Text

Exam Rept 50-297/OL-86-01 on 860423-24.Exam Results:All Five Candidates Passed Oral & Written Exams
	ML20211A438
Person / Time
Site:	North Carolina State University
Issue date:	05/19/1986
From:	Douglas W, Munro J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML20211A406	List: ML20211A401; ML20211A438;
References
	50-297-OL-86-01, 50-297-OL-86-1, NUDOCS 8606110167
	Download: ML20211A438 (96)
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ENCLOSURE 1 EXAMINATION REPORT 297/0L-86-01 Facility Licensee: North Carolina State University

. Raleigh, NC 27695-7909 Facility Name: North Carolina State University Facility Docket No.: 50-297 Written and oral examinations were administered at the North Carolina State University, PULSTAR Reactor near Raleigh, North Carolina.

Chief Examin : .Mu W/ G. Do p s f w F/7 /Se Date Signed Approved by: c a rr # T//9 /Pd pfin F. y o, p ting Section Chief Date Signed Summary:

Examinations on April 23-24, 1986 Oral and written examinations were administered to five candidates, all of whom passed.

8606110167 860529 7 PDR ADOCK 0500 V

REPORT DETAILS

1. Facility Employees Contacted:

T. C. Bray, Reactor Operations Manager

S. M. Grady, Chief Reactor Operator

Attended Exit Meeting

2. Examiners:

W. G. Douglas, Region II K. E. Brockman, Region II

Chief Examiner

3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided S. M. Grady, Chief Reactor Operator, with a copy of the written examination and answer key for review. The comments made by the facility reviewers and the NRC Resolutions to these comments are listed below,

a. SR0 Exam (1) Question J.07 Facility Comment: These are normal criteria always used with procedure and not appropriate for memorization. Recommend deletion.

NRC Resolution: Agreed. Question deleted.

b. R0 Exam (1) Question A.02 Facility Comment: The NCSU Operations Manual does not specify conditions for calling the reactor critical; it only says log approximately critical. Recommend accepting either response a or b.

NRC Resolution: Accepted. Difference in specificity does conform to facility standards.

(2) Question C.03 Facility Comment: The term " average coolant temperature" is confusing as used in the question. Recommend question be deleted.

NRC Resolution: Examinees could have asked examiner for interpretation if they were confused. Comment not accepted.

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Enclosure 1 2 MAY 2 91986 (3) Question C.05 Facility Comment: Four hours is not the normal run time at PULSTAR and the operators have not memorized the four hours Xenon curve. Allow a greater tolerance to answer.

NRC Resolution: Answer key modified to accept 125-E00 pcm as correct response.

(4) Question C.06 Facility Comment: Same as SR0 Question J.07.

(5) Question D.08 Facility Coninent: Since question asks for only two responses, change answer key to reflect two answers at 0.75 each.

NRC Resolution: Accepted. Answer key modified.

4. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination. Those individuals who clearly passed the oral examination were identified.

There were no generic weaknesses noted during the oral examination.

The cooperation given to the examiners and the effort to ensure an atmosphere in the control room conducive to oral examinations was also noted and appreciated.

The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.

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i o DKIDSURE 3 (1 of 2)

U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION

__________________b__fh' REACTOR TYPE: TEST DATE ADMINISTERED: 86/04/24 EXAMINER: JERRY DOUGLAS APPLICANT: _________________________

INSTRUCTIONS TO APPLICANT:

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

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

% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY

_2'_3 501_____1__ __13 50 ___________ ________ A. PRINCIPLES OF REACTOR OPERATION 14.00- 14.00 FEATURES OF FACILITY DESIGGN

________ ______ ___________ ________ B.

14 0 14 0 GENERAL OPERATING

___I__0 __ ___1__0 ___________ ________ C. -

CHARACTERISTICS 14.50 14 5 INSTRUMENTS AND CONTROLS

________ ___1_0 _ ___________ ________ D.

15.00 15.00 SAFETY AND EMERGENCY SYSTEMS

________ ______ ___________ ________ E.

14.00 14.00 STANDARD AND EMERGENCY OPERATING

________ ______ ___________ ________ F.

PROCEDURES 15.00 15.00 RADIATION CONTROL AND SAFETY

________ ______ _._________ ________ G.

100.00 100.00 TOTALS FINAL GRADE _________________%

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

i IPPLECIEiT5~5E5 IiURE~~~~~~~~~~~~~~

. o-A. PRINCIPLES OF REACTOR OPERATION PAGE 2 GUESTION A.01 (1.00)

Which of the followins statements concerning delayed neutrons is correct?

a. The magnitude of the EFFECTIVE delayed neutron fraction is greater at EOL than at BOL.

b. When calculating reactor period (SUR), the delayed neutron term may be considered to be insignificant if the reactivity added is less than the EFFECTIVE delayed neutron fraction.

c. The delayed neutron fraction is the ratio'of the number of delayed neutrons produced to the total number of neutrons produced.

d. The presence of delayed neutrons cause the average neutron generation time to decrease.

QUESTION A.02 (1.00)

Given: You are in the course of a reactor startup. Which of the following conditions are most appropriate for announcing that the reactor is critical?

a. No control rod motion, stable zero SUR, stable source range count rate.

b. No control rod motion, stable positive SUR, increasin3 source range count rate.

c. No control rod motion, stable zero SUR, increasing source range count rate.

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d. Control rod motion, stable positive SUR, increasing source range count rate.

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4 5 A. PRINCIPLES OF REACTOR OPERATION PAGE 3

. QUESTION A.03 (1.00)

During a power escalation on the Log N channel, it takes 30 seconds to double reactor. power level. Which of the followin3 is the stable reactor period that would cause this cate of change?

a. 21 seconds

b. 30 seconds ,

c. 39 seconds

d. 43 seconds GUESTION A.04 (1.00)

Which of the following is the correct definition of microscopic cross section?

a. The actual target area of the nucleus.

b. The effective target area of the nucleus.

c. The total actual target area of all nuclei within the core.

d. The total effective target area of all nuclei within the core.

QUESTION A.05 (1.00)

Which of the following is defined as 'the fractional chan3e in neutron population per Seneration'?

a. keff

b. Delta k

c. Reactivity

d. Delta reactivity I

l (xxxxx CATEGORY A CONTINUED ON NEXT PAGE **xxx)

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A. ORINCIPLES OF REACTOR OPERATION PAGE 4 QUESTION A.06 (1.00)

Which of the followins terms is defined as 'the enersy equivalent of the mass defect *?

a. Excitation energy

b. Bindins energy

c. Fission energy

d. Critical energy GUESTION A.07 (1.00)

Which of the followins express the relationship between differential rod worth (DRW) and intescal rod worth (IRW)?

a. DRW is the slope of the IRW curve at that location. -

b. DRW is the area under the IRW curve at that location.

c. DRW is the square root of the IRW at that location.

d. There is no relationship between DRW and IRW.

QUESTION A.08 (1.00)

Which of the following terms of the six-factor formula has the highest value?

a. Fast Fission Factor

b. Reproduction Factor- ,,

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c. Thermal Utilization Factor l d. Thermal Non-leakase Probability

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

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A. PRINCIPLES OF REACTOR OPERATION PAGE 5 00ESTION A.09 (1.00)

In a suberitical reactor, Keff is increased from .88 to .965. Which of the following is the amount of reactivity that was added to the core?

a. .005 (8500 pcm)

b. .10 (10000 pcm)

c. .125 (12500 pcm)

d. .220 (22000 pcm)

QUESTION A.10 (1.00)

Movement of the rods has the most effect on which of the following factors?

a. Reproduction Factor

b. Fast Fission Factor

c. Thermal Utilization Factor

d. Resonance Escape Factor GUESTION A.11 (1.50)

During a reactor startup, equal increments of reactivity are added and the count rate is allowed to reach equilibrium each time. Choose the bracketed ( [] ) word (s) that describe what is observed on the Source Range recorder and/or SUR meter.

a. The change in equilibrium count rate is Clarger3 Ethe same3

Esms11er] each time. . (0.5)

b. The time required to reach equilibrium is [ longer] Ethe same]

Cshorter3 each time. (0.5)

c. The point of supercriticality can be identified by a(n)

Cincreasing] Cconstant] [ decreasing] positive SUR several seconds after the reactivity addition is terminated. (0.5)

(zumma CATEGORY A CONTINUED ON NEXT PAGE *****)

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A. PRINCIPLES OF REACTOR OPERATION PAGE 6 QUESTION A.12 (1.00)

Xenon _has two production and two removal mechanisms.

a. List the most significant production mechanism. (0.5)

b. List the most significant removal mechanism while at low (less than 10%) power levels. (0.5)

GUESTION A.13 (1.00)

a. What is a delayed neutron? (0 5)

b. Why are delayed neutrons important? (0.5)

(***** END OF CATEGORY A *****)

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S. FEATURES OF FACILITY DESIGGN PAGE 7 QUESTION B.01 (1.00)

Which of the following is the purpose of the 10 graphite reflectors in 3 rid positions 1A - 66 and 6B - 6E?

a. Reduce the neutron irradiation of the beam tubes.

b. Add excess reactivity to the core.

c. Provide a high prompt negative temperature coefficient.

d. Serve as an irradiation facility.

QUESTION B.02 (1.00) l The flow rate of the primary system is varied by which of the following nethods?

a. Adjusting the speed of the primary pump.

b. Adjusting the orifice downstream of the flow straightening tubes.

c. Adjusting the control signal from the flow transmitter.

d. Adjusting the position of the primary pump discharge valve.

QUESTION B.03 (1.00)

Which of the following correctly describes the flow path through the primary coolant system?

a. Pool, Delay Tank, Heat Exchanger, Primary Pump, Core

( b. Pool, Delay Tank, Primary Pump, Heat Exchanger, Core I c. Core, Delay Tank, Primary Pump, Heat Exchanger, Pool

d. Core, Delay Tank, Heat Exchanger, Primary Pump, Pool (musma CATEGORY B CONTINUED ON NEXT PAGE *****)

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9. CEATURES OF FACILITY DESIGGN PAGE 8 QUESTION B.04 (1.00)

Which of the following describes how secondary system inventory is asintained? -

a. The Chief of Reactor Maintenance (CRM) manually adds makeup on a predetermined schedule.

b. Makeup is automatically initiated by cooling tower basin level.

c. Makeup is manually initiated on a low cooling tower basin level,

d. Makeup is automatically initiated by secondary pump suction temperature.

QUESTION B.05 (1.50)

Should a tube leak develop in the primary to secondary heat exchanger, which way will the leakage flow (PRIMARY-TO-SECONDARY or SECONDARY-TO-PRIMARY) for the following plant conditions?

a. Reactor a 1.0 hW, primary and secondary pump running. (0.5)

b. Reactor secured, primary pump running and secondary pump secured. (0.5)

c. Reactor at 50 kW in natural circulation with secondary pump secured. (0.5)

DUESTION B.06 (1.50)

Answer TRUE or FALSE to the following,

a. The primary backup for the reactor air compressor is the BEL air compressor.

b. The purification system uses a H-OH mixed resin bed to control primary system pH.

c. The service water system is used to directly supply water for beam tube annulus recirculation.

(xxxxx CATEGORY B CONTINUED ON NEXT PAGE *****)

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Bo FEATURES OF FACILITY DESIGGN PAGE 9 QUESTION B.07 (1.00)

Fill.in the blanks with.the proper material.

The basic fuel module is a pin made up of -______ pellets contained in a _______ tube.

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QUESTION B.08 (1.50)

List THREE uses of reactor air.

QUESTION B.09 (1.50)

List the THREE loads that can be supplied by the auxiliary distribution panel.

QUESTION B.10 (1.00)

List FOUR components on which the Main Exhaust Fan takes a suction.

QUESTION B.11 (1.00)

Describe how the three-way mixins valve responds to an increase in the secondary pump suction temperature. Include in your description the motive force for operating the valve.

GUESTION B.12 (1.00)

What is the purpose of the' Pneumatic Nitrosen Purse System?

5 (m**** END OF CATEGORY B *****)

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C. GENERAL OPERATING CHARACTERISTICS PAGE 10 QUESTION C.01 (1.00)

Which of the following rods has the hishest worth?

a. Safety 41

b. Safety 42

c. Regulatins

d. Pulse GUESTION C.02 (1.00)

During a reactor startup (after shutdown for two weeks) with the startup source installed, the rod withdrawal is stopped at the -200 pcm position and power level stablizes. Which of the following state-cents concerning how power level will respond in the next hour, if no other actions are taken, is correct?

a. Reactor power will remain essentially constant.

b. Reactor power will slowly decre'ase due to being suberitical.

c. Reactor power will rapidly decrease to initial prestartup level.

d. Reactor power will slowly increase due to lens-lived delayed neutrons.

