ML20246N736

Exam Rept 50-298/OL-89-01 on 890228-0302.Exam Results:One Senior Reactor Operator & Four Reactor Operators Passed All Portions of Exams.One Reactor Operator Failed Written Exam

ML20246N736
Person / Time
Site:	Cooper
Issue date:	03/20/1989
From:	Pellet J, Whittemore J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20246N734	List: ML20246N729 ML20246N736 NLS8900104, Forwards Comments on Questions & Answers Associated W/Nrc Administered During on 890228-0302.Concerns Should Be Considered During Grading of Written Exams
References
50-298-OL-89-01, 50-298-OL-89-1, NUDOCS 8903280018
Download: ML20246N736 (84)

Text

{{#Wiki_filter:- O I i APPENDIX U.S. NUCLEAR REGULATORY COMMISSION REGION IV Operator Licensing Examination Report: 50-298/0L 89-01 Docket No.: 50-298 Operating License No.: DPR-46 1 Licensee: Nebraska Public Power District i P. O. Box 499 Columbus, Nebraska 68602-0499 Facility: Cooper Nuclear Station Examinations at: CooperNuclearStation(CNS) J ch f( 9 Chief Examiner: / f.E.Whittemore, Examiner Date Uperator Licensing Section Division of Reactor Safety j Approved by: k& 3 20 J.'L. Pellet, Chief Date Operator Licensing Section Division of Reactor Safety Summary NRC Administered Examinations Conducted on February 28 - March 2, 1989 (Report 50-298/0L 89-01) NRC administered examinations to one SRO and five R0 applicants. The SR0 and four R0 candidates passed all portions of their examinations and have been issued the appropriate license. One R0 failed the written examination. l 8903280018 890322 PDR ADOCK 0500 {S

c--,- J-i DETAILS 1 l 1. Persons Examined SRO 'R0 Total License Examinations: Pass - l' 4' 5 1 Fail - 0 1 1 2. Examiners 1 J. E. Whittemore, Chief Examiner M. W. Parrish 3. Examination Report Performance results for individual examinees are not included in this i report as it will be placed in the NRC Public Document Room and these results are not subject to public disclosure. i a. Examination Review Comment and Resolution l 1 In general, editorial comments or changes made during the examination, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made by CNS staff. The only comments addressed in this section are i those which were not accepted for incorporation into the examination or answer key. Those comments accepted are incorporated into the master examination key, which is included in this report. Comments may be paraphrased for brevity. The full text of the comments is attached. 2.16 Also accept drywell temperature effects on Nuclear Boiler 5.21 Level Instrumentation due to increasing Drywell temperature Comment not accepted as _this problem is mitigated by E0P cautions and a correction table, and the major concern remains differential expansion of the bellows flange. 3.03 Also accept RPIS inop, Rod Select power off, or RSCS voltage low. Will accept RPIS inop as a condition that will cause a select block. Cannot accept other conditions as' reference material does not support that they will cause an actual " Select Block". l _ _ _ _ _ _ _ ~

, 1 i 1 i 3.08 Question should be deleted due to no single answer being 6.07 correct for CNS. At 5% power vessel level must be controlled with the start up flow control valves which are 1 l controlled normally using.a single level instrument. When j the level instrument fails downscale, the startup flow control valves will fully open in response to the sensed low level causing feed flow to increase and reactor level to slowly increase to 58.5 inches at which point the RFP's l will trip causing level.to decrease to the Reactor Low Water Level scram. A correct answer would be, feed flow i increases to the high level trip, the RFP's trip, feed flow decreases and the reactor scrams on low level. Not accept'd as b. is a valid answer that correctly e describes the plant response that will occur without operator interference. Other answers were accepted that could be supported by assumptions stated by the examinee. 3.26 Question should be deleted since CNS Procedure 0.16 j 6.23 specifically states that no independent fire watch is ever i required. ] Question cannot be deleted as the intent of CilS'0.16 is that any individual working in the immediate vicinity can function as the required fire watch. Three of the_four distracters do not indicate that any one is in attendance, or in other words acting as a_ fire watch. The implication of accepting this comment as valid is that there is no circumstance where an assigned fire watch is ever required. b. Site Visit Summary (1) At the end of the written examination administration, the facility licensee was provided a copy of the examination and answer key for the purpose of commenting on the examination' content validity. The licensee was' informed that written examination grading would not be started until licensee review comments were received in the regional office. A set of unsigned comments was provided to the Chief Examiner at the_end of the examinations prior to leaving the site, t (2) The following items were communicated to the facility licensee representatives as comments, observations, suggestions, or deficiencies: 1

l _4 (a) Candidates experienced cifliculty.in utilizing the local procedure for. locally styt ting an energency diesel generator. after failure to start upon loss of offsite power. The' problem appears to be due to'the poor. procedure rather.than a weakness in the candidates. j (b) During a control room evacuation and subsequent HPCI. cooldown,1the' local procedure adequately served the purpose of placing the plant in.the desired condition.- However, this was'not the case.when the HPCI pump became unavailable. The local procedure'for initiating RCIC cooldown does not-give the operator clear guidance as to how to initiate and control the cooldown locally. c. Master Examination and Answer Key Master copies of the CNS license examinations and. answer keys are-attached. The facility licensee comments which'have been accepted are incorporated into.the answer key. 'd. facilityExamination.ReviewComments 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. I l

6 e U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4 FACILITY: CggggC_S1211gD___________ REACTOR TYPE: BWB:GEd__________________ DATE ADMINISTERED: $24Q2/2B_________________ INSIBUGIIQUS_IQ_Q86DIQ6IEi 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 at least 70% in each category and a final grade of at. least 80%. Examination papers will be picked up six (6) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY __V8LUE_ _IDIeL ___SQQEE___ _VeLUE__ ______________CoIEQQBI_____________ _25100__ _2SzQQ 1. REACTOR PRINCIPLES ~ 7%) [ THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) j _2ZiDQ__ _2Z100 ________ 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) _dH1DQ__ _dB100 ________ 3. PLANT SYSTEMS'(38%)'AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%) _1981Q__ TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature l l l

I J i I It__BEeQIQB_EBINGIELES_LZil_IBE800010601Q1 Page 4 LZ11_eUQ_QQUEQUEUIS_L1111_LEUUQedEUI6LE_EMedl i QUESTION 1.01 ( 25.0) GENERIC FUNDAMENTALS EXAMINATION i l 1 1 1 l 1 1 ) l i I 1 1 l l l 1 l l l l 1 (***** END OF CATEGORY 1 *****)

i l l 21__EUEBGEUQ1_oVR_oBUDBUSL_ELoul_EV9LVIIQUE Page S L2Z13 I o i I l I QUESTION 2.01 (3.00) l l a. How do the Emergency Operating Procedures (EOP's) provide the operator with guidance for essessing Reactor Pressure Vessel (RPV)_Li! VEL during? elevated temperature conditions in the Drywell? (1.0) I b. What are the TWO (2) conditions, either one of.which must be met, that i E0P-1, RC/L specifies for the operator to escertain prior to placing in MANUAL or securing any Core Standby Coolirg System (CSCS)? (0.8) J l c. What are 2 purposes of " Emergency Depressurization"? (0.6) d. What are 2 of the 3 conditions that would reouire RPV flooding? (0.6) l l l \\ l l QUESTION 2.02 (1.00) 1 According to Operations Department Policy, CNS 2.0.1, when is any licensed operator authorized to shutdown the reactor? (1.0) I i j J (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

i ] Zi__EdEBGEUQY_6UQ_eBUQBdeL_ELoNI_EVOLul100$ Page -6 12Zhl { l i QUESTION 2.03 (2 00) The automatic actions listed for a main turbine and generator trip per CNS I 2.4.9.1.10 " Turbine Trip", include reactor scrams. For parts "a" and."b" below select the answer from items 1 - 4 that will most likely initiate the l reactor scram. o. The turbine trips from 24% reactor power 1. Main turbine stop valve position 2. Turbine control valve position 1 3. Reactor vessel level 4. APRM (1.0) l 1 b. The turbine trips from 79% reactor power 1. Main turbine stop valve positf.on 2. Turbine control valve position 3. Reactor vessel level 4. APRM (1.0) QUESTION 2.04 (1.00) A scram condition exists (MSIVs shut) with the reactor at power. The reactor did not shutdown. Core cooling is adequate. Which concern below is being most severely challenged in this condition? (1.0) a. fuel integrity b. RPV integrity c. containment integrity d. in.jection system operability 1 l l l t ( (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) ( {

2t__EdEBrgUgy_AUQ_6BNQB06L_EL60I_EyQLbilgUS Page 7 2 L2Zil QUESTION 2.05 (2.00) If the control rods frsil to insert when required on a scram, state FIVE (5) methods that may be tried to obtain control rod insertion per E0P-1A. (2.0) QUESTION 2.06 (0.50) If boron inj ect ion is required and SLC is not available, whet is the alternate method of injecting boron at CNS? (0,5) QUESTION 2.07 (0.50) In accordance with CNS 2.4.1.3, " Unexplained Increase in Reactor Power" what immediate action is required if all indications are that power is increasing for no apparent reason? a. Attempt to reduce power with rod insertion, b. Attempt to reduce power with RP flow. c. Manually scram, d. Initiate emergency shutdown. QUESTION 2.08 (1.00) The reactor is operating at 100% when one recirculation pump trips due to an electrical fault. What is required of the operator if the core is operating in the region of instability and 9% peak to peak flux oscillations are occurring? a. Shut the effected loop RR pump discharge valve. b. Initiate manual reactor s c r a m., c. Insert rods and/or increase RR flow. d. Commence CNS 2.1.5, " Emergency Shutdown from Power". (1.0 l I, (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1

i e l 3t__EUEBGEUCX_8UQ_aBUQBdeL_EL60I EVQLUIIQUI Page 8 L2211 QUESTION 2.09 (1.00) Which of the following does NOT serve to bypass the Group.I isolation that will automatically occur on a scram due to loss of condenser vacuum? a. Condenser vacuum bypass switches in bypass. b. Control valve fast closure, i c. Stop valve closure. l 1 d. Reactor Mode Switch in startup. (1,0) j QUESTION 2.10 (2.50) l l During a complete loss of AC power (station blackout), in accordance with j l CNS 5.2.5.1, " Loss of All Site AC Power Station Blackout": l a. What can be done to suppleraent the available control room instrumentation? Specify any equipment needed and location (s) (0.75) j l i l b. State Four (4) actions t hat should be taken to conserve the available 1 DC power during on extended power loss. (1.0) -{ l c. What are the TWO (2) maj or concerns about the elevated Drywell temperatures that may occur. (0.75) i ( 1 I (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) {

2t__EdEBGEUCX_eUQ_8BUQBd6L_EL6HI_EYQLUIIQU$ Page 9-12Z12 QUESTION 2.11 (2.00) Match up the symptoms.or conditions in the right-hand column that will result from.the loss of the power system in the left hand column. Right hand column symptoms may be used more than once or not at all. i s. A 24VDC system 1. RCIC system out of service b. 18 125VDC system 2. Loss of RHR Pumps A & B c. lA 250VDC system 3. GP VI isolation l l 4. Loss of control room closing and l tripping capability for 480VAC breakers. 5. Prevent protective tripping on main turbine. (2.0) i QUESTION 2.12 (2.50) ) l The control room was evacuated earlier. The reactor is presently shutdown i and has been cooled down using HPCI. Torus cooling.is in progress and the control room is now habitable, j a. What are FOUR (4) systems that must have their' isolation switches returned to NORMAL? (1.0) b. Upon control room re-entry, in what positioniwill the Reactor Mode-switch be found? (0.5) j i c. After control room evacuation, what TWO (2) actions were taken by the I by the designated Reactor Building Operator to VERIFY that the reactor had been scrammed? (1.0) l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l I a

