ML20006E757

Exam Rept 50-302/OL-89-02 on 891218-20.Exam Results:Three Senior Operators Passed Exams

ML20006E757
Person / Time
Site:	Crystal River
Issue date:	02/02/1990
From:	Casto C, Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20006E756	List: ML20006E755 ML20006E757
References
50-302-OL-89-02, 50-302-OL-89-2, NUDOCS 9002260320
Download: ML20006E757 (105)

Text

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REGION il Y _. ],.7,, ' -e I s, jg g- .W HUs /j.- 1 , y? "4 101 MARIETTA STREET,N,W/ 'd" '/ (( 'r-1 ATLANTA, GEORGI A 30323 Ys N .. l; " h \\ . i . p ^ .o 7 h;;s u a ENCLOSURE l' ? t- 'x> ~, ? ' '4 s i- ] REPORT. DETAI" LS-i ) n m Facility Licensee: > Florida _ Power. Corporation; -M P. 0. Box.1240 1 [ Crystal ~ River.'FL 32629 ? 50-302' l; h 9/ f Facility Docket-No.: M h !,s Facility License No.: DPR-72

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m. =, [ g U.--Si NUCLEAR: REGULATORY COMMISSIONL ~ "gy SENIOR REACTOR-OPERATOR LICENSE EXAMINATION r REGION 2- .Js b 'FACILITYi Crystal River 13 a REACTOR TYPE: PWR-B&W177L DATE!ADMINSTERED: -89/12/18 -CANDIDATE: INSTRUCTIONSJTO CANDIDATE: 1 PointsLfor each question"are indicated in parentheses after_the question. ' L.Tha passingEgrade requires-at least 80% correct overall.. Examination oprpers_will be picked up four and one half;(4 1/2)_ hours after the. icxamination starts. ~, m. CATEGORY' % OF, NUMBER ~ 'VALUE TOTAL CORRECT CATEGORY 234.00. 42.50 EMERGENCY AND. ABNORMAL PLANT EVOLUTIONS ' (43%) r

46=.00) 57.50.

PLANT SYSTEMS (40%) AND. PLANT-WIDE GENERIC RESPONSIBILITIES-(17%)- 7 80.00-OVERALL CORRECT OVERALL All workEdone on this examination is my own. I.have neither given nor. received aid. i Candidate's Signature j

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Daring the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application cnd could result in more severe penalties.

2.LAfter the examination has been completed, you must sign the statement on the. cover sheet indicating that the work is your own and you have not r0ceived o.r given assistance in completing the examination. This must be done after you complete the examination. 3.;R:stroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or posetbility of cheating.

4. Une black ink or dark pencil only to facilitate legible reproductions.

5. Print yona namo in the blank provided in the upper right-hand corner of the exantr.stien cover sheet.

8. Fill in the date on the cover sheet of the examination (if necessary).

7. You may write your answers on the examination question page or on a

- coparata sheet of paper. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

8. If you write your answers on the examination question page and you need tore space to answer a specific question, use a separate sheet of the p2per provided and insert it directly after the specific question.

DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.

9. Print your name in the upper right-hand corner of the first page of each c;ction of your answer sheets whether you use the examination question p ges or separate sheets of paper.

Initial each page.

10. Bafore you turn in your examination, consecutively number each answer cheot, including any additional pages inserted when writing your answers on the examination question page.

11. If you are using separate sheets, number each answer as to category and number (i.e. Plant Systems # 04, EPE # 10) and skip at least 3 lines between answere to allow space for grading.

12. Write "End of Category

" at the end of your answers to a category.

13. Start each category on a new page.

14.-Write "Last Page" on the last answer sheet.

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

Avoid using symbols such ae < or > signs to avoid a simple transposition orror resulting in an incorrect answer. Writo it out. 16.' The point'value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.

r~- a S 17 ~Show.Oli?calculatieno, method 3, cr cacumpticna.uoed to obtain cn cncacr'. [18L Pcrtial credit may be given. Therefore, ANSWER ALL' PARTS OF THE QUESTION

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AND DO NOT LEAVE ANY ANSWER BLANK.

NOTE:-partial credit will NOT be L, given on multiple choice' questions, ) e+

19. Proportional. grading will be applied.

Any additional wrong information ~ . that is provided may'coint against you. For example, if a question is. ) ' ccrth one point and-asks for four responses, each of which is worth 0.25 l points, and you give five responses, each of your responses will be worth' o 0.20 points. If one of your five responses is incorrect, 0.20 will be F - d: ducted and your total credit for that question will be 0.80 instead of i 1',W3 even though you got the four correct answers. 20 m. If the intent of a question is unclear, ask questions of the examiner i only. n [21..'When turning'in'your examination, assemble the completed examination with I cxamination questions, examination aids and answer sheets. In addition, sturn in a13 scrap paper.- f !22'.iTo' pass the examination, you must achieve an overal.). grade of 80% or - greater. I F 0 r L23 1There is a time limit of (4 1/2) hours for completion of the examination. (or uome other time if less than the full examination is taken.) [24. When you are done and have. turned in your examination.-leave the examin-1 i [ ction area as defined by the examiner. If you are.found in this-area 1 L while the examination is still in progress, your license may be denied or rsvoked. 1 s . i $ 7 i t i L I t i h i 't t w. ,.a

p 1EMERGENCYiAND ABNORMAL PLANT.IVOLUTIONS' Pag]

4' (43%)- s O. vi b f QUESTION: 01 (1.00) e Which one~of the choices.will correctly complete the following. i1 Ctatement as described in-STS 3/4.1.3 LCO 3.'1.3.1 " Movable Control Rod [ 'As cablies? I

All control (safety'and regulating) rods shall.be. OPERABLE and-L<

. positioned so that their group average height is within +/ __?__. -(Indicated Position) h [- 'a. 6% r l' tb. 6.5 % I c,- 7% (( d. 7.5 %- i. i: [. 4 QUESTION:.02 ( 1. 00 )' 1All of the following are part of the bases.for the limits on Control Rad operability as described in B3/4.1.3 on the STS'except;- a. -Ensure that acceptable power distribution limits are maintained.- b.- . Ensure that the minimum SHUTDOWN MARGIN is maintained. c. Limits.the potential effect of a slow reactivity-addition-

accident.

id.

Limits the potential effect of a rod ejection accident.

(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ^' o

b, EMERGENCY;AND ABNORMAL PLANT EVOLUTIONS ' Pasi 5 (43%) - *( 4 QUESTION: 03 ~(1.00)- baAllofthefollowingareentryconditionsforEP-140" Emergency L'R;2stivity Control" except; j; a.- 'An unexplained rise in neutron flux l' b. Continuous control rod motion exists y, [ . c.- In modes l'or-2 with regulating rode in the unacceptable region of the rod index curves d. Less than required shutdown margin 4.. I: h {'t QUESTION: 04 (1.00): k In'cccordance with AP-545 " Plant Runback" the first immediate step l ~ ct0 trac " Ensure Auto: plant runback to </ maximum %FF". L" zWhich one'of the following is the maximum Full Power limit for an Ady: metric Rod?- a.- 50% i ~b. 55% c. 60% d. 65%~ 1 \\ 1 w v l l: l(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 3 J~ ,b :.

77 J EMERGENCY AND'ABNORHAL'PLAdT EVOLUTIONS Pass 6 [' (43%) I L t ' QUESTION: 05 (l.00) 'AP-380 " Engineered Safeguarde Actuation" refers to stopping the Rea; tor Coolant Pumps within 2 minutes. Which one of the following la the condition requiring the Reactor Co31 ant Pumps to be stopped within that two minute time period? a. A LOCA occurred b. Reactor Protection initiates a Reactor Trip h c.- High Pressure Injection System Initiates C d. Subcooling Margin la lost [ l-QUESTION: 06 .(1.00) l' LDuring a Loss'of Coolant Accident, the initiating event for tripping tha Reactor Coolant' Pumps has occurred and the two minute time limit f0r_ tripping the Reactor Coolant Pumps has passed and they were NOT tripped. The Nuclear Operator has tripped one Reactor: Coolant Pump ,.. p~;r. loop as required, p- .Which one of the following in the required OTSG level limit for this pitnt. condition? a. 95% b. 80% c. 65% i d. 50% (***** CATEGORY S CONTINUED ON NEXT PAGE 4****) [.-

3 EMERGENCY AND ABNORMAL. PLANT EVOLUTIONS Paga 7 (434). bQUESTION:07 (1.00) I L Which one of the following. conditions would require.an immediate trip cf the effected Reactor Coolant Pump? .a. High Controlled Bleed - off temperature is 164 F b. Cooling Water Temperature leaving the pump is 182 F l c. Total seal outflow is 2.8 gpm and increasing rapidly b d. Thrust Bearing Temperature is 215 F ?. ? t i QUESTION: 08. (1.00) L It'has been determined that Emergency Boration is required. I Which one of the.following choices accurately describes the source of Cc.tcr'and the required flow rate to meet Emergency Boration requirements for the mode of operation it which it is applicable 7 a-Mode 4 10 gpm from BWST b. ' Mode 6, 55 gpm from BAST c. Mode,2, 35 gpm from BWST d. Mode 5, 10 gpm from BAST l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l.

P INERGENCY:AND ABNORMAL PLANT EVOLUTIONS Paga 8

(43%).

ft I . QUESTION: 09' (1~.00) Which one of.the following is an Limiting Condition for Operations Lconcerning Movable Control Assemblies Technical Specificat1ons, ~3/4.1.3.x? a. All safety, regulating and axial power shaping control' reed switch position indicator channels and pulse stepping position indicator channels shall be operable and capable of l -determining the control rod position within +/- 2%. s b. "?!ae position of each regulating group shall be determined to be within the insertion,. sequence and overlap limits at i l-least once every 24 hours. c. The individual safety and regulating rod drop time from the fully withdrawn position shall be less than or equal to 2.1 seconde from power interruption at the control rod drive breakers to 3/5 insertion with Tave greater than or equal to 525 F and all RCPs operating. { d. All axial power shaping rods.(APSR) shall be operable, unless fully withdrawn, and shall be positioned within +/- 2.5% (indicated position) of their. group average height. ' QUESTION: 10 (1.00) .Which one of the following choices is the immediate. action step, that wh0n not met, requires the implementation of EP-140, " Emergency R cctivity Control." as described in AP-580 " Reactor Trip"? l a. Ensure CRD group 1 through 7 are fully inserted. b. Ensure Intermediate range flux is decreasing. l j c.. Verify Shutdown margin less than 1%. d, Verify TVs and GVs are closed. I s I a ~ (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) P I E v

,w. I . EMERGENCY AND"APNORMALlPLANT EVCLUTIONS Pag 3 9 b (43%) a m QUESTION: 11 (1.00) t Which 'oneLof. the following is an accurate list of five (5) valves that must be verified closed when performing the IMMEDIATE ACTION of pr cedure AP-400, " Steam Generator Isolation Actuation"? l AT:ume a OTSG 'B' isolation. h a. .MSV-411."MSIV" F 1FWV-32 " Low Load Block Viv" FWV-15 "MFWP Suction" L EFV-33 "EFW Isol" EFV-57 "EFW' Flow Cntrl V3v" L b. 'HSV-412 "MSIV" FWV-33 "Startup Block Viv" i" FWV-15 "MFWP Suction" FWV-31 " Low Load' Block Viv" EFV-55 "EFW Flow Cntrl V1v" c. MSV-413 "MSIV" FWV-32 " Low Load Block V1v" FWV-28 " Cross - Tie" FWV-15 "MFWP Suction" FWV-29 " Main Block V1v" d. MSV-414 "MSIV" FWV-32 " Low Load Block Vlv" FWV-15 "MFWP Suction" L EFV-32 "EFW Isol" EFV-55 "EFW Flow Cntrl Vlv" si b (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

g. c EMERGENCY AND ABNORMAL PLANT EVOLUTIONS -Pag 3 10 (43%)- [t r.

