: 068 (1.00) Concerning PRESSURIZER design and performance attributes, the designed programmed pressurizer steam volume: a. Should not contribute to the release of excess energy during a LOCA. L b. Must be sufficient to accept maximum insurge without lifting code safety valves (if 1 PORV is operable). c. Should be large enough to effectively control pressure with 10% gas (by volume) in the vapor space during design insurge, d. Must be sufficient to accept full insurge and not exceed a level of 95%. L l' l QUESTION: 069 (1.00) F0r the purpose of fire protection, why is it preferred NOT to use water on fires-that occur in the containment or auxiliary building? a. Because of the vital electrical equipment in these spaces. b. To preclude problems with the chemicals used in these areas.- c. To prevent the spread of radioactive contamination. d. Flooding that could occur due to inadequate drainage. i

j REACTOR OPERATOR P0g3 34 l I i -QUESTION: 070 (1.00) Where can the Variable overpower Trip setpoint can be reset? i a. At the four RPS cabinets. i b. The four RPS cabinets and AI-3. c. On CB-4. d. CB-4 and the four RPS cabinets. QUESTION: 071 (1.00) LThe FCS Axial Power Distribution (APD) reactor trip will ensure that: a. Maximum DNBR or high core power density is not reached. b. Fuel is protected from high LOCAL power density. l^ c. Fuel is protected from high power density. i d. DNB or high local power density is not attained. l QUESTION: 072 (1.00) t A malfunction in the pressurizer pressure measurement channel A (A/PT-102) causes the output to go to minimum. Which one of the following is the l proper system response to the malfunction? a. High Pressure and TM/LP Channels A trip causing a reactor trip. b.- Only TM/LP Channel A trips. c. Only High Pressure Channel A trips, d. High Pressure and TM/LP Channels A trip. { t

~.. ..... ~. -......... _ REACTOR OPERATOR Paga 35 QUESTION: 073 (1.00) During normal operation at 50% power, air is temporarily lost to one of the Fced Water Regulating Valves. A valid method of level control while remaining at 50% power is: a. For a decreasing S/G level, open FW Reg. Valve bypass valve. b. For an increasing level, clowly increase steam load via Turbine Bypass valve. c. For a decreasing level, reduce Tave to lower S/G steam pressure and increase feed rate. d. For an increasing level, close the FW Reg. Valve bypass valve. QUESTION: 074 .( 1. 00 ) An event for which the Steam Generator Asymmetrical Reactor Protection Trip was designed to offer protection ist a. Reduced RCS flow in one loop. b. Inadvertent closure of an MSIV. c. Steam header rupture upstream of MSIV. d. A steam generator with a high level out of control. QUESTIONt 075 (1.00) Why is a Limiting Safety System Setting for steam generator (S/G) low level reactor trip required, a. Prevent uncovering S/G tubes. b. Prevent exceeding RCS design Pressure, c. Provide sufficient heat sink until AFW is available, d. Prevent thermal stress cracking of S/G tube sheet.

s- ] ' REACTOR-OPERATOR P;ga 36 l QUESTION: 076 (1. 00) Given the following conditions: Reactor power 100% Pressurizer level: At setpoint GEMAC control knob BAL (2) position If a 40 gpm leak develops in the RCS, approximately how long will it be before the second charging pump starts? a. 100 seconds v b. 150 secon(1 c. 220 seconds d. 250 seconds QUESTION: 077 (1.00) The reactor is at 80% power when the signal from the Reactor Regulating system to the Pressurizer Level control system fails to maximum output with no operator action. Which of the following responses would you expect to see on the pressurizer lovel recorder? t a. increase to 100% b. increase to 60% J r L c. decrease to 40% d. decrease to 0% L L I

