Text

Exam Rept 50-369/OL-90-02 on 900730-0802.Exam Results:All Applicants Passed Written & Operating Exams
	ML20059K010
Person / Time
Site:	McGuire
Issue date:	09/05/1990
From:	Curtis Rapp; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20059K006	List: ML20059K005; ML20059K010; ML20059K029;
References
	50-369-OL-90-02, 50-369-OL-90-2, NUDOCS 9009210112
	Download: ML20059K010 (41)
	v • d • e

,.,

-I

' A f.tig UNITED STATES -

'o NUCLEAR REGULATORY COMMISSION

,z.

'b-REGION il.

f-

' g,'

101 MARIETTA STREET,N.W.

2 ATLANTA,0EOROl A 30323 S

- - - - /

o ENCLOSURE 1 EXAMINATION REPORT NO.: 0L-90-02 Facility' Licensee:

Duke Power Company McGuire Nuclear Station' 12700 Hagers Ferry Road Huntersville, N. C. 28078-8985

' Facility Docket No.: 50-369 and 50-370 Facility License No.: NpF-9 AND NPF-17 Examinations were administered at McGuire Nuclear Station near Cornelius, NC.

/J//90 Chief Examiner:

,es,

/ Curt Rapp Ddte Signed h7 029-Po Approved by:

+

Charles Casto, Section Chief.

Date Signed

't Operator Licensing Section 2' t

Operations Branch Division of Reactor Safety

SUMMARY

Examinations administered on July 30 - August 2, 1990.

U Written and operating examinations were administered to six SR0 applicants and

'four R0 applicants. All applicants passed these examinations.,Requalification' re-examinations were administered to three SR0 licensed ~ individuals.

All individuals passed these re-examinations.

T I

.f

^ ip, t

-i l

l l

9009210112 900905 POR ADOCK 05000369 V

PDC 4

a f

1r' i

u 1

e P,

REPORT DETAILS 1.

Facility Employees Contacted I

D. McGinnis,.0perations Training Director

D. Baxter, 0parations Support Manager

C. Majure, Operations Training Senior Instructor

J. Painter, Operations Training Instructor i

S. Helms, Operations Training Instructor

L. Massey, Operations Coordinator 1

Attended Exit Meeting 2.

Examiners

C Rapp,' Region II B. Gruel,_PNL-A. Lopez, PNL G. Benjamin, PNL

- K.'VanDoorn, Senior Resident Inspector

Chief Examiner

- Attended Exit Meeting Only 3.

Pre-Examination Review On July 18, 1990, representatives of the facility reviewed the written examination.at the Region II office. -This review was conducted to improve examination technical accuracy and ensure all test items were ' correct and concise prior to administration, i

4.

Post-Examination = Review Following examination administration, copies of the written examination __

were left with facility representatives for review.

The facility submitted three comments for NRC review.

l

5.

Exit Meeting 4

l At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination.

-The fol_ lowing items were discussed at the exit meeting.

I 1)

EP/1/A/5000/13.1, Response to Loss of Secondary Heat Sink, does. not include direction against use of ruptured or-leaking steam generators when depressurizing to allow use of condensate booster pumps.

L 2)

EP/1/A/5000/11.1, Response to Nuclear Power Generation /ATWS, does not provide direction for insertion order of individual control red bank,s,.

y,

=

2 3)

AP/1/A/5500/10, NC System Leakaoe within the Capacity ci NV Pumps, does not provide direction for manual initiation of SI ;r the reactor fails to trip.

4)

AP/1/A/5500/08, Malfunction of NC Pump, does not address #1 seal leakoff alreedy decreased wher. checking for a #2 or 63 seal failure.

5)

Candidates demonstrated a general weabess in understanding of instrumentation and control systems off-,rmal response during simulator examinations and plant walkthroughs.

6)

When attempting to start the diesel generator from the control room, two candidates failed to reset the sequencer.

7)

The Special Orders log book was observed to be audited in January and June 1990.

OMP-2.1, Operations Work List, Routine Task List, and Special Orders Log, states the Special Orders log book should be audited monthly.

8)

Special Order 90-16 for EMF-43, Control Room Air Intake Radiation Monitor, requires the intake dampers be reopened if power is removed.

This will allow control room differential air pressure to remain within Technical Specification limits.

Technical Specification 3.3.3.1 requires the intake dampe*s to be closed within one hour if EMF-43 is inoperable.

JC0 89-15 addresses control room diff arential air pressure but does not address Technical Specification 3.3.3.1.

The f acility committed to reviewing these items.

The cooperation given to the examiners was also noted and appreciated, lhe licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

- [ :,a strog'o.

UNITED STATES NUCLEAR REGULATORY COMMIS$10N

)

^

-r-

[

e.

.REGtONll 101 MARIETTA STREET N.W.

ATLANTA, GEOA01 A 30323 ENCLOSURE 1-EXAMINATION REPORT N0.:

OL-90-02 Facility Licensee:

Duke Power Company McGuire Nuclear Station 12700 Hagers Ferry. Road Huntersville, N. C. 28078-8985 Facility Docket No.: 50-369 and 50-370 Facility License No.: NPF-9 AND NPF-17 Examinations were administered at McGuire Nuclear Station near Cornelius, NC.

/J//90 Chief Examiner:

eeo

[ / Curt Rapp

.Dste Signed j

Approved by: (

hI

.f, ) w P o

+

1:

Charles Casto, Section Chief Date signed l

Operator Licensing Section 2 o

Operations Branch Division of Reactor Safety J

SUMMARY

Examinations administered on July 30 - August 2, 1990.

. Written and operating. examinations were administered to six SRO applicants and '

four R0 applicants. All applicants passed these examinations.

Requalificatior, re-examinations were administered to three SR0 licensed -individuals.

All

'I individuals' passed these re-examinations.

e

-l

'l "I

'l

.i i

+1 REPORT DETAILS 1.

Facility Employees Contacted

D. McGinnis, Operations Training Director

D. Baxter, Operations Support Manager

C. Majure, Operations Training Senior Instructor

J.; Painter, Operations Training Instructor s'. Helms, Operations Training Instructor

L. Massey, Operations Coordinator

'* Attended Exit Meeting 2.

Examiners

C, Rapp, Region II B. Gruel, PNL A. Lopez, PNL G. Benjamin, PNL

K. VanDoorn, Senior Resident Inspector

Chief Examiner

'** Attended Exit Meeting Only 3.

Pre-Examination Review

.On' July 18, 1990, representatives-of the facility reviewed the written examination at the Region II office. This review was conducted to improve examination technical accuracy and ensure all test items were' correct and concise prior to administration.

4.

Post-Examination Review-Following examination administration, copies of the written examination were'left with facility representatives for review. The facility submitted three' comments for NRC review.

5.

Exit Meeting

- At the conclusion of the site visit the examiners met with representatives of the plant staff - to discuss the results of the examination.

The m

following items were discussed at the exit meeting.

,1)

EP/1/A/5000/13.1, Response: to-Loss of Secondary Heat Sink, does not include direction against use of ruptured or leaking steam generators c

when depressurizing to allow use of condensate booster pumps.

2)

EP/1/A/5000/11.1, Response to Nuclear Power Generation /ATWS, does not provide-direction for insertion order of individual control rod banks.

l v

y

-2 l.

4 i3)-

AP/1/A/5500/10, NC System Leakage within 'the Capacity of ~ NV Pumps, does

'not'. provide direction for manual initiation of SI if the reactor' fails to trip.-

. 4)

AP/1/A/5500/08, Malfunction of NC Pump, does not address #1' seal leakoff. already decreased when checking for a #2 or #3 seal failure, i

5)

Candidates ^ demonstrated a general weakness in understanding of instrumentation: and control systems.off-normal response during simulator examinations and-plant walkthroughs.

I 6)

When attempting to start the diesel generator-from the control room, two candidafxs._ failed to reset the sequencer.-

7)

The _ Special Orders log book was observed to be audited in January and_

l June 1990.

OMP-2.1, Operations. Work List, Routine Task List, and Special Orders Log, states the Special Orders ' log book should be-audited monthly.

8)

Special Order 90-16 for EMF-43, Control Room ' Air. Intake Radiation Monitor, requires the intake dampers be reopened if power is removed.

Thit will allow-control room differential air pressure to remain within Technical-Specification limits.

Technical Specification 3.3.3.1 requires the intake dampers _to-be closed within one hour-if EMF-43 is

~;

inoperable.

JC0 89-15 addresses control room differential air pressure K

but does not address Technical Specification 3.3.3.1.

The facility committed to reviewing these items.

The cooperation given to the examiners was also noted and appreciated.

The. licensee did not identify as proprietary any of.the material provided to or reviewed by the examiners.

I h

1

~

I I

-- -;y 3

>.; u Yr)

..ENCt.0SURE 2

'R0'

.L)

, W.

..e JNRC"0'fficial Use'Onlyr n

..v

-J i m.

g

! *l,

S I,-

l 'c

f..

L.

3 Nuclear Regulatory Commission' Operator Licensing Examination.

.g ;

- gg a go-9 i

U. H

'l y

R fnST Entn: B GD^

.ls 3

y 9,

s' j

l This document'is removed from

' Official-Use. 0nly category on

-date of' examination.

4 i

.,i

). k t NRC Official Use Only 6

f

\\.

3 e

m

c.

s.

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 2 FACILITY:-

McGuire-1-& 2 REACTOR TYPE:

PWR-WEC4 DATE ADMINISTERED:

90/07/30 CANDIDATE:

' INSTRUCTIONS TO CANDIDATE:

. Points for each question are indicated in parentheses after the question. -To pass this examination, you must achieve an overall grade of at-least-80%.

~

Examination papers ~will be picked. up four and-one half:(4 'I/2) hours after-

_the examinationistarts.

NUMBER:

TOTAlt CANDIDATE'S CANDIDATE'S J9-

-QUESTIONS POINTS-POINTS OVERALL GRADE (%)

I 99 100.00

- A11ework =done on this e Tmination is my own.

I have neither given nor. received aid.

i Candidate's Signature l

j 4

4

n i

l f

i l

c.

.o 7

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

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

2. After the examination has been completed, you must sign ne itatement on

-the cover sheet indicating that the work is your own and you t, ave not received or given assistance in completing the examination. This must be done after you: complete the examination.

E

3. Restroom trips are to be limited and only one candidate at' a time may

~

1 eave.

You must avoid all contacts with anyone outside the examination room to avoid even-the appearance or possibility of cheating.

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

5.: Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

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

f8. If you write your answers on the examination question page and you need more. space to answer a specific question, use a separate sheet of the-paper provided and insert it directly after the specific question.

DO NOT 1

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 answer sheets whether you use the examination question pages or separate sheets

.i of paper.

Initial each of the following answer pages.

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

11. If you are using separate sheets, number each answer and skip at'least 3 lines between answers to allow space for grading.

1

12. Write "Last Page" on the last answer sheet.

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

Avoid using symbols such as < or > signs to avoid a simple transposition error resulting in an incorrect answer.

Write it out.

y/ r?y, q

n y

tg

- 14. 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.

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

16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY' ANSWER BLANK. NOTE: partial credit will NOT be given on multiple choice questions.

17. Proportional grading will be applied. Any additional wrong information that is provided may count against you.

For example, if a question is-worth one point and asks for four responses, each of which is worth 0.25 points, and you give five responses, each of your responses will be worth 0.20 points.

If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will. 'oc 0.80 instead of 1.00 even though you got the four correct answers.

18. If the intent of a question is unclear, ask questions of the examiner

-only.

19. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.

In addition, turn in all scrap paper.

20. To pass the examination, you must achieve an overall grade of 80% or greater.

121. There is a. time' limit of (4 1/2) hours for completion of the examination.

(or some other time if less than the full examination is taken.)

22. When you are done and have turned in your examination, leave the examin--

ation area as. defined by the examiner-.

If you are found in this area while the exar; tion is still in progress, your license may be denied or revoked.

7:

je7

,c v.

v jar 1 REACTOR OPERATOR:

.Page 4 i

ho

(

QUESTION: : 001!-(1.00):

WHICH ONE (1): of:the following conditions will cause a Logic Cabinet Urgent i

/

Failure: in the Rod Control System?

a.

Multiplexing error

(

i

( 3

?

?h, b.

Slave. cycler failure t

c.

Phase failure

~

d. -Logicierror 4.

t i

.QVESTION: 002 (1.00)

-t WHICH.0NE (1) of the following responses complete. the statement concerning

contro1Jofsthe source range channel high voltage power?

t a

- During:a reactor.,..

a. -....startup, one.IR channel increasing above P-5 will turn:off the Thigh voltage.

b.. off the high voltage.

... startup, one out of'four PR ;hannels above 10% power will turn 4

Lc;

... shutdown, two IR channel decreasing below P-6 will turn on ;he:

~

highuvoltage.

1

'd.

... shutdowr., t'wo out of four PR channels below 10% will turnion the d

high voltage.

q i

a i

E

]

\\

u

)

L

7

+

4 j

P REACTOR OPERATOR Page 5 l

t-QUESTION: 003 (1.00)

Given the following conditions:

o s-NC pump start in progress.

1 seal leakoff flow is 0.1 gpm.

WHICH ONE (1) of the following actions needs to be performed before starting i

the pump per OP/1/A/6150/02A, " Reactor Coolant Pump Operation?"

a.:

Raise VCT pressure.

b.

Decrease NO. I seal differential pressure.

c.

Close the seal return line vent.

l d.

Rotate the NC pump shaft.

t

. QUESTION: 004 (1.00) i WHICH ONE'O., of the following is the purpose for the NC pump anti-reverse rotation device?

i a

To minimize NC pump starting voltage.

l b.

