Text

Exam Rept 50-313/OL-86-01 on 860415.Exam Results:Seven Reactor Operator Candidates,Two Reactor Operators & Five Senior Reactor Operators Passed Exams
	ML20206S368
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/26/1986
From:	Cooley R, Mccrory S; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20206S356	List: ML20206S352; ML20206S368;
References
	50-313-OL-86-01, 50-313-OL-86-1, NUDOCS 8607070340
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'6 ANO-1 EXAMINATION REPORT No. 50-313/0L-86-01 Docket No: 50-313 License No.: DPR-51 Licensee: Arkansas Power & Light P.O. Box 551 Little Rock, AR 72203 Examinations administered at Arkansas Nuclear One Unit 1 Chief Examiner: /

6 d

E,/LY McCrory, Lead Exam Qate /

Approved by:

4 2

R./A. Cooley, Section C Q6te /

Summary Examinations conducted on April 15, 1986.

Written and operating examinations were administered to eight (8) Reactor Operator License Candidates, four (4) licensed Reactor Operators, and seven (7)

Senior Reactor Operators.

Seven(7)ReactorOperatorCandidates,two(2)

Reactor Operators and five (5) Senior Reactor Operators passed these examinations.

8607070340 860702 l'-

PDR ADOCK 0500 3

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i Report Details 1.

Examination Results SR0 candidates R0 Candidates Total Pass Fail Total Pass Fail i

0 8

7 1

87 SR0 Requalification R0 Requalification Total Pass Fail Total Pass Fail 4

7 5

2 71 4

2 2

50 i

2.

Examiners

.,l S. L. McCrory, Chief Examiner J. Pellet j

R. Cooley W. Apley, PNL J. Huenefeld, PNL 3.

Examination Report 3

This Examination Report is compused of the sections listed below.

A.

Examination Review Comment Resolution B.

Exit Meeting Minutes C.

Generic Comments i

D.

Requalification Program Evaluation Report E.

AN01ExaminationKey(SR0/R0QuestionsandAnswers)

Performance results for individual examinees are not included in this report because examination reports are placed in the NRC Public Document Room as a matter of course.

Individual results may be retained in the NRC j

Region office during the period that the facility is evaluated as unsatisfactory but are not subject to public disclosure.

A.

Examination Review Comir.ent 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 4

1 J

3 resolution of substantive comments made during the examination review. The modifications discussed below 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. Attachment 1 is the facility comments on the examination. Unless otherwise indicated in this section, the facility comments were incorporated into the answer key.

COMMENTS (1) 1.03/ There is no instrumentation in the control room which 1.10/ provides indication of reactor power in percent power 1.06*/ below 1%. The questions give stated power levels as 5.06*

10 EE-03% and 10 EE-04%.

Examinees may interpret these indications to be 10 EE-3(4) amps which is considerably higher power than as stated in the question. Credit should be given if examinees make this assumption.

Resp.

REJECT. A satisfactory operator should be able to recognize that the stated power levels are 3 to 4 decades below the pawer range (1% and higher) and thereby realize that actual power is in the intermediate range.- The lack of control room instrumentation which indicates reactor power in percent power below the power range should have no bearing on an operator's ability to recognize which range power is in when expressed as % power.

(2) 1.04/ In part "c." of this question, the word " rapidly" may 1.02* alter the response to the question. Another acceptable answer should be:

Disagree - A rapid increase in steam flow rate could cause a decrease in RCS pressure that would allow voids to form inside the tubes of the OTSG, and temporarily block natural circulation flow.

Resp. Voids will not form in the hot legs or OTSG until the pressurizer has emptied and level is down to the hot leg nozzles. The examinee must state these conditions to receive full credit for the proposed answer.

(3) 2.01/

1.

Operators at ANO are not expected to memorize power 2.01*

supplies for other than important safety equipment.

2.

Operator consoles in AN01 are labeled to help operators identify power supplies for cyipment without reference to procedures or E-prints.

Efforts now underway will result in these labels being converted to permanent type plaques.

3.

The previous ANO Unit 2 R.0. license examination required only that license candidates identify

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4 (matching) the voltage of various busses based on letter designators.

Based on these three points, we feel full credit should be awarded if the examinees can identify the power source, voltage and current items a, g, and h and identify the voltage and current only for the remaining items.

Resp.

REJECT.

1.

NRC does not expect operators to memorize the power supplies to all electrical equipment either but NRC does expect a satisfactory operator to be familiar enough with electrical distribution to be able to identify power supplies to most of the types of equipment found in the question.

2.

The placement and use of operator aids can be very helpful until the operators begin to rely on them to the point that they cannot function satisfactorily if the aids are not available or are incorrect.

3.

NRC examination questions are not constrained in scope, complexity, or difficulty based on previous question structure for the same subject area.

(4) 4.09/ The unit 1 Emergency Operating Procedure, OP1202.01, is 4.05*

identified as having 4 specific types of information.

1.

Immediate Actions 2.

Follow-up Actions 3.

Entry Conditions 4.

Discussions For this reason, examinees may respond to this question by listing the four immediate actions.

If this is the case, we feel full credit should be awarded based on training received.

Resp.

REJECT.

If an operator mechanically responds to "immediate actions" by always going to the basic, overall imediate actions of OP1202.01, the operator is reacting incorrectly.

(5) 7.03 Work orders are now processed by SIMS, and a work order log is no longer kept in the control room.

Full credit should be given if Station Log, and Hold and Caution Card logs are included.

Resp.

REJECT. OP1102.02 requires that outstanding work orders be considered. Whether this is by a work order log, SIMS, or through the work control center is immaterial.

(6) 8.04 See Attachment 1 for discussion.

Resp. The remaining criteria for events which require one hour reporting may or may not develop conditions which require

5 EAL classification. Again, familiarity not memorization is adequate to respond to this question.

B.

Exit Meeting Summary At the conclusion of the examination period, the examiners met with the members of the facility staff to discuss the results of the examinations. The following personnel were present for the exit meeting:

NRC UTILITY S. McCrory J. Levine J. Pellet J. Vandergrift W. Johnson E. Force E. Wentz E. Ewing D. Smith B. Baker B. Garrison NRC informed the facility staff that all operating examinations were clear passes and no generic weaknesses were identified during the course of these examinations.

It was noted, however, that inconsistencies in terminology between plant training material and actual usage caused some confusion during the written examination.

The facility expressed concern that the material used by NRC to develop the written examinations was not wholly appropriate because the system descriptions, provided to NRC and used for much of the examination development, were not given to operators and candidates for study nor used as classroom training material. When NRC inquired why material considered appropriate by the facility, such as lesson plans and outlines, had not been provided to NRC, the facility responded that they had not been specifically asked to provide this particular material.

C.

General Coments NRC emphasizes that it is the responsibility of the facility to provide the most accurate, complete, and appropriate material for use by NRC during examination development.

NUREG 1021 provides a comprehensive list of materials NRC considers important for examination development. Since Region IV maintains a permanent set of facility procedures and training material, the standard letter to the utility Vice President of nuclear operations scheduling

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examinations may not contain an attachment specifying required reference material. However, this does not remove the facility's responsibility to ensure that NRC has apprcpriate material for examination development.

7 D.

Requalification Program Evaluation Report Facility:

Arkansas Nuclear One Unit 1 Examiner:

S. L. McCrory I

Dates of Evaluation:

4/15/86 Areas Evaluated:

X Written Oral X Simulator j

Written Examination 1.

Evaluation of Examination:

SATISFACTORY 2.

Evaluation of Facility Examination Grading:

J Oral Examination 1.

Overall Evaluation:

SATISFACTORY 2.

Number Observed:

Number Conducted:

11 Overall Program Evaluation Satisfactory:

X Marginal:

Unsatisfactory:

(Listmajordeficiency areas with brief Descriptive comments.)

The AN01 requalification training program is satisfactory.

Submitted:

Forwarded:

Approved:

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~Lw8middN pection Chief gr Branch Chief (W, ]

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AliO1 Exmination Key Date Administered: 4/18/86 Type of Examination:

Reactor Operator License Reactor Operator Requalification Senior Reactor Operator Requalification 1

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NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION 1

FACILITY:

_88K8N585_ NUCLE 88_QNE:1__

REACTOR TYPE:

_EWB:R&W1ZZ______________

DATE ADMINISTERED:_HhlQ8415________________

EXAMINER:

_dQQBQB1t_5t_____________

l APPLICANT:

INSIBUCIIQNH_IQ_8EELIQ8BIl Uno separate paper for the answers.

Write answers on one side only.

I Stsple 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 lecst 80%.

Examination papers will be picked up six (6) hours after i

tho examination starts.