o REACTOR OPERATOR P ga 37 QUESTION: 078 (1.00) Given the following conditions: The reactor is shutdown The RCS at saturation Pressurizer temperature is 432 degrees F Actual pressurizer level is 75 inches UJing the attached TDB figures, TDB-III.1.a and TDB-III.2, determine which Cf the following describes the relationship between pressurizer level instruments LI-106 and LI-101X or Y. a. LI-101 indicates 36% and is closer to actual level than LI-106. b. LI-101 indicates 49% and is closer to actual level than LI-106. c. LI-106 indicates 49% and is closer to actual level than LI-101. d. LI-106 indicates 36% and is closer to actual level than LI-101. QUESTION: 079 (1.00) Following a loss of all AC that removes the automatic start signals from fire pumps FP-1A and FP-1B, the diesel fire pump is started by: a. Manual pushbutton from the control room. b. Manual pushbutton at the intake structure, c. Manual engagement of the starter locally. d. Mechanical pressure sensor with header pressure < 99 psi. e =

\\ .o o ' REACTOR CPERATOR P ga 38 i l QUESTION: 080 (1.00) What is the proper sequence of events and response of the compressed air cystem to an unisolable rupture beyond air compressor makeup capacity? No cther transient is in progress. a. PLANT AIR PRESS LO alarm, service air isolates, INSTRUMENT AIR PRESS LO alarm b. INSTRUMENT AIR PRESS LO alarm, instrument air isolates, service air isolates c. Standby compressor starts, INSTRUME!!T AIR PRESS LO alarm, service air isolates d. Standby compressor starts, PLANT AIR PRESS LO alarm, instrument air isolates QUESTION: 081 (1.00) Given the following conditions: The plant is operating at 100% power Tavg is indicating failed high Delta T is indicating failed low Which failure would result in these conditions? a. Thot RTD is failed high b. Tcold RTD is failed low c. Thot RTD is failed low d. Tcold RTD is failed high 4

~! .o REACTOR OPERATOR Pcg3 39 l -QUESTION: 082 (1.00) The pressurizer level transmitter selected for level control is isolated at the transmitter and the variable leg of the transmitter is depressurized. A:sume the plant is initially at normal operating temperature and pressure, cnd actual pressurizer level is at program level. What is the plant response to this condition? a. Pzr control channel level hi-lo alarm, backup heaters energize, spray valves full open. b. Pzr control channel level lo-lo alarm, spray valves shut, one backup charging pump starts. c. Pzr control channel level hi-lo alarm, letdown at maximum, proportional heaters go off, d. Pzr control channel level lo-lo alarm, letdown to minimum, both backup charging pumps start. QUESTION: 083 (1.00) What is the response of the Fire Protection System to a ffre in the EAST twitchgear room (room A)? a. The first detector actuated causes the ventilation dampers to the affected space only to shut. The second detector, actuated causes the Halon bank to discharge 50% of its contents to the affected

space, b.

After two detectors have actuated in the same space, the dampers for both switchgear rooms shut. After 60 secords time delay, the Halon bank discharges 100% of its contents to the affected space. c. The first detector actuated causes the ventilation dampers in both switchgear rooms to shut. The second detector actuated causes the Halon bank to discharge 50% of its contents to the affected space. d. After two detectors have actuated in the same space, the dampers for the affected space only shut. After 60 seconds time delay, the Halon bank discharges 100% of its contents to the affected space. i

REACTOR; CPERATOR PCgo 40 QUESTION: 084 (1.00) The Reactor. Coolant Pumps have lost cooling for seal leak-off.due to:an -inadvertent closure of one containment isolation valve that supplies the c:a1 leak-off cooler. What other components have lost cooling? a. RCP motors, and RCP oil coolers. b. RCP oil coolers, and SI Tank leakage coolers. c. Detector Well Cooling, and RCP motors. d. RCP oil coolers, and CEDMs. QUESTION: 085 (1.00) During a plant transient where SIAS is actuated and off-site power is lost, two CCW pumps are required to be operating. For which condition would only cne CCW pump be operating if one EDG failed to start? a. Bus 1B3A-4A is grounded, DG1 fails, operator action is taken. b. DG 1 fails but no operator action is taken. c. DG 2 fails but no operator action is taken. d. Bus 1B3B-4B is grounded, DG 2 fails, operator action is taken. QUESTION: 086 (1.00) During plant start up in the winter, CCW temperature is dropping below minimum allowed temperature Choose the action required of the operator. a. Reduce the Raw water flow to the inservice heat exchanger. b. Decrease the CCW flow to all components in the containment. c. Momentarily stop a CCW pump, as long as one is left running, d. Direct CCW flow through a heat exchanger not in service.

