Text

Exam Rept 50-002/OL-93-04 on 931207-08.Exam Results: One RO & Two Sroi Were Administered Exam & Operating Test. All Candidates Passed
	ML20059K864
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Site:	University of Michigan
Issue date:	12/27/1993
From:	Caldwell J, Issac P; Office of Nuclear Reactor Regulation
To:	;
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	50-002-OL-93-04, 50-2-OL-93-4, NUDOCS 9402020314
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l ENCLOSURE I

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i U. S. NUCLEAR REGULATORY COMMISSION i

OPERATOR LICENSING INITIAL FXAMINATION REPOR1 4

j REPORT NO.:

50-002/0L-93-04 j

FACILITY DOCKET NO.:

50-002 j

FACILITY LICENSE NO.:

R-28 l

j FACILITY:

University of Michigan l

EXAMINATION DATES:

December 7-8, 1993 I

CXAMINER:

Patrick Isaac, Chief Examiner SUBMITTED BY:

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APPROVED BY:

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Jafes L. Ca5dw H1, Chief

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i Nyn-PowerReactorSection j

Operator Licensing Branch j

Division of Reactor Controls i

and Human Factors 4

Office of Nuclear Reactor Regulation 4

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SUMMARY

i NRC administered written examination and operating tests to one Reactor i

Operator (RO) and one Senior Reactor Operator Instant (SROI) candidate.

l A retake of section A of the written examination was administered-to one R0 candidate. Operating tests were also administered to one Senior Reactor j

Operator Upgrade (SROU) candidate. All applicants passed their respective j

portion of the examinations and have been issued the appropriate license.

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. REPORT DETAILS 1.

Examiners:

Patrick Isaac, Chief Examiner 2.

Results:

R0 SR0 Total (Pass / Fail)

(Pass / Fail)

NRC Grading:

2/0 2/0 4/0 3.

Written Examination:

The written examination was administered on December 7, 1993 to one R0 and one SROI candidate. A retake of section A was administered to one additional RP candidate. At the conclusion of the examination, the proctor immediately secured the master examination answer key and all the candidate answer sheets. A copy of the master "as given" examination with answer key was given to the Reactor Supervisor for his formal review.

During the administration of the written examination, the proctor identified the omission of part of question A-013. The candidates were asked to disregard question A-013. The examination answer key was later corrected to reflect this change.

The facility's written examination comments and the NRC's resolution to those comments are found in Enclosure 2.

All applicants passed the written examination.

4.

Operating Tests:

Operating tests were administered on December 8, 1993 to one R0, one SROI and one SR00 candidate.

l All candidates passed the operating tests.

5.

Exit Meeting:

Personnel attending:

Mr. Bernard Pierre Ducamp, Assistant Manager FNR Lab.

Mr. Marvin Mendonca, NRC Mr. Patrick Isaac, NRC The exit meeting was conducted on December 8, 1993.

Some of the facility examination comments were discussed as noted in Enclosure 2.

Mr. Ducamp commented on what he thought was a challenging examination.

1

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ENCLOSURE 2 NRC RESOLUTIONS - WRITTEN EXAMINATION SECTION A OVESTION A.11 Which one of the following is the definition of Shutdown Margin?

l Shutdown margin is the amount of negative reactivity

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a.

which would be inserted into the core if rods were dropped from j

the fully withdrawn position, with the exception of one rod which remains stuck at the fully withdrawn position b,

which would be inserted into the core if rods were dropped from critical rod height, with the exception of one rod which remains stuck at the fully withdrawn position c.

which would be inserted into the core if all the rods were fully inserted in the reactor.

d.

inserted by an increase in moderator temperature within the core when the reactor is brought from zero to full power.

ANSWER A.11 c.

FACILITY COMMENT A.11 Both answers b. and c. are correct. Shutdown margin is defined with all i

three shim-safety rods inserted and with the most reactive shim-safety rod stuck fully out.

Ref:

Ford Nuclear Reactor Technical Specifications, section 3.1.1.

"The shutdown margin relative to the cold, xenon free, critical condition shall be at least 0.025 delta K/K with all three shim-safety rods fully inserted and the regulating rod fully withdrawn and 0.0045 delta K/K with the most reactive shim-safety rod and the regulating rod fully withdrswn..."

Ref:

INTRODUCTION TO NUCLEAR REACTOR OPERATIONS, Chapter 6, page 6-4, section 6.2.3

" Shutdown margin, SDM, is the amount of negative reactivity that would be inserted into a reactor core if all rods were dropped from critical height. Technical Specifications for a reactor specify the minimum value of SDM if all rods are inserted and if one rod remains stuck in the fully withdrawn oosition."

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In fact, the stuck rod shutdown margin is the limiting SDM for our reactor in terms of fuel loading and critical rod heights.

The two i

operators who chose answer b. chose it because they knew both definitions were correct, but the stock rod SDM was most limiting and 1

important to our operation.

NRC RESOLUTION A.ll l

As stated on page 6-4 of INTRODUCTION TO NUCLEAR REACTOR OPERATIONS, the actual amount of negative reactivity by which the reactor is shutdown or shutdown margin is defined as:

...the amount of negative reactivity that would be inserted into a reactor core if all rods wire drooped from critical heiaht." The definition provided in the Technical Specifications (T.S.)

describes the " minimum value of SDM if all rods are inserted and if one rod remains stuck in the fully withdrawn position."

The staff understands that the T.S. definition is most limiting and, as recommended in the facility's comment, will accept both answers b. and c. as correct.

I OUESTION A.16 Which one of the following is correct regarding subcritical count rate?

The subcritical count rate is directly proportional to the sourcc rate and inversely a.

proportional to the departure from criticality.

b.

directly proportional to the source rate and K,g.

c.

inversely proportional to the source rate Lad directly 1

proportional to K en-1 d.

inversely proportional to the source rate and K,g.

ANSWER A.16 a.

FACILITY COMMENT A.16 Both a. and b. are correct.

Ref:

Ford Nuclear Reactor Examination Question Bank, Section A, Page A-341. l

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The exam bank question is enclosed. This was taken from an NRC examination of a few years ago. As you can see. the correct answer to the question is that subcritical counts are directly proportional to both S and Keff.

Ref:

INTRODUCTION TO NUCLEAR REACTOR OPERATIONS, page 5-5, section 5.3 and page 5-35, question 5.7.16.

C - S/(1-K)

As S increases, C increases.

As K increases, (1-K) decreases. Since (1-K) is in the denominator, C increases. Thus, C is directly proportional to S and K.