% OF CATEGORY

% OF APPLICANT'S CATEGORY

__V8LUE_ _IQI6L

___5CQBE___

_V8LUE__ ______________C8IEQQBl_____________

i

_25tDQ__ _25tQQ

________ 1.

t2RINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW 1

1

_25t00__ _25tDQ

________ 2.

PLANT DESIGN INCLUDING SAFETY j

AND EMERGENCY SYSTEMS l

_251Q0__ _25tQQ

________ 3.

INSTRUMENTS AND CONTROLS i

I

_2510Q__ _25tQQ

________ 4.

PROCEDURES - NORMAL, ABNORMAL,

}

EMERGENCY AND RADIOLOGICAL CONTROL 1DQt0D__ lQQiQQ

________ TOTALS 1

i FINAL GRADE _________________%

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

i IPPLiCIUT 5~55G ITURE I

~~~~~~~~~~~~~~

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INtC 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 oiIe 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 commonly 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.

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 ANY 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 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:

a. Assemble your examination as follows:

(1) Exam questions on top.

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

(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 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.

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

i

Iz__EBINQ1ELER_QE_NUGLE88_EQWEB_EL8HI_QEEB8IlQNm PAGE 2

IBEBdQQ1H8dlG1t_BE8I_IB8HSEEB_8NQ_ELUIQ_ELQW QUESTION 1.01 (2.00)

TRUE or FALSE 7 e.

Beta-effective is smaller than Beta.

b.

The life time for a prompt neutron is about 10-14 seconds.

c.

A reactor's period is the time required to change power by a factor of 10.

d.

The startup rate is the number of decades reactor power will change in 1 minute.

QUESTION 1.02 (2.00)

After criticality is achieved, the operator levels power at 10 -8 amps to rocord critical data.

The operator quickly establishes a ZERO DPM SUR and vorifies that the intermediate range N.I.'s are steady with no rod motion.

One minute later, the operator notices that power is increasing.

Explain why.

QUESTION 1.03 (1.00)

With the reactor critical at 10 EE-04 %,

rod withdrawal is used to increase power to 10 EE-03 %.

Select the statement that correctly describes the position of rods after the power is stabilized at 10 E-3%.

(1.0) e.

The rod position will be higher than at 10 EE-04% because more fuel must be exposed to the available neutrons to maintain the higher power level.

b.

The rod position will be higher than at 10 EE-04% to overcon.e the power defect.

c.

The rod position will be the same.

The outward' rod motion needed to achieve a given startup rate equals the inward motion needed to reduce the startup rate to zero.

d.

The rod position will be lower than at 10 EE-04% due to the increased delayed neutron population associated with the higher power level.

(*****

CATEGORY 01 CONTINUED ON NEXT PAGE *****)

li__EBINCIELES_QE_ NUCLE 88_EQWEB_EL8HI_QEEB8I1QNi PAGE 3

IBEBdQQ188d1GSi_HE8I_IB8NSEEB_8NQ_ELUID_ELQW QUESTION 1.04 (3.00)

Actume that your plant has experienced a degraded electrical pcwer condition and that you are monitoring the plant's cooldown on natural circulation.

Explain why you agree or disagree with the following statements:

c. A slow downward trend in indicated Tave is a good indication of well - established natural circulation flow.

b.

A difference between wide-range T h and wide-range T c of 65"F and slowly increasing indicates developing natural circulation flow.

c.

Natural circulation flow rate can be increased by rapidly increasing the steam flow rate.

QUESTION 1.05 (3.00)

True or False?

a.

The differential temperature necessary to transfer heat is inversely proportional to heat flux.

(0.5) b.

Pump runout is the term used to describe a centrifugal pump when it is operating with its discharge valve shut.

(0.5) c.

The latent heat of vaporization is another term for the latent heat of condensation.

(0.5) d.

One of the pump laws for centrifugal pumps states that power required by the pump motor is directly proportional to the square of the pump speed.

(0,5) c.

The faster a centrifugal pump rotates, the greater the NPSH required to prevent cavitation.

(0.5) i f.

When comparing a parallel-flow heat exchanger to a counter flow heat exchanger, the temperature difference between the two fluids along the LENGTH of the heat exchanger tubes is MORE uniform for the parallel-flow heat exchanger.

(0,5)

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

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lA__EBINCIELE1_QE_NUGLE88 EQWEB_EL8NI_QEEB8IIQN1 PAGE 4

IBEBdQQ1NadIQ1t_BE81_IB8NSEEB_8ND_ELUID ELQW QUESTION 1.06 (2.00)

Explain why and in what direction the boron coefficient changes when the concentration is increesed from 3000 ppm to 5000 ppm.

QUESTION 1.07 (2.00)

Consider the heat exchanger shown below. Using the data provided, dotermine the following:

a.

Heat transfer per unit time.

(BTU /Hr.)

(1.00) b.

Mass flow rate of tube side.

(1bm/Hr.)

(1.00)

Data Specific heat (Cp) 1.0 BTU /lbm_ F

=

Coef. of heat transfer (u) 80 BTU /hr.- sq. Ft - F

=

Surface area of tubes (A) 95 Sq Ft.

=

Tout = 150 F I

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______I______________________________l_________

Tin = 225 F _______________________________________________ Tout 120 F

=

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I Tin = 80 F QUESTION 1.08 (2.00)

Why does xenon peak later following a shutdown from a high power level than it does following a shutdown from a low power level?

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1 t

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

Iz__EBINQlELES_QE_ NUCLE 68_EQWEB_EL6NI_QEEBellQNt PAGE 5

IHEBdQDYNedlCSi_UE6I_IBeBSEEB_eND ELVIQ_ELQW 1

QUESTION 1.09 (3.00)

HOW would the actual critical rod position very from the estimated critical rod position (ECP) for EACH of the following situations.

Include a BRIEF explanation WHY.

a.

After a trip from 100% power, an ECP is calculated using zero xenon reactivity for a startup 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the trip.

b.

The actual boron concentration is 100 ppm lower than the value used for the ECP.

c.

20 EFPD is used in the ECP instead of the actual 200 EFPD.

d.

The source count rate has decreased from 20 cps to 10 cps between the time the ECP was calculated and the beginning of the startup.

QUESTION 1.10 (3.00)

The reactor is critical at 10 E-4% POWER when an atmospheric dump fails open.

(Isolation valve is open) a.

EXPLAIN what happens to reactor power and Tave.

(Assume the reactor is undermoderated, at BOL and no reactor trip occurs)

b. Assume the same transient occurs at EOL.

EXPLAIN any differences in the power /Tave response as a result of the increased burnup.

QUESTION 1.11 (2.00)

A pump has the following parameters:

speed Chigh):

8000 RPM Discharge head: 2200 PSIG Motor power:

800 Kw.

Flow:

600 GPM

a. What would be the value of each parameter, if the pump is shifted to slow speed (4000 RPM) ?

(1.5) b.

How does the temperature of the fluid (water) being pumped affect the power required by the pump motor ?

(0.5)

(*****

END OF CATEGORY 01 *****)

2t__ELeNI_DE11GN_INCLUQ1ND_18EEII_eND_EMEBGENC1_1YSIEUS PAGE 6

QUESTION 2.01 (4.00)

Give the normal electrical power source for each of the items listed below.

Identify the source by bus or control center alpha-numeric designator, voltage, and current type.

c.

Reactor Coolant Pump C b.

Reactor Building Cooler Fan VSFMID c.

Reactor Coolant Pump Emergency 011 Lift Pump P80D d.

Fire Pump P6A e.

Control Rod Drive Cooling Water Pump PM748 f.

Makeup Letdown Bleed Feed Valve CV-1248 g.

Reactor Protection System Channel I h.

Emergency Feedwater Pump P78 QUESTION 2.02 (4.00) c.

Describe the operation of the Pyrotronics System - 3 including the types of detectors used to provide input signals.

(1.5) b.

Explain the terms " single zone" and " cross zoned" as they apply to the System - 3 (1.5) c.

List three areas or rooms protected by the System - 3.

(If an area is given as well as a room which the STM identifies as being in the area, only the area will be given credit.)

(1.0)

QUESTION 2.03 (4.00) a.

Describe how a mixed-bed demineralizer in the Makeup and Purification System (MAPS) is placed in the " LITHIUM-7 BORATE FORM".

(1.0) b.

When is a demineralizer in the " LITHIUM-7 BORATE FORM" normally used?

(0.5) c.

What is the condition of the other domineralizer in the MAPS?

(0.5) d.

When is the other demineralizer used and why?

(2.0)

(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2z__EL6NI_DE110N_INGLUQ1NQ_18EEIY_6NQ_EdEBGENQ1_SYSIEd3 PAGE 7

QUESTION 2.04 (4.00)

Using figure 2.1 indicate all penetrations in the RCS piping and Reactor Vessel except detector and instrument penetrations and identify the system or component to which the penetration is connected.

Where a single penetration serves more than one system or component, identify all the systems or components served.

i QUESTION 2.0S (2.00)

Describe how decay heat is removed when RCS pressure is above the shutoff head of the LPI system and the BWST has emptied during a small break LOCA.

QUESTION 2.06 (2.00) a.

What is the purpose of the service air connection on the discharge piping of the Containment Spray pumps?

b.

What is the purpose of the condensate water connection on the suction side of the CS pumps but down stream of the NaOH tanks?

QUESTION 2.07 (3.00)

Fully describe the flow path of dirty liquid waste from tank T20, Dirty Weste Drain Tank, to the circ water flume via the clean liquid waste system.

Include all maj or components such as tanks, pumps, etc.

A drawing or word description is acceptable.

QUESTION 2.08 (2.00)

List eight separate components that are supplied service water for cooling purposes.

Redundant components count as one.

(***** END OF CATEGORY 02 *****)

Az__IN11BudENI1_ANQ_CQNIBQLS PAGE 8

QUESTION 3.01 (3.00)

The Reactor Protection System (RPS) provides signals to other systems. One of these is the margin to saturation monitor.

Give the three remaining control / regulating systems which receive signals from the RPS.

For each of these systems, specify the signal (s) it receives from the RPS.

QUESTION 3.02 (1.S0)

The Integrated Control System shifts to track mode when any of its stations / control panels are placed in manual.

List three OTHER conditions or events that cause the ICS to go to track.

QUESTION 3.03 (1.50)

When tracking conditions cause the ICS to go to track, operator control at the Unit Master Station is removed.

List three OTHER Cnon-tracking) conditions which remove operator control at this station.

QUESTION 3.04 (4.00)

Fully explain the impact of a failure of inverter Y11 on the ESAS and how Engineered Safeguards Protection is maintained if the inverter fails.

QUESTION 3.05 (4.00)

While operating at full power, a trip is initiated by a complete loss of feedwater.

EFIC initiates EFW, however, check valve FW-138 fails blocking flow to OTSG B.

Describe the sequence of events in the transient that follows the valve failure emphasizing the response of EFIC, Assume no operator action.

l QUESTION 3.06 (2.00)

During operation at full power, the primary makeup and purification system temperature control valve CV-1221 is shut.

Assume no operator action and describe the resulting transient in the pressurizer emphasizing the response of the pressurizer level control system.

(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)

2i__INSIBVMENIS_eND_CQNIBQLS PAGE 9

QUESTION 3.07 (3.00) n.

What feature on the SPDS color CRT's alerts the operator to an alarm condition?

b.

How does the operator acknowledge the alarm on the primary SPDS?

c.

If the alarm condition on the SPDS color CRT clears before the operator can acknowledge the alarm, how can the operator determine what parameter caused the alarm?

QUESTION 3.08 (3.00)

List the six functions of the power range signals to the RPS.

QUESTION 3.09 (3.00)

Match the items in column 1 with the proper RCS temperature instrument from column 2 that provides them with an input.

COLUMN 1 COLUMN 2 1.

RCP interlock A.

Tc wide range 2.

ICS reactor control subsection B.

Loop delta T 3.

BTU limit calculation C.

Tc narrow range 4.

RPS 0.

T ave 5.

RC flow compensation E.

T hot 6.

Saturation margin monitors F.

Delta Tc l

7.

Daisy panel RCS temperature j

indication 8.

Remote shutdown panel by makeup tank 9.

ICS feedwater ratio control 10.

Remote shutdown panel by E/A Hester RCS temperature indication

{

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

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4 __EBQQEQUBE1_:_NQBdekt_eRNQBdekt_EMERGENC1_eNQ PAGE 10 i

t B&DIQLQGIQaL_CQNIBQL i

l QUESTION 4.01 (1.00)

What is the basis for the absolute maximum pressurizer level of 290 inches any time the reactor is critical of?

(1.0)

~

QUESTION 4.02 (2.00) e.

Define a " dry" OTSG per OP 1101.01, " Limits and Precautions."

(0.5) b.

Assuming both main and auxiliary feed is available, how should each i

be used when recovering level in a dry OTSG?

(1.5)

QUESTION 4.03 (3.00) i MATCHING Match each of the controllers (or stations) below with the correct mode or setpoint from the opposite column, for starting up from Hot Shutdown to Hot Standby.

Modes may be used more than once or not at all.

(3.0)

STATION MODE OR SETPOINT 1.

Turbine Bypass Valves A&B.

a. Manual (Set at 0%).

2.

Steam Header Pressure Stpt.

b.

34%.-

3.

Startup Feedwater Valves A&B.

c. Manual (Set at 50%).

4.

Low Load Feedwater Valves.

d.

449% (895 psig).

5. Main FW Pump Speed Demand A&B.

e.

Auto.

4 6.

Loop Feedwater Demand A&B.

f.

459%~ (579 F).

7.

Steam Generator Load Ratio.

8.

Reactor Demand.

9.

SG - Reactor Demand.

10. Unit Load Demand.

[

QUESTION 4.04 (1.00)

What action must be taken if the instructions on a CAUTION Card conflict with requirements specified in Operating Procedures?

(1.0) i F

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

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1 4 __EBQGEQUBE1_:_NQBd8Lt_8BNQBd8Lt_EMEBGENGl_8NQ PAGE 11-2 88DIQLQQIG8L_GQNIBQL 4

i QUESTION 4.05 (3.50)

Fill in the blanks in the following paragraph dealing with 10CFR20 and AP&L i

exposure limits.

Blanks may contain one or more words.or numbers.

The basic permissible dose (10CFR20) for exposure of the whole body is _(a)_.

Under certain conditions, the quarterly dose may be increased to _(b)_.

Per 1000.31, "Radirtion Protection Manuel," en individual may be permitted to receive a whole body done greater than i

the basic permissible dose provided:

1.

The yearly dose to the whole body does not exceed _(c)_.

The

_(d)_ must authorize extensions above this limit.

2.

The whole body dose, when added to the accumulated occupational dose to the whole body, shall not' exceed _Ce)_.

Exposure of minors (individuals less than _(f)_) shall not exceed

_(g)_.

QUESTION 4.06 (1.50)

I i

