ML20202J298

NRC Operator Licensing Exam Rept 50-223/OL-97-01 (Including Completed & Graded Tests) for Tests Administered on 970929- 1001

ML20202J298
Person / Time
Site:	University of Lowell
Issue date:	10/16/1997
From:	Doyle P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20199C162	List: ML20199C156 ML20202J298
References
50-223-OL-97-01, 50-223-OL-97-1, NUDOCS 9712110119
Download: ML20202J298 (34)

Text

--. _..

4 U. S _ NUCLEAR REGULATORY COMMISSION OPERATOM LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

tio 223/OL 97-01 FACILITY DOCKET NO.:

50 223 FACILITY LICENSE NO.:

R 125 FACILITY:

University of Massachusetts - Lowell EXAMINATION DATES:

September 29 - October 1,1997 EXAMINER:

Paul Doyle, Chief Examiner SUBMITTED BY:

[

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7 Paul'Doyle,"Ch TxarWfner D' ate

SUMMARY

During the week of September 1,1997, the NRC administered operator licensing examinations to two Reactor Operator I; cense candidates and One Senior Reactor Operator license candidate. One of the Reactor Operator license candidates failed section B of the written examination.

REPORT DETAILS 1.

Results:

RO PASS / Fall SRO PASS / FAIL TOTAL PASS / Fall Written

-1/1 0/0 1/1 Operating Tests 2/0 1/0 3/0 Overall 1/1 1/0 2/1 2.

Exit Meeting:

Paul Doyle, NRC, Examiner Dr. Lee Bettenhausen, Reactor Supervisce, U. Mass.-Lowell Mr. David Medich, Chief Reactor Operator, U. Mass.-Lowell During the exit meeting Mr. Doyle thanked the reactor staff for their support in ensuring the examinations progressed smoothly. The facility reported that they would have ccmments on the examination. Comments and NRC resolution are included in enclosure 2 to this letter.

ENCLOSUREi 9712110119 971110 PDR ADOCK 05000223 V

PM

Facility Comments on Written Examination Question (B.3)

Technical Specification 3.3 and its table require scrams for coolant flow rate (2), seismic disturbanco (1), and coolant gates open (1), among others. Since the Pottermeter is one of l

the required coolant flow rate, there are 3 correct answers, b, c, and d.

Suggested Resolution:

Discard Question (B.3)

Question (B.4)

A sentence existing in the control room copy of the procedure for crane operation, but missing from the copy supplied to NRC prohibits using the crane to make side Pulls (copy attached).

Suggested Resolution:

Accept both b. and c. as correct.

Question (B.11)

All answers given are correct per R.O.6.

%vvested Resolution:

Discard Question (B.11)

Question (B.13)

Answer b. should read: " channel E (Fission Product Monitor)

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l Question (C.1)

Answer a) for valve P 3 sh9uld be C, Closed for normal cross stall flow operation i

Suggested Mesolution:

Change answer a) from 0 to c l

Question (C.2) i The stem of the question should read, "Which one of the following points is exhausted by tlw main exhiust fan EF 12?"

r Question (C.7)

The stern of this question is a bit confusing. The thermal column shellis cooled by water i

in natural convection. The Graphite is then coming in contact with the coolorf shell walls.

Suggested Mesolution:

Accept either a. or o as correct.

Question (C.15)

Answer b. should read:

"lon Chamber, to determine if there is a dose rate present."

And answer d should read:

"lon chamber, to determine if there is contamination present."

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Revision 1 1002/07 S.P. 21 Movement of Objects By Crane 1.0 Puroose and Secoe The purpose of this procedure is to assure that objects moved by the crane are handled in a safe manner and so as not to endanger vital reactor componento.

2.0 2.1 Adequate slings and rigging equipment.

3.0 Beferenceq 3.1 Shepard Ndos Crane & Holst Corporation, Montour Falls, New York 14865.

Onerstion and Maintenance Manual.

3.2 USA Standard USAS B30.2 1967 publirted by the American Society of Mechanicci Engineers, United Engineering Center, 345 East 47"' Street, New York, New York 10017, 4.0 hgcedure 4.1 The crane (s) shall be operated only by the operc' ions staff and by mairstenance and test personnel when it is necassary in the performance of the. duties, and inspectors, but only when Arrangements have been made with ULR Operations.

