ML050550257

Retake Examination Report No. 50-288/OL-05-01, Reed College, February 7, 2005

ML050550257
Person / Time
Site:	Reed College
Issue date:	03/01/2005
From:	Madden P NRC/NRR/DRIP/RNRP
To:	Frantz S Reed College
Doyle P, NRC/NRR/DRIP/RNRP, 415-1058
Shared Package
ML050100331	List: ML050070265 ML050550257 ML050550291
References
50-288/OL-05-01 50-288/OL-05-01
Download: ML050550257 (16)

Text

March 1, 2005 Mr. Steven G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-288/OL-05-01, REED COLLEGE

Dear Mr. Frantz:

During the week of February 7, 2005, you administered an operator licensing examination at your Reed College Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.390 of the Commission's regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Paul V. Doyle, Jr. at 301-415-1058 or via internet E-mail at pvd@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Initial Examination Report No. 50-288/OL-05-01

2. Examination and answer key cc w/encls: Please see next page

March 1, 2005 Mr. Steven G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

RETAKE EXAMINATION REPORT NO. 50-288/OL-05-01, REED COLLEGE

Dear Mr. Frantz:

During the week of February 7, 2005, you administered an operator licensing examination at your Reed College Reactor. The examination was conducted according to NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.390 of the Commission's regulations, a copy of this letter and the enclosures will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/NRC/ADAMS/indesx.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 Paul V. Doyle, Jr. at 301-415-1058 or via internet E-mail at pvd@nrc.gov.

Sincerely,

/RA/

Patrick M. Madden, Section Chief Research and Test Reactors Section New, Research and Test Reactors Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No. 50-288

Enclosures:

1. Initial Examination Report No. 50-288/OL-05-01

2. Examination and answer key cc w/encls: Please see next page DISTRIBUTION:

PUBLIC RNRP/R&TR r/f PMadden Facility File (EBarnhill) O-6 F-2 DHughes EXAMINATION PACKAGE ACCESSION NO.: ML050100331 EXAMINATION REPORT ACCESSION #: ML050550257 TEMPLATE #: NRR-074 OFFICE RNRP:CE IROB:LA E RNRP:SC NAME PDoyle EBarnhill PMadden DATE 2/ 25 /2005 2/ 28 /2005 2/ 28 /2005 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

Reed College Docket No. 50-288 cc:

Mayor of the City of Portland 1220 Southwest 5th Avenue Portland, OR 97204 Reed College ATTN: Dr. Peter Steinberger Dean of Faculty 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 Reed College ATTN: Dr. Colin Diver, President 3203 S.E. Woodstock Boulevard Portland, OR 97202-8199 Oregon Department of Energy ATTN: David Stewart-Smith, Director Division of Radiation Control 625 Marion Street, N.E.

Salem, OR 97310 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.: 50-288/OL-05-01 FACILITY DOCKET NO.: 50-288 FACILITY LICENSE NO.: R-112 FACILITY: Reed College EXAMINATION DATES: February 11, 2005 SUBMITTED BY: ________/RA/___________________ 2/28/05 Paul V. Doyle Jr., Chief Examiner Date

SUMMARY

The NRC mailed a Section A only operator licensing written examination to the facility for administration to a Reactor Operator candidate who had failed section a of the examination administered May, 2004. The facility administered the examination on February 11, 2005. The candidate passed the examination.

REPORT DETAILS

1. Examiners:

Paul V. Doyle Jr., Chief Examiner

2. Results:

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

3. Exit Meeting:

There was no exit meeting. The facility mailed the written examination to the NRC where it was graded. The facility had no comments on the examination.