QUESTION

12 (1.00) 1:

Acc;rding to a NOTE _found in AP-460, " Steam Generator Isolation ( A tuation": -Which one of the following is the reason for the expected level change .f cpproximately 10% on various instruments following a steam i -13:k incide the reactor building? a. Pressure increase in the containment. [ b. Temperature increases in the containment. c. Humidity changes in the containment. d. Flooding of instruments in the lower containment. ' QUESTION: 13 (1.00) Act:rding to EM-216 " Duties of the Nuclear Plant Fire Brigade" Which one of the following is the most desirable method of fighting a ! 'high_ voltage electrical fire with water? a. Straight stream directly on fire from at least 50 ft. b. Wide fog pattern from at least 10 ft. c. Fog / stream combination from as close as possible. id. Narrow fog pattern from at least 40 ft. l I: o (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

y r ENERGENCY AND ABNORMAL PLANT EVOLUTIONS-Pagd la p '(434) [i t ' QUESTION: 14' (1.00) The following PostLTrip Window is an indication of which one of the l f:;ur choices? POST 1141P WINDOW Te / I Tc I.: l l 4 e. a. Loss of Heat Transfer b. Excessive Heat Transfer c.-

Inadequate Core Cooling-d.

Loss of~Subcooling Margin I

e 4

l L -(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l l

bI L EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pcg3 12 f (43%) r QUESTION: 15 (l'00) Which one of the four choices will correctly complete the following F ctatement? L A rding to OP-607 section 4.5 " Loss of Condenser Vacuum" the Caution Nita states that the Main Turbine must be tripped if. delta T between l C:ndensers exceeds __?__ F. a. 50 i V '40 b. c. 30 d. 20 k -QUESTION: 16 (1.00)- ' According to Technical Specificatior.3 3/4.3.3.8 Table 3.3-12 r L Action 21: Wh n conducting a Liquid Radwaste discharge from the Auxiliary F Building Waste Treatment System and RML-2 " Aux 31dg Liquid Radwaste Eff Line Monitor" is out of service. All of-the following acticos are r quired except; With less than the required number of OPERABLE channels, effluent releases via this pathway may continue, provided that prior to initiating a release: o. At.least two independent samples are analyzed in accordance with specification 4.11.1.1.1, b. A portable monitor is attached to the discharge path to allow for continuous monitoring during the release, c. An Independent Verification of release rate calculations is performed, \\ d. An Independent Verification of discharge valve lineup is (? performed, (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

h ~ Pagi13' d EMERGENCY AND ABNORMAL' PLANT EVOLUTIONS [ . (43%)-

e i

~ h-FQUESTION: 17 (1.00) EP-290 " Inadequate Core Cooling", requires the RCP's to be started, [ in the event the incore temperatures enter. Region 4. Which one of the following conditions would require tripping the RCP if it was started in accordance with EP-2907 ? e a. Cooling water leaving the RCP is'195 F b. ' Seal Injection flow and NSCCCW flow is lost l c. Excessive current is indicated on the RCP d. Thrust bearing' temperature is 283 F b . QUESTION: 18-(1.00) Which onciof the following is the reason for closing or verifying the M31n Turbine Throttle and Governor Valves are closed following a r:Cetor. trip;per the IMMEDIATE ACTIONS of'AP-580, " Reactor Trip?" a.- To ensure the Main Generator is removed from the-grid and power is transferred to off-site for the Vital buses. Lb. To allow'the' Turbine bypass valves to control the OTSG I pressure and' plant cooldown rate. c.. Stop overcooling leading to possible emptying the PZR and a saturated RCS. d. To allow the rapid breaking of the condenser vacuum so plant-temperature. control can be transferred to the atmospheric relief valves. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l J

ENERGENCY'AND' ABNORMAL PLANT EVOLUTIONS Paga 14-b ~ (43%) ife l L QUESTION: 19 (1.00) Which'one of.the following immediate steps of-AP-580 " Reactor Trip" if

• NOT met requires the Main Feedwater Pumps to be tripped?

l a.. Ensure TVs or GVs are closed E b. Ensure ICS and NNI power is available f }. c. Ensure "LO LOAD FW BLOCK" valves are closing -l d. Ensure PZR" level ie >/ 50" t QUESTION: 20 (1.00)- Which one of:the following is the reason that the cooldown rate, i ,during natural circulation, is limited to </= 50 F/hr? a. Thermal stresses in the OTSG b. Waterhammer in the EFW lines c. Brittle fracture of the RCS loop-welds d. " Voiding of the Rx '/essel head P - QUESTION:- 21 (1.00) Which one of the.following is the purpose of ensuring that Pressuricer Lavc1 is greater than or equal to 50 inches in the IMMEDIATE ACTIONS of_AP-580, " Reactor Trip?" i a.- To provide the operator with a setpoint at which additional l action is required, b. To prevent thermal shocking the pressurizer c. To provide automatic pressurizer level control. d. .To prevent loss of letdown from the RCS. P (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) \\ u

~~ N, > < qq W EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Paga 15-(43%) p* } h QUF.STION: 22' (1.00) ( -Whi;h one of the following is an entry condition for AP-360, " Loos of Deccy Heat Removal?" i a. Refueling is in progreso with the core off-loaded to the spent i fuel area when a leak develops in the "A"'RCP-seal package. l b. During_cooldown at 250 F the "A" train DHR pump trips on overload leaving only the "B" train pump to continue cooldown. t c. Loss of off-eite power during cold shutdown conditiona prior L to start of refueling and the failure of the "B" train EDG to start on an undervoltage condition. i d. Cooldown to cold shutdown is continuing with both trains of i DHR when DHV-42.eump suction valve is opened causing air binding of both pumps. i' QUESTION: 23 (1.00) Tho unit in operating at 80% power and all systema are in Automatic. If the temperature compensation circult-for the selected pressurizer . loval failed such that the. indication is uncompensated, which of the below best-describes the units responae? 'Accume NO operator action! L a. The control room will receive a low pressurizer level alarm and the level will transfer to the alternate channel. (LT2-1) b. HUV-31 (Pressurizer level control valve) will open to return level to the~ program band. c. The.eelected chancel (LT1-1) power available indication from-l ~ bus RPS "A" will extinguish alerting the operator of-the malfunction, e d. All the prosaurizer heaters vill immediately deenergize ha indicated by the PZR HTR LYL AUX RELAY"PWR FAIL white . light being energized. ?. 1 (***** CATEGORY 5 CONT.?NU2D ON NEXT PAGE *****) c

m y l L EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pago 16 [. (43%) h L. k ~ QUESTION: 24 (1.00) While performing a reactor startup, the operator must verify Int 2rmediate Range Instrumentation is on scale and indicating prior to Source Range Instrumentation indicating >10 E5 cps, while withdrawing regulating rods. Which one of the following indicates the minimum number of decades cvarlap1 ensure by the above mentioned step? a. - one half b. one c. 'one and one half d. two QUESTION: 25 (1.00) EP-390 " Steam Generator Tube Leak" step 3.23 states: "When RCS Th is </= 540 F.and affected OTSG is identified, then isolate affected 0TSG". Which one of'the following choices is the reason for isolating the OTSG at'this time? At this point: a. Pressure in the affected SG should.be below the lowest MSSV

setpoint, b.

Natural Circulation has been established and ensured of continuing with only one SG steaming. L c. The pressure is such that the ADV"s can be placed in Auto without~ adjusting the null, so when the SG is isolated the pressure will not fluctuate. d. The leak rate has slowed to the point the OTSG will not go solid if SG blow down is established. y (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)

i EMERGENCY,AND ABNORMAL PhANT EVOLUTIONS-Paga 177 (43%) g,; e jQUESTION: 26 (1.00) r Emergency Chile at~ power a trip of both Hain Feed Water Pumps occurs. l F:rd Water. actuates, but is only feeding to the 'A' OTSG. L. Which one of the choices completes the following statement? 4 .. Arorrding.to AP-450 " Emergency Feedwater Actuation" 'B' OTSG is ccnaidored dry when on the EFIC Low Range, level is less than __?__. a. 10" b; 8" r [ c. 6" d. 4" r QUESTION: 27 (1.00) Which one of the following statements accurately gives three c:nditions that should be met to feed a dry SG, as out lined in AP-450 "Exorgency.Feedwater Actuation"?- FO:d rate should be: i -a, </='150 pgm, Feed should be thru the low OTSG nozzles,-and 2 RCPs. operating in the loop with the dry OTSG. .b. </= 125 gpm, feed should be thru the high OTSG nozzles, and no RCPs operating in the loop with the dry OTSG. j c. </= 100 gpm, feed should be thru the high OTSG nozzles, and >/=-1 RCP operating in the loop with the dry OTSG. d. </= 75 gpm, feed should be thru the low OTSG nozzles, and </= 1 RCP operating in the loop with the dry OTSG. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) r

('s. ^ ' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS-Pag] 18-e .(43%) ye ' QUESTION:.28 (1.00) I ThD diesel driven Fire Water Pum7 (FSP-2A) will auto start at a fire 'h:cder pressure of ? psi decreasing. a.. 95 k b. 85 c.- 75 t d. 65 -QUESTION:.29 (1.00) i If during fuel handling, a-problem arises which prohibits the cc pletion of the step-by-step performance of a procedure: Which-one of the-following is the correct action to be taken?- a. Immediately perform those actions to maintain 23 feet of water above the fuel. (including any fuel on one of the cranen) b. Continue fuel handling operations and process the appropriate temporary procedure change forms. 'c. Suspend fuel handling and receive permission from the Nuclear Plant Manager for corrective action.. d. EnterJapp11 cable step of another section of procedure if the Refueling Consultant, Refueling Supervisor, and CCR0 agree. 1 s i f (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 1

L}$fi - ENERGENCYLAND ABl?ORMAL PLANT-EVOLUTIONS-PagJ 19 - (434) g 7 ? x QUESTION:L30' (1 ; 50)- O TComplete'the following table as applicable to the entry conditions of -EP-220 " Pressurized Thermal Shock".- ?1f RCS' temperature is <'500-F, AND STS'cooldown rate limits are ~ 6 DCxceededr RCS; TEMP' 'C/D LIMIT -_a- </: 10 F/hr A __b__ </= 50 F/hr __c__ </: 100 F/hr-QUESTION 31 '(2.00) Which"of the following controln and indications are available ON the R rote Shutdown Panel?: a. Wide Range RCS Pressure b.- Normal' Makeup Flow L, c. MUP-1A d; .MUV-49 " Normal-Letdown" -_e. Loop'"A" Harrow 2suge T cold f.: SWP-1A lg. Loop "A" Delta Temperature 'h. Makeup _ Tank Level ,4-1. DHV-91 " Aux' Par Spray Isol" c j. Condensate Storage Tank Level k.- PZR-Htr Group 10 '1. EFP-1 2:. x 4 l i+ (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ,f f + 1

7 .pO-(EMERGENCYANDABNORMALPLANTEVOLUTIONS g Pag 12] Pi (43%) - Vv N'1 + [ ' QUESTION: 32-(1.50)- i [ Ace 2rding to EM-201 " Duties of an Individual Who Discovers an Em:rgency" an' individual who. discovers an emergency condition shall notify-the Control _ Room by dialing 311 on a PAX or conventional L ;ictra-plant _ telephone, and give specific information. L Which'of-theffollowing items of information are requiredsto be given,' ? colo. minimum, by EM-201 for an accidental gaseous release? l u 'a. The safe area for personnel -b. . Type of Emergency E o c. Location of Emergency d. Names of. personnel in the' area e. Visible _. damage to plant components. l ~ f. . Whatraction (if any) has been-taken [ g. Power supplies to the effected equipment h. .Name of person making the report 1. Whether.or not there.are any injured personnel 'j. Recommendations on equipment to secure-j I e e i h ri '- ? i t i ?' -i n p V 'l i i (***** END OF CATEGORY 5 ****a. + 5 I / bkN -'rd

