Text

Exam Rept 50-134/90-01OL on 900416-17.Exam Results:All Candidates Passed Exam & Issued Licenses
	ML20055D087
Person / Time
Site:	05000134
Issue date:	06/21/1990
From:	Eselgroth P, David Silk; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20055D085	List: IR 05000134/1990001; ML20055D084;
References
	50-134-90-01OL, 50-134-90-1OL, NUDOCS 9007030193
	Download: ML20055D087 (69)
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U. S. NUCLEAR REGULATORY COMMI$$10N REGION I

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OPERATOR LICEN$1NG EXAMINATION REPORT i

REPORT No:

50-134/90-01(OL)

' FACILITY DOCKET No:

50-134 FACILITY LICENSE No:

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LICENSEE:

Worcester Polytechnic Institute e.

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FACILITY:

Worcester Polytechnic Institute Open Pool Reactor

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EXAMINATION DATES:

April.16 - 17, 1990 EXAMINERS:'

David Silk, DRS, Region I L

Beth Wetzel HQ, OLB t-Richard Laufer, HQ OLD N

. SUBMITTED BY:. /O(

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David. Silk.

Date

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Senior Operations Engineer E

- APPROVED BY:-

I/fd Peter W. Eselgroty, thief Date

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PWR Section, Op#ations Branch SUMMARY:

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Written and operating examinations were administered to three reactor operator.

- (RO) and one senior reactor operator (SRO) candidates. All candidates passed

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all portions of the examination and were issued licenses.-

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DETAILS l

TYPE OF EXAMINATIONS:

Replacement EXAMINATION RESULTS:

$

l R0 l SRO I Total l

Grading l Pass / Fail l Pass / Fail.l Pass / Fail l

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l Written 3/0 l

1/0 l

4/0 l

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l l Simulator N/A-l N/A N/A l

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l Operating 3/0 l

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4/0 l

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1/0 l

4/0 l

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EXAMINERS AT SITE: B. Wetzel R. Laufer 2.

The following is a summary of generic deficiencies noted from the operat-ing examinations.

This information is being provided to aid the licensee-in upgrading license and requalification training programs. No licensee-response is required, a.

The reactor operators demonstrated an unfamiliarity with Technical Specifications during the walkthrough by not being able to readily find various items.

(See Section 5.b for details)

b.

- The reactor operators demonstrated a weakness.-in the knowledge of-the Emergency Plan.

(See Section 5.c for details)

3.

The: following. is a summary of generic deficiencies noted from the grading of the written examinations.

(Note: A deficiency is considered to exist when all candidates lose points on the same question and/or the total number of points missed by the candidates on the same question is greater than 50*4 of the total possible points for that question). This informa-tion is being provided to. aid the licensee in upgrading license and requalification training programs. No licensee response-is required.

Question No.

Knowledge A.2.1 Definition of the fast fission factor A6 Calculation of added reactivity given a change in Keff L

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B.3 rerson responsible for directing activities in the event of a nuclear emergency B.15 Area that is specified as the Emergency Planning Zone B.16 Person that can authorize a temporary procedure which does not change the intent of the procedure C.8.6 Automatic system response to a 10 second reactor period 4.

Personnel present at Exit Interview:

NRC Personnel: B. Wetzel R. Laufer WP1 Personnel: T. Newton 5.

NRC Comments at Exit Interview a.

For future exams, the specific sections of Introduction to Nuclear Engineering (or other text) that are used for training the candidates in reactor theory should be listed along with the reference material in order to avert the use of theory principles that are not used for training, b.

The reactor operators demonstrated an unfamiliarity with Technical Specifications during the walkthrough by not being able to readily find various items in Technical Specifications.

For example, one candidate paged through Technical apecifications and referred to the Index several times before he was able to locate the Surveillance Section. Another candidate was unaware that there was a copy of Technical Specifications attached to the Operations Log Book for the operator's use and went to the Reactor Facility Office to look for Technical Specifications.

c.

The reactor operators demonstrated a weakness in the knowledge of the Emergency Plan. The operators were not familiar with the terminology used in the Emergency Plan, such as " Emergency Planning Zone" or

" Emergency Actions Levels" and, when asked to identify the Emergency Plan during the walkthrough, f ailed to do so.

They are not trained on the Emergency Plan; however, they are trained on their specific duties during emergency conditions. lhe one SRP candidate examined during this trip was very familiar with the Emergency Plan.

d.

In the event of an evacuation, potentially contaminated personnel must walk two blocks to the WPI Security Office to be frisked.

This is because the Security Office, which was previously located next door to the Reactor Facility, has recently moved, l

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Facility Comment at' Exit Meetinc

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Re~ actor, staff were aware of' the potentia 1 ' contamination problems

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associated with the locale of the closest frisker outside of the reactor i

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facility and is:considering possible options,

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ATTACHMENTSi

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Written-Examination with Answer Key i

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.3, NRC Resolution of Facility. Comments to Written Exam

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ATTACHMENT 1 Written Examination with Answer Key

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U. S. NUCLEAR REGULATORY COMMISSION NON POWER REACTOR LICENSE EXAMINATION o'

hk FACILITY:

Worcester Polv. Inst.

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REACTOR TYPE:

TEST DATE ADMINISTERED:

90/04/16 REGION:

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CANDIDATE:

LICENSE APPLIED FOR:

INSTRUCTIONS TO CANDIDATE:

Answers are to be written on the exam page itself, or the answer sheet provided. Write answers one side ONLY.

