ML20237J538

Exam Rept 50-368/OL-87-01 on 870804-06.Exam Results:Five of Six Reactor Operator Candidates Passed.Exam & Answer Key Encl

ML20237J538
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/20/1987
From:	Cooley R, Mccrory S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20237J536	List: ML20237J533 ML20237J538
References
50-368-OL-87-01, 50-368-OL-87-1, NUDOCS 8708260209
Download: ML20237J538 (49)

Text

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ARKANSAS NUCLEAR ONE UNIT 2 OPERATOR LICENSE EXAMINATION REPORT No. 50-368/0L-87-01 Licensee: Arkansas Power & Light Company P.O. Box 551 Little Rock, AR 72203 Docket No: 50-368 License No.: NPF-6 ,

Examinations administered at Arkansas Nuclear One Unit 2 1

Chief Examiner: ) me 20 2 VMicCrory; Lead Exami Date /

Approved by: ' '

W R. A. Cooley, Sect [An Chief Dat'e Summary Examinations conducted on August 4-6, 1987.

Written and operating examinations were administered to six (6) Reactor ,

Operator candidates. One candidate failed the written examination. All other '

candidates passed these examinations.

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s 8708260207 870021  !

PDR ADOCK 05000360 i l V PDR l

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n 2 l Report Details 1.- PERSONS EXAMINED-R0 candidates Total Pass Fail %  ;

6 5 1 83

'2.- EXAMINERS S. L.: McCrory, Chief Examiner J. E. Whittemore

3. - EXAMINATION REPORT Performance results for individual candidates are not included in this I report because examination reports are placed in NRC's Public Document

. Room as a matter of course. Individual performance results are not I subject to public disclosure,

a. EXAMINATION REVIEW COMMENT RESOLUTION In general, editorial ~ comments or changes made during the examination, the examination review, or subsequent grading _ reviews are not addressed-by this resolution section. This section reflects resolution of substantive comments submitted to the NRC after review of the examination by the facility licensee. The modifications discussed beloe'are included in the master examination key which is provided elsewhere in this report as are all other changes mentioned above but not discussed herein. The facility licensee examination comments, less the supporting documentation, are included in the report immediately following the master examination key. Unless otherwise indicated in this section, the facility licensee comments were incorporated into the answer key. ]

1.05b The wording of the question was further reviewed and' determined to be of sufficient clarity'to convey the intent of the question. Additionally, most of the candidates asked the examiner for clarification during the ,

examination and indicated their understanding.

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-b., EXIT NEETING

SUMMARY

At the conclusion of the examination period, the examiners met with the members of- the facility staff to discuss the results of the

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examinations. The following personnel were present for the exit

' meeting:

NRC- UTILITY S. McCrory J. Vandergrift B. Baker W. Johnson W. Perks J. Teter S. Quennoz C. Anderson C. Fite NRC informed the facility staff-that several of the candidates had difficulty using the BORON 2 program to compute boration to achieve shutdown margin. No other' areas of generic weakness were noticed, o c.

GENERAL COMMENT

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- Review of the written examination results indicated that the candidates'had difficulty with the following questions:

1.09- 3.05 2.12 3.10a 3.04c This'is provided for information only. No facility licensee action or response is required. If the facility licensee has any comments on'these questions, they may be forwarded to the NRC for review for.

future examination development.

Overall examination performance both written and operating was very good. Several of the candidates demonstrated SR0 levels of knowledge and understanding in many areas of the operating examination.

'd. EXAMINATION MASTER COPY A master ~ copy (questions and answers) of the R0 license examination follows this page. Handouts and other examination aids provided to j the candidates are not included.

.e.- FACILITY LICENSEE EXAMINATION COMMENTS LThe facility licensee examination review comments follow the examination master copy. Supporting documentation provided with the comments is not included, w:_ _ -_- - -

3 U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _eEEANSAS_NUCLEGE_QUE=2__

REACTOR TYPE: _ EWE =CE..__ ____ __

DATE ADMINISTERED _82ZQEZQa___ _

EXAMINER: _dCCEDEX._S.__ [

}

CANDIDATE: _- _ _ _

INSIEUCIlONS_ID_CeUD1DeIE1 Use separate paper for the answers. Write answers en one side only.

Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at l least 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY  % OF CANDIDATE'S CATEGORY

__UALUE_ _IDIeL ___ SCORE ___ _UALUE__ _ CeIEEDEY__

_25.0D__ _25.0Q _ 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW

_25.QQ__ _25.00 __ ___2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS

_25.QQ-- _25.00 3. INSTRUMENTS AND CONTROLS

_25.QQ__ _25.QQ ___ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL LQQ.QQ__ _% Totals Final Grade AII work done on this examination i s my own. I have neither given nor received aid.

Candidate's Signature l

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l NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS ,

I lDuring'the administration of this examination the f oll owi ng rul es appl y:

l 1. _ Cheating on the examination means an automatic denial of your application l

! and could resul t in more severe penal t i es.

2. Restroom trips are to be limited and only one candidate at a time may loave. You must avoid all contacts with anyone outside the examination room to avoid even the' appearance or possibility of cheating, j

3. Use bl ack ink or dark pencil onix to facilitate legible reproductions.

'4. Print your name in the blank provided on the cover sheet of the examination.

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

'6. Use only the paper provided for answers.

7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.

8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a naw page, write onix on one sida of the paper, and write "Last Page" on the last answer sheet.

9. Number each answer as to category and number, for example, 1.4, 6.3.

'10. Skip at least ihtaa lines between each answer.

11. Separate answer sheets from pad and place finished answer' sheets face down on your desk or table.

12. Use abbreviations only if they are commonly used in facility lilacaluce.

13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

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

to mathematical problems whether indicated in the question or not. 1

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of I the examinec only.

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17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has l been completed.

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18. When you complete your examination, you shall:

a. Assemble your examination as follows:

(1) Exam questions on top.

(2) Exam aids - figures, tables, etc.

(3) . Answer pages including figures which are part of the answer.

b. . Turn in your copy of the examination and all pages used to answer the examination questions.

c. Turn in all scrap paper and the balance of the paper that you did not use 'for answering the questions.

- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.

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GUESTION 1.01 (1.00)

During a reactor startup, an initial reactivity addition causes power to increase from 20 to 40 CPS. A second reactivity addition causes power to change to 80 CPS. Which of the following statements is correct?

a. The'first reactivity addition was smaller. l

b. The second reactivity addi t i on was smal l er .

c. The first and second reactivity additions were equal.

d. There is insufficient data to determine a relationship between the reactivity additions. (1.0)

QUESTION 1.02 (1.00)

Which of the following statements concerning power defect is correct?

a. The power defect is the difference between the measured power coefficient and the predicted power coefficient.

b. The power defect increases the rod worth requirements necessary to maintain the desi red shu tdown margi n f oll owing a reac tor trip.

c. Because of higher boron concentration, the power defect is more negative at the beginning of core life,

d. The power def ec t necessi tates the use of a ramped Tavg program to maintain an adequate subcooling margin.

QUESTION 1.03 (1.00)

List four factors that af+ect CEA worth. (1.0)

QUESTION 1.04 (1.00)

What are the two major factors that cause the Doppler Coefficient to become more negative over core life? (1.0) 1

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QUESTI0tO 1.05" (2.00)

The'~ reactor.Is~taken critical'and a + 1/3 DPM startup rate is established.-

a.. .From control room NUCLEAR instrumentation, what'are two ways the operator'tell when~the point.of adding heat has been reached? '(1.0)

E b. Under.which of the f ol l owi ng se t of condi t i ons 'was the heating range entered?

