ML102800387

Initial Examination Report No. 50-326/OL-10-01, University of California-Irvine

ML102800387
Person / Time
Site:	University of California - Irvine
Issue date:	10/08/2010
From:	Johnny Eads Research and Test Reactors Branch B
To:	Geoffrey Miller University of California - Irvine
Nguyen JT, DPR/PROB, 301-415-4007
References
50-326/OL-10-01
Download: ML102800387 (33)

Text

October 8, 2010 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-326/OL-10-01, UNIVERSITY OF CALIFORNIA - IRVINE

Dear Dr. Miller:

During the week of September 27, 2010, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of California - Irvine Triga reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Johnny H. Eads, Jr., Chief Research and Test Reactors Oversight Branch Division of Policy and Rule Making Office of Nuclear Reactor Regulation.

Docket No. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-10-01

2. Written Examination cc w/out encls: Please see next page

October 8, 2010 Dr. George E. Miller Department of Chemistry 516 Physical Sciences 1 University of California, Irvine Irvine, CA 92697-2025

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-326/OL-10-01, UNIVERSITY OF CALIFORNIA - IRVINE

Dear Dr. Miller:

During the week of September 27, 2010, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your University of California - Irvine Triga reactor. The examinations were conducted according to NUREG-1478, "Operator Licensing Examiner Standards for Research and Test Reactors," Revision 2. Examination questions and preliminary findings were discussed at the conclusion of the examination with those members of your staff identified in the enclosed report.

In accordance with Title 10, Section 2.390 of the Code of Federal Regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). The NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. If you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via internet e-mail John.Nguyen@nrc.gov.

Sincerely,

/RA/

Johnny Eads, Chief Research and Test Reactors Oversight Branch Division of Policy and Rule Making Office of Nuclear Reactor Regulation.

Docket No. 50-326

Enclosures:

1. Examination Report No. 50-326/OL-10-01

2. Written Examination cc w/out encls: Please see next page DISTRIBUTION:

PUBLIC RidsNrrDprPrta RidsNrrDprPrtb Facility File (CRevelle) O-07 F-08 ADAMS ACCESSION No.: ML102800387 TEMPLATE #: NRR-074 Office PROB/CE IOLB/OLA PROB/BC Name JNguyen CRevelle JEads Date 10/6/10 10/08/10 10/08/10 OFFICIAL RECORD COPY

University of California at Irvine Docket No. 50-326 cc:

Dr. Donald Blake, Chair Department of Chemistry University of California, Irvine Irvine, CA 92697-2025 Mr. Steve Hsu Radiological Health Branch State Department of Health Services P.O. Box 9442732 Sacramento, CA 94234-7320 Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

ENCLOSURE 1 EXAMINATION REPORT NO:

50-326/OL-10-01 FACILITY:

UNIVERSITY OF CALIFORNIA - IRVINE FACILITY DOCKET NO.:

50-326 FACILITY LICENSE NO.:

R-116 SUBMITTED BY:

_____________/RA/______________

10/6/2010 John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of September 27, 2010, the NRC administered examinations to one Reactor Operator and three Senior Reactor Operator Instant (SRO-I) candidates. One SRO-I candidate failed Section B, Normal and Emergency Operating Procedures and Radiological Controls, of the written examinations. All the other candidates passed all portions of the examinations.

REPORT DETAILS

1.

Examiner: John T. Nguyen, Chief Examiner

2.

Results:

RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 1/0 2/1 3/1 Operating Tests 1/0 3/0 4/0 Overall 1/0 2/1 3/1

3.

Exit Meeting:

George Miller, Reactor Supervisor John Nguyen, NRC, Examiner The NRC Examiner thanked the facility for their support in the administration of the operating tests. The facility licensee had no comments on the written examination except the comments presented during the administrative of the examination, which have been incorporated into the examination included as Enclosure 2 to this report.

