ML20137Z997

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Exam Rept 50-313/OL 85-03 of Retake Exam Administered on 850905.Exam Results:Candidate Successfully Completed Written Exam & Issued Appropriate License
ML20137Z997
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 09/25/1985
From: Cooley R, Pellet J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20137Z977 List:
References
50-313-OL-85-03, 50-313-OL-85-3, NUDOCS 8510080419
Download: ML20137Z997 (37)
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4 OPERATOR LICENSE EXAMINATION REPORT No. 50-313/0L 35-03 Licensee: Arkansas Power & Light P. O. Box 551

' ittle Rock, Arkansas 72203 Docket: 50-313 License No.: DPR-51 Operator License examination at Arkansas Nuclear One - Unit 1 (AN01)

Chief Examiner: eh Join L. Pellet, Examiner

@05-BT Date Signed

~

Approved by: hCb MAS' S e R. A. Cooley, Section Chief 9-35-65 Date Signed 4

Summary A single written retake examination (oral examination waived) was administered by NRC site personnel at the AN01 facility on September 5, 1985. The Senior Reactor Operator candidate successfully completed the written examination and lias beer, issued the appropriate license.

8510000419 851001 PDR ADOCK 05000313 G PDR

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Report Details

1. Persons Examined SR0 Candidates:

PASS FAIL TOTAL 1 0 1

2. Examiners J. Pellet, NRC (Chief Examiner)

(Administered and proctored by NRC site personnel)

3. Examination Report Individual performance results are not included in this report because these reports are placed in NRC's Public Document Room.

A. Examination Review Comment Resolution In general, editorial comments or changes made during the exam, the exam review, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made in AP&L letter AN0-85-ll781, dated September 9, 1985. The modifications discussed below are included in the master exam key which is provided elsewhere in this report, as are all other changes mentioned above but not discussed herein.

1. 5.02c Answer should read Beta effective gets smaller.

Resp.: ACCEPT. Key modified.

2. 5.05b Prompt neutron lifetime is 10EE-5 not 10EE-4 seconds.

Resp.: ACCEPT. Key modified.

3. 6.02 Answer key drawing is wrong per STM-1-32, Figure 32.33. No diode on rectifier output, no static switch shown, no manual switch shown.

Resp.: ACCEPT. Key modified.

4. 6.03 Answer not found in reference supplied. Based on outdated design information.

, Resp.: ACCEPT. For future reference.

5. 6.04 Answer key should read " coils" not " coolers."

Resp.: ACCEPT. Key modified.

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6. 6.05 Constant speed mode is labeled MANUAL on control switch. Auto Start-Stop mode is labeled AUT0.

Resp.: ACCEPT. Key modified to accept alternate designations if description accurate.

7. 6.08g Answer should be N0 not YES per reference.

Resp.: ACCEPT. Key modified.

8. 6.09a Accept also RB pressure = 4 psig. Reference table is 4.13 NOT 4.14.

Resp.: ACCEPT. Key modified.

9. 6.10 Answer 7 is normally bypassed. Answer 9 may be referred to as " preferred trip."

Resp.: REJECT. " Preferred" is not a parameter

10. 6.11b Answers should include 1" H 2O crankcase press.

Resp.: ACCEPT. Key modified.

11. 6.12 Reference should be STM 64, Table 64.1.

Resp.: ACCEPT. Key modified.

12. 7.05 Cat. I RWP's time period not to exceed 90 days.

Resp.: ACCEPT. Key modified.

13. 7.07 Proper reference is 1203.29. Copies of duty sheets will be at location of first action, answers given are correct.

Resp.: ACCEPT. Key modified.

14. 7.08 Answer 4 should read "0TSG level LT 15" or GT 375" (95% on operating range).

Resp.: ACCEPT. Key modified.

15. 7.11 Cold "J" leg = Cold leg pump elevation and 95%

operating range = 375" 0TSG level.

Resp.: ACCEPT. Key modified.

16. 8.04 TS 4.0 is stated as Nuclear Flux Channel but Ops uses N.I. cal., a slightly different term.

Resp.: ACCEPT. Current key acceptable.

17. 8.08 Key left off several items such as performance tests, rad. releases, operating evolutions, comm.

checks, and leak rate.

Resp.: REJECT. Areas listed are specifically excluded by the question.

19. 8.10 Let the applicant know that one or more word or number may be used in each blank.

Resp.: ACCEPT. For future reference.

I

8. EXIT MEETING

SUMMARY

Since this examination was administered by NRC site personnel (Resident Inpsector), no exit meeting was held.

C. GENERIC COMMENTS No generic problems or weaknesses were identified during grading of the written examination.

D. EXAMINATION MASTER COPY (SRO QUESTIONS AND ANSWERS)

The SR0 examination master and answer key follows, including the formula and instruction sheets supplied during the examination.

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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _6BKANS63_NQQLE68_QNE:1__

REACTOR TYPE: _EWB:Q&W1ZZ______________

DATE ADMINISTERED: _QElQ92Q5________________

EXAMINER: _EELLEIz_Jz______________

APPLICANT: _________________________

INSIBUDIIQUS_IQ_aEELIQaNIl Use separate paper for the answers. Write answers on one side only.

Stcple 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 least 80%. Examination papers will be picked up six (6) hours after the examination starts.

