ML20005D948

Retake Exam Rept 50-482/OL-89-01 Administered on 891120-21. Exam Results:All Four Reactor Operator & Two Senior Reactor Operator Applicants Passed All Portions of Exams & Issued Appropriate Licenses

ML20005D948
Person / Time
Site:	Wolf Creek
Issue date:	12/13/1989
From:	Kennedy K, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20005D947	List: ML20005D946 ML20005D948
References
50-482-OL-89-01, 50-482-OL-89-1, NUDOCS 9001020314
Download: ML20005D948 (80)

Text

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION-REGION IV Operator Licensing Examination Report: 50-482/0L 89-01

- Operating License: NPF-42 Docket No.: -STN 50-482 Licensee: Wolf-Creek Nuclear Operating Corporation P.O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station

- Examination ~at: Wolf Creek Generating Station (WCGS)

Chief Examiner: I.9 M

ft Gh Au QK.' PG Kennedy, Examiner ali-Operator Licensing Section Division of Reactor Safety Approved by:

.gif(Sh J.sl. Pellet, Chief Date Operator Licensing Section Division of Reactor Saf ety Summary HRC Administered Examinations Conducted on November 20-21, 1989 (NRC heport 50-482/0L 89-01)

HRC administered retake examinations to four reactor operator (RO) applicants and two senior reactor operator (SRO) applicants.

Four R0 applicants and one SR0' applicant were administered the written examination and one R0 applicant and one SR0 applicant were administered the simulator portion of the operating examination. The applicants passed all portions of the examination and have been issued the appropriate licenses.

9001020314 891215 PDR ADOCK 050 2

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DETAILS 1.

' Persons Examined SRO R0 Total c

Licensee Examinations: Pass -

2 4

6 Fail _-

0 0

0 2.

-Examiners K. M. Kennedy, Chief Examiner J. M.,Keeton 3.

Examination Report Performance results for individual examinees are not included in this report as it will be placed in the NRC Public Document Room and these l

'results are not subject to public disclosure, a.

Examination Review Comment / Resolution In general, editorial comments or changes made during the examinatien or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made by WCGS. The only comments addressed in this section are those which were'not accepted for incorporation into the examination and/or answer key. Those comments accepted are incorporated into the master examination key, which is included in this report. Comments may be paraphrased for brevity. The full text of the comments is attached.

32 a.

(RO)

Due to single loop loss of flow (1/4) ~not satisfying 26 a.

(SRO) the "AND" gate logic for P-7, two loop loss of flow (2/4), it can be determined that P-7 would also between P-7 (10 percent power) gle loop (48 percent prevent a reactor trip on a sin loss of flow.

and P-8 power) as power ascends from 10 percent to 48 percent.

Therefore, Answer No. 3 from Column B (P-7) should also be allowed for Part a.

P-8 (48 percent) prevents a reactor trip on a single loop loss of flow upon a power descension from 48 percent until shutdown.

Response

Reject. Comment and reference cited do not support acceptance of Answer No. 3 (P-7) as a correct answer for 32a.

-l t.

36.

(RO)

Answer Part C should also be allowed s';. ice;

. pressurizer narrow' range pressure instruments also provide compensatory signals to the~ core subcooling monitors.

Response

Coment accepted and question deleted, b.

Site Visit Sumary At-the end of the written examination administration, the facility licensee was provided a copy of the examination and answer key for the purpose of commenting on the examination content validity.

It was explained-to the facility licensee'that regional policy was to have examination results finalized within 30 days. Thus, a timely response was desired to' attain this goal.

= c.

Master Examination and Answer Key Master copies of the WCGS license written examinations and answer keys are attached. The facility licensee coments, which have been accepted, are incorporated into the answer key, d.

Facility Examination Review Coments The facility licensee coments regarding the written examination are attached. Those coments which not incorporated into the examination answer key have been addressed in the resolution section of the report.

e.

Simulation Facility Fidelity Report No significant discrepancies were observed during the administration of the simulator portion of the operating tests.

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i Nbvember 22, 1989 Nuclear Regulatory Conmission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 s

Dear Mr. Kennedy:

1his package consists of our responses to the exam recently given.at Wolf Creek Generating Station. Attached to each response is the justification or du'=antation to support the respmse, where applicable.

If you have any questions, please feel free to call ne.

Sincerely, f

James E. Gilnore Supervisor License Training Jm/ PAL /tsg Attachments m

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NOGS Reactor Operator (/ Senior Reactor Operator) Damm (11/20/89)

Utility Post Exam Ccmmants EMIII(EIFT NO AIEGGIhL PIAMP IMIMIGS No ocsanents.

l PtAMP SYSTIBE ABD PIANT WIDE GREIRIC RIISPOEIBILITIES Ouestion Number Cament 32 (26) part (a)

Due to single loop loss of flow (1/4)

Dat; satisfying the "AND" gate logic for P-7, two loop loss of flow (2/4), it can be detemined that P-7 would also prevent a reactor trip on a single loop loss of flow between P-7 (10% power) and P-8 (48% power) as power ascends fu m 10% to 48%.

Therefore, Answer No. 3 frun Coltan B (P-7) should also be allowed for Part a.

P-8 (48%) prevents a reactor trip on a single loop loss of flow upon a power descension frczn 48% until shutdown.

Reference attached, drawing 10466-M-744-0022-05.

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Ouestion Number Ca ment 36 f,Not on SRO Exam)

Answer Part C should also be allowed since pressurizer narrow range pressure instruments also provide cmpensatory signals to the Core Subcooling Manitors. Reference the attached drawings:

I 10466-M-12 BB04 (Q) Rev. 1 10466-M-12 BB02 (Q) Rev. 2 Drawing 10466-M-12 BB04 indicates the expected L

response, answer Part b and drawing 10466-M-12 BB02 indicates Answer Part C would also be correct.

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L U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION REGION 4

FACILITY:

WOLF CREFK REACTOR TYPE:

PWR-WEC4 DATE ADMINSTERED:

1989/11/20 CANDIDATE:

INSTRUCTIONS TO CANDIDATE 1 R;td and follow the NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS attached to your examination.

An overall grade of at least 80% is required to pass the oximination.

Examination papers will be picked up TWO (2) hours after the examination starts.

SITE SPECIFIC WRITTEN EXAMINATION

. EXAMINATION POINTS 33 00 CANDIDATE'S SCORE FINAL GRADE All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature l

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W e

.i NRC RULES AND GUIDELINES FOR-LICENSE EXAMINATIONS'

-During the administration of this examination the followingLrules apply:'

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

2._Restroom trips are-to be limited and only one candidate at a time may leave.-.You must avoid all. contacts with anyone outside the examination

= room to avoid even the appearance or possibility of cheating.

4

3. To pass the examination, you must achieve an overall grade of 80%.

70. There is a time limit of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for completion of the examination.

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

~

I question.

The amount of blank space on an examination 1 question page is.

NOT an indication of the depth of answer required.

6. Show all calculations, methods, or assumptions used to obtain an answer except'for multiple choice and matching questions.

7. Partial credit may be given.

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

NOTE: pot tial credit will NOT be-given on multiple choice questions.

8. Proportional grading will be applied.

Any additional wrong information 1

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 l

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 be 0.80 instead of 1.00 even though you got the four correct answers.

NOTE: Proportional Lgrading will NOT be applied to multiple choice, matching, or

-fill-in-the-blank questions.

'9. Multiple choice questions may contain one or more choices which are correct IF certain assumptions are made.

However, the correct answer

.will not need assumptions or qualifiers.

Therefore, when more than one choice-seems to be correct, select the choice which BEST answers or completes the question or statement.

10.'If the intent of a question is unclear, ask questions of the examiner only.

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

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

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

14. Write your answers on the examination question page or on a separate sheet of paper as specified by the examiner.

USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

se****************************************************************************

When examination specific answer eheets are provided, ONLY the answers c

maked on the answer sheet will be considered for examination grading.

C Information or answers marked on scratch paper or on the examination will NOT be credited during examination grading.

c*****************************************************************************

15. Print your name in the upper right-hand corner of the first page of your answer sheets whether you use the examination question pages or separate sheets of paper.

Initial each succeeding page.

16. After you complete your examination, you must sign the statement on the cover sheet indicating that the work is your own and you have not received nor given assistance in completing the examination.

17. When turning in your examination, assemble the completed examination in the following crder:

1.

Signed cover sheet 2.

Answer sheets 3.

All other examination material 4.

Scrap paper

18. 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 examination is still in progress, your license may be denied or revoked.

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-PLANT SYSTEMS-(40%) AND PLANT-WIDE GENERIC l

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- QUESTION: 01 (1.00)

A sume steady state operation and the pressuriserespray valve has just. opened ot 100% power.

The Pressure Master Controller setpoint is then inadvertently changed to_2370 psig.

Assume a. step change in the setpoint and assume 1that

'pressuriser pressure control remains in automatic.