Attach any answer sheets to the examination.

Points for each question are indicated in parentheses for each question.

A 70% in each section is required to pass the examination.

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Examinations will be picked up three (3) hours after the examination starts.

% OF

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CATEGORY % Of CANDIDATE'S CATEGORY j

VALUE TOTAL SCORE VALVE CATEGORY 17.00 1 81 A.

REACTOR THE0RY, THERMODYNAMICS

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AND FACILITY OPERATING CHARACTERISTICS i

20.00 33.90 B.

NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS

22.00 37.29 C.

PLANT AND RADIATION MONITORING SYSTEMS 59.00

%

TOTALS FINAL GRADE

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All work done on this examination is my own.

I have neither given

nor received aid.

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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS

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During the administration of this examination the follcwing rules apply:

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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 whether you use the examination question pages or separate sheets of paper.

Initial each page.

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

The amount of blank space on an examination question page is NOT an indication of the depth of answer required.

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

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10. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets.

In addition, turn in all scrap paper.

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11. To pass the examination, you must achieve at least 70% in each category.

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

(or some other time if less than the full examination is taken.)

13. When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner.

If you are found in this area while the examination is still in progress, your license may be denied or revoked.

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EQUATION SHEET

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Energy (in)

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k CR (1 * Kett)2 UA aT CR (1 * Kett)1

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RX THEORY. THERM 0 & FAC OP CHARS

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QUESTION: 001 (1.00)

Reactor power is increased at a steady rate from 1 kW to 10 kW in one minute.

What is the reactor period during this interval?

a.

13 seconds b.

26 seconds c.

34 seconds d.

42 seconds

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AL RX THEORY, THERM 0 & FAC OP CHARS Page 5

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QUESTION: 002 (2.00)

Match the factors which contribute to the Keff of a reactor in Column I with their definitions in Column II.

Items in Column I have only one answer and items in Column 11 may be used once, more than once or not at all (0.50 pts, per response).

Column I (Factor)

1.

Fast Fission Factor 2.

Resonance Escape Probability

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3.

Reproduction factor y

4.

Thermal Utilization Factor Column II (Definition)

a.

The number of neutrons born from fission by thermal neutrons The number of thermal neutrons absorbed in fuel b.

The number of thermal neutrons absorbed in fuel The number of thermal neutrons absorbed in all materials

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c.

The number of neutrons that do not leak out while thermal The number of neutrons that escape resonance capture while slowing down d.

The number _pf neutrons that escape resonance canture while slowina down The number of neutrons that do not leak while fast e.

The number of neutrons that do not leak out while fast Net number of neutrons born from fission by neutrons of all energies f.

The net number of neutrons born from fission by neutrons of all eneraies The number of neutrons born from fission by thermal neutrons

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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A RX THEORY. THERM 0 & FAC OP CHARS Page 6

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QUESTION: 003 (1.00)

Which one of the following statements concerning the reactivity values of equilibrium (at power) Xenon and peak (after shutdown) Xenon is correct? Assume shutdown occurs from equilibrium conditions.

Equilibrium Xenon is INDEPENDENT of power level; peak Xenon is INDEPENDENT a.

of power level, b.

Equilibrium Xenon is INDEPENDENT of power level; peak Xenon is DEPENDENT on power level, c.

Equilibrium Xenon is DEPENDENT on power level; peak Xenon is INDEPENDENT of power level.

d.

Equilibrium Xenon is DEPENDENT on power level; peak Xenon is DEPENDENT on power level.

QUESTION: 004 (1.00)

Given the following neutron interaction equation:

Rh + o *

Rh"' + o y n

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a.

elastic scattering b.

fission c.

inelastic scattering d.

radiative capture (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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RX THEORY, THERM 0 &'FAC OP CHARS Page-7'

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QUESTION: 005 '(1.00)

l Which one of the following describes the beta decay of a nuclide?

a.

Atomic mass # decreases.by'l and number of protons remains constant

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b.

Atomic mass # remains-the same and number of protons increases by 1-

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Atomic mass # remains the same and number of protons remains constant i

d.

Atomic mass # decreases by 1 and number of protons decreases by 1 l

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QUESTION: 006 (1.00)

I Which of the following is the correct amount of reactivity added if Keff is.

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increased from 0.861'to 0.9657 a.

.086 delta k/k

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.104 delta k/k

c.

.125 delta k/k

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.220 delta k/k r

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QUESTION: 007 _(1.00)

j Using the representative heat flux curve pictured below, select the point at

.which departure from nucleate boiling occurs.

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RX' THEORY, THERM 0 & FAC OP CHARS Page 9

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QUESTION: 008 (1.00)

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Using the representative' heat flux curve pictured below, select the area of the i

curve in which heat is transferred by convection ONLY.

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Area Ill d.

Area IV

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i QUESTION: 009 (1.00)

i Which one of the following' accurately describes the effect that FUEL Temperature i

has'en core physics?

A fuel temperature INCREASE will DECREASE the resonance escape probability.

a.

b.

A fuel temperature DECREASE results in Doppler Broadening of U 238 and Pu-240 resonance peaks and the DECREASE of-resonance escape probability.-

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A DECREASE in fuel temperature will INCREASE neutron absorption by U-238 c.

and Pu-240.

i d.-

A fuel temperature INCREASE results in Doppler Broadening of U 238 and Pu-240 resonance peaks and the DECREASE of neutron absorption during

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moderation.

