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Examination Results Report, No. 50-27/OL-14-01, Washington State University
	ML14163A034
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Site:	Washington State University
Issue date:	06/18/2014
From:	Isaac P J; Research and Test Reactors Licensing Branch
To:	Wall D; Washington State Univ
	Nguyen J
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June 18, 2014

Dr. Donald Wall, Director Nuclear Radiation Center

Roundtop Drive Washington State University Pullman, WA 99164-1300

SUBJECT:

EXAMINATION REPORT NO. 50-27 OL-14-01, WASHINGTON STATE UNIVERSITY

Dear Dr. Wall:

During the week of June 2, 2014, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations at your Washington State University 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 Section 2.390 of Title 10 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 Av ailable 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 co ncerning this examination, please contact Mr.

John T. Nguyen at (301) 415-4007 or via email John.Nguyen@nrc.gov.

Sincerely,

/RA/

Patrick J. Isaac, Acting Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Docket No. 50-27

Enclosures:

1. Examination Report No. 50-27/OL-14-01

2. Facility Comments with NRC Resolution

3. Written examination with facility comments

cc: Corey Hines, Washington State University cc: w/o enclosures: See next page

ML14163A034 OFFICE NRR/DPR/PROB NRR/DPR/PROB NRR/DPR/PROB NAME JNguyen CRevelle PIsaac DATE 06/17/2014 06/18/2014 06/18/2014

Washington State University Docket No. 50-27 cc:

Director Division of Radiation Protection Department of Health

7171 Cleanwater Lane, Bldg #5 P.O. Box 47827

Olympia, WA 98504-7827 Mr. David Clark Director, Radiation Safety Office Washington State University P.O. Box 641302 Pullman, WA 99164-1302

Dr. Ken Nash Chair, Reactor Safeguards Committee Nuclear Radiation Center Washington State University P.O. Box 641300

Pullman, WA 99164-1300

Test, Research and Training

Reactor Newsletter P.O. Box 118300 University of Florida

Gainesville, FL 32611-8300

ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT

REPORT NO.: 50-27/OL-14-01

FACILITY DOCKET NO.: 50-27

FACILITY LICENSE NO.: R-76

FACILITY: Washington State University TRIGA Reactor

EXAMINATION DATES: June 2 - June 4, 2014

SUBMITTED BY: __________________________ _________

John T. Nguyen, Chief Examiner Date

SUMMARY

During the week of June 2, 2014, the U.S. Nuclear Regulatory Commission (NRC) administered operator licensing examinations to two Reactor Operator (RO) license candidates. One license candidate passed all applicable portions of t he examinations, but the other passed the NRC operating test and failed the written examination.

REPORT DETAILS

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

2. Results:

RO PASS/FAILSRO PASS/FAIL TOTAL PASS/FAILWritten 1/10/01/1 Operating Tests 2/00/02/0 Overall 1/10/01/1

3. Exit Meeting:

John T. Nguyen, Chief Examiner, NRC Corey Hines, Reactor Supervisor, Washington State University

At the conclusion, the examiner met with representative of the facility staff to discuss the results of the examinations. The facility licensee had no comments on the written examination except recommendation of changing the answer key on question B.2 (see ).

ENCLOSURE 2 FACILITY COMMENTS ON THE WRITTEN EXAM WITH NRC RESOLUTION Question B.2 Facility Comment: The answer key references Administrative Procedure #9 Section E. Using this reference, section E is Physical Inventory. The procedure states that "The physical

inventory shall comply with the provisions of 10 CFR 70.51(d) and shall be made by two individuals, one of whom shall be a licensed senior operator or the Director of the Facility."

Since the location and disposition of SNM is SGI, only licensees may participate in the inventory, resulting in a minimum of a Senior Reactor Operator and Reactor Operator needed to perform the inventory. Answer D is the correct answer instead of C

Reference:

Administrative Procedure #9, Section E NRC Resolution: The NRC agrees with the facility comment and accepts D as a correct answer.

ENCLOSURE 3 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Washington State University REACTOR TYPE: TRIGA DATE ADMINISTERED: June 2, 2014 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 Section A - Rector Theory, Thermohydraulics & Facility Operating Characteristics 2 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.

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 ___

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 *****)

Section B - Normal/Emergency Procedures and Radiological Controls 3 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.

