Initial Examination Report No. 50-005/OL-13-01, Pennsylvania

September 3, 2013

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

SUBJECT: EXAMINATION REPORT NO. 50-005/OL-13-01, PENNSYLVANIA STATE UNIVERSITY BREAZEALE RESEARCH REACTOR

Dear Dr. Unlu:

During the week of August 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Breazeale Nuclear 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 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. Gregory M. Schoenebeck at (301) 415-6345, or via e-mail at [email protected].

Sincerely,

/RA/

Gregory T. Bowman, 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-13-01 2. Facility Comments with NRC Resolution 3. Written examination with facility comments incorporated cc: Mark Trump, Associate Director for Operations w/o enclosures: See next page

September 3, 2013

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

SUBJECT: EXAMINATION REPORT NO. 50-005/OL-13-01, PENNSYLVANIA STATE UNIVERSITY BREAZEALE RESEARCH REACTOR

Dear Dr. Unlu:

Sincerely,

/RA/

Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-005

DISTRIBUTION: PROB r/f RidsNrrDprProb RidsNrrDprPrlb

ADAMS Accession No: ML13239A334 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME GSchoenebeck CRevelle GBowman DATE 08/28 /2013 08/30/2013 09/03/2013 OFFICIAL RECORD COPY

Pennsylvania State University Docket No. 50-005 cc:

Mr. Eric J. Boeldt, Manager of Radiation Protection The Pennsylvania State University 304 Old Main University Park, PA 16802-1504

Dr. Eva J. Pell Vice President and Dean of the Graduate School Pennsylvania State University 304 Old Main University Park, PA 16802-1504

Director, Bureau of Radiation Protection Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469

Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT

REPORT NO.: 50-005/OL-13-01

FACILITY DOCKET NO.: 50-005

FACILITY LICENSE NO.: R-2

FACILITY: Pennsylvania State University Breazeale Nuclear Reactor

EXAMINATION DATES: August 12 – August 15, 2013

SUBMITTED BY: ______/RA/______08/29/13_ Gregory M. Schoenebeck Date

SUMMARY:

During the week of August 12, 2013, the NRC administered operator licensing examination to one Senior Reactor Operator (SRO) and seven Reactor Operator (RO) license candidates. The entire license candidates passed all applicable portions of the examinations.

REPORT DETAILS

1. Examiners: Greg M. Schoenebeck, Chief Examiner, NRC

2. Results: RO PASS/FAIL SRO PASS/FAIL TOTAL PASS/FAIL Written 7/0 N/A 7/0 Operating Tests 7/0 1/08/0 Overall 7/0 1/08/0

3. Exit Meeting: Gregory M. Schoenebeck, Chief Examiner, NRC Paulette Torres, Reactor Engineer, NRC Mark Trump, Associate Director for Operations Dr. Kenan Unlu, Director

At the conclusion of the site visit, the examiner met with representative of the facility staff to discuss the results of the examinations. The facility licensee had three comments on the written examination recommending changing the answer key on question A.7, A.18 and C.1 (see Enclosure 2).

ENCLOSURE

FACILITY COMMENTS ON THE WRITTEN EXAM WITH NRC RESOLUTION

QUESTION A.7 [1.0 point]

An experiment worth 13 cents of negative reactivity is added to a reactor that is initially critical at a power of 1000 Watts. Assuming there is no automatic system response, operator action, or any other reactivity effects, calculate the power level 2 minutes after the reactivity insertion.

Given:

βeff= 0.0070 -1 λeff= 0.05 sec

a. 2 Watts

b. 406 Watts

c. 500 Watts

d. 750 Watts

Given:

βeff= 0.0070 -1 λeff= 0.05 sec

First, converting negative $0.13 to ∆k/k -0.13*0.0070= -0.00091

(0.007-(-0.00091))/((0.05)*(-0.00091))= -173.4 sec

= 1000 e (120/-173) = 499.7 Watts or 500 Watts

Facility Comment: The facility stated that the answer key correctly calculates the power at 2 minutes as being 499.7 Watts (answer C), however lists letter A (2 Watts) as the correct answer. The answer key should be changed to: C (500 Watts)

NRC Resolution: The NRC agrees with the facility comment and accepts c as the correct answer.

ENCLOSURE 2 - 2 -

QUESTION A.18 [1.0 point]

The PSBR has what is known as a prompt negative temperature coefficient. Which of the following is the largest contributing factor to the prompt negative temperature coefficient? a. Doppler effect b. Compton’s Scattering c. Cell effect d. Core Leakage

Answer: d Reference: PSBR Training Manual, Chapter 3 Appendix A.10

Facility Comment: The facility stated that the answer key references the PSBR Training Manual, Chapter 3 Appendix A.10. According to this reference, 15% of the prompt negative temperature coefficient is caused by Doppler effect, 65% by cell effect, and 20% by core leakage. The answer key lists d (core leakage) as the correct answer. The answer key should be changed to c (cell effect).

NRC Resolution: The NRC agrees with the facility comment and accepts c as the correct answer.

