ML20246N713

Exam Rept 50-458/OL-89-01 on 890214-17 & 22-23.Exam Results: All 13 Candidates Passed All Portions of Exams & Issued Appropriate License

ML20246N713
Person / Time
Site:	River Bend
Issue date:	03/20/1989
From:	Graves D, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20246N709	List: ML20246N705 ML20246N713
References
50-458-OL-89-01, 50-458-OL-89-1, NUDOCS 8903280011
Download: ML20246N713 (93)

Text

{{#Wiki_filter:~ 'l_i ~ 1 .0 \\' APPENDIX: U. S. NUCLEAR REGULATORY COMMISSION-REGION IV ' Operator Licensing Examination Report: 50-458/0L 89-01 Docket No.: 50-458 Operat'ing License No.: ' NPF-47 Licensee: Gulf States Utilities P. O. Box 2951- ' Beaumont, TX 77704 - Facility: River Bend Station. Examinations at: River' Bend Station (RBS) .i . Chief Examiner: 5 bO .Qc D.'N.. Graves Examiner Date: Operator ~ Licensing Section Division of Reactor Safety ' l l 2Ofd9 Approved by: o . Pellet, Chief Date l Operator Licensing Section Division of Reactor Safety Summary NRC Administered Examinations Conducted the Weeks of February 14-17,'and 22-23, 1989 (Report 50-458/0L 89-01) ' NRC administered examinations to four R0 and nine SRO applicants. A'll thirteen candidates passed all portions'of their examinations-and have been issued the appropriate license. Several simulation facility fidelity items were noted and are detailed in the Simulator Fidelity Report. o 4 v

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j 1 , t I 1 DETAILS l 1 i 1. Persons Examined j SR0 R0 Total .] License Examinations: Pass - 9 4 -13~ l Fail - 0 0-0 2. Examiners '1 D. N. Graves,' Chief Examiner J. L. Pellet K. M. Spencer J.-M. Mcghee q .i 3. Examination Report Performanceresultsforindividualexamineesarenotinc1Uded:inthis report as it will be placed in the NRC Public Document Room and.these. results are not subject to public disclosure, a. Examination Review Comment and Resolution Ir, general, editorial coments or changes made~ during the examination, or - subsequent grading reviews are not addressed by this resolution section. ~ .i This section reflects resolution of substantive coments made by RBS 1 staff. The only comments addressed in this section are those.which j were not accepted for incorporation.into the examir;ation or answer i key. Those comments accepted are incorporated into the master examination key, which is included in this report. Coments may be paraphrased for brevity. Theifull text of the comments is-attached.. l 3.31a Request additional correct answer to' read."Use in critical j or emergency' situations only." Response: The question specifically asks.for the' purpose.of the-2000: series key, which is to open valve locks. 5.16 Request additional correct answer to read 1" downshift-recirculation pumps to LFMG." Response: The pumps are downshifted to prevent'a. turbine trip on high levelfwhen.they are tripped, not to. add negative-reactivity'. 6.27 Request additional correct answers to be "b", "c", and "d". i C_ ~ UJ

g .w [ iu .a P.[ j L. m q c q i .i i Response: In all cases, the Recovery Manager is making the recommendations.. He/she may be acting in an additional ' capacity as well,'such as Emergency Director; but'he/she is stil.1-the Recovery Manager. 'l b. Site Visit Sumary (1) ' At the end of the written examination administration, the. J facility licensee was provided a copy.of the examination 1and-1 answer key for the purpose.of commenting on the. examination l content validity.: The licensee was.infomed that written:. examination. grading would not_ be. started 'until' licensee' review. comments were received in the. regional office?. A set of comments ~was provided;to.and discussed with the Chief Examineri-at the end of the.first week of; examinations prior,to leaving the site. ~F (2) The following items were communicated to the facility licensee-1) representatives as comments, observations, suggestions, or 9 deficiencies: 1 d (a) When shifting the recirculation pumps to fast speed, the, switches had to.be held in the " START" position for several i seconds to effect the transfer. Failure to do so resulted in the trip of the pump.' If the switches do need to be ' o i held in a specific position for a specific length of time, the procedure should address this_. fact. If the: switch does not need to be held in the' required position ~ for that

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i length of time, then the simulator does not correctly model: actual plant conditions. (b) A number of. candidates were~not aware that copies of~ Radiation Work Permits were kept in the Shift Supervisor's office. ) i c. Master Examination and Answer Key ] Master copies of the RBS license examinations and' answer keys are.. h attached. The facility 1.icensee coments wh.ich have been accepted are incorporated into the answer. key.; 1 d. Facility Examination Review Comments The facility licensee. comments regarding the written examinations are attached. Those comments'not incorporated into the answer key have been addressed in the resolution section of this report. a e. Simulation-Facility Fidelity Report - All items in the attached Fidelity Report have been discussed with -the licensee staff. l

l U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION 1 REGION 4 I FACILITY: Blvgr_@2Dd_1_____________ REACTOR TYPE: BWB-QEh__________________ j l DATE ADMINISTERED: gg40241d_________________ l l INSIBUCIl0NS_IQ_QaNQlDoIE1 l Use separate paper for the answers. Write answers on one side only. q Staple question sheet on top of,the answer sheets. Points for each i question are indicated in parentheses after the question. The passing { grade requires at least 70% in eacn category and a final grade of'at 'j least 80%. Examination papers will be picked up six (6) hours after the examination starts. l % OF CATEGORY % OF CANDIDATE'S CATEGORY l __VaLUE_ _IQIaL ___EQQBE___ _VaLUE__ ______________CaIEQQBl_____________ l _25tDQ__ _25ths ________ 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) l _ZhtDQ__ _2hthZ ________ 2. EMERGENCY AND ABNORMAL PLANT I EVOLUTIONS (27%) I _dhthD__ _dZ1h2 ________ 3. PLANT SYSTEMS.(38%) AND 1 PLANT-WIDE GENERIC R RESPONSIBILITIES (10%) I i _HZzhD__ TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature i 1 e 1 1 1 l J

y i l l 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 j 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 1 room to avoid even.the. appearance or possibility of cheating. 3. Use black ink or dark pencil'only to facilitate legible reproductions. 4. Print your name in the' blank provided.on the cover sheet of the j examination. i 5.. Fill in the date on the cover' sheet of the examination (if necessary). 6. Use only the paper provided for answers. 7. Print your name in the upper right-hand corner of the first page of each i section of the answer sheet. 1 8. Consecutively number each answer sheet, write "End of' Category __"~ as appropriate, start each category on a new.page, write only on one side of the paper, and write "Last Page" on the last answer sheet, g. Number each answer as to category and number, for example, 1.4, 6.3. )

10. Skip at least three lines between each answer.-

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

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12. Use abbreviations only if they are commonly used in facility literature.

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13. The point value for each question is indicated'in parentheses after-the question and-can be used as a guide for the depth of answer required.

14. Show all calculations, methods, or assumptions used to obtain an answer.

to mathematical problems whether indicated in toe question or not; l 1S, Partial credit may be given.- Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions cf I

the examiner'.only. 1 17.- You must sign the statement on the cover sheet that indicates that the I work is your own and you have not received or been given assistance in l completing the examination. This must be done after the examination has been completed. l l 1 l l t l l

i .i r ( l s.. I' ) , 18.fWhen.you complete your examinati~on, you shall: a. Assemble your examination as..follows:- '(1) Exam questions on. top. 1 (2) Exam aids - figures, tables, etc. J (3) Answer pages including' figures which are'part of the answer. l b.- Turn.in,your copy of-the examination'and all.pages'use'd to., answer l; ~the examination questions. ~ c. . Turn in all scrap ' paper.,and the balances o.f the paper.that you did not use for answering-the questions. 1 t 1 1 as defined by;the examiner.- If after-q l d. Leave the examination area, l. ' leaving, you'are found in this area while'the-examination is still' l-in progress, your,-license may be denied or revoked. 1 l \\ t { f u .j l. l l

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d Page 4 l 12__BE69IDB_EBINGIELES_LZ11_IBEBdQDXNodICS LZ11_6ND_G9dE9hENIH_L1111_LEUNDedENI6LS_EX8dl QUESTION 1.01 '(0.00) GENERIC FUNDAMENTALS EXAM i l l l l I l l l '1 1 1 1 1 i i l i 1 l l l l l l 1 (***** END OF-CATEGORY' 1 *****)

f. .c 6 ,e N{g uj - 2t__EdEBGENCX_eND_eBN9BdeL_PL6NI_gygLyIIQNg . Pade 15 12Z11-ti a p QUESTION 2.01 (2.00). 'The "At the Controls" operator.will manuallyfinitiate a reactor scram when one-of two general conditions are met. State.these.two gpneral s conditions per A0P-0001, " Reactor Scram." ( 2. 0 )' - QUESTION '2.02 (2.00) The automatic actions l'isted.for a main turbine andfgenerator. trip'per ( AOP-0002, " Main-Turbine end Generator Trips", include' reactor scrams. For parts "a" Land "b" below select'the answer.from. items: 1 - 4'that will-initiate'the reactor scram. s. The-turbine trips from.15%. reactor. power -(1.0) l i. 1. Main turbine.stop valve position 4~ 2. Turbine control valve position l 3. Reactor vessel level l 4. APRM b. The turbine trips from 45% reactor power (1.0) 1. Main turbine stop valve position. } a-2. Turbine control valve position' i 3. Reactor vessel level 1: 4. APRM L l l' 1:h QUESTION 2.03 (2.00) L j River Bend E0P's acknowledge three viable mechanisms of adequate core cooling. List the three-mechanisms, INCLUDING which one is. preferred.(2.0). g i I l l L (***** CATEGORY 2 CONTINUED:0N NEXT-PAGE *****) L _ _= - --

y 1 4 21_ _ E U E B D E NG L 6 N D_6 B N9 B d 6 L _ E L 6NI_ E Y D L UI I O N S Page 6 L2Z11 l 1 l i QUESTION 2.04 (1.00) i A ceram condition exists (MSIVs shut) with the reactor at power., The j racctor did not shutdown. Core cooling is adequate. Which concsrn below is being most severely challenged in this condition? (1.0) c. fuel integrity b. RPV integrity c. containment integrity d. inj ection system operability i QUESTION 2.05 (2.50) If the control rods fail to insert when required on a scram, state FIVE (5) methods that may be tried to obtain control rod insertion.per E0P-1A. (2.5) 1 i QUESTION 2.06 (0.50) If boron injection is required and SLC is not available, what is the most reliable alternate method of inj ecting boron at River Bend? (0.5) QUESTION 2.07 (2.50) The reactor is operating at 100% when one recirculation pump trips due to en electrical fault. I c. What immediate actions are required per AOP-0024, " Decrease in Recirculation System Flow Rate"? Include any conditional actions, (i.e. If then ...) and values as applicable. (1.5) b. Even though Technical Specifications allow for operation of the plant in single loop, what additional authorization is required? C0.5) I 1 c. What is the main operational concern due to a loss of forced j f recirculation through the core? (0.5) j (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) j

. l i 1 i 2t__EdEBGENGX_6ND_6BNQBd6L_PL6NI_EVOLUIIDNS Page 7 l 12Z11-I l J -QUESTION 2.08 (2.00) a.. A loss of 125 VOC has occurred. How should the'mainLturbine be (1.0) tripped if the trip pushbutton on.the EHC' panel does not. function? b. I f.. t h e loss.of 00, involved control power to.the main generator output 1 breakers, whatinegative consequence would occur as s' result of j tripping the main turbine? (1.0) - 1 r I l 1 1 l QUESTION 2.09 (1.00) p e. During a station blackout 1 l Closs of all AC,' including EDGs), what is L the only system capabit of inj ecting ~ into the RPV7 ( 1. 0 )- j l 0 l l l l l l QUESTION 2.10 (2.00) j l l a. Describe why both an increase and a decrease in Off Gas. flow.might be j i indicative of the cause of a loss of condenser. vacuum. (1.0) j l b. At what point during a loss of condenser vacuum would.aLreactor scram automatically occur (setpoint) and what would initiatec it? Assume NO OPERATOR ACTION. . ( 1. 0 ). ] l L 1 l -QUESTION 2.11 (2.00) l a. When, during a loss of Reactor Plant Component. Cooling. Water ( C C P.), l should the reactor be scrammed? (1.0) l l b. Which one of the following loads will not be affected by a loss;of ' l CCP: (1.0) 1. Drywell coolers 2. Drywell equipment drain heat exchanger 3. RWCU pump seel cooler 4. RHR' pump seal cooler 4 l' (***** CATEGORY 2 CONTINUED ON NEXT,PAGE

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.- ] j 21__EdEBDENC1_6ND_6HNQBdeL_EL6NI_EYQLUIIONS: Page 8 l 'f2211 7 j 'I QUESTION 2.12 (2.00) t -r State =the name of'the radiation monitor (with automatic. actions) that'will- -j alarm.and the automatic ~ action' associated with that' monitor'if a fuel" i handling accident causing significant damage to.a' fuel bundle occursLin: j a. Fuel Building -(1.0) ( b. Containment- . (1.0) l l I l 1' l l