B01 a ___ b ___ c ___ d ___ (0.25 each)

B02 a b c d ___

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 ___

B08 a b c d ___

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

B10 a ___ b ___ c ___ d ___ (0.25 each)

B11 a b c d ___

B12 a b c d ___

B13 a b c d ___

B14 a b c d ___

B15 a b c d ___

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 *****)

Section C - Plant and Rad Monitoring Systems 4 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.

C01 a b c d ___

C02 a b c d ___

C03 a b c d ___

C04 a b c d ___

C05 a b c d ___

C06 a b c d ___

C07 a b c d ___

C08 a ___ b ___ c ___ d ___ (0.25 each)

C09 a ___ b ___ c ___ d ___ (0.25 each)

e ___ f ___ g ___ h ___

C10 a b c d ___

C11 a b c d ___

C12 a b c d ___

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 ___

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

6 EQUATION SHEET

DR - Rem, Ci - curies, E - Mev, R - feet

1 Curie = 3.7 x 10 10 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 10 3 BTU/hr 1 Mw = 3.41 x 10 6 BTU/hr 1 BTU = 778 ft-lbf °F = 9/5 °C + 32 1 gal (H 2 O) 8 lbm °C = 5/9 (°F - 32) c P = 1.0 BTU/hr/lbm/°F c p = 1 cal/sec/gm/°C

()()2 2 max=P 1 sec 1.0=eff=t e P P 0 eff K S S SCR=1sec 10 1 4*x=+=eff SUR 06.26 ()()2 1 1 1 2 1 eff eff K CR K CR=()()2 2 1 1=CR CR 2 1 1 1 eff eff K K M=1 2 1 1 CR CR K M eff==)(0 10 t SUR P P=()0 1 P P=eff eff K K SDM=1=*+=eff* 2 1 1 2 eff eff eff eff K K K K=693.0 2 1=T eff eff K K 1=t e DR DR=0 ()2 6 R n E Ci DR=2 2 2 2 1 1 d DR d DR=()()1 2 1 2 2 2 Peak Peak=T UA H m T c m Q P===

WASHINGTON STATE UNIVERSITY TRIGA REACTOR Operator Licensing Examination

Week of June 02, 2014

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 1 QUESTION A.1 [1.0 point]

Which ONE of the following is the MOST affected factor in the six factor formula when changing the control rod material from boron carbide to cadmium?

a. Fast fission factor

b. Reproduction factor

c. Thermal utilization factor

d. Resonance escape probability

QUESTION A.2 [1.0 point] Reactor is increasing power from 100 W to 10 kW in steady state mode. Which ONE of the following best describes the values of K eff and during the power increment?

a. K eff = 1 and = 0 b. K eff = 1 and = 1 c. K eff > 1 and 0 < < -eff d. K eff > 1 and -eff < < 1 QUESTION A.3 [1.0 point]

Reactor A with a K eff of 0.1 and reactor B with a K eff of 0.8, K eff is increased by 0.1 for each reactor. The amount of reactivity added in reactor A is ______ in reactor B for the same increment.

a. less than

b. same

c. eight times

d. thirty-six times

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 2 QUESTION A.4 [1.0 point] During a reactor startup, criticality occurred at a LOWER ROD HEIGHT than the last startup. Which ONE of the following reasons could be the cause?

a. Xe burn-up

b. Fuel temperature increased

c. Moderator temperature increased

d. Adding an experiment with negative reactivity

QUESTION A.5 [1.0 point] Few minutes following a reactor scram, the reactor period has stabilized and the power level is decreasing at a CONSTANT rate. Given that reactor power at time tconstant is 10 kW power, what will it be five minutes later?

a. 0.2 kW

b. 4.7 kW

c. 7.5 kW

d. 85 kW

QUESTION A.6 [1.0 point]

The RESONANCE ESCAPE PROBABILITY is defined as a ratio of:

a. A number of thermal neutrons absorbed in fuel over a number of thermal neutrons absorbed in fuel and core materials

b. A number of fast neutrons produced by fission in a generation over a number of total neutrons produced by fission in the previous generation

c. A number of fast neutrons produced by U-238 over a number of thermal neutrons absorbed in fuel

d. A number of neutrons reaching thermal energy over a number of fast neutrons starting to slow down