St__EdEBGEUQ1_6UQ_eBUQBdeL_ELeUI_EVQLVIIQU$ Page 10 12Zil QUESTION 2.13 (1.00) Which of the following is NOT considered Immediate Operator Action for loss of all Reactor Equipment Cooling (REC) water? a. Isolate the RWCU system. b. Start Service Water Backup switchover. c. Run both RR pumps to minimum speed. d. Scram the reactor. (1.0) QUESTION 2.14 (1.00) Failure of both CRD pumps would be of the most concern during: (Choose the correct answer) a. plant startup and heatup. 1 b. Turbine Generator synchronization to grid. l c. beginning of life operation at 75% power l d, end of life operation at maximum power for stretchout or coastdown conditions. (1.0) QUESTION 2.15 (1.50) During the late summer with suppression pool temperature at 94 1/2 degrees F., it is necessary to perform the quarterly flow tests for the RCIC and HPCI pumps, as the tests were overlooked during recovery from a recent outage. The plant is at 85% power and successful completion of pump tests is THREE (3) hours away from the maximum extended deadline for operability verification. State what the problem is and how continued operation may or may not be possible. (1.5) l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1 J

2&__EUEBQEUQ1_eUQ_8BUQBdeL_ELeNI_ Ell 0LVIIQUE Page 11 l 12Zil I l QUESTION 2.16 (1.50) A loss of all Drywell (DW) coolers has caused a reactor scram due to high drywell pressure. DW pressure is still increasing. a. Considering only DW temperature, what is the greatest concern? (0.5) b. What are TWO (2) specific actions that can be taken.to mitigate the increasing DW pressure without spraying? (1.0) QUESTION 2.17 (1.00) l During refueling, an incident occurs causing RMP-RM-452A & B, Reactor _ Bldg. Ventilation Exhaust Monitors to reach the high-high setpoint. What are THREE (3) cutomatic actions that must be verified? (1.0) QUESTION 2.18 (1.00) According to the Emergency procedure for high refueling floor radiation, CNS 5.3.5, which statement below is correct? 1 l a. It is not necessary to enter the E0P's during a refueling accident. I b. E0P's should be entered if the fuel pool area monitor exceeds 5 mrem /hr. I -1 c. E0P's should be entered if the fuel pool level decreases. I d. E0P's should be entered if RB Ventilation Exhaust radiation exceeds 10 ) mr/hr. (1.0) i i I 'l l l l l i l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1

~ ) o s j 2t__EUEBQEUQ1_oGR_oEUQBUoL_ELeUI_EVQLVIIQU$ Page 12 L2ZU 1 QUESTION 2.19 (1.00) l During a loss of shutdown cooling, due to a service water malfunction with the reactor head in place and RPV et 50 psig. (CHOOSE THE CORRECT ANSWER) { a. It is permissible to open the reactor head vents to promote cooling. 4 i b. Running a recirculation pump at minimum speed is allowed. { c. Control vessel below 48" to promote convection flow d. Cross-connect and place fuel pool cooling in service. (1.0) i i ( 4 l i l l l (***** END OF CATEGORY 2 *****) 1 1

l 2t__ELoNI_SYSIEMS_L2Hil_6UQ_EL6HI:W10E_QEUEB1Q Page 13 l BESEQUSIBILIIIES_f1Dil l QUESTION 3.01 (1.00) i { Backup Scram valves provide a redundant means of venting air from the scram pilot valves and scram discharge valves. These backup valves are: (Choose. the correct answer) l a. normally energized and will de-energize upon a RPS Scram signal. b. all'gned such that two valves in series, one from each RPS trip ) l channel, must actuate to vent the scram air header. / c. designed such that both RPS channels must trip in order for any one of the valves-to actuate. d. powered from the RPS Buses A and B. ) i i QUESTION 3.02 (1.00) Select the statement below which is correct: a. A " Rod Drift" alarm occurs when a rod passes an even numbered reed switch position. I b. a " Rod Drift" alarm occurs when a rod leaves an odd numbered reed switch position. ] l c. A drift alarm is reset by placing the alarm test switch in the " Test" i position. i 1 d. A drift alarm can be reset only when the rod in an even numbered reed switch position. (1.0) QUESTION 3.03 (1.00) What are TWO (2) conditions that initiate a-Reactor Manual Control System " Select Block"? l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

N n l I lt__ELoNI SYSIEdS_L2Hil_oND_ELoUI: WIDE _EEUEBIQ Page 14 BESEQUSIBILIIIES_L1911 QUESTION 3.04 (2.00) ] For each of the situations below, describe how and why the recirculation flow control system will respond. Also state which component of the control system will be controlling RR pump speed. Assume no operator j action. a. 28% power, recirc. pumps at minimum speed with both M/A transfer stations in manual. Recirc-pump "A" M/A transfer station is switched to "AUT0" () i 1 b. 75% power, recire, flow control in master manual when ONE (1) reactor feedwater pump trips. () I 1 QUESTION 3.05 (1.00) i I l During an event a High Drywell Pressure greater than TWO (2) psig and I l Reactor Vessel Low Water Level result in automatic initiation of the High i l Pressure Coolant Injection System (HPCI). Reactor water level is restored j and continues to increase until the HPCI turbine automatically trips on a { high reactor water level. High Drywell Pressure greater than +2 psig still j remains. CHOOSE which of the following is required for auto restart of.the HPCI System. a. Reactor water level drops below the high reactor water level f setpoint. b. Reactor water level drops below a reset setpoint a few inches lower than the high reactor water level setpoint. 1 l c. Reactor water level drops below the low reactor water level setpoint. ) d. The reactor operator depresses the Auto Isolation Reset button. f,1.0) j 1 l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l

j 2t__EL6UI_51SIEdS_L2all_690_EL6UI: WIDE _GENEBIQ Page 15 I BESEQUSIBILIIIES_L1011 I i QUESTION 3.06 (2.50) i l n. What are 3 different controls available to the control room operator ) to retard or prevent the automatic operation-of ADS Safety / Relief j volves? (9.75) b. What condition (s) should be verified before using any of these 1 features or controls? (0,5) i c. What can the control room operator do to DEACTIVATE automatic operation of the ADS system? (0.5) d. What conditions will cause automatic lowering of the setpoint of the i TWO (2) lowest set relief valves? (0.75) QUESTION 3.07 (1.00) Choose the correct statement below concerning the Primary Containment Isolation System (PCIS): a. A loss of power to a cont ainment isolation char.nel will not cause the affected channel to trip. b. All motor operated isolation valves are DC powered. c. A PCIS channel trip due to a loss of a 12CVAC RPS bus will NOT initiate all group isolations. i d. All Group Isolation bypass functions are initiated by the position of the Reactor Mode Selector Switch. 1 l l l l l l l I l t l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l t

21__EL6BI_SISIEdS_L2A11_600_EL6BI: WIDE _SENEB1Q Page 16 BESEQUSIBILIIIES_L1Dil-QUESTION 3.08 (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 occur as a result of this failure? Assume no operator action. (1.0) a. Feedwater flow increases and the reactor trips on high reactor level. b. Feedwater flow decreases and the reactor trips on low reactor vessel level. c. The reactor feedwater pump receives a lockout and vessel level is maintained near initial setpoint. d. A generated flow error signal will a maintain higher RPV level via the Vessel Master Controller. QUESTION 3.09 (1.00) Select the answer below that best indicates how far above the top of the active fuel water level is maintained in automatic assuming normal system operation. (1.0) a. 213" b. 198" c. 172" d. lig" QUESTION 3.10 (2.50) a. What are TWO (2) automatic actions that mey occur within the Standby Gas Treatment (SGT) system if a filter train low flow alarm is actuated after receiving an initiation signal? (1.0) l b. What are THREE (3) viable reasons for excessive air temperature of the airstream leaving an SST train? (1.0) c. What system parameter is measured and controlled to automatically control train flow rate? C0.5) l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l- --w_-----xa_--__u_

21__EL6UI_111IEUS_L20il_6SR_EL6HI: WIDE _QENEBIQ Page 17 BESEQU11BILIIIES_11D12 QUESTION 3.11 (3.00) a. It becomes necessary to stop an Emergency Diesel Generator (EDG) that is running with an auto initiation signal present. What are TWO (2) methods of stopping the EDG? (1.0) b. What is the FUNCTION and ULTIMATE PURPOSE of the NORMAL-ISOLATE control switches on the. diesel engine panels? (1.0) c. Provide the name and explain the operation of the device, mechanism, or methodology that functions to preserve starting air pressure in the event the EDG will not auto start on en initiation signal. Provide sensed persmeters end setpoints. (1.0) 1 l QUESTION 3.12 (1.00) l Comparing the TWO (2) different types of detectors used in the Startup Range Neutron Monitoring (4RM) system, choose the item below which is

correct, a.

Both detector chambers use the same inert gas. i 1 b. The fission chamber operates at a higher voltage. l c. Only the proportional counter has active coating on the inside of the I outer electrode, d. Both detector chambers use the same active coating. (1.0) l QUESTION 3.13 (1.00) l An Intermediate Range Monitoring (IRM) system detector operates with an approximate voltage of _____: (Choose the correct answer) a. 24VDC b. 48 VDC l l c. 100VDC 1 d. 300VDC (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__ELeUI_11SIEUS_L2H11_6UD_EL6HI: WIRE _GENEB1Q Page 18 BESEQUSIBILIIIES_L1Dil QUESTION 3.14 (2.00) Fill in the blanks in the in the following paragraph concernism the Average Power Range Monitor (APRM) system. Assume the mode switch is in run. The APRM system contains (a)_______ APRMs. Channels (b)_______ supply inputs to RPS 8. The source of power for the APRM system is (c)_______. Each APRM channel averages inputs from (d)________ LPRM detector chambers. These inputs are averaged and compared with (e)_________ to obtain an APRM rod block signal at (f)________ % power and an APRM scram signal at (g)____ % power. To prevent generating an INOP trip, each.APRM channel must have et least (h)_______ LPRM chambers operable. (2.0) l QUESTION 3.15 (2.50) l For the Rod Sequence Contro'. System (RSCS), answer the following a. The purpose for the system. (0.5) b. The condition (s) at which the system is ENABLED. (0.75) l f c. What provisions, if any, exist to manually bypass the ENTIRE system during operation? (0.5) d. When and why are the bypass switches on Pensi 9-27 utilized? (0.75) QUESTION 3.16 (1.00) Which one of the following Main Steam Line components le designed to limit the differential pressure across the steam dryer assembly? (1.0) a. Main Steam Line flow elbows b. Main Steam Isolation Valves c. Main Steam Shutoff Valves d. Main Steam Line flow restrictors (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)-

