Text

Examination Report No 50-005/OL-17-01, the Pennsylvania State University
	ML17256A266
Person / Time
Site:	Pennsylvania State University
Issue date:	09/14/2017
From:	Anthony Mendiola; Division of Policy and Rulemaking
To:	Unlu K; Pennsylvania State Univ, State College, PA
	John T. Nguyen
References
	50-005/OL-17-01
	Download: ML17256A266 (42)
	v • d • e

September 14, 2017 Dr. Kenan Unlu, Director The Pennsylvania State University Breazeale Nuclear Reactor Radiation Science and Engineering Center University Park, PA 16802-2301

SUBJECT:

EXAMINATION REPORT NO. 50-005/OL-17-01, THE PENNSYLVANIA STATE UNIVERSITY BREAZEALE RESEARCH REACTOR

Dear Dr. Unlu:

During the week of August 14, 2017, the U.S. Nuclear Regulatory Commission (NRC) administered an operator licensing examination at your Pennsylvania State University Breazeale research 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 with those members of your staff identified in the enclosed report at the conclusion of the examination.

In accordance with Title 10 of the Code of Federal Regulations, Section 2.390, 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 NRC is forwarding the individual grades to you in a separate letter which will not be released publicly. Should you have any questions concerning this examination, please contact Mr. John T. Nguyen at (301) 415-4007 or via e-mail at John.Nguyen@nrc.gov.

Sincerely,

/RA/ William Schuster for Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.50-005

Enclosures:

1. Examination Report No. 50-005/OL-17-01

2. Written Examination cc: Candace Davison cc w/o enclosures: See next page

K. Unlu 2

SUBJECT:

EXAMINATION REPORT NO. 50-005/OL-17-01, THE PENNSYLVANIA STATE UNIVERSITY BREAZEALE RESEARCH REACTOR DATED SEPTEMER 14, 2017.

DISTRIBUTION PUBLIC AMendiola AAdams Xyin OFont JNguyen ADAMS ACCESSION #: ML17256A266 TEMPLATE #:NRR-074 OFFICE NRR/DPR/PROB:CE NRR/DIRS/IOLB:OLA NRR/DPR/PROB:BC NAME JNguyen ABaxter AMendolia WSchuster for/

DATE 08/29/2017 09/13/2017 09/14/2017 OFFICIAL RECORD COPY

The Pennsylvania State University Docket No.50-005 cc:

Jeffrey A. Leavey Manager of Radiation Protection The Pennsylvania State University 0201 Academic Project BL University Park, PA 16802 Dr. Neil A. Sharkey, Interim Vice President for Research of the Graduate School The Pennsylvania State University 304 Old Main University Park, PA 16802 Director, Bureau of Radiation Protection Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105 Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611 Candace Davison Research & Education Specialist Supervisor Reactor Operators Radiation Science & Engineering Center Breazeale Nuclear Reactor Building University Park, PA 16802-1504

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-005/OL-17-01 FACILITY DOCKET NO.: 50-005 FACILITY LICENSE NO.: R-002 FACILITY: The Pennsylvania State University EXAMINATION DATES: August 15 - 17, 2017 SUBMITTED BY: __________/RA/________________ __08/29/17_

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of August 14, 2017, the NRC administered the operator licensing examinations to one Reactor Operator (RO) and three Senior Reactor Operator Instant (SROI) candidates.

All candidates passed all portions of the examination.

REPORT DETAILS

1. Examiners: John T. Nguyen, Chief Examiner, NRC

2. Results:

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

3. Exit Meeting:

Candace Davison, Associate Director for Operations, PSBR John Nguyen, Chief Examiner, NRC At the conclusion of the meeting, the NRC Examiner thanked the facility for their support in the administration of the examinations. The examiner discussed the weaknesses observed from the operating tests including the generic weaknesses in a basic understanding of 10 CFR 50.59, and a lack of knowledge in the operations of nuclear instrumentation channel. The facility licensee promised to take actions to improve program performance in the training programs.