1.2 The operator shall obey a stop signal at all times, no matter who Give it.

4.3 Each operator shall be held directly responsible for the safe operation of the eqeipment. Whenever there is any doubt as to safety, the operator has the authority to stop and refuse to handle loads until safety has been assured.

4,4 Before leaving the crane unattended, the operator should land any Attached load; exceptions may be permissible with the approval of the Reactor Supervisor or Chief Reactor Operator.

4.5 The crane shall not be loaded beyond its rato load except for test purposes, as provided t y pre-operational Test 13, 4.6 Loads should be attached to the load block hook by means of slings Or other approved devices, and the hoist rope and slings should be free, from kinks or twists. Care should be taken tn assure that slings or loads clear all obstacles befoic and during movement of the load. Sudden accelerations should be dVoided, and people should not be under the load. Cranes shat! not be used for side pulla nor may two cranes be used to lif t a load unless specifically approved by the RS or CRO.

)

i 4.7 Fuel shipping casks that are within the rate load capacity of the crane may I

be hoisted to the pool level from the vicinity of the truck door, moved toward the bulk pool over the floor adjacent to the stall pool NOT OVER THE l

STALL POOL and then moved over the bulk pool and lowered into the bulk pool provided the gate is in place in the stall pool.

I 4.8 Extreme care shall be exercised when moving any object over the reactor pool, in general, heavy objects such as shipping casks and storage casks should not be transported over the core.,

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Radian A B Theory. Thermo. and Facky Operating Charadaristics Page 2 i

QUESTION (A.1) [1.0) l Excess readMty is the amount of reactivity...

I a.

associated with samples.

b.

required to achieve prompt criticality.

c.

available above that required to make the reactor critical.

d.

assodated with Xenon production QUESTION (A.2) [1.0)

The reactor is shutdown by 0.015 AK/K. The startup range count rate is 15 counts per minute.

After placing a sample into the reactor, the count rate INCREASES to 60 counts per minute.

What is the worth of the sample?

a.

+ 0.0006

[

b.

+ 0.0113 c.

- 0.0006 d.

- 0.0113 QUESTION (A.3) [1.0)-

- Which ONE of the following isotopes would cause a colliding neutron to lose the most energy?

a.

N' b.

H8

[

c.

C" d.

U'"

Sadion A B Theory. Thermo. and Facihty Operating Characteristics Page 3 i

QUESTION (A.4) [1.0)

Which ONE of the following is the MAJOR recoverable source of energy released during the fission process?

a.

Prompt gamma rays b.

Neutrinos c.

Capture gamma rays d.

Kinetic energy of the fission fragments.

QUESTION (A.5) [2.0,0.5 each)

Match the terms in column A with the correct definition in column B Column A Column B a.

Fast Neutrons 1.

Neutrons refer. sed promptly from fission.

b.

Prompt Neutrons 2.

High energy neutrons, c.

Slow Neutrons 3.

Neutrons released from decay after fission.

d.

Delayed Neutrons 4.

Low energy neutrons.

QUESTION (A.6) (1,0)

If all of the delayed neutrons were instantaneously removed from an exactly critical reactor, the resultant K., would be...

a.

1.007 b.

1.000 c.

0.993 d.

0.000

d MM A B Theorv. Thermo. and Facility Ooeratina Characteristics Page 4 QUESTION (A.7) [1.0)

You have shutdown the reactor and reactor power is decreasing at a steady negat!ve period.

~

The fission chamber output reads 100 counts per minute. What level would you expect to read on the fission chamber output three minutes later.

a.

50 cpm b.

25 cpm c.

10 cpm d.

5 cpm OUESTION (A.8) [1.0)

The reactor has been shutdown for two weeks. You start up the reactor and raise power to 1 Megawatt. Which ONE of the following describes the regulating rod response you would expect to see for the next three hours?

a.

Rods will drive in b.

Rods will drive out c.

Rods will remain at the critical position for i Megawatt, d.

Rods will initially drive out then start driving back in.

QUESTION (A.9) [1.0)

A thin foil target of 10% copper atoms and 90% atoms aluminum is in a thermal neutron beam.