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 3 QUESTION A.7 [1.0 point] The following data was obtained during a reactor fuel load. Step No. of Elements Detector A (count/sec) 1 0 100 2 4 120 3 8 140 4 12 200 5 15 400

The estimated number of additional elements required to achieve criticality is between:

a. 2 to 3 b. 4 to 5

c. 6 to 8 d. 9 to 11

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 4 QUESTION A.8 [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. 9 seconds

b. 69 seconds

c. 100 seconds

d. 180 seconds QUESTION A.9 [1.0 point]

Which ONE of the following is a number of neutrons in the tritium nucleus (1 T 3 or 1 H 3 )? a. 1

b.

b. 2

c. 3

d. 4

QUESTION A.10 [1.0 point] List from high to low by thermal neutron cross section of the following isotopes:

1. B-10 2. Sm-149 3. Xe-135 4. U-235

a. 3,2,1,4

b. 2,3,4,1

c. 1,3,4,2

d. 3,1,2,4

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 5 QUESTION A.11 [1.0 point]

The delayed neutron fraction, , is defined as a ratio of:

a. Thermal utilization over fast fission factor

b. The number of thermal neutrons over the number of fast neutrons in the core

c. The number of delayed neutrons over the number of total neutrons in the core

d. The number of thermal neutrons absorbed in fuel over the number of thermal neutrons absorbed in core materials including in fuel

QUESTION A.12 [1.0 point] It takes approximately 92 seconds for reactor power to increase by a factor of 10. The reactor period is:

a. 34 seconds

b. 40 seconds

c. 122 seconds

d. 140 seconds

QUESTION A.13 [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 radiation limit by using thermal neutrons

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

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 6 QUESTION A.14 [1.0 point] A reactor is subcritical with K eff of 0.955. Which ONE of the following is the MINIMUM reactivity (K/K) that must be added to produce PROMPT criticality? Given eff=0.007 a. 0.0052

b. 0.0070

c. 0.0540

d. 0.9620

QUESTION A.15 [1.0 point] The reactor has a K eff of 0.950 with an instrument reading of 60 counts per second (cps). You add an experiment which causes the reading to double. Which ONE of the following is the new

K eff?

a. 0.925 b. 0.955

c. 0.975

d. 0.985 QUESTION A.16 [1.0 point] Which ONE of the following nuclides will cause a fast neutron to lose its most energy per collision?

a. H 1

b. B 10 c. C 12 d. U 238

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 7 QUESTION A.17 [1.0 point] Which ONE of the following best describes the effects of moderator temperature decrease on neutron multiplication?

a. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth b. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth

c. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth d. Fast non-leakage probability ; Thermal non-leakage probability ; Rod worth

QUESTION A.18 [1.0 point] Reactor is at 100 % power. The following graph shows the reactor time behavior following a reactor scram. Which ONE of the following best describes the transition of power between point A and B after the initial insertion? .

a. An immediate decrease in the prompt neutron fraction due to leakage, absorption, and a reduction in the fission rate

b. Fission product gases such as xenon begin to buildup causing the expansion of fuel density

c. The longest lived delayed neutron precursor begins to effect

d. The short lived delayed neutron precursors begin to effect

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 8

Section A - Reactor Theory, Thermohydraulics & Fac. Operating Characteristics Page 9 QUESTION A.19 [1.0 point] You are the reactor operator performing two pulsing operations. The first pulse has a reactivity worth of $1.20 which results in a peak power of 200 MW. If the second pulse has a peak power of 5000 MW, the corresponding reactivity worth is:

Given: =0.0070

a. $1.50

b. $1.75 c. $2.00

d. $4.00 QUESTION A.20 [1.0 point]

The effective target area in cm 2 presented by a single nucleus to an incident neutron beam is defined as:

a. a macroscopic cross section

b. a microscopic cross section

c. a mean free path

d. a neutron flux

- - - - End of Section A *****************

Section B - Normal/Emergency Procedures and Radiological Controls Page 10 QUESTION B.1 [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. A secured experiment 1. $0.50

b. A movable experiment 2. $1.00

c. The sum of the absolute values of 3. $2.00 all individual experiments

d. Maximum excess reactivity 4. $5.00

5. $6.56

6. $7.46

QUESTION B.2 [1.0 point] What is the MINIMUM staffing requirement to be present at the facility for fuel accountability?

a. Senior Reactor Operator ONLY

b. Reactor Facility Director ONLY

c. Senior Reactor Operator and non-licensed staff member

d. Senior Reactor Operator and Reactor Operator

QUESTION B.3 [1.0 point] An unshielded source has a dose rate of 1 Rem/hr. What is the actual dose rate if shielded by 1/2 inch lead?