QUESTION 2.13 (1.00) l

~ l Arrange the following four systems in order-of. preference.for making up.to the' Upper Containment Pool if the leakage rate exceeds the sump capacity I and a fuel bundle is not in a safe storage location:- ( 1. 0 ); j l l a. HPCS inj ect ion j l l b. Standby Service Water crosstie to FPC HX's 'J l c. Condensate System injection via Feedwater lines l L d. Standby Service Water via RHR B l a 1 l 1 l QUESTION 2.14 (2.50) { l l State five (5) conditions requiring Emergency RPV Depressurization per the River Bend E0P's. (2.5) l l Q'UESTION 2.15 (1.00) L List the three (3) injection systems that should be initiated prior to L ovacuating the control room during the implementation of:A0P-0031, " Shutdown from Outside the Main Control Room." (1.0). L l l l b> (***** END.0F CATEGORY 20*****) l i o

1 2___EL6HI_SISIENS_fSpil_6NQ_EL6NI:WIQg_QgNEBIQ Page 9 BESEQUSIBILIIIES_ flail I j i l 1 l 1 .l QUESTION 3.01 (1.00). ) l An event has occurred which has caused RPV level to decrease to 6", RPV l pressure has reached 1075 psig, and drywell pressure has reached 1.2 psig. Which of the following correctly describes the status of the scram valve solenoids, the backup scram valve solenoids,. and the ARI solenoids for the. I above conditions. No manual actions have been taken and the event occurred during power operation with the Mode Switch in RUN. (1.0) O. Scram solenoids deenergized, backup scram solenoids deenergized, ARI l solenoids deenergized j l 1 b. Scram solenoids deenergized, backup scram solenoids energized, ARI l solenoids deenergized l 1 I l c. Scram solenoids deenergized, backup scram solenoids energized, ARI solenoids energized j i d. Scram solenoids energized, backup scram solenoids deenergized, ARI l solenoids deenergized ( i QUESTION 3.02 (1.00) l The Alternate Rod Insertion logic is automatically actuated at the same setpoint as which one of the following: (1.0) i a. Reactor scram b. Main Steam Line isolation c. Low Pressure Core Spray actuation d. ATWS trip of both Recire pumps (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__EL6NI_SISIEUS L2a11_6ND_EL6NI:WIDg_QENEBlQ Page 10 l l BESEDNSIBILIIIES_ LIQ 12 ) i J QUESTION 3.03 (1.50) l For each of the following, state the normal power supply AND indicate whether the supply is safety-related or not: (1.5) l o. Scram pilot valve solenoids b. Backup scram valve solenoids c. ARI valve solenoids l I i l QUESTION 3.04 (4.00) l l o. List the setpoints for the RC&IS Low Power Setpoint (LPSP), Low Power l Alarm Point (LPAP), and High Power Setpoint (HPSP). (1.5) i l b. What is the measured variable that determines these setpoints? (0.5) I c. Describe the control function performed / changed by each setpoint (LPSP, HPSP) and alarm point (LPAP)? (1.5) ] I d. What action must an operator take if a control rod is withdrawn in j l Operational Condition 1, one turbine bypass valve is 50% open and I thermal power is greater than the LPSP? (0.5) QUESTION 3.05 (2.50) l List five (5) controls available to the control room operator which would stop Recirculation Flow Control Valve movement if the valve starts to ramp open while operating in Loop Manual control. (2.5) l l QUESTION 3.06 (1.50) 1 Name three (3) systems receiving inputs from the Containment and Reactor Vessel Isolation Control System (CRVICS) that have BYPASS SWITCHES i associated with them that, if the switches are taken to BYPASS, will l provent automatic isolation of these systems. (1.5) l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__EL6NI_SXSIEb1_f2811_6SD_EL6NI: WIDE _QENEBIC Page 11 BESEQNSIBILIIIER_LIDil j QUESTION 3.07 (0.50) j i { l Which system covered by CRVICS will'not isolate (neither inboard nor outboard) on a loss of one RPS bus? (0,5) i l QUESTION 3.08 (2.00) I Match the combinations of armed and depressed containment isolation ) pushbuttons (a-f) with the expected isolations, if any, (1 - 4) resulting ) from that action. NOTE: MORE THAN ONE ISOLATION MAY APPLY. (2.0) i a. A and B 1. Full MSIV closure b. 8 and C 2. BOP Inboard c. C and 0 3. BOP Outboard d. A and C 4. No Isolation e. A and 0 f. B and D QUESTION 3.09 (3.50) a. What are three (3) components in the HPCS system that can be manually overridden and operated on P-601 with a HPCS initiation signal present? (1.5) b. Once HPCS has ceased inj ect ion due to a Level 8 signal, describe the two (2) methods by which inj ection may be restarted as level decreases. (2.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

m '2i__EL6NI_SYSIEdS_L2313_6NQ_EL6NI: WIDE _ GENE BIQ : Page 12~ BESEQNSIBILIIIES_ LID 11 QUESTION 3.10-(1.00) The reactor is operating at 5% power, 920 psig,.with the Mode Switch in STARTUP, when the Reactor Level instrument selected for-feedwater control-fails downscale. Which one of the following actions / signals will NOT occur as a result'of this failure? Assume no. operator action.: (1.0) l a. Feedwater flow increases and the reactor trips on high' reactor-level'. l b. Feedwater flow increases and the. reactor feedwater pumps trip:on high reactor level. l l l c. A recirculation flow control valve runback signal is generated. l d. A signal to downshift the recirculation pumps-to slow'speedEis l generated. 1 l QUESTION 3,11 (1.00) Select the answer below that indicates how far above theEtop.of the. active-l fuel water level is maintained in automatic assuming' normal system operation. (1.0) l a. 213" b. 197" c. 172" d. 119" (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l I } 21__EL6NI_SISIEUS_f2a11_6HD_EL6NI: WIDE _QENEBIG Page 13 l BESEQNSIBILIIIES_fl011 1 1 QUESTION 3.12 (0.50) Match the type of Division 1 Diesel Generator start (a) with the action necessary (1

3) to reinstate all protective trips on the machine.

(0.5) a. Manual Emergency Start (local) 1. depressing the NORMAL START and EN'iRGENCY START pushbuttons 2. depressing only the NORMAL START pushbutton 3. diesel must be shutdown QUESTION 3.13 (1.00) The reactor is operating at 100% power when a trip of both recirculation pumps occurs. With no operator action, which of the following is most likely to scram the reactor: (1.0) a. High reactor pressure b. MSIV isolation (low steam line pressure) c. High reactor level d. Flow biased thermal power QUESTION 3.14 (1.50) a. At what point during a power escalation does the EOC-RPT become effective (include the sensed parameter)? (0.5) b. Why is the E00-RPT necessary? (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

4 '2t__EL6NI_SXHIENS_12all_6ND_EL6NI: WIDE _DENEBIQ. Page 14 BESEDNSIBILIIIES_LIDil LQUESTION' .3.15' (1.00') 'Which combination of valve closures and.! actions below displays how the EOC-RPT logic functions: .(1.0) one. turbine stop valve and one control' valve trip one recirculation-a. pump. b.' two turbine'stop' valves tr'ip one recirculat' ion, pump o. one turbine stop valve and.one control. valve trip'both recirculation-pumps 'd. two turbine stop valves trip both recirculation pumps QUESTION 3.16 (1.50) The reactor is operating at 100% with a RCIC flow surveillance -in progress. RHR A is in suppression pool' cooling with the following lineup:' - RHR Heat Exchanger Inlet and Outlet valves F003A and F0047A open fully RHR Heat Exchanger Bypass Valve F048A throttled to approximately-mid-position i l - RHR A Minimum Flow Valve F064A closed RHR Test Return to Suppression Pool Valve F024A1cpen RHR pump suction from' suppression pool F004A open-l - RHR pump A outboard isolation valve'F027A open l. - RHR pump A inj ect ion isolation valve F042A shut RHR pump A running l l-A small steam leak occurs which causes ECCS initiation on high drywell' pressure. RPV level is being controlled adequately byfthe feedwater level I I control system. DESCRIBE.the changes that occur in'the above' lineup.as a result (directly or. indirectly).of the ECC actuation'signale (1.5) l l l u 4 ~. 1 1l. U (*****' CATEGORY 3' CONTINUED ON NEXTEPAGE *****) l. t ____________.______________________j

l ?22 EL6HI_SISIEdH_12a91_6NQ_EL6NI: WIDE _QENEBIG Page 15 k BESEQN21BILIIIES_11011 , QUESTION-3.17 (2.00) r a. Assuming the'MSIV. Leakage Control Systemfis.in a-normal standby. lineup, what are three (3) actions / conditions that must!be met-for the system to begin automatic operation?- INCLUDE VALUES AS. 1 L APPLICABLE. (1.5) i b. 'The Penetration Valve' Leakage Control Air Compressors pr' ovide.a backup' air supply to what components? (0.5) j 1 QUESTION 3.18 (1.00) Normal water additions ( < 1 foot) to either the upper or lower fuel. pools l should be made via: (1.0) l a. water hose from CNS service box directly'into the pool. l l b. the Fuel Pool Purification pump from the' CST. c. the Fuel Pool Cooling pump from the CST. d. Purification or Cooling pump,from the condensate' system. 1 QUESTION 3.19 (2.50) For each combination of Main Steam Line Radiation Monitor Trips'Ca - e), select the appropriate automatic action (s) (1 - 5). (2.5) a. Channel A High, Channel B High-High 1. Half-scram b. Channel A High, Channel D High 2. Scram l c. Channel B Downscale, Channel C Inop 3. Mechanical Vacuum l Pump A trip l d. Channel A Inop, Channel C High-High l 4. Mechanical Vacuum e. Channel C Inop, Channel D High-High Pump B trip f i 4 5. No Automatic Actions 1 l .I (***** CATEGORY 3 CONTINUED ON NEXT PAGE 2****) w________

I Ji__EL6HI_SXSIEdS_12Hil_6BD_EL6NI: WIDE _QENEBIQ Page 16 l BESEQNS1HILIIIEH_I1Dil l l I QUESTION 3.20 (1.00) What are the power supplies to the Main Steam Line Radiation Monitoring System and the Off-Gas Radiation Monitoring System? (1.0) l l QUESTION 3.21 (1.00) Which one of the following conditions in the Stator Winding Cooling System WILL NOT initiate a turbine generator runback? (1.0) a. St9 tor winding cooling inlet low pressure b. Stator winding outlet water high temperature c. Stator winding cooling system low flow d. Stator winding cooling system high conductivity QUESTION 3.22 (2.00) The main generator is ready to be paralleled to the grid with the synchroscope rotating slowly in the " fast" direction, s. What does this synchroscope condition tell the operator about the relationship between the generator output and the grid? (1.0) b. What condition exists between the generator and the grid as the synchroscope passes through the "12 o' clock" position? (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l i 2i__EL6HI_SXSIEUS_1SS13_6ND_EL6NI: WIDE _GENEBIC. Page 17' BESEQUSIBILIIIES_11011 l 'l QUESTION-3.23 (1.00) l 1 Which:one-of the following steam' flows is.NEITHER indicated NOR included'in indicated main steam flow in.the control room?. (1.0) y

a..