$P -PLANT' SYSTEMS-(40%)'AND PLANT-WIDE GENERIC Paga'21 ~RESPONSIBELITIES (17%) hQUESTION:01 - ( 1. 00) ' i' - Which one of the following combinations of control rod drive breakers b cndLeontacts will cause all rods to be inserted in the core? a. Breaker A, Breaker C, Contact F. J 'b. Breaker A, Breaker D, Contact E. r i; c. Breaker B, Breaker C, Contact E. f. d. Breaker B, Breaker D, Contact F. i i t f g QUESTION: 02 (1.00) A 1ces of makeup has occurred from a trip of the Makeup ptimp due to~ an-clectrical fault.. Seal Injection Isolation Valve has been closed ~ Ccnually due to flow being lost for more than 2 minutes. Which one of'the following gives the reason why the special pr: caution of slowly. increasing the flow must be used in the r00t: ration of seal injection flow? t c. Prevents waterhammer, b. Ensures.the MUP maintains NPSH. i c. Avoids thermal shock to seal parts. d.. Allows time for the PZR level control valve to respon.:' V h ? (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

N'

PLANT SYSTEMS'(40%)'AND PLANT-WIDE GENERIC-Paga 22' Li

RESPONSIBILITIES (17%)

m j*; f-i ] u [ QUESTION: 03-~ (1.00) ~ iTh:)! reactor is'at 100% of full power when a regulating rod hasL Lbe:ome misaligned resulting in a. Quadrant Power Tilt of 12%. F~ Action to reduce reactor power must be taken to bring the QPT to L,cithin 4.12%. V If'Whicikone of the following is the MINIMUM value by which reactor' power ' Ucuat'be reduced? [' a '. 7.88% I-b. 11.824-bEf ic. 15.76%~ 4 d. 19.-70% !QUE'STION:-04 (1.00) 1 - Wh'ich one of the following components will have its service water flow ,1colatedifo11owing a valid ES RBI&C signal? ~"

a.

Letdown coolers.- b.. RB MainiFan Assemblies.

c.

. Makeup: pumps, j d. . Spent-fuel coolers.. t 1 y i + 4. ' s t ' F : (***** CATEGORY 6 CONTINUED ON NEXT'PAGE *****) i y,

3'_

~ ~~ _. PLANT' SYSTEMS (40%)-AND PLANT-WIDE GENERIC' Pag 3 23 JRESPONSIBILITIES,(17%) 1 ', QUESTION: 05 ( 1 ~. 00 ) b'Which*oneofthefollowingDecayHeatvalvesprovides-overpressure [.pr;tection for the Decay Heat System? M< a. DHV-41-Outside containment suction isolation valve. 1 b. DHV-91 Outside. containment pressurizer' spray isolation valve. ? D r L io. DHV-3 Inside containment suction isolation valve, e d. DHV-5 Outside containment return isolation valve. i E i V.' t:~, e IEQUESTION:J06' l(1.00) = Which one'of the following conditions will result in the 50 psi bias l beLcpplied to.the turbine bypass valves operating setpoint?- ~ a. The' reactor is tripped ~as indicated by a trip CONF > light on R the diamond panel and decreasing reactor l flux.

b.. 'The reactor is'notttripped, and the main turbine is tripped.

1 I The' reactor and turbine are not tripped'. Steam header c. pressure deviation is 5 psig below.setpoint. i, d.' The reactor and turbine are not tripped, all turbine bypass -valves'are closed and ULD is at 10%. b a .1 U (***** CATEGORY-6 CONTINUED ON NEXT PAGE *****)

p.,

I' ? PLANT 0SYSTEMSE(40%)-AND PLANT-WIDE GENERIC P ga 24 . RESPONSIBILITIES (17%) ! QUESTION: 07 (1.00) l r Which one of the choices will accurately complete the following l ct;tement? l f Total feedwater flow control will be implemented when a IO% RCS iflow; error exists, there are three-RCP's running: a. 'A' and 'B' OTSG's are on low level limits and L the 'A' feedwater master is in auto and i L the 'B' feedwater master is in manual. L b. 'A* 0TSG'is NOT'on' low level limits and L the. 'B' OTSG is on low level limits and [ the 'A' feedwater' master is in auto and t,n* 'B' feedwater. master is in manual. I c. 'A' OTSG is NOT' on low level limits and the 'B' OTSG is on lou level limits and the 'A' feedwater master is in manual and the 'B' feedwater master is in auto. d. 'A' and 'B' OTSG's are NOT on low level limits and the 'A' and 'B' feedwater masters are in auto. b' L QUESTION: 08 (1.00) !Which one of the following best describes the. sequence of events e cruaing the trip of the Main Feedwater Pumps (MFWPs)? r The initiating event in a trip of both FWBPs as the FWBPDVs close: a. When the FWBPDVs are 60% open, the MFWPSVs start closing. I' The MFWPs. trip when the MFWPSVs leave the open' seats. b. When the FWBPDVs leave the open seats the MFWPSVs start closing. The MFWPs trip when the MFWPSVs are 25% open. c. When the FWBPDVs are 40% open, the MFWPSVs start closing. [ The MFWPs trip when the MFWPSVs leaves the open seat. d. When the FWBPDVs leave the open seats the MFWPSVs start closing. The MFWPs trip when the MFWPSVs are 75% open. (***** CATEGORY 0 CONTINUED ON NEXT PAGE *****)

p I rt. -PLANT-SYSTEMSL(40%) AND PLANT-WIDE GENERIC Paga 25 3 RESPONSIBILITIES (17%) "Y hQUESTION: 09 (1.00) L Which one of the~following is an accurate statement regarding the iSource Range.Excore Nuclear Instrument detector count rate as the core uncovers during a LOCA with the RCP's off? r a. The-detector count-rate.will increase as the core begins.to uncover..- The count rate will reach a maximum level then i-b begin to fall as the water level continues to decrease. ~ b. The detector count rate will decrease as the core begins to ' uncover. The count rate will reach a minimum level then 'I L begin to~1ncrease as-the water level continues to decrease. I c. The detector count rate will increase as the core begins to uncover. The count rate will continue to increase as the P core level continues to decrease. d.. The detector count rate will decrease as the core begins to uncover. The count. rate will continue to decrease as the 1 core level continues to decrease. c f i QUESTIONi 10 (1.00) Which one of the following is the transient the Code Safety Valves cro sized for? l a.. Loss of Feedwater Flow at 100% power. i b. Complete loss of all power at 100% power. .c. Turbine trip from 100% power. j d. Control Rod Withdrawal from 0% power. i I (***** CATEG03Y B CONTINUED ON NEXT PAGE *****) i

PLANT SYSTEMS ~(40%) AND: PLANT-WIDE GENERIC Paga 26 [ RESPONSIBILITIES (17%)- I ( i' l, QUESTION: 11 (1.00). Which one of t following-choicec is an accurate list of four (4) aut matic initia ing conditions.for Emergency:Feedwater Actuation? [All four of._the in tlating conditions must initiate EFW for the . choice to be correct. a. - Both HFW pum trip with'Rx Pwr at 15% 'A' OTSG at 5-

psig,

'B' OTSG 1evel t 5", - 4 RCP's tripped th Rx Pwr at 15%. 'B' 0TSG at 550 psi b. 'A' OTSG 1evel at 10' - 4'RCP's tripped with R Pwr at 12%, ~ ~.HPI initiated on both 'A and 'B' ES channels. 'B'.OTSG at 5", c. i - 4 RCP's tripped with Rx Pwr t 15%, 'HPI initiated on both 'A' and 'B' ES channels, - both MFW pumps trip with Rx Pwr t.25% L ( t/ d. - 4 RCP's tripped with Rx Pwr at 8%, Q - HPI initiated on both 'A' and 'B' ES a

41a,

'A' OTSG at 550 psig, l9p 'B' OTSG at"5". p l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

. PLANT SYSTEMSc(40%) AND PLANT-WIDE GENERIC Pcga 27 PESPONSIBILITIES (17%) -QUESTION: 12 (1.00) Which one of the following is an accurate des;ription of the start i sequencing of BSP-1A (Reactor Building Spray pump) and EFP-1 (Em rgency-Feedwater pump)? f. If HPI/EFIC and RB Spray are actuated, and the RB Spray actuation occurred: a. less than 5 seconds after the EFW actuation, BSP-1A.will-start as a block 6 load, and EFP-1 will start as a block 5 load, t b. greater than 5 seconds after the EFW actuation, BSP-1A will start as a block 4 load, and EFP-1 will start as a block 6 load. i. c. less than 5 seconds after the EFW actuation, BSP-1A will start as a block 5 load, and EFP-1 will start as a block 4 load. d. greater than 5 seconds after the EFW actuation, BSP-1A will start as a block 6 load, and EFP-1 will start as c ~ l block 5 load. ' QUESTION: 13 (1.00) Which one of the following statements regarding the Emergency Core Cooling Systems operation is correct? a. Automatic initiation of HPI by the ES system starts BOTH. selected HPI pumps and all pumps necessary for LPI. -b. The HPI pumps may be started at their local 480 V breakers located on'ESMCC 3AB on the 119' elevation. c. .The LPI pumps are automatically lined up to supply the HPI Pumps from the RB sump when the BWST reaches a specified minimum level. d. The system is designed such that during a low pressure condition, as long as only two HPI pumps are running, pump runout is not an operational concern. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

f) l ~ 1. PLANT SYSTEMS-(40%):AND PLANT-WIDE GENERIC Pagi 28 RESPONSIBILITIES-(17%) M. 6 QUESTION: 14 (1.00) ' - Which one of the following is the power supply to the Air Handling Fan

AHF-10 RB Main Fan Assembly?

t e 'a. ES Bus 3B i l: 'b. Reactor MCC-3A l c. ES HCC-3AB ~d. LVent!MCC-3B p 4 QUESTION: 15 (1.00) . Which.one of the following, along with the radiation. monitoring - alarms, will~ prevent the release of liquid waste during a RML-7 rcicase?: F a-Discharge pump flow from the waste storage tank drops below the setpoint. Lb. Less than-2 Service Water Raw Water pumps are operating. -c.

Total circulating water flow does not exceed 1,300,000-gpm.

d.c The low level setpoint is reached in the storage tank. b I E ' r: (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

f \\1! PLANT SYSTEMS'(40%) AND PLANT-WIDE GENERIC Paga 29 h? j f(RESPONS1BILITIES(17%) g h> h, QUESTION: 16 .(1.00) "Which;one of the following is an accurate list of'the Reactor o k LPr;tection System trips bypassed when the Shutdown Bypass Key Switch 10 in the bypasa position? Ii a.~ Flux /DeltE Flux / Flow Trip, I Low Press Trip, l-RCPPM Trip, Press / Temp Trip. 1 l b.~ RCPPM' Trip, Low Press. Trip, High Press Trip, D ' Press / Temp Trip. h1 L c. Flux / Delta Flux / Flow Trip, -Press / Temp Trip, RCPPM Trip, 7' .High Flux Trip.. T d.- Flux / Delta. Flux / Flow Trip, Hi.RB Press, Low' Press Trip, -RCPPM Trip. j.

QUESTION

'17 (1.00)

'i LWhich one of the following failures will cause the.NNI power-supply g' c:nitor to trip..it's respective NNI source breakers (S1 & S2)? q a. Any + or - 24 VDC power supply fails. b. Any~two 24 VDC~ power supplies fail, e -c. 'The 118 VAC field power. supply fails. d. 'Either + or - 24 VDC bus fails. [ (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i c_. t

JF ^ aPLANTTSYbTFf'! '40%)- AND?: PLANT-WIDE GENERIC Page 30 -"^ RESPONSIBIL1 RIM'J-(17%)

i

' QUESTION : ; 18 ' (1.00) Which one of the choices below accurately completes the following

statement?

