IR 05000366/1990027

Exam Rept 50-366/90-27OL on 901003.Exam Results:Reactor Operator Candidate Passed Written Exam & Issued Reactor Operator License on 901009

ML20058B613
Person / Time
Site:	Millstone, Hatch
Issue date:	10/15/1990
From:	Briggs L, Eselgroth P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20058B605	List: IR 05000336/1990027 IR 05000366/1990027
References
50-336-90-27OL, NUDOCS 9010300335
Download: ML20058B613 (86)

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{{#Wiki_filter:- -. - _.. -. .. U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT .. EXAMINA110N REPORT NO.

50-336/90-27 FACILITY DOCKET NO.

50-336 FACILITY LICENSE NO.

DPR-65 LICENSEE: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270 FACILITY: Millstone Nuclear Power Station, Unit 2 EXAMINATION DATES: October 3, 1990 ',

1. 8/[8 CHIEF EXAMINER: _//fv [

. < - Larrygf. Briggs, at or Operations Engineer Date APPROVED BY: ?>-

J 6 /wt _/6//.f/po Peter Eselgrofh, C ief, PWR se'ction late , Operations Branch, Division of Reactor Safety * SUMMARY: A written examination retake was administered to one reactor operator (RO) candidate..The reactor operator candidate passed the written examination and was issued a Reactor Operator License on October 9, 1990.

, 9010300335 901017 ADOCK0500g6 DR

_ _ _ _ - _ _ _ _ _ _ $$ ' i .s - e

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I DETAILS i . TYPE OF EXAMINATIONS: Replacement 1.0 EXAMINATION RESULTS: , One reactor operator candidate was administered a retake written exami-

' nation on October 3, 1990.

The candidate passed the examination and was issued a license on October 9,1990.

r CHIEF EXAMINER:- Larry' E. Briggs, Senior Operations Engineer

PROCTOR:. Peter Habighorst,-Millstone' Unit 2, Resident' Inspector "- . LICENSEE PERSONNEL PRESENT AT THE EXIT MEETING: The-exit meeting <was conducted by Mr. Briggs, via telephone conversation with Mr. Wilson, Supervisor Operator Training for Unit 2, on October 9, 1990, during which the results of the examination were discussed.

2.0 _ PRE-EXAMINATION REVIEW-

On October 1, 1990, prior-to the administration of the Reactor Operator' - (RO) written examination', three (3) Millstone Point 2 training. staff members,.all under security' agreement, reviewed the examinations at the NRC office in King of Prussia, Pennsylvania.

This review was performed to ensure that'the examination to be administered was content valid and-performance based.

3.02-SUMMARY OF NRC AND LICENSEE COMMENTS MADE AT THE EXIT MEETING: u

A.

The Chie' f' Examiner informed the licensee that the candidate had passed'the written-examination.- . B.

'The Chief Examiner informed the licensee < that' the written' explanation' W of reference material usage =provided in a letter to the. contractor E .had-greatly. simplified and' enhanced the usability of the reference.

-. material -in the preparation.for 'the examination.

. -- Att'achment: Written Examination and Answer Key (RO)' !. . U.S. NUCLEAR REGULATORY COMMIS$10N REGION I OPERATOR LICENSING EXAMINATION REPORT .. EXAMINATION REPORT NO.

50-336/90-27 FACILITY DOCKET NO.

50-336 FACILITY LICENSE NO.

DPR-65 LICENSEE: Northeast Nu'elear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270 FACILITY: Millstone Nuclear Power Station, Unit 2 EXAMINATION DATES: October 3, 1990 CHIEF EXAMINER: /// [[

[8 Larryg. Briggs, M#ior Operations Engineer Date APPROVED BY: C'-

J /wt /oJ//po FeiEfiilgrorh, C71efdd ion Date Operations Branch, Division of Reactor Safety SUMMARY: A written examination retake was administered to one reactor operator (RO) candidate.

The reactor operator candidate passed the written e.vamination and was issbed a Reactor Operator License on October 9, 1990.

l t I

! . , f . DETAILS TYPE OF EXAMINATIONS: Replacement 1.0 EXAMINATION RESULTS: One reactor operator candidate was administered a retake written exami-nation on October 3, 1990.

The candidate passed the examination and > was iss ad a license on October 9, 1990.

CHIEF EXAMINER: .

Larry E. Briggs, Senior Operations Engineer PROCTOR: Peter Habighorst, Millstone Unit 2, Resident Inspector ! LICENSEE PERSONNEL PRESENT AT THE EXIT MEETING: ' The exit meeting was conducted by Mr. Briggs, vic telephone conversation with Mr. Wilson, Supervisor, Operator Training for Unit 2, on October 9, , 1990, during which the results of the examination were discussed.

2.0 PRE-EXAMINATION REVIEW , " On October 1, 1990, prior to the administration of the Reactor Operator (RO) written examination, three (3) Millstone Point 2 training staf f members, all under security agreement, reviewed the examinations at the L NRC office in King of Prussia, Pennsylvania.

This review was performed ' te ensure that the exar.iination to be administered was content valid and ' performance based.

3.0 SUMMARY OF NRC ANO LICENSEE COMMENTS MADE AT THE EXIT MEETING: A.

The Chief Examiner informed the licensee that the candidate had passed the written examination.

B.

The Chief Examiner informed the licensee that the written explanation of reference material usage provided in a letter to the contractor had greatly simplified and enhanced the usability of the reference material in the preparation for the examination.

Attachment: Written Examination and Answer Key (RO) ,

gesimiis-is i i

= ATTACHMENT 1 ,

< __.._. - _ _ _ _ - - _ _ _. _ _ _ _ _ _ _ _ _ _. _ _. _ _.. _ _. _ _. _. _ _. _ _ _. _ _.. _ _ _... _ _ _ _ _ _ _ _ _ _. _ _ -. _ _ _ _ _ _ _ _ _. _ _. _ _ _ _ _ _ - _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -

' . ' MASTER . , U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION

FACILITY: Millstone 2 REACTOR TYPE: PWR-CE DATE ADMINISTERED: 90/10/03 CANDIDATE: - INSTRUCTIONS TO CANDIDATE: .. Points for each quet, tion are indicated in parentheses after the question.

To pacs this examination, you must achieve an overall grade of at least 80%. Examination papers will be picked up four and one half (4 1/2) hours after tha examination s+. arts,

- . ____ __ I , , I e , i e i NUMBER i TOTAL i CANDIDATE'S l CANDIDATE'S i ! QUESTIONS l POINTS l POINTS ! OVERALL ! l l l ! GRADE (%) l l......__......;_______... ...... ___. ___j ....__________l

! l l ! l

l 99.50 i I ! l' I ! ! l l__ l l-I All work done on this examination is my own.

I have neither given ! nor' received aid, t Candidate's Signature

1 ,

___ _ __ _ _ ' l ' . NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

2; After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination.

This must be done after you complete the examination.

' 3. 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.

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.

8.

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 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 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.

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.

l

'. 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. Pcrtial 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 w:rth 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 0.00 points.

If one of your five responses is incorrect. 0.20 will be d:d. toted and your total credit for that question will be 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 cxamination 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.

21. 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-ction 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 ' rcvoked.

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i . REACTOR OPERATOR Page

i QUESTION: 001 (1.00) According to ACP-QA-2.20, " Independent Verification" procedure, proper

v0rification of the position of a throttled valve which is NOT located in a ' high radiation area requires the valve to be manipulated: a.

open from the closed position to the throttle position while counting the number of turns required and repeated by the independent verifier.

b.

closed from the throttle position while counting the number of turns required and then reopened the correct number of turns and repeated by the independent verifier, c.

open from the closed position to the throttle position while counting the number of turns required and the independent verifier will verify proper position by observing a process parameter such as flow or pressure.

d.

closed from the throttle position while counting the number of turns required to fully close the valve and then reopening it to the required throttle position while the independent verifier abserves the operation.

.

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i QUESTION: 002 (1.50) i Listed below are three types of tags used in station tagging, and d scriptions of the tags.

MATCH the best description to each tag.

(A description may be used more than once as an answer.)

Column I Column II a.

Red Tag 1.

Tags of other colors OR the i _ same color may NOT be attached to the device with the tag, b.

Blue Tag 2.

Tags of other colors may NOT be attached to the device with the tag.

Additional tage of the same color MAY be attached.

____ c.

Yellow Tag 3.

Tags of other colors MAY be attached to the device with the tag.

Additional tags of the uame color may NOT be attached.

4.

Additional tags of any color MAY be attached to the device with the tag.

' QUESTION: 003 (1.00) - , l , Which of the following statements is correct concerning the Technical Specification minimum staffing requirements at Unit-27 ' a.

An STA'is required on-site in all modes.

b.

A Chemistry Technician is required on-shift in all modes.

I c.

An HP Technician is required on-shift in all modes.

d.

None of the above listed personnel are required on-site in all modes.

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QUESTION: 004 (1.00) A00 rding to SHP 4906, Posting Of Radiological Controlled Areas", all of " tho following areas are defined by being able to receive a respective dose in cny one hour period in excess of 0.5 mrem EXCEPT7 a.

Radiation Area i b.

Neutron Radiation Area c.

Contaminated Area d.

Noble Gas Exposure Area-QUESTION: 005 (1.00) 'Atoarding to ACP-QA-2.06B, " Station Bypass Jumper Control" procedure, which ONE of the following statements describes the requirement for placement of , " control tags" on electrical or mechanical jumpers? < Electrical jumpers require a control tag attached at each end of a.

, l the jumper while mechanical jumpers require a control tag attached ' at the source end of the jumper only.

l b.

Mechanical jumpers require a control tag attached at each end of the jumper while electrical jumpers require a control tag attached at the source end of the jumper only.

Both electrical and mechanical jumpers require a control tag c.

attached at each end of the jumper in all cases, d.

Only electrical and mechanical jumpers, of which both ends'are not visible from the same point when installed, require a control tag attached at each end of the jumper.