Given:

Lead density: 11.35 g/cm 3 Lead Mass Attenuation Coefficient: 0.0708 cm 2/g 1 in = 2.54 cm

a. 181 mrem/hr

b. 362 mrem/hr

c. 742 mrem/hr

d. 914 mrem/hr

Section B - Normal/Emergency Procedures and Radiological Controls Page 11 QUESTION B.4 [1.0 point] Which ONE of the following conditions is NOT a violation of a Limiting Condition for Operation?

a. Reactor operator conducted a pulse. The peak temperature reached 850 °C

b. The reactor pumps failed. The primary coolant temperature reached 55 °C

c. The shutdown margin was found to be $0.20 in the reference core condition

d. The pH of the primary coolant indicated 7.0

QUESTION B.5 [1.0 point]

Per 10 CFR 20, a radiation worker can receive an annual limit of ________ to the skin of whole body.

a. the shallow-dose equivalent of 50 Rems

b. the deep-dose equivalent of 5 Rems

c. the committed-dose equivalent of 5 Rems

d. the sum of deep-dose equivalent and the committed-dose equivalent of 50 Rems

QUESTION B.6 [1.0 point]

A radioactive source reads 10 Rem/hr on contact. Five hours later, the same source reads 5.0 Rem/hr. How long is the time for the source to decay from a reading of 10 Rem/hr to 50 mRem/hr?

a. 9.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months

b. 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months

c. 38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months

d. 47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months

Section B - Normal/Emergency Procedures and Radiological Controls Page 12 QUESTION B.7 [1.0 point] Per WSU Emergency Classification, failure of an in-core experiment with a minor release of radioactive material is an example of:

a. normal operation

b. Safety Event - (non-reactor related)

c. Unusual Event - (reactor related)

d. Alert

QUESTION B.8 [1.0 point] Consider two point sources, each having the SAME curie strength. Source A's gammas have an energy of 1.0 MeV, while Source B's gammas have an energy of 4.0 MeV. If using a Geiger-Müller detector, the reading from source B will be: (Ignore detector efficiency)

a. four times that of source A

b. twice that of source A

c. the same

d. quarter that of source A

QUESTION B.9 [2.0 points, 0.5 each]

For Research and Test reactors we primarily worry about two isotopes N 16 and Ar 41. Identify the approximate half-life and gamma energy for each. (Each item has only one answer.)

Isotope Radiological Parameters

a. Ar 41 half-life 1) 1.8 sec 2) 1.8 min 3) 1.8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4) 1.8 day

b. Ar 41 gamma energy 1) 10 KeV 2) 100 KeV 3) 1 MeV 4) 10 MeV

c. N 16 half-life 1) 7 sec 2) 7 min 3) 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 4) 7 day

d. N 16 gamma energy 1) 6 kev 2) 60 keV 3) 600 keV 4) 6 Mev

Section B - Normal/Emergency Procedures and Radiological Controls Page 13 QUESTION B.10 [1 point, 0.25 point each] Match the items listed in Column A with the proper definition in Column B. Each item can be used only once.

Column A Column B

a. Emergency Plan 1. Area for which offsite emergency planning is performed.

b. Emergency Planning Zone 2. Instructions that detail the implementation actions and methods required to achieve the objectives of the emergency plan.

c. Emergency Classes 3. Provides the basis for actions to cope with an emergency.

d. Emergency Procedure 4. Grouped by severity level for which predetermined emergency measures should be taken or considered.

QUESTION B.11 [1.0 point]

You run an experiment with reactor at full power. Half-way through a 6-hour operation, you discover that ALL ventilation fans have been turned OFF with dampers OPENED. Which ONE of the following actions should you take?

a. Immediately secure reactor operations. This event is a Technical Specification (TS) violation.

b. Immediately secure reactor. This event is NOT a TS violation because the dampers are still in opening.

c. Continue with reactor operations. Up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is allowed to run reactor before repairing the fans.

d. Continue with reactor operations. The WSU Technical Specifications requires the fan turn OFF during full power.