l 1 REACTOR OPERATOR P0g3 41- ] +- QUESTION: 087 (1.00) i n. With the Shutdown Cooling System in operation using one-LPSI pump, what is the approximate normal flow rate and what controls this flow rate? a. 1200 GPM / HCV-341, HX outlet.- b. 1500 GPM / FCV-326, HX Bypass. c. 2400 GPM / FCV-326, HX Bypass. i d. 3000 GPM / HCV-341, HX outlet. QUESTION: 088 (1.00) l Surveillance requirements dictate that shutdown cooling (SDC) flow be ctopped for a finite period. Given equal starting conditions of RCS tcmperature and time after shutdown, choose the safest set of conditions for performing the surveillance. a. The primary system volume does not affect safety. b. RCS at normal operating volume for SDC operation. c. SDC'in operation at mid loop RCS level. d. SDC in operation with the refueling cavity flooded. -QUESTION: 089 (1.00) 'The respective positions of the Selector Switch and Load Transfer Switch of l l c normally operating plant air compressor are: 1 e a. STANDBY and 1 or 2. b. CS and OFF. c. CS and 1 or 2. d. STANDBY and OFF. 1.

REACTOR OPERATOR PCg3 42 QUESTION: 090 (le00) All offsite power has been lost. DG1 and DG2 have re-energized buses 1A3 Cnd 1A4. The PREFERRED method to quickly restore an air compressor is: a. Start a bearing water pump from CB-10/11 and then restart the compressor from CB-10/11. b. The standby air compressor will start when its power supply bus is re-energized. c. Send an EONT to room 19 to establish backup cooling and start the air compressor. d. Start a bearing water pump from CB-10/11 and send an EONT to manually start an air compressor. l i QUESTION: 091 (2.00) { l Match the areas in Column A, as labeled on the attached figure from j Standing Order 0-1, Appendix 12.1, to the correct description in Column B. E;ch' description in Column B may be used only once or not at all, and only a single answer may occupy one answer space. Column A Column B i I (Areas on figure) (Description) j l a. 1. Control Board Operations Area i 2. Control Room Boundary b. 3. Main Control Area 4. Emergency Surveillance Area c. 5. Shift Supervisor's Office 6. Computer Room d. 7. Equipment Room I

• .e

-REACTOR OPERATOR Pago 43 l . QUESTION: 092 (2.00) Match the occurrences in Column A with the appropriece problem identification and correction method in Column B. Each method may be used once, more than once, or not at all, and only a single answer may occupy one answer space. Column A Column B (Occurrences) (Method) a. Eating in radiologically 1. Radiological controlled area. Work Practices Program b. Dropping and breaking a self reading pencil dosimeter. 2. Radiological Occurrences Reporting c. Valve packing leak in liquid and Training radwaste line spilling 10 gallons of laundry water then being isolated. 3. NRC Incident Report d. Poor frisking practices. QUESTION: 093 (2.00) Match each of the components in Column A with the Engineered Safeguards Control (ESC) signal in Column B that causes it to change position. The oignals in Column B may be used once, more than once, or not at all,.and only a single answer may occupy a single answer space. Column A column B (COMPONENTS) (ESC SIGNALS) a. 480 V load shed 1. SIAS 2. CSAS b. CCW heat exchanger 3. RAS inlet & outlet valves 4. CIAS 5. VIAS c. Containment air cool-6. SGIS ing units VA-7C and VA-7D 7. AFAS d. Chemical and Volume control System letdown isolation valves