% OF CATEGORY  % OF APPLICANT'S CATEGORY

__V6LVE_ _IQI6L ___SQQBE___ _VaLUE__ ______________Q61EGQBX

_25tDQ__ _25AQQ ___________ ________ S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS

_25AQQ__ _2510Q ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION

_25tQQ__ _25 1QQ ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL

_25100__ _25tQQ ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 1DQtDQ__ 1DQzQQ ___________ ________ TOTALS FINAL GRADE _________________%

All work done on this examination is my own. I have neither given nor received aid.

APPLICAUTI5~55GUIiUR5~~~~~~~~~~~~~~

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Sz__IBEQBl_9E_NQQLE68_EQWEB_EL6NI_QEEB611QN t _E(ylQSt_6NQ PAGE 2 IBEBdOQ1uablGS QUESTION 5.01 (3.00)

During a reactor startup, with the reactor critical at 10EE-08 amps, an atmospheric dump valve fails open with the isolation valve open.

a. Explain what happens to reactor power and Tave. (Assume the reactor is at MOL and no reactor trip occurs.) (1.0)
b. Explain any changes that would occur in plant response if the transient occurred at EOL conditions. (1.0)
c. Explain how plant response would differ if the valve stuck open with the reactor subcritical at 1000 cps. (1.0)

QUESTION 5.02 (2.00)

a. True or False? After a reactor scram, the reactor will reach a stable negative startup rate of about 0.33 dpm (80 sec. period). (0.5)
b. How does the change in Beta-effective over core life affect the STABLE reactor period after a reactor trip? (0.5)
c. How does Beta-effective change over core life? (0.5)
d. How does the change in Beta-effective over core life affect the TRANSIENT reactor period after a reactor trip (before reaching a stable period)? (0.5)

QUESTION 5.03 (2.00)

What are two (2) functions of installed neutron sources?

QUESTION 5.04 (2.00)

a. HOW does equilibrium Xenon reactivity (Xe-eq) at hot full power change as a function of core age (EFPD)? (0.5)
b. WHY does Xe-eq change as a function of core age (EFPD)? (1.5)

QUESTION 5.05 (3.00)

c. What is the minimum reactivity that must be added to a critical reactor for it to be prompt critical? (1.0)
b. How much (by what factor) would power increase in one second at AN01 if it were prompt critical? (2.0)

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

. , _ _ . - _ _ _ - . _ - _ - . . - - - - __ - _ _ , , _ - . - . - - - = . - ._ . . _ - ,

Sz__IBEQBl_QE_UMCLEaB_EQWEB_ELaNI_QEEBoI1QUt_ELMlQSt_aNQ PAGE 3 IBEBdQQ10ad1CS QUESTION 5.06 (2.00)

a. TRUE or FALSE? The AN01 reactor is always operated with an under-moderated core. (0.5)
b. What observable plant behavior supports your answer to part (a)? (1.5)

QUESTION 5.07 (1.00)

When loading fuel into the core, should fuel be 1)aded toward the detector or away from it? EXPLAIN.

QUESTION 5.08 (1.50)

Why is EFW more efficient in establishing natural circulation than MFW?

QUESTION 5.09 (2.50)

If a main steam safety valve leaks at high power, how will the steam parameters below change across the leak? No explanation is required.

c. Enthalpy.
b. Entropy.
c. Pressure.
d. Temperature.
e. Density.

QUESTION 5.10 (2.00)

TRUE or FALSE 7 No explanation required.

c. For a centrifugal pump, maximum power is required at shutoff head.
b. For an axial flow pump, maximum power is required at shutoff head.
c. The point where NPSH(min) and NPSH(avail) curves meet is pump runout.
d. NPSH required increases as pump flow decreases.

1

(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)

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Sz__IHEQBl_DE_UUQLE6B_EQWEB_EL6NI_QEEB6I198t_ELVIRS&_80Q PAGE 4 IBEBdQQ1980101 QUESTION 5.11 (2.50)

o. What are four fuel pin changes due to aging that affect fuel temperature distribution? (1.0)
b. Do each of the changes in (a) increase or decrease fuel centerline temperature? (1.0)
c. Does overall fuel temperature increase or decrease with core age? (0.5)

QUESTION 5.12 (1.50)

TRUE or FALSE? No explanation required.

a. As condenser vacuum is increased (pressure decreased), more energy can be extracted from the steam.
b. The main condenser uses the conduction mode of heat transfer to rej ect heat to the circulating water system.
c. Increasing condensate depression will increase overall efficiency.

V 1

(***** END OF CATEGORY 05 *****)

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ht__EL8UI_SYSIEUS_ DES 106t_QQUIBQLt_8UQ_INSIBudEUISIIQN PAGE 5 QUESTION 6.01 (2.00)

a. What is the system accuracy limit (in inches) of the analog output group of the Rod Position Indicator Assembly reed switches? (0.5)
b. What are the other three (3) reed switch groups as described in STM-1-02? (1.5) l QUESTION 6.02 (3.00)

Sketch a simplified single line diagram of an ESF inverter. Show all inputs, outputs, and maj or internal blocks.

QUESTION 6.03 (1.50)

Why is one Circulating Water Pump capable of being supplied by a vital bus?