The immediate automatic responses of the system will be:

-c..

Power operated relief l valve PCV-455A opens, spray valves open, pressuri=er heaters de-energize.

b.,

Spray valves open, pressurizer heaters; energize.

c.-

Spray valves close,-pressuriser heaters energize.

d.

Power Operated Relief Valves PCV-455A and PCV-456A open, spray valves open, pressuriser heaters energize,

. QUESTION: 02 (1.00)

Which statement describes the reactor coolant pump # 2 seal?

c.

.# 2 RCP seal is a face type rubbing seal with a leakoff flow rate of 3 sph to the RCDT.

b,

1. 2 RCP scal is a face type rubbing seal with a leakoff flow rate of 3 gpm to the VCT.

c.

1. 2 RCP seal is a film riding seal with a leakoff flow rate of 400 cc/hr-'

to the containment sump and 400 cc/hr to the RCDT.

d.

1. 2 RCP seal is a film riding seal with a leakoff flow rate of 3 spm to the RCDT.

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CATEGORY 6 CONTINUED ON NEXT PAGE *****)

^ 1 PLANT:SYSTEMSV(40%)cAND PLANT-WIDE GENERIC P~sy-5 j.i,,..

.RESPONSIBILITIESS(17%)

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' QUESTION:l03L

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. Fallowing an: emergency start of the diesel, the. emergency' diesel generator' thutdown relay (SDR);will energize on:

c p

- Ov-

_Overcurrent.

v.

Eb. -

Loss of field.

c.

Under frequency..

d.

LGenerator differential lockout relay.

QUESTION: 04

-(1.00)

-The. wide range'T-hot. instrument signal is used as an. input to:

c.

RVLIS.

b.

Calculated Tavg.

ic.

Calculated loop temperature difference.

"d.

Rod control.

QUESTION: 05

.(1.00)

.The plant'is operating at 60% power.when loop 3 Delta-T indication fails I

LOW-and loop 3 Tavg indication fails HIGH.

The most probable cause for l-

,these indications is that loop 3:

c.

.Thot failed high.

.b.

Thot failed low.

l L

c.

Teold failed high.

-d.

lTeold failed ~ low.

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CATEGORY 6 CONTINUED ON NEXT PAGE *****)

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PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC Pag]

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RESPONSIBILITIES (17%)

. QUESTION: 06 (1.00)

'Tcchnical Specifications states that with the Quadrant Power Tilt Ratio creater than 1.02 but less than 1.09, the operator must, within two hours, r; duce the QPTR to within its limits or reduce thermal power.

The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow time for:

c.

corrective action in the event of xenon redistribution following power

changes, b.

identification and correction of a dropped or misaligned rod, c.

boron concentration changes to restore the QPTR to less than 1.02, d.

identification and correction of a failed excore detector.

QUESTION: 07 (1.00)

When synchronizing the generator to the grid. AC-120. " MAIN TURBINE GENERATOR STARTUP," directs the operator to adjust the " Load Set" until the synchroscope is rotating slowly in the fast direction.

The two p;rameters indicated by the synchroscope are:

c.

current and voltage differences.

b.

frequency and current differences.

c.

frequency and phase differences, d.

current and phase differences.

QUESTION: 08 (1.00)

Interlocks on the Refueling Machine may only be defeated with permission of:

a.

The Shift Technical Advisor.

b.

The Senior Reactor Operator in charge of the refueling.

l c.

The Maintenance Department Supervisor in charge of refueling.

l d.

The Plant Manager l

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CATEGORY 6 CONTINUED ON NEXT PAGE *****)

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PLANT SYSTEMS (40%)-AND PLANT-WIDE GENERIC PagJ 7

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RESPONSIBILITIES (17%)

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' QUESTION: 09 (1.00)

The Refueling Machine interlock that prevents motion of the bridge or trolley s

unless the gripper is.in the full up position is the:

c.

Hoist Lowering Interlock.

?

b.

Gripper Disengage-' Interlock.

c.

Fuel Transfer Interlock, d.

Traverse' Interlock'.

QUESTION: 10 (1.00)

The excess letdown divert valve (BG HV-143) NORMALLY directs excess letdown flow to the:

c.

PRT b.

RCDT c.

Seal water heat exchanger.and VCT

'd.

Letdown heat exchanger and VCT QUESTION: 11 (1.00)

During a reactor startup, the estimated critical rod position based on 1/M calculation is greater than 500 pcm above the rod position used in the ECP,

-The startup:

a.

must be stopped and reactor conditions maintained constant while the ECP is recalculated and the operators verify control rod positions and boron concentration, b.

.may continue if the DRPI and step counters are operating normally.

c.

must be stopped while rods are borated out to above the rod insertion limit and the ECP is recalculated.

d.

may continue after the rods are driven to the rod position used in the ECP and dilution of the RCS has been started.

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. QUESTION: 12 (1.00)-

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Auxiliary lFeedwater pump suction valves from Essential Service Waterfopen' icutomatically when

l a.'

.both main feed pumps have tripped and AFW suction header pressure drops below 7 peig.

i 15.

.both motor driven AFW pumps have started on SI and a condensate j

storage tank Lo Lo level alarm is received.

~

c.

the turbine driven AFW pump has been started' manually with the i

ACTUATE pushbutton from MCB RLOl8 end a condensate storage tank Lo r

level alarm ie received.

d.

safety injection has occurred following a LOCA and an AFP SUCTION PRESSURE LO alarm is received.

I

-QUESTION: 13

'(1.00)

' Identify the statement that describes the way the positive displacement charging pump is configured in the system, a.

The minimum flow line provides a minimum charging flow of 60 gpm to ensure proper-seal flow to the reactor coolant pumps.

b.

The pump is protected during low flow conditions by a 47 gpm minimum flow line that is directed to the VCT.

c.

The minimum speed of the pump is mechanically set to provide a minimum flow of 60 gpm to protect the pump during low flow conditions, d.

The minimum speed of the pump is mechanically set to provide a minimum flow of 47 spm to ensure proper seal injection flow to the reactor coolant pumps.

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CATEGORY 6 CONTINUED ON NEXT PAGE *****)

-PLANT SYSTEMS (40%) AND PLANTiWIDE GENERIC Paga 9

RESPONSIBILITIES-(17%)

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QUESTION: 14 (1.00)-

Which conditions or actions will actuate BOTH trains of the Auxiliary Feedwater Actuation System - Motor Driven Pumps (AFAS-M)?

a.

Any two steam generators with one of four detectors at Lo Lo level, b.

Pressing the pushbutton ACTIVATE on MCB RLOl8 for a single AFAS-M train.

c.

Any one steam generator with two of four detectors at Lo Lo level.

d.

Any two steam generators with two of four detectors at Lo level coincident with one main feed pump tripped.

QUESTION: 15 (1.00)

A Rod Position Indication (RPI) Rod Deviation Alarm (C-080) is generated if:

a.

data A and B channels are lost for any single rod or group of rode, b.

the position of any shutdown bank rod is below 220 steps.

c.

the position of any rod in control bank B is less than 161 steps.

d.

any control rod's position indication is in half accuracy mode.

QUESTION: 16 (1.00)

RHR Train A has been aligned to cooldown the reactor coolant system in accordance with GEN 00-006, HnT STANDBY TO COLD SHUTDOWN, and SYS EJ-120, STARTUP OF RHR TRAIN.

The desired RCS cooldown rate is established by adjusting the position of the:

a.

CCW Inlet Valve EG HV-101 to RHR Heat Exchanger A.

b.

CCW Outlet Valve EJ-V033 to RHR Heat Exchanger A.

c.

RHR Heat Exchanger A Bypass Valve EJ FCV-618.

d.

RHR Heat Exchanger A Outlet Isolation Valve EJ HCV-606.

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CATEGORY 6 CONTINUED ON NEXT PAGE ***** )

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. PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC Pcga 10 RESPONSIBILITIESL(17%)

QUESTION:-17 (1.00)-

b If pressurizer level transmitter LT 459 is selected.for control when the

.r:ference leg for.LT 459 develops a slow' leak, which of the-following I

d scribes anticipated instrument or plant response?

BB-LI-459 (RLO2)

BB-LI-460 (RLO2)

VCT LEVEL PZR LVL INDICATION PZR LVL INDICATION i

c.

INCREASING DECREASING INCREASING b.

DECREASING INCREASING INCREASING c.

INCREASING DECREASING DECREASING d.

DECREASING-INCREASING DECREASING QUESTION: 18 (1.00)

The plant is operating at 100% power with CCW pumps C and D supplying system loads. -An SIS is received.

Which statement describes the response-of the-CCW system?

a.

CCW pumps A and B will auto start, b.

CCW pumps C and D will be shed from their busses, then the LOCA sequencer will start CCW pumps A, B, C, and D.

c.