QUESTION C.03 (1.50)

Answer TRUE or FALSE to the followins. ,.

a. By maintaining a constant pool temperature, T-2, th~e average coolant temperature increases as power level increases. (0.5)

6. At 105 degrees F, xenon-freer the reactor can be taken critical with the lowest worth rod completely inserted. (0.5)

c. The normal purification flow rate is approximately 50 spa. (0.5) i l

(zumum CATEGORY C CONTINUED ON NEXT PAGE *****)

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C. CENERAL OPERATING CHARACTERISTICS PAGE 11 GUESTION C.04 (2.00)

Indicate whether the ACP would be HIGHER THAN, THE SAME AS, or LOWER THAN the ECP for the followin3 conditions. Consider each separately,

a. Beam Tube 2 is inadvertently filled after the ECP is calculated. (0.5)

b. The reactor is started up 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months after S/D from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 1.0 MW instead of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after shutdown. (0.5)

c. The ACP is taken at 100 W instead of 10 W with other parameters as calculated on ECP. (0.5)

d. The primary pump is secured just prior to startup. Note: the reactor has been shutdown all weekend. (0.5)

GUESTION C.05 ( .50)

List the approximate xenon reactivity value for a startup at peak xenon following operations for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 1.0 MW.

-lMESTIN- C ,0 ' '2.5^) -

d d e.,k- - __ __._- -

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In order to use the _SDM ' A = n c h ; ; n. ror ver'ifying SDM on a reactor S/Ur 21,. . . -snsI4 fii6s - a r e a s s u m ed . List FIVE of- these eight condittuna.

QUESTION C.07. (1.00)

Is the Gang rod worth LESS THAN, EQUAL TO, or MORE THAN the sum of the ind.ividual rod worths? EXPLAIN.

OUESTION C.08 (1.00)

Indicate HOW and WHY power level will initially respond to starting the primary pump while at 100 kW.

1 (xxxxx CATEGORY C CONTINUED ON NEXT PAGE xxxxx) l l

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C. GENERAL OPERATING CHARACTERISTICS PAGE 12 GUESTION C.09 (2.50)

Calculate the reactivity associated with the following changes. Indicate whether this change is positive or negative. Consider each separately.

a. Pool temperature increases by 5.0 degrees F. (0.5)

b. Power level is decreased from 1.0 MW to 700 kW. (0.5)

c. Startup source is removed from holder (placed on pool floor). (0.5)

d. Pneumatic sample container is inserted (rabbit in reactor). (0.5)

o. Neutron Radiography Facility is installed. (0.5)

QUESTION C.10 (1.00)

Given the following indications, what is the reactor power level? Consider oach separately.

a. Delta T across core = 13.9 degrees F with a constant temperature. (0.5)

b. N-16 Channel reads a stable 0.395 x 10 E-8 amperes. (0.5) i

(***** END OF CATEGORY C *****)

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D. INSTRUMENTS AND CONTROLS PAGE 13 DUESTION D.01 (1.00)

The process of determining an instrument's accuracy by visually comparing the indication to other independent instrument channels measuring the same parameter is defined in Technical Specifications as at

a. Channel Calibration

b. Channel Check

c. Channel Functional Test

d. Channel Verification QUESTION D.02 (1.00)

Which of the following reactions is used for neutron detection in the startup channel detector?

a. Neutron + Uranium-235 ---> 2 Fission Fragment Ions

b. Neutron + Nitrogen-16 ---> Nitrogen-17 + Gamma

c. Neutron + Baron-10 ---> Lithium-7 Ion + Helium-4 Ion

d. Neutron + Fluorine-19 --~> Nitrogen-15 Ion + Helium-4 Ion QUESTION D.03 (1.00)

Which of the following -statements describes the signal path from the Startup Channel detector to the level (eps) meter on the console?

a. Detector, Pre Amp, Discriminator, Los Integrator, Meter

b. Detector, Los Integrator, Pulse Shaper, Pulse Counter, MeteY

c. Detector, Pre Amp, Los Integrator, Discriminator, Meter j d. Detector, Los Amp, Meter l (mmmum CATEGORY D CONTINUED ON NEXT PAGE mummm) i l

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D. INSTRUMENTS AND CONTROLS PAGE 14 OUESTION D.04 (1.00)

Which of the following methods is used to remove the samma signal from the neutron signal in the Los N Channel?

a. The outer chamber prevents sammas from ionizin3 the inner chamber,

b. Inner chamber current cancels out samma current in the outer chamber.

c. A pulse height discriminator does not allow the samma signals to be counted.

d. Squaring the combined signal makes the samma contribu-tion insi 3nificant.

QUESTION D.05 (1.00)

Indicate whether the following statements concerning a resistance temperature detector (RTD) are TRUE or FALSE.

a. An RTD is connected across one les of a bridge circuit. As temperature that is sensed by the RTD changes, a proportional change in the output voltage (current) across the bridge occurs. (0.5)

b. When an RTD fails open, it will indicate a downscale (low) reading on its meter. (0.5)

GUESTION D.06 (1.50) ,,

What THREE conditions will generate a reverse drive of the control rods?

GUESTION D.07 (2.00)

What FOUR conditions must be met to operate the regulating rod in automatic control?

(xxxxx CATECORY D CONTINUED ON NEXT PAGE xxxxx)

D.- INSTRUMENTS AND CONTROLS PAGE 15 QUESTION D.08 (1.50)

List TWO functions of the Los N Operative (4 W) relay.

QUESTION D.09 (1.00)

What is the purpose of the 9 x 10 E 4 cps rod drive inhibit?

DUESTION D.10 ( .50)

Many of the reactor protection and control setpoints are sensed by P-E switches. Explain how a P-E switch works.

QUESTION D.11 (1.00)

Why isn't the Safety Power Channel downscaled prior to a reactor S/U?

QUESTION D.12 (2.00)

During the performance of a long form st'artup checklist, how is the Over-the-Pool VAMP checked for proper operation? Include all checks and/or readings required.

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(***** END OF CATEGORY D *****)

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E. SAFETY AND EMERGENCY SYSTEMS PAGE 16 QUESTION E.01 (1.50)

a. What TWO scram inputs can be automatically bypassed? (1 0)

b. When are they bypassed? (0.5)

GUESTION E.02 (2.00)

List the EIGHT signals, either automatic or manual, that will cause an Evacuation signal. No setpoints are required.

QUESTION E.03 (2.50)

Excluding the Low Flow reactor scram, list the other FIVE scrams and their setpoints.

QUESTION E.04 (2.00)

Describe how the reactor instrumentation and protection channels would respond to BOTH a high and a low failure of the regulator supplying the flow measuring channel. Include any applicable setpoints.

QUESTION E.05 (1.00)

How is the auxiliary Senerator started on a loss of commerical power?

GUESTION E.06 (1.50)

Lis't all the actions that occur upon the receipt of a Confinement si,3nal.

QUESTION E.07 (2.00)

Basically, explain how redunancy is achieved in the scram logic unit.

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'E.- SAFETY AND EMERGENCY SYSTEMS PAGE 17 i

QUESTION E.08 (1.50)

Explain how core heat is removed in the event of a loss of commerical Power.

QUESTION E.09 (1.00)

[ In the event of a failure of the pool level measuring channel, what TWO methods are available to monitor pool water level?

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F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 18 QUESTION F.01 (1.50)

What are the THREE requirements that must be met in order to do a Key-On Startup?

OUESTION F.02 (2.00)

The Operations Manual gives four ranges of action depending upon the SOM. List these FOUR ranges and the actions (requirements) of each.

QUESTION F.03 (1.00)

What are the TWO conditions that require the performance of a Long Form Startup Checklist?

OUESTION F.04 (2.00)

List FOUR differences in steps that are performed between the Long Form end Short Form Startup Checklists, i.e., the Over-the-Pool VAMP check is more thorough on the Long Form.

QUESTION F.05 (1.50)

a. What criteria determines what category of high residual startup can be performed? (0.5)

b. What is the major difference in how the two categories of high residual startups are performed? (1.0)

QUESTION F.06 (2.00)

List ALL Immediate Actions for a reactor scram.

QUESTION F.07 (1.50)

What actions are required if the reactor operator suspects a Primary Coolant leak while operating at 1 MW?

(m**** CATEGORY F CONTINUED ON NEXT PAGE *****)

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 19 QUESTION F.08 ( .~50)

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What is the Immediate Operator Action for a loss of commerical power?

GUESTION F.09 (2.00)

Assuming the reactor is at 1.0 MW, list the Immediate Actions for-a Reactor Building Evacuation?

(***** END OF CATEGORY F *****)

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S. RADIATION CONTROL AND SAFETY -

PAGE 20

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LOUESTION G.01 (1.00)

-7 Which of the following is i 10 CFR 20 exposure limit?

a. 5 rem / year - whole body. .

b. 1 rem / quarter - whole 6ady.

fI- c. 18.75 rem / quarter - hands.

d. 7 rem / quarter - skiry ofw hole body.

s QUESTION G.02 (1.00)

. .Which of the following radiation exposures would inflict the Greatest biolo3 1 cal damage to man?

1 Rem of GAMMA.

a.

b. 1 Rem of ALPHA. ,

c. 1 Rem of NEUTRON.

d. NONE of the above; they ar_e al'1 equivalent.

QUESTION G.03 (1.00)

_

What would be the activity of 28 grams of Al-20? (Al-28 has a half-life of 2.24 minutes).

a. 1.95 E24 dps -

"' 1.86 E23 dps b.

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c. 3225 E22 dps -

j d. 3.,10 E21 dps

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b '(***ws CATEGORY G CONTINUED ON NEXT PAGE *****)

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.G.- RADIATION CONTROL AND SAFETY PAGE 21 GUESTION G.04 (1.00)

If a point source of samma radiation gives an exposure rate of 10 mR/hr -

et 1 meter, what would be the exposure rate a 5 meters?

a. 2.0 mR/nr

b. 1 0 mR/hr

c. 0.4 mR/hr

d. 0.2 mR/hr QUESTION G.05 (1.00)

When frisking-with the RM-3, at what level (reading) are you considered contaminated?

a. 200 cpm (absolute)

b. 100 cpm (absolute)

c. 100 cpm (above background)

d. 50 cpm (above background)

QUESTION G.06 (1.00)

How much radiation exposure is a minor (under 18) visitor allowed to receive?

a. 10% of the 10CFR20 limit

b. 20% of'the 10CFR20 limit -

l c. 25% of the 10CFR20 limit

d. 50% of the 10CFR20 limit (m**** CATEGORY G CONTINUED ON NEXT PAGE *****)

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G. RADIATION CONTROL AND SAFETY PAGE 22 QUESTION G.07 (2.00)

For the followins radiation detector types, indicate whether the output intensity (current or pulse height) is Proportional to the incident radiation enersyi i.e., if the incident energy increases, will the out-put intensity increase? (Answer YES or NO to each part.)

a. Ion Chamber (0 5)

b. GM (0.5)

c. Proportional Counter (0.5)

d. Scintillation (0.5)

QUESTION G.08 (1.50)

Match the isotopes in Column A with the principal type of radiation

-cuposure hazard in Column B. Column B choices may be used more than once each.

COLUMN A COLUMN B

a. Ar-41 1. Alpha

2. Beta

b. Tritium 3. Neutron

4. Gamma

c. N-16 5. Proton i

OUESTION G.09 (1.50) l Match the radiation detector in Column A to the detector type in Coloan B.

l COLUMN A COLUMN B

a. Control Room 1. Ion Chamber

2. Proportional Counter i b. Stack Gaseous 3. GM l 4. Scintillation

c. Stack Particulate QUESTION G.10 (1.50) l List THREE ways in which personnel exposure may be monitored at NCSU.

l (***** CATEGORY G CONTINUED ON NEXT PAGE xxxmm) l

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G. RADIATION CONTROL AND SAFETY PAGE 23 GUESTION G.11 (1.00)

As a reactor-operator, - what are the TWO conditions that must be met for YOU to authorize the release of irradiated samples?