QUESTION: 010 (1.00)

Which one cf the following best describes the difference between a reflector and

a moderator?

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Reflectors slow down neutrons while moderators decrease core leakage.

a.

b.

Reflectors decrease core leakage while moderators thermalize neutrons.

Reflectors shield against neutrons while moderators decrease plutonium c.

production.

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d.

Reflectors shield against neutrons while moderators decrease core leakage, i

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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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RX THEORY, THERM 0 & FAC OP CHARS Page 11 P

QUESTION: 011 (1.00)

What is the period that would cause the reactor power to double in 40 seconds?

a.

3.7 seconds b.

27.7 seconds c.

57.7 seconds

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d.

80.0 seconds

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QUESTION: 012 (1.00)

Which of the following accurately details a factor contributing to Xenon balance within the reactor?

a.

Most Xe-135 is formed by fission.

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b.

Tellurium 135 is a fission product which quickly decays to 1-135.

Within approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months after startup, Xe-135 has reached its c.

equilibrium value.

d.

Several minutes following a reactor shutdown, Xe level is increasing because 1-135 is not being produced.

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(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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QUESTION: 013 (1.00)-

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Select the statement which is accurate concerning the' differences between prompt i

and delayed neutrons.

Prompt neutrons account for less than one percent of the neutron population a.

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the neutron population, b.

Prompt neutrons are released during fast fiscions while delayed neutrons are released during thermal fissions.

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Prompt neutrons are released during the fission c;

neutrons are released during the decay process, process while delayed

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Prompt neutrons are the dominating factor in determining the reactor period -

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i QUESTION: 014 (1.00)

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Which one of the following is MOST a'fected by fission product poisons?

a.

fast. fission factor

b.

thermal utilization factor c.

thermal non-leakage probability

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d.-

fast non-leakage probability

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i QUESTION: 015 (1.00)

Which of the following describes the inherent safety feature provided by the temperature coefficient of reactivity?

Its negative value causes reactivity to increase as moderator temperature a.

increases,

b.

Its negative value causes reactivity to decrease as moderator temperature

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increases.

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Its positive value causes reactivity to increase as moderator temperature c.

increases.

d.

Its positive value causes reactivity to decrease as moderator temperature increases.

QUESTION: 016 (1.00)

g During steady state equilibrium operation the reactor bulk average coolant temperature is reduced de 10 degrees F and an experiment is activated which introduces 0.5% effective void into the core.

Given:

Temperature Coefficient = -2 E-5 delta k/k/ degrees F Void Coefficient-2 E-3 delta k/k/% void Regulating Rod Worth = 2.6 E 4 delta k/k/ inch In what direction and how far must the regulating rod be moved to maintain equilibrium?

The regulating rod must'be withdrawn approximately 1.0 inch.

a.

b.

The regulating rod must be withdrawn approximately 3.0 inches.

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c.

The regulat$ng rod must be inserted approximately 1.0 inch.

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d.

The regulating rod must be inserted approximately 3.0 inches.

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END OF CATEGORY A *****)

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NORMAL /EMERG PROCEDURES & RAD CON'

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QUESTION: 001' (1.00)

An accessible area with a radiation level of 75 mrem /hr should be posted as a(n)

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a.

restricted area b.

radiation area c.

high radiation area-d.

exclusion area QUESTION: 002 (1.00)

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If you are working in a radiation zone where the. general background is 50 mrem /hr

. gamma radiation, how long can you stay in that zone before you would exceed the minimum 10 CFR 20 whole body quarterly limit?

a..

25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months b.

50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months

.c.

75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months d.

100 hour0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months s-L-

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NORMAL /EMERG PROCEDURES & RAD CON Page 15

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QUESTION: 003 (1.00)

-Who has the primary responsibility for directing the necessary activities required to cope with a nuclear emergency?

a.

SRO on Duty b.

Reactor Facility Director c.

Chairman, Radiation Health and Safety Committee d.

Campus Radiological Safety Officer QUESTION: 004 (1.00)

The dose rate at a distance of six inches from a point source is 5000 mrem /hr.

At what approximate distance from the source must a *High Radiation Area" sign be posted?

a.

1.5 feet b.

3.5 feet

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c.

4.0 feet d.

6.0 feet

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(***** CATEGORY B CONTINVED ON NEXT PAGE *****)

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NORMAL /EMERG PROCEDURES & RAD CON Page 16

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QUESTION: 005 (1.00)

L A visual check for normal pool water level is required during the performance of the " Reactor Check-Out Procedure." What does the procedure reference as a

" normal pool water level"?

from the overflow pipe to not more than six inches below it a.

b.

no more than one foot below the bottom surface of the bridge from six inches to one foot below the overflow pipe c.

d.

plus or minus three inches from the hash mark painted on the concrete shield wall i

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QUESTION: 006 (1.00)

At what radiation level does the area radiation monitor which is next to the thermal column door alarm?

a.

20 mrem /hr

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b.

40 mrem /hr c.

50 mrem /hr i

c.