CCW pumps C and D will be shed from their busses, then the LOCA sequencer will start CCW pumps A and B.

i d.

CCW pumps C and D will continue to run and supply system loads, CCW pumps A and B will not start.

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CATEGORY 6 CONTINUED ON NEXT PAGE *****)

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PLANT ' SYSTEMS (40%) AND PLANT-WIDE GENERIC Pag] 11 RESPONSIBILITIES (17%)

~ QUESTION:'19' (1.00) e I

The Liquid Radwaste discharge valve (HB RCV-018) will AUTOMATICALLY isolate-

- the discharge'flowpath on high radiation from the Liquid Radwaste Discharge M;nitorL(HB-RE-18) and on:

c.

Service Water Radiation Monitor Hi Hi.

t b.

Low dilution water flow rate.

c.

High liquid radwaste discharge ~ flow rate.

4 d.

Waste Mon 1 tor Tank low level alarm.

QUESTION: 20 (1.00)

. Which statement describes the response of the Containment Cooling System during a LOCA?

c.

The component cooling water flow to the containment fan coolers increases from 1100 gpm to 2000 gpm.

- b, The containment fan coolers start in fast speed if not running and, if running in slow speed, automatically shift to fast speed when started by the LOCA sequencer, c.

The hydrogen mixing fans start in slow speed if not running, then shift to fast speed after a 60 second time delay, d.

The containment fan cooler exhaust damper fusible links melt at 160 degrees F in containment, releasing a hinged steel plate outward in each discharge duct.

QUESTION: 21 (1.00)

Both Containment Hydrogen Recombiners are turned on af ter a LOCA.

c.

I hour b.

5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> c.

1 day l

d.

9 days

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PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC _

Paga-12 RESPONSIBILITIES ~(17%)

4 QUESTION: 22_

-(1.00)

Nitrogen-induction from the Containment Spray Additive-Tank into the suction

-h:aders of the containment spray pumps is prevented by:

c.

the tank-isolation valves automatically closing on a tank low low level.

b.

.the close permissive on tank low low level allowing the operator to manually shut the tank isolation vr,2.ves.-

c.

the tank isolation valves automatically closing on low eductor NaOH suction flow.

Ed.

the tank isolation valves automatically closing on low tank pressure.

QUESTION: 23 (1.00)

Intermediate Range (IR) compensating voltage fails low for one of the IR dctectors.

The reactor subsequently trips.due to other causes, but the IR current on the felled.dctector does not go below 5 E-5 amps.

Which one of the following describes how the operator will monitor reactor

. power through the Source Range?

a.

Once the non-failed IR detector decreases to less than 1 E-10 amps, the Source Range Manual Reset pushbuttons will be used to manually reenergize the source range detectors, b.

Once the non-failed IR detector decreases to less than 1 E-10 amps, the failed IR detector will be bypassed allowing the source range detectors to energize, c.

Once the non-failed IR detector decreases to less than 1 E-10 amps, P-6 will be unblocked and the source range detectors will automatically reenergine.

d.

Once the non-failed IR detector decreases to less than 1 E-10 amps, i

one source range detector will automatically reenergine and the other will be manually reenergized using the Reset pushbuttons.

1

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

m.

PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC P g1 13 RESPONSIBILITIES (17%)

. QUESTION: 24

-(1.00)

Which input signals are used to control the feedwater bypass flow control v:alve when in automatic?

c.

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

I b.

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

c.

Steam generator level,-programmed steam generator level, steam flow, faed flow.

d.

Steam generator level, programmed steam generator level, total steam

-flow.

4 QUESTION: 25 (1.00)

Which Engineered Safety Features Actuation System (ESFAS) signal can be 4

roset at any time following initiation regardless of the status of the initiating signal?

a.

AFAS-M b.

MSLIS c.

CSAS d.

CPIS l

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

y n.

PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC Pcg3 14 RESPONSIBILITIES.(17%)

QUESTION: 26-(3.00)

Hitch the Protective Interlock function in-COLUMN A with the protective interlock designation in COLUMN B.

(Items in Column B may be used more i

than once or not at all.)

COLUMN A COLUMN B-O.

Prevents reactor trip on single 1.

P [

loop loss of flow.

2.

P-6 b.

Allows reset of SIS after 60 s but does not block manual actuation.

3.

P-7 c.

Prevents reactor trip if a main 4.

P-8 turbine trip occurs.

5.

P-9 d.

Blocks steam dump operation if Tavs drops below 550 degrees F.

6.

P-10 c.

Trips main turbine and both MFW 7.

P-11 I

pumps-on high-high SG level.

8.

P-12 f.

Allows the source range high flux trip to be blocked.

9.

P-13 10.

P-14 QUESTION: 27 (1.00)

Identify the source that DOES NOT have an input to the Pressuriser Relief Tank.

a.

Reactor Vessel Head Flange Leakoff b.

.CVCS Letdown Relief Valve c.

RHR Suction Relief Valve i

d.

RCDT pumps

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

p-=

e.,

w, PLANT-SYSTEMS ;(40%) AND PLANT-WIDE GENERIC Pa g 3 ' l-5 L

RESPONSIBILITIES (17%)

t E

p QUESTIONO28 (3.00)

-MATCH the automatic actions in COLUMN A with its associated VCT level 1

I cctpoint in Column B.

The Reactor Makeup System is the Automatic mode.

(Items in Column B'may be used more than once or not at all.)

COLUMN A COLUMN B t

c.

LCV-112A (Divert Valve) FULL DIVERT to RHT 1.

5%

4: b.

LCV-112A:(Divert Valve) STARTS TO OPEN to RHT 2.

22%

c.

VCT Low Level Alarm 3.

30%

d.'

FCV-110B-(BORIC ACID TO VCT DISCHARGE) opens fully 4.

35%

o.

FCV-110B (BORIC ACID TO VCT DISCHARGE)' closes fully 5.

45%

f.

VCT High Level' Alarm 6.

50%.

7.

63%

8.

70%

9.

80%

f 10.

'90%

11, 97%

12.

'100%

QUESTION: 29 (1.00)

The Atmospheric relief valve accumulators are sized to allow hours I

of operation with an atmospheric relief cycle every minutes and one feedwater valve cycle every

minutes, i

a.

20, 10, 8 l

b.

20, 8, 10 c.

8, 20, 10 d.

8, 10, 20

(***** END OF CATEGORY 6 *****)

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

e

'l

-PLANT 1 SYSTEMS:(40%) AND PLANT-WIDE GENERIC P g] 16 y

RESPONSIBILITIES (17%)

I j'.

L ANSWER:

01

^ ( 1. 00 ).

o.

REFERENCE:

LOL13 010 00. Rev. 5, p.

15-18, 23; EO 4

-010000A107 010000K603

..(KA's) i I

' ANSWER:

02 (1.00)

O.

REFERENCE:

LO 13 003 00, Rev. 4.

p.

9. 10: EO 2 003000K103

. (KA's)

ANSWER:

03 (1.00) d.

REFERENCE:

LO 14 064 00. Rev. 6, p. 47-48 EO 7 064000K402

..(KA's) l ANSWER:

04 (1.00) j

.s.

REFERENCE:

I LO 13 002 02. Rev.

4. p. 11: EO 4.

17 002000K107

..(KA's) i ANSWER:

05 (1.00)

C.

(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)

L.

~~e

'O-

. p' PLANT SYSTEMS-(40%) AND PLANT-WIDE GENERIC Pas) 17 RESPONSIBILITIES (17%)

A l

ro J

REFERENCE:

i LO.13 002 02, Rev.

4,.p.

12; EO.4 002020K509

-.. ( KA 's )

' ANSWER:

06 (1.00) i b.

REFERENCE:

T0chnical' Specification 3.2.4 BASES 001000G006 001050A202

..(KA*s) t 1 ANSWER:

07 (1.00) i o,

l REFERENCEi AC 120. Rev. 18, p. 22 062000A403

..(KA's) l ANSWER:

08 (1.00) b.-

t

REFERENCE:

i FHP 03-001, Rev. 5, p.

1 034000K402

..(KA's) 1 ANSWER:

09 (1.00) d.

REFERENCE:

ERP 03-001 Rev. 5, p.

31 L

034000K401

..(KA's)

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

b

PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC Peso 18 RESPONSIBILITIES (17%)

ANSWER:

10 (1.00)

C.

EFERENCE:

LO 13 004 00, Rev 5, p. 39; EO 7 004000G007

..(KA*s)

ANSWER:

11 (1.00) b.

REFERENCE:

GEN 00-003, Rev. 19, p. 10-11 001010A207

..(KA*s)

ANSWER:

12 (1.00) 8.

REFERENCE:

LO 14 061 00, Rev. 5, p.

16: EO 5, 20, 27 061000K107

..(KA*s)

ANSWER:

13 (1.00) d.

