ML20151P788
| ML20151P788 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 07/20/1988 |
| From: | Elin J, Johnston G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20151P786 | List: |
| References | |
| 50-027-OL-88-01, 50-27-OL-88-1, NUDOCS 8808100188 | |
| Download: ML20151P788 (75) | |
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r Examination Report No.:50-27/0L-88-01 Facility: Washington State University - TRIGA , Docket No. 50-27 - Examinations administered at the OSU T IGA facilities, Pullman, Oregon. - Chief Examiner: Gary chn 'f6n, Dperator Licensing 7!/78 Dfit/ Signed q Approved: - AM d _ 7.M v//r , sin 0. Elin, Chief, Operations Section Date Signed Summary: Examinations on June 23,.1988. Written and operating exami'otions were adrainistered to one SRO candidate. The candidate passed both the operating and written examination. 'l I l i 1 , i 1 1 1 i i 8808100188 880725 i PDR ADOCK 05000027 V PDC l
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, B Report Details
- 1. Examiners:
*G. Johnston, RV M. Royack, RV, Observation
- Denotes Chief Examiner
- 2. Persons attending the exit meeting:
G. Johnston, RV M. Royack, RV W. Wilson, WSU J. Neidiger, WSU
- 3. Written Examination and Facility Review:
The written examination was administered as follows: 1 SRO Exam - June 23, 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 report. The facility reference material provided to the examiner had not shown any significant improvement over the last submittal for the examination conducted on October 6, 1987. The examiner has determined that future examinations may be delayed if a distinct improvement is not made to the material. The effort to write a comprehensive examination is inhibited' by the lack of specific information on various systems. The areas most in need of improvement include: the reactor protection circuitry (at present represented only with logic diagrams); the reactor console; the radiation detection instrumentation; and details of the rod control circuitry. In the future the examiners will be insistent in requesting specific information.
- 4. Operating Examination:
i5e operating examination was administered to the candidate on June 23, 1988.
)
- 5. Exit Meeting:
On June 23, 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.
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- Attachment 1 Resolution of Facility Comments Question I-13:
Facility. Comment:
"Excessive contamination levels are specifically. defined in SOP 10 rather than in the "General Decontamination Procedures." ;
Resolution: The facility reviewer appears to have read the question as asking for contamination levels. The question however, is asking what the policy is at the Nuclear Radiation Center concerning surface contamination. The answer is "Constant vigilance to prevent contamination, or to contain its spread, must be maintained by every user." The examiner would give full-credit'for the concept of' constant vigilance. No change will be made to the key. Question K-8: Facility Comment: l "The core was very recently changed and the new control rud worths I are attached." Resolution: The examiner will change the key to reflect the current control rod worths. Question L-5: Facility Comment: )
"10 CFR 50.72 applies to power reactors. Tt.e W3U reactor facility l technical specifications as well as the Emercency Plan both state a 24-hour notification requirement in the event that a safety limit is exceeded."