75 mrem /hr l

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NORMAL /EMERG PROCEDURES & RAD CON Page 17

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s QUESTION: 007 (1.00)

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When are the rooms above the reactor required to be locked?

a.

when the reactor is critical b.

at all times, except when the reactor has been shutdown for greater than 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months c.

when the reactor power is above 100 watts

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d.

when the reactor power is above 1 kW QUESTION: 008 (1.00)

What is the minimum personnel requirements, per procedure, during fuel loading

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and unloading operations?

one licensed operator in the bridge area and on senior operator present a.

b.

one licensed operator at the console and one senior operator in the bridge area one licensed operator at the console, one licensed operator in the bridge i

c.

area and one senior operator present I

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d.

one licensed operator at the console, one licensed operator in the bridge area, one senior operator present and the Radiation Safety Officer present

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(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

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NORMAL /EMERG PROCEDURES &' RAD CON Page 18

i QUESTION: 009 (1.00)

According to the " Safety Rules for Operation in the Reactor Laboratory,"

radioactive material should be stored in a container when not in use and shielding sufficient to reduce the radiation level below at the surface

!

of the shielded container should be in place.

I a.

2 mr/hr b.

5 mr/hr c.

10 mr/hr d.

15 mr/hr

'

QUESTION: 010 (1.00)

Where is the Assembly Area in the event of a Facility Evacuation?

a, the entranceway to Salisbury Laboratories b.

the front door area of the Washburn Laboratory the Staff Parking Lot behind Gordon Library c.

d.

the front door area of Gordon Library I

(***** CATEGORY B CONTINVED ON NEXT PAGE *****)

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1). NORMAL /EMERG PROCEDURES & RAD CON Page 19

,

l

i +

QUESTION: 01)

(1.00)

If a person suspects that he might be contaminated, according to the Contamination Control Measures in the Emergency Plan, what should he do?

a.

Phone the Radiation Safety Officer for decontamination, b.

Report directly to the facility Director for assistance, c.

Report directly to Security where he can be monitored, d.

Inform the person in charge of the experiment and report to the Facility Director for monitoring.

QUESTION: 012 (1.00)

How often is the complete Reactor Check Out required to be performed?

a.

Prior to each reactor startup.

b.

Before each day's initial reactor operation, c.

The first day of each work week.

d.

Once a month, i

!

l l

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

/

S. NORMA 1./EMERG PROCEDURES & RAD CON Page 20

,

c.

QUESTION: 013 (1.00)

What is the minimum personnel requirement during reactor critical operation, per Technical Specifications?

one licensed operator at the controls and a senior operator readily a.

available on call b.

two persons in the reactor facility, including one licensed operator at the controls, and a senior operator readily available on call two persons in the reactor facility which include the following:

c.

one licensed operator at the controls and either a health physics technician or a senior operator d.

three persons in the reactor facility which include the following:

one licensed operator at the controls, one senior operator and one security officer QUESTION: 014 (1.00)

In the event of a radioactive spill, what type of action should be followed for operation of the ventilation system?

a.

close the dampers b.

shut the ventilation system off until radiation levels decrease c.

continue to operate the ventilation system as normal d.

turn the fans to half speed I

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

^

^ NORMAL /EMERGPROCEDURESERADCON B.,

Page 21

.,

QUESTION: 015 (1.00)

What-is the " Emergency Planning Zone," as defined by the WPI Emergency Plan?

a.

The Reactor Room which is bounded by walls and locked doors b.

The Washburn Laboratory Building c.

The WPI Campus d.

The area within a 1 mile radius of the WPl Pool Reactor QUESTION: 016 (1.00)

Per Technical Specifications, who may authorize the use of a temporary procedure which does not change the intent of the initial approved procedure?

a..

the SR0 on duty b.

.a licensed SRO and another member of the. facility staff

.c.

-the Facility Director d.

a licensed Reactor Operator and the Radiation Safety Officer QUESTION:'017 (1.00)

,

When. reloading fuel into the core to a-. standard configuration what type of loading-technique is used?

Central elements are loaded first working out towards the periphery, a.

b.

~ Peripheral elements are loaded first working in towards the center.

Elements are fitted next to the control blades first and then loaded into c.

-the other. core positions.

d.

Elements are loaded in increments, with a smaller number of elements per increment as more fuel is loaded.

,

(***** CATEGORY B CONTINVED ON NEXT PAGE *****)

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.a B.. NORMAL /EMERG PROCEDURES & RAD CON Page 22

'

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,

QUESTION: 018 (1.00)

How are-the power level detectors calibrated on the WP1 pool reactor?

a.

By irradiating a gold foil, counting it to determine power level and adjusting the detector positions to give proper indication, b.

By. performing a heat balance on the pool at power to determine reactor power and adjusting the gain on the detectors to give proper indication.

By using a calibrated ion chamber to read reactor power and adjusting the c.

gain on the other detectors to read the same power level, d.

By measuring the neutron flux in the beam port at power and adjusting the detector positions to read the proper flux.

QUESTION: 019 (1.00)

Rod withdrawal times are measured at least annually.

The blade system must be adjusted if the time to withdrawal a blade a distance of 7.5 inches is measured to be less than

,

a.

I minute b.

1.5 minutes c.

2 minutes d.

3' minutes (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

_

I'e-

,B ; NORMAL /EMERG. PROCEDURES & RAD CON Page 23'

,-

-

e

QUESTION:-020 (1.00)

,

~ When is the' regulating blade withdrawn during a reactor startup?