GUESTION G.12 (1.50)

What THREE individuals must sign a RWP before commencing work in'an area controlled by the Radiation Work Permit (RWP)? -

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(***** END OF CATEGORY G *****)

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

-Aa-E PRINCIPLES OF REACTOR OPERATION PAGE 24

. ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER A.01' (1.00) c REFERENCE Basic Reactor Theory ANSWER A.02 (1.00)

.6 REFERENCE-Basic Reactor Theory

' ANSWER A.03 (1.00) d -(period = 1.443 x doubling time)

REFERENCE NCSU, Reactor Operator Training, Exp. 3, p. 3

' ANSWER A.04 (1.00) b REFERENCE CP&L, Nuclear Reactor Theory,-p.-5-2' ANSWER A.05 (1.00) .

c REFERENCE NUS, Heactor Theory ANSWER A.06 (1.00) b

t A. PRINCIPLES OF REACTOR OPERATION PAGE 25 ANSWERS -- NORTH CAROLINA STATE' UNIV.-86/04/24-JERRY DOUGLAS REFERENCE CP&L, Nuclear Reactor Theory, p. 2-15

-ANSWER A.07 (1.00)

D.

REFERENCE

.DPC, Fundamentals of Nuclear' Reactor Engineering, p. 138 WNTO, pp.-I-5.36.- 43

'001/000-K5.02 (2.9/3.4)

ANSWER A.08 (1.00) b REFERENCE NUS, Reactor Theory ANSWER' A.09 (1.00) b REFERENCE NUS, Vol 3, pp 6.1-3 ANSWER A.10 (1.00)

. c .

! REFERENCE Reactor Theory Manual - Six Factor Formula l

4 I

t l

f ..

i i

E L

A.- PRINCIPLES OF' REACTOR OPERATION PAGE 26-ANSWERS - NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER A.11' (1.50)

a. LARGER (0.5)

b. LONGER (0.5)

c. CONSTANT (0.5)

REFERENCE Westinghouse _ Reactor Physics, Section I-4 DPC, Fundamentals of Nuclear Reactor Engineering, Sect. IV 004/000-K5.08 (2.6/3.2)

ANSWER A.12 (1.00)

a. Decay of Iodine (Tellurium) (0.5)

b. Decay of Xenon (0.5)

REFERENCE Westinghouse Nuclear Training Operations, pp. I-5.64:a 65 001/000-K5.33 (3.2/3.5)

ANSWER A.13 (1.00)

a. A neutron born at some time (>1E-14 seconds) after fission (0.25 pts.) from the decay of fission fragments (0.25 pts.) (0.5)

b. They allow control of the reactor (0.25 pts.) by increasing the average neutron lifetime (0.25 pts.) (0.5)

c. Decreases (0.25 pts.) due to buildup of Plutonium (0.25 pts.) ,

(0.5)

REFERENCE Westinghouse Nuclear Training Operations, pp. I-3.4 & I-3.10 - 12 001/000-K5.47 (2.9/3.4)

.Bo FEATURES OF FACILITY DESIGGN PAGE- 27 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER ~ B . 01 ' (1.00) b' REFERENCE NCSU, . Ops Manual, p. 1-3 ANSWER B.02 (1.00) d-REFERENCE NCSU, Ops Manual, Figure 15.1 ANSWER B.03 (1.00)

C REFERENCE-NCSU,-Ops Manual, Figure 5.1 ANSWER B.04 (1.00)

.b REFERENCE NCSU, Ops Manual, p. 5-14 ANSWER B.05 (1.50) .

a. SECONDARY-TO-PRIMARY (0.5)

L b. PRIMARY-TO-SECONDARY (0.5)

-c.. SECONDARY-TO-PRIMARY (0.5)

REFERENCE.

NCSU,10ps Manual, pp. 5-8 and 5-17

(

i p

r l

t ..

..~ ._

B. FEATURES OF FACILITY DESIGGN PAGE 28 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ,

j ANSWER B.06 (1.50)

a. FALSE (0.5)

6. TRUE (0.5)

c. FALSE (0.5)

REFERENCE NCSU, Ops Manual, pp. 5-34, 5-21, and 5-7 ANSWERE B.07 (1.00)

1. Uranium Dioxide (0.5)

2. Ziracoly (0.5)

REFERENCE NCSU, Ops Manual, p. 1-3 ANSWER B.08 (1.50)

Any THREE at 0.5 points each

1. Pulsing

2. Pool Level (Bubbler)

3. Flow Transmitter (Primary)

4. Experimental Air Supply REFERENCE NCSU, Ops Manual, p. 5-32 ANSWER B.09 (1.50)

- 1. ' Confinement Fan #1 (0.5)

2. Confinement Fan #2- (0~.5)

3. Control Room Distribution Panel (0.5)

REFERENCE

'NCSU, Ops Manual, Figure 8.1

.B. PAGE 29 FEATURES OF FACILITY DESIGGN ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER B.10 (1.00) 1.- BP&TC' Exhaust Fan (0.25)

~2. Rx Bridge Glove Box _

~(0.25)

3. Pneumatic System ~ Exhaust (0.25)

4. Rx Bay Hood (0.25)

REFERENCE NCSU, Ops Manual, Figure 8.1 ANSWER B.11 (1.00)

A~ pneumatic signal (proportional to temperature) (0.5) positions the three-way mixing valve to direct more flow to the cooling tower (less directly to suction of pump) (0.5)- (1.0)

REFERENCE NCSU, Ops Manual, p. 5-16 ANSWER B.12 (1.00)

Reduce Ar-41 released from pneumatic system (0.7) when the pneumatic system is not being used (0.3). -(1.0)

REFERENCE NCSU, Ops Manual, p. 9-5

.. .6

'C. GENERAL OPERATING CHARACTERISTICS PAGE -30 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY' DOUGLAS ANSWER- C.01 (1.00) e REFERENCE NCSU, PDS, Vol. II, p. 4 ANSWER C.02 (1.00) a REFERENCE 1 Basic Reactor Theory, Suberitical Multiplication ANSWER C.03 (1.50)

.a. TRUE (0.5)

b. FALSE. (0.5)

c. FALSE (0.5)

REFERENCE NCSU, PDS, Vol. II, pp. 4& 13 and Ops Manual, Sections 3 & 5 ANSWER C.04 (2.00)

a. THE SAME AS (0.5)

b. HIGHER THAN (0,5)

c. -THE SAME AS (0.5)

d. THE SAME-AS (0.5)

REFERENCE NCSU, PDS, Vol. II, p. 11 ANSWER C.05 ( .50) l 150 pcm (+/- 15 pcm) (0.5) l ,

l l

C. GENERAL OPERATING. CHARACTERISTICS PAGE 31 ANSWERS --' NORTH CAROLINA STATE. UNIV.-86/04/24-JERRY DOUGLAS REFERENCE

-NCSU, PDS, Vol. II, p. 11 do\ t1, p ek se.ao

$MHHi* W .Gs Any FIVE at 0.5 point ach

1. 5x5 Reflected C e #3

.2.- Control rods nked, pulse rod at 24.0 inches

3. NRF instal d

4. BT plugs and filled

5. Pool t perature < 110 de3rees F

6. Lat rod-gan3 worth

7. P installed

8. ess xenon than peak after 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months at 1.0 Mw EFERENCE MCOU, POOR -4trb--Ih- p r-te ANSWER C.07 (1.00)

-LESS THAN (0.5) due to rod shadowing (0.5) (1.0)

REFERENCE NSCU, PDS, Vol. II, p. 4 ANSWER C.08- (1.00)

Power level will increase (0.7) due to primary pump circulating cooler (than water in core) pool water through core (0.3). (1.0)

REFERENCE CAF 4

f 1

I d

r-4 C. . GENERAL' OPERATING CHARACTERISTICS PAGE 32 ANSWERS - . NORTH-CAROLINA; STATE UNIV.-86/04/24-JERRY ~ DOUGLAS ANSWER 'C . 09 - (2.50)

(0.25' points for value,;0.25 points for sign)

'o.- -19.5 pcm.(+/- 2 pcm) (-3.9 x 5) (0.5)'

b. +99 pcm _ (+/- 5'pcm) (-330 x' .3)

(0 5)

-c.- -16 pcm (+/ 2 pcm) (0,5)

d. - +9.pcm (+/- 1 pcm) -

(0.5)

e. -35 pcm (+/- 3:pem) (0.5).

REFERENCE NCSU, PDS, Vol. II, pp. 15 and 16 ANSWER C.10 (1.00)

e. 1.007 MW (13.9/13.8) (0.5)

b. 0.975 MW (.395/.405) (0.5)

REFERENCE NCSU, PDS, Vol. II, pp. 25 and 28-4 0

D. INSTRUMENTS AND CONTROLS ~ PAGE 33 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER' D.01 (1.00)

-- b REFERENCE McG, TS, p. 1-1 Surry, TS 1.0-3

' CAT, TS, p. 1-1 WBN, _ TS , p.-1-1 VCS, TS, p. 1-1 HBR, TS, p. 1-3 NCSU, TS, p. 2

~ ANSWER D.02 (1.00) e REFERENCE NCSU, Ops Manual, Section 4 ANSWER D.03 (1.00) a REFERENCE FNP,'Excore Nuclear Instrumentation System, Fig. 7 Surry, Instrumentation Manual, Excore Instrumentation System, p. IV-1.29 VEGP, Training Text, Vol'>me 5, Fig. 3a-2

' CAT, Figure CN-IC-ENB-4 ,

NCSU, ops Manual, pp. 4-2 & 3 015/000-K6.03 (2.6/3.0)

ANSWER D.04 (1.00) b REFERENCE Nuclear Power Reactor Instrumentation Systems Handbook, Vol. 1, Ch. 2 NCSU, Ops Manual, Section 4 015/000-K5.02 (2.7/2.9)

e D. INSTRUMENTS AND CONTROLS PAGE 34 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS

' ANSWER D.05 (1.00)

o. TRUE (0.5)

b. FALSE -(0.5)

REFERENCE Nuclear Power Reactor Instrumentation Systems Handbook, Vol. 1, Ch. 4 ANSWER' D.06. !(1.50)

1. . Linear ~ power at 73.5 % (1.1 MW) of scale (0.5)

2. Operation of the " Ganged Insert' switch -( 0,5 ) .

3. Reactor' scram (if keyswitch is on) (0.5)'

REFERENCE NCSU,' Ops Manual, pp. 4-22 & 23 ANSWER D.07 (2.00)

1. Mode Selector Switch _in ' Steady State" (0.5)

2. No manual' operation of sanged drive switch (0.5)

'3. Servo error (deviation) < 0.5 % (0 5)

4. Regulating rod withdrawn beyond 13.5 inches- (0.5)

REFERENCE NCSU, Ops Manual, pp. 4-20 & 21

-ANSWER D.08 -(1.50) -

1. , Bypass S/U Channel inhibits (0 5)

2. - Switch LCRM/Los N recorder (0.5)-

3. Pulse interlock (0.5)

REFERENCE NCSui Ops Manual, pp. 4-21 & 22

D. INSTRUMENTS AND CONTROLS PAGE 35 ANSWERS -- NORTH CAROLINA ST ATE UNIV.-86/04/24 -JERRY DOUGLAS ANSWER D.09 (1.00)

Prevent operation of.the S/U Channel in flux levels where saturation of the detector may occur. (1.0)

REFERENCE NCSU, Ops Manual, p. 4-22

. ANSWER D.10 ( .50)

A device that at the set pneumatic pressure senerates an electrical output signal (on or off). (0.5)

LREFERENCE

'NCSur Ops Manual, p. 4-12 ANSWER D.11 (1.00)

Because it uses an uncompensated ion chamber (0.7) and would only read the Samma level if downscaled (0.3). (1.0)

REFERENCE NCSU, Ops Manual, p. 4-8 ANSWER D.12 (2.00)

1. White light illuminated (0.5)

2. Record reading . (0.5)

.3.' Record alarm setpoint (0.5) 4.' Verify battery operation (0,5)

REFERENCE NCSU, Ops Manual, p. 3-3

Eo SAFETY AND-EMERGENCY SYSTEMS PAGE 36

' ANSWERS - . NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER E.01 (1.50)

a. 1. Safety Power Channel (0.5)

2. Linear Power Channel (0.5)

b. During pulsing (0.5)

REFERENCE NCSU, Ops Manual, p. 4-18 ANSWER E.02 (2.00)