't.  : Reactor power increases by a factor of 6 in 143 seconds. l

2. Reactor power increases by a factor of 3 in 109 seconds.

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3. Reac tor

power increases by a factor of 5 in 129 seconds. '

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1 (iQUESTION- 1.06 (1.50) i L , ,

l If reactor power'is-increasing from 39 MW to 90 MW at 0.025 MW/SEC,:what the Start Up' Rate (SUR)? (1.5)

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QUESTION '1.07 (1.50)

Assume the reactor'is Xenon free. It is taken to critica1'ity and the power I is raised to 50% at 5%/ min..- If a trip occurs as power reaches 50%, how will the Xenon concentration be trending in the f ol l owi n g three situations?

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.Uselone of the five choices (1-5) below to provide an answer for each one of.the situations a, b, and c.

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1. Increasing toward peak Xenon concentration

2. Increasing toward 100% equilibrium '

3. Decreasing toward a dip ,

4. Decreasing toward a zero per cent power equilibrium value

5. At zero per cent equilibrium value a., One hour after the trip.

b. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the trip.

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c. If, after 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the reactor is started up and returned to 50% power at 1%/ min., what is the trend as power reaches 50%. (1.5)

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, IBEEMODY.dedlCS MEeI_IEeUSEER_eUD_ELU1D_ELOW QUESTION 1.08 (2.00)

Explain the long term changes in Shutdown Margin resulting from fission product poisons after a reactor trip from full power with equilibrium

-conditions. The answer should address both the individual AND collective effects. (2.0)

QUESTION 1.09 (2.00)

New fuel is being added to the reactor with an initial Keff of 0.85 and new fuel worth 0.1 dK is added. -

a. What is the new Keff after adding new fuel (0.1 dK)? (0.5)

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b. What is the new Shutdown Margin? (0.5)

c. What is the new Subcritical Multiplication Factor? (0.5)

d. If at this time all Shutdown CEA's were withdrawn, would the reactor go critical? Explain your answer. (0.5)

QUESTION 1.10 (1.00)

Would it be possible to attain criticality on a new core without an installed neutron source? Expiain your yes or no answer and why the reactor is equipped with a source. (1.0) l l

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1' __EElblC1ELES_DE_bluCLEeE_EDWER_ELeblI_OBEEeIlObl PAGE b IBEEldODXblet:11CS BEeI_IEeblSEEE_ablD_ELU1D_ELOW QUESTION 1.11 (1.00)

With the reactor critical at 5000 CPS, CEA withdrawai is used-to increase power to 10000 CPS. Select the statemen t bel ow that correctly describes tho position of the CEA's after power is stabilized at 10000 CPS. (1.0)

a. The rod position will be higher than previous as more fuel must exposed to.the' neutron flux to maintain the higher power level.

b. Rods will be further withdrawn to compensate for the temperature defect at the higher power.

.c. The rod position will be the same because the outward motion needed to attain a given startup rate equals the inward motion necessary to kill the startup rate.

d. The final position will be lower due to the increasing delayed neutron population associated with the higher power level.

QUESTION 1.12 (2.50)

'Balow is'a representative heat' flux curve for a fuel element.

a. Describe the change (s) in the heat transfer process which cause the inflection point (change in slope) at point a on the curve. (1.0)

b. Describe the change (s) in the heat transfer process which cause the inflection point at point b on the curve. (1.0)

c. If a fuel element were operated to the right of point b on the curve, is it likely to be to the left (less delta T) or right (more delta T) of point c on the curve? (0.5)

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• temperature differential l

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l QUESTION 1.13 (2.00) ]

a. Explain how a loss of heat sink disrupts natural circulation flow.(1.0)

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b. Expl ain how depressuri z i ng too rap i dl y disrupts natural circulation i flow. (1.0) l ,

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! QUESTION 1.14 (2.00)

a. Why does a single RCP pump running during hot shutdown draw more motor amperage than when one of four running at power? (0.5)

b. Why does a RCP running at cold condi tions draw more motor amperage than at hot conditions? (0.5)

c. Why is RCP motor amperage higher when starting the pump than when running? (0.5)

d. Why should operating a pump with too much flow and no discharge pressure be avoided? (0.5)

QUESTION 1.15 (2.00)

Indicate whether each of the following will INCREASE, DECREASE, or NOT AFFECT the Departure from Nucleate Boiling Ratio (DNBR). Assume all ,

other parameters remain constant. (2.0) I

a. Primary cool an t temperatur+ decreases

b. Primary coolant pressure decreases

c. Primary coolant flow decreases

d. Reactor power decreases l

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QUESTION 1.16 -(1550)

Unit 2 iscat.90X' power withLeontrol-rods in MANUAL when the turbine is remped down ~to 60%. . Indicate whether the parameters below will increase,

. decrease or remain-the same during bothLthe .i n i t i al response-(first:30 seconds of the transient) and after; turbine power has stabilized relative to the' initial' conditions. (Assume the'following _No changes'to-boron / xenon L -Loop transport time is 10 seconds No operator actions)

. NOTE .No; answer. required where it-is already filled in below.

I Initial Response Steady State a) S/G Pressure NO ANSWER RQRD b). Reactor Power NO ANSWER RQRD c) Tcold d)' Tavg l.

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4 2 __"EL6NI_ DESIGN _1NCLUDING_S6EEIY.AUD_EMERGENC1_SYSIEMS PAGE 8 l

-. q 2.01 (2.00)

L QUESTION The Post Accident Sample System (PASS) can take a hard-piped liquid sample from what-four (4) locations? (2.0)

QUESTION 2.02' (2.00)

What three (3) separate sources of power feed into a typical static inverter power supply? Include the order of preference for the inputs.

.Spocific circuit, bus, or panel numbers are NOT required. (2.0)

QUESTION 2.03 (2.50)

a. What conditions are necessary to cause an automatic shift of l Emergency Feedwater System suction sources? (1.0)

b. What are the suction sources involved in the above shift (normal and alternate)? (1.0) l c. Once an EFAS has been received, what automatic action prevents i overfilling the steam generator? (0.5)

QUESTION 2.04 (2.00)

a. What is the normal mode or lineup of the Steam Dumps' and Bypass '

Control Valves' Permissive Switches (OFF, MANUAL, or AUTC)? (1.0)

b. List three (3)' locations for SDBCS EMERGENCY OFF pushbuttons. (1.0)

QUESTION 2.05 (1.50)

Explain the purposes of the RCP Anti-Rotational Device and Flywheel. (1.5)

QUESTION 2,06 (1.00)

If en ESF component is automatically actuated, how may it be overridden?

(Consider both pumps and valves.) (1.0)

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> QUESTION 2.07: '(1.50)

'Antwer-TRUE or FALSE for each of the f oll owing concerning 480 vol t motor control center operation.: (1.5) a .: 'If the contr'o1 power fuses are' blown, the load may still be operated using the l oc al handswitch. ,

~b. Depressing the open/close contactors does not bypass the valve position / torque contacts in the control circuit.

'c.- If-the control power fuses are blown, the load may still be operated' by depressing the contactors.

- QUESTION 2.08 (2.00) l l a. . What will cause'an auto start of an emergency diesel generator? (1.0) 1

-b.- List five (5) conditions necessary for the diesel generator output L breaker,to auto close onto its respective 2A3/2A4 bus. (1.0)-

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QUESTION 2.09- (2.00)

List five (5) ELECTRICAL interlocks associated with the refueling machine hoist. (2.0)

-QUESTION 2.10 (2.00)

On SIAS the SW pumps receive a start signal. List six (6) valves in the SW/ACW system that au tomat i cal l y respond to SIAS and whether the valves receive an OPEN or CLOSE signal. (Redundant components will be considered as'one response.) (2.0)

QUESTION 2.11 -(1.50)

L The C CCW pump f a l l s wh i l e supplying loop-II. The A CCW pump is servicing

' loop I at the. time. Assuming that the line up of the remainder of the CCW

. system-is as per procedure for A and C pumps operating, describe the sequence of events following the failure of pump C. (1.5)

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.2 _ELANI_DESIGu_1NCLUDING_SeEEIY_eND_ EMERGENCY _SYSIEMS PAGE 10 QUESTION 2.12 (2.00)

Anewer TRUE or FALSE for each of the following concerning the control room ventilation system. Assume for each case that the ventilation system is initially in the normally prescribed line up during full power operations and.that no operator action is involved. (2.0)

c. Receipt of. a SIAS causes the CR ventilation system to shift to the emergency recirc mode.