QUESTION 6.04 (2.50)

MATCHING. Match each of the components listed with the system which ,

supplies it cooling water. Each system may be used more than once.

COMPONENTS SYSTEM

___ a. Decay Heat Coolers. 1. Service Water

___ b. Control Room Chillers. 2. Auxiliary Cooling Water

___ c. Isophase Bus Coolers. 3. Intermediate Cooling Water

___ d. Exciter Air Coolers

e. Letdown Coolers.

^(( f.

Emergency Diesel Generator Jacket Heat Exchangers.

Reactor Building Cooling Coils.

___ g.

___ h. Instrument Air Compressor Aftercoolers.

___ i. Control Rod Drive Cooling Coils.

___ j. Generator Hydrogen Coolers.

QUESTION 6.05 (2.00)

a. Describe the two (2) operating modes of the instrument air system.(1.0)
b. Which is the normal mode and when is the other mode used? (1.0)

(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

y 4

! ht__ELeNI_1111Edi_DE110Nt_QQNIBQLt_eNQ_INSIBudENIeIIQN PAGE 6 i 3

. QUESTION 6.06 (l~.00) j  ; Describe'the plant condition (s) where the two (2) types of rod position indication can be expected to disagree. (1.0) f I -QUESTION 6.07~ (1.00)

' 'What locations in the Reactor' Coolant System are monitored for vibration or loose parts?

., QUESTION 6.08 (3.00)

State whe'ther the Reactor Coolant Pump STARTING interlocks listed below are satisfied by the values given (i.e.,-will the value given satisfy the

-interlock such that a start is permitted)?

.a.. Reactor power at 25%.

b. RCP seal inj ection flow at 3.5 gpm.

^

c. RCP motor ICW cooling flow at 300 gpm.
d. RCP' pump seal cooling ICW flow at 35 gpm.
e. RCP motor upper bearing oil. reservoir level at 11 inches.
f. RCP HP oil lift pressure at 1570 psig.
g. RCP reverst rotation at 15 gpm return oil flow.

! h. RCP motor lower bearing oil reservoir level at 8 inches, i.- RCS temperature at 475 degrees F with 3 RCP's running (start 4th).

QUESTION 6.09 (3.00)

n. List the signalsa with setpoints, which will initiate Hig'. Pressure Inj ect ion (ES actuation channels 1 and 2). (1.0)
b. On the attached Figure 4.9, circle all components.which receive a signal from ES actuation channels 1 or 2. Remove Figure 4.9 and place it with your answer pages. (2.0)

QUESTION 6.10 (2.00)

List five (5) plant or equipment parameters which are monitored by the Main Feedwater Pump trip system. Do NOT include manual pushbuttons.

Setpoints are NOT required.

i n

. (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)

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ht__ELaNI_SYSIEUS_DE110Nt_GQUIBQLt_aND_INSIBRUENIal10B PAGE 7 QUESTION 6.11 (2.00)

n. List two (2) Emergency Diesel Generator relay protection parameters NOT including engine trip. (1.0)
b. List two (2) Emergency Diesel Generator engine trips, including setpoints. Do NOT use emergency stop as an answer. (1.0)

QUESTION 6.12 (2.00)

[

Complete the blanks in the table below dealing with ICS runbacks.

CAUSE MAX. LOAD LIMIT RATE LIMIT I

Low RC Flow Proportional to RC Flow (a.) l Loss of 1 RCP (b.) 50%/ min. i Loss of 1 RCP in (c.) 50%/ min.

Each Loop Loss of 1 FW Pump {

(d.) 50%/ min. i

, Loss of 2 Condensate (e.) 50%/ min.

f Pumps Assymetric Rod Condition 40% (f.)

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{

+

(***** END OF CATEGORY 06 *****)

-Zi__EBQQEQuBES_ _NQBdokt_8BNQBd8Lt_EMEBGENQ1_6NQ PAGE 8 88010LQQ1Q6L_QQUIBQL QUESTION 7.01 (1.00)

a. . What is the maximum short-term steady power level permitted by procedure 1102.04, " Power Operations"? (0.5) b '. What is the maximum average steady power over an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, per.the-same procedure? (0.5)

QUESTION 7.02 (1.50)

Fill in the blanks in the following sentence dealing with ESAS override.

Each blank may contain one or more words or phrases.

Operators shall not override automatic actions at ESAS features, unless directed by,___(a)___ or ___(b)___.

l QUESTION '7.03 (2.00)

What are two (2) diverse (different) symptoms of a Steam Generator-Tube Rupture per 1202.01, " Emergency Operating Procedure"?

QUESTION 7.04 (1.00)

Why is the following statement FALSE?

Protective actions which violate a technical sp'ecification LCO or are contrary to procedures are permitted in emergency circumstances per 10CFR50.54(X) if notification is made prior to taking the action.