To minimize'NC pump' starting torque.

.c.

To prevent overheating of NC pamp-seals in an idle locp.

j d.

To minimize re-start time of.the NC pump at low power Myels.

~ QUESTION:. 005 (1.00)

WHICH ONE-(1) of the following meets the " limits and precautions" for starting NC pump 1A per procedure OP/1/A/6150/02A, " Reactor Coolant Pump Operation"?

E

'a.

Reactor power is 12%.

b.

NC-27.(Loop pressurizer spray control) is open, c.

Oil lift pump has been operated for 1 (one) minute.

I "d.

Delta pressure across #1 seal is 150 psid.

L i

i<

~. _,

.l REACTOR OPERATOR Page 6 c i QUESTION: 006 (1.00)

WHICH ONE (1) of the following responses completes the following statement?

If flashing is occurring in the letdown line, then charging flow is too (1) or NV-124 (letdown pressure control valve) is (2) too far.

a.

(1) Low, (2) opened b.

(1) Low, (2) closed c.

(1) High, (2) opened d.

(1) High, (2) closed QUESTION: 007 (1.00)

Given the following conditions:

g

~

-Reactor power is 100%.

-Pressurizer level control selector switch in the 1-2 position.

-Pressurizer level channel 1 fails-LOW.

Pressurizer level control is in AUTO.

t WHICH ONE-(It of the following describes the plant response to the pressurizerlevelchannelfailure? ASSUME N0 operator action is taken.

,a.. Charging flow decreases, actual level decreases, letdown isolates, and-the level. stabilizes at setpoint.

b.

Charging flow remains the same, letdown flow temperatures increase, and backup heaters turn on.

c., Charging flow increases, letdown isolates, actuel level increases, and I

the reactor trips on high pressurizer level.

i d.

Charging flow remains the same, letdown isolates, heaters turn off, and the reactor trips on.ow pressurizer pressure.

'{

REACTOR OPERATOR Page 7 i

n.

i.

i QUESTION: 008 (1.00)

WHICH ONE (1) of. the following sets of plant conditions is used as the basis for the mitiimum shutdown margin in MODES 14 as specified in Technical i

Specifications 3.1.1.1, Shutdown Margin Tave>200F?*

a.

End of core life, NCS temperature 557 degrees, steam line break.

b.

End,of core life, NCS temperature 588.1 degrees, a stuck open P2R PORV.

.]

-c.

Beginning of core life, NCS temperature 588.1 degrees, steam line

]

break.

j d.

Beginning'of core life, NCS temperature 557 degrees, a stuck open PZR I

PORV.

QUESTION: 009 (1.00)-

l WHICH ONE (1) of the following plant conditions will result in a main feedwater isolation?

1 a.

Doghouse level 10.5 inches

. b.

Steam line pressure 575 psig lc.

Steam. generator level 80 F-

'd.

Reactor trip and Tave 558 F h

r l

r

A.

)

a y

!', REACTOR' OPERATOR' Page 8 1

i I

QUESTION: 010 (1.00)

Given the following plant condition:

)

Performance of OP/1/A/6100/01, " Controlling Procedure for Unit Startup.*

WHICH ONE (1) of the following would cause the CLA discharge i

isolation valves to receive an.open signal?

1 a.

P-4 actuation l

b.

Pressurizer low level l

c.

Steam generator low level d.

P-11 setpoint QUESTION: 01.1 (1.00)

Given'the following conditions:

- Reactor power is 75%.

- Channel N414 the highest reading Power Range Channel.

i Rod control is in AUTOMATIC.

- Channel N42 ins".intaneously fails LOW.

- N0 operator action is taken.

.WHICH ONE (1) of the following describes the resultant control rod system-i response?.

-a.

Control rods will drive in at maximum

ate.

b.

Control rods will drive in at minimum rate.

c.

Control rods will drive out.

d.

Centrol rods will not move.

I l

t l

l-1.

e

7r-

"r REACTOR OPERATOR Page 9 i

QUESTION: 012 (1.00)

WHICH ONE (1) of.the following statements describes one of the purposes of the Nuclear Instrument Channel Comparator?

a.

Detects axial flux tilts, b.

Detects faulty PR channels, c.

Compares upper vs. lower detectors, d.

Alarms on 1% deviations, i

QUESTION: 013 (1.00)

Given the following conditions:

(

-Reactor is in MODE 5.

Source range instrument N31 has read 80 cps for several hours

-Boron concentration is 1300 ppm

-Electronic noise from a welder caused N31 to reach 3000 cps for 30.

seconds.

WHICH ONE (1) of the following describes plant response?

I a.. Suction of the centrifugal charging pumps switches from VCT to FWST.

.l

~

.i

. b..

Containment purge supply and exhaust dampers close.

- c.

Containment evacuation alarm.'ounds.

d.

A containment ventilation isolation actuates, i

t 1

1 r

P4 a

I

c.

REACTOR OPERATOR Page 10 QUESTION: 014 (1.00) i WHICH ONE (1) of the followin) describes the location of the incore thermocouples?

a.

The incore thermocouples are located over fuel' assemblies in the core to measure fuel assembly outlet temperatures, b.

The incore thermocouples are inserted into the reactor core through tubes and measure the coolant temperature axially through the core.

c.

The incore thermocouples are located beneath the fuel assemblies to measure coolant temperature before it passes through the core.

d.

The incore thermocouples are located in the center of the core to measure the maximum fuel assembly temperatures.

QUESTION: 015 (1.00)

WHICH ONE (1) of the following describes the response of the VUL system if containment pressure increases to 0.5 psig?

a.

VU AHUs and RA fans go to maximum cool b.

VL AHVs shift to hi speed c.

VL AHUs RV flow goes to maximum d.

Pressurizer booster fans alternate fan auto starts s

QUESTION: 016 (1.00)

WHICH ONE (1) of the following systems supplies cooling water for the VUL system AHVs?

a.

RC system b.

KC system c.

RL system d.

RV system

j REACTbROPERATOR.

Page 11 j

. QUESTION: 017 (1.00)

WHICH ONE (1) of the following causes the steam to flow up t.hrough the ice condenser following a LOCA?

a.

Lower inlet doors opening to the turning vanes.

b.

Containment fans in the bottom of the ice condenser blowing steam up through the ice condenser.

I c.

Impingement plates directing steam flow upward from the lower plenum.

d.

Containment fans in upper containment drawing the stuam flow upward.

i

. QUESTION: 018 (1.00) r WHICH ONE (1) of the following would cause "A" FWPT to trip?

a, ' Pump suction pressure is at 200 psig.

b.

FWPT oil pressure is at 12.5 psig.

c.

FWP discharge pressure is 1325 psig, d.

Water level in outer doghouse is at 10.5 inches.

i B

i b

j

. REACTOR OPERATOR ~

Page 12 QUESTION: 019 (1.00).

j Given the following list of plant actions:

j

1. 10 CA pump trip.

l

2. CF isolation.

3. TurL!ne trip.

4. CF pumps trip.

i WHICH ONE:(1) of the following selections will result if a steam generatur level INCREASES to 82%7 a.-

1, 2, 3 b.

1, 2, 4 l

c.

1, 3, 4 d.

2,3,4 QUESTION: 020 (1.00)

Given the following list of valves:

1. CF to CA nozzle isolation valve (CF 129)

2. S/G CF control valve (CF 20) 3..-S/G CF tempering isolation valve (CF-153)

4. FWP, isolation valve (CF-5)-

o WHICH ONE (1) of the following combinations of valves will close from u manual feedwater isolation signal?

[

3 a.

1, 2, 3 b.

1. 2, 4 i

c.

1, 3, 4 d.

2,3,4 i

L

! REACTOR OPERATOR-Page 13' f

i QUESTION: 021 (1.00) l y

Given the following list of CA pump suction sources:

I

1. Hotwell

2. CA condensate storage tank 3.-Upper surge tank

4. Nuclear service water e

WHICH ONE (1) of the following selections lists the CA pump suction sources in order of preference?

a.

2, 3, 1, and 4 b.

2, 3, 4, and I c.

3, 2, 4, and I d.

3, 2, 1, and 4 QUESTION: 022 (1.00)

WHICH ONF (1) of the following describes the rate of heat transfer from the NC system to the steam generators following a reactor trip?

j

a. - Decrease at higher NC system temperatures.

P b.

Decrease at higher CA flow rates.

t

c. - Increase at higher NC system flow rates.

d.

Increase at higher CA temperatures.

t l

L l

c REACTOR OPERATOR Page 14 QUESTION: 023 (1.00)

WHICH ONE (1)'of the following_ items will AUTOMATICALLY terminate a waste gas discharge?

a._ High radiation alarm on EMF-36 UNIT V v.T GAS (Low Range).

b.

EMF 50 WASTE GAS (High Range) fa' u low.

4

c. -W'aste ga: analyzer high oxygen in discharge line, d.

Waste gas decay tank high pressure.

4 QUESTION: 024- (1.00)

Given the following conditions:

Reactor power is 60%.

-Loop 10 Delta T indicates LOW.

-Loop'lC Tave indicates HIGH.

WHICH ONE (1) of the following RTO failures cause these indications?

a.

Thot failed high.

b.

Thot failed low, c.

Tcold failed high.

d.

Teold failed low.

QUESTION:.025 (1.00)

.WHICH ONE-(1) of the following sources discharges into the NCDT?

a.

Reactor vessel 0-Ring leakoff.

b.

NV letdown relief valve downstream of letdown orifice (NV-6).

c.

NV letdown relief valve downstream of letdown heat exchanger (NV-h 156).

d.

NI pump suction relief valves.

I

l m

' REACTOR OPERATOR.

Page 15-1 4

i QUESTION: 026 (1.00) o At WHICH ONE (1) of the following NC system pressures would a CLA tank level 1

decrease first be noted following a large break LOCA?

)

a.

780 psig i

b.

680 psig c.

580 psig d.

480 psig.

QUESTION: 027 (1.00)

.WHICH ONE-(1) of.the following conditions describes the Technical Specification 3.5.5, " Refueling Water Storage Tank," requirement for.an operable RWST in MODE 17 Borated Water.

Boron Solution Volume Concentration Temperature a.

375,000 gallons 2050 ppm 95 F.

b.-

375,000 gallons 1950 ppm 95 F t

c.

395,000 gallons 2050 ppm 65 F

~

d.-

395,000 gallons 1950 ppm 65 F X

QUESTION: 028 (1.00)

WHICH ONE (1);of th6 following sets of conditions is indicative of pump runout?

L a.

High disci r9e pressure, high flow, and high power requirements.

b.

High-c+h ic pressure, low flow, and low power requirements.

1 l

c.

Low discharge pressure, high flow, and low power requirements.

d.

Low discharge ;,)ressure, high flow, and high power requirements.

I REACTOR OPERATOR' Pagt'16 1

a QUESTION: _029 (1.00) i WHICH ONE (1) of the following is the set of pressures that will energize-the "C" (proportional) and backup heaters, respectively? ASSUME pressurizer i

pressure control is set for normal operation.

a.

2280 ps'y, 2210 psig b.

2250 psig.

2210 psig c.

2280 psig, 2250 psig

.d.

2250 psig,. 2240 psig J

1

-QUESTION: 030 (1.00)

Given the following conditions:

-Reactor power is 100%.

-Pressurizer spray control is in AUTO.

Pressurizer spray valves open.

WHICH ONE (1); of the following is the response of the PORVs and spray valves

-if pressurizer master controller setpoint is inadvertently changed to 2370 psig? ASSUME a step. change in the setpoint and that pressurizer pressure control remains in automatic.

,,,,. % n ar k r.+-

The. automatic responses of the PORVs and spray valves will be:

g a.

PORV NC 34 opens, spray valves remain open, b.

PORVs NC 32, 54, a,nd 35 retain closed, spray valves remain open.

c.

PODW NC 32, 34, and 36 remain closed, spray valves close.

d.

C/Ws NC 32 and NC 36 open, spray valves close.

Y

-REACTOR OPERATOR Page 17

-QUESTION: 031 (1.00)

WHICH ONE (1) of. the following describes the reason for the pressurizer program level changes?

a.

Pi vides an adequate margin between the program level and the high level reactor trip, b.

Maintains a constant mass in the reactor coolant system reducing the need to increase and decrease charging and letdown for changing reactor power levels, c.

Provides an adequate margin between program level and low level heater shutoff and letdown isolation, d.

Designed to permit the pressurizer system to properly function and maintain a constant pressure at full power.

QUESTION: 032 (1.00)

WHICH ONE (1) of the following statements describes a trip associated with e

the P 8 permissive?

a.

Source range reactor trip b.

Pressurizer high pressure trip c.

Single loop -low coolant flow trip d.

NC pump bus undervoltage trip

(:

REACTOR OPERATOR Page 18 L

QUESTION: 033 (1.00)

WHICH ONE (1) of the following will result in clearing the " ROD AT BOTTOM" annunciator as the control banks are withdrawn?

a.

Bank A reaches 7 steps.

~

i b.

Bank B reaches 7 steps.

c.

Bank C reaches 7 steps.

J.

Bank D reaches 7 steps.

i QUESTION: C34 (1.00) i WHICH ONE (1) of the following is an input to the ROD BANK LOW LOW alarm?

a.

Auctioneered high Tave b.

Auctioneered high Tref c.

Auctioneered high NI power level d.

Auctioneered high delta T f

4

[

a 1

9 h

h l

.,_-m

,~, _..

j REACTOR OPERATOR Page 19 i

QUESTION: 035 (1.00)

WHICH ONE (1) of the following statements contains logic that would result in containment spray actuation? ASSUMF Containment Spray / Phase B has actuated.

]

a.