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY:

UNIVERSITY OF CALIFORNIA - IRVINE REACTOR TYPE:

TRIGA DATE ADMINISTERED:

09/27/2010 CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% in each section to pass. Examinations will be picked up three (3) hours after the examination starts.

% of Category

% of Candidates Category Value Total Score Value Category 16.00 34.04 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 16.00 34.04 B. Normal and Emergency Operating Procedures and Radiological Controls 15.00 31.91 C. Plant and Radiation Monitoring Systems FINAL GRADE

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

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS 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 neither received nor 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 and each answer sheet.

6.

The point value for each question is indicated in [brackets] after the question.

7.

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

8.

To pass the examination you must achieve a grade of 70 percent or greater in each category.

9.

There is a time limit of three (3) hours for completion of the examination.

10.

When you have completed and turned in you examination, leave the examination area

EQUATION SHEET 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr T

UA

=

H m

=

T c

m

=

Q p

l (k) 2

)

(

=

P 2

max seconds 10 x 1

=

-4

• l sec

-1 eff 0.1

=

)

K (1

CR

=

)

K (1

CR eff 2

eff 1

2 1

K 1

S

=

SCR eff

26.06

=

SUR eff K

1 K

1

=

M eff eff 1

0 CR CR

=

K 1

1

=

M 2

1 eff 10 P

=

P SUR(t) 0 e

P

=

P t

0 P

)

(1

=

P 0

=

• l

eff

+

=

l K

)

K (1

=

SDM eff eff K

x k

K K

=

eff eff eff eff 2

1 1

2

0.693

=

T K

1)

K

(

=

eff eff

e DR

=

DR t

0 R

6CiE(n)

=

DR 2

d DR

=

d DR 2

2 2

1 2

1 Peak

)

(

=

Peak

)

(

1 1

2 2

2 2

1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O). 8 lbm EC = 5/9 (EF - 32)

Section A L Theory, Thermo, and Facility Characteristics A N S W E R S H E E T Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

A001 a b c d __

A002 a b c d __

A003 a b c d __

A004 a b c d __

A005 a b c d __

A006 a b c d __

A007 a b c d __

A008 a b c d __

A009 a b c d __

A010 a b c d __

A011 a __ b __ c __ d __

A012 a b c d __

A013 a b c d __

A014 a b c d __

A015 a b c d __

Section B Normal/Emerg. Procedures & Rad Con A N S W E R S H E E T Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

B001 a b c d __

B002 a __ b __ c __ d ___

B003 a b c d __

B004 a b c d __

B005 a __ b __ c __ d ___

B006 a b c d __

B007 a b c d __

B008 a b c d __

B009 a __ b __ c __ d ___

B010 a b c d __

B011 a b c d __

B012 a b c d __

B013 a __ b __ c __ d __

B014 a b c d __

B015 a b c d __

Section C Facility and Radiation Monitoring Systems A N S W E R S H E E T Multiple Choice (Circle or X your choice)

If you change your answer, write your selection in the blank.

C001 a b c d __

C002 a b c d __

C003 a b c d __

C004 a b c d __

C005 a b c d __

C006 a b c d __

C007 a __ b __ c __ d __

C008 a b c d __

C009 a b c d __

C010 a b c d __

C011 a b c d __

C012 a b c d __

C013 a b c d __

C014 a b c d __

C015 a b c d __

• • • • • END OF EXAMINATION *****

Section A L Theory, Thermo, and Facility Characteristics Question A.1 [1.0 point] Change was made per facility comment during the administrative of the examination.

Which ONE of the following is the major source of energy (heat) generated after SHUTDOWN?

a. Delayed neutrons.

b. The gamma radiation.

c. The kinetic decay energy of the fission fragments.

d. The heat liberated from neutrons slowing down in media.

Question A.2 [1.0 point]

Which ONE of the following is the MOST affected factor in the six factor formula when a poison in the control rods is changed from BORON (B) to CADMIUM (Cd)?

a. Fast fission factor ().

b. Thermal utilization factor (f).

c. Neutron reproduction factor ().

d. Resonance escape probability (p).

