ML20151P729

Exam Rept 50-243/OL-88-01 on 880621-22.Exam Results: Candidate Passed Both Operating & Written Exam

ML20151P729
Person / Time
Site:	Oregon State University
Issue date:	07/22/1988
From:	Elin J, Johnston G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20151P728	List: ML20151P724 ML20151P729
References
50-243-OL-88-01, 50-243-OL-88-1, NUDOCS 8808100169
Download: ML20151P729 (79)

Text

{{#Wiki_filter:' 3 Examination Report No. 50-243/0L-88-01 Facility: Oregon State University - TRIGA Docket No. 50-243 Examinations administered at the CSU TRIGA facilities, Corvallis, Oregon. Chief Examiner:

1. 1. - y /[/s'M N

' //z e// / Gary W. Johnston, Operator Licensing Date Signed Approved: -rf - # M _ fi 7Ac/# John 0. Elin, Chief, Operations Section Date Signed Sumary: Examinations on June 21-22, 1988. Written and operating examinations were administered to one SR0 candidate. The candidate passed both the operating and written examinations. 6808100169 880725 PDR ADOCK 05000243 V PDC

h t l Report Details I i 1. Examiners:

• G. Johnston, RV M. Royack, RV, Observation
• Denotes Chief Examiner 2.

Persons attending the exit meeting: G. Johnston, RV M. Royack, RV T. Anderson, OSU B. Dodd, OSU 3. Written Examination and Facility Review: The written examination was administered as follows: 1 SR0 Exam - June 21, 1988. All sections. At the conclusion of the examination, the Chief Examiner provided instructions to the facility staff about the review process for the written examination. The staff was instructed to provide written ~ comments within five working days from the exit meeting. The examiner's resolution of these comments are documented in Attachment 1 to this l 4 report. 4. Operating Examination: l The operating examination was administered to the candidate on June 22, 1988. 5. Exit Meeting: On June 22, 1988, the Chief Examiner met with the facility representatives denoted in Paragraph 2. The examiner discussed the examination process to that point and emphasized the importance of providing timely comments on the written examination. i b i il

t ) Resolution of Facility Comments Question J-4: Facility Comment: The facility pointed out that the' calculation used the total amount I of reactivity inserted by the Transient rod, rather than the amount above beta. Resolution: The examiner will change the key to reflect only the amount above beta. Question J-5: i 3 Facility Comment: The facility pointed out that the calculation used the total amount i of reactivity inserted by the Transient rod, rather than the amount above beta. Resolution: The examiner will change the key to reflect only the amount above beta. Question K-3.b: Facility Comment: The reviewer stated that the question asks for something different a than the key supplies. The reviewer supplied the needed information i to calculate the Shut Down Margin. Resolution: The examiner will change the key to reflect the information supplied by the reviewer. Question K-6: Facility Comment: The reviewer points out that part a. is correct as far as the answer that is provided in the reference. However there is no rack at present that will hold 12 elements, and there is a significant change pending in the procedure. They have asked to delete Part a. 3 Part b. is incorrect and should be 0.8 not 0.83. a I i n

m Resolution: The examiner will delete part a. because of the conflict with the rack size. Part b. will be changed to 0.8. Question L-{; Facility Comment: The facility reviewer stated that there may be confusion because of the differences between the administrative procedure and the Technical Specifications. Specifically between the meeting frequency, and the quorum. Another concern about the actual size of the committee being 9 rather than 7 as specified in the procedure was raised. Resolution: The examiner will change part c. to accept either 9 or 7 members as the correct answer. This will meet the call of the question. Parts

a. and b. will remain as is (no change).

Question L-5: j Facility Comment: The facility reviewer rightly pointed out that 10 CFR 50.72 does not 1 1 apply to the facility, as it applies only to power reactors, i Resolution: j The examiner will delete the question. Question L-7: Facility Comment: "It is not clear that the question is asking for a numerical value. It could also be asking for a description of the limiting safety system setting such as that given in the Technical Specification definition 1.23." Resolution: l The examiner will not change the key. The reason is the question asks for the "Limiting Safety System Setting" (LSSS). Note that the wording is capitalized, this infers the specific setting as described in the Technical Specifications. The numerical value is specific to the LSSS. i -l 4

Question L-9: Facility Comment: The facility reviewer supplied four more channels of instrumentation [ that are required for operation per the Technical Specifications, i The reviewer stated that this was based on the definition in the T. t S. 1.29 definition. Resolution: The examiner notes that the question requested those channels specifically required as measuring channels. Although the others meet the T.S. definition 1.29, the examiner feels that the question is explicit in asking for the measuring channels of T.S. 3.5.2. No change will be made to the key. The facility reviewer provided other clarifying comments that did not result in requests for changes to the key. These comments were provided as a courtesy in future examination preparation. The examiner appreciates the comments and will incorporate them into the key prior to uploading the examination to the Examination Question Bank. s V 1 i 1 I 1 1 1

] l i U.S. NUCLEAR REGULATORY CO MISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: Oregon State University Reactor Type: r, w Me 11 E $ Date Administered: ' June 21.is56 / Examiner: Gary W. vonnswn Candidate: INSTRUCTIONS TO CANDIDATE Usv 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 grade requires at least 70% in each category. after the examination starts. Examination papers will be picked up six (6) hours Category % of Applicant's % of Category Value Total Score Cat. Value 21.0 21.0 H. Reactor Theory 21.0 21.0 I. Radioactive Materials Handling Disposal and Hazards 19.0 19.0 J. Specific Ope ~ rating 49M Characteristics l].0 19.0 K. Fuel Handling and Core Parameters 4 20.0 i L. Administrative Procedures, Conditions and Limitations ._1 Totals Final Grade All work done on this exam is my own. I have neither given nor recieved aid. i Candidate's Signature t i l e s u.k 'N