Q'UESTION 7.05 (1.00)

~

What 4 is the. maximum allowable period for each of the RWP classes or categories ~ listed below?

a.- Category I.

b.. Category II.

c. Category III.

d.. ~ Standing.

i

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

Z1__EBQQEQUBES_:_NQBd6Lt_6HNQBd6Lt_EMEBGENQ1_6NQ PAGE 9 88Q10LQQ10aL_QQNIBQL QUESTION 7.06 (3.50)

An irradiated component measuring 2"x 2"x 2" is surveyed with a portable instrument. At a distance of 2 feet, the open window reading is 2.65 Rem /hr and the closed window reading is 1.75 Rem /hr. SHOW ALL WORK!

o. What is the beta dose rate? (0.5)
b. How long could you remain at the survey distance without exceeding AN01 weekly and quarterly limits (2 answers req'd per 1622.011)? (1.0)
c. Who {by j ob title (s)} must approve exceeding the weekly control limit? (1.0)
d. What would the WHOLE BODY dose rate be if you moved back to a distance 10 ft. from the component ? (1.0)

QUESTION 7.07 (2.00)

Where can each of the operators listed below find his written instructions during a remote shutdown? (2.0)

a. Auxiliary Operator,
b. Ass ist ant Plant Operator,
c. Plant Operator, and
d. Waste Control Operator.

QUESTION 7.08 (3.00)

List five (5) of the seven (7) entry conditions or symptoms given in OP 1202.01 that require the operator to manually trip the reactor.

QUESTION 7.09 (3.00)

What are the four (4) indications of natural circulation as stated in the Emergency Operating Procedures?

(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)

. -. -. - _~ -_ ., .__ -_- - . - .

Zz__BBQGEQuBES_=_UQBd8Lt_8ENQBM8Lt_EUEBGEUQ1_8NQ PAGE 10 86010LQQ198L_GQUIBQL QUESTION 7.10 (2.50)

Fill in the blanks below dealing with cooldown rates per OP 1102.10.

c. _____ F/hr down to _____ F.

, _____ F/hr down to _____ F.

_____ F/hr below _____ F

b. Maximum pressurizer cooldown rate is _____ F/hr.
c. Maximum step change of _____ F is allowed when removing all RCP's from operation with the decay heat system operating.

Step' Change = _____

QUESTION 7.11 (2.50)

e. When using-the reflux boiling method of cooling'during post accident conditions, at what level is OTSG inventory maintained? (1.0)
b. Why is this necessary? (1.5)

QUESTION 7.12 (2.00)

'Using the data presented below, explain if either a PROCEDURE or TECHNICAL SPECIFICATION heatup rate limit has been exceeded.

TIME (minutes) RCS TEMPERATURE (degrees F) 0 300 15' 320 25 330 40 350 65 390 90 440 100 450

(***** END OF CATEGORY 07 *****)

at__8DdINISIBoIIVE_EBQQEQUBESt_GQUQ1110NSt_eUQ_L1dIIeI1QNH PAGE 11 QUESTION 8.01 (2.00)

What are two (2) of the three (3) requirements which are imposed by

. Technical Specifications for making temporary procedure changes?

QUESTION 8.02 (2.00)

What are the AN01 Technical Specification leakage limits below?

a. Total identified (non-returnable) leakage,
b. Unidentified leakage.
c. Leaka'ge through any unisolable strength boundary (except OTSG tubes).
d. Returnable leakage.

QUESTION 8.03 (2.00)

a. What percentage of the heat / smoke detectors must be operable per Technical Specifications in areas where they are required? (0.5)
b. What must the shift supervisor do if the required minimum number / percentage is not operable? (1.0)
c. How long is the time period to complete the action in (b)? (0.5)

QUESTION 8.04 (2.00)

.What are the two (2) calibration intervals required by Technical Specifications for the power range detectors and under what plant conditions does each apply?

QUESTION 8.05 (3.00)

What are the three (3) containment building isolation requirements imposed by Technical Specifications during handling of irradiated fuel?

QUESTION 8.06 (3.00)

Per Technical Specifications, .under what conditions is reactor building 3 integrity required to be maintained?

(***** CATEGORY 08 CONTINUED ON NdXT PAGE *****)

gt__6QUINiglB6IlyE_PBQQEQUBE$t_QQNQlllQNSt _6NQ_Lldll611QN3 PAGE 12 QUESTION 8.07 (3.00)

What are the four (4) cases where the Shift Supervisor is given specific cuthority to order a plant shutdown per OP 1015.01?

QUESTION 8.08 (1.00)

What are three (3) operating occurrences relating to plant equipment (not personnel, surveillance, or maintenance related) that should be recorded in the station log per OP 1015.01, " Conduct of Operations".

QUESTION 8.09 (1.50)

a. Per Technical Specification 3.0, on general Limiting Conditions for Operation (LCO), what action must be taken if an LCO is not met? -(1.0)
b. What is the minimum time permitted for this action? (0.5)

QUESTION 8.10 (2.00)

Fill in the blanks in the following statements relating to minimum crew composition per Technical Specifications.

o. At least ____ shall be in the control room when fuel is in the reactor.
b. At least ____ shall be in the control room during reactor startup.
c. At least ____ shall be onsite when fuel is in the reactor.
d. At least ____ with fire protection training shall be maintained at all times.

QUESTION 8.11 (2.50)

TRUE or FALSE? No explanation required.

a. The four Emergency Action Levels are: Notification of Unusual Event, Alert, Site Area Emergency, and General Emergency.
b. Activation of the Emergency Plan supersedes all non-emergency plant procedures,
c. In the event of an emergency, the Shift Operations Supervisor of the affected unit assumes the responsibilties of the DEC.
d. The Shift Administrative Assistant must perform all notifications. i
e. Receipt by an indiviual of a radiation dose greater than 10 R requires compliance with 1903.23, " Personnel Emergency".