If you are working in a radiation area and your TLD badge is damaged such that an accurate reading cannot be determined, explain the basic process that will be used to determine the official dose you will be assigned.(1.5)

I QUESTION 4.07 (2.00) 1 i

What symptoms (3) would require implementation of section IA, "Immediate Control Room Evacuation," of 1203.02, " Alternate Shutdown"?

(2.0) l I

QUESTION 4.08 (1.00) 1 What immediate action is required by section IB of 1203.02, " Alternate Shutdown," that is not required by section IA of the same procedure Cin IB, Control Room evacuation MAY be required, as opposed to being immediately 1

necessary for IA)?

(1.0) 1 1

1 1

}

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

l-

.~

l.

1 iz__EBQQEQUBE1_ _NQBd8Lt_8ENQBd8Li_EMEBQENQ1_8NQ PAGE 12 88DIQLQQ1Q8L_QQNIBQL QUESTION 4.09 (3.00) c.

What three immediate actions are required by 1202.01, " Emergency Operating Procedure," if subcooling margin is lost?

(2.0) l b.

Give a numeric value for subcooling margin and one instrument which can be used to determine if margin is adequate.

(1.0)

.i QUESTION 4.10 (2.00)

What are four (4) parameters (i.e.,

Control Room instrumentation) which should be observed to verify that natural circulation is established and decay heat is being removed after all RC pumps have tripped?

(2.0)

QUESTION 4.11 (3.00)

If Inadequate Core Cooling exists, using the regions identified on Figure 5 from 1202.01, " Emergency Operating Procedure," (copy attached):

a.

What are two (2) potential core or reactor vessel problems from entry into Region 37 (1.0) b.

In general, what are two (2) corrective actions which should be i

initiated upon entry into Region 3?

(1.0) 4 l

c.

What additional corrective action (s) should be initiated if core conditions degrade to Region 47 (0.5) d.

If an accident has progressed to Region 4, what must be considered in addition to core and primary system effects (i.e.,

what safety function may be threatened)?

(0,5)

NOTE: Specific actiors are not required for full credit on this question.

General discussion of maj or ef f ects and success paths is sufficient.

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

st__EBQQEQMBEl_:_NQBd8Lt_8BNQBd8(t_EMEBGENQ1_6NQ PAGE 13 88Q10LQQ1 gel _QQNIBQL QUESTION 4.12 (2.00)

Complete the following ta'ble dealing with reactor operating conditions, per Technical Specifications.

(2.0)

MODE REACTIVITY TAVG POWER Cold Shutdown (a)

(b)

Hot Shutdown (c)

(d)

Hot Standby (e)

(f)

(g) i l

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

annnnnnnnnnnnn-

IstC LICENSE EXAMINATION HANDOUT EQUATIONS, CONSTANTS, AND CONVERSIONS 6 = m*C '*deltaT 6=U*A*deltaT p

P = Po*10sur*(t) p, po.,t/T SUR = 26/T T=1*/p+(p-p)/Ip T=1/(p-5)

T=($-p)/Xp P = (Keff-1)/Keff = deltaKeff/Keff p=1*/TKeff+hrf/(1+1T) 4 A = In2/tg = 0.693/tg K = 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 lb /ft3 = 1 gm/cm3 s

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

Miscellaneous Conversions 1 curie = 3.7 x 10'u disintegrations per second 1 kilogram = 2.21 lba 1 horsepower = 2 54 x 103 Btu /hr 1 mw = 3.41 x 105 Btu /hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) 1 Btu = 778 ft-lbf

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PLANT MANUAL SECTION:

PROCEDURE / WORK PLAN TITLE:

N O.

EMERGENCY OPERATING EMERGENCY OPERATING PROCEDURE 1202.01 PAGE lbV of 13Y ARKANSAS NUCLEAR ONE aev=ON e DATE wovea CHANGC DATE FIGURE 5 CORE EXIT THERMOCOUPLE TEMPERATURE FOR INADEQUATE CORE COOLING 2600 I

RC 2400 SUPERHEATED RC

\\

SUSC00 LED 2200 2000 1800 g

REGION I REGION 2 REGION 3 g

1600 S

5 1400 0

2 2g T

1200 m

CLA0 M

C 1000 REGION 4 800

~

D 1

d

[g%

600 j

400

~

200 400 500 600 700 800 900 1000 1100 1200 1300 Care Exit Tnermacauple Temperature (F)

L iz__EBINQ1 ELE 1_QE_NMQLE88_EQWEB_EL8NI_QEE8611QNi PAGE 14 IBEBdQQ1Ned1Q1t_BE6I_IB6NSEEB_8ND_ELMIQ_ELQW ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-NCCRORY, S.

ANSWER 1.01 (2.00) c.

True.

b.

False.

c.

False, d.

True.

REFERENCE Basic Reactor Theory ANSWER 1.02 (2.00)

When rods were inserted only prompt neutrons were affected and reactor power was stabilized.(1.0) During the time that the operator was taking critical data, the delayed neutrons contributed-to the overall neutron population [1.0) thus power i r.c r e as e s.

(2.0)

REFERENCE B&W177 EQB ANSWER 1.03 (1.00) c.

Rod position will be the same.

REFERENCE Basic Nuclear Physics (CAF)

4 iz__EBINQIELES_QE_NVQLE88_EQWEB_EL8NI_QEEBel1QN PAGE 15 t

IBEBdQQ1Ned10St_BEoI_IB8NSEEB_6NQ_ELu1Q_ELQW ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.04 (3.00) a.

Disagree - Tave is a calculated indication and one parameter decreasing will cause Teve to decrease giving a false indication.

(Agree - If other indications are used in conj unction with Tave. )

(1.0) b.

Disagree - Natural Circulation is indicated by Th stabilizing then tends to decrease. Tc tends to track OTSG sat. temp.

(i.e. decrease). dT will decrease as decay heat load decreases.

(1.0) c.

Agree - lowering steam pressure will lower saturation temp which will increase heat transfer across the tubes.

(1.0)

(If examinee disagrees on the basis that voids may form in the hot leg which will interupt N.C.

flow, he must state this will occur only after plant cooldown has caused sufficient contraction of the RCS to empty the pressurizer thus shifting the bubble to the vessel head or the hot legs)

REFERENCE B&W177 EQB ANSWER 1.05 (3.00) a.

False b.

False c.

True d.

False e.

True I

f.

False (6 8 0.5 ea)

(3.0)

REFERENCE B&W177 EQB ANSWER 1.06 (2.00)

The boron coefficient is negative. Increasing the boron 2000 ppm will cause the coef. to become LESS NEG or move in the POS.

direction because of the competition for neutrons in the core.

REFERENCE I

Basic Reactor Theory l

i I

I l

l 4

i 1

-._=

1z__EBINQ1 ELE 1_QE_NVQLE88_EQWEB_EL6NI_QEEBel1QNi PAGE 16 IBE850Q1N6510ft_BE81_IB8NSEEB_6NQ_ELulD_ELQW ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.07 (2.00)

n. Heat transfer per unit time:

Q = UA(dT) ave (dTlave =(dT1 +dT2)/2 =(C225-150) + (120 -803)/2 = 115/2 = 57.5 F Q = (80 BTU /Hr-sq ft-F)(95 sq ft)C57.5 F)

Q = 4.37

10E5 BTU /hr.

(1.0) b.

Mass flow rate of tube side:

Q = m Cp dT m= Q/(Cp dT) m=

(4.37*10E5 BTU /Hr)/((1 BTU /lbm-F)(225-120 F) m=

4.37*10E5/105 m=

4161 lbm/hr.

(1.0)

REFERENCE B&W177 EQB ANSWER 1.08 (2.00)

Equilibrium iodine is proportional to power, while equilibrium xenon is not. (1.0). Therefor you have a higher ratio of I to Xe at higher power levels.

The greater the I to Xe ratio the longer it takes for sufficient I to decay to Xe such that equilibrium production and decay of Xe is occurring (i.e. the peak). (1 ~ 0)

REFERENCE B&W177 EQB

Iz__EBINQ1ELES_QE_NVQLE88_EQWEB_EL8BI_QEEB611QNi PAGE 17 IBEBdQQ188510S _SEeI_IBeNSEEB_eNQ_ELU10_ELQW t

ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.09 (3.00) a.

Actual critical position will be higher [0.35] due to Xenon peak after the trip. [0.4]

b.

Actual critical position will be lower [0.35) with less boron in the RCS the Control Rods will need to be inserted to compensate for the lower reactivity of the boron.[0.4]

c.

Actual critical position will be higher [0.35] due to less excess reactivity remaining in the core at 200 EFPD.[0.4]

d.

Actual critical position will be the same [0.35] since initial count rate has no effect on ECP (only power at which ECP occurs) [0.4]

(Accept HIGHER if examinee states an assumption that negative reactivity has been added from some source to cause count rate to decrease.)

REFERENCE Nuclear Fundamentals ANSWER 1.10 (3.00)

A. The excess steam flow causes Tave to decrease and insert positive reactivity.

The positive reactivity increase causes power to rise at an ever increasing rate.

When the plant reaches the POAH, the fuel temperature rise will add negative reactivity via the doppler feedback and add reactor heat to stop the temperature decrease.

The power rise and cooldown will continue until reactor power equals steam demand.

(1.5) 4 B.

The rate at which power rises will be much higher and the time to reach the POAH will be much shorter because the Beff is smaller and the rate at which reactivity is introduced is larger (more negative MTC).

At the end, power will be the same but temperature much higher (more negative MTC) but still below no-load Tave.

(1.5)

REFERENCE ANO 1 Reactor Theory part 17 pg 27 i

i

Iz__EBINQ1ELER_QE_NUQLE88_EQWEB_ELaNI_QEEB8IlQNi PAGE 18 IBEBMQQIN851Q1t_BE8I_IB8NSEEB_aNQ_ELU10_ELQW ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.11 (2.00) a.1.

Discharge head: 550 PSIG (2200/(8000/4000)^2)

2. Motor Power:

100 Kw (800/(8000/4000)^3) 3.

Flow:

300 GPM (600/(8000/40003) b.

As the temperature of the water decreases, fluid-density increases (0.25) requiring pump motor power to increase.(0.25)

Copposite is also true) 0.5 EACH REFERENCE i

B&W177 EQB a

5

.... ~. -,,, - -

.--n, e --

,n-

21__EL8NI_DE11GN_ INCLUDING _18EEI1_8ND_EMEBGENCY_111IEMS PAGE 19 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.01 (4.00) a.

1H1 6.9 KVAC b.

(LC) B6 480 VAC c.

(CC) 002 125 VDC d.

1A1 4160 VAC e.

(MCC) 822 480 VAC f.

(MCC) B31 480 VAC g.

RS1 120 VAC h.

1A3 4160 VAC (0.5 each)

REFERENCE AN01 SINGLE LINE ELECTRICAL DIAGRAMS i

1 7

9 a

l 1

4

2z__EL8NI_QESIGN_INCLUQ1NG_18EEI1_eNQ_EME8GENGr_h11IEd1 PAGE 20 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.02 (4.00) a.

The System - 3 ties together the inputs from various detectors to provide alarm indication of fire locations and to initiate fire suppression systems in the affected area automatically (0.5).

The system uses signals from smoke (0.25), flame (0.25), and protectowire(0.25) detectors to actuate trip devices and solenoid valves (0.25) which cause or allow actuation of specific suppression

systems, b.

" Single zone" actuation occurs when only one signal, smoke or flame, is required for actuation (0.5).

" Cross zoned" actuation requires two actuation signals (0.2) either from two different types of detectors in the same room (0.4) or area OR two similar detectors in different strings monitoring a common area (0.4).

c.

(any 3 at 0.333 each) 1.

North electrical penetration areas 2.

South electrical penetration areas

(" Electrical penetration areas" is an acceptable single answer.)

3.

Diesel Generator A 4.

Diesel Generator B

(" Diesel Generators" is an acceptable single answer.)

5.

Cable Spreading Room 6.

Corridor no. 98 7.

Control Room Chalon system) 8.

Fuel Oil Storage Specific breakdowns for the above areas are found on STM FIGURE 60.15 REFERENCE AN01 STM-1-60 l

J

21__EL8N1_QEglGN_lNQLQQ1NG_18EEI1_6ND_EMEBQENCY_SYSIEMS PAGE 21 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.03 (4.00) a.

Reactor coolant containing concentrations of boric acid and lithium hydroxide is passed over the mixed resin bed of the demineralizer until it is saturated with boron and lithium-7 at a concentration equal to the reactor coolant (equilibrium).

(1.0) b.

The " LITHIUM-7 BORATE FORM" demineralizer is used during normal plant operation or as required by plant chemists.

(concept)

(0.5) c.

The other demineralizer is in the basic unsaturated form with a H0H mixed bed or could be same as RCS depending on usage.

(concept)(0.5) d.

Near the end of core life, it is uedd to help reduce the boron concentration (reducing the amount of liquid waste generated by dilution).

(concept)

This demineralizer may be used to control lithium concentration as required by plant chemists.

REFERENCE l

AN01 STM-1-04 ANSWER 2.04 (4.00)

SEE FIGURE 2.1 KEY If the total number of penetrations shown is less than 16, deduct 0.25 for each missing and deduct 0.125 for each that is out of sequence or labeled incorrectly.

If the total number of penetrations shown is more than 16, deduct 0.125 for each in excess of 16 and deduct 0.125 for each that is out of sequence or labeled incorrectly.

REFERENCE AN01 P&ID M230 ANSWER 2.05 (2.00)

The DHR system is placed in the " Piggyback Mode" of operation where the decay heat pumps take a suction on the RB sump (1.0) and discharge to the suction of the makeup pumps which discharge into the RCS (1.0).

i REFERENCE AN01 AA-51002-02 I

2t__EL8NI_QESIGN_INCLUQ1NG_S8EEIl_6ND_EMEBGENC1_SYSIEd1 PAGE 22 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.06 (2.00) a.

The air connection is used to periodically test the operability of the spray nozzles (by verifying that air will flow freely through each nozzle).

(1.0) b.

This condensate connection is used to flush the CS pumps (this would be necessary if NaOH flow had been initiated to reduce the corrosive impact on the pump casing and impeller) and to allow testing of NaOH tank valves (without subj ecting CS piping to corrosive NaOH) (stroke test of outlet valve and flow verification on outlet check valve).

(1.0) 4 REFERENCE P&ID M-236, STM-1-08, ASO 1104.05 ANSWER 2.07 (3.00)

T20 -> DIRTY WASTE DRAIN PUMPS -> DIRTY WASTE FILTERS -> CLEAN WASTE RECEIVER TANKS -> CLEAN WASTE RECEIVER TANK TRANSFER PUMPS -> CLEAN WASTE FILTERS -> RADWASTE DEMINEP.ALIZERS -> TREATED WASTE MONITOR TANKS ->

TREATED WASTE MONITOR PUMPS -> CIRC WATER FLUME If a component is left out deduct 0.4.

If a component is incorrectly identified but in the proper order deduct 0.2.

If a component is correctly identified but in the wrong order deduct 0.2 REFERENCE P& ids M - 213, 214, STM-1-52 4

l 4

f f

21__EL8NI_QE11EN_INCLUDINE_18EEI1_8NQ_EMEBEENGl_111IEd1 PAGE 23 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.08 (2.00) i 1.

DH lube oil cooler 2.

DH cooler 3.

Spray pump lube oil cooler 1

4.

DH vault cooler 5.

EDGs 6.

MU pump lube oil cooler 7.

MU pump room cooler 8.

ICW coolers 9.

Reactor building cooling coils 10.

ACW system 11.

VCH 4A&B emergency chillers 12.

EFW pump suctions (emergency supply) 13.

ANO-1 Control room emergency air conditioner 14.

Unit 2 control room emergency chillers (any 8 at 0.25 each)

REFERENCE AA-21002-033-14A-2 (AN01 QUESTION BANK) i l

1 4

2t__IN11BVMENI1_6NQ_GQNIBQL1 PAGE 24 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 3.01 (3.00)

ICS - RCS FLOW, NEUTRON POWER RCS pressure control - RCS pressure EFW - MFW status, RCP status (not the same as flow), NI power 0.5 each for system and 0.5 for signal sets Allow 1/2 credit for:

Neutron Noise monitor - reactor power CRDM system - startup rate i

1 J

REFERENCE STM-1-63, IaC OP 11.5.05 4

l 1

ANSWER 3.02 (1.50) 1 1.

Turbine EHC Control NOT in ICS auto 2.

Reactor trip i

3.

BOTH turbine generator output breakers open 4.

Cross limits i

0.5 each REFERENCE STM-1-64 1

ANSWER 3.03 (1.50) 1.

Runback in progress i

2.

High load limit exceeded 3.

Low load limit exceeded Allow 1/2-credit for individual runback events.

REFERENCE STM-1-64 1

i i

=

1 2___INSIByMENIS_6ND_QQUIBQL3 PAGE 25 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

I 1

i ANSWER 3.04 (4.00)

Analog subsystem 1 will be deenergized and revert to a tripped condition i

providing one of the 2 of 3 trip signals necessary to initiate ESF (1.0).

Digital subsystem 1 must energize to output an actuation signal.