Question A.3 [1.0 point]

If the mean generation time for neutrons in a reactor is 0.1 sec and k = 1.001, the time for the power to double is:

a. 10 seconds

b. 69 seconds

c. 2 min

d. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

Section A L Theory, Thermo, and Facility Characteristics Question A.4 [1.0 point]

Which ONE of the following best describes the beta decay (-1) of a nuclide?

a. The atomic mass number unchanged, and the number of protons increases by 1.

b. The atomic mass number unchanged, and the number of protons decreases by 1.

c. The atomic mass number increases by 1, and the number of protons decrease by 1.

d. The atomic mass number increases by 2, and the number of protons increase by 1.

Question A.5 [1.0 point]

When compared to, eff is Y

a. smaller, because delayed neutrons are born at lower energies than prompt neutrons.

b. larger, because delayed neutrons are born at lower energies than prompt neutrons.

c. smaller, because delayed neutrons are born at higher energies than prompt neutrons.

d. larger, because delayed neutrons are born at higher energies than prompt neutrons.

Question A.6 [1.0 point]

Given a source strength of 100 neutrons per second (N/sec) and a multiplication factor of 0.8, the expected stable neutron count rate would be?

a. 125 N/sec

b. 250 N/sec

c. 400 N/sec

d. 500 N/sec

Section A L Theory, Thermo, and Facility Characteristics Question A.7 [1.0 point]

The reactor is on a CONSTANT positive period. Which ONE of the following power changes will take the longest time to complete?

a. 5%, from 95% to 100%

b. 10%, from 80% to 90%

c. 15%, from 15% to 30%

d. 20%, from 60% to 80%

Question A.8 [1.0 point]

The reactor is SHUTDOWN by 5.0% k/k with the count rate of 100 counts per second (cps).

The Shim rods are withdrawn until the count rate is a steady 2000 cps. What is the value of Keff at this point?

a. 0.952

b. 0.973

c. 0.998

d. 1.020 Question A.9 [1.0 point]

The term PROMPT JUMP refers toY

a. the instantaneous change in power due to raising a control rod.

b. a reactor which has attained criticality on prompt neutrons alone.

c. a reactor which is critical due to both prompt and delayed neutrons.

d. a negative reactivity insertion which is greater than eff.

Section A L Theory, Thermo, and Facility Characteristics Question A.10 [1.0 point]

Which ONE of the following conditions will INCREASE the shutdown margin of a reactor?

a. Lowering moderator temperature (assume negative temperature coefficient).

b. Insertion of a positive reactivity worth experiment.

c. Burnout of a burnable poison.

d. Fuel depletion.

Question A.11 [2.0 points, 0.5 each]

Match each of the terms in column A with the correct definition from column B.

Column A Column B

a. Fast neutrons

1. Neutrons released directly from fission.

b. Prompt neutrons

2. High energy neutrons.

c. Slow neutrons

3. Neutrons released from decay of fission products.

d. Delayed neutrons

4. Low energy neutrons.

Question A.12 [1.0 point]

Assume that the worths of the Shim rod, Reg rod, Adjustable Transient rod (ATR), and Fast Transients rod (FTR) are, respectively, $3.70, $2.80, $1.80 and $0.70. The reactor is critical at 5 W after WITHDRAWING the following control rod worths: Shim rod fully up, Reg rod at $2.00, ATR fully down, FTR at $0.50. What is the core excess?

a. -$0.90

b. $2.80

c. $6.20

d. $9.00

Section A L Theory, Thermo, and Facility Characteristics Question A.13 [1.0 point]

Which ONE of the following is the time period in which the maximum amount of Xe135 will be present in the core?

a. 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a startup to 100% power.

b. 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power increase from 50% to 100%.

c. 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a power decrease from 100% to 50%.

d. 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> after a scram from 100%.