2t__EkeUI SYSIEMS_L2011_eND_ELeUI: WIDE _GENEBIQ Page 19 BESEQUSIBILIIIES_L1011 QUESTION 3.17 (2.00) For each combination of Main Steam Line Radiation Monitor Trips (a - e), select the appropriate automatic action (s) (1 - 4). I a. Channel A High, Channel B High-High 1. Half-scram l l b. Channel A High, Channel D High 2. Scram c. Channel B Downscale, Channel C Inop 3. Mechanical Vacuum l Pump (s) trip l d. Channel A Inop, Channel C High-High I 4. No Automatic Actions ( e. Channel C Inop, Channel D High-High (2.0) l f QUESTION 3.18 f3.00) { List the setpoints for the RWM Low Power Setpoint (LPSP) and Low Power. a. ( Alarm Point (LPAP). (0.5) l 1 b. What measured variables determine each specific setpoint? (0.75) i c. Describe the control function performed / changed by each setpoint l l (LPSP and LPAP)? (1.0) d. What are TWO (2) methods (for overriding RWM blocks) available for performing a Shutdown Margin check while RWM sequence is being enforced? (0.75) i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

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~ i \\ j 2t__EL6NI_SYSIEdi_LSail_8NQ_ELeUI: WIDE _GENEBig Page 20 l BEEE0N11BILIIIE1_11Dil I 1 QUESTION 3.19 (2.00) Match the list of power supplies in the right hand column (1 -3) to the specific 4160VAC bus (a-d) in the left hand column. i l a. 4160VAC Bus 1A 1. Normal: 4160 Bus 18 Alternate: 4160 Bus 1B b. 4160VAC Bus 1E 2. Normal:- Normal SS XFMR Alternate Startup SS XFMR c. 4160VAC Bus 10 3. Normal: 4160 Bus 1A Alternate 4160 Bus 18 l d. 4160VAV Bus 1G 4. Normal: 4160 Bus 1B Alternate: 4160 Bus 1A (2.0) l l QUESTION 3.20 (1.50) l 1 I 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 Exchangee Inlet and Outlet valves MO 12A and MO 65A open fully - RHR Heat Exchanger Bypass Valve MO 66A throttled to approximately mid-position - RHR A Minimum Flow Valve MO 16A closed - RHR Test Return to Suppression Pool Valve MO 39A open - RHR pump suction from suppression pool, MO 13A open - LPCI LOOP A outboard inj ect ion isolation valve MO 27A open - LPCI LOOP A inboard inj ect ion isolation valve MO 25A shut - RHR pump A running A small steam leak occurs which causes CSCS initiation on high drywell pressure. RPV level is being controlled adequately by the feedwater level control system. DESCRIBE the IMMEDIATE changes that occur in the above lineup as a result of the CSCS actuation signal. (1.5) l l l l l i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__ELeUI_HYSIEdi_L2H11_600_EL6UI: WIDE _QENEBIG Page 21 BESEQUSIBILIIIES_L1011 QUESTION 3.21 (1.00) Concerning"the Off Gas System, choose the correct statement below: a. Main steam line high radiation will cause trip of the SJAE inlet valves. b. Continued plant operation at power is possible, even if both Off-Ges dilution fans are lost. c. A burn-back in the Off-Gas system can cause the SJAE outlet valves to shut. d. Off-Ges dilution flow less t han 1100 scfm will start's time delay to close the'SJAE inlet valves in FIVE (5) minutes. QUESTION 3.22 (1.00) Concerning the Reector Water _ Cleanup (RWCU) System, Choose the correct l statement below: 1 I s. Return Isolation Valve M0-68 (outside containment) is NOT en automatic i containment isolation valve b. Automatic action to isolate a Filter-Demineralized (F/D) will occur on j high conductivity at the F/D outlet. c. The F/D holding pumps will auto start on high F/D dp. d. The RWCU has automatic protection for a vacuum condition that may occur due to complete system isolation and subsequent cooling. (1.0) l l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

y 2t__EleNI_SYSIEUS_f2all_680_EL691: WIRE _GENEB10 Page 22 BESE9NSIBILlIIES_f1Dil l 1 1 QUESTION 3.23 (2.00) For each of the following situations, determine whether or not the activity l can occur and provide the action necessary in order to perform the I activity. f 1 a. Refuel platform is over the vessel and in motion toward the fuel pool l with the fuel grapple loaded. All rods are inserted. Mode switch is selected from SHUTDOWN to STARTUP. Will the bridge continue to move? b. Refueling Platform near the core. The frame mounted hoist is loaded. One rod is at position 30. Can the load on the hoist be lowered into ) the vessel ? c. Refueling platform over the core. Mode switch in REFUEL. Grapple fully j lowered and unloaded. Can a control rod be withdrawn ? (2.0) 1 l l QUESTION 3.24 (1.00) Which of the following is NOT en input to the process computer from the i I l Transversing In-Core System (TIPS)? l l a. Detector position signal. b. Detector flux signal. j l l c. Detector speed signal. l d. Channel select switch position. (1.0) QUESTION 3.25 (3.00) { a. Explain how the CNS Equipment Clearance and Tagging procedure assures that a system is returned to a normal lineup after maintenance or l repair is complete. The explanation should include the title of any I personnel involved. (1.0) 1 l b. Why may independent verification required in "a" above be ignored for maintenance or repair performed during cold shutdown outage? (1.0) c. Who are 3 individuals that may sign the " Clearance Released By" section of the clearance when the j ob is complete? (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

Hz__EL6NI_SIEIEUS_L2fil_eSQ_ELeUI: WIDE _GENEBIQ Page 23 BESEQUSIBILIIIES_L1Dil QUESTION 3.26 (1.00) Which of the following requires an independent fire watch? a. A Category II door is open and obstructed with a security guard controlling access. b. A Category III door is open and unobstructed. c. A Category I door is open and obstructed. d. A Category I door is open and unobstructed. (1.0) I QUESTION 3.27 (1.00) l What documentation would identify the on shift Fire Brigade Leader? (1.0) l l QUESTION 3.28 (2.00) l l a. What two (2) conditions must an unlicensed individual meet before I he/she is permitted to manipulate the controls that directly affect l reactivity or power level of the reactor? (1.0) i l b. What requirement must a CNS control room 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 license once it has been " inactive" (at CNS) per 10 CFR 55? (0.5) QUESTION 3.29 (1.00) Any individual or group of individuals permitted _to enter High Radiation Areas must meet one of three monitoring criteria. State one of these three criteria. (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

r a v 2t__ELeNI_S1HIENS_L2a11_eND_EL6NI: WIDE _GENEBIQ Page 24 BESEQNSIBIL111ES_L1911 QUESTION 3.30 (1.00) If the assigned Shift Communicator cannot reach the NRC Operations Center via the Emergency Notification System (ENS) for initial notification, the preferred alternative is to_______ 1 l a. establish contact with the NRC Region IV office using the dedicated j line. l b. contact NRC Operations Center via commercial Telephone. c. contact the NRC Region IV office'on the Health Physics Network (HPN). d. contact the NRC Operations Center via the HPN. (1.0) QUESTION 3.31 (1.00) Choose the item below that best describes non-conformance with established facility policy or guidelines: a. A routine evolution is performed without the procedure in hand. b. During an emergency, a system is placed in service to mitigate the event before the procedure is referenced. c. During the execution of an Emergency Procedure, immediate actions are verified complete upon completion of followup action. d. Plant management notification requirements are ignored while shift supervisory personnel establish conservative conditions for en on going off-normal event. (1.0) (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********)

It__BEaQIQB_EBIURIELE1_LZ11_IBEBdQDYueb1GS Page 25 LZ11_8UQ_QQUEQUENIS_L1111_LEUUD8dEUIeLS_ Exed) I i ANSWER 1.01 ( 25.0) l GENERIC FUNDAMENTALS EXAMINATION ( REFERENCE i GENERIC FUNDAMENTALS EXAMINATION .l 1 1 1 i I ) i ) l 1 l l I' (***** END OF CATEGORY 1 *****) l l

21__EbEBGEUQ1_600_6EUQBdeL_EL6UI_EVQLUIIQUs Page 26 i L2Zil ANSWER 2.01 (3.00) l La. There is a table in the CAUTIONS section that specifies instrument accuracy level ranges at various DW temperatures. (1.0) b. The operator must determine the the system was auto initiated i inadvertently, (0.4) OR adequate core cooling exists. (0.4] (0.8) l c. To maintain adequate core cooling (by promoting injection). (0.3) To maintain Primary Containment Integrity (by minimizing release potential). (0.3) .I d. 1. RPV Level cannot be determined. 2. DW Temp. reaches RPV sat. temp. j 3. DW pressure cannot be maintained below the Primary Containment i design pressure. (any'2, 0.3 es. (0.6) l REFERENCE l 295031K305 295031K101 295031A201 ..(KA's) l ANSWER 2.02 (1.00) l A licensed operator may shutdown the reactor when in his j udgement, l continued operation could j eopardize station saf ety. (1.0) l REFERENCE CNS Proc. 2.0.1, P. 1 1 295006G011 ..(KA's) l l ANSWER 2.03 (2.00) l l a. "4" (1.0) ( b. "1" (1.0) l l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) I { j

1 2t__EdEBGEUQ1_eUQ_eBUQBdeL_ELoul_EVQLUIIQU$ Page 27 L2Zil P.EFERENCE CNS 2.4.9.1.10, P. 2 COR002-21, Pp. 16, 17 295005A206 295005K101 ..[KA's) -ANSWER 2.04 (1.00) "c" (1.0) REFERENCE CNS,E0P-1, Pp. 38 l l l 295037A207 ..(KA's) ( ANSWER 2.05 (2.00) - deenergize the scram solenoids ] - vent the scram air header J l - reset the scram, drain SDV, menually scram again l - individual scram switches to TEST increase CRD cooling water dp - insert using CRDH, normal insert l - vent CR0 overpiston volume - initiate ARI - emergency in 4"' - place RPS test trip logig switches to trip (Any 5, 0.4 es.] I REFERENCE f l 4 E0P-1, Pp. 41-46 295037A105 3.9/4.0 295037K307 ..(KA's) ANSWER 2.06 (0.50) i Via the RWCU system. [0.53 (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1 u

1 a 8 j ( l 2t__EdE80ENQX_eUQ_eBUQBdeL_ELeUI_EVQL911QN1 Page 28 j L2Zil j l i I REFERENCE CNS 5.2 14 E0P-1, P. 39 295037K213 ..(KA's) l ANSWER 2.07 (0.50) "b." (0.5) ] REFERENCE i CNS 2.4.1.3, P. 1 j i 295014G010 295014K207 ..(KA's) l I ANSWER 2.08 (1.00) "c." [1.0] 1 REFERENCE ) I CNS 2.4.2.2.1, P. 2 1 1 295001G010 ..(KA's) l k l l ANSWER 2.09 (1.00) "b." [1.0) REFERENCE CNS 2.4.9.3.5, P. 1 l 295002K203 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l l l

1 at__EdEBGENQ1_aND_eBUQBdaL_ELeUI_EVQLUI1QU$ Page 29 l L2Zil 1 l l l ANSWER 2.10 (2.50) l a. Dispatch an operator with sound powered phones (0.4) to instrument racks 25-5 and 25-6. [0.35] b. 1. Secure TG emergency lube oil pump. l 2. Secure Seal oil back up pump. l 3. Reduce NBPP loads to minimum. 4. Secure RFP emergency lube oil pumps l 5. Secure RRMG DC oil pumps. (any 4, 0.25 es.] l c. 1. Erroneous RPV level indication. 2. Degradation of safety related systems or components. [0.375 ea.] l REFERENCE l l CNS 5.2.5.1, Pp. 1-3 1 295003A103 295003G007 295003K101 ..(KA's) ANSWER 2.11 (2.00) a. 3. b. 4, 5. c. 1. [0.5 es.] REFERENCE CNS 2.4.6.9, CNS 2.4.6.10, CNS 2.4.6.11 295004A102 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