REFERENCE:

LO 13 004. Rev. 5, p. 28: EO 004000K604

..(KA*s)

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE * **** )

i

PLANT SYSTEMS (40%)'AND PLANT-WIDE GENERIC Page 19 O

RESPONSIBILITIES (17%)

f t

. ANSWER:

14 (1.00)-

O. -

i

REFERENCE:

?;

LO 14 061 00, Rev. 5, p. 27; E0 17 061000K402

..(KA*s) i t

1 i

(~

ANSWER:.

15 (1.00)

L Oc

[

REFERENCE:

i k

I LO'13 014 00, Rev. 1, p.

20-21; EO 5.

014000K406

..(KA's) i.

L ANSWER:

16 (1.00) i d.

t

REFERENCE:

j SYS-EJ-120. Rev. 13, p.

8

.i 005000K410 005000A101

..(KA's) j i

f ANSWER:

17 (1.00)

C.

REFERENCE:

LO 13 010 00, Rev. 5. p.

26-31; EO 3

-011000K101 011000K301 011000K404 011000A210

..(KA's)

{

ANSWER:

18 (1.00) d.

t 1

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE ***** )

L=

W p.-

PLANT' SYSTEMS (40%) AND PLANT-WIDE GENERIC Page~20 '

p E

. RESPONSIBILITIES (17%)

hs?'

=

REFERENCE:

'LO'14-008 00, Rev.E4, p.

21; EO 6 008030A304

.(KA's).

au ANSWER:

19 (1.00)

.b.

u

REFERENCE:

LO 14 069 00,'Rev. 2, p.

18; EO 6 068000K401

..(KA's)

-ANSWER:.

20 (1.00) d.

REFERENCE:

LO-13 022 00, Rev. 2, p.

7 022000K101 022000A101

..(KA's)

ANSWER:

21 (1.00)

.C.

REFERENCE:

-SYS GS-120, Rev. 4, p.

1 028000G001~

028000K601

..(KA~e)

ANSWER:

22 (1.00) l

'O.;

REFERENCE LO 13 026 00, Rev. 2, p.

14 EO 6, 9 026000A401 026020A101

..(KA's)

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

d

PLANT SYSTEMS (40%) AND PLANT-WIDE GENERIC Pego 21 RESPONSIBILITIES (17%)

ANSWER:

23 (1.00) a.

REFERENCE:

LO 13 015 01, Rev. 3. p.

27; EO 27 015000K407 015000A202 015000A303

..(KA's)

ANSWER:

24 (1.00) b.

REFERENCE:

LO 15 059 02, Rev. 3.

p.

16 EO 10 035010K401 035010A301

..(KA's)

ANSWER:

25 (1.00) c.

REFERENCE:

LO 13 013 01, Rev. 3,

p. 25: EO 9 013000A402 013000K402 013000K403 013000K105 013000K101

..(KA's)

ANSWER:

26 (3.00) a.

4 b.

1 c.

5 d.

8 e.

10 f.

2 (0.5 pts each)

(*****

CATEGORY 6 CONTINUED ON NEXT PAGE *****)

PLANT. SYSTEMS'(404) AND PLANT-WIDE GENERIC Page 22 RESPONSIBILITIES-(17%).

REFERENCE:

LP'050, LO 13 012 00. Rev. 4, p. 24 012000K406

..(KA*s) e

[-.

?

ANSWER:

27 (1.00)

.O..

REFERENCE:

LO-13 002 01, Rev. 1, p.

10 LO'13 002 00, Rev. 2. p.

13: EO 1, 3 i

007000A301

..(KA's) t ANSWER:

28 (3.00)

c. '

11 b-

~8

(

- c.

2 j

~d..

3 i

G.:

6 l

f.

11-r (0.5 pte each)'

i

REFERENCE:

LO 13 004 00,-Rev. 5, p.

25, 50 EO 3, 5

~004020A305

..(KA's) l h

ANSWER:

29 (1.00) i d.

REFERENCE:

1 LP 006-8, LO 15 039 00, Rev.

4, p.

17

-039000G004

..(KA's) l l

1

(***** END OF CATEGORY 6 *****)

( * * * * * * * * *

• END OF E XAMI NATION * * * * * * * * * * )

o l

b

.c i

i U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 4

FACILITY:

Wolf Creek l

REACTOR TYPE:

PWR-WEC4 DATE ADMINSTERED:

1989/11/20 i

f CANDIDATE:

)

INETRUCTIONS TO CANDIDATE-Read and follow the NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS attached to your examination.

An overall grade of at least 80% is required to pass the cxamination.

Examination papers will be picked up four and a half (4 %) hours cfter the examination starts.

SITE SPECIFIC WRITTEN EXAMINATION EXAMINATION POINTS 78.00 CANDIDATE'S SCORE FINAL GRADE All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature

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

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

2. After the examination has been completed, you mus+ aign the statement on the cover sheet indicating that the work is your own and you have nct received or given assistance in completing the examination.

This must be done after you complete the examination.

3. Restroom trips Pre to be limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of 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 eheet of the examination (if necessary).

7. You may write your answere 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.

8. If you write your answers on the examination question page and you need more space to knewer a specific question, use a separate sheet of the paper 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 section of your answer sheets whether you use the examination question pages or separate sheets of paper.

Initial each page.

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 anewer as to category and number (i.e. Plant Systems # 04. EPE # 10) and skip at least 3 lines between anewere 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 as < or > signe to avoid a simple transposition error resulting in an incorrect answer.

Write 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 de'th of answer required.

p

17ehhowcl1 calculations,methds,ortesumpticn3u;;dtoobtain.ancnewer.

18. Partici credit may be given.

Th:rof ra ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

NOTE: partial credit will NOT be given on multiple choice questions.

r.

I 19.-Proportional grading will be applied.. Any additional wrong information that is provided may count against you.

For example, if a question is l-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 be 0.89 instead of 1.00 even though'you got the'four correct answers,

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

r I-only.

f

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

In addition, 3

turn in all scrap paper.

l

-i

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

greater.

23. 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.)

24.-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 examination is still in progress. your license may be denied or revoked.

L t

l l

l l

L

• EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Paga 4

(36%)

I QUESTION: 01 (1.00)

'During the sequence of actions following a LOCA, adverse containment conditions will have a large effect on the:

c.

core exit thermocouple indications.

b.

RCS wide range RTD indications.

c.

RCS pressure indications.

d.

pressurizer level indications.

QUESTION: 02 (1.00)

Following an event that requires entry into FR-P1 because of an Integrity ORANGE path condition, the operator must suspend that procedure and enter another if:

a.

the Integrity path turns GREEN while performing step 3 of FR-Pl.

b.

a Suboriticality path turns YELLOW while performing FR-Pl.

c.

an Inventory path turns ORANGE while performing FR-P1 d.

a Containment path turns RED while performing FR-Pl.

QUESTION: 03 (1.00)

Besides EMG E-0, the only EMG procedures that can be entered DIRECTLY (i.e., not sent there from another procedure) are:

a.

ES-02 and C-0 b.

ES-02 and C-1 c.

E-1 and C-0 d.

E-2 and C-1

(*****

CATEGORY 2 CONTINUED ON NEXT PAGE * * * * * )

1

)

.EMERCENCY AND ABNORMAL PLANT EVOLUTIONS Pcg3 5

'(36%)

b' i

QUESTION: 04 (2.00)

Match the condition or action in COLUMN A with the corresponding Instrument Air pressure in COLUMN B at which each condition or action occurs or begins cecording to OFN 00-019. " LOSS OF INSTRUMENT AIR."

(Items in COLUMN B may b2 used more than once or not at all.)

COLUMN A COLUMN B a.

Nitrogen Supply Accumulators start 1.

70 peig supplying N2 to critical components 2.

80 psig 3.

90 peig b.

First Standby compressor starts 4.

100 peig 5.

110 peig c.

Normal system operating pressure 6.

115 psig 7.

100 psig d.

Service air system isolation valve 8.

105 peig (KA-PV-11) closes QUESTION: 05 (1.00)

Evacuation of the Control Room is required because of a control room fire.

The immediate responsibilities of the Reactor Operator (Operator C) include:

a.

trip the RCPs and verify Turbine trip.

b..

deenergize DC control power to NB01 and NB02.

c.

transfer control to SAS and verify Reactor trip, d.

open specified supply breakers on NG03C and NGO4C.

QUESTION: 06 (1.00)

The plant is operating at steady-state 60% power.

An IMMEDIATE manual reactor trip is required if:

a.

RCP A seal differential pressure equals 220 paid and is increasing, b.

RCP B frame vibration equals 3 mils, c.

RCP C motor bearing temperature equals 200 degree F and is increasing, d.

RCP D shaft vibration equals 17 mile.

(*****

CATEGORY 2 CONTINUED ON NEXT PAGE

• • • • • )

,o

• EMERGENCY /AND ABNORMAL PLANT EVOLUTIONS Pega 6

(36%)

[

QUESTION: 07 (1.00)

A pressurizer PORV is leaking to the PRT at a rate of 1 spm and all other system components will function normally.

