IR 05000223/1988006

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Exam Rept 50-223/88-06OL on 881205.Exam Results:One Reactor Operator Candidate Successfully Completed Exam & Granted License
ML20246H435
Person / Time
Site: University of Lowell
Issue date: 02/15/1989
From: Eselgroth P, Yachimiak E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20246H406 List:
References
50-223-88-06OL, 50-223-88-6OL, NUDOCS 8903200175
Download: ML20246H435 (20)


Text

{{#Wiki_filter:, - . .. ... _ q J -,-. . 3 ' { s l l l d U.S. NUCLEAE M UULATORY' COMMISSION REGION I OPERATOR LIC:.NSING EXAMINATION REPORT EXAMINATION REPORT N0.: 50-223/88-06 (OL) FACILITY DOCKET NO.: 50-223 FACILITY LICENSE NO.: R-125 , LICENSEE: University of Lowell 1 University Avenue j Lowell, Massachusetts 01854 ' FACILITY: University of Lowell Reactor EXAMINATION DATE: December 5, 1988 i EXAMINATION SITE: USNRC Region l' Offices 475 Allandale Road , King of Prussia, PA 19406 CHIEF EXAMINER: /I k Edward Yachimiak, Operifions. Engineer /Date' i ! dd /6 [[- APPROVED BY: /# / Pk"er' W. Eseigroth, Chief, PWR Section Date ' SUMMARY: Section G of a written examination was readministered to.One (1) Reactor Operator (RO) candidate.

The candidate successfully completed the examination and was granted a;1icense, i ki ,f ICI > d s v LL -_-- _ _ _ _ _ _-_ a.

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REPORT DETAILS l j TYPE OF EXAMINATION: Replacement (Retake) . i EXAMINATION RESULTS: , l R0 l l Pass / Fail I l l l I I l Written i 1/0 l l l l l l l

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I l l l l l l Overall i 1/0 l l l l CHIEF EXAMINER AT SITE: E. Yachimiak, USNRC i Attachments: 1. R0 Written Examination and Answer Key _ - _ _ _ _ _ -

-- , hrTM &l} 171C/1 ' U. S. NUCLEAR REGULATORY COMMISSION -

REACTOR OPERATOR LICENSE EXAMINATION - REGION

1 , FACILITY: Univ. of Lowell REACTOR TYPE: RESEARCH' DATE ADMINISTERED: 88/12/05 INSTRUCTIONS TO CANDIDATE: ' CANDIDATE'S NAME: MCdIGA b /O u ' O Use separate paper for the answers.

Write answers on one side only.

Staple question sheet on top of the answer-sheets.

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

The. passing j grade requires at'least 70% in each category.

Examination papers will I be picked up six (6) hours after the examination starts.

i '% OF ! CATEGORY % OF CANDIDATE'S CATEGORY ' VALUE TOTAL SCORE VALUE CATEGORY 13.00 100.0 G.

RADIATION CONTROL AND SAFETY l l 13.00 % TOTALS FINAL GRADE i All work done on this examination is my own.

I have.neither given nor received aid.

4 i i Candidate's Signature

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- - -NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS - ' During th.e 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.

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.

! 3.

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

' 4.

Print your name in the blank provided on the cover sheet of the examination.

i S.

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

6.

Use only the paper provided for answers.

7.

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

8.

Consecutively number each answer sheet, write "End of Category __." as appropriate, suart each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.

9.

Number each answer as to category and number, for example, 1.4, 6.3.

, 10. Skip at least three lines between each answer.

11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.

< 12.. Use abbreviations only if they are commonly used in facility literature.

13, The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.

14. Shra all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.

15. Partial credit may be given.

Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.

16. If parts of the examination are not clear as to intent, ask questions of the examiner only.

17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.

This must be done after the examination has been completed.

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~,-, _ .. i 18..When you complete your examination, you shall: a.

Assemble your examination as follows: .(1) Exam questions on top.

(2) Exam aids - figures, tables, etc.

(3) Answer pages including figures which are part of the answer.

.b.

Turn in your copy of the examination and all pages used to answer the-examination questions.