Section B - Normal/Emergency Procedures and Radiological Controls Page 14 QUESTION B.12 [1.0 point]

A system or component is defined as "OPERABLE" by Technical Specifications when:

a. a system was calibrated recently

b. it is capable of performing its intended function

c. a system turns from OFF to ON when reactor is in operation

d. a qualitative verification of acceptable performance by observation of channel behavior

QUESTION B.13 [1.0 point] Which ONE of the following requires the NRC APPROVAL for changes?

a. Revise the requalification operator licensing examination

b Revise the SOP#1, Standard Procedure for Use of the Reactor c Major changes in the Administrative Procedure #7, Special Nuclear Material Search

d Delete the definition of BNC Facility listed in the TS Definitions because the BNC Facility has not been utilized for 10 years QUESTION B.14 [1.0 point] The figure attached is a basic design of :

a. Thermoluminescent Dosimeter (TLD)

b. Film badge

c. Pocket ionization chamber

d. Scintillation detector

Section B - Normal/Emergency Procedures and Radiological Controls Page 15 QUESTION B.15 [1.0 point] Attached is the gas-filled detector curve (detector effect vs. voltage). Different regions of this curve are useful for different detectors. Which ONE of the following is the Geiger Mueller region?

a. II

b. III

c. IV

d. V

Section B - Normal/Emergency Procedures and Radiological Controls Page 16 QUESTION B.16 [1.0 point] Which ONE of the following modifications would be considered a "50.59" in which the WSU must file a request to NRC for change? The facility plans to :

a. Replace an identical NLW-1000

b. Measure a xenon poisoning characteristics with new method

c. Replace a fission chamber with an un-compensated ion chamber in the Wide Rang Log Channel

d. Perform a reactor power calibration with the new resistance temperature detector (RTD) probe QUESTION B.17 [1.0 point] The discharge of Ar-41 shall be calculated:

a. Biennially

b. Annually

c. Semiannually

d. Quarterly

QUESTION B.18 [1.0 point] You conduct a facility tour for the WSU Dean. The reactor is operating at a certain power level where radiation levels at the pool reads 20 mrem/hr by the area monitoring equipment. How long can the Dean stay before he exceeds his 10 CFR 20 limit?

a. 20 hrs

b. 10 hrs

c. 5 hrs

d. 2 hr

Section B - Normal/Emergency Procedures and Radiological Controls Page 17 QUESTION B.19 [1.0 point]

"Sealed sources shall NOT be stored or used closer than five feet from an operating reactor core." This is an example of

a. a Special Nuclear Material storage requirement

b. a Surveillance Requirement (SR)

c. a Limiting Safety System Setting (LSSS)

d. a Limiting Conditions for Operation (LCO)

QUESTION B.20 [1.0 point, 0.25 each] Each fuel experiment shall be limited such that the total radioactivity inventory of iodine isotopes 131 through 135 is less than ______?

a. 150 millicuries

b. 300 millicuries

c. 1500 millicuries

d. 3000 millicuries

- - - - End of Section B ********************************

Section C: Plant and Rad Monitoring Systems Page 18 QUESTION C.1 [1.0 point] The Beam Port Plugs alarm signal will trigger:

a. a RED light on its panel ONLY

b. a YELLOW light on Console Alarm Board ONLY

c. a RED light on its panel and a YELLOW light on Console Alarm Board

d. a RED light on its panel, a YELLOW light on Console Alarm Board, and Annunciator sounding QUESTION C.2 [1.0 point] Reactor is at 100 kW. You receive an Exhaust Gas Monitor (EGM) alarm. Per SOP #18, you should:

a. Immediately secure reactor and notify the Health Physicist on duty

b. Continue with reactor operations and deactivate the EGM alarm

c. Immediately secure reactor and notify the Senior Reactor Operator on duty

d. Continue reactor operations after isolation of the ventilation and also notify the Senior Reactor Operator on duty

QUESTION C.3 [1.0 point]