Resolution: The examiner will delete tha question. l l l l l l j i
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- l U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: Washington State University I Reactor Type: Triaa Modified i
Date Administered: June 23, 1988
/ GP Examiner: r,arv W. Johnston
~
Candidate: INSTRUCTIONS TO CANDIDATE Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer shet'.s. indicated 'n parentheses after the question. Points for each The passing question grade are at requires least 70% n each category. after the examination starts. Examination papers will be picked up six (6) hours Categor: % of Applicant's % of Value Total Category Score __ Cat. Value 21.0 21.0 H. Reactor Theory 21.0 21.0
- 1. Radioactive Materials Handling Disposal and Hazards 20.0 20.0 J. Specific Ope ~ rating Characteristics 19.0 19.0 ~
- K. Fuel Handling and gY Core Parameters 19.0 L. Administrative Procedures,
?$D Conditions and Limitations
_Lgt, _ Totals Final Grade % All work done on this exam is my own. I he.va neither given nor recieved aid. i
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Candidate's Sigdatura
, ~. ES-201-1 Enclosure 2 ATTACHMENT 1 (continued) Enclosure 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAM 1. A single room shall be provided for completing the written examination. The location of this room and supporting restroom facilities shall be such as to prevent during contact the duration with of the all other written facility and/or contractor personnel examination. motel, or other building.should make arrangements for the use of a the licensee. Obtaining this room is the responsibility of , t 2. Minimum by the chief spacing examiner.is required to ensure examination integrity as determined with a 3-ft space between tables. Minimum spacing should be one candidate per table No wall charts, models training materials shall be present in the examination roo,m.and/or other 3. Suitable arrangements to have lunch, coffee, or other shall be made by the facility if the candidates are refreshments. comply with Item 1 above. These arrangements shall These arrangements shall be reviewed by the j examiner and/or proctor. i 24. The facility staff shall be provided a copy of the written examination and answer key examination. after the last candidate has completed and handed in his written The facility staff shall then have five working days to pro- , vide formal written comments with supporting documentation on the examiI tion and answer key to the chief examiner or tc the regional office sectio chief. i 5. The facility licensee shall provide pads of 8-1/2 by 11 in. lined paper in l unopened packages for each candidate's use in completing the examination ' The examiner shall distribute these pads to the candidates. . material All reference examiner. needed to complete the examination shall be furnished by the ! intobethe shall examination room, and no other equipment or r allowed. 6. Only black questions. ink or dark pencils should be used for writing answers to s i l Examiner Standards O e e ,
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. , ES-201-1
, Enclosure 2 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of thic 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.
- 5. 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 " as appropriate, start each category on answer sheet, a new page, write write "End only one s of Category _ide 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 cach 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 comnionly 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.
- 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. . 1
- 17. You must sign the statement on the cover sheet that indicates that the I work is your own and you have not received or been given assistance in l comnleting the examination.
been completed. This must be done after the examination has I l 1 Examiner Standards I I t - o, .w . , ..
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. > ES-201-1 ;
Enclosure 2 !
- 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 a 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 exar.ination is still in progress, your license may be denied or revoked.
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I 1 Examiner Standards 1
. . ES-201-1 Enclosure 3 ATTACHMENT 1 (Continued)
Enclosure 3 Requirements for Facility Review of Written Examination
- 1. There shall be no 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 tha 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:
- a. Listing of NRC Question, answer and reference,
- 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.
Examiner Standards l I
I F = ma y=s/t Cycle efficiency = Ne (kout) W = mg s = vo t + j at 2 A=AN A=Ao e** E = mc2 a = (vr - vo )/t A = In 2/tg = 0.693/tg t KE = j mv 2 vt = v + at tg (eff) = ((gg)c,) (tm) PE = mgh w = 6/t I = Io e-E" W = va P I=Io e #" A E = 931A m I = I 10-x/m Q = ri1Cp AT Q=6Ah TVL = 1.3/p 4 = UAAT Q = UA (TAVG - Tsnt) HVL = 0.693/p Pwr = Wr s SCR = S/(1 - k g) P = P,10sua(t) CR, = S/(1 - k.a ) P=Po e /r t CR (1 - k g)3 = CR2 (1 - k g)2 i SUR = 20.06/r M = 1/(1 - keg) = CR t/CRo r = 1.14 DT M = (1 - k g)o /(1 - k.g)1 SUR = 26 ( SDM = (1 - k.g)/k.a r = (t*/p) + [(B - p) /A ge p) l' :::: 1 x 10-8 seconds r = P/ (p -4) A g = 0.1 seconds-1 7 = (B - p)/Aeg p It di =I 2 d2 ' p = (k.a - 1)/k g = Ak g/k.a 11 d2 = 12 dj p = (P/rkeg} + [B/(1 + A.ar)] R/hr = (0.5 CE)/d2 (meters) P = E4V/(3 x 1010) R/hr = 6 CE/d2 (reeg) 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 1ft3 = 7.48 gal I hp = 2.54x103 Btu /hr Density = 62.4 lbm/ft* 1 MW = 3.41x108 Btu /br Density = 1 gm/cm 3 1 Btu = 778 ft lbf Heat of Vaporization = 970 Btu /lbm I inch = 2.54 cm Heat of fusion = 144 Btu /lbm *F = (9/5'C ) + 32 1 Atm = 14.7 psi = 29.9 in. Hg.