. c.

Turn in all scrap paper and the balance of the paper that you did not use for answering.the questions, d.

Leave the examination area, as defined by the examiner.

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

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.__ _____-_______ ___ . .- ~ , - . , QUESTION G.01 (1.00).

For EACH of the restricted areas listed below, state the radiation: levels which an'could be expected in that area: -! a.

Radiation Area ) .b.

High Radiation Area.

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- _ _ _ - _ - - _ ~ . .. . . QUESTION G.02 (1.50) An individual is 1x) perform work inoan area where the concentration of soluble Iodine-135 in air was found to be 5 X 10E-7 (micro-C1/ml).

Utilizing 10 CFR, a. HOW muet this area be posted? b. WHAT protective equipment should an individual utilize to enter such an area? c. HOW many MPCs is the above concentration? I ., l i

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. ... - .) ' . , QUESTION G.03 (0.50') WHAT is the major source'of gamma radiation in the reactor coolant during power operations? -d , . I \\ < i l

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. - - - - ' . . , QUESTION G.04 (0.50) Multiple Choice: ) During steady 1 MW operation, WHAT is the typical exposure rate ON CONTACT with the surface of the Holdup Tank? A. < 100 mr/hr B.,100 mr/hr < > 500 mr/hr C. 1000 mr/hr < > 2000 mr/hr D. > 2000 mr/hr i I i l i i . ,

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, ,, _______ _ -~_ _- - - - - _ _ - . , QUESTION G.05 (0.50) ' i Multiple Choice: During steady 1 MW operation, WHAT is'the approximate, typical exposure , rate above the reactor pool under the reactor bridge?. ) A. 1 mr/hr B. 10 mr/hr C. 20 mr/hr , D. 30 mr/hr d i l l l l-j ) i

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~ j .. .. . i < . , ' -QUESTION.

G.06 (1.50) a. WHAT is the University of Lowell ADMINISTRATIVE limic for Whole Body i dose? (0.50) b. WHAT TWO'(2) individuals need to approve exposures in~ excess of the . - above limit? (1.00) j i . a ! )

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___ __ ,,,, ', . QUESTION G.07 (1.50) fFor EACH of the area radiation' monitors listed below, specify the' TYPE of detector.used AND its approximate RANGE.

a. Tracerlab TA-61 b. Tracerlab TA-62 c. Tracerlab TA-64 s-i ! , - ! l < l l _ s' l l t (***** CATEGORY G CONTINUED ON NEXT PAGE *****) . l t I.

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- . , QUESTION G.08 (1.50) Answerveach of the following-questions regarding the reactor containment ! building constant air particulate monitors (CAMS), a. During normal reactorcoperations, WHAT is the major source of activity - ; detected by the CAMS? b. WHERE are each of the two (2): CAMS located? WHAT would be the most likely cause of a CAM high level trip alarm' c.

assuming NO releases from experimental facilities?- .

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.,.... i + . , l QUESTION G.09 (1.50)-

For EACH of the radiation types listed below, statenthe type of portable instrument.which'would be used for detection purposes, a '. Alpha b. Beta / Gamma > c. Neutron ' . \\ l i

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-.._ - _ _. ome ce .... - , . , . QUESTION.

'G.10 (1.50) - A mixed-beta-gamma point source measures 100 mr/hr at ONE (1) foot and 0.'1.tr/hr-at TEN (10)-feet.

WHAT is the dose rate at ONE (1)' foot due ONLY ) to the Beta particles? SHOW ALL WORK.

STATE ALL ASSUMPTIONS.

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' . t QUESTION G 11 (1.50) An experiment containing a source which' emits mono-energetic gamma-rays at 1 MeV requires TWO (2) centimeters of lead shieldingEto reduce the radiation dose rate at a certain distance away from the source from 500 mr/hr to 106 mr/hr.

If the thickness of the lead shielding is' DOUBLED, WHAT will the resultant dose rate be reduced to? SHOW ALL WORK.

Assume the mass attenuation coefficient for lead is 0.0684 (cm*2/gm) and-the density of lead is 11.35 (gm/cc).