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. - , . REACTOR OPERATOR Page

QUESTION: 006 (1.00) LADO:rding to ACP 6.01, " Control Room Procedure", what is the MINIMUM IE3ident Classification made in accordance with EPIP 470.1, which would meet , th3 definition of an " Accident Situation"7 a.

Unusual Event b.

Alert c.

Site Emergency d.

General Emergency QUESTION: 007 (1.00) Acc:rding to ACP 6.01, " Control Room Procedure", which ONE of the following positions is responsible for controlling access to the " Control Room Op; rations Area"? a.

Shift Supervisor (SS) b.

Supervising Control Operator (SCO) c.

Secondary Plant Operator (SPO) d.

Primary Plant Operator (PPO) t

. . R$ ACTOR OPERATOR Page

QUESTION: 008 (1.00) -A;;crding to ACP 7.05, " Access Control" procedure, which ONE of the following " Identification Badge Types", if non pictured, would be allowed Cocorted access'only? a.

"E" b.

"NU" c.

"C" d.

"V" QUESTION: 009 (1.00) According to ACP 10.05, " Log Book Requirements (Control Room)", which ONE cf the following is responsible for maintaining the legal record of unit status and events? 6.

Shift Supervisor b.

Supervising Control Operator c.

Primary Plant Operator d.

Secondary Plant Operator

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. l R' ACTOR OPERATOR E Page

i QUESTION: 010 (1.00) According to ACP 6.12 " Shift Relief Procedure", all of the following are to be conducted prior to assuming the shift EXCEPT? a.

Discuss important items affecting plant operation, b.

Review pertinent information which has been generated during the last twenty - four hours, c.

Conduct a shift briefing.

d.

Walk - down appropriate control boards.

' QUESTION: 011 (1.00) According to ACP-QA-3,02, " Station Procedures And Forms", which ONE of the fellowing would be an example of a "Non-Intent Procedure Change"? a.

Changing the " Pressurizer Low Level" alarm setpoint.

- ' b.

Correcting the valve number for'the "HPSI-Pump A Suction Valve".

, c.

Adding a QC hold point to a " Maintenance Procedure", i d.

Updating the acceptance criteria for the "AFW Pump Surveillance Procedure".

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' ., RNACTOROPERATOR Page 10 QUESTION:~012. (1.00) According to ACP-QA-3,02E, " Procedural Compliance", which ONE of the following activities would NOT require the user to refer directly to a procedure? , a.- Repacking.the " Charging Pump A" seal, b.

Performing a post maintenance surveillance test on " Charging Pump ~A".

c.

Placing " Charging and Letdown" in service.

l-" d.. Adding lube oil to " Charging Pump A".

o u . l QUESTION::013 (1.00) . ,

i According-to OP.2217 " Secondary Chemistry Control", during a normal plant b 'ctartup from Cold Shutdown conditions to 100% power, which ONE of the >

Lfollowing evolutions would NOT have chemistry specifications which must be l mat prior to performing the evolution?

a.

RCS-heatup te 200 degrees F.

} 'b, Placing-the Condensate system on long recycle, ~ - j c.-l Initiating Main Feedwater flow to the St am Generators.

d,- Admitting steam-to the hain Turbine.

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. ~c.

- ,, LREACTOR OPERATOR Page 11 QUESTION:-014 (1.00) The Reactor Regulating System calculates T-ref as a function of: a.

reactor coolant system differential temperature.

b.- main turbine steam chest pressure, c.

main turbine first stage pressure.

d.- reactor power (from control channel nuclear instruments).

-_ UESTION: 015 (1.00) Q Which'ONE of the following conditions / signals will generate a CEA Motion lnhibit (CMI) signal? a.

Any CEA below the PDIL generated by the Metrascope, b.

'A CEA out of sequence by more than 5 steps generated by the Metrascope.

10. MISH generated by the Metrascope preventing any shutdown CEA

movement if regulating CEA's are above 13-steps.

.d.

MIRG--generated by the Metrascope preventing any regulating CEA movement-if the shutdown CEA's are less than 163 steps.

- ._ m.

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REACTOR OPERATOR Page 12 QUESTION: 016 (1.00) .While withdrawing a Shutdown Group, GROUP motion will: a.

stop due to the highest CEA in the group reaching its Upper Electrical Limit (UEL).

b, stop due to the lowest CEA in the group reaching its UEL.

be' stopped by the computer when the lowest CEA in the group c.

reaches its Upper CEA Stop (UCS).

d.

be: stopped by the computer when the highest CEA in the group reaches its UCS.

, QUESTION: 017.

(1.00).

'R0cetor Coo 1 ant Pump' seal bleedoff flow can discharme (flow) to all of the ~ ' following tanks EXCEPT: a.

Quench Tank .b.- Primary Drain Tank c.

-dquipment Drain Sump Tank d.

' Volume Control Tank QUESTION: 018 (1.00) ,. .If Reactor Coolant Pump (RCP) seal flow reaches 10 gpm, the bleedoff excess flow ~ check valve will close to prevent: i a.

exceeding bleedoff line temperature requirements, b.

blockage of bleedoff flow from other RCPs.

! c.

exceeding-design temperature of the volume control tank.

di-inventory loss of the reactor coolant system.

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_ _ _. _....... - .- i REACTOR OPERATOR Page 13 , . QUESTION: 019 (1.00) If the control switch for any charging pump is placed in the " pull to lock" position at the hot shutdown panel (C-21), then that pump: a.

cannot be manually started from control panel CO2.

b.

will. start and continue to run regardless of pressurizer level.

c.- can only be started manually and only from control panel CO2.

d.

will start only on a valid SIAS initiation signal.

QUESTION: 020 (1.00) During a major RCS-boron concentration change: the pressurizer must be maintained at a constant temperature while a.

.(at the same time) pressure is raised by increasing pressurizer level.

=b, the pressurizer backup heaters are-manually. energized, but pressure is kept constant by lowering the pressurizer pressure . controller setpoint.

the pressurizer b'ackup heaters are energized by lowering the c.

pressurizer pressure controller setpoint.

d ~. the pressurizer spray valves must be kept shut or the backup . heaters may energize, thus raising pressurizer temperature.

!

- _I ~ f RhACTOROPERATOR Page 14 QUESTION: 021 (1.00) Which ONE of the following Charging Pump trips is blocked by an SIAS signal? a.

Low suction pressure b.

Pressurizer low level c.

Undervoltage d.

Overcurrent , QUESTION: 022 (2.00) For each Volume Control Tank (VCT) automatic control function listed in Column A, indicate the appropriate VCT level from Column B at which the automatic function occurs. Each VCT level in Column B may be used ONLY < once.

Column A Column B (Function) (Level) } a.

RWST suction opens, VCT outlet closes 1.

90% - b. - Flow diverts to clean liquid rad waste 2.

88% c.

VCT outlet opens, RWST suction closes 3.

72%- d.

Auto make up starts 4.

-70% _ 5.

9% 6.

5%

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RNECTOROPERATOR Page 15 QUESTION: 023 (1.00)

While heating up the pressurizer to draw a bubble, Reactor Coolant System pressure is controlled by: a, letdown flow control valves in automatic, b.

. cycling the PORVs on Low Temperature Overpressure.

c.

initiation of Auxiliary Spray in manual, d.

adjusting the setpoint of the letdown backpressure regulating valves.

QUESTION:'024 (1.00)

The "2-of-4" logic for a Salety Injection Actuation Signal is actually processed in'the: a.

bistable drawers, b.

isolation amplifier-circuits.

c.

actuation modules.

.d.

logic matrix ladder circuits.

, I

, e REACTOR OPERATOR Page 16 QUESTION: 025 (1.00) Choose the ONE answer that best describes how technical specification curveillance OP 2601D, "NI And Delta T Channel Calibrations", affects RPS op: ration: a.

If the plant calorimetric is inaccurate, due to incorrect SG blowdown flow adjustments, performance of OP 2601D will correct any RPS power value mismatch with ACTUAL reactor power.. b.

Performance of OP 2601D ONLY affects the TM/LP trip on RPS.

Performance of OP 2601D can directly affect the accuracy of any c.

RPS trip using Q POWER.

d.

If the plant calorimetric is inaccurate, for any reason, performance of OP 2601D will generate a TM/LP trip on that L channel.

l-QUESTION: 026 (1.00) l All of the following will cause the Power ~ Trip Test Interlock (PTTI) to cotuate EXCEPT7 ' ! a.

"A&B/2" switch in the "B" position.

b.: RPSCIP calibrate switch out of " operate".

, c.

40mparator Averager channel select switches in the "off" position.

d.

" Calibrate-Operate-Zero" switch in the "Zero" positio _ - _ _ _ - _ - - ._ __ l . ., REACTOR OPERATOR Page 17 QUESTION: 027 (1.00) The NIS Comparator Averager provides an input to which ONE of the 'following? a.

Deviation-Alarm Comparator b.

TM/LP Setpoint Calculation c.

Axial Offset Calculation d.

Qdnb Calculation QUESTION: 028.(1.00) .If any of the test switches on a linear power range drawer are NOT in the " operate" position, the High Voltage bistable trips.

Tripping the High. Voltage bistable for that channel PREVENTS the : a.

Power ~ Trip Test Interlock (PTTI) from being generated, b.

Rod drop oistable from initiating a rod drop alarm.

• c.

High power trip signal from being generated.

d.

Comparator Averager from receiving power' output summer signals.

QUESTION: 029 (1.00) Which'ONE of the below listed components will assume the position indicated as the result of a Facility 11 Safety Injection Signal (SIAS)? a.. 2-RB-28.2B-(6" CAR cooler "B" outlet valve) will open, b.

2-HV-2 (CAR "B" outlet damper) will open.

c.

F-14D ("D" CAR unit) will start in fast or shift to fast speed.

d.

2-RB-28.3D (10" CAR cooler "D" outlet) will open.

,

.