Enclosure 1

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Pool REACTOR TYPE: TRIGA DATE ADMINISTERED: 08/15/2017 CANDIDATE: _______________________

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the Answer sheet provided. Attach all Answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.3 C. FACILITY AND RADIATION MONITORING SYSTEMS 60.00 % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature Enclosure 2

A. RX THEORY, THERMO & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

A01 a b c d ___

A02 a b c d ___

A03 a b c d ___

A04 a b c d ___

A05 a ___ b ___ c ___ d ___ (0.25 each)

A06 a b c d ___

A07 a b c d ___

A08 a b c d ___

A09 a b c d ___

A10 a b c d ___

A11 a b c d ___

A12 a b c d ___

A13 a b c d ___

A14 a b c d ___

A15 a b c d ___

A16 a b c d ___

A17 a b c d ___

A18 a b c d ___

A19 a b c d ___

A20 a b c d ___

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

B. NORMAL/EMERG PROCEDURES & RAD CON ANSWER SHEET Multiple Choice (Circle or X your choice)

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

B01 a b c d ___

B02 a ___ b ___ c ___ d ___ (0.25 each)

B03 a b c d ___

B04 a b c d ___

B05 a b c d ___

B06 a b c d ___

B07 a ___ b ___ c ___ d ___ (0.25 each)

B08 a b c d ___

B09 a ___ b ___ c ___ d ___ (0.25 each)

B10 a b c d ___

B11 a b c d ___

B12 a b c d ___

B13 a ___ b ___ c ___ d ___ (0.25 each)

B14 a b c d ___

B15 a ___ b ___ c ___ d ___ (0.25 each)

B16 a b c d ___

B17 a b c d ___

B18 a b c d ___

B19 a b c d ___

B20 a b c d ___

(***** END OF CATEGORY B *****)

C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice)

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

C01 a b c d ___

C02 a ___ b ___ c ___ d ___ (0.25 each)

C03 a b c d ___

C04 a b c d ___

C05 a ___ b ___ c ___ d ___ (0.25 each)

C06 a b c d ___

C07 a b c d ___

C08 a b c d ___

C09 a b c d ___

C10 a b c d ___

C11 a b c d ___

C12 a ___ b ___ c ___ (0.33 each)

C13 a b c d ___

C14 a b c d ___

C15 a b c d ___

C16 a b c d ___

C17 a b c d ___

C18 a b c d ___

C19 a b c d ___

C20 a b c d ___

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

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

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 PSBR 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. Mark your Answers on the Answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.

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

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

9. When turning in your examination, assemble the completed examination with examination questions, examination aids and Answer sheets. In addition turn in all scrap paper.

10. Ensure all information you wish to have evaluated as part of your Answer is on your Answer sheet. Scrap paper will be disposed of immediately following the examination.

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

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

EQUATION SHEET Q&= m&c p T = m&H = UA T ( - )2 P max = * -4

= 1 x 10 seconds 2 (k)

S CR 1 (1 - K eff 1 ) = CR 2 (1 - K eff 2 )

SCR =

1 - K eff eff = 0.1 sec -1 SUR = 26.06 eff 1 - K eff 0

- 1 CR1 M= M= =

1 - K eff 1 1 - K eff CR 2 P = P0 10 SUR(t) t P = P0 e (1 - )

P= P0 (1 - K eff )

SDM = = = +

K eff eff

( 2 )2 = (1 )2 Peak2 Peak1 K eff 2 - K eff 1 0.693 ( K eff - 1)

T=

k eff 1 x K eff 2 K eff 6CiE(n) 2 DR1 d 1 = DR 2 d 2 2

DR = DR0 e- t DR = 2 R

eff = 0.1/sec 1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5°C + 32 931 Mev = 1 amu °C = 5/9 (°F - 32)

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.01 [1.0 point]

The first pulse has a reactivity worth of $1.35 which results in a peak power of 100 MW. If the second pulse has a reactivity worth of $2.70, the corresponding peak power is:

Given: eff=0.0070

a. 200 MW

b. 1070 MW

c. 1350 MW

d. 2360 MW QUESTION A.02 [1.0 point]

The MAJOR source of energy released during fission comes from:

a. Fission neutrons

b. Fission fragments

c. Prompt gamma rays

d. Fission product decay for beta, gamma, and neutrinos QUESTION A.03 [1.0 point]

During the time following a reactor scram, reactor power decreases on an 80 second period, which corresponds to the half-life of the longest-lived delayed neutron precursors of:

a. 80 seconds

b. 55 seconds

c. 40 seconds

d. 20 seconds

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.04 [1.0 point]

Which ONE of the following correctly describes the SIX- FACTOR FORMULA?

a. K = Keff

the utilization factor

b. K = Keff

the total leakage probability

c. Keff = K

the total non-leakage probability

d. Keff = K * (the resonance escape probability

the reproduction factor)

QUESTION A.05 [1.0 point, 0.25 each]

Identify the descriptions or graphs in Column A in accordance with describe or depict integral control rod worth or differential rod worth Column A Column B

a. total reactivity worth of the control rod at that height 1. Differential Rod Worth

b. reactivity change per unit movement of a control rod 2. Integral Rod Worth c.

d.