- 3 -

QUESTION C.1 [1.0 point]

When the ventilation system is in the emergency exhaust mode ______. a. air outside of the PSBR facility is pulled into the emergency exhaust system through a screened opening in the east wall of the reactor bay to dilute the filtered air that is ultimately released through the 18” PVC Emergency Exhaust Stack which terminates above the main Reactor Bay roof. b. air outside of the PSBR facility is pulled into the emergency exhaust system and a DCC-X message “Emerg Ventilation Flow On” can be observed by the Reactor Operator which is the most positive indication that the system has flow. c. filtered air is recirculated in the reactor bay to prevent the potential release of fission products to the environment. d. filtered air is ultimately released through the 18” PVC Emergency Exhaust Stack which terminates above the main Reactor Bay roof.

Answer: a Reference: PSBR Training Manual, Chapter 5.3.4.3

Facility Comment:

Answer Key should be changed to “d” the correct Answer.

Analysis: a. Incorrect EES pulls only from the screened opening on the east wall reactor bay, the air released from the Exhaust stack is not diluted, only filtered. b. Incorrect no outside air is pulled into EES. All air discharged by the EES during operation originates from within the reactor bay. c. Incorrect no recirculation occurs filtered air is discharged above the main reactor bay roof d. Correct – Filter air is released from the EES exhaust stack above the reactor bay roof level

NRC Resolution: The staff agrees with the facility’s comment. The answer key will be modified to accept “d” as the correct answer for question C.1.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR INITIAL LICENSE EXAMINATION

FACILITY: PENN STATE UNIVERSITY

REACTOR TYPE: POOL TYPE, MODIFIED TRIGA

DATE ADMINISTERED:

CANDIDATE: ______

INSTRUCTIONS TO CANDIDATE: Answers are to be written on the answer sheet provided. Attach the answer sheets to the examination. Points for each question are indicated in parentheses for each question. A 70% overall is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY % OF CANDIDATE’S CATEGORY CATEGORY VALUE TOTAL SCORE VALUE

A. REACTOR THEORY, 20.00 33.3 ______THERMODYNAMICS, AND FACILITY OPERATING CHARACTISTICS

B. NORMAL AND EMERGENCY 20.00 33.3 ______OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS

20.00 C. FACILITY AND RADIATION 33.3 ______MONITORING SYSTEMS

60.00 ______TOTALS FINAL GRADE

ALL THE WORK DONE ON THIS EXAMINATION IS MY OWN. I HAVE NEITHER GIVEN NOR RECEIVED AID.

______CANDIDATE'S SIGNATURE

- 2 -

Section A: Reactor Theory, Thermodynamics & Facility Operating 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.

MULTIPLE CHOICE

001 a b c d _ 011 a b c d _

002 a b c d _ 012 a b c d _

003 a b c d _ 013 a b c d _

004 a b c d _ 014 a b c d _

005 a b c d _ 015 a b c d _

006 a b c d _ 016 a b c d _

007 a b c d _ 017 a b c d _

008 a b c d _ 018 a b c d _

009 a b c d _ 019 a b c d _

010 a b c d _ 020 a b c d _

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

- 3 -

Section B Normal, Emergency and Radiological Control Procedures

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.

MULTIPLE CHOICE

001 a b c d _ 011 a b c d _

002 a b c d _ 012 a b c d _

003 a b c d _ 013 a b c d _

004 a b c d _ 014 a b c d _

005 a b c d _ 015 a b c d _

006 a b c d _ 016 a b c d _

007 a b c d _ 017 a b c d _

008 a b c d _ 018 a b c d _

009 a b c d _ 019 a b c d _

010 a b c d _ 020 a b c d _

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

- 4 -

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.

MULTIPLE CHOICE

001 a b c d _ 011 a __ b __ c _

002 a b c d _ 012 a b c d _

003 a b c d _ 013 a b c d _

004 a b c d _ 014 a b c d _

005 a b c d _ 015 a b c d _

006 a b c d _ 016 a b c d _

007 a b c d _ 017 a b c d _

008 a b c d _ 018 a b c d _

009 a b c d _ 019 a b c d _

010 a b c d _ 020 a b c d _

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

- 5 -

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

During the administration of this examination the following rules apply:

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

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

3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.

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

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

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

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

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

9. Partial credit will NOT be given.

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

11. When you are done and have turned in your examination, leave the examination area as defined by the examiner.

- 6 -

EQUATION SHEET ════════════════════════════════════════════════════════════

2 2 ()ρ − β ()ρ − β −1 2 = 1 λ =0.1sec = Δ = Δ = Δ eff Q m cP T m H UA T Peak Peak 2 1

t = Τ S S * −4 P P0 e SCR = ≅ =1×10 sec − ρ −  1 Keff

λ ρ + ρ  eff   SUR = 26.06 ( − )= ( − )  β − ρ  CR1 1 Keff CR2 1 Keff CR ()− ρ =CR ()− ρ   1 2 1 1 2 2

β ()− ρ 1 CR = 1 M = = 2 P = P 10SUR(t) P P0 − 0 β − ρ 1 K eff CR1

1− K * eff1 1− K M = SDM = eff Τ=  1− K ρ − β eff 2 Keff

*  β − ρ  0.693 K − K  = eff 2 eff1 Τ= +   T1 Δρ = ρ λ ρ + ρ 2 λ  eff   K K   eff1 eff2