~ fter the B-10 counter is withdrawn and the power range instrumentation

'

a.

a is'on scale

.b..

when reactor power reaches 10 watts c.

after the third control blade is withdrawn 15 inches d.

after all three control blades are fully withdrawn i

l l

\\

1 l

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i:

I I

!

[

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

v -w

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Lf,

'C.

PLANT AND RAD MONITORING SYSTEMS Page 24

4, QUESTION: 001 (2.00)

Match the conditions in Column I with their Reactivity Limits in Column 11.

Items in Column 11 may be used once, more than once or not at all.

(0.50 points per response)

Column I Column II (Condition)

(Reactivity Limit)

1. Maximum excess reactivity above a. 0.02 % delta k/k cold, clean critical b. 0.06 % delta k/k 2. Minimum Shutdown Margin c. 0.5% delta k/k 3. Maximum Total Worth of.all experiments d. 0.7% delta k/k 4. Maximum Total Worth of the e.1.0% delta k/k Regulating Blade QUESTION: 002 (1.00)

During critical operation of the reactor, the maximum bulk water temperature of-the pool is and the minimum is

,

a.

100 degrees F, 60 degrees F b.

100 degrees F, 70 degrees F c.

110 degrees F, 60 degrees F d.

110 degrees F, 70 degrees F

.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

l

i

kL 7;;

Q.-

PLANT AND RAD MONITORING SYSTEMS Page 25

- i.

t QUESTION: 003 (1.00)

i What type of detector is used in the Log N Period Channel?

a.

Boron-10 Proportional Counter a

,

b.

Uncompensated Ionization Chamber c.

Sodium Iodide Gamma Scintillation Detector d.

Gamma-Compensated Ionization Chamber

!

QUESTION: 004 (1.00)

Under which of the following conditions will the control blade drive motors NOT

!

be interlocked to prevent withdrawal of the blades?

,

-1 a.

The reactor is in a scram condition.

i i

b.

The regulating blade is 3 inches above its lowest position.

The master control switch has been turned to the "on" position for'5 c.

seconds, d.

The log count rate meter reads 70 counts /sec.

!

i QUESTION:-005 (1.00)

Which of the following control. rod configurations is required during core l

alterations to provide the necessary fast scram capability?

i a.

All three safety blades must be fully withdrawn, b.:

.All three safety blades must be withdrawn 12 -inches.

c.

Two safety blades must be withdrawn 15 inches.

d.

Two safety blades must be withdrawn 10 inches.

i L

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

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C.-- ' PLANT AND RAD MONITORING SYSTEMS Page'26

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c QUESTION: 006 _(1.00)

Which of the following is the operating range of the Log N period channel?

a.

0.01 W to 20 kW b.

0.1 W to 12 kW c.

0.2 W to 15 kW d.

0.5 W to 10 kW QUESTION: 007 (1,00)

What'is.the minimum nuclear instrumentation required for startup?

a.

Startup Channel and Log N Period Channel, b.

Startup Channel and one Linear Channel, c.

Startup Channel, Log N Period Channel and one Linear Channel, d.'

Startup Channel, Log N Period Channel and Linear Channels 1 & 2.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

,

m

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f j, lG.

PLANT AND RAD' MONITORING SYSTEMS Page 27

,

g

,

?

QUESTION: 008 (3.00)

Match.the facility conditions in Column I with the type of automatic response expected to occur from the safety system in Column II.

Items in Column I have only one correct answer and items in Column 11 may be used once, more than once or not at all.

(0.50 points per response).

Column I Column II (Condition)

(Automatic Response)

1.

4 second reactor period a.

Electronic Scram

!

2.

Ar-41 setting exceeded b.

Relay Scram 3.

Two CIC's (charnels 1 and 2) read c.

Panel Alarm Only

'

150% of Full Power

,

d.

No Safety System 4.

Control Blade disengaged Response

5.

High Voltage failure in Control Center Cubicle 6.

10 second reactor period

,

QUEST 10N: 009 (1.00)

Which of the following is the composition of the poison section of the Safety

'

Blades?

.

a.

boron carbide and aluminum plates b.

boron oxide and stainless steel plates boron carbide and stainless steel plates c.

t d.

boron carbide and nickel plates (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

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:+.

C. ' PLANT AND' RAD MONITORING SYSTEMS'

Page 28

'

.g.

m-QUESTION: 010 (1.00)

At steady state full power, approximately how much radiation would you expect at the pool surface (bridge) monitor?

a.

10 mR/hr

.

b.

25 mR/hr i

c.'

50 mR/hr-i d.

75 mR/hr

'

i QUESTION: 011 '(1.00)

There are four basic Regions on the curve illustrating the Applied Voltage versus the Log of the Collected Charge which represent different types of detector

,

u operation.- In which of the regions does a single ionizing event cause a total discharge (avalanche) of the detector?

a.

-Ion Chamber b.

Proportional

,

c.

Geiger-Mueller d.

. Continuous Discharge i

QUESTION: 012 (1.00)

At what setpoint does the pool level alarm initiate at?

!

'

a.

approximately 3 inches below normal b.

approximately 6 inches below normal c.

approximately 10 inches below normal d.

approximately 12 inches below normal l

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

h;. h T

C.-

PLANT AND RAD _ MONITORING SYSTEMS:

Page 29 t.