QUESTION A.06 [1.0 point]

A reactor contains a neutron source that produces 10,000 neutrons/second. The reactor has a keff = 0.92. What is the stable total neutron production rate in the reactor?

a. 100,000 neutrons/sec

b. 115,074 neutrons/sec

c. 125,000 neutrons/sec

d. 135,135 neutrons/sec

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.07 [1.0 point]

Which ONE of the following is an atomic weight in the tritium nucleus (1T3 or 1 H3 )?

a. 1 b.

b. 2

c. 3

d. 4 QUESTION A.08 [1.0 point]

Which ONE of the following is the MAIN reason for operating reactor with thermal neutrons instead of fast neutrons?

a. The atomic weight of thermal neutrons is larger than fast neutrons, so thermal neutrons are easily to slow down and be captured by the fuel.

b. The neutron lifetime of thermal neutrons is longer than fast neutrons, so the fuel has enough time to capture thermal neutrons.

c. Fast neutrons give off higher radiation than thermal neutrons. Reactor needs to reduce a radiation level by using thermal neutrons.

d. The fission cross section of the fuel is much higher for thermal energy neutrons than fast neutrons.

QUESTION A.09 [1.0 point]

Which ONE of the following is the MINIMUM amount of reactivity that makes the PSBR (finite) critical reactor to be a prompt critical reactor? This MINIMUM amount is equal to:

a. $1.00

b. the k-effective value

c. 1.0 %K/K

d. A shutdown margin of $1.0

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.10 [1.0 point]

A few minutes following a reactor scram at full power, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. What is a reactor power level two minutes later from 1 kW?

a. 975 W

b. 446 W

c. 223 W

d. 111 W QUESTION A.11 [1.0 point]

Reactor A increases power from 10% to 20% with a period of 25 seconds. Reactor B increases power from 80% to 100% with a period of also 25 seconds. Compared to Reactor A, the time required for the power increase of Reactor B is:

a. longer than A

b. exactly the same as A

c. twice that of A

d. shorter than A QUESTION A.12 [1.0 point]

Given the associated graph, which of the following answers best describe the neutron behavior within Region II?

a. The neutron cross section is inversely proportional to the neutron velocity (1/V)

b. The neutron cross section decreases steadily with increasing neutron energy (1/E)

c. Neutrons of specific energy levels (e.g., 50 ev, 100 kev) have more likely leakage from the reactor core

d. Neutrons of specific energy levels (e.g., 50 ev, 100 kev) are more likely to be absorbed than neutrons at other energy levels

Section A L Theory, Thermo & Fac. Operating Characteristics Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.13 [1.0 point]

The Reactor is critical at 50 watts. A reactor operator makes a mistake by inserting a sample worth of $1.50 into the reactor core. Which ONE of the following best describes the values of Keff and during the power increment?

a. Keff = 1 and = 1

b. Keff > 1 and -eff < < 1

c. Keff > 1 and = 1.5

d. Keff > 1 and 1 < < infinity QUESTION A.14 [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.15 [1.0 point]

Delayed neutrons are produced by:

a. decay of N-16

b. Photoelectric Effect

c. decay of fission fragments

d. directly from the fission

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.16 [1.0 point]

Which ONE of the following describes the term PROMPT DROP?

a. A reactor is subcritical at negative 80-second period

b. A reactor has attained criticality on prompt neutrons alone

c. The instantaneous change in power level due to inserting a control rod

d. The instantaneous change in power level due to withdrawing a control rod QUESTION A.17 [1.0 point]

Which ONE of the following is a correct statement describing prompt and delayed neutrons?

Prompt neutrons:

a. are released during U-238 interacts with fast neutrons, while delayed neutrons are released during U-235 interacts with thermal neutrons.

b. account for less than 1% of the neutron population, while delayed neutrons account for the rest.

c. are released during the fission process, while delayed neutrons are released during the decay of fission products.

d. are the dominating factor in determining reactor period, while delayed neutrons have no effect on reactor period.

QUESTION A.18 [1.0 point]

If the multiplication factor, k, is increased from 0.900 to 0.950, the amount of reactivity added is:

a. 0.05 %K/K

b. 0.10 %K/K

c. 5.85 %K/K

d. 8.55 %K/K

Section A L Theory, Thermo & Fac. Operating Characteristics QUESTION A.19 [1.0 point]

Which ONE of the following physical characteristics of the TRIGA fuel is the MAIN contributor for the prompt negative temperature coefficient?

a. As the fuel heats up, the resonance absorption peaks broaden and increases the likelihood of absorption in U-238 and/or Pu-240.

b. As the fuel heats up, a rapid increase in moderator temperature occurs through conduction and convection of heat transfer mechanism which adds negative reactivity.

c. As the fuel heats up, the oscillating hydrogen in the ZrH lattice imparts energy to a thermal neutron, thereby increasing its mean free path and probability of escape.

d. As the fuel heats up, fission product poisons (e.g., Xenon) increase in concentration within the fuel matrix and add negative reactivity via neutron absorption.