According to Technical Specifications, this is:

a.

identified leakage that requires shutdown.

b.

unidentified leakage that requires shutdown.

c.

identified leakage but does not require shutdown, d.

unidentified leakage but does not require shutdown.

QUESTION: 08 (1.00)

The Computer is out of service and you are directed to determine the cubcooling margin for these RCS parametere:

Preceurizer pressure : 440 psig Thot = 350 degrees F Teold = 340 degrees F Tavs = 345 degrees F The subcooling margin is:

a.

104 degrees F.

b.-

107 degrees F.

c.

109 degrees F.

d.

112 degrees F.

(*****

CATEGORY 2 CONTINUED ON NEXT PAGE * **** )

e H

h EIGRGENCY AND ABNORMAL PLANT EVOLUTIONS Page 7

(365)

[

QUESTION: 09 (1.00)

L

Steam Generator A has an identified primary to secondary. leak of 30 gallons L

per day.

While operating at 75% power. radiation alarms are received on-L the Main Condenser vacuum pump vent and Steam Generator blowdown.. Level in the Pressurizer is'23% and RCS pressure is 1850 psig, both parameters are decreasing rapidly.

The appropriate operator response is to:

c.

start additional charging pumps to determine the size of the leak.

'b.

initiate a shutdown in accordance with the OFNs.

l I

c.

initiate a manual safety injection and enter EMG E-3.

d.

initiate a manual reactor trip and safety iniection and enter EMG E-0.

QUESTION: 10 (1.00)

During a reactor start up all indications are normal. however,.at 3% power you notice that one of the Intermediatt Range ceunt rate channel indications' r

is decreasing.

I&C investigates and says it's a minor problem and will take cbout two hours to correct.

i

~

According to OFN 00-008, " Instrument Malfunctions," you should:

I a.

increase power to a maximum of 15% to allow the secondary system to j

be prepared for power increase and hold there until the problem is corrected.

l b.

hold power about where it is, above P-6 and below 5%. until the j

problem is corrected, c.

continue the power increase to get above P-10 in case the other Intermediate Range channel should fail.

d.

insert the rods to decrease power below P-6 and reinsert Source Range protection until the problem is corrected.

l l

(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

l l

l

~

+w T: * '

EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 8

1

~(365)

E QUESTION: 11 (1.00)

-Identify.which step.is NOT an IMMEDIATE operator action for'EMG C-0,

'f Loss of All AC Power. "'

o, Verify AFW flow, b..

Verify reactor trip.

c.

Verify turbine / generator trip.

d.

Restore power to any AC emergency bus.

' QUESTION: 12 (1.00)

t. -

The reactor is operating at 75% power with control rods in manual when o control rod is dropped.

i According to 0FN 00-011. " Dropped or Misaligned Rod..and Realignment."

i.

.the Tavg/ Tref mismatch is INITIALLY maintained by:

5 c.

moving individual control rod banks in manual.

b.

. moving individual control rod groups in manual.

[

c.

changing RCS boron concentration.

'd.

changing Turbine load.

QUESTION: 13 (1.00)

If a rod ejection accident. occurs. the first reactivity coefficient to insert negative reactivity will be the:

o, moderator temperature coefficient.

b.-

pressure coefficient.

c..

void coefficient.

d.

doppler coefficient.

1 l

(*****

CATEGORY 2 COWTINUED ON NE XT PAGE * * * * * )

u

~ c EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pase 9

(36%)

r.

i QUESTION: 14 (1.00)

L The Emergency Diesels receive a start signal because a SIS has occurred.

i Fifty seconds later a CSAS signal is received causing:

L o.

the load sequence to stop, the loads stripped, and the 111 second i

timer to restart the sequence at time O seconds.

b.

the load sequence to pause, the CS pumps to start, and the' load sequence to continue from time 50 seconds.

t

[

c.

the load sequence to continue, the 111 second timer to time out, and l

the CS pumps to start at the end of the sequence.

}-

d, the load sequence to stop, the loads started after 15 seconds to be stripped, and the sequence to restart at time 15 seconds, i

QUESTION: 15 (2.50)

[

M;tch the radiation monitors in COLUMN A with the expected automatic action i

in COLUMN B if the radiation level increases above setpo1nt.

(Items in Column A may require more than one response and items in Column B may be u;ed more than.once or not at all.)

l COLUMN A COLUMN B i

c.

Unit Vent - GT RE-21 A&B 1.

CRVIS actuatec b.

Containment Atmosphere 2.

Gas Decay tank vent GT RE-31 & 32 HA HVC-14 elosee c.

Fuel'Bu11 ding Exhaust 3.

Emergency exhaust fane GG RE-27 & 28 CGG02 A&B start d.

Red Waste building GH RE-10 4.

No automatic action-(*****

CATEGORY 2 CONTINUED ON NEXT PAGE *****)

t

• EMERGENCY AND ABNORMAL PLANT EVOLUTIONS

~Page 10-( 36% )-

~

' QUESTION: 16 (1.00)

[

I Fallowing a loss of Vital 125 VDC Bus NKG1 at 90% power with nu operator cation, a reactor trip will occur because:

u c.

an RCP will. trip on loss of control power.

l I

b.

level in the steam generators will decrease.

c.

the MSIVs will drift shut, d

pressurizer PORVs will open causing low RCS pressure.

QUESTION: 17 (1.00)

-The RHR is providing shutdown cooling during preparations for refueling

[

with pressuricer level on-program.

.According to a CAUTION in OFN 00-015. " Loss of Shutdown Cooling," if you b

icse pressurizer level you are required to:

o.

isolate letdown flow.

L b.

trip the running RHR pump.

j.

c.=

trip any running RCPs.

L d.

start additional charging pumps.

(

l p

L

(*****

CATEGORY 2 CONTINUED ON NEXT PAGE ***** )

1

h 1 EMERGENCY'AND. ABNORMAL ~ PLANT EVOLUTIONS Page 11

'(36%)1 h.

QUESTION: 18 (1.00)

I Nith.one PORV block valve closed because of excessive. seat leakage in its respective PORV, excessive seat leakese develops in the other PORV.

The Technical Specification requires that:

O.

at least one PORV be restored to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in Cold Shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, l'

b.

both PORVs-be restored to operable status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be I

in Cold. Shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

c.

both block valves be closed with power removed and be in Hot

-Shutdown within S hours, l-d.

the recond PORV be restored to operable status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or close its associated block valve.

QUESTION: 19 (1.00)

The reactor is operating at 60% power when turbine load is increased 10% with NO control rod motion or change in boron concentration.

An indication you would expect to receive is a:

.c.

TREF /TAUCT H1 annunciator, b.

TREF /TAUCT LO annunciator, c.

RPI ROD DEV annunciator, d.

RPI DEV PR TILT annunciator.

QUESTION: 20 (1.00)

An event that requires IMMEDIATE BORATION would be when:

c.

a control rod is at or below the lo insertion limit, b.

three out of four loop Tavgs reach 540 degrees F after reactor trip.

c.

minimum shutdown margin is in question.

d.

a control rod is misaligned +/- 12 steps from ite group.

($****

CATEGORY 2 CONTINUED ON NEXT PAGE *****)

l

' EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 12 (38%)L QUESTION: 21 (1.00)

TA loss of containment integrity (as defined by Technical Specifications) till occur if:

-0.-

both doors on a containment airlock are blocked'open for maintenance' while in Mode 4.

o b.

the leakage rate of a containment penetration exceeds the limits of Technical Specifications while in Mode 5.

j c.

an outer airlock door is found open while in Mode 2.

d.

an inner airlock door is left open while performing maintenance in containment while in Mode 1.

QUESTION: 22 (1.00)

Pressurized Thermal Shock caused by a Steam Line Break could-recult in:

c.-

brittle fracture of the vessel occurring because the nil-ductility l

temperature of the vessel decreases with age.

t b.

thermal stresses exceeding the critical yield stress of the vessel and cause a vessel wall flaw to grow and fail the vessel.

i c.

the need to determine whether or not the RCS pressure-temperature boundary-limit has been exceeded based on the-time history of the i

transient.

i d.

the loes of reactor vessel integrity because of the r%pid cooldown and pressurization initially caused by the steam line break.

e P

(*****

CATEGORY 2 CONTINUED ON NEXT PAGE *****)

1 I

--,m-m

+y v

b

'# EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 13 (36%).

t i

QUESTION: 23 (1.00)

The basis for ensuring control of steam generator levels during Natural Circulation is:

t-c.

to prevent unnecessary positive or negative reactivity insertions caused by varying the cooldown-rate.

b.

to prevent a Technical Specification violation caused by an i-excessive cooldown rate.

i i

I-to provide continuous flow to the steam generator to ensure steam c.

s l'

generator tube integrity.

d.

to provide a stable heat sink for decay heat removal at the steam generator no-load level.

l QUESTION: 24 (1.00)

All-plant systems and controls are in the NORMAL at power lineup.