MainLsteam linel drain flow b. .SRV flow' c. 'RCIC' flow .) i d.' RPVLhead vent l QUESTION' 3.24 (1.00) Which one of the following Main Steam Line components isfdesigned to limit the differential pressure across the steam dryer assembly? (1;0) n. ' Main Steam Line flow elbows b. MainfSteam Isolation Valves c.- Main Steam Shutoff Valves i d. Main Steam Line flow restrictors j i 1 QUESTION 3.25 (1.00) List the OPERATIONAL CONDITIONS when a Reactor Operator may be designated to assume the control room command function. ( 1. 0 )' l QUESTION 3.26 ( 2. 0 0 )' b a. How or where is it documented which individuals make up the Fire-Brigade f or a given shif t? (0.5) b. Which five'(5) personnel, by title or position, are specifically-I excluded from being on the Fire Brigade? - ( 1. 5 )- l b l (***** CATEGORY 3 CONTINUED-ON NEXT'PAGE *****)

I "St__EL6NI_SYSIENS_ flail _6ND_EL6NI: WIDE _DENEBIQ P ag'e 18 .l BESEDNSIBILIIIES_flDil-1 I J QUESTION 3.27 (2.00) Il j a. What-two-(2) conditions must an unlicensed individual meet before he/she is' permitted to manipulate the controls that directly? affect reactivity or power level of the reactor? ( 1. 0 ) - l f l b. What requirement must a River Bend reactor' operator licensee meet to. . maintain the license-in an " active" status (in addition to maintaining. a license in an " inactive" status) per 10 CFR 55? (0.5) c. 'What action must be taken to re-activate a R0 license once it has'been 'l " inactive" Cat River Bend) per.10 CFR.55? ( 0. 5). ] l -) I l l l QUESTION 3.28 (1.50) .J l l If air operated valves are to be used for equipment isolation (protective .l tagging), what action (s) must be taken on the valve, valve operator, and/or I controls prior to beginning work?- ADDRESS FAIL OPEN'and FAIL CLOSED j) j valves. (1.5) l l l 1 1 J QUESTION 3.29 (1.50) l l What temperature and pressure conditions require.the use of two. closed l volves between the work area and system conditions? (1.5) j 1 l QUESTION 3.30 (1.00) l Any individual or group of individuals permitted to-enter High or Very High l Radiation Areas must meet one of three monitoring requirements. . State one j of these three requirements. (1.0) l l l l 1 l 1 l (***.** CATEGORY 3 CONTINUED.ON NEXT PAGE *****)

e 8 -- 2 t__ E L 6NI_S YSI E d1_ L 2811_6NQ_ E L 8NI:WI D E _ G EN E BIQ " Page 19 BESEQN11HILIIIE2_11011-1 F . QUESTION' 3.31- '(1.00) What is'the purpose of)the 2000 series;keyLaddedito the NEO.and;NCO: e.- rounds keys?- (0.5) b.- Whose approval is. required: prior-to use of this~ key?- .( 0. 5 ); I l l L \\ l 1 1 ./ L (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********) __1_l -~

4 4 l 1 1 1 11__BE6CI98_EBIUCIELES_LZ11_IBEB0001U601Q$ Page 20 l LZ11_6ND_QDdEDNENI1_L1131_LEUNDedENIBLS_EMedl -( I i l ANSWER-1.01 (0.00) I { GENERIC FUNDAMENTALS EXAM l REFERENCE l l GENERIC FUNDAMENTALS EXAM 1 l l l l 1 l l l 1 \\ l l 1 l l l l-l l l l l l l l i l l l l l l l l l l l (***** END OF CATEGORY l'*****)

.I 21__EUEBDENCY_6ND_6aN9806L_EL6NI_EVOL9IIQNS Page 21 i L2Z11 -i . ANSWER 2.01 (2.00) - A scram setpoint is exceeded and an automatic scram did not occur (1.0) - Plant conditions are approaching an unsafe condition and a manual reactor a scram will mitigate the consequences of this condition (1.0) REFERENCE I l l AOP-0001, Reactor Scram, Rev 4, pg 2 295006G011 4.3*/4.5* 295006G011 ..(KA's) l l l ANSWER 2.02 (2.00) { a. 4 (1.0) b. 1 (1.0) REFERENCE i A0P-0002, Main Turbine and Generator Trips, Rev 3, pg 3, 4 ) 295005K101 4.0/4.1 295005K301 3.8/3.8 j 1 295005K101 295005K301 ..(KA's) l 1 l ANSWER 2.03 (2.00) l - core submergence (0.5) preferred (0.5) - steam cooling with inj ection of makeup water to the RPV (0.5) - steam cooling without injection of makeup water to the RPV (0.5) l l REFERENCE E0P Appendix 8, Technical Bases for E0P Steps., Section 3, pg 6 of 191 1 295031A204 4.6*/4.8* 295031A204 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

u-p; 1 1 2t_ EDEBGENCX_6ND_6HNQBd6L_EL6NI_EYQLUIIONS. Page 22 12Z11 l i ANSWER 2.04 (1.00) i

.c:(1.0) j l

REFERENCE. L 'EOP. Appendix'B,.pg 91 of 191 295037K306'3.8/4.1 1 295037K306 ..(KA's) J er p . ANSWER. 2.05 (2.50) 1 L .-=deenergize the scram solenoids j l - vent the scram. air header ~ - reset the scram,_ drain SOV, manually. scram again. ~f - individual scram switches to TEST l - increase CRD cooling water dp l - insert'using CROH - vent CRD overpiston volume - arm and depress ARI pushbuttons l -(5 required at 0.5 each) l L REFERENCE EOP-1A, Appendix 8, pg 94, 95 295037A105 3.9/4.0 295037A105 ..(KA's) 1 l L ' ANSWER 2.06 (0.50) 1 l 'Use of a hydro pump (0.5) (-. ' REFERENCE-l l E0P-1A, Appendix B, pg 98 .295037K213 3.4/4.1 295037K213 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT!PAGE *****) = _________________.__._z_______________________.___-_______________.__.-.______.__

q u Page 23-l 22__EMEBGENGX_6ND_6BN9Bd6L_EL6NI_EYQLUIIDNS. .12Zu .j I ANSWER '2.07 (2.50)., l a. . Insert control' rods to less than'80% rod line (0.3). Monitor. APRM l! back. panels for. flux' oscillations'CO.3). If APRM oscillations are'. l ~ .{ >25%. peak.to peak'.(0.3),.and;the magnitude is.incr. easing (0.3), scram the reactor (0.3).- Accepted actions per Rev 2,.3, or.4.of AOP-0024 due to the rapid number of. revisions to the procedure. .1 f b. Plant Manager 1(0.5) or APM-0.-in-his absence: 1 l c; thermal - hydraulic instabilities: in the core.(0.5) .l REFERENCE l AOP-0024,. Decrease in Recirculation System Flow Rate,'Rev 2, pgs.2, 3 Standing Order. #69, Operation With Single Loop Recirculation Flcw-l 295001K103.3.6/4.1 295001G010 3.8*/3.7* ~- ,i 295001G010 295001K103 ..(KA*s)- 1 ANSWER 2.08-(2.00) a. Use the manual trip handle at the~ turbine front-standard ( 1.' 0 ). L b. Motoring of the generritor (1.0) and subsequent turbine damage ( 0. 5 if turbine damage is only. response). 1 l ? q REFERENCE I i l A0P-0014, Loss of 125 VDC, Rev 3, pg 3 l 295004K105 3.3/3.4 295004A102 3.8/4.1 l I 295004K105' 295004A102 ..(KA's)- j l i ANSWER 2.09 (1.00) I l l a. RCIC (1.0) l \\ l .(***** CATEGORY 2 CONTINUED ON NEXT-'.PAGE *****) j l

l l 1 ~ J

2t__EdEBQENQ1_6ND_6BNQBdeL_EL6NI_EVQLUIIQNg

'Page 24' L2Zil l ) REFERENCE-A0P-0050, St'ation Blackout, Rev 2, pg 11,-12 L, 295003A103 4.4*/4.4*'295003G011 4.1*/4.3* g 295003A103 295003G011 ..(KA's) l Y LANSWER 2.10 .(2.00) i l-l n. increase ' air inleakage-(0.5) .s L decreast - Off Gas-System.line blockage (0;5). Also accept ' closure!of. ' L SJAE steam supply or-regulator. 1: L b. 22.3" HG (0.5)'due-to the' turbine trip (stop valveLc'losure)1(0.5) ) REFERENCE A0P-0005, Loss of-Main condenser Vacuum, Rev 3, pg 2 295002K201 3'.5/3.5-295002K301 3.7/3.8'295002K207 3.1/3.1 ,l i 295002K201 295002K301 295002K207 ..(KA's). l l l l l l l ANSWER 2.11 (2.00) n. When.no CR0 pumps are running (0.5) and.>1 CRD accumulator troub'le l l alarm'is in (0.5). q b. 1 (1.0) ~ REFERENCE ll l AOP-0011, Loss of Reactor Plant Component Cooling Water, Rev 3, pg 2, 3 1 l' 295018K201 3.3/3.4 295018G010 3.4*/3.3* j 1 i i 295018G010 295018K201 ..(KAi s) I ~ i l 1 J L J l-L L l i 1 (***** CATEGORY.

2. CONTINUED ON NEXT PAGE *****)

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._ y 2t__EUEBGENCY_6ND_6BNDBd6L_EL6NI_EVQLUIIQNg Page 25 L2Zil ANSWER 2.12 (2.00) c. Fuel Building Effluent High Rad (0.2) isolates the Fuel B1hJg normal supply and exhaust ventilation.(0.4) and auto initiates'the1 Fuel Bldg Exhaust Charcoal Filter Trains (0.4). S. b. Annulus Exhaust High~ Rad (0.2) auto starts Annulus Mixing System (0.4) and Standby Gas Treatment System (0.4). REFERENCE A0P-0027, Fuel Handling Mishaps, Rev 4, pg 2 295023K206 3.4/3.8 295023K203 3.4/3.6 l l l 295023K203 295023K206 ..(KA's) I ANSWER 2.13 (1.00) c, a, d, b (0.33 for each manipulation to put in the correct order) REFERENCE l AOP-0C27, Fuel Handling Mishaps, Rev 4, pg 3 295023K202 2.9/3.2 295023K202 ..(KA's) l l I l L i i 1 l l l l l 1 O l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i

",r[.2t__EdEBQENCY_8ND_8BNDBd8L_EL8NI_EVDLUI1QN3 'Page'26' E L2Z11

ANSWER-2.14 (2.50)

.(5 required at 0.5 Leach)- l'. Containment to annulus dp >5 psid 2. Containment temperature >185' des F 3.- Drywell temperature _>330 deg F 4. Reactor-pressure and Suppression. Pool temperature cannot' be. maintained: in the safe zone.cf the appropriateffigure; l S. Suppression pool leve1~and delta.THC cannot be maintained in the safe j. zone'of the appropriate' figure in L 6. Suppression pool. level and> reactor ~ pressure'cannot be maintained l the. safe. zone of the' appropriate figure' l 7. A primary system is ; discharging into secondary? containment and1any-area temperature, area radiation leveli or area water level exceeding-its maximum safe operating value in more than one' area of the 4 l appropriate table 8. Offsite release rates requiring.a General Emergency with.a primary system discharging outside' primary and secondary containments l i REFERENCE l E0P-1 ~ 295028G012 3.8*/4.3* 295029G012.3.6/4.4*- l 295028G012 295029G012 ..(KA's) l ANSWER 2.15 (1.00) HPCS, LPCS, RCIC C0.33 each) t. l REFERENCE l l A0P-0031, Shutdown from Outside the Main Control Room, Rev 5, pg 5 l 295016G010 3.8*/3.6* [ 295016G010 ..(KA's) l l L l l l 1 i (***** END OF CATEGORY 2 *****)

_m 2t__EL6HI_SYSIEd1_L2all_6ND_EL6HI: WIDE _DENESIC Page 27 BESEQUSIBILIIIES_11Dil ANSWER 3.01 (1.00) b (1.0) REFERENCE LOTM-15-2, Reactor Protection System, pg 5-7 201001K404 3.6/3.6 201001A204 3.8/3.9 1 201001K404 201001A204 ..(KA's) I i l ANSWER 3.02 (1.00) i d (1.0) l l REFERENCE 1 I l LOTM-15-2, Reactor Protection System, pg 2 212000K401 3.4/3.6 l \\ l 212000K401 ..(KA's) l ? l \\ l ANSWER 3.03 (1.50) a. RPS MG sets (accept 125 VAC) (0.25) non-safety (0.25) l b. 125 VOC C0.25) safety related (0.25) l l c. 125 VOC (0.25) non-safety related (0.25) l 1 i l REFERENCE l LOTM-15-2, Reactor Protection System, pg 2, 4, 9 l LOTM-56-2, AC Distribution LOTM-57-2, 00 Distribution l 201001K202 3.L*/3.7 201001K203 3.5*/3.6* 201001K205 4.5*/4.5* 201001K202 201001K203 201001K205 ..CKA's) l l l (***** CATEGORY 3 CONIINUED ON NEXT PAGE *****) l'