Confusion amy have arisen on the part of our_ operators with regard to answer a. because of your use of the term " departure from criticality".

1 We do not use those words tu express (1-K).

In fact, (K-1) is departure from criticality.

(1-K) would more properly be called negative departure from criticality.

NRC RESOLUTION A.16 The staff agrees with your comment. The answer key has been corrected to reflect (a) and (b) as acceptable answers.

OVESTION C.3 The reactor is operating with the linear level-servo control system maintaining power at 1 MW. High voltage is then lost to the compensating-I circuit of the control system Compensated Ion Chamber.

Which one of the following describes the response of the plant to this malfunction?

a.

Indicated power will decrease, resulting in the linear level-servo control system dropping out of automatic control, b.

Indicated power will decrease, resulting in the control rods.being j

withdrawn from the core at normal speed.

Indicated power will increase, resulting in the control rods being c.

driven inward at normal speed.

d.

Indicated power will remain constant.

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ANSWER C.3 d.

FACILITY COMMENT U None of the answer is correct, but from among the choices c. is the best.

The facility has performed this experiment many times in training and in laboratory experiments. When compensating voltage (approximately 5 vdc) is turned off, the electronics in the amplifier resist the loss of voltage similar to a capacitor resisting a change in circuit voltage.

Indicated power surges upward dramatically (25% or more). The automatic control system attempts to maintain indicated power by inserting the regulating rod. Unable to keep up, the system drops out of auto control.

Eventually (several minutes), the circuit transient dies out, and indicated power will return to its original value plus approximately 5% because the system is now seeing both neutrons and gammas. The effect is major, contrary to what theoretical texts might state conceptually. We would be happy to demonstrate for you.

NRC RESOLUTION C.3 The answer key has been modified to accept c. as correct.

QUESTION C.10 Primary coolant flow rate is indicating 75 percent of scale. The diaphragm for D/P 2 (Primary flow measuring channel 2) ruptures. Which one of the following describes the result of the failure of D/P 27 a.

No effect.

i b.

Primary flow will go to 100 percent (full scale) i 1

c.

Reactor trips on Hdr Up/No Flow i

d.

Reactor trips on Hi Pwr/No Flow ANSWER C.10 d.

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FACILITY COMMENT C.10 The answer is correct, but which trip signal comes off which D/P cell has no significance. As you saw when you were here, none of the licensed operators including me knew the answer without looking it up in the System Descriptions.

If the examinees answered correctly, it was just a lucky guess.

This type of question does not test their ability to safely operate the reactor.

NRC RESOLUTION C.10 Comment noted. No change to the examination grading is required.

ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY:

Univ. of Michigan REACTOR TYPE:

FNR DATE ADMINISTERED:

1993/I2/07 REGION:

'III CANDIDATE:

INSIRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheet provided. Attach the answer sheets to.the examination.

Points for each question are indicated in paren--

i theses for each question. A 70% in each section is required to pass the exanination.

Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 19.00 31.67 A.

REACTOR THE0RY, THERMODYNAMICS AND FACILITY OPERATING-CHARACTERISTICS 20.00 33.33 B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 21.00 35.00 C.

PLANT AND RADIATION MONITORING SYSTEMS 60.00 TOTALS i

FINAL GRADE J

All work done on this examination is my own.

If have neither given nor received aid.

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.

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

3. Restroom trips are to be limited and only one candidate at a time may leave.

You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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

5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

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

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

8. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.

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

10. Partial credit will NOT be given.

11. If the intent of a question is unclear, ask questions of the examiner only.

12. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.

If you are found in this area while the examination is still in progress, your license may be denied or revoked.

Section A R Theory. Thermo & Fac. Operatino Characteristics Page 3

QUESTION (A.1)

[1.0]

An experiment requires that power be ramped from 15 watts to 500 kilowatts on a 45 second period.

Which one of the following will be the elapsed time to reach 500 kilowatts for this ramp?

a.

157.6 seconds b.

243.0 seconds c.

365.0 seconds d.

468.6 seconds

QUESTION (A.2)

[1.0]

Which one of the following figures most closely depicts the reactivity versus time plot for xenon for the following sequence of evolutions:

TIME EV0LUTION 1

2 MW startup, clean core; 2

Operation at 2 MW for four days; 3

Shutdown for 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months ; 4

1 MW for 29 hours3.356481e-4 days 0.00806 hours 4.794974e-5 weeks 1.10345e-5 months , a.

b.

c.

d.

(See attached figures for choice selections.)

QUESTION (A.3)

[1.0]

Given the following:

Moderator temperature coefficient:

-1.0 x10 AK/K/*F Control rod worth:

0.003 AK/K/ inch The reactor is operating in automatic at 300 KW. The moderator temperature decreases slowly by 18'F.

Which one of the following is the direction and distance that the control rod will move to compensate for the change in temperature?

a. The control rod moves in 0.3 inches.

b. The control rod moves out 0.3 inches.

c. The control rod moves in 0.6 inches.

d. The control rod moves out 0.6 inches.

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Section A R Theory. Thermo & Fac. Operatina Characteristics' Page 4 3.

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QUESTION (A.4)

[1.0]

During reactor operation at 2 MW, one shim rod with a total worth of. 3%

scrams into the reactor.

Which one of the following is the stable reactor power level after the transient?

a. 388 KW

b. 412 KW

c. 647 KW

d. 689 KW i

QUESTION (A.5)

[1.0]

With the reactor on a constant period, which transient requires.the longest time to occur?

a.

5% power -- going from 1% to 6% power:

b.

10% power -- going from 10% to 20% power c.

15% power -- going from 20% to 35% power d.

20% power -- going from 40% to 60% power

QUESTION (A.6)

[1.0]

The operator is approaching criticality by a pull' and wait procedure.

Which one of the following describes the time required for the startup instrumentation to level out at each subcritical level?

Longer periods of time with each successive pull due to larger a.

subcritical multiplication factors at higher neutron levels b.

Shorter periods of time with'each successive pull due to larger subcritical multiplication factors at higher neutron levels Longer periods of time with each successive pull due to smaller c.

subcritical multiplication factors at higher neutron levels d.

Shorter periods of time with each successive pull due to smaller subcritical multiplication factors at higher neutron levels

=

6 Section A R Theory. Thermo & Fac. Operatina Characteristics Page 6

QUESTION (A.7)

[1.0]

The reactor is operating at 500 kilowatts.

j Which one of the following is the INITIAL reactor period which would result r

from a 10*F decrease in moderator temperature?

i The following data is provided:

i Decay constant 0.1 sec-1

=

Effective delayed neutron precursor fraction

.0075

=

-1.5 x 10 AK/K/F Temperature coefficient of reactivity a.