L A reactor trip may. result because of a complete loss of power to:

i (Assume that NO operator action is taken.)

j o.

inverter NN11.

i b.

inverter NN12.

j c.

- transformer XNN05.

d.

transformer. XNN06.

f i

i

(***** CATEGORY -2 CONTINUED ON NEXT PAGE 4****)

L

3annm anvat anu _nenuwau rueue cvvuvuvna rage Aa (36%)

'GUESTION: 25 (1.00)

Based on these' plant parameters and indications:

Reactor power 72%

RCP A vibration 3 mile on frame and:17 mile on shaft RCP A HI'81 Seal Leakoff Flow alarm RCP A #1 Seni inlet temperature 213 degreesLF CCW inlet temperature to RCP A thermal barrier 98 degrees F RCP A motor bearing temperature 165 degrees F the first action that the operator should take is to:

c.

close RCP A #1 seal leakoff isolation valve within 5 minutes.

b.

rapidly reduce power to < 48% and trip RCP A.

c.

trip the reactor, turbine, and RCP A and enter EMG EO.

d.

attempt to reopen CCW isolation valve to RCP A and increase flow.

QUESTION: 26 (1.00)

The basis for depressurizing all intact steam generators to 100 psig in Step 12 of FR-Cl, " Response to Inndequate Core Cooling," is to:

c.

ensure core exit thermocouple temperatures are reduced to lesc than 700 degrees F.

b.

ensure core exit thermocouple temperatures are reduced to less than 1200 degrees F.

c.

reduce RCS pressure to aid in recovery of reactor water level, d.

enhance natural circulation cooling of the reactor core.

(*****

END OF CATEGORY 2 *****)

h

PIANT SYSTEMS (51%) AND PLANT-WIDE GENERIC.

PasJ 15'

-RESPONSIBILITIES (13%)

j 1

P.

l QUESTION: 01

-(1.00)

The.CCW Surge Tank level and CCW pump discharge pressure are decreasing.

The automatic action that occurs when system diceharge pressure decreases i

t3 26 psig is:

)

4 O.

automatic makeup initiates to the affected train, b.

CCW to the Radwaste Building and Post Accident Sampling Station isolate.-

i the standby CCW pump in the unaffected train starts, c.

d.

the standby CCW pump in the affected train starts.

t QUESTION: 02 (1.00)

Assume steady state operation and the pressuriser spray valve has just opened i

Ot 100% power.

The Pressure Master Controller setpoint is then inadvertently-changed to 2370 psig.

Assume a step change in the setpoint and assume that l

pressuricer pressure control remains in automatic.

l The immediate automatic responces of the system will be:

c.

Powerfoperated relief valve PCV-455A opens, spray valves open, pressuricer heaters de-energize, i

b.

Spray valves open, pressuriser heaters energize.

c.

Spray valves close, pressurizer heaters energise.

d.

Power Operated Relief Valves PCV-465A and-PCV-456A open, spray j

valves open, pressurizer heaters energize.

l

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

h.

.raanr c 21&Mb (013) AND YinN1-01Da'taaNEMAV rage.10' RESPONSIBILITIES (13%)

GUESTION: 03 (1.00)

Which statement describes the reactor coolant pump 8 2 seal?

c.

1. 2 RCP seal is a face type rubbing seal with a leakoff flow rate of 3.gph to the RCDT.

b.

1. 2 RCP seal is a face type rubbing seal with a leakoff flow rate of 3 spm to the VCT.

I, c.

1. 2 RCP seal is a film riding seal with a leakoff flow rate of 400 cc/hr to the containment sump and 400 cc/hr to the RCDT.

L d.

1. 2 RCP seal is a film riding seal with a leakoff flow rate of 3 gpm to the RCDT.

QUESTION: 04 (1.00)

Following an emergency start of the diesel, the emergency diesel generator chutdown relay (SDR) will energize on:

c.

Overcurrent.

b.

Loss of field.

c.

Under frequency.

d..

Generator differential lockout relay.

QUESTION: 05 (1.00)

The wide range Thot instrument signal is used as an input to:

o.

RVLIS.

F b.

Calculated Tavg.

c.

Calculated loop temperature difference, d.

Rod control.

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

E

f#

, 5 PLANT' SYSTEMS (bl4) AND PLANT-WIDE GENERIC Page 17 N

RESPONSIBILITIES (13%)

QUESTION: 06 (1.00)

The plant is operating at 60% power when loop 3 Delta-T indication fails LOW and loop 3 Tavs indication fails HIGH.

The_most probable cause for-these' indications is that loop 3:

c.

Thot failed high.

[

b.

Thot failed low, c.

Teold failed high.

d.

Teold failed low.

E I

QUESTION: 07 (1.00) l_

A centrifugal charging pump has been started when a piping failure occurc cn the pump discharge.

If pump-RUNOUT-follows, it will be indicated by:

t c.-

high discharge pressure, high flow, and high power requirements, j

b.

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

c.

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

d.

low discharg7 pressure, high flow. and high power requirements, j

i QUESTION: 08 (1.00)

When synchronizing the generator to the grid. AC-120. " MAIN TURBINE

-GENERATOR STARTUP." directs the operator to adjust the " Load Set" until the synchroscope is rotating slowly in the fast direction.

The two

_p2rameters indicated by the synchroscope are:

c.

current and voltage differences.

b.

frequency and current differences, c.

frequency and phnee differences.

d.

current and phase differences.

r l

(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

tw iPLANT SYSTEMS-(51%) AND PLANT-WIDE GENERIC Page 18 RESPONSIBILITIES (13%)

I 1

QUESTION: 09 (l'.00)

During a reactor startup, the estimated critical rod _ position based on 1/M calculation is greater than 500-pcm above the rod position used in the ECP.

[

The Startup:

l t

o, must be stopped and reactor conditions maintained constant while the f

ECP is recalculated and the operators verify control rod positions and boron concentration.

b.

may continue if the DRPI and step counters are operating normally.

F

_c.

must be stopped while rods are borated out to above the rod insertion limit and the ECP is recalculated.

l t

d.-

may continue after the rods are driven to the rod position used in the ECP and dilution ef.the RCS has been started.

l 5

QUESTION: 10 (1.00)

The Refueling Machine interlock that prevents motion of the bridge or trolley unless:the gripper is in'the full up position is the:

-c.

Hoist Lowering Interlock.

b.

Gripper Disengage Interlock.

c.

Fuel Transfer Interlock.

d.

Traveree Interlock, i

r

-QUESTION: 11 (1.00)

A Rod Position Indication (RPI) Rod Deviation Alarm (C-080) is generated if:

o.

data A and B channels are lost for any single rod or group of rods, b.

the position of any shutdown bank rod is below 220 steps, j

c.

the position of any rod in control bank B is less than 161 steps.

d.

any control rod's position indication is in half accuracy mode.

L L

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

l

f

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC Par] 19 RESPONSIBILITIES (13%)

o t

b QUESTION: 13 (1.00)

Identify the. statement that describes the way the positive displacement

> charging pump is configured in the system.

.j o.

The minimum flow line provides a minimum charging flow of 60 gpm to r

ensure proper seal flow to the reactor coolant pumps.

i b.

The pump is protected during low flow conditions by a 47 gpm minimum i

flow line that is directed to the VCT.

I c.

The minimum speed of the pump is mechanically set to provide a minimum flow of 60 gpm to protect the pump during low flow conditions, d.

The minimum speed of the pump is mechanically set to provide a minimum flow of 47 gpm to ensure ptoper seal injection flow to the reactor

[

coolant pumps.

t T

QUESTION: 13 (1.00)'

Which conditions or actions will actuate BOTH trains of the Auxiliary Fcedwater Actuation System - Motor Driven Pumps (AFAS-M)?

c.

Any two steam generators with one of four detectors at Lo Lo level, b.

Pressing the pushbutton ACTIVATE on MCB RLOl8 for a single AFAS-M train.

i c.

Any one steam generator with two of four detectors at Lo Lo level.

d.

Any two steam generators with two of four detectors at Lo level coincident with one main feed pump tripped.

i i

b

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

i I'

+ PLANT SYSTEMS (bl%) AND PLANT-WIDE GENERIC Pogo 20 RESPONSIBILITIES (13%)

l QUESTION: 14 (1.00)

Auxiliary Feedwater pump suction valves from Essential Service Water open cutomatically when:

a.

both main feed pumps have tripped and AFW succion header pressure drops below 7 psig.

b.

both motor driven AFW pumps have started on SI and a condensate storage tank Lo Lo level alarm is received, c.

the turbine driven AFW pump has been started manually with the ACTUATE pushbutton from MCB RLO18 and a condensate storage tank Lo level alarm is received.

d.

safety injection has occurred following a LOCA and an AFP SUCTION PRESSURE LO alarm is received.