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(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)

. l at__8Dd1NISIBoIIVE_EBQQEQUBEnt_GQNQ1119NSt_eUQ_L1511ellQU$ PAGE 13 l

1 QUESTION 8.12 (1.00)

List two groups which are specifically granted access-to the Control Room by OP 1015.01 during emergencies. Do NOT include shift operating personnel in your answer.

(***** END OF CATEGORY 08 *****)

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

.. IEtC 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. 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.

3. Use black ink or dark pencil only 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 new page, write on only olie side 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 three 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 comonly used in facility literature.
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.

1

14. Show all calcualtions, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE l.NY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
17. You must sign the statement on the cover sheet that indicates that the work is i

your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.

18. When you complete your examination, you shall:

l

a. Assemble your examination as follows:

! (1) Exam questions on top.

(2) Exam aids - figures, tables, etc. l (3) Answer pages including figures which are a part of the answer.

b. Turn in your copy of the examination and all pages used to answer the l l examination questions.  !
c. Turn in all scrap paper and the balance of the paper that you did not use l I

for answering the questions.

d. Leave the examination area, as defined by the examiner. If after leaving, l
you are found in this area while the examination is still in progress, your i i

license may be denied or revoked.

e. Do not dicuss the examination with other licensee staff personnel until the formal examination review is complete. .

l l l -

\

MtC LICENSE EXAMINATION HANDOUT A

EQUATIONS, CONSTANTS, AND CONVERSIONS 6 = n'i*Cp *deltaT 6=U*A*deltaT P = Po*10sur*(t) P = P *et /T SUR = 26/T T=1*/p+(p-p)/Xp T=1/(p-p) T=(p-p)/Ep f * (Keff-1)/Keff = deltaKeff/Keff p=1*/(T*Keff)+Jeff/(1+%T)

> = ln2/tg = 0.693/tg E = 0.1 seconds-1

~

I = Io*e "**

CR = S/(1-Keff) 2 R/hr = 6*CE/d feet Water Parameters 1 gallon = 8.345 lbm ' = 3.87 liters 1 ft3 = 7.48 gallons Density 9 STP = 62.4 lbm/ft3 = 1 gm/cm3

Heat of vaporization = 970 Btu /lbm l Heat of fusion = 144 Btu /lbm 1 atmosphere = 14.7 psia = 29.9 inches Hg.

l Miscellaneous Conversions .

I curie = 3.7 x 1010 disintegrations per second 1 kilogram = 2.21 lbm

I horsepower = 2.54 x 103 Btu /hr l 1 mw = 3.41 x 106 Btu /hr 1 inch = 2.54 centimeters l

degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) 1 Btu = 778 ft-lbf I

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Sz__IBEQBl_QE_NVQLEoB_EQWEB_EL8NI_QEE8611QNt_ELylQ$t_68Q PAGE 14 IBEBUQQ1 nom 10S ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 5.01 (3.00)

o. High steam flow causes decr. Tave which inserts pos. react (0.333).

Power increases to POAH (0.333) where fuel or doppler turns power until demand = output (0.333).

b. Rate of power rise will be faster due to smaller beta and larger MTC (0.5). Final power will be the same but at higher temperature (0.5) due to larger MTC.
c. If the reactor is suberitical, reactivity added by the cooldown may be insufficient to reach criticality (0.5), so the plant would simply level out at a new subcritical count rate (0.5).

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Various chapters ANO HEAT TRANSFER THERMODYNAMICS AND FLUIDS HANDBOOK ANSWER 5.02 (2.00)

a. TRUE.
b. NONE.
c. Beta (eff) gets smaller,
d. Transient period shorter (due to faster response w/ smaller Beta).

(4 answers 0 0.5 ea.)

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Core Characteristics ANSWER 5.03 (2.00)

1) Provide a reliable source of neutrons during startup.
2) Indicate nuclear instrumentation is operating properly.
3) Frovide a visible change in nuclear instrumentation during approach to criticality.

(any 2/3 answers e 1.0 ea.)

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Subcritical Multiplication

Ez__lBEQBl_QE_NyGLE88_EQWEB_EL8NI_QEEB811QNt _ELylQSt_8NQ PAGE 15 IBEBdQQ18851Q1 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 5.04 (2.00)

s. Xe-eq gets larger as a function of core age. (0.5)
b. Xe-eq is a function of flux (not power) (0.75) and flux increases as a function of core age (0.75).

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Fission Product Poisons ANSWER 5.05 (3.00)

a. p>/= beta (0.005< beta (or -eff)<0.007) (1.0)
b. T=1-ster /p + (B-p)/tp (0.5) so for prompt critical neglect delayed term & T=1-ster /p (0.25) 1-star ~10EE-05 seconds (0.25) 0.005<p<0.0075 (0.25)

T~10EE-5/0/007~ .0014 seconds (0.25)

P/Po=eEEtime/T so power would increase ~eEE600~700 / 1 second (0.5)

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Transient Analysis ANSWER 5.06 (2.00) c ',' FALSE. (Sometimes operates overmoderated.)

b. During low power / temperature (0.5) high boron concentration (0.5) operation, alpha (MT]/the heatup coefficient may be positive (0.5).