1 ,j 2A__EL6NI_SYSIENS_12811_6ND_EL6NI: WIDE _DENEBIC. .Page 28 BESEQNSIBILIIIES_ LID 11 lu i ANSWER 3.04 (4.00) l i j C e. LPSPL27.5% reactor power CorL157.6 psig ist stage: turbine" pressure)~ 'HPSP 62.5% reactor power (or'410.7 psig 1st stage turbine pressure) LPAP 37.5% reactor power Cor' 220.6 psig. ist stage L turbine pressure)- -j (0,5) L b.. turbineffirst stagelpressure l .l c. LPSP: fBelow the LPSP, the Rod Pattern.Contro1 System. imposes. j 3 ~ restrictions on rod movements with regard to rod pattern (0.5).- Above-l the'LPSP,'the. Rod Withdrawal Limiter limitsithe number.of notches a I j control rod may be. withdrawn (0.25)dto.,4 (0.25). I HPSP: Above the HPSP, the Rod Withdrawal Limiterilimits the number of L notches a control rod may be withdrawn-(0.25) to 2 (0.25)'. I 1 I LPAP: No control function,--indication only. l l d. Immediately return the control rod to_the position prior.to the H withdrawal (0,5) REFERENCE i 1 LOTM-6-2, Rod Control and Information System, pg 14 l River Bend Technical' Specification 3.1.4.1 l 201005K102'3.3/3.5 201005K507 3.5/3.5 201005K509 3.5/3.'S 201005K510 3.'2/3.3. j 201005A101 3.2/3.3-201005G014 3.5/3.8 .) 201005A101 201005K102 201005G014 201005K507' 201005K509 201005K510 ..CKA's) I I [- I l l ~. 1' i l' L l l. t .(*****. CATEGORY <3. CONTINUED ON NEXT PAGE *****) L

a l { l21_EL6NI_SYSIEdS_L28&l_6ND_ELANT-WIQg_QENE Page 29 BESEQNSIBILIIIES_110hl l ANSWER 3.05 (2.50) i 1. Shutdown the HPU using the manual pushbutton at H13-P680 j 2. Shutdown the HPU using the shutdown pushbutton at H13-P614 3. Shutdown the HPU at H13-P614 by placing both subloops in Maintenance 4. Shut the drywell isolation valves at H13-P808 1 5. Depress the Drywell Pressure Tent pushbutton at H13-P614 q 6. Depress the CRVICS BOP pushbuttons on the H13-P680 panel 1 (5 required at 0.5 each) ] i l REFEREK02 { l LOTM-8-2, Recirculation Flow Control, pgs 5-8, Figure 4 202002A402 2.8/2.8 i i 202002A402 ..(KA's) 1 ANSWER 3.06 [1.50) 1. RWCU (0.5) 2. RCIC (0.5) 3. RHR (0.5) REFERENCE LOTM-51-2, CRVICS, pg 21 223002G007 3.8/3.9 223002G007 ..(KA's) ANSWER 3.07 (0.50) Main Steam (0.5) \\ (***** CATEGORY 3 CONTINUED ON NEXT PAGE ***'**)

i 'i I L i '2t__EL6NI_SYSIEdS_L2H11_6ND_EL6NI:WIDg_GENgB1C ' Page 30: BESEQNSIBILIIIES_L1Dil- ~ q .j . REFERENCE j q LOTM-51-2, CRVICS, pgs.3.- 5' 9 223002K608 3.5/3.7 223002A201 3.2/3.5 223002A201 223002K608 ..(KA's) 1 -j L ANSWER 3.08 (2.00) 1. 1 l a. 1-(MSIV)- j-b. 1, 2 (Inboard). I c. 1 d. 4'(no' isolation) o. 1, 3 (outboard). l ) f. 4 (8 at 0.25 each)' l l REFERENCE l I i LOTM-51-2, CRVICS, Figure 13 j l 223002A402 3.9/3.8 ] l 223002A402 ..(KA's) ] l l ANSWER 3.09 (3.50) L a. F004 HPCS Injection Valve (0.5) l F015 Suppression Pool Suction Valve ( 0. 5 ) - HPCS Pump (0.5) l I b. 1. Level decreases to Level 2-(1.0) and the system automatically l. restarts. 2. High Level 8 signal is reset by the' operator (1.0) after the l 1evel decreases to below the level 8 setpoint. l l REFERENCE l l LOTM-18-2, HPCS, pg 8 l 209002A305 3.7/3.7 209002A401 3.7/3.7 209002A402 3.6/3.6 209002A403E3.8/3.8 l l 209002A305 209002A401 209002A402 209002A403 ... ( K A 's )' l l (***** CATEGORY 3' CONTINUED ON NEXT PAGE *****)-

~1 x, .] ]j .z 1 ) 21__EL6NI_SISIEd2_12811_6ND_EL6NI: WIDE _QENEBIC Page:31 '] BESE9NSIBILIIIES_L1Dil J 1 -l .i . ANSWER 3.10 (1.00) 1 .) a'(1.0) J ) 1' REFERENCE .) LOTM-34-2, Feedwater Level Control System, Figure 1 -j 259002K302 3.7/3.7 259002K304 2.9/3.0'259002K305 2.8/2?9 259002K302 259002K304' '259002K305 ..(KA's) l 1 i H l ~ L ANSWER 3.11 (1.00) I { l b (1.0) 1 'l I j REFERENCE. q t a I LOTM-3-2, Nuclear Boiler Process Instrumentation, Figure l' ( 216000K122 3.6/3.8 l-216000K122 ..(KA's) l l -. l ANSWER 3.12 (0.50) a. 1 (0.5) l l.. ( REFERENCE l [ LOTM-58-2, Standby Diesel Generators and Auxiliar.ies, pg 16'- 17 l 264000K401 3.5/3.7 264000K402 4.0/4.2 1 264000K401 264000K402 ..(KA's) l-L ANSWER 3.13 (1.00) i l l d (1.0) also accept c j 1 i I. l \\ q (***** CATEGORY 3 CONTINUED ON NEXT1PAGE *****) i

1 s. 22__ELoNI_SX2IEdS_12a11_oND_EL6NI: WIDE _QENEBIC-Page 321 j BESEQNSIBII.IIIES_ LIQ 11 i l J REFERENCE ll LOTM-7-2, Recirculation System, pg 21 j 202001A204 3.7/3.8' I d .202001A204 _..(KA's) l l ANSWER 3.14 (1.50) j .1 s. .40% (0.25) by turbine first stage pressure-(0.25) i h b. During;the first part of a scram at the end of cycle, the controb: rods j cannot-insertinegative reactivity as fast as the= collapsing' voids'can: i l insert positive reactivity (1.0) due to.the sudden' decrease in steam ) l flow due to a turbine trip or-control valve; fast' closure. a l l REFERENCE' j T12-LO1M-7-2,2 Recirculation System, pg 202001K104 3.3/3.3 202001K505 3.5/3.6~ j I -202001K104 202001K505 ..(KA's) q L 1 l l ANSWER 3.15 (1.00) j b (1.0) I t-] REFERENCE LOTM-7-2, Recirculation System, pg 12 202001K128 3.9/4.1 202001K128 ..(KA's) l^ l ANSWER 3.16 (1.50) L - HX'BPV F048 opens fully (0.5) j - RHR Test' Return to-SP F024 shuts (0.5) j - Minimum Flow Valve F064 opens (0,5) l l l' (***** CATEGORY-3 CONTINUED ON NEXT PAGE.*****) w-___-

2t__EL6NI_SISIEdS_f2all_6ND_EL6NI: WIDE _QENEBIC page 33 l

BESEDNSIBILIIIES_f1D12 ) l I . REFERENCE-LOTM-19-2,~RHR, pgs 7,; Table 5 l 219000A406 3.9/3.7 219090A406 ..CKA's) l . ANSWER-3.17 (2.00) 4 -l a. - OPERATE SWITCH to.0PERATE (0.5) for each subsystem. Reactor.PressureL<-25 psig (0.5) - PVLCS air pressure >.50 psig (0.5). ]j b. SRVs-(0,5) W REFERENCE- .l LOTM-52-2, Penetration Valve and MSIV Leakage Contro1' Systems,.pg 5,-Fig!1 239003A301 3.0/2.81239003K101 3.3/3.4: l 239003K101 239003A301. ..(KA's) ANSWER 3.18 (1.00) t a (1.0) REFERENCE. SOP-0091, Fuel' Pool Cooling and Cleanup System,'Rev 5, pg 39 233000K406 2.9/3.2 233000K406 ..CKA's) I L ANSWER 3.19 (2.50) n. 1, 4 l b. 5 i c. 1, 3 1 d. 1, 3 e. 2, 3, 4 I (10 at 0.25 each) I 1 l. .(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l

St__EL6HI_SISIEdS_LSahl_6ND_EL6NI: WIDE _DENEBIG Page;34 CS BESEQUSIBILIIIES_L1Dil REFER 6NOE LOTM-66-2, Process Radiation. Monitoring, pg 4 272000K402 3.7/4.1 272000A206 2.8/2.9 272000K402 272000A206 ..(KA's) ANSWER 3.20 (1.00) MSL Rad Monitors - RPS CO.5) Off-Gas Monitors - 125 VOC (0.5) l REFERENCE 1.OTM-66-2, Process Radiation Monitoring System 272000K201 2.5/2.8 272000K202 2.5/2.8 272000K201 272000K202 ..(KA's) i ANSWER 3.21 (1.00) d (1.0) i l l REFERENCE LOTM-55-2, Main Generator Auxiliaries, pg 3 245000r.605 2.9/2.9 245000K605 ..(KA's) l i l b I ANSWER 3.22 (2.00) l n. That the generator frequency is slightly higher than the grid j frequency (1.0). l b. That the generator frequency and grid frequency are in phase (1.0). l l I i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) f

i f 2t__EL6NI_SXIIEd!_L2All_6HD_EL6NI: WIDE _QENEBIG Page 35. ) BESE98SIBILIIIES_L10&l i f > REFERENCE LOTM-54-2, Generator Exciter and Voltage Regulator, pg'12 245000K507 2.6/2.9 i 245000K507 ..(KA's) ANSWER 3.23 (1.00)' c (1.0) l l REFERENCE l f LO TM-2 4 -2, Main Steam, Figure 1 l 230001K119 3.1/3.2 239001K119 ..(KA's) t l I f ANSWER 3.24 (1.00) 4 3 d (1.0) REFERENCE i LOTM-24-2, Main Steam, pg 7 239001K404 3.4/3.5 1 239001K404 ..(KA's) 1 l l ANSWER 3.25 (1.00) l Operational Conditions 4 and 5 (0.5 each) REFERENCE RBS Technical Specifications Table 6.2.2-1 l 294001A103 2.7/3.7 294001A103 ..(KA's) 1 L 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE.*****) 1

..)'f .i. : j c 7 n Pagef36' j 2t__EL6NI_SYSIENS_L2SilieND_EL6NI: WIDE _9ENEBIC BESEDNSIBILIIIES_L1911 4 I il NNSWER 3.26 (2.00). I a. Control room log book ( 0. 5); j i b. SS,.~C0F,.STA, ATC Operator, 1 NEO.(0.3 each) j L REFERENCE. -j ADM-0022, Conduct of Operations,cRev.11, pg 11 7-l12 -294001K116 3.5/3.8 H .i L 294001K116 ..(KA's) q l l-ANSWER 3.27 (2.00) n. - Under the direct supervision of a licensed individual (0. 5)- --Enrolled in approved operator licensing trainingL. class (0.5) j b. Stand a minimum of seven 8 hour shifts or five-12 hour shifts per calendar quarter performing the' functions of the. license (0. 5)- c. Complete 40 hours'under instruction at the position for which'the l re-activation is' sought (0.5). REFERENCE l RBS ADM-0022, Conduct of Operations, Rev 11, pg 14 . 10 CFR 55.53(e) and (f)(2). t 294001A103 2.7/3.7 l 1 294001A103 ..(KA's) i ANSWER 3.28 (1.50) l l Fail closed: Should have the air and or power removed (0.5), and the ~ I control switch in the closed position (0.5). J L I L Fail Open: Valve should be gagged or a blocking device installed to l ensure the valve stays shut (0,5) I 1 I I 1 l l o 'i l (*****' CATEGORY = 3 CONTINUED ON.NEXT PAGE *****) l'

'2t__EL6NI_SYSIEd!_12Sil_6ND_EL6NI: WIDE _9ENESIQ Page'37 BESE0NSIBILIIIES_11011' REFERENCE-ADM-0027,' Protective Tagging, Rev'7, pg.5-294001K102D3.9/4.5* 294001K102- ..(KA's) ANSWER -3.29 '(1.50) 50 psig -or 200Edeg F (0.75 each) l REFERENCE i ADM-0027, Protective Tagging, Rev 7, Lpg 6 l 294001K108 3.1/3.4 294001K109.3.4/3.8 294001K108 294001K109 ..(KA's) l ANSWER 3.30 (1.00) - A radiation monitoring device which continuously indicates the' dose-rate in the area. j .A dose integrating monitor which is set toialarm when.a preset dos e ' is L received. - Accompanied by an individual qualified in radiation protection procedures, with m' dose-rate monitoring device. ( 1 of 3 at 1.0) REFERENCE l RSP-0200, Radiation Work Permits, Rev 4, pg 11 294001K103 3.3/3.8 l 294001K103 ..(KA's) l' I L ANSWER 3.31 (1.00) I a. 2000 series key is a valve lock master (0.5) l l b. Shift Supervisor (0.5) 1 l (***** CATEGORY 3 CONT 1NUED'ON NEXT PAGE *****)

l 2t__EL6NI_SYSIEdS_12all_6ND_EleNI: WIDE _9ENEBIG Page 38 BESEQUSIBILIIIES_ LIQ 11 REFERENCE Stending Order #63, June 1, 1988 294001K105 3.2/3.7 i 294001K105 ..(KA's) l l

k

• .h 3

s l ~ i i { l i i 1 4 i i l l (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********)

m j TEST CROSS REFERENOE Page i QUESIl0N V6LUE BEEEBEUGE_ l 1.01 0.00 9000138 si 1 1.02-25.00 25.00 ] 2.01 2.00 90000S?' 2.02 2.00 9000083-2.03 2.00 9000084 .i 2.04 1.00 9000085 j 2.05 2.50 9000086 .i 2.06. 0.50 9000087 2.07 2.50 9000088 l l 2.00 2.00 9000089 a l 2.09 1.00 9000090 .l 2.10 2.00 9000091 2.11 2.00 9000092 I ( 2.12 2.00 9000093 2.13 1.00 9000094 j 2.14 2.50 9000095 2.15 1.00 9000096 l 26.00 l 3.01 1.00 9000049 1 3.02 1.00 9000050 I l 3.03 1.50 9000051 3.04 4.00 9000053 l 3.05 2.50 9000054 3.06 1.50 9000055 ( 3.07 0.50 9000056 l 3.08 2.00 9000057 l 3.09 3.50 9000058 l 3.10 1.00 9000059 3.11 1.00 9000060 3.12 0.50 9000061 l 3.13 1.00 9000062 3.14 1.50 9000063 3.15 1.00 9000064 l 3.16 1.50 9000065 l 3.17 2.00 9000066 3.18 1.00 9000067 3.19 2.50 9000068 3.20 1.00 9000069 1 3.21 1.00 9000070 l 3.22 2.00 9000071 l 3.23 1.00 9000072 l 3.24 1.00 9000073 3.25 1.00 9000074 i l 3.26 2.00 9000075 i 3.27 2.00 9000076 3.28 1.50 9000077 3.29 1.50 9000078 1 3.30 1.00 9000079 l 3.31 1.00 9000080 L