, b. If a fire breaks out in the CR, only the CR ventilation exhaust path is affected by automatic control s i gnal s ,

c, Detection of radiation or chlorine in the CR ventilation system results in air being recirculated on the unit i side of the CR and cooling being secured to both sides of the CR.

d. Activation of the smoke detectors in the outside air supply duct will cause auto start of the Emergency Air Filtering System portion of the CR Emergency Ai r Condi t i on i ng and Ven t i l at i on System.

QUESTION 2.13 (1.00)

a. What are two (2) undesirable potential effects of introducing oil into the Instrument Air system? (0.5)

'b. True or False. On loss of power to the solenoid operated IA crosstle valve fails open, automat i call y cross connec t i ng the unit 1 and unit 2 IA systems. (0,5)

QUESTION 2.14 (2.00)

a. With the plant at full power steady state conditions and no periodic or infrequent evolutions in progress, what would be the control room indication of each of the f oll owi ng condi t i ons of a Safety Injection Tank discharge check valves. Assume no operator action. (1.5)

1. Only the check valve nearest the SIT leaks by.

2. Both check valves leak by.

3. Only the check valve nearest the RCS leaks by.

b. If the valve which admits nitrogen to a SIT fails open WHAT will be the maximum pressure in the SIT and WHY? (0.5)

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rQUESTION .3.01t (3.00) a .' .In~ reference to the,. Steam Dump. Bypass and Control System (SDBCS) quick-opening BLOCK, signals:

1=, What are?the two signals?. (0.5) 2.= What valves are.affected.by each signal? (0.75)-

3.- What'is'the purpose.of the block signals? (0.75)

b. Explain the. purpose of the following interlocks:

1. - Upstream Atmospheric Dump Valves closure on MSIS. (0.5)

2. Turbine Bypass. Valves'close.on decreasing' condenser vacuum.(0.5).

- QUESTION 3.02 (l .00)-

Concerning the High Level Override (HLO) feature of the Feedwater' Control

. system.(FWCS), choose the statement below which is INCORRECT.

a. . --The. purpose.of the feature is to protect the Main turbine.

b.. - The 'HLO sends a 5% flow demand signal to feed pump and control valves.

c. 'The-HLO setpolnt' is 94%.

.d..- The feedwater pump will be controlled by the fl ow demand si gnal from the other FWCS. (1.0) l i

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i QUESTION 3.03 (1.00)

Concerning the Reactor Trip Override (RTO) feature of the Feed water Control System (FWCS), choose the statement below which is CORRECT.

a. The RTO is generated i n each FWCS direc tl y by a matrix of contacts depicting CEA position.

b.- The feedwater pump speed decreases to minimum speed.

c. The RTO signal may automatically reset if flow demand increases and j remains above 5%.

d.- The Bypass Feedwater Control Valve positions to a position corresponding to a 11% demand signal . (1.0) i 1

QUESTION 3.04 (2.50)

a. Describe the design feature and the basic procedure for using this feature to test an ESFAS trip initiation channel with a channel already out of service due to a failed component (detector, relay, etc.) (1.0)

6. State the one ESFAS initiation signal that does not deenergize lockout relays and explain the reason. (0.75)

c. What other trip actuation signals may be generated by the measurement channels which generate a Containment Isol ation Ac tuation Signal (CIAS)? (0.75)

QUESTION 3.05 (2.00) l What four (4) conditions will cause a valve misalignment alarm for the Low Temperature Over Pressure Protection System? Include any applicable temperature or pressure values. (2.0) l l

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. QUESTION 3.06 ( 3. 0 0 )'

i-La. :  : Explain how,and'why1the Startup Range Nuclear indication could be expected to vary from normal reactor shutdown indication during extended ~ design basis LOCA conditions. (1.0) b.' ' Explain how the-Boron Dilution Monitor alarm setpoint is changed-if i actualfflux level is increasing or decreasing due to normal plant-  !

operation. (0.75) c.. What.is the function of,the source bistables that operate off.the log. H output of.the Safety Channels? (0.5)

d. What are three (3) actions orEabnormalities that will cause a " Safety Channel Trouble " alarm due-to a " Nuclear Instrumentation Inoperative". 1 condition? (0.75)

. QUESTION 3.07 (3.00)

. Answer.the following concerning the CEDMCS, True or False:

'a. A single' control rod may be placed on the cabine t hold bus, b'. A:" Maintenance Error" al arm 'i s caused by improper voltage on the hold bus.

l -c. The hold bus places' holding vol tage on the upper gripper of the affected CEA's.

d. The CEDMCS Power Cabinet auxiliary undervoltage relays output to the Rod Motion Inhibit circuitry.

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! e. The operator may withdraw CEA's beyond the upper group stop in " Manual l Individual".

f. Indirect CEA position indication is used in the reactor protection system tripping circuitry.

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. . 1 l .~ QUESTION L3.08~

(l'.00);

.Concerning!the' Radiation. Monitoring' System,: choose ~the correct statement.

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La.- 'The area monitoring system uses'only gamma sensitive GM-Tubes. ;l

b. . .The processfmonitor.ing system uses only scintillation detectors.

Jc. :The CVCS monitor (2RE-4S06) monitors for gross lodine, and will not detect accrud' release. ,

d.- :The Gaseous Effluent Monitor System (GERMS)'SPING-3/4 monitor,.uses a i single. detector. ( 1.' 0 )

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' QUESTION- 3.09 (1.50)

State the three (3) locations where the' Radiation Monitoring System will  !

!dstect radioactive in-leakage'to the Service Water System.- (1.5) 1

-QUESTION 3.10 (2 50)

Answeritheffo11owing concerning the Core Operating' Limits Supervisory

' System (COLSS):

a. What are two (2) _ direct parameter inputs'to.the COLSS that are NOT subject to a sensor validity check? (0.5) .

b'-

Explain'how and what calculated power i s automat icall y selec ted f or comparison under all conditions of reactor power (1.0)

c. List the five (5) parameters used to calculate COLSS power when power i level is 10%.. (1.0)

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3 _'1blSIRutdEtJIS hblD_COblIROLS. PAGE 15 Tk s

. QUESTION'.3.11 ' ( 1. 0 0 ) .-

Chooseothe; correct. answer.concerning differences in the1 Core Protection LCal cul ator' (CPC) channel' operator's modules:  ;

a.- Modules for A'& B.have the same capabil'ities.'

b. . Modules for:A & C have the same' capabilities.

Lc . . : Modules.for' C &'D have the same' capabilities.

1

'd.'  : Modul e s - f or - B & C have the same, capabi l i t i es. (1.0) l

' QUESTION 3.12 (1.00)

'Concerning:the CPC's, choose.the following statement that is corrects s '. . .Only twol(2)' Reactor Coolant Pumps running may generate a CPC DNBR trip, but will not generate an auxiliary trip.

b..

Auxi.liary CPC trips will' result from high, but not low Tcold. ,

c. Ex treme Ax i al Shape Index:(ASI) values will causeca CPC Local 1 Power Density (LPD) trip,'but not'an auxiliary CPC trip.

d. Upon reaching.the Asymmetric; Steam Generator setpoint, an auxiliary .

CPC trip will' result ~. (1.0)

QUESTION 3.13 (2.50)

Answer the following concerning the Reactor Protection systems

a. - What is the trip and pre-trip logic? (0.5) ]

b' LWhat are the parameters or conditions and logic that result in a CEA Withdrawal Prohibit (CWP)? (0.5) j

~

ic.- ~What are the three.(3) interlocks / trips provided with OPERATING BYPASSES, and WHY? (1.5) I j.'