A MAIN purpose of the interlock to prevent withdrawal of more than one control rod at a time is to prevent:

a. inadvertently large reactivity insertion

b. damage of control rod drive system

c. initiation of a pulse while on a positive period

d. initiation of a pulse during a reactor startup

Section C: Plant and Rad Monitoring Systems Page 19 QUESTION C.4 [1.0 point] One of the blade connecting rods needs to be replaced. Per SOP #8, before removing the control rod, the Senior Reactor Operators need to:

a. calculate the Maximum reactivity in excess of cold, Xenon-free critical shall not exceed $8.0

b. move enough fuel elements to ensure that the shutdown margin shall be $0.25

c. move the neutron source near the center core

d. move all fuel elements from the reactor core

QUESTION C.5 [1.0 point] Per SOP #14, the high temperature SCRAM setpoint is between:

a. 420 °C - 435 °C

b. 436 °C - 460 °C

c. 461 °C - 475 °C

d. 476 °C - 500 °C

Section C: Plant and Rad Monitoring Systems Page 20 QUESTION C.6 [1.0 point] Attached is the WSU reactor core 35-A. Which ONE of the following is a position of the Log-N Fission Chamber?

a. 1

b. 2 c. 3

d. 4

Section C: Plant and Rad Monitoring Systems Page 21 QUESTION C.7 [1.0 point] The source interlock system will prevent rod withdrawal unless source level is above a preset level. This source interlock signal comes from:

a. Log-N Power Channel

b. Linear Channel

c. Fuel Temperature Channel

d. Percent Power Channel (Safety Chanel #2)

QUESTION C.8 [1.0 point, 0.25 each] Reactor is in operation. Match the input signals listed in column A with their AUTOMATICALLY responses listed in column B. (Items in column B may be used more than once or not at all.)

Column A Column B

a. Loss of C.I.C High Voltages 1. Alarm ONLY

b. Low pool level = 8 in. 2. Rod run in

c. Linear High Flux = 110% 3. Interlock

d. Perform pulse at 2 kW 4. Scram

Section C: Plant and Rad Monitoring Systems Page 22 QUESTION C.9 [2.0 points, 0.25 each] The WSU ventilation system is in the DILUTE mode. Provide a correct status for FANS (ON/OFF) and AUTO-DAMPER (OPEN/CLOSED). See Table below

a. F1

b. F3 c. F4

d. D1

e. D2 f. D3

g. D4

h. D5 QUESTION C.10 [1.0 point] The MAIN purpose of small flow holes drilled at the bottom of the shroud is to:

a. reduce the effects of viscous damping on the blade fall time

b. increase of the blade speed during withdrawal

c. allow water to cool the blade during shutdown

d. prevent corrosion on the control blade

Section C: Plant and Rad Monitoring Systems Page 23 QUESTION C.11 [1.0 point] The reactor is at 200 kW when the high voltage of inner chamber (chamber without B-10 coating) of Linear Power Channel is lost. What effect would this have on reactor power?

a. power will slightly increase

b. power will slightly decrease

c. Rod will remain the same level

d. Reactor will scram due to a high voltage loss of C.I.C

QUESTION C.12 [1.0 point] After the performance of Thermal Power Calibration, the NPP-1000 Power Channel indicates only 97 % of actual power. To complete the calibration, you should:

a. raise its detector position to increase channel indication

b. lower its detector position to increase channel indication

c. increase the H.V. of the NPP 1000 to increase channel indication

d. No adjustment of detector is required because the actual power and indicated power are within 3% of each other

QUESTION C.13 [1.0 point]

Which ONE of the following is your proper action when you receive an experiment request for conducting an experiment with a reactivity worth of $1.50 in the Thermal Column? You shall:

a. Secure the experiment to prevent movement during reactor operations

b. Perform this experiment with a reactor power not exceeding 100 kW

c. Perform under the direct supervision of the Reactor Director

d. Not conduct this experiment because it violates the TS limit

Section C: Plant and Rad Monitoring Systems Page 24 QUESTION C.14 [1.0 point]

During the startup, you test a pulsing operation to collect the reading on the peak power and 1-kW pulse interlock. The peak power information comes from the _______ and the 1-kW pulse interlock information comes from the _________.

a. NPP 1000 channel, NMP 1000 channel

b. NLW 1000 channel, NPP 1000 channel

c. NPP 1000 channel, NLW 1000 channel

d. NLW 1000 channel; NMP 1000 channel

QUESTION C.15 [1.0 point] Ion exchange resin shall be replaced when:

a. Ion exchanger OUTLET conductivity exceeds 0.5 micomho/cm

b. Ion exchanger INTLET conductivity exceeds 0.5 micomho/cm

c. pH of the SECONDARY coolant exceeds 7.0

d. pH of the PRIMARY coolant exceeds 7.0

QUESTION C.16 [1.0 point] The Transient Control Rod is located at:

a. D5NE

b. D5NW

c. C7NE

d. C7NW

Section C: Plant and Rad Monitoring Systems Page 25 QUESTION C.17 [1.0 point] Which ONE of the following systems will be received a backup power from the Auxiliary Reactor Emergency Supply (ARIES) in event of a power loss?