Given o.u = 3.79 barns,0,2 = 0.23 barns, o,u = 7.90 bams and o.s = 1.49 barns, which ONE of the following reactions has the highest probability of occurring? A neutron...

a.

scattering reaction with aluminum.

b, scattering reaction with copper, c.

absorption in aluminum.

d.

absorption in copper.

l

i Sadian A B Theory. Thermo. and Facky Operating Charadaristics Page 5 i

, QUESTION _ (A.10) [1.0)

[

Which C'.4E of the following conditions would INCREASE the shutdown margin of a reactor?.

s._

inserting an experiment adding popitive reactivity; b.

Lowering it. Aerator temperature if the moderator temperature coefficient is negatNo.

c.

Depletion of a bumable poison.

d.

Depletion of uranium fuel.

QUESTION (A.11) [1.0)

Which ONE of the following correctly describer the behavior of the reactor as P. apprnaches criticalstv?

_ Ti.w to stabilize Size of change in neutron count equihbrium neutror count a.

longer larger.

b, shorter larger -

c.

' longer smaller -

d.

shorter smaller QUESTION - (A.12) [1.0)

During a reactor start'sp, the Reactor Opemtor notes that the source is not in. After inserting the neutron source he/she notes that power is increasing LINEARLY What was the condition of the reactor just prior to inserting the sourca?

a-Substantially subcritical

. b.

Slightly subcritical c.

Exactly critical

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d.-

Slightly supercritical i

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Sadian A B Theory. Thermo. and Fadidy Operapng CharacuNittics Page 6 QUESTION (A.13) [1.0)

Which ONE of the following statements is FALSE 7 r

a.

The value of an isotope's neutro') absorption cross section is independent of a neutron's energy.

b.

A U'" stom car, be fissioned by a */asr neutron.

c.

A U'" stom is less likely to have a 'thermar fission than a Pu " stom.

r d.

Approximately 210 MeV is released per fission event.

- QUESTION (A.14) [1.0]

Which ONE of the following is the PRINCIPAL source of heat an hour after shutdown from extended operations at 1 Megawatt?

a.

Slowing down of delayed neutrons.

. b.

Suberitical reaction of photoneutrons.

c.

Spontaneous fission of U'".

d.

Decay of fission fragments.

QUESTION (A.15) [1.0)

Which ONE of the following is the purpose of having en installed neutron source?

a.

To compensate for neutrons absorbed by experiments installed in the reactor, b.

To generate a sufficient neutron population to start a fission chain for reactor startup.

c.

To provide a means for allowing reactivity changes to occur in a suberitica! reactor, d-To generate a detectable neutron level for monitoring reactivity changes in a suberitical resctor.

Sachon A R Theory. Thermo. and Facility Ooeratina Characteristica Page 7 QUESTION (A.16) (1.0)

Due to the loss of a fan in the cooling towers, pool temperature INCREASES by 20'F. Given a

= -0.0005 AK/K/'F and an average regulating rod worth of 0.004 AK/K/ inch. By how r

me:h and in what di action did the regulating rod move to compensate for the ter"perature change?

a.

0.25 inches in b.

0.25 inches out c.

2.5 inches in d.

2.5 inches out QUESTION (A.17) [1.0)

During a reactor startup, as K, approaches criticality, the value of 1/M..,

a.

decreases towards zero.

b.

decreases towards one.

c.

increases towards infinity, d.

increases towards one QUESTION (A.18) [1.0)

The average number of neutrons produced by thermal fission is of U" is...

a.

2.00 b.

2,07 c.

2.42 d.

2.87 T'

4 T

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Radian A-R Theory Thermo and FadlN Operatina Charadarl=+h -

Page 8 OUESTION. (A.19)' [1.0)

What characteristic make graphite a good reflector?

Scattering Cross Section Absorption Cross Section a.

High

' High -

b.-

Low High c.

High Low d.

Low Low l

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e-Sedian B Normal. Emergency and Radelogica' Control Procedures

_ Page g --

QUESTION (B.1). [1.0)

Total Effective Dose Equivalent (TEDE) is defined as the sum of the deep dose equivalent and the committed effective dose equivalent. The deep dose equivalent is related to the...

a.

' dose to orgaris or tissues.'

b.

extemal exposure to the skin or an extremity, c.

- extemal exposure to the lens of the eyes.

i d.

extemal whole-body exposure.-

- QUESTION (B.2) [2.0, 0.5 each)

Match the Code of Federal Regulations (CFR) part 55 requirements for an actively licensed l Operator (or senior Operator) listed in column A with the correct time period from column B.