*C = 5/9 (*F - 32) 1 ft. H2 O = 0.l335 lbf/in Typuetting b> s. Zepik, unirne Tg
l 1 l l Section H 1 Reactor Theory J l
- 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 is the area under the IRW curve up to a gi'ven location.
- c. DRW is the square root of the IRW at a given location.
- d. There is no relationship between DRW and IRW.
i
*fiNGWER
- e. (0.75)
- REFERENCE NEDO-10396 pg 121 - 127 1
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*Q'JESTI ON H. 2 In a subtritical reactor, Keff is increased from .861 to .965.
What is the amount 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 Keffl Delte, rho = (0.861 - 1) (0.965 - 1) (0.5) O.861 0.965 Delta rho = 0.1614 - 0.0363 = 0.125 (+/- 0.005) (0.25) Keff2 - Keff1 0.965 - 0.861 ar Delta rho = ------------- = ------------- = 0.125 Keff2
- Keffi O.965
- O.861 Points (1.0) formulation, (0.75) use, (0.25) answer.
- REFERENCE Unit 6, pg 6- 11
- QUESTION H.3 MULTIPLE CHOICE (Choose the best answer.)
Assuming that shutdown occurs from equilibrium conditions. Which one of the following statements concerning the reactivity values of equilibrium (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 power level.
- b. Equilibrium xenon is INDEPENDENT of power level; peak xenon is DEPENDENT on power level.
- c. Equilibrium xenon is DEPENDENT on power levelp peak xenon is INDEPENDENT of power level.
- d. Equilibrium xenon is DEPENDENT on power level; peak xenon is DEPENDENT on power level.
- ANSWER
- d. (0.75)
- REFERENCE NEDO-10396 pg 149 - 157 l
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- QUESTION H.4 MULTIPLE CHOICE (Choose the best answer.)
What is the reason for the -1/3 DPM start up rate following a reactor scram? (0.75)
- a. The 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 NEDO-10396 pg 149 - 157 e
l
*OUESTION H.5 MULTIPLE CHOICE (Choose the best answer.)
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 Le the statuu of the reactor? (0.75)
- a. Prompt Critical
- b. Supercritical
- c. Critical
- d. Subcritical
- ANSWER b.
- REFERENCE Unit 6 pg 6 - 18 1
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- QUESTION 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 population to increase by a factor of "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 Decay (0.5)
- c. Period (Fermi Age) (0.5)
- d. Photoelectric Effect (0.5)
- REFERENCE Glossary
)
i l i l l l l _ _ _ _ _ _ _ _ _1,
- 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 Mans # 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
o , f
- QUESTION 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 i to 150 cps and Keff was initially O.95 7 Show All of Your Work! (3.0)
- ANSWER cri /cr2 = (1-Keff2) / (1-Keffi) (0.75) 100 /150 = (1-Keff2) / (1-0.95) (0.5) 1-Keff2 = 10/15 x 0.05 Keff2 = 0.967 (0.25)
Change in reactivity = (Keff2-1)/Keff2 - (Keffi-1)/Keffi (0.75)
= (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 Unit 6 NEDO-10396 4
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*0UESTION 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)
InC2OOO3 =1n[e^(t/50)J (0,5) 7.6 = t/50 t= 380 sec or 6.33 min. (0.25)
- REFERENCE Unit 6 NEDO-10396 i
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- QUESTION H.10 Figurr H-1 shows an instantaneous positive reactivity insertion into an already critical reactor core 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)
RANSWER
- a. and b. on attached drawing. Scoring on Figure H-1 KEY.
- REFERENCE NEDO-10396 pg 149 - 156
4 5 8 Figure H -l a e Ib
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l Figure i-} - 1 1 l i i% i.o a: _d tso 1:1 Time, > (Prempt Emp)0.25
" +
J(Stable Period)0.25 Oc D0 to tso i
%(ggg ggg.- 0) a (Promp t ep)0.25 '"
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(Prompt Decp)0.2.5 h w" hh 9cteoSC)0.Y (Stableber)o25 t 3 Y P' f -(Prompt Jump) 0.25 1 8 ! N ! i - t:0 - Iime > t-l ' __...m.-_- "
I
*QUESlION H.11 l I
MULTIPLE CHOICE (Choose the best answer.) Which of the following best describes the negative reactivity due to the fission product Samarium 7 (0.75)
- a. Samarium has an equilibrium.value independent of power level and decreases slowly after uhutdown 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 NEDO-10396 pg 149 - 156, 157
I
- QUESTION H.12 MULTIPLE CHOICE (Choose the best answer.) i 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.