REACTOR OPERATOR Paga 44 -QUESTION: 094 (2.00) Given the following conditions: Prest,urizer pressure is 2270 psia decreasing. Presuurizer level is -3.0% from program level and decreasing. The reactor is operating at 100%. Charging pump Standby Switch is selected to CH-1B-1C. Match each of the components in Column A with the correct condition in the Column B for the event described above. (NOTE: Terms such as OFF and MINIMUM are NOT synonymous.) The conditions in Column B may be used once, core than once, or not at all, and only a single answer may occupy one answer space. Column A Column B (COMPONENT) (CONDITION) a. Spray valves 1. ON 2. OFF b. Proportional heaters 3. OPEN 4. SHUT c. Letdown flow control valves 5. MAXIMUM 6. MINIMUM d. CH-1A 7. 1/2 OPEN 8. 1/2 MAXIMUM

i REACTOR OPERATOR Pag 3 45 QUESTION: 095 (2.00) Match each of the plant locations in Column A with<the type of automatic fire suppression system installed at the location in Column B. The items in Column B may be used once, more than once, or not at all, and only a cingle answer may occupy one answer space. C31umn A Column B (LOCATION) (SUPPRESSION SYSTEM) a. Turbine Lube Oil Reservoir 1. Dry pipe i 2. Wet pipe b. Cable Spreading Room 3. Deluge 4. Pre-action c. Diesel Generator Rooms 5. Cardox 6. Halon d. Air Compressor Room t (********** END OF EXAMINATION **********)

i o REACTOR OPERATOR Pr.g3 46 ANSWER: 001- (1.00) C.

REFERENCE:

FCS S0-G-28, p. 7 194001K113 194001K116 ..(KA's) 1 ANSWER: 002 (1.00) b. i

REFERENCE:

FCS TS 5.11.2, p. 5-19a 194001K104 ..(KA's) i ANSWER: 003 (1.00)

a..

l

REFERENCE:

FCS RP-201, p. 7 194001K103' ..(KA's) ANSWER: 004 (1.00) d l

REFERENCE:

FCS-S.O. O-20, p. 5 194001K102 ..(KA's)

o. ' REACTOR.CPERATOR P2go 47 l i' ANSWER: 005 (1.00) d. 1

REFERENCE:

FCS S.O. 0-16, p. 2 194001A102 ..(KA's) ] 1 H ANSWER: 006 (1.00) d.

REFERENCE:

TDB Figure II.D.5 & V.1-2 194001A108 ..(KA's) ANSWER: 007 (1.00) b.

REFERENCE:

FCS TDB-II.B.6. [ l l 194001A108 194001A102 ..(KA's) l. i l -. ANSWER: 008 (1.00) c.

REFERENCE:

FCS S.O. O-1,

p. 92 194001A104

..(KA's) i 1

O!' li., * '<' s REACTOR OPERATOR Ptg3 48 i is ' MLSWER: 009 (1.00) c. 4

REFERENCE:

i FCS S.O. G-7, p. 2 194001A101 ..(KA's) 7 ANSWER: 010 (1.00) i b.

REFERENCE:

I FCS TS 2.10.2 Basis 000005K103 ..(KA's) P ANSWER: 011 (1.00) d.

REFERENCE:

FCS OI-RC-9, p. 2 l L 000015K202 ..(KA's) ANSWER: 012 (1.00) l c. l' l-L

REFERENCE:

FCS LP 7-12-10, p. 16 000040K201 ..(KA's)

y..o . i REACTOR OPERATOR Pcg3 49

ANSWER:

013 (1.00) .b.

REFERENCE:

FCS LP 7-12-1, p. 7-10 FCS LP 7-12-2, p. 7 000068A209 ..(KA's) ANSWER: 014 (1.00) d.

REFERENCE:

FCS EOP-00, p. 25, 27 1 l t ANSWER: 015 -(1.00) .c.

REFERENCE:

FCSLSTM AUX. FEEDWATER, p. 14 l FCS'EOP-05, p. 16' l 000074A102 ..(KA's) l l l l ANSWER: 016 (1.00) c. l v

ia REACTOR CPERATCR P g3 50

REFERENCE:

FCS 7-11-17,.p. 30 000074A125 ..(KA's) ANSWER: 017 (1.00) o.

REFERENCE:

FCS EXAM QUESTION BANK, 1.7.12.25, 1.6 000015A203 ..(KA's) i ANSWER: 016 (1.00) c.