Column _A column B i

s._

License Expiration 1.

1 year b.

Medical Examination -

2.

2 years c.

Requalification Written Examination 3.

3 years d.

Requalification Operating Test 4.

4 years 5.

5 years 6.

6 years

_ QUESTION (B.3) (1.0)

Which ONE of the following scrams IS REQUIRED by Technical Specifications for Reactor Operation?

' Coolant Outlet Temperature a.

b.

- Pottermeter c.

~ Stall pool End d.

Coolant Gate

0 Section B Normki. Emeroency and Radioloaical Control Procedures Page 10 QUESTION (B.4) [1.0)

Which ONE of the following statements conceming crane operations is FALSE?

a.

The crans may be used to move fuel shipping casks, but not over the stall pool.

b.

Fuel shipping casks may be lowered into the bulk pool providing the gate is in place in the stall pool.

c.

The cranes may be used for side pulls.

d.

' Loads may be attached to the load block hook using slings.

QUESTION (B.5) [1.0)

During a severe storm, the decision is made to secure the reactor and evacuate the facility.

Which ONE of the following is the condition the staff should place the ventilation and process control systems in prior to leaving?

VENTILATION SYSTEM PROCESS CONTROL SYSTEM a.

on on b.

o#-

on c.

on o#

d.

o#

o#

QUESTION (B.6) [1.0)

If the normal method for filling the primary system is unavailable, whose permission is required to use an attemate method?

a.

any licensed Reactor Operator b.

any licensed Senior Reactor Operator c.

Chief Reactor Operator d.

Reactor Supervisor

\\

Wlan B Normal. Emeroency and Radioloolcal Control Procedures Page 11 QUESTION (B.7) [1.0)

During an emergency plant conditions have degraded badly enough that in order to ensure the health and safety of the public, you must deviate from technical specifications per 10CFR50.54(x). What is the minimum level of approval you must have to take this action?

a.

any licensed Reactor Operator b.

any licensed Senior Reactor Operator c.

Chief Reactor Operator d.

Reactor Supervisor.

QUESTION (B.8) [2.0,0.5 each)

- Identify each of the following as either a Safety Limit (SL) or a Limiting Safety System Setting

- (LSSS).

a.

1250 gpm b.

24 feet above core centerline.

c.

110*F d.

1.25 Mwatt.

QUESTION (B.9) [1.0]

When performing a calibration of the Log N neutron monitor, what is the minimum amount of time required to allow the equipment to warmup?

a.

30 minutes, regard;ess of time secured.

b.

15 minutes, regardless of time secure.

c.

twice as long as the time secured up to 30 minutes.

d.

as long as the time secured up to 30 minutes.

I Section B Normal. Emeroencv and RadiMmical Control Procedurer Page 12 QUESTION (B.10) [1.0)

At what power level during startup is the source normally withdrawn?

a.

500 milliwatts b.

5 watts c.

50 watts d.

500 watts QUESTION (B.11) [1.0]

Which ONE of the following readings required to taken hourly during forced convection cooling is NOT r%uired during natural convection operations?

a.

Log N b.

Linear Safety Channels c.-

Log Count Rate d.

Magnet Current QUESTION (B.12) [1.0)

The Co* source is in use. RO-13, Radiation Monitoring Equipment Checkout, states that you shall not perform checks on channel Q (Gamma Cave) and channel...

a.

F (Facilities Filter).

b.

G (Rabbit filter).

c.

H (Hot Cell).

d.

O (Stairwell).

g i

_____________.._.______j

Sggon B Normal. Emeroency and Radioloaical Control Procedures Page 13 QUESTION (8.13) [1.0) m when performing RO-13, Radiation Monitoring Equipment Checkout, you use a Co* gamma emitting source or equivalent, with one exception, for which you use a Cf2s2 neutron emitting source or equivalent. The channel which is checked with the neutron emitting source is...

a.

channel C (Continuous Air Monitor #1) b.

channel F 5 (Fission Product Monitor) c.

channel I (Plenum) d.

channel L (Thermal Column)

QUESTION (B.14) [1.0) in accordance with Standing Order #4, what is the maximum level allowed on Pico #2 in the 100 kwatt range?

a.

95%

b.

90 %

c.

85%

d.