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R'EACTOR OPERATOR Page 18 QUESTION: 030 (1.00) Which ONE of the following is a proper alignment for main feedwater configuration following a reactor trip? a.

Two main feed pumps running and at minimum speed control, b.

One condensate pump running, c.

Main feed regulating valve open 5%. d.

Main feed regulating valve bypass valve closed.

LQUESTION: 031 (1.00) During a plant startup,_the main feed pump turbines are initially driven by-mnin steam, but eventually end up being driven by " cross-over" steam.

LThio_ change in driving steam supply is accomplished by: ' remote valve manipulations accomplished at C0-5.

a.

b.

pressure-instruments actuating the automatic steam supply valves.' ' c.

the control valve arrangement and normal speed control mechanism.

d.- normal'" cross-over" steam valve operation.

I l l l ' -QUESTION: 032 (1.00)

7 Condensate Storage Tank (CST) MINIMUM capacity exists to maintain Hot Stendby' conditions for how-many hours? a.

b.

c.

d.

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. - _.. . . ' .. ) R$ ACTOR OPERATOR Page 19 QUESTION: 033- (1.00) According to ACP 6.03, " Radioactive-Liquid Waste Discharge Policy", if any Gf the 'following were to occur while performing a discharge which ONE would ALLOW fo:: continued discharge? a.

Steam Generator blowdown is placed in service, b.

Discharge radiation monitor flow monitor fails, c.

Two (2) ciro. water pumps trip.

. d.

Lev 91 increases in the tank being discharged.

H QUESTION: 0'l4 -(1.00) 1~ While operating.at 100% power bus "VA 10" deenergizes.

With respect to the Engineered Safeguards Actuation System (ESAS), choose the correct answer 'from below.

a.

EActuation~ Cabinet 5 is the only cabinet deenergized.

< b.

Actuation Cabinet 5 and Sensor Cabinet A are the only cabinets deenergized, o c.

Actuation Cabinet 5 and Sensor Cabinet C are the only cabinets deenergized, d.

No ESAS cabinets are deenergized.

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' . - RNkCTOROPERATOR Page 20 QUESTION: 035 (1.00)- What is the power _ supply to the No.1 Steam Generator Supply Valve to Auxiliary Feedwater Pump Turbine, 2-MS-2017 a.

-B51 ' b.

B52 c.

B61 d.

B62 , -QUESTION: 036 (1.00) Which ONE of the following conditions would be classified as Pressure Boundary. Leakage? a.

A steam generator tube leak, b.

Reactor head / vessel leakage past the inner "0" ring.

c.

Valve stem leakage on a pressurizer spray valve.

d.

A crack in a' charging line where it is welded to the RCS piping.

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' . . . ' REACTOR OPERATOR Page 21 ! i ! QUESTION: 037 (1.00) ! 'Given the following data: The plant is in a startup evolution - T-cold 543.2 degrees F - ' T-hot 576.4 degrees F - i Tavs 560 degrees F ! - l Pressuriser ! - temperature 652.0 degrees F l RCS/ pressurizer ! - pressure 2250 psia

Datermine the. MINIMUM RCS subcooling, i

a.. 108.8 degrees F i b.

92.0 degrees F l c.

-75.6. degrees F i-i d.

59.6 degrees F-i ! ! -! ! , ! i n .,

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_ _ _ _ _ _ _ _ _ _ _.. _... _ ' . REACTOR OPERATOR Page 22 QUESTION: 038 (1.00) Two separate channels, X and Y, are provided for pressurizer PRESSURE control.

Which ONE of the following statements descrites the interface between these-two channels? a.

All indication, controls, and alarms in the control room are associated with either X or Y channels and cannot be selected between these two channels.

b.

A handswitch is provided to determine which channel is used to accomplish various control functions.

c.

The two channels (X and Y) use a common D/P cell with two-transmitters connected to the one common D/P cell.

d.

The. signal from the lowest indicating of the two pressure channels

is auctioneered and compared to the pressure setpoint that is controlled by the operator.

I

.. . -REACTOR' OPERATOR Page 23 QUESTION:.039 (2.00) ' For each Pressurizer Level Control System (PLCS) function listed in Column-A, indicate the appropriate switch from Column B which is used to perform thnt function. Each switch in Column B may be used ONLY once.

Column A Column B (Function) (Switch) a.

Change from the "C" charging 1.

Letdown Limiter pump running to the "B" Bypass Switch charging pump running, and HIC-110

.. b.

Increase charging flow when 2.

Pressurizer Program increased-letdown is desired.

Level Bypass Switch c.

Tarottle letdown flow to 15 3.

Charging Pumps GPM when re-establishing Override Selector ' letdown flow.

Switch ' d.- Prevent'both backup charging 4.

Charging Pump pumps from. tripping while Selector Switch = flooding the pressurizer.

! .S.

Pressurizer Level Indicator Controller l QUESTION: 040 (1.00) H L iTha Reactor Regulating System calculates pressurizer level setpoint as a function-of which ONE of the following?- a.

Turbine first-stage pressure.

.b.

Reactor. Power'(from. control channel NI's).

c.

'RCS T-avg.

d.

RCS delta T . - - - - - - - -

__ _ _ _ _. _ _ _ _. '

R$ACTOROPERATOR Page 24 QUESTION: 041 (1.00) .If the bias thumbwheel on HIC-110 (letdown flow controller) is not adjusted 'after starting.a second charging pump, which ONE of the following will-occur? a.

Charging flow will be less than letdown flow and pressuriner level will decrease.

b.

Charging flow will be greater than letdown flow and pressurizer level will decrease.

c.

Charging flow will be less than letdown flow and pressurizer level will increase.

d.. Charging flow will be greater than letdown flow and pressurizer level will increase.

QUESTION: 042 (1.00) .During a_ transient, pressurizer level decreases to 4.2% below the LProgrammed pressurizer level. Assuming normal _cperation, what is the expected automatic response of the pressuriser level control system? '

a.

Both backup charging _ pumps will be running with minimum letdown flow, b.

Only the first backup-charging pump will be running with minimum letdown flow.

c.. Only the first backup charging pump will be running with letdown flow-reduced but still greater than minimum.- d.

No backup charging pumps will be running but letdown flow will be minimum, . . ...

- _._.

- e.

. REACTOR OPERATOR Page 25 + -QUESTION: 043 (1.00) . Which ONE of-the following is the basis for the Local Power Density (LPD) . trip?- a.

Prevent exceeding 15.6 kw/ft linear heat rate.

b.

Prevent fuel centerline melt, c.

Prevent exceeding a clad surface temperature of 2200 degrees F.

d.

Prevent exceeding a minimum DNBR of 1.17.

' QUESTION: 044 (1.00) .Tricodium phosphate (TSP) is placed in the containment sump to ensure that', during a LOCA: a.

.the reactor remains ~ shut down when in sump recirculation.

b.

iodine removal is accomplished more effectively by the Containment Spray System.

.c.

corrosion damage to metal compcnents is minimized.

d '. boron precipitation.in the containment sump is minimized.

QUESTION: 0451 (1.00) ' Following a LOCA, which ONE of the following'is a-criteria in the E0P's for .cscuring the Containment Spray System? a.

Equipment will be affected by continued operation.

> b.

Containment pressure is less than 10 psig.

c.- The CSLpump is not operating on Containment Sump Recire.

d.

The hydrogen concentration monitor is required to be placed in operatio. . ,- REACTOR OPERATOR Page 26 , QUESTION: 046 (1.00) Which ONE of the following statements is a design feature for storage of fuol assemblies in the Spent Fuel Pool? a.

Both, new fuel assemblies and spent fuel assemblies can be stored in Region II racks due to the spacing arrangement.

b.

Both, new fuel-assemblies and spent fuel assemblies can be stored in Region I racks due to poison plates in these racks.

c.

Any fuel assembly can be stored in any SFP rack location due to boron requirements now being maintained in the SFP.

- ~d.

Only completely spent fuel assemblies (spent through 3 complete fuel cycles) can be stored in the Region II racks of the SFP.

' i ' QUESTION: 047 (1.00) i All.of-the following are DIRECT (hard piped) sources of makeup to the Spent ' .Fusl Pool EXCEPT? a.

Primary Makeup Water ' b.

RWST ! c.- BAST /RBAST d.

huxiliary.Feedwater

, .- ..

'

RSACTOR OPERATOR Page 27 . QUESTION: 048 (1.00) Which ONE of the following describes the design feature that prevents or citigates an inadvertent draining of the Spent Fuel Pool Cooling System (SFPC)? a.

All piping systems, including pumps and valves, are located at-or above the normal operating level, b.

The SFPC suction piping is provided with an anti-syphon device, c.

The SFPC return piping is provided with an anti-syphon device, d.

The SFPC primary makeup valve (2-RW-167) automatically opens on a SFP low level alarm.

QUESTION:.049 (1.00) Which'ONE of the-following is the primary purpose of scavenging steam flow in'the Moisture Separator Reheaters (MSR's)? , a.

Prevent accumulation of--condensate and non-condensables in the tubes.

- b, Provide for warmup of the tubes.

c.

Provide overpressure /overtemperature protection for the tubes.

d.

Control the rate of change of first and second stage reheat temperatures.

..,. ...

- _ - _ _ - _ _ _ _ _ _ _ _

.

R$ ACTOR OPERATOR Page 28-QUESTION: 050 (1.00) 'All of the following statements concerning the Halon Fire Suppression System for the DC Switchgear Room are correct EXCEPT: a.

Fire / smoke dampers between the Battery rooms and DC Switchgear rooms are shut by Electrical Thermal Links upon receipt of a Halon predischarge signal, b.

Ventilation fans (54A and 54B) continue to run upon receipt of a smoke detector alarm and during the Halon discharge.

c.

Smoke dampers between the Auxiliary Building Cable V3 ult and each of the DC Switchgear rooms are shut by Electric Thermai Links upon receipt of a Halon discharge signal.

d.

When Halon is actuated manually at a pull station, the Halon discharge immediately takes place and the warning lights and horns will go to a steady-on condition.