QUESTION A.20 [1.0 point]

In a 50-watt power, adding 1.0% K/K worth of reactivity will cause:

a. The peak power to be equal to 1.1 MW.

b. The reactor period to be equal to (-)/.

c. A number of prompt neutrons equals to a number of delayed neutrons.

d. The resultant period to be a function of the prompt neutron lifetime (T=*/).

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

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.01 [1.0 point]

A room contains a source which, when exposed, results in a general area dose rate of 300 millirem per hour. This source is scheduled to be exposed continuously for 10 days. Which ONE of the following statements correctly describes an acceptable method for controlling radiation exposure from the source within this room?

a. Monitor the current dose rate in the reactor control room.

b. Post the area with the words Caution - Radiation Area.

c. Control is not required because the presence of radioactive source is less than 30 days.

d. Equip the room with an electronic surveillance that is capable of preventing unauthorized entry.

QUESTION B.02 [1.0 points, 0.25 each]

Match the radiation reading from Column A with its corresponding radiation area classification (per 10 CFR 20) listed in Column B. Answer in Column B can be used more than once, or not at all.

Column A Column B

a. 2 mrem/hr at 1 m 1. Public Area

b. 20 mrem/hr at 1 m 2. Radiation Area

c. 50 mrem/hr at 1 m 3. High Radiation Area

d. 5.5 grays/hr at 1 m 4. Very High Radiation Area QUESTION B.03 [1.0 point]

Per PSBR Technical Specifications, which ONE of the following will exceed the Limiting Safety System Settings?

a. Pulse operation exceeds 4.9 %k/k

b. Instrumented fuel temperature exceeds 650 °C

c. Steady State power exceeds 1.1 MW

d. Shutdown margin is less than 0.10 %k/k

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.04 [1.0 point]

A radiation from an unshielded source is 100 mrem/hr. What is a radiation level when shielding it with a lead sheet of 20 mm thickness? Given the half-value-layer (HVL) of lead = 10 mm.

a. 10 mem/hr

b. 25 mrem/hr

c. 50 mrem/hr

d. 75 mrem/hr QUESTION B.05 [1.0 point]

Which ONE of the following is NOT the MAIN function of the reactor coolant system?

a. Neutron moderator and reflector

b. Provide shielding of the reactor radiation

c. Dissipate heat generated in the reactor

d. Minimize effluents release to the environment QUESTION B.06 [1.0 point]

Hot Cell #2 is used for storage of Special Nuclear Material (SNM). What is the minimum level of authorization to be present when the SNM is unsecured?

a. Reactor Safeguards Committee

b. Reactor Supervisor

c. Licensed Senior Reactor Operator

d. Licensed Reactor Operator

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.07 [1.0 point, 0.25 each]

Identify each of the following surveillances as a channel check (CHECK), a channel test (TEST), or a channel calibration (CAL).

a. Adjust the Wide Range Linear Power Channel in accordance with recent data collected on the reactor thermal power calibration.

b. Verify the reactor interlock system by removing the neutron source away from the reactor core.

c. Compare readings of area radiation monitors during a reactor operation.

d. Verify a fuel temperature scram during the checkout.

QUESTION B.08 [1.0 point]

Which ONE of the following changes must be submitted to NRC for approval prior to implementation?

a. Replace a regulating control rod with identical one.

b. Revise the thermal power calibration procedure.

c. Add more responsibilities to the Radiation Protection Officer listed in the health physics procedure.

d. Change a minimum number of the Reactor Safeguards Committee from 5 to 7 members listed in the TS 6.2.1.

QUESTION B.09 [1.0 point, 0.25 each]

Match the appropriate radiation unit in Column A with its definition in Column B.

Column A Column B

a. Curie 1. Equal to absorbed dose of 100 ergs/gram

b. Roentgen 2. Amount of radioactive material decaying at a rate of 3.7x1010

c. RAD 3. Amount of x-ray or gamma ray leading to the absorption of 88 ergs/gram in air

d. Dose Equivalent 4. Equal to absorbed dose in RAD times quality factor

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.10 [1.0 point]

Per PSBR Emergency Plan, who is responsible for authorization of radiation exposure to personnel during an emergency response function that are in excess of normal occupational dose?

a. Police Chief with the occurrence of Emergency Director

b. Public Relations Coordinator with the occurrence of Reactor Director

c. Radiation Safety Officer with the occurrence of Dean of School

d. Emergency Director with the occurrence of Radiation Safety Officer QUESTION B.11 [1.0 point]

Which ONE of the following radionuclide causes a severe damage to thyroid gland from an intake?

a. I131

b. N16

c. Ar41

d. Co60 QUESTION B.12 [1.0 point]

A two-curie source, emitted 100% of 6.17 Mev gamma, is to be stored in the reactor building.