Manual sctuation with Contait, int Spray / Phase B actuation signal 1

CPCS at 0.0 psig j

b.

Manual' actuation with Containment Spray / Phase B reset CPCS at 0.40 psig

]

c.

Auto actuation with.

1 Containment Spray / Phase B actuation signal CPCS at 0.28 psig-1 d.

Auto actuation with Containment Spray / Phase B reset j

CPCS at 0.40 psig j

QUESTION: 036.(1.00)

WHICH ONE (1) of the following sets of signals are used to control the feedwater bypass flow control valve when in AUTOMATIC?

a.

Steam header pressure, feed pump discharge pressure, steam flow, b.

Steam generator-level, programmed steam generator level, auctioneered high nuclear power.-

c.

Steam generator level, feed pump discharge pressure, steam flow.

L d.

Steam header pressure, programmed steam generator level, auctioneered high nuclear power.

l l

l l.

l 3

f 6

k

.-...-------.---r

,~

n

,m.,

u REACTOR OPERATOR Page 20

. i a

I

-QUESTION:.037 (1.00) l l

WHICH ONE (1) of the following states the effects on reactivity due to changes in secondary plant parameters? ASSUME the moderator temperature i

coefficient is negative.

a.

An increase in feedwater temperature results in a positive O etivity addition.

1 b.

An increase in feedwater flow results in a negative reactivity I

. addition.

o c.

A decrease in steam flow results in a negative reactivity addition.

t d.

A decrease in condensate. temperature results in a negative reactivity addition.

i l

QUESTION: 038 (1.00)

WHICH ONE (1) of the following describes the conditions which will cause a

+

rapid transfer on the IATB 6.9 KV bus supply breakers?

]

a.

lA, IB,.and ID NCPs in operation, and 1ATA and 1ATB out of synchronism.

.b.

lA, 1C, and ID N Ds in operation, and IATA and 1ATB out of synchronism.

j

'1A, IC, and ID NCPs in operation,.and 1ATA and 1ATB in synchronism.

[

.d.

lA, 18, an.d ID NCPs in operation, and i

1ATA and 1ATB in synchronism.

l l

I l:

L

REACTOR OPERATOR Page 21 l,

QUESTION: 039 (1.00) l t.

When. manually synchronizing the generator to the grid, OP/1/A/6300/01, TurbineGeneratorOperation,*directstheoperatortoadjustthegenerator speed-until the hand on the synchroscope moves slowly in the " fast direction.

WHICH ONE (1) of the following parameters are indicated by the synchroscope?.

i a.

Current and voltage differences, b.

Frequency and currer.t differences.

c.

Frequency and phase differences.

.d.

Current and phase differences.

QUESTION' 040 (1.00)

WHICH Ohi (1) of'the following statements describe a power cabinet NON URGENT FAILURE in the rod control system?

a.

Coil current does not match the ordered current.

b.

Zere current ordered simultaneously to moveable and stationary coil.

c.

Zero current from a DC power supply in a power cabinet.

d.

Current is present to non selected rod or rod groups moveable and lift coils.

b

.7 I

P s

j 0 REACTOR OPERATOR' Page 22 QUESTION: 041 (1.00)

I WHICH ONE (1) of the following is the MINIMUM voltage and frequency which will allow the diesel generator to accept the loads assigned by the 3equencer i

during an AUTOMATIC start?

a.

75% voltage and 75% frequency b.

75% voltage and 95% frequency c.

95% voltage and 75% frequency f

d.

95% voltage and 95% frequency QUESTION: 042 ~(1.00)

WHICH ONE (1) of the following completes the statement?

The diesel generator must be able to start and attain rated speed within:

a.

5 seconds r

b.

11 seconds c.

20 seconds d.

30 seconds

'QUESTIONi043 (1.00)

WHICH ONE (1) of the following discharges into the pressurizir relief tank?

a.

Alternate flowpath for excess letdown l

b.

PORV INC36B valve packing leakoff c.

NS pump suction relief valve l

d.

NC pump seal #2 leakoff l-L l -.

~

REACTOR OPERATOR Page 23 QUESTION: 044 (1.00)

WHICH ONE.(1) of the following loads is supplied by the KC system?

a.

Waste gas compressors b.

Diesel Generator cooling water heat exchanger

{

c.

VC chillers d.

Containment ventilation units i

. QUESTION: 045 (1.00)-

Given the following conditions:

f

-Reactor power is 100%.

KC pumps B1 and B2 are supplying system loads.

-Safety injection signal is received.

WHICH ONE (1) of the following statements describe the response of the KC l

system?

a.

KC pumps B1 and B2 will continue to run, KC pumps Al and'A2 will auto start'.

l l

l b.

KC pumps B1 and B2 will be shed from their busses, then the LOCA early sequencer will start KC pumps A1, A2, B1, and B2, c.

KC pumps B1 and B2 will be shed from their busses, then the LOCA accelerated sequencer will start KC pumps Al and A2.

i l-d.

KC pumps B1 and B2 will continue to run, KC pumps Al and A2 will not start.

o l

,b n.

,-e-.-,-

REACTOR OPERATOR Page 24 i

QUESTION: 046 '(1.00) i 1

WHICH ONE (1) of the following is the time delay for the automatic start of i

the hydrogen skimmer fans on a phase "B" actuation?

a.

10 seconds l

b.

30 seconds

c.

7 minutes i

d.

10 minutes QUESTION: 047 (1.00) j WHICH ONE (1) of the following choices completes the statement?

t

.The atmospheric steam dumps are designed to handle (1)

% of total. steam flow, and the condenser steam dumps are designed to i

handle (2)

% of total steam flow, a.

(1)_35,(2)45 b.

(1) 35, (2) 55 c.

(1) 45, (2) 40 d.

(1) 55, (2) 35 QUESTION: 048 (1.00)

I WHICH ONE (1) of the following loads is isolated from the RN after a safety injection?

a.

NV(PDP) coolers b.

VC chillers c.

KD heat exchanger d.

NC pump motor air cooler v

4

+

~n----

.-,--v..-

w

~

REACTOR OPERATOR Page 25 QUESTION: 049 (1.00) j WHICH ONE (1) of the following will AUTOHATICALLY isolate containment ventilation?

a.

Phase "B" isolation b.

1 EMF 36, unit vent gas low range trip c.

2 EMF 37, unit vent iodine high range trip 1

d.

Safety injection

)

QUESif0N: 050 (1.00)

)

WHICH ONE (1) of the following describes the reason for ensuring control of i

steam generator levels for natural circulation?

a.

To prevent unnecessary positive or negative rear ^fvity additions due to varying cooldown rates.

'b.

To prevent a Technical Specification violation due to an excessive cooldown rate.

1 c.

To provide continuous flow to the steam generators to ensure steam generator tube integrity.

-d.

To provide a stable heat sink for decay heat removal at the steam

_ generator no-load level.

C

+

L b

I a

v

~

5 REACTOR OPERATOR Page 26 i

QUESTION: 051 (1.00)

WHICH ONE (1) of the following groups of parameters indicates the existence of adequate natural circulation?

a.

-Steam pressures - stable or decreasing.

-Core exit T/C's - stable or increasing.

-NCS cold leg temperatures - near saturation temperature for steam pressure.

b.

-Steam pressures - stable or increasing.

-NCS subcooling - more subcooled than instrument error.

-NCS hot leg temperatures - stable or decreasing.

c.

Steam pressures stable or increasing.

-NCS pressure - stable or decreasing.

-NCS cold leg temperatures - near saturation temperature for NCS

pressure, d.

-Steam 3ressures - stsble or decreasing.

-NCS su) cooling - more subcooled than instrument error.

-NCS cold leg temperatures - near saturation for steam pressure.

QUESTION: 052 (1.00)

WHICH.ONE (1) of the following describes a condition that requires emergency bor. tion according to AP/1/A/5500/38, " Emergency Boration?"

a.

Less than 2000 ppm boron in MODE 5.

b.

C0KTROL ROD BANK LO-LO LIMIT alarm in MODE 1.

c. -Three out of four loop Tavgs reach 540 F after reactor trip.

d.

Failure of a single control rod to drop following reactor trip.

L

)

i B

l.

c REACTOR OPERATOR Page 27 QUESTION: 053 (1.00)

Given the following conditions:

i A normal plant cooldown is in progress.

-The computer alarm for the KC surge tank indicates a need for makeup from the makeup demineralized water system.

t

-Locally, there is no cause for the problem.

-The water level in the surge tank compartment lA is slowly DECREASING.

-The associated makeup valve to the surge tank compartment lA is fully open.

WHICH ONE (1) of the following is the cause of the problem?

a.

There is a leak in an NCP thermal barrier heat exchanger, b.

A leak is present in a KC heat exchanger, c.

A leak is present in the letdown heat exchanger, d.

The plant is being cooled down at an excessively fast rate.

QUESTION: 054 (1.00)

WHICH ONE (1) of the following describes an RNO of the Immediate Action required in AP/1/A/5500/ll, " Pressurizer Pressure Anomalies" if pressurizer pressure is DECREASING and a pressurizer spray valve will NOT close?

a.

Trip reactor.

b.

Decrease reactor power to less than P-7.

c.

Decrease reactor power to less than P-8.

d.

Initiate SI.

l 1

i

~

REACTOR OPERATOR Page 28 J

i QUESTION: 055 (1.00)

Given the following coi.Jitions:

A steam line break has occurred.

EP/1/A/5000/14.1,

Response _ to Imminent Pressurized Thermal Shock Conditions," step 11 has been completed.

1 The CAUTION above step 12 states, " Steps 12-17 provide for a rapid SI termination for pressurized thermal shock events...* and directs terminating SI when the criteria is met.

WHICH ONE (1) of the following is NOT a reason for terminating SI?

a.

SI may be contributing to the cooldown, b.

Inventory needs to be made up faster than 51 can.

c.

Poor mixing of S1 will increase thermal stress.

j d.

SI may cause the plant to repressurize.

f QUESTION: 056 (1.00) i WHICH ONE (1) of the following is the basis for isolating all feedwater to a faulted steam generator per EP/1/A/5000/03, " Steam Line Break Outside l

Containment" step 3?

a.

To reduce the probability of occurrence of a steam generator tube rupture in the faulted steam generator.

b.

To limit the cooldown by limiting the blowdown of the faulted steam generator.

l c.

To prevent all feedwater flow from entering the faulted steam generator and filling the generator, causing the PORV's to lift.

d.

To allow raising the faulted steam generator PORV setpoint to reduce f

environmental releases.

r v

v P

s e

m y

y

REACTOR OPERATOR Page 29 QUESTION: 057 (1.00)

Given the following conditions:

l

-The, plant has experienced a main steamline rupture and the operators have l

entered EP/1/A/5000/14.1, " Response to Imminent Pressurized Thermal Shock i

Conditions."

[

WHICH ONE (1) of the following reflects the major actions of the above

[

procedure?

a.

Maintain NC system cooldown rate Maintain NC system pr ssure b.

Maintain NC. system cooldown rate Depressurize NC system c.

Stop NC system cooldown t

Maintain NC system pressure d.

Stop NC. system cooldown Depressurize NC system QUESTION: 058 (1.00)

Which ONE (1) of the following is the pressure at which containment conditions are considered adverse per EP/1/A/5000/12. " Core Cooling?"

t a.

0.35 psig j

b.

1.0 psig c.

1.5 psig d.

3.0 psig P

---n---..

)

REACTOR OPERATOR Page 30 QUESTION: 059 (1.00) j

.Given the following plant conditions:

1

- Reactor / Turbine power 39%.

1

- CONDENSER LO VACUUM (PRE TRIP) lit.

- Condenser vacuum - 18 inches.

)

i WHICH ONE (1) the following describes the Immediate Actions for the above conditions?

a.

Manually trip the reactor and turbine and refer to EP/1/A/5000/01,

)

" Reactor Trip of Safety Injection."

4

'h.

Var' c'r ejectors operating properly, add more air ejectors if 4

vm u'npatch operator to locally align and start main vacuum

.sd "B".

e c

i

c..

.1, w A ernouncement, reduce turbine load, start more NC pumps,

- o

, ctors operating properiv, and add more air ejectors.

J d.

En c. --

,per number of circulating pumps are operating, and manually trip the turbine if generator load decreases to less than 35% of rated load.

t QUESTION: 060- (1.00)

WHICH ONE (1) of the following is an Immediate Action for EP/1/A/5000/09,-

Loss of All AC Power"?

a.

Place KC pump switches in pullout position.

b.

Check if letdown isolation valves are closed.

c.

Send an operator to locally start DG.

d.

Send an operator to standby shutdown facility to start NC pump seal

-injection.

t

{

\\:

REACTOR OPERATOR Page 31 j

1 QUESTION: 061 (1.00)

WHICH ONE (1) of the following is the MINIMUM time limit battery EVCD (for

' vital instrument-and control power) is sized to carry all its DC loads?

a.

12 minutes b.

30 minutes c.

45 minutes d.

60 minutes QUESTION: 062 (1.00)'

WHICH ONE (1) of the following is the order for the loading of the blackout, sequencer?

l. RN pumps

2. CA pumps

3. ELXC/ELXD a.

1, 2, 3 b.

2, 3, I j

c.

3, 2, I

'd.

3, 1, 2.

4 h

?

i L

J

REACTOR OPERATOR Page 32 QUESTION: 063 (1.00)

WHICH ONE (1) of the following are immediate Actioits for loss of IETB per AP/1/A/5500/07, " Loss of Electrical Power, Case I, Loss of IETA or IETB7" r

a.

Verify lA RN pump running.

Notify Unit 2 operator to start 2A RN Pump.

b.

Verify IB RN pump -running.