ENCLOSURE 1

U.S. Nuclear Regulatory Commission OPERATOR LICENSING EXAMINATION With Answer Key REED REACTOR FACILITY Week of February 7, 2005 ENCLOSURE 2

L Theory, Thermodynamics and Facility Operating Characteristics Page 2 QUESTION A.01 [2.0 points, 1/2 each]

The listed isotopes are all potential daughter products due to the radioactive decay of 35Br87. Identify the type of decay necessary (Alpha, Beta, Gamma or Neutron emission) to produce each of the isotopes.

a. 33 As83

b. 35 Br86

c. 35 Br87

d. 36 Kr87 QUESTION A.02 [1.0 point]

What is the definition of reactivity? A measure of the

a. number of neutrons being produced in the core.

b. number of neutrons being absorbed by the fuel.

c. reactors multiplication factor.

d. reactors departure from critical.

QUESTION A.03 [2.0 points, 1/2 each]

Using the drawing of the Integral Rod Worth Curve provided, identify each of the following reactivity worths.

a. Total Rod Worth 1. B - A

b. Actual Shutdown Margin 2. C - A

c. Technical Specification Shutdown Margin Limit 3. C - B

d. Excess Reactivity 4. D - C

5. E - C

6. E - D

7. E - A

L Theory, Thermodynamics and Facility Operating Characteristics Page 3 QUESTION A.04 [1.0 point]

Shown below is a trace of reactor period as a function of time. Between points A and B reactor power is:

a. continually increasing.

b. continually decreasing.

c. increasing, then decreasing.

d. constant.

QUESTION A.05 [1.0 point]

What is the kinetic energy range of a thermal neutron?

a. > 1 MeV

b. 100 KeV - 1 MeV

c. 1 eV - 100 KeV

d. < 1 eV QUESTION A.06 [1.0 point]

Which ONE of the following is the difference between prompt and delayed neutrons? Prompt neutrons

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

b. are released during fast-fission events, while delayed neutrons are released during the decay process.

c. are released during the fission process (fast & thermal), while delayed neutrons are release during the decay process.

d. are the dominating factor in determining reactor period, while delayed neutrons have little effect on reactor period.

QUESTION A.07 [1.0 point]

Suppose the temperature coefficient of a core is -2.5 x 10-4 K/K/EC and the average control rod worth of the regulating control rod is 5.895 x 10-3 K/K/inch. If the temperature INCREASES by 50EC what will the automatic control command the regulating rod to do? Select the answer that is closest to the calculated value.

a. 5.6 inches in

b. 2.1 inches out

c. 0.5 inches in

d. 4.3 inches out

L Theory, Thermodynamics and Facility Operating Characteristics Page 4 QUESTION A.08 [1.0 point]

Given the following data, which ONE of the following is the closest to the half life of the material?

TIME ACTIVITY 0 2400 cps 10 min. 1757 cps 20 min. 1286 cps 30 min. 941 cps 60 min. 369 cps

a. 11 minutes

b. 22 minutes

c. 44 minutes

d. 51 minutes QUESTION A.09 [1.0 point]

During a fuel loading of the core, as the reactor approaches criticality, the value of 1/M:

a. Increases toward one

b. Decreases toward one

c. Increases toward infinity

d. Decreases toward zero QUESTION A.10 [1.0 point]

Which ONE of the following is the major source of energy released during fission?

a. Prompt gamma ray absorption

b. Slowing down of fission fragments

c. Neutrino interactions

d. fission neutron scattering reactions QUESTION A.11 [1.0 point]

Which one of the following is the definition of the FAST FISSION FACTOR?

a. The ratio of the number of neutrons produced by fast fission to the number produced by thermal fission

b. The ratio of the number of neutrons produced by thermal fission to the number produced by fast fission

c. The ratio of the number of neutrons produced by fast and thermal fission to the number produced by thermal fission

d. The ratio of the number of neutrons produced by fast fission to the number produced by fast and thermal fission

L Theory, Thermodynamics and Facility Operating Characteristics Page 5 QUESTION A.12 [1.0 point]

In a reactor at full power, the thermal neutron flux () is 2.5 x 1012 neutrons/cm2/sec. and the macroscopic fission cross-section Gf is 0.1 cm-1. The fission reaction rate is:

a. 2.5 x 1011 fissions/sec.

b. 2.5 x 1013 fissions/sec.

c. 2.5 x 1011 fissions/cm3/sec.

d. 2.5 x 1013 fissions/cm3/sec.