1. Manual switch on RAP (0.25)

2. Remote manual switch in basement corridor (0.25)

3. West Wall monitor (0 25)

4. Over-the-Pool monitor (0.25)

5. Control Room monitor (0.25)

6. Particulate monitor (0.25)

7. Stack Gas monitor . (0.25)

8. Auxiliary GM monitor (0.25)

REFERENCE NCSur Ops Manual, p. 8-11 ANSWER E.03 (2.50)

1. Manual (0.3) pushbutton (0.2) (0.5)

2. Linear Overpower (0.3) - 80% of scale (1.2 MW) (0.2) (0.5)

3. Safety Overpower (0 3) - 80% of scale (1.2 MW) (0.2) -

(0.5)

4. Flapper Open (0.3) - open > 150 kW (0.2) (0.5)

5. Low Water Level (0.3) - -36 inches (0.2) (0.5)

REFERENCE NCSU, Ops Monval, p. 4-28

E. SAFETY AND. EMERGENCY SYSTEMS PAGE 37 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER E.04 (2.00)

1. HIGH - High flow indication-(0.25), Low Flow reactor. scram (0.25) at'23-psi-re3vlator output (0.25) if > 150 kW-(0.25) (1.0)

2. LOW - Low flow-indication (0.25), Low Flow reactor scram (0.25) at 475 SPm (0.25) i f > 150 kW (0.25) (1.0)

REFERENCE NCSU, Ops Manual, pp. 4-12 & 19 ANSWER E.05 (1.00)

Manually (0.5) by switch on reactor console (0.5). (1.0)

REFERENCE NCSU, Ops Manual, p. 6-7 ANSWER E.06 (1.50)

1. Main H&V system off (supply a exhaust fans and dampers) (0.3)

2. CR HVAC off (0.3)

3. BP&TC exhaust fan off (and damper) (0.3)

4. Confinement Fan il starts (and damper opens) (0 3) 3.. If after set time delay, confinement fan it is not started,

. confinement fan 92 will start (and damper opens) (0.3)

REFERENCE NCSU, Ops Manual, p. 8-12 ,

ANSWER E.07 (2.00)

1. NAND gate turns off solid' state switch in magnet current loop and energizes ' scram relay' to open contact which removes magnet power. (1.0)

2. AND gate causes relay to drop out and interrupt magnet power. (1.0)

REFERENCE NCSU, Ops Manual, p. 4-18 4

E. SAFETY AND' EMERGENCY.SY' STEMS PAGE '30 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY' DOUGLAS ANSWER- E.08 (1.50)

-When the primary pump _is loste flapper falls.open (0.5) establishing a path for natural circulation (0.5). The core heat is transferred

-to the pool water and dissipated to the bay atmosphere at the pool surface (0.5). (1 5)

REFERENCE

-NCSU, Ops Manual, p. 1-6

. ANSWER E.09 (1.00)

1. Two radiation monitors on the pool bridge. (0.5)

2. Yardstick attached to overflow weir. (0.5)

REFERENCE NCSU, Ops Manual, pp. 3-4 & 4-13 9

t . *.

[

}

!~

L Fo STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE 39

[ . ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS i

ANSWER F.01 (1.50)

1. Keyswitch off for < 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (0 5)

2. No RSS maintenance performed (0.5)

3. Lons or Short Form completed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (0.5)

REFERENCE NCSU, Ops Manual, p. 3-29 l

ANSWER F.02 (2.00) i 1. > 800 pcm (0.2) - can use benchmark (0.3) (0.5)

2. < 800 pcm & > 500 pcm (0.2) - must calculate (0.3) (0.5) l

3. < 500 pcm & > 400 pcm (0.2) - DSRO permission to operate (0.3) (0.5)

4. < 400 pcm (0.2) --

scram and notify DSRO (0.3) (0.5)

REFERENCE NCSU, Ops Manual, pp. 3-36 & 37 ANSWER F.03 (1.00)

1. Last successful operation more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ago. (0.5)

2. Greater than 7 days since last Lons Form has been completed. (0.5)

REFERENCE NCSU, Ops Manual, p. 3-3 l ANSWER F.04 (2.00)

(Any FOUR at 0.5 points each)

1. Nitrogen purge pressure

2. Pulse safety disconnect removed l 3. Inspection of reactor bay area

! 4. Inspection of MER

5. Manual Evacuation

6. Confinement system delta P

! 7. S/U Channel period test

8. Reverses (Evaluate other responses against procedure) l l

l l

L

F. STANDARD AND EMERGENCY OPERATING PROCEDURES PAGE. 40 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS REFERENCE NCSU, Ops Manual, pp. 3-64 -

75 ANSWER F.05 (1.50)

a. Whether less than or greater than 10 watts. (0.5)

b. 1. If greater than 10 W, Log N compensation is set to 6 0 volts. (0.5)

2. If less than 10 W, Los N compensation is set using checklist procedure once less than 10 E 3 ces (with fission chamber fully inserted). (0.5)

REFERENCE NCSU, Ops Manual, pp. 3-37 & 38 ANSWER F.06 (2.00)

1. Verify rods ' seated' (0.2) and 'off magnet' (0.2). If not, initiate manual scram or turn.off keyswitch (0.2). (0.6)

2. Insure prompt power drop and power level decreasing (0.4) (0.4)

3. Insure follow-on reverse (0.4). If not, turn ganged insert switch to on (0.2). (0.6)

4. Inform DSRO (0.2)

5. Make los entries (0.2)

REFERENCE NCSU, Ops Manual, p. 3-51 ANSWER F.07 (1.50) ,

1. Secure the reactor (0.4)

2. Stop the primary pump (0.4)

3. Inform DSRO (0.2)

4. Attempt to isolate leak (0 4) while maintaining water over the core by any means (0.1) (0.5)

REFERENCE NCSU, Op- Manual, p. 3-52

F. STANDARD AND ENERGENCY OPERATING PROCEDURES PAGE 41 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER F.08 ( .50)

Turn off Reactor Keyswitch (0.5)

REFERENCE WCGU, Ops Manual, p. 3-57 ANSWER F.07 (2.00)

1. Check status of Confinement (0.3) - manually initiate if necessary (0.2) (0.5)

2. Evacuate BEL if (0.1)

a. CR Rad alarm (0.1)

b. 2 of 3 pool status alarms (0.1)

c. Any 2 (of 6) radiation alarms (0.1)

d. Your judgement (0.1) (0.5)

3. Inform Emergency Squad members (0.3) using 'All Call' (0.2) (0.5)

4. Verify personnel clear of bay (0 5)

REFERENCE NCSU, Ops Manual, p. 3-60

4 Go RADIATION CONTROL AND SAFETY PAGE 42 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER G.01 (1.00)

C REFERENCE 10 CFR 20.101 000/060-K1.02 (2.5/3.1)

ANSWER G.02 (1 00) d REFERENCE 10CFR20 068/000-K5.04 (3.2/3.5)

ANSWER G.03 (1.00) d REFERENCE NUS, NET, Volume 2 ANSWER G.04 (1.00) c REFERENCE Rad Health Handbook, USDHEW, p. 56 '

ANSWER G.05 (1.00)

CAF REFERENCE CAF

G. RADIATION CONTROL AND SAFETY PAGE 43 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY 00UCLAS

. ANSWER G.06 (1.00) a REFERENCE NCGU, Ops Manual, p. 2-21 ANSWER G.07 (2.00)

a. -YES (0.5)

b. NO (0.5)-

c. YES (0.5)

d. YES (0 5)

REFERENCE FNP,-Health Physics and Radiation Protection Lesson Plans, pp. 41-46.

William J. Price, Nuclear Radiation Detection, pp. 46, 77, 138, and 196 VEGP, Treining Text, Volume 9, pp. 23 42 072/00-K5.01 (2 7/3 0)

- ANSWER G.08 (1.50)

a. 4 (0.5)

b. 2 -(0.5)

c. 4 (0.5)

REFERENCE ,

Chart of the Nuclides ANSWER G.09 (1 50)

c. 1 (0.5)

b. 3 (0 5)

c. 4 (0.5)

REFERENCE NCSU, Ops Manual, Table 7-1 k.-___._________________________._____________________.____-___________._.___.____.______.___.__.__.__.__________.___.___________________________._____.____.____.._.______

r a ..'s' G. RADIATION CONTROL AND SAFETY PAGE 44

. ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS

. ANSWER G.10 (1 50)

1. Film Badse (0.5)

2. TLD (0.5) '

3. Pocket Dosimeter (0.5)

REFERENCE NCSU, Ops Manual, p. 2-21 ANSWER G.11 (1 00)

1. Person receiving sample is known (on user list) (0.5)

2. Release limited to BEL (0.5)

REFERENCE NCSU, Ops Manual, p. 2-24 ANSWER G.12 (1.50)

1. Person in charge (0.5)

2. Reactor Manager (Tom Bray) (0.5) .

3. Health Physics (0.5)

REFERENCE NCSU, Ops Manual, p. 2-22

.a ..s TEST CROSS REFERENCE PAGE 1

~00ESTION VALUE REFERENCE

.A.01 1.00 WGD0000189 A.02 1.00 WGD0000190 A.03 1.00 WGD0000514 A.04 1.00 WGD0000515 A.05 1.00 WGD0000516 A.06 1.00 WGD0000519 A.07 1.00 WGD0000520 A.08 1.00 WGD0000521 A.09 1.00 WGD0000561 A.10 1.00 WGD0000888

.A.11 1.50 WGD0000890 A.12 1.00 WGD0000669 A.13 1.00 WGD0000006 13.50 B.01 1.00 WGD0000955 0.02 1.00 WGD0000957 0.03 1 00 WGD0000958 B.04 1.00 WGD0000961 B.05 1.50 WGD0000959 B.06 1.50 WGD0000963 B.07 1.00 WGD0000956 B.08 1.50 WGD0000962 B.09 1 50 WGD0000964 0.10 1 00 WGD0000965 0.11 1 00 WGD0000960 B.12- 1 00 WGD0000966 14.00 C.01 1.00 WGD0000968 C.02 1.00 WGD0000976 C.03 1.50 WGD0000977 C.04 2.00 WCD0000974 C.05 .50 WGD0000970 C.06 2.50 WGD0000971 C.07 1.00 WGD0000969 C.08 1.00 WGD0000975 C.09 2.50 WGD0000972 C.10 1.00 WCD0000973 14.00 D.01 1.00 WGD0000262 0.02 1.00 WGD0000979 0.03 -

1.00 WGD0000980 0.04 1 00 WGD0000988 D.05 1.00 WGD0000981 0.06 1 50 WCD0000984

o.o e TEST CROSS REFERENCE' PAGE 2 GUESTION VALUE REFERENCE ~

D.07 2.00 WGD0000986 0 08 1.50 WGD0000991

'D.09 1.00 WCD0000983

'D.10 .50 WGD0000985 0.11 1.00 WGD0000989

?

0 12 2.00 WGD0000990 J 14.50

, E.01 1.50 WGD0000987 E.02 2.00 WGD0000993.

E.03 2.50 WGD0000995 E.04 2.00 WGD0000982 E.05 1.00 WGD0000992 E.06 1.50 WGD0000994 ,

E.07 2.00 WGD0000996 E.08 1.50 WGD0000997 E.09 1 00 WGD0000998 .

15 00 F.01 1 50 WGD0001001 F.02 2 00 WGD0001002 F.03 1.00 WGD0000999 F.04 2.00 WGD0001000-F.05 1.50 WGD0001003 F.06 2 00 WGD0001004 F.07 1 50 WGD0001005 F.08 .50 WGD0001006 F.09 2.00 WGD0001007 ,

14 00 G.01 1.00 WGD0000647 G.02 1 00 WGD0000648 G.03 1.00 WGD0000892 G.04 1.00 WGD0000893 C 05 1.00 WGD0000895 G.06 1.00 WGD0000896 G.07 2.00 WGD0000891 G.08 1.50 WGD0000894' G.09 1 50 WGD0000897 G.10 1.50 WGD0000898 C.11 1 00 WGD0000899 G.12 1 50 WGD0000900 15.00 100.00

s .o l

ENCIOSURE 3 (2 of 2)

U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: NORTH CAROLINA STATE UNIg.

REACTOR TYPE: TEST DATE ADMINISTERED: 86/04/24 EXAMINER: JERRY DOUGLAS APPLICANT: _________________________

INSTRUCTIONS TO APPLICANT:

Use separate paper for the answers. Write answ'ers on one side only.