2t__EdEBGEUQ1_6UQ 6BUQBd6L_EL6UI_EYQL911QU$ Page 30 12Z11 ANSWER 2.12 (2.50) a. HPCI RCIC ADS RHR REC [Any 4, 0.25 es.] b. RUN [0.5) c. 1. Check that scram discharge volume drain valves are closed. [0.5) 2. Check all CRD HOU scram valves open. [0.5) REFERENCE CNS 5.2.1, Pp. 1-17 295000A101 295016A107 ..(KA's) ANSWER 2.13 (1.00) l "b." [1.0) i I REFERENCE i CNS 5.2.4, P. 1 i 295018G010 ..(KA's) ANSWER 2.14 (1.00) "a." REFERENCE CNS 2.4.1.1.4, P. 2 295022K101 ..(KA's) l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l l l

2___EdEBQENCY_eUQ_6BNQBdeL_ELeNI_EYQLUIIQUE Page 31-L2Z13 ANSWER 2.15 (1.50) The license limit for suppression pool temperature is 95 degrees which will likely be exceeded during the test. [0.5) However the Tech. Spec's allow exceeding this limit by 10 degrees for necessary testing, [0.5.1 (as long as temperature is 95 o F. or lower within.24 hours). Therefore operation may continue. [0.5) REFERENCE Tech. Spec. 3.7.A.1.c &d 295026G008 ..(KA's) ANSWER 2.16 (1.50) a. Unequal expansion of the refueling bellows flange. [0.5) b. 1. Vent and purge the DW with N2. [0.5) 2. Initiate reactor cooldown. [0.5) l REFERENCE CNS 2.4.8.4.2, Pp. 1, 2 295028A104 295028K102 ..(KA's) ANSWER 2.17 (1.00) l Secondary containment isolated. l SGT started. l Primary containment vent and purge valves shut l REC critical loop operation initiated. (Any 3, 0.33 es.) REFERENCE l l CNS 5.3.5, P.1 l l 295023K303 295023K203 ..(KA's) l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

1 s i i l 2t__EdEBGEUQ1_eUQ_oBUQBdeL_ELeUI_EV9L91199S Page 32. 12Z1.1 i ANSWER 2.18 (1.00) q "d." q 1 REFERENCE. CNS 5.3.5, P. 2 295023G011 ..(KA's) ANSWER 2.19 (1.00) l "b." i REFERENCE CNS 2.4.2.4.1, P. 2 295021A207 ..(KA's) L f I l l (***** END OF CATEGORY 2 *****) l

i 1 2t__EL6NI_11 HIED 1_f2a11_eND_EL8NI: WIRE _GENEBIQ Page 33 BESEQUSIBILIIlliS_L1012 4 1 l ANSWER 3,01 (1.00) "c." l REFERENCE I COR002-04, Pp. 26, 27 LO 12.f I 201001K107 ..(KA's) l l ANSWER 3.02 (1.00) 1 l ) L "d" [1.0) l l \\ l REFERENCE I COR002-20, P. 13 LO 8.b, 5.d 1 l l l 201002A303 ..(KA's) l I i ANSWER 3.03 (1.00) 1. Timer malfunction. ( 2. The Timer Malfunction Select Block Test Switch in the " Test" position. f i 3. RPIS INOP. (Any 2, 0.5 ea.] 1 i REFERENCE COR002-20, P. 13, 14 LO 7 201002A104 ..(KA's) ANSWER 3.04 (2.00) a. "A" pump speeds up to 45% [0.25] which is the low setting on the dual speed demand-limiter. [0.25] The "B" pump is not affected. [0.5] b. No change until RV level is at 27.5", [0.5] then both pumps will runback to 45% [0.25] due to single limiters. [0.25] (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

) aa. _ _ E L e UI _ S Y S I E U S _ L S a il.. e U Q _ E L o u l:W10 E _9 E U E B 1 Q Page 34 BESEQUSIBILIIIES_L1011 I l REFERENCE i Facility Test Bank, QNUM COR002_22 (26) 1 202002K407 ..(KA's) 1 ANSWER 3.05 (1.00) "c" [1.0) ] REFERENCE i COR002-11, Pp. 28-33 LO 4 l 206000K403 206000K407 ..(KA's) i l ANSWER 3.06 (2.50) a. ADS inhibit, ADS Timer reset, or stop all LP CSCS pumps..[0.25 es.) b. Ensure level is increasing due to inj ect ion. [0.5) c. Place " ADS INHIBIT SWITCHES" to " INHIBIT". [0.5) l d. Any Safety / Relief valve has opened (0.25] AND [0.25) a HP Reactor Scram signal is present. [0.25] REFERENCE COR002-16, Pp. 13-15, L. O. Obj. 3, 6 218000K501 218000K401 218000A206 ..(KA's) ANSWER 3.07 (1.003 "c." REFERENCE l COR002-03, Pp. 26-32 l l 223002K607 ..(KA's) l l t 1 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) L

at__ELoNI_SYSIEUS_L2011_6UQ_EL6UI: WIDE _GENEBig Page 35 BESEQUSIBILIIIES_11Dil ANSWER 3.08 (1.00) "b" [1.0) REFERENCE COR002-32, Pp. 25-28, LO Sb. 259002K302 ..(KA's) ANSWER 3.09 (1.00) b (1.0) REFERENCE COR002-15, Nuclear Boiler Instrumentation, Figure 1, LO. 3 216000K122 ..(KA's) ANSWER 3.10 (2.50) a. 1. Affected train heaters trip. 2. Other fan will start (if in standby). [0.5 es.] b. 1. Malfunctioning heaters. 2. Decay of fission products. 3. Combustion of charcoal. [0.33 ea.) c. Offferential pressure across the train. [0.5) REFERENCE COR002-28, Pp. 15, 16 Facility Test Bank, COR002-28, #8 261000A301 261000A408 261000A101 ..(KA's) l 4 i f (***** CATEGORY 3 CONTINUED'ON NEXT PAGE *****)' 1

q ~ 1 i i 2t__ELoNI_SYSI'EdS_12B11_oND_ELoNI: WIDE _QENEBIQ Page 36 l BESEQUSIBILIIIES_11011 j i 4 1 ANSWER 3.11 (3.00) a. 1. Emergency shutdown button on local control panel. 2. Emergency shutdown button on west side of the engine. [0.5 es] b. Function: Isolate / bypass the control cabling between the EDG and the control room. [0.5]

Purpose:

Protect the plant safe shutdown capability in-the event of a fire in the cable spreading room. [0.5] l I c. Incomplete. sequence trip. [0.3] Inserted,if EDG speed has not reached i 280 RPM [0.35] after cranking for 20 seconds. [0.35) REFERENCE i i COR002-08, Pp. 19, 40, 41 LO 3, 5,d 1 264000K402 264000K407 264000G014 ..(KA's) I i ANSWER 3.12 (1.00) "a" I REFERENCE l 1 COR001-10, Pp. 14-17 215004K501 215004K201 ..(KA's) 1 ANSWER 3.13 (1.00) l l "c" [1.0] l l REFERENCE COR001-10, P.17 l 215003K201 ..(KA's) l I (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

4 2t__ELoNI_SYSIEUS_L2H11_oND_EL8UI: WIDE _GEUEBIQ Page 37 i BESEQUSIBILIIIES_L1012 ANSWER 3.14 (2.00) a. Six b. B, D, &F c. RPS 120 VAC d. 14 or 17 c. Flow-biased trip reference f. (0.66W + 42)% power 9 (0.66W + 543% power [0.25 es.] h. 11 REFERENCE Facility Test Bank, Qnum COR002_01, # 12 l l 215005K603 215005K202 215005K116 215005K103 ..(KA's) l ANSWER 3.15 (2.50) 1 a. The purpose is to limit control rod motion to provide protection (limit peak fuel enthalpy ) for a postulated rod drop accident.[0.5) b. The system is enabled between 100% rod density [0.25]and 20% power [0.25) as measured by main turbine first stage shell pressure.[0.25) c. No provision to bypass. [0.5) d. To provide a simulated rod position signal [0.25) if: 1. An indicator har failed. 2. A rod is stuck. 3. Needed for surveillance. [Any 2, 0.25 es.) REFERENCE COR002-25, Pp. 5, 6, 9 LO 1, 5, 8 201004A201 201004K404 201004K501 ..(KA's) ANSWER 3.16 (1.00) d (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

1 o 2,.__EL6HI_SYSIEMS_L2B11_800_ELeUI: WIDE _QENEBIQ Page 38 BESEQUSIBILIIIES_1101) REFERENCE COR002-14, P.9, LO. 2 239001K404 ..(KA's) 1 I l ANSWER 3.17 (2.00) I a. 1 l b. 4 c. 1 d. 1 e. 2, 3 (6 at 0.33 each) REFERENCE COR001-18, Pp. 9-12, LO. 4 272000K402 3.7/4.1 272000A206 2.8/2.9 272000K402 272000A206 ..(KA's) ANSWER 3.18 (3.00) a. LPSP 20% LPAP 35% [0.25 es.] b. LPSP: Total Steam Flow and Total Feed Flow [0.5) LPAP: Total Steam Flow [0.25] c. LPSP: Below the LPSP, the RWM sequence is enforced imposing restrictions on rod movements with regard to rod pattern (0.5]. LPAP: Above the LPAP, The RWM alarms and error displays are discontinued. [0.5] d. 1. Reprogram the RWM. [0.25] 2. Bypass the RWM. [0.5] REFERENCE I COR002-26, Pp. .10, 23, 29 l 201006A401 201006K104 ..(KA's) ] (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

2t__ELeUI_SYSIEd1_L2011_680_EL88I: WIDE _QEUEBlQ Page 39 BESEQUSIBILIIIES_L1011 ANSWER 3.19 (2.00) a. 2. b. 3. j c. 2. d. 1. (0.5 es.] l REFERENCE COR001-01, Figure 1, LO 4.a 262001K406 ..(KA's) i ANSWER 3.20 (1.50) - HX BPV MO 66 opens fully (0.5) - RHR Test Return M0 39A shuts (0,5) - Minimum Flow Valve MO 16A opens (0.5) REFERENCE COR002-23, Pp 39-42 LO 3.A, 3.8 219000G015 219000A214 ..(KA's) ANSWER 3.21 (1~.00) "b" REFERENCE COR00-16, Pp. 38-34, LO 6 271000K408 271000A202 271000A206 ..(KA's) ANSWER 3.22 (1.00) - "a" l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) {

i 4 .t i 2t__ELoNI_SISIEUS_L2B11_800_EL6NI: WIDE _GENEBIG Page 40 BESE9NSIBILIIIES_L1Dil REFERENCE COR001-20, Pp. 16-25,. LO 4, 6 204000A304 ..(KA's) ANSWER 3.23 (2.00) a. Yes [0.5] b. No. [0.53 Must insert the rod. [0.25] c. No [0.53 Must raise the grapple fully. [0.25] REFERENCE COR001-21, Pp. 46, 47 234000A302 234000K502 ..(KA's) l ANSWER 3.24 (1.00) l "c" REFERENCE COR002-31, P. 22 LO 8.B 1 215000K102 ..(KA's) ANSWER 3.25 (3.00) a. The " Normal Position" section of the clearance will be filled out (0.5] by the (Shift Supervisor or the) Control Room Operator, [0.5] detailing the required position of valves, switches, etc. [0.5] 1 b. For this condition the lineup will be returned to normal by the system i valve lineup prior to startup. [1.0] l c. Person responsible for the j ob, Person signing the " Clearance Issued" section, Supervisor of the person signing the " Clearance Issued" section, or person completing the repair. [any 3, 0.33 ea.] I (NOTE: SS may sign for any of the above via TELCON) ( (***** CATEGORY 3 CONTINUED ON NEXT'PAGE *****)