1 Notify Unit 2 operato? to start 2A RN Pump.

c.

Verify 1A RN pump - running.

Notify Unit 2 operator to start 2B RN Pump.

d.

Verify IB RN pump - running.

Notify Unit 2 operator to start 2B RN Pump.

QUESTION: 064 (1.00)

WHICH ONE (1) of the following statements describes containment sump isolation valves following an SI?

a.

Will not open unless the ND pump suction valves (from n!ST) are closed.

l-b.

Will not open unless the vtMnment sump reaches the interlock 1

level.

I c.

Will automatically open if the ND pump suction valves (from FWST) are opened.

d.

May be manually opened after the FWST low level alarm.

H l

l 1

.V

. REACTOR OPERATOR

.Page 33 e

il

QUEST 10N:f065.(1.00)

WHICH ONE (1) of the following represents a red path ior core cooling per EP-12.1." Response to Inadequate Core. cooling," if subcooling is -10 F?

NCPs RVLIS Running Core Exit Temperature Vessel 'Leve' STEADY AT.

a.

None 750 F 40 %

-b.

None 850 F 60 %

u c.

lA 750 F 40 %

1 d.

IB 850 F 60 %

h b,

. QUESTION: 066 -(1.00)-

. HICH ONE (1) of the following describes the Immediate Actic;i to ba taken L

W per AP/1/A/5500/14, " Rod Control-Malfunctions, Case II Continuous Insertion / Withdrawal Of A Control' Rod Bank?"

a.

Initiete. emergency boration to counteract the positive reactivity addition.

i, H

~ b.

Place rods 'in Bank D Select 'and drive rods in until Tavg and Tref are

]

matched.

I c.

Place rod bank selector switch in manual and-verify rod motion has

~ topped.

s d.: Manually _ initiate SI and perform EP/1/A/5000/01, " Reactor Trip or Safety Injection."

'l

-l l

a t

I a

l'

,,_3

p REACTOR OPERATOR Page 34 QUESTION: 067 (1.00)

WHICH ONE (1) of the following selections is NOT an indication of continuous rod withdrawal?

a.

P/R OVER POWER R00 STOP b.

Reactor Power - Turbine Power Mismatch c.

R0D CONTROL URGENT FAILURE d.

Tave Deviation QUESTION: 068 (1.00)

Given the following conditions:

- Reactor power is 35%.

- Raising power during startup.

- RPI AT BOTTOM R0D DROP alarms.

- Rod bottom light for rod C-5 lights.

WHICH ONE (1) of the following is an Immediate Actior?

a.

Manually adjust control bank D to maintain power.

b.

Decrease turbine load to below the P-7 reactor trb.

c.

Place the control rod bank selector switch in manual, d.

Trip the.eactor if Teve and Tref deviate by more than 8 F.

g

..,7 REACTOR'OPERATORL

- Page 35 I

1 s

c QUESTION:!069 (1.00)

Given the following conditions:

t-

+

'-Reactor-power is 35%.

.-One rod is' misaligned below its group by 15 steps.-

r WHICH ONE (1). of the following actions would, per AP/1/A/5500/14, " Control

' Rod Malfunctions, Case:IV Control Rod Misalignment" provide indication that

?,

w-the' rod will move if required?

i

= a.. Tave Tref mismatch within 1 degree F with the Bank-Selector switch in-1 t

t

auto,

b. : Check the -indicator fuses for the affected rod at the rod control cabinets.

Drive.the affected bank inward ten steps observing that the affected

..w c.

rod moves.

I d.: Verify that na URGENT FAILURE alarm exists for the affected bank and that lift coils are connected, j

j

-QUEST 10N:1070'.(1.00)

The: Computer-is.out:of service and you are directed to determine the 4

f

subcooling.' margin for these NCS parameters:-

1

-Low range pressure is 440 psig.

~

' Thot'.is-450 F.

-TcoldL.is 430 F.

-Tave is 440tF.

Ll LT

>The subcooling margin is:

n C.:gdegreesF' q

-b.-

eg'rees F j

K.

c.

degrees F.

+ 13 -

['

d.o #27" degrees F t

g

.\\.

i< '

j l ',5 5 1 j.1

(

, 's L'

{,'L

]!)

~;j,

8

n RK

h. &,

s f,

(REACTOR OPERATOR Page.36 a

a

-QUESTION:"071 (l '. 00) '

a

' WHICH ONE.(1) of the following-indications has-an alterr,;te -limit during.

adverse cantainment?.

(

a.

Core exit thermocouples l

b NCS wide range RTDs

-(,

NCS pressures h'

!d Pressurizer levels i

i

+

OL QUESTION: 072 (1.00)

WHICH ONE (1) off the following statements is the basis for tripping the NC i

pumps when foldout page trip cr.iteria in-EP/1/A/5000/01, " Reactor. Trip or Safety Injection," are presente a'

Prevent-pump runout in the event of a small. break LOCA..

i

.b.

Ensure-adequate core cooling during a sr.all break LOCA.

j 4

c.

Prevent loss of suction to a NC pumr, during a large break LOCA.

d.

Ensure core reflood during a -lr.cge break LOCA.-

a y

(

6 Y

1 '

\\E f

Y r

H h*'

b_

(f ? p r '

p 4 }

7 x.

/

E j;[Ij[ '

hy^t;..

t!N(. ?

^ '

\\

a c

f;.

1

,'y;l REACTOR-OPERATOR Page 371 j

r, w

-v

,1,

t' i QUESTION:. 073, (1.00).

YGiven the following conditions:-

-a pressurizer PORV is leaking 21 gpm to the PRT-j

.-All other system components are normal a

..WHICH ONE (1) oflthe following conditions exist per Technical Specification 3.4.6.2, " Operational Leakage?"

j c

a'.

IDENTIFIED LEAKAGE ~1imit has been exceeded and a' shutdown;is required.

]

^

Lb.

IDENTIFIED LEAKAGE is less than the shutdown limit.

c.

Reactor. Coolant System Pressure -Isolation Valv9 leakage limit has been exceeded and a shutdown.is required, d.

Reactor Caolant System Pressure Isolation Valve. leakage is less than o

the shutdown limit, a

l.

i a

1\\

,f p

t:

s

. QUESTION::074 (1.00)-

l-L' WHICH ONE (1) of the following is sequence of the AUTOMATIC LOCA sequencer -

actions?.

1. Starts diesel =

.i H.

2; Verifies Bus Voltage..

a k

13. Loads a-safety-injection pump L;

a.

I ', - 2, -' 3 t

.l L,

b.

2, 3,,.1 c >. : 3, -. I,. 2

[

('

'd.

2, ' 1, 3 '

i I.

'fak5 Dh. '

?

^

o v

REACTOR OPERATOR Page 38 1

J QUESTION: 075 (1~00)

Given the following condit$ons:

1

- Reactor power is 100%

- Pressurizer level is DECREASING H

- Back-up heaters are energized-

Charging flow INCREASING 4

- VCT levt.1 is 12".

J

- PRT level is 88%

--Contai.1 ment sump pump has' started The CVCS letdo <n isolation valves.have just CLOSED due to LOW pressurizer leiel and pressurizer level is now steady.

WHICH 0NE (1) orthe following identifies the location of the leak?

a.

Letdown piping b.

Charging piping 5

c. ' Regenerative heat exchanger twoc. /enk,qe_

r d.

Seal' water return header relief valve stuck open

.(

QUESTION: 076 (1.00)'

'WHICH ONE'(1) of.the following describes AMSAC automatic actions upon actuation?

a.

Trips turbine.

l Closes S/G sample valves.,

Starts MD CA' pumps, b.

Trips turbine.

. Closes S/G blowdown lines.

Starts TD CA pumps.

.c.

Trips MSIV and bypass valves.

Closes-S/G sample valves.

Starts TD CA pump.

d.

Trips MSIV.and bypass valves.

Closes S/G. blowdown valves.

Starts MD CA pumps.

i c.

y

i REACTOR OPERATOR Page 39 l

f

'QilESTION:-077 (1.00)

'Th'e following' plant conditions exist:

-A valid' reactor trip signal has been received.

.-Rod bottom lights are NOT lit and flux is NOT decreasing.

-The turbine is tripped, i

-The CF pumps are _ running and NC' loop ter.perature is stable.

1

-Emergency boration is in progress.

l

-NC system pressure is'2350 psig.-

1 WHICH ONE (1) of the following represents the action to be~taken and the 4

basis for-those actions to reduce NC system pressure per EP/a/A/5000/II.1,

" Response to Nuclear Power Generation /ATWS"?

a.

Depressurize the NC system with pressurizer.P0RVs to-allow enough borated water flow to insure addition of negative reactivity to the Core.

b.

Depressurire the NC system with pressurizer PORVs to prevent a rapid overprett. iration trans.3nt and begir a controlled cooldown.

1 c._

Depressu',9;, '.ne NC system with pressurizer : prays to allow enough borated waio:- flow to-insure addition of-negative reactivity to the Core.

d.

Depressurize the NC system with pressurizer sprays to prevent a rapid-overpressurization transient and begin a controlled cooldown.

- QUESTION: 078 _(1.00)

WHICH ONE (1) of the following conditions indicates an intermediate range channel' detector which has had a loss of compensating voltage?

a.

Some neutron flux and all gamma flux signals are oeing subtracted from the~ outer detector output.

.b.

Detector output will read less than actual neutron flux level.

c.' Detector output will read higher than-actual neutron flux level.

ed.

Source range detectors may-be automatically re-energized too early.

,e r

r l

1

t 3

e.

REACTOR OPERATOR-

'Page 40:

Y

}

lQUESTION:079 (1.00)

^

The following plant-conditions' exist '

L

.)

j

-Reactor power is IX10E-6 amps.

L

-N 35 Intermediate. Range channel has failed LOW.

-A reactor startup'is in progress.

i

- WHICH ONE (1)L of-the following actions is correct per Technical Specification 3.3.1, " Reactor. Trip System Instrumentation"?

a.

Restore inoperable channe' prior to exceeding P-6.

l

b.. Restore inoperable channel prior to-exceeding.5% power.

c.

Restore inoperable channel prior to exceeding 10% power.

1 l

l d.-

Bypass the inoperable channel and continue with reactor startup..

. QUESTION:- 080-(1.00)

+

1The first Immediate Action of:AP/1/A/5500/10, "NC System Leakage.Within Capacity' of Both NV ' umps," is to " Check pzr level - AT ~0R INCREASING T0

-PROGRAHMED LEVEL."

1 WHICH ONE -(1) of the following. lists the first four Response Not Obtaineds?.

1

.a.

Verify pressurizer spray flow at a minimum Open' seal injection flow control. valve-iStart NV pump.

j Reduce letdown

]

-b.

Terify charging line flow control valve opening m'

Open seal. injection flow control valve cI Start NV pump Reduce letdown-l

c. ? Verify charging'line flow control valve ;pening Start NV pump

'Open seal injection flow control valve JVerify pressurizer spray flow at a minimum W

d. Verify charging line_ flow control valve openiro Verify preasurizer spray flow at a minimum

+

Open seal injection flow control valve Redt.se letdown t

j.b n

't H u c,,

s

REACTOR' OPERATOR!

Page 41-QUESTION: 081 (1.00) l WHICH ONE (1) of the following describes the result of feeding a. hot, dry

. steam generator after a loss of all feedwater?

r a.-

Steam generator failure due to thermal stresses.

.b.

Steam generator failure due to intergranular stress corrosion

t. racking.

l

-c.

Overcooling event due to excessive feeding of the steam generator.

d.

Overcooling event due to excessive steaming of the steam generator.

+

I QUESTION: 082 (1.00)

)

-WHICH ONE (1)-of the:following statements describes the automatic actions of

'the Process Radiation Monitor EMF-46B, Component Cooling B, HIGH radiation

. al arm.

p a.' The KC surge-tank vent is automatically closed.

D L

b.

The' regenerative heat exchanger is isolated.

f N

1 c.

The excess letdown heat exchanger is isolated.

d The letdown heat exchanger is isolated.

,I.

a l

l t

y b1

)

\\r.

i l.

I s

.m._,__m....__m__..m._m..m__.______m___

m

REACTOR OPERATOR Page142 I

QUEST 10N:;083, (1.00)

If pressurizer -level control select switch is-in the 3-2 position when the reference--leg for. level III develops a leak, WHICH ONE (I) of the.following describes-plant response?

Level II' Level III VCT LEVEL PZR LVL INDICATION' PZR LVL-INDICATION

a. ' INCREASING DECREASING INCREASING b.

DECREASING-INCREASING 1MCREASING c.

INCREASING-DECREASING DECRET. SING d.

DECREASING INCREASING DECREASING

-QUESTION: 084- (1.00).

Given the following conditions:

-SPENT FUEL P0OL LEVEL LOW is lit.-

-SPENT FUEL P00L' BUILDING BRIDGE EMF-17 is lit.

-Level is' decreasing in refueling canal.

WHICH ONE (1). of the-following is the final. required position for each piece-of' equipment according to AP/l/A/5500/40, " Loss of Refueling Canal Level "

t Immediate Actions? ASSUME a= fuel assembly is in each piece of equipment.

Upender in Reactor.

Spent

New Spent Building-Fuel Fuel Fuel Manipulator Manipulator.

Elevator Pool Crane Crane a.

las is fully down fully down fully down

- b.

fully down as is-fully dewn fully down c.

fully down fully down as is

-fully down d.

fully down fully down fully down as is q

f i

)

J n

9

[ '

L NEACTOP. OPERATOR Page:43-t t

QUESTION:'085 (1.00)

Given the. following conditions:

- Reactor power is 100%.

-: Control rod drive selector in MANUAL.