J (***** END OF CATEGORY 03 *****)

I l'

l E ,

l >N lb 4 f

id _._EROCEDURES = blDEt2L.,._eBblDBtML.,._EtdERGEblCY_eblD - , PAGE 16 j sc RAD 1DLOGICaL'_COMIEDL -)

-t .i o s QUESTION- 4 '. 01 ' (1.00) 4

. . . 1 During a plant heatup,..the: operator obser,ves-that RCS temperature goes  !

.from 350 deg FitoE362 deg F over~a six.ninute period. Explain why this. l

.specifi'c interval of' temperature changeJdoes or deps not violate.the '

j

, ;Techn i cal ' Spec i f i cat i on -l imi t on heatup rate . ( 1. 0 ) -

J 1

-QU$STION 4.02 .(1.00) , ,

How i s- a L vibrat i on al arm on a RCP de termined f to be val i d? (1.0)-

3 ,

QUESTION 4.03 - (3. 00)- '

What immediate. actions shou'Id be pe6 formed if a condrol room evacuation is deemed necessary? Component numbers are not required. . ( 3. 0 )-

A jdOESTION '4,04 (2.00)

< < {k What observation'would be indicative lof voiding in the reactor

. head. whil e 'perf errai ng. a natural c i rcuist i on cool down? (1,0) j b j b. Br;i o f l y' de scr i be the method by which the bubble in thh' head

>$. region'would be' collapsed. Specific procedure steps 45e'not v required fon full credit. Note the indication that'would verify.

collapse o4..the bubble.

$- i

, )

4

%>a, >  : ,

i 3 ,

1 6, s i  !

b i

1' A i ND.. (***** CATEGORY 04 LONTINUED ON NEXT PAGE *****)

N-g

_m_._m._.m.__.__._. __ _ _ _ . - . - . _ _ .-

l; ' d.__EROCEDURES - NDEtML _aBblOEtML,_EldEEGEtlCE eblD PAGE 17

,. - EAD10 LOG 1CeL_COblIROL QUESTION 4.05 (1.50)

n. What two items or actions must be verified or performed if cocked CEA protection is not establ ished during a pl ant heatup? (1.0)

6. Once' cocked CF1 protection is established, the remaining CEA's are withdrawn.just enough to clear the LEL lamps. This is performed primarily to (CHOOSE THE CORRECT ANSWER): .(0.5)

1. Verify the CEA indication system is operable.

2. Allow for thermal expansion of the.CEA's .

3. Verify the CEA dr i ve system . i s f unc t i onal for all groups.

4. Places the CEA's in an area where reactivity revponse is more significant (CEA's have more " bite").

QUESTION 4.06 (1.00)-

When the shutdown margin is found to be less than the Limiting Condition for Operation for the operational mode the plant is in, what is the operator Tech. Spec. action that must be taken? (1.0)

QUESTION 4.07 (1.50)

Match the following concerning the reactivity balance procedures

a. doppler defect curve 1. considers power defect

6. ITC 2. includes S/D Pu239 build up

c. core excess reactivity 3. MTC + FTC ,

d. Xe worth 4. includes redistribution effects e, transient insertion limit 5. considers eq. Sm worth

f. SAM 2 program 6. should not be considered when Tavg is < 525 deg F.

QUESTION 4.08 (1.00)

If, during power esca'lation, ASI cannot be maintained within 0.01 of ESI, what action (s) is(aro) required? (1.0)

(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

l

- ~ ~ _ - - - - _ _ _ _ i

. 1

< l Ld

• __EROCEDUEES - NDEtieL _eStJOEdeL+_EtdEEGENCX_etJD PAGE .18 j red 1DLOGICeL_COMIROL l

. QUESTION 4.09 (1.50)

I

a. What protective clothing / equipment would you expect to be required when entering a space with Tritium contamination? (1.0)

6. Explain why Tritium will not set off area radiation monitors. (0.5)

I' QUESTION 4.10 (2.00)

List the safety functions in order of their priority as listed in the EOP.

QUESTION 4.11 (1,00)

What conditions in the Reactor Trip Recovery tab of OP 2202.01 direct the  !

operator to go to the Emergency Reactivity Control tab? (1.0)

QUESTION 4.12 (1.00)

List three (3) symptoms, other than alarms, of a " Loss of shutdnwn cooling with a pressurizer bubble or with reactor coolant system open to atmosphere". (1.0)

QUESTION 4.13 (1.00)

Concerning " Loss of Shutdown Cooling", what al ternat ive me thods of cool ing should be considered if restoration of SDC flow is celayed? (1.0)

QUESTION 4.14 (1.50)

The last step of the Inadequate Core Cooling tab of the EOP directs establishing an RCS " feed and bleed". What are three (3) options available for estabilshing a " bleed" path from the RCS? (1.5) l I

( (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)

~

a . . -

d.i__RROCEDURES =_NORtdaL _ABtJORMaL _EtdERGEblCY_atJD PAGF.- 19.-

r,1 RADIOLOGICAL _COtJIROL '

5 QUESTION 4 .15 -' (1.00). .

. Tr u e/Fal se '. If any two earthquake annunciators have alarmed, and are veri f ied as' ac tual , manuall y trip the reac tor and cool down to col d . shu tdown at the maximum controllable cooldown' rate. (1.0)

-QUESTION- 4.16- (3.00)

'A. condition ~ arises which requires entry-into containment while critical at 40% power.- The operator entering will receive a whole body dose of 40 mrem. . Data is available on the following persons: (3.0)

Candidate 1 2 3 4 Sox male mal e female male-

' Ag21 27 38 24 20' Wk/ exposure 35 mrem 280 mrem 0 mrem 30 mrem

'Otr/ exposure 1230 mrem. 970 mrem 90 mremL 1120 mrem L

!ife' exposure- -

54730 mrem 5200 mrem 9770 mrem Romarks history -

4 months -

unavailable pregnant Each candidate i s techn i call y compe tent and physi cally capabl e of perf orm-  !

'ing the task.- Emergency 1.mits do not apply but. time constraints do not permi.t obtaining authorization;for an exposure limit increase. For each s

person Indicate if that person could or could not be selected to' perform

.the task based on ANO 2 exposure requirements only and Justify (explain) your response.

-QUESTION- 4.17 (1.00)

What three (3) graphs are plotted every 15 minutes (not to exceed 30 minutes) during plant heatup? (1.0) 1 1

(***** END OF CATEGORY 04 *****)

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

\ . :_=_=____--__-___--_ __

(

, .a.J_EEluC1ELES_DE_UUCLEGE PNJFP EIANT_nEFRATfDU. PAGE 20 IBERtdDD.YUAtd1CS _HFAT_IRAtJRFFR AND ELUID_ELDW j l

ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S. '

l ANSWER 1.01 (1.00)

b. The second reactivity addition was smaller. (1.0)

REFERENCE UNIT 2 SPECIFIC THEORY, Pp. 157-159 001010K536 015000K506 ...(KA'S)

. ANSWER -1.02 (1.00) b.

REFERENCE (

UNIT 2 SPECIFIC THEORY, Pp. 194, 195 001000K549 ...(KA'S)

ANSWER 1.03 (1.00)

1. Size of the rod i

2. Flux distribution (rod location)

3. Moderator temperature

4. Type of absorber material

5. Boron concentration [Any 4, 0.25 ea.3 (1.0)

REFERENCE FACILITY QUESTION BANK 001010K504 001010K524 ...(KA'S) l ANSWER 1.04 (1.00)

1. The decrease in fuel temperature.

l

2. The buildup of Pu-240. [0.5 ea.] (1.0) j REFERENCE l UNIT 2 SPECIFIC THEORY, Pp.181,186 001000K549 ...(KA'S)

{

l

-s lwEEluCIELES_DE_ULICLEeE pnWER_ELANT....DEEEeI1 dbl _ PAGE 21 IBEEtdDD.YNAM f CS_BEeI_IEeblSEFR (AID FilIiD_ELOW ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 1.05 (2.00)

n. 1. Change of log power is leveling off.