- c. Reflectors shield against neutrons while moderators decrease plutonium production.
- d. Reflectors decrease core leakage while moderators thermalize neutrons.
- ANSWER
- d. (0.75) i
- REFERENCE Unit 6, Glossary i
I h
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- QUESTION H.13 When the Washington 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. Immediately after a pulse ( a f ew millisecorids, before heat transfer becomes significant) where is the hottest location in an individual fuel element? (1.0)
- ANSWER
- a. Along the centerline o+ the fuel element. (1.0)
- b. Along the edge of the fuel element (just inside the surface of the element.) (1.0)
- REFERENCE liigure 6-21, Unit 2 b
4 i a - - - - - - - - . - - , . . , - , , , . . . - , , , , . ...-n -, +,-~-4 pn., ns -- - , , , , , - . . , , , . - - -
l
- QUESTION 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? (0.7S)
- a. Across the fuel from centerline to edge. l 4
- 6. Across the fuel / clad gap.
- c. Between the cladding ead the bulk coolant.
- d. From the inner surface of the clad to the outer surface.
- ANSWER
- b. (0.75)
- REFERENCE Figure 6-21, Unit 2 l a
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.._.. ,.,,, ., ,, . - . , , - ~ . . ...nn- . -- - _ - . , . , _ , , , , ,
- QUESTION H.15 Significant time dependent reactivity effects occur as a result of Xenon 135 and Samarium 149.
- a. What are the removal mechanisms for Xenon 135 when the Washington State Triga Reactor is operating? (1.0)
- b. What are the two principal production mechanisms for Xenon 135 when the Washington State Triga Reactor'is operating?
(1.0)
- ANSWER
- a. Decay and burnout. (1.0)
- b. Fission production and the decay of Iodine 135. (1.0)
- REFERENCE NEDD-10396 pg 149 - 156, 157 End of Section H Go on to Section I ,
l I i I i l l l l l _ /
Section I Radioactive Materials, I Handling, Disposal, and Hazards
*OUESTION I.1 A point source of gamma radiation gives an exposure -ate of 90 mRom/hr at 1 meter, calculate the exposure rate at 3 meters?
(1.5)
*ANEWER
\ j I(1)
- R(1)' (2)
- R(2)^2 (0.75) l 90 * (1)^2 = I(2) * (3)^2 (0.5) l I(2) = 90 / 9 l 1(2) = 10 mrem /hr (O.25) i l
- REFERENCE l Radiation Safety Guidelines pg 2 !
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*f)uESTION I.2 What are the alarm cetpoints for the Area Radiation Monitors?
i a, Reactor Bridg- (0.5)
- o. Sample Monitor (0.5)
- c. Cave Monitor (0.5)
- d. All other monitors. (0.5)
- ANSWER
- a. 200 mrem / hour (0.5)
- b. 100 mrem / hour (0.5)
- c. 50 mrem / hour (0. 6)
- d. 10 mrem / hour (0.5)
- REFERENCE SDP 17 1
I . o
- QUESTION I.3 The Argon-41 Monitor has two specific types of detectors. What are those two (2) detector types? (1.0)
- ANSWER
- 1. Proportional (v.5)
- 2. NaI(TI) (scintillation) (0.5)
- REFERENCE SDP 18
- QUESTION I.4 What are the quarterly limits for occupational expo'r e 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. (v.5)
- c. The hands and forearms; feet and ankles. (0.5)
- ANSWER
- a. 1.25 Rem (0.5)
- b. 7.5 Rem (0.5)
- c. 18.75 Rem (C 5)
*REFERENCZ l 10 CFR 20.101 d
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*0UESTION 1.5 If you are in a 100 mrad / hour gamma fie.1d for 45 minutes, what is your dose in mrem after 45 minutes? (1.O)
- ANSWER QF=1 for gamma: 100(45/60)(1) = 75 mRe,., (1.O)
- REFERENCE 10 CFR 20
l l l l
- 01 '"J.iT I ON 1.6 A radiological haz ar d from two gases occurs when operating the reactor.