Therefore it will not output an actuation signal if 2 of 3 of the analog subsystems trip. This makes one train of ESF components inoperable (1.0).

Analog subsystems 2 and 3 and digital subsystem 2 are unaffected by the inverter failure.

However, the logic needed to generate an actuation signal from digital subsystem 2 is now 1 of 2 since it already has a trip signal from analog subsystem 1 (1.0).

If either of the remaining analog subsystems detect a valid trip demand, a trip signal will be sent to digital subsystem 2 which will actuate one train of ESF components (1.0).

i The point values indicated apply to the discussion preceding them back to j

the previous point value indicated.

I 4

REFERENCE l

STM-1-65, GENERIC B&W TRAINING MATERIAL i

1 1

ANSWER 3.05 (4.00)

EFIC will try to control level in both steam generators, but "B" OTSG 1evel will decrease.

When "B" OTSG boils dry its pressure will drop to less than 600 psig givingB-MSLI.

EFIC will isolate "B" OTSG and feed and contol level in "A" OTSG.

RCS response will be normal post trip on one OTSG.

REFERENCE STM-1-66, P&ID M-204, IRC OP 1105.05 i

ANSWER 3.06 (2.00) i I

When CV-1221 is shut, letdown flow stops.

This will cause pressurizer i

level to increase (1.0).

As level increases the level control system will send a signal to throttle down CV-1235.

However, without letdown flow, f

pressurizer level will continue to increase until the level control system j

causes CV-1235 to go completely shut.

Pressurizer level will continue to increase as a result of seal inj ection. (1.0) f REFERENCE STM-1-69, STM-1-4 i

Sz__INSIBudENIS_8NQ_GQNIBQLS PAGE 26 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

i ANSWER 3.07 (3.00) a.

The border around the touch button for the display in which the alarm exists changes from white to a blinking magenta color.

b.

The alarm is acknowledged by pushing or touching the touch button that has the blinking magenta border.

c.

An alarm message will appear on the alarm CRT on the operator's i

console.

1 pt each REFERENCE AA-21002-041-088-3, AA-21002-041-080-3 ANSWER 3.08 (3.00) 1.

High flux trip 104.9% power l

2.

High flux trip (S/D B.P.) 5% power

.i 3.

Flux / flow / imbalance trips I

4.

Flux / pumps trips 5.

MFW pump anticipatory trip 6.

Rod withdraw inhibit cutoff 7.

Turbine anticipatory trip 8.

EFIC enable (aux ekt)

Cany 6 at 0.5) l REFERENCE i

AA-21002-006-000-3 I

I l

21__IN11BVMENIS_6NQ_QQNIBQL3 PAGE 27 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 3.09 (3.00) 1.

A 2.

D 3.

E 4.

E 5.

E 6.

E 7.

A B.

E 9.-

F 10.

E 0.3 EACH REFERENCE AA-21002-009-05A-3

'1

e st__EBQQEQVBEl_:_NQBd8Lt_aRNQBd8Lt_EMEBQENQ1_eND PAGE 28 86DIQLQGIQ8L_GQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-McCRORY, S.

ANSWER 4.01 (1.00)

It is the maximum water level at which the system can accommodate a turbine trip without causing the pressurizer safety valves to open.

REFERENCE AN01 OP 1101.01, Rev.

6, p.

17 ANSWER 4.02 (2.00) a.

< 8 on the startup range instrumentation.

(0.5) b.

Feed from aux feed until minimum level is established (0.75) then use main feed until either the main nozzles are flooded (or reactor power exceeds 5%) (0.75)..

REFERENCE AN01 OP 1101.01, Rev.

4, p.

22 ANSWER

'4.03 (3.00) 1.

e, 2.-d, 3.-4.

e, 5.-6.

a, 7.

c, 8.-9.-10.

a (10 ans 0.3 ea.)

REFERENCE AN01 1102.02, Rev. 33, p.

18 ANSWER 4.04 (1.00)

Changes shall be made to the procedure. (may be temporary)

(1.0) l l

REFERENCE I

AN01 1000.27, Rev.

4, p.

15 c_

4 __EBQQEQUBES_ _NQBd6Lt_6BNQ8d6Lt_EMEBQENQ1_6NQ PAGE 29 t

B6Q1QL2Q1Q6L_QQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 4.05 (3.50) c.

1250 mrem /qtr b.

3000 mrem /qtr c.

5 rems d.

AP&L Vice-President-Nuclear Operations e.

5(n-18),

N= age in years f.

18 years of age g.

10% of a,

or 125 mrem /qtr (7 answers at 0.5 es.)

REFERENCE AN01 1000.31, Rev.

3, p.

35 ANSWER 4.06 (1.50)

Pocket dosimeter or chamber results may be used (0.75) by HP in an investigation (0.75) to determine your dose.

REFERENCE ANO 1000.31, Rev.

1, p.

40 ANSWER 4.07 (2.00) 1.

A Control Room (CR) fire which renders the CR uninhabitable.

(0.6) 2.

A CR fire which threatens immediate damage to a maj or portion of vital controls.

(0.6) 3.

A fire in the Cable Sucead Room which threatens immediate damage to a significant number of cables.

(0.8)

REFERENCE AN01 1203.02, Rev.

1, p.

5 ANSWER 4.08 (1.00)

In IB, the fire announcement is made before evacuating the control room, while IA does not require the announcement until after evacuation, as a followup action (Accept concept).

(1.0)

REFERENCE AN01 1203.02, Rev.

1, p.

5, 16

e 81__PBQQEQUBES_=_NQBd8Lt_8ENQBd8Lt_EMEBQENQ1_8NQ PAGE 30 B6010LQQ1Q8L_QQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 4.09 (3.00) n.

1.

Trip all RCP's.

(0.67) 2.

Verify proper EFW actuation and control.

(0.66) 3.

Select the REFLUX BOILING setpoint for EFW, both trains.

(0.67) b.

1.

30 F OR 50 F (def'n changes for immed. act. vs. later).

(0.5) 2.

Subcooling margin recorder.

SPDS CRT display.

RCS pressure / temperature indicators.

Low saturation margin alarm.

(Any 1/4 at 0.5)

REFERENCE AN01 1202.01, Rev.

6, p.

4 ANSWER 4.10 (2.00)

RC temperatures (including incore T/C's) decreasing.

(0.5)

Thot-Tcold dT < 50 F and decreasing.

(0.5)

Continued demand for EFW to maintain SG 1evels.

(0.5)

Continued demand for steam removal to limit secondary pressure.

(0.5)

REFERENCE AN01 1202.01, Rev 7, p.

10 ANSWER 4.11 (3.00) a.

Clad / fuel damage (0.5) & accumulation of noncondensible gas (0.5).

b.

Depressurize the RCS (0.5) & start 1 RCP per loop (0.5).

c.

Start all 4 RCP's (0.5).

d.

Reactor building integrity (0,5).

REFERENCE AN01 1202.01, Rev.

7, p.

62

..-,~~-v.

,.--.r,,-

. ~.,

., - ~. - -,,,

.,,.,-.,,~-,.,.-e,.

w.

e

..w

l

- dz__EBQQEQUEE1_:_NQBdekt_aRNQBdeL&_EMEBQENQ1_8NQ PAGE 31 88DIQLQQIQ8L_GQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 4.12 (2.00) a.

SDM > 1% dK/K b.

< 200 F (2 answers at 0.33 es.)

c.

SDM > 1% dK/K d.

> 525 F (2 answers at 0.33 ea.)

e.

Rx critical f.

> 525 F g.

Power <'2% rated (3 ans at 0.22 ea.)

REFERENCE AN01 TS, Section 1.2, p.

1 i

l J

s e

4 4

e l

l

U.S.

NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION Facility:

ANO UNIT 1 Reactor Type:

PWR-B&W177 Date Administered:

4/15/86 Examiner:

S.

L.

MCCRORY Candidate:

INSTRUCTIONS TO CANDIDATE:

READ THE ATTACHED INSTRUCTION PAGE CAREFULLY.

THIS EXAMINATION REPLACES THE CURRENT CYCLE FACILITY ADMINISTERED EXAMINATION FOR DEMONSTRATION OF OPERATOR PROFICIENCY AND LICENSE RENEWAL.

FAILURE OF THIS EXAMINATION WILL REQUIRE RETRAINING UNDER THE CURRENT FACILITY REQUALIFICATION TRAINING PROGRAM AND MAY REQUIRE RE-EXAMINATION BY NRC.

Points for each question are indicated in parentheses after the question number.

The passing grade requires at least 70% in each category and a final grade of at least 80%.

Extmination papers will be picked up FOUR (4) hours after the examination starts.

% of Cctegory

% of Candidates's Category Value Total Score Value Category i

17.0 25.56 1.

Principles of Nuclear Power Plant Operations, Fluids, and Thermodynamic 17.0 25.56 2.

Plant Design Including Safety and Emergency Systems 16.0 24.06 3.

Instruments and Controls 16.5 24.81 4.

Procedures - Normal, Abnormal, Emergency, and Radiological Control

__66.5 TOTALS Final Grade All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS I

During the administration of this examination the following rules apply:

1.

Cheating on the examinacion 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.

l You must avoid all contacts with anyone outside the examination room to avoid j

even the appearance or possibility of cheating.

l 3.

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

I 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.

1 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 one 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.

1

12. Use abbreviations only if they are coninonly 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.

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 ANY ANSWER BLANK.

I

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 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:

a. Assemble your examination as follows:

(1) Exam questions on top.

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

(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 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 i

license may be denied or revoked.

e. Do.aot dicuss the examination with other licensee staff personnel until the forn.31 examination review is complete.

.,--,__.-~,#

-..._,,__.m,

- _ _. _m.,y

... -p m,

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

i Iz__EBINQ1 ELE 1_QE_NVQLE68_EQWEB_ELaNI_QEE86IIQNt PAGE 2

IBEBMQQ1NedlG1t_BEaI_IBaNSEEB_aNQ_ELu1D_ELQW QUESTION 1.01 (2.00)

After criticality is achieved, the operator levels power at 10 -8 amps to record critical data.

The operator quickly establishes a ZERO DPM SUR and verifies that the intermediate range N.I.'s are steady with no rod motion.

One minute later, the operator notices that power is increasing.

Esplain why.

QUESTION 1.02 (3.00)

Assume that your plant has experienced a degraded electrical power condition and that you are monitoring the plant's cooldown on natural circulation.

Explain why you agree or disagree with the following statements:

a.

A slow downward trend in indicated Tave is a good indication of well - established natural circulation flow.

(1.0) b.

A difference between wide-range T h and wide-range T c of 65~F and slowly increasing indicates developing natural circulation flow.

(1.0)

I c.

Natural circulation flow rate can be increased by rapidly increasing the steam flow rate.

(1.0) l l

i

(*****

CATEGORY 01 CONTINUED ON NEXT PAGE *****)

Iz__EBINCIELE1_QE_NUCLEaB_EQWEB_EL6NI_QEEB8IIQNi PAGE 3

IBEBMQQ1NaMICSt_BE6I_IB6NSEEB_6NQ_ELUID_ELQW QUESTION 1.03 (2.00)

Consider the heat exchanger shown below. Using the data provided, dotermine the following:

a.

Heat transfer per unit time.

(BTU /Hr.)

(1.00) b.

Mass flow rate of tube side.

(1bm/Hr.)

(1.00)

Octa Specific heat (Cp) 1.0 BTU /lbm-F

=

80 BTU /hr.- sq. Ft - F Coef. of heat transfer (u)

=

Surface area of tubes (A) = 95 Sq Ft.

Tout = 150 F I

I I

I Tin = 225 F _______________________________________________ Tout = 120 F I

I I

I Tin = 80 F QUESTION 1.04 (2.00)

Why does xenon peak later following a shutdown from a high power level than it does following a shutdown from a low power level?

(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)

It__EBINGIELE1_QE_NVQLE88 EQWEB_ELeNI_QEE86IIQNt PAGE 4

IBEBdQQ1NedIGS _BE81_IB6NSEEB_8NQ_ELVIQ_ELQW t

QUESTION 1.05 (3.00)

HOW would the actual critical rod position very from the estimated critical rod position (ECP) for EACH of the following situations.

Include a BRIEF explanation WHY.

a.

After a trip from 100% power, an ECP is calculated using zero xenon reactivity for a startup 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the trip, b.

The actual boron concentration is 100 ppm lower than the value used for the ECP.

c.

20 EFPD is used in the ECP instead of the actual 200 EFPD.

d.

The source count rate has decreased from 20 cps to 10 cps between the time the ECP was calculated and the beginning of the startup.

QUESTION 1.06 (3.00)

The reactor is critical at 10 E-4% POWER when an atmospheric dump fails open.

(Isolation valve is open)

e. EXPLAIN what happens to reactor power and Tave.

(Assume the reactor is undermoderated, at BOL and no reactor trip occurs) b.

Assume the same transient occurs at EOL.

EXPLAIN any differences in the power /Tave response as a result of the increased burnup.

QUESTION 1.07 (2.00)

A pump has the following parameters:

speed (high):

8000 RPM Discharge head: 2200 PSIG Motor power:

800 Kw.

i Flow:

600 GPM i

c. What would be the value of each parameter, if the pump is shifted to slow speed (4000 RPM) ?

(1.5) i b.

How does the temperature of the fluid (water) being pumped affect the power required by the pump motor ?

(0,5)

(***** END OF CATEGORY 01 *****)

21__EL8MI_DE11GN_INCLUDINE_18EEI1_6NQ_EMEBGENC1_111IEb1 PAGE 5

QUESTION 2.01 (4.00)

Give the normal electrical power source for each of the items listed below.

Identify the source by bus or control center alpha-numeric designator, voltage, and current type.

a.

Reactor Coolant Pump C b.

Reactor Building Cooler Fan VSFMID c.

Reactor Coolant Pump Emergency 011 Lift Pump P80D d.

Fire Pump P6A e.

Control Rod Drive Cooling Water Pump PM748 f.

Makeup Letdown Bleed Feed Valve CV-1248 g.

Reactor Protection System Channel I h.

Em,ergency Feedwater Pump P78 4

QUESTION 2.02 (4.00) a.

Describe the operation of the Pyrotronics System - 3 including the types of detectors used to provide input signals.

(1.5) b.

Explain the terms " single zone" and " cross zoned" as they apply to the System - 3 (1.5) c.

List three areas or rooms protected by the System - 3.

(If an area is given as well as a room which the STM identifies as being in the area, only the area will be given credit.)

(1.0)

QUESTION 2.03 (4.00) a.

Describe how a mixed-bed demineralizer in the Makeup and Purification System (MAPS) is placed in the " LITHIUM-7 BORATE FORM".

(1.0) b.

When is a demineralizer in the " LITHIUM-7 BORATE FO.:.t normally used?

(0.5) c.

What is the condition of the other demineralizer in the MAPS?

(0.5) d.

When is the other domineralizer used and why?

(2.0)

(*****

CATEGORY 02 CONTINUED ON NEXT PAGE *****)

2___ELeNI_DE11EN_INGLUQ1NE_leEEII_880_EMEBEENQ1_111IEd1 PAGE 6

QUESTION 2.04 (2.00) c.

What is the purpose of the service air connection on the discharge piping of the Containment Spray pumps?

b.

What is the purpose of the condensate water connection on the suction side of the CS pumps but down stream of the NaOH tanks?

QUESTION 2.05 (3.00)

Fully describe the flow path of dirty liquid waste from tank T20, Dirty Weste Drain Tank, to the circ water flume via the clean liquid waste system.

Include all maj or components such as tanks, pumps, etc.

A drawing or word description is acceptable.

(***** END OF CATEGORY 02 *****)

Iz__INSIBudENI1_aND-QQNIBQL1 PAGE 7

QUESTION 3.01 (4.00)

Fully explain the impact of a failure of inverter Yll on the ESAS and how Engineered Safeguards Protection is maintained if the inverter fails.

QUESTION 3.02 (4.00)

While operating at full power, a trip is initiated by a complete loss of feedwater.

EFIC initiates EFW, however, check valve FW-138 fails blocking l

flow to OTSG B.

Describe the sequence of events in the transient that follows the valve failure emphasizing the response of EFIC.

Assume no operator action.

QUESTION 3.03 (2.00) 4 During operation at full power, the primary makeup and purification system temperature control valve CV-1221 is shut.

Assume no operator action and describe the resulting transient in the pressurizer emphasizing the response of the pressurizer level control system.