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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 4 FACILITY: 'Blvgr_Baad_1_____________ REACTOR TYPE: BWB-GEh__________________ DATE ADMINISTERED:- Q22Q221d_________________ INEIBUGIl0NE_IQ_GeNQ10aIE1 Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires,t least'70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after I l the examination starts. t f l % OF ) CATEGORY % OF CANDIDATE'S CATEGORY l __V8LUE_ _IQI8L ___ECQBE___ _YoLUE__ ______________G81EQQBX_____________ l l 24100__ _24tk2 ________ 4. REACTOR PRINCIPLES (7%) 1 THERMODYNAMICS (7%) AND l COMPONENTS (10%) (FUNDAMENTALS l EXAM) 1 _22tQQ__ _32tB2 ________ 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) _dithD__ _d2tEk ________ 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%) 1 _BZtEQ__ TOTALS FINAL GRADE 1 i All work done on this examination is my own. I have neither given nor received aid. l \\ l Candidate's Signature l l l l l l l l

l l NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS l During the administration of this examination the following rules apply: f 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 l leave. You must avoid all contacts with anyone outside the examination-1 room to avoid even the appearance or possibility of cheating. i 3. Use black ink or dark pencil only to facilitate legible reproductions. 4. Print your name in the blank provided on the cover sheet of the examination. l i f 5. Fill in the date on the cover sheet of the examination (if necessary). .6. Use only the paper provided for answers. -] 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet. 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet. i I 9. Number each answer as to category and number, for example, 1.4, 6.3. I

10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your dosk or table.

12. Use abbreviations only if they are commonly used in facility literature.

13. The point value for each question is indicated in parentheses after the j

question and can be used as a guide for the depth of answer required. I

14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE l QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

l

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed. l l

. 18. When you complete your. examination,:you shall: a.- Assemble your. examination as.follows:

j.,

(1) Exam questions on top. (2) Exam aids - f igur es, tables, etc. -(3). Answer.pages including figures which are part of the answer. b. Turn in your copy.of1the examination'and all pages used to answer the' examination' questions.: c. Turn in all scrap; paper and the'ba' lance of the paper that you did. s not-use for. answering'the' questions. d. -Leave the examination area, as defined by the examiner.- If after leaving, you are found,in.this area while~the examination is still in progress, your, license may.be denied or. revoked. l L 1 l l l l 9 1 I i l 1 i 1 L lu L 1 J l I l 1 l l j l' i 1 l l l l l

i h __BE8CIDB_EBIN91ELEH_LZ11_INEBdQQXNob1G3 Page 4 ] LZ11_8ND_QQUE9NENIH_11011_LEUNDodENI6LH_E86dl { i QUESTION 4.01 ( 24.0) l GENERIC FUNDAMENTALS EXAM j i I 1 l 1' j I. l 4 l l l i l l' I l l l l l l l l-l l l l l (***** END OF CATEGORY 4 *****)

~ Sz__EdEBGENQX_6NQ_6HNQBd66_EL6NI_gyQLQIIQN3 Page 5 j L2211 1 J QUESTION 5.01 (2.00) ) The automatic actions listed for a main turbine and generator trip per A0P-0002, " Main Turbine and Gene'rator Trips", include reactor scrams._For parts "a" and "b" below select the answer from items 1 - 4 that will l initiate the reactor scram, s. The turbine trips from 15% reactor power (1.0) l '1. Main turbine stop valve position L I 2. Turbine control valve position l 3. Reactor vessel level l l 4. APRM 1 l b. The turbine trips from 45% reactor power. (1.0) 1. Main turbine stop valve position 2. Turbine control valve position 3 3. Reactor vessel level 4. APRM QUESTION 5.02 (2.00) River' Bend E0P's acknowledge three viable mechanisms of adequate core cooling. List the three mechanisms, INCLUDING which one is preferred.(2.0) { l i i l i l I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l )

)

LI I i 52__EMEB0 ENC 1.~6ND_6HNDBdeL_EL8NI_EVQLUIIQN1 Page. 6 L2211 i QUESTION 5.03 (1.00)- 1 A~ scram condition' exists (MSIVs. shut) with'the= reactor at. power. The i reacior did not shutdown. Core cooling-is-adequate.- Which concern below-q is being most severely challenged in'this condition? (1.0) .l l 1 ~, a a. fuel iniegrity l .b. RPV-integrity 1 c. . containment integrity ) J l d. . injection system operability L l J 4 l { QUESTION-5.04 (2.50) [1 If the control rods fail to insert when required on'a scram, state FIVE-(5) methods that may be tried to obtain control rod insertion per E0P-1A.,C2.5) QUESTION 5.05 (0.50) If boron inj ect ion is required and SLC is not available, what is the.most reliable alternate method of inj ecting boron at ofyar Bend? '( 0. 5 ). QUESTION 5.06 (2.50) The reactor is operating at 100% when one recirculation ~ pump t r.ip s due to-an electrical fault. a. What immediate actions are required per AOP-0024, " Decrease in-Recirculation-System Flow Rate"? Include any conditional actions, (i.e. If then ...) and applicable values.- (1.5) l b. Even though Technical Specifications allow for operation.of the plant l in single loop, what additiona1' authorization is required? (0.5) What.is t'he main operational concern due to a 1 css of forced c. l ' recirculation through the core? C0.5) l 1. (***** CATEGORY 5 CONTINUED ON NEXT PAGE.*****)

m 5___EdEBOENGX_eUQ_oHN9BdeL_EkeUI_EYDLUII9Ng Page 7-12231 QUESTION 5.07 (2.00) a. A loss of 125 VOC has occurred. How should the main turbine be (1.0) tripped if the trip pushbutton on the ElC panel does not function? b. If the loss of DC involved c9ntrol power to the main generator output breakers, what negative consequence would occur as a result of tripping the main turbine? (1.0) l QUESTION 5.08 (1.00) a. During a station blackout (loss of all AC, including.EOGs), what is j the only system capable of inj ect ing into the RPV? (1.0) I QUESTION 5.03 (2.00) 1 c. When, during a loss of Reactor Plant Component Cooling Water (CCP), should the reactor be scrammed? (1.0) I l b. Which one of the following loads will not be affected by a loss of CCP: (1.0) 1. Drywell ec olers 2. Drywell equipment drain heat exchanger 3. RWCU pump seal cooler l 4. RHR pump seal cooler l l l l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l

52__EMEBQEN9X_6N9_6BN9Bd6L_EL6NI_EY9LUIIONS Page 8 L221) QUESTION 5.10 (1.00) Arrange the following four systems in order of preference for making up.to tho' Upper Containment Pool if the leakage rate exceeds the sump capacity cnd a fuel bundle is not in a safe storage location: (1.0) s a. HPCS inj ection b. Standby Service Water crosstie to FPC HX's c. Condensate System injection via Feedwater lines d. Standby Service Water via RHR 8 QUESTION 5.11 (2.50) i State five (5) conditions requiring Emergency RPV Depressurization per the 'I River Bend E0P's. (2.5) 'd j .w QUESTION 5.12 (1.00) l List the three (3) inj ection systems that should be initiated prior to evacuating the control room during the implementation of AOP-0031, " Shutdown from Outside the Main Control Room." (1.0)- QUESTION 5.13 (1.00) What is the meaning of the red border around a decision step in the E0P's as compared to a decision step that is not red coded? (1.0) i (***** CATEGORY 5 CONTINUED CN NEXT PAGE *****) C

l., 5___EdEB9EN91_oND_eBN9BdeL_ELoNI_EY9LUI1QN3 Page 9

L2211, d

i QUESTION 5.14 (2.00) l During'the use of the E0P's, what function / position is assumed by tiid j i s. 00F. l .0) l 'l I b.- SS (1.0) 1 l i l d I i L QUESTION 5.'15 (1.00) [ What'is:the-most important " ingredient" to: successful 'r~ efficient luse of o [ the'EOP's per OSP-0009, " Author's Guide / Control and Use of' Emergency d 4 L Operating Procedures?" '(1.0) 1 l l i ~I l QUESTION 5.16 (1.50) j l l With the eactor in a failure-to-scram condition, what'are'three (0) L actions taken, other than attempting to insert control rods, tisat. attempt l to reduce reactor power by insertion of negative-reactivity? -(1.5) l l QUESTION 5.17 (1.00) If it is decided that the MSIV'c must be reopened to facilitate heat removal from the reactor under emergency conditions, and they have i l automatically shut, a procedure' exists for bypassing a portion of the l automatic closure logic. Which automatic closure signal'below is bypassed [- by this procedure? ( 1. 0 ). a. Low reactor level l-l b. High main steam line flow ra'istion c. Main steam line high d y l

d..

Main steam line-tunnel high temperature l' l 1 1 I l j. (***** CATEGORY .5 CONTINUED ON NEXT PAGE *****) V

Sz__EMEB9ENCY_eND_6HUDBuoL_EL6NI_EYDLUIIQU3 Page 10' 12211 QUESTION 5.18 (1.50) Decreasing instrument air header pressure has been observed and a Gaitronics announcement to cease non-essential use of air has been made. What three (3) conditions require a reactor scram to be manually initiated per A0P-0008, " Loss of Instrument Air?" (1.5) QUESTION 5.19 (1.00) l Which one of the following will occur as a result of a loss of Instrument j l Air? (1.0) 1 a. CRD flow control valve fails open b. Heater drain pumps' recirc valves fail open c. Scram Discharge Volume vent and drain valves fail open d. Steam supply to SJAE PCV fails open I 1 QUESTION 5.20 (1.00) ] ] Why is it necessary to scram the reactor on a loss of service water if the main turbine is on the line? (1.0) 1 l ) QUESTION 5.21 (1.50) Fill in the blanks below concerning reactor power estimation using SRV's: l Decay heat six minutes after a scram (from full power) is approximately f ___(a)___% power which will require ___(b)___ SRV(s) to be cycling. If the l l number of SRV's cycling is too large, indicating reactor power too high, l l proceed to ___(c)___ (procedure name or number). (1.5) i l l l f l l I i 1 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l l 1 I

1 1 i i i 1 Sz__EdEBQENCX_6ND_6BUQBdoL_EL6NI_EYQLVIIQNS-Page 11 12211-al -I i i QUESTION 5.22 (0.50) Where do control: room personnel assemble following a control room J evacuation per AOP-0031, " Shutdown From Outside the Control Room?" (0.5) l l i 'l l i 1 -l i .) l l 1 l l i I l l I I l i 1 l l i I 1 l \\ 1 l I 1 I l l l l i l l l t 4 1 t 1 l l l l l 1 1 (***** END OF CATEGORY 5 *****)