Question A.14 [1.0 point]

The reactor is critical at 5 W. Which ONE of the following is the MINIMUM reactivity that must be added to produce prompt criticality?

a. Reactivity equal $1.10.

b. Reactivity equal to the eff.

c. Reactivity when Keff equals 1.008.

d. Reactivity when the stable reactor period equals 3 seconds.

Question A.15 [1.0 point]

Which of the following physical characteristics of the TRIGA fuel accounts for the majority of the negative temperature feedback?

a. Geometric buckling

b. Doppler broadening

c. Thermal expansion of the fuel matrix

d. Hardening of the neutron spectrum caused by heating the U-ZrH fuel

Section B Normal, Emergency and Radiological Control Procedures Page 17 Question B.1 [1.0 point]

An accessible area within the facility has general radiation levels of 500 mrem/hr. What would be the EXPECTED posting for this area?

a. "Caution, Very High Radiation Area"

b. "Danger, Airborne Radioactivity Area"

c. "Danger, High Radiation Area"

d. "Caution, Radiation Area" Question B.2 [1.0 point, 0.25 each]

Match the 10 CFR 55 requirements for maintaining an active operator license in column A with the corresponding time period from column B.

Column A Column B

a. Renew License 1 year

b. Medical Exam 2 years

c. Pass Requalification Written Examination 4 years

d. Pass Requalification Operating Test 6 years Question B.3 [1.0 point]

Exposing a 2 mCi check source to the continuous air monitor (CAM) detector to verify that its output is operable is

a. a Channel Test.

b. a Channel Check.

c. a Channel Calibration.

d. a Channel Verification.

Section B Normal, Emergency and Radiological Control Procedures Question B.4 [1.0 point]

Class II, Untried experiment must be submitted to

a. the Reactor Operator and such experiment shall be reviewed and approved by the Reactor supervisor.

b. the Reactor Supervisor and such experiment shall be reviewed and approved by the Reactor Administrator.

c. the Reactor Supervisor and such experiment shall be reviewed and approved by the ROC.

d. the Reactor Administrator and such experiment shall be reviewed and approved by the Radiation Safety Officer.

Question B.5 [1.0 point, 0.25 each]

Match type of radiation (a thru d) with the proper penetrating power (1 thru 4)

a. Gamma

1. Stopped by thin sheet of paper

b. Beta

2. Stopped by thin sheet of metal

c. Alpha

3. Best shielded by light material

d. Neutron

4. Best shielded by dense material Question B.6 [1.0 point]

Which ONE of the following is considered a damaged fuel?

a. In measuring the transverse bend, its lateral bending exceeds 1/16 inches over the length of the cladding.

b. In measuring the elongation, its length exceeds its original length by 1/16 inches.

c. A reactivity worth of fuel element is $0.02 less than the previous measure.

d. Fuel element that performed 500 pulses of magnitude greater than $1.50.

Section B Normal, Emergency and Radiological Control Procedures Question B.7 [1.0 point]

In order to maintain an active reactor or senior reactor operator license, the license-holder must perform the functions of his/her position for at least:

a. four hours per calendar quarter.

b. six hours per calendar quarter.

c. one hour per month.

d. sixteen hours per year Question B.8 [1.0 point]

The power level monitoring channels shall be calibrated at least _______ by calorimetric calibration.

a. monthly

b. quarterly

c. annually

d. biennially Question B.9

[2.0 points, 0.5 each] New paragraph was added per facility comment during the administrative of the examination.

Match each of the measuring channels in column A with the reactor modes for which it must be operable in column B. Items in column B is to be used only once.

Column A Column B

a. Fuel Temperature

1. Steady State ONLY

b. Reactor Power Level

2. Pulse ONLY

c. Startup Count Rate

3. All Modes

d. Reactor Power Level (high range)

4. During Reactor Startup

Section B Normal, Emergency and Radiological Control Procedures Question B.10

[1.0 point]

As permitted by 10 CFR 50.59, the UCI reactor facility may:

a. Modify systems and change the Technical Specifications (TS) if the NRC is notified afterwards.

b. Perform new and little understood experiments when they are for research.

c. Determine the affects of modifications and their impact on TS.

d. Redefine the boundaries of accidents previously analyzed in the Safety Analysis Report (SAR).