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

% OF CATEGORY % OF APPLICANT'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20 0 O REACTOR THEORY

__.I.0___ _'I__.00 __ ___________ ________ H.

20.00 20.00 I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS O0 00 SPECIFIC OPERATING .-

_'I_I_0___ _'O I I.. ___________ ________ J.

CHARACTERISTICS

_ I __ _ I .____ .. __ ________ K. FUEL HANDLING AND CORE PARAMETERS 20.00 ADMINISTRATIVE PROCEDURES,

______.. 2'O.00

____ ___________ ________ L.

CONDITIONS AND LIMITATIONS 100.00 100.00 TOTALS FINAL' GRADE _________________%

All work done on this examination is my own. I have neither siv0n nor received aid.

IPPL CAUTI5~5 GUITUR5~~~~~~~~~~~~~~

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r H. RCACTOR THEORY PAGE 2 QUESTION H.01 ( 1. 0 0 ') '

Which of t,.he following is the units of heat flu::?

a. Watts / cubic centimeter

b. BTU / (he square ft)

c. Calories / gram

d. kW / ft QUESTION H.02 (1.00)

Which of the following is the correct definition of microscopic cross cection?

I a. The actual target area of the nucleus.

b. The effectivy target area of the nucleus.

c. The total actual target area of all nuclei within the core.

d. The total effective target area of all nuclei within the core.

QUESTION: H.03 / (1.00)

Which of the following can be defined as 'the number of neutrons causing fission that were originally bcisn delayed divided by the total number of

! neutrons causing fission'? .

a. Lambda effective .

l b. Rho ,

c. Beta effective

! d. Tau (um*** CATEGORY H CONTINUED ON NEXT PAGE *****)

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i e Ho- REACTOR THEORY PAGE 3 QUESTION H.04 (1.00)

Which of the following terms is defined as 'the energy equivalent of the mass defect *?

a. Excitation energy

b. Binding energy

c. Fission energy

d. Critical energy QUESTION H.05 (1.00)

Which of the following express the relationship between differential rod worth (DRW) and integral rod worth (IRW)?

a. DRW is the slope of the IRW curve at that location.

b. DRW is the area under the IRW curve at that location.

c. DRW is the square root of the IRW at that location.

d. There is no relationship between DRW and IRW.

QUESTION H.06 (1.00)

In a subcritical reactor, Keff is increased from .88 to .965. Which of ,

the following is the amount of reactivity that was added to the core?

a. .085 (8500 pcm)

b. .10 (10000 pcm) ,

c. .125 (12500 pcm)

d. .220 (22000 pcm)

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(mmmmu CATEGORY H CONTINUED ON NEXT PAGE *****)

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H. REACTOR THEORY PAGE 4 GUESTION H.07 (1.00)

Which of the following statements best characterizes Natural Cireviation?

a. It needs a pump to get started.

b. The elevation of the heat source must be above that of the heat sink.

c. The driving force is a difference in density.

d. Heat transfer is more efficient if steam is mixed with water.

QUESTION H.08 (1.00)

One of the characteristics of water is that-it will hold gases dissolved in solution. Which of the follo. wing will INCREASE the concentration of dissolved gases in a quantity of water?

a. INCREASING the pressure and LOWERING the temperature. .

b. DECREASING the pressure and LOWERING the temperature.

c. INCREASING the prescuro and RAISING the temperature.

d. DECREASING the presse.e and RAISING the temperature.

QUESTION H.09 (1.00)

Which of the following statements concerning the reactivity values of equilibrium (at power) xenon and peak (after shutdown) xenon is correct?

Assume shutdown occurs frora equiliorium conditions,

s. Equilibrium xenon is INDEPENDENT of power leveli peak xenon-is INDEPENDENT of power level.

b. Equilibrium xenon is INDEPENDENT of power leveli peak xenon is DEPENDENT on power level.

c. Equilibrium xenon is DEPENDENT on power leveli peak xenon is INDEPENDENT of power level.

d. Equilibrium xenon is DEPENDENT on power level; peak xenon l

1s DEPENDENT on power level. -

(****x CATEGORY H CONTINUED ON NEXT PAGE *****)

H. REACTOR THEORY PAGE 5 QUESTION H.10 (1.00)

The reactor is operating at 700 kW with a 10.0 degree delta T, which of

! the following is the mass flow rate?

a. 518 spm l

b. 500 spm

c. 495 spm

d. 483 spm OUESTION H.11 (1.00)

During a reactor startup (after shutdown for two weeks) with the startup source installed, the rod withdrawal is stopped at the -200 pcm position and power level stablines. Which of the following, state-ments concerning how power level will respond in the next hour, if no other actions are taken, is correct?

a. Re, actor power will remain essentially constant.

b. Reactor power will slowly decrease due to being suberitical.

c. Reactor power will rapidly decrease to initial prestartup level.

d. Reactor power will slowly increase due to long-lived delayed neutrons.

! QUESTION H.12 (1.00)

( The -1/3 DPM SUR following a reactor trip is caused by which of the following?

a. The decay constant of the longest-lived group of delayed neutrons.

b. The ability of U-235 to fission with source neutrons.

c. The amount of negative reactivity added on a trip being 3reater than the Shutdown Margin.

d. The doppler effect adding positive reactivity due to the temperature decrease following a trip.

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

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4 9 H. REACTOR THEORY PAGE 6 QUESTION H.13 (1.00)

Which of the following statements concerning the use of water as the coderator is correct?

a. Water has a HIGH scattering cross-section, a LOW absorption cross-section, and a LARGE energy decrement per collision.

b. Water has a LOW scattering cross-section, a HIGH absorption cross-section, and a LARGE energy decrement per collision.

c. Water has a HIGH scatterin3 cross-section, a LOW absorption cross-section, and a SMALL ener3y decrement per collision.

d. Water has a LOW scattering cross-section, a HIGH absorption cross section, and a SMALL energy decrement per collision.

QUESTION H.14 (1.00)

With the reactor initially at a kef.f of 0.99, a certain reactivity change causes the count rate to double. If this same amount of reactivity is again added to the reactor, which of the following will be the status of the reactor?

a. Suberitical

b. Critical

c. Supercritical

d. Prompt Critical

(***mm CATEGORY H CONTINUED ON NEXT PAGE *****)

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H. REACTOR THEOPY PAGE 7 GUESTION H.15 (1.00)

During a reactor startup, the first reactivity addition caused count rate to increase from 10 cps to 16 cps. The second reactivity addi-tion caused count rate to increase from 16 cps to 32 cps. Assuming the reactor is subcritical after the second reactivity addition, which of the following statements describing the relationship between the first and second reactivity additions is correct?

a. The first reactivity addition was larger.

b. The second reactivity addition was larger.

c. The first and second reactivity additions were equal.

d. There is not enough data given to determine relationship between reactivity values.

QUESTION H.16 (1.50)

Indicate whether the following statements are TRUE or FALSE.

a. A positive 100 pcm reactivity addition and a negative 100 pcm addition produce the same value of startup rates; only the signs are different. (0.5)

b. A delayed neutron has a higher probability of causing fission than does a prompt neutron. (0.5)

c. If a reactor is supercritical, the fraction of delayed neutrons shifts to the shorter lived precursors and the value of the average decay constant (lambda) decreases. (0.5)

00ESTION H.17 (2.00)

Indicate how (INCREASE, DECREASE, or REMAIN THE SAME) an increase in l

aoderator temperature will affect the following parameters.

i a. Resonance Escape Probability (0.5) l

b. Thermal Utilization Factor (0.5)

c. Fast Non-Leakage Probability (0.5) l

d. Fast Fission Factor (0.5)

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

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! H. REACTOR THEORY PAGE 8 QUESTION H.18 (1.50)

For the following definitions, give the term that is defined.

a. The amount of reactivity that is needed to go from hot =ero power to hot full power. (0.5)

6. The fractional change in neutron population per generation. (0.5)

c. The decay of a neutron into a proton with the simultaneous ejection of an electron (and antineutrino) from the nucleus. (0.5)

(***** END OF CATEGORY H *****)

I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 9 QUESTION I.01 (1.00)

Which of the following is a 10 CFR 20 exposure limit?

a. 5 rem / year - whole body.

b. 1 rem / quarter - whole body.

c. 18.75 rem / quarter - hands.

d. 7 rem / quarter - skin of whole body.

QUESTION I.02 (1.00)

Which of the following radiation exposures would inflict the greatest

-biological damage to man?

a. 1 Rem o'f GAMMA.

b. 1 Rem of ALPHA. .

c. 1 Rem of NEUTRON.

d. NONE of the above; they are al'1 equivalent.

QUESTION I.03 (1.00)

What would be the activity of 28 grams of Al-28? (Al-28 has a half-life of 2.24 minutes).

a. 1.95 E24 dps

b. 1.86 E23 dps

c. 3.25 E22 dps .-

d. 3.10 E21 dps (xxxxx CATEGORY I CONTINUED ON NEXT PAGE xxxxx) 1 y ,y - -

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o n Io RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 10 0UESTION I.04 (1.00)

If a point source of samma radiation gives an exposure rate of 10 mR/hr at 1 meter, what would be the exposure rate a 5 meters?

a. 2.0 mR/hr

b. 1.0 mR/hr

c. 0.4 mR/hr

d. 0.2 mR/hr QUESTION I.05 (1.00)

. When frisking with the RM-3, at what level (reading) are you considered contaminated?

a. 200 cpm-(absolute)

b. 100 cpm (absolute)

c. 100 cpm (above background)

d. 50 cpm (above background)

OUESTION I.06 (1.00)

How much radiation exposure is a minor (under 18) visitor allowed to receive?

a. 10% of the 10CFR20 limit b.. 20% of the 10ChR20 limit ,.

c. 25% of the 10CFR20 limit

d. 50% of the 10CFR20 limit

(***x* CATEGORY I CONTINUED ON NEXT PAGE xxxmm) l l

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I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 11 GUESTION I.07 (1.00)

If a contaminated person requires prompt medical attentions he should be cent to which of the following facilities?

a. The NCSU Infirmary

b. Rex Hospital

c. Wake Memorial Hospital

d. Raleigh Community Hospital QUESTION I.08 (2.00)

For the following radiation detector types, indicate whether the output intensity (current or pulse height) is proportional to the incident radiation energy; i.e., if the incident energy increases, will the out-put intensity increase? (Answer YES or NO to each part.) ,

s. Ion Chamber (0.5)

b. GM (0.5)

c. Proportional Counter (0.5)

d. Scintillation (0.5)

QUESTION I.09 (1.50)

Match the isotopes in Column A with the principal type of radiation exposure hazard in Column B. Column B choices may be used more than ~

i once each.

COLUMN A COLUMN B l

! a. Ar-41 1. Alpha

2. Beta

! b. Tritium 3. Neutron j 4. Gamma

c. N-16 5. Proton (xxxxx CATEGORY I CONTINUED ON NEXT PAGE xxxxx) l l

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I. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 12 QUESTION I.10- (1.50)

Match the radiation detector in Column A to the detector type in Column B.

COLUMN A COLUMN B

a. Control Room 1. Ion Chamber

2. Proportional Counter

b. Stack Gaseous 3. GM

4. Scintillation

c. Stack Particulate GUESTION I.11 (1.50)

What THREE individuals must sign a RWP before commencing work in-an area controlled by the Radiation Work Permit (RWP)?

QUESTION I.12 ( .50)

As the designated senior reactor operator, to what locations are you approved to release irradiated material?

1 QUESTION I.13 (2.00)

List, in order of severity (from lowest to highest), the FOUR Emergency Action Levels (EAL's) specified in the Emergency Plan.

QUESTION I.14 ( .50)

What is the most limiting site boundary for gaseous radioactive releases

from the PULSTAR stack?

l QUESTION I.15 (1.00) l For the following surveys, give the frequency they are conducted AND who conducts them.

a. Routine Radiation Survey (0.5)

b. Routine Contamination Survey (0.5)

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

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. e I. RADIDACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 13 QUESTION I.16 (1.50)

Answer the following questions concerning the Liquid Waste Control Panel.

a. Where is this panel located? (0 5)

6. What indications are on this panel? (0.5).

c. What controls are on this panel? (0.5)

GUESTION I.17 (1.00)

According to the Technical Specifications, under what TWO conditions and for how long can the Over-the-Pool monitor be bypassed?