Q-- Et__EL6NI_SXSIEdS_12011_6ND_EL6NIzWIQE_GENEBIG Page 12 BESEQNSIBILIIIES_11213 i QUESTION 6.01 (1.00) An event has occurred which has caused RPV level to decrease to 6", RPV pressure has reached 1075 psig, and drywell pressure has reached 1.2 psig. Which of the following correctly describes the status of the scram valve s o l e n o li.'s, the backup scram valve solenoids, and the ARI solenoids for the above conditions. No manual actions have been taken and the event occurred during power operation with'the Mode Switch in RUN. (1.0) a. Scram solenoids deenergized, backup scram solenoids deenergized, ARI solenoids deenergized b. Scram solenoids deenergized, backup scram solenoids energized,. ARI l solenoids deenergized l c. Scram solenoids deenergized, backup scram solenoids energized, ARI solenoids energized l d. Scram solenoids energized, backup scram solenoids deenergized, ARI solenoids deenergized 1 l 1 1 l l QUESTION 6.02 (1.00) j i The Alternate Rod Insertion logic is automatically actuated at the same I setpoint as which one of the following: (1.0) a. Reactor scram b. Main Steam Line isolation c. Low Pressure Core Spray actuation l l ATWS trip of both Recirc pumps I d. l l (***** CATEGORY 6 CONTINUE 0 ON NEXT PAGE *****)

nt__EL6NI_SYSIEUS_f2011_6ND_EL6NI: WIDE _DENEBIC Page 13 I BESEDNSIBILIIIES_ flail QUESTION 6.03 (1.50) For each of the following, state the normal power supply AND indicate whether the supply is safety-related or not: (1.5) a. Scram pilot valve solenoids b. Backup scram valve solenoids i c. ARI valve solenoids a l,h QUESTION 6.04 (1.00) 1 l ) l Placing.the "A" and "B" switches on a control rod's HCU to the TEST position performs which one of the following functions on that control rod /HCU: (1.0) a. Deenergizes the scram pilot solenoids for that control rod b. Bypasses the A and/or B RPIS data for that rod c. Energizes the selected directional control solenoid valve (s) d. Shuts the selected stabilizing valve (s) QUESTION 6.05 (4.00) a. Liut the setpoints for the RC&IS Low Power Setpoint (LPSP), Low Power Alarm Point (LPAP), and High Power Setpoint (HPSP). (1.5) b. What is the measured variable that determines these setpoints? (0,5) c. Describe the control function performed / changed by each setpoint (LPSP, HPSP) and alarm point (LPAP)? (1.5) d. What action must an operator take if a control rod is withdrawn in Operational Condition 1, one turbine bypass valve is 50% open~and i thermal power is greater than the LPSP? (0.5) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

~ y ~. y ~ a 62__EL8NI_SYSIENS_fSDil_8NQ_EL8NI: WIDE _QENEBIG Page 14 BESEQNSIBILIIIES_f1311 ) i l QUESTION 6'.06 '(2.50) List five s(5) controls avbilable to'the control room operatorEwhich would-l ,stop Recirculation Flow Control Valve movement if the val'veistarts;to ramp- 'open while operating in Loop Manual control. (2. 5): ~ .;-p - QUESTION 6.07 (1.50): Name three C3) systems receiving. inputs;from the Containment and. Reactor . Vessel Isolation Control System'(CRVICS).that:have BYPASS SWITCHES associatediwith/them that, if the switches are taken to BYPASS, will-prevent automatic isolation of these systems. (1.5) l l ' QUESTION 6.08 (0.50) l Which. system covered by CRVICS will not isolate (neitherEinboard nor outboard) on a loss of one RPS bus? (0.5) I QUESTION 6.09 (3.50) I a. What are three (3) components in the,HPCS system that can be, manually y overridden and operated on P-601'with a HPCS initiation signal present? ( 1 '. 5 ) I b. Once HPCS has ceased inj ection due to a Level 8 signal, describe the two (2) methods by which injection may be restarted as level decreases. (2.0) L L l l (- 1 l l l 1 ] (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) ) l i-

h___EL6NI_SYSIEd1_f20&l_6HD_ELobi: WIDE _GENEBIG Page 15 BEHE9N11BILIIIES_f1211 QUESTION 6.10 (1.00) The reactor is operating at 5% power, 920~psig, with the Mode Switch in STARTUP, when the Reactor Level instrument selected for feedwater control l I fails downscale. Which one of the f ollowing actions / signals will NOT occur as a result of this failure? Assume no operator action. (1.0) n. Feedwater flow increases and the reactor trips on high reactor level, b. Feedwater flow inctenses and the reactor feedwater pumps trip on high reactor level. c. A recirculation flow control valve runback signal is generated. d. A signal to downshift the recirculation pumps to slow speed is generated. 1 l l QUESTION 6.11 (1.00) Select the answer below that indicates how far above the top of the active fuel water level is maintained in automatic assuming normal system operation. (1.0)- c. 213" b. 197" c. 172" d. 119" l l l I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

a1, 62__EL6NI_SYSIENS_12011_6NQ_EL6NI: WIDE _QENEBIQ Page 16 BESEQNSIBILIIIES_II211 1 1 'l l QUESTION. 6.12. (0.50). l 1 Matchithe type;of Division 1 Diesel Generator start (a) with the action. 1 -necessary (1.- 3) to reinstate.all protective trips.on the machine. (0.5) i c. Manual Emergency' Start (local) 1. depressing;the. NORMAL. START. q and' EMERGENCY START pushbuttons 2.- depressing only the NORMAL j l START.pushbutton. i 1 3. ' diesel must be' shutdown i L QUESTION 6.13 .(1.50) l 's. At what. point during a power escalation'does the EOC-RPT become. effective (include the sensed parameter)?- .(0.5) l l b. Why is the EOC-RPT necessary? ( 1. 0 ) QUESTION 6.14 (2 00) l a. Assuming the MSIV Leakage Control System is in a normal standby -l l lineup,'what are three (3) actions / conditions that must be met for i the system to begin automatic operation? INCLUDE VALUES AS l l APPLICABLE. (1.5) ) l L b. The Penetration Valve Leakage Control Air Compressors provide a backup air supply to what components? (0.5) j l l l' i 1 i 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l 6 t _ _ E L 6 NI _ S ISIE d S _12011._6 N D _ E L o NI: WIDE _DENEBIC Page 17 BESEDNSIBILIIIES_ flail l l l l l QUESTION 6.15 (1.00) l .1 Normal water additions ( < 1 foot) to either the upper or lower fuel pools should be made via: (1.0) a. water hose from CNS service box directly into the pool. j i b. the Fuel Pool Purification pump from the CST. ] c. the Fuel Pool Cooling pump from the CST. l d. Purification or Cooling pump from the condensate system. l l QUESTION 6.16 (1.00) j I What are.the power supplies to the Main Steam Line Radiation Monitoring System and the Off-Gas. Radiation Monitoring System? [1.0) j QUESTION 6.17 (1.00) Which one of the following conditions in the Stator Winding Cooling System WILL NOT initiate a turbine generator runback? (1.0) a. Stator winding cooling inlet low pressure b. Stator winding outlet water high temperature c. Stator winding cooling system low flow d. Stator winding cooling system high conductivity (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

y l' \\: 61__EL6NI_SYSIEMM_L2011_6ND_EL6NI:W10E_GENEBIG .Page 18 BESEQUSIBILIIIES_L1311 QUESTION 6.18 (2.00) The nisin ' generator is ready to be paralleled to'.the grid.with-.the-synchroscope'rotat.ing. slowly insthe " fast" direction.- 'oes this'synchroscope condition tell the operator:about the a. What d relationship between the generator output.and the. grid? (1.0)' b.' What condition exists between the.generatorfand-the' grid as'the synchroscope passes 1through the "12 o' clock" position? ( 1. 0 )l l QUESTION 6.19 (1.00)- Which one of the following steam flows is NEITHER indicated NOR included in indicated main steam flow in the control room?' -(1.0) a. Main steam line drain flow r b. SRV flow c. RCIC flow d. RPV head vent QUESTION 6.20 (1.00) Which one of the following Main Steam Line components is designed to limit the differential pressure across the steam dryer assembly? (1.0) l a. Main Steam Line flow elbows L l b. Main Steam Isolation Valves c. Main Steam Shutoff Valves l' p-d. Main Steam Line flow restrictors L l-l l '(***** CATEGORY 6~ CONTINUED ON NEXT PAGE *****) 1 L

, i k 1 ( t I 62__ELoNI_SXSIEUS_L2011_6ND_EL6NI: WIDE _GENEBIG Page 19 BESEDNSIBILIIIES_11211-1 i QUESTION 6.21 (1.00) Where would one find a list of licensed individuals that requires the presence of an additional licensed individual while performing licensed i duties as the ATC operator? (1.0) l l QUESTION 6.22 (1.00) List the OPERATIONAL CONDITIONS when a Reactor Operator may be designated j to assume the control room command function. (1.0) I s l l l QUESTION -6.23 (1.50) If air operated valves are to be used for equipment isolation (protective tagging), what action (s) must be taken on the valve, valve operator,.and/or l controls prior to beginning work? ADDRESS FAIL OPEN and FAIL CLOSED' I valves. (1.5) l l I l l QUESTION 6.24 (1.50) 1 I What temperature and pressure conditions require the use of two closed valves between the work area and system conditions? (1.5) l QUESTION 6.25 (2.00) l l Any individual or group of individuals permitted to enter High or Very High l Radiation Areas must meet one of three monitoring requirements. State TWO l of these three requirements. (2.0) l l QUESTION 6.26 (2.00) If a General Emergency is declared, what offsite protective actions shall I be recommended immediately? (2.0) i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

I J hi__EL6HI_SISIENS_12911_6ND_EL6MI: WIDE _9ENEBIG Page 20 ) BESE0NSIBILIIIES_LI211 I I l l 1 1 QUESTION 6.27 (1.00) 1 Protective action recommendations for the general public shall be made by { .the: (1.0) 'j e. Recovery Manager b. Shift Supervisor c. Emergency Director d. Plant Manager I l I 1 l l I I QUESTION 6.28 (1.00) l The protective action recommendations made by Gulf States personnel shall be made directly to: (1.0) a. NRC Operations Center 1 I b. Louisiana Of f ice of Emergency Preparedness c. Louisiana Nuclear Energy Division d. Appropriate Parish authorities l I QUESTION 6.29 (1.00) Certain individuals or groups control access to various plant areas by I controlling issuance of keys. For each of the following items (a - d), 1 indicate which individual / group (1 - 3) controls key issuance for access to those areas. (1.0) a. High Radiation Areas 1. SS/C0F b. Very High Radiation Areas 2. Senior Radiation Protection Technician c. Radiation Exclusion Area 3. Security d. Locked valves (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********)

st__BEoGIDB_EBINGIELES_LZil_IBEBUDQXNedIGS' Page 21 LZ11_6ND_0DdEDUENI2_11011_LEUNDodENI6Lg_gxedl ' ANSWER 4.01 ( 24.0) GENERIC FUNDAMENTALS EXAM-REFERENCE l GENERIC FUNDAMENTALS EXAM l 1. l-l 1 l l l l-l l l J l I (***** END OF CATEGORY 4 *'****) w

l St__EdEBDENQX_6ND_6BN9Bd6L_EL6NI_EVQLUIIQNS Page 22 q L2211 I ANSWER 5.01 (2.00) a. 4'(1.0) b. 1 (1.0) REFERENCE A0P-0002, Main Turbine and Generator Trips, Rev 3, pg 3, 4 j 295005K101 4.0/4.1 295005K301 3.8/3.8 i 295005K301 295005K101 ..(KA's) l ANSWER 5,02 (2.00) t 1 - core submergence (0.5) preferred (0.5) l - steam cooling with inj ection of makeup water to'the RPV (0,5) l - steam cooling without injection of makeup water to the RPV (0,5) i k 1 i REFERENCE j l E0P Appendix B, Technical Bases for E0P Steps, Section 3, pg 6 of 191 295031A204 4.6*/4.8* i 295031A204 ..(KA's) J I ANSWER 5.03 (1.00) l c (1.0) 1 l REFERENCE 1 l E0P Appendix B, pg 91 of 191 l 295037K306 3.8/4.1 l 295037K306 ..(KA's) ) f l l l l l (***** CATEGORY 5 CONTINUE 0 ON NEXT PAGE *****)

1 1 .St__EMEBQENCX_6ND_8BN9BdeL_EL8NI_EY9LUI1ONg Page 23

L22%Y ANSWER 5.04 (2.50).

deenergize the: scram-solenoids 'l - vent the scram air header reset the scram,' drain SDV, manually scram again 1 individual scram switches to TEST. 'l increase CRD' cooling water!dp -] insert using CRDH. i - vent CRD overpiston. volume 1 - arm an'd depress ARI pushbuttons ) (5 required-at'O.5'each) <l j 'l l REFERENCE 'j E0P-1A, Appendix B, pg 94, 95 l 295037A105 3.9/4.~0 i ) 295037A105 ..(KA's)' l- -1 l L l ANSWER 5.05 (0.50) .) 'i I Use of.a hydro pump (0.5) l REFERENCE l E0P-1A, Appendix B, pg 98 o L 295037K213-3.4/4.1 l 295037K213 ..(KA's) l ANSWER. 5.06 (2.50) a. Insert control rods to less than 80% rod line (0.3). Monitor APRM j' back panels for flux oscillations (0.3). If. APRM. oscillations are l 125% peak to. peak (0.3), and the magnitude is increasing (0.3), scram j; the: reactor.(0.3). Accepted actions per Rev 2, 3, or 4 of.A0P-0024 l due to the rapid number of revisions to this procedure. i b. Plant Manager (0.5) or APM-0 in his absence i c. thermal - hydraulic _ instabilities in the core (0.5) ) 1 (*****. CATEGORY 5 CONTINUED ON NEXT PAGE *****) ) bl_.__._____..___.____._.___________..______.____._____