80%

QUESTION (B.15) [1.0)

The readings from a point source are 4 rem /hr at 3 inches and 0.5 mrem at 10 feet. Based on these readings what percentage of the radiation is due to gammas?

a.

90 %

b.

80%

c.

20%

d.

10%

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W% B Normal. Emeroency and RadiMil Control Prx*dures Page 14-QUESTION (8.16) [1.0)

When taking logs, you must inform the chief reactor Operator when you notice a discrepancy between power channels greater than...

ai 2%

b.

3%

c.

4%

d.

5%'

QUESTION (B.17) [2.0,0.5 each)

Match the type of radiation from column A with its associated Quality Factor from Column B.

Radiation Quality Factor a.

alpha 1

b.

beta 2

c.

gamma 5

d.

neutrons (unknown energy) 10 20 w

Sadion C Plant and Radiation Monitorina Systems Page 15 QUESTION (C.1) [2.0,0.4 each)

Using the drawing of the primary system provided list the normal position of the following valves (Open, Locked Open, Closed, Locked Closed, or Throttled) a.

P-3 b.

P-9 c.

P-11 d.

P-13 e.

P-LJ QUESTION (C.2) [1.0)

Queston ctHlWOp@erAnol%fm Which ONE of the following points is exhausted by the main exhaust fan EF-44 }g?

1 a.

Pneumatic Tubes Exhaust b.

Experi

• ental Sasement Hood Vent c.

Beamports & Medical Embedment Drain Line d.

Gamma Cave QUESTION (C.3) [i.0)

The baffles in the holdup tank are designed to allow which two isotopes time to decay?

a.

,H2 and.C'8 b.

,H2 and N

7 c.

.C ' 8 and,O

d.

N and,O

7

Rar*1an C Plant and Radi=+ian Monitorina Systems '

Page 16 QUESTION (CA) [1.0)_

Which ONE of the following radioisotopes is sampled for in the Secondary to detect a primary to secondaiy leak?

a.

H2 3

b.

,N

c.

,,Na

d.

Rb" 37 QUESTlON (C.5). [1.0)

How was primary temperature originally designed to be controlled automatically? A signal from a primary temperature controller sends a signal edjusting a.

the position of a motor operated valve in the secondary, b.

the position of a motor operated valve in the primary, c.

primary pump speed.

d.

secondary pump speed.

QUESTION (L6) [1.0)

Which ONE of the following correctly describes the type of radioactivity detected by the CAMS and the stack monitors.

CAMS Stack Monitors a.

particulate only gaseous and particulate b.

gaseous only gaseous and particulate c.

particulate only gaseous only d.

gaseous and particulate particulate only w-mey v

Ser43an C Plant and Radiation Monitorina Systems Page 17 '

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I

' QUESTION (C.7) [1.0)

Which ONE of the following is the method used to cool the graphite in the thermal column? - The section embedded in concrete is encased in a double shell through which...

a.

cooling water passes by natural convection.

b.

cooling water passes by forced convection.

c.

cooling air passes by natural convection.

d.

cooling air passes by forced convection.

QUESTION (C.8) [1.0)

Which ONE of the following communications systems allows ail stations to talk to each other simultaneously?

a.

main intercom system b.

Phone System c.

Sound Powered Headset System d.

Public Address System.

QUESTION (C9) [2.0,0.5 each)

Identify the primary source of each of the radioisotopes listed below as due to irradiation of either air or water in the reactor.

a.

H' b.

NS c.

O

d.

Ar"

~_-

Sedian C Plant and RadiWion Monitoring Systems

- Page 18 QUESTION (C.10) [1.0}'

Using the drawing of the primary system provided, which ONE of the following valves will cause -

i a scram N the valve is opened (moved off closed seat)?

a.~

P-1 b.

Pg c.

P-11 l

- d.

P-12 QUESTION (C.11) [1.0)

Points A on the one-line diagram of the seccndary system provided represent a capped 8-inch' line. Which ONE of the following is the reason for these two capped lires.

a.-

Provide a place to connect a precision Heise Gage to calibrate the secondary flow gages.

I b.

Provide a place to connect fire hoses for emergency cooling of the secondary system.

c.

Provide a place to connect fire hoses to flush out the secondary system, following a primary to secondary leak.

d.

- Provide a place to connect an additional pump and heat exchanger to upgrade to 5 Megawatt operation.