Human exposures to both Halon 1301 and-Halon 1211 have shown that Halon: a. 1231 concentrations up to 1% by volume, have little noticeab.le effect, and 1% to 3% results in dizziness and tingline of the extremities. b. 1301 concentrations up to 3% by volume, have little . noticeable effect, and 3% to 5% results in dizziness and . tingling of the extremities. c. 1211' concentrations'up to SS by-volume, have little . noticeable-effect, and 5% to 7% results in dizziness and tingling of the extremities. s;~ -d. 1301' concentrations up to~7% by volume, have little noticeable effect, and 7% to 9% results in dizziness and-tingling of'the extremities. f (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) a i.i ,,i., i.,i..i... .i, m

y,a b;$5TPLANT;SYSTEMST(40%)iAND PLANT-WIDE GENERIC- _Pcgr 31_ s i: - - RESPONSIBILITIES (17%) Ir 1 3-4 L [ijl0ESTION 19 (1.00) Accor' ding to the STS Bases 3/4 9.11, which of the following is-the J = banis for maintaining :23 ft of water above the spent fuel. assemblies twh;nJatored in:the Spent Fuel Pool? .The restrictions on minimum water level ensure that sufficient y r

water depth is available to

a. remove 99% of the assumed-10% iodine gap activity released from the rupture of an irradiated fuel ' assembly.. b. . reduce the: exposure rate of personnel and equipment.in. I e .the area by a factor of 10 of_the assumed radioactivity. t generated.by. fuel 1being stored an average of=20 years-with a'15% fuel cladding failure.'

c..

maintain the spent fuel 1 covered'for'6 hours in the event' that a' spent fuel pool cooling line rupture occurred-with the--flow rate-based on gravity draining through t the spent fuel pool cooling piping. .d. iensure a sufficient volume of water is available for cooling in the event that spent fuel' pool cooling is-lost..for'a: period of 15 hours based on the heatup rate from 1x1/3 cores.being stored with a high decay heat load. 1 c-QUESTIGli: 20' .(1.00) 'Which one of the following coolers does NOT have its cooling water faupply~ isolated in tho' event?a valid ES RBI & C signal is received?- a '. 'CRDM Coolers 1 . b.i . Spent Feel Coolers or 'RC pump Coolers d.:

Waste Gar Compreesor Coolers

(***** CATEGORY

6. CONTINUED ON HEXT PAGE *****)

v yj + sp V)

,m h $ PLANT SYSTEMS (40%'!AND' PLANT-WIDE GENERIC: iPdgy 32 L T ) y QRESPONSIBILITIES~(l?%) W,

<P f,

-~+ l p L (QUESTION:,21L (1.00) s-fM Which oneiof'the:following: choices is the accurate' listing of the (;7fo~ur(4):NuclearServicesClosedCycleCooling'Systemloadsthat'are

J equipped

with differential-flow alarms for detecting leakage?

l

^

a. Letdown Coolers & RC Drain. Tank Cooler, i RB: Fan' Assemblies & Vent Fan Motor Coolers,. Rx Coolant Pump Coolers, Spent-Fuel Coolers. J b.: -RBLFan Assemblies & Vent Fan Motor Coolers, Rx-Coolant Pump Coolers, CRDM Coil Coolers, Makeup-Pump' Coolers'. 'i co. Rx1 Coolant Pump! Coolers, CRDM: Coolers, -Letdown Coolers & RC Drain Tank ~ Cooler, 1 Emergency Feed. Pump Motor Coolers. d. Letdown Coolers-& RC Drain Tank Cooler, a RB-Fan Assemblies &' Vent Fan Motor Coolers, j

Rx1 Coolant; Pump Coolers,-

1/ - ~CRDM Coil. Coolers, a t qQUESTION: 22. -( 1. 00 ) c Which-oneEofLthe following statements-is correct regarding the power Ecupply; system to the Control Rod-Drive System?- Q Power isfeupplied by: a.c ...the Rx Aux Bus'3A through the 'A' CRD Bkr to the Primary 4 -VoltageJRegulator 1 I through-the 'B'.CRD Bkr to the j b. ...the Rx. Aux Bus eb, Secondary Voltage Regulator .j

a K9x sc.

...the Turbine Aux Bus 3A,:through.the 'A' CRD Bkr to the gj-Primary Voltage Regulator fd. ...the; Turbine = Aux Bus 3B, through the 'B' CRD Bkr to the i Secondary. Voltage Regulator j g, Us l (***** CATEGORY 6 CONTINUED ON NEX1 PAGE *****) j ~~ jY: 3 b

n i

a;:,, ' ' ( \\ i b~ E A'

e " PLANT SYSTEMS (40%)JAND PLANT-WIDELGENERIC Pcga133 j i ,' ~ RESPONSIBILITIES (17%) p. i.,. r W iQUESTION:7 23 (2.00) 0 iMitchitheLau'tomatic actions / permits-in-Column 'B' with their. b Erccpective setpoint.in Column 'A'. e ~ [Thb-items in' Column 'B' may be used once, more than once, or not at-

cl1.]

' COLUMN 'B' COLUMN 'A' SETPOINTS RCS. PRESSURE AUTO ACTIONS / PERMITS 3 e .a. Saa 1. RS Spray Act. be 900 2. Low' Press Inj.. Act. I c. 1800 3. High' Press Inj. Act. d; 21es 4. Low Press Rx Trip y e. 2155 5. 'D' Pzr Htr Bank ON -f. 2205 6. HPI Reset Permit g. .2355 7.. .PORY Opens h. '2380'

8..

Spray Valve Ope'ns 41; 2450 9. Safety' Valve Open j. 2500

10. High Press Rx Trip

11. All Pzr Htr are ON

12. PORV Closes

13. Permit to Bypass HPI'

14. Spray Valve Closes

15. Permit to Bypass LPI

[10fanswers @ 0.2 ea) a-a j .3 F l l t t e (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 'bh ' t

- ;mm i Yd; PLANT 1 SYSTEMS'(40%) AND PLANT-WIDE GENERIC- 'Pcga 34 p /, RESPONSIBILITIES'(17%)' b QUESTION: 24 . ( 2. 00 ) : [LFeriesch'ofthetwo'questionegivenbelowselecttheonecorrect ' :n ::er from-the four possible choices following the questions. F .l.. The Spent Fuel' Bridge. Hoist will be prevented from moving up ?.M if-there is no grapple " engaged" or " disengaged" light'or the weight on the hoist is greater than 2,.. The Spent Fuel Bridge Hoist will~be prevented from moving' down'-if'the grapple is engaged, the grapple' tube is not down, and the' weight on the hoist is.less than t a. 3000 f b. 2750 r c. 2450 j d. 2100' s = QUESTION: 25-(1.00) Mutchlthe: loads given in' Column 'B' with.their respective loading

rcquence blockLlisted.is Column

'A' as applied to the Engineered .i

Safcguards

Diesel' Generator Loading Sequence.

.[Tho:Atems in Column 'B' may be used once, more than once, or not at t .c11.] COLUMN 'A' COLUMN 'B' L BLOCK LOADS 1. Block 2 a. Emergency lighting b. Decay Heat Sea Water. Pump n c. Emer Nuc Ser Sea Water Pump 2.. Block 3 d. Battery Chargers e. Rx Bldg Fan Assemblies f. Emer Nuc Ser Closed Cycle Cooling Water Pump-g. Decay.' Heat Closed Cycle Cooling Water pump h. Miscellaneous valves l' l (***** CATEGORY S CONTINUED ON NEXT PAGE *****) i 9 i

g . ;c - ~ 1 k ? Wy : PLANT 7, SYSTEMS (40%).AND PLANT-WIDE GENERIC Paga 351 iRESPONSIBILITIES (17%). 1 me (? ! h UESTION: -26[ .(2.00)- l VMitchethetinterlocksJ11sted in~ Column 'B' with the. radiation Tin 2tr'ument thattinitiates the action listed,in Column 'A'. m [Thi ithmsf-in' Column 'B' may be.used once,.moreithan once, or not at. ' ' ' c11'. ]. i ICOLUMN 'A' COLUMN 'B RAD INST' INTERLOCKS. -a.- RMA-2 1. AHF-7A & 7B (RB Purge Exh)=Stop 2. .AHF-9A & 9B-(Penetration Cooling) Stop b. RMA-3 31 -AHF-10 (Fuel Handling Area Sup) Stop 4. AHF-11A & 11B (Aux Bldg Sup)'Stop. l c0 RMA-11 5. AHF-14A & 14B (Aux Bldg Exh) Stop 6. AHF-19A-& 19B (CC Return) Stop, d. RML-7 7. -AHF-30 (Chem Lab Sup).Stop .i 8. AHF-34 (Hot Mach. Shop Weld Hood Exh) Stop 9. AHV-1A, 1B', 10, 1D (RB Purge Vlvs) Closed 10. SDV-99-(Sec Liq Rel Iso) Closed i. +

11. -WDV-436, 437, 438,.(WGDT Disch Vlv) Closed.

12. WDV-439, (Waste Gas Bel V1v)' Closed 13, WDV-393, 394,.395 (WGDT's Recy1Vlv)' Closed 14. WDV-891, 892 (Pri Liq Rel Iso) Closed a I f k l ) : 1 r (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) .~ d!

p ,q ~ %" PLANT. SYSTEMS'(40%) AND: PLANT-WIDE GENERIC - Pcgo 36- ~ RESPONSIBILITIES:(17%) l i EQUESTION: 27 (1<.00) LR:g:rding1the: Absolute Posttion Indication ( API) and the Relative iPacition Indication _(RPI)' MATCH 2theiterms and functions listed in TColumn 'B' with the respective ~CRD position indications: listed in 4, Column ~'At. -COLUMN 'A' COLUMN 'B' a., ARI 1. Auto Inhibit 2. Asymmetric Rod detection b. 'RPI-3. Feed and Bleed. permits 4. Group in/and out limits 5. Indication raine/ lower switch 4 6. -Pulse Stepping Motor 7. Sequence enable t 6. Sequence monitor -u 9. Zone Reference indication El 10. 45 reed switches ' l, . QUESTION: 28: -(2.00)

Which of the

following conditions, when the alarm setpoint~1s (cxoceded, will energize the SDR (Shutdown Relay) resulting in a trip Tof the-Emergency Diesel Generator?.[4-@ 0.25~ea.]

CONDITIONS. a. Lube-' Oil Level Low: i 'b.