'St__EMEBGEU91_eUD_eBN9BdeL_ELeNI_EY9LUI1gNg Page 24 L33&l REFERENCE AOP-0024, Decrease in Recirculation System Flow Rate, Rev 2, pgs 2, 3 Standing Order #69, Operation With Single Loop Recirculation Flow 295001K103 3.6/4.1 2950010010 3.8v/3.7* 295001G010 295001K103 ..(KA's) ANSWER 5.07 (2.00) a. Use the manual trip handle at the turbine front standard (1.0) l b. Motoring of the generator (1.0) and subsequent' turbine damage (0.5 if l turbine damage is only r es p o ns e'). l REFERENCE 1 l AOP-0014, Loss of 125 VDC, Rev 3, pg 3 1 295004K105 3.3/3.4 295004A102 3.8/4.1 295004A102 295004K105 ..fKA's) ANSWER 5.08 (1.00) a. RCIC (1.0) REFERENCE AOP-0050, Station 31ackout, Rev 2, pg 11, 12 295003A103 4.4*/4.4* 295003G011 4.1*/4.3* 295003G011 295003A103 ..(KA's) i ANSWER 5.09 (2.00) a. When no CR0 pumps are running (0.5) and >1 CRD accumulator trouble i ala. r is in (0.5). i b. 1 (1.0) (***** CATEGORY 5 CONTINUED ON NEXT PAGE ***c*)

j \\ l 1 4 Et__ENEBGEN91_eND_6DN9BdeL_EL6NI_EY9LVIIQNH Page 25 12211 j \\ L b 1 REFERENCE j ( AOP-0011, Loss of Reactor Plant Component Cooling Water, Rev 3, pg 2, 3 1 295018K201 3.3/3.4 295018G010 3.4*/3.3* l l 295018K201 295018G010 ..(KA's) I ANSWER '5.10 (1.00) l o e, d, b (0.33 for each manipulation to put in the correct order) l c l 1 REFERENCE l I l AOP-0027, Fuel Handling Mishaps, Rev 4, pg 3 j l 295023K202 2.9/3.2 ] l 295023K202 ..(KA's) i 1 ANSWER 5.11 (2.50) J (5 required at 0.5 each) 1. Containment to annulus dp >5 psid j 2. Containment temperature >185 deg F 3. Drywell temperature >330 deg F l 4. Reactor pressure and Suppression Pool temperature cannot be maintained j in the safe zone of the appropriate' figure 5. Suppression pool level and delta THC cannot be. maintained in the safe j zone of the appropriate figure l 6. Suppression pool level and reactor pressure cannot be maintained in the safe zone of the appropriate figure 7. A primary system is discharging 2nto secondary containment and any ) area temperature, area radiation level, or area water level exceeding its maximum safe operating value in more than one area of the appropriate table 8. Offsite release rates requiring a General Emergency with a primary system discharging outside primary and secondary containments REFERENCE E0P-1 295028G012 3.8*/4.3* 295029G012 3.6/4.4* 295029G012 29502LG012 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

~. L [,

. ; a 1-p 5t__EMEBDENG118ND_8HNDBd8L_EL6NI_EVQLUI1QNS Page 26 i

-12211 l_ L I l ' ANSWER. 5.12 (1.00). HPCS,.LPCS,-RCIC (0.33.each). ' REFERENCE l l 1 AOP-0031, Shutdown'from Outside the Main Control Room, Rev 5, pg 5-I- .295016G010.3.8*/3.6*: l: I 295016G010 ..CKA's) l l l ANSWER- ' 5.13'- [1.00) If conditiene change such that the opposite decision is now'true, the-procedure must.be. reentered at that' step (1.0). Non coded decision steps do not have to be reentered.. REFERENCE OSP-0009, Author's Guide / Control and Use of Emergency Operating: Procedures, Rev 4, pg 5 ~295024G012 3.9/4.5 -{ 295024G012 ..(KA's) ANSWER 5.14. (2.00) a. E0P director / coordinator ( 1. 0 ) I b. Advisor to the C0F (1.0) l REFERENCE ) l OSP-0009, Rev 4, pg 19, 20 295025G012 3.9*/4.5* 295016G010 3.8*/3.6* l \\ l-295024G012 295016G010 ..(KA's) i 1 l (***** CATEGORY 5' CONTINUED ON NEXT PAGE.*****). i

j ) =Sz__EMEBAENGl_6ND_6HN9Bd6L_EL6HIiEY9LUIIQNS' Page'27 ? 12211 i l l . ANSWER: 5.15 (1.00) / The most important. ingredient is the dialog between the C0F and the NCO's. ] .Also accept: communication es dialog.'(1.0) q REFERENCE 4 OSP-0009, Author's Guide / Control and Use of Emergency Operating Procedures,. 'Rev 4, pg'21 295025G012 3'.9*/4.5* 295024G012 ..(KA's). 1 ANSWER 5.16 (1.50) SLC (0.5) ] - tripping recirculation pumps (0.5) j - lowering reactor water level (0.5). REFERENCE i E0P-1A

j 295037K102 4.1*/4.3* 295027K103 4.2/4.4*

1 l 295027K103 295037K102 ..(KA's) ] 4 ANSWER 5.17 (1.00) a (1.0) j REFERENCE E0P-1A, step 53 295037K306 3.8/4.1 295037K306 ..(KA's) -(***** CATEGORY 5 CONT 1dVED ON NEXT PAGE.*****)

j .St._EdEBGENCX_6HD_6HNDBd6L_EL6NI_EYDLUII9NH Page 28 l 12213 l l I 1 I 1 ANSWER 5.18 (1.50) q - W he..

..dividual rod movement is observed (0.5)

) - 65 preg IA header pressure (0.5)- u - When it is determined that instrument air cannot be restored (0.5) ) l REFERENCE 1 l AOP-0008, Loss of Instrument Air, Rev 3, pg 2, 3 ) l 295019G010 3.7*/3.4* q l a l 295019G010 ..(KA's) [ l i ) { f ANSWER 5.19 (1.00) 1 b (1.0) l l ' REFERENCE l l AOP-0008, Loss of Instrument Air, Rev 3, pg 2, 4 l 295019K207 3.2/3.2 295019K201 3.8/3.9 i 295019K201 295019K207 ..(KA's) l i ANSWER 5.20 (1.00) I l fn anticipation of a turbine trip (0.5) from loss of cooling to the turbine lube oil coolers (0.5). REFERENCE A0P-0009, Loss of Normal Service Water, Rev 3, pg 2 1 295005G007 3.1/3.3 l 295005G007 ..(KA's) l l l l l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) - A

i l 4 St__EdEBGEN91_6ND_6BN9Bd6L_EL6NI_EVDLVIIQNg Page 29 j L2211 l 1 ANSWER 5.21 (1.50) { -l o. 3% power (0.5) accept 2 to 4. b. 1 (0.5) c. E0P-1A ATWS C0.5) REFERENCE j A0P-0031, Shutdown from Outside the Control Room, Rev 5, pg 13 295016A201 4.1*/4.1* 295016A201 ..CKA's) ) ANSWER 5.22 (0.50) Div I remote shutdown panel (0.5) j REFERENCE A0P-0031, Shutdown from Outside the Control Room, Rev 5, pg 5 295016K201.4.4*/4.5* 295016K201 ..(KA's) l l l l 4 i l 1 l l (***** END OF CATEGORY 5 *****) l

~.. 1 1 J 1 1 i 62__EL6HI_SYSIENS_12Dil_6ND_EL6HI:WIQg_GENEBIG Page 30 BESEDNSIBILIIIES_LI21) l I ANSWER 6.01 (1.00) j l b (1.0) J l REFERENCE LOTM-15-2,. Reactor Protection System, pg 5-7 ) 201001K404 3.6/3.6 i 201001A204 3.8/3.9 ) 201001A204 201001K404 201001A204 201001K404 ..(KA's) ANSWER 6.02 (1.00) d'C1.0) i REFERENCE LOTM-15-2, Reactor Protection System, pg 2 212000K401 3.4/3.6 f 1 212000K401 212000K401 ..(KA's) ANSWER 6.03 (1.50) e. RPS MG sets (accept 125 VAC) (0.25) non-safety (0.25) b. 125 VDC (0.25) safety reinted (0.25) c. 125 VOC (0.25) non-safety related (0.25) l REFERENCE I LOTM-15-2, Reactor Protection System, pg 2, 4, 9 LOTM-56-2, AC Distribution l LOTM-57-2, DC Distribution 201001K202 3.6*/3.7 201001K203 3.5*/3.6* 201001K205 4.5*/4.5* 201001K205 201001K203 201001K202 201001K205 201001K203 201001K202 ..(KA's) (***** CATEGORY' 6 CONTINUED ON NEXT PAGE.*****)

1 6t__EL6Nf_SYSIEdS_f20&l_6dD_EL6NI:WIQg_GENEBIG Page 31 BESEQUSIBILIIIES_ flail i l ANSWER 6.04 (1.00) i e (1.0) 1 ) REFERENCE { LOTM-15-2, Reactor Protection System, pg 9 l { 212000A413 3.4/3.6 t 212000A413 212000A413 ..(KA's) i 1 I ANSWER 6.05 (4.00) l l a. LPSP 27.5% reactor power (or 157.6 psig ist stage turbine pressure) 1 HPSP 62.5% reactor power (or 410.7 psig ist stage turbine pressure) l LPAP 37.5% reactor power (or 220.6 psig ist stage turbine pressure) 1 1 b. turbine first stage pressure (0.5) j I c. LPSP: Below the LPSP, the Rod Pattern Control System imposes restrictions on rod movements with regard to rod pattern (0,5). Above the LPSP, the Rod Withdrawal Limiter limits the number of notches a control rod may be withdrawn to 4 (0.5). } HPSP: Above the HPSP, the Rod Withdrawal Limiter limits the number of ) i notches a control rod may be withdrawn to 2 (0.5). l 1 LPAP: No control function, indication only. l 1 l d. Immediately return the control rod to the position prior to the l l withdrawal (0.5) l REFERENCE 1 \\ l LOTM-6-2, Rod Control and Information System, pg 14 l River Bend Technical Specification 3.1.4.1 l l 201005K102 3.3/3.5 201005K507 3.5/3.5 201005K509 3.5/3.5 201005K510 3.2/3.3 201005A101 3.2/3.3 201005G014 3.5/3.8 L 201005G014 201005A101 201005K510 201005K509 201005K507 1 201005K102. 201005G014 201005A101 201005K510 201005K509 201005K507 201005K102 ..(KA's) L 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l

I i -e. LA__EL8HI_SXSIEdS_LSD11_8NQ_EL6NI:WIDg_GENgBIC Page 32-BESEQNSIBILIIIES_LISil .) .l ' ANSWER .6106 'C2.50) y 1 1.. Shutdown the HPU using the manualspushbutto'n at H13-P600 ) '2.. Shutdown the HPU using the shutdown pushbutton at H13-P614 ] I 3. Shutdown!.the HPU at H13-P614:by: placing.both subloops in, Maintenance-l ,1 l .'4. ' Shut the' drywell. isolation valves at : H13-P808 j ) l 5.. Depress-the Drywell Pressure Test pushbutton at H13-P614 l 6.

l Depress the CRVICS B0P-pushbuttons on the H13-P680 panel' (5 required at'0.5 each) l 5

REFERENCE-I [ LOTM-8-2, Recirculation Flow Control, pgs.5 --:8, Figure 4 i 202002A402 2.8/2.8 L 202002A402 202002A402 ..(KA's) i I ANSWER 6.07 (1.50) i l 1. RWCU (0.5) 2. RCIC (0.5) 3.. RHR (0.5) REFERENCE LOTM-51-2, CRVICS, pg 21 223002G007 3.8/3.9 223002G007 223002G007 ..(KA's) l ANSWER' 6.08 (0.50) Main Steam (0.5) .a l l '(***** CATEGORY 6 CONTINUED ON NEXT!PAGE *****) {

Et__EL68I_SYSIENS_f20?l_6ND_EL68I: WIDE _GENEBIG Page 33 BESEQNSIBILIIIgS_LI231 1 REFERENCE .LOTM-51-2, CRVICS, pgs 3-5 j 223002K608 3.5/3.7 223002A201 3.2/3.5 t i 223002K608 223002K608 223002A201 223002A201 ..(KA's) l 1 ' ANSWER 6.09 (3.50) { a. F004 HPCS Injection Valve (0.5) F015 Suppression Pool Suction Valve (0.5) HPCS Pump (0.5) l b. 1. Level decreases to Level 2 (1.0) and the system automatically restarts. 1 2. High Level 8 signal is reset by the operator (1.0) after the q 1evel decreases to below the level 8 setpoint. 4 I REFERENCE i LOTM-18-2, HPCS, pg 8 209002A305 3.7/3.7 209002A401 3.7/3.7 209002A402 3.6/3.6 209002A403 3.8/3.8 { l 209002A403 209002A402 209002A401 209002A305 209002A403 209002A402 209002A401 209002A305 ..CKA's) ) ANSWER 6.10 (1.00) o (1.0) REFERENCE LOTM-34-2, Feedwater Level Control System, Figure 1 259002K302 3.7/3.7 259002K304 2.9/3.0 259002K305 2.8/2.9 259002K305 259002K304 259002K302 259002K305 259002K304 { 259002K302 ..(KA's) -(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****).