Question B.11

[1.0 point]

A radioactive source reads 35 Rem/hr on contact. Five hours later, the same source reads 1.5 Rem/hr. What will the sample read in another five hours?

a. 55 mrem

b. 65 mrem

c. 75 mrem

d. 750 mrem Question B.12

[1.0 point]

After 5 pulses, a gamma survey in a working area shows a radiation level of 1 R/hr. What is the longest time you can remain in that area without exceeding 50 mRem TEDE?

a. 1 min

b. 3 min

c. 10 min

d. 15 min

Section B Normal, Emergency and Radiological Control Procedures Question B.13

[1.0 point, 0.25 each]

Identify each of the following as a Safety Limit (SL), a Limiting Safety System Setting (LSSS), a Limiting Condition for Operation (LCO), or a normal operation (NO)

a. The temperature of a fuel element is 1000EC.

b. The temperature of a fuel element is 800EC at B-ring.

c. The maximum step insertion is $3.00 in the pulse mode.

d. The pool water level is 20 feet above the reactor top grid plate.

Question B.14

[1.0 point]

Which ONE of the following types of experiments shall NOT be irradiated at UCI Triga reactor?

a. The experiment can generate radioactive gases or aerosols.

b. The movable experiment has a reactivity worth of - $1.10.

c. The experiment has an I-131 inventory of 0.1 curies.

d. The experiment contains a corrosive material.

Question B.15

[1.0 point]

Which ONE of the following is the appropriate Emergency Classification due to a fuel handling accident in which major damage to fuel cladding occurs?

a. Non-Reactor, Safety-related Events

b. Notification of Unusual Events

c. Alert

d. Site Area Emergency

Section C Plant and Radiation Monitoring Systems Question C.1

[1.0 point]

The UCI Adjustable Transient Rod is located at:

a. B-ring.

b. C-ring.

c. D-ring

d. F-ring.

Question C.2

[1.0 point]

Which ONE of the following is the actual design feature which prevents siphoning of primary water on a failure of the primary piping?

a. Signal from a float switch shuts off the primary pump.

b. Signal from a float switch shuts a valve in the pump suction line.

c. All components of the water piping on both systems are above pool water level.

d. Level in the pool drops below the Net Positive Suction Head pressure minimum required to operate the pump.

Question C.3

[1.0 point]

Graphite inserts are placed in the top and bottom of the fuel element. Which ONE of the following best describes the function of these inserts?

a. To absorb thermal neutrons.

b. To reduce neutron leakage.

c. To absorb fission product gases.

d. To increase fast neutron flux.

Section C Plant and Radiation Monitoring Systems Question C.4

[1.0 point]

On a loss of normal electrical power, which ONE of the following systems is NOT provided by an emergency diesel generator?

a. RAM

b. CAM

c. Primary cooling pump

d. Emergency lightning in the control room Question C.5

[1.0 point]

What is the maximum acceptable time between the initiation of a scram signal, and the time that the SHIM rod is fully inserted in the core?

a. 2500 msec.

b. 2000 msec.

c. 1000 msec.

d. 500 msec.

Question C.6

[1.0 point]

The output of the compensated ion chamber (CIC) provides the signal for:

a. Period Channel.

b. Wide Range Linear Power Channel.

c. Power Range Channel (0 to 125% power).

d. Log Power Channel (10-8 to 200 % of full power).

Section C Plant and Radiation Monitoring Systems Question C.7 [2.0 points, 0.5 each]

Match the input signals listed in column A with their respective responses listed in column B.

(Items in column B may be used more than once or not at all.)

Column A Column B

a. Manual scram.

1. Indication only.

b. 30-sec period.

2. Indication and scram

c. 110% in linear channel

3. Indication and interlock

d. Apply air to the Adjustable Transient Rod while its cylinder is fully up at steady state mode.