Generator Stator Temp High c.--

--Lube Oil Press--Low } d. Jacket CoolantJTemp High e. No: Field f. Fuel Oil Press Low ge-Engine'Overspeed - h '. Crankcase Press High 1. Start Failure 4 m-b ) . i S m v t m 8 Y ~. f-l

• Jh e g,n

"^'

_c I<JPLANTSYS'TEMS(40s)iAND: PLANT-WIDEGENERIC. P g2137 p - RESPONSIBILITIES;(17%) (:. *: t l. " QUESTION: 29 (1.00) -Which.oneJof-the following choices is an accurate list of-areas which crt;;uire authorization from the Nuclear Fire Protection Specialist on , c' Fire Work Permit. i li.-- Cable Spreading Room, ES Switchgear Rooms, Station Battery ^ Rooms, ICS Equipment Room. 4 b; CRD Equipment Room, ES Switchgear Rooms, Station Battery Rooms,- Cable Spreading Room. ?, e c. ES Switchgear Rooms, Station Battery Rooms, ES. Equipment . Rooms, Control Center. d. Station Battery Rooms,.ES Equipment Rooms, Control Center, ICS Equipment Room. ' QUESTION: 30 -(1.00) ,Which one of the'following choices accurately lists areas which, if. cffected-by a procedure, require that the procedure be done in a etcp-by-step manner, as required by AI-500, " Conduct of Operations"? Operating procedures'shall be step-by-step if they directly. affect: a. Nuclear Fuel, Primary Coolant Pressure Boundary, Containment' Integrity, Engineered Safeguards (ES) Systems. b. . Primary Coolant Pressure Boundary, Containment-Integrity, Secondary Coolant pressure boundary,. Engineered = Safeguards (ES) Systems. c. Containment Integrity, Secondary Coolant pressure boundary, Engineered Safeguards (ES)-Systems, Nuclear Fuel. d. Secondary Coolant pressure, boundary, Engineered { . Safeguards-(ES) Systems, Nuclear Fuel,-Primary Coolant i Pressure Boundary. f h 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i 6

p.s.m, a" x 1 :l PLANT-: SYSTEMS-(40%)-JAND: PLANT-WIDE.GENERICJ ..PigO.38 q/ RESPONSIBILITIES 1(17%);. y,:7 4 4 ,4 E-3 K QUESTIO.N: 31. '(1.00) p-g LWhich.one/of the;following combinations:of tags. hung on a b,cingle' component'is permissible? i e a. 2 blue tage: l f, tb'.- 2-~ red and 1 blue-F c. '1.whiteiand23? red tags Ld. -1. white, 1 red.and 1 blue b IQUESTION: 32- -('1.00) An cpproved! system valve lineup has been altered in accordance_uith; ,fscility procedures,to: perform special testf.ng, Nhichoneof'thefollowingmustibe.usedtoproperlytrackthisspecial' ~ L v21ve - line-up?;. a. -- Entriessin the operator's log. + . b. <An-immeditateLtemporary change. t c. Entries in'-the; shift ~~ supervisor's log, j d. .An, interim' procedure; change. + lV ..k. lo i t 4 - k***** CATEGORY 6' CONTINUED ON NEXT PAGE *****) c 1 } '*)(, ll? l{i .,..p;;_I.;

fsu, I

p, ~ .o Pf-PLANT"SYSTEMSL(40%)aAND PLANT-WIDE l GENERIC. ,Prgr 39-se ' RESPONSIBILITIES.(17%) IE ~r a: !Iql 5

rj.

~ L FLQUESTION:-33 '(1.00): b* Which oneio'flthe;following must be completed by a licensed operator;to caintain his/her 11censelin an " active" statust per the regulations of. 10 CFR 55 " Operators Licenses"? 1.)Thf operatorishall actively 1 perform?the functions of the H ;cppropriately: licensed operator on a minimum of: ,l -a. . seven'8 hour shiftsior five 12 hour chifts:per calendar 4 E P month.- b.-1seven;8chour:shiftsfor five 12 hour shifts per' calendar + $1 quarter. Y* c. five 8 hour shifts or.four 12 hour shifts per' calendar month. d. five 8 hour shifts or four.12 hour shiftsfper calendar. quarter. 4

7 iQUESTION

.34' (2.00) 1Fron the choices,(a, - d.), choose the Emergency. Classifications for m cc.ch'of;the following~ summary statements:

~ ~.17 An' event that has or'is causing-major t'ailure of systems. required to protect the public..It-is 1 likely.that some exposure to the public may occur.. 2. l Actual.or' potential; substantial degradation.of the level of. safety of the plant. a :. Unusual Event .b. Alert E 'c. Site Area. Emergency d. General Emergency .i w l 1 ~(***** CATEGORY-6 CONTINUED ON NEXT PAGE *****) n e L (, l lbN N t

- ~ - SPLANTJSYSTEMS (40%)-AND PLANT-WIDE GENERIC Pag 3:140. 1 ~

RESPONSIBILITIES.-(17%)-

y!

EU' y

+ 6 i

QUESTION: 35-

. ( 2. 00): cbrb;er tiie' following TWO'(2)' questions regarding the "CP-115' Nuclear P1cn~ Clearances". , (; 1. Wiio'is responsible.forLdeterminingaif Independ'ent. Verification is . required lforga' clearance?- (Choose One)- ~ j,

a; Nuclear Plant Operations Mane.ger; e

' b'. -. Nuclear Operations Superintendent "c. ~ Nuclear Shift = Supervisor d '. - Nuc1' ear *0perator-2; cWhichlone'of the following statements gives two actions that must. ,Jbe; undertaken.by.the Clearance Holder for those clearances--that have been outstanding.for 30 days or more? 'a. . Perform a physical verification of tage, review and verify. applicability. 3 b.. Review:and' verify appl'icability, reissur the clearance'tage. 11. Perform, a physical-verification of tags, Reissue the-r li clearance. tags. e Jd. Review 1and; verify appl.tcability,-Re-date the clearance tags. .,q 't.. -l 1 l e t i e d ( I -(41***, CATEGORY 6 CONTINUED ON NEXT PAGE *****) , :( 11 [

~.i... .5 fi R.,. ] 1 fp ' iPLANT SYSTEMS!(40%)i.'AND PLANT-WIDE GENERIC Pcgof41; 1 RESPONSIBILITIES-(17%); y 1 . 9l J 7 ;.. Q i -l 4 1 QUESTION::36. (2.00)- -Fill?in-lthe' exposure-limits,Las required to. complete.the following. . table'. Column 0 ADMIN.LMTJ is the:. limit set ~down by the facility and ,iii the; maximum exposure. allowed without. management approval:.

10 CFR 20 column is the

maximum. limit set'down by-20.101.

}[NRCForm4is<on,filo.J

)

y N 1 AREA EXPOSED. ADMIN LMT^ 10CFR20 I ______g______________________ Quarterly Whole' Body a' b-MYqdrlyt WhblhEBody.. c d Quarterly Extremities' e __.__f

(Handesand feet)'

Quirt'erly. Skin of whole ___._g h-l g ; body ~ k s i n t I r C H Y ...9

,c; q

I \\ w. k i (*****: CATEGORY 6 CONTINUED ON NEXT PAGE *****) t I J q. t y v

@g .E ~T ]* Et. iPLANTESYSTEMS:(40%)1AND: PLANT-WIDEJGENERIC-Pegai42 L RESPONSIBILITIES'(17%). 1 u cc 1 ,_;g (Ll; LQUESTION:.37 -(1.00). 'SLM;tch the funct'iona/responsiblities in column 'B' with the: Emergency. ' Teca in column 'A':that is' responsible. ([ Column 'B' item may be used'once, more_than once, or not at all.) {o COLUMN 'A' COLUMN 'B' i i lc'., Fire brigade 1. Decon injured personnel. 2. Extinguish a fire. I Jb., Radiation Emergency Team 3. Make needed repairs. 4. Perform a radiological _ sample. c. -Emergency _ Repair Team 5. Perform surveys...on site. 6. Provide radiological monitoring .d. Emergency ~ Medical Team; devices. _7 7. Provide-the EC with information ( 6..

EnvironmenLal Survey Team relating to radiation exposure l

and travel.of airborne releases.. 8. SearchLfor missing personnel. 9. Track radioactive releases. 10. Transport an injured person to-as. a medical: facility. ' QUESTION: 08 -(2.'00)_ i LFor'each of the two types of fires described, indicating which of the. ffollowingfchoices1accuratelyclassifiesit. ,H 1. The Emergency Diesel. Generator. output breaker fails to open on an overload therby'failing to deenergize the and' smoke is emitting from the-breaker cubical. R-2. 'The-Hydrogen cooling system on.the Main Generator develops a leak.and recults in.an explosion. g a. Class 'A' b. Class 'B' -c. Class 'C' ad. Class 'D' (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) t

5f * ; ;t y,- g r dj ag w ; + t, ~ . ANSWER SHEET 4,q, *. gq" - SENIOR REACTOR 0PERATOR' u. ~ EMERGENCY AND, ABNORMAL PLANT EVOLUTIONS-_(43%)- , Multiple Choics '(Circle or X your choice); ~ jf; Iflyou change.y ur answer,1, write your' selection in the blank. Gic _

B j

r. . 02 :: -C' 103 B: 4l i 45 C: i tS; D' 06 ,-A. ,07= <B' 4 -t 4\\ 108.. D~ C9. A. g i 10 . B '. 11' 'C 112"- .B! s i-13 i. .< B. 1 o .14; - :- B 't !.15,

A'

'i

16 -

B-

,}1h I-C "18' O.

19i B.'

st (20 - D Jo L21 'A i F221 (D i 1 ') 4 j;g 4 'l_ d i

mq ^n v - s. nz3 3 A. .-ANSWER SHEET-li, i ' *gfl ~ ' - SENIOR REACTOR OPERATOR-ENERGENCY-AND.ABNORMALhLANTEVOLUTIONS(43%)-~ 'Nti1tiple Choice (Circle'or X your choice)' ~ .h ~ "g 'If:L you' change l-. your answer,. write ' your selection in the iblank. l23; 'B, i B i-2 4 ' --

25 A:

y ';26 ; C 027P C: l -28; B 129) D- { ANSWER.

30

.luh, -O=.170_F' [0. 5]. ] t bY, 270 to 171'F' '[0.5) c. J ). - 270 l F [0'.5] R l: ANSWER- '31 LAh :.B'i,LD.,.F;, G.,'I., J.,'K. y r 4 i NSWER- '32-A lB'.,!C.,' E.,,F.,'H,., I. t x .?j,,n '? P 1 y hf e)., jo g k( ), y _ _ Q ir;, - p ws

3m g&:, -. 4 k .y .o 1 g~+ -ANSWER SHEET: ._ ;Jm c... -s I l 5.le f:- ? b} c. SENIOR REACTOR OPERATOR. y-f -i [ PLANT SYSTEMS'(40%) .g E ^'. Multiple Choice + (Circle or X your choice) 4 .. s.

31 If-you change your answer, write your, selection in the blank,. a p<

C11

C' 4,

LO2J C t'.. t E3'- C I:

00 A.-

n li iD5: 1C' o;. C6: .C !.07 B' i 108-B' i t cJ9. 4 .A: T101 D .i ) l:11" 'C 41.2... D ~ 13 ?-- lA' 514 C ! 15-D' t 16 A .i -17

D.

I18

D 4

4 g

A-20 '-

.' B. .2 11-1 SD 22; iA. l: ? s L 'I s sc ( ,1 i ); h) ?

y _ -, ~ ~, -t. M,: c.. c, 5 L ,4 . ANSWER. SHEET %m-r* .s d; t Eb u'

SENIOR ~ REACTOR OPERATOR or

+ .;u, ce. PLANT' SYSTEMS (40%) k ANSWER.: ~23 r.: i {, :C; 2. . 7 n > b p 15 1 . = o 6 -

c.~.'

-4 .c OdL 111. i 14~ 3,c l -. u !t. 6.- ,1 - r ;. 11 0 ; l g'..

}.,

~ .4-lh;a .g '12..- 'i.. .7. a } L;- 9. iANSWER.: 24 L1.. ':D- ~:.i '2.- D. I ? ANSWER 25-w ..C., E. = l'1. r r o ' 1, - B.,x F; !2 F l-hNSWER 26' ]

'4

!,cd ;;; - 2,, 3'.,.4., 7., 8.,

11..

.l ~ 4..:

b ?-

1 L,- .- u j!? j ~ 12... 13. Ld;s. 10. s 1' l,' l i n . ?' y 1 b a ., -) t ^_. of m / ; b,, r ,l.',. ' i i ; r

p. 3_ , (.. 1 i J W.: / ANSWERt.. SHEET .n.- g gy i - 'l . SENIOR REACTOR OPERATOR. }8 t F-PLANT SYSTEMS (40%) iANSWERl 27-u, p, t .= .t . 1.,.2. .3.,',4., 7.,.9.,f-10, T::, W. ibR 5., 6,,. 8. 4 kAN'SWER -28' (C!,-[E.,-G', I. 4-bl ' 4 , f-t ( , f6 i ' )I ab .j I + -I-u ) 5

• k 1

i 1, t i + 3 I t j p 4 u k t -l 's_= s j{ -a dg a. 'fkW s t. ? s ,,?.1.,

(

m exn ,s lt i' ~' ^l*((?'i l

{ _

r '*y Y y ' ANSWER SHEET 9'"- ~. SENIOR' REACTOR-OPERATOR -p, s . PLANT-WIDE' GENERIC.RESPONS BI IT ES_(1 %)-- K. I L I 7 N s Tu ' Multiple Choicef (Circle or X your choice): ,n p. If you: change your. answer, write.your1 selection in;the blank. l ~ [29: B: r<. ..'A- $301. < w x i 3 11 C I i

32 (

'DT f.. ..B k 33:' v u y a ar 4 4 '.( a '4. 4 9 ' i u l } f -i e l- 'I 1' 3,' { } r! t r Jgi:};- i g i,'y.{.j. ; ;

q,1 ,m ~ Idit?ne. mp* . ANSWER SHEETi i FE9l m -<:: JSENIOR' REACTOR-OPERATOR 1 . PLANT-WIDE GENERIC RESPONSIBILITIES'(17%);: ANSWER: 34-l IW C. Y2;.'