ES-201-1 ATTACHMENT 1 (continued) REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EX t 1. A single room shall be provided for completing the written examination ~ -........ - The location of this room and supporting restroom facilities shall-be-s as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination. should make arrangements for the use of a suitable room at a local sch motel, or "the licen. other building. Obtaining this room is the responsibility of see. 2. Minimum spacing is required to ensure examination integrity as determ 4 by the chief examiner. Minimum s with a 3-ft space between tables. pacing should be one candidate per table, No wall charts, models and/or other training materials shall be present in the examination roo,m. 3. Sultable arrangements shall be made by the facility if the candidates to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. examiner and/or proctor, These arrangements shall be reviewed by the r4. The facili_ty staff shall be provided a copy of the written examinatio answer key after the last candidate has completed and handed in his wr examination. The facility staff shall then have five working days to pro-vide formal written comments with supporting documentation on the tion and answer key to the chief examiner or to the regional office s chief. n i 5. unopened packages for each candidate's use in The examiner shall distribute these pads to the candidates. material needed to complete the examination shall be furnished by the All reference examiner. into the examination room, and no other equipment shall be allowed. 6. Only black ink or dark pencils should be used for writing answers to questions. s Examiner Standards k (

ES-201-1 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. 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. 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, start each category on a new page, write only o_n,e 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. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not. I 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 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. Examiner Standards j e.;' w M rl-M s "

• 2

='

ES-201-1

18. When you complete your examination, yo u vial ::

i Assemble your examination as follows: a. (1) Exam questions on top. (2) Exam aids - figures, tables, etc. \\ (3) Answer pages including figures which are a part of the answer. b. Turn in your copy of the examination and all pages used to answer the examination questiens, Turn in all scrap pape r and the balance of the paper that you did c. not use for answering the questions, d. Leave the examination area, as defined by the examiner. If after leaving, yo's are found in this area while the examination is still in progress, your license may be denied or revoked. = 9 1 l Examiner Standards $j. h E

ES-201-1 ATTACHMENT 1 (Continued) Requirements for Facility Review of Written Examination 1. There shall be ne review of the written examination by the facility staff before or during the administration of the examination. Following the administration of the written examination, the facility staff shall be provided a marked-up copy-of the examination and the answer key. 2. The facility will have'five (5) working days from the day of the written examination is given to provide formal comment submittal. The submittal will be made to the responsible Regional Office by the highest level of corporate management for plant operations, e.g., Vice President for Nuclear Operations. A copy of the submittal will beforwarded to the chief examiner, as appropriate. Comments not submitted within five (5) working days will be considered for inclusion in the grading process on a case by case basis by the Regional Office section leader. Should the comment submittal dead-line not be met, a long delay for finalization of the examination results may occur. '3. The following format should be adhered to for submittal of specific comments: Listing of NRC Question, answer and reference, a. b. Facility comment & Evaluation c. Supporting documentation NOTES: 1. No change to the examination will be made without submittal of complete, current, and approved reference material. 2. Comments made without a concise facility recommendation will not be addressed. I Examiner Standards ( 'k b e ee Ch E

EQUATION SHEET F = ma y=s/t Cycle efficiency = 1*(([ W = mg s = v t + } at A=AN A = A. e-At 2 o E=mc2 a = (v - v )/t A = In 2/tg = 0.693/tg r KE = } mv y, = y, 4,g (,fr) = og) 6.) 2 g g,) PE = mgh w = 6/t I=Io e4" W = vA P I=Io e'#"

6. E = 931 A m I = I.10-x/m Q = sCp AT Q = s Ah TVL = 1.3/9 4 = UAAT 4 = UA (T va - Tsnt)

HVL = 0.693/8 A Pwr = Wr s SCR = S/(1 - kg) P = P 10smo) CR, = S/(1 - ka,) P = P e /* t CR (1 - kg): = CR (1 - km)2 2 SUR = 26.06/r M = 1/(1 - kg) = CR /CRo i r = 1.44 DT M = (1 - kg)o /(1 - ka): ) SDM = (1 - kg)/km SUR = 26 r = (t*/p) + [(4 - p) /A.a p] l' = 1 x 10-s seconds r = t*/ (p - 4) Aar = 0.1 seconds'1 r = (4 - p)/Aa p In dx = 1 d2 2 p = (km-1)/km = Aka/ka I d2 = la d2 t p = (t*/rka) + [#/(1 + A.gr)) R/hr = (0.5 CE)/d2 (meters) P = E4V/(3 x 10 0) R/hr = 6 CE/d2 (reet) 1 E = Ncr WATER MISCELLANEOUS PARAMETERS CONVERSIONS 1 gal = 8.345 lbm 1 Curie = 3.7x1010 dps 1 gal,= 3.78 liters 1 kg = 2.21 lbm 1 ft8 = 7.48 gal I hp = 2.54x10 Btu /hr 3 Density = 62.4 lbm/ft 8 1 MW = 3.41x10' Btu /hr Density = 1 gm/cm3 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm 1 inch = 2.54 cm Heat of fusion = 144 Btu /lbm 1 Atm = 14.7 psi = 29.9 in. Hg.