- a. How is Nitrogen-16 generated in the primary cool ant water? I (1.0)
- b. How is Argon-41 generated in the primary coolant water?
(1.0)
- ANSWER 1
- a. Neutron - proton (n,p) activation of Oxygen-16. (1.0)
- b. Neutron absorption activation of Argon-40 in the water.
(1.0)
- REFERENCE Unit 4 and 5 l
1 i
)
- 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. (4.0)
- REFERENCE 10 CFR 20.202
*OUESTION I.8 What five (5) emergency immediate actions are required for a minor spill in which there is no serious radiation hazard? (2.5)
- ANSWER
- 1. Notify people in the area. (U.5)
- 2. Prevent the spread. (0.5)
- 3. Restrict access. (0.5)
- 4. Initiate cleanup. (0,5)
- 5. Monitor hands, feet and clothing after.ist). (0.5)
- REFERENCE Emergency Plan 1
l l 1 1 l l I l 1
*OUESTION 1.9 Matching Multiple Choice:
Match the isotopes in Column A with the principal type of radiation exposure hazard in Column B. Column D choices may be used more than once. (1.5) COLUMN A COLUMN B
- 1. Ar-41 a. Alpha
- 2. Tritium b. Beta
- 3. N-16 c. Neutron
- d. Gamma
- ANSWER
- 1. d (b) (0.5)
- 2. b (0.5)
- 3. d (0.5) ;
- REFERENCE Chart of the Nuclides t ___
*OUESTION I.10 For each of the following, what in the maximum whole body dose that is permitted during an emergency as specified in the Emergency Response Plan?
- a. Rescue of personnel (li f esaving) . (0.5)
Prevent serinuu damage to p .- + or personnel. (0.5) b.
- c. Planned exposure during ems.gency. (0.5)
- ANSWER
- a. 100 Rem (0.5)
- b. 25 Rem (0,5)
- c. 12 Rem (0.5)
*REi:ERENCE Tabl e 3.5 Emergency Pl an l
l l I
1 J
- QUESTION I.11 To ensure that exposure to radiation i s minimi=ed every person working in an environment when occupational exposure can occur must learn three basic principles to reduce hi s/her exposure.
What are those three (3) BASIC PRINCIPLES? (1.5)
- ANSWER
- 1. Time (0.5) 1
- 2. Distance (0.5)
- 3. Shielding (0.5)
- REFERENCE Radiation Safety Guidelines pg 2.
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- QUESTION 1.12 During a routine Health Physics survey you must note any excessive dose equivalent rates. What are the two limiting conditions for dose equivalent rates? (2.0)
- ANSWER
- 1. >5 mFem/ hour in a Radiation Area. (1.0)
- 2. >1 mRein/ hour in Unrestricted Area. (1.0)
- REFERENCE BOP 10
- QUESTION I.13 What is the Nuclear Radiation Center policy for users of the facility concerning surface contamination? (1,0)
- ANSWER "Constant vigilance to prevent con t ami n ati on , or to contain its spread, must be maintained by every user."
Concept of "Constant Vigilance" for full credit. (1.0)
- REFERENCE General Decontamination Procedures
*OUESTION I.14 When may decontamination be done on a contaminated injured person? (1.O) j l
- ANSWER l 1
Only if it will not aggravate an injury. (1.0) , {
- REFERENCE General Decontamination Procedures End of Section I Go on to Sec.ti on J
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Section J [ Specific Operating Characteristics
- QUESTION 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 minumum at the centerline.
Why does the thermal flux profile 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 fission, thus shielding the interior. (1,0)
- REFERENCE Unit 6
1 .
- l l
*OUESTION J.2 1
MULTIPLE CHOICE (Choose the best answer.) During a power escalation on the Log N channel, it takes 45 l seconds to double reactar power level. What is the stable reactor period that would cause this rate of change? (1.0)
- 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 sec (1.0)
- REFERENCE Unit 7 pg 6-26
*OUEST10N J.3 Several factors (not necessarily all from the fuel) account for the prompt negative reactivity coefficient of the TRIGA reactor with Flip fuel.