QUESTION A.13 [1.0 point]

The number of neutrons passing through a one square centimeter of target material per second is the definition of which one of the following?

a. Neutron Population (np)

b. Neutron Impact Potential (nip)

c. Neutron Flux (nv)

d. Neutron Density (nd)

QUESTION A.14 [1.0 point]

Which ONE of the following explains the response of a SUBCRITICAL reactor to equal insertions of positive reactivity as the reactor approaches criticality? Each insertion causes a

a. SMALLER increase in the neutron flux resulting in a LONGER time to stabilize.

b. LARGER increase in the neutron flux resulting in a LONGER time to stabilize.

c. SMALLER increase in the neutron flux resulting in a SHORTER time to stabilize.

d. LARGER increase in the neutron flux resulting in a SHORTER time to stabilize.

QUESTION A.15 [1.0 point]

Which ONE of the following atoms will cause a neutron to lose the most energy in an elastic collision?

a. Uranium238

b. Carbon12

c. Hydrogen2

d. Hydrogen1

L Theory, Thermodynamics and Facility Operating Characteristics Page 6 QUESTION A.16 [1.0 point]

A thin foil target of 10% copper and 90% aluminum is in a thermal neutron beam. Given a Cu = 3.79 barns, a Al = 0.23 barns, s Cu = 7.90 barns, and s Al =1.49 barns, which ONE of the following reactions has the highest probability of occurring? A neutron

a. scattering reaction with aluminum

b. scattering reaction with copper

c. absorption in aluminum

d. absorption in copper QUESTION A.17 [1.0 point]

When performing rod calibrations, many facilities pull the rod out a given increment, then measure the time for reactor power to double (doubling time), then calculate the reactor period. If the doubling time is 42 seconds, what is the reactor period?

a. 29 sec

b. 42 sec

c. 61 sec

d. 84 sec QUESTION A.18 [1.0 point]

Which ONE of the following statements concerning reactor poisons is NOT true?

a. Following shutdown, Samarium concentration will increase to some value then stabilize.

b. Following shutdown, Xenon concentration will initially increase to some value then decrease exponentially

c. During reactor operation, Samarium concentration is independent of reactor power level.

d. During reactor operation, Xenon concentration is dependent on reactor power level.

L Theory, Thermodynamics and Facility Operating Characteristics Page 7 A.01 a, alpha; b, neutron; c, gamma; d, Beta Ref: Training Manual, Reed Reactor Facility § 2.4 A.02 d REF: Training Manual, Reed Reactor Facility § 9.2 A.03 a, 7; b, 5; c, 6; d, 2 REF: Training Manual, Reed Reactor Facility § 10.2 A.04 a REF: Standard NRC question A.05 d REF: Training Manual, Reed Reactor Facility § 7.3 A.06 c REF: Training Manual, Reed Reactor Facility § 10.4 A.07 B REF: Training Manual, Reed Reactor Facility § 10.6 The temperature increase will result in reactivity change of: -2.5 x 10-4 K/K/EC x 50EC = -1.25 x 10-2 K/K. Since the temperature rise is a negative reactivity insertion, the control rod must drive out to add positive reactivity. D = (1.25 x 10-2 K/K) ÷ (5.895 x 10-3 K/K/in.) = 2.12 in.

A.08 b REF: Training Manual, Reed Reactor Facility § 2.6 A.09 d REF: Training Manual, Reed Reactor Facility § 8.4 A.10 b REF: Training Manual, Reed Reactor Facility § 7.1 A.11 c REF: Training Manual, Reed Reactor Facility § 8.2 A.12 c REF: R = Gf = (2.5 x 1012) x 0.1 = 2.5 x 1011 NRC Question Bank A.13 c REF: Training Manual, Reed Reactor Facility § 6.3 A.14 b REF: Training Manual, Reed Reactor Facility § 8.4 A.15 d REF: Training Manual, Reed Reactor Facility § 3.3 A.16 a REF: Training Manual, Reed Reactor Facility § 6.2 A.17 c REF: Training Manual, Reed Reactor Facility § 9.4 ln (2) = -time/ = time/(ln(2)) = 60.59 . 61 seconds A.18 c REF: Training Manual, Reed Reactor Facility § 10.4

U. S. NUCLEAR REGULATORY COMMISSION RESEARCH AND TEST REACTOR OPERATOR LICENSING EXAMINATION FACILITY: Reed College REACTOR TYPE: TRIGA DATE ADMINISTERED: 2005/01/____

CANDIDATE:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the answer sheets provided. Points for each question are indicated in brackets for each question. You must score 70% to pass. Examinations will be picked up one (1) hour after the examination starts.

% of Category % of Candidates Category Value Total Score Value Category 20.00 100.0 A. Reactor Theory, Thermodynamics and Facility Operating Characteristics 20.00  % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.

Candidate's Signature

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

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

2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have neither received nor given assistance in completing the examination. This must be done after you complete the examination.

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

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

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

6. 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 proctor 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.

12. There is a time limit of one (1) hour for completion of the examination.

13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked.

EQUATION SHEET 44444444444444444444444444444444444444444444444444444444444444444 Q'mcp T'mH'UAT Pmax'( &)2 2(k)R R('3x10 &5 secon eff'0.1seconds &1 SCR (Neq)'&S.1&S Kef CR1(1&Keff 1

)'CR 2(1&Keff2

)

CR 1(&1)'CR 2(&2)

SUR '26 .06eff& '26 .0 M'1 &Keff0 M'1&1K 'CR 1 1&K eff CR eff eff 1 2 P'P0 10 SUR(t) t P'(1 &)

P'P0 e

& P0 SDM '(1& Keff) ' R( 'R( % &

Keff &

eff

'K 2&K eff eff1 keff1xKeff2 T1/2'0.693 '(KK &1) eff eff DR 'DR 0e

&t DR '6Ci E(n)

R2 DR 1d1 'DR 2

2d2 2

DR - Rem, Ci - curies, E - Mev, R - feet (2&)2 '(1&)2 Peak 2 Peak 1 44444444444444444444444444444444444444444444444444444444444444444 1 Curie = 3.7 x 1010 dis/sec 1 kg = 2.21 lbm 1 Horsepower = 2.54 x 103 BTU/hr 1 Mw = 3.413 x 106 BTU/hr 1 BTU = 778 ft-lbf EF = 9/5 EC + 32 1 gal (H2O) . 8.272 lbm EC = 5/9 (EF - 32) cP = 0.998 BTU/hr/lbm/EF cp = 0.998 cal/sec/gm/EC T = -3.9 pcm/EF Pool Volume = 15650 gallons

Section A L Theory, Thermo, and Facility Characteristics Page 4 A.1a alpha beta gamma neutron ___ A.7 a b c d ___

A.1b alpha beta gamma neutron ___ A.8 a b c d ___

A.1c alpha beta gamma neutron ___ A.9 a b c d ___

A.1d alpha beta gamma neutron ___ A.10 a b c d ___

A.2 a b c d ___ A.11 a b c d ___

A.3a 1 2 3 4 5 6 7 ___ A.12 a b c d ___

A.3b 1 2 3 4 5 6 7 ___ A.13 a b c d ___

A.3c 1 2 3 4 5 6 7 ___ A.14 a b c d ___

A.3d 1 2 3 4 5 6 7 ___ A.15 a b c d ___

A.4 a b c d ___ A.16 a b c d ___

A.5 a b c d ___ A.17 a b c d ___

A.6 a b c d ___ A.18 a b c d ___

E: Control Blade Top D: Top of Core plus wort C: Top of Core B: Top of Core less worth A: Control Blade Bottom Reactor at Cold, Clean Critical.