QUESTION: 15 (1.00)

If pressuricer level transmitter LT 459 is selected for control when the reference leg for LT 459 develops a slow leak, which of the following describes anticipated instrument or plant response?

BB-LI-459 (RLO2)

BB-LI-460 (RLO2)

VCT LEVEL PZR LVL INDICATION PZR LVL INDICATION a.

INCREASING DECREASING INCREASING b.

DECREASING INCREASING INCREASING c.

INCREASING DECREASING DECREASING d.

DECREASING INCREASING DECREASING

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE * * * * * )

1

PLANT SYSTEMS (51%) AND PLANT-WIDE GENERIC

-Pase 21

RESPONSIBILITIES (13%)

5f

' QUESTION: '16 (1.00)

RNR Train A has been aligned to cool down the reactor coolant system in accordance with GEN 00-006, HOT STANDBY TO COLD SHUTDOWN. and SYS EJ-120.

STARTUP OF'RHR TRAIN.

The desired RCS cooldewn rate is established by Ed,iusting the position of the:

o.

CCW' Inlet Valve EG HV-101 to RHR Heat Exchanger A.

l b.

Cr*W Outlet Valve EJ-V033 to RHR Heat Exchanger A.

E o.' -

RHR Heat Exchanger A Bypass Valve EJ FCV-618, 11 RHR Heat Exchanger A Outlet Isolation Valve EJ HCV-606.

b QUESTION: 17 (1.00)

The~ excess letdown divert valve (BG HV-143)-NORMALLY directs excess letdown.

flow to the:

l

c..

PRT b.

RCDT k

c.

Seal water heat exchanger and VCT d.

Letdown heat er. changer and VCT l

QUESTION: 18 (1.00)

The. plant is operating at 100% power with CCW pumps C and D supplying system loads.

An SIS is received.

Which statement describes s i

, response of the CCW system?

c.

CCW pumps A and B will auto start.

.b.

CCW pumps C and D will be shed from their busses, then the LOCA sequencer will start CCW pumps A. B. C. and D.

'c.-

CCW pumps C and D will be ehed from their busses, then the LOCA sequencer will start CCW pumps A and B.

d.

CCW pumpo C and D will1 continue to run and supply system loads. CCW pumps A and B will not start.

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE ** ** * )

. PLANT SYSTEMS ($1%) AND PLANT-WIDE GENERIC Paga 22 RESPONSIBILITIES (13%)

~

l QUESTION: IP (1.00)

The Liquid Radwaste diacharge valve (HB RCV-018) will AUTOMATICALLY isolate the discharge flowpath on high radiation from the Liquid Radwaste Discharge Monitor (HB-RE-18) and on:

a.

Service Water Radiation Monitor Hi Hi.

b.

Low dilution water flow rate.

c.

High liquid radwaste discharge flow rate.

d.

Waste Monitor Tank low level alarm.

QUESTION: 20 (1.00)

Which statement describes the responee of the Containment Cooling System during a LOCA?

a.

The eomponent cooling water flow to the conte.inment fan coolers increases from 1100 gpm to 2000 gpm.

b.

The containment fan coolere start in fast speed if not running and, if running in slow speed automatically shift to fast speed when started by the LOCA sequencer, c.

The hydrogen mixing fans start in slow speed if not running, then shift to fast speed after a 60 second time delay.

d.

The containment fan cooler exhaust damper fusible links melt at 160 degrees F in containment, releasing a hinged steel plate outward in each discharge duct.

QUESTION: 21 (1.00)

Both Containment Hydrogen Recombiners are turned on after a LOCA.

a.

I hour b.

5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> c.

1 day d.

9 days

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE ** * * * )

(([b]'.FLANTSISTEMS(bl%)ANDPLANT-WIDEGENERIC' E

P g5 23 j

J ~-

(RESPONSIBILITIES-(13%)

?-

7.

[. !

r f

i 7

.;. QUESTION: 22

-(1.00).

I?

Nitrogen-induction from the Containment Spray Additive Tank.into tr.e suction ~--

p

htaders_of the containment spray pumps is prevented by:

v

.:(

dr

the ' tank isolation valves automatically closing cn1 a tank low low level.-

E ib.

the1close permissive on tank low low level allowing _the operator to manually shut the~ tank isolation valves.

i Fr c.--

-the tank ioolation valves automatically closing on low eductor NaOH l

suction' flow..

t t

D

'd.

the tank isolation valves automatically closing on low tank-pressure, i

i

_ QUESTION: 23 (1.00)

. Intermediate Range'(IR) compensating voltage fails low for one of the IR dotectors.

The reactor subsequently. trips due to other causee, but the IR-current on'the failed-detector does not go below 5 E-5 amps.

Which.one of the following describes 1how the operator will monitor reactor power through the Source Range?

c.

-Once the non-failed IR detector decreases to less then-1 E-10 amps, the Source Range Manual Reset pushbuttons-will be used to manually reenergine the source range detectors.

- b.-

Once the non-failed IR detector decreases to less than 1 E-10 amps, i

the failed IR detector will be bypassed allowing the source range detectors to energize.

c.

LOnce the non-failed IR detector decreases to less than 1 E-10 amps, P-6 will be' unblocked and the source range detectors will automatically reenergice.

~

)

Once^the non-failed IR detector decreases to less than 1 E-10 amps, one source range detector will automatically reenergice and the other will be manually reenergized using the Reset pushbuttons.

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

h'i

l. PLANT' SYSTEMS-(51%)-:AND PLANT-WIDE GENERIC ~

Pas? 24-.

b RESPONSIBILITIES (13%)

u'

\\'

,e l"

[

b LQUESTION: 24: -(1.00)

U h

WhichLinput signals are used to. control the feedwater bypass' flow control valve when in automatic?

l-E lc.

Steam header pressure, feed pump discharge pre'ssure, total steam flow.

n b.

Steamigenerator-level, programmed steam generator. level, auctioneered~

high nuclear power.

r c.

Steam generator level, programmed steam generator. level,-steam flow, feed flow.

d.

Steam = generator level, programmed steam generator. level, total steam.

E

-flow.

. QUESTION: 25 (l;00.)

Which Engineered Safety Features Actuation System (ESFAS) signal can be reset at any' time following-initiation regardless of the status of the initiating signal?.

a.

AFAS-M b.-

MSLIS c'

CSAS s

Id.

CPIS QUESTION: 26 (1.00) 1Whr.. starting the FIRST Turbine Driven MFW pump, BOTH pumps should be raset to prevent:

a.

' trip of the MFW pump turbine on overspeed.

-b.

tripping the Startup feed pump on low suction pressure.

c.

spurious actuation of the AFAS.

.d.

spurious actuation of the FWIS.

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

. PLANT SYSTEMS'(51%)'AND PLANT-WIDE GENERIC Pcgo 25

- a-RESPONSIBILITIES (13%)

4' l

QUESTION:.27 (1.00)

-With the plant at 82% power, trip of a single Main-Feedwater Turbine-(with.NO. operator action) will result in:

a.

automatic runback of the Main Turbine.

b.

a reactor' trip on loss of feedwater signal, c.

automatic start of the Startup feed water pump.

d.

a' reactor trip on low steam generator water level.

QUESTION: 28 (1.00)

-The Condensate system procedure states that the Starting Duty Limits on a condensate pump at ambient temperature are:

a.

2 starts in succession with subsequent starts one hour-apart, b.

2 starts in succession with subsequent starts one-half hour apart.

c.

1 start with subsequent starts one hour apart.

'd.

1 start with subsequent starts one-half hour apart.

QUESTION: 29 (1.00)

The plant is at full power with LP heater string A isolated.

Problems with heater 3C require isolation of that heater.

To isolate heater 3C, reactor

power must be reduced to; a.

95% or less initially then can be increased back to full power after the isolation.

b.

65% or less initially and maintained at or below that power level.

c.

65% or less initially then can be increased back to 95% or less after the isolation.

d.

95% or less initially and maintained at or below that power level.

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE ** *** )

ym p

.PLANTLSYSTEMS;(bl%) AND PLANT-WIDE GENERIC, Pag 1.26 L,

RESPONSIBILITIES (13%);

g s

[ 2.-

=

p QUESTION: 30~

(l'.00);

t The:=Incore Thermocouple System (ITS)? output'provides: inputs to the= plant'

[

' computer where the signals are processed:and used for:-

~

V i

p e..

'information display and-temperature compensation of RVLIS.-

Eb.

information-display and feedback to hot reference junction box.

Ec.

information' display and referenceitemperature.for'the: MIDS.

"d.

information; display only.

-QUESTION: 31' -(1.00)

A Waste Gas System Gas' Decay Tank is being operated 11n the Release Mode.