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Reactivity Coefficients ANSWER 5.07 (1.00)

Fuel should be loaded away from the detector (0.333) so that the 1/M plot conservatively predicts criticality (0.667).

St__IBEQBl_QE_UUQLE68_EQWEB_EL6NI_QEE8611QNt_ELQlD$t_6NQ PAGE 16 IBEBdQQ18801QS ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

REFERENCE AN01 PLANT SPECIFIC REACTOR THEORY, Subcritical Multiplication.

ANSWER 5.08 (1.50)

EFW inj ects higher in the UTSG (0.5) which raises the cold leg thermal conter (0,5) and the thermal driving head (0.5).

REFERENCE AN01 ATOG GUIDELINES, Part II, Vol. 1, Chapter A ANSWER 5.09 (2.50)

e. Constant.
b. Increase.
c. Decrease.
d. Decrease.
e. Decrease.

(5 answers e 0.5 es.)

REFERENCE AN01 HEAT TRANSFER THERMODYNAMICS AND FLUIDS HANDBOOK ANSWER 5.10 (2.00)

a. False.
b. True,
c. False.
d. False.

(4 answers 0 0.5 es.)

REFERENCE AN01 THERMODYNAMICS HEAT TRANSFER AND FLUIDS HANDBOOK l

i i

Ez- IHEQBl_QE UUQLEaB EQWEB_ELoNI_QEEBaIIQUt_ELUIQSt 6NQ PAGE 17 IBEBdQQ1Nad101 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 5.11 (2.50)

a. -------------------------- ---b. ---

fuel densification Increase fuel thermal conductivity decrease Increase fuel pellet swell Decrease Gcp gas dilution Increase Clad creep Decrease

c. Decrease (c/b: any 4/5 0 0.25 es. part; c 0.5)

REFERENCE AN01 THERMODYNAMICS HEAT TRANSFER AND FLUIDS HANDBOOK ANSWER 5.12 (1.50)

c. True,
b. True.
c. False.

REFERENCE AN01 HEAT TRANSFER THERMODYNAMICS AND FLUIDS HAND 000K

1 6t__EL6NI_SYSIENS_QE$1QUt_QQUIBQLt_6NQ_INEIBQUEUI611QN PAGE 18 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

i ANSWER 6.01 (2.00)

a. 1.5 inches (0.5)
b. in-limit / 0%

out-limit / 100%

5 absolute / zone reference (3 answers e 0.5 ee.)

REFERENCE AN01 STM-1-02, p. 6 ANSWER 6.02 (3.00) 480 V AC (ESP) __ Input __ Bridge ______ Static __ Static __ 120 V AC Norm Sup. Xformer Rectifier I Invert. Switch Vital Bus (0.4) (0.1) (0.4) 1 (0.4) I \ (0.3)

I i \

125 V DC ____ Diode __I I \

Bat Bus (0.1) I (0.4)

(0.4) 1 480 V AC ____ 120 V AC __________________________________t Alt Sup. Xformer (0.4) (0.1)

REFERENCE AN01 STM-1-32, Figure 32.33 ANSWER 6.03 (1.50)

One cire water pump can be supplied by a vital bus to enable steam dumping during a loss of electrical (offsite?) power.

REFERENCE AN01 STM-1-40, p. 1 ANSWER 6.04 (2.50)

c. 1, b. 2, c. 3, d. 2, e. 3, f. 1, g. 1, h. 3, i. 3, J. 2 (10 answers 0 0.25 ea.)

REFERENCE AN01 STM-1-42, p. 1, 2

ht__EL8UI_SXSIEUS_ DESIGN t_QQUlBQLt_60Q_IN11BQUEN1611QU PAGE 19 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/OS-PELLET, J.

STM-1-43, p. 1, 2 ANSWER 6.05 (2.00)

1. Constant Speed (motor & comp run @ constant speed with comp load /

unloading controling hdr. press.). Accept switch label of MANUAL.

2. Automatic Stop-Start (motor stops and starts to control header press.).

Accept switch label of AUTOMATIC.

1 is the normal method and 2 is used when instrument air loads are light.

REFERENCE AN01 STM-1-48, p. 2, 3 ANSWER 6.06 (1.00)

They will disagree any time rod motion occurs without activation of the CROM motor, i.e., on a reactor scram. (1.0)

REFERENCE AN01 STM-1-02, p. 7, 8 ANSWER 6.07 (1.00)

Vibration is monitored in the RCS at: upper vessel, lower vessel, & ea. SG

-(3 answers at 0.333 ea.)

REFERENCE AN01 STM-1-03, p. 2 ANSWER 6.08 (3.00)

n. n, b. y, c. y, d. y, e. y, f. n, g. n, h. y, i. n (9 answers e 0.333 ea.)

REFERENCE AN01 STM-1-03, p. 8

r Ez__EL6NI_1111 EMS _gESigNt_CONIggLt_aug_INSIRgdENI611gg PAGE 20 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 6.09 (3.00)

a. RCS Pressure </= 1500 psig (0,5), RB Pressure >/=18.7 psia /4 psig (0.5)
b. P36A CV-1214 CV-1220 CV-1228 CV-1271 CV-1274 CV-1407 P368 CV-1216 CV-1221 CV-1234 CV-1272 CV-1300 CV-1408 P360 CV-1219 CV-1227 CV-1270 CV-1273 CV-1301 (20 answers e 0.1 ea.)