(***** END OF CATEGORY I *****)

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J. SPECIFIC OPERATING CHARACTERISTICS PAGE 14 QUESTION J.01 (1.00)

The flow rate of the primary system is varied by which of the following cethods?

a. Adjusting the speed of the primary pump,

b. Adjusting the orifice downstream of the flow straightening tubes.

c. Adjusting the control signal from the flow transmitter.

d. Adjusting the position cf the primary pump discharge valve.

QUESTION J.02 (1.50)

Should a tube leak develop in the primary to secondary heat exchanger, which way will the leakage flow (PRIMARY-TO-SECONDARY or SECONDARY-TO-PRIMARY) for the following plant conditions?

a. Reactor a 1.0 MW, primary and secondary pump runnins. (0.5)

b. Reactor secured, primary pump runnin's and secondary pump secured. (0.5)

c. Reactor at 50 kW in natural circulation with secondary pump secured. (0.5)

GUESTION J.03 (1.50)

Answer TRUE or FALSE to the following.

e. By maintaining a constant pool temperature, T-2, the average coolant temperature increases as power level increases. ~ (0.5) f b. At 105 degrees F, xenon-free, the reactor can be taken critical with the lowest worth rod completely inserted. (0.5)

c. The normal purification flow rate is approximately 50 spm. (0.5) l (xxxxx CATEGORY J CONTINUED ON NEXT PAGE xxxxx) l l

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J. SPECIFIC OPERATING CHARACTERISTICS PAGE 15 GUESTION J.04 ( .50)

TRUE or FALSE?

The longer the reactor is run at full power, the longer it will take for xenon to peak following reactor shutdown.

QUESTION J.05 (2.00)

Indicate whether the ACP would be HIGHER THAN, THE SAME AS, or LOWER THAN the ECP for the following conditions. Consider each separately.

c. Beam Tube 2 is inadvertently filled after the ECP is calculated. (0.5)

b. The reactor is started up 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months after S/D from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 1.0 MW instead of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after shutdown. (0.5)

! c. The ACP is taken at 100 W instead of 10 W with other parameters as calculated on ECP. (0.5)

d. The primary pump is secured just prior to startup. Note: the reactor has been shutdown all weekend. (0.5)

GUESTION J.06 ( .50)

List the approximate xenon reactivity value for a startup at peak xenon following operations for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 1.0 MW.

n,.-rvenu ,m,

.._e.= Edh- . ,

t In order to use the SDM ' Benchmark" for verifying SDM on a reactor S/U, l -- c i 3ht cenditions are assumed. - List--FIVE of these- eisht' ~coner T 2.... .

OUESTION J.08 (1.50)

3. What TWO scram inputs can be automatically bypassed? (1.0)

b. When are they bypassed? (0.5)

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

. s J. SPECIFIC OPERATING CHARACTERISTICS PAGE 16 QUESTION J.09 (1.00)

Describe how the three-way mixing valve responds to an increase in the.

secondary pump suction temperature. Include in your description the native force for operating the valve.

QUESTION J.10 (1.00)

-Is the Gang rod worth LESS THAN, EQUAL T0r or MORE THAN the sum of the individual rod worths? EXPLAIN.

QUESTION J.11 (1.00)

Indicate HOW and WHY power level will initially respond to starting the

' primary pump while at 100 kW.

QUESTION J.12 (2 00)

Describe how the reactor instrumentation and protection channels would respond to BOTH a high and a low failure of the regulator supplying the flow measuring channel. Include any applicable setpoints.

QUESTION J 1? (1.50)

E:tplain how core heat is removed in the event of a loss of commerical power.

i (***** CATEGORY J CONTINUED ON NEXT PAGE *****)

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4 J. SPECIFIC OPERATING CHARACTERISTICS PAGE -17 GUESTION J.14 (2.50)

Calculate the reactivity associated with the following changes. Indicate whether this change is positive or negative. Consider each separately.

m. Pool temperature increases by 5.0 degrees F. (0.5)

b. Power level i s decreased from 1.0 MW to 700 kW. (0.5)

,. c. Startup source is removed from holder (placed on pool floor). (0.5)

d. Pneumatic sample container is inserted (rabbit in reactor). (0.5)

o. Neutron Radiography Facility is installed. (0.5) 4 3

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 18 QUESTION K.01 (1.00)

Which of the following is NOT a reason for pressurizing the fuel rods with helive?

a. Minimize clad creeping inwards toward fuel pellets.

b. Increase gap (pellet to clad) thermal conductivity.

c. Allow detection of clad failure by helium analysis of the coolant.

d. Maintain lower fuel centerline temperature.

QUESTION K.02 (1.00)

Following a reactivity insertion of +50 pcm to a suberitical reactor, the count rate will take longest to reach equilibrium if :

a. The new keff is .997 and source strength is 50 N/sec. -

b. The new keff is .999 and source strength is 50 N/sec.

c. The new keff is .997 and source strength is 100 N/sec.

d. The new keff is .998 and source strength is 100 N/sec.

QUESTION K.03 (1.00)

A 1/M curve that predicts criticality early is referred to as which of the following?

a. Useless

b. Conservative

c. Non-conservative

d. Ideal

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

T K. FUEL HANDLING AND CORE PARAMETERS PAGE 19 GUESTION K.04 (1.00)

Which of the following conditions would cause a 1/M curve to predict i criticality earlier than it will actually occur?

a. Source located too near detector.

b. Fuel assemblies loaded too far from detector.

c. Highest worth fuel assemblies loaded first.

d. Control rod located between fuel assemblies loaded and detector.

QUESTION K.05 (1.00)

The integral rod worth of Safety 42 is which of the following?

a. 3580 pcm

b. 2780 pcm

c. 2640 pcm

d. 2260 pcm GUESTION K.06 (1.00)

The Shutdown Hardin is correctly calculated by which of the following?

a. Total Rod Worth - Highest Rod Worth + Cold, Clean Excess

b. Highest Rod Worth - Cold, Clean Excess + Total Rod Worth

c. Cold, Clean Excess - Highest Rod Worth - Total Rod Worth ,

d. Total Rod Worth - Highest Rod Worth - Cold, Clean Excess

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

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K. FUEL HANDLING AND CORE PARAMETERS PAGE 20 GUESTION K.07 (1.00)

Which of the following is the bases of the maximum total energy release during Pulsing?

a. Energy density less than 470 W-sec/ gram

b. Cladding temperature less than 273 degrees F

c. No bulk boiling

d. Departure from Nucleate Boiling Ration less than 2.0 QUESTION K.08 (1 00)

The following are the boiling phases associated with nucleate boiling and departure from nucleate boiling.

1) Transition Boiling

2) Bulk Boiling

3) Film Boiling

4) Sub-cooled (Local) Boiling Which of the following is the order in which they would occur in a enannel with normal flow and high heat flux?

a. 2, 4, 3, 1

b. 2, 4, 1, 3

c. 4, 2, 3, 1

d. 4, 2, 1, 3 OLIESTION K.09 (1.00) turing fuel loading, which of the following will have NO effect on the shape of a 1/M plot?

a. Location of the neutron source in the core.

l b. Strength of the neutron source in the core.

4

c. Location of the neutron detectors around the core.

d. Order of placement of fuel assemblies in the core.

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

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K. FUEL MANDLING AND CORE PARAMETERS PAGE 21 QUESTION K.10 (2.00)

Indicate whether the following statements concerning fuel handling are TRUE or FALSE.

a. A fuel handler must be a licensed operator or a trainee under the direct supervision of a licensed operator. (0.5)

b. Unless specifically exempted by the RHP,.a Radiation Work Permit is required for fuel-handling evolutions. (0.5)

c. Loading fuel into a water hole or 'U' is NOT permitted. (0.5)

d. Having the Designated Senior Reactor Operator as the fuel handler and a Reactor Operator Assistant as the numbering and orientation observer meets the minimum required two person fuel handling crew.(0.5)

QUESTION K.11 (1.50)

Indicate whether the following parameters INCREASE, DECREASE, or REMAIN THE SAME over core life. Assume 5 x 5 Reflected Core 43 installed.

a. Maximum Axial Peak ta Average Ratio (0.5)

b. Total Core Peak to Average Ratio (0.5)

c. Power Imbalance (Absolute Value) (0.5)

GUESTION K.12 (1.00)

Fill in the blanks with the proper material.

The basic fuel module is a pin made up of _______ pellets contained"in a _______ tube.

GUESTION K.13 (1.00)

During fuel movement the control rods are ' cocked'. What TWO conditions must be met for the rods to be considered " cocked'?

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

rw K. FUEL' HANDLING AND CORE PARAMETERS PAGE 22 QUESTION K.14 (1.50)

In the event of an Evacuation signal during fuel movement, what THREE

, actions are taken by the fuel handling crew?

00ESTION K.15 (1.00)

What are the TWO Technical Specification design limits for fuel storage locations?

OUESTION K.16 (1.00)

What are the minimum radiation monitoring detectors that must be in operation during fuel handling evolutions?

OUESTION K.17 (2.00)

Given the Fuel Temperature Coefficient is -1.6 pcm/ degree F, calcualte the average fuel temperature increase when goin3 from 10kW to 1.0 MW.

Assume pool. temperature remains constant at 105 degrees F.

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(***** END OF CATEGORY K *****)

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L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 23 GUESTION L.01 (1.00)

During repair of the ventilation system, the Technical Specifications allow operation without the required negative differential pressure.

Which of the followins is the limit for this operation?

a. Power limited to 500 kW for less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

b. Power limited to 100 kW for less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

c. Power limited to 500 kW for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

d. Power limited to 100 kW for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months QUESTION L.02 (1.00)

Answer TRUE or FALSE to the followins.

a. The licensee (you) shall notify the NRC within 15 days after the occurrence of a disability. (0,5)

b. If a licensee (you) have not been actively performins the functions of a senior operator for a period of five months, you can NOT resume licensed activities without NRC concurrence. (0.5)

QUESTION L.03 (1.50)

Match the evolution in Column A to the responsible person in Column B.

COLUMN A COLUMN B

1. Insure Reactor Buildin3 secured each evening a. REACTOR SUPERVISOR

2. Approve bypass of interlocks b. DESIGNATED sRO

3. Approve operations with pulse rod in core c. RHP

4. Approve bypass of radiation monitors d. CRM

5. Allow operation with SOM of 600 pcm e. REACTOR OPERATOR I 6. Approve access to MER with reactor operatins l

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

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L. ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 24 GUESTION L.04 (2.00)

What is the minimum. required operating crew with the reactor at 1.0 MW, steady state conditions? Indicate whether each individual must be at the facility or may be on call.

QUESTION L.05 (1.00)

The operator is authorized to leave the area in front of the console to obtain replacement recorder paper. What conditions must be met in order for he/she to leave the area?

QUESTION L.06 (2.00)

The following questions concern the'PULSTAR Tag System.

e. Who may initiate red tas-outs? (0.5)

b. Who may close red tas-outs? (0.5)

c. Who may close yellow ta3-outs? (0.5)

d. What type tas-out is placed on a channel of the Reactor Safety System that is out of specification? (0.5)

GUESTION L.07 (1.00)

Assuming approval has been granted, what FIVE conditions are necessary to work on an enersi ed circuit?

, QUESTION L.08 (1.50) /

List the Safety Limits for full flow forced convection while in the Steady State mode of operations.

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La ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE 25 QUESTION L.09 (1.50)

List the following Limiting Conditions for Operations,

a. In pulse mode, maximum pulse rod travel in terms of reactivity. (0.5)

b. Maximum pneumatic rabbit reactivity insertion. (0.5)

c. Maximum rate of reactivity insertion. (0.5) 00ESTION L.10 ( .50)

Other than the Radiation Protection Council, what campus group is responsible for independent appraisals of reactor operations?

DUESTION L.11 (1.50)

What THREE conditions constitute an abnormal reactivity change? Give categories, not examples of specific events.

QUESTION L.12 (1.00)

What FOUR conditions must be met for the reactor to be considered secured?

GUESTION L.13 (2.00)

Describe the requirements to make a Temporary Change to the Operations Manual. Include any time requirements and approvals / reviews before or after implementation.

QUESTION L.14 (1.00)

What is the basis for the Limiting Safety System Setting for power while operating with natural convection flow?

OUESTION L.15 (1.50)

Give THREE examples of a Reportable Event as defined in the Technical Specifications.