'i.

l QUESTION: 013 (1.00)

<

What type of radiation source is provided for experiments by use of-the beamport?

l f

a.

beta

!

l b.

beta and gamma I

c.

thermal neutrons-

!

d.

fast neutrons i

!

QUESTION: 014 (1.00)

What type of-neutron source is used in the WPI Pool Reactor?

a.

1 Curie of Polonium-Fluoride i

b.

1 Curie of Plutonium-Beryllium c.

2 Curies of Americium-Lithium

-

d.

2 Curies of Polonium-Beryllium i

!

QUESTION: 015 (1.00)

Wha't is the' normal flow through the demineralizer pump?

a.

2 gpm b.

5 gpm c.

10 gpm d.

15 gpm (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

.pf Y

0.

PLANT AND RdD MONITORING' SYSTEMS J

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Page 30

.,

.

QUESTION: 016 (1.00)

What does a RED light illuminated on the control panel indicate concerning the

'

control rod-drive mechanism of a specific control blade?

"

a.

The Control Blade is full out, b.

The Control Blade is inserted fully into the core.

c.

The Control Blade is disengaged from its magnet.

d.

.The Control Blade is in motion.

QUESTION: 017 (1.00)

What is the purpose of the " TEST" position of the master ' control switch?

a.

It is used to test the facility evacuation alarm.

b.

It permits exercising of the control drives without energizing the scram magnets and withdrawaling the blades.

c.

It allows for testing of the safety blades in various configurations by overriding the blade withdrawal. interlocks.

d.

It is used to verify adequate power supply to the Control Center Cubicle without having to turn the master switch to "0N".

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

i

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<C.

PLANT AND RAD MONITORING SYSTEMS Page 31

,

.t.

QUESTION: 018 (1.00)

What type of Control Blade motion does the Octuation of-the "re,ual run-down" switch cause?

This switch moves the Regulating Blade down approximately one to three a.-

hundredths of an inch each time it-is activated, b.

This switch moves the selected Control Blade continuously inward until the switch is released, This' switch moves all three Safety Blades and the Regulating Blade c.

continuously inward until the switch is released.

d.

This switch moves all three Safety Blades and the Regulating Blade inward until all blades are full in, shutting off automatically.

QUESTION: 019 (1.00)

mircroCuries/ml is the maximum limit for pool water activity, a.

10E-3 b.

10E-4 c.

10E-5 d.

10E-6 (***** END OF CATEGORY C *****)

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

__ - - _

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_--__ _ - _ - - - - -

N :.:

A._

RXiTHEORY, THERM 0 & FAC OP CHARS Fage 32

-

i,;

ANSWER:-

001 :(1.00)

b REFERENCE:

,,

WPI: Operator Exam Question, Cat. 1.

ANSWER:

002 (2.00)

.

1. f 2. d 3. a 4. b REFERENCE:

>

" Introduction to Nuclear' Engineering," Lamarsh, p. 239.

ANSWER:

003 (1.00)

d REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, pp.319-323.

ANSWERi 004 (1.00)

d-(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

_ _ _ _ _ _ _. _...........

.

'r

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A. ' RX-THEORY,' THERM 0 & FAC OP CHARS-Page 33

,

REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, pp. 44-45.

1.

ANSWER:

005 (1.00)

b REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, p.19.

-ANSWER:

006 (1.00)

-C REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, p.282.

ANSWER:

'007 (1.00).

a REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh pp. 377-380.

(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

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o1 LAN ~ 'RX THEORY, > THERM 0' &. FAC OP CHARS Page 34-

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f ANSWER:-

008 (1.00)

,,

,

a

. REFERENCE:

,

'" Introduction to, Nuclear Engineering," Lamarsh, pp. 377-379.

ANSWER:

009 (1.00)

a REFERENCE:

,

" Introduction to Nuclear Engineering," Lamarsh, p.209.

ANSWER:

010 '(1.00)

b'

'

REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, p.ll8.

' ANSWER:

011- (1.00)

c (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

l l

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SY ;!!

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'.3

A; RX THEORY, THERMO.& FAC OP-CHARS Page 35

)

' :,

<

REFERENCE:

" Intr 6 duction to Nuclear Engineering," Lamarsh, p. 289.

-

,.

ANSWER:

012 (1.00)'

b i

REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, pp.316 324.

<

' ANSWER:

013 (1.00)

c REFERENCE:

I WPI: Typical Operator Exam Questions, ' Category 1.

l l

r ANSWER:

014 (1.00)

I l

bI

REFERENCE:

" Introduction to Nuclear Engineering," Lamarsh, p. 316.

>

-(***** CATEGORY A CONTINUED ON NEXT PAGE *****)

.

-

.

-l t

-'

Je A. 'RX THEORY, THERM 0'& FAC OP CHARS Page 36-t,-

ANSWER:

015 -(1.00)

b i

!

i REFERENCE:

j

.:

" Introduction to Nuclear Engineering," p. 307.

i I

ANSWER:

016 (1.00)

i b-(

REFERENCE:

WPI SAR, p. 11 and p. 29.

!

i i

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

m 9-

-

.

s41

80- NORMAL /EMERG PROCEDURES & RAD CON

'Page 37

-

.!'

y-

' ANSWER:

001.(1.00)

{

b l

!

l REFERENCE:

'

i 10 CFR Part 20

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I

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ANSWER:.

002 (1.00)

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a i

!

REFERENCE:

,

!