• F = (9/5'O ) + 32
• C = 5/9 (*F - 32)

I ft. iia 0 = 0.4335 lbf/in a

L i Section H Reactor Theory i

• QUESTION H.1 MULTIPLE CHOICE (Choose the best answer.)

Which one of the following expresses the relationship between differential rod worth (DRW) and integral rod worth (IRW)? (0.75) a. DRW is the slope of the IRW curve at a given location. b. DRW it the area under the IRW curve up to a given location. I c. DRW is the square root of the IRW at a given location. d. There is no relationship between DRW and IRW. 1

• ANSWER a.

(0.75) t

• REFERENCE Volume 3, p0 18.

t l i l l l l l 1 l i 1 I d i 1

• QUESTION H.2 In a subcritical reactor, Keff is increased from.861 to.965.

What is the amoi.nt of reactivity that was added to the core? (2.0)

• ANSWER rho = Keff 1

(0.5) Keff Delta rho = Keff2 - 1 Keffi - 1 (0.75) Keff2 Keffi (0.861 - 1) (0.965 - 1) (0.5) Delta rho = 0.861 0.965 0.125 (+/- 0.005) (0.25) 0.0363 0.1614 Delta rho = = Keff2 - Keffi O.965 - 0.861 or Delta rho = ------------- = ------------- = 0.125 Keff2

• Keffi O.965
• O.861 t

Points (1.0) formulation, (0.75) use, (0.25) answer.

• REFERENCE Volume 3, pg 10.

4 t 9 (

• QUESTION H.3 MULTIPLE CHOICE (Ch - 9 the best answer.)

Assuming that shutdown occurs from equilibrium conditions. Which one of the f ollowing statements concerning the reactivity values nf ec,uilibrium (at power) xenon and peak (after shutdown) xenon is correct ? (0.75) a. Equilibrium xenon is INDEPENDENT of power level; peak xenon is INDEPENDENT of ower level. b. Equilibrium xenon is INDEPT iDENT of power level; peak xenon is DEPENDENT on power l evel. c. Equilibrium xenon is DEPENDENT on power levul; peak xenon is INDEPENDENT of power level. d. Equilibrium xenon is DEPLADENT on power level; peak xenon is DEPENDENT on power level.

• ANSWER d.

(0.75)

• REFERENCE Volume 3, pgs. 22 - 25.

= e

• QUESTION H.4 MULTIPLE CHOICE (Choose the best answer.)

What is the reason for the -1/3 DPM start up rate following a reactor cram? (0.75) a. T..v doppler effect adding positive reactivity due to the temperature decrease following a scram. b. The ability of U-235 to fission with source neutrons. c. The amount of negative reactivity added on a scram being greater than the Shutdown Margin. d. The decay constant of the longest-lived group of delayed neutrons.

• ANSWER d.

(0.75)

• REFERENCE Volume 3, pgs 30 - 31.

--y 9 -y

• QUESTION H.5 MULTIPLE CHOICE (Choose the best ower.)

With the reactor initially at a keff of 0.99, a certain reactivity change causes the count rate to double. If this same amount of reactivity is again added to the reactor, which one of the following will be the status of the reactor? (0.75) a. Prompt Critical b. Supercritical c. Critical d. Subcritical

• ANSWER b.
• REFERENCE Volume 3, pgs 14 - 50.

l j I

• OUESTION H.6 For each of the following definitions: WHAT is the term that is being defined?

a. The factor by which neutron population changes between generations (from fission). (0.5) b. The decay of an excited nucleus into a stable nucleus with the simultaneous ejection of electromagnetic energy. (0.5) c. The amount of time required for the neutron populstion to increase by a factor af "e" (2.718). (0.5) d. A gamma ray causes the ejection of an electron from a target atom; the gamma ray's energy is totally transmitted to the electron for ejection. (0.5)

• ANSWER a.

K-effective (0.5) b. Gamma becay (0.5) c. Period (Fermi Age) (0.5) d. Photoelectric Effect (0.5)

• REFERENCE Volume 3, pgs 10, 44 - 50; Glossary r

w

• QUESTION H.7 MULTIPLE CHOICE (Choose the best answer.)

Which one of the following best describes the beta decay of a nuclide? (0.75) a. The Atomic Mass # decreases by 1, and the number of protons remains constant. b. The Atomic Mass # remains the same, and the number of protons increases by 1. c. The Atomic Mass # remains the same, and the number of protons remains constant. d. The Atomic Mass # decreases by 1, and the number of protons decreases by 1.

• ANSWER b.

(0.75)

• REFERENCE Glossary

-l

• OUESTION H.8 How much reactivity (in % delta k/k) has been added to a subcritical reactor if the count rate has increased from 100 cps to 150 cps and Keff was initially 0.95 7 Show All of Your Work!

(3.0)

• ANSWER (1 Keff2) / (1-Keff1)

(0.75) cri /cr2 = (1-Keff2) / (1-0.95) (0.5) 100 /150 = 10/15 x 0.05 1-Keff2 = Keff2 = 0.967 (0.25) (Keff2-1)/keff2 - (Keff1-1)/Keffi (0.75) Change in reactivity = (Keff2 - Keff1) / Keffi x Keff2 (0.5) = = 0.967 - 0.95 / O.95 x 0.967 1.85 % delta K/K (0.25) = (No points off for carryover of errors.)

• REFERENCE Volume 3
• QUESTION H.9 Assuming the reactor is at 125 watts and on a stable sustained period of 50 seconds, how long will it take to reach 250 KW7 Show All of Your Work!