(***** END OF CATEGORY L *****)

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

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H. . REACTOR' THEORY PAGE 26 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER H.01 (1.00) b REFERENCE General Physics, HT & FF, p. 229 002/000-K5.01 (3.1/3.4)

ANSWER H.02 (1.00) b REFERENCE-CP&L, Nuclear Reactor' Theory,.p. 5-2 ANSWER H.03 (1.00)

C REFERENCE NUS. Reactor Theory ANGWER H.04 (1.00) b REFERENCE CP&L, Nuclear-Reactor Theory, p. 2-15 ANSWER H.05 (1.00) a REFERENCE DPC, Fundamentals of Nuclear Reactor Engineering, p. 138 WNTO, pp. I-5.36 - 43 r 001/000-K5.02 (2.9/3.4)

H. REACTOR THEORY. PAGE 27 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY 00VGLAS

~

ANSWER H.06 (1.00) b REFERENCE NUS, Vol 3, pp 6.1-3 ANSWER H.07 (1.00) c REFERENCE General Physics, HT&FF, pp. 355 - 358 ANSWER H.08 (1.00) a REFERENCE General Physics, HT a FF, Chapter 1 ANSWER H.09 (1.00) d REFERENCE Westinghouse Nuclear Training Operations, pp. I-5.66 - 70 001/000-K5.26 (3.5/3.7)

ANSWER H.10 (1.00) d REFERENCE NCSU, PULSTAR Data Summary and Second Law of Thermodynamics l

l.

l i

I H. REACTOR THEORY PAGE 28 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER H.11 (1.00) e REFERENCE Basic Reactor Theory, Suberitical Multiplication

,s ANSWER H.12 (1.00) a REFERENCE VEGP, Training Text, Vol. 9, p. 21-47 Westinshouse Reactor Physics, pp. I-3.17 & 19 DPC, Fundamentals of Nuclear Reactor Engineerins, p. 106 001/000-K5.49 (2.9/3.4) .

ANSWER H.13 (1.00) a REFERENCE Westinghouse Reactor Physics, pp. I-2.19 - 21 HBR, Reactor Theory, Session 14, p. 3 DPC, Fundamentals of Nuclear Reactor Engineering, p. 53 001/000-K5.57 (3.0/3 2)

ANSWER H.14 (1.00) c REFERENCE HBR- Reactor Theory, Session 42, pp. 3&4 DPC, Fundamentals of Nuclear Reactor Engineerins 004/000-K5.08 (2.6/3.2) i

Ho REACTOR THEORY PAGE 29 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS -

ANSWER H.15 (1.00) a REFERENCE HDR, Reactor Theory, Sessions 41 and 42 DPC, Fundamentals of Nuclear Reactor Engineerins, pp. 121 and 122 004/000-K5.08 (2.6/3.2)

ANSWER H.16 (1.50)

a. FALSE (0.5)

b. FALSE (Power Reactor)i TRUE (Research Reactor) (0.5)

c. FALSE (0.5)

REFERENCE Westinghouse Nuclear Training Operations, pp. I-3.9 - 15 ANSWER H.17 (2.00)

a. DECREASE (0.5)

b. INCREASE (0.5)

c. DECREASE (0.5)

d. INCREASE (0.5)

REFERENCE Wes, tinh 3 ouse Nuclear Training Operations, pp. I-2.31 - 36 ANSWER H.18 (1.50)

a. Power Defect (-0.25 for power coefficient) (0.5)

b. Reactivity -( 0. 5 )

c. Beta (minus) Decay (0.5) l REFERENCE Westinghouse Reactor Physics, pp. I-5.26, I-3.2, and I-1.18 HBR, Reactor Theory, Session 32, p. 3 and Session 21, p. 2 and l Session 4, p. 2 l

l l

l

- x

't

.J s Ty<.

o 1

30 lI. RADI0 ACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS- PAGE ANSWERS -' NORTH CAROLINA-STATE UNIV.-86/04/24-JERRY DOUGLAS s

ANSWER I.01 (1.00) c REFERENCE

'10'CFR;20.101

~

~000/060-K1.02 (2.5/3.1) i ANSWER. I.02 (1.00) d #

REFERENCE J 10CFR20 068/000-K5.04 (3.2/3.5)

~

ANSWER I.03 (1.00) d REFERENCE ~ '

3 NUS, NET,' Volume 2 , -

ANSWER I.04 (1.00)

~

. C REFERENCE

Rad Health Handbooks USDHEW, p.i 56 .

ANSWER I.05 (1.0f1 i CAF

-REFERENCE ,

CAF 9

4

., ,7

-. Ul,. .

,___h

I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS PAGE 31 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER I.06 (1.00) a REFERENCE NCSU, Ops Manual, p. 2-21 ANSWER I.07 (1.00) g-b REFERENCE NCSU, Emer3ency Procedure 1.0, p. 4 ANSWER I.08 (2.00)

a. 'YES (0.5)

b. NO (0.5)

c. YES (0.5)

d. YES (0.5)

REFERENCE FNP, Health Physics and Radiation Protection Lesson Plans, pp. 41-46 William J, Price, Nuclest Radiation Detection, pp. 43 - 46, 77, 138, i and 196 VEGP. Training _ Text, Volume 9, pp. 23 42 072/00-K5.01 (2.7/3.0) j ANSWER I.09 (1.50)

a. 4 (0.5)

b. 2 (0.5)

c. 4 (0.5)

REFERENCE Chart of the Nuclides

p I.- RADI0 ACTIVE MATERIALG HANDLING DISPOSAL AND HAZARDS PAGE 32 ANSWERS - tNORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER I'.10 (1.50)

a. l' (0.5)

b. 3 ._( 0.5)

c. .4 (0.5)-

REFERENCE NCSU, Ops Manual, Table 7-1 ANSWER. I.11 (1.50)

1. Person in charse -(0.5)

2. Reactor Manager (Tom Bray) (0.5)

- -3.- Health Physics (0.5) 1 REFERENCE

~ NCSt', Ops Manual, p. 2-22 ANSWER I.12 ( .50)

Release-limited to BEL (0.5)

REFERENCE NCSU, Ops Manual, p. 2-24 ANSWER I.13 (2.00)

~

(0.3 for.EAL, 0.'2 for order) -

1. Unusual' Event (0.5)

2. Alert (0.5)

(0.5)

( 3. Site Emergency (0.5) i 14. General Emergency l REFERENCE l NCSU, Emergency Procedure 4.0, p.

1 l-F -

I l

l l

L

'I . .RADI0 ACTIVE MATERIALS HANDLING-DISPOSAL AND HAZARDS PAGE 33 ANSWERS -- NORTH. CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSW."R I.14 ( .50) 0.H. Hill' Library (0.3), 8th floor (0.2) (0.5)

. REFERENCE NCSU, Emergency Procedure 4.0, p. 2 ANSWER I.15 (1.00)

a. Monthly (+/- 7 days) (0.25) - conducted-by any qualified person (normally RHP) (0.25) (0.5)

b. Twice weekly (0.25) -

conducted by RPO (0.25) (0.5)

REFERENCE NCSU, Standing Order 444 ANSWER. I.16 (1.50)

a. Health Physics Laboratory (Room B103) (0.5)

b. Tank levels (3) (0.5)

c. 1. Inlet valve control switches (3) (0.2) (0,5)

2. Outlet valve control switches (3) (0.2)

3. Level alarm setpoints (3) (0.1)

REFERENCE NCSU, Ops Manual, p. 7-5

' ~

ANSWER I.17 (1.00)

1. During return of rabbit capsule (0.3) for less than i minute (0.2)(0.5)

2. During removal of experiments from pool (0.3) for less than 3 minutes (0.2) (0.5)

REFERENCE NCSU, TS, p. 22 I

l

j f ..,

J. SPECIFIC OPERATING CHARACTERISTICS PAGE 34 ANSWERS --~ NORTH CAROLINA STATE UNIV.-86/04/24-JEPRY.000GLAS

. ANSWER J.01 (1.~00) d REFERENCE NCSU, Ops Manual, Figure 5.1 ANSWER J.02 (1.50)

a. SECONDARY-TO-PRIMARY. (0,5) b.. PRIMARY-TO-SECONDARY (0.5)

c. SECONDARY-TO-PRIMARY (0.5)

REFERENCE NCSur' Ops Manual, pp. 5-8 and 5-17 ANSWER J.03 (1.50)

a. TRUE (0.5)

6. FALSE (0.5)

c. -FALSE '(0.5)

REFERENCE NCSUr PDS, Vol. II, pp. 4 & 13 and Ops Manuali Sections 3.& 5 ANSWER J.04 ( 50)

FALUE (0.5)

REFERENCE NCSUr PDSr Vol. II, p. 11

--__--__.__.___._m...-..._ _

J. SPECIFIC OPERATING CHARACTERISTICS PAGE' 35 ANSWERS- - NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLA9 ANSWER J.05 (2.00)

c. THE'SAME AS (0.5)

'b. . HIGHER.THAN (0.5)

c. THE'SAME AS (0.5)

d. THE SAME AS (0.5)

REFERENCE NCSU, PDS, Vol. II, p. 11 ANSWER J.06 ( .50) 150 pcm (+/- 15 pcm) (0.5)

REFERENCE NCSU, PDS, Vol. II, p. 11 d d ok,c5

-4MS"EP J ^ 7- . 2 "')/

Any FIVE at 0.5 points each

1. ~5x5 Reflected Care 13

?. . Contrcl rods banked, pulse rod at 24.0 inches

3. NRF installed 4.- BT plussed and filled

5. Pool temperature < 110 degrees F

6. Latest rod gang worth

'. PGU installed G. Less ::enon than peak af ter 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months at 1.0 Mw R$FERENCE

- N C S H , ~ P D S-,--V o+ r m -t v .13 -

ANSHER J.08 (1.50)

a. 1. Safety Power Channel (0.5)

2. Linear Power Channel (0.5)

b. During pulsing (0.5) 5

v..

J. SPECICIC OPERATING CHARACTERISTICS PAGE 36 ANSWERS ---NORTH CAROLINA STATE UNIV.-86/04/2a-JERRY DOUGLAS REFERENCE

-NCSU,r0ps Manual, p. 4-10 ANSWER -J.09 (1~.00)

A pneumatic signal.(proportional to temperature) (0.5) positions the three-way mixing valve to direct more flow to the cooling tower (less

.directly to suction of pump) (0.5) (1.0)

REFERENCE NCSU.-Ops Mar. val, p. 5-16 ANSWER J.10 (1.00)

LESS THAN (0.5) .due to rod shadowing (0.5) (1.0)

REFERENCE NSCU, PDS, Vol. II, p. 4

-ANSWER -J.11 (1 00)

Power level will increase (0.7) due to primary pump' circulating cooler-(than water in core) pool water through core (0.3). (1.0)

REFERENCE CAF ANSWER J.12 (2 00) ,.

1. HIGH - High flow indication (0.25), Low Flow reactor scram (0.25) at 23 psi regulator output (0.25) if > '150 kW . (0.25) .

(1.0)

2. LOW - Low flow indication (0.25), Low Flow reactor scram (0.25) at 475 spm (0.25) if > 150 kW (0.25)- (1.0)

-REFERENCE NCSU, Ops Manual, pp. 4-12 & 19

e,

.. 6 J .- SPECIFIC OPERATING CHARACTERISTICS .PAGE 37 ANSWERS -- NORTH CAROLINA' STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER JJ.13 (1.50)

When'the primary pump is lost, flapper falls open (0.5) establishing a path.for natural cireviation-(0.5). The core heat is transferred

-to the pool water and' dissipated to the bay atmosphere at the pool surface (0.5). (1.5).

REFERENCE.