B

, g, i ' :\\* '. tANSWER E35 s p t'." ' n 1L.- 'C: H \\;. 2. 1A w-e, i! 36-1 ANSWER - g io.- 1.25 rem /qtr [0.25] l ! b.. 3.0-rem /qtr . [0. 25] - n; c., 5 rem /yr! [0;25] i

.,, e

!d. 12.0 rem /yr or no limit given [0.25] l r ..18;75Lrem/qtr [0.25] K6.5 1 f [-_ =18.75l rem /qtr. [0.25] ya [0.25] Fg. - 7.5. rem /qtr. ' h..- 17'5 rem /qtr-

[0.25]-

,f i s ,1, 1 h n C 1 .., ; y

4; 1

i ,,, ;. t ?

-), C' -

Ed h..

k:; ': Q,,, f. ' j.,i i +, rh s',. a -.. n; .. f },' 5 x !~ i _l t f; tb

V L [' :;-9.

4 s in .y

' ANSWER SHEET w,

^ a, f,.,,, ' SENIOR = REACTOR OPERATOR-mIM e -PLANT-WIDE GENERIC, RESPONSIBILITIES (17%) ,m.' h, p _ v. L: - 37. : . ANSWER: .t. ld.c-2.. . x bn 5.,.6., 8. 4 L.. - 3. c ist 1., 10, w fd., 9.'. t lANSWER:- 385 q o

1'. -

~C T2 ;. D-4 g g:. / w 4. ,1{,* 7 i ,' i + '~; 7 I , i g- .a; l s I f j .q.:, .j r a _i r'an e ..i ...is' ' i -l a .? ?v{.' 10,, '.i = 4 4 b :' ' / m c. i f 1, z 4 j, i'.

t

'l

j., ;_. d-J 9 r,i

'.o QT.'n Q,,;<f : . L, r,', 9, r gg. -

f

/ rq m __- _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ __ __ _a._'. _ _ _ ij

@ ? nlEMERGENCYJAND:., ABNORMAL PLANT; EVOLUTIONS-Pogoe43- ~(4,3%)? v, r + sp

.h s

[1NSWER' 01= :(1.00) ~b.-

REFERENCE:

hCR'STSl3/4.1.3SECTION3'.~1.3.1pg3/41-18 ~ " LESSON:0BJECTIVE ROT 5- ' TERMINAL OBJECTIVE SECTION 3/4 -;a: (,3. 9 )f 000001G008 ..(KA's) 4ANSWERi-02 T1 ~. 00 ) ; c,- L

REFERENCE:

{CRLSTSLBASES 3/4.1.3'pg.B3/4 1 NO LESSON OBJECTIVE : IDENTIFIED Li;(4.3)l. iO00001K302 ..(KAis) 1(ANSWER: 03' (1.00) b.: /l

REFERENCE:

CR)EPs140 pg 1,uAP-525 pg 1-LLESSON OBJECTIVE ROT 5-16 #1 l._(4.1-)7

.v:{ iOOOOO10011 ..(KA's)

g

-(*****7 CATEGORY CONTINUED ON NEXT PAGE *****) %~s -N

Y .EME'GEbCYJANDNABNORMALLPLANT EVOLUTIONS-4 t P;ga-44; R kam ,;(43%)f 1 4 s i =..: e 4 4 . ANSWER:: -04 (1^.00) e, 4 x : c.s 1 f"?;: 1 0

REFERENCE:

(CR'AP-545 pg 3.

LESSONLOBJECTIVE CR ROT 5-68 #2 1

b '(4f1). '000003A105. ..(KA's) t. t ANSWER: OS> s ( 1. 00 ). -1 b. I f f.:

REFERENCE:

CR AP-380:pg 7 &<8 step 3.3

. LESSON 0BJECTIVE ROT 5-63'#2 L ( 4. 0 )'. 000011A103L ..(KA's) LANSWER: 06: , (1.00)

a.

L .REFERENCEO f 'CR;AP-380' STEP 3.3 pg 8, IMMEDIATE ACTION CAUTION NOTE pg 3 LESSON 0BJECTIVE ROT 5-63 #2 $4.7)' 000011A201 ..(KA's) m. 's ~ (***** CATEGORY 'S CONTINUED ON NEXT PAGE *****) i., w. J Ai'J

=r no ~ /EMERGENCYEANDfABNORMAL; PLANT l EVOLUTIONS 'Pcg545 i f 434)i ( F(,7, y *1 ' e b' ' l ' ~ +. IEANSWER: 07. -( 1. 00 ). - 6.. g - m ,e

REFERENCE:

CROP-302 pg:19 &'20, LIMITS & PRECAUTIONS pg 6-iLESSON OBJECTIVE ROT 5-76 #4 l(3.7.)

. 000015A210 ..(KA's): J r ! ANSWER:- 08 -(1~.00)

d. :

U

REFERENCE:

2 .u CRiEP-140 IA.2.1:pg 3 LESSON 0BJECTIVE. ROT 5-16=-#2 j "(3.9)- 000024A205 ..(KA's) ) ANSWER: 09 (l'00)' c. t

o

-I

REFERENCE:

l q R ! CR1 Tech Spac 3'.1. 3.x, pp ~ 3/4: 1-18. through 3/4 1-37 LLESSONTOBJECTIVE ROT 5-1 TERMINAL OBJECTIVE FOR 3/4 1 (3.6) j im 4 1 OG '000005G003' ..(KA's) I 'I l 1 1 '(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 2 m i

m. a. m 4 v. .d'., 'U'.,IEkERGENCYLAND' ABNORMAL 1PLANTEVOLUTIONS> n .1 Pag 3i46l j A<m (- (4315); M, - h o:; ;i N< .gf y: 5 NSWER's ) :10,, l(1~.00): y %. 1 ( 4-:--

REFERENCE:

C Abnormal Proceddre,:AP-580, p. Se b LESSON;0BJECTIVE-ROT 5-28 #2-ci, a ((4.4) ~ ~ 000024K301: .(KA's) + .4 9 . p: ,ihNSWER:1 '111 (1.00)- .c t C. REFNRENCE: l'CR?AP-460 lA 2.1 pg 3~- < LESSON 0BJECTIVE'~ ROT 5-65 #2-r I( 4 ~.~7 )[ u-.. 000040K304 .(KA's) li:(ANSWER:

12 (1.00)

} ' b. n

REFERENCE:

'CR P'-460' Note pg 5 ~-LESSON OBJECTIVE ROT 5-65 #3 p.((3i9) O -000040K306 .(KA.'s) 4 i l f .(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) O r 1_

.. c ' .g e s p'? <P(43%)g ' Pago:47-i .q C,'itEMERGENCY>AND' ABNORMAL PLANT 7. EVOLUTIONS. t. a. c as 4' ,E j y ~tF ~ + l ANSWER: ,134 -('1.00)- Me

REFERENCE:

p, y o

c 'CR$ Emergency: Implementing Procedurei EM-216,.p. 2-' 1 V 'NO LESSON OBJECTIVE-IDENTIFIED _

g;

-( 3 '. 9 )"

1;- 7000067K102- ..(KA's) yANSWER: -14; '(1-00) 11 :. b '... L

REFERENCE:

CR?EP-220 pg i Entry Conditions: p LESSON.03JECTIVE'ROTi5-73 #1; i n

-( 3; 9 )

0000405119 ..(KA's) 3 L., fANSWER:- ~15 (1.00) -4 -W. :

REFERENCE:

CR OP'-607' Caution Note pg'11 !NO LESSON 0BJECTIVE IDENTIFIED i ( 4.1~)' g /p 000051A202 ..(KA's) p-- i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 5

? . 7;f

• t

( ; gc 4 EMERGENCY ANDEABNORMAL PLANTcEVOLUTIONS' Pcgi 48. ..g ' (;43%)* - 3 ,~ m t + p:j ', g ,.i'm -rANSWER:.. 16 1(1.00)L kb.'. 3 i., I

4

REFERENCE:

V.CR: Tech Spec 3/4':.3'.-3.8 Table 3.3-12. Action 21,pg 3/4 3-44' t 3 ! LESSON 03JECTIVE ROT 5-1-#12 -(3.8) n R 000059G005- ..(KAs) a i. ,l ANSWER: 17 '(l00):

c.

?

REFERENCE:

5 .CR-EP-290. Step-3.24 pg;25 ROT 5-19 step 3 15 pg'22. LESSON OBJECTIVE ROTc5-19 #3. 2 (4.2). - 000074K308~ ..(KA's). j ~ . ANSWER: .18 (1.00) a l 4. -.

REFERENCE:

CR ROT:5-28,'p. 4- ? LESSON OBJECTIVE 3' 4 1(4i0); 000007K103 ..(KA's) .p =(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) I i:: e 6 'y i' y

w- .s, cm 41 $ EMERGENCY;AND.~' ABNORMAL PLANT-EVOLUTIONS' .Pcg3 49' 1;1K',f(43%); 1 7e-g. 1; ,,i % ANSWER:.19: (1.00) ..~N... 1 Il

REFERENCE:

t .+ y CR-AP-580'Section'2.0 pg 4 & 5

LESSONt0BJECTIVE.' ROT 5-28 #2

-(4.1)[ ~000007G010 .=.(KA's) 1. t s ' ANSWER; 20 -(1.00) l ,1

v.. d_

f; e- ' IlEFERENCE:

CRi-EP-390-' Caution pg.17 '

LESSON 0BJECTIVE ROT 5-20 #3

(4.4).

'000037K307 ..(KA*s) r i 3

1. ANSWER:

21 l ( 1. 00) - + - a; r d r t', 5 I l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) )

j -

'0l'

f f : EMERGENCY-ANDiABNORMAL.:PLANTLEVOLUTIONS f 3 7 x :s. .v Pcg2 50: L # (( 4 31r,): ', h' a, <. e t.t. "j 'r-REFERENCEi. i Fl):;CRiROT;5-28,-pp 3-6 AP-580,-pp 3-5 s l 4' LESSON' OBJECTIVE ROT 5-28.#2- ? (4?6); ~;; s -f.. T000007K301'- ..(KA's)- + s-f- i fANSWER: 122 - ( 1. 00 ); . d '. E

REFERENCE:

CR' ROT 5-62, p. 2 & 3, AP-360',

p. I c

LESSON ~0BJECTIVE--ROT-5-62 #1'

?! i-('3.9) '000025G011 ..(KA's) ? / ANSWER: 23 .(1.00)- . bl a

REFERENCE:

.i .Cryatal. River, ROT:4-01, Instrumentation and Controls,"page.10-1 ELESSON--0BJECTIVE ROT-4-1 #3 (3.4)I 000028A210' ..(KA's) LANSWERi-2 4 -- (1.00) .b.. m 1 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ~ l P

w / pg y_ o ; - __ M' LEMERGENCY ANDJABNORMAL PLANT EVOLUTIONS-P:gb-51E' $@d-:. ( 43% )!' i o %dl., c v- ,y

REFERENCE:

LCR.OP-210 step'4.2.10 pg--13'- vW LESSO,NLOBJECTIVEiROT 5-2,:#51 [(ii6) 000033A204l ...(KA's) ANSWER": 25 ' ( 1. 00 ). o: so. 1

REFERENCE:

CR ROT 5-20 step 3.23 pg 22 . LESSON, OBJECTIVE ROT.5-20 #3-1 q ,7( 4. 5 ):

\\

000038K302.-

..(KA's) ANSWERi 26, (1.00) '_ C i l L

REFERENCE:

I 'CR:AP-450 Note pg 9 i' LESSON-0BJECTIVE. ROT 5-64 #3 l .(4.6)_ j i -000054K304- ..(KA's) i 1 8 VANSWER: 27 (1.00) -C. ~! (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) n. i '?

fyjyp;t EMERGENCYi AND l ABNORMAL.- PLANTJ EVOLUTIONS:

3.., W. : 1.