Question C.8

[1.0 point]

Which one of the following correctly describes the operation of a Thermocouple?

a. A bi-metallic strip which winds/unwinds due to different thermal expansion constants for the two metals, one end is fixed and the other moves a lever proportional to the temperature change.

b. a junction of two dissimilar metals, generating a potential (voltage) proportional to temperature changes.

c. a precision wound resistor, placed in a Wheatstone bridge, the resistance of the resistor varies proportionally to temperature changes.

d. a liquid filled container which expands and contracts proportional to temperature changes, one part of which is connected to a lever.

Section C Plant and Radiation Monitoring Systems Question C.9

[1.0 point]

Question deleted during administrative of the examination. No correct answer in the distractors.

This question will not factor into the candidates grades.

If the Linear Power Channel output is 7% higher than the calculated thermal power calibration, the reactor operator needs to adjust the Linear Power Channel output by:

a. adjusting the CIC detector high voltage.

b. move the neutron source away from the CIC detector.

c. physically adjusting the height of the detectors in the support assembly.

d. move the graphite reflector to change the neutron flux near the detectors.

Question C.10 [1.0 point]

For calibration of the control rod, the operator calculates the reactor period by measuring the time required for the power to double or power to triple. This technique is called:

a. Rod Drop Method

b. Positive Period Method

c. Negative Period Method

d. Thermal Power Calibration Method Question C.11 [1.0 point]

Which ONE of the following is the main function of the demineralizer in the primary purification system?

a. Remove soluble impurity to maintain low conductivity in the tank water.

b. Reduce N-16 formation, thus reduce the dose rate at the reactor pool.

c. Absorb thermal neutrons, thus increase life of the reactor pool.

d. Absorb tritium, thus maintain purity of the pool water.

Section C Plant and Radiation Monitoring Systems Question C.12 [1.0 point]

Which ONE of the following best depicts the series of boundaries preventing fission product release to the environment?

a. Core shroud, pool water, positive sealing dampers

b. Pool water, reactor tank wall, high efficiency particulate air (HEPA) filters

c. Stainless steel fuel element cladding, pool water, positive sealing dampers, HEPA filters

d. Zirconium hydride lattice structure, pool water, HEPA filters Question C.13 [1.0 point]

Which ONE of the following elements is used as the neutron absorber in the Shim control rod?

a. Hafnium

b. Cadmium and boron

c. Borated stainless steel

d. Graphite with boron carbide Question C.14 [1.0 point]

Which ONE of the following is a correct mode of ventilation system when CAM is placed in the EMERGENCY alarm mode?

a. Main air inlets: OFF; purge exhaust fan: ON; pneumatic system blower: OFF

b. Main air inlets: ON; purge exhaust fan: OFF; pneumatic system blower: ON

c. Main air inlets: OFF; purge exhaust fan: ON; pneumatic system blower: ON

d. Main air inlets: ON; purge exhaust fan: OFF; pneumatic system blower: OFF

Section C Plant and Radiation Monitoring Systems Question C.15 [1.0 point]

A neutron flux will activate isotopes in air. The primary isotope we worry about in the pneumatic transfer system is

a.

N16 (O16 (n,p) N16).

b.

Kr80 (Kr79 (n, ) kr80).

c.

Ar41 (Ar40 (n, ) Ar41).

d.

H2 (H1 (n, ) H2).

• • • • • • • • • • • • • • • • • • • End of Section C *****************************

• • • • • • • • • • • • • • • • • • • End of the Exam ***************************

Section A L Theory, Thermo, and Facility Characteristics Answer Key A.1 c

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.2.1 A.2 b

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 4.5.

A.3 b

REF: T = L/k-1 T =.1/(1.001-1) = 100 N = Noet/T 2 = et/100.693 = t/100 t = 69.3 seconds A.4 a

REF: Chart of the Nuclides A.5 b

REF: Fundamentals of Nuclear Reactor Engineering (FONRE), ' 29.d, p. 29 A.6 d

REF: CR = S/(1-K) CR = 100/(1 -.8) = 500 A.7 c

REF: Time is related to ratio of final power to initial power. 2:1 is the largest ratio.