' QUESTION: 051 (1.00)- All of the following are Emergency Core Cooling System (ECCS) Acceptance-Criteria EXCEPT? Limit peak cladding temperature to less than 2200 degrees F.

a.

b.

Limit maximum oladding oxidation to less than 17% of total cladding thickness.

Limit containment pressure to less than 54 psig, c.

d.

Limit maximum hydrogen generation to less than 1% of the amount generated if all the Zirconium reacted.

t . .

- ) . - REACTOR OPERATOR Page 29 . QUESTION: 052 (1.00) Following a Loss Of Coolant Accident (LOCA), RCS pressure is at 350 psia cnd dropping.-- 'Which ONE of the following statements describes what should be the " normal" status of Emergency Core Cooling flow at this point in time? a.

Oc.tstant HPSI. flow exists with no LPSI flow, b.

Increasing HPSi flow exists with no LPSI flow.

c.

Constant-HPSI and LPSI flow exists, d.

Increasing HPSI and LPSI flow exists.

QUESTION: 053 (1.00) Concerning.the 125 volt DC system ground detector, which ONE of the following statements describes how a ground is indicated? a.

.High voltage reading indicates a ground.

b.

Low voltage reading indicates a ground.

' c, .High current-reading indicates a ground.

d; Low current reading indicates a ground.

r t - -

. s.

i RNhCTOROPERATOR Page 30 QUESTION: 054 (1.00) -Which ONE of the following AC busses is designed to relieve an Emergency Diesel Generator in an accident condition when normal power is not cvailable? a.

24 D b.

24 E c.

14 H .d.

14 G

QUESTION: = 055 (1.00)

'Which ONE of the following components is NOT served by RBCCW7 a.

Primary Sample Coolers b.

Blowdown Quench. Tank Coolers c.

Secondary Sample Coolers d.

Engineered Safety Feature Room Coolers-l QUESTION: 056 (1.00) Which ONE of the following % Hydrogen concentratione is-considered EXPLOSIVE 7 a.

b.

c.

d.

' . R$EACTOROPERATOR Page 31 QUESTION: 057 (1.00)

Concerning the refueling machine hook weighing system, the load interlocks:

a.- when bypassed, are indicated by a yellow light.

b.

must be bypassed if the hoist is empty, c.

are independent of hoist height.

d.

function only in the out direction.

, - 1 QUESTION: 058-( 1. 00 ) LAll of the following are interlocks on the Refueling Machine EXCEPT? a.- Hoist operation up or down is prevented when the transverse drive is being operated.

b. 'All Hoist motion is stopped automatically if mast bumper is ' actuated.

c.

Hoist down motion is automatically stopped by a slack cable - switch, regardless of hoist position.

d.- Holst up motion is automatically-stopped when in the upper grapple operate zone and the grapple is not closed, w , -

---

-- m

- - - _ -, - - - -

- . . . . REACTOR OPERATOR Page 32 QUESTION: 059 (1.00) With the' turbine on line, which ONE o# the following Steam Dump / Turbine Bypass Control System valves will automatically respond to secondary-prOssure? a.

A b.

B c.

O d.

D fQUESTION: 060 (1.00) During a turbino startup, what valve operation occurs when the turbine is rocot? i -- a.. Stop valves open.

, b.

Intermediate stop valves open, c.

l'& 2 control valves.open.

L d.

Intercept valves-open.

1 I a

_.

. l a- =. \\ ' REACTOR' OPERATOR Page 33 QUESTION: 061 (1.00) Givsn the following conditions: The turbine control system is operating with the LOAD LIMIT - LIMITING light illuminated.

Reactor power is 95%. - The plant is stable.

- Whi3h ONE of'the following statements is describes the expected automatic rssponse.of the turbine control system? a.

If turbine control speed decreased (to 1780 rpm), the control valves would open, trying to return the speed error to zero, b.

If turbine speed increased (to 1890 rpm), the control valves would close,-trying to return the speed. error to zero, c.

The load limit circuit will cause the control valves to close until the load limit light extinguishes, d.

The load limit circuit will prevent any signal from moving the control valves.

. TQUESTION: 062 (1.00) !

j, Which ONE:of the following is the reason the Instrument. Air and LP Nitrogen L ayatems should not be cross-connected? 'a.

The Nitrogen is at.a-higher system pressure and would be' depleted at a faster than desirable use rate, b.

The Air is at a higher system pressure and the inerting capability of a nitrogen blanket could be defeated.. , 'c.

The Nitrogen is at a higher system pressure and would prevent the .us'e of the air system for breathing air.

d.

The Air is at a higher system pressure and could cause oil contamination of the Nitrogen system.

_ _. .

_ _ _ _ -.. - - - -..... .. " - " " - ..... . - . REACTOR OPERATOR Page 34 QUESTION: 003 (1.00) Following a reactor trip, three (3) CEAs did NOT fully insert.

According to EOP 2525 " Standard Post Trip Actions", how long is the PPO required to borate if two (2) charging pumps are used? a.

1.5 hours b.

3 hours c.

4.5 hours d.

6 hours-QUESTION: 064 (1.00) Given the following conditions: Containment Pressure 15 psig - Containment 1 Temperature .- -- (plant-computer) 215 degrees-F RCS T-hot - (unaffected-loop) 440 degrees F - RCS T-cold (unaffected loop) 430 degrees =F Using E0P 2536 " Excess Steam Demand", Figure 4.2, "RCS Pressure - Temperature Limits" (PROVIDED), determine the MINIMUM acceptable RCS pressure, a.

540 psia b.

.522 psia c.

515 paia d.

490 psia

_ _ .. . .. ' REACTOR OPERATOR Page 35 QUESTION: 065 (1.00) -During an Excess Steam Demand event, both steam generators are suspected of baing affected.

Which steam generator should be isolated?

a.

Both steam generators, since a potential existe to over-pressurize the containment.

b.. Only one steam generator, that which has the lowest Tc.

, c.

-Either steam generator, since it will aid in identification of the ' effected S/G.

d.

Only one steam generator, that which has the highest pressure.

, QUESTION: 066 (1.00) .EOP 2536, " Excess Steam Demand" requires specific operator actions / controls to be taken if the RCS has experienced an nncontrolled cooldown due to a potsntial for Pressurized Thermal Shock (PTS) of the reactor vessel.

-Tha MINIMUM RCS cooldown that will require imp.'.ementation of these cdditional controls is a cooldown from' normal operating temperature to a i temperature of...? a.

500-degrees-F b.

.450 degrees-F c.

400 degrees-F D d.

350 degrees-F , 15-

- '.: , REACTOR OPERATOR Page 36-QUESTION: 067- (1.00) A precaution in OP 2345B, "120 Volt Vital Instrument AC System" states that oortain operator action (s) must be performed when re-energizing VIAC-1 to prcvent actuation of ESAS equipment.

Which ONE of the following actions will prevent inadvertent ESAS actuation? a.

Reset all bistable trip lamps, b.

Remove the 24 VDC SIAS and block fuses, c.

Depress the actuation cabinet Actuation Reset pushbuttons, d.

Remove the +1S VDC fuses at the actuation cabinet.

, QUESTION: 068- (1.00)' Following a reactor trip, Pressuriser pressure is observed to be 1500 psia tnd deureasing. EOP 2525 " Standard Post Trip Actions", is implemented and all automatic actions are verified.

When verifying " normal" Containment conditions, all of the following would' ba VALID indications EXCEPT: a.

Containment pressure on C01.

b, Containment temperature on computer point CVCONTEMP.

c.

Containment Sump level on C06.

d.

Containment Radiation Monitor readings on RC1 ~ i l

...; . l: -REACTOR OPERATOR Page 37 ! QUESTION': 069~ (1.00) j ! i Which statement best describes the method by which mixing of the atmosphere intthe. containment dome region is achieved following a Loss of Coolant , . Accident (LOCA)? a_ Auxiliary circulation fans are automatically shifted to slow speed l . - on SIAS.

! ., b.'- P.I.R. fans-are automatically started en SIAS.

-c.

Auxiliary circulation fans =are manually started in slow speed after containment pressure is less than 10 psig.

. ad. - P.I.R.1 fans are manually placed in operation within the first few , hours-following-the incident.

! y.

! V la ~l QUESTION: 070- (1.00)

-Th2LEOPs provide-a Caution which states that pressurizer level alone may - 'i

notiprovide an~ accurate indication of total RCS inventory due to voids.

EAllfof'the following~are indications-which can be used to determine that ' >tho core'isLcovered"EXCEPT: , ! 'a.. Pressurizer leve1Lin conjunction with indications of~a subcooled j - RCS.

.; - b.1-RVLMS greater than O.

cb -Subcooled hot leg RTDs.

Ed.. Subcooled CETs.

I ,y

% r ! f -' >

.x ,' . . . REACTOR OPERATOR Page 38 QUESTION: 071 (1,00) While operating at 100% power the following data for Reactor Coolant Pump '(RCP) 'B' was obtained in response to alarms on 00-2/3: TIME: 0000 0100 > VAPOR SEAL 60 psig 55 psig ' UPPER SEAL 752 psig 215 psig HIDDLE SEAL 1480 psig 1220 psig Basod on this data, which of the following statements would be the Oppropriate diagnosis? + . a.

RCP-A lower seal is degraded.

b.

RCP-A middle seal is degraded, c.

RCP-A upper seal is degraded.

d.

RCP-A vapor seal is degraded.

.QUERTION: 072 (1.00) ' L According to AOP 2558, " Emergency Boration", what is the " MINIMUM" flow rate required for Emer ency Boration? o a, 25 apm b, 30 gpm , . o, 35 spm , " d.

40 spm ! ,

.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _. . l l REACTOR OPERATOR Page 39 QUESTIOJ: 073 (1.00) 'According to EOP 2540B, " Functional Recovery Of Vital Auxiliaries (AC And DC Power)", which ONE of the following Unit 2 systems can be supported by Unit 1 but with imposed limitations on the source? a.