HOW does each of the following factors insert reactivity on a power INCREASE? f
- a. Cel! -d : -'h amcg en t i c ur . (1.0)
- b. Doppler effect. (1.0)
- c. Spectrum- harden i n g ( shi-f t ) . b7 <~ <~ C- 6 (1.O)
- ANSWER
.a. As temperature raises the ZrH becomes less effective as a moderator. (Concept.) (1.0)
- b. Absorption cross sectionn of resonance peaks broaden as temoerature increases. (1.O)
- c. Hardening- of - spectrum -i ncreases - neutron loss at erbium resonance-peak. (1.O)
- REFERENCE General Atomics TRIGA Manual i Unit 7 pg 6-36 CEv-d e wie di 3 cx n .vos k -
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- QUESTION J.4 l
An estimate of the peak power from a pulse of the Washington ( State Triga Reactor is desired prior to conducting a pulse. The following parameters from the last pulse in the log book are 1 provided: Peak Power = 1800 MW l Reactivity added for 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 O. 302T 1800 MW * (G'. 55 ) ^2 1800 MW
- 2,405-P2 = ------------------ = --------------- = (0.5)
Qt.95)^2 @:-8025 0,iO2f P2 = 44-38 MW (+/- 10 MW) 6C3 3 (0.5)
- REFERENCE Unit 7 pg 6-37, 6-41 ,
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- QUESTION J.5 ;
The energy release during a pulse in MW-sec is desired prior to a pulse. The following is provided from the logi i
^
Energy release from prior pulse = 15 MW-sec 1 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)
*AN5WER i
The energy release is directly proportional to the amount of reactivity added. 1 P1 P2 l
----- = ----- (1,0) !
rhol rho 2 rho 2
- P1 1.35
- 15 MW-sec P2 = ---------- = ---------------- (0.5) ;
rhol 1.95 ; P2 = 10.38 MW-sec (+/- 0.2 MW-sec) (0.5) l
- REFERENCE Figure 6-16 General Atomics Triga Manual l
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- QUESTION J.6 The Washington 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)
- ANSWER A higher power level wc.t1d have fuel temperature aiready high, a pulse would then add several hundred degrees to that. The result would be the potential o+ exceeding the temperature limits for the fuel. (1.0)
- REFERENCE T. S. 3.6.3 I
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*0UESTION J.7 The WSU TRIGA reactor is JUST critical with the source in place.
What effect would be observed if the neutron source were to be removed at this point? (1.0)
- ANSWER When the source is removed the reactor would go subtritical. (The contribution of the source neutrons at a low power level are part of the total neutron population sustaining criticality.) ti.C)
- REFERENCE WSU RO Training Manual Unit 6
- QUESTION J.8 The bath coefficient cescribes the change in reactivity associated with a change in bath (pool) temperature. What effect does the bath coefficient have on prompt transients? (1.0)
- ANSWER None, or very little. (1.0)
- REFERENCE Unit 6 I
*OUESTION 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 Unit 11 1
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- QUESTION J.10 The quality of the watar in the reactor pool has to be maintained at high purity.
What arn the two (2) most important functions nf the demineralizer in treating the reactor pool water? (2.0)
- ANSWER
- 1. Maintain low electrical conductivity to lessen c or rosi on .
(1.0)
- 2. Reduce radioactivity in the water. (1.0)
- REFERENCE T. S. Bases 3.13 i
I I
- QUESTION J.11 The core design of Triga type reactors, such as the Washington State Triqa 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 enuure that the moderator temperature coefficient is negative (i . e. a density change from temperature increase is negative.) (i.0)
- REFERENCE Unit 7 pg 6-22
- QUESTION J.12 The use of Erbium in the TRIGA-FLIP element is f or 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 FLIP SAR s
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- QUESTION J.13 If the reactor was at i MW and one central fuel element failedt
- a. What three categories of fission products would escape?