2. Indicated SUR is decreasing. [0.5 ea.] (1.0)

b. 2, (from P/Po = 10E (SUR x Time) the SUR in condition 2 has decreased from 1/3 DPM.

REFERENCE UNIT 2 SPECIFIC THEORY, P. 144 192008K115 192008K117 ...(KA'S)

I ANSWER 1.06 (1.50)

Rate of power change = 0.025 MW

• 60 sec = 1.5 MW / min. [0.25]

Time of power change = 51 MW / 1.5 MW- min. = 34 minutes [0.253 P = Po e E(t/T), and T= t/In P/Po [0.53 I

T = 2042/.8362 =2440 seconds [0.25] j SUR = 26/2440 = 0.0106 DPM (Accept .008 .012 DPM) [0.253 Accept any viable method of arriving at approximate answer (1.5)

REFERENCE UNIT 2 SPECIFIC THEORY, P. -

001000A105 ...(KA's)

ANSWER 1.07 (1.50)

a. (1)

b. (4)

c. (3)

REFERENCE UNIT 2 SPECIFIC THEORY, Pp. 204, 205 001000K538 ...<KA'S) 1 r i l

L___-- __--- -_--- l

l '

-s 4__ERINCIELES..DE_UDELEaE_EDWFR RfANT DEERATTfN PAGE 22 l IEEEtdDDYUAM i r%.BEeI_IRANREFR ANB..ELUID_ELDW 1'

! ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

l l

ANSWER 1.08 (2.00)

Xenon [0,5) will peak and then decay, adding positive reactivity and decreasing SDM. [0.253 Scmarium [0.53 will peak after shutdown and remain at peak until cubsequent startup, adding negative reactivity and increasing the Sui.

[0.253 The overall effect considering all aspects will significantly decrease SDM over a l ong term per i od. [0.53 (2.0)

REFERENCE UNIT 2 SPECIFIC THEORY, Pp.208, 209 001010K526 001010K527 ...(KA'S)

ANSWER 1.09 (2.00)

a. K2 = K1 + 0.1 = 0.95 OR K2 = K1/[1-(dP x K1)] = 0.93 (0.5)

b. SDM = 1 - Keff/Keff = .05/.95 = .053 (+/- .005) (0.5)

c. M= 1/1-Keff = 1/.05 = 20 (+/- 1.0) (0.5)

d. No. [0.25] Total Shutdown CEA worth is much less than 0.05 dK/K and more reactivity is needed to attain criticality. [0.253 (0.5)

REFERENCE UNIT 2 SPECIFIC THEORY, P. 140 i 001000K518 001010K515 ...(KA'S) I 1

l ANSWER 1.10 (1.00) 1 Yes. [0.53 Several different reactions produce source neutrons in a l reactor. These intrinsic sources usually result from from spontaneous I fission or radioactive decay of heavy nuclei (including fuel) yielding i source neutrons. [0.25] The reactor is equipped with a source to provide l early indication of neutron multiplication. [0.25] (1.0) l REFERENCE ,

UNIT 2 SPECIFIC THEORY, Pp.62-66  !

015000K506 ...(KA'S) j

p.__EBIND1ElFA DE_ NUCLEAR _EDWER_ELANI DEFRATIDth PAGE 23 TuPpMnnyNAMfCA. MFAT IRANAEpp Aun ELUID_ELDW ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 1.11 (1.00)

c. . Rod positions will be the same. (1.0)

REFERENCE UNIT 2 SPECIFIC THEORY, Pp. 145-150 001000K510 ...(KA'S)

ANSWER 1.12 (2.50)

a. Point a on the cur;>c marks the transition from convection heat removal to nucleate bubble formation. Since bubble formation is more effective than pure convection, flux per degree temperature difference is-increased. (CONCEPT) (1.0)

-b. Point b on the curve marks the departure from nucleate boiling, where bubble formation can be expected to produce vapor blanketing, greatly reducing heat flux for a given delta T. (CONCEPT) (1.0)

c. Right. (Since it is difficult to reduce heat flux while increasing delta T, the element is most likely to experience a large increase in delta T for a slight increase in flux.) (0.5)

REFERENCE HTTF HANDBOOK, FIG. 8-8 002020K501 ...(KA'S)

ANSWER 1.13 (2.00)

a. With no heat removed from the primary coolant, no density difference will be established, thus no driving force for the fluid and no flow will occur (1.0 for concept).

l

b. Natural c.irculation may be disrupted by violent boiling in the core which disrupts the thermal forces causing the driving force (1.0). i OR Rapid depressurization may cause a steam bubble to form in the RCS hot leg and/or S/G U-tubes causing fowl restrictions (increase loop resistance).

REFERENCE

, Thermal Sciences, FND-121, lesson D-3, pg 30 of 36 000056EK10 ...(KA'S)

\

l l

L .1,.__EH18CIELES_DE_ NUN FAE_EDWFR Pi ANI_DEFRATTDth PAGE 24 IBF RM nDYNAM ICS, ._.MFAT IEaNSEFR AND ELillD_ELDW I ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

l ANSWER 1.14 (2.00)

a. A single pump running has a higher flow than when all 4 are operating (due to reduced discharge' pressure) so more work is done and more amperage drawn. (ACCEPT CONCEPT FOR ALL PARTS) (0.5)

b. At cold conditions, fluid density is higher, so more mass is moved so more work is done and more amperage drawn. (0.5) .

l

c. It must accelerate more mass, which requires more work, and amps.(0,5)

OR The high starting current is caused by the lack of counter EMF, which will oppose normal current flow as it is created.

d. Operating at runout may cause pump damage / trip on overcurrent. (0.5)

REFERENCE EQB GENERIC RT & HTFF 191004K104 191004K107 ...(KA'S)

ANSWER 1.15 (2.00)

{

a. Increase (0.5) i

b. Decrease (0.5) I

c. Decrease (0.5) )

I

d. Increase (0.5) l I

REFERENCE l' Thermal Sciences, Lesson D-6, pgs 14-15 193008K105 ...(KA'S)

ANSWER 1.16 (1.50) I a) increase; (no answer) (+.25 ea response) b) (no ans); decrease c) increase; increase d) increase; increase REFERENCE EGB GENERIC RT & HTFF 039000A205 ...(KA'S)

9- PLeUI_DESir#J INri lin1NS_SaEEIY ND FMFRGENCY_SYSIEldS PAGE 25

' ANSWERS'-- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER- 2.01 (2.00)

- RCS hot leg

- PZR surge'line (or water ' ace)

- P2R steam space

- Containment building sump (0.5 each)

REFERENCE ANG Procedure 2104.15, Post Accident Sampilng System, Rev 3, pg 1 002000SG13 ...(KA'S)

' ANSWER 2.02 (2.00)

- 480 VAC (0.5) to inverter is normal preferred supply (0.17) 125 VDC (0.5) is the normal backup supply (0.17)

- 480 VAC from a different supply (0.5) is the al ternate supply (0.16)

REFERENCE ANO2 Lesson Plan AA-52002-007, Electrical Distribution, Rev 2, pg 25 062000K103 063000K102 ...(KA'S)

ANSWER 2.03 (2.50)

a. EFAS present (0.5) and Emergency Feedwater Pump suction is (5 psig (0.5).

b. Normal - Condensate Storage Tank OR CST and S/U & BLWDN DI EFF (0.5)

Alternate - Service Water (0.5)

c. Once adequate level has been restored in the steam generator (s),

The EFAS signal will close the EFP's discharge valves (0.5).