Instrument Air ' b.' AC Electrical Power c.

Condenser Air Removal . d.

Service Water . -QUESTION: _074 (1.00) According to EOP 2040B, " Functional Recovery Of Vitel Auxiliaries (AC And DC Power)", if an Emergency Diesel Generator (EDG) started but it's ' r0spective vital bus did not energize, then the EDG is emergency tripped.

'Which ONE of the followjrc is the reason for tripping the EDG in this case? a.

Conserve fuel oli incase offsite power is not restored.

' b.

Allow Electrical to perform maintenance on the output breaker, c.

Prevent overl. eating due to no cooling water flow.

d.

Minimize potential for exhaust fire doe to running unloaded.

_ , ' i ' e i -

.. REACTOR OPERATOR Page 40 i QUESTION: 075 (1.00) ACO rding to AOP 2574, " Loss Of Condenser Vacuum", which ONE of the following parameters is affected by low condenser vacuum to the point that it Cay result in the turbine being tripped? , L a.

Turbine exhaust hood temperature . b.

Turbine vibration i c.

Moisture separator level d.

Turbine expansion '

QUESTION: 076 (1.00)

Which ONE of the'following Hot Shutdown Panel (C-21) indications is rcquired by Technical Specificationo? . ' , a.

Auxiliary Feedwater Flow b.

RCS Hot Leg Temperature i - o.

Reactor Power .d.

Condensate Storage Tank Level , . > c h I i l'

' , ! ' l

.

.__.

,,. . ' REACTOR OPERATOR Page 41

J QUESTION: 077 (1.00) AOP 2570A and AOP 2579AA are both " Contingency Fire Procedures" for " Appendix R Fire Area F-1".

What is the difference between the two procedures? a.- AOP 2579A deals with shutting down and cooling down the plant while AOP 2579AA deals with the equipment damaged by the fire.

b.

AOP 2579A deals with getting che plant to Hot Standby while AOP 2579AA deals with getting the plant to Cold Shutdown.

c.

AOP 2579A deals with the actions performed at the Hot Shutdown Panel (C-21) while AOP 2579AA deals with the actions performed locally in the plant.

d.

AOP 2570A deals with placing the plant in a stable condition while AOP 2579AA deals with the Emergency Plan requirements.

t QUESTION: 0781 (1.00) - While performing EOP 2525 " Standard Post Trip Actions", it is discovered * that bus.25A did.not transfer to the'RSST.

', Wh:it action (s) should the Secondary Plant Operator take? I' a.. Immediately go to'EOP 2528. " Electrical Emergency Procedure".

b.

Complete the Standard Post Trip Actions, then go to EOP 2528, " Electrical Emergency Procedure".

' c.

Inform the SS/SCO of the situation and complete the Standard-Post Trip Actions.

. .d.

Complete the Standard Post Trip Actions and go to the AOP 2553, ~ " Natural Circulation Cooldown Procedure".

L ) l' -,. ....

! ' l . . . REACTOR OPERATOR Page 42 ' QUESTION: 079 (1.00) Tripping the RCP's is a standard response to an event which causes the RCS t"; depressurise.

. Th3 need to trip the RCP's is based on provic?ng core protection during which of the following accidents? a.

Steam Generator Tube Rupture (SGTR) - b.

Main Steam Line Break (MSLB) , c.

Loss Of Coolant Accident (LOCA) d.

Anticipated Transie..t Without Scram (ATWS) ' , -QUESTION: 080 (1.00) AOP 2572, " Loss Of Shutdown Cooling" directs action to be taken IMMEDIATELY to catablish Containment Closure based on which ONE of the following RCS par meters? a.

Pressure , b' Temperature- . ' c.

Heatup rate d.

Level l l l t L

l l l l

. , e . REACTOR OPERATOR Page 43 ' ', . i QUESTION: 081 (1.00) AOP 2569, " Steam Generator Tube Leak" procedure states that SG blowdown ch;uld be re established as quickly as possible, if the magnitude of the tub 3 leak permits (and with management concurrence).

Which ONE of the following is the reason for re-establishing blowdown "as quickly as possible"? a.

To allow a flow path for obtaining SG samples.

l

b.

To minimize concentration of activity in the SG(s), c.

To prevent the SG from overfilling.

k-d.

To minimize any unmonitored releases.

QUESTION: 082 (1.00) i .i

Which'ONE of'the following primary to secondary leak rates is the Technical Specification limit per steam generator, according to AOP 2509, " Steam G:n rator, Tube Leak" procedure? ' a.

0.10 GPM b.

0.15 GPM c.

0.50 GPM - , d.

0.75 GPM l< ' i .. . P

- . RkACTOROPERATOR Page 44 QUESTION: 083 (1.00) It is NOT advisable to isolate the atmospheric dump valve (using the manual ioolation valve) on the faulted SG during a SGTR event because: a.

the atmospheric dump will be needed for decay heat removal, b.

it is preferable to open the atmospheric dump (from the Control Room) than to permit the SG safeties to lift.

c.

the operator making the lineup would receive a high radiation exposure, d.. the atmospheric dump will be required for cooldown of the faulted SG.

QUESTION: 084 (1.00) According to E0P 2534 " Steam Generator Tube Rupture", if a tube rupture occurs in BOTH Steam Generators, which ONE of the following parameters would be used to determine the Steam Generator to be isolated? .- a.- Main Steam Line Radiation Monitor readings.

b.

Steam Generator boron concentrations, c.

Steam Generator levels, d.

Feedwater flow rates.

., i , . . .

. .. . REACTOR OPERATOR Page 45 QUESTION: 085 (1.00) Ac00rding to EOP 2540D, " Functional Recovery of Heat Removal", which ONE of .tho fol'.owing success paths would NOT be an optimum method for RCS heat , removal? . a.

Condensate Pumps b.

Shutdown Cooling c.

Once Through Cooling d.- Breakflow QUESTION: 086 (1.00) t r 'A0cerding to EOP 2540B, " Functional Recovery Of Vital Auxiliaries (AC And DC Power)".. if DC power cannot be restored to at least one DC bus, then imm:diate actions must be started on which ONE of the following safety functions? a.

Reactivity Control . b.

.RCS Inventory and Pressure Control c.

Heat Removal d.. Containment: Integrity 1.

l l

- , _ n ,.,. - -.-

- i { REACTOR OPERATOR Page 46 i QUESTION: 087 (1.00) A00crding to AOP 2556, " Dropped CEA Recovery", if one (1) CEA dropped into tha core, which ONE of the following conditions would require the reactor i to be tripped? j a.

Pressurizer level decreases to <20%. b.

The dropped CEA is determined to be inoperable, c.

Reactor power decreases by 15%. d.

Pressurizer pressure decreases to 2225 psia.

t QUESTION: 088 (1.00) 'Which ONE of~the following trends for a Loss Of Coolant Accident (LOCA) .s: curring on the Hot Leg would be different if the break were on top of the 'Prassurizer? a.

Tave constant.

b.

~Pressuriser pressure decreasing.

' c.

Pressuriner level decreasing.

d.

Containment pressure increasing.

-

i . ' i . REACTOR OPERATOR Page 47 l QUESTION: 089 (1.00) . F011owine, a Continuous Rod Withdrawal event from 100% power, the operator calcots "Off" on the CEA Control Console.

Assuming "NO" other operator cetion is taken and "NO" reactor trip occurs, which ONE of the following parcmeters will return to essentially the same value that it was before the Cv0nt?

a.

Tave , b.

Pressuriser level c.

Reactor power d.- Steam Generator pressure QUESTION: 090 (1.00) Which ONE of the following post trip indications would determine that a L:2s Of Coolant Accident was occurring instead of an Excess Steam Demand ' Ev:nt? , a.

RCS subcooling lowering

b.

RCS pressure dropping c.

Pressurizer level dropping d.

Containment pressure rising l'

.

. . . REACTOR OPERATOR Page 48 QUESTION: 091 (1.00) Which ONE of the following indicators could be used to determine that a 1cck in the Charging Line is outside containment? Regenerative Heat Exchanger Outlet Temperature (TI-221) a.

b.

Letdown Heat Exchanger Outlet Temperature (TI-224) ' o.

Charging Header Pressure (PI-232) d.. Charging Line Temperature (TI-229) QUESTION: 092 (1.00) Which ONE of.the following parameters would be the most likely cause o. en " AIR BOUND" LPSI pump while running for Shutdown Cooling? a.

Throttled flow, b.

Rising suction temperature, c.

Lowering suction level.

' d.

Lowering suction pressure.

' QUESTION: 093 (1.00) According to AOP 2572,. " Loss Of Shutdown Cooling", during a loss'of ichutdown cooling flow, which ONE of the following temperature indications chould-be used to determine heatup or cooldown rates? 'a.

Unheated Junction Thermocouples b.

RCS Tave-c.

Shutdown Cooling Temperature d.

RCS Teold

c .. i . ' REACTOR OPERATOR Page 49-QUECTION: 094 (1.00) According to Technical Specifications, a loss of which ONE of the following Nualear Instrumentation Systems would have a required action if the plant w;s in Mode 57 , l a.

Incore b.

Safety Channel Narrow Range ' c.

Wide Range d.

Reactor Regulating Channel Narrow Range < I' QUESTION: 095 (1.00) During Refueling, the Reactor Cavity Seal fails causing both the Reactor , 02vity and Spent Fuel Fool level to decrease.

, , LA0 cording to AOP 2578, " Loss Of Refuel Pool And Spent Fuel Pool Level", which ONE of the following sources of water would be the LAST resort for rock up to the Spent Fuel Pool? . . , a.

The CST.

, b.

The Fire Water System.

c.

The'PMW System.

d.

The AFW System.

~ ?'. > l . .. ...

. _.. r . s' -REACTOR OPERATOR Page 50 " QUESTION: 096 (1.00) Following restoration of Electrtical Power in accordance with EOP 2628, "Elcetrical. Emergency" procedure, it is desired to restart an RCP.