P 1 l '2t__EL68I_SYSIEdS_L20il_680_EL6Ul: WIDE _GENEBIC Page 41 l BESEQUSIBILIIIES_L1012 REFERENCE CNS Proc. 0.9, Pp. 6, 7, 294001K102 ..(KA's) l ANSWER 3.26 (1.00) "b" [1.0) REFERENCE CNS Proc. 0.16, P. 1 l 294001K116 ..(KA's) l l l ANSWER 3.27 (1.00) Control Room Log. (1.0) REFERENCE 'i l l CNS Proc. 0.23, P. 2 l 294001K116 ..(KA's) ANSWER 3 28 (2.00) Under the direct supervision of a licensed individual (0.5) e. - Enrolled in approved operator licensing training class (0,5) 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 reactivation is sought (0.5]. s REFERENCE CNS 2.0.3, P. 3 10 CFR 55.53(e) and (f)(2) 294001A103 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

1 21__EL6UI_SISIEUS_L2B11.6UD_EbeUI: WIDE _QEUEBI9 Page 42 BESEQUSIBIL111ES_L1911 I ANSWER 3.29 (1.00) i A radiation monitoring device which continuously indicates the dose rate in the area. l A dose integrating monitor which is set to alarm when a preset dose is' I received. An individual qualified in radiation protection procedures, with a i dose rate monitoring device. ( 1 of 3 at 1.0) 1 REFERENCE i CNS Proc. 9.1.1.2, P. 5 294001K103 ..(KA's) i i ANSWER 3.30 (1.00) i "b" REFERENCE CNS Proc. 2.0.5, P. 1. ] 294001A116 ..(KA's) ANSWER 3.31 (1.00) "c" j REFERENCE l 8 l CNS Proc 2.0.1, Pp. 1, 2 i 294001A102 ..(KA's) I (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********) f I a

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 4 5 FACILITY: QQgogc_S12112D___________ REACTOR TYPE: EMB-GE4___.,______________ i DATE ADMINISTERED: H24Q2/2D_________________ j 1 INSIBUQIIQUS_IQ_Q6UDIQeIEt 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 at least 70% in each category and a final grade of at least 90%. Examination papers will be picked up six (6) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY __VeLUE_ _IQI6L ___SQQBE___ _V8LUE__ ______________QoIEQQBY_____________ _24ADQ__ _26100 ________ 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) _2210D__ _22 00 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) _d210D__ _d2200 ________ 6. PLANT SYSTEMS (30%) AND l PLANT-WIDE GENERIC l RESPONSIBI.ITIES (13%) 1 _1DQtQ__ TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received sid. I Candidate's Signature

1 1 l L.__BE6910B_EBINQ1ELES_LZ11_IBEBd9DINedIGS Page 4 I LZil_ oN D _ G 0 U E Q U E NIS _ L1Dil _ L E!J U D ad E NIo L1_ E 88dl I i l I l QUESTION 4.01 ( 24.0) GENERIC FUNDAMENTALS EXAMINATION l i l l { i i i i l 1 i 4 l l 1 l l I i l l l 1 f. l l l (***** END OF CATEGORY 4 *****)

I St__EdEBSEUQ1_8HD_6BUQBd8L_ELoNI_EVOLUIIQUE Page 5 12212 1 I i l QUESTION 5.01 (1.00) On a loss of all Reactor Equipment Cooling at high power, which action below is NOT taken immediately? a. Scram from existing power. l ) b. Isolate RWCU c. Scram from minimum RR flow conditions. d. Trip both RR pumps from minimum speed. (1.0) i i l QUESTION 5.02 (1.00) l l l According to Operations Department Policy, CNS 2.04 1, when is any licensed I operator authorized to shutdown the reactor? (1.0) l l l l l QUESTION 5.03 (2.50) l l a. Following a manual reactor scram with Group 2, 3, and 6 isolations, the operator judges the cooldown rate to be excessive. Suppression pool temperature is normal and steady with reactor pressure at 800 psig. What are TWO (2) separate actions / methods the operator may use l to mitigate the excessive cooldown rate? (1.0) b. What is the potential problem with obtaining only a half scram reset after a full scram? (0.5) c. Following a reactor scram from high power, it is noted that the RR pumps are tripped (vice 20% speed). What are TWO (2) conclusions that may be drawn regarding conditions that possibly existed before or during the scram (1.0) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

i u s 51__EdEBGEUQY_eUD_eEUQBdeL_ELeUI_EVQLUIIQUS Page 6 12211 QUESTION 5.04 (3.00) ] a. How do the Emergency Operating Procedures (EOP's) provide the operator with guidance for assessing Reactor Pressure Vessel (RPV) LEVEL during elevated temperature conditions in the Drywell? (1.0) b. What are the TWO (2) conditions, either one of which must be met, that E0P-1, RC/L specifies for the operator to ascertair prior to placing in MANUAL or securing any Core Standby Cooling System (CSCS)? (0.8) c. What are 2 purposes of " Emergency Depressurization"? (0.6) d. WF9t are 2 of the 3 conditions that would require RPV flooding? (0.6) QUESTION 5.05 (1.00) l A scram condition exists (MSIVs shut) with the reactor at power. The j L reactor did not shutdown. Core cooling is adequate. Which concern below l l is being most severely challenged in this condition? (1.0) l j a. fuel integrity l b. RPV integrity 1 c. containment integrity l d. injection system operability l QUESTION 5.06 (2.00) 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. (2.0) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) L-

) i St__EdEBGEUQ1_600.6BUQBdeL_ELoUI_EVQLUIIQU3' Page 7 j L22&l l l QUESTION 5.07 (0.50) l In accoidance with CNS 2.4.1.3, " Unexplained Increase in Reactor Power" f what immediate action is required if all indications are that power is increasing for no apparent reason? i I a. Attempt to reduce power with rod insertion. f l b. Attempt to reduce power with RR flow. ) c. Manually scram. d. Initiate emergency shutdown. l l QUESTION 5.08 (2.50) During a complete loss of AC power (station blackout), in accordance with CNS 5.2.5.1, " Loss of All Site AC Power Station Blackout": a. What can be done to supplement the available control room instrumentation? Specify any equipment needed and locution (s) (0.75) b. State Four (4) actions that should be taken to conserve the available DC power during an extended power loss. (1.0) c. What are the TWO (2) maj or concerns about the elevated Drywell temperatures that may occur. (0.75) QUESTION 5.09 (2.50) The control room was evacuated earlier. The reactor is presently shutdown q and has been cooled down using HPCI. Torus cooling is in progress and the j control room is now habitable. i i a. What are FOUR (4) systems that must have their isoletion switches returned to NORMAL? (1.0) b. Upon control room re-entry, in what position will the Reactor Mode switch be found? (0.5) j c. After control room evacuation, wnat TWO (2) actions were taken by the by the designated Reactor Building Operator to VERIFY that the reactor had been scrammed? (1.0) l l 1 -(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l __ _ _ L

l Et__EUEBQEUQ1_eUQ_6BUQBdeL_EL6UI_EVQLV11QUS Page ,8 L22&l QUESTION 5.10 (1.50) During-the late summer with suppression pool temperature at 94 1/2 degrees F., it is necessary to perform the quarterly flow tests for the RCIC and HPCI pumps, as the tests were overlooked during recovery from a recent outage. The plant is at 85% power and successful completion of pump tests is THREE (3) hours away from the maximum extended deadline for operability verification. State what the problem is and how continued operation may or may not be possible. (1.5) l QUESTION 5.11 (1.00) ) During refueling, an incident occurs causing RMP-RM-452A & B. Reactor Bldg. Ventilation Exhaust Monitors to reach the high-high setpoint. What are 4 THREE (3) automatic actions that must be verified? (1.0) ) l i I l QUESTION 5.12 (1.00) l According to the Emergency procedure for high refueling floor radiation, ] CNS 5.3.5, which statement below is correct? j a. It is not necessary to enter the E0P's during a refueling accident. b. EOP's should be entered if the fuel pool area monitor exceeds 5 s mrem /hr. i c. E0P's should be entered if the fuel pool level decreases. I d. E0P's should be entered if RB Ventilation Exhaust radiation exceeds 10 mrem /hr. (1.0) l l I I l l l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE **** ) I

1 l 5t__EUEBQENCY_eNQ_eENQBU6L_EL6NI_EVQLUIIQNS Page 9 L3211 l l QUESTION 5.13 (1.00) The preferred method for determination of an offsite release rate due to post accident containment venting would be to use input data from: a. Elevatod Release Point (ERP) collected sample counted and analyzed in the Radiochemistry Lab. b. ERP Noble Gas Effluent Monitor, c. Site Boundary radiation readings, d. In-Containment Radiation Monitors. (1.0) QUESTION 5.14 (2.00) The automatic.ac t i o ns listed for a main turbine and generator trip per CNS 2.4.9.1.10 " Turbine Trip", include reactor scrams. For parts "a" and'"b" i l below select the answer from items 1 - 4 that will most likely initiate the reactor scram. l l a. The turbine trips from 24% reactor power l 1. Main terbine stop valve position 1 2. Turbine control valve position i 3. Reactor vessel level 4. APRM (1.0) b. The turbine trips from 79% reactor power 1 l 1. Main turbine stop valve position l 2. Turbine control valve position l l 3. Reactor vessel level l 4. APRM (1.0) l l i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

~ ,,i 1 Ez__EMEBGENC1_6ND_oBN9Bb6L_ELeNI_EV9LUIIQNS .Page 10 l 12211 .) i QUESTION 5.15 (1.00) The reactor is operating at 100% when one recirculation pump trips due.to en electrical fault. What is required of the operator if.the core is operating in the region of instability and 9% peak to peak flux oscillations are occurring? a. Shut the affected loop RR pump discharge valve. b. Initiate manual reactor scram. I c. Insert rods and/or increase RR flow. j d. Commence CNS 2.1.5, " Emergency Shutdown from Power". (1.0 1 1 I QUESTION 5.16 (1.00) l 1 Which of the following is NOT considered Immediate Operator' Action for l I loss of all Reactor Equipment Cooling (REC) water? l ( i a Isolate the RWCU system. l b. Start Service Water Backup switchover. c. Run both RR pumps to minimum speed. I d. Scram the reactor. (1.0) J l QUESTION 5.17 (3.00) During a sustained loss of REC due to piping failure, the system is being shifted critical loop operation with Service water bsckup: a. What are THREE (3) maj or systems / components that must be manually secured by the operator due to loss of cooling? (1.5) b. How will heat be removed from the primary containment? (0.5) c. What should the operators first and second choice be, for maintaining RPV inventory? (1.0) I i I (***** CATEGORY 5 CONTINUED ON.NEXT PAGE *****) l;