REFERENCE AN01 STM-1-04, Table 4.14, p. 1 ANSWER 6.10 (2.00)

1. Thrust bearing wear (forward & revers <3 = 2 answers if given).
2. Rotor vibration.
3. Turbine (over) speed.
4. Bearing oil pressure Clo).
5. FW pump disch. press. (hi).
6. FW pump suct. press. Clo).
7. FW pump flow (lo).
8. Exhaust vacuum (lo).
9. Main turbine (tripped).

(5/9 answers e 0.4 ea.)

REFERENCE AN01 STM-1-19, p. 5 ANSWER 6.11 (2.00)

a. 1. Hi generator differential / phase neutral vs. output current.
2. Electrical fault / hi current w/ voltage comparison.
3. Loss of field / excitation.
4. Motoring / reverse power.

(any 2/4 answers e 0.5 ea.)

b. 1. Overspeed e ~980 rpm.
2. Low oil pressure e 17 psi.
3. Crankcase pressure 8 1" H20.

(4/6 answers - para. x2 0 0.4 ea' setpoint x2 0 0.1 es.)

REFERENCE AN01 STM-1-31, p. 6

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bz.._EL6NI_SISIEUS_DESIGNt_GQNIBQLt_8NQ_INSIBudENI6I1QN PAGE 21 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -65/09/05-PELLET, J.

ANSWER 6.12 (2.00)

c. 20%/ minute, b. 75%, c. 45%, d. 40%, e. 40%, f. 30%/ minute (6 answers 8 0.333 ea.)

REFERENCE AN01 STM-1-64, Table 64.1

Z1__EBQ;gDVBEE_:_NQBd8L&_6BNQBuoLt_gegBQEug1_88Q PAGE 22 BoDIQLQQ10aL_QQUIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 7.01 (1. 00)

a. 102% of b or 2619.36 +/- 1 MWthermal (0.5)
b. 2568 MWthermal ' (0.5)

REFERENCE AN01 Power Operations, 1102.04, Rev. 15, p. 4 ANSWER 7.02 (1.50)

o. emergency procedure
b. shift supervisor (2 answers 8 0.75 ea.)

REFERENCE AN01 Engineered Safeguards Actuation System, 1105.03, p. 4 ANSWER 7.03 (2.00)

1. Increased RCS leakage.
2. Increased secondary radiation (steam line N-16 alarm & cond. vac. pump radiation alarm).

(2 answers 8 1.0 en.)

REFERENCE AN01 E0P, 1202.01, p. 3 ANSWER 7.04 (1.00)

Prior notification is required ONLY if time permits.

REFERENCE AN01 Alternate Shutdown AOP, 1203.02, p. 4

Zt__PBQQEQQBES_ _NQBd8Lt_8HNQBd8(t_EUEBQENC1_86Q PAGE 23 88Q10LQQ1Q8L_GQUIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 7.05 (1.00)

a. 14 days, b. job duration, c. job duration, d. 1 month (4 answers e 0.25 ea.)

REFERENCE AN01 1612.003, Radiological Work Permits, Rev. 5, p. 5 ANSWER 7.06 (3.50)

c. Beta dose rate = open - closed window = 0.9 Rem /hr (0.5)
b. Stay time: qtrly : 2.50 RC1mts)/1.75 R/hr = 1.5 hr = 85 minutes (0.5) weekly: 0.30 RC1mts)/1.75 R/hr = .17 hr = 10 minutes (0.5)

(Accept B-dose if explicitly stated WB if dose to eye.)

c. HP Supervisor (@ 100mr; HP Superintendent 0 600mr; & GM @ 1000mr) (1.0)
d. 1.75 x (2 ft.)^2 = Dose x (10 ft.)^2 Crelation w/ dist 0.7, math 0.3)

Dose = 1.75 x 4/ 100 = 0.07 Rem /hr.

REFERENCE AN01 1622.011, Rev. 4, p. 3 ANSWER 7.07 (2.00)

a. Stair rail to H2/N2 storage room (SU boiler room).
b. A-1/2, H-1/2, bus area.
c. Desey Panel.
d. MCC B61.

(4 answers e 0.5 ea.)

REFERENCE AN01 OP 1203.29 i

l

Zt__EBQQEQUBES_:_UQBMakt_aBUQBuaLt_EMEBGENQ1_8NQ PAGE 24 BaQ10LQGlQaL_QQN18QL ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 7.08 (3.00)

1. Reaching an RPS setpoint with no reactor trip.
2. Pressurizer level > 375".
3. MSLI actuation or MSIV C' closure.
4. OTSG 1evel < 15" or , 290" (90% on the operating range).
5. Any sys. degrad. where operator or TS say trip rx.
6. Pressurizer level < 100" w/ no indication it is being controlled
7. RB pressure > 3 psig.

(cny 5 0 0.6 ea.)

REFERENCE AN01 OP 1202.01 ANSWER 7.09 (3.00)

1. RC temperature (including incore TC's) decreasing.
2. RC hot-cold leg dT < SOF & decreasing (w/ decr. decay heat load).
3. Continued demand for EFW to maintain OTSG levels.
4. Continued demand for steam relief (BPV, MADV, or SV).