How far from the source does a survey meter read 100 mrem/hr?

a. 7 feet

b. 17 feet

c. 27 feet

d. 37 feet

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.13 [1.0 point, 0.25 each]

Match each of the Technical Specification Limits in column A with its corresponding value in column B. (Each limit has only one answer, values in Column B can be used once, more than once or not at all.)

Column A Column B (limit shall not exceed)

a. Maximum excess reactivity 1. $0.25

b. Maximum individual fixed experiment worth 2. $0.50

c. Minimum Shutdown Margin 3. $2.00

d. Maximum Reactivity Insertion 4. $3.50 in Pulse Mode

5. $5.00

6. $7.00 QUESTION B.14 [1.0 point]

The reactor is in a SHUTDOWN condition, as defined by PSBR Technical Specifications, when:

a. all rods are inserted to the reactor core.

b. the reactor is subcritical by at least $1.00 in the reference core condition, but EXCLUDED the reactivity worth of all installed experiments.

c. the console key is OFF position and no work is in progress involving core fuel, core structure, installed control rods, or control rod drives.

d. the reactor is subcritical by at least $1.00 in the reference core condition with the reactivity worth of all installed experiments INCLUDED.

QUESTION B.15 [1.0 point, 0.25 each]

Match type of radiation listed in column A with their quality factor listed in column B. Items in column B can be used once, more than once or not at all.

Column A Column B

a. X-ray 1. 1

b. Gamma 2. 5

c. Alpha particles 3. 10

d. High-energy neutron 4. 20

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.16 [1.0 point]

Which ONE of the following is NOT a responsibility of the SRO and RO?

a. Review and audit of safety aspects of reactor facility operations

b. Preparation of logs and records of reactor operations

c. Participation in requalification program

d. Insertion and removal of experiments QUESTION B.17 [1.0 point]

Per PSBR Emergency Classification, abnormal continual loss of reactor pool water that exceeds the combined makeup capability of all available refill system is an example of:

a. Non-Classified Event

b. Abnormal Condition of Operation

c. Unusual Event

d. Alert QUESTION B.18 [1.0 point]

A radioactive source reads 4 Rem/hr on contact. Two hours later, the same source reads 1 Rem/hr. How long is the time for the source to decay from a reading of 4 Rem/hr to 20 mRem/hr?

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

b. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

c. 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months

d. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Section B Normal/Emergency Procedures and Radiological Controls QUESTION B.19 [1.0 point]

Which ONE of the following materials may be irradiated in the reactor core?

a. Single movable experiment worth exceed $2.00.

b. Experiment with boiling point exceeds 200 °F and 25% of the vapors escaped.

c. Total inventory of I -131 through I-135 in the experiment exceeds 2 Ci.

d. Experiment causes the concentration of Ar-41 in the reactor stack exceeding 1.0 x 10 -9

µCi/ml over the year.

QUESTION B.20 [1.0 point]

Which ONE of the following conditions is NOT a violation of a Limiting Condition for Operations?

a. Reactor operator conducted a pulse and the peak power exceeded 500 MW.

b. Reactor was at full power. The heat exchanger failed, cause the primary coolant temperature exceeding 150 °F.

c. During a reactor operation, high voltage to reactor power detector failed and the reactor changed from automatic to steady state mode.

d. Reactor operator could withdraw the SHIM rod in the PULSE Mode.

(***** END OF CATEGORY B *****)

Section C Facility and Radiation Monitoring Systems QUESTION C.01 [1.0 point]

Per PSBR Technical Specifications, fuel elements are stored in a safe array with the MAXIMUM keff of _______.

a. 0.6

b. 0.7

c. 0.8

d. 0.9 QUESTION C.02 [1.0 point, 0.25 each]

Use the following diagram of the facility compressed air system. Match for the position locator listed in the diagram to the correct components.

a. Air dryer

b. Large compressor

c. Small compressor

d. To Transient Rod

Section C Facility and Radiation Monitoring Systems QUESTION C.03 [1.0 point]

A three-way solenoid valve controls the air supplied to the pneumatic cylinder of the transient rod. Which ONE of the following statements correctly describes when the solenoid is de-energized? When the solenoid is de-energized:

a. The valve cuts off the compressed air supply. The air in the cylinder is depleted thus allowing the piston to drop by gravity to its original position.

b. The valve opens the compressed air supply and build a pressure in the cylinder, thus allowing the compressed air drives the piston upward in the cylinder and causes the rapid withdrawal of the transient rod from the core.

c. The valve cuts off the compressed air supply and apply the pressure in the top of the cylinder, thus allowing the piston to drop by forcing the transient rod down.

d. The valve opens the compressed air supply and exhausts the pressure in the cylinder to an accumulator tank, thus allowing the piston to drop by gravity to its original position.