___s, St__EdEBGEUGl_oNQ_6BUQBdeL_EL691_EVOLUIIQUE Page 11 12211 l

l J QUESTION 5.18 (1.50) l During the performance of E0P-3, Secondary Containment Control, the l operator is directed to attempt isolation of all primary systems J discharging into the secondary containment. Systems required to perform THREE (3) specific tasks are exempted from this_ requirement. What are the THREE'(3) tasks? (1.5) ] l QUESTION 5.19 (1.00) I Which of the following is not an entry condition for E0P-3, Secondary j Containment Control? l a. Secondary Containment area radiation above maximum normal. l b. Secondary Containment Exhaust plenum radiation greater than 10 mr/hr. l L c. Secondary Containment differential pressure less than 0 inches. l [ d. Secondary Containment area temperature above maximum normal. (1.0) l i i l QUESTION 5.20 (1.00) Failure of both CRD pumps would be of the most concern during: (Chooseithe correct answer) J k a. plant startup and heatup. I b. Turbine Generator synchronization to grid. i c. beginning of life operation at 75% power ( d. end of life operation at maximum power for stretchout or coastdown conditions. (1.0) i { (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l

Ez__EUEBQEURY_eUQ_eBUQBdeL_ELeUI_EVQLul1003 Page 12 f2213 i l QUESTION 5.21 (1.50) A loss of all Drywell (DW) coolers has caused a reactor scram due to high drywell pressure. DW pressure is still increasing. l a. Considering only DW temperature, what is the greatest concern? (0.5) b. What are TWO (2) specific actions that can be taken to mitigate the increasing DW pressure without spraying? (1.0) i 1 QUESTION 5.22 (0.50) 4 For the current format of the E0P's why are cautions listed in the E0P/C section of the E0P's and within the body of the procedures? I l l l 1 1 i i l 1 l l l l (***** END OF CATEGORY 5 *****) i.

61__EL681_S111Edi_L2011_eUD_ELoul: WIDE _9EUEBIC Page 13 BESEQUSIBILIllE1_L1211 i I l QUESTION 6.01 (2.00) For each of the situations below, describe how and why the recirculation j flow control system will respond. Also state which component of the control system will be contro111no RR pump speed. Assume no operator action. l a. 28% power, recire. pumps at minimum speed with both M/A transfer l stations in manual. Recirc. pump "A" M/A transfer station is switched I to "AUT0" (1.0) { b. 75% power, recirc. flow control in master manual when ONE (1) reactor feedwater pump trips. (1.0) j l QUESTION 6.02 (1.00) During an event a High Drywell Pressure greater than TWO (2) psig and Reactor Vessel Low Water Level result in automatic initiation of the High Pressure Coolant Injection System (HPCI). Reactor water level is restored j and continues to increase until the HPCI turbine automatically trips on a high reactor water level. High Drywell Pressure greater than +2 psig still remains.. CHOOSE which of the following is required for auto restart of the HPCI System. a. Reactor water level drops below the high reactor water level setpoint. l b. Reactor water level drops below a reset setpoint a few inches lower than the high reactor water level setpoint. c. Reactor water level drops below the low reactor water level setpoint. d. The reactor operator depresses the Auto Isolation Reset button. (1.0) l l l l l j (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

7 l 1 1 ht__ELeUI_1XEIEUS_L20il_eUQ_ELeUI: WIDE _EEUEBIQ Page 14 BEEEQUElBILIIIEE_fl2il l l QUESTION 6.03 (1.00) Choose the statement below that is a correct response of the Reactor Core Isolation Cooling (RCIC) system. a. With the ROIC operating normally, a low level occurs in the Emergency Condensate Storage Tenk (ECST). The pump suction from the ECST closes i and then suction from the suppression chamber opens. l t b. The RCIC system is operating with reactor level increasing. When the high level setpoint is reached, the steam supply inboard and outboard I isolation valves close, c. The RCIC system is operating in the test mode.using the flow controller set at 400 GPM and test line discharge fully open. If the l suppression pool suction valve is inadvertently opened, turbine speed I i l may decrease. l d. The RCIC system is operating in the test mode', discharging to the ECST. A valid low reactor level initiation signal is received. The test circuitry is bypassed, the test bypass to ECST closes, and flow controller controls flow automatically. (1.0) QUESTION 6.04 (2.50) I a. What are 3 different controls available to the control room operator to retard or prevent the automatic operation of ADS Safety / Relief ( valves? (0.75) { l b. What condition (s) should be verified before using any of these i features or controls? C0.5) l c. What can the control room operator do to DEACTIVATE automatic operation of the ADS system? (0.5) d. What conditions will cause automatic lowering of the setpoint of the TWO (2) lowest set relief valves? (0.75) l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

e hi__EL8UI_SYSIEUS_L2011_8UR_EL8BI: WIDE _SEUEBIQ Page 15 BEEEQUllBILIIIES_fl2il QUESTION 6.05 (1.00) Choose the correct statement below concerning the Primary Containment Isolation System (PCIS): a. A loss of power to a containment isolation channel will not cause the affected channel to trip. b. All motor operated isolation valves are DC powered. c. A PCIS channel trip due to a loss of a 120VAC RPS bus will NOT initiate all group isolations. d. All Group Isolation bypass functions are initiated by the position of the Reactor Mode Selector Switch. QUESTION 6.06 (2.00) State the conditions necessary (interlocks) for the operator to attain " Spray Valve Control" for containment spraying. (2.0) l QUESTION 6.07 (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 occur as a result of this failure? Assume no operator action. (1.0) a. Feedwater flow increases and the reactor trips on high reactor level. b. Feedwater flow decreases and the reactor trips on low reactor vessel level. c. The reactor feedwater pump receives a lockout and vessel level is maintained near initial setpoint. d. A generated flow error signal will a maintain higher.RPV level via the Vessel Master Controller. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

e e j l bz__ELeUI_S11IEUS_L2Hil_eUQ_ELeNI: WIDE _GENEBIQ Page 16 BESEQN21@lLillE!_ll21] QUESTION 6.08 (1.00) Select the answer below that best indicates how far above the top of the active fuel water level is maintained in automatic assuming normal system nperation. (1.0) a. 213" I b. 198" I c. 172" i d. 119" l QUESTION 6.09 (2.50) a. What are TWO (2) automatic actions that may occur within the Standby Gas Treatment (SGT) system if a filter train low flow alarm is actuated after receiving an initiotion signal? (1.0) b. What are THREE (3) viable reasons for excessive t'r temperature of the airstream leaving an SGT train? (1,0) c. What system parameter is measured and controlled to automatically control train flow rate? (0.5) QUESTION 6.10 (3.00) e. It hacomes necessary to stop an Emergency Diesel Generator (EDG) that is running with an auto initiation signal present. What are TWO (2) methods of stopping the EDG? (1.0) b. What is the FUNCTION and ULTIMATE PURPOSE of the NORMAL-ISOLATE control switches on the diesel engine panels? (1.0) c. Provide the name and explain the operation of the device, mechanism, or methodology that functions to preserve starting air pressure in the event the EDG will not auto start on an initiation signal. Provide sensed parameters and setpoints. (1.0) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

6t__EL6UI..S1SIEUS_L2011_eUQ_EL601: WIRE _QEUEBIQ Page 17 BESEQU21RILIIIES_L1211 QUESTION 6.11 (1.00) Comparing the TWO (2) different types of detectors used in the Startup Range Neutron Monitoring (SRM) system, choose the item below which is correct. a. Both detector chambers use the same inert gas, b. The fission chamber operates at a higher voltage, c. Only the proportional counter has active coating on the inside of the outer electrode. d. Both detector chambers use the same active coating. (1.0) QUESTION 6.12 (1.00) Backup Scram valves provide a redundant means of venting air from the scram pilot valves and scram discharge valves. These backup valves are: (Choose the correct answer) a. Normally energized and will de-energize upon a RPS Scram signal b. Aligned such that two valves in series, one from each RPS trip l channel, must actuate to vent the scram air header. c.- Designed such that both RPS channels must trip in order for any one of the valves to actuate. d. Powered from the RPS Buses A and B. l l l 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) s

1 1 3 k___EL6UI_SISIEbS_L2011_6NQ_EL6UI:WlgE_QEugBig Page 18 BESEQU21BILIIIE2_L1211 QUESTION 6.13 (1.00) Select the statement below which is correct: a. A " Rod Drift" alarm occurs when a rod passes an even numbered reed switch position. b. a " Rod Drift" alarm occurs when a rod leaves an odd numbered reed switch position. c. A drift alarm is reset by placing the alarm test switch in the " Test" position. d. A drift alarm can be reset only when the rod in an even numbered reed switch position. (1.0) QUESTION 6.14 (1.00) Concerning the Reactor Water Cleanup (RWCU) System, Choose the correct statement below. l a. Return Isolation Valve MO-68 (outside containment) is NOT an automatic i containment isolation valve f I b. Automatic action to isolate a Filter-Demineralized (F/D) will occur on high conductivity at the F/D outlet. f c. The F/D holding pumps will auto start on'high F/D dp. 1 d. The RWCU has automatic protection for a vacuum condition that may j occur due to complete system isolation and subsequent cooling. (1.0) j l QUESTION 6.15 (1.00) An Intermediate Range Monitoring (IRM) system detector operates with an approximate voltage of (Choose the correct answer) a. 24VDC b. 48 VDC c. 100VDC d. 300VDC (1.0) l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

l l 6t__ELeUI_SISIEMS_L2011_eUQ_ELeUI: WIDE _GENEBIQ Page 19 BESEQUSIBILIIIES_fl2il l l l QUESTION 6.16 (1.00) Concerning the Off Gas System, choose the correct statement'below; a. Main steam line high radiation will cause trip of the SJAE inlet valves. b. Continued plant operation et power is possible, even if both Off-Gas l dilution fans are lost. c. A burn-back in the Off-Gas system can cause the SJAE outlet valves to shut. d. Off-Ges dilution flow less than 1100 sofm.will start a time delay to j close the SJAE inlet valves in FIVE (5) minutes. j l 1 l QUESTION 6.17 (2.00) For each combination of Main Steam Line Radiation Monitor Trips (a-e), select the appropriate automatic action (s) (1 - 4). a. Channel A High, Channel B High-High 1. Half-scram j l b. Channel A High, Channel D High 2. Scram i c. Channel B Downscale, Channel C Inop 3. Mechanical Vacuum Pump (s) trip d. Channel A Inop, Channel C High-High 4. No Automatic Actions e. Channel C Inop, Channel 0 High-High (2.0) I i QUESTION 6.18 (1.50) j i Describe the general response (simple phrase) of the control room j ventilation system due to: l o. Radiation b. Smoke c. Certain Toxic gas (ses) (1.0) l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) J