(2.0)

• ANSWER P = Po e^(t/T)

(0.75) 250 KW = 0.125 e^(t/50) (0,5) InE2OOO3 =1nte^(t/50)3 (0.5) 7.6 = t/50 t= 380 sec or 6.33 min. (0.25)

• REFERENCE Volume 3
• OUESTION H.10 Figure H-1 shows an instantaneous positive reactivity insertion into an already critical reactor co.e at time T = 0.

After a stable period is reached an instantaneous removal of this positive reactivity occurs at time T = 1. Respond to the following questions assuming that source neutrons are not significant. a. Sketch the reactor power level as a function of time on Figure H-1 for these reactivity changes. (1.0) b. Sketch the resulting reactor period as a function of time on Figure H-1 for these reactivity changes. (1.0)

• ANSWER a.

and b. on attached drawing. (2.0)

• REFERENCE Volume 3

8 9 Figure H -l l 1 j w ( I i i e tso ty Time. O l + + ^ WDO v) t-o oo g =f o ene i S/ h I, I (~3 ($ P c. Sodv i t:0 t ime-t l'

Figure l} -l a 10 e Y ~ i l t'

• H T'%

g(Prempt Lp)o.25 j(Stable fbriod)0.25 &D0

• [

'(staae suR = o) m (Promp+ Dcoe)o.2s s-l% (Prompt Dcop)0.2.5 9cte@*10.16 (%ble.ber)o.25 l s y %W \\ -(Prompt Tump) 0.25 d l tc lime t=l e

i

• QUESTION H.11 MULTIPLE CHOICE (Choose the best answer.)

Which of the following best describes the negative reactivity due to the fission product Samarium? (0.75) a. Samarium has an equilibrium value independent of power level and decreases nlowly after shutdown of the reactor, b. Samarium has an equilibrium value independent of power level and increases slowly after shutdown of the reactor. c. Samarium has an equilibrium value which increases with power level and decreases slowly after shutdown. d. Samarium has an equilibrium value which increases with power level and decreases slowly after shutdown.

• ANSWER b.

(0.75)

• REFERENCE Volume 3

o l

• QUESTION H.12 MULTIPLE CHOICE (Choose the best answer.)

Which of the following best describes the difference between a reflector and a moderator? (0.75) a. Reflectors slow down neutrons whiles moderators decrease core leakage. b. Reflectors shield against neutrons while moderators decrease core leakage. Reflectors shield against neutrons while moderators decrease c. plutonium production. d. Reflectors decrease core leakage while moderators thermalize neutrons.

• ANSWER d.

(0.75)

• REFERENCE Volume 3 1

1 t - -

e

• QUESTION H.13 When the Oregon State Triga Reactor is operating the fuel is hotter than the surrounding coolant.

a. During steady state full power operation, where is the hottest location in an individual fuel element? (1.0) b. What happens to the heat capacity of the fuel elements as reactnr power is increased from 1 watt to 1 megawatt? (1.0)

• ANSWER a.

Along the centerline of the fuel element. (1.0) b. The heat capacity of the fuel increases with temperature, which will rise with power. (1.0)

• REFERENCE Volume 3 General Atomics Manual l

1

• w w
• 0UESTION H.14 MULTIPLE CHOICE (Choose the best answer.)

Immediately after a pulse (a few milliseconds, before heat transfer becomes significant) where is the the greatest difference in temperature occurring? (0.75) a. Across the fuel from centerline to edge, b. Across the fuel / clad gap. c. Between the cladding and the bulk coolant. d. From the inner surface of the clad to the outer surface.

• ANSWER b.

(0.75)

• REFERENCE Volume 3 General Atomics Manual
• QUESTION H.15 Significant time dependent reactivity effects occur as a esult' of Xenon 135 and Samarium 149.

a. What are the removal mechanisms for Xenon 135 when the Oregon State Triga Reactor is operating? (1.0) b. What are the two principal production mechanisms for Xenon 135 when the Oregon State Triga Reactor is operating? (1.0)

• ANSWER a.

Decay and burnout. (1.0) b. Fission production and decay from lodine 135. (1.0)

• REFERENCE Volume 3 End of Section H Go on to Section I

Section I Radioactive Materials, Handling, Disposal, and Hazards

• QUESTION 1.1 A point source of gamma radiation gives an e>tposure rate of 90 mrem /hr at i meter, calculate the e>:posure rate at 3 meters?

(1.5)

• ANSWER I(1)
• R(1)^2 = I(2)
• R(2)^2 (0.75)

I(2) * (3)^2 (0.5) 90 * (1)^2 = I(2) 90 / 9 = 10 mrem /hr (0.25) I(2) =

• REFERENCE Volume 5, pg 49.

1 l

• OUESTION I.2 While you are frisking at the nand and foot monitors when exiting the Reactor Bay, the detector indicates a significant increase above the background count rate, a.

Who should you contact about the contamination? (1.0) b. What other action must you adhere to at the exit point? (0.5)

• ANSWER a.

^all Reactor Control Room (and contact Sr. Health Physicist, Radiation Specialist, or Reactor Operations staff.) (1.0) b. Stay behind red line (or in close proximity to exit point. ) (0.5)

• REFERENCE Volume 5, pgs.

9-10. 1

• QUESTION 1.3 What is the kind of detector that is utilized for each of the following radiation monitoring channels 7 a.

Old Area Radiation Monitors. (0.5) 6. New Area Radiation Monitors. (0.5) c. Continuous Area Monitor particulate channel. (0.5) d. Stack Monitor particulate channel. (0.5)

• ANSWER a.