10 CFR Part 20

!

f:

,

ANSWER:

003 (1.00)

!

b-i i

REFERENCE:

WPI Emergency Plan, p. 2.

,

/

ANSWER:

004- (1.00)

b.

L i

..

l.

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

l

'

l^

L..

=

.B.1 NORMAL /EMERGPROCEDURES&RADCON

.-

Page 38 i.

"

REFERENCE:

WPI: Typical Operator Examination Questions, Category 4.

.\\

t ANSWER:

005 (1.00)

a

,

REFERENCE:

b WPI Operating and Test Procedures

" Reactor Check-out," p, 1.

,

ANSWER:

006 (1.00)

a

=l

. REFERENCE:

WPI Operating and Test Procedures

" Reactor Check-out," p.l.

I

,

ANSWER:

007 (1.00)

d-

,

(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

4.. r

.Bb NORMAL /EMERG PROCEDVRES &' RAD CON s.-

'

Page 39

.r r

REFERENCE:

WPI Operating and Test Procedures

" Reactor Startup," p. 6.

ANSWER:

008 (1.00)

C (

REFERENCE:

WPI Operating and Test Procedures

" Fuel Unloading and Fuel Reloading," pp. 11

'

and 12.

.

-ANSWER:

009 (1.00)

v a

i REFERENCE:

"WPI Operating and Test Procedures," p. 18.

'

E ANSWER:

010 (1.00)

d

,

i (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

!

t-

<6

Bi NORMAL /EMERG PROCEDURES'& RAD CON Page 40 4.

REFERENCE:

"WPI Operating and Test Procedures," p. 10.

!

t i

!

ANSWER:

011 (1.00)

,

c REFERENCE:

t WPI SAR, p. 38c.

ANSWER:

012- ( l'. 00)

b REFERENCE:

WPI SAR, p. 32 and "WPI Operating and Test Procedures," p, 6.

,

ANSWER:

013 (1.00)

b'

'(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

-

s,

., ;

.B.-

N0'RMAL/EMERG PROCEDURES & RAD CON:

'

+

.

Page 41

!1

.

,

i REFERENCE:

l WPI' Tech Specs, p. 4.

ANSWER:

014 (1.00)

C REFERENCE:

WPI, SAR, p. 16

!

ANSWER:

015 (1.00)

a v

REFERENCE:

WPI Emergency Plan ~, p. 2.

,

ANSWER:

016 -(1.00)

b (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

.

B.. NORMAL /EMERGLPROCEDURES & RAD CON Page-42 I

.

REFERENCE::

WPI-Tech = Specs, p. 12.

.

~ ANSWER:

017 (1.00)

'

d REFERENCE:

"WPI Operating and Test Procedures," p. 12.

ANSWER:

018 (1.00)

a

,

REFERENCE:

' WPI Operating and Test Procedures," p. 15.

"

ANSWER:

019 (1.00)

a-(***** CATEGORY B CONTINUED ON NEXT PAGE *****)

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i

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l" ' t 7,;

B.

NORMAL /EKERG PROCEDURES & RAD CON-

~Page 43

-

t

. [t l-i;

--REFERENCE:

"WPI~0perating and Test Procedures," p. 47.-

f ANSWER:

020-(1,00)

i-

-d

!-

.

,

-REFERENCE:

"WPI Operating and. Test Procedures," p. 6.

l,

)

f-

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

,

'z, 4.:. PLANT AND RAD MONiiORING SYSTEMS Page 44'

,-

'

ANSWER:l 001- (2.00)

'1.

c 2. e 3. c 4, d REFERENCE:

WPI Tech Specs'pp. 3-4.

,

ANSWER:

002 (1.00)

a

. REFERENCE:

WPI Tech Specs.

ANSWER:

003 (1.00)

d REFERENCE:

WPI Safety Analysis Report, p. 23.

ANSWER:

004 (1.00)

d (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

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C; PLANT AND1 RAD MONITORING-SYSTEMS--

Page 45

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c,;

REFERENCE:'

'!

.-

WPI Safety' Analysis Report, p. 24.

-l y

I

!

ANSWER:

005 (1.00)

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c

!

REFERENCE:

,

WPI, SAR, Section 6.3.2, p.34.

t i

i

i ANSWER:

006 (1.00)

l C

REFERENCE:

WPI Tech Specs, p. 9.

l ANSWER:

007 (1.00)

d

' REFERENCE:

WPI Tech Specs, p.9.

j i

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

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_ _ _ _ _ _ _ _. _ - - - - - _ _ _ - - - - - - - - - - -

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ANSWER: _

008 -(3-00)

.

,

1. b 2. c 3. a 4. c

,

5 '. b 6. c REFERENCE:

WPI: Typical Operator Examination Questions, Category 6.

ANSWER:

009 (1.00)

a REFERENCE:

WPI, SAR, Section 4.1.1, page 17, ANSWER:

010 (1.00)

c REFERENCE:

WPI: Typical Reactor Operator Questions, Category 2.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

l e

4a L.-

G.--PLANT AND RAD MONITORING-SYSTEMS Page 47:

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,

ANSWER:

011 (1.00)'

c REFERENCE:

" Basic ~ Nuclear Engineering " Foster and Wright, p. 126.

ANSWER:

012 (1.00)

d REFERENCE:

WPI-Tech Specs, p. 10.