QUESTION 3.04 (3.00)

The Reactor Protection System (RPS) provides signals to other systems. One of these is the margin to saturation monitor.

Give the three remaining l,

control / regulating systems which receive signals from the RPS.

For each of these systems, specify the signal (s) it receives from the RPS.

QUESTION 3.05 (1.50)

The Integrated Control System shifts to track mode when any of its stations / control panels are placed in manual.

List three OTHER conditions l

or events that cause the ICS to go to track.

QUESTION 3.06 (1.50)

When tracking conditions cause the ICS to go to track, operator control at I

the Unit Master Station is removed.

List three OTHER (non-tracking) conditions which remove operator control at this station.

4

(*****

END OF CATEGOP.Y 03 *****)

r

=

4 __EBQQEQVBES_:_NQBd6Lt_aRNQBd8Lt_EMEBQENQ1_8NQ PAGE 8

t 88Q10LQQ1 gel _QQNIBQL QUESTION 4.01 (1.00)

What is the basis for the absolute maximum pressurizer level of 290 inches Eny time the reactor is critical of?

(1.0)

QUESTION 4.02 (2.00) a.

Define a " dry" OTSG per OP 1101.01, " Limits and Precautions."

(0.5) b.

Assuming both main and auxiliary feed is available, how should each be used when recovering level in a dry OTSG?

(1.5)

QUESTION 4.03 (3.00)

MATCHING Match each of the controllers (or stations) below with the correct mode or sotpoint from the opposite column, for starting up from Hot Shutdown to Hot Standby.

Modes may be used more than once or not at all.

(3.0)

STATION MODE OR SETPOINT 1.

Turbine Bypass Valves A&B.

a.

Manual (Set at 0%).

2.

Steam Header Pressure Stpt.

b.

34%.

3.

Startup Feedwater Valves A&B.

c.

Manual (Set at 50%).

4.

Low Load Feedwater Valves.

d.

449% (895 psig).

5. Main FW Pump Speed Demand A&B.

e.

Auto.

6.

Loop Feedwater Demand A&B.

f. 459% (579 F).

7.

Steam Generator Load Ratio.

8.

Reactor Demand.

9.

SG - Reactor Demand.

10. Unit Load Demand.

I

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

4 __EBQQEQUBES_=_NQBdekt_aRNQBd8Lt_EMEBGENQ1_8NQ PAGE 9

t 86010LQQ108L_QQNIBQL QUESTION 4.04 (3.50)

Fill in the blanks in the following paragraph dealing with 10CFR20 and AP&L oxposure limits.

Blanks may contain one or more words or numbers.

The basic permissible dose (10CFR20) for exposure of the whole body is _Ca)_.

Under certain conditions, the quarterly dose may be increased to _(b)_.

Per 1000.31, " Radiation Protection Manual," an individual may be permitted to receive a whole body dose greater than the basic permissible dose provided:

1.

The yearly dose to the whole body does not exceed _(c)_.

The

_(d)_ must authorize extensions above this limit.

2.

The whole body dose, when added to the accumulated occupational dose to the whole body, shall not exceed _(e)_.

Exposure of minors (individuals less than _(f)_) shall not exceed

_(g)_.

QUESTION 4.05 (3.00) n.

What three immediate actions are required by 1202.01, " Emergency Operating Procedure," if subcooling margin is lost?

(2.0) b.

Give a numeric value for subcooling margin and one instrument which can be used to determine if margin is adequate.

(1.0)

QUESTION 4.06 (3.00)

If Inadequate Core Cooling exists, using the regions identified on Figure 5 from 1202.01, " Emergency Operating Procedure," (copy attached):

e.

What are two (2) potential core or reactor vessel problems from entry into Region 37 (1.0) b.

In general, what are two (2) corrective actions which should be initiated upon entry into Region 37 (1.0) c.

What additinnel corrective action (s) should be initiated if core conditions degrade to Region 47 (0.5) d.

If an accident has progressed to Region 4, what must be considered in addition to core and primary system effects (i.e.,

what safety function may be threatened)?

(0.5)

NOTE: Specific actions are not required for full credit on this question.

General discussion of major effects and success paths is sufficient.

(*****

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

8A__E8QQEQMBEl_=_NQBd8kA_8ENQBd8kA_EdE8QENQ1_8NQ PAGE 10 88DIQLQQ198L_QQNIBQL 1

QUESTION 4.07 (1.00)

What action must be taken if the instructions on a CAUTION Card conflict with requirements specified in Operating Procedures?

(1.0) l

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

i

INtc LICENSE EXANINATION HANDOUT EQUATIONS CONSTANTS, AND CONVERSIONS 6 = m*C '*deltaT 6=U*A*deltaT p

P = Po*10sur*(t) p, po.,t/T SUR = 26/T T=1*/p+(p-p)/Kp T=1/(p-5)

T = ($-p)/X y p=1*/TKeff+hff(1+I.T) p = (Keff-1)/Keff = deltaKeff/Keff

/

'l A = In2/tg = 0.693/tg K = 0.1 seconds-1 I = Io*e~"*

CR = S/(1-Keff) 2 R/hr = 6*CE/d feet i

i 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 Heat of fusion = 144 Btu /lbe i

1 atmosphere = 14.7 psia = 29.9 inches Hg.

1.

b Miscellaneous Conversions I

1 curie = 3.7 x low disintegrations per second I kilogram = 2.21 1hm 1 horsepower = 2 54 x 103 Btu /hr 1 mw = 3.41 x 105 Btu /hr 1 inch = 2.54 centimeters l

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

PLANT MANUAL SECTION:

PROCEDURE / WORK PLAN TITLE:

NO:

EMERGENCY OPERATING EMERGENCY OPERATING PROCEDURE 1202.01 PAGE lbV 01 ist ARKANSAS NUCLEAR ONE

><v=oN 6

= Art 11/e/e4 CHANGE DATE FIGURE 5 CORE EXIT THERMOCOUPLE TEMPERATURE FOR INADEQUATE CORE COOLING 2600 I

RC

^

2400 SUPERHEATED RC SU8C00L ED 2200 2000 1800 g

REGION I REGION 2 REGION 3 g

1600 S

5 1400 0

2g T

1200 m

CLA0 M

C 1000 4

REGION 4 800 s

g 600 j

400

~

200 400 500 600 700 800 900 1000 1100 1200 1300 Core Exit inermacauple Temperature (F)

J It__EBINCIELER_QE_NUGLE68_EQWEB_EL6NI_QEEBoI1QN PAGE 11 i

IBEBdQQ1Ned1GSt_ME61_IBeNSEE8_8NQ_ELu1D_ELQW 4

ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

i d

l ANSWER 1.01 (2.00)

When rods were inserted only prompt neutrons were affected and reactor power was stabilized.(1.0) During the time that i

the operator was taking critical data, the delayed neutrons contributed to the overall neutron population (1.0) thus power increases.

(2.0)

REFERENCE B&W177 EQB 4

ANSWER 1.02 (3.00) a.

Disagree - Teve is a calculated indication and one parameter j

decreasing will cause Tave to decrease giving a false indication.

i (Agree - If other indications are used in conj unction with Tave. )

(1.0) b.

Disagree - Natural Circulation is indicated by Th stabilizing then tends to decrease. Tc tends to track OTSG sat. temp.

(i.e. decrease). dT will decrease as decay heat load decreases.

(1.0) c.

Agree - lowering steam pressure will lower saturation temp which will increase heat transfer across the tubes.

(1.0)

(If the examinee disagrees on the basis that voids may form in the hot legs interupting N.C.

flow, he must state that this can only happen after the RCS has been cooled sufficiently to cause enough contraction a

to empty the pressurizer thus shifting the bubble to the vessel head or

{

the hot legs.)

REFERENCE 88W177 EQB i

i s

i h

t

It__EBINQlELES_QE_ NUCLE 88_EQWEB_ELaNI_QEEB8IlQNi PAGE 12 IBEBdQQ1N851QS _BE81_IB8NSEEB_6ND_ELUIQ_ELQW t

i ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.03 (2.00) a.

Heat transfer per unit time:

Q = UA(dT) ave (dTlave =(dT1 +dT2)/2 =((225-150) + (120 -80))/2 = 115/2 = 57.5 F Q = (80 BTU /Hr-sq ft-F)(95 sq ft)C57.5 F) 1 i

Q = 4.37

10E5 BTU /hr.

(1.0)

I I

b.

Mass flow rate of tube side; i

Q = m Cp dT 1

m= Q/[Cp dT) m=

(4.37*10E5 BTU /Hr)/((1 BTU /lbm-F)(225-120 F) j m= 4.37*10E5/105 i

j m=

4161 lbm/hr.

(1.0)

REFERENCE B&W177 EQB ANSWER 1.04 (2.00)

Equilibrium iodine is proportional to power, while equilibrium i

xenon is not. (1.0)

Therefor you have a higher ratio of I to Xe et higher power levels.

The greater the I to Xe ratio the longer it takes for sufficient I to decay to Xe such that equilibrium production and decay of Xe is occurring (i.e. the peak). (1.0)

REFERENCE B&W177 EQB I

I

It__EBINGIELES_QE_ NUCLE 6B_EQWEB_EL8NI_QEEBoI1QN PAGE 13 t

IB E Bd Q Q1N ed1G1t_ B E eI_IB eN S Eg B _eN Q _ E L u1D_ EL QW ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.05 (3.00) a.

Actual critical position will be higher [0.35] due to Xenon peak after the trip. [0.4]

b.

Actual critical position will be lower [0.35) with less boron in the RCS the Control Rods will need to be inserted to compensate for the lower reactivity of the boron.[0.4]

c.

Actual critical position will be higher [0.351 due to less excess reactivity remaining in the core at 200 EFPD.[0.41 d.

Actual critical position will be the same [0.35] since initial count rate has no effect on ECP (only power at which ECP occurs) [0.41 (Accept HIGHER if the examineee states an assumption that negative reactive activity has been added from some source to cause count rate to decreasc.)

REFERENCE Nuclear Fundamentals ANSWER 1.06 (3.00)

A. The excess steam flow causes Tave to decrease and insert positive reactivity.

The positive reactivity increase causes power to rise at an ever increasing rate.

When the plant reaches the POAH, the fuel temperature rise will add negative reactivity via the doppler feedback and add reactor heat to stop the temperature decrease.

The power rise and cooldown will continue until reactor power equals steam demand.

(1.5)

B.

The rate at which power rises will be much higher and the time to reach the POAH will be much shorter because the Beff is smaller and the rate at which reactivity is introduced is larger (more negative MTC).

At the end, power will be the same but temperature much higher (more negative MTC) but still below no-load Tave.

(1.5) i REFERENCE ANO 1 Reactor Theory part 17 pg 27 1

11__EBINQIELER_QE_NWQLE88_EQWEB_EL8HI_QEEB8IIQNi PAGE 14 IBEBdQQYN8MIQ1t_HE81_IB8NSEEB_8ND_ELUIQ_ELQW ANSWERS -- ARKANSAS NUCLEAR'ONE-1

-86/04/15-MCCRORY, S.

ANSWER 1.07 (2.00) e.l. Discharge head: 550 PSIG (2200/(8000/4000)^2)

.2.

Motor Power:

100 Kw (800/(8000/4000)^3) 3.

Flow:

300 GPM (600/C8000/4000))

b.

As the temperature of the water decreases, fluid density increases (0.25) requiring pump motor power to increase.[0.25)

Copposite is also true) 0.5 EACH REFERENCE B&W177 EQB

Zi__ELANI_QE11EN_INGLuQ1NG_18EEIX_8ND_EdEBGENQ1_1111Ed1 PAGE 15 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.01 (4.00) a.

1H1 6.9 KVAC b.

(LC) 86 480 VAC c.

(CC) D02 125 VDC d.

1A1 4160 VAC o.

(MCC) 822 480 VAC f.

(MCC) B31 480 VAC 9

RS1 120 VAC h.

1A3 4160 VAC (0.5 each)

REFERENCE AN01 SINGLE LINE ELECTRICAL DIAGRAMS

2___EL6HI_ DESIGN _INGLUQ1NE_18EEIl_6NQ_EdEBGENQ1_SYSIEd3 PAGE 16 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 2.02 (4.00) e.

The System - 3 ties together the inputs from various detectors to provide alarm indication of fire locations and to initiate fire suppression systems in the affected area automatically (0.5).

The system uses signals from smoke (0.25), flame (0.25), and protectowire(0.25) detectors to actuate trip devices and solenoid valves (0.25) which cause or allow actuation of specific suppression systems.

b.

" Single zone" actuation occurs when only one signal, smoke or flame, is required for actuation (0.5).

" Cross zoned" actuation requires two actuation signals (0.2) either from two different types of detectors in the same room (0.4) or area OR two similar detectors in different strings monitorirg a common area (0.4).

c.

(any 3 at 0.333 each) 1.

North electrical penetration areas 2.

South electrical penetration areas

(" Electrical penetration areas" is an acceptable single answer.)

3.

Diesel Generator A 4.

Diesel Generator B

(" Diesel Generators" is an acceptable single answer.)

5.

Cable Spreading Room 6.

Corridor no. 98 7.

Control Room Chalon system) 8.

Fuel Oil Storage Specific breakdowns for the above areas are found on STM FIGURE 60.15 REFERENCE AN01 STM-1-60 i

2t__EL8NI_ RESIGN _INGLUDINQ_S8EEII_8NQ_EMEBQENC1_SYSIEd3 PAGE 17 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

~

ANSWER 2.03 (4.00) a.

Reactor coolant containing concentrations of boric acid and lithium hydroxide is passed over the mixed resin bed of the domineralizer j

until it is saturated with boron and lithium-7 at a concentration equal to the reactor coolant (equilibrium).

(1.0) b.

The " LITHIUM-7 BORATE FORM" domineralizer is used during normal plant operation or as required by plant chemists.

(concept)

(0.5) l c.

The other demineralizer is in the basic unsaturated form with a H0H mixed bed or could be same as RCS depending on usage.

(concept)(0.5) y d.

Near the end of c

'e life, it is used to help reduce the boron concentration (ruducing the amount of liquid waste generated by dilution).

(condept)

This demineralizer may be used to control lithium concentration as required by plant chemists.

REFERENCE AN01 STM-1-04 1

I ANSWER 2.04 (2.00) a.

The air connection is used to periodically test the operability of the spray nozzles (by verifying that air will flow freely through each nozzle).

(1.0) b.

This condensate connection is used to flush the CS pumps (this would be necessary if NaOH flow had been initiated to reduce the corrosive impact on the pump casing and impeller).

(1.0) l REFERENCE P&ID M-236, STM-1-08, ASO 1104.05 ANSWER 2.05 (3.00)

T20 -> DIRTY WASTE DRAIN PUMPS -> DIRTY WASTE FILTERS -> CLEAN WASTE l

RECEIVER TANKS -> CLEAN WASTE RECEIVER TANK TRANSFER PUMPS -> CLEAN WASTE FILTERS -> RA0 WASTE DEMINERALIZERS -> TREATED WASTE MONITOR TANKS ->

TREATED WASTE MONITOR PUMPS -> CIRC WATER FLUME l

If a component is left out deduct 0.4.

If a component is incorrectly identified but in the proper order deduct 0.2.

If a component is correctly identified but in the wrong order deduct 0.2 l

)

i 2z__ELeNI_ DESIGN _INCLUDINE_leEEII_eND_EMEBGENC1_111IEMS PAGE 18 t

ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

i h

i REFERENCE P& ids M - 213, 214, STM-1-52 i

.t 4

.l 4

4 5

1 l

l i

j I

l 1

d d

r J

1 1

i I

I i

i 1

1 i

l t

i

2t__INSIBuMENIS_AUQ_QQUIBQLS PAGE 19 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 3.01 (4.00)

Analog subsystem 1 will be deenergized and revert to a tripped condition providing one of the 2 of 3 trip signals necessary to initiate ESF (1.0).

Digital subsystem 1 must energize to output an actuation signal.

Therefore it will not output an actuation signal if 2 of 3 of the analog subsystems trip. This makes one train of ESF components inoperable (1.0).

Analog i

subsystems 2 and 3 and digital subsystem 2 are unaffected by the inverter failure.

However, the logic needed to generate an actuation signal from digital subsystem 2 is now 1 of 2 since it already has a trip signal from analog subsystem 1 (1.0).

If either of the remaining analog subsystems detect a valid trip demand, a trip signal will be sent to digital subsystem 2 which will actuate one train of ESF components (1.0).

The point values indicated apply to the discussion preceding them back to the previous point value indicated.

REFERENCE STM-1-65, GENERIC B&W TRAINING MATERIAL ANSWER 3.02 (4.00)

EFIC will try to control level in both steam generators, but "B" OTSG 1evel i

will decrease.

When "B" OTSG boils dry its pressure will drop to less than 1

600 psig giving B-MSLI.