25 seconds b.

30 seconds c.

35 seconds d.

40 seconds

QUESTION (A.8)

[1.0]

The reactor is subcritical with a reactor startup in progress. The reactor i

operator notices a significant change in neutron count rate while withdrawing a peripheral control rod. The operator next withdraws a center control rod 1

and observes a very small increase in neutron count rate.

Which one of the following would explain these observations?

a.

The rod at the center of the core is in an area of higher neutron flux as compared with the periphery of the core, resulting in greater rod worth for the center control rod.

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b.

The rod at the periphery of the core is in an area of higher neutron flux as compared with the center of the core, resulting in greater rod worth for the peripheral control rod.

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c.

The rod at the center of the core is in an area of higher neutron flux as compared with the periphery of the core, resulting in greater rod worth for the peripheral control rod.

d.

The rod at the periphery of the core is in an area of higher neutron flux as compared with the center of the core, resulting in greater rod worth for the center control rod.

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Section A R Theory. Thermo & Fac. Operatina Characteristics Page 7

QUESTION (A.9)

[1.0]

The reactor is shutdown by 5%6k/k with a court rate of 100 cps on the startup channel. Rods are withdrawn until the count rate is 2000 cps. After the rods are withdrawn, the reactor is a.

supercritical with K,,, - 1.05 b.

supercritical with K,,, - 1.002 suberitical with K,,, equal to 0.998 c.

d.

subcritical with K,,, equal to 0.952

QUESTION (A.10)

[1.0]

Which one of the following is a correct statement concerning the factors affecting control rod worth? Assume constant reactor power.

a.

Moderator temperature increase causes rod worth to decrease.

b.

Fuel burnup causes the rod worth to decrease in the center of the core.

c.

Samarium concentration increases over core life causing the rod worth to decrease in the periphery rods.

d.

The withdrawal of an adjacent rod causes the rod worth of the stationary control rod to decrease.

QUESTION (A.11)

[1.0]

Which one of the following is the definition of Shutdown Margin?

Shutdown margin is the amount of negative reactivity a.

which would be inserted into the core if rods were dropped from the fully withdrawn position, with the exception of one rod which remains stuck at the fully withdrawn position b.

which would be inserted into the core if rods were dropped from critical rod height, with the exception of one rod which remains stuck at the fully withdrawn position c.

which would be inserted into the core if all the rods were fully inserted in the reactor.

d.

inserted by an increase in moderator temperature within the core when the reactor is brought from zero to full power.

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Section A Re Theory. Thermo & Fac. Operatina Characteristics Page 8

QUESTION (A.12)

[1.0]

Reactor power decreases on a stable negative period after a reactor scram, i

following an initial prompt drop. Which ONE (1) of the following is the reason for this?

a.

All prompt neutrons decay during the prompt drop, and the subsequent rate of power change is dependent ONLY on the half-life of the longest lived prompt gamma emitter.

b.

This rate of power change is dependent on the MEAN 'ifetime of the shortest lived delayed neutron precursor.

c.

This rate of power change is dependent on the MEAN lifetime of the longest lived delayed neutron precursor.

d.

This rate of power change is dependent on the CONSTANT decay rate of prompt neutrons following a scram.

J

QUESTION (A.13)

[1.0] DELETED During a critical loading experiment, the neutron source and detector are loaded as shown in Figure 1.

The fuel is loaded first at position 1, with each successive fuel element being positioned closer to the neutron detector until finally, fuel element 5 is put in place.

Which one of the following describes the correct shape of the 1/M plot and the i

implications of loading fuel in this manner?

a.

The 1/M plot is depicted in Figure 2.

The actual critical mass will be less than that predicted by the 1/M plot.

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b.

The 1/M plot is depicted in Figure 3.

The actual critical mass will be less than that predicted by the 1/M plot.

c.

The 1/M plot is depicted in Figure 2.

The actual critical mass will be greater than that predicted by the 1/M plot.

d.

The 1/M plot is depicted in Figure 3.

The actual critical mass will be greater than that predicted by the 1/M plot.

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Section A R Theory. Thermo & Fac. Operatina Characteristics Page 9 i

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QUESTION (A.14)

[1.0]

i The following data was obtained during a reactor fuel load.

i No. of Elements Detector A (cos) 0 20 8

30 16 40 22 60 24 90 26 155 Which one of the following is the number of fuel elements required to.make the reactor critical? (The attached figure may be used to determine the correct j

response.)

i a.

16 b.

24 c.

28 1

d.

32 1.0 O.9 ;

0.8 '

O.7 1 0.6 M 0.5 i

0.4 0.3 I

0.2 0.1 l

0.0 2

4 6

8 10 12 14 16 18 20 22 24 26 28 30 32 NUMBER OF ELEMENTS INSTALLED l

QUESTION (A.15)

[1.0]

)

Which one of the following could result from an attempt to start up the 1

reactor with N0 installed neutron source?

a.

The reactor could not be started up because there would be no source of neutrons to start the chain reaction.

b.

It is possible that reactor power would not be indicated on the nuclear instrumentation until after the reactor has reached a very high power level.

c.

Subcritical multiplication would result in a stable count rate on the nuclear instrumentation even though power was increasing.

d.

Startup of the reactor would require increasing the voltage on the source range detectors to establish a count rate from photoneutrons.

1 Section A R Theory. Thermo & Fac. Operatino Characteristics Page 10

QUESTION (A.16)

[1.0]

Which one of the following is correct regarding subcritical count rate?

The subcritical count rate is a.

directly proportional to the source rate and inversely proportional to the departure from criticality.

b.

directly proportional to the source rate and K,,,.

c.

inversely proportional to the source rate and directly proportional to K,,,.

d.

inversely proportional to the source rate and K,,,.

QUESTION (A.17)

[1.0]

Which one of the following describes the location in the core where the peak fuel temperature is observed?

a.

At the core midplane because this is where the maximum peak heat generation is found.

b.

At the top of the core because this is where the worst combination of heat generation and coolant temperature occurs.

c.

Between the core midplane and the bottom of the core because this is where the worst combination of heat generation and coolant temperature occurs.

d.

At the bottom of the core because this is the area where coolant temperature is the greatest.

QUESTION (A.18)

[1.0)

Assume reactor power is held steady at 2 MW.

Which one of the following describes the change in radial flux pattern over core life?

a.

The flux pattern becomes more peaked in the center due to the withdrawal of control rods from the core.

b.