Which ONE of the following criteria / conditions would satisfy RCE restart requirements? a.

PZR level greater than 20%. b.

Subcooling pressure / temperature limits of figure 4.2 (RCS pressure / temperature curve) for Toold are satisfied, c.

Neither steam generator is removing heat.

d.

RCP oil lift pumps operating for 3 minutes.

QUESTION: 097 (1.00) Which ONE of the following conditions would cause indicated Pressurizer Icyc1 to-be " LOWER" than ACTUAL level? a.

A Pressurizer temperature less than the temperature for which the' level transmitter was calibrated.

t b.

A leak in the variable leg of the transmitter.

L 'c.

A leak in the reference leg of the transmitter, d.

A ruptured diaphragm on the transmitter.

l l 1 \\ (********** END OF EXAMINATION **********) _ ._.

_ ._ .

- . i . t . a REACTOR OPERATOR Page 51 ANSWER: 001 (1.00) ' d.

REFERENCE: Millstone 2 Exam dated 4-23-90, Question 90.

.ACP-QA-2.20 Sections 6.1.8 & 6.3.3 No Facility Objective Found [3.6/3.7) 194001K101 ..(KA's) ' ANSWER: 002 (1.50) c.

[0.5) b.

1.

[0.5) o.

2- .[0,5) REFERENCE: ACP-2.06A/6.1.17 ACP-2.06A/6.1.18 l' ^ACP-2.06A/6.1.19 ' (3.7) [4.1) . ! - 194001K102 ..(KA's) , ANSWER: 003 (1.00) l c.

REFERENCE: Technical Specification 6.2.2 [2.5) [3.4) 194000A103 ..(KA's) ,

... . . REACTOR OPL.RATOR Page 52 ANStIER: 004 (1.00) c.

REFERENCE: SHP 4906, Definitions OJT Guide M2-OP-LOIOJT-ADMIN-SHP, Knowledge Requirement C.1.

[2.8/3.4) 194001K103 ..(KA's) A'ASWER: 005 (1.00)

d.

REFERENCE: 'ACP-QA-2.06B, Step 6.6.2.

< OJT Guide.M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement F.6.

.[3.6/3.7) 194001K107 ..(KA'a) . . l ANSWER:. 006 (1.00) b.. l. REFERENCE: ACP 6.C1, Definitions - LOJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement G.I.

[3.1/4.4) , 194001A116 ..(KA's) J ANSWER:- 007 (1.00) b.

. _ _ _ _.... _...... _ _........................... _. _.. _. _...... _. _.... _ _.. _. _.. _ _ _ _ _ _ _ =

. - _ _ _ _ _ _ _ _ _ _ _ _ - _ _. ._ _ - . REkCTOROPERATOR Page 53 REFERENCE: ACP 6.01, 6.3.2.1.

OJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement G.B.

[3.1/3.4) 194001K105 ..(KA's) ANSWER: 008 (1.00) d '. REFERENCE: ACP 7.05, Step 6.3.1.

OJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement I.3 (3.1/3.4) 194001K105 ..(KA's) 1 ANSWER:: 000 (1.00) o.

REFERENCE: ACP 10.05, Definitions and Responsibilities OJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement K 1.

[3.4/3.4] 194001A106 ..(KA's) l ANSWER: 010- (1.00).

.o.

REFERENCE: ACP 6.12 Steps 6.3, 6.4, 6.6, 6.8 OJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement M.3.

[2.5/3.4) 194001A103 ..(KA's)

. ' REACTOR OPERATOR Page 54 . ANSWER: 011 (1.00) b.

REFERENCE: , .ACP-QA-3.02, Definitions OJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement P.2.

[3.3/3.4) 194001A101 ..(KA's) ' ANSWER: 012 (1.00) d, REFERENCE: . ACP-QA-3.02E, Steps 6.1.1, 6.1.2 .Ny Fccility. Objective Found [4.1/3.9) 194001A102 ..(KA's) . . ANSWER: 013 (1.00) b.

!' REFERENCE: l OP 2217, Step 4.10.1 L TPG 2217/5.0, EO 1 [2.5/2.9) 194001A114 ..(KA's) ANSWER: 014 (1.00) C.. .-. - _ .

.__ .* , .. REACTOR OPERATOR Page 65

REFERENCE: FC3111ty Exam Bank section 2386, item 000530.

[3.1/3.4) 001000A102 ..(KA's) ANSWER: 015 (1.00) , c.

REFERENCE.

Millstone 2 Exam dated 4-23-90, Question 40.

CEDS SD, pp 28-30.

E06 (3.7/3.8) 001000K407 ..(KA's) ANSWER: 016 (1.00) o.

. REFERENCE: Fccility Exam Bank section 2302A, item 000911.

. [3.7/3.8) 001000K407 ..(KA's) ANSWER: 017 (1.00) ! Q.

l REFERENCE: " Fccility Exam Bank section 2301, item 000361.

. [3.3/3.6) ! 003000K103 ..(KA's) l -

_ _.. _ -. ... - _.... _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - . I R$ACTOROPERATOR Page 56

ANSWER: 018 (1.00) __ b.

REFERENCE: [ Facility Exam Bank section 2301, item 000587.

' (2.8/3.1) 003000K404 ..(KA'a) ANSWER: 019 (1.00) L a.

_ _ REFERENCE: Facility Exam Bank section 2304, item 000163.

[3.6/3.4) 004000G009 ..(KA's) l_ ANSWER:. 020 (1.00) .b..

. REFERENCE: - ' Facility Exam Bank'section 2304A item 000946.

[3.6/3.5) - 004000G013 ..(KA's) - ANSWER: 021 (1.00) a.

_.

_. _ _ _ _ _.. _ _ _ _ _ _ _ _ _ _ _. _ _. _ _ _ _ _. _ _ _ _. _. _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _m

. . . RNACTOROPERATOR Page 57 REFERENCE: CVCS SD, pp 13-14.

EO 6 (4.1/4.3) 004010A205 ..(KA's) ANSWER: 022 (2.00) (0.5 each) c.

6.

b.

2.

c.

5.

d.

3.

REFERENCE: Fooility Exam Bank section 2304, item 000940.

[3.2/3.0) 004020A305 ..(KA's) . ANSWER: 023 (1.00) d.

- REFERENCE: Focility Exam Bank section 2304, item 000948.

[3.8/4.1) 004020K602 ..(KA's) ANSWER: 024 (1.00) .o.

REFERENCE: Facility Exam Bank section 2384, item 000978.

[3.7/3'.9) 013000A301 ..(KA's) .,

. . REACTOR OPERATOR Page 58 AN3WER: 025 (1.00) c.

' REFERENCE: Focility Exam Bank section 2380-1, item 001466.

[4.1/4.2) 015000K101 ..(KA's) ANSWER: 026 (1.00) C.

REFERENCEL 'Fccility Exam Bank section 2380-2, item 000128.

[4.3/4.5) 015000K405 ..(KA's) . ANSWER: 027 (1.00) C.

REFERENCE: Focility Exam Bank section 2380-2, item 000432 [3.3/3.5) 015000A304 ..(KA's) ANSWER: 028 (1.00) b.

.

i ) ' ,, REACTOR OPERATOR Page 59 REFERENCE: Millstone 2 Exam dated 4-23-90, Question 10.

NI SD, p 21.

EO 7c.5 [3.9/4.3] 015000K301 ..(KA's) ANSWER: 029 (1.00) i d.

l REFERENCE: P&ID 25207-26028 SH 1 P&ID 25207-20022 SH $ OP-2313A/7.3 [4.1) [4.3) 022000A301 ..(KA's) i ANSWER: 030 (1.00) b.

. REFERENCE: . Facility Exam Bank section 2321, item 000018.

(2.8/3.0) C59000K418 ..(KA's) l ANSWER: 031 (1.00)

l 0. - ! REFERENCE: i Facility Exam Bank section 2321, item 000431.

[2.5/2.6) -059000A107 ..(KA's) .- ++1

_ _ _ _ _ ............ _. -,, ,, RhACTOROPERATOR Page 60 ANSWER: 032 (1.00) d.

REFERENCE: AFW SD, pp 2.3.

EO 2g [3.9/4.2) 061000K401 ..(KA's) ANSWER: 033 (1.00) .a.

REFERENCE: ACP 6.03, Steps 6.2.4, 6.2.5 OJT Guide M2-OP-LOIOJT-ADMIN-ACP, Knowledge Requirement T.2.

[3.2/3.1) 068000A402 ..(KA's) . ANSWER: 034 (1.00) b.

REFERENCE: P&ID 25203-30024 OP-2384/7.1.3 [3' 6) [4.2) . 013000A204 ,,(KA's) ANSWER:. 035 (1.00) b.

-_

!

. . REACTOR OPERATOR Page 61

, REFERENCE: LP M2-OP-RO-ELEC-2342, p 20 LP M2-OP-RO-SEC-2322, p 14 LP M2-OP-RO-SEC-2322, EO Ba [3.2/3.3) i C61000K201 ..(KA's) P ANSWER: 036 (1.00) d.

REFERENCE:

Fas111ty Exam Bank section 2301, item 000034.

[3.0/4.1) 002000G005 ..(KA's) , ' . ANSWER: 037 (1.00) 3.

F . REFERENCE: Facility Exam Bank section 2301, item 001532.

[3.9/4.1) < 002000A104 ..(KA's) , ' ANSWER: 038 (1.00) b.

REFERENCE: l Fccility Exam Bank'section 2304A, item 000074.

[3.2/3.6) 010000K603 ..(KA's) l ! .

- .. - RNACTOROPERATOR Page 62 ANSWER: 039 (2.00) o.

4.

b.

3.

c.

1.

-d.

2.

-REFERENCE: Facility Exam Bank section 2304A, item 000521.

[3.6/3.9) 011000K101 ..(KA's) ANSWER: 040 (1.00) c.