Gei g er-Muel l er (0.5) b. Scintillator (0.5) c. Scintillator (0.5) d. Geiger-Mueller (0.5)

• REFERENCE Volume 5 9

e c- ,-g1

• QUESTION I.4 What are the quarterly limits for occupational exposure from 10 CFR 20 for each of the following?

a. The whole body; head and trunk. (0.5) b. The skin of the whole body. (0.5) c. The hands and forearms; feet and ankl es. (0.5)

• ANSWER a.

1.25 Rem (0.5) b. 7.5 Rem (0.5) c. 18.75 Rem (0.5)

• REFERENCE 10 CFR 20.101 i

l

• 0UESTION I.5 If you are in a 100 mrad / hour gamma field for 45 minutes, what is your done in mrem after 45 minutes?

(1.0)

• ANSWER QF=1 for gamma:

100(45/60)(1) = 75 mrem (1.0)

• REFERENCE 10 CFR 20 Volume 5

o

• OUESTION I.6 A radi o'.ogical hazard from two gases occurs when operating the reactor.

a. H )w is Ni trogen-16 generated in the primary coolant water? (1.0) b. How is Argon-41 generated in the primary coolant water? (1.0)

• ANSWER a.

Neutron - proton (n,p) activation of Oxygen-16. (1.0) b. Neutron absorption activation of Argon-40 in the water. (1.0)

• REFERENCE Volume 5, pg.

9. i l

• QUESTION I.7 How does 10 CFR 20 define a "High Radiation Area" ?

(1.0)

• ANSWER An area where a dose in excess 100 mrem can be received in any one hour.

(1.0)

• REFERENCE 10 CFR 20.202
• QUESTION I.8 You are at the console when an experimenter calls and notifies you a spill of radioactive material has occurred. What six emergency immediate actions are required for a spill in which there is a radiation hazard (millicurie to curie size)7 (2.0)
• ANSWER (0.5) 1.

Clear area. 2. Prevent the spread. (0.5) 3. Shield the source (if possi bl e). (0.25) 4. Close room. (0.25) 5. Call for help (notify Sr. Health Physicist). (0.25) 6. Decontaminate personnel (if needed). (0.25)

• REFERENCE E-4-1 Notice

i

• QUESTION I.9 Matching Multiple Choice What isotopes in Column A match with the principal type of radiation exposure hazard in Column B7 Column D choices may be (1.5) used more than once.

COLUMN A COLUMN B 1. Ar-41 a. Alpha 2. Tritium b. Beta i 3. N-16 c. Neutron d. Gamma

• ANSWER 1.

d (b) (0.5) 2. 6 (0.5) 3. d (0.5)

• REFERENCE Chart of the Nuclides I
• 0UESTION 1.10 For each of the following, what is the maximum whole body dose that is permitted during an emergency as specified in the Emergency Response Plan 7 a.

Rescue of personnel (lifesaving). (0.5) b. Corrective actions. (0.5) c. Providing medical treatment (First Aid). (0,5)

• ANSWER a.

75 Rem (0.5) b. 25 Rem (0.5) c. 1.25 Rem (0.5)

• REFERENCE Emergency Response Plan, Section 7.4.1 i

l i

• QUESTION 1.11 To ensure that exposure to radiation is rinimized every person working in an environment where occupational exposure can occur must learn three basic principles to reduce his/her expoco-e.

What are those three (3) BASIC PRINCIPLES 7 (1.5)

• ANSWER 1.

Time (0.5) 2. Distance (0.5) 3. Shielding (0.5)

• REFERENCE Volume 5, pg 3.
• QUESTION 1.12 Besides Beam Port #1 and Beam Port #3, what are the two (2) other areas designated as High Radiation Areas?

(1.0)

• ANSWER 1.

The reactor top. (0.5) 2. The second floor level by the bulk shield tank. (0.5)

• REFERENCE Volume 5, pg 3.

1 1 l

• OUESTION 1.13 What is the Radiation Center policy when surface contamination has been detected?

(1.0)

• ANSWER It is to be cleaned up immediately.

(1.0)

• REFERENCE Volume 5, pg 5.

e 3 I i i l i

• QUESTION I.14 The Radiation Center provides five types of personnel dosimetry devices. What are four (4) of the personnel doaimetry devices?

(2.0)

• ANSWER 1.

Film badge. 2. Neutron badge. 3. Pocket ionization chamber. 4. Finger ririg dosimeters. 5. audible radiation detectors (chirpers). (Any 4 G O.5 each)

• REFERENCE Volume 5, pas 14 - 15.

End of Section I Go on to Section J l i

i 1 Section J Specific Operating Character,9 tics

• OUERTION J.1 The thermal flux profile across a Triga fuel element while the reactor is at power varies from a peak at the periphery to a minimum at the centerline.

Why does the thermal flux preFile across a fuel element reach a minimum at the centerline of the fuel? (1.0)

• ANSWER The fuel absorbs thermal neutrons in the periphery for f i ssi on,

thus sheilding the interior. (1.0)

• REFERENCE Volume 3, pg 14 i
• QUESTION J.2 During a power escalation on the Log N channel, it takes 45 seconds to double reactor power level.

What is the stable reactor period that would cause this rate of change? (1.0) i l

• ANSWER Either P = Po e^t/T P/Po = e^t/T in 2 = t/T ; T = t/In 2 = 45/ In 2 = 64.9 sec or:

T= 1.44 DT = 64.8 set (1.0)

• REFERENCE Volume 3
• OUESTION J.3 Several factors (not necessarily all from the fuel) account for thn prompt negative reactivity coefficient of the TRIGA reactor with Flip fuel.