a. Primary pumps

b. Seismograph alarm

c. Digital telephone system

d. Reactor control room light

QUESTION C.18 [1.0 point] Which ONE of the following statements describes the operation of the solenoid valve of the Transient rod air system? The Transient rod air system is consisted of

a. Three ways solenoid. When the solenoid valve is energized , the vent (exhaust) port is closed, the supply port is opened and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

b. Two ways solenoid. When the solenoid valve energized, the supply port opened and the actual port to the cylinder opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

c. Three ways solenoid. When the solenoid valve is de-energized , the vent (exhaust) port is closed, the supply port is closed and the actual port (to the cylinder) is opened. Air from the accumulator is continuously supplied to the pneumatic cylinder of the Transient rod.

d. Two ways solenoid. When the solenoid valve de-energized; the actual port (to the cylinder) is closed. Air flows from pneumatic cylinder back to the accumulator.

Section C: Plant and Rad Monitoring Systems Page 26 QUESTION C.19 [1.0 point] The fuel temperature as measured by the Instrumented Fuel Rod shall not be more than 10 ° C above the pool temperature during the fuel movement. The main reason of this requirement is:

a. to maintain the integrity of the fuel element cladding

b. to ensure a lateral bending and an elongation of a fuel element are correctly measured

c. to ensure the fuel temperature increase will not cause any damage to the fuel measurement tool

d. to ensure the reactivity measurement to be made at low power without having to correct for negative temperature coefficient contributions

- - - - End of Section C **************************** ******************* End of the Exam ***************************

Section A - Theory, Thermo & Facility Operating Characteristics Page 27 A.1 Answer c

Reference:

18.

A.2 Answer: c

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, © 1982, Sec 3.3.3, page 3-21. reactor A = (Keff 1-Keff 2)/(Keff 1*Keff 2). (0.2-0.1)/(0.2*0.1) = 5 k/k reactor B = (Keff 1-Keff 2)/(Keff 1*Keff 2). (0.9-0.8)/(0.9*0.8) = 0.139 k/k 5/0.139 = 36

A.4 Answer: a

Reference:

A.5 Answer: a

Reference:

P = P 0 e-t/T = 10 kW e(300sec/-80sec)

= 10 kW e-3.75 = 0.0235 10 kW = 0.24 kW A.6 Answer: d

Reference:

16.

A.7 Answer: a

Reference:

A.8 Answer: b

Reference:

Period T = l*/ = k-1/k = 0.001 T = 0.1 /0.001 = 100

N = N o et/T 2 = et/100 0.693 = t/100 t = 69.3 seconds

Section A - Theory, Thermo & Facility Operating Characteristics Page 28 A.9 Answer: b

Reference:

Nuclides and Isotopes N = A - Z 3-1 = 2 A.10 Answer: a

Reference:

P = P 0 e-t/ . Find , = - t/ln(0.10) = -92/-2.30 = 40 sec.

A.13 Answer: d

Reference:

from k=0.955 to criticality (k=1), = (k-1)/k = -0.047 k/k or = 0.047 k/k needed to reach criticality. From criticality to JUST prompt, k/k = eff required, so minimum reactivity added to produce prompt criticality will be: 0.047+0.007= 0.054

A.15 Answer: c

Reference:

CR 2/CR 1 = (1 - K eff1)/(1 - K eff2) 120/60 = (1 - 0.950)/(1 - K eff2) K eff2 = 0.975

A.16 Answer: a

Reference:

Section A - Theory, Thermo & Facility Operating Characteristics Page 29 A.18 Answer: d

Reference:

Burn, R., Introduction to Nuclear Reactor Operations, ©4.5, 1988 "a" cannot be a correct answer, it describes a prompt drop.