REFERENCE: Facility Exam Bank section 2304A, item 000523.

[3.4/3.5) 011000K105 ..(KA's)

ANSWER: 041 (1.00) d.

-REFERENCE: Focility Exam Bank section 2304A, item 000941.

[3.3/3.5) .011000A102 ..(KA's) ANSWER: 042 (1.00) a.

- .. REhCTOROPERATOR Page 63 REFERENCE: Focility Exam Bank section 2304A, item 000949.

[3.3/3.4) 011000K402 ..(KA's) ANSUER: 043 (1.00)- b.

REFERENCE: Fecility Exam Bank section 2380-1, item 000537 [3.1/3.3) 012000K502 ..(KA's) ANSWER: 044 (1.00) C.

REFERENCE: . .Focility Exam Bank section 2306, item 000059.

[3.1/3.6) - 026000K402 ..(KA's) ANSWER: 045 (1 00) b.

' REFERENCE: Focility Exam Bank section 2306, item 00045 [3.2/3.7) 026020A203 ..(KA's)

- -,. - - -, - - . . _ . REACTOR OPERATOR Page 64 ! - ., ANSWER: 046 (1.00) _ b.

. -- REFERENCE: Facility Exam Bank section 2303, item 000849.

[3.1/3.3~) 033000K405 ..(KA's) - ' ANSWER: 047 (1.00) _ c.

REFERENCE: Facility Exam Bank section 2305, item 001522.

[2.9/3.P.)

, 033000K401 ..(KA's) - . ' ANSWER: 048-(1.00) c.

REFERENCE: _ Millstone 2 Exam dated 4-23-90, Question 47.

SFPC SD, pp 7.24.

EO 3,7 [2.9/3.2) 033000K401 ..(KA's) LANSWER: 049 (1.00)

a.

.

. $ . . . REACTOR OPERATOR Page 65 REFERENCE: Fccility Exam Bank section 2317, item 000137.

(2.9/2.9) C39000G004 ..(KA's) . ' ANSWER: 050 (1.00) .d.

REFERENCE: Millstone 2. Exam dated 4-23-90, Question 44.

Firo Protection SD, pp 18-22.

EO 2 [3.0/3.4) . C86000K405 ..(KA's) ANSWER: 051 (1.00) c.

REFERENCE: " LP M2-OP-RO-PRI-2306-9 pp 4 & 5 JLP M2-OP-RO-PRI-2306-0, E0 19 [4.3/4.4) 006000K302 ..(KA's) , ANSWER: 052 (1.00) ' b.. REFERENCE: LP M2-OP-RO-PRI-2306-9, pp 18, 27 'LP M2-OP-RO-PRI-2306-9, E0 12, 18 r [3.5/3.9) 006000K506 ..(KA's) t I - - -

m.z . . Ju >c,t REACTOR' OPERATOR Page 66 ANSWER: 053 (1.00) a '. ' REFERENCE: LP M2-OP-RO-ELECT-2345, p9 LP M2-OP-RO-ELECT-2345, EO 7 [2.7/3.1) 063000A301 ..(KA's) JANSWER: 054 (1.00) c.. REFERENCE: LPJM2-OP-RO-ELEC-2342,- p3 'LP M2-OP-RO-ELEC-2342, EO 9 [3.3/3.4) 062000K201 ..(KA's) LANSWER: 055.(1.00) C.+ JREFERENCEt Facility Exam Bank section 2330A, item 000648.

[3.3/3.4] .008000K102 ..-(KA's) ? ANSWER: '056 (l.'00) c.

i, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - -.. _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

---

'----- --------------------- -~-- --

_

., . - I i .- -

-. ' LREACTOR OPERATOR-Page 67 REFERENCE: Milletone 2 Exam dated 4-23-90, Question 29.

Containment and Ctmt systems LP, p 78.

EO 23b [3.4/3.9) 028000K501 ..(KA's) ANSWER: 057 (1.00) - b.

' . REFERENCE: Fccility Exam Bank section 2303, item 000969.

[2.6/3.3) > 1034000K403 ..(KA's) LANSWER: 058 (1.00) ! ' b.

1 REFERENCE:

M111' stone 2' Exam' dated 4-23-90, Qu<,stion - 4 5.

' Cont 0inment Area Refueling.Equipm'.nt SD, p 14,15.

EO 2a -[2.5/3'.3) 034000K402 ..(KA's) ' A' N S W E R : 059 (1.00) - ! , ~ - o..< . > t ) REFERENCE:-

LP M2-0P-RO-SEC-2316A,-

p 51 ~ '5P ; M2-OP-RO-SEC-2316A, EO 7.d.

[ 3.' 4 / 3 '. 6 ) .t 041020K418 ..(KA's) , , -

- - - - - - - -........ . . .. REACTOR OPERATOR-Page 68 ANSWER: 060 (1.00) b.

REFERENCE: ' Facility, Exam Bank section 2323A, item 000138.

[2.8/2.7) 045000A406 ..(KA's) ANSWER: 061 (1.00) b.

' REFERENCE: Facility Exam Bank section 2323A, item 000151.

[2.6/2.9) 045000A305 -..(KA's) ANSWER-L.062.(1.00) 6.

REFERENCE: M111 stone'2 Exam dated 4-23-90,. Question 26.

LCompressed-Air Systems LP, p 34.

EO_16 [3'.2/3.5).

078000K402 ..(KA's).

ANSWER: 063 (1.00) ~ b.' l !

L .* REkCTOROPERATOR Page 69 . REFERENCE: , -EOP 2525' step 3.1 NOTE Lascon Plan M2-OP-RO-TA-2525/6 E0 13.

[3.5/4.4] 000005A203 ..(KA's) ANSWER 064 ( 1. 00 )' . .O.

REFERENCE: . Facility Exam Bank section.2026, item 001475.

i [4.2/4.2) 000040A112 ..(KA's) Ai1SWER: 065' (1.00).

fb[ .REFERENCEi Fccility Exam. Bank section 2536, item 001128.

[4.5/4.7)

000040K304

..(KA's) . ~ ? ANSWER: 066L (1.00) 10.

REFERENCE: . M111 stone 2 Exam dated 4-23-90,-Question 78.

EOP 2536,' Caution Step.3.17, p 12.

TPG'2536(0)/Al1

.EO'9,10 . [4.1/4.4] 000040K101 ..(KA's) . - - - - - -

,e- . REACTOR OPERATOR Page 70 .

ANSWER: 067 (1.00)- ib.

. REFERENCE: Millstone 2 Exam dated 4-23-90, Question 84.

OP 2345B, Step 6.4, p 4; OP 2384, pp 5-7.

TPG 2345B(6)/8.0 E0 lb (Note: similar-River Bend event 2/12/90) [3!6/3.9) ' 000057A220 ..(KA's) ANSWER: 068 (1.00) ' d., . REFERENCE: Millstone =2 Exam dated 4-23-90,. Question 54.

EOP'2525. Step 3.5 Loccon Plan M2-OP-RO-TA-2525/6 EO 18.

1[3.7/4.3).

000069A201 ..(KA's)

ANSWER: 069 (1.00)

.d.

-REFERENCE: OP-2313/9.2 -[3.2) [3.3) 028000G007 ..(KA's) ~ s

=* : . -REACTOR OPERATOR Page 71 ANSWER: 070 (1.00) -c.- l REFERENCE: . Fccility: Exam Bank section 2532, item 001642.

[4.2/4.4) , 000074A101 ..(KA's) [' ANSWER:- 071 -(1.00) 'C.

. REFERENCE: OP-23010/8.14 OP-23010/8.12 [ 3. 5 3 - [ 3 '. 9) ' 003000A201- ..(KA's) IANSWER: 072.(1.00) -e f d =.' < REFERENCE:

AOP'2558, Objective

!TPG-2558(0)/4.0, EO 1" [3.8/4.1]' 000024A201 ..(KA's) . ANSWER: 073 (1.00) '..... - -.- REACTOR OPERATOR Page 72 REFERENCE: EOP 2540B, Step 3.5-TPG 2540B(0)/All, EO 5 [4.3/4.5) 000055A107 ..(KA's) ANSWER: 074 (1.00) c.- -REFERENCE: E0P:2540B; Step 3.4 .TPGx2540B(0)/All,. EO 6 [4.3/4.6)

000055K302 ..(KA's) ANSWER: 076 (1.00) -a.. . REFERENCE: 1AOP'2574 Step 4.8 ,TPG 2574(1)/4.0, E0 1 [3.9/4.13-000051A202 ..(KA's) ANSWER: 076 -(1.00) ~ c.

REFERENCE: Technical Specification 3.3.3.5 'LPLM2-OP-RO-AOP-2551 EO 3 [3.1/3.6) 000068G003 ..(KA's)

..

. . REhCTOROPERATOR Page 73 i ' ANSWER: 077 (1.00) -b.

EREFERENCE: LP M2-OP-RO-AOP-2579, EO 1 [3.3/4.1] 000067K304 ..(KA's) ANSWER: 078 (1.00) c.. . FREFERENCE: Facility Exam Bank section 2525, item 000162.

-[3.8/3.9] l 000007G012 ..(KA's) ! '. ANSWER: 079' (1.00) I c.: ' REFERENCE: ' Facility Exam Bank section 2026, item 001173.

' [4.2/4.3] . 000009K323 ..(KA's) , a.. LANSWER: 080 (1.00) __ _ . _ _ _. _ _ _. _ _...... _. __ l' , -4 REACTOR OPERATOR Page 74 REFERENCE: Millstone 2 Exam dated 4-23-90, Question 53.

AOP 2572, Step 4.1 and Caution before Step 4.3 No Facility Objective Found [3 9/4.1).

000025K303 ..(KA's)- ~ ANSWER:- 081 (1.00) b'. REFERENCE: -Millstone 2 Exam dated 4-23-90, Question 79.

AOP 2569, Note p 5 .TPG 2569(1)/4-'0 EO 4g,6 . [3.7/4.0) 000037K305 ..(KA's) l ANSWER: 082 (1.00) a.

iREFERENCE: Millstone 2 Exam dated 4-23-90, Question 80.