ANSWER:

-013 (1.00)

d REFERENCE:

WPI-SAR, p. 21.

ANSWER:

014 (1.00)

b (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

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G;. PLANT AND: RAD MONITORING SYSTEMS Page 48-

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REFERENCE:

WPI SAR, p. 26.

\\

. ANSWER:

015 (1.00)

C i

REFERENCE:

j WPI: Typical Operator Examination Questions, Category 3.

.

!

ANSWER:

016 (1.00)

c REFERENCE:

>

WPI SAR, p. 18.

ANSWER:

017 -(1.00)

b REFERENCE:

WPI SAR, p. 23.

.

(***** CATEGORY C CONTINUED ON NEXT PAGE *****)

'.y.

c

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f. : PLANT!AND RAD MONITORING SYSTEMS C

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i ANSWERi 018 (1.00).

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i WPI. Operating and-Test Procedures, p. 3.

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i ANSWER:

019 -(1.00)

t

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- REFERENCE:

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WPI Tech Specs, p.:3.

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

~

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END OF: EXAMINATION **********)

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QUESTION VALUE REFERENCE

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ATTACHMENT 2 Comments on Written RO Exam

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0.e COMMENTS ON WRITTEN R.O. EXAM 4/16/90 Section A - Question 3 - Xe is not produced in significant quantities in the WPI Reactor because of low neutron flux levels.

Because of this, operators are not required to know Xenon production.

Section A - Question 12 - Xe question, see above.

Section A - Question 14 - Because of the low flux levels, significant I

fission product poisons are never seen at the WPI Reactor.

'

Operators are not required to have an understanding of fission product poisoning.

Section B - Question 8 - Although answer

"c" is correct, minimum personal requirements are 1 SRO, 1 RO, and an additional person (not necessarily licensed).

WPI Operating Procedures, p 11-12.

Section B - Question 11 - During the examination, one of the

candidates inquired whether the question was referring to

!

a reactor emergency or to a routine laboratory exercise.

Upon being told to assume a normal exercise, he should have then chosen answer

"d", from WPI Operat.i.ng l

Procedures, p. 18.

Section C - Question 8-1 - Current setting for the electronic scram is 5 seconds.

Therefore, answer "a" or

"b" would be correct.

Section C - Question 10 - Answer is wrong.

It should be

"b".

Section C - Question la - The manual run down switch will insert

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blades until it is released, or until all blades are in; therefore answers "c" and

"d" are correct.

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NRC Resolution of Facility Comments to Written Exam

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NRC RESOLUTION OF FACILITY COMMENTS TO WRITTEN EXAM Section A Questions 3 and 12 NRC Resolution:

Comments accepted.

Xe effects are not seen at the WPI reactor due to very low power levels (administratively limited to I kw).

Both questions dealing with Xe will be deleted from the exam.

Question 14 NRC Resolution:

Comment not accepted.

Fission product poisons effects on the six factor formula is considered basic nuclear theory which a reactor operator should know.

10 CFR Part 55.41 says that the written examination for a Reactor Operator shall include a sampling of 14 items

,

of which item (1) " Fundamentals of Reactor Theory" includes poison effects.

The question will remain in the exam.

Section B Question 8 NRC Resolution: C9mment noted. Although answer 'c' is the only possible correct anse er, the comment will be incorporated into the exam before being loaded inte the question bank for use on future exams.

Question 11 l.

NRC Resolution:

Comment accepted.

Answer 'd' will be accepted as a

!

correct answer only for the candidate that was told to assume non-I emergency conditions during the contamination incident. According to "WPI Operating Procedures,"

p.18, answer 'd'

would be correct under non-Emergency condition ]

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Section C Question 8-1 NRC Resolution:

Comment accepted, based on additional material that was not provided prior to administration of the written exam. The electronic scram setting was documented to measured at 5.25 seconds on 8/7/86 in the Maintenance Log.

The Daily Startup Checksheet verifies the relay scram setting to be 7.5 seconds prior to operations, therefore answer 'a' would be correct.

A4 second period would result in an electronic scram, not a relay scram.

However, the reference used to develop this question is incorrect and should be revised.

Questions 2 and 3 of Category 6 of

Typical Operator Examination Questions WPI Open Pool Nuclear Reactor,"

states that the period settings are 3 seconds for the electronic and 5 seconds for the relay scram.

Question 10 NRC Resolation:

Comment accepted.

The correct answer is

'b'.

This was a typograohical error on the answer sheet.

Question 18

'NRC Resolution:

Comment accepted.

Both answers 'c'

and 'd' will be accepted as correct answers.

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v t e Inspection Report - - 1990001
80 \| 81 \| 82 \| 83 \| 84 \| 85 \| 86 \| 87 \| 88 \| 89 \| 90 \| 91 \| 92 \| 93 \| 94 \| 95 \| 96 \| 97 \| 98 \| 99 00 \| 01 \| 02 \| 03 \| 04 \| 05 \| 06 \| 07 \| 08 \| 09 \| 10 \| 11 \| 12 \| 13 \| 14 \| 15 \| 16 \| 17 \| 18 \| 19 \| 20 \| 21 \| 22 \| 23 \| 24 \| 25 \|
1990 Quarterly Integrated 1Q (0) 2Q (0) 3Q (0) 4Q (0) Assessments Mid Cycle End of Cycle Security Operator Exams Emergency Planning Other

IR 05000134/1990001

Text

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