− Keff 1 −λ ρ = = t 2 2 DR DR0 e = DR1 d1 DR2d2 K eff

() = 6Ci E n μ DR 2 R

DR – Rem/hr, Ci – curies, E – Mev, R – feet

1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 inch=2.54 cm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.41 x 106 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32

1 gal (H2O) ≈ 8 lbm °C = 5/9 (°F - 32) cP = 1.0 BTU/hr/lbm/°F cp = 1 cal/sec/gm/°C

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics - 7 -

QUESTION A.1 [1.0 point] Complete the following sentence. ______is a unit of measure, which most correctly relates to the ______. a. Percent millirho (pcm), delayed neutron precursor decay constant (λ) b. %Δk/k, fast fission factor (ε) c. Δk/k / ˚F, moderator temperature coefficient d. A Dollar ($1), delayed neutron fraction (β)

QUESTION A.2 [1.0 point] Isotopes are nuclides that have the same atomic number and are therefore the same element, but differ in number of ______. a. protons b. electrons c. neutrons d. positrons

QUESTION A.3 [1.0 point] When an irradiated sample used for an experiment is removed from the reactor, it reads 25 rem/hr. Five hours later it reads 1.5 rem/hr. What is the half-life of the radioactive element in the sample? Assume all readings are taken on contact. a. 0.25 hr b. 0.81 hr c. 0.96 hr d. 1.23 hr

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics - 8 -

QUESTION A.4 [1.0 point] You are performing a 50 Watt Critical Rod Position. Given the following data listed in the table below, calculate the Shutdown Margin, as defined by Technical Specifications, given a clean, cold reactor core condition.

Core Reactivity Evaluation Data Control Total Critical Rod Worth Worth Transient $3.02 $1.64 Safety $4.23 $2.40 Shim $2.87 $1.60 Regulating $2.85 $1.54 a. $1.31 b. $2.92 c. $2.95 d. $5.79

QUESTION A.5 [1.0 point] The number of nuclei that decay (or disintegrate) per unit time is called the ______of a sample? a. Cross-Section b. Activity c. Criticality d. Reactivity

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics - 9 -

QUESTION A.6 [1.0 point] Which of the following is the MOST CORRECT statement regarding various neutrons that are typically produced in a TRIGA reactor? a. Fast neutrons are those that occur directly from the fission reaction. b. Slow neutrons are low energy neutrons that enable more control over the reactor. c. Prompt neutrons are high energy neutrons (> 1MeV). d. Delayed neutrons are released through fission fragment decay.

QUESTION A.7 [1.0 point] An experiment worth 13 cents of negative reactivity is added to a reactor that is initially critical at a power of 1000 Watts. Assuming there is no automatic system response, operator action, or any other reactivity effects, calculate the power level 2 minutes after the reactivity insertion.

Given:

βeff= 0.0070 -1 λeff= 0.05 sec e. 2 Watts f. 406 Watts g. 500 Watts h. 750 Watts

QUESTION A.8 [1.0 point] Suppose a reactor scram has just occurred in a reactor where βeff =0.0070 with rods that have a worth of 0.10 Δk/k. Following the scram, what percentage of the initial starting power will reactor power drop? a. 5.9% b. 6.8% c. 7.2% d. 13.7%

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics - 10 -

QUESTION A.9 [1.0 point] The total energy released per fission will vary from one fission event to the next, depending on what fission products are formed, but the average total energy released per fission of uranium- 235 with a thermal neutron is ______? a. 10 W b. 10 MeV c. 200 MeV d. 1 MW

QUESTION A.10 [1.0 point] The following terms are variables that help to determine the fraction of neutrons that remain after every possible process in a nuclear reactor. Which of the following equations best describes the number of fission neutrons that exist at the end of a life cycle that are available to start a new generation?

Terms: ε Fast Fission Factor η Reproduction Factor p Resonance Absorption Probability Lf Fast Non-leakage Probability Lth Thermal Non-Leakage Probability f Thermal Utilization Factor a. N= No ε b. N= No ε Lf p Lth c. N= No ε Lf p Lth f d. N= No ε Lf p Lth f η

QUESTION A.11 [1.0 point] Complete the following sentence: Due to greater neutron ______and less ______by D2O than by H2O, the power in the front of the core is enhanced when the reactor is operated against the D2O tank. a. reflection, absorption b. absorption, reflection c. capture, activation d. activation, capture

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics - 11 -

QUESTION A.12 [1.0 point] Coolant flows through a reactor core at a rate of 50 GPM, resulting in a coolant temperature increase of 6 degrees F. The power of the reactor is ______. a. 5.3 kW b. 14.7 kW c. 44.0 kW d. 329.1 kW

QUESTION A.13 [1.0 point] Which of the following most correctly describes the "prompt critical" condition for a reactor? a. It occurs when there is an instantaneous jump in reactor power when the condition of the reactor is past the point of adding heat. b. It is a condition when the reactor is supercritical with only prompt neutrons. c. It is a condition when the reactor is supercritical with the summation of prompt and delayed neutron effects. d. It occurs when the amount of reactivity inserted into the reactor exceeds the core excess with the most reactive rod stuck in its highest position.