HOW does each of the following factors insert reactivity on a power INCREASE 7 a. Cell and inhomogenties. (1.0) b. Doppler effect. (1.0) c. Spectrum hardening (shift). (1.0)

• ANSWER As temperature rises the ZrH becomes less effective as a a.

moderator. (1.0) b. Absorption cross sections of resonance peaks broaden as temperature increases. (1.0) c. Hardening of spectrum increases neutron loss at erbium resonance peak. (1.0)

• REFERENCE General Atomics TRIGA "anual Volume 3, pgs 69 - 77

i 1

• QUESTION J.4 An estimate rf the peak power from a pulse of the Gregon State Triga Reactor in desired prior to conducting a pulse. The following parameters from the last pulse in the log book are l

provided 1800 MW Peak Power = Reactivity added ior pulse = $1.95 Reactivity to be added for new pulse = $1.55 What is the anticipated peak power from the new pulse? (2.0)

• ANSWER Since peak power varies as the square of the reactivity:

P1 P2 (1.0) (rhol ) ^2 (rho 2) ^2 1800 MW * (d.55)^2 1800 MW

• 2-40".c P2 = ------------------

---------------

(0.5) C.95)^2 3rB025-P2 = FE5e MW (+/- 10MW)(,0;'y (0.5)

• REFERENCE Volume 3, pg 85 - 89.

I

• OUESTION J.5 The energy release during a pulse in MW-sec is desired prior to a pulse. The following is provided from the log:

Energy release from prior pulse = 15 MW-sec Reactivity added during prior pulse = $1.95 Reactivity to be added for the new pulse = $1.35 What will be the energy release from the new pulse? (2.0)

• ANSWER The energy release is directly proportional to the amount of reactivity added.

P1 P2 (1.0)

---

= -----

rhol rho 2 rho 2

• P1 0 35
• 15 MW-sec (0.5)

P2 = = rhol (). 95 r T v O's (0.5) P2 = ttrr38 MW-sec (+/- 0.2 MW-sec)

• REFERENCE Volume 3, pg 86.
• OUESTION J.6 The Oregon State Triga Reactor is required to pulse from low power levels (less than 1 kilowatt.)

What is the reason for the limitation on power prior to a pulse? (1.0)

• AhSWER The result would be the potential of exceeding the temperature limits for the fuel.

(1.0)

• REFERENCE Volume 3, pg 83.

T. S. 3.5.3

• 0UESTION J.7 The Oregon State Triga Reactor is being operated in the "atttomatic" mooe at 100 Watts. Consider each of the following i

situation ONE AT A TIME. What will you, as the operator, see on the linear recorder when the following actions are taken? a. The Regulating rod "down" pushbutton is depressed. (0.5) b. The Shim rod "down" pushbutton is depressed momentarily. (1.0) c. The range switch is switched to the next higher range. (1.0)

• ANSWER a.

No change in indicated power. (0.5) b. The power will initially decrease and then return to 100 watts. (1.0) c. The linear recorder trace decreases (f rom f ull scale to less than half scale.) (1.0)

• REFERENCE Volume 3

t

• QUESTION J.8 f

The bath coef ficient describes the change in reactivity associated with a change in bath (pool) temperatur e. a. Approximately what is the average bath coef ficient for the Oregon State Triga Reactor? (0.5) 6. What effect does the bath coefficient have on prompt transients? (0.5)

• ANSWER a.

About -0.05 Cents per deg. Celsius. (0.5) j b. None, or very little. (0.5) l

• REFERENCE l

Volume 3, pg 79. \\ i 1

• QUESTION J.9 During operation at power the heat generated in the reactor has to be removed.

What is the driving force that circulates the water in the reactor core during operation at high power and transfers the heat produced in the core to the surrounding pool water? (1.0)

• ANSWER Natural convection of the water.

(1.0)

• REFERENCE Volume i i
• QUESTION J.10 The quality of the water in the reactor tank has to maintained at high purity, a.

What are the two (2) most important functions of the demineralizer in treating the reactor tank water? (1.0) b. What is the most important function of the filter in the Reactor Water System? (0.5)

• ANSWER a.

1. Maintain low electrical conductivity to lessen corrosion. 2, Reduce radioactivity in the water. b. Maintain water clarity.

• REFERENCE Volume 1, pg 113 - 116.
• DUESTION J.11 The core design of Triga type reactors, such as the Oregon State Triga Reactor, have an under-moderated configuration by controlling the ration of Hydrogen, Uranium, and water. What is the primary reason for this design feature of under-moderation?

(1.0)

• ANSWER The under-moderation helps to ensure that the moderator temperature coefficient is negative (i. e.

a density change from temperature increase is negative.) (1.0)

• REFERENCE Volume 3, pg 62.

1 l

• QUEST 10N J.12 The use of Erbium in the TRIGA-FLIP element is for two discrete purposes. What are those two (2) purposes?

(2.0)

• ANSWER 1.

Burnable poison. (1.0) 2. Enhancement of the prompt temperature coefficient. (1.0)

• REFERENCE Volume 3, pg 71.

End of Section J Go on to Section K

Section K Fuel Handling, and Core Parameters

• OUEST10N K.1 What are the TWO Technical Specification design limits'for fuel storage locations?

(2.0)

• ANSWER 1.

Keff less than O.8, (1.0) 2. Temperature less than design limits for fuel. (1,0)

• REFERENCE T.