The flux pattern becomes more peaked in the center due to fuel depletion near the periphery of the core.

c.

The flux pattern becomes flatter due to the withdrawal of control rods from the core.

d.

The flux pattern becomes flatter due to fuel burnup near the center of the core.

Section A R Theory. Thermo & Fac. Operatina Characteristics Page 11

QUESTION (A.19)

[1.0]

The shutdown margin (SDM), upon full insertion of all control rods following a reactor scram from full power, is the SDM immediately prior to the scram.

a.

Equal to b.

Less than c.

Greater than d.

Independent of

QUESTION (A.20)

[1.0]

The reactor has been operating at 100% power for the past 20 days.

Which one of the following is the primary source of heat generation in the core 30 seconds following a reactor scram from 100% power?

a.

Fission from the longest lived delayed neutron precursors.

b.

Fission resulting from installed source neutrons.

c.

Beta and gamma heating from fission decay products.

d.

Beta and gamma heating from fission generated by installed neutron sources.

I

(** End of Section A **)

Section B Normal /Emero. Procedures & Rad Con Page 12

QUESTION (B.1)

[1.0]

In determining the T.S. limit on the allowable value for excess reactivity, which ONE one of the following was NOT considered?

a.

Reactivity effects of fission product Xenon and Samarium buildup in a clean core.

t b.

Preclude a stable reactor period of less than 30 seconds.

c.

Power defect due to increasing from a zero power, cold core to a 2 MW, hot core.

d.

Overcome the reactivity effects of moveable experiments.

QUESTION (B.2)

[1.0]

The following qualified operator has been assigned to enter a radiation area that is reading 75 mrem /hr.

Male, 24 years old Current week exposure is O millirem Current quarter exposure is 1025 millirem Current year exposure is 4850 millirem j

Current lifetime exposure is-28,900 millirem Current exposure history on file.

No special extensions have been approved for this quarter Which one of the following is the MAXIMUM stay time in the radiation area before the operator will exceed Federal whole body exposure limits?

a. I hour

b. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

c. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

d. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

QUESTION (B.3)

[1.0]

A radioactive sample was removed from the reactor core, reading 40 Rem / hour.

Four (4) hours later, the sample reads 4 Rem / hour.

Which one of the following is the time required for the sample to decay from 4 Rem /hr to 100 mrem / hour?

a.

1.9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months b.

5.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months c.

6.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months d.

10.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Section B Normal /Emero. Procedures & Rad Con Page 13 1

QUESTION (B.4)

[1.0]

Which one of the following would be posted on an entry to an area with a dose rate of 17 mrem /hr.

a. CAUTION - RADIATION AREA

b. CAUTION - HIGH RADIATION AREA

c. CAUTION - AIRB0PNE RADIATION AREA

d. CAUTION - RADI0 ACTIVE MATERIALS

QUESTION (B.5)

[1.0)

You have been assigned to decrease the dose rate being emitted by a point source. The dose rate is due to 1.5 Mev gamma. What thickness of lead will be required to decrease the dose rate by a factor of 107 Given:

Mass attenuation coefficient for lead 01.5 Mev = 0.5814 cm" a.

0.2 cm b.

2 cm c.

4 cm d.

8 cm

QUESTION (B.6)

[1.0)

Which one of the following would indicate ABNORMAL operation of the Mobile Airborne Particulate (MAP) Monitor?

a.

Pump power pilot light lit.

b.

Air flow is 4 cfm.

c.

Rate meter response switch is selected to SLOW d.

PF and BHF scale multiplier is on the X10 scale 1

l Sgction B Normal /Emero. Procedures & Rad Con Page 14 i

I

QUESTION (B.7)

[1.0)

It is April 1, 1994. You have stood watch for the following hours during the l

last quarter:

j Jan. 11, 1994 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Feb. 24, 1994 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Mar. 16, 1994 1.0 hours0 days 0 hours 0 weeks 0 months e

What requirements must you meet in order to stand an R0 watch today?

a.

None. You've met the minimum requirements of 10 CFR 55.

b.

You must perform 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of shift functions under the direction of a licensed operator or licensed senior operator as appropriate.

c.

You must perform 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of shift functions under the direction of a licensed operator or licensed senior. operator as appropriate.

{

d.

You must submit a new application form to the NRC requesting a waiver to i

reactivate your license.

QUESTION (B.8)

[1.0]

Which ONE of the following statements is applicable when fuel handling is in progress at the FNR?

During fuel movement, the fission chambers should be moved only a.

when direct communication is established between the control room 1

and the bridge.

i b.

During fuel movement, all heavy water transfers should be supervised by a SR0 other than the Fuel Movement Coordinator, c.

The control console operator grants specific permission to unlatch the fuel tool from elements inserted into the core.

d.

The control cons @ operator will be responsible for maintaining the Fuel Logbook.

l e

---e.m

-ewa-

,,i w m~s5-w.4e--

Section B Normal /Emera. Procedures & Rad Con Page 15

QUESTION (B.9)

[1.0]

Reactor conditions are as follows:

i Reactor power 400 KW Reactor coolant inlet temperature 138'F i

Pool water height (above core) 18.5 feet

]

Natural convection mode i

Which one of the following lists the fuel cladding integrity safety limits l

that have been exceeded?

i a.

Reactor power and reactor coolant inlet temperature b.

Reactor power and water height l

c.

Water height ONLY d.

Reactor coolant inlet temperature ONLY

QUESTION (B.10)

[1.0]

Which one of the following describes the reason why shutdown margin is measured with the reactor critical at low power?

a.

To minimize the negative reactivity contribution from temperature coefficient effects.

b.

To minimize xenon burnout at higher neutron fluxes.

l c.

To ensure that the entire shutdown margin is due to the shim-safety rods alone.

d.

To minimize the effects of the installed neutron source.

I

QUESTION (B.11)

[1.0]

l A calorimeter is conducted at 100% indication on the Linear Level 1 Mw scale.

Actual power based on the calorimeter is determined to be 1.3 Mw.

What would i

be the correct linear level setpoint for 1 Mw.

j a.

103%

~

b.

95.7%

i c.

90.9%

d.

76.9%

P i

Section B Normal /Emero. Procedures & Rad Con Page 16

QUESTION (B.12)

[2.0]

Match the conditions in Column I with their Technical Specification Reactivity Limits in Column II.

Items in Column B may be used once, more than once or not at all. Only one response may occupy a single answer space. (0.50 points per response).