4 ht__EL6HI;SXSIEUS_L2011 600_EleUI: WIRE _GENEB1Q Page 20 BESEDNSIRILIIIES_11111 1 \\ QUESTION 6.19 (1.00) Which of the following is NOT an input to the process computer from the i Transversing In-Core System (TIPS)? I a. Detector position signal. I b. Detector flux signal. c. Detector speed signal. d. Channel' select switch position. (1.0) QUESTION 6.20 (2.00) a. What Control Rod Drive Mechanism (CRDM) component supplies the input to the rod position information system? (0.5) b. For what type of accident.does the control rod velocity limiter l provide protection against? (0.5) l c. When a control rod is to be withdrawn, why is it given a short duration insert signal, and then the withdraw signal? (1.0) l QUESTION 6.21 (1.50) a. Describe the TWO (2) specific interlocks that become effective when the portable jib crane is correctly installed on the refueling service platform. (1.0) b. What can be deduced about a grappled load if the Refueling Bridge Control Console indicating lights for " HOIST LOADED" and " SLACK CABLE" are NOT illuminated? Provide specific values or range. (0.5) l l l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l

61__EL6UI_SXSIEUS_L2011_6BD_EL6UI: WIDE _SENEBIQ Page 21 BESEQUSIBILII1ES_L1211 1 QUESTION 6.22 (3.00) i ) a. Explain how the CNS Equipment Clearance and Tagging procedure assures 1 l that a system is returned to a normal lineup after maintenance or repair is complete. The explanation should include the title of any l personnel involved. (1.0) I l l b. Why may independent verification required in "a" above be ignored for j maintenance or repair performed during cold shutdown outage? (1.0) l l c. Who are 3 individuals that may sign the " Clearance Released By" l section of the clearance when the job is complete? (1.0) i I f QUESTION 6.23 (1.00) l Which of the following requires an independent fire watch? I a. A Category II door is open and obstructed with a security guard I f controlling access. l l b. A Category III door is open and unobstructed. I c. A Category I door is open and obstructed. d. A Category I door is open and unobstructed. (1.0) QUESTION 6.24 (2,00) 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) b. What requirement must a CNS control room reactor operator licensee meet to maintain the license in an " active" status (in addition to maintaining a license in en " inactive" status) per 10 CFR 557 (0,5) c. What action must be taken to re-activate a license once it has been " inactive" (at CNS) per 10 CFR 55? (0,5) (***** CATEGORY 6 CONTINUED ON NEXf PAGE *****)

-v J f i ht__ELeUI_SYSIEUS_L2011.eUQ_ELeUI:W10E_GENEB1Q Page 22 BESEQUSIBILIIIES_Llatl QUESTION 6.25 (2.00) l L' Any individual or group of individuals permitted to enter e High Radiation i Area must meet one of three monitoring criteria. State TWO (2)oof these i i three criteria. (2.0) ,1 QUESTION 6.26 (1.00) If the assigned Shift Communicator cannot reach the NRC Operations Center via the Emergency Notification System (ENS) for initial notification, the preferred alternative is to_______ a. establish contact with the NRC Region IV office using the dedicated line. b. contact 'AC Operations Center via commercial Telephone. c. contact the NRC Region IV office on the Health Physics Network (HPN). d. contact the NRC Operations Center via the HPN. (1.0) QUESTION 6.27 (1.00) Choose the item below that best describes non-conformance with established facility policy or guidelines: a. A routine evolution is performed without the procedure in hand, b. During an emergency, a system is placed in service to mitigate the event before the procedure is referenced. c. During the execution of an Emergency Procedure, immediate actions are verified complete upon completion of followup action. I d. Plant management notification requirements are ignored while shift -4 l supervisory personnel establish conservative conditions for en on going off-normal event. (1.0) j i 1 1 l l l l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)-

l. t l-L 61__EL6HI_SYSIEMS_12011_6UD_EL6UI: WIDE _QEUEBIQ Page 23 l BESERNSIBILIIIES_Ll2tl J l l l QUESTION 6.28 (2.00) a. What are the FOUR (4) basic modules that depict the major types of l events in EPIP 5.7.1, Emergency classifications? (1.0) l 1 b. While escorting an unbadged NRC examiner within the protected' area, a license applicant hears the signal and announcement requiring l personnel. assembly and accountability. What action should be taken by .] the escort? (O'5) j \\ c. If the Technical Support Center (TSC) becomes uninhabitable, where l should it's function be transferred to? (0.5) l I i l I l 1 1 l l 1 l (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********)

i 4 __BEoGIQB_EBINGIELEE_LZ11_IBEBd001885191 Page 24 ) t LZ 11_6U Q _ G Q U E Q U E NI S _ L 1011.. f. E UU Q 6d E UI 6 L E _ E X e dl I 1 I ANSWER 4.01 ( 24.0) l GENERIC FUNDAMENTALS EXAMINATION l l REFERENCE l 1 f GENERIC FUNDAMENTALS EXAMINATION l l l l \\ l l l 1 l l l l l l } i l l l l i \\ 1 l l l l l (***** END OF CATEGORY 4 *****)

s q-5t__EdEBQEURY_680_6BNQBd6L_EL6MI_EYQLVIl0Ng Page 25 L2211 ) i ANSWER 5.01 (1.00) "a." (1.01 REFERENCE CNS 5.2.4, P.1 295006G010 ..(KA's) ANSWER 5.02 (1.00) A licensed operator may shutdown the reactor when in his j udgement, continued operation could jeopardize station safety. [1.0) REFERENCE CNS Proc. 2.0.1, P. 1 295006G011 ..(KA's) l ANSWER 5.03 (2.50) l l a. 1. Close the MSIV's and steam.line drains.- [0.5] 2. Return the Mcde switch to RUN (to cause a GP I isolation) [0.51 l b. Inadvertent loss of coolant to secondary containment. c. 1. The RRMG's were on the normal station transformer. [0.5] 2. ARI was initiated. [0.5] REFERENCE CNS 2.1.5, Pp. 2-5 295006AK30 295006K207 295006K203 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

x, s s St__EdEBQEUQY_oND_oBUQBdeL_ELoNI_EYQLVIl003 Page 26 L22).1 i l ANSWER 5.04 (3.00) l I a. There is a table in the CAUTIONS section that specifies instrument-1 l accuracy le cs1 ranges at various DW temperatures. (1.0) l 1 1 1 b. The operator must determine the the system was auto initiated 1 l inadvertently, (0.43 OR adequate core cooling exists. (0.43 (0.8) { l c. To maintain adequate core cooling (by promoting inj ection). (0.3) I l To maintain Primary Containment Integrity.(by minimizing release j I potential). (0.3) l l d. 1. RPV Level cannot be determined. i l l 2. DW Temp. reaches RPV sat. temp. 3. DW pressure cannot be maintained below the Primary Containment l l desigr. pressure. (any 2, 0.3 es.) (0.6) 1 i REFERENCE l EOP/C, P. 3 E0P-1, Pp. 6, ATT.I & E0P-2, P. 3 29f,031K305 295031K101 295031A201 ..(KA's) ANSWER 5.05 (1.00) "c" (1.0) REFERENCE CNS EOP-1, Pp. 38 295037A207 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

Et__EdEBGEUQ1_800_6BUQBd6L_EL6NI_EVQLUIl0Ng Pagel27 12211 ANSWER' 5.06 (2.00) - deenergize the scram solenoids - vent the scram air header reset the scram, drain SDV, manually scram again individual scram switches to TEST - increase CRD cooling water d r. - insert using CRDH, normal insert - vent CRD overpiston volume - initiate ARI - emergency in - place RPS test trip logic switches in trip [Any 5, 0.4 each] REFERENCE E0P-1, Pp. 41-46 295037K307 ..(KA's) j l ANSMER 5.07 (0.50) "b." [0.5] REFERENCE CNS 2.4.1.3, P. 1 295014K207 295014G010 ..(KA's) ANSWER 5.08 (2.50) a. Dispatch an operetor with sound powered phones (0.4] to instrument racks 25-5 and 25-6 [0.35]. b. 1. Secure TG emergency lube oil pump. 2. Secure Seal oil back up pump. 3. Reduce NBPP loads to minimum. 4. Secure RFP emergency lube oil pumps l 5. Secure RRMG DC oil pumps. [any 4, 0.25 ea.] l l c. 1. Erroneous RPV level indication. 2. Degradation of safety related systems or components. [0.375 es.] \\ l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) L

~ l Et__EUEBGENQ1_600_eBNQBdeL_ELoNI_EkQL911QN3 Page 28 l 12211 I 1 REFERENCE J CNS 5.2.5.1, Pp. 1-3 ] 1 295003A103 295003G007 295003K101 ..(KA's) ANSWER 5.09 (2.50) a. HPCI RCIC ADS { RHR ) REC [Any 4, 0.25 es.] i b. RUN [0.5) c. 1. Check that scram discharge volume drain valves are closed. [0.5) 2. Check all CRD HOU scram valves open. [0.5) REFERENCE l CNS 5.2.1, Pp. 1-17 1 295016A107 295016A101 ..(KA's) ANSWER 5.10 (1.50) i The license limit for suppression pool temperature is 95 degrees which will likely be exceeded during the test. [0.5) However the Tech. Spec's al' low i ] exceeding this limit by 10 degrees for necessary testing, [0.53 (as long as temperature is 95 o F. or lower within 24 hours). Therefore operation may J continue. [0,5) 1 REFERENCE q Tech. Spec. 3.7.A.1.c & d l 295026G008 ..(KA's) I l l l l i l I (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) j

j 1 Et__EME80ENGl_eUR_eBUQBbeL_ELoNI_EYQLUIl0N3 Page 29 L2111 l l l ANSWER 5.11 (1.00) l Secondary containment isolated. ) SGT started. I Primary containment vent and purge valves shut REC critical loop operation initiated. (Any 3, 0.33 ea.] REFERENCE CNS 5.3.5, P.1 l 295023K303 295023K203 ..(KA's) ANSWER-5.12 (1.00) f "d." l REFERENCE ) CNS 5.3.5, P. 2 l l 295023G011 ..(KA's) l l ANSWER 5.13 (1.00) { 1 "b." [1.0) REFERENCE i l CNS 5.7.16, Pp. 1, 2 295017A104 ..(KA's) ANSWER 5.14 (2.00) a. "4" [1.0) b. "1" [1.0) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

7 _7 5___EdEBGEUQ1_680 8BUQBdeL_EL6UI_EVQLVIIQNS Page 30 ) L2211 i l REFERENCE CNS 2.4.9.1.10, P. 2 .00R002-21, Pp. 16, 17 j 295005A206 295005K101 ..(KA's) i ANSWER 5.15 (1.00) "c." [1.0) REFERENCE CNS 2. 4. 2. 2.1, - P. 2 l 295001G010 ..(KA's) j l i l ANSWER. 5.16 (1.00) 1 "b." [1.0) I l REFERENCE CNS 5.2.4, P. 1 295018G010 ..(KA's) ANSWER 5.17 (3.00) a. 1. CR0 pumps 2. RR pumps 3. RWCU [0.5 ea.] b. Air purge [0.5) c. 1st: Condensate /Feedwater 2nd RCIC [0.5 es.] REFERENCE CNS 5.2.4, Pp. 1-3 295018A102 295018K101 ..[KA'S) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) m _.m _---.__.m. __--a.- m___ m._m_.. _m .m_:.. -__m_____ _.._-____..__m-__