QUESTION C.04 [1.0 point]

You plan to perform a $1.50 pulse. Using the Transient Rod (TR) worth curve provided, find the pre-pulse TR position to be placed in for the initial 100 watt critical condition.

a. Fully down position

b. Fully up position

c. Between 425 - 435 position

d. Between 520 - 530 position

Section C Facility and Radiation Monitoring Systems Section C Facility and Radiation Monitoring Systems QUESTION C.05 [1.0 point, 0.25 each]

Match the input signals listed in column A with their AUTOMATIC Control Systems responses (reactor will automatically response when exceeding the conditions) in column B. (Items in column B may be used once, more than once or not at all). Assume that the reactor is in operation.

Column A Column B

a. HV loss to the Log Power detector 1. Indication ONLY

b. Watchdog timer time-out 2. Rod withdraw prohibit

c. Power Channel exceeds 1.0 MW 3. Scram

d. Withdrawal of Reg rod 4. Rod run-in during a pulse mode QUESTION C.06 [1.0 point]

The Power Range Channel consists of:

a. a gamma ion chamber, Multi-Range Amplifier, and the Power Range Monitor.

b. a gamma ion chamber, in-core thermocouples, and the Power Range Monitor.

c. a fission chamber, Wide Range Amplifier, and the Wide Range Monitor.

d. a fission chamber, in-core thermocouples, and the Power Range Monitor.

QUESTION C.07 [1 point]

Which ONE of the following elements is used as the neutron absorber on the PSBR Safety control rod?

a. Fuel follower

b. Zirconium-hydride

c. Borated graphite

d. Gold-indium-cadmium

Section C Facility and Radiation Monitoring Systems QUESTION C.08 [1.0 point]

Reactor is in a PULSE ready mode and you want to switch to a AUTO mode. Which ONE of the following can cause the control rod interlock when you switch it?

a. SHIM rod drive DOWN and SHIM control rod DOWN

b. SHIM rod drive UP and SHIM control rod DOWN

c. Pneumatic cylinder DOWN

d. Pneumatic cylinder UP QUESTION C.09 [1.0 point]

The nominal Hydrogen- Zirconium atom ratio in the TRIGA LEU fuel elements is:

a. 1.65 H atoms to 1.0 Zr atom

b. 1.0 H atom to 1.65 Zr atoms

c. 20 H atoms to 8.5 Zr atoms

d. 8.5 H atoms to 20 Zr atoms QUESTION C.10 [1.0 point]

For calibration of the control rod, the operator determines the rod reactivity by measuring the reactor period vs. rod withdrawal. This technique is called:

a. Rod Drop Method

b. Positive Period Method (In-hour Method)

c. Thermal Power Calibration Method

d. Negative Period-Differential Worth Method

Section C Facility and Radiation Monitoring Systems QUESTION C.11 [1.0 point]

The MAIN purpose for setting a conductivity limit of the pool water is to:

a. Maintain the departure of nucleate boiling ratio (DNBR) greater than the unity.

b. Minimize the possibility of corrosion of the cladding on the fuel elements.

c. Extend integrity of resin bed on the demineralizer.

d. Minimize Ar-41 released to the public.

QUESTION C.12 [1.0 point, 0.33 each]

Use the following diagram of the control rod. Match the three limit switches listed in Column A to the appropriate labels in Column B?

Column A Column B

a. The magnet Down limit switch 1

b. The rod Down limit switch 2

c. The magnet Up limit switch 3

Section C Facility and Radiation Monitoring Systems QUESTION C.13 [1.0 point]

The following diagram depicts:

a. Uncompensated Ion Chamber

b. Fission Chamber

c. Compensated Ion Chamber

d. Proportional Counter QUESTION C.14 [1.0 point]

Several sources of water are available for adding water to the reactor pool. Which ONE of the following sources provides the lowest conductivity?

a. Use 6000 gallon underground tank to pump water into the recirculation loop.

b. Directly add water from the University water system through a fire hose.

c. Directly add water from Thomson Pond through a fire hose.

d. Directly add water from a campus fire hydrant.