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...... , , ANSWER G.01 (1.00) a. 5 - 100 mr/hr [0.50] b. > 100 mr/hr.[0.50] REFERENCE ' Radiation Safety Guide, page 23 10CFR20 ..(KA's) ANSWER G.02 (1.50) . a. CAUTION AIRBORNE RADIOACTIVITY AREA [0.50] b. full face gas mask [0.50] c. Five (5) [0.50] REFERENCE 10 CFR Part 20 FSAR section 8.3.2.3.

ANSWER G.03 (0.50) N-16 [0.50] l REFERENCE , FSAR section 8.1.3.1 ANSWER G 04 (0.50) B. [0.50] j , , REFERENCE i

FSAR section 8.1.3.1

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ANSWER G.05 (0.50) [[0.50] f3l}(2-lJok)AQ-MY Of&cd7y

d'l'O Mrenilll(z . ' tC j (***** OATEGORY G CONTINUED ON NEXT PAGE *****). _ _ - - _ _ _ - - - - - -

, .- --- _ - _ _ _ - _ _ _ _ - - - - - _ ,o . REFERENCE .FSAR section^8.1.1-2 ' s.

ANSWER G.06 (1.50) .a.

100 mr/ week [0.50] b. Radiation Safety Officer [0.50] Individual's Supervisor [0,50]

REFERENCE \\ Radiation Safety Guide, page.26 ' . ANSWER G.07 (1.50)- a.~GM Tube-[0.30] 0.01 mr/hr [0.10] to 100 mr/hr [0.10] b. GM tube [0.30] 1 mr/hr [0.10] to 10 R/hr [0.10]

c. Ion Chamber [0.30] 0.1 mr/hr-[0.10] to 10 R/hr [0,10] Give credit for RANGE values within a~ factor of ten (10).

REFERENCE FSAR section 8.1.4 ~ ANSWER G.08 (1.50) l a. Radon (222) [0.50]

b. on the third floor near the main ventilation exhaust. plenum [0.25] on the experimental floor of the reactor building [0.25] c.

fission product release Co,$o] REFERENCE FEAR section 7.4.5 ' ANSWER G.09 (1.50) a.

(Eberline-ZnS Alpha Probe)' Scintillation- ' b. GM or Ionization [3 X 0.50; c. Tracerlab " Snoopy" NP-2 t (***** CATEGORY 13 CONTINUED ON NEXT PAGE *****) ,-c h Li--.--_-_-.__:--_ ._.

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P REFERENCE j i FSAR section 8.3.2.1 l I ANSWER - G.10 (1.50) l DicR1^2 = D10 * R10^2 [0.50] At 10 feet, all radiation is from gammas.

Thus, D10 = 0.1 mr/hr [0.50] l D1 (gamma) = 10 mr/hr [0.253 D (beta) 100 mr/hr - 10 mr/hr 90 mr/hr [0.25] = = j REFERENCE Introduction to Nuclear Reactor Operations (NRO), page 2-35

ANSWER G.11 (1.50) I = Io*e"(*mu*X) [0.50] mu = (0.0684)*(11.35) = 0.776 (1/cm) [0.50] j ! I = 500*e"(-0.776*4) = 22.5 mr/hr '[0.50] I l ' REFERENCE l - Intro to NRO, page 2-23 i l ! (***** END OF CATEGORY G *****) (********** END OF EXAMINATION **********) - l l I' .

- , TEST CROSS REFERENCE Page ~1 . ..r QUESTION VALUE REFERENCE , G.01' 1.00 9000007 G.02 1.50 9000008 G.03 0.50 9000004 G.04 0.50 9000003 G.05 0.50 9000011 G.06 1.50 9000006 G.07 1.50 9000001 G.08 1.50 9000010 G.09 1.50 9000009 G.10 1.50 9000002 G.11 1.50 9000005 ______ 13.00 ______ ______ 13.00 s a f _ _. _ _ _ _ _ _ _. _ _ _ _ _ -. _ _ _ - -. -. __ }}