I 6t__EL8HI_SYSIEUS_12D11_6ND_EL6HI: WIDE _DENEBIG Psge'34 BESEQNSIBILIIIES_11211-l l l ' ANSWER 6.11 (1.'003 b (1.0) REFERENCE LOTM-3-2, Nuclear Boiler Process Instrumentation, Figure 1 216000K122 3.6/3.8 216000K122 216000K122 ..(KA's) ANSWER 6.12 (0.50) a. 3 (0.5) REFERENCE LOTM-58-2, Standby Diesel Generators and Auxiliaries, pg 17 264000K401 3.5/3.7 264000K402 4.0/4.2 264000K402 264000K401 ..(KA's) ANSWER 6.13 (1.50) a. 40% C0.25) by turbine first stage pressure (0.25) b. During the first part of a scram at the end of cycle, the control rods cannot insert negative reactivity as fast as the collapsing voids can insert positive reactivity (1.0) due to the sudden decrease in steam flow due to a turbine trip or control valve fast closure. REFERENCE l LOTM-7-2, Rarirculation System, pg 12 202001K104 3.3/3.3 202001K505 3.5/3.6 1 l 202001K505 202001K104 202001K505 202001K104 ..CKA's) l l l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

Et__EL6NI_SYSIEMS_12Dil_6ND_EL6HI: WIDE _QENEBIG Page 35 BESEQUSIBILIIIES_LI211 ANSWER 6.14 (2.00) o. - OPERATE SWITCH to OPERATE (0,5) for each subsystem. - Reactor Pressure < 25 psig (0,5) - PVLCS air pressure > 50 psig ( 0. 5 ) ~ b. SRVs (0.5) REFERENCE LOTM-52-2, Penetration Valve and MSIV' Leakage Control Systems, pg 5, Fig i 239003A301 3.0/2.8 239003K101 3.3/3.4 239003K101 '239002A301 239003K101 239003A301 ..tKA's) ANSWER 6.15 (1.00) e (1.0) ) REFERENCE l l SOP-0091, Fuel Pool Cooling and Cleanup System, Rev 5, pg 39 ) i 233000K406 2.9/3.2 233000K406 233000K406 ..(KA's) ANSWER 6.16 (1.00) l MSL Rad Monitors - RPS (0.5) l Off-Gas Monitors - 125 VDC C0.5) l l REFERENCE 1 l LOTM-66-2, Process Radiation Monitoring System l 272000K201 2.5/2.8 272000K202 2.5/2.8 l l 272000K202 272000K201 272000K202 272000K201 ..CKA's) l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

r .4 ~ -8 I

62__EL8NI SXSIEdS_ISD11_8ND_EL8NI: WIDE _GENEBICf Page 36 BESEQNSIBILIIIES_I1211' s.

r ANSWER '6.17I -(1.00) d:(1.0) REFERENCE s LOTM-55-2, Main Generator Auxiliaries, pg 3 245000K605.2.9/2.9 i 245000K605 245000K605 ..(KA's) 1 t l H ANSWER 1 6.18 (2.00' 1 1

a..

That the generator f requency -is slightly higher than the grid frequency.(1.0).. L L b. That the generator frequency and grid frequency are in phase: (1'. 0 ). I i -1' I REFERENCE 1 + LOTM-54-2, Generator Exciter and Voltage-Regulator; pg 12 l 245000K507'2.6/2.9 245000K507 245000K507 ..(KA's) 1 1 ANSWER 6.19 (1.00) l c (1.0)- i REFERENCE ) -LOTM-24-2, Main Steam,' Figure 1-239001K119 3.1/3.2 1' l ?39001K119 ..(KA's) 1: 1 I l 1 a l Niy (***** CATEGORY 6 CONTINUED 0N NEXT PAGE ***;*) 1,. L. E----------.

1 E___EL6NI_SYSIEdS_LSD12_6ND_EL6NI: WIDE _QENEBIQ Page 37 BESE9NSIBILIIIES_LISil l ANSWER 6.20 (1.00) d ( l'. 0 ) REFERENCE l LOTM-24-2, Main Steam, pg 7 1 239001K404 3.'4/3.S d l 239001K404 239001K404 ..(KA's) 1 l ANSWER 6.21 (1.00) j l Standing Orders (1.0) l REFERENCE i Standing Order #41 ] 294001A103 2.7/3.7 l I 294001A103 ..(KA's) ) l l 4 ANSWER 6.22 (1.00) i Operational Conditions 4 and 5 (0.5 each) REFERENCE l RBS Technical Specifications Table 6.2.2-1 294001A103 2.7/3.7 294001A103 294001A103 ..CKA's) (***** CATEGORY 6 CONTINUED ON~NEXT PAGE *****)

y;- a.

3 j

2 (,. 1 j. 1 p l 61__EL6BI_SX1IEd1_L1011_6ND_EL6NI:WIDElGENEBIG Page 38 L

BESEDNSIBILIIIEl_L1111 j.

j-a l l

cANSWER

.,6.23 '(1. 5 0 ). 9 Fai1~ Closed:.Should have the aireand or; power removed'(0.5), and1 the, l-control switch in the' closed porition.(0.5)'. Fail;Cpen: Valve should be' gag 0ed or a blocking device installed to, L ensure the valve stays shut (0.5) g l l~ REFERENCE. 1 o 'ADM-0027, Protective Tagging, Rev 7,.pg 5-l 294001K102 3.9/4.B*< l t-294001K102 ... ( K A ' 9 3 I i ANSWER 6.24' (1.50) 1^ it 50 psig or 200 deg F (0.75 each); ] l REFERENCE ADM-0027, Protective. Tagging, Rev 7, pg 6 294001K108.3.,1/3.4 294001K109 3.4/3.0L l '294001K180 4294001K109 294001K108 294001K109 ..(KA's) l l ANSWER 6.25 (2.00) l l - A radiation monitoring device which continuously indicates the dose-rate in the area. 1 H - A' dose integrating monitor which is set to alarm ~when a preset dose?Is

received, i

l l . Accompanied by an individus1 qualified-in radiation protection i procedures, with a dose-rate monitoring device. L ,(2 of 3 at.1.0 each) l l 4 l g l b (***** C'ATEGORY 6 C014TINUEO. ON ' NEXTlP AGE *** 2 )- n ct________________ _1 J

t ] f 6.r.__EL8NI_SXSIEUS_L3Dil_6UQ_EL6NI: WIDE _QENEBIG Page 39 ,l BESEQNSIBILIIIES_L1211 ~ REFERENCE RSP-0200, Radiation Work Permits, Rev 4, pg 11 294001K103 3.3/3.8 294001K103 ..(KA's) ANSWER. 6.26 (2.00) i Shelter (0.5) to the 2 mile radius around the station (0.5) Shelter (0,5) to the'5 mile radius (0.25) in the downwind (0.125) and adj acent sectors (0.125) REFERENCE EIP-2-005, General Emergency, Rev 6, pg 6 294001A116 2.9*/4.7* 294001A116 ..(KA's) l ANSWER 6.27 (1.00) a (1.0) REFERENCE } EIP-2-007, Protective Action Recommendation Guidelines, Rev 7, pg 4 294000A116 2.9*/4.7* 294001A116 ..(KA's) ANSWER 6.28 (1.00) d (1.0) ) (***** CATEGORY 6 CONTINUED ON NEXT.PAGE *****)

6t__EL6NI_SYSIEdS_f2Dil_6ND_EL6NI: WIDE _GENEBIG Page 40 BESEDNSIBILIIIES_flatl REFERENCE EIP-2-007, Rev 7, pg 4 294001A116 2.9*/4.7* 1 294001A116 ..(KA's) l l l ANSWER 6.29 (1.00) l 1 a. 2 l b. 2 f c. 3 b.25each) l I i REFERENCE l ADM-0020, Plant Key Control, Rev 4. pg 3 l 294001K105 3.2/3.7 294001K105 ..(KA's) 1 1

• l

(***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) l

i = 1. l TEST CROSS REFERENCE Page 1 L QUESIl0U _V6LUE BEEEBEUGE_ l 4.01 24.00 9000137 l l '24.00 l 5.01 2.00 9000.139 l 5.02 2.00 9000140 ( .5.03 1.00 9000141 i 5.04 2.bO-9000142 5.05 .0.50 9000143 5.06 2.50 9000144 l 5.07 2.00 9000145 5.08 1.00 9000146 i E 5.09 2.0P 9000147 L 5.10 1.00 9000148 1 5.11 2.50 9000149 5.12 1.00 9000150 5.13 1.00 9000151 5.14 2.00 .9000152 5.15 1.00 9000153 5.16 1.50 9000154 5.17 1.00: 9000155 1 5.18 1.50 9000156 l 5.19 1.00. 9000157 5.20 1.00 9000158 5.21 3.50 9000159 5.22 0.50 9000160 32.00 6.01 1.00 9000097 6.02 1.00 9000098 6.03 1.50 9000099 6.04 1.00 9000100 6.05 4.00 9000101 6.06 2,50 9000102 6.07 1.50 9000103 6.08 0.50 9000104-6.09 3.50 9000105 6.10 1.00 9000106 6.11-1.00 9000107 6.12 0.50 9000108 6.13 1.50 9000109 6.14 2.00 9000110 6.15 1,00 9000111 l 6.16 1.00 9000112 6.17 1.00 0000113 6.18 2.00 9000114 6.19 1.00 9000115 6.20 1.00 9000116 6.21 1.00 9000083 6.22 1.00 9000117 6.23, 1.50 9000118 l 6.24-1.50 9000119 l, 6.25i ll2. 0 0 9000120 6.26 < ,2.00 9000133

x. 1 i TEST CROSS REFERENCE Page 2 QUESIl0N _VaLUE BEEEBEURE_ 6.27 1.00 9000134 6.28 1.00' 9000135 6.29 1.00 9000136< 41,50 97.50 l L 1 1 i l l l I. i l

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FACILITY COMMENTS ON NRC EXAM ADMINISTERED ON FEBRUARY 14, 1989 2.05 (5.04) - Request additional correct answer to be: ARM and depress ARI pushbuttons. (

Reference:

E0P-1A. step 8) 2.07 (5.06) - a.) Due to the high NRC visibility concerning the LaSalle Events, several revisions _of AOP-024 have taken place in L a short period of time. Request acceptance of immediate actions of AOP-024, Rev. 2, 3 & 4. c.) Request additional correct answer: flux noise (Reference AOP-024 - Step 5.4.1) 2.09.(5.08) - b.) Request part "b" be deleted - not an immediate action to A0P-050 - operators not required to memorize details of an AOP enclosure. (

Reference:

A0P-050, Enclosure 4) 2.10 - a.) decrease - also accept as an answer " failure of SJAE l pressure regulator." 5.16 - Request additional correct answer - Downshift recire. pumps to LFMG. (Reference E0P-1A, Step 11) 3.12 (6.12) - Request deletion of parts a, b and c of this question. (Reference S0?-0053, Step 2.22)i LOTM 58-2 incorrect. 3.13 - Request additional correct answer to be "c". (Reference E0P-1A, Step 11 - Appendix A pg. 86 of 186) l 6.27 - Request additional correct a'nswers to be "b, c & d". (Reference EIP-2-007, pg. 4 of 19, para. 5.6) 3.27 b & c - Reactor operator not trained on 10 CFR 55.53 e & f. Reference KA 294001A103 stated ability to locate and use procedures and station directives related to shift staffing and activities. 3.31 - a.) Request additional correct answers to read "Use in critical situations or emergency situations only." T L

s---- 7 a. i SIMULATION FACILITY FIDELITY REPORT Facility Licensee: Gulf States Utilities Facility Licensee Docket No.: 50-458 Facility License No.: NPF-47 Operating Tests Administered at: River Bend Station Operating Tests Administered: February 15-17 and 22-23, 1989 During the conduct of the simulator portion of the operating tests identified 1 above, the following apparent performance discrepancies were observed: 1. SWP-MOV-4A did not fail open when overridden open. It shut upon receiving 4 an isolation signal. An attempt to recreate the event resulted in the j valve failing open as demanded. 2. The procedure to shift recirculation pumps to fast speed in the simulator reflects the changes made to the feedwater flow interlock in the plant. The interlock in the simulator has not been changed to reflect the change made in the actual plant, thus the sinulator procedure and simulator system performance do not match. 3. The Division III diesel generator output breaker could not be locally tripped following a loss of 125 VDC. The breaker should be trippable locally without 125 VDC available. 4. When shifting recirculation pumps to fast speed, the START pushbutton for the 5A(B) breaker had to be held in the START position for several seconds to effect the transfer. If not, the pumps tripped. This may not reflect actual plant performance. 5. The displays on the Digital Radiation Monitoring System (DRMS) in the simulator are different from the ones in the plant control room. The displays have different radiation monitoring detector inputs. RBS training staff informed NRC that this was previously noted and a modification package was already in progress to correct the discrepancy. I - _ _ _ _ _ _ _ _}}