Section C Facility and Radiation Monitoring Systems QUESTION C.15 [1.0 point]

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

a. Pool water, reactor tank wall, HEPA filters.

b. Fuel element cladding, Demineralizer system, HEPA filters.

c. Core shroud, pool water, Reactor building with negative pressure.

d. Fuel element cladding, pool water, Reactor building with negative pressure, HEPA filters.

QUESTION C.16 [1.0 point]

The reactor is at full power. All facility exhaust fans are suddenly OFF and only emergency exhaust system is operable. For this event, which ONE of the following is the best action?

a. The operator shall shutdown the reactor; and then immediately report the result to the NRC due to TS 3.5 violation.

b. The operator may continue an operation for periods of time up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per TS 3.5.

c. The operator shall shutdown the reactor; and then immediately report the result to the supervisor due to TS 3.5 requirement.

d. The operator may continue an operation since the emergency exhaust system is still operable; but immediately report the result to the supervisor.

QUESTION C.17 [1.0 point]

During reactor operation, a leak develops in the SECONDARY to PRIMARY heat exchanger.

Which ONE of the following correctly explains the reactor pool level?

a. Pool level will increase because the Primary pressure is HIGHER than the Secondary pressure.

b. Pool Level will increase because the Primary pressure is LOWER than the Secondary pressure.

c. Pool Level will be the same because the Primary pressure is EQUAL to the Secondary pressure.

d. Pool Level will decrease because the Primary pressure is LOWER than Secondary pressure.

Section C Facility and Radiation Monitoring Systems QUESTION C.18 [1.0 point]

Which ONE of the following conditions will prevent applying air to the Transient Rod (TR) system due to TR air interlock?

a. Pool temperature exceeds 40 °C.

b. In pulse mode and initial power low (200 W).

c. Air has previously been applied (permissive latch).

d. In steady state mode and transient rod drive at its top of travel.

QUESTION C.19 [1.0 point]

Fill out the blank. There consists _____magnetic float switches providing the input to the console for _____ pool level low alarms and _____ pool level high alarm.

a. 3/2/1

b. 3 /1 / 2

c. 4 / 2 /2

d. 2 / 2/ 0 QUESTION C.20 [1.0 point]

Which ONE of the following is considered the subsystem of Reactor Safety System (RSS)?

a. The SCRAM and Alarm Panel Assembly, contains annunciator lamps for display of the trip status of each control rod, for the DCC-X Watchdog SCRAM and for visual indication of trip status from individual spare inputs.

b. A control computer (DCC-X) system with hardware I/O and computer monitor / keyboard operator interface.

c. All Radiation Monitoring System to ensure personnel radiation safety during reactor operation.

d. A hardwired reactor safety system which uses relay logic to perform SCRAM and operational interlock functions.

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

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

Section A L Theory, Thermo & Fac. Operating Characteristics A.01 Answer: d

( 2 )2 = (1 )2 Peak2 Peak1 1=($1)(eff)=($1.35)(.007)=(.00945) 2=($2)(eff)=($2.70)(.007)=(.0189)

Peak Power 2 = 2359 MW

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, 1988. § 4.6, p. 4-16 A.02 Answer: b

Reference:

A.03 Answer: b

Reference:

Group 1 is the longest-lived delayed neutron precursor for thermal fission in U-235, with a half-life of 55.72 sec.

Lamarsh, J. Introduction to Nuclear Engineering p. 88 A.04 Answer: c

Reference:

DOE Fundamentals Handbook, NPRT, Vol. 2, Module 3, EO 5.4, EO 5.5, EO 5.6, pp 51-53 A.06 Answer: c N = (S) (M)

M = 1 / (1-keff) = 1 / (1-0.92) = 12.5 N = (10,000)(12.5) = 125,000 neutrons/second

Reference:

DOE Fundamentals Handbook, NPRT, Vol. 2, Module 4, EO 1.2, p 4 A.07 Answer: c

Reference:

Nuclides and Isotopes A.08 Answer: d

Reference:

Section A L Theory, Thermo & Fac. Operating Characteristics A.09 Answer: a

Reference:

P = P0 e-t/T = 1 kW

e(120sec/-80sec) = 1 kW

exp(-1.5) = 0.223

1 kW = 0.223 kW = 223 W A.11 Answer: d

Reference:

The power of reactor A increases by a factor of 2, while the power of reactor B increases by a factor of 1.25. Since the periods are the same (rate of change is the same), power increase B takes a shorter time.

A.12 Answer d

Reference:

DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2 A.13 Answer: b

Reference:

decreasing the reactivity worth in the core will increase the shutdown margin.