Section A: Reactor Theory, Thermodynamics, and Fac. Operating Characteristics - 12 -

QUESTION A.14 [1.0 point] The following figure represents the differential rod worth of a reactor core. Based on this figure, which of the following statements best describes the characteristic of differential rod worth in the core?

a. The amount of reactivity per inch of travel is greatest at the bottom of the core because the rods have the greatest amount of worth in this region. b. The amount of reactivity per inch of travel is the greatest in the center of the core is greatest because the neutron flux is greatest in this region. c. As the rods approach the top of the core the reactivity effects become greater and the change in rod worth per inch of travel becomes greater. d. The reactivity at the center of the core is where the differential rod worth is greatest and varies significantly with rod motion.

QUESTION A.15 [1.0 point] Light water, like that found in the PSBR’s pool, is an excellent moderator for thermalizing neutrons. Which of the following most correctly describes one of the nuclear properties of an ideal moderator? a. Large absorption cross-section. b. Small energy loss per collision c. Large scattering cross-section d. Small Doppler Broadening effect

Section B: Normal/Emergency Procedures & Radiological Controls - 13 -

QUESTION A.16 [1.0 point] Which of the following is the MOST CORRECT response that describes an effect delayed neutrons have in a reactor? a. Delayed neutrons decrease the mean neutron lifetime (l*) from ≈1 x 10-4 sec to 1 x 10-4 minus the βeff. b. Following a prompt drop (e.g., reactor scram), neutron level in the reactor core is sustained by the decay of fission product precursors. c. In a reactor with delayed neutron effects, the reactor period (τ) would be equal to the mean neutron lifetime (l*) divided by the reactivity addition. d. Without delayed neutrons, Keff would always be less than 1.

QUESTION A.17 [1.0 point] Which of the following statements best characterizes the process of “natural circulation” which is present during PSBR operations? a. The driving force is related to a difference in density. b. Heat transfer is more efficient as the heat source decays. c. The Cherenkov radiation creates an ideal temperature differential for the thermal driving force through the core. d. The elevation of the heat source must be above that of the heat sink.

QUESTION A.18 [1.0 point] The PSBR has what is known as a prompt negative temperature coefficient. Which of the following is the largest contributing factor to the prompt negative temperature coefficient.? a. Doppler effect b. Compton’s Scattering c. Cell effect d. Core Leakage

QUESTION A.19 [1.0 point] A reactor contains a neutron source that produces 110,000 neutrons per second. The reactor has a keff of 0.986. Calculate the stable total neutron production rate in the reactor. a. 5.54 x 104 neutrons/second b. 1.08 x 105 neutrons/second

Section B: Normal/Emergency Procedures & Radiological Controls - 14 - c. 9.86 x 105 neutrons/second d. 7.86 x 106 neutrons/second

QUESTION A.20 [1.0 point] Which ONE of the following is the MOST CORRECT time period in which the MAXIMUM amount of Xe-135 will be present in the core? a. 8 hours after a startup to 100% power b. 8 hours after a scram from 100% power c. 8 hours after a power increase from 50% to 100% d. 8 hours after a power decrease from 100% to 50%

QUESTION B.1 [1.0 point] Without any operator actions, Code 11 “Evacuation Initiated” is automatically sent to the University Police when the following situation exists. Assume all Code numbers are correct. a. Code 03 Intrusion- Reactor b. Code 04 Reactor Pool Level Low (1) c. Code 14 East Bay Radiation High d. Code 96 Line Busy

QUESTION B.2 [1.0 point] By definition, ______are those constraints in the Technical Specifications that are required for safe operations of the reactor. a. Safety Limits (SLs) b. Limiting Conditions for Operation (LCOs) c. Surveillances d. Licensed Operational Conditions (LOCs)

QUESTION B.3 [1.0 point] Assume an individual has received whole body occupational exposures of:

• 25 mrads of gamma • 2 mrads of alpha • 1 mrads of neutrons with unknown energy

Section B: Normal/Emergency Procedures & Radiological Controls - 15 -

What would be the cumulative dose equivalent (HT) in mrem for this individual? a. 28 mrem b. 55 mrem c. 67 mrem d. 75 mrem

QUESTION B.4 [1.0 point] According to the PSBR Operating License, the maximum reactivity insertion during pulsing operations shall not exceed ______? a. $2.00 b. $3.25 c. 2.45%Δk/k d. 1.40%Δk/k

QUESTION B.5 [1.0 point] Which of the following is NOT an SOP-1 requirement for the channels required for reactor operation per the PSBR TS? a. RSS Fuel 1 and DCC-X Fuel 1 OR RSS Fuel 2 and DCC-X Fuel 2 b. RSS Percent Power OR DCC-X Digital Power (kW) c. RSS Log Power AND DCC-X Digital Log Power (dec) d. RSS Percent Power AND DCC-X Digital Power (kW)

QUESTION B.6 [1.0 point] What would you expect to find in an area that is only posted with a sign that reads, “CAUTION, RADIOACTIVE MATERIAL”? a. Quantities of licensed materials ≥ than those listed in 10 CFR 20, Appendix C values. b. Quantities of licensed materials with airborne concentrations that are ≥ 1 DAC. c. Quantities of licensed material whose streaming radiation is ≥ 5 rem at 30 cm from the radiation source. d. Quantities of licensed material whose dose would exceed the 10 CFR 20 limit for a member of the public within 1 hour.