EFIC will isolate "B" OTSG and feed and control level in "A"

OTSG.

RCS response will be normal post trip on one OTSG.

REFERENCE STM-1-66, P&ID M-204, I&C OP 1105.05 ANSWER 3.03 (2.00)

When CV-1221 is shut, letdown flow stops.

This will cause pressurizer level to increase (1.0).

As level increases the level control system will send a signal to throttle down CV-1235.

However, without letdown flow, pressurizer level will continue to increase until the level control system causes CV-1235 to go completely shut.

Pressurizer level will continue to i

increase as a result of seal injection. (1.0)

REFERENCE STM-1-69, STM-1-4

=. ------

2t__INSIBudENI1_6NQ_GQNIBQL3 PAGE 20 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 3.04 (3.00)

ICS - RCS FLOW, NEUTRON POWER RCS pressure control - RCS pressure j

EFW - MFW status, RCP status (not the same as flow), NI power 0.5 each for system and 0.5 for signal sets 1

i Allow 1/2 credit for:

)

Neutron noise monitor - reactor power CRDM system - startup rate REFERENCE STM-1-63, I&C OP 11.5.05 3

ANSWER 3.05 (1.50) i 1.

Turbine EHC Control NOT in ICS auto 2.

Reactor trip 3.

BOTH turbine generator output breakers open 4.

Cross limits 0.5 each REFERENCE j

STM-1-64 i

ANSWER 3.06 (1.50) 1.

Runback in progress 2.

High load limit exceeded 3.

Low load limit exceeded Allow 1/2 credit for individual runbacks.

REFERENCE STM-1-64 l

i i

1 I

i

l st__EBQQEQVBEl_:_NQBd8Lt_8ENQBd&Lt_EMEBQENQ1_8NQ PAGE 21 B6DIQLQQ1 gel _CQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

O ANSWER 4.01 (1.00) i It is the maximum water level at which the system can accommodate a turbine j

trip without causing the pressurizer safety valves to open.

REFERENCE AN01 OP 1101.01, Rev.

6, p.

17 l

1 i

ANSWER 4.02 (2.00) s.

< 8 on the startup range instrumentation.

(0.5) i b.

Feed from aux feed until minimum level is established (0.75) then use main feed until either the main nozzles are flooded (or reactor power exceeds 5%) (0.75).

REFERENCE l

AN01 OP 1101.01, Rev.

4, p.

22 ANSWER 4.03 (3.00) 1.

e, 2.

d, 3.-4.

e, 5.-6.

a, 7.

c, 8.-9.-10.

a (10 ans 0.3 ea.)

REFERENCE AN01 1102.02, Rev. 33, p.

18 t

ANSWER 4.04 (3.50)

J j

e.

1250 mrem /qtr b.

3000 mrem /qtr c.

5 rems d.

AP&L Vice-President-Nuclear Operations o.

5(n-18), N=nge in years f.

18 years of age g.

10% of a,

or 125 mrem /qtr (7 answers at 0.5 es.)

REFERENCE AN01 1000.31, Rev.

3, p.

35 i

a l

4

=

d 1-it__EBQQEQWBE1_:_NQBd8Lt_8BNQBd8Lt_EDEBGENQ1_8NQ PAGE 22 88Q1QLQQ108L_CQUIBQL i

ANSWERS -- ARKANSAS NUCLEAR ONE-1 86/04/15-MCCRORY, S.

1

\\

ANSWER 4.05 (3.00) e.

1.

Trip all RCP's.

(0.67) 2.

Verify proper EFW actuation and control.

(0.66) 3.

Select the REFLUX BOILING setpoint for EFW, both trains.

(0.67) b.

1.

30 F OR 50 F (def'n changes for immed. act. vs. later).

(0.5) 2.

Subcooling margin recorder.

SPDS CRT display.

RCS pressure / temperature indicators.

Low saturation margin alarm.

(Any 1/4 at 0.5)

REFERENCE AN01 1202.01, Rev. 6, p.

4 1

ANSWER 4.06 (3.00)

]

a.

Cleo/ fuel damage (0.5) & accumulation of noncondensible gas (0.5).

k b.

Depressurize the RCS (0.5) & start 1 RCP per loop (0,5).

c.

Start all 4 RCP's (0.5).

d.

Reactor building integrity (0.5).

I REFERENCE AN01 1202.01, Rev. 7, p.

62 i

ANSWER 4.07 (1.00).

Changes shall be made to the procedure. (may be temporary)

(1.0)

REFERENCE AN01 1000.27, Rev.

4, p.

15 i

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NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OP,ERATOR REQUALIFICATION EXAMINATION Facility:

ANO UNIT 1 Reactor Type:

PWR-B&W177 Date Administered:

4/15/86 Examiner:

S.

L.

McCRORY Candidate:

INSTRUCTIONS TO CANDIDATE:

READ THE ATTACHED INSTRUCTION PAGE CAREFULLY.

THIS EXAMINATION REPLACES THE CURRENT CYCLE FACILITY ADMINISTERED EXAMINATION FOR DEMONSTRATION OF OPERATOR PROFICIENCY AND LICENSE RENEWAL.

FAILURE OF THIS EXAMINATION WILL REQUIRE RETRAINING UNDER THE CURRENT FACILITY REQUALIFICATION TRAINING PROGRAM AND MAY REQUIRE RE-EXAMINATION BY NRC.

Points for each question cro indicated in parentheses after the question number.

The passing grade roquires at least 70% in each category and a final grade of at least 80%.

Excmination papers will be picked up FOUR (4) hours after the examination oterts.

% of Category

% of Candidates's Category Value Total Score Value__

Category 17.0 24.64 5.

Theory of Nuclear Power Plant Operations, Fluids, and Thermodynamics 17.0 24.64 6.

Plant Systems Design, Control and Instruments 17.5 25.36 7.

Procedures - Normal, Abnormal, Emergency, and Radiological Control 17.5 25.36 8.

Administrative Procedures Conditions, and Limits 69.0 TOTALS Final Grade All work done on this examination is my own.

I have neither given nor received aid.

Candidate's Signature

f l4 j

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS j

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.

I 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 one side of the j

paper, and write "Last Page" on the last answer sheet.

i 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.

1

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

question and can be used as a guide for the depth of answer required.

i

14. Show all calcualtions, methods, or assumptions used to obtain an answer to l

mathematical problems whether indicated in the question or not.

15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND l

DO NOT LEAVE ANY ANSWER BLANK.

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

examiner only.

1

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:

a. Assemble your examination as follows:

(1) Exam questions on top.

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

(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 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.

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

I

6 St__IBEQBl_QE_NUGLE88_EQWEB_ELeNI_QEEB8110Nt_ELU101t_8NQ PAGE 2

IBEBdQQ1885101 QUESTION 5.01 (3.00)

For each of the conditions below determine if they are subcooled, caturated, or superheated, by how many degrees, and where these conditions would exist in your plant.

c.

2150 psig and G04 F b.

28" vacuum and 90 F c.

895 psig and 580 F d.

2165 psig and 648 F QUdSTION 5.02 (2.00) a.

Why does Moderator Temperature Coefficient (MTC) become more negative as temperature increases at operating boron concentrations?

(1.0) b.

Why does MTC become more negative as a function of core age?

(1.0)

QUE9 TION 5.03 (1.0C)

What ar e the three reasons for establishing regulating group insertion limits?

QUESTION 5.04 (3.00)

HOW would the actual critical rod position very from the estimated critical rod position (ECP) for EACH of the following situations.

Include a BRIEF explanation WHY.

a.

After a trip from 100% power, an ECP is calculated using zero xenon reactivity for a startup 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after the trip.

b.

The actual boron concentration is 100 ppm lower than the value used for the ECP.

c.

20 EFPD is used in the ECP instead of the actuar 200 EFPD.

l d.

The source count rate has decreased from 20 cps to la cps between the time the ECP was calculated and the beginning l

of the startup.

l l

(***** CA EGORY 05 CONTINUED ON NEXT PAGE *****)

s St__IBEQBl_QE_NuGLE88_EQWEB_ELeNI_QEEB8IIQNt_ELMIQSt_8NQ PAGE 3

IBEBdQQ1NedlGS QUESTION 5.05 (3.00)

What effect would each of the following failures have on a natural circulation cooldown which is underway at 490 F.

Explain your answers and consider each failure independently.

a.

The steam dump valve which is being used to control cooldown rate fails open.

b.

Level is lost in the pressurizer.

c.

The auxiliary feedwater valve to one of the SG's fails shut.

QUESTION 5.06 (3.00)

The reactor is critical at 10 E-4% POWER when an atmospheric dump fails open.

(Isolation valve is open) a.

EXPLAIN what happens to reactor power and Tave.

(Assume the reactor is undermoderated, at BOL and no reactor trip occurs)

b. Assume the same transient occurs at EOL.

EXPLAIN any differences in the power /Tave response as a result of the increased burnup.

QUESTION 5.07 (1.00)

The main steam line break accident forms the basis for the shutdown margin requirement at end-of-life CEOL) conditions because:

a.

Beta-effective is at its maximum value.

b.

Boron concentration is at its maximum value.

c.

Control rod insertion limits are most restrictive.

d.

Hot channel factors are at the most conservative values.

o.

MTC is at its most negative value.

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

s Et__IBEQBl_QE_UUQLEeB_EQWEB_EL8NI_QEEB8Il0Nt_ELUIDSt_8NQ PAGE 4

IBEBdQQ1NedIQS 4

QUESTION 5.08 (1.00)

The startup, intermediate and power range channels all use boron in their respective detectors (BF3 or boron lined).

Which of the following is the CORRECT reason for use of boron?

o.

It reduces the critical volume (size) of the detector.

Detectors which rely solely on gas ionization by neutrons are much larger.

b.

Neutrons do not carry a net electric charge.

Neutron detection must depend upon their interaction with target nuclei.

t c.

Ionization of the boron by neutrons is much more responsive and accurate than other ionizations such as neutron-rhodium used in the in-core detectors.

d.

The neutron-boron reaction produces beta particles which have a much higher specific ionization than neutrons alone.

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

ht__ELBNI_SYSIEUS_QESIGNt_QQNIBQLt_aNQ_INSIBudENIaIIQN PAGE 5

QUESTION 6.01 (4.00) a.

Describe how a mixed-bed demineralizer in the Makeup and Purification System (MAPS) is placed in the " LITHIUM-7 BORATE FORM".

(1.0) b.

When is a demineralizer in the " LITHIUM-7 BORATE FORM" normally used?

(0.5) c.

What is the condition of the other demineralizer in the MAPS?

(0.5) d.

When is the other demineralizer used and why?

(2.0)

QUESTION 6.02 (2.00) n.

What is the purpose of the service air connection on the discharge piping of the Containment Spray pumps?

b.

What is the purpose of the condensate water connection on the suction side of the CS pumps but down stream of the NaOH tanks?

QUESTION 6.03 (3.00)

Fully describe the flow path of dirty liquid waste from tank T20, Dirty Waste Drain Tank, to the circ water-flume via the clean liquid waste system.

Include all major components such as tanke, pumps, etc.

A drawing or word description is acceptable.

QUESTION 6.04 (4.00)

While operating at full power, a trip is initiated by a complete loss of feedwater.

EFIC initiates EFW, however, check valve FW-138 fails blocking flow to OTSG B.

Describe the sequence of events in the transient that follows the valve failure emphasizing the response of EFIC.

Assume no operator action.

QUESTION 6.05 (2.00)

During operation at full power, the primary makeup and purification system temperature control valve CV-1221 is shut.

Assume no operator action and describe the resulting transient in the pressurizer emphasizing the response of the pressurizer level control system.

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

f

=

6t__PL6HI_1111Edi_QE11QNt_QQNIBQLt_6NQ_INSIBydENI611QN PAGE 6

i QUESTION 6.06 (2.00)

The Reactor Protection System (RPS) provides signals to other systems. One of these is the margin to saturation monitor.

Give the three remaining control / regulating systems which receive signals from the RPS.

For each of these systems, specify the signal (s) it receives from the RPS.

l l

I

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

s Zz__EBQQEQUBES_:_NQBdekt_8HNQBd6Lt_EMEBQENQ1_86Q PAGE 7

88Q10LQQ1 gal _QQNIBQL QUESTION 7.01 (3.00)

Answer the following questions relating to a natural circulation cooldown, per 1203.13, " Natural Circulation Cooldown."

a.

How is cooling of the reactor vessel head accomplished?

(0.75) b.

What is the maximum cooldown rate that should be maintained?

(0.25) c.

What would indicate formation of a steam bubble in the head?

(0.5) d.

What actions (4) should be taken if a steam bubble occurs?

(1.0) e.

Why should RCS pressure be maintained as high as permitted during a natural circulation cooldown?

(0.5)

QUESTION 7.02 (3.00)

Answer TRUE or FALSE for each of the statements below dealing with Technical Specification limitations on fuel handling.

a.

At least one decay heat removal loop shall be in operation whenever core geometry is being changed.

(0.5) b.

Radiation levels in the reactor building refueling area shall be monitored by instrument RE-8017 during all refueling activities.(0.5) c.

Core suberitical neutron flux shall be continuously monitored by at least two neutron flux monitors whenever core geometry is being changed.

(0.5) d.

Two irradiated fuel assemblies shall not be meved simultaneously by the bridges within the fuel transfer canal.

(0.5) e.

Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

(0.5) f.

All fuel handling shall cease upon notification of the issuance of a

)

tornado watch for Pope, Yell, Johnson, or Logan counties.

(0.5)

QUESTION 7.03 (2.00)

During a plant startup, the Shift Supervisor is permitted to skip system lineups for systems on which maintenance was not performed.

What three 1 cgs is he required to check prior to doing so, per 1102.02, " Plant Startup"?

(2.0)

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

Zz__EBQQEQUBES_ _NQEd8Lt_6BNQBdekt_EMEBGENQY_6NQ PAGE 8

88Q10LQGlQ6(_QQNISQL QUESTION 7.04 (3.00)

During a reactor trip recovery, per 1102.06, the Shift Supervisor makes the datermination of the authorization required to restart by evaluating 7 criteria.

a.

If all criteria are negative, who (by job title) must authorize a reactor restart? (2 titles required for full credit.)

(1.0) b.

If one or more criteria are positive, who (by job title) must authorize a reactor restart, in addition to those in part a?

(0.5) c.

List three (3) of the seven (7) criteria mentioned above.

(1.5) i QUESTION 7.05 (3.50)

Fill in the blanks in the following paragraph dealing with 10CFR20 and AP&L exposure limits.

Blanks may contain one or more words or numbers.

The basic permissible dose (10CFR20) for exposure of the whole body is _(a)_.

Under certain conditions, the quarterly dose may be increased to _(b)_.

Per 1000.31, " Radiation Protection Manual," en individual may be permitted to receive a whole body dose greater than the basic permissible dose provided:

1.

The yearly dose to the whole body does not exceed _(c)_.

The

_(d)_ must authorize extensions above this limit.

2.

The whole body dose, when added to the accumulated occupational dose to the whole body, shall not exceed _(e)_.

Exposure of minors (individuals less than _(f)_) shall not exceed

_(9)_.

l

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

t Zi__EBQQEQUBES_:_NQBd8Lt_8HNQBd8Lt_EMEBGENQY_8NQ PAGE 9

88Q10LQQ1Q8L_QQNIBQL QUESTION 7.06 (3.00)

If Inadequate Core Cooling exists, using the regions identified on Figure 5 from 1202.01, " Emergency Operating Procedure," (copy attached);

a.