REFERENCE:

FCS E0P-07, p. 5 000057G012 ..(KA's) ANSWER:~ 019 (1.00) .e. or'd. (based on post-exam review by the facility, d. was also accepted i L for full credit)

REFERENCE:

[ FCS E0P-00, p. 33 (Edditional references cited by the facility reviewers) FCS E0P-00, p. 11 and 16; FCS E0P-05, p. 2 000057G011 ..(KA's) t f b.

u. REACTOR OPERATOR .PCg3 51 F L l L . ANSWER:- 020 (1.00) Q. i

REFERENCE:

FCS EOP-00, p. 7-9 t 000057G010 ..(KA's) ^ ANSWER: 021 (1.00) c.

REFERENCE:

FCS OI RC-7, p. 5 L 000027K303 ..(KA's) P ANSWER: 022 (1.00) l

o..

REFERENCE:

FCS EXAM QUESTION BANK, 7-12-J4, 1.5 -i 000027A216 ..(KA's) t ANSWER: 023 (1.00) d.

REFERENCE:

l-FCS OI-RC-3 p. 12, STM - ECCS p. 10 l-000027K101 ..(KA's) l t I-1.

j i REACTOR OPERATOR PCg3 52 -ANSWER: 024 (1.00) d. 1

REFERENCE:

.] FCS STM CCW, p. 10 1 000026A101 ..(KA's) i ANSWER: 025 (1.00) 1 b. l 1 REFERENCES FCS STM-CCW

p. 13 000026A10.1

..(KA's) ' ANSWER: 026 (1.00)

d. ;

REFERENCE:

FCS STM ECC, p. 17 000025K101 ..(KA's) e ANSWER: 027 (1.00) l l d. l

REFERENCE:

FCS AOP-19, p. 8 l l-000025A207 ..(KA's) 1, 1

~ REACTOR OPERATOR PCg3 53 ANSWER: 028 (1.00) c.

REFERENCE:

FCS LP 7-11-20, p. 58, 59 000008A101 ..(KA's) ANSWER:- 029 (1.00) .b.

REFERENCE:

1 FCS AOP-22, p. 49 000008A102 ..(KA's) -ANSWER: 030 (1.00) a. =

REFERENCE:

FCS AOP-22, p. 49 000008A105 ..(KA's)

ANSWER:

031--(1.00) l c.

REFERENCE:

FCS'OI-RR-1, p. 4 L

000001K208 ..(KA's) I

I ] REACTOR OPERATOR Pag 3_ 54 ) i l ANSWER: 032 (1.00) b.

REFERENCE:

J FCS OI-RR-1, p. 1 000001K206 ..(KA's) ' ANSWER: 033 (1.00) c.

REFERENCE:

FCS EOP-20, p.72, 88 000058K301 ..(KA's) ANSWER: 034 (1.00) L b.

REFERENCE:

Fi!S EOP-02 p. 13-I r 000058G012 ..(KA's)- l-ANSWER: 035. (1. 00) Ed..

REFERENCE:

FCS EOP-00, EOP-20 000058G011 ..(KA's)

r-REACTOR OPERATOR'- Pago 55 1 1 ANSWER: 036 (1.00) b. j

REFERENCE:

FCS STM AFW, p. 18 000054A102 ..(KA's) P ANSWER: 037 (1.00) d. I t

REFERENCE:

FCS EOP-00, p. 16 000054G010 ..(KA's) i l t ANSWER: 038 (1.00) b. L C

REFERENCE:

i FCS'E0P-06, p. 3 1: 1 000054G011 ..(KA's) ANSWER: 039, (1.00) d.

>.a.. REACTOR CPERATOR POg3 56 l ~

REFERENCE:

FCS AOP-15, p. 7 FCS'TS 2.15 000033G011 ..(KA's) ANSWER: 040 (1.00) d.

REFERENCE:

FCS AOP-02, p. 10 000003G003 ..(KA's) s ANSWER: 041 (1.00) d.

REFERENCE:

FCS LP 7-12-3 p. 29-41 000037K307 ..(KA's) ANSWER: 042' (1.00) o.