5t__EUEBGENQ1_60Q_6BUQBd6(_E(6UI_EyQLyllQU$ Page 31 L2211 ANSWER 5.18 (1.50) a. Shutdown the Reactor, b. Assure adequate core cooling. c. Suppress a fire. [0.5 es. REFERENCE CNS 5.8, P. 4 295033K303 ..(KA's) \\ ANSWER 5.19 (1.00) "c." REFERENCE E0P-3, P.1 295035G011 ..(KA's) ANSWER 5.20 (1.00) REFERENCE CNS 2.4.1.1.4, P. 2 295022K101 ..(KA's) ANSWER 5.21 (1.50) a. Unequal expansion of the refueling bellows flange. [0.5) b. 1. Vent and purge the DW with N2. [0.5) l 2. Initiate reactor cooldown. [0.5) l k (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

~ Sz__EdEBGENGY_oND_ABNQBb6L_EL6NI_EY9LUIIDNS Page 32 L2211 -REFERENCE CNS 2.4.8.4.2, Pp. 1, 2 295028A104 295028K102 ..(KA's) ANSWER 5.22 (0.50) Those precautions listed in EOP/C are applicable at all times for executing the E0P's, while those in the procedure are applicable to a particular step or evolution. REFERENCE CNS 5.8, P.2 295029G012 ..(KA's) l l l l l l l l l l (***** END OF CATEGORY 5 *****) l l

Et__EL6UI_111IENS_L2Dil_6UQ_EL6UI: WIDE _GENEBIQ Page 33 BESEQUSIBILIIIE1_Li2il ANSWER 6.01 (2.00) a. "A" pump speeds up to 45% [0.25) which is the low setting on the dual speed demand limiter. [0.25] The "B" pump is not affected. [0.5) b. No change until RV level is at 27.5", [0.5) then both pumps will runback to 45% [0.25] due to single limiters. [0.25] REFERENCE Facility Test B..nk, QNUM COR002-22 (26) 202002K407 ..(KA's) ANSWER 6.02 (1.00) "c" [1.0) REFERENCE COR002-114 Pp. 28-33 LO 4 206000K40'? 206000K407 ..(KA's) ANSWER 6.03 (1.00) " 1. " [1.0) REFERENCE i Facility Test Bank, COR002-18, QNUMS 18, 20, LO's 4, 7, 8 217000K604 217000K203 ..(KA's) ? (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

3 6t__EL6NI_11SIEdS_L2011_680_EL6NI: WIDE _GENEBIQ Page 34 BESEQUSIBILIIIES_Llail ANSWER 6.04 (2.50) a. ADS inhibit, ADS Timer reset, or stop all LP-CSCS pumps. [0.25 es.] b. Ensure level is increasing due to inj ect ion. [0.5) c. Place " ADS INHIBIT SWITCHES" to " INHIBIT". [0.5) l d. Any Safety / Relief valve has opened [0.25) AND [0.25] a HP Reactor Scram signal is present. [0.25] REFERENCE i COR002-16, Pp. 13-15, L. O. Obj. 3, 6 4 218000A206 218000K501 218000K401 ..(KA's) ) ANSWER 6.05 (1.00) j "c." REFERENCE COR002-03, Pp. 26-32 223002K607 ..(KA's) I l ANSWER 6.06 (2.00) a. LPCI signal present. b. DW pressure > 2 psig. f c. Water level in shroud must cover 2/3 of the core. (This can be i overridden.) J d. Switch to manual. [0.5 ea.] REFERENCE COR002-23, Pp. 15, 16 l 226001K203 ..(KA's) l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

4 e 6:__ELeNI_SYSIEUS_LSQ11_eND_ELeNI: WIDE _QENEBIQ Page.35 BESEQNSIBILIIIES_L1211 ANSWER 6.07 (1.00) f "b" (1.0) REFERENCE COR002-32, Pp. 25-20, LO Sb. i 259002K302 ..(KA's) ANSWER 6.08 (1.00) "b." (1.0) REFERENCE COR002-15, Nuclear Boiler Instrumentation, Figure'1, LO. 3 216000K122 ..(KA's) 1 l ANSWER 6.09 (2.50) 1 a. 1. Affected train heaters trip. 2. Other fan will start (if in sten.'by). [0.5 es.] b. 1. Malfunctioning heaters. 2. Decay of fission products. 3. Combustion of charcoal. [0.33 ea.] ] c. Differential. pressure across the train. [0.5) ) REFERENCE COR002-28, Pp. 15, 16 Facility Test Bank, COR002-28, #8 1 261000A101 261000A301 261000A408 ..(KA's) t-(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) a

kz__ELeNI_SYSIEdE_L20il_eNQ_ELeUI: WIDE _QENEBIG Page 36 BESE9N11BILIIIES_L1211 ( ANSWER 6.10 (3.00) a. 1. Emergency shutdown button on local con' trol panel. 2. Emergency shutdown button on west side of the engine. [0.5 ea] b. Function: Isolate / bypass the control cabling between the EDG and the control room. [0.5] f

Purpose:

Protect the plant safe shutdown capability in the event of a fire in the cable spreading room. [0.5) c. Incomplete sequence trip. [0.3) Inserted if EDG speed has not reached 280 RPM [0.35) after cranking for 20 seconds. [0.35] REFERENCE COR002-08, Pp. 19, 40, 41 LO 3, 5,d l 264000K402 264000K407 264000G014 ..(KA's) l I I ANSWER 6.11 (1.00) I "a" [1.0) REFERENCE COR001-10, Pp. 14-17 215004K501 215004K201 ..(KA's) ANSWER 6.12 (1.00) "c." REFERENCE COR002-04, Pp. 26, 27 LO 12.f 201001K107 ..(KA's) ANSWER 6.13 (1.00) "d" [1.0) l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1

k___ELoNI_SYSIEd1_L2011_eUD_ELeUI: WIDE _9ENEB1Q Page 37 BESEQUSIBILIIIES_ flail REFERENCE COR002-20, P. 13 LO 8.b, 5.d 201002A303 ..(KA's) ANSWER 6.14 (1.00) REFERENCE COR001-20, Pp. 16-25, LO 4, 6 l 204000A304 ..(KA's) ANSWER 6.15 (1.00) "c" (1.0) REFERENCE COR001-10, P.17 215003K201 ..(KA's) ' ANSWER 6.16 (1.00) "b" REFERENCE COR00-16, Pp. 38-34, LO 6 j 271000A202 271000A206 271000K408 ..(KA's) l 1' 1 1 l l l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1

Et__EL8NI_111IEUS_L2Dil_600_EL6HI: WIDE _QENEBIQ Page 38 BEREQUSIBILIIIER_fl2il ANSWER 6.17 (2.00) i a. 1 l b. 4 c. 1 d. 1 e. 2, 3 (6 at 0.33 each) l REFERENCE COR001_18, Pp. 9-12, LO. 4 272000A206 272000K402 ..(KA's) i i ANSWER 6.18 (1.50) a. Goes to emergency bypass. l b. Supply fans stop. c. Goes to emergency bypass due to anhydrous ammonia. Also accept no l action. (0.5 es.) REFERENCE COR001-08, Pp. 50-65 290003K401 ..(KA's) ANSWER 6.19 (1.00) i l l "c" REFERENCE l COR002-31, P. 22 LO 8.8 q l 215000K102 ..(KA's) l l l { (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) _1 _ - _ _ _ _ _ _ _ - _ _ _ = _ _ _ _ _ -

Ez__EL6UI_SYSIEMS_L20il_aNQ_ELeUI: WIDE _GENEBlQ Page 39 BESEQUSIBILIIIE1_ flail ANSWER 6.20 (2.00) a.. Position indicating probe. [0.5] b. High reactivity insertion rate ( caused by a control rod drop)[0.5] c. CRDM is initially signaled to insert to remove the rod weight from the collet fingers and allow them to expand. [1.0) REFERENCE Facility Test Bank, COR002-05, QNUM 2, 10, 17 201003A301 201003K401 201003K103 ..(KA's) ANSWER 6.21 (1.50) a. 1. Control rod withdrawal is prevented if the hoist is loaded. [0.5] 2. Hoist power is interrupted if the hoist is loaded, and all rods are not fully inserted. [0.5] l b. That the grappled load weighs somewhere between 50 (accept 40-60) and 485 (accept 470-500) pounds. [0.5] REFERENCE 1 COR001-21, Pp. 19, 20, 43 i 234000K501 234000K402 234000K401 ..(KA's) l ANSWER 6.22 (3.00) a. The " Normal Position" section of the clearance will be filled out l by the (Shift Supervisor or the) Control Room Operator, [0.5] l detailing the required position of valves, switches, etc. [0.5] b. For this condition the lineup will be returned to normal by the system l valve lineup prior to startup. [1.0] c. Person responsible for the j ob, Person signing the " Clearance Issued" l section, Supervisor of the person signing the " Clearance Issued" I section, or person completing the repair. (any 3, 0.33 es.] l (NOTE: SS may sign for any of the above via TELCON) l l (*****-CATEGORY 6 CONTINUED ON NEXT PAGE *****) l l

A kt__EL6HI_1111Edi_L2011_680_EL6MI: WIDE _GENEB'Q Page 40" BESEQU21BILII1E1_L1211 REFERENCE CNS Proc. 0.9, Pp. 6, 7, 294001K102 ..(KA's) ANSWER 6.23 (1.00) "b" (1.0) l REFERENCE l l -CNS Proc. 0.16, P. 1 l l 294001K116 ..(KA's) l l l l ANSWER 6.24 (2.00) l f a. - Under the direct supervision of a licensed individual (0.5] l - Enrolled in approved operator licensing training class (0.5] b. Stand a minimum of seven 8 hour shifts or five 1? 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 reactivation is sought (0.5]. REFERENCE CNS 2.0.3, P. 3 10 CFR 55.53(e) and (f)(2) 294001A103 ..(KA's) ANSWER 6.25 (2.00) A radiation monitoring device which continuously indicates the dose rate in the area. l A dose integrating monitor which is set to alarm when a preset dose is received. An individual qualified in radiation protection procedures, with a dose rate monitoring device. (2 of 3 at 1.0 ea.) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) L_-_____-_--__--_-_-___-____--___

l ) l k___EL8NI_111IEdS_L2011_aNQ_EL6SI:MIDE_GENEB19 Page 41 BESEQUSIBILIIIE1_L1212 l REFERENCE CNS Proc. 9.1.1.2, P. 5 294001K103 ..(KA's) ANSWER 6.26 (1.00) ) "b" REFERENCE i CNS Proc. 2.0.5, P. 1. 294001A116 ..(KA's) ANSWER 6.27 (1.00) i "c" REFERENCE CNS Proc 2.0.1, Pp. 1, 2 294001A102 ..(KA's) ANSWER 6.28 (2.00) a. 1. Radiological 2. Operational 3. Fire-Natural-Security 4. Miscellaneous (0.25 es.) b. Take him to the exit turnstile, (and instruct him to report'to the security b1dg. auditorium.) (0.5) c. Control room. [0.5) l l l l l (***** CATEGORY 6 CONTINUED ON NEXT.PAGE *****) h L

k __EL6NI_HISIEbE_12011_eND_EL6NI: WIDE _QENEB1Q ,Page 42 BESEQN11BILillES_11212 REFERENCE i EP!P 5.7.1,'P. 1 i EPIP 5.7.7, P.3 { EPIP 3.7.10, P. 2 294001A116 ..(KA's) 1 1 I l l l l l l I ) l l I 1 l l (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) - _ _ _ - _ _ _ - _ _ _ _ _ _ - _ __-_ __--_ _ _-_ _ ____- -_- ___ - -_--. - - _ - _ _ _ - - - _ _ _ _ - _ _ _ - - _ _ - - _ -}}