QUESTION (C.12) (1.0)

Which ONE of the following condi' ions could result in an inability to withdraw control rods for startup?

a.

Fission Chamber fully inserted into core.

b.

Neutron source fully withdrawn from core, c.

Loss of compensating voltage to Compensated lon Chambers d.

Discriminator voltage set too low in Fission Chamber circuit.

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9 Section C Plant and Radiation Monitoring Systems Page 19 QUESTION (C.13) [1.0]

Which ONE of the following is the purpose of the Wimi Gate in the Rabbit systems? The Wind Gate provides a means for...

a.

changing the direction of air flow, thus determining the direction of the rabbit.

b.

varying vacuum in the system, thus determining the rabbit speed, s

c.

breaking vacuum, thus mitigating draining of the pool should a leak occur.

d.

cooling the system, thus preventing thermal expansion of the rabbit piping, and therefore experiment binding.

. QUESTION (C.14) (1.0)

The secondary side of the heat exchanger is designed to supply water at 80*F and retum it at g1 A*F, with a flow rate of 1500 gpm. Given a gallon of water = 8.0 lbm, determine the design heat removal capacity for the heat exchanger.

a.

1.0 Megawatt b.

1.4 Megawatts -

c.

2.2 Megawatts d.

2A Megawatts QUESTION (C.15) [1.0) giuggggBe6 During a weekend, you are called in by the police who have received a radiation alarm from the facility. Prior to opening the door, you hold up a meter to the glass on the inner door to determine if there is an actual radiation problem. What type of meter would you use for this purpose and why?

a.

Geiger-M0ller, to determine if there is a dose rate present.

b.

Propedre: Ocuater lon,Chambg, to determine if there is a dose rate present.

i c.

Geiger-Moller, to determine if there is contamination present.

d.

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Pr:pedue: 0:uner lagt;hergbM, to determine if there is contamination present.

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4 Section C Plant and Radiatinn Monitorina Systems Page 20 QUESTION (C.16) [1.0)

With the MASTER SWITCH in the TEST position, and the SLADE OUTlight energized, what is the position of the BLADE 1 control rod?

a.

The rod is fully out, the lead screw is fully inserted.

b.

The rod is fully inserted, the lead screw is fully out, c.

Both the rod and the lead screw are fully out, d.

Both the rod and the lead screw are fully inserted.

QUESTION _ (C.17) [1.0)

According to the updated Facility Safety Analysis Report (UFSAR), which of the following listed locations has the potential for generating the most Ar"?

a.

Thermal Column Case Vent.

b.

Beam Ports.

c.

Pneumatic Tube Exhaust.

d.

Primary Coolant System.

QUESTION (C.18) [1.0)

The reactor is operating at 100 Kilowatts in automatic mode when the reactor operator scrams the reactor due to an unexplained power excursion. Which ONE of the following is the status of the regulating rod? The regulating blade...

a.

scrammed with the other rods and is fully inserted into the core.

b.

remained in automatic mode, and is withdrawing in an attempt to maintain power.

c.

dropped out of automatic mode, and remains at the same position as when the scram was initiated, d.

dropped out of automatic mode, and is automatically driven in to its bottom position.

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4 h% A R Theorv. Thermo. and Facility Ooerating Characteristics Page 21 ANSWER (A.1) c REFERENCE (A.1)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 6 6.2.2, pp. 6-2 & 6-3.

ANSWER (A.2) b REFERENCE (A.2)

Reactivity (p) = -0.015 AK/K K., = 1/(1-p) = 1/((1-(-0.015)) = 1/1.015 = 0.9852 CR,/CR, = (1-K.)/(1 K.) 1 - K.,2 = [CR, (1 K,)/CR,]

K,,2 = 1 - [CR, (1-K.)/CR,)

K.a2 = 1 -[(15/60) x (1 - 0.9852) = 1 - %(1 - 0.9852) = 1 - (0.01478 )% = 1 - 0.003695 = 0.9963 Worth = (K

- K.a2)/(K. K.n2) = (0.9963 - 0.9852)/(0.9852 x 0.9963) = +0.0113AK/K ANSWER (A.3) a REFERENCE (A.3)

Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $$ 3.81 - 3.85, Table 3.3, pp.164,165.

ANSWER (A.4) d REFERENCE (A.4)

Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $$ 1.50 - 1.55, Table 1.2, pp. 16,17.