REFERENCE:

FCS QB 7-17-04, 1.13 000037K308 ..(KA's) ANSWER: 043 (1.00) l C. l

,,a REACTOR CPERATOR .Pcg3 57

REFERENCE:

FCS LP 7-12-7 SHB, p. 7 -000036A101 ..(KA's) ANSWER: 044 (1.00) c.

REFERENCE:

~FCS OP-10, A.39-7 000036A102 ..(KA's) t ANSWER: 045 (1.00) c.

REFERENCE:

FCS.STM, MAIN 1 STEAM, p. 13-15 i 000056A101 ..(KA's) i t ANSWER: 046 (0.00) .D3leted this question based on post-exam review and comment.

REFERENCE:

FCS OI-WDG-02, REV. 08, p. 2 - 1 (cdditional reference cited by facility reviewers) L PCS OI-WDG-02, Rev. 08, p. 3 071000A202 ..(KA's)

E" l l d ] {.-c JtEACTOR OPERATOR Pcg3 58 s 1 h; - L ANSWER: 047 (1.00) h d. t

REFERENCE:

1 FCS LP 7-11-31 SH, " GAS DECAY TANK FLOWPATH" LINE DIAGRAM (- FCS LP 7-12-3 p. 24, 35. 071000A209 ..(KA's) j;>- ANSWER: 048 (1.00) b.

REFERENCE:

FCS LP 7-12-3 REV 2,

p. 48, 49 FCS LP 7-11-31 REV 2 SH " DISCHARGE FLOW CONTROL VALVE CIRCUITRY" LOGIC r

DIAGRAM 071000A303 ..(KA's) ANSWER: 049 (1.00) b.

REFERENCE:

FCS LP 7-12-3 REV 2,

p. 48, 49 FCS P&ID 11405 M-9, OI WDL-3 REV 19 FCS LP 7-11-31 REV 2 p. 32 068000A402 068000A302 068000A204

..(KA's) 1 l ?. ANSWER: 050 (1.00) d.

1 REACTOR CPERATOR Paga 59 1 i

REFERENCE:

FCS ST-RPS-1 REV 43, p. 8. FCS NUCLEAR INSTRUMENTATION STM, p. 26 015000A101 ..(KA's) 4 ANSWER: 051 (1.00) o.

REFERENCE:

1 i FCS NUCLEAR INSTRUMENTATION STM, p. 25 015000A104 ..(KA's) ANSWER: 052 (1.00) c.

REFERENCE:

FCS TS 2.8-072000K302 ..(KA's) ANSWER: 053 (1.00) -b.

REFERENCE:

FCS LP 7-14-2, p. 34, 35 FCS ESC STM p. 8 FCS MR-88-110 p. 4 022000K402 022000K403 022000A301 013000K103 (KA's) i

REACTOR OPERATOR Page 60 ANSWER: 054 (1.00) d.

REFERENCE:

FCS L.P. 7-11-31, D.1.1, 7-12-3, p. 25 071000A405 ..(KA's) ANSWER: 055 (1.00) a.

REFERENCE:

FCS NIS STM, p. 2, 9, 13, & 14 015000A102 ..(KA's) ANSWER: 056 (1.00) c.

REFERENCE:

FCS NIS STM, p. 10 015000A103 ..(KA's) ANSWER: 057 (1.00) b.

t. REACTOR' OPERATOR Page 61

REFERENCE:

.FCS, Engineered Sateguards Controls STM, p. 14 FCS AOP-8, p. 1 FCS L.P. 7-12-3 SHB 072000K402 072000K403 073000K401 ..(KA's) = ANSWER:- ~058 (1.00) a.

REFERENCE:

FCS Reactor Protection STM, p. 26 h- [ 001050K202 ..(KA's) ^

ANSWER

059-(1. 0 0 )-

d.

E

REFERENCE:

v-FCS L.P. 7-12-26, p. 47 0010.00G009~- ..(KA's) az

ANSWER:

060 (1.00) i a, y

REFERENCE:

FCS RCS STM,'p. 17 003000K614 ..(KA's) ~ L K. m 2 ^ ,V k

n r .\\ s REACTOR OPERATOR Pags.62 i ANSWER: 061 (1. 00) c..