Section B: Normal/Emergency Procedures & Radiological Controls - 16 -

QUESTION B.7 [1.0 point] The following statement in the PSBR Emergency Plan is an example of a(n) ______that would be used to classify an event for response purposes.

“Actual or projected radiological effluents at the site boundary which are calculated or measured to result in either of the following conditions, both of which are based on an exposure of 24 hours or less. A deep dose equivalent of 15 mrems or a committed effective dose equivalent of 15 mrems based on the following considerations.” a. Emergency Classification Guide b. Emergency Limiting Condition for Operation c. Emergency Action Level d. Protective Action Guideline

QUESTION B.8 [1.0 point] If you ARE NOT active watchstander, by the Requalification Plan, how many hours of licensed RO or SRO activity must you perform to become current? a. 2 b. 4 c. 6 d. 8

QUESTION B.9 [1.0 point] You are a reactor operator at the PSBR and handling irradiated samples in accordance with PSBR procedures and precautions. One of the irradiated sample you pull directly from the core measures 100 Rem/hr at 1 meter. If you moved 10 meters away how long would you have to wait before you would exceed your Total Effective Dose Equivalent (TEDE) limit for radiation exposure? a. 0.5 hr b. 1 hr c. 2 hrs d. 5 hrs

Section B: Normal/Emergency Procedures & Radiological Controls - 17 -

QUESTION B.10 [1.0 point] To minimize radiation effects, SOP-1 prohibits reactor operation closer than ______to the pool divider walls. a. 1 foot b. 2 feet c. 3 feet d. 4 feet

QUESTION B.11 [1.0 point] You are diligently studying for your NRC Operator License Examination, when the on-duty SRO comes into your office and asks you to fill the necessary information from the table below. What is the most probable reason the SRO needs this information?

qgenerated = qremoved by HX + qwall + qconduction + qevap + qpool heat up

qremoved by HX = Flow rate x ∆T x 265 watts / gpm - °C

qwall = 3 kW for maximum ∆T

qconduction = 9 kW for maximum ∆T

qevaporation = 3 kW from experimental data

qpool heat up = 170 kW per 1 °C / hr

a. A determination of the PSBR moderator temperature coefficient is being made. b. The data will be used as part of a thermal power calibration at the PSBR. c. The reactor’s core excess determination is being made for the PSBR. d. The information is required as part of the daily startup checklist at the PSBR.

QUESTION B.12 [1.0 point] According to the PSBR E-Plan, the ______is responsible for the termination of an emergency classified as an “ALERT” at the reactor. a. Emergency Director b. Senior Reactor Operator c. University Police d. Dean of the Graduate School (i.e., Licensee for the PSBR)

Section B: Normal/Emergency Procedures & Radiological Controls - 18 -

QUESTION B.13 [1.0 point] As a precaution in SOP-1, when performing a PULSE, the MINIMUM limit of reactivity is ____ with the transient rod. a. β b. $1.50 c. $2.50 d. $3.00

QUESTION B.14 [1.0 point] You are sitting at the reactor control console reviewing approved experiment authorizations. Of the following who would you most likely expect to have been the approving signature of authority for a new experiment (reviewed in accordance with TS and procedures) that is being inserted into the PSBR core? a. PSBR Associate Director for Operations b. The On-Duty SRO c. The Reactor Safeguards Committee d. Dean of the Graduate School (i.e., Licensee for PSBR)

QUESTION B.15 [1.0 point] You are the reactor operator with the reactor operating at power. You receive when you receive a DCC-X alarm that reads “HX Differential Pressure Low”. Which of the following actions would you most likely take based on this alarm? a. Immediately scram the reactor because there is insufficient primary coolant flow required by TS. b. Inform the SRO and perform a normal shutdown because pool water level has gotten too low (by TS) and must be refilled by normal means. c. Press the evacuation alarm because it is likely that you have a primary to secondary contamination leak. d. Recommend that the SRO or someone off-duty go to the Pump Room in the lower level of the PSBR to check the status of the secondary cooling pump.

Section B: Normal/Emergency Procedures & Radiological Controls - 19 -

QUESTION B.16 [1.0 point] You are performing the “POWER RANGE MONITOR CHECKS AND TESTS, SHIM ROD SYSTEM FUNCTIONAL PERFORMANCE CHECK” per SOP-2. After following the steps for aligning the system for the checks and tests, you ramp % Power on Power Range Monitor using POWER TEST pushbutton. Which of the following is NOT an expected system response following this action? a. There will be increasing indications of power visible on the RSS LCD bar graph display and the DCC-X digital displays. b. GIC Power Hi RSS SCRAM is visible on the DCC-X LCD display. c. Transient rod air releases. d. The N-16 pump turns on at ≈180 kW.