4

- Bus Line IB is lost.

WHICH ONE- (1) of the following describes an immediate action for this load a

rejection case?

E Verify turbine speed decreases to 1800 RPM.

If turbine has NOT a..

decreased to 1800-RPM, control turbine at 1800 RPM.

b.

Verify turbine impulse pressure-DECREASES to 410 psig.

If impulse pressure has NOT decreased to 410 psig, control turbine at 410 psig.

i t

V c.

Verify TAVE DECREASING.

If Tave has NOT decreased, MANUALLY control

' turbine AND decrease load.

'd, Verify control ' rod: drive selector in MANUAL. Verify turbine load is decreasing.- -If turbine load is NOT decreasing, MANUALLY decrease

.i turbine.

'r

-QUESTION: 086- (1.00)

-WHICH ONE (1) of the following statements describe when a tag sticker is

. REQUIRED due to the safety 4 tag. obscuring other indications or controls?

ta.

Red' tag on'the' local diesel generator alarm panel.

q b.

Yellow-tag on control room switches, c;

Yellow-tag on local ~ diese1' generator local-remote control panel.

t d.' White tag on control room panel.

it i

{

L I

f

' iY,i' t

/Q@ !F D.

m

.o.

,ww

REACTOR OPERATOR Page 44 I

QUESTION: 087 :(1.00)

Given the.follocing conditions:

-Motor driven (MD) CA pump has been removed from service for repair.

-Maintenance has completed repairs.

-Prior to returning the CA pump to service, the.CA pump fails testing with the same symptoms.

WHICH ONE (1) of the following statements describes the handling of the safety tags removed and their stubs?'

. a.

The tags-and stubs should be marked " VOID" and filed.

b.

Tags and stubs should be retained for six months-and then discarded as the wort supervisor sees fit, c.

The tags should be replaced on the components and the stub re-used.-

d.

Tags and stubs should'be matched and filed in the Tag Lifted for Testing File (TLTF).

QUESTION: 088 (1.00)

1. hen replacing a Human Red Tag, WHICH ONE (1) of the'following lists of individuals must. agree upon the replacement Human Red Tag?

2. Shift, supervisor /assistantshiftsupervisor

' 2 Werk supervisor-

3. Person performing work

. 4. Supervisor with operational responsibility for the component '

a.

1, 2, and 3 b.

2, 3, and 4 c.

1,1 3, and 4 d.

1, 2, and 4 t

)

REACTOR OPERATOR--

Page 45:

(QUESTION: 089'(1.00).

.WHICH of= the following selections reflect those individual responsible for identifying. UNQUALIFIED personnel to do independent verification n valves 3

l essential to. safety according to OMP l-6, " independent Verification ?

1. Shift supervisor

/

2. Unit supervisor

3. McGuire station training manager

~4. Nuclear equipment operator a.

1,-2, 3 j

]!

b.

2, 3, 4 c.-

1, 2, 4 l

d.

1, 3, 4.-

j

_Il QUESTION: 090,(1.00)

{

' WHICH ONE (1) of the following describes:how sn independent verification of 1

position. for a-manually operated valve in i.he THROTTLL_ position is: done?

a.

Move the valve slightly in,the closed direction and then return it to

-its original position..

b.

Inspect the last valve lineup sheet for verification signature and 1

compare recorded' valve position.with the-required position.

c.

Observe the operator initially place the valve _in the position that the valve is to be throttled to.'

'd.

Compare visual observation of stem or indicator position with the

. required position.

j l'

i 1

i e

...=

e REACTOR OPERATOR.

Page 46 QUESTION: 091 (1.00)

-WHICH ONE (1) of the following describes the relationship between the Unit Supervisor log, PT log, and the Tech Spec Action Item log books?

a.

The Unit Suoervisor log should contain nearly all the information in the Tech Spec Action item log book. The PT. log is independent of the other two, b.

The Tech Spec Action Item log is the controlling log book. The PT log is for specific tests and the Unit Supervisors log is for general information, c.

The PT log is for recording Tech Spec CALIBRATIONS, TESTS, and CHECKS.

Most significant information from this log should be reported in either the Tech Spec Action Item log or the Unit Supervisor log, d.

The Unit Supervisor log is the controlling log.

The other two logs are for the convenience of the Unit Supervisor log and duplication of information in either-the PT log or the Tech Spec Action Item log is not necessary, 4

).

g

J REACTOR OPERATOR Page 47

]

J 4

QUESTION: 092 (1.00)

I Given the following conditions:

-Startup is in progress.

-Heatup rate was 60 F for the last hour.

-0P/1/A/6100/01 " Controlling Procedure for Unit Startup," has a 50 F/ hour hcatup rate limit.

WHICH 0NE (1) of the following describes required operator actions?

a.

If the Technical Specification LCO is not exceeded, the heatup rate I

will be logged in the Unit Supervisor log.

If Tech Spec heatup rate is exceeded, the reactor is to be in at least HOT STANDBY within 6 i

hours, b.

Immediately shut the reactor down.

Get N.; permission before restart.

c.. Hold power while a calometric is completed to' verify that the. limit was exceeded.

If the limit was not exceeded, continue startup.

If the limit was exceeded, return to the limit within one hour or terminate startup.

d.

Note that the procedural limit was exceeded in the procedure.

Report exceeding the limit to the Control Room SRO.

i QUESTION: 093 (1.00)

WHICH ONE (1).of the following is the MINIMUM number of Fire Brigade members required to be' maintained onsite?

E l

a.

3 b.

5 c.

7 d.

9' i

'{

l-i t

k lm

7kEACTOROPERATOR-Page 48

QUESTION: 094 (1.00)

I Ah R0 has the Duke Powr.r' Company radiation limit for the quarter approved for.

'1000 mrem for Job 1 on Unit 1.

Job 1 is cancelled with no exposure taken.

However the same job is to be;done on Unit 2.

ASSUME the RO's previous

. radiation for the quarter was zero (0).

WHICH 0NE-(1) of the fellowing is the RO's exposure limit for' the same-job on Unit 27 r,

a.

150 mrem b.

200 mrem c.

500 mrem d.

1000' mrem o

o

N I

i fI I

e l

yC a

,e l \\ ';

's '

y

'. ~

,f f -

~s

,e

[, REACTOR OPERATOR

'Page 49'-

QUESTION: J95 (1.00).

s i

Given the following condition:

gl ~

l l'

- A~ pint source in the auxiliary building is reading 500 mRein/hr 1

at a distance of two-(2) feet.

Two (2) options exist to complete a mandatory. assignment near this radiation source.

- OPTION 1:

Operator X can perform the assignment in thirty minutes working at a distance of-four (4) feet from the point source.

-OPTION'2: -Operators:Y and Z, who have been trained in the use of special extension tooling, can perform the same. task in 75 minutes at a c81 stance of eight-(8) feet from the

j

-point ~ source.

. WHICH ONE (1).of the f,lo ing options is preferable and consistent with the -

i the facility ALARA an

~

_m

- a.

Option 1 should be used because of the lower exposure.

L b

,b.. Option.2 !should be~ used because of'the lower exposure.

1 i

c.

Option 1 should be used-because fewer personnel and hours are l

' involved.

1;

.d.

Option 2. should be used because a reduced dose rate per -individual ic important.

r

.i

~

-1 QUESTION: 096 (1.00)

MWHICH ONE-(l)~of the following is the MINIMUM number.of escorts required in

'each respective area for a group of 16 visitors?

.l o

Protected Area-Vital Area-a.-

1 2

1

(

b.-

2-2

[

-c.

2 4

('

d.

4 4

a

>\\

m.

'5 t

6

.}

s !!-

~

's 61

,i q

'(

j REACTOR ~ OPERATOR:

uPage 50I g

l

ll

QUESTION: ;097i(1.00);

m WHICH ONE (1)' of the following is the LOWEST emergency classii'ication that

' REQUIRES activation of the. Technical Support Center?

l a.

Unusual event b.

Alert 4

_c.

-Site area emergency.

d.

General emergency t

'QVESTION: 098 (1.00)

WHICH ONE (1)1of the following statements apply to.the use of. critical safety

i function (CSF) status trees? ~

a.

CSF status-trees must be monitored continuously if _ any condition other _

+

than GREEN exists; otherwise, monitoring frequency may be reduced-to.

4 10-20 minutes.-

b',

During: functional restoration.of a Heat Sink RED path,- a Core Cooling

-l 10 RANGE path develops. The correct operator action is to continue with i.

-the function restoration of the Heat Sink RED path.

l

c. _During functional restoration of a Containment ORANGE path,' an.

a

-Integrity-ORANGE-path develops.

The correct operator action is to continue with the functional restoration of the Containment'0 RANGE path.

D i

d.'

A YELLOW path must always be restored. prior to a ORANGE flow. path p

unless permission has been obtained from senior operations management.

l-l 1:

i, l

5 i

4

+

5 1:

,.q ;

g; o

I4 s

..i.

p.

-o.

7 y'DIlREACTOROPERATOR Page 51 l

L Y

cv i

LQUEST!0N:1099 (2.00) 3

Match the plant component in COLUMN A with its associated power source in-.

COLUMN B.

COLUMN.B power sources may be used more than once or not at all.

(2.0)

COLUMN A-'

COLUMN-B

- t a.; NS' pump lB 1.

ITD b.

VI compressor D-

-2.

ITB c.

KC. pump 181 3.

1 ETA

- d.- NC pump D 4.

IETB

+

5.

Load Center SLXB 6.

14CC SMXU r

.II s

E f I

i i

L w

(

r i'

ie b

4

=b b

t>

h

(**********ENDOFEXAMINATION**********)

4 3 -:

s..

REACTOR OPERATOR.

Page -11 ANSWER S'H'E E.T Multiple Choice'

'(Circle or'X'your choice) g o.

lt

'If you change your answer, write your selection in the blank.

l-.

001' a=

b c

d a

002' a

b.

c d

003 a

b' c

d t

004 a

b c

d

!4 b

c d

m:

-005' a

006-

'a b

c d

' 007 a

b c

d i

008 a-b c

d' x

009-a b

c d

010 a

b c.

d

011 a

b c

-d j

012:

a b

c d

013 a

b' c

d 1

014 a

b.

c d

- 015

'a b'

c d

-'016' a

b c

d

' 017..

a

'b c

d I

0181 a-b c

d-019 a

b c

d 020 a

b c

d t

021 a

b c

d

(

022 a

b c

d 023-

-a b

c d

- 024-a b

c d

t - 0257 a.

. b c

d t:.,

y

= f l., - ;j',.

i' c

n,.

EACTOR OPERATOR'.

Page 2 A N.S-W E R:

S'H E'E T

.}'.

LMultiple Choice.

(circle or X your choice) b m-

-If you change your answer, write ~your ' selection in the blank.

026 a-b

'c d.

027 a

b-c d

CtB a

b.

c

-d 029 a'

b' -

c d

030:

a-b c

d

.031

- a b

c d

032 a

b c

d 033-8 b

c d

l-

'034-

!a b

c d

035

- a b

c d-036-a b

c d

l c037:

a b:

c d

L 038

~a' b

c d

i;

039' a

b.

c d

040 a

bt c

d i

. 041-'

-a

.b c,

d L

042l.

a.

b c

d.

~~

1 043 a.

b c-d 044

-,a-b c'

d

}

.'045 a-b c

d

.046:

a b

c

-d 047 a.

'b c

d 048$,

a b-c' d

1-g

049 t

'o:

c d

l c

050 a

b c

t',

t n

!c 1

s

-(

<s l' <;y_p l

3

)i

gt, Page 3-REACTOR' OPERATOR J

ANSWER

. SHEET b

m ic ; -

r-Multiple-Choice (Circle or.X your choice).

1 LIf you change.your answer,' write your selection lin the blank.

L a

051:

a b.

c-d-

t J052!

a b-c

-d 053 a

b c

d v

054--

a b

c d

i

'055-a-

b c-d il.

056 a

b c

d f

057' a

b c

d

.[

T

.058.

a b

c d

^

_'059 a-b c.

d 4

060:

a b

c.

d-3 061 a

b c-d 062:

a:

b

.c d-063 a' -

b.

c d

064~

-a-b c

d

-065

a" b

c d

=066:

a b

c d

067' a

b.

c d

068.

- a'.

b.

c' d

069-

'a

.b'

- c' d

070.

a b

c d

071.

a b

c d

r.

072 a

b c

d

!=

073 fa-b c

d

.074 a

b c.

d 075-a' b

c

'd i

,yj y;;! O:s

,; \\

v

F4

r. g y,

.A REACTOR 0PERATOR:-

Page 4 7

.a..

.S H'E E T AhSWER

/s 4

> ! Multiple Choice'_

(Circle or X'your choice)'

E

-W-IfLyou change =your answer,- write your selection in-the-blank.

. 075-a:

.b.

-c

.d

.s" 077 a-b-

c d

i

078:

a:

b c

d

'079.

a-b c

d i

080' a

b c

5 E

'0811 a

b c

d

~

082:

La b

c d

i 1

i-

'083 a

b c

d l

084-a b

c d.

L l[

08C-a b

c' d

lr 1

.086:

a-

-b c

d L

.087

-: a b

c d

088-

.a b

c d-

!l 089-a

.b

- c'.

d

'090!

a' b'

-c' d

N l-091 a

b c

d 092 a-

.- b -

.c'

.d 1093' a-b c

d 094 a

b c-d-

1

'095-a'

'b c

d'

-1 1096' a-

'b

'c d

g 1097

.a b

c d

~l

.:n i t:ri 998) a

-b c

d j

H

i.

4 t

.?