S. 5.5 1 i i i

• OUESTION K.2 During movement of fuel a fuel element is engaged in the fuel handling tool. Why is it not advisable to coil the control cable in a circle of less than 2 feet in diameter?

(1.0)

• ANSWER Coiling the cable smaller than 2 feet will pull the inner cable enough to disengage the fuel element.

(1.0)

• REFERENCE OSTROP 11.1 v,
• OUESTION K.3 The Technical Specifications describe the method by which the SHUTDOWN MARGIN is to be calculated.

a. What is the minimum SHUTDOWN MARGIN that the Technical (0.5) Specifications allow? b. What are the three (3) factors used to calculate the SHUTDOWN MARGIN? (1.5)

• ANSWER a.

$0.57 (0.5) b. 1. Experiments in place, and most reactive non-secured experiment in its most reactive state. (0.5) 2. Most reactive rod full out. (0.5) 3. Cold, clear, core. (0.5)

• REFERENCE T.

S. 3.2 fl4b o ( jv y,i ; s ,b ' a l knav ""'" + y.j, J v a / w o A. 2 c,,e ce an. c wedrw' ' ",, tocifjr c -) . -. = _

• QUEST 10N K.4 The Technical Specifications require that fuel element inspection must be accomplished at least once r

c, What are the three types of measurements in the Technical Specifications for a "damaged" fuel element? (Don't provide the numerical measurement, just the type of measurement.) (3.0)

• ANSWER 1.

Bend. (1.0) 2. Elongation. (1.0) 3. No clad defects. (1.0)

• REFERENCE C'

~ft9( c m y )/ / p

• QUESTION K.5 There is a distinct difference between the Tri-flute on the Flip l

fuel element versus the Standard fuel element. Draw on the diagram on the following page the top view of the Tri-flute for a Flip fuel element. (1.0)

• ANSWER On fol1owing page.

(1.0)

• REFERENCE OSTROP 11.1 figure 1.

IV. ll.8A 'IOP VIEff OF THE OSTR TRIGA FUEL ELEMENT TRI-FI.,UTE SPACERS b 4 ( 8 t 4 t L STANDARD FUEL pnyp pgg Figuro K.l I t l l l ,, l t }

s.

"4 A4-

4_4, O

4 4 b IV.ll.8A 2 S TOP VIEW OF TIE OSTR-TRIGA FUEL ELEMENT TRI-FLUTE SPACElG G 4 I t f v Y e STANDARD FUEL FLIP FUEL I (I 0) Gc thur Gldes u;fk n - u-eek % vafava, i i Figure R.l I e

\\ \\

• QUESTION K.6 OSTROP 11 "Fuel Element Handling Procedures" governs the movement and storage of the fuel.

a. What is the administrative l i mi t per OSTROP 11 for the storage of the maximum number of Flip fuel elements in a fuel storage pit? (1.0) 4 b. What is the maximum K effective (Keff) for the storage of fuel elemtnts outside the reactor core? (1.0) i

• ANSWER a.

12 (1.0) 6. 0.83 (+ or - 0.05) (1.0)

• REFERENCE OSTROP 11 pg. 5a l

y i u#h C [L (). 9 7 b' }@ 4 i 1/U i i

o

• OUESTION K.7 OSTROP 11 "Fuel Element Handling Procedures" governs the movement and storage of the fuel.

What color of ink is used to log fuel movements / transfers in the consolo log? (1.0)

• ANSWER Red.

(1.0)

• REFERENCE OSTROP 11 pg. 24.

i

• OUESTION K.8 What are three (3) of the four fuel handling activities that the Reactor Supervisor can authorize 7 (3.0)
• ANSWER 1.

Movement of any fuel element out of core for experiment, and the subsequent replacement of same fuel element. 2. Any movement within the reactor facility of new or irradiated fuel elements not in the core. 3. Removal of fuel elements for maintenance, provided reactor is shut down. 4. Replacement of fuel elements removed for work in part 3 above, provided core configuration reinains the same. (ANY 3 above (1.0) each.)

• REFERENCE OSTROP 11 pg 33.

i l 6 l I

• QUESTION K.9 Who is the person responsible f or supervising all movement of f uel ?

(1.0)

• ANSWER The Reactor Supervisor.

(1.0)

• REFERENCE OSTROP 11 pg 33.

1

i i

• QUESTION K<10 From the diagram on the f ollowing page (Figure K.2), what component is associated with each of the following core positions?

a. G-17 (0,5) b. b-4 (0.5). c. A-1 (0.5) d. C-4 (0,5) l e. D-1 (0.5) f. G-2 (0.5)

• ANSWER a.

Source. (0.5) b. Instrumented Fuel Element. (0.5) c. Central Thimble. (0.5) d. Transient Rod. (0,5) e. Safety Rod. (0.5) f. Rabbit terminus. (0.5)

• REFERENCE Core Diagram, Operator Reference Data End of Section K Go on to Section L

O W /' // rd 88 g@@0 g0@0@e O O 0 ...o @g. 0 0 ,S..g...'gg 6 0@ O @8 O O @ @O @@ 8@ F,jun k.2

b Section L Administrative Procedures, Conditions and limitations J

• QUESTION L.1 There are three classifications of Reactor Experiments per OSTROP 18 "Procedure for the Use and Approval of Reactor Experiments".

What are the conditions that define each of the following classifications of Reactor Experiments? a. Class A. (0. 5) b. Class B. (0.5) c. Class C. (0.5)

• ANSWER a.