NCSU, Ops Manual, p. 1-6 ANSWER J.14 (2.50)

(0.25 points for value, 0.25 points for sign)

a. -19.5 pcm-(+/- 2 pcm) (-3.9.x 5) (0.5)

b. +99 pcm-(+/- 5 pcm) (-330 n .3) (0.5)

c. -16 pcm (+/- 2 pcm) . (0'.5)

d. +9 pcm (+/- 1 pcm) (0.5)

e. -35 pcm (+/- 3 pcm) (0.5)

REFERENCE

'NCEU. PDS, Vol. II, pp. 15 and 16

[

E n

1 I

I

, _ . . . . . . _ . . , , , . . . ,._...m. _ . , _ , _ . . , . _, . . _ - , - . - . . . . .. . _ . - -

-K. FUEL. HANDLING AND CORE-PARAMETERS PAGE 38 a ____________________________________

ANSWERS'-- NORTH-CAROLINA STATE 1 UNIV.-86/04/24-JERRY DOUGLAS

, : ANSWER K.01- '(1.00) c REFERENCE General Physics, HT & FF, pp. 239 and 240

~

ANSWER K.02 (1.00) b REFERENCE-VEGp, Training Text, Vol. 9, p. 21-17 LANSWER K.03 (1.00),

b REFERENCE

NUS, Reactor' Theory ANSWER K.04 (1.00) c REFERENCE-Westinghouse Nuclear Training Operations, pp. I-4.19 - 21 ANSWER K.05 (1.00) ,.

d REFERENCE NCSur PDS, Vol. II, p. 4' ANSWER K.06 (1.00) d i

a i

?

l 1

L .

e, t

-4. FUEL H ANDLING. AtJD' CORE' P AR AME TERS PAGE 30

= ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY 00UGLAS

-REFERENCE-NCSur10ps Manualrlp. 3 : ANSWER' 'K.07' (1.00)

-a REFERENCE

-NCSU, TSr p.-9 .

ANSWER K.08 (1.00)

-d

~ REFERENCE NUS, Vol 4, pp 3.3-2 i Turkey Point, Thermal-Hydraulic Principles and Applications, pp. 13-17:-~20 ANSWER K 09 (1.00) b' REFERENCE-Wettinghouse Reactor Physics, pp. I-4.19 - 24 DPC, Fondsmentals of' Nuclear Reactor Engineering.-op. 120 - 129 ANSNER K.10 (2.00)

3. ' FALSE '

- (0.5)

b. FALSE (0,5)

.c. FALSE (0.5)

d. FALSE l0.5).

, REFERENCE HCSU, Special Procedure 3.2, pp. 1 -3

F' K .' ' FUEL HANDLING AND CORE PARAMETERS- PAGE 40 ANSWERS'-- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS

. ANSWER K.11 C1.50)

a. DECREASE- .(0.5)

b. DECREASE - (0,5) c.- DECREASE (0.5)

REFERENCE NCSU, PDS, Vol. II, p. 29 ANSWER K.12 (1.00)

1. Uranium Dio>:ide (0.5)

2. Ziracoly (0.5)

~ REFERENCE NCSU, Ops Manual, p. 1 -3 ANSWER K.13 (1.00)

1. Postioned at least-400 pcm below ECP (0.5)

2. Positoned at least 400 pcm withdrawn (0.5)

REFERENCE HCSU, Special Procedure 3.2, p. 1

- ANSWER K.14 (1.50)

1. Fue'l assembly in transit stored in recorded location (0.5)'

2. Fuel handling tool disconnected from fuel (0.5)

' (0.5)

3. Evacuate Reactor Bay REFERENCE NSCU. Special Procedure 3.2, p. 1

)

i i

i I

l

s. . . .

'Ko FUEL. HANDLING AND CORE PARAMETERS PAGE 41 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER K.15 (1.00)

1. - Keff less than 0.8 (0.5)

-2. Temperature less than 90 degrees C (0.5)

REFERENCE-NCSU, TS, p. 35 ANSWER K.16 (1.00)

1. 3 fi>:ed area monitors (West Wall, Over-the-Pool, VAMP, or Control Room) (0.2 points each) (0.6)

2. Stack Particulate (0.2)

3. Stack Gas (0.2)

REFERENCE NCSU, TS, p. 22-ANSWER K.17 (2.00)

Delta Tave = 13.8/2 = 6.9 degrees F (0.5)

.pcm (Delta Tave) = 6. 9 :: -3.9 = -27 pcm (0,5) pcm (Delta Tfuel) = -330 - -27,= -303 pcm (0.5)

Delta Tfuel = -303/-1.6 = 189 degrees F (0.5)

REFERENCE NCSU, PDS, Vol. II, p. 15 t

I

-- - - - - - - , , , - - - -,w -, , , . . _ _ _

C s .

'. A S M IN IS T R A T I'd M O C I: :_ _ S - C0riOITIONS ANO LIMITArIDMS CAGE 42 ANSUERS -- NORTH CAROLINA S T AT E UNIV . -8 6 /04 / 2 4--JEPRY DOUGLAS A M S '.' E R L,01 '

00' b

REFERENCE NC'J u r TS. p. 24 ANSWER L.02 /1.00)

a. TRUE (0.5)

6. TRUE (0.5)

REFERErlCE 10CFP55.41 and 10CFR55.31(e)

A t1G U E P L.03 (2.904

. ; (0.25)

2. 5 (0.25)

3. 5 (0.25)

4. b (0.25)

5. e (0.25)

6. e (0.25)

PEFERENCE NCSU, Ops Manual, pp. 2-25 a 26 and 3-36 ApsugR L.04 (2.00) .

1. 09RO (0.3) - May be on call (0.2) (0.5)

2. R0 (0.3) - At the facility (0.2) (0.5)

3. ROA 'O.31 - At the f,cility (0.2) (0.5)

4. MHP (0 35 - nr, he on es11 (0.2) (0.5)

REFEREtiCE NCSU, Ops Manual. pp. 2-4 &5

. s r.

1, ~ADnINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS PAGE. 43

' ANSWERS:-- NORTHLCAROLINA' STATE UNIV.-86/04/24-JERRY DOUGLAS ANSWER L'.05 (1',00)

1. ' Lass thon one minute in duration (0.5)

2. Reactor'in " Auto" (0.25) or rods seated (0.25) (0.5)

REFERENCE NC3Uk Ops Manual, p.-2-6 ANSWER L.06 (2.00)

e. Licensed operators (0.25) and ROAs (0.25) (0.5)

b. CRM (0.25) or RS (0.25) (0,5) c.- Inittstor (0.25) or SRO (0.25) (0.5)

d. RED (0.5) i REFERENCE .

NCSU, Ops Manuals pp. 2-17.& 18 ANSuER L~.07 (1.00) 1 Second person present (0.2)

2. Tools insulated -(0.2)

3. Safety glasses (0.2)

4. Work with one hand (0.2)

5. Insulated work mat (0.2)

REFERENCE .

f1CSur Ops Manual, p. 2-19 -

ANSWER L.08 (1.50'

1. Power (0.3) - 3.8 MW (0 2) -(0.5)

~2. Level (0.3) - 14 fr.et above top of core (0.2)- (0.5)

3. ' Inlet Temperaturo (0.3) -

120 degrees F (0.2) (0.5)-

REFERENCE I NCSUr :TSr p. 5 4

g F

^

r;

.\ .

...... ( -.

f:,

-L. 1 ADMIT'ISTRAT!VE P40CEDURES- CONOITIOr'S AMD LIFITuiI"He fGC aa Ar4SWERS -- NORTH C AROLIN A ST A TE 'Jt4IV.-96/04/24-JCRRY 00UCL AS ANSWER L.09 (1,50) a.. 1720 pcm (0,5).

b. 300.pcm (0i5)

'100 pcm/sec (0,5)'

c ._

REFERENCE NCSU, TS, p. 14 ANSWER L.'10 ( .50)

Reactor Safeguards Advisory Group (RSAG) (0i5)

REFERENCE

.NCSU, TS, p. 40 ANSWER L.11 (1.50)

1. ACP not within 200 pcm of ECP (0 5)'

2. . Unanticipated change (100 pcm) in reactivity (0,5).

3. Significant variation in reactivity.value of experiment (0,5)

REFERENCE NCSU,' Ops Manual, p. 3-54

.ANS4ER L.12 (1.00)

1. Reactor shutdown .. (0.25)

2. Magnet power off (0.2)~and key removed (0.05) (0.25)

'3 . Flapper open.(0 1),'or, when closed, primary pump. operating at 500 gpm (0.15) (0.25)

4. No work involving fuel (0.1), in-core experiments (0.05), or rods (0.1) (0.25)

REFERENCE

'HCSU, TS, p. 1

F:-

t e:.. .

L. abd!NISTRATIVE'*ROCEDURES, CONDITIONS AND LIMITATIONS '* AGE 45 ANSWERS -- NORTH CAROLINA STATE UNIV.-86/04/24-JERRY 00UGLAS ANSWER L.13 /.2.00) 1.~ Do not change original intent (0.4)

2. Approved by NOA-(AO) prior. to implementation (0.4) 3.- ' og of Temporary Changes in Operations Manual (0.4)

4. . Maximum use of two months (0.4)

'5. Submitted to RPC-within two months (0.4)

REFERENCE NCSU, Ops Manual, p. 2-12 ANSWER L.14 (1.00)

Minimize N-16 release (0.7) aided by steam bubble rise during opflow during natural convection (0.3) (1.0)

REFERENCE NCSU, TS, p. 11 ANSWER L.15 (1.50)

(Any THREE at 0.5 points each)

1. SSS less conservative than LSSS

2. Violation of LCO

3. Incident which prevented (or could have) intended safety function of ESF or RSS

4. Release of fission products-from fuel

5. Uncontrolled or .inanticipated change in reactivity .

6. Inadequacy of procedural controls REFERENCE NCSU, TS, p. 2

.S

,.w TEST CROSS REFEPENCE PAGE 1 QUESTION VALUE REFERENCE H.01 1.00 WGD0000192 H.02 1.00 WGD0000515

-H.03 1.00 WGD0000518 H.04 1.00 WGD0000519 H.05 1.00 WGD0000520

'H.06 1.00 WGD0000561 H.07 1.00 WGD0000599 H.08 1.00 WGD0000665 H.09 1.00 WGD0000668 H.10 1.00 WGD0000883 H.11 1.00 WGD0000976 H.12 1 00 WGD0001026 H.13 1.00 WGD0001027 H.14 1.00 WGD0001028 H.15 1.00 WGD0001029 '

H.16 1.50' WGD0000660 H.17 2.00 WGD0000659 H.18 1.50 WGD0000418 20.00 I.01 1.00 WGD0000647 I.02 1.00 WGD0000648 I.09 1.00 WGD0000892

'I . 0 , 1.00 WGD0000893 I.05 1.00 WGD0000095 I.06 1.00 WGD0000896 I.07 1.00 WGD0001032 I.08 2.00 WGD0000891 ,

I.09 1.50 WGD0000894 I.10 1.50 WGD0000897 I.11 -1.50 WGD0000900 I.12 - . 50 WGD0001030 I.13 2.00 WGD0001031 1.14 .50 WGD0001033 I.15 1.00 WGD0001034 I.16 1 50 WGD0001035 I.17 1.00 WGD0001036 20.00 J.01 1.00 WGD0000957 J.02 1.50 WGD0000959 J.03 1.50 WGD0000977 J.04 .50 WGD0001037 J.05 '

2.00 WGD0000974 J.06 .50 WGD0000970 J.07 2.50 WGD0000971 J.08 1.50 WCD0000987 J.09 1.00 NGD0000960

..o-..

TEST CROSS REFERENCE PAGE 2

'00ESTION' -VALUE REFERENCE J.10 l'.00' WGD0000949.

'd .11 - 1 00 UG000004'5 TJ.12 2 30 4GD9900932

.) . *3 1 50 WGD0000997 M.14 2 . *2 0 ' WGD0000972 20.00 K.01 1.00 WG00001048 K'. 0 2 ' 1.00 WGD0000101 K.03 1 00 WGD0000517 K.04' 1.00 .WGD0000463 K.05 1.00 WGD0001043 K.06 1.00 WGD0001044 K.07 1l00' WGD0001047 K.08. 1.00 4GD0001049 K.09 1.00 WGD0001050 K.10 2.00 WGD0001040

.K.11 1.50 WGD0001046 K.12 1.00 4GD0000956 K.13 1.00 WGD0001038

'tf ,14 1.50 WGD0001030 K.15 1.00 WGD000LO41

K .16 - 1.'00 WCD0001042 K.17 2.00 WGD0001045 20.00 L.01 1.00 WGD0001060 L.02 1.00 WGD0001065 '

L.C3 1.50 WGD0001056 L.04 2 00 WGD0001051 L.05 1.00 WGD0001052 L.06 2 00 WGD0001054

-L.07 1.00 WGD0001055 L.08 1.50 WCD0001057 L.09 1.50 WGD0001059 L 10 .50 WGD0001061 L.11 1 50 WGD0001062 L.12 1.00 WGD0001063 L.13 2.00 WGD0001053 L.14 1.00 WG00001053 L.15 1.50 WGD0001064 20.00 i 100.00 3

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