A.19 Answer: c =($)*; 1=$1.20*0.007= 0.0084 k/k (Peak1 /Peak2)*(0.0084-.007) 2 = (1- ) 2 0.000049=(1- ) 2 ;0.007= 1- or 1=0.007+0.007= 0.014 k/k or $2.0 Or Peak2 ($1-$1) 2 = Peak1*( $2-$1 /)2 ($1-$1.0) 2 = (5000/200)*( $1.20-$1.0) 2 $1-$1.0 = $1.0, $1 = $2.0 A.20 Answer: b

Reference:

Peak)-( = Peak)-(1 1 2 2 2 2 Section B - Normal, Emergency and Radiological Control Procedures Page 30 B.1 Answer: a(3) b(2) c(4) d(6)

Reference:

TS 3.1 and 3.6 B.2 Answer: c d change made per facility comment

Reference:

Administrative Procedure # 9, Section E B.3 Answer: b

Reference:

and Solving for µ=

x B.4 Answer: d

Reference:

TS 3.1, 3.2 and 3.3

B.5 Answer: a

Reference:

10 CFR 20 (the committed-dose equivalent and the deep-dose equivalent used for individual organ)

B.6 Answer: c

Reference:

DR = DR*e -t 5 rem/hr =10 rem/hr* e

-(5hr) Ln(5.0/10) = -*5 --> =0.1386; solve for t: Ln(.05/10)=-0.315 (t) t=38 hours B.7 Answer: c

Reference:

Emergency Plan, 4.3

B.8 Answer: c

Reference:

Standard NRC Health Physics Question. G-M detector is not sensitive to incident energy levels

B.9 Answer: a(3); b(3) c(1); d(4)

Reference:

SAR 11.3 B.10 Answer: a, 3 b,1 c,4 d,2

Reference:

Emergency Plan 2.0

Section B - Normal, Emergency and Radiological Control Procedures Page 31 B.11 Answer: a

Reference:

TS 3.4 B.12 Answer: b

Reference:

TS, Section 1 B.13 Answer: d

Reference:

TS 6.2.1 and 10 CFR 50.59 B.14 Answer: d

Reference:

Basic knowledge of radiation detector (Reed Training Manual, Scintillation Detectors).

B.15 Answer: d

Reference:

Reed Training Manual, 5.1

B.16 Answer: c

Reference:

Administrative Procedure # 3 and 10 CFR 50.59

B.17 Answer: b

Reference:

TS 4.1.3 B.18 Answer: c

References:

100 mrem dose limit to members of the public (10 CFR 20)

B.19 Answer: d

Reference:

TS 3.7

B.20 Answer: c

Reference:

TS 3.6

Section C - Facility and Radiation Monitoring Systems Page 32 C.1 Answer: a

Reference:

SOP #18, Section C C.2 Answer: d

Reference:

SOP #18, Section C C.3 Answer: a

Reference:

TS 3.2

C.4 Answer: d

Reference:

TS 3.13 and SOP # 8

C.5 Answer: c

Reference:

SOP#14 C.6 Answer: b

Reference:

SAR, Figure 4-10 C.7 Answer: a

Reference:

SAR 7.3 C.8 Answer: a(4) b(1) c(1) d(3)

Reference:

TS 3.2 and WSUNRC Form No.34

Section C - Facility and Radiation Monitoring Systems Page 33 C.9 Answer: a(OFF) b(ON) c(OFF) d(CLOSED) e(OPEN) f(OPEN) g(CLOSED) h(OPEN)

Reference:

SAR 9.1, Table 9-1 C.10 Answer: a

Reference:

SAR 4.2.2 C.11 Answer: a

Reference:

Reed Training Manual, Chapter 5. The CIC will act just like UCIC when losing the inner HV. Power will slightly increase due to additional gamma

C.12 Answer: b

Reference:

SOP #13, Section D C.13 Answer: a

Reference:

SOP #1 C.14 Answer: c

Reference:

SOP #4, Section D C.15 Answer: a

Reference:

SOP #24, Section B C.16 Answer: b

Reference:

SAR Chapter 4, Figure 4-6

Section C - Facility and Radiation Monitoring Systems Page 34 C.17 Answer: b

Reference:

SAR Chapter 8.2 C.18 Answer: a

Reference:

SAR 4.2.2 and Figure 4-16 C.19 Answer: d

Reference:

SOP #7, Sec B.9

ML14163A034

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SUBJECT:

Dear Dr. Wall:

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