ANSWER (A.5) a,2; b,1; c,4; d,3 REFERENCE (A.5)

Burn, R., Introduction to Nuclear Reactor Operations, C 1988, 6 3.2.2 Delayed Neutrons, also figure 3.3.

ANSWER (A.6) e REFERENCE (A.6)

Glassione, S. and Sesonske, A, Nvdear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $ 5.9, p. 321.

ANSWER (A.7) '

c REFERENCE (A.7)

Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $ 5.45, p. 246. P = P e" = 100 (e") = 10.54

Rae+1an A R Theory. Thermo. and Farla Ooeratina Characteristics Page 22 -

v l ANSWER (A.8) b REFERENCE (A.8)

Sum, R., Introduction to Nuclear Reactor Operations, C 1988, 5 8.4, Xenon Transient Behavior.

ANSWER (A.9) c REFERENCE (A.9)

Glassione, S. and Sesonske, A, NuclearReactor Engineering, Kreiger Publishing, Malabar, Florida, 1991, $ 2.108 - 2.114, pp. 77 - 80.

-ANSWER (A.10) d

- REFERENCE (A.10)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 9 6.2.3, p. 6-4.

ANSWER (A.11) a REFERENCE (A.11)

Bum, R., Introduction to Nuclear Reactor Operations, @ 1988, 9 5.3, Example 5.3(b)

ANSWER (A.12) c REFERENCE (A.12)

Bum, R., Introduction to Nuclear Reactor Opemtions, C 1988, S 5.6, Neutron Soume Addition to a Reactor.

ANSWER (A.13) a REFERENCE (A.13)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, Chap. 5 pp. 5 6 28.

ANSWER (A.14) d REFERENCE (A.14)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 9 4.9, pp. 4 4-26.

ANSWER (A.15) d REFERENCE (A.15)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, Gg 8,1 - 8,4, pp. 8 8-14.

ANSWER (A.16) d.

REFERENCE (A.16)

+20*F x -0.0005 AK/K/*F = - 0.01 AK/K. To compensate the rod must add +0.01 AK/K. Which implies +0.01 AK/K + +0.004 AK/K/ inch = +2.5 inches OUTWARD

c.

W A' R Theory. Tharme. and Fariikv Ooeratina Charadedstle* '

Pa9e 23 ANSWER (A.17) a REFERENCE (A.17)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 9 5.4 Inverse Multiplication.

ANSWER (A.18) e REFERENCE (A.18)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 6 3.2, Nuclear Fission.

ANSWER (A.19) c REFERENCE (A.19)

Bum, R., Introduction to Nuclear Reactor Operations, C 1988, 9 4

s

Secuan B Normal. Emeroency and Radioloalcal Control Procedures Page 24 ANSVER (B 1) -

d REFERENCE (B.1)

- 10 CFR 20.1201 ANSWER (B.2) a, 6 b, 2 c, 2 d,1 REFERENCE (B.2) 10 CFR 55 $$ 21,55, and 59.

AN6WCC (S.3) d n n 3 L.;.1 u.;..

CC"CRCNOE (S.3)

RO Obij CW; (,"riT.;ri 0;;';r.: 0;;;.T.;) erd T.S. T;.b : 3.

ANSWER (B.4) borg mgMggeolgygpagme@

REFERENCE (B.4)

SP-21, p. 4.6.

ANSWER (B.5) e REFERENCE (B.5)

EO-3, #3 and 7. NRC examination administered January,1987 ANSWER (B.6) d REFERENCE (B.6)

SP-18, p. 4.8.1. Also, NRC examination administered January,1987 A.NSWER (B.7) b i

REFERENCE (B.7) 10 CFR 50.54(y)

ANSWER (B.8) a, LSSS; b, SL; c, SL; d, LSSS j

REFERENCE (B.8) l T.S. 5 2.0 Safety Limits and Limiting Safety System Settings ANSWER

-(8.9) d-

)

REFERENCE (B.9) l CP-1, Calibration of Log N Neutron Monitor, @ 4.1, p. CP-1-1.

l

p.

W B Normal Emeroency andi sdioloalcal Control Procedures Page 25 ANSWER (B.10) d

= REFERENCE (B.10):

RO-5, Routine Startup, 9 5.1.5.i p. RO5-3.

i

^JOS"!CR (e.ii) b MAQUND0f&'

ncicnct:Oc (e.it).