REFERENCE:

s FCS Chemical'and Volume Control STM, p. 44 004000K123 ..(KA's) .s s A.NSWP.R: 062- (1.00) n. 1

REFERENCE:

FCS AOP-22, p. 2, 7. 1 l: 022000A405 ..(KA's) e J ANSWER: 063 l(1.00) i d.. 1' 1 1

REFERENCE:

i i l L FCS Chelmical,and Vo'lume Contrcl STM, p. 55-59 l' FCS;TS 2'.2 004000G011 ..(KA's) ' ANSWER:: 064 (1.00). i b e'- r 1; h i 4 l' y -I: 'l ~

o. s -REACTOR OPERATOR' Paga 63

REFERENCE:

FCSDComponent Cooling Water STM, p.o16 022000A301 ..(KA's) ' ANSWER: 065- (0.00) ' Deleted'this question based on post-exam review and comment.-

REFERENCE:

-FCS Auxiliary Feedwater STM, p. 19 -(additional references cited by facility reviewers) FCS Chemistry procedure' CMP-1.0; YCS AOP-30, Rev. O,

p. 4 061000K401

..(KA's) ANSWER: 066- (1.00)- .a..

REFERENCE:

FCStAuxiliary Feedwater STM,.p. 13 FCS OP-3,,p.-

1-1061000K101

..(KA's) -ANSWER: 067', (1. 00)' b.

REFERENCE:

'FCS LP'.7-11-20, p. 34 010000K403- ..(KA's)

.? 3 ,. g.:.. :- o REACTOR OPERATOR. ..Pccj3 64' L ANSWi'R: 068- (1.00) a 0. l' 1: l

REFERENCE:

i FCS LP 7-11-20, p. 34, 35 010000K602 ..(KA's) ... ANSWER: 069 (1.00) c.. l-L

REFERENCE:

FCS LP 7-11-12, p. 53 1 .086000K504- ..(KA's) . ANSWER: 070 (1.00) i, 1> ld. 1' [

REFERENCE:

i.: L -FCS LP 7-12-25, p. 30 012000G001 ..(KA's) ANSWER: 071 (1.00) 'd.

REFERENCE:

FCS STM, RPS, p. 22, 23 012000G004 ..(KA's) /' 1

6- ,10 3 + ~l. c. ;,: c =.,.... n . REACTOR OPERATOR' Pag 3 65 4 JANSWER:- .072 (1.00) 'b.

REFERENCE:

FCS'LP 7-12-25, p. 57 012000A202 ..(KA's) ANSWER:' 073- (1. 00) - i l

REFERENCE:

i FCS STM FEED & CONDENSATE, p. 37 .l 035000G001- ...(KA's) ANSWER:- 074- (1.00) l-

b. :

1:1

REFERENCE:

FCS-STMIMS, p. 31 035000G004 ..(KA's) i j ANSWER: 075 (1.00)~ b. [:

REFERENCE:

FCS STM, MN. STM., p. 26 035000G005 ..(KA's) =

g 7 hi 4 - }. 5 ~ ' REACTOR' OPERATOR Pags 66 J ' ANSWER: -076-- (l'. 00 ) i c. (based on 52 gpm = 1.3 %/ min)

REFERENCE:

FCS STM, 7-11-20, Rev. 3,

p. 125; SHB 7-11-20, Rev.

3, p. 41 ~ 011000A101 ..(KA's) ANSWER: 077 (1.00) 'b.

REFERENCE:

FCS STM,c7-11-20, Rev. 3,

p. 38 011000A104

..(KA's) A!;SWER: 078 (1.00)

d..

REFERENCE:

-) ~FCS STM, 7-11-20, Rev. 3,

p. 37;. Steam Tables 3

1 010000K501 ..(KA's) l~ ANSWER:' 079 '(1.00) -C. l l.

REFERENCE:

'FCS STM, 7-11-12, Rev. 2, LO 1.0 086000K400 ..(KA's) l; 1

.' o. -.