Ns

(

'i

+

.i

. n_

Page 5 REACTOR OPERATOR"

)

dr ANSWER

-S H E-E T-Multiple Choice'

-(Circle or' X'your choice)

.i

-i

,1f you change your answer,-write' your selection in the blank.

u 090 match 'with' selected ~ number in the blank c

a.

v, _

]!

b m

(

C d

i k

i t

r

\\

'k

\\

1I e

f'

(

r.

ht 6

(********** END OF EXAMINATION **********)

i

?

{,'.:

+

1

+-' ' '

,l '

-).

i il i

.i.'

j

( ~

8 u

1 5

m OP/1/A/6100/22 ENCLOSURE 4.3 Curve 1.10A McGUIRE NUCLEAR STATION UEIT 1 SUBCOOLED MARGIN MONITOR Saturation' Curve Adjusted For Instrument Error Low Range NC Pressure Sensor 1

I i

Saturation Temp.

Adjusted For 3

NC Pressure Instrument Erroe (PSIG)

(Deg F)

L' O.0 200.00 35.3 241.22 85.3 297.82 135.1 335.33 j

185.3 362.00 235.3 382.97 285.3 400.65 335.3 415.83

.385.3 429.30 435.3 441.38 485.3 452.51 l

~15.3 462.74 585.3 472.20 635.3 481.09 685.3 489.48' 735.3 497.34 1

785.3 504.81 dB l

m.

o

-a m

t i

Prepared Bygpb_

Dateg24T7 '

E N

}

.w s;

1 ' d..

I 1

O.

0-

...... 6

+.........;......

g.-

4................

0.

........... * * ~

. __g...

.....W p

...... r q

...+.

v.

o'

..=

t

. *. "... * ~ ~. ~.. *. *. '.

A' O

O' 9

L

-t

........ ~

~....._.....

y

+..,..

M C

~.. ~.

. < '.. *. '. =. =. ~.... *. * *. ~... ~ ~.. < ' ' '..... '

= *'.

.. ~......

.o g...

O 3

9 30

.e

............ ~

tg.

E 4C

~.. * ".. *.. *..

mC M

C (n

.. ~. *.

@'~

'H

+

6.

o g

yp g

N 4LL Q

_g

' g.

At On

....W.

.NTOO3

~

'D,

-O e h. a

' ' ' ~ ~

~~

+ ' ' * * * ~

~ ~ * ' *

,O,,,,,3 9,H ' '.. ' ' ' '. '. ' ' *. *. *.

O9 gLg 10 3 9 (. F-lD

. % e G U D. H

~ *

40>m 2 D '.

O-g-

(.

-O, p

m NHL303 m

.y

e u 3.m Z N C U t3

- m.

g, g 4g

(~

O O

(D wC

.4 a

>g..

-.O E

gg o

g~

.b3 1 N ' h C) 4 Q

e-y O-i g.

L O

N 3

.....o.

y

..+

~...y (a

O 0

+

u

~..

o O'

l e-O O

o o

o W

h O

m v

M N

e (9ISd) aanSSGJd DN

IRE CTOR' OPERATOR Page'52 f'Ocior.

z 1-

)

1 1

LM NNSWER:!.001 --(1.00) l l

b.. [+1.0) if l

1

REFERENCE:

1. McGuire:

Lesson'. Plan, Topic 16, 0P-MC-IC-IRE, page 14.

2. KA 001050K401:(3.4/3.8) 001000G007 (3.2/3.3) i

/

d

'.001000G007 001050K401

.. (KA'.s)

J ANSWER:

002 '(1.00) i

~

c.

[+1 '. 0)

I

REFERENCE:

J l-I'.. McGuire:

Lesson Plan, topic 16, OP-MC-IC-ENB, page 36.

i.

~2. McGuire:

Lesson Plan, Topic 16, OP-MC-IC-IPE, page.21.

j l'

-3 McGuire:; Technical Specifications, page B~2-8.

i

4. KA 015000K407.(3.7/3.8)'

3 001000A303-

..(KA's) k I

6 JANSWER::

003 (1.00) d.

.[+1.0) b

REFERENCE:

1._ McGuire: OP/1/A/6150/02A, page 1.

3.:.KA 003000A201'(3.5/3.9) 003000A201

. (KA's) 1

m j

0: ANSWER:-

004 (1.00) j

.q b.

[+1.0]

j j

l d

r-

r

~

REACTOR OPERATOR Page 53

REFERENCE:

1. McGuire:

Lesson Plan OP-MC-PS-NCP, ~ Topic 15,. objective 4, page 11.

F

2. KA 003000A302 (2.6/2.5) 003000A402-(2.9/2.9) l 003000A302; 003000A402-

..(KA's)

ANSWER:'

005 (1.00) a.;-[+1.0) i

REFERENCE:

1. McGuire: OP/1/A/6150/02A, pages 1 and 2 and Enclosure 4.1, page 2.

~2. KA 003000K614 (2.6/2.9) 003000K614

..(KA's) i ANSWER:

006 (1.00) a.

[+1.0)

J

REFERENCE:

I l

1. McGuire:

Lesson Plan, Topic 12, OP-MC-PS-NV,- page 30.

H

2. KA 004020A402 (3.7/3.3) 004010K403 (3.1/3.6)-

i 004020A402 004010K403

..(KA's) d ANSWER:

007 (1.00)

~c.-[+1.0)

REFERENCE:

'l'-McGuire:

Lesson Plan, Topic 15, OP-MC-PS-ILE handout MC-IC-ILE-3.

2. KA 004000A202 (3.9/4.2)

L 004000A202

..(K\\'s)

L i

b

7 4

REACTOR OPERATOR-Page 54 1

ANSWER:

008 (1.00) a.-

[+1.0)-

REFERENCE:

1

1. McGuire: Tech Spec Bases 3/4.1.1.1 and 3/4.1.1 2'

-2. KA 004000K519 (3.5/3.9) 1 004000K519

..(KA's)

ANSWER:

009 (1.00) b.

[+1.0].

f

REFERENCE:

1. McGuire:

Lesson Plan, Topic 17, OP-MC-ECC-ISE, pages 26-and 27.-

2. McGuire:

Lesson Objective OP-MC-ECC-ISE 1.I.

13. KA 013000K413_(3.7/3.9)-

Ol3000K413

..(KA's)

I

ANSWER:

010 (l'. 00) d.-

[+1.0) l

REFERENCE:

1. McGuire:

Lesson Plan, Topic 17, OP-MC-ECC-CLA, Objective 6.

2McGuire:

Lesson Plan, Topic:17, OP-MC-ECC-CLA, pages 9 and 10.

3. KALOl3000K106 (4.2/4.4) 013000K106-

..(KA's) q ANSWER:. '011- (1.00) d.

[+ 1~. 0) 4

REACTOR OPERATOR:

Page 55 o

i

REFERENCE:

t

1. McGuire:-

Lesson Plan, Topic 16, 0P-MC-IC-IRX, page -19.

6

-2; KA 015000K302 (3.3/3'.5) 015000K302

..(KA's) i ANSWER:

012 (1.00) b.

(+1.0].

]

i

REFERENCE:

1. McGuire:

Lesson: Plan, Topic 13, OP-MC-IC-ENB, page 31.

2. KA OlS000G007 (3.3/3.4).

015000G007

..(KA's)

'l ANSWER:

013- (1.00)

c. '[+1.0]

[

REFERENCE:

1. McGuire:

Lesson Plan, Topic 16, OP-MC-IC-ENB, page 26.

2. KA 015000K604 (3.1/3.2) l t

.015000K604

..(KA's)

ANSWER:

014L (1.00)

'a.

[+1.0) c;

REFERENCE:

-i 1.:McGuire:

Lesson Plan, Topic 16, OP-MC-IC-ENA, page 5.-

.2. McGuire:

Lesson Plan, Topic-16, objectives 2 and 4.

~

3. KA 017020K102 (3.3/3.5) 017020K102

..(KA's) i

e 1

m.:

REACTOR OPERATOR' Page 56' i

I i

' ANSWER:

015 (1.00);

.j

b.

[41.0]

l k

REFERENCE:

1. McGuire:

Lesson Plan, Topic 14, OP-MC CNT VUL page 20.

2. McGuire:

Lesson Plan OP-MC-CNT-VUL objective 3.

3. KA 022000K402 (3.1/3.4) j 4

022000K402

..(KA's) l ANSWER:

016 (1.00) 9

d. -[+1.0)

REFERENCE:

1. McGuire:

Lesson Plan, Topic 14, OP-MC-CNT-VUL page 17,

2. KA 022000K101 (3.5/3.7).

022000K101

..(KA's)

ANSWER:

017 (1.00) a.

[+1.0).

y

REFERENCE:

1.~McGuire:

Lesson Plan, Topic 14, OP-MC-CNT-NF page 16.

2. KA 022000A301 (4.1/4.3) 022000A101 (3.6/3.7) 1

'022000A301 022000A101

..(KA's)

ANSWER

018 (1.00) a.

[+1.0)

$l 4

. REACTOR OPERATOR' Page 57

REFERENCE:

1. McGuire:

Lesson Plan, Topic 10, OP-MC-CF-CF, page 26.

.2. KA 059000K416 (3.1/3.2) 1.-

L 059000K416.

..(KA's)

ANSWER:

019 (1.00) d.

[+1.0) 1 g

REFERENCE:

P

1. McGuire:

Lesson Plan, Topic 10, OP-MC-CF-CF, pages 14 and 26,

2. McGuire:

Lesson Plan, Topic 17, OP MC-ECC-ISE, page 20.

3. KA 059000A203 (2.7/3.1) 059000K104 (3.4/3.4) l l-059000K104 059000A203

..(VA's) l 020 (1.00)

ANSWER:

a.

[+1. 0] -

.l

REFERENCE:

[

1..McGuire:

Lesson Plan, Topic 10, OP-MC-CF-CF, page 21.

2. McGuire:. Lesson Plan, Topic 17, OP-MC-ECC-ISE, page 21.

c,

3. KA 059000A412 (3.4/3.5) 059000A412

..(KA's) s

ANSWER:

021 (1.00)

-a.

(+1. 0].

l L

REACTOR OPERATOR Page 58 l

REFERENCE:

l

1. McGuire:

Lesson Plan, Topic 10, OP-MC-CF CA, page 9.

2..McGuire: ' Lesson Plan, Topic 10, OP-MC-CF-CA, ~ objective 3.

E

3. McGuire:

OP/1/A/6250, enclosure 4.2 and 4.6.

3. KA'061000K401 (3.9/4.2).

061000K401-

...(KA's)

J ANSWER:

022 (1.00) c.

[+1.0)

REFERENCE:

1. McGuire:

Lesson Plan, Topic 10, OP-MC-CF-CA.-

2. KA;061000K501 (3.6/3.9) 061000K501

..(KA's)

ANSWER:

023 (1.00) a.

[+1.0)

REFERENCE:

i

1. McGuire:- Lesson Plan, Topic 22, OP-MC-WE-EMF, page 14,

2. McGuire:

Lesson Plan,; Topic 22, OP-MC WE-EMF, objective 3.

3. KA 071000A303 (3.6/3.8).

071000A303

..(KA's) 4

'i ANSWER:

024 -(1.00)

C.

(+1.0) s i

l

.J

_ REACTOR OPERATOR Page 59

{

4

REFERENCE:

1 1.<McGuire:

Lesson Plan, Topic :15, OP MC-PS-NC. -

l

'2. KA 002020K509 (3.6/3.9)

.j 002020K509

..(KA's) l

-1 ANSWER:.

025- (1.00) j a.

[+1' 0)

]

i

REFERENCE:

1. McGuire:

Lesson Plan, Topic 22, OP-MC-WE-WL, handout MC-WE-WL-3.

2. McGuire: MC-1553 2.1

3. KA 002000K110 (2.8/3.1) 002000K110

..(KA's)

O

' ANSWER:

026 (1.00) c.

(+ 1. 0] '

REFERENCE:

~

1. McGuire:

Lesson Plan, Topic 14, OP-MC-ECC-CLA page 11,

2. KA 006020K603 (3.0/3.2) 006000K602 (3.4/3.9) 006000A301 (4.0/3.9) 006000A301 006000K602 006020K603

_..(KA's)

ANSWER:

027 (1.00) a.-

[+1.0)

REFERENCE:

e 1.-McGuire: Technical Specification 3.5.5.

2. KA'006000A102 (3.0/3.6)'

006000A102

..(KA's)-

L

,i.

.3

' REACTOR OPERATOR-Page 60 2

y l-

. ANSWER:

028: -(1.00) d.

[+1.0) i l

l

REFERENCE:

1.-McGuire:

System Description, MC-1223.04 page 5.

2. KA 006000K613 (2.6/2.9) 006000K613

..(KA's)

[

l.

ANSWER:

029 (1.00)

}

b..

[+1.0) l

REFERENCE:

u L

.1, McGuire:

Lesson-Plan, Topic 15, OP-MC-PS-IPE, handout MC-IC-IPE-13.

l

2. KA 010000A402 (3.6/3.4) 010000A402

..(KA's)

L ANSWER:

-030.(1.00)-

'd.

-[+1.0)

REFERENCE:

1. McGuire:

Lesson Plan, Topic 15, OP-MC-PS-IPE pages 20 and 37.

2. KA 010000K603 (3.2/3.6) 010000A403 (4.0/3.8)

' 010000A403 010000K603

..(KA's)

LANSWER:

031 (1.00) b.

-[+1.0)

T' w

TQ REACTOR OPERATOR Page 61

REFERENCE:

l. McGuire:

Lesson Plan, Topic 15, OP-MC-PS-ILE, page 5._

2. McGuire:

Lessoni Plan, Topic'15, OP-MC-PS-ILE objective 1.B.