Column I Column II I

(Conditions)

(Tech Spec Limits)

a. Maximum reactivity worth of a movable

1. 0.0012 ok/k i

experiment.

2. 0.006 ok/k

b. Maximum reactivity worth of the regulating rods.

3. 0.012 ok/k

c. Maximum total reactivity worth of all

4. 0.025 ok/k experiments.

5. 0.038 ok/k

d. Maximum overall core excess reactivity worth, including moveable experiments.

6. 0.0436 ok/k I

QUESTION (9.13)

[1.0]

An area radiation monitor and a MAP monitor are both alarming.

Which one of the following describes the reactor operator's first required action?

Shut the reactor down by running in all control rods, a.

b.

Notify the Nuclear Reactor Laboratory Manager.

Scram the reactor when either a second area radiation monitor or c.

MAP alarm is received.

d.

Notify the On-call Supervisor.

l I

l

Section B Normal /Emera. Procedures & Rad Con Page 17

QUESTION (B.14)

[1.0]

A fire has occurred at the FNR and a building evacuation is in progress in accordance with EP-101, Reactor Building Emergency. The control room operator has arrived in the lobby and notes that the piant operator has not arrived in the lobby within a reasonable amount of time.

Which one of the following actions should the control room operator take?

a.

Proceed to the south side entrance door and await the fire department.

b.

Attempt to locate the plant operator by retracing the plant operator's prescribed route.

c.

Dial 911 and report to Public Safety and Security that the plant operator has not yet reported to the lobby.

d.

Await the fire department in the lobby and inform them that the plant operator has not yet reported.

4

QUESTION (B.15)

[1.0]

A reactor startup is in progress in accordance with OP-101, Reactor Startup.

All shim-safety rods have just been withdrawn to the shim range point.

Which one of the following indications should be observed on the LCR?

Count rate should have increased by less than two (2) decades, a.

indicating that the reactor is subcritical.

b.

Count rate should have increased by less than two (2) decades indicating that the reactor is critical on delayed neutrons.

Count rate should have increased by greater than u (2) decades c.

indicating that the compensated ion chambers are functioning

properly, d.

Count rate should have increased by greater than two (2) decades indicating the reactor is supercritical with less than a 30 second period.

QUESTION (B.16)

[1.0]

Which one of the following describes a situation which requires the console l

operator to manually insert all control rods in accordance with OP-103, Reactor Operation, Maintenance, Systems, and Components?

a.

Only one (1) Reactor Coolant Temperature Monitor indication available during forced circulation operation.

b.

Greater than 10% blockage of a single water channel flow area.

c.

Greater than 25% blockage of a fuel element flow area.

d.

Reactor building exhaust Gaseous Activity Detector (GAD) out of service for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Section B Normal /Emero. Procedures & Rad Con Page 18 I

i

QUESTION (B.17)

[1.0]

l Which one of the following describes all of the actions which must be performed immediately following an UNSCHEDULED shutdown?

a.

Notify the Shift Supervisor; initiate the Reactor Building Emergency procedure (EP-101) if required; Determine the cause of the shutdown.

b.

Log the shutdown; announce the shutdown; initiate the Reactor Building Emergency procedure (EP-101) if required.

c.

Announce the shutdown; notify the Shift Supervisor; initiate the Reactor Building Emergency procedure (EP-101) if required.

d.

Announce the shutdown; notify the Shift Supervisor; determine the cause of the shutdown.

QUESTION (B.18)

[1.0]

Which one of the following is the MINIMUM operating shift for a critical reactor?

a.

Two operators, one of whom must possess a valid senior reactor operator's license.

b.

Two operators, one of whom must possess at least a reactor operator's license.

Three operators, one of whom must be a certified Shift Supervisor.

c.

d.

Three operators, one of whom must be signed in as the console operator.

QUESTION (B.19)

[1.0]

It has just been brought to your attention that a release of I-131 at the reactor stack discharge of 2x10 a uC1/ml has been detected.

10CFR20 lists 10" uti/ml as permissible. What do you do?

a.

Scram the reactor. A T.S. limit has been exceeded.

This constitutes a Reportable Occurrence.

b.

Shutdown the reactor. The Nuclear Reactor Laboratory Manager shall be notified of the occurrence.

l c.

Notify the on-call supervisor. The discharge is below 10CFR20 l

limits.

l l

d.

Secure the reactor.

Initiate evacuation. Cic,.e the stack 2 exhaust damper.

i

(** End of Section B **)

i 4

Section C Plant and Rad Monitorina Systems Page 19

QUESTION (C.1)

[1.0]

The Phoenix Laboratory and Reactor Building have experienced a temporary loss of electrical power.

Which one of the following components must be restarted by first closing the l

circuit breaker and then resetting its mercury switch?

a.

MAP monitor vacuum pump b.

Steam recirculation pump c.

Reactor building exhaust fan d.

Laboratory stack exhaust fan

QUESTION (C.2)

[1.0]

While operating at full power, the operator observes that the green beamport door status light is illuminated.

Which one of the following is the significance of the green status light?

a.

The beamport door is closed and. entry into the area is permitted.

b.

The beamport door has been opened and personnel should be warned to exit the area.

c.

The beamport door is open and the interlock is defeated.

I d.

The beamport door is closed and a scram will be initiated if the door is opened.

QUESTION (C.3)

[1.0]

l The reactor is operating with the linear level-servo control system maintaining power at 1 MW. High voltage is then lost to the compensating circuit of the control system Compensated Ion Chamber.

Which one of the following describes the response of the plant to this malfunction?

a.

Indicated power will decrease, resulting in the linear level-servo control system dropping out of automatic control.

b.

Indicated power will decrease, resulting in the control rods being withdrawn from the core at normal speed.

Indicated power will increase, resulting in the control rods being c.

driven inward at normal speed.

d.

Indicated power will remain constant.

)

l I

h Section C Plant and Rad Monitorino Systems Page 20

QUESTION (C.4)

[1.0]

Which one of the following describes the purpose of the control fuel element holddown mechanism?

a.

Prevents the inadvertent withdrawal and possible subsequent dropping of a fuel element while withdrawing a control rod.

b.

Prevents the inadvertent ejection of the fuel element during a steam explosion caused by a catastrophic reactivity excursion.

c.

Provides vertical support to the fuel element thereby preventing tipping or leaning into unanalyzed fuel geometries.

d.

Provides horizontal support thereby preventing flow induced vibrations during forced circulation.

QUESTION (C.5)

[1.0]

The reactor is operating at 2 MW with Primary Pump number 1 providing forced circulation flow. The inlet butterfly valve to the Holdup Tank is moved from its fully open position.