(1.5)
- b. What effect would the presence of the pool water have on the release? (0.5)
- ANSWER
- a. 1. lodine (0.5)
- 2. Halogens (Bromine) (0.5)
- 3. Noble gases (0.5)
- b. Water would trap the halogens (& slow the iodine) (0.5)
- REFERENCE WSU Flip fuel SAR, p. 42-44 End of Section J Go on to Section K
1 Section K Fuel Handling, and Core Parameters
*OUEST1ON K.1 What are the TWO Technical Specification design limits for fuel storage locations? (2.0)
- ANSWER
- 1. Keff 1ess than O.8. ( 1. O)
- 2. Temperature less than design limits for fuel. (1.0)
*REFERENCC.
T. S. 5.'
*OUESTION K.2 Wnat are the noi nimum personnel requirements to perform fuel loading ar.d unloading? (1.5)
- ANSWER A SRO must be present to supervise the movement - fuel (0.75),
and a licensed operator must be at the console c. ring the movement of f u,< 1 (0.75).
- REFERENCE SOP 7 9
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- QUESTION K.3 The Tec.ini cal Specifications describe the method by which the SHUTDOW24 MARGIN is t o b '.s calculated.
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- a. What is the minimum SHUTDOWN MARGIN that the Tecnnical Specifications allow? (0.5)
- b. What are the three (3) factors used to calculate the SHUTDOWN MARGIN 7 (1.5)
*ANSWE9
- a. $0.25 (O.5)
- b. 1. Most reactive non-secured experiment in its most reactive state. (0. 5)
- 2. Most reactive control element ful1 out. (O.5)
- 3. Cold, clean core. (0. 5)
- REFERENCE T. S. 3.2
*OUESTION K.4 What are the three types of measurements in the Technical Spec >fications for inspectichi of a 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 '
T. S. 4.* t
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- QUESTION K.5 What is the inspection interval for the fuel as required in the Technical Specifications? .(1.0)
- ANSWER
$3500.00 in pulses. (1.0)
.
- REFERENCE T. S. 4.4
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*0UESTION K.6 What is the minimum depth of water for the storage of fuel elements cutside the reactor core? (1.0)
- ANSWER 16 f eet (1.0)
- REFERENCE SOP 7 i
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- QUESTION K.7 When performing a complete reactor core unloading:
- a. Why is a scrammable control element (a shim blade or ;
transient rod) required to be withdrawn fully before unloading? (1.0)
- b. Why should the source be located in the grid box during unloading? (1.0)
- ANSWER
- a. To make available regative reactivity for insertion (CAF).
(1.0)
- b. To assure adequate countrate indication on nuclear instrumentation during unloading (CAF). (1.0)
- REFERENCE SOP 7 i
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- QUESTION K.8 What are the five (5) control elements in order of increasing worth? (Least to hi.. Test worth.) (2.5)
- ANSWER Servo #5 (0.5)
Shim #1 (0.5) Sl i m #2 (0.5) Transient rod #2 (0.5) Shim #4 (0.5)
- REF ERE.NCE WSU TRIGA Reactor Characteristics
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*DUESTION K.9 Who is the person responsible f or nupervising all movenant of fuel? (1.0)
- ANSWER A licensed Senior Reactor Operator. (1.0)
- REFERENCE SOP 7 6
0
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- QUESTION K.10 From the diagram on the f ollowing page (Figure K.1) what j component is associated with the following grid positions?
- a. A- 1 (0.5)
[ b. G-4, and D - 9 (0.5) l l c. C-4, and D - 6 (0.5)
- d. C-7 (0.5)
- e. G- 1 (0.5)
- f. D-2 (0.5)
- ANSWER
- a. No. 2 Linear power CIC (0.5)
- 6. Rabbit terminus. (0.5)
- c. Instrumented fuel element. (0.5)
- d. Wet tube. (0.5)
- e. Pulse gamma chamber. (0.5)
- f. Source. (0.5)
- REFERENCE Core Diagram l
End of Section K I Go on to Section L I t I l i
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. s I Section L Administrative Procedures, Conditions and limitations i
*OUESTION L.1 There are two claesifications of Reactor Experiments per SOP 3 "Standard Procedure f or Perf orming Experir, ents Using the Reactor". What are the conditions that define each of the following classifications of Reactor Experiments 7
- a. Non-Operational. (1.0) i
- b. Operational. (1.0)
- ANSWER
- a. Require control mainpulations to measure reactor parameters or charachteristics. (1.0)
- 6. Insertion of apparatus, device, or material. (1.0)
- REFERENCE SOP 3 .