What are two (2) potential core or reactor vessel problems from entry into Region 3?

(1.0) b.

In general, what are two (2) corrective actions which should be initiated upon entry into Region 3?

(1.0) c.

What additional corrective action (s) should be init iat e d if core conditions degrade to Region 47 (0.5) d.

If an accident has progressed to Region 4, what must be considered in addition to core and primary system effects (i.e.,

what safety function may be threatened)?

(0.5)

NOTE: Specific actions are not required for full credit on this question.

General discussion of maj or effects and success paths is sufficient.

I l

l

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

8 __ogd1NIgIB611Yg_EBggggUBgst_ggNDIIlgNS _aug_LidlleIIQU$

PAGE 10 1

t QUESTION 8.01 (4.00)

The plant is operating at 100% reactor power.

Pope and the surrounding counties are under a severe weather alert which contains reports of severe electrical disturbances and tornado sightings.

An operator has j ust completed an RCS leakrate calculation which indicates that the RCS leakage has increased by 12 gpm since the last leakrate was performed.

At the same time you receive the radiochemistry report for the RCS which shows an activity level of 120 uCi/gm DE I131.

Before you can specify a course of action a reactor trip occurs.

The operators quickly evaluate the cause to be a loss of off sight power.

One of the operators reminds you that only one amergency diesel generator is operating because the other has been removed from service as allowed by Technical Specifications for repairs and maintenance and cannot be made available for several hours.

While verifying the plant response to the trip another operator informs you that one of the steam generator relief valves failed to close and steam pressure has gone below no-load value.

Using only this information answer the following.

a.

Using EPIP 1903.10, classify each separate event which meets the classification requirements stating the classification level and the and the j ustif ying criteria.

b.

Assign an Emergency Action Level classification to your overall situation and j ustif y your selection.

QUESTION 8.02 (1.50)

What actions, if any should be taken if during a reactor startup NI-1 fails low?

Prior to the failure all channels had been increasing with the exception of NI-2 which had been holding constant at 3x E+3 cpm.

At the time of the failure the channels read:

NI-1 SX E+5 CPM NI-2 3X E+3 CPM NI-3 SX E-10 AMPS NI-4 1X E-10 AMPS JUSTIFY YOUR ANSWER.

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

at__aQUIN11IBaIIVE_EBQQEQUBEft_QQNQ1110N1t_8ND_ Lid 1I8IIQN1 PAGE 11 QUESTION 8.03 (1.00)

On your shift a monthly surveillance item is discovered overdue.

Roquired due date was 25th of the month, assume today is the 31st, and the performance of the SP has begun.

All previous surveillances were completed on time as scheduled.

Which of the statements below is correct sbout the surveillence (SP)?

o.

The SP has been missed and the system must be declared inoperable until the SP is completed satisfactory.

b.

The system is operable as the Technical Specifications allow a monthly SP to be waived 1 month out of 3.

c.

The system is inoperable because the 3.25x time interval for 3 consecutive SPs was not met.

d.

The system is operable because the Technical Specifications allow a time extension which has not been exceeded.

j QUESTION 8.04 (4.00) a.

When an event occurs which must be reported to the NRC within one hour, at what point does the " clock" start for the one hour limit?

(1.0) b.

List three situations or conditions which require report to the NRC within one hour.

Do not use the examples given below and DO NOT give SPECIFIC accidents or events.

(3.0)

EXAMPLES 1

1.

The declaration of any of the Emergency Classes specified in the licensee's approved Emergency Plan.

2.

The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.

QUESTION 8.05 (2.00)

The Shift Supervisor shall have specific authority to order power reduction or shutdown if continued operation of the unit will result in ___.

List the four items from OAP 1015.01, CONDUCT OF OPERATIONS, which complete the above statement.

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

Hz__6DdlNISIB611VE_EBQQEQUBESt_QQNQlIl0NSt_6ND_LIdlI6IlQNS PAGE 12 QUESTION 8.06 (3.00)

Fill in the blanks in the following statements taken from AOP 1015.03, OPERATIONS LOGS AND LOGTAKING.

Blanks may represent individual words or phrases, c.

Where equipment is ___, and consequently the readings are meaningless, associated blanks should be annotated with ___.

If equipment or indicators are malfunctioning and consequently ___ and

___ are not available, the associated blanks should be annotated with b.

Parameters being recorded on manual logs shall be reviewed by the operator on a routine basis to determine their consistency with ___

and in an effort to detect ___ which may be important to continued c.

The Shift Supervisor must be notified of any instrument failure which prevents ___ from being conducted.

QUESTION 8.07 (2.00)

Fill in the blanks in the following statements taken from OAP 1015.05, SHIFT SUPERVISOR KEY CONTROL.

Blanks may represent individual words or phrases.

c.

The Shift Supervisor shall log all keys issued in ___ and obtain ___

and ___ of the recipient prior to issuing the key.

b.

Safety Systems and Interlocks shall be bypassed only in the following situations.

1.

2.

3.

c.

Reactor Building / Containment Personnel Hatch keys shall be issued only by ___ during ___.

l l

1

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

j

IstC LICENSE EXAMINATION HANDOUT EQUATIONS, CONSTANTS, AND CONVERSIONS i

6 = rii*C '*deltaT 6=U*A*deltaT p

P = Po*10sur*(t) p, po,e /T SUR = 26/T t

T = 1*/p + (p-p)/I P T=1/(e-5)

T = (0-e)/Xe p = (Keff-1)/Keff = deltaKeff/Keff p=1*/Reff+hff/(1+1T)

A = In2/tg = 0.693/tg X = 0.1 seconds-1 j

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 lb /ft3 = 1 gm/cm3 m

Heat of vaporization = 970 8tu/lbm Heat of fusion = 144 Btu /lba 1 atmosphere = 14.7 psia = 29.9 inches Hg.

Miscellaneous Convgrsions 1 curie = 3.7 x 101U disintegrations per second 1 kilogram = 2.21 lbm l

1 horsepower = 2 54 x 10' Btu /hr 1 mw = 3.41 x 10b Btu /hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 degrees C = 5/9 (degrees F - 32) i 1 Btu = 778 ft-lbf

PLANT MANUAL SECTION:

PROCEDURE / WORK PLAN TITLE:

NO:

[MERGENCY OPERATING EMERGENCY OPERATING PROCEDURE 1202.01 PAGE 159 or lar ARKANSAS NUCLEAR ONE arv=oN 6 DATE 11/ov/o+

CHANGE DATE FIGURE 5 CORE EXIT THERMOCOUPLE TEMPERATURE FOR INADCQUATE CORE COOLING 2600 I

RC

~

2400 SUPERHEATED RC SUSC00L E0 2200

/

TCLA0 > 1400F 2000 1800 g

REGION I REGION 2 REGION 3 g

1600 5

S 5

1400 0

w I

1200 y

T CLA0 M

1000 a:-$

REGION 4 800 1

1 s

i

[

[4 600 400

)

200' 400 500 600 700 800 900 1000 1100 1200 1300 Care Exit inermacauple Temperature (F)

5t__IBEQBl_QE_NVQLE68_EQWEB_EL8HI_QEEB8110Ni_ELVIQSt_6NQ PAGE 13 IBEBdQQ1Nad10S ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

I ANSWER 5.01 (3.00)

o. subcooled, ~44 F, Th-leg b.

subcooled,

~9 F, condenser c.

superheated, ~50 F, OTSG Coutlet steam) d.

saturated,

~0, pressurizer (12 8 0.25 ea.)

REFERENCE B&W177 EQB ANSWER 5.02 (2.00) a.

Water expands exponentially as temperature increases (0.67).

This increases the density and boron-related changes to reactivity per degree change in moderator temperature (0.33).

b.

MTC primarily changes with core age due to the decrease in boron concentration (0.5), which reduces the positive reactivity added by driving boron out of the core (plus reduced competition) (0.5).

i

-REFERENCE C-E POWER SYSTEM NSS SERIES LECTURE NOTES, p.

VIII-69 ANSWER 5.03 (1.00)

Shutdown margin (0.33), ejected rod worth (0.34); ECCS pwr peaking (0.33).

REFERENCE Technical Specification 3.10.5.a i

Et__IBEQBl_QE_N9GLE68_EQWEB_EL6NI_QEEB6110Nt_ELulDSt_6ND PAGE 14 IBEBdQQ1N6 DIGS ANSWERS -- ARKANSAS NUCLEAR ONE-1

.-86/04/15-MCCRORY, S.

ANSWER 5.04 (3.00) a.

Actual critical position will be higher (0.35] due to Xenon peak after the trip. [0.4]

b.

Actual crit ical position will be lower (0.35) with less boron in the RCS the Control Rods will need to be inserted to compensate for the lower reactivity of the boron.[0.4) c.

Actual critical position will be higher (0.35] due to less excess reactivity remaining in the core at 200 EFPD.[0.4]

d.

Actual critical position will be the same (0.35] since initial count rate has no effect on ECP (only power at which ECP occurs) [0.4]

(Accept HIGHER if examinee states an assumption that negative reactivity has been added from some source to cause count rate to decrease.)

REFERENCE Nuclear Fundamentals r

ANSWER 5.05 (3.00) l o.

Increase cooldown.ete (0.4) since more energy is being removed from the primary. (0.61 b.

May interrupt natural circulation (0.4) since hot legs maybe voided, i

t (0.6) l c.

Decrease cooldown rate (0.4) since SG tubes will become uncovered reducing heat removal. (0.6)

REFERENCE Basic Reactor Theory l

i 4

I i

i

.~

Et__IBEQBl_QE_UMQLE88_EQWEB_EL6NI_QEEBaIIQNt_ELUIgS _6NQ PAGE 15 t

IBEBdQQ188dIQS ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 5.06 (3.00)

A.

The excess steam flow causes Tave to decrease and insert positive reactivity.

The positive reactivity increase causes power to rise at an ever increasing rate.

When the plant reaches the POAH, the fuel temperature rise will add negative reactivity via the doppler feedback and add reactor heat to stop the temperature decrease.

The power rise and cooldown will continue until reactor power equals steam demand.

(1.5) a B.

The rate at which power rises will be much higher and the time to reach the POAH will be much shorter because the Beff is smaller and the rate at which reactivity is introduced is larger (more negative MTC).

At the end, power will be the same but temperature much higher (more negative MTC) but still below no-load Tave.

(1.5)

REFERENCE ANO 1 Reactor Theory part 17 pg 27 i

ANSWER 5.07 (1.00) i (e)

REFERENCE B&W177 EQB ANSWER 5.08 (1.00)

(b)

REFERENCE B&W177 EQB 1

i

?

-_-,_.__I

Et__EL6HI_SISIEMS_DESIGNt_QQNIBQLt_6NQ_INSIBUMENI611QN PAGE 16 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

l ANSWER 6.01 (4.00)

I c.

Reactor coolant containing concentrations of boric acid and lithium hydroxide is passed over the mixed resin bed of the demineralizer until it is saturated with boren and 11thium-7 at a concentration equal to the reactor coolant (equilibrium).

(1.0) b.

The " LITHIUM-7 BORATE FORM" demineralizer is used during normal plant operation or as required by chemistry.

(concept)

(0,5) c.

The other demineralizer is in the basic unsaturated form with a H0H mixed bed or could be same as RCS depending on usage.

(concept)(0.5) d.

Near the end of core life, it is used to help reduce'the boron concentration (reducing the amount of liquid waste generated by dilution).

(concept)

This demineralizer may also be used to control lithium concentration as required by plant chemists.

REFERENCE AN01 STM-1-04 ANSWER 6.02 (2.00) n.

The air connection is used to periodically test the operability of the spray nozzles (by verifying that air will flow freely through each nozzle).

(1.0) b.

This condensate connection is used to flush the CS pumps (this would be necessary if NaOH flow had been initiated to reduce the corrosive impact on the pump casing and impeller) (0.5) and to allow testing of NaOH tank valves (without subjecting the CS piping to the corrosive effects of NaOH) (stroke test of outlet valve and flow verification of outlet check valve) (0.5).

REFERENCE P&ID M-236, STM-1-08, ASO 1104.05 t

6 __PL6NI_gIgIENg_QggiqNt_QQNIBQ(t_6NQ_lNSIBQNENI611QN PAGE 17 t

ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 6.03 (3.00)

T20 -> DIRTY WASTE DRAIN PUMPS -> DIRTY WASTE FILTERS -> CLEAN WASTE RECEIVER TANKS -> CLEAN WASTE RECEIVER TANK TRANSFER PUMPS -> CLEAN WASTE FILTERS -> RADWASTE DEMINERALIZERS -> TREATED WASTE MONITOR TANKS ->

TREATED WASTE MONITOR PUMPS -> CIRC WATER FLUME 1

If a component is left out deduct 0.4.

If a component is incorrectly identified but in the proper order deduct 0.2.

If a component is correctly j

identified but in the wrong order deduct 0.2 i

REFERENCE P& ids M - 213, 214, STM-1-52 4

ANSWER 6.04 (4.00) i EFIC will try to control level in both steam generators, but "B" OTSG 1evel will decrease.

When "B" OTSG bcils dry its pressure will deop to less than 600 psig giving B-MSLI.

EFIC will isolate "B" OTSG and feed and control level in "A"

OTSG.

RCS response will be normal post trip on one OTSG.

REFERENCE STM-1-66, P&ID M-204, I&C OP 1105.05 ANSWER 6.05 (2.00)

When CV-1221 is shut. letdown flow stops.

This will cause pressurizer level to increase (1.0).

As level increases the level control system will send a signal to throttle down CV-1235.

However, without letdown flow, pressurizer level will continue to increase until the level control system causes CV-1235 to go completely shut.

Pressurizer level will continue to increase as a result of seal inj ection. (1.0)

REFERENCE STM-1-69, STM-1-4 4

ht-_EL8NI SISIEdS-QESIGNt_GQUIBQLt_8NQ_INSIBudENI8IlQN PAGE 18 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 6.06 (2.00)

ICS - RCS FLOW, NEUTRON POWER RCS pressure control - RCS pressure EFW - MFW status, RCP status (not the same as flow), NI power i

0.333 each for system and 0.333 for signal sets Allow 1/2 credit for:

Neutron noise monitor - reactor power CRDM system - startup rate REFERENCE j

STM-1-63, I&C OP 11.5.05 a

a d

1 i

I 4

. - - ' +, - -,

- - + -..

,e--4,-,,r

&,e

ssw-w

,er

,,w,w

-,----,r.-

<--+,--r,--y--

m.,,y,-.=*,--re

Zz__EBQGEQUBEE_:_NQBdakt_6BNQBd8Lt_EUEBGENCY_aNQ PAGE 19 B6019LQQ1G6L_QQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 7.01 (3.00) e.

Head cooling is accomplished by head vent flow.

(0.75) b.

Cooldown rate should be maintained < 40 F/hr.

(0.25) c.

A bubble would be indicated by a rapid increase in pressurizer level while depressurizing (or decrease when repress.).

(0,5) d.

1.

Terminate depressurization.

(0.25) 2.

Repressurize slightly (to reduce bubble size).

(0.25) 3.

Ensure / verify continued natural circulation.

(0.25) 4.

Proceed with cooldown/ depress. at a reduced rate.

(0.25) o.

To prevent bubble formation in the vessel head.

(0.5)

REFERENCE AN01 1203.13, Rev.

4, p.

3 ANSWER 7.02 (3.00) c.

F b.

F c.

T d.

F e.

T f.

F (0.5 ea.)

REFERENCE AN01 TS, Section 3.8, p.

58, 59 ANSWER 7.03 (2.00)

Plant, Hold Card, & Work Request Logs.

(3 enswers at 0.666 ea.)

REFERENCE AN01 1102.02, Rev 31, p.

4

Zz__EBQQEQuBEg_:_NDBUatt_6HNQBuaLt_EMEBQENQ1_6NQ PAGE 20 B6DIQLQQ1Q8L_GQNIBQL ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

1 i

ANSWER 7.04 (3.00) a.

Shift Supervisor (0.5), Operations Superintendent (0.5).

d b.

Operations Manager (0.5).

i c.

1.

Did automatic ESAS occur?

i 2.

Did any EFIC train actuate?

3.

Did any maj or equipment damage occur?

4.

Is the cause of the trip unknown?

5.