REACTOR [ OPERATOR Pago'67 ANSWEtt

-080 (1.00) 1 C.

REFERENCE:

FCS LP 7-11-7 p. 30, OP-10 p. A 26, 27, AOP-17 p. 6, 14, MR-88-011 p. 2, 3 079000K101 078000K402 078000K301 078000A301 078000K302 ..(KA's) ANSWER: 081 (1.00) d.

REFERENCE:

'FCS LP 7-12-24 p. 14-16, 67 002000K606' 016000A201 ..(KA'c) ANSWER: 082 (1.00) -d.

REFERENCE:

'FCS STM CVCS, p. 41, OP-10-A4, p. 9. 27 011000A208 ..(KA's) '_; ANSWER:- 083 (1.00) .b. i 'l

) ec7-3, ; -.;,

REACTOR OPERATOR '

.Paga 68'

REFERENCE:

I p, -.FCS'SD III-16-p.'60,_LP 7-11-12 p. 62-72, LP 7-14-1 p. 36 " 1086000K405 086000K403 ..(KA's) ANSWER:) 084 (1.00) d. r i

REFERENCE:

4 FCS STM CCW, p. 8' o 008030K302- ..(KA's)' ANSWER: 085 (1.00) .t b.

REFERENCE:

FCS STM.'CCW, p.15, 16 .008030K201 ..(KA's) ANSWER:- 086 l(1.00) e od. - {

REFERENCE:

I 4 -FCS STM CCW, p. 12, 15 4 008030A404 ..(KA's)

ANSWER:i, 087 (1.00).

m b. J d

.A g :. c 4. 1 .A REACTOR OPERATOR Pags 69 m J

REFERENCE:

4

ii. FCS'LP 7-11-23, p. 22-31 005000A102

..(KA's) ' ANSWER: 088 (1.00) d. s

REFERENCE:

FCS AOP-19, FIG'S 2,,3, &4 005000A106-. ..(KA's) l. e ANSWER: 089. (1.00) l -c. l

REFERENCE:

FCS.OI CA-1, p. 8.. lt FCS STM,-COMPRESSED. & INST. AIR, p. 5

078000K401-

.. -( KA ' s ). l l: l ANSWER: 090. (1.00)- 1 c.:

REFERENCE:

FCS EXAM BANK QUESTION 17-11-07, 1.2 q. . 078000K403 ..(KA's) 4 l t ' L ' E -

.) 4: : a: o'; -r 1RF.ACTORiOPERATOR Pags 70 h ANSWER:' '091 '(2.00) - C '. 3 b.- 1 -c. 4 .d.. 5 -- . i..

REFERENCE:

FCS.:S0-0-1, p. 84 194001K105 ..(KA's) l l. ANSWER: 092 (2.00) i

10. '

1 l b.: 2'

c.-

2 d' 1:

REFERENCE:

l -FCS: Radiation ~ Protection Plan Section 11.3, p. 100 ~194001K104 ..(KA's) i t 1

ANSWER:

'093 (2.00) l l 1 <g, 1. b. 1 L-c. 2' L d. 4 l-i,

REFERENCE:

i;. FCS Engineered Safeguards Controls STM, p. 7-13 -013000K106 ..(KA's)- ^ f ' [:

~ l ,. - y REACTOR OPERATOR-Page 71' ANSWER':' 094 (2.00) s.> '3. --open b. 2. Off. c. 6. Minimum d '. 1. .On i

REFERENCE:

.FCS LP.7-11-2,;LO 4.1 011000A102 010000K603 ..(KA's) ANSWER: 095 (2.00) .a. 3. . Deluge-b.- 6. Halon c '. - 1. Dry = Pipe d. 4. Pre-action i

REFERENCE:

.FCS SD III-16 REV 18, p. 40, 54,.77,-81, AOP 2203.09 REV 8,~p. 6'6 1 0 086000K404 086000A302 ..(KA's) l- ~ l t \\ ..i. c._ l (.. I 1' l I. (********** END OF EXAMINATION **********) l: 1.i L =}}