3. KA 011000K512.(2.7/3.3) b

.011000K512-

..(KA's) 4 ANSWER:

032 (1.00) c.-

[+1.0]

REFERENCE:

i

1. McGuire:

Technical Specifications 2.2.1 and bases page B 2-8.

2. KA 012000K406 (3.2/3.5' 012000K406

..(KA's)

ANSWER:

033 (1.00) a.

[+1.0]

i

REFERENCE:

1. McGuire:

OP/1/A/6100/10C, Panel 1AD2 - D - 9.

2'1McGuire:

Lessor Plan, Topic 16, OP-MC-IC-IRE, objective 12.

'3. McGuire:

Lesson Plan,' Topic 16, OP-MC-IC-EDA page '18.

'4.10\\ 014000K403 (3.2/3.4) 014000G007 - (2.8/3.0) s 014000G007 014000K403

..(KA's)

ANSWER:

034 (1.00) d.'[+1.0]

f

~.:

. REACTOR OPERATOR-Page 62

.REFERENCEi

1. McGuire: Annunciator / Alarm Procedure, " Control Rod Bank LO-LO Limit."'

.2. KA 014000A103-(3.6/3.8).014000G007 (2.8/3.0) 014000A103 014000G007.

..(KA's) 1 ANSWER:

035 (1.00) l b.

[+1.0]

REFERENCE:

1. McGuire:

Lesson P1an,-Topic 17,'0P-MC-ECC-NS, pages 11, 12, and 13, i

2. McGuire:

Lesson Plan, Topic 17, OP-MC-ECC-ISC, pages 16 and 17.

l

3. KA 026000A401 (4.5/4.3)

L 026000A401

..(KA's)

-ANSWER:

-036- (1.00) i b.

[+1.0) 1 I'

REFERENCE:

l Lesson Plan, Topic 10, OP-MC-CF-IFE handouts OP-MC-IFE-1A and

1. McGuire:

OP MC-IFE-3.

2. KA 035010A101 (3.6/3.8) 035010A101

..(KA's)

, ANSWER:

- 037 ~(1.00)

c..[+1.0]

L

REFERENCE:

1. McGuire:

Lesson Plan, Topic 8, OP MC-STM-SG.

Dj

2. KA'035010K501.(3.4/3.9) 035010K501

..(KA's) u he

g y, ",..,.

REACTOR! OPERATOR-Page 63

[

P ANSWER::

038 (1.00)

~d.

[+1.0]:

REFERENCE:

1.'McGuire:

Lesson Plan, Topic 6, OP-MC-EL-EP, page 25.

2. McGuire:-- Lesson P1an, Topic 6, OP-MC-EL-EP, handout OP-MC-SLYS-EP-1.

' 3.: KA 062000K201 (3.3/3.4) 062000K201

..(KA's)

. ANSWER:

,039 (1.00)'

c.~[+1.0)

REFERENCE:

l

-1..McGuire: OP/1/A/6300/01, ENCLOSURE.4.2, page 8.

2.-KA 062000A403 (2.8/2.9) 062000A403

..(KA's)

ANSWER:'

040 (1.00)-

j

c.

[+1.0]

REFERENCE:

1. McGuire:

Lesson Plan, Topic 16, OP-MC-IC-IRE page 22.

2. McGuire:

Lesson Plan, Topic 16, OP-MC-IC-IRE, Objective 9 and 10.

3' KA 063000K302 (3.5/3.7) 063000K302

..(KA's)

ANSWER:

041 (1.00) b.

[+1.0]

c s

I

w REACTOR OPERATOR Page 64-

REFERENCE:

.1. McGuire:

Lesson Plan, Topic 12, OP-MC-DG-DG, page :10.

j 0

-2. hcGuire:

Lesson Plan, Topic 12, OP-MC-DG-DG, Objective 3.

3. KA 064000A103 (3.2/3.3) ~

j 064000A103

..(KA's).

7 ANSWER:

042 (1.00) b'.

(+1.0)'

4

REFERENCE:

1. McGuire:

Question bank, Q-DG-DG-06.

2. McGuire:

Lesson Plan, OP-MC-DG-DG, page 10.

3. KA 064000A302 (3.4/3.7) i 064000A302

..(KA's) 4 o

ANSWER:

043.- (1.00) c.-[+1.0)

]

REFERENCE:

-1. McGuire:. Lesson Plan, Topic 15, OP-MC-PS-NV page 11,

2. McGuire:

Drawing MC-1553 and MC-1554.

3. KA 007000K103 (3.0/3.2) 007000A301 (2.7/2.9).

007000A301 007000K103

...(KA's)

ANSWER:

044-(1.00) ec.

[+1.0) 7 I

N

g' o

REACTOR:0PERATOR

_Page 65

.g.

REFERENCE:

l A

. 1. McGuire:

Lesson Plan, Topic 10, OP MC-PSS-KC-2,

2. McGuire: _ System Description RN, Table 1.

t

, 3. KA 008000K102 (3.3/3.4):

+

008000K102

..(KA's) 9 ANSWER:

045 (1.00) i a.

(+1.0)

REFERENCE:

1. McGuire:

Lesson Plan, Topic-17, OP-MC ECC-ISE, page 14.

2. McGuire:

Lesson Plan, Topic 13, OP-MC-PSS-KC, pages 7,18, and 29.

3, McGuire:

Lesson Plan, Topic 12, OP-MC-DG-EQB,. page 11.

. 4. KA 008030A304 (3.6/3.7) 008030A304

..(KA's) i ANSWER:

046 (1.00) d.

(+1.0]

REFERENCE:

1. McGuire:

Lesson Plan, Topic 14,. OP-MC-CNT-VX, page 19.

'2. KA 028000A401 (4.0/4.0) 1 028000A401

..(KA's) i'

. ANSWER:

047 (1.00) c.

(+1.0]

REFERENCE:

j.

1. McGuire:

Lesson Plan, Topic 8, OP-MC-STM-IDE, page 13.

2. KA 041000G004 (2.8/2.9)-

+

041000G004

..(KA's) l L

L 1

c t

REACTOR OPERATOR Page 66 l

ANSWER:--

048 (1.00)-

a._(+1.0)-

,t

REFERENCE:

L l

1. Mcguire:

Lesson Plan, Topic 13, OP-MC-PSS-RN, handout MC-SYS-RN-10.

2. KA 076000K119 (3.6/3.7) 076000K307 (3.7/3.9) i 076000K119 076000K307

..(KA's)

L' i

ANSWER:

049 (1.00)

J d.

[+1.0) i

REFERENCE:

F l1. McGuire:

Lesson Plan, Topic 17, OP-MC-ECC-ISE, objective 1.C, page 14.

-2..KA 103000K406 (3.1/3.7).

103000K406

..(KA's) j 1

ANSWER:

.050 (1.00) il 1

d.

[+1.0)

~

REFERENCE:

-1. McGuire:

Lesson Plan,- Topic 20, OP-MC-TA-AM, page 26.

2. WOG'ES-0.2, page 28.

i L

3. McGuire:

EP/1/A/5000/1.1,page'5.

4. KA- 000015K307 -(4.1/4.2)-

'000015K307'

..(KA's) 1 l-ANSWER:

051 (l.00) d.

[+1.0) b 1

+

1 REACTOR OPERATOR Page.67'

REFERENCE:

.j

-l'. McGuire:

EP/1/A/5000/1.1, FoldoutL

2. KA 000015K101 (4.4/4.6)

I 000015K101

..(KA's) t ANSWER:

052 {l.00) b.

[+1.0)

REFERENCE:

1. McGuire:

AP/1/A/5500/38, " Emergency Boration," page 2.

2. KA 000024G011 (3.8/3.9) 000024K301 (4.1/4.4) l-000024K301 000024G0ll-

..'(KA's)

ANSWER:

053 (1.00) b.

[+1.0)

REFERENCE-

1. McGuire:

System Description 1223.23, pages 9 and-22.

2. KA 000026A105 (3.1/3.1) l l

l.

000026A105

..(KA's) 1 ANSWER:

054 (1.00) c.

[+1.0)

REFERENCE:

1. McGuire: ' AP/1/A/5500/11, page.2.

2. KA 000027A101 (4.0/3.9)

-000027A101

..(KA's)

i REACTOR OPERATOR, Page_68 ANSWER':

055- (1.00) b.-

( + 1. 0] -

REFERENCE:

l

1. McGuire: OP-MC-EP-EP9, Objective B.2., p. 7.

2. McGuire:

EP/1/A/5000/14.1, " Response to Imminent Pressurized

- Thermal Shock Conditions."

-3. KA 000040K101 (4.1/4.4)

't 000040K101

..(KA's)

- ANSWER:

056 (1.00) b.

(+1.0)

REFERENCE:

l' McGuire:

EP/1/A/5000/03, page 3.

e

2. McGuire:

Lesson Plan, Topic 21, OP-MC-EP-EP3, page 5.

3.-McGuire:

Lesson Objective 2b.

.4. KA-000040K304 (4.5/4.7) 000040K304

..(KA's)

.i

- ANSWER:

057 (1.00)

d.

[+1. 0 ).

4

REFERENCE:

1.,McGuire:L, lesson Plan, Topic 21,-OP-MC-EP-EP9, page 6.

E 2'. ' McGui re:- EP/1/A/5000/14.1, pages 1 and 2.

3.;KA 000040K101-(4.1/4.4) KA 000040K304 (4.5/4.7) 000040K101 000040K304

..(KA's) 1 I

l-L r

l

s,j.

j 3

-REACTOR OPERATOR Page 69

~ 58_- (1.00).

ANSWER::

0 d.

[+1.0)

REFERENCE:

-1. McGuire:

Lesson Plan, Topic 21, OP-MC-EP EPF, page 25.

2. McGuire:

EP/1/A/5000/12, 12.1, 12.2, and 12.3.

3. KA 000040K306 (3.4/3.9)

- t 000040K306

..(KA's)

ANSWER:

059- (1.00) a.

(+1.0]

i c

REFERENCE:

1. McGuire: AP/1/A/5500/23, pages 2 and 3.

2. KA 000051A202.(3.9/4.1) 000051G011 (2.7/2.9) 1 000051A202 000051G011

...(KA's)

' ANSWER:

060 L(1.00)

~d.

[+1.0)

REFERENCE:

.i

1. McGuire:

EP/1/A/5000/09, " Loss of All AC Power".

2. McGuire:

Lesson Plan, Topic: 21, OP-MC-EP-EPS.

3.'KA 000055G010 (4.1/4.3) 000055K302.(4.3/4.6)

-000055K302 000055G010

..(KA's)

. I e

-ANSWER:. -061 (1.00) g d.

(+1 - 0) f

REACTOR OPERATOR.

Page 70~-

x

.s.

7

REFERENCE:

l. McGuire: 'OP-MC-EL-EPL, page 11.-

2..McGuire:

Question Bank, Q-DG-EPQ 01.

3.KA 000055K301 (2.7/3.4)^

I

'000055K301

..(KA's)

ANSWER:

062 (1.00) d.

[+1.0)

~

REFERENCE:

1. McGuire:- Lesson Plan, Topic 12, OP-MC-DG-EQB Handout MC-ELE-EQB-1.

y i

2. KA 000055K302 (4.3/4.6) i 000055K302'

..(KA's) fg.

' ANSWER:.

063 (1.00) i a.

(+1.0)

REFERENCE:

1. McGuire: AP/1/A/5500/07, page 2.

l

2. KA 000057A214 -(3.2/3.6) 000057A219 (4.0/4.3) 000057A219 000057A214 (KA's)

ANSWER:

064 (1.00).

d.

[+1. 0) '

.a l

l).

v 5

.l i

REACH 0ROPERATOR-Page 71'-

l

REFERENCE:

=

j

1. McGuire: Nuclear Systems Description, NI.MC-123.12, pages 15 and 16.

2.'McGuire:' MC-1562-3.1~and MC-1561-1.0.

3. McGuire: OP-MC-PS NDL Objective.4, page 2.

~4. KA 000074A111-(3.6/3.7) 000074A111-

..(KA's)

LANSWER:

065 (1.00) a.

[+1. 0) ~

q

REFERENCE:

1. McGuire:

EP-12.1, " Response to Inadequate Core Cooling."

i

2. McGuire:

Status Trees.

3. McGuire: OP-MC-EP-EP7, Objective B.

4.-KA.000074G011 (4.5/4.6).

000074G011

..(KA's)

ANSWER:

~066 (1.00)

.I

.c.

[+1.0) 1

REFERENCE:

~1. 'McGuire: AP/1/A/5500/14, page 4.

.2. KA:000001A205 (4.4/4.6) 00000lG010 (3.9/4.0) 00000lG010 000001A205

..(KA's) 1 ANSWER:-

067 (1.00) c.

[+1.0) k i

t I

3..

REACTOR OPERATOR

- Page 72-

REFERENCE:

I'-

11=.- McGuire:

1.esson Plan, Topic 16, OP-MC-IC IRE.

2. KA 000001A205 (4.4/4.6)

.000001A205

..(KA's) iANSWER:. 068 l(1.00).

c.

[+1.0]

REFERENCE:

1. McGuire: OP/1/A/5500/14, page 6,

2. KA 000003G010 (3.9/3.8) 000003G010

..(KA's)-

ANSWER:

069 (1.00) a c.-

[+1.0].

REFERENCE:

1. McGuire: AP/1/A/5500/14, page 16.

2. KA 000003K205 (2.5/2.8) 000003K308 (3.1/4.2) 000003K205 000003K308

..(KA's)

ANSWER:

070 -(1.00) b

-[+1.0]

REFERENCE:

1. McGuire: Steam Tables.

E. KA 000007A103 (4.2/4.1)

'i

'000007A103

..(KA's)

)

w e

r'-==s w

'e

.D, 1

' REACTOR OPERATOR.