3 .g - Pcgd!52; ~ j y.p g , -.. 3 %. )~! l(4 -o N %,g'. @DiREFEREICE:: ......11 - i l-k v; '.. .+ ~ d[ CRTAP.-450 step 3.9 pg 9 _. @ LLESSONt0BJECTIVE ROT:5-64LTERMINAL. OBJECTIVE cl(4I2');. I 000054K102' ..-(KA's)' fy > 4 '? ANSWER:- 128 - ( 1. 00 ) ' L ,;, ' b. @ 8;j. r ?b

REFERENCE:

NCR :: ROT-4-7. pg ' 26. _ LESSON OBJECTIVE ROT 4-7 #11-j

f. l(3.9) m4

000067G009'

..(KA's)- 7 ANSWER: 29 -(1 00) !d. r s F

REFERENCE:

3 JCR ROT-4-26',. , LEARNING OBJECTIVE'#6. _{ (3.8)l ~000036G010 ..(KA's) ? iANSWER: . 30 (1~.50) l6. </=.170 F-i . b '. - -270-to-171 F

c.

> 270 F (3 @ 0.5 ea). (*****. CATEGORY 5 CONTINUED ON NEXT PAGE *****) } - m

.a, g:. 3 . +. Paga;53

!-EMERGENCY.: ANDi ABNORMAL PLANT EVOLUTIONS:

p,- -:.,. ' 1( 4 3Qf 'X l(ge.gi.n

REFERENCE:

n s 9>CR';EP-220' Entry-Conditions.pg'1. Wi: LESSON... OBJECTIVE I(OT-5--73 #1 m, 4

;;(4.;1);

o Q 000009K308 ../(KA's) if g .t jANSWERb 31= (2.00) ._ ;.a c;,--b.,fd., f., g., i.... J.,. k. (8 @ 0.25 ea) T

REFERENCE:

I

CR ROT 4-16 Section 3.1 pg~6 -115-& Section 3.3 pg 38 '

,NO: LESSON OBJECTIVE-IDENTIFIED -(4'.0)' 1 .'000068K201 ..(KA's)- + -1 i ) ' ANSWER: 3 2 -- l(1.50) 'b.,pe., e., f.,.h., 1. (6 @ 0.25 ea)

REFERENCE:

LCR EM-201.Section'4.1 1 pg 3 LESSON OBJECTIVE-ROT'5-35 #6- [ .' ( 3. 8 ) -

i

'000060G010' ..(KA's) t ,i ' t

(.

l (***** END OF CATEGORY 5 *****)

WW '.1 PLANT SYSTEMSL(40%)1 ANDl PLANT-WIDE

• GENERICL I&

..f r,qq iPaga 54E /* ~ RESPONSIBILITIES -(17%):- 4 j;7 %j,: m; Jp) i;3 a pr hd ANdWER:. Oil -(liOO) ' .c ;. ed'h

REFERENCE:

JCR ROT:4-12 REACTOR PROTECTION! SYSTEM section~1.2.2.8 pg.12.

LESSON OBJECTIVE 3.

p (3.7)' (3.1)J-(4'.0) ,7 .:012000A307: 012000K103 012000K603 .,(KA's) a B. ,E < '.:LANSWER: 02J -(1.00) C.- 1

REFERENCE:

a 'CR ROT'5-76:0P-402 SECTION 3.2. 13 P..&1L pg 8 X. LESSON:0BJECTIVE 6. c q L(3.6) 1003000G010i ..(KA's) I LANSWER:- 03l 1.00) ( c. <+ i

REFERENCE:

1 .T.S.-3.2.4.B. l . LESSON OBJECTIVE-#9 g; (3.6)E(3.7). ] m i l 001000G005 001050A202 ..(KA's) i s D / (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) a .c r a.

-- v, m p*t;. PLANT) SYSTEMS M 40%):-'AND~ PLANT-WIDE GENERIC-~ y Pegos553 j E., -RESPONSIBILITIES'(17%) 4 ~- m- &',m'.. n ~;.," ' ;l?? kAN6WER':l04;

(1.00) d: a e

fl'c -C, y ' l !.w E-L

REFERENCE:

u (y JCR[ROTi 4-2:..CH c 2 - .~' 'LCR SRO-88 EXAM #1 QUESc17.0- !",' LESSON 0BJECTIVE ROT 4-2-#7 s,. n c(3'.8) s ji. e' .e- 076000K116, ..(KA's)- >e f EANSWER-05' - (1:00) c '. g .iq

REFERENCE:

CR ROT ~4-1, Chapter 3, section 4.2.2 p. 77 d LESSON OBJECTIVE 12-

s

~(302) s

005000K401;

..(KA's)- LANSWER:~ .'06:- -(1.'00) -; C. : l l

REFERENCE:

CRiROT:4-14 section 1.5.2 page 13 LESSON' OBJECTIVE 3' ' ( 3. 9 )- l-041020K417' ..(KA's) i l l- -(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

HfPLENTSYSTENSi(40%)AND PLANT-WIDEIGENERIO PcgY,56l ~ W# "RESPONSIBILITIESL(17%)~ a-. h b bb " 4. bb '1 -{ i k ( .(1100)- . ANSWER: b. g 1

REFERENCE:

W CR ROT 4-14 section,1.5.4 pg 21 'LESSONL-0BJECTIVE 4 . (3 2 2j ' '059000A410. ..(KA'a) 1J t ~ ' ANSWER: =08: (1.00). 'b. :

REFERENCE:

I -CRiNAO-96-Section. 1.'4'5.3.& 1.4.5.4.pg 9 --12 LLESSON, OBJECTIVE NAO-963#3 4 (3.2): 059000K416- ..(KA's) j ' ANSWER: 09-(1.00) A. :. + ~

REFERENCE:

ICR ROT 3-10 SECTION 3.1 PG 10 & 11 ' LESSON OBJECTIVE #5 c:(3^.8); 1015000A202 ..(KA's)' (*****-CATEGORY 6 CONTINUED ON NEXT PAGE *****)

wn +, :3 m'/$LANf::SYSTEMSl(40%)JAND) PLANT HIDE: GENERIC l 1 Jl LRESPONSIBILITIESS(17%)-- /Pcgd 57:. L s-.>..-. 4 [.i-L,w-1 ANSWER: .10, -(1.00) fd..

p.,,

REFERENCE:

s< ll,

• ;CR.'STS' LIMITING SAFETY SYSTEM' SETTINGS BASES pg-2-6

'^ N0! LESSON:: OBJECTIVE IDENTIFIED. n i.i-9(4.4)!- c

002000K410 '

..((KA*s)- --i; 1 . ANSWER: 11 -(1.00) .c. s

REFERENCE:

> -CR ROT.4-15-SECTION 2;1:pg 13;& 14, CR EXAM BANK SRO-88 EXAM #1 QUES .,18 '- . LESSON OBJECTIVE ROT 4-15 #9 l(4.6)" 061000K402 ..(KAL's) o ? ANSWER: 12- -(1.00) l ' d '. ~!

REFERENCE:

.,CR---ANO-90:SECTION:2 3 pg 24 l "1 LESSON:0BJECTIVE #6 I _'(4.5)- . 026000A301 ..(KA's) l '? l1 'I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) it l i t. i

m, m . + - 1/ =, >. >.. -.,.. f iPLANT BYSTEMSV(40%)"AND PLANT-WIDE' GENERIC'. - Pagi S8.- r f R.ESPONSIBILITIES?(17%):. .:m NF 1 dANSWER-J 13. (l'.00)E \\

3...

> l f. .) L

REFERENCE:

"I i: CR ROT 4-13 AND'CR 19'88.SRO EXAM #3 QUESTION-6.1~ [ ' LESSON OBJECTIVE 1.,-4.-, 6. . ( 4. 4 ): 013000K106-- ..(KA~s) '{ n. 0 ~ l hiANSWER; 14 -(1300) S t 8C4 , s g, 4 il.. j 1-

REFERENCE:

i G y CR ROT.4-8, Chapter.1, p. 19-Drawing EC-206-017 LESSON, OBJECTIVE ROT 4-8 #4 ...J( 3.1) : .022000K201-. .. (KA 's )' 3 s.i . ANSWER: 15- .(1.00) 1 'd. 3

REFERENCE:

' CR'. ROT. 5-48', p. :11 ~ LESSON OBJECTIVE 4 - i 1( 3. 6 ) - i068000A302 ..(KA's) -- i t 1 4 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i

W" .l. +. IS K .I'. :.... L, (gb~i$PLANTP_SYSTENGl-(40%)AND: PLANT-WIDE. GENERIC 4 iPcga 594' j qijRESPONSIBILITIES.(17%) y {s:a Q f-

t w

t M.

p-ANSWER:- -.16? (1.00)- l lt m.;s._ o i -i i

REFERENCE:

.t 3. s.. C?CR ROT-4-12 FIGURE'#2 CR'EXAH CATEGORY THREE QUESTION 3.9 LLESSON-0BJECTIVE 13' (3.2).- 01.2000K406) ..(KA'e) i, ANSWER': 17' -( 1. 00 ) id;

REFERENCE:

E CR' ROT 4-9 SECTION-l3.2.E pg 20, CR EXAM BANK QUESTION.29.:pg 9 . LESSON OBJECTIVE 6 l J' (._ 3.2): 1063000K402 ..(KA*s) .i

ANSWER:

18

('1. 00 ) -

d '. l

REFERENCE:

! CR ANAO-39 SECTION-2.5-pg 36 >l LESSON OBJECTIVE 10.C. j ~(3'.5) 086000K504 ..(KA's) i r -: a,; (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) o 1 < ~.jji ( t. ,W' 's 's

~ Fi-S..si'o,,.. ... ' - -..c. -d pMfiRESP0HSIBILITIESi(17%)? JPagi 60~ .,', l F .PLANTOSYSTEMST(40%)VAND; PLANT-WIDEsGENERICL ( 1 e i e.k +i ~ ,iANSWER'; 19I (1.00) + 4 16. . ~ ' ' i i

REFERENCE:

(7CR ROT"! L29lSECTION 4.4 pg=42, STS BASES SECTION-3/4.9.11 pg B 3/4 9-3' E 4 'LESSOH 0BJECTIVE NOT IDENTIFIED 1 ~

(3.1) ~

'033000G006: ..(KA's) 4 ANSWER: 20' '( 1. 00 ) b. )

REFERENCE:

CR ROT 4-2, CR EXAM; BANK: QUESTION'2.15 LESSON;0BJECTIVE CHAPTER 2:#7 .(3.8) _-_013000K108 ..(KA's) hNSWER: 121 --(1;00) ed, i l [RE'ERENCE: F LCR'ANO-84 SECTION'1.4.4, 1.4.5,~1.4.8, & 1.4.9 pg 10 -19 ] LESSON.0BJECTIVE #7 1 't L(3.5)- ) 'l 008000K301 ..(KA's) i L l _ (***** CATEGORY 13 CONTINUED ON NEXT PAGE *****) i . !) l 1: 3

p - g,. .:r _ m.

.

h M "iPLANU SYSTEMS '(40%)TAND PLAN _T-WIDE [ GENERIC) ~ Pcg1 617 ' M' ,.y !, RESPONSIBILITIES'.(17%); s .j. l,

4...'. l pp s

ANSWERrl [22.