QUESTION B.17 [1.0 point] According to 10 CFR 20, the NRC requires that workers exceeding what percentage of the annual dose limit be monitored (i.e., issued dosimetry) for radiation exposure? a. 5% b. 10% c. 20% d. 50%

QUESTION B.18 [1.0 point] In the event of a suspected fuel leak from a 30/20 TRIGA element, which of the following nuclides would most likely be found in an Air Particulate Sample? a. Cs-138 b. Rn-226 c. Xe-133 d. Co-60

QUESTION B.19 [1.0 point] The PSBR facility pool wall is breached and there is significant leakage, resulting in the lowering of pool level at a rate of 1 cm/minute. Which of the following is the greatest issue/concern as a result of this event? a. Overheating the TRIGA fuel, resulting in clad failure and fission product release.

Section B: Normal/Emergency Procedures & Radiological Controls - 20 - b. Overheating the TRIGA fuel, resulting in Zirconium-Hydride reaction which releases explosive hydrogen gas. c. Groundwater contamination to the surrounding water table. d. Increased personnel exposure to higher amounts of radiation.

QUESTION B.20 [1.0 point] Bypass for SCRAM (F1) is used in SOP-2 ______. a. to allow for reactor reset with SCRAM conditions present b. to allow for testing of the DCC-X SCRAM setpoints c. to allow for testing of RSS SCRAM setpoints d. to prevent a scram on high radiation levels when using the rabbit system

Section C: Facility and Radiation Monitoring Systems - 21 -

QUESTION C.1 [1.0 point] When the ventilation system is in the emergency exhaust mode ______. a. air outside of the PSBR facility is pulled into the emergency exhaust system through a screened opening in the east wall of the reactor bay to dilute the filtered air that is ultimately released through the 18” PVC Emergency Exhaust Stack which terminates above the main Reactor Bay roof. b. air outside of the PSBR facility is pulled into the emergency exhaust system and a DCC-X message “Emerg Ventilation Flow On” can be observed by the Reactor Operator which is the most positive indication that the system has flow. c. filtered air is recirculated in the reactor bay to prevent the potential release of fission products to the environment. d. filtered air is ultimately released through the 18” PVC Emergency Exhaust Stack which terminates above the main Reactor Bay roof.

QUESTION C.2 [1.0 point] The figure below is an example of the gas ionization curve for gas-filled detectors. Which of the following ROMAN NUMERALS corresponds to the GEIGER-MUELLER REGION?

a. Region II b. Region III c. Region IV d. Region V

Section C: Facility and Radiation Monitoring Systems - 22 -

QUESTION C.3 [1.0 point] The purge gas for the Power Range Monitor is ______. a. CO2 b. Argon c. Nitrogen d. Oxygen

QUESTION C.4 [1.0 point] The output of the ______is always proportional to the neutron population in the core regardless of the power level. a. Power Range Monitor b. Wide Range Monitor c. Pulse Power Monitor d. Instrumented Fuel Element

QUESTION C.5 [1.0 point] The ______is coupled to its drive by air pressure applied to its cylinder via a solenoid valve. a. Safety rod b. Shim rod c. Regulating rod d. Transient rod

QUESTION C.6 [1.0 point] Regarding experimental apparatus setup at the PSBR, a gamma shield is located at a 45- degree angle to the D2O tank collimator tube in order to ______. a. minimize streaming core gammas from entering the collimator tube b. minimize the positive reactivity excursion that could exceed PSBR TS when the core is in the D2O position c. allow the maximum amount of heat transfer between the core and the collimator tube when the core is in the D2O position d. reduce the amount of fast neutron embrittlement to the steel structure components on the experiment bridge and the pool wall when the core is in the D2O position.

Section C Facility and Radiation Monitoring Systems Page 23

QUESTION C.7 [1.0 point] According to the PSBR Training Manual, which of the following sources of pool makeup water provides very poor water quality due to Chlorine? a. Processed water from the 6000 gallon evaporator hold underground tank that can be pumped into the recirculation loop. b. Water from the University water system that can be added to the pool through the demineralizer via a hose connection in the pump room. c. Water from Thomson Pond the secondary side of the heat exchanger that can be diverted directly to the pool through a fire hose stored in the reactor west bay floor pit for emergency make-up water. d. University water that can be added via a fire hose from a campus fire hydrant with the assistance of the Fire Company.

QUESTION C.8 [1.0 point] Per PSBR TS under no conditions should any experiment or action be initiated which would allow ______to be introduced into the pool water. If ______came in contact with the stainless steel fuel element cladding, it could possibly cause a failure of the cladding leading to a fission product release. a. Nitrogen b. Argon c. Mercury d. Chlorine

QUESTION C.9 [1.0 point] Unlike the standard control rods, the Transient rod has a(n) ______filled follower that is 21" long. a. air-filled b. boron carbide c. 8.5% weight uranium d. graphite

Section C Facility and Radiation Monitoring Systems Page 24

QUESTION C.10 [1.0 point] In addition to prolonging the amount of time for the N-16 radiation to reach the pool surface, the N-16 diffuser pump is used ______a. to determine the coolant ion exchanger inlet conductivity. b. to better distribute the heat generated by the fuel throughout the pool. c. to circulate the normal natural convective flow from the core. d. as a backup detector to reactor power level indication.