Page:73 j

i

' ANSWER:'

071 (1.00)-

d.-

(+1.0) l REFERENCE-I

.l. McGuire:. Lesson Plan, Topic 17, OP-MC-TA-AM, page 53.

2. McGuire:- Lesson Plan, Topic 21, OP-MC-EP-EP9, page 6.

.3. KA: 000008K202-(2.7/2.7) 000008K202

..(KA's)'

' ANSWER:

072 (1.00) b.

(+1.0) l

REFERENCE:

-1. McGuire:

Lesson Plan, Topic 21, OP-MC-EP-EP2, page 14..

2. McGuire:

EP/1/A/5000/01, Foldout page.

3. KA 000009K323 (4.2/4.-3)

)

-l 000009K323

..(KA's)

1

' ANSWER:

073 (1.00)

-a._

[+1.0) c.

REFEREhCE:

.l. McGuire: ' Technical Specifications 3.4.6.2 and Definitions.

-1

2. KA 000009G003 (3 5/4.1) 000009G003-

..(KA's)

ANSWER:

074 (1.00) a.-

(+1.0]

1 REACTOR OPERATOR Page 74 1

c

REFERENCE:

l. McGuire-Question-bank, Q-DG-EQB-6.

l

-2. McGuire:

Lesson Plan, Topic 12, OP-MC-DG-EQB, page 11.

{

3..KA 0000llA113 (4'.1/4.2) 0000llA113

..(KA's) 1

<-l

. ANSWER:

075 (1.00) g L

a.-

[+1.0) 1; l

\\

1

REFERENCE:

1 l

1. McGuire:

Lesson Plan, Topic 15, OP-MC-PS-NV, pages 31-35.

'2. McGuire: ' Malfunction Description, NV-18.

3. KA 000022A201 (3.2/3.8)

L 000022A201

..(KA's) l

. ANSWER:

076 (1._00)

I

'a.-[+1.0]

l

REFERENCE:

'l. McGuire:

Lesson Plani Topic 10, OP-MC-CF-CF, page 16.

'd L

2. McGuire:

EP/1/A/5000/II.1, " Response to Nuclear Power Generation /ATWS."

l

3. KALO00029All5 (4.1/3.9) 000029K312 (4.4/4.7) 4 000029K312 000029All5

..(KA's)

ANSWER

077'(1.00)

L a.

[+1.0) 1

^

h

.i t

L 1

J,.

REA TOR OPERATOR; Page 75:

~

REFERENCE:

1.-McGuire:

Lesson Plan,. Topic-21, OP-MC-EP EP6-page 7.

2. McGuire:- Lesson Plan,=-Topic 21, OP-MC-EP-EP6, objective B.3.

3. McGuire:- EP/1/A/5000/ll.1 page 2.

,4. KA 000029K312-(4.4/4.7) 000029K312-

..(KA's)

ANSWER:

078 (1.00) p

c. -[+1.0]

REFERENCE:

1. McGuire: AP/1/A/5500/ii, page 5.

j

-2. KA 000033A211 (3.1/3.4).

000033A211

..(KA's)

ANSWER:

079 (1.00) c.

[+1.0]

REFERENCE:

)

1. McGuire: Technical Specification 3.3.1.

2. KA 000033A209 (3'.4/3.7) KA 000033G008 (2.8/3.4) j 000033A209 000033G008

..(KA's)

.]

1 ANSWER:

080 (1.00) q

b.. [+1.0]

REFERENCE:

1. McGuire: AP/1/A/5500/10, page 2~.

j 2; KA 000037K307 (4.2/4.4) 4 000037K307

..(KA's) i

J

. REACTOR OPERATOR' Page.76'

~

ANSWER: - "081- (1~00).

a.

[+1.0)

REFERENCE:

~l'. McGuire:

Lesson Plan, Topic 20, OP-MC-TA-SA.

i

2. KA 000054K102 (3.6/4.2) 1 000054K102

..(KA's)

=

.q ANSWER:.

082 (1.00) a.

{+1.0)

REFERENCE:

l. McGuire:

Lesson P1an, Topic 22,0P-MC-WE-EMF, page 22.

2; KA 000061A101 (3.6/3.6)._

i 000061A101'

..(KA's)

.i ANSWER:

083 (1.00)

-l b.

[+1.0) 1

REFERENCE:

. 1. McGuire:

Lesson Plan, Topic 15,'0P-MC-PS-ILE, hando'ut MC-IC-ILE-2,3.

2. McGuire:

Lesson Plan, Topic 15, OP-MC-PS-ILE, pages 8, 9.

3.' KA 000028K202 (2.6/2.7) 000028K101 (2.8/3.1) 000028K101 000028K202

..(KA's) j d

ANSWER::

084- (1.00) d.

[+1.0]

l

.i

y

[i.;

E REACTOR OPERATOR Page 77 F

REFERENCE:

-AP/1/A/5500/40, page 2.

1. McGuire:

1

2. McGuire:

Lesson Plan, Topic 23, OP-MC-FH-FC,-objective 13.

4 3' KA 000036K201 (2.9/3.7) 000036G010 (3.7/3.8) 000036K201 000036G01d

..(KA's)

' ANSWER:-

085 (1.00) b.

[+1.0)

REFERENCE:

l. McGuire: AP/1/A/5500/03, p ages 2, 9, and 16.

5 l

-2. KA 000056K302-(4.4/4.7) 000056K302

..(KA's) 1 ANSWER:

086 (1.00) d.- [+1.0)

REFERENCE:

1. McGuire:

S.D. 3.1.19, page 11.

2. KA 194001K102 (3.E4.1) 19400lK102

..(KA's)

L !

Lj ANSWER:

087 (1.00)'

c.

[+1.0]

REFERENCE:

1. McGuire:

S.D. 3.1.19, page 20.

'2. KA 19400lK101 (3.6/3.7) 19400lK101

..(KA's) a

N

T REACkOROPERATOR Page 78 ANSWER:

088 (1.00) b.

[+1.0)

REFERENCE:

1. McGuire:

S.D. 3.1.19, page 30,

2. KA : 9400lK102 (3.7/4.1)

Iv400lK102

..(KA's)

ANSWER:

089 (1.00) c.

[+1.0)

REFERENCE:

1. McGuire: OPM l 6 page 2.

2. KA 194001A110 (2.9/3.9) 194001A110 (KA's)

ANSWER:

090 (1.00)

[+1.0) c'(, g,,,

c.

REFERENCE:

1. McGuire: OPM l-6, page 5,

2. KA 19400lK101 (3.6/3.7) 19400lK101 (KA's)

ANSWER:

091 (1.00) d.

[+1.0) i d

REACTOR OPERATOR Page 79

REFERENCE:

i

1. McGuire: OMP 2-4, page 3,

2. KA 194001A106 (3.4/3.4) 194001A106

..(KA's)

ANSWER:

092 (1.00) d.

[+1.0)

REFERENCE:

1. McGuire:

OMP l-2, page 3.

2. KA 194001A102 (4.1/3.9) 194001A102

..(KA's)

ANSWER:

093 (1.00) b.

[+1.0)-

REFERENCE:

1. McGuire:

Lesson Plan Topic 5, OP-MC-ADM-0MP, learning Objective F.3.

2. KA 19400lKil6 (3.5/4.2) 19400lK116

..(KA's)

ANSWER:

094 (1.00) c.

[+1.0)

REFERENCE:

1. McGuire:

Radiation Physics Manual, section 2.1, pages 3 to 6.

2. KA 19400lK103-(2.8/3.4) 19400lK103

..(KA's) l

I REACTOR OPERATOR

.Page 80 i

I ANSWER:

095 (1.00) a.

[+1.0) j

REFERENCE:

i 19400lK104

..(KA's) i ANSWER:

096 (1.00) c.

[+1.0) i

REFERENCE:

1. McGuire:

SD 3.7.1, section 5.1.2.2.

2. KA 19400lK105 (3.1/3.4) i 19400lK105

..(KA's)

ANSWER:

097 (1.00) b.

[+1.0)

REFERENCE:

l. McGuire:

RP/0/A/5700/02, section 2.1.3, page 1.

2. KA 194001All6 (3.1/4.4) 194001All6

..(KA's)

[

6 ANSWER:

098 (1.00) b.

[+1.0) 4

4

)

REACTOR OPERATOR Page 81 I

REFERENCE:

1. McGuire:

Lesson Plan, Topic 21, OP MC rp.EPF.

I

2. KA 194001A102 (4.1/3.9) 194001A102

..(KA's) i i

ANSWER:

099 (2.00) l

a. 4.

+0.5

b. 5.

+0.5 i'

c. 4.

+0.5

d. 1.

+0.5

REFERENCE:

1. McGuire:

Lesson Plan, Topic 7 OP MC SS-VI, page 67.

2. McGuire:

Lesson Plan, Topic 13, OP MC-PSS KC, page 29.

3. McGuire:

Lesson Plan, Topic 15, OP MC-PS-NCP, page 19.

4. McGuire: ' Lesson Plan, Topic 17, OP-MC-ECC NS, page 17.

t

5. KA 026000K201 (3.4/3.6) 062000K201 (3.3/3.4) 078000K201 (2.7/2.9) 062000K201 078000K201 026000K201

..(KA's) i i

(********** END OF EXAMINATION **********)

I REACTOR OPERATOR Page 1 ANSWER KEY P

001 b

002 c

003 d

004 b

005 a

006 a

007 c

008 a

009 b

010 d

011 d

012 b

013 c

014 a

015 b

i 016 d

017 a

018 a

019 d

i J

020 a

021 a

022 c

i 023 a

L 1

024 c

L 025 a

1

REACTOR OPERATOR Page 2 ANSWER KEY r

026 e

1 027

.a 028 d

029 b

030 d

031 b

032 c

033 a

034 d

035 b

036 b

037 c

038 d

{

039 c

040 e

i

.041 b

042 b

043 c

044 a

045 a

046 d

047 c

040 a

049 d

050 d

.I a

REACTOR OPERATOR Page 3 ANSWER KEY

?

l 051 d

052 b

053 b

054 c

055 b

l 056 b

057 d

i 058-d 059 a

060 d

061 d

062 d

063 a

064 d

065 a

066 c

067 c

.06B c

069 c

070 b

071 d

072 b

073 a

074 a

075 a

l REACTOR OPERATOR Page 4 ANSWER KEY 076 a

077 a

078 e

079 c

080 b

081.

a 082 a

083 b

084 d

085 b

086 d

087 c

.f 088 b

089 c

090 c

i

-091 d

092 d

1 093 b

i 094 c

095 a

096 c

P 097 b

098 b

i

i REACTOR OPERATOR Page 5 AN5WER KEY 099 match with selected number in the blank a

4 b

5 C

4 I

d 1

.I i

I t

i P

L I

(**********

END OF EXAMINATION **********)

TEST CROSS REFERENCE Page 1 QUESTION VALUE REFERENCE 001 1.00 9000032 002 1.00 9000054 003 1.00 9000001 004 1.00 9000003 005 1.00 9000004 006 1.00 9000005 007 1.00 9000015 008 1.00 9000061 009 1.00 9000016 010 1.00 9000025 011 1.00 9000002 012 1.00 9000008 013 1.00 9000023 014 1.00 9000033 015 1.00 9000041 016 1.00 9000042 017 1.00 9000043 018 1.00 9000029 019 1.00 9000030 020 1.00 9000031 021 1.00 9000009 022 1.00 9000084 023 1.00 9000010 074 1.00 9000068 025 1.00 9000074 026 1.00 9000006 027 1.00 9000034 028 1.00 9000065 029 1.00 9000014 030 1.00 9000066 031 1.00 9000091 032 1.00 9000045 033 1.00 9000017 034 1.00 9000046 035 1.00 9000086 036 1.00 9000073 037 1.00 9000085 038 1.00 9000022 039 1.00 9000069 040 1.00 9000053 041 1.00 9000024 042 1.00 9000052 043 1.00 9000040 044

.l.00 9000007 045 1.00 9000071 046 1.00 9000072 047 1.00 9000021 048 1.00 9000047 049 1.00 9000011 050 1.00 9000075 051 1.00 9000077 052 1.00 9000019 053 1.00 9000093 054 1.00 9000057 1

I TEST CROSS REFERENCE Page 2 QUESTION VALUE REFERENCE 055 1.00 9000027 056 1.00 9000044 057 1.00 9000081 058 1.00 9000083 059 1.00 9000088 060 1.00 9000037 061 1.00 9000094 062 1.00 9000097 063 1.00 9000038 064 1.00 9000020 065-1.00 9000026 t

066 1.00 9000048 067 1.00 9000089 068 1.00 9000018 069 1.00 9000092 070 1.00 9000064 071 1.00 9000062 072 1.00 9000035 073 1.00 9000063 074 1.00 9000096 075 1.00 9000013 076 1.00 9000028 077 1.00 9000078 3

078

'l.00 9000059 l

079 1.00 9000079 080 1.00 9000039 081 1.00 9000076 082.

1.00 9000060 083 1.00 9000070 084 1.00 9000090 085 1.00 9000012 086 1.00 9000098 t

087 1.00 9000099 088 1.00 9000100 089 1.00 9000102 090 1.00 9000103 091 1.00 9000104 092 1.00 9000105 093 1.00 9000106 094 1.00 9000107 095 1.00 9000109 096 1.00 9000112 097 1.00 9000113 098 1.00 9000115 099 2.00 9000087 100.00 100.00

--

ML20059K010

Text

SUMMARY

SUMMARY

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE: