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Initial Examination Report No. 50-288/OL-02-03, Reed College
	ML022590196
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Site:	Reed College
Issue date:	09/19/2002
From:	Madden P; NRC/NRR/DRIP/RORP
To:	Frantz S; Reed College
	Isaac P, NRC/NRR/DRIP/RORP, 301-415-1019
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September 19, 2002 Mr. Stephen G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-288/OL-02-03, REED COLLEGE

Dear Mr. Frantz:

During the week of September 2, 2002, the NRC administered examinations to an employee of your facility who had applied for a license to operate your Reed College Reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.790 of the Commissions 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 NRCs 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 Patrick Isaac at 301-415-1019.

Sincerely,

/RA/

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

Enclosures:

1.

Initial Examination Report No. 50-288/OL-02-03

2.

Examination and answer key cc w/enclosures:

Please see next page

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

September 19, 2002 Mr. Stephen G. Frantz, Director Reed Reactor Facility 3203 SE Woodstock Blvd.

Portland, OR 97202

SUBJECT:

INITIAL EXAMINATION REPORT NO. 50-288/OL-02-03, REED COLLEGE

Dear Mr. Frantz:

During the week of September 02, 2002, the NRC administered examinations to an employee of your facility who had applied for a license to operate your Reed College Reactor. The examination was conducted in accordance with NUREG-1478, "Non-Power Reactor Operator Licensing Examiner Standards," Revision 1.

In accordance with 10 CFR 2.790 of the Commissions 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 NRCs 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 Patrick Isaac at 301-415-1019.

Sincerely,

/RA/

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

Enclosures:

1.

Initial Examination Report No. 50-288/OL-02-03

2.

Examination and answer key cc w/enclosures:

Please see next page DISTRIBUTION:

PUBLIC RORP/R&TR r/f Facility File EBarnhill (O6-D17)

ADAMS ACCESSION #: ML022590196 TEMPLATE #: NRR-074 OFFICE RORP:CE IEHB:LA RORP:SC NAME PIsaac:rdr EBarnhill PMadden DATE 09/ 16 /2002 09/ 17 /2002 09/ 18 /2002 C = COVER E = COVER & ENCLOSURE N = NO COPY OFFICIAL RECORD COPY

U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.:

50-288/OL-02-03 FACILITY DOCKET NO.:

50-288 FACILITY LICENSE NO.:

R-112 FACILITY:

Reed College EXAMINATION DATES:

09/03/2002 EXAMINER:

Patrick Isaac, Chief Examiner SUBMITTED BY:

/RA/

09/12/2002 Patrick Isaac, Chief Examiner Date

SUMMARY

During the week of September 02, 2002, NRC administered a retake of Section A of the Operator Licensing written examinations to one Reactor Operator (RO) candidate. The candidate passed the examinations.

ENCLOSURE 1 REPORT DETAILS 1.

Examiners:

Patrick Isaac, Chief Examiner 2.

Results:

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

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

Reed College REACTOR TYPE:

TRIGA DATE ADMINISTERED:

2002/09/03 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% is required to pass the examination. 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 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.

Candidates Signature ENCLOSURE 2

A. RX THEORY, THERMO & FAC OP CHARS 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.

001 a b c d ___

002 a b c d ___

003 a b c d ___

004 a b c d ___

005 a b c d ___

006 a b c d ___

007 a b c d ___

008 a b c d ___

009 a b c d ___

010 a b c d ___

011 a b c d ___

012 a b c d ___

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016 a b c d ___

017 a b c d ___

018 a b c d ___

019 a b c d ___

020 a b c d ___

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

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

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

1.

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

2.

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

3.

Restroom trips are to be 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.

12.

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

EQUATION SHEET

Q = m cp T

Q = m h SCR = S/(1-Keff)

Q = UA T CR1 (1-Keff)1 = CR2 (1-Keff)2 26.06 (

eff )

(1-Keff)0 SUR =

M =

( - )

(1-Keff)1 SUR = 26.06/

M = 1/(1-Keff) = CR1/CR0 P = P0 10SUR(t)

SDM = (1-Keff)/Keff P = P0 e(t/ )

I = Io e-ux (1- )

P = Po

* = 1 x 10-4 seconds

= (*/ ) + [( - )/

eff ]

= */( - )

= (Keff-1)/Keff R = 6 C E n

= Keff/Keff 0.693 T1/2 =

= 0.007 DR1D1 2 = DR2D2 2

DR = DRoe-t Cp (H20) = 0.146 kw P = S / (1 - Keff) gpm F 1 Curie = 3.7x1010 dps 1 kg = 2.21 lbm 1 hp = 2.54x103 BTU/hr 1 Mw = 3.41x106 BTU/hr 1 BTU = 778 ft-lbf

F = 9/5C + 32 931 Mev = 1 amu

C = 5/9 (F - 32)

Section A Theory, Thermo & Fac. Operating Characteristics QUESTION (A.1)

[1.0]

Shortly after a reactor trip, reactor power indicates 0.5% where a stable negative period is attained. Reactor power will be reduced to 0.05% in approximately _______ seconds.

a.

90 b.

180 c.

270 d.

360 QUESTION (A.2)

[1.0]

The following data was obtained during a reactor fuel load.

No. of Elements Detector A (cps) 0 20 8

28 16 30 24 32 32 42 40 80 Which one of the following represents the number of fuel elements predicted to reach criticality?

a.

48

b.

52

c.

56

d.

60 1.0

0.9

0.8

0.7

0.6

0.5

0.4

0.3

0.2

0.1

0.0

4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 NUMBER OF ELEMENTS INSTALLED

Section A Theory, Thermo & Fac. Operating Characteristics QUESTION (A.3)

[1.0]

An initial count rate of 100 is doubled five times during startup. Assuming an initial Keff =

0.950, what is the new Keff?

a.

0.957 b.

0.979 c.

0.988 d.

0.998 QUESTION (A.4)

[1.0]

When a reactor is critical on prompt neutrons alone, it is said to be prompt critical. If Keff equals 1.0, how much reactivity must be added to make the reactor prompt critical? The amount of reactivity added equals:

a.

the fraction.

b.

the amount to make Keff equal to 1.1.

c.

the amount to make the reactor period infinite.

d.

the amount needed to increase the mean neutron lifetime to 0.080 seconds.

QUESTION (A.5)

[1.0]

The reactor is shutdown by 0.05 K/K, this would correspond to Keff of:

a.

0.9995 b.

0.9524 c.

0.7750 d.

0.0500 QUESTION (A.6)

[1.0]

Which one of the following is the effect due to an INCREASE in water temperature?

a.

Neutron spectrum hardens due to less moderation.

b.

Neutron spectrum softens due to increased leakage.

c.

Reactivity increases due to less leakage.

d.

Reactivity decreases due to more moderation.

Section A Theory, Thermo & Fac. Operating Characteristics QUESTION (A.7)

[1.0]

A reactor is subcritical with a shutdown margin of 0.0526 K/K. The addition of a reactor experiment increases the indicated count rate from 10 cps to 20 cps.

Which one of the following is the new Keff of the reactor?

a.

.53 b.

.90 c.

.975 d.

1.02 QUESTION (A.8)

[1.0]

Which one of the following statements describes how fuel temperature affects the core operating characteristics?

a.

Fuel temperature increase will decrease the resonance escape probability.

b.

Fuel temperature decrease results in Doppler Broadening of U238 and Pu240 resonance peaks and the decrease of resonance escape probability.

c.

Decrease in fuel temperature will increase neutron absorption by U238 and Pu240.

d.

Fuel temperature increase results in Doppler Broadening of U238 and PU240 resonance peaks and the decrease of neutron absorption during moderation.

QUESTION (A.9)

[1.0]

Which statement illustrates a characteristic of Subcritical Multiplication?

a.

As Keff approaches unity (1), for the same increase in Keff, a greater increase in neutron population occurs.

b.

The number of neutrons gained per generation gets larger for each succeeding generation.

c.

The number of fission neutrons remain constant for each generation.

d.

The number of source neutrons decreases for each generation.

Section A Theory, Thermo & Fac. Operating Characteristics QUESTION (A.10)

[1.0]

Select the statement that describes why neutron sources are used in reactor cores.

a.

Increase the count rate by an amount equal to the source contribution.

b.

Increase the count rate by 1/M (M = Subcritical Multiplication Factor).

c.

Provide the source neutrons to initiate the chain reaction when first starting-up the reactor.

d.

Provide a neutron level high enough to be monitored by source range instrumentation.

QUESTION (A.11)

[1.0]

With the reactor critical at 50% power, the reactor operator withdraws the regulating rod. As power increases, a stable doubling time (DT) of 24 seconds is recorded. (Assume a of 0.1 sec-1) Which one of the following is the reactivity added to the core by the operator?

a.

0.14% K/K b.

0.16% K/K c.

0.18% K/K d.

0.20% K/K QUESTION (A.12)

[1.0]

The term "Shutdown Margin" describes:

a.

the time required for the rods to fully insert b.

the departure from Keff 1.00 c.

the amount of reactivity by which the reactor is subcritical d.

the amount of reactivity inserted by all the rods except the most reactive rod.

QUESTION (A.13)

[1.0]

Which one of the following factors is the most significant in determining the differential worth of a control rod?

a.

The rod speed.

b.

Reactor power.

c.

The flux shape.

d.

The amount of fuel in the core.

Section A Theory, Thermo & Fac. Operating Characteristics QUESTION (A.14)

[1.0]

Assuming the Samarium worth is 0.006 K/K at full power, which one of the following is the Samarium worth 10 days after shutdown from full power?

a.

Essentially zero.

b.

It increases by a factor of 2.

c.

Less than 0.006 K/K but greater than zero.

d.

Greater than 0.006 K/K QUESTION (A.15)

[1.0]

The reactor is operating at 100 KW. The reactor operator withdraws the Regulating Rod adding $0.15 of reactivity and allowing power to increase. The operator then inserts the same rod to its original position, decreasing power.

In comparison to the rod withdrawal, the rod insertion will result in:

a.

a longer period due to long lived delayed neutron precursors.

b.

a shorter period due to long lived delayed neutron precursors.

c.

the same period due to equal amounts of reactivity being added.

d.

the same period due to equal reactivity rates from the rod.

QUESTION (A.16)

[1.0]

The reactor is shutdown after an extended, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , run at 240 kilowatts. Which one of the following is the time it takes for the MAXIMUM Xenon concentration to be achieved?

a.

0 to 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months b.

2 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months c.

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

18 to 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months

Section A Theory, Thermo & Fac. Operating Characteristics QUESTION (A.17)

[1.0]

The Reed Reactor is operating at 250 KW and the reactor scram is set for 110% of full power.

What will be the power at the time of the scram if a nuclear excursion creates a 0.5 second period and the scram delay time is 1.0 second?

a.

275 KW b.

670 KW c.

1847 KW d.

25000 KW QUESTION (A.18)

[1.0]

An experiment to be placed in the central thimble has been wrapped in cadmium. Which one of the following types of radiation will be most effectively blocked by the cadmium wrapping?

a.

Thermal neutrons

b.

Fast neutrons

c.

Gamma rays

d.

X-rays QUESTION (A.19)

[1.0]

Which one of the following factors in the "six factor" formula is the most strongly affected by the Negative Temperature Coefficient ?

a.

The fast fission factor

b.

The thermal utilization factor

c.

The resonance escape probability

d.

The thermal non-leakage probability QUESTION (A.20)

[1.0]

A reactor with an initial population of 24000 neutrons is operating with Keff = 1.01. Of the CHANGE in population from the current generation to the next generation, how many are prompt neutrons?

a. 25

b. 238

c. 2500

d. 24240

Section A Theory, Thermo & Fac. Operating Characteristics ANSWER (A.1) b REFERENCE (A.1)

Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 7.1, p. 289.

ANSWER (A.2) a REFERENCE (A.2)

ANSWER (A.3) d REFERENCE (A.3)

Burn, R., Introduction to Nuclear Reactor Operations, 1982, § 5.7, pp. 5-28 5-38.

CR1/CR2 = (1 - Keff2)/(1 - Keff1) 1/32 (1 - 0.95) = 1 - Keff2 1 - 0.05/32 = Keff2 = 0.9984 ANSWER (A.4) a REFERENCE (A.4)

ANSWER (A.5) b REFERENCE (A.5)

p=(k-1)/k; p= -0.05; -0.05k = k-1; 1 = k-(-0.05k) = k(1+0.05); k=1/1.05; k=0.9524 ANSWER (A.6) a REFERENCE (A.6)

Lamarsh, J.R., Introduction to Nuclear Engineering, Addison-Wesley Publishing, Reading, Massachusetts, 1983. § 5.10, p. 213 215.

ANSWER (A.7) c REFERENCE (A.7)

SDM = (1-Keff)/Keff Keff = 1/(SDM + 1)

Keff = 1/(.0526 + 1) =.95 CR1/CR2 = (1 - Keff2) / (1 - Keff1) 10/20 = (1 - Keff2) / (1 - 0.95)

(0.5) x (0.05) = (1 - Keff2)

Keff2 = 1 - (0.5)(0.05) = 0.975 ANSWER (A.8) a REFERENCE (A.8)

Glasstone, S. and Sesonske, A, Nuclear Reactor Engineering, 1991, § 5.98, p. 264.

ANSWER (A.9)

Section A Theory, Thermo & Fac. Operating Characteristics a

REFERENCE (A.9)

Glasstone, S. and Sesonske, Nuclear Reactor Engineering, §§ 3.161 3.163, pp. 190 191.

ANSWER (A.10) d REFERENCE (A.10)

Glasstone, S. and Sesonske, Nuclear Reactor Engineering, §§ 2.70 2.74, pp. 65 -- 66.

ANSWER (A.11) b REFERENCE (A.11)

T = ( - )/

T = t/ln 2 = 24/.693 = 34.6 seconds 34.6 =.0070 - /0.1 x 3.46 =.007- /

(3.46+1)=.007

=.007/4.46 =.00157 =.16% K/K ANSWER (A.12) c REFERENCE (A.12)

ANSWER (A.13) c REFERENCE (A.13)

ANSWER (A.14) d.

REFERENCE (A.14)

ANSWER (A.15) a REFERENCE (A.15)

ANSWER (A.16) c REFERENCE (A.16)

ANSWER (A.17) c REFERENCE (A.17)

Pf = P0 et/T Pf = 250 KW e(1 sec/0.5 sec) = 1847 KW ANSWER (A.18) a REFERENCE (A.18)

Glasstone, S. and Sesonske, 1991, § 10.34, pp. 639.

Section A Theory, Thermo & Fac. Operating Characteristics ANSWER (A.19) b REFERENCE (A.19)

Glasstone, S. and Sesonske, 1991, § 5.98, p. 264.

ANSWER (A.20) b REFERENCE (A.20) 24000 x 1.01 = 24240 neutrons in next generation 24240 - 24000 = 240 neutrons added 240 neutrons added - 0.7% delayed neutron fraction = 238 prompt neutrons added

ML022590196

Contents

Text

SUBJECT:

Dear Mr. Frantz:

Enclosures:

SUBJECT:

Dear Mr. Frantz:

Enclosures:

SUMMARY

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ML022590196

Text

SUBJECT:

Dear Mr. Frantz:

Enclosures:

SUBJECT:

Dear Mr. Frantz:

Enclosures:

SUMMARY

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