QUESTION C.11 [1.0 point, 0.33 each] The Emergency Exhaust System (EES) filter system consists of three stages. Match the following three stages with their purpose. a. Pre-filter 1. high efficiency for removing fission gases b. Absolute filter 2. low-cost, filter atmospheric dust c. Carbon filter 3. high-efficiency, needed to remove particulate radiation

QUESTION C.12 [1.0 point] Operations above 900 kW require balanced rods ______. a. to prevent exceeding the 1 MW license limit b. to prevent a 110% overpower scram c. to compensate for the inability of the automatic control system to keep up with a rod withdrawal at full speed d. to minimize local power peaking at high powers

QUESTION C.13 [1.0 point] According to the PSBR SOP-1 pulses shall be initiated from a stable 100W with balanced rods to ______. a. allow enough time to start-up the reactor b. ensure repeatability and facilitate the comparison of pulsing results c. position the Transient rod cylinder d. prevent exceeding the maximum pulse limit of 2000 MW

Section C Facility and Radiation Monitoring Systems - 25 -

QUESTION C.14 [1.0 point] By procedure, reactor core rotation and reactor bridge movement north, south, east or west is prohibited when the amount of reactivity removed from the core is ______. a. greater than $5.50 b. less than $1.00 shutdown c. less than $4.50 d. equal to the shutdown margin.

QUESTION C.15 [1.0 point] The gamma ion chamber and the in-core thermocouples are subsystems of the ______, which is part of the Reactor Safety System (RSS). a. Wide Range Channel b. Power Range Channel c. Control and Alarm d. Power Distribution

QUESTION C.16 [1.0 point] ______is the mode of operation initiated by firing the transient rod to provide an immediate step increase in reactor power to a desired level. a. Manual b. Auto c. Square Wave d. Pulse

QUESTION C.17 [1.0 point] Which ONE of the following conditions would most likely initiate a reactor stepback? a. The pulse timer times-out. b. High radiation from the East Bay Monitor c. Inadvertent actuation of the emergency evacuation button d. A reactor operation inhibit signal during reactor startup.

Section C Facility and Radiation Monitoring Systems - 26 -

QUESTION C.18 [1.0 point] The start-up source used in the PSBR is a ______source. a. Am-Li b. Am-Be c. Sb-Be d. Pu-Be

QUESTION C.19 [1.0 point] According to the PSBR TS, the Core Excess limit is ______. a. $0.25 b. $1.00 c. $3.50 d. $7.00

QUESTION C.20 [1.0 point] Which of the following best describes the purpose of the bottom reactor grid plate? a. It supports the weight of the fuel. b. It maintains lateral fuel alignment. c. It permit insertion of wires for in-core measuring purposes. d. It has a central thimble with a 1.33" inside diameter to facilitate the irradiation of large in- core experiments.

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Section A: Reactor Theory, Thermodynamics, and Facility Operating Characteristics

Question:

A.1 Answer: c Reference: Reactor Theory (Neutron Characteristics) 93 DOE-HDBK-1019/1-93 Nuclear Physics and Reactor Theory Vol. 2

A.2 Answer: c Reference: DOE Fundamentals Handbook DOE-HDBK-1019/1-93 Nuclear Physics and Reactor Theory Vol. 1

A.3 Answer: d

-λt DR2=DR1e ln(DR2/DR1)/t= -λ=-0.693/t0.5 t0.5 =(-0.693)(5 hrs)/ln(1.5 Rem/25 Rem) =1.23 hr

Reference: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2

A.4 Answer: c

Core Reactivity Evaluation Data Control Total Critical Rod Worth Worth Transient $3.02 $1.64 Safety $4.23 $2.40 Shim $2.87 $1.60 Regulating $2.85 $1.54

SDM = ∑Critical worth – Most reactive Rod worth remaining out of core SDM = ($1.64+2.40+1.60+1.54)-$4.23 = $2.95

Reference: PSU Exam Reference Material (Adapted CP-11 data, performed 5/22/2012)

A.5 Answer: b Reference: PSU Training Manual Section 1.3 Activity

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Given:

βeff= 0.0070 -1 λeff= 0.05 sec

= First, converting negative $0.13 to ∆k/k -0.13*0.0070= -0.00091 (0.007-(-0.00091))/((0.05)*(-0.00091))= -173.4 sec

= 1000 e (120/-173) = 499.7 Watts or 500 Watts

A.8 Answer: c Using the following from the given equation sheet:

β ()1− ρ P = P β − ρ 0  P/Po=((0.0070)(1+0.10))/(0.0070+0.1)= 7.2%

A.9 Answer: c Reference: PSU Training Manual Chapter 3, pg. 16

A.10 Answer: d Reference: PSU Training Manual Chapter 3, pg. 55

A.11 Answer: a Reference: PSU Training Manual Chapter 3, A.5 Operation of Reactor Against D2O Tank

A.12 Answer: c

Power = (Mass flow rate)(Specific heat)(temperature increase) Power = (50 GPM)(8.34 lbs/gallon)(1 Btu/lb-deg F)(6 deg F)(60 min/hour) Power = (150,120 Btu/hour)(1 kW/3413 Btu/hour) = 44.0 kW

Reference: INITIAL EXAMINATION REPORT 50-005/OL-07-01, PENNSYLVANIA STATE UNIVERSITY, July 6, 2007, Question A.17

A.13 Answer: b

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Reference: 10.