Which one of the following describes the impact of these events on the plant?

a.

The reactor will scram on high power / low flow due to the Primary Pump tripping on low Net Positive Suction pressure.

b.

The reactor will scram due to the inlet butterfly valve being off i

its fully open seat.

c.

The Holdup tank will be slowly pumped dry resulting in a high radiation condition due to insufficient N-16 holdup time.

d.

Reactor power will lower slightly due to negative temperature coefficient of reactivity effects resulting from the lower flow conditions.

QUESTION (C.6)

[1.0]

Which one of the following would indicate that a leak had developed between the heavy water tank and the reactor pool?

a.

Positive reactivity addition as light water dilutes the heavy water in the heavy water tank.

b.

Increase in beamport thermal flux due to greater moderation of fast neutrons, c.

Increase in the gross beta analysis due to tritium in the pool water.

d.

Abnormal rod insertions dee to greater reflection of neutrons from the heavy water tank into the core.

6 Section C Plant and Rad Monitorina Systems Page 21 1

QUESTION (C.7)

[1.0]

Which one of the following would be indicative of a secondary heat exchanger tube rupture?

a.

Recurring HIGH WATER LEVEL HOT SUMP alarms; increasing readings on the pool conductivity recorder.

b.

Recurring HIGH WATER LEVEL HOT SUMP alarms; decreasing readings on the pool conductivity recorder.

c.

Lowering pool levels, increasing secondary system pH readings.

d.

Lowering pool levels, decreasing secondary system pH readings.

QUESTION (C.8)

[1.0]

l Which one of the following is the reason for adding sulfuric acid to the Secondary System?

Prevents the growth of micro-biological materials.

a.

b.

Keeps dissolved solids in solution.

c.

Prevents chlorine stress corrosion.

d.

Retards scale formation.

QUESTION (C.9)

[1.0]

Which one of the following will result in a reactor scram and a ventilation system isolation?

a.

5.2 mrem /hr in the fuel vault b.

1.6 mrem /hr in PML exhaust stack 2 c.

0.5 mrem /hr in the building supply header d.

Deenergizing the FNR main exhaust fan

QUESTION (C.10)

[1.0]

Primary coolant flow rate is indicating 75 percent of scale. The diaphragm for D/P 2 (Primary flow measuring channel 2) ruptures. Which one of the following describes the result of the failure of D/P 2?

a.

No effect.

b.

Primary flow will go to 100 percent (full scale) c.

Reactor trips on Hdr Up/No Flow d.

Reactor trips on Hi Pwr/No Flow

E

~

l*

i Section C Plant and Rad Monitorina Systems Page 22

QUESTION (C.11)

[1.0]

Which one of the following describes the consequences of exceeding 2.4 MW on ONLY safety channel A?

a.

Only ONE scram signal is generated turning off magnetic power to Channel A.

i b.

TWO scram signals are generated, one deenergizing magnetic power to Channel A and the other deenergizing magnetic power to all three channels.

c.

A SAFETY AMPLIFIER TROUBLE ALARM is generated.

I d.

A reactor Auto Rundown signal is generated.

QUESTION (C.12)

[1.0]

Which one of the following radiation monitors actuates the stack alarm?

i a.

FNR Gaseous Activity Detector (GAD) b.

Beamport floor Mobile Air Particulate (MAP) c.

Stack 2 MAP l

d.

Pool Floor MAP

QUESTION (C.13)

[1.0]

l Which one of the following is the purpose of the sleeve surrounding the beamport plug?

Reduces the number of neutrons which " stream" through the annulus a.

around the plug.

b.

Provides a water seal preventing the leakage of water in the annular space.

c.

Prevents excessive wear of aluminum casing.

I d.

Acts as a "collimeter", reducing the size of the neutron beam.

1

Section C Plant and Rad Monitorina Systems Page 23

QUESTION (C.14

[1.0]

Which one of the following describes 'the prescribed method used to de-ice the l

Cooling Tower Bay inlet louvers?

a.

Operate the cooling tower fans in REVERSE for periods not to exceed five (5) minutes.

b.

Operate the cooling tower fans in REVERSE for periods not to exceed thirty (30) minutes.

c.

Heat the secondary inlet water by the steam l'ine at the inlet of the secondary heat exchanger AND operate the cooling tower fans in NORMAL for periods not to exceed two (2) hours.

d.

Heat the secondary inlet water by the steam line at the inlet of the secondary heat exchanger AND STOP the cooling tower fans for periods not to exceed two (2) hours.

i i

QUESTION (C.15)

[1.0]

Which one of the following describes the construction of a standard fuel element?

Uranium dioxide (9.0% enriched with U"5) mixed with 1100 aluminum a.

with aluminic cladiing b.

Uranium dioxide (9.0% enriched with U"5) mixed with 1100 aluminum with zirconium cladding c.

Uranium aluminide (19.5% enriched with UUS) mixed with 1100 aluminum with aluminum cladding d.

Uranium aluminide (19.5% enriched with U"5) mixed with 1100 aluminum with zirconium cladding

QUESTION (C.16)

[2.0]

Match the Radioactivity Monitors listed in Column I with the type of detector listed in Column II.

Note: The items in Column II may be used once, more than once, or not at all, j

i Each response is worth 0.5 points.

Column I Column II Radioactivity Monitors Detector Type i

a.

FNR Building Exhaust

1. Proportional counter i

b.

Beamport Floor MAP

2. Geiger Mueller (GM)

)

c.

PL-4 Hood

3. Compensated ion chamber d.

Fuel Vault

4. NaI Scintillation

\\

Section C Plant and Rad Monitorina Systems Page 24

QUESTION (C.17)

[1.0]

Which one of the following describes the operation of the log count rate (LCR) system?

l a.

To overcome the shim-safety rod inhibit interlock, the LCR fission chamber must be raised to the upper limit, b.

LCR will cause an inhibit interlock to prevent shim-safety rod motion of the LCR recorder if greater than 2 cps.

c.

At the bottom of travel, the LCR fission chamber is approximately level with the top of the reactor core.

d.

Energizes a switch at 1.8 MW which turns on the Effective Full Power Hour (EFPH) level clock.

QUESTION (C.18)

[1.0]

Which one of the following would be powered by the emergency generator in the event of a loss of normal power?

a.

Northwest Column Area Radiation Monitor, Reactor Air. Compressor, Fuel Vault Alarm system b.

Northwest Column Area Radiation Monitor, Standby Air Compressor, Door Access Alarm system c.