A.15 Answer: c

Reference:

A.16 Answer: c

Reference:

A.17 Answer: c

Reference:

= (keff1-keff2)/(keff1 x keff2) = (0.95-0.9) /(0.9*0.95)=0.0585 K/K or 5.85

%K/K

Section A L Theory, Thermo & Fac. Operating Characteristics A.19 Answer: c

Reference:

TRIGA Fuel Design A.20 Answer d

Reference:

Section B Normal/Emergency Procedures and Radiological Controls B.01 Answer: d

Reference:

10 CFR 20.1601(b)

B.02 Answer: a(2); b(3); c(3); d(4)

Reference:

10 CFR 20.1003 Definitions 2 mrem/hr at 1 m = 22.2 mrem/hr at 30 cm => Radiation area 50 mrem/hr at 1m = 0.55 rem/hr at 30 cm => high radiation area 20 mrem/hr at 1m will be equal to 222 mrem/hr at 30 cm :=> high radiation area 5.5 grays 550 rad/hr at 1 m very high radiation area Definition High Radiation Area: 100 mrem/hr at 30 cm Radiation Area : 5 mrem/hr at 30 cm Very High Radiation Area: 500 rads/hr at 1 m B.03 Answer: b

Reference:

TS 2.2 B.04 Answer: b

Reference:

From 100mrem to 50 mrem required 10 mm of lead sheet From 50 mrem to 25 mrem required another 10 mm of lead sheet So 20mm of lead sheet will reduce a radiation from 100 mrem/hr to 25 mrem/hr B.05 Answer: d

Reference:

SAR, Chapter 5, Introduction B.06 Answer: c

Reference:

AOP-1, Hot Cell Lab Procedure B.07 Answer: a = CAL; b = TEST; c = CHECK; d = TEST

Reference:

TS 1.1 B.08 Answer: d

Reference:

NRC Standard Questions B.09 Answer: a (2), b(3), c(1), d(4)

Reference:

Training Manual 6 B.10 Answer: d

Reference:

EP 3.5

Section B Normal/Emergency Procedures and Radiological Controls B.11 Answer: a

Reference:

Basic Health Physics B.12 Answer: c

Reference:

6CEN = R/hr @ 1 ft. -> 6 x 2 x 6.17 x 1 = 74 R/hr at 1ft.

I0D02 = I*D2 74 R/hr*(1 ft) 2 = 0.1 R/hr *D 2 D= sqrt(74/0.1) = 27.2 ft.

B.13 Answer: a(6); b(3); c(1); d(4)

Reference:

TS 3.1 B.14 Answer: d

Reference:

TS 1.1.30 B.15 Answer: a(1) b(1) c(4) d(3)

Reference:

10 CFR 20 B.16 Answer: a

Reference:

TS 6.2 B.17 Answer: d

Reference:

EP 4.2 B.18 Answer: b

Reference:

DR = DR*e -t 1 rem/hr =4 rem/hr* e -(2hr)

Ln(1/4) = -*2 --> =0.693; solve for t: Ln(.02/4)=-0.693 (t) t=7.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B.19 Answer: d

Reference:

TS 3.7 B.20 Answer: a

Reference:

TS 3.7

Section C Facility and Radiation Monitoring Systems C.01 Answer: c

Reference:

TS 5.4 C.02 Answer: a(3) b(2) c(1) d(4)

Reference:

Training Manual 5.3.1 C.03 Answer: a

Reference:

NRC Standard Question C.04 Answer: d

Reference:

SOP-1 C.05 Answer: a(3) b(3) c(1) d(2)

Reference:

SAR, Instrumentation and Control C.06 Answer: b

Reference:

NRC Standard Question C.07 Answer: c

Reference:

SAR, Figure 4-6 C.08 Answer: d

Reference:

SAR 7.4.3 and 7.4.4 C.09 Answer: a

Reference:

TS 5.1 C.10 Answer: b

Reference:

CCP-15 C.11 Answer: b

Reference:

TS 3.3.5 C.12 Answer: a(1) b(3) c(2)

Reference:

SAR, Figure 4.9

Section C Facility and Radiation Monitoring Systems C.13 Answer: c

Reference:

Training Manual 4.1 C.14 Answer: a

Reference:

Training Manual 5.2.2 C.15 Answer: d

Reference:

NRC Standard Question C.16 Answer: c

Reference:

TS 3.5 C.17 Answer: b

Reference:

Training Manual 5.2.5 C.18 Answer: d

Reference:

SAR 7.4.3 C.19 Answer: a

Reference:

Training Manual 5.2.1 C.20 Answer: d

Reference:

SAR 7.2.3 and Training Manual 4.2

ML17256A266

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