A.8 c

REF: Keff1=1/1-1 Keff1 =1/(1-(-.05)) -->Keff1= 0.952, Count1*(1-Keff1) = Count2*(1-Keff2)

Count1*(1-0.952) = Count2*(1-Keff2) 100*(1-0.952) = 2000(1-Keff2); Keff2 = 0.998 A.9 a

REF: FONRE, ' 79.h(3), p. 68 A.10 d

REF Standard NRC question A.11 a, 2; b, 1; c, 4; d, 3 REF: FONRE, 24 & 25, pp. 27 & 28 A.12 b

REF: Total worth=$(3.7+2.8+1.8+0.7)=$9; Reactivity at 5 W= $3.7 + $2.0 + $0.5 = $6.2 Core excess = Total worth - Reactivity at 5 W

$9.0-$6.2 = $2.8

Section A L Theory, Thermo, and Facility Characteristics A.13 d

REF: NRC Standard Question A.14 b

REF: Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 4.2.

A.15 d

REF: TRIGA Fuel Design

Section B Normal, Emergency and Radiological Control Procedures Answer Key B.1 c

REF: 10CFR20 B.2 a, 6; b, 2; c, 2; d, 1 REF: 10CFR55.

B.3 a

REF: T.S. Section 1.3 B.4 c

REF: UCINRF SOP, Sec 2.1 B.5 a, 4 b, 2 c, 1 d, 3 REF: Reactor Training Manual - Health Physics B.6 a

REF: Technical Specifications 4.1.b B.7 a

REF: Requalification Program.

B.8 c

REF: Technical Specifications 4.3 B.9 a, 3; b, 1; c, 4; d, 2 REF: Technical Specifications 3.3 B.10 b or c second answer added per facility comment during the administrative of the examination REF: 10 CFR 50.59 B.11 b

REF DR = DR*e -t 1.5 rem/hr =35 rem/hr* e -(5hr)

Ln(1.5/35) = -*5 --> =0.623; solve for another 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> later DR DR=1.5 Rem* e -0.623*(5)

DR=6.6*10 -2 Rem or ~65 mrem B.12 b

REF: 1000mR per hour or 16.7 mR per min (1000mR/60min).

To exceed 50 mR, staff can stay ~(50 mR/16.7 mR)*min or 3 min.

B.13 a, SL; b, LSSS; c, LCO; d, NO REF: Technical Specifications 2.1 and 2.3.

Section B Normal, Emergency and Radiological Control Procedures B.14 b

REF: UCINRF SOP, Sec 2.4.1 B.15 c

REF: EP, Sec 4.3

Section C Plant and Radiation Monitoring Systems Answer Key C.1 c

REF: SAR, Figure 4-13 C.2 c

REF: SAR, ' 13.4.1, page 13-15 C.3 b

REF: SAR, ' 4.2 &.

C.4 c

REF: Instruction Manual for Operators, Sec 4.9 C.5 c

REF: Technical Specifications 3.1 C.6 b

REF: Instruction Manual for Operators, Sec 6.2.2 C.7 a,2 b,1 c,2 d,3 REF: Instruction Manual for Operators, Sec 6.2 and TS 3.4 C.8 b

REF: NRC Standard Question C.9 c

REF: UCINRF SOP, Sec 4.3.2 Question deleted during administrative of the examination. No correct answer in the distractors.

This question will not factor into the candidates grades.

C.10 b

REF: UCINRF SOP, Sec 4.4.2.b C.11 a

REF: NRC Standard Question C.12 c

REF: NRC Standard Question C.13 d

REF: Instruction Manual for Operators, Sec 5.3

Section C Plant and Radiation Monitoring Systems C.14 a

REF: UCINRF SOP, Sec 4.7.3 C.15 c

REF: NRC Standard Question

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