REFERENCE ANO2 Lesson Plan AA-42002-021, Emergency Feedwater System, Rev 1, pgs 2-4, 16 061000K101 061000K401 ...(KA'S)

m.

I ?,2 PI MJT DES 1Gti INCLUD1blG_SeEFTY MJD_EMERGEblCY_SYSIEMS PAGE 26 ANSWERS -- ARKANSAS NUCLEAR ONE -87/08/04-MCCRORY, S.

ANSWER 2.04; (2.00)

L 'a. Bypass valves in AUTO (0.5)-

l Atmospheric dump-valves in OFF'(0.5)

b. Control Room (2C-02)

Remote-Shutdown Panel-(2C-80)

.SDBCS Panel l

(0.33'each).

REFERENCE

.AND Procedure 2105.08, Steam Dump and Bypass Control System Operations, Rov 3, pg 2, 3 041000SG9 ...(KA'S) i ANSWER' '2:.05 (1.50) 1

' Anti-Rotational Device - helps reduce loop backflow-in idle loop (improves total core flow with one RCP secured) (0.5)

- reduces pump starting current by preventing backward rotation (0.5)

-Flywheel - improves coastdown time (0.5)

' REFERENCE ANO 2 STM-2-03, LP. AA-52002-001-3H ',

003000K405 003000K410 003000K502 003000K608 ...(KA'S) l, ANSWER 2.06' (1.00)

If a' component is automatically actuated, it may be overridden by placing l the control handswitch in pull - to - lock for pumps (0.5) or by cycling the handswitch to the actuated position and then.to the desired position for' valves (0.5).

. REFERENCE' ANO 2~0P2104.39 LP AA-52002-004-15A 006000K409 006000K603 ...(KA'S) 1 l

.l l

i

__a__w_----.-___--n __..-wuu_ -

LEl ANT _DESILbLINCLUD1blD_SeEEIY_etJD_EMERSC.NCY_SYSIEMS PAGE 27 ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 2.07 (1.50)

-a. F

b. F

c. T REFERENCE ANO 2 STM-2-32, LP AA-52002-007-8A 191008K104 191008K109 ...<KA'S)  ;

-ANSWER 2,08 (2.00)

a. SIAS (0.5)

Under voltage condition (on 2A or 28 buses) (0.5)

b. 1. Diesel at or near rated speed (>810 rpm)

2. Generator near rated voltage (>3744 volts)

3. No 2A3/4 lockout

4. Generator output breaker remote controller NOT in pull-to-lock.

5. Affected bus tie breaker open

6. Affected bus feeder breaker open

7. Bus undervoltage (any 5 at 0.2 ea)

REFERENCE ANO 2 STM-2-31, LP AA-52002-016-2A 013000K112 064000K101 ...(KA'S)

I l

ANSWER 2.09 (2.00)

]

1. cannot be operated if bridge or trolley drive are energized. ]

2. "UP" limit switch j

3. hoist overload j

4. grapple in upper grapple operate zone and is not closed. l

5. down motioti inhibited if under loaded {

6. down motion inhibited if sl ack cable condition exists. )

7. Simultaneous bridge / trolley movement prohibited if the hoist is in l operation or operated since bridge movement. l

8. Operate in slow speed while assembl y is in core. 1 l

(any 5 at 0.4 ea) i i

I l REFERENCE l AND 2 OP 2503.03, LP AA-52002-026-3A ,

034000K401 034000K402 ...(KA'S) l l

l E_ - - - - - - _ - - - - - - - - - - - -

A _El_ ANT D F R 1 GbLINEL11 DING _SeEEIY_eUD_ EMERGENCY _SYSIEMS PAGE 28 ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 2.10 (2.00)

1. ACW supply -

close

2. SFP supply - close

3. CCW supply - close

4. ESF header supply - open

5. ACW return (cooling tower makeup) - close

6. ECP return - open (0.333 ea)

REFERENCE ANO 2 STM-2-42,- LP 'AA-52002-027-4A 076000K116 076000K403 ...(KA'S)

ANSWER 2.11 (1.50)

Ten (10) seconds (0.25)after the C pump discharge pressure goes (88 psig (0.25), the B pump crossover valves open (0,5) and the B pump starts (0.5),

supplying loop II .

REFERENCE ANO 2 STM-2-43, LP AA-52002-030-3G 008000A201 ...(KA'S) i ANSWER 2.12 (2.00)

c. f

b. t C. t

d. f (0.5 EACH)

REFERENCE ANO 2 STM-2-47 072000K204 086000K403 086000K404 ...(KA'S) 1 1

l c _. - . _ _ _ _ ___- _____-_ -__-_- - - - _ _ _ _ - _ _ _ - -

. 1

' 2 __EletJI_DESIGbl_1blCLUD1blG_SaEEILetJD_Et1ERGEblCLSYSIEtdS PAGE 29-ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S. l l

l i

l i

ANSWER 2.13 (1.00) i l

a. 1. fouling of.the air dryers l

2. damage.to valve operators j

3. explosion / fire J (any 2 at 0.25 ea) j

b. f

( . REFERENCE ANO 2 STM-2-48 1 078000K402 078000SG7 ...(KA'S)

ANSWER 2.14 (2.00) 4 j

a. 1. no indication

2. Increased level in SIT (1/2 credit for increased pressure only).

3. increased pressure indication from the detector between the check valves (0.5 ea)

6. .The max pressure will be 700 psig (0.25) because of a relief valve on the top of the SIT (0.25). (The valve is capable of handling max pressurization rate.)

REFERENCE ANO 2 STM-2-05 006000K103 006000K109 ...(KA'S) i i

l i

i 1

i i

l I

, i 1 i 1 1 1

t l I l i L__-- 1

$__1USIRIIMmTS_AND_CDNIEDLS PAGE 30' ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 3.01 (3.00) c.. 1. Tave low & Reactor tripped [0.25 ea.3 (0.5)

2. o Rx. tri p bl ocks 2. upstream and 1 downstream atmospheric dump valves. [0.53 o Rx. trip and low Tave blocks remaining valves. [0.253 (0.75)

3. Prevent excessive cooling of the RCS. (0.75)

b. 1. Shuts these valves to eliminate possible rupture. flow path.(0.5)  !

2. Provide condenser (turbine) protection. (0.5)

-REFERENCE AA-52002-011, Pp . 5-7 -

-041000G007 ...(KA'S)  :

1 ANSWER 3.02 (1.00)

B.

REFERENCE AA-52002-015, P.5 059000K418 ...(KA'S) l s

ANSWER 3.03 (1.00)

6. or d.

REFERENCE AA-52002-15, Pp . 5, 6 ,

059000K418 ...(KA'S) 1 1

i

b_INSIRl)MNS AND CDtIERDLS PAGE 31 ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 3.04 (2.50)

c. Each trip channel has provisions for bypassing [0.253 and is interlocked so only one channel may be bypassed at any time. [0.253 A channel that is already bypassed may be placed in the tripped condition to allow bypassing a second channel for testing or maintenance.and preserve allowable trip logic. [0.53 (1.0)

6. EFAS [0.53, the valve logic is not latched so that valves may be closed when level is returned to setpoint. [0.253 (0.75)

c. SIAS, CSAS, CCAS, and Reactor trip (0.1875 ea.) (0.75)

REFERENCE AA-52002-13, Pp . 5, 7, 12 013000K404 013000K408 013000K415 ...(KA'S)

ANSWER 3.05 (2.00)

Any of the LTOP i sol at i on val ves:

1. Closed during heatup with temperature < 275 deg. F.

2. Open during heatup or normal ops. with temp. > 280 deg. F.

3. Open dur i ng cool down wi th temp. > 275 deg. F.

4. Closed during cooldown with temp. < 270 deg. F.

[0.25 for each condition and position, 0.25 for ea. temperature] (2.0)