(1 00); Llf3,,

1. '

i

REFERENCE:

EA. ,CR-ROT 4-281Sec 1.2 pg 2: ' < LESSON-OBJECTIVE'#5' l(317)-- tr". ^001000K202. ..(KA's) K l: KfANSWER: 23 (2.00) 3 a'. 12.-. (10'@ OI2 EA) .l b.-'15. 11 c. ' 4 '. d.. l:1 1.. c41. - 714 ;

f.

' 8 '. .g. 10..- .h. 12. '1. .7. j,. 9.. j

REFERENCE:

[LCR40Ti4-l'SECTION-2 2. 3, 2. 2. 8, -2. 2. 5, pg '16' - 19 e ~CR cxam bank SRO-88 Exam #1 Question 6 l-cLESSON.: OBJECTIVE #6- -l i(4.1) 002000A101- ..(KAfs) ~ l ANSWER: 24-(2.00) 1. b. (1.0) 12. d.e (1.0) ]-t 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i f 1 x

! PIINT SYSTEMST( 0%)E AND PLANT-WIDE' GENERIC ~ - Pcgi62 - " '( RESPONSIBILITIES;(17%): .. rt - e r-pt;r's kREFERENCEi 'JCRfROTf4-26'SECTION2.3.2pg~27,CR.SRO-88: EXAM #2 QUESTION:6-

1. 'LESSONLOBJECTIVE ' 4 g.

,;(3'.3) y 034000K403--

.;(KA's) ir:' [ ANSWERi'l25-(1.00). b' ; 1. - c. ',. - e. (4 @ 0.25 ea). 5 J2.; : b.,: f. ni'

REFERENCE:

i CR ROT 4-6'SECTION 11.4'pg 31 LESSON 0BJECTIVE #5" d

(3.7);

064000A307 ..(KA's) X 7 'ANSWERi

- 26.

'(2.00) a. 2.,J3._, 4., 7., 8.,--11'. . b '. -: ^ 4 '.

ci. 12..

13'.,

d.

10.~ (10 @-0.2xEA). i

REFERENCE:

CR: ROTf 4-25 TABLE 5 pg 31, ~ 32, - 33 and CR EXAM BANK QUESTION 3.13

~ LESSON OBJECTIVE ~4 (4.3) 1(3.9) -;073000K101 073000K401 ..(KA's) o (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 4 i 1 l ; 2

g9 y;3 g. [ 1 =- = 9' W

,. PLANT SYSTEMSL(40%)- AND ' PLANT-WIDE GENERIC

PagaT63J F

-RESPONS.IBILITIES;(17%) y,. [a \\ s. A 4- [i (1.00) lAMSWER: 27' n.. 1., 2. ', 3.., c 4., ! 7.,1 9., : 10. " b'.. S'.,'6.. 8. ~. . (10 @ 0.1:ea)- t [

REFERENCE:

CR ROT 4-28 Section li4 8, 1~.4.9,-1.4.10,,& 2.4>pg 15.. '24 & pg 31-l 2 L. 'CR' EXAM BANK SRO-88 EXAM #2' QUESTION 27 B! LEXXON OBJECTIVE ROT. 4-28 # 4., 5~., 6., 7. i o " ( 3 ^. 8 )- L 001000K401 ..(KA's) ge -i (ANSWER: 28 '(2.00) a 'I c., e.,Eg.','i. (4'@LO.5 ea) t .i

REFERENCE:

CR AR-901.

-CR. ROT-.4-6 section ' 3. 0.

LESSON _ OBJECTIVE ROT'4-6 #4 L (4.2)- -064000K402! ..(KA's)' .j = ANSWER:- 29 (1.00)-' Lb. t + l l i l (*****-CATEGORY 6 CONTINUED ON NEXT PAGE *****) u e

1. C7

. i. . ~.. ~ ' _ _ -p o [.l$ 5 PLANT? SYSTEMS 3(40%) AND PLANT-WIDE' GENERIC; PegaL64: !by LRESPONSIBILITIESL(17%) ?k,y:Wc. g M. ~ R

REFERENCE:

S. 3 s. 't

CR ROT 5-40,' CP-118,.: pp -2..

cLESSON<0BJECTIVE ROT 5-40 #1-L j(4!2); v; gl 7p = _..(KA,'s) i Ls 194001K116' L ^ I cr ' AhSWER*; 30 1(1.00)- L,. 42.o

REFERENCE:

L '(H1 AI-500, SECTION'4.2 pg 8;~ LESSON OBJECTIVE ROT 5-38, #13 e ((.{. 9 ) - .194001A102 .'.(KA's)' LANSWER: 31 (1.00) ,c..

REFERENCE:

'CR CP-115 SECTION 4;5.1,L4'.5.2, 4.5.3'pg_15-& 16 . LESSON' OBJECTIVE. ROT-5-40_#7 & #8

-(4".1) 194001K1021

..(KA's) ANSWER: J32 '(1.00) u 7d, ~1 i (***** CATEGORY 6 CONTINUFD ON NEXT PAGE *****) lc pd,

p firfe n y irl.- 3: hd PLANTESYSTEMS:(40%)-AND. PLANT-WIDE GENERIC:

• Pcgo 851

.- ?'- 9 9 RESPONSIBILITIESi-(17%): EQ f / y ,) @l-;REFERENCEY' c. ((, LESS,ON: OBJECT 1VE ~ ROT 5-77. #2 - l[CR)AI400C[SECTION'4';2.1,pg8 i g; = 8 + 4(3.7): D y, i194001K101: ..(KA's) kt:4:- i t i it. 4

' ANSWER:

33 (1,00.)..

s.

5b.

i F q f

REFERENCE:

s Issued:1-1-88 10 CFR 55.53(e) NO LESSON.0BJECTIVE IDENTIFIED. h31:4). 194001A103-. ..(KAIs)- -i L ANSWER: ~34-(2f00) t .1. c. (1.0) 2. b. (1.0) y =

REFERENCE:

CR'EM-202 SECTION 1.4 pg 5 & 6 f -LESSON.0BJECTIVE ROT 5-47'#2-i - L( 4. 4 ) ~ "194001Al'16 ..(KA's)- r iANSWER: 35 (2.00) 'l~..c. (1,0) 2. a. (1,0) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

$ N PLANT x ?. , ;~ W W nix ;ISYSTEMSh(40%) BAND PLANT,-WIDE GENERIC. i;;;i .m Pcg3 66. ir,:RESPONSIBILITIESt(17%)N -( E'gg ~ foR ?ie, ' 1 ;; U .. ' '.:7 i

s

~' C

REFERENCE:

14:,

i;:?-;CR CP.115 SECTIONL3;l'.8 PG'2 & SECTION'3.1.5 PG.2,u AI. -500 PG 2 - S' 9 LESSON 0BJECTIVES; ROT;5-40 CP-115.8 3. g,-; j( 4 '.1 )? 1 hW 194001K102;; .,.(KA's)" E! bhi. ' .'36- '(2.00)- l' ANSWER:' C .(

1. c'.a'1.25 rem /qtr-k : b'.-

3;0' rem /qtr -i i' ' c. '5 rem /yr a Jd. '12 0-rem /yr'or no; limit,given-y Jo,- 18';75. rem /qtr

f.

.18.75: rem /qtr- [~g. .7.5' rem /qtr th.-.7 5 rem /qtr s '..( 8 @ ; 0. 2 5' e a c h ) f t

REFERENCE:

fl0:CFR 20 sec. 20.101 " Radiation dose standards'for individuals in 1 'rsstricted areas.":page 268 of 10' parts 0 to 50 Revised as of January 1,J1988.. q 'CR'RSP-101'SECTION-3.2.13 PG-10 TLESSON.0BJECTIVE ROT 5-43 #3-& #5-113. 3);. (2.8): .1 ' 194001K104 194001K103 ..(KAis) L ve m

ANSWERi4 -37 (1.00)

'c.

2...

(0.2) .b; 5., 6.,.8. (0.2) 'c. 3. (0.2) Ed. 1, 10. (0.2) o. 9. (0.2)- l l .) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l \\r

i iPLANT' SYSTEMS (40%) AND: PLANT-WIDE" GENERIC'- Pago 67: ~ ~ f iRESPONSIBILITIES3(17%); y% ' :-,l ! ?$.i i DEFERENCE:- C 5 s

CR. ROT-5-34

"':>CR:= EXAM BANK: CAT 8 QUESTION 8.5- . LESSON 0BJECTIVE ROT 5-34l#-4 1 .l(4.2) i194001K116 ..(KA's). t LANSWER: .-38

('2.00)

l.lC.. ' 2 '. : b. ; REFENENCE:

CR EM-216 Section 3.1 pg l'& 2 NO LESSON OBJECTIVE. IDENTIFIED

+:(4.2) f.. 194001K116 ..(KA's) i ,.l' ' h,'! y e 1,2 (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********) i 5 J - -L

IPCC$6- ' lia Pigi i1: l5} 1 TEST CROSS REFERENCE

• +

w, + y. ) 8 ^ r k/, QUESTION ~.VALUEf REFERENCE j /'+n 4 '02l '. il' 00 - "90001771- ~01{:

1. 00 ~

29000178. a k 1,i 103( ,1.00; 90001791 [ 104 1.00 .9000180 [' 051 1.00 9000181: 06: 1.00 9000182 ' 07L -1.00

9000183 208:

1.00' -9000184-1 y

09-l'.00; 9000185

10!

1.00- _9000186- .,s '11" 1.00 9000187 s 1 il2. 1,00

9000188L j"

13 1.00 0000189 4 -14' 1.00' 9000191' J' 15- '1.00' ~~ 9000192

16 '

1.00. 9000194 17- - 1. 00 - 9000197-l-dT '18 1.00. 90001981

19

'1.00 9000199' 20' -1.00 '9000200 21 1.00' '9000201 H22 -1.00 9000202; 231 .1.00 9000203

24 1 ~ 00 '

9000204 .25: 1.00: 19000205 2 6.- 1-~ 00 9000206 '27: 1.00-9000207 E28-1.00

9000208

29 1.00 9000209 30 1.50-9000193~

' 31=.. .2.00-9000195 32' 1.50 9000196 J 34.00 01 1.00 5725 02-1.00= 12361 03 1.00 12364 04-l'.00 9000140 4 05 1.00: 9000141 06E .1.00

9000142-07 11.00 9000144 08 l'00J 9000145 09' 1 ~. 00 '

9000150 '10' 1.00 9000151 ( 11 .1.00 -9000153 s (;:~ 13-1.00 9000155 12: 1.00 9000154 'I 14' l'00 9000158 i 15-1.00 9000159 16 1.00 9000160 17 1.00 9000161 '18 1.00 9000164 1 19 1.00 '9000165 J l =

yp

,7+l,y 7--

.y 7 7 jp 3 jc 'O ' TEST 1CROSSLREFERENCE' ' LPaga::2: y p; w> sj[ QUESTION: VALUE 1 REFERENCE 1 f.^ft ?_ ,j sNa, 9000166-c. ~20- -1.004 I 21 1400 9000174- .9000175e I h 23 2.00-- '9000152: 2 21 1".00; 1 H 'S24 - 2.00l 9000156 L: ', ' f 25 -' 1.00-t9000162 !261 2.00-- 9000163-

f

~27l l 00' 9000167: _28 ' 'L2.00 9000176 ' 2 9 '. - 1:00 .~ 6190-I i', ' > 3g-1.00 6191 i' L 31 '- ' 1.00t 6305i 32: 11.00: 6312. l'.00 12377 33 i

34-2.00-6316

= ' 35- - 2. 00 - -12367 =; .f 3 6 :- 2. 00 ;' 9000149- -? '37' - 1.001 9000168 ,1 38-2.00 9000190 j t 46.00 7 -80.00 ? 'k f i. I i l i k n lt j-i s -} } .tsi}}