ML20246Q128
| ML20246Q128 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 08/15/1989 |
| From: | Isaksen P, Johnston G, Miller L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20246Q097 | List: |
| References | |
| 50-228-OL-89-01, 50-228-OL-89-1, NUDOCS 8909110356 | |
| Download: ML20246Q128 (65) | |
Text
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,4 Examination Report No.: 50-228/0L-89-01 g Facility: Aerotest Research and Radiography Reactor Docket No.: 50-228 l
Facility License No.: R-98 l Examinations administered at Aerotest Operations, Inc. San Ramon, California;.