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*OUESTION L.2 Regarding experimtents involving the reactors
- a. What is the maximum reactivity worth of all experimentu in the reactor at one time? (0.S)
- b. What is the maximum worth of a non-secured experiment? (O.S)
- c. What is the maximum worth of a single experiment? (0.5)
- ANSWER
- a. $5.00 (O.5) b, $1.00 (O.S)
- c. $2.00 (0,5)
- REFERENCE r . S. 3.10 I
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- QUESTION L.3 ,
1 An unanticipated scram has occurred. What actions are required before the reactor may be restarted? (2.0)
- ANSWER
- 1. Notify SRO immediately. (0.5)
- 2. Enter SCRAM in Comments Section of Log. (0.5)
Record SCRAM in SCRAM Record Section. (0,5) 3.
- 4. Upon completion of determination of cause, get permission from SRO to startup. (0.5)
- REFERENCE SOP 4 Appendix B.
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- QUESTION L.4 Technical Specifications 6.5.2 and 6.5.3 detail the requirements
! for the Reactor Safeguards Committee (RSC). I a. What is the required meeting frequency for the full RSC7 (0.5) {
- b. How many members are required for a nuoruin? (0.5)
- u. How many members are on the RSC7 (0.5)
- ANSWER
- a. At least semi-annually. (0.5)
- b. Chairman plus two others. (0.5)
- c. Five. (0.5)
- REFERENCE T. S. o.5.2 and 6.5.3 l
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*OUEST10N L.5 A safety limit (fuel temperature) has been exceeded during operation of the Washington State Triga Reactor.
What is the reporting time requirement fer reporting this event to the NRC per 10 CFR 50.72? (1.0)
- ANSWER 1 hour (1.0)
- REFERENCE 10 CFR 50.72 I
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*OUESTION L.6 When mcking a liquid radioactive waste release from the retc.ition l
tank, to what activity concentration (in picocuries per liter) should the effluent be diluted? . ( 1. 0 ) '
- ANSWER 20 picocuries/ liter (1.0)
- REFERENCE SOP 21 s
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- QUESTION L.7 What is the Limiting Safety System Setting? (1.0)
- ANSWER The setting in 500 deg. C (950 deg. F measured in an instrumented fuel element).
(1.0;
- REFERENCE T. S. 2.2 9
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- QUESTION L.8 What are the differences in control rod manipulations and reactor power manipulations for a steady state startup versus a startup for pulsing operations ? (2.0)
- ANSWER During a startup for pulsing the transient rod is not used :. 3 attain criticality (1.0) and power is restricted to <1 KW (300 KW).(1.0)
- REFERENCE SDP 4 l
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*OUESTION L.9 What are the three required measuring channeln that must be operable when the Washington State Triga Reactor is operating in the Steady State moc. / (3.O)
- ANSWER
- 1. Fuel Element Temperature (1.0)
- 2. Linear Power Level (1.0)
- 3. Log Power Level (1.0)
- REFERENCE T.S. Table 3.1
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*CUESTION L.10 The Technical Specifications in Sect- 00 6.8 specifies how changes are to be made to procedures.
- a. What requirements must be met for a Temporary Procedural Change? (1.0)
- b. Who can authorize a Temporary Procedural Change? (1.0) ;
*PNSWER
- a. Intent of procedure may not be changed. (1.0)
- 6. Any Senior Reactor Opeartor. (1.0)
- REFERENCE T. S. 6.8 i
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- QUESTION L.11 When performing a power calibration in accordanc.e with SOP 13:
What are the TWO (2) conditions that require a reactor power calibration to be performed? (2.0)
<
- ANSWER
( 1. A.inual survei11ance. (1.O)
- 2. Movement of fuel or changes to tha control elements. (1.O)
- REFERENCE SOP 13, Part A 4
End of Section L End of f.xamination
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