A.14 Answer: b Reference: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2

A.15 Answer: c Reference: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 1

A.17 Answer: a Reference: General Physics, HT&FF, pp. 355 - 358

A.18 Answer: c Reference: PSBR Training Manual, Chapter 3 Appendix A.10

A.19 Answer: d

Substituting M= 1/ (1-keff)

Reference: PSU Training Manual Chapter 3 and DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2

A.20 Answer: b Reference: DOE Fundamentals Handbook Nuclear Physics and Reactor Theory Vol. 2

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Section B: Normal Emergency Procedures & Radiological Controls

Question:

B.1 Answer: c Reference: PSU Training Manual Chapter 5 “Facility Design and Emergency Systems”

B.2 Answer: b Reference: AP-5 “R-2 License and PSBR TS”, November 2009

B.3 Answer: d

Reference: PSU Training Manual Chapter 6 “Radiation Protection Topics”

B.4 Answer: c Reference: AP-5 “R-2 License and PSBR TS”, November 2009

B.5 Answer: b Reference: SOP-1 “Reactor Operating Procedure”, Rev. 21

B.6 Answer: a Reference: PSU Training Manual Chapter 6 “Radiation Protection Topics”

B.7 Answer: c Reference: EP-1 “Emergency Preparedness Plan Implementation”, Rev.16

B.8 Answer: c Reference: 10CFR55.53(e)

B.9 Answer: d 2 2 (DR1)(R1) = (DR2)(R2)

(100 R/hr)(1 m)2=(X) (10 m)2= 1 R/hr Occupational whole-body dose (i.e., TEDE) limit per 10 CFR 20= 5 Rem for The individual would have to stay in the area for 5 hours before they exceeded this dose limit.

Reference: 10 CFR 20

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B.10 Answer: d Reference: SOP-1, “Reactor Operating Procedure” Rev. 21

B.11 Answer: b Reference: CCP-2 “Reactor Thermal Power Calibration”, Rev. 2

B.12 Answer: a Reference: EP-1 “Emergency Preparedness Plan Implementation”, Rev. 16 B.13 Answer: b Reference: SOP-1, “Reactor Operating Procedure” Rev. 21

B.14 Answer: a Reference: “R-2 License and PSBR TS”, November 2009

B.15 Answer: d Reference: “R-2 License and PSBR TS”, November 2009 and PSU Training Manual Chapter 5 “Facility Design and Emergency Systems”

B.16 Answer: d Reference: SOP-2, Rev. 25 Step H. and I.

B.17 Answer: b Reference: 10 CFR 20; Bevelacqua, J. Basic Health Physics.

B.18 Answer: a Reference: PSBR SAR and Operator Training Manual

B.19 Answer: d Reference: SOP-1 “Reactor Operating Procedure”

B.20 Answer: c Reference: SOP-2 “Daily Checkout Procedure”, Rev. 25 and PSBR 2012 Exam Bank Questions for Section B

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Section C: Facility and Radiation Monitoring Systems

Question:

C.1 Answer: d Reference: PSBR Training Manual, Chapter 5.3.4.3

C.2 Answer: d Reference: PSBR Training Manual, Chapter 4, Figure 4.1

C.3 Answer: a Reference: PSBR Training Manual, Chapter 4, Section 4.1.14

C.4 Answer: b Reference: PSBR Training Manual, Chapter 3, A.3

C.5 Answer: d Reference: PSBR Training Manual, Chapter 4, Section 4.2.4

C.6 Answer: a Reference: PSBR Training Manual, Chapter 5, Section 5.4.2

C.7 Answer: d Reference: PSBR Training Manual, Chapter 5, Section 5.2.2

C.8 Answer: c Reference: PSBR Training Manual, Chapter 5, Section 5.1.4

C.9 Answer: a Reference: PSBR Training Manual, Chapter 5, Section 5.1.6

C.10 Answer: c Reference: PSBR Training Manual Chapter 5, Section 5.2.7 & PSBR SAR, Chapter 4, Section 4.4, pg. IV-20

C.11 Answer: a2, b3, c1 Reference: PSBR Training Manual Chapter 5, Section 5.3.4.1

C.12 Answer: d

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Reference: PSBR Training Manual, Chapter 3, A.7

C.13 Answer: b Reference: PSBR SOP-1, Section V.F., pg. 11

C.14 Answer: a Reference: PSBR SOP-1, Section G.3, pg. 24

C.15 Answer: b

Reference: PSBR SAR, Chapter 7, Section 7.2.3.1, pg. VII-8

C.16 Answer: c Reference: PSBR SAR, Chapter 7, Section 7.3.1.1, pg. VII-14

C.17 Answer: d Reference: PSBR SAR, Chapter 7, Section 7.3.1.3, pg. VII-15

C.18 Answer: b Reference: PSBR SAR, Chapter 4, Section 4.2.4, pg. IV-17

C.19 Answer: d Reference: PSBR SAR, Chapter 4, Section 4.5.1, Table 4-1, pg. IV-21 & TS 3.1.2 (a) pg. 11 of 56

C.20 Answer: a Reference: PSBR SAR, Chapter 4, Section 4.2.5, pg. IV-18