RO4;-C,^;; :M :l.":::::;;;d Adja.::,,;nl: in," :::: L;; l, 99 C.2.1 S S.2.2, pp, nOS-2 S S&:

ANSWER (B.12) a REFERENCE (B.12)

RO-13, $ 13.1.b.2.

ANSWER (B.13) b REFERENCE (B.13)

RO-13, G 13.1.a.

ANSWER-(B.14) b REFERENCE (B.14)

Standing Order #4, step 5.

ANSWER (B.15) c REFERENCE (B.15)

Essential no ps make it to 10 feet. Therefor the % mrem is due to gammas only. Using A /d/ =

i A/d 8 the dose due to gammas at 3 inches = 0.5 mrem /0.252 x 102 = 50/0.0625 = 800 mrem.

i 800 mrem /4000 mrsm = 0.2 or 20%

ANSWER (B.16) b REFERENCE (B.16)

Standing Order #4 Sequence of Operations during Startup and at Rated Power ANSWER (B.U) a 20; b 1; c i; d,10 REFERENCE (B.17) 10CFR20.1004 Table 1004.b(1) 4-

i Section C Plant and Radiation Monitorina Svstems Page 26 ANSWER (C.1) a, O g; b,0; c, T; d, LC; e, C REFERENCE (C.1)

- Study Guide for Key Access and intro, to Operato: T;rbing, $ covering Primary System.

ANSWER (C.2) b REFERENCE (C.2)

Study Guide for Key Access and intro, to Operater Training,6 covering Ventilation Systum.

ANSWER (C.3) d REFERENCE (C.3)

Study Guide for Key Access and intro. to Operator Training,9 covering Primary System.

' ANSWER (C.4) c REFERENCE (C.4)

Study Guide for Key Access and Intro, to Operator Training,6 covering Secondary System.

ANSWER (C.5) c REFERENCE (C.5)

Study Guide for Key Access and Intro. to Operator Training,6 covering Secondary System.

ANSWER (C.6) a REFERENCE (C.6)

Study Guide for Key Access and intro, to Operator Training,6 covering Radiation Monitors.

ANSWER (C.7) a WM SM0gd;agpWer added yetfacility costgenti REFERENCE (C.7)

UMLR Safety Analysis Report, $ 4.3.1 Thermalcolumn.

ANSWER (C.8) c REFERENCE (C.8)

UMLR Safety Analysis Report, $ r. 3.1 Communications System ANSWER (C.9) a, water; b, water; c, water; d, air REFERENCE (C.9)

UFSAR, 9 4.2.2 Primary Coolant, 9 7.1.2 Source Term for Gaseous Radioactive Wastes.

4'

.-. Rar*H C Piarf and Radia*% Monitorina Svatare.i Page 27 -

ANSWER

. (C.10) d' REFERENCE lC.10)

Study Guide for Xey Access and Intro, to Operator Training, $ covering Primary System.

ANSWER-(C.11) d REFERENCE (C.11)

SP 18, Draining tho Pool, Provisions fxIncreased Cocling.

ANSWER (C.12) b REFERENCE (C.12)

, NRC Examination Question Bank

-. ANSWER (C.13) a REFERENCE (C.13)

Rewrite of Operator Licensing question administered March,1994.

ANSWER (C.14) d REFERENCE (C.14)

Rewrite of Operator Licensing Exam question administered August,1988.

mc AT p

ga#on x 60bb = 720,000 '

• m = 1800 x8 min.

gallon hour hour BN c = 1.0 p

Ibm *F AT = 91.4 -80.0 = 11.4'F and 1Mw=3.41 x 10' hour f, 72000 x 1.0 x 11.4 M07han 3.41 x 10' ANSWER (C.15) b' REFERENCE (C.15)

Standard NRC question 1

w

,s C

r Saden C Plant and Radiation Monitonng Sys^ ems Page 28 ANSWER-(C.16) b-REFERENCE (C.16)

UFSAR, $ 4.4.3, Table,4.3, p. 4-49.

ANSWER (C.17) b REFERENCE (C,17)

UFSAR $ 7.1.2, p. 7-2.

ANSWER (C.18) c

= REFERENCE (C.18)

UFSAR, Paragraphs 4.1.7 ControlRod Blades, and 4.1.8 Servo Regulating Rod Drive.

d

,