(4 answers e 0.75 ea.)

REFERENCE AN01 OP 1202.01 ANSWER 7.10 (2.50)

o. 100 to 280 50 to 150 25 below 150
b. 100
c. 75 RC temp - DH temp (10 ansers 0 0.25 ea.)

REFERENCE AN01 OP 1102.10

Zt__EBQQEQUBES_=_NQBdakt_688Q856Lt_EME8QEUQ1_6NQ PAGE 25 BaQ1QLQQ1 gal _QQUIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 7.11 (2.50)

a. >95% (375") on the operate range.
b. This is required so that condensed rx coolant in the OTSG maintains a level high enough to cause flow over the cold "J" leg (cold leg pump elevation) and into the core.

REFERENCE B&W Degraded Core Recognition & Mitigation, Lesson 5.

ANSWER 7.12 (2.00)

The nrocedural limit is 1.67 degrees per minute (0.5). This was violated bett an 65 ~ 90 minutes where the rate was 2 F/ min (0.5).

The tech spec limit is 100 degrees F in any one hour period (0.5). This was violated between ~30 to ~90 when heatup was ~105 F (0.5).

REFERENCE AN01 Plant Startup, 1102.02, Rev. 30, p. 9 AN01 Technical Specifications, 3.1.2, p. 18, 19, 20b

I

Hz__8QUINISIB811ME_PBQQEQUBEft_QQNQIllQNEt_68Q_LidlI611QNE PAGE 26 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 8.01 (2.00)

1) The intent of the procedure is not changed.
2) The change is approved by 2 members of plant staff, at least one of which is SRO-licensed.
3) The change is documented, reviewed by the PSC, and approved by the Plant Manager within 14 days.

(any 2/3 e 1.0 ea.)

REFERENCE AN01 TS 6.8.3 ANSWER 8.02 (2.00)

c. 10 gpm.
b. 1 gpm.
c. O gpm.
d. 30 gpm.

(4 answers e 0.5 ea.)

REFERENCE AN01 TS 3.1.6 ANSWER 8.03 (2.00)

a. 50%.
b. Establish a fire watch patrol (0.5) to check the area once per hour (0.5).
c. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

REFERENCE AN01 TS 3.5.5 ANSWER 8.04 (2.00)

1) Twice weekly during steady state operation.
2) Daily during non-steady state operation.

1 l

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Et__8QUINISIB611YE_EBQGEQUBESt_QQUQ1110NSt_eNQ_ Lid 11al10NS PAGE 27 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

REFERENCE AN01 TS 4.0 ANSWER 8.05 (3.00)

1) At least 1 door on the personnel hatch closed.
2) At least i door on the emergency hatch closed.
3) The equipment hatch in place with a minimum of 4 bolts securing it.

(3 answers 8 1.0 ea.)

REFERENCE AN01 TS 3.8.6 ANSWER 8.06 (3.00)

1) All of the following conditions are met:
1. RCS pressure > 300 psig. (0.5)
11. RCS temperature > 200 F. (0.5) 111. Nuclear fuel in the core. (0.5)
2) RCS open to the RB (0.75) & req'ments for refuel. S/D not met (0.75).

REFERENCE AN01 TS ANSWER 8.07 (3.00)

If continued operation would result in:

1) Immediate equipment damage.
2) Danger to station personnel.
3) Violation of operating license /TS/LCO.
4) Unnecessary automatic trip.

(4 answers 0 0.75 ea.)

REFERENCE AN01 OP 1015.01

o at__aQUINISIBoIIVE_EBQGEQUBESt_GQNQ1110N1t_aNQ_LIdlleI1QU1 PAGE 28 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, J.

ANSWER 8.08 (1.00)

1) Maj or plant evolutions.
2) Change of status of mjr pwr gen components.
3) " " "

" safety systems.

4) " maj or aux systems.
5) Operating trends that warrant observation.
6) Events which actuate sig. annunc.

(3/6 0 0.333 ea.)

REFERENCE AN01 OP 1015.01 ANSWER 8.09 (1.50)

c. Place the plant in an OPERATING CONDITION where the TS LCO does not apply.
b. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

REFERENCE AN01 TS 3.0.3 ANSWER 8.10 (2.00)

c. 1 licensed Operator.
b. 2 licensed Operators.
c. 1 individual qualified in rad. protect. procedures / SRO.
d. 5.

(4 answers e 0.5 ea.)

REFERENCE AN01 TS 6.2.2

o at__aQUINISIB611VE_EBQQEQUBESt_QQUQlI10NSt_6UQ_L1011aI1QU$ PAGE 29 ANSWERS -- ARKANSAS NUCLEAR ONE-1 -85/09/05-PELLET, 1 ANSWER 8.11 (2.50)

o. False.
b. False.
c. True,
d. False.
o. False.

REFERENCE AN01 1903.001, 1903.002, 1903.10, 1903.23 ANSWER 8.12 (1.00)

1) Line-of-command m9mt personnel.
2) NRC (Resident Inspector).
3) Support personnel specifically requested (for tech. support).

(any 2/3 answers 0 0.5 ea.)

REFERENCE AN01 OP 1015.01

-

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