AOP 2569, p 3; TS 3.4.6.2.

'No' Facility Objective Found.

.. [3.2/4.1]

000037A210

..(KA's) fANSWER: 083 (1.00) ' . . JREACTOR-OPERATOR Page_75 ' REFERENCE: Focility Exam Bank section 2026, item 001016.

[4.4/4.5] '000038K302 ..(KA's) i

ANSWER:

084 (1.00) C.- REFERENCE: Milletone 2 Exam dated 4-23-90, Question 57.

, EOP 2534, Steps 3.11 and 3.15.

No Facility Objective.Found.

[4.1/4.7) 000038A201- ..(KA's) ' L , - ANSWER:~ 085 (1.00) L o.. i ' I - ' REFERENCE: l : Millstone 2 Exam' dated 4-23-90, Question 56.

LEOPJ2540D, Step.3.1 Caution 2.

', L.TPG 2540D(1)/A11-E01c [4.4/4 6) 000054K304- ..(KA's) ,

NSWER:- 086 (1.00) r

C.

. I

e

)

. L REACTOR OPERATOR Page 76 TREFERENCE: EOP 2540B, Step 3.2.h.

TPG 2540B(0)/All, EO 4 .[3.7/3.8) 000058G011 .. ( KA ' s )' ANSWER: 087 (1.00) .c.

, . REFERENCE:

AOP 2556,. p3

TPG 2556(0)/4.0,- E0 1

[3.1/3.7) 000003K104 ..(KA's) v , ' ANSWER: ~088 (1.00) .C.

REFERENCE:

LP'M2-OP-RO-PRI-2306-9, p 67 LP M2-OP-RO-PRI-2306-9, E0 18 i

, .[3. 4 /3. 7]. ~000008A212=' ..(KA's) .,. . . i JANSWER.. 089 (1.00) -bi ' i ^REFERENCEi LP M2-0P-RO-FUND-2116 TO 2 - - [ 4'. 2/4 ' 3 ) - , 000001A204 ..(KA's)

!

. . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -.

-... < , .> _

i ' REACTOR OPERATOR Page 77 ' ANSWER: 000 (1.00) c.

REFERENCE: TPG 2532(1)/A11,. E0 1~.b.

[3.7/3.7) '000011A213 ..(KA's) . ANSWER: 091 (1.00)' .O.

REFERENCE:

.LP.M2-OP-RO-PRI-2304, E0 2, 25 [3.2/3.8]. 000022A201 ..(KA's) -ANSWER: 092 (1.00) - , C.

l REFERENCE: ' L LP M2-0P-RO-PRI-2310, HE0 16

[3.9/4.3)

'000025K101 ..(KA's)

ANSWER:

'093-(1.00) G.

. . --

'l . . -. REACTOR OPERATOR Page 78 - - REFERENCE: ' AOP 2572, Step 4.4.8 LP H2-0P-RO-PRI-2310,- EO 17.b.

-[3.9/4.1] . 000026A101 ..(KA's) ANSWER: 094 (1.00) .C.

! REFERENCE:

!-- T.S.

3.3.1.1 LP M2-OP-RO-I&C-2380-2, E0 12 ' [2.6/3.3] 000032G003 ..(KA's) , L lI ANSWER: 095 (1.00) b.

. i bREFERENCE: l-M111sto.e'2 Exam dated 4-23-90,-Question 61.

AOPL2673, Note 3 before Step 4.8 No;Focility.0bjective Found '[3.7/4.1]

000P16K303

..(KA's) - . ANSWER: 096 (1.00) t .. _. -;.., - , ! . REACTOR OPERATOR Page 79 REFERENCE: Millstone 2 Exam dated 4-23-90, Question 73.

EOP 2528, p 16; OP 23010, p4.

, TPG'2528(0)/A11 EO 6 [3.3/3.4] 000056G007 ..(KA's) ANSWER: 097 (1.00) - b.

REFERENCE: LP M2-OP-RO-I&C-2304A, EO 9 [2.8/3.1) < 000028K101 ..(KA's) l t (********** END OF EXAMINATION **********) - . - .

- - -, - -..... .,,,... .. _ . , -REACTOR OPERATOR Page

ANSWER KEY 001 d- -002-match with selected number in the blank a

b

c

003 o - 004 ~ c 005 d 006 b 007-' b 008-- d 009 a-f010 .c 1011' b 012: d

013 b

'014-c-015.

a 616-c 017 a.

'

018 b

- 019 a 020' b 021 a . . .. - - . .

.. i .. . .. , 022. match with selected number in the blank

9

.

.

, REACTOR OPERATOR Page

ANSWER KEY (

a

b

o

d

023 d 024 c 025.

o '026 c ! 027 a l 028-b , 029 d 030 b ,.,031-c l- ' 032 d.

l:033 a ~034 b 035 b.

-i H036 d l :037-c l 038-b- 039 match with selected number.tn the blank a

L b

l

,pw~n- _ < .. .-e' , S' c

t , 8: I.

. .' F ? < h ! I (

r ' l'. i lr. , .

..

.. .

.. _ .

. , 9' REACTOR OPERATOR Page

ANSWER KEY - d

-C40 c 041 d' - C4 2 - a 043 b C44-c 045: b C46 b d47 c' =048 c 'C49-a 050 d . -g31 - -c ' C52l b 053: a' 054.

- c '055 c'- C56.

c 057 b 058-b 059' a.

000 b C61 b 062 b . - .. . . .

- .. - - - -,.,,, .O - . 063 b -. - . _._ - - W - .

.. . . REACTOR ~0PERATOR Page

ANSWER KEY 064 a 005 b '066-. a 067 b-068-d C60' d 070-c G71 c 072 d

073 b ' -074

c

, 075 a . 076 'o 577-b

078 o

079 c C80? d- ~ '031 b-002' a 083 b $84' ' a 085 e 086 c 087 a - . .i

-- - - -.. - - - - - - -. k ' d- -- 088 . c

__ -i i .. - -............,.... v.

, REACTOR OPERATOR Page

ANSWER KEY-z _ 089'- b 090 a , ~ 091 a _ 092 c 093 a 094 .c

095 'b - 096 d , 097 b _ . _ - _ _ E.- . - _ - (********** END OF EXAMINATION **********) - . .. ...... .

_ _ _. _ _.....

-

. 9.. RCS PRESSURE / TEMPERATURE LIMITS Figure 4.2 PTS LINitT 100* FIH R DEGRADED p 200'F COOLDOWN CTNIT SUBCOOLED SUBCOOLED CURVE-RCS SATURATION NilNINIUT.! AllNINIUNI N1 AXINIUN1 hlAXIhlUhl TENIP PRESSURE PRESSURE PRESSURE PRESSURE PRESSURE ('F) psia (ptiaj (psia) (psia ) (psia t hun.

1543 1919 1919 Upper Limit of 595 1487 1S52 1852 2350 590 1432 1787 1787 ~ 585 1378 1723 1723 5A0 1326 1662 1662 575 1276 1602 1602 .570 1227 1543 15a3 565' i180 1487 1487 560 1133 1432 1432 555 1089 1378 1376 550 1045 1326 1326 545 1003 1276 1276 540 963 1227 1227 '535 924 ll80 1180

530 885 I[33 1133-525 848 1089 1989 520 813 1045 1045

.- ? ? S 1003 1003 'i 10 -- 744 963 963 '505-712 924 924 500 681 885 885 . -495 650 848 Sa8 '440 621-913 813 485 593 773 773 . 480 f66 744 744 J.7 5 ' 540 712 712 470-515-681 687 ' Jh5; 440 650 657 ]f 460 467 621 633 2350 455 434 593 607 2286 f50 '423 566 582~ 2208 ~445 402 540-561 2133 340 382 515 540 20h0

4 L 35 362 490 522 1o89 430 3J4 467 502 1919 425 'J 26 434 ag3 gg$3 i 420, 309 J23 467 1787 415'. 242 an2 451 1723 !410 277 392 436 1662 ' y '5-262 362 408 i602 400 247' 344 Joh 1543 EOP 2534 Page 29 Rev 8 ..... _ _ _ _ _

- _ _... _ _.... _'_D P ' RCS PRESSURE / TEMPERATURE LIMITS Figure 4.2 PTS LINilT 100 * FlH R DEORADED 300F 200*F COOLDOWN CTNIT SUBCOOLED SUBCOOLED CURVE RCS SATURATION sigNistesg NIINIhlCSI N1 AXINIUhl N1 AXihll\\1 . T E N1P PRESSURE PRESSURE PRESSURE PRESSURE PRESSURE (*F) ' psia (psla n (psia) (psia) (psia l 30$ 233 326 392 1487 Upper Limit ol 300 220 309 378 L432 2350 385 208 292 366 137B 380 196-277 353 1326 375 184 262 340 1276 370 173 247 329 1227 36$ 163 233 319 1180 3no 153 220 309 1133 355 144 208 299 1089 350 135 196 289 1045-3J5 126 184 281 1003 340 118 173 275 963 335 110 163 265 924 33n 103 153 256 88<

325'

144 251 848 320

135 2J2 8g3 'l5

126 236 ~78

78 118 230 aa >"5

IIH 224 712 300

103 2tg 33g 243 62-Oh 2la 830 Y 290

90 2go ng ,,30 285

8a 205 $03 Inn 25"

78 202 566 5970 275'

72 198 540 1850 270

67 196 515 1730 265

62 192 490 1620 26"

58 190-467 153o 'j55

53 188 a34 1450

_30

184 423 g370

f,

j do2 1300-352 i230

- -

35

3 362 117o

' ' L'30 3J4 II"" ' '5 '33H 320 1040 309 98n '^ 292 930

n[,

'd 277 880 ',l, 262 840 247 300 - EOP 2534 Pace 30 ' Rev 8 .. _.............. . ....... . . .. ....... .. .. . }}