Were any RAC's written due to off-normal performance?

6.

Were any sections of the emergency plan activated?

7.

Did plant parameters go beyond the bounds of the normal transient limit envelop of SPDS (1600 psig < Prcs < 2450 psig, Trcs < 510 F, subcooling margin < 50 F).

(Any 3/7 answers at 0.5 es.)

REFERENCE AN01 1102.06, Rev.

7, p.

4 ANSWER 7.05 (3.50) a.

1250 mrem /qtr b.

3000 mrem /qtr c.

5 rems d.

AP&L Vice-President-Nuclear Operations

)

e.

5(n-18),

N= age in years f.

18 years of age g.

10% of a,

or 125 mrem /qtr (7 answers at 0.5 ea.)

REFERENCE AN01 1000.31, Rev.

3, p.

35 ANSWER 7.06 (3.00) a.

Clad / fuel damage (0.5) & accumulation of noncondensible gas (0.5).

b.

Depressurize the RCS (0,5) & start 1 RCP per loop (0.5).

c.

Start all 4 RCP's (0.5).

d.

Reactor building integrity (0.5).

REFERENCE AN01 1202.01, Rev.

7, p.

62 i

gt__6Q51NigIg611yg_E8QQEgygggt_QQNDIIIQNSt_8ND_LidlI6IIQNS PAGE 21 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 8.01 (4.00) s.

1.

Leakrate greater than 12 gpm:

Reactor shutdown required by limiting condition for operation.

NOUE.

t 2.

OEI 120 uCi/ gram I-131 in the RCS, ALERT based on greater than 100 100 uCi/gm DE I-131 in RCS.

e.

3.

Loss of offsite power with one EDG out of service, NOUE, reactor shutdown required by LCO.

Insufficient number of offsite power sources.

(1 pt each) b.

ALERT:

Most severe classification of the three in effect.

REFERENCE AN01 EPIP 1903.10, TS 3.7.2, 31.

6, 3.1.4 l

ANSWER 8.02 (1.50)

No action. (0,5)

No SR required if one channel of IR is above E-10 emps. (1.0)

(If the examinee converts cpm to cps and then states that proper and expected overlap is not achieved and startup cannot continue, give full credit.)

1 REFERENCE TS 3.5.1, TABLE 3.5.1-1 i

ANSWER 8.03 (1.00)

D.

l REFERENCE TS f

i I

4

at__8Dd1NISIB8IIVE_P8QQEQQ8Egt_QQNQlliQNit_8NQ_LidlI611QN3 PAGE 22 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 8.04 (4.00) a.

The clock starts when the event occurs (or is recognized) and not l

when its reportability is determined. (1.0) b.

(ANY THREE) 1.

Any deviation from the TS necessary to protect the health and safety of the public for which there are no provisions in the license or TS.

2.

Any event or condition during operation that results in the condition of the nuclear powerplant, including it's principal; safety barriers, being seriously degraded; or results in the nuclear plant being' i.

In an unanalyzed condition that significantly compromises i

plant safety; 11.

In a condition that is outside the design basis of the plant; or 111. In a condition not covered by the plant's operation and emergency procedures.

3.

Any natural phenomenon or other external condition that poses an actual threat to the safety of the nuclear plant or significantly hampers site personnel in the performance of duties necessary for the safe operation of the plant.

4.

Any event that results or should have resulted in ECCS discharge into the RCS as a result of a valid signal.

5.

Any event that results in a major loss of emergency assessment a

capability, offsite response capability, or communications capability.

6.

Any event that poses an actual threat to the safety of the nuclear plant or significantly hampers site personnel in the performance of duties necessary for the safe operation of the plant including fires, toxic gas release, or radioactive release.

Value is one point each.

Wording need not be exact but the intent must be met.

REFERENCE OPAP 1000.08 ATTACHMENT 1

at__8DMIN11188IIVE_EBQQEQUBEnt_QQNDIIIQNit_8ND_LidII6110NS PAGE 23 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 8.05 (2.00) 1.

Immediate equipment-damage 9

2.

Danger to station personnel 3.

Violation of Operating Licenses or TS requirements 4.

Unnecessary automatic trip.

(0.5 each) i REFERENCE l

OAP 1015.01 SEC 6.1.3 i

i ANSWER 8.06 (3.00)

I a.

idle the word IDLE out-of-service alternate indicators the initials 00S b.

plant status developing trends plant operation i

c.

Tech Spec logging (0.333 each)

REFERENCE i

OAP 1015.03 SEC 6.3 a

4 1

-)

Az__aQUINISIB611YE_EBQQEQWBEft_QQNDIIl0 Nit _8NQ_LidlI8Il0NS PAGE 24 ANSWERS -- ARKANSAS NUCLEAR ONE-1

-86/04/15-MCCRORY, S.

ANSWER 8.07 (2.00) c.

the Shift Supervisors's Key Log the signature badge number b.

1.

Equipment failures 2.

Authorized testing 3.

IAW approve procedures c.

the Shift Supervisor power operation (0.25 each)

REFERENCE OAP 1015.05

~

ATTACHMENT 1 ins?lo ARKANSAS POWER & LIGHT COMPANY INTRA COMPANY CORRESPONDENCE Arkansas Nuclear One Russellville, Arkansas April 18, 1986 AN0-86-03783 l

l MEMORANDUM l

T0:

John Pellet FROM:

Ed A. Force

SUBJECT:

Arkansas Nuclear One ANO License / License Requalification Exam In regard to the tests conducted on 4-15-86 at ANO-1, we would appreciate your consideration of the following points:

R.O.

Reactor Operator License Candidates R.O.R.

Licensed R.0. Requalification Examination S.R.0.

Licensed S.R.0. Requalification Examination R.0.

1.03 and 1.10 R.O.R.

1.06 S.R.O.

5.06 l

l All of these questions refer to power levels of 10 EE-03% and/or 10EE-04%.

I ANO Unit I has no calibrated nuclear instrumentation that is used in this power range. Although the Gamma-Metrics channels have a wide range log power scale, it is not calibrated for power operation.

Some R.O., R.O.R., or S.R.O. candidates may interpret these numbers as intermediate range current readings; i.e., 10 EE-04 amps. We feel this should be considered, and points awarded based on the examinees ability to describe what would happen based on that assumption. A reading of 10EE-4 amps is considerably higher in power than 10 EE-4%. Determination of power level based on the information provided will be assumptions only on the part of examinees. On question 1.03, this would make answer c. more correct than b.

h R.O.

1.04 I

R.O.R.

1.02 S.R.0.

N/A

U John Pellet April 18, 1986 ANO-86-03783

.Pg 2 In part "c." of this question, the key word " rapidly" may alter the response to the question.

Another acceptable answer should be:

4 j

Disagree - A rapid increase in steam flow rate could cause a decrease in RCS pressure that would allow voids to form inside j

the tubes of the OTSG, and temporarily block natural circulation flow.

4 R.O.

1.06 R.O.R.

N/A S.R.O.

N/A J

Boron in quantities of 3,000 to 5,000 ppa are unreali-stically high and may cause confusion rather than testing knowledge or skills.

The question would be more effective if more realistic concentrations were used (1,000 - 2,000 ppe).

R.O.

1.09 part d.

R.O.R.

1.05 i

S.R.O.

5.04 Points should be awarded if the examinee assumes some negative reactivity caused the count rate to decrease, and based his answer on that assumption.

R.O.

2.01 R.O.R.

2.01 S.R.O.

N/A We feel the following points should be considered when grading question 2.01:

)

1.

Operators at ANO are not expected to memorize power supplies j

for other than important safety equipment items.

2.

Operator consoles in ANO-1 are labeled to help operators identify power supplies for equipment without reference to.

procedures or E prints., Efforts now underway will result in' these labels being converted to permanent type plaques.

3.

The previous ANO Unit 2 (see copy attached) R.O. license examination required only that license candidates identify (matching) the voltage of various busses based on letter designators (H = 6.9 KV).

Based on these three points, wel feel full credit should be awarded if the examinees can identify the' power source, voltage, and current for items a.,

g.,

and h., and identify the voltage and current only for items b.,

c.,

d.,

e.,

and f.

John Pellet April 18, 1986 ANO-86-03783 Pg 3 R.O.

2.03 R.O.R.

2.03 S.R.0.

6.01 To this point in time, use of STM's is counter productive as a source document for test questions. The STM's were issued for use less than one month ago, and contain terminology that is not currently in use at the plant. For example, Lithium-7 Borate form may confuse examinee's simply because they have not been exposed to it in the past. STM-1-04 gives a theoretical explanation of Lithium control.

In actual practice, both demineralizers are used for lithium control. OP1042.005, attachment A, shows the allowable band for lithium concentration as a function of Boron. At the present time, the A demineralizer is lithium-boron sat-urated and B is partially saturated. The B deminineralizer is placed in service periodically to control the RCS lithium concentration. Answers to part b, e and d may vary depending on whether the candidate is basing his answer on pure theory or on actual plant practice.

(See excerpts of OP1042.005 attached).

R.0.

2.06 R.O.R.

N/A i

S.R.0.

6.02 Credit should also be allowed for:

"Used during stroke testing of Na0H " tank outlet valves".

R.O.

2.08 R.O.R.

N/A S.R.0.

N/A Key list is incomplete and should include.

VCH 4A&B Emergency Chillers EFW Pump suctions (Emergency supply)

ANO-1 Control Room Emergency Air Conditioner.

Unit 2 Control Room Emergency Chillers R.O.

3.01 R.O.R.

3.04 S.R.0.

6.06 Although it is not a control / regulating system, precedent is set by using the Saturation Margin Monitor which is not a control / regulating system.

Therefore, the " Neutron Noise Monitor"'and CRD system inteilocks should be included.

Neutron Noise Monitor - Power level CRDM system - Startup Rate EFW may be identified as EFIC t

John Pellet April 18, 1986 ANO-86-03783 Pg 4 R.O.

3.03 R.O.R.

3.06 S.R.O.

N/A Since any runback is a non-track conditon/ event that causes control to be removed from the Unit Master, listing any 3 runbacks should be awarded full credit. These include:

1.

MFW pump trip 2.

RCP trip (1) 3.

RCP trip (2) 4.

Condensate Pump trip (2) 5.

Assymetric Rod 6.

RCS flow vs. Demand (variable)

R.O.

3.06 R.O.R.

3.03 S.R.O.

6.05 Terminology - CV1221 is generally referred to as the letdown isolation valve. The answer should take into account the fact that 30-40 gpm RCP seal injection will continue to flow into the RCS, and pressurizer level will continue'to increase.

R.0.

3.08 R.0.R.

N/A S.R.0.

N/A On the answer key: #5 SR Hi voltage off. This is no longer an active ciruit.

It was removed when Gamma-Metrics source range was installed.

Add MFW Pump & Turbine anticipatory trips and auxiliary _ relay enabling circuit to EFIC.

R.0, 4.02 R.O.R.

4.02 S.R.O.

N/A Although the question is in reference to a statement in OP1101.01, we feel credit for answers should also be awarded if in agreement with OP1202.01, page 48 (attached).

In OP1101.01, the terms " auxiliary feedwater" and " emergency feedwater" are used interchangeably in most cases.

In this case, OP1202.01 would have precedence.

R.0.

4.04 R.O.R.

4.07 S.R.O.

N/A OP1000.27, Rev. 6, 01-22-86 (attached) now reads' simply " changes shall-be made to the affected procedures." Temporary or permanent is not specified.

e John Pellet April 18, 1986 ANO-86-03783 Pg 5 R.O.

4.09 R.O.R.

4.05 S.R.O.

Terminology. The unit 1 Emergency Operating Procedure, OP1202.01, is identified as having 4 specific types of information.

1.

Immediate Actions 2.

Follow-up Actions 3.

Entry Conditions 4.

Discussions For this reason, examinees may respond to this question by listing.the four immediate actions.

If this is the case, we feel full credit should be awarded based on training received.

The following comments apply to questions that appeared only on the SRO requalification exam.

5.03 The answer key is based on ANO Unit 2 Tech Specs. Refer to Unit 1 T.S., sect. 3.5 bases, page 48.a.

1.

ECCS power peaking 2.

Ejected Rod Worth 3.

Shutdown Margin 5.05 Terminology: answer could be based on Emergency or auxiliary -

(main) feedwater valve going shut, and should be graded accordingly.

7.01 part e.

(no answer on key)

To prevent bubble formation in RV head area.

7.03 Work orders are now processed by SIMS (computer),-and a work order log is no longer kept in the control room.. Full credit should be given if Station Log, and Hold and' Caution Card logs are included.

8.02 New NI-1 has a range of.1.to 10 E5-cps. -Question should be withdrawn.

8.04 Due to redundant listings of various reporting requirements, the required answers to part b. of question 8.04 nullify most: operator responses. The question prohibits answers that would result in declaration of an EAC. However,-as can be demonstrated from OP1903.10, most of the remaining responses would result in declaration of an EAC. For example, from the answer key response:

m

=

John Pellet April 18, 1986 ANO-86-03783 Pg 6 b.3. Natural phenomenon ** etc.

OP1903.10, page 15, 7.1.7. (Alert) b.4. Any event ** ECCS discharge OP1903.10, page 5, 6.1.2.D (NUE) b.5. Any event that *** communications capability.

OP1903.10, page 5, 6.1.6 (NUE) b.6. Any event that *** hampers personnel *** fires, toxic gas, etc.

OP1903.10, page 5, 6.1.7.A (NUE) 6.1.7.E (NUE) page 15, 7.1.4 (ALERT)

This would seem to eliminate 4 of the 6 answers in the key.

Describing circumstances that would lead to conditions stated in answers b.1. and b.2. without requiring an EAC be declared is very difficult.

Senior Operators at ANO are required to be familiar with OP1000.008 and its requirements but are not asked to memorize the attachments.

Operator interactions with this procedure are more closely related to the R.A.C. (Report of Abnormal Condition). Page 4 of the RAC guides the operator through a series of checks to determine reportability requirements. Those checks are specifically intended to lead.the shift supervisor through all the steps outlined in the answer key. However, in many instances, (generalizations and redundancies) an EAC would be appropriate.

The question requires 3 responses, and 4 of the six in the answer. key can be shown as unsuitable. We feel a more suitable way to get a response would be to present the SRO with a situation (s) and require he use the RAC form to determine reportability requirements.

In.its current form, we feel the question should be withdrawn.

General comments: There were a number of terms used on the written test that are not generally used on Unit 1, and these may have caused problems for personnel taking the test. Several questions expressed reactor power levels in terms outside the range of nuclear instrumentation currently in use at ANO-1. Questions 8.04, 8.06, and 8.07 required memorization of procedures. If the examinees were not familiar with specific passages from the procedures used, the possibility existed for using terms or answers that appeared correct in context but were not the responses.

required by the key. Additionally, 8.04 was worded in such a way that specific incidents could not be used, although specific incidents are more likely to be used, presented to, and recognized by the operators.

Again, unless the SR0 had memorized OP1000.008, Attachment "A",-he may not have recognized what the question required.

EAF:EDW:rab cc: ANO-DCC

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ML20206S368

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