REFERENCE ANO2 PROCEDURE 2203.12J, P.18 010000G008 010000K403 ...(KA'S) l 1

l 1

l l

- __ __ A

S_ SIRLt1ENIS_etlD_COblIROLS PAGE 32 ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

l' l-ANSWER 3.06 (3.00)

a. Flux indication would increase [G.53 due to decreased vessel /downcomer level'[0.253.resulting in higher leakage-to the detectors.[0.253(1.0)

b. The alarm'setpoint automatically decreases as actual flux level

, decreases..[0.253 When actual flux level is increasing, a manual alarm setpoint reset pushbutton is used. [0.53 (0.75) c .- Turns on/off an indicating light. Accept "none" if detector

.changeout is' referenced. (0,5)-

1

d. 1. Loss of voltage.(high'or low)

2. Removal of c K t '. card.

3. Test switches not..in " Operate". [0.25 ea.] (0.75)

~ REFERENCE

'AA-52002-014, Pp . 9, 13, 14, 15 015000A302 015020A202 015020K502 ...(KA'S)

' ANSWER 3.07 (3.00)

a. . False

' b .' Fal se i

c. True d

'.-- False e .' -.True

d. Fal se REFERENCE AA-52002-12, Pp . 6, 13, 16 001000A407 001000G008 001000K105 001000K202 001000K401

...(KA'S)

ANSWER. 3.08 (1.00)

A.

l l

l J. IUSIEUdEUIS_eUD_fDUIRDLS PAGE 33

-ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

REFERENCE

'AA-52002-018, Pp . . 1, 3, 10 072000K601 073000K501 073000K601 ...(KA'S) i L

I ANSWER 3.09 (1.50) i

1. Containment cool i ng coil s.

2. Shutdown heat exchangers

3. Fuel pool heat exchanger. [0.5 each] (1.5)

REFERENCE AA-52002-018, P. 4 073000K101 ...(KA'S) i ANSWER 3.10 (2.50)

a. o CEA Positions o In-Core flux [0.25 ea.] (0.5)

6. Less than 15% power, Delta T power is used. [0.253 At greater than 15% power, COLSS automatically selects the higher of [0.253 Turbine power, [0.253 or secondary calorimetric power. [0.253 (1.0)

c. Thot, Tcold, RCP speed, RCP head, RCS press. [0.2 ea.] (1.0)

REFERENCE AA-52002-019, P. 3, Fig. 19.1 012000K608 ...(KA'S)

ANSWER 3.11 (1.00)

D.

REFERENCE AA-52002-024, P. 10 012000K607 ...(KA'S) l 1

1

l-L .M ItsSIRIiMFNTS_eblD_fDblIRDLS : PAGE 34 u ANSWERS--- ARKANSAS-NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

H.

/

l.

ANSWER 3.12 (1.00)'

'A.or D..

REFERENCE.

AA-52002-024, P' . 14 012000K603 012000K607 ...(KA'S)

. ANSWER 3.'13 (2.50)

a .- Trip'-- 2/4, Pre-trip logic -- 1/4 10.25 ea.] -(0.5)

b. 2/4 Pre-trips on [0.13 high pressurizer pressure (0.13, high LPD [0.13

, CEA dev [0,13, or low DNBR. [0.13 (0.5) 1;

- c .- High log power [0.2533 to al l ow. f or re ac tor st ar tup . [0.253

, CPC/CWP [0.263 as'CPC cannot perform the required calculations at low power. [0.253 OR prevent CPC trip j

-Pressurizer. pressure [0.253 so that the shutdown CEA's may be withdrawn at low temperature and pressure conditions. [0.253 RWT low level [0.25]to prevent inadvertent RAS when cooled down.[0.25]

(any 3 at 0.5 ea)

REFERENCE AA-52002-006, P. 7 STM 2-63, Pp , 11,'12 f

012000K603 012000K604 012000K610 ...(KA'S) j i

1 1

s i

j

)

l 4

_ _ _ _ _ _ ____ ___ _ _ _ d

$ __REDDEDilBES - NORMAL _eBNnR M FMFRAEblD.Y_eblD PAGE 35

. RADID1.DGICALCDblIRDL o LANSWERS -- ARKANSAS NUCLEAR DNE-2 -87/08/04-MCCRORY, S.

ANSWER 4.01 (1.00)

The heatup'.is only over a six minute-period (at 120 deg F/hr). The actual limit:Is 100 deg F (0.5),over any one hour period (0.5). Thus no 11mit was exceeded.

REFERENCE,

~ANO2, Technical Specification.3.4.9 002000SG5 ...(KA'S)

ANSWER '4.02 (1.00)

If the vibration alarm clears with the vibration reset pushbutton, then realarms.when-the pushbutton is released, the al arm is valid (1.0).

REFERENCE ANO AOP 2203.25, RCR Emergencies, Rev 1, pg 3 003000A101 ...(KA'S)

ANSWER 4.03 (3.00)

- Manually' trip the reactor (0.4)

- Secure letdown (0.3)

-.Open BAMT gravity feed valves (0.2) and close VCT outlet (0.2)

- Manually initiate EFAS (0.4)

- Trip MFW pumps (0.9)

- Shut MSIV's (0.0)

Trip: All four RCP handswitches (0.3) 2A1 to 2A3 tie breaker (0.3) 2A2 to 2A4 tie breaker (0.3)

OR Immediate actions from AOP 2203.30, Remote Shutdown REFERENCE

'ANO AOP 2203.14, Alternate Shutdown, Rev 2, pg 7 000068SG10- ...(KA'S)

g ,. - _- .-_ __

4.__.ERDEED11REE '- blDRMAI ,_eBblDRMAf FMFRAFNCY -etJD PAGE 36 "

SkDIDLDB1 ras enuTEDL y

ANSWERSl- EARKANSAS-NUCLEAR ONE-2 -87/08/04-MCCRORY, S.-

1 i

l i

4.04 'l

-44SWER (2.00)

a. A. rapid pressurizer level Increase while.depressurizing.(1.0).

b '. Increase' pressurizer pressure:by energizing the. heaters (0.5). An outsurge from the pressurizer,:or level decrease,1 will occur as the

. bubbl e coll apses (0.5) .

L REFERENCE ANO.AOP- 2203.13,- Natural' Ci rcul at i on Cool down , Rev 4, pg 2-3 000074EA20 - ...(KA's) lP

r. ANSWER 4.05- '

(1.50)

a. Verify at'least...one boron dilution monitor is operable (0,5) and leave'theftrip circuit breakers open (0.5) until the heatup is completed, y

b. 2-(0.5)

REFERENCE AND Procedure. 2102.02, Plant Startup, Rev 17, pg 9, 10

'001000K506 ...(KA'S)

ANSWER 4.06 (1.00)

Immediately initiate and continue boration at >/= 40 gpm of 1731 ppm boric acid solution or equivalent (emergency borate)'(0.5) until the required SDM is' restored (0.5).

REFERENCE ANO 2 TS 3.1.1.1, LP AA-52009-001-4D 000024. .301 ...(KA'S)

i L

! 4.__PEDCEDURFA - NnRMAf AAUDRMAI__ FMFRSFNrY AND PAGE 37 BaDIDLDBICAL CDUIEDL  :

ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 4.07 (1.50)

c. 4. Includes redist. effects

b. 3. MTC + FTC

c. -5. considers eq Sm worth

d. 6. should not be considered when Tavg < 525 deg F

e. 1. considers power defect

f. 2. incl udes S/D Pu239 bu il d up (0.25 ea)

REFERENCE ANO 2 2103.15, LP AA-52009-003-2A 3 001000K549 ...(KA'S) i l

ANSWER 4.08 (1.00) j Slow the power increase to 3% per hour (0.5) maintaining ASI at ESI +/- .05. (0.5)

REFERENCE ANO 2 2102.04, LP AA-52009-007-3N 001050A206 ...(KA'S)

ANSWER 4.09 (1.50)

a. Self-contained respirator (0.5) and a plastic suit (0.5) (to reduce skin absorption). f

b. Tritium emits weak beta radiation which area rad monitors will not detect. (0.5)

REFERENCE.