Small reactivity changes, no shielding changes, and/or limited isotope production. (0.5) b. Larger reactivity changes, external shielding, and/or larger isotope production. (0.5) c. Special setup required, irradiation of special material ' explosives, etc.), fuel element changes, incere facilities. (0.5)

• REFERENCE OSTROP 18.4 l

J k P-

mOUESTION L.2 Regarding experiments involving the reactors a. What in the reximum reactivity worth of all experiments in the reactor at one time? (0.5) 6. What is the maximum worth of a non-secured experiment? (0.5) c. What: is the maximum worth of a single experiment? (0.5)

• ANSWER a.

$3.00 (0.5) b. $1.00 (0.5) c. $2.55 (0.5)

• REFERENCE T.

S. 3.8 i l l

m

• 0UESTION L.3 An unanticipatec scram has occurred while you are at the console.

) What administrative actions are required before the reactor may be restarted? (1.0) l

• ANSWER f

Must inform the Reactor Supervisor, and cannot restart without his per mission ar d initials in the reactor logbook. (1.0)

• REFERENCE OSTROP 1.2 I

l l I l l l l l l ( { j i ( 1 l 1

n

• QUEST 10N L.4 OSTROP 6 "Administrative and Personnel Procedures".section 6.4 details the requirements for the Reactor Operations Committee (ROC).

a. What is the required meeting frequency for the ROC 7 (0.5) 6. How many mem'oers are required, per OSTROP 6, fer a quorum? (0.5)- c. How many members are on the ROL? (0.5)

• ANSWER a.

At least quarterly. (0.5) b. Four. (0.5) c. Seven. (0.5)

• REFERENCE OSTROP 6.4 I

(, hc, pf 4" 7 [P g, d tr 4 ' o cvd I ^~ (, G 9 -w, {l ac wf

e o

• QUESTION L.5 A safety limit (fuel temperature) has been e>tceeded during operation of the Oregon State Triga Reactor.

What is the reportir.g time requirement for this event per 10 CFR 50.727 (1.O)

• ANSWER 1 hour (1.0)
• REFERENCE 10 CFR 50.72 f

.t I <h '

1. g D

n u l l 4 1 [

e s

• QUESTION L.6 Technical Specification 3.7.2 "Reactor Pool Water", specifies that the reactor cannot be operated if pool water temperature exceeds a certain value, and if the pool water level is less than a certain height above the core.

a. What is the minimum height for the depth of water above the core allowed by the Technical Specifications? (0.5) b. What is the maximum pool water temperature allowed by the Technical Specifications? (O~5) c. What is the basis for the maximum pool water temperature limitation? (1.0)

• ANSWER u.

14 teet. (0.G) b. 120 deg F. (0.5) c. To ensure the aluminum reactor tank retains its integrity and is not degraded. (1.0)

• REFERENCE T.

S. 3.7.2

~ ~ - D

• QUESTION L.7 What is the Limiting Safety System Setting?

(1.0) < ANSWER The setting is 510 deg. C (950 deg. F measured in an instrumented fu?1 element). (1.0)

• REFERENCE T.

S. 2.2

0

• OUESTION L.8 Technical Specification 3.3 "Pul se Mode Operati on" specifies that a mechanical block must be in place to limit the amount of reactivity the pulse rod can insert into the core.

What is the maximum amcunt of reactivity allowed to be inserted by the pulse rod? (1.0)

• ANSWER

$2.55 (1.0)

• REFERENCE T.S.

3.3

e D

• QUESTION L.9 What are the six required measuring channels that must be operable when the Oregon State Triga Reactor is operating in the Steady State mode?

(3.0)

• ANSWER 1.

Fuel Element Temperature (0.5) 2. Linear Power Level (0.5) 3. Log Power Level (0.5) 4. Percent Power Level (0.5) 5. Period circuit (0.5) 6. Safety Power Channel (0.5)

• REFERENCE T.S.

3.5.2 ./ - ofL 'f,,,s ll ps clc s U~ l l l i

o

• OUESTION L.10 OSTROP 6 " Administrative and Personnel Procedures" describas how changes are made to facility procedures.

a. What requirements must be met for a Temporary Procedural Change? (1.0) b. Who can authorize a Temporary Procedural Change? (1.0) c. How much time does the Reactor Operations Committee have to review and approve Temporary Procedural Change? (1.0)

• ANSWER a.

1. Must not be described in the SAR. (0.5) 2. Intent of procedure may not be changed. (0.5) 6. Reactor Supervisor (or his designated alternate.) (1.0) c. 30 days. (1.0)

• REFERENCE OSTROP 6.8

- +, r

e s

• QUESTION L.11 The Reactor Status Board allows up-to-date information about the reactor to be easily seen. What are the THREE (3) specific items the board provides information about?

(1.5)

• ANSWER 1.

Location of Core Components. (0.5) 2. Contents of Experimental Facilities. (0,5) 3. Contents of Storage Facilities. (0.5)

• REFERENCE OSTROP 6.8.6 l

l l l l l ) I ( 1 1 f I I l l l i t {

• QUESTION L.12 Regarding Access Control to the Reactor Bay What persons are allowed unescorted access to the Reactor a.

Bay? (1.0) b. If you were escorting visitors what action must you take prior to entry to the Reactor Bay? (1.0)

• ANSWER a.

Authorization List A and those on Indefinite Entry List B with the proper required access codes. (1.0) b. The control room must be contacted and acknowledgement received. (1.0)

• REFERENCE OSTROP 6.7.2 End of Section L End of Examination

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