Cooling Tower Fans, Standby Air Compressor, Fuel Vault Alarm system d.

Cooling Tower Fans, Reactor Air Compressor, Door Access Alarm System

QUESTION (C.19)

[1.0]

Which one of the following conditions will cause an auto rundown?

a.

Pool Level

-9 inches Reactor Period

+25 seconds Coolant Exit Temperature 130*F b.

Pool Level

-8 inches Reactor Period

+40 seconds coolant Exit Temperature 125*F c.

Pool Level

-7 inches Reactor Period

+15 seconds Coolant Exit Temperature 108'F d.

Pool Level

-6 inches Reactor Period

+20 seconds Coolant Exit Temperature ll7'F

I P

Section C Plant and Rad Monitorina Systems Page 25

QUESTION (C.20)

[1.0)

Select the choice that completes the following statement.

In the event of a rupture in the Hot Demineralizer system, system isolation is accomplished by a flow switch that:

a.

signals the inlet and outlet pump motor controllers to stop both pumps.

The flow signal also deenergizes the auto-shut off valve.

b.

deenergizes the auto-shut off valve. The closure of the auto-shut off valve causes the inlet and outlet pump motor controllers to stop both pumps, c.

signals the inlet and outlet pump motor controllers to stop both pumps. The inlet pump motor controller also deenergizes the auto-i shut off valve.

d.

signals the inlet and outlet pump motor controllers to stop both -

i pumps. The auto-shut off valve closes upon sensing a low water pressure.

l

(** End of Section C **)

l Section A R Theory. Thermo & Fac. Operatina Characteristics Page 26

ANSWER (A.1) d.

REFERENCE (A.1)

Introduction to Nuclear Reactor Operations, p. 4-4 Introduction to Nuclear Reactor Operations L.0. 4.1.1.2

+

ANSWER (A.2) a

REFERENCE (A.2)

Introduction to Nuclear Reactor Operations, Chapter 8.

Introduction to Nuclear Reactor Operations L.0. 3 i

ANSWER (A.3) c.

REFERENCE (A.3) 1.

UM: Introduction to Nuclear Reactor Operations, p. 6-5, LO 2.

(Moderator Temperature Coefficient)*(Change in Temperature)/(Control Rod Worth per Inch) = (Control Rod Movement) a positive sign would be rod insertion and negative sign would be rod withdrawal.

(-1.0 x 10)*(-18)/(.003)= +0.6 inches 2.

Category: A.17

ANSWER (A.4) l b.

REFERENCE (A.4) 1.

UM: Introduction to Nuclear Reactor Operation, p 4-21, LO 2.

I P = [B*(1 - p)/(8 - p)]*P 3

P, = 412 KW[(0.0075*1.03)/(0.007$+0.03)]x2000KW P

=

2.

Category: A.11 (Ask facility if candidates are required to know values for beta.

If not, this information can be given to them.)

ANSWER (A.5) a.

REFERENCE (A.5)

Introduction to Nuclear Reactor Theory, pg. 4-35 i

P -P e"* => t = [ln (P /P )] 7 I,n(6/1) > In(20/10) > I,n(35/20) > In(60/40) o o

i

ANSWER (A.6) i a.

J

REFERENCE (A.6)

Introduction Nuclear Reactor Operations, p. 5-7.

ANSWER (A.7) d.

REFERENCE (A.7)

Introduction to Nuclear Reactor Operations, Chapter 6, p. 6-15 Introduction to Nuclear Reactor Operations, Chapter 6, L.0.1 Period (T) - (8 - p)/(decay constant (A) p)

T - (0.0075 - 0.0015) / (0.1 0.0015) --> 0.006/0.00015 = 40 seconds a

i 1

..Section A' R Theory. Thermo & Fac. Operatina Characteristics Page 27'

ANSWER (A.8) b.

t

REFERENCE (A.8)

Introduction to Nuclear Reactor Operations, Chapter.7, p. 7-15.

ANSWER (A.9) c.

REFERENCE (A.9)

Introduction to Nuclear Reactor Operations, p. 5-5 Introduction to Nuclear Reactor Operations,. Chapter 5, L.O. 4

~

p = -0.05 Ak/k j

K,,, = 1/(1-p) = 0.952 CR (1-K ) - CR (1-K ) with CR = 100 and CR* = 2000 l

1 (1 K ) =3 CR,/Ck, kl-K

=(100/2000)-(l-0.9524)

= 1/20 (0.0476) 3) 0.00238 1-

=

K2=

.998

ANSWER (A.10)

I b

i

REFERENCE (A.10)

Introduction to Nuclear Reactor Operations, p. 7-15 to 7-18.

r l

ANSWER (A.ll) b, c-

REFERENCE (A.ll)

Introduction to Nuclear Reactor Operations, p. 6-4 Introduction to Nuclear Reactor Operations,' Chapter 6, L.O.11 i

ANSWER (A.12) c

REFERENCE (A.12)

I Introduction to Nuclear Reactor Operations, p. 4-33 Introduction to Nuclear Reactor Operations, Chapter 4,. L.O. 3 & 4

ANSWER (A.13)

DELETED b

REFERENCE (A.13)

Introduction to Reactor Operations, p. 5-19 Introduction to Reactor Operations, Chapter 5, L.0. 3

A.NSWER (A.14)

C.

REFERENCE (A.14)

Introduction to Nuclear Reactor Operations, p. 5-33.

ANSWER (A.15) b.

REFERENCE (A.15)

Introduction to Nuclear Reactor Operations, p. 5-5.

ANSWER (A.16) a, b

REFERENCE (A.16)

Introduction to Nuclear Reactor Operations, p. 5-35 l

Introduction to Nuclear Reactor Operations, Chapter 5, L.0. 4

l l

j.

Section A Re Theory. Thermo & Fac. Operatina Characteristics Page 28 i

j

ANSWER (A.17)

C.

L

REFERENCE (A.17) i Introduction to Nuclear Reactor Operations, p. 9-14.

j

ANSWER (A.18) d i

REFERENCE (A.18)

(

j Introduction to Nuclear Reactor Operations, p. 9-12

ANSWER (A.19) i a

l

REFERENCE (A.19)

Introduction to Nuclear Reactor Operations, p. 6-4 Definition of SDM and Shutdown Reactivity l

l

ANSWER (A.20) c.

j

REFERENCE (A.20)

Introduction to Nuclear Reactor Operations, p. 4-23 3

Introduction to Nuclear Reactor Operations Chapter 4, L.0. 4 t

l i

i 1

t

(** End of Section A **)

l i

q Section B Normal /Emero. Procedures & Rad con Page 29

ANSWER (B.1) b.