ANO 2 AA-52009-001 072000K501' ...(KA'S) l 1;

i l

i J

. 4.__BBDEEDUEFA - NORMAL,_eBNDRMAt FMFRAFNEY AND PAGE 38 EADIDLDDIDAL_CDLEEDL 1.

ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

1, 1

i ANSWER 4.10 (2.00)

REACTIVITY CONTROL ELECTRICAL POWER RCS PRESSURE CONTROL RCS INVENTORY CONTROL RCS HEAT REMOVAL'  !

CORE HEAT REMOVAL CONTAINMENT INTEGRITY (0.2 for each safety function, 0.1 for each priority shift.)

REFERENCE ANO 2 2202.01, LP AA-62002-0081I2 000007EA20 ...(KA'S)

' ANSWER 4.11 (1.00) '

two or more CEAs fail to insert (1.0)

REFERENCE AND 2 2202.01, LP AA-62002-008-1M2 000005EA20 ...(KA'S)

ANSWER 4.12 (1.00)

1. low or erratic SDC flow

2. unexplained increase in CET temperature

3. low or erratic SDC pump discharge pressure (0.333 ea)

REFERENCE 000025SG11 ...(KA'S)

ANSWER 4.13 (1.00)

1. S/G feed and steam (or f eed and bl owdown)

~2. RCS feed and bleed (0.5 ea)

REFERENCE ANO 2 2203.29, LP AA-62002-008-103 000074SG11 ...<KA'S)

A __BEDCEDUBES_ _NnpMal. AnwnBMAl FMFREEbJCY_ MO PAGE 39 BADIDLDDICAL CDbLTBDL

' ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 4.14 (1.50)

1. ECCS vent valve path

2. unisolate the LTOPs

3. open the reactor vessel & pzr high point vent valves (0.5 ea)

REFERENCE .

ANO 2 2202.01, LP AA-62002-008-1U3 l 000074 103 ...(KA'S) l ANSWER 4.15 (1.00)

FALSE i

REFERENCE ANO 2 2203.08 LP AA-62002-008-1W3 194001A116 ...(KA'S)

ANSWER 4.16 (3.00) candidate H1: rejected (0.25) since he has no history on file and will exceed 1.25 REM /QTR whole body exposure (0.5) candidate #2: rejected (0.25) since he will exceed the weekly limit of 300 mrem whole body without Rad Protection Supervisor's approval (0.5) candidate M3: rejected (0.25) since she will exceed 125 mrem per quarter whole body during the term of her pregnancy (0.5) candidate M4: accepted (0.25) since he will not exceed the admin limit of 300 mrem /wk (0.25) or the whole body limit of 1.25 REM /QTR

(.25)

REFERENCE ANO 2 1000.31 194001K103 ...(KA'S) l l

}

l

~ A__EEDEEDDBES_- NnRMAI ;_aBNDEMeL _ EMERGENCY AND PAGE 40

.BeDIDLDS1 Eat enNToni y ANSWERS -- ARKANSAS NUCLEAR ONE-2 -87/08/04-MCCRORY, S.

ANSWER 4.17 (1.00)

1. RCS PRESS / TEMP

2. RCS TEMP us. TIME

3. .P2R TEMP vs. TIME (0.333 ea)

REFERENCE AND 2 2102.02, LP AA-52001-007-2R 002000A103 002000K518 ...(KA'S) 1 i

l

t 's FACILITY LICENSEE REVIEW COMMENTS 1.05b Recommend deleting Part "b" REFERENCE - Reactor Theory Training Manual, Page 144 The question is not clear as to whether it is asking for SURs that would indicate that you have not yet gone into the heating range (in which Response 1 & 3 are correct), or SURs which indicate you have exceeded the point of adding heat (in which Respotise //2 is correct).

1.09A Also acceptable:

K2 : K1 /1 - AP(Kg)

= .85/1 - (.1)(.85)

= 0.93 (and other acceptable methods for adding AK/K to Keff)

REFERENCE - Reactor Theory Training Manual Chapter 14 We do not teach or use AK when performing calculations, AK is not used as a parameter for plant operations.

1.13b Add as an optional answer:

Rapid depressurization may cause a steam bubble to form in the RCS hot leg and/or S/G U-tube causing flow restrictions (increase loop resis-tance).

REFERENCE - Heat Trensfer, Thermodynamics & Fluids Handbook, Chapter 9 This response is the effect which was emphasized during the training program.

1.14c Another acceptable answer:

The high starting current is caused by the lack of counter EMF, which will oppose normal current flow as it is created.

REFERENCE - AA-52010-006 This answer is factual and has been covered during the training program.

ATTACHEMNT TO ANO-87-2-00885

o v

w 2.03B Change wording of " Normal" suction path to Startup and Blowdown DI Ef-fluent and/or Condensate Storage Tank.

REFERENCE - STM 2-19 EFW suction can be aligned to both or just the CST.

2.09 Split out Part 5 of answer, i.e.

down motion inhibited if under loaded down motion inhibited by cable slack REFERENCE - STM 2-51 The two interlocks are independent of each other.

3.03 Should accept "b" or "d". Bypass Feedwater Control Valve will position due to the 11% to 15% demand signal from its controller. 11% demand from the bypass valve controller will position the valve 11% open which corresponds to 5% flow demand. "d" should have specified " flow" demand.

REFERENCE - OP 2202.01, Rev. 3 This is how R0 verifies RTO in E0P Rx Trip Recovery Tab. The question does not specify which " demand" signal is being referred to. The bypass valve controller demand signal to the valve is 11% - 15% in RTO.

3.04c Add Rx Trip (RPS Actuation)

REFERENCE - STM 2-63 Rx Trip, CIAS, SIAS, CCAS, CSAS all actuated by Cont. Press Transmitters /

Loops.

3.12 The question specifically asks for only one response, therefore "a" or "d" should be acceptable, based on CPC Aux Trips listed in CPC/CEA Operations Procedure.

REFERENCE - OP 2105.01 ATTACHEMNT TO ANO-87-2-00885

p ..

t 0;

v 3.13b Answer'should read:

2/4 pre-trip logic on low DNBR, high LPD, High Pzr pressure, or when either CEAC detects a CEA deviation.

RFFERENCE - OP 2105.01 CPC/CEAC software modification 3.13c Other acceptable answers should be:

S/G high/ low trip bypass - to disable trips below 200 F to allow cocked rod protection AND.

RWT low level bypass (enabled off same handswitch as low pressurizer pressure bypass) to prevent inadvertent RAS when cooled down.

Also the WHY on CPC/CWP Bypass should include bypassing on shutdown to prevent CPC trip.

REFERENCE - STN 2-63 There operating bypasses are used along with the ones stated on key.

4.03 Should accept immediate actions from either the remote shutdown AOP 2203.30, Rev. 1 or the Alternate Shutdown A0P 2203.14, Rev. 2 REFERENCE - 2203.30, 2203.14 Either procedure addresses a Control Room evacuation based on different situations.

I ATTACHEMNT TO ANO-87-2-00885

7n ,[

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e dj i - ., ,

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i

-j Candidate //3: change ".. 125 mrem whole body..." to read ".. 125 mrem ,

per quarter whole body..." ,

REFERENCE - ANO 1000.31 Paragraph 6.2.2.E ANO Administrative Control Limit for Pregnant Women j reads: .'

The exposure limits for the fecus and therefore, the expectant mother is 125 mrem per quarter. I J

l 1

I l<

l 1

l l

l 1

ATTACHEMNT TO ANO-87-2-00885 I l

1

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