-The release must be terminated immediately if:

a.

a Radwaste Building Exhaust Fan. trips and only one is left-: running.

~b.

the purge ~on the-VCT is isolated during the release.

Ec.

. radiation monitor RE-10B becomes inoperable, d.

radiation monitor RE-22 fails low.

-t h

.i

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

wy n

' P s]'27--

R 3aPLANT--SYSTEMS (51%)'AND PLANT-WIDE:GENERICL k.

( RESPONSIBILITIES : (-13% )-

b s

!i

.: QUESTION: 32 (3.00);

j w.

N MatchLtheiProtective. Interlock function in< COLUMN A-_with the-protective I

(L

interlock designation in. COLUMN B.

(Items'in. Column B.may beiused more h

than once or:not at'all.)-

E n

~

COLUMN A COLUMN:B-l Oc-Prevents' reactor trip on single 1.

P-4=

d

~

loop loss;of flow.-

l

,3; 2

P-8 ib, Allows reset of SIS after 60 s but t

does not block' manual actuation._

3.

P-7 I

c.

Prevents _ reactor. trip'if a main 4.

P-8 turbine tripn occurs.

5.

-P-9

d.

Blocks-steam dump operation-if Tavgudrops below 550' degrees F.

6.

P-lO-i o._

Trips main-turbine and both MFW

'7.

P-ll

-f pumps <nt high-high SG - level.

.i 8.

P-12 l

Lf -

2A11ows the source range high flux trip to:be blocked.

9.

P-13

+

10.

P-14 4

QUESTION: 33 (1.00)

Identify the source that DOES NOT have an input to' the Pressuriser Relief

Tank, a.

Reactor Vessel Head Flange Leakoff

.b.

CVCS Letdown Relief Valve c.

'RHRESuction Relief Valve d.

'RCDT pumps i

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

k iPLANTJSYSTEMS-[(51%) BAND-PLANT-WIDE GENERIC

'PCsy 28:

RESPONSIBILITIES,(13%)

j k

U r

?C (QUESTION: 347

-(3.00) t i[

.MATCHithe automatic' actions in' COLUMN-A with its' associated VCT level cstpoint: in-Column B.

The Reactor Makeup System is~the Automatic mode.

p

' (Items in Column B-may;be'used more than once or'not at'all.)

[_

COLUMN A-

~ COLUMN B-t:

c.

LCV-112AD(Divert ValveL) FULL DIVERT to RHT' 1.

5%

1 h^

'b..

LCV-112Al(Divert-Valve) STARTS TO OPEN1to RHT' 2.

22%

i-L-

_ ~.

VCT Low Level Alarm 3.

30%

c E

FCV-110B (BORIC ACID.TO VCT DISCHARGE) opens fully 4.

35%

d.

t I'

e.

FCV-110B (BORIC ACID TO VCT DISCHARGE) closes fully-5.

45%

.f.

VCT High Level Alarm 6.

50%

7.

- 63%-

8.

70%

9.

80%

i 10, 90%~

r 11.

97%:

12.

100%

-QUESTION: 35 (1.00)

ThefAtmospheric relief valve accumulators are sized to allow hours Lof operation with an atmospheric relief cycle every minutes and

.one feedwater-valve cycle every.

minutes, a.

20, 10, 8-lb.

20, 8, 10 c.

8, 20, 10 ud.

8, 10, 20

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

=

y.

. ' VTPLANTf5YSTEMS M i%) AND PLANT-WIDE' GENERIC-Peg 129;

&jp

, RESPONSIBILITIES / ( 13%).~

y o-g.

QUESTION: 136 (0.00)'

Deleted.

IJ '

L fk$,

} 4-1 e.

1

.\\i h>

W F

' QUESTION:. -37

-(1.00).

A--' confined space entry.is in progress and 'YOU are the Standby Person.

The' y

Entry?Permitt shows these atmospheric-conditions' exist:

(\\

Oxygen 19.2%

Hydrogen 0.3%.

YOU.are, required'to:

<a.

stand just inside.the confined area with a donned Self Contained-Breathing: Apparatus (SCBA) to maintain visual contact with the i

-worker (s)'.

' bi --

-stand just inside~the confined area with a SCBA within 50-feet-to-h

< maintain visual contact with the. worker (s).

E c.-

stand just outside the confined area with-a donned SCBA and be in radio or ' lifeline contact with the worker (s).

.d.

stand just outside the confined area'with a SCBA within 50 feet

and be in radio or lifeline contact with the worker (s).

4 L

l i

5

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE ***** )

k.

I i.

^ ^ > -

u VS PLANT! SYSTEMS ~(51%)AND PLANT-WIDE. GENERIC:

.Pago 30

RESPONSIBILITIES:(13%)'

4' s

UL ?

i i

l LQUESTION:!38-(1.00)'

r l When working on electrical-equipment the: absence-of an L" Equipment

[

Energized Tag" within that cubicle-means

i ca.

all equipment within'that cubicle is.deenergized..

b..

all~ equipment within that cubicle must have: a~ grounding ' device

~

-and ground dise' attached.

c'.

a Human DNO must be postediat the cubicle.

-[

t

[

.d.

equipment within-that cubicle should still be considered energized =

until proven otherwise.

-QUESTION: 39 (1.50)

,Mhtch the-Locked Valve described in COLUMN A with the1Tagfcolor,that1 l

identifies the valve' position from COLUMN B.

(Items in COLUMN B may__

Lba used more than once or not.at'all.)

COLUMN A.

COLUMN B a.

Locked _ Closed

.l.

Red

[

. b '.

Locked Open1 2.

Orange c.

Locked Throttled 3.

Green

-l

d' Locked Neutral

'4.

Blue o.

' Chain Locked Closed 5.

Black i

f.

Chain Locked Open 6.

White

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

L

g P sy 31 m, PLANT SYSTEMS (51%) AND PLANT-WIDE GENERICL 9:4 RESPONSIBILITIES (13%)

y y

tp E.

240.

(1.'00) hj' LQUESTION:.

V

[

During normal' power; operation, an NLO: reports that:a fire-doorJto the k

.S;uth ESF Swicthgear' Room cannot be closed because:it was damaged while A moving'a-toolbox.

~

ADM 13-103, " Fire Protection: Impairment: Control," requires:

f c...

Tthe~ fire watch patrol'toJincrease-the frequency of surveillance to every half. hour.

.b..

a continuous fire-watch'be posted because-of a potential for.

. loss of Halon.

I n

c.

4 notification of the Fire Protection Specialist within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to expedite repair.

d.

the NLO to obtain'a' permit from the Fire Protection Specialist 4

authori=ing the impairment.

l L

QUESTION: 41 (3.00)-

4 MatchitheLQUARTERLY; EXPOSURE LIMIT description in COLUMN A with the maximum numerical dose in COLUMN B.

(Items in COLUMN B.may be used more than once or not at all.)

1 COLUMN A COLUMN B-

.a.

10 CFR 20 Limit to skin 1.

1-Rem s

b.

10 CFR 20 Limit to whole 2.

2 Rem 5

body with exposure history 3.

3 Rem 1 c '.

10 CFR120~ Limit to feet 4.

5 Rem j

d.

WCGS Limit to whole body 1

without special approval 5.

7.5 Rem o.

WCGS-Limit to whole body 6.

18.75 Rem with PSRC approval

.l f,

'WCGS Limit-to whole body

'with Manager Radiation Protection approval i

l s

(*****

CATEGORY 3 CONTINUED ON NEXT PAGE *****)

.i

,c Bi: " '

i# PLANT-:~ SYSTEMS 2 ( 51% ); AND! PLANT-WIDE V GENERIC

~

- Post 32!

tRESPONSIBILITIES (13%);

g N

.! QUESTION:!42:

(1.00) v.

M

The ALARAlconcept

fJ

'c.

' specifies:WCNOC's exposure limits.in emergency situations.

bi 2 prevents' exceeding 10 CFR 20 exposure 111mits.-

-f F

if

,c.

appliesoto-both~' external and'internalt exposure.

d.

' defines minimum dosimetry requirements"for; radiation work permits.

i

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p I

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r.-

l l.

(***** END OF CATEGORY 3 *****)

( * * * * * * * * ** END OF E XAMINATION * * * * * * * * * * )

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(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)

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(*****

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l:

L D

g.ia@;S:"9 ePLANT> SYSTEMS -(51%) AND PLANT-WIDE GENERIC:

. Pas > 39 :

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(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)

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M-PLAhlTSYSTEMSi(51%)6ANDPLANT-WIDEGENERIC-Paga 40

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,iPLANT. SYSTEMS (51%)'AND-PLANTtWIDE? GENERIC 1 Pagef43-g LRESPONSIBILITIES-(13%);

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(*****

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613 n PC s y.4 4 -'

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L RESPONSIBILITIES 1(13%)

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(*****

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.(***** CATEGORY ~ 3 CONTINUED ON NEXT PAGE *****)

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