REFERENCE (8.1)

FNR Operating License and T.S. pg. 11

ANSWER (B.2) b.

REFERENCE (B.2) 1.

UM: Nuclear Power Plant Health Physics and Radiation Protection, p.

8-8.

(current annual exposure will be exceed 5 rem after 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s: 4850 mrem + (2 X 75 mrem /hr) - 5000 mrem) 2.

UM: Health Physics Manual, p. 2 3.

Category: B. Radiation Control,10 CFR 20 limits

ANSWER (B.3) c.

REFERENCE (B.3)

Nuclear Power Plant Health Physics and Radiation Protection, p. 4-10 Nuclear Power Plant Health Physics and Radiation Protection, Chapter 4, L.O. 4 decay const.- in(4 Rem per hour / 40 Rem per hour)/ 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months -- 0.58 hr-1 t=ln(100 mrem per hour / 4000 mrem per hour) /(- 0.58 hr(-1)) - 6.36 hr.

ANSWER (B.4) a.

REFERENCE (B.4)

Nuclear Power Plant Health Physics and Radiation Protection, 8-7 to 8-14

ANSWER (B.5) c

REFERENCE (B.5)

I - I, e"

==> In (0.1) - -(0.5814) X X - 2.3026/0,5814 - 3.9672

=

4

ANSWER (B.6) b.

REFERENCE (B.6)

OP 201, Building Checklist, p. 2.

ANSWER (B.7) 3 c.

l

REFERENCE (B.7) 10CFR55.53(e) & (f)

i Section 8 Normal /Emero. Procedures & Rad con Page 30 i

ANSWER (B.8) c.

REFERENCE (8.8)

Admin. Proc. #301 - Reactor Fuel

ANSWER (B.9) a.

REFERENCE (B.9)

FNR Technical Specifications, p. 7.

ANSWER (B.10) a t

REFERENCE (B.10)

OP-105 Core Excess Reactivity and Shutdown Margin 1

ANSWER (B.11) d.

REFERENCE (B.11)

{

OP-106 Power Level Determination Exam Question Section B pg. B-333

ANSWER (B.12) i

a. I

b. 2

c. 3

d. 6

REFERENCE (B.12)~

FNR Technical Specifications 3.1

ANSWER (B.13) a.

REFERENCE (B.13)

EP-101, Reactor Building Emergency, p. 2

ANSWER (B.14)

'l b.

REFERENCE (E.14)

EP-101, Reactor Building Emergency, p. 5-6

ANSWER (B.15) a.

REFERENCE (8.15)

Reactor Startup, OP-101, p. 4.

ANSWER (B.16) c.

REFERENCE (B.16)

OP-103, Reactor Operation, Maintenance, Systems, and Components, p. 9.

ANSWER (B.17) c.

REFERENCE (B.17)

OP-103, Reactor Operation, Maintenance, Systems, and Components

~

Section B Normal /Emero. Procedures & Rad Con Page 31

ANSWER (B.18) a.

REFERENCE (B.18)

OP-103, Reactor Operation, Maintenance, Systems, and Components

ANSWER (B.19) c.

REFERENCE (B.19) 10CFR20 FNR T.S. section 3.6 Exam. Question section B pg. B-592

(** End of Section B **)

.i Section C Plant and Rad Monitorina Systems

.Page 32

ANSWER (C.1) d.

REFERENCE (C.1)

OP-301, Building Power Failure, p. 2

ANSWER (C.2) d.

j

REFERENCE (C.2) i FNR System Description, Chapter 13, p. 13.

ANSWER (C.3) c.

REFERENCE (C.3) l FNR System Description, Chapter 13, p. 13-23 to 13-25' i

ANSWER (C.4) a.

REFERENCE (C.4)

FNR System Descriptions, Chapter 3, p. 3-9

ANSWER (C.5) b.

REFERENCE (C.5)

FNR System Descriptions, p. 13-30.

ANSWER (C.6) c.

REFERENCE (C.6)

FNR System Descriptions, Chapter 3.

Facility Question on p. C-248.

ANSWER (C.7) i a.

REFERENCE (C.7)

FNR System Descriptions, Chapter 4 and 5.

.i Based on Facility Question C-245

ANSWER (C.8) d.

REFERENCE (C.8)

FRN System Descriptions, Secondary Systems, p. 5-4

ANSWER (C.9) a.

REFERENCE (C.9)

I FNR System Description, p. 12-1

ANSWER (C.10) d.

REFERENCE (C.10)

FNR System Descriptions, p. 13-31

ANSWER (C.ll) b.

REFERENCE (C.11)

FNR System Descriptions, Chapter 13, p. 13-11

Section C Plant and Rad Monitorina Systems Page 33

ANSWER (C.12) c.

REFERENCE (C.12)

FNR System Description, Chapter 13, p. 13-34

ANSWER (C.13) a.

REFERENCE (c.13)

FNR System Descriptions, Chapter 3, p. 3-6

ANSWER (C.14) b.

REFERENCE (C.14)

FNR System Descriptions, Chapter 5, p. 5-3 OP-203, Cooling Tower Fan Operation, p. 1

ANSWER (C.15) c.

REFERENCE (C.15)

FNR System Description, Chapter 2, p. 2-1

ANSWER (C.16)

a. 4

b. 2

c. 2

d. 4

REFERENCE (C.16)

FNR System Description, Chapter 12, p. 12-3 FNR System Description, Chapter 13, p. 13-35

ANSWER (C.17) c.

REFERENCE (C.17)

FNR System Descriptions, Chapter 13, p.13-20 Based on Facility question C-3.

ANSWER (C.18) i b.

REFERENCE (C.18)

FNR System Description, Chapter 8, p. 8-1

ANSWER (C.19) a.

REFERENCE (C.19)

FNR Exam Questions Sect. C pg. C-312

ANSWER (C.20) c.

REFERENCE (C.20) i FNR System Descriptions, Chapter 7, p. 7-1 and 7-2.

1 l

(** End of Section C **)

(** End of Examination **)

i

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i A.4 b.

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p Section B Normal /Emera. Procedures & Rad con Page 35 i

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1 EOUATION SHEET

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Ped, 1 Curie = 3.7 x 10" dis /sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 108 BTU /hr 1 Mw = 3.41 x 106 BTU /hr 1 BTU = 778 ft-lbf

F = 9/5 *C + 32 1 gal (H O) = 8 lbm

C = 5/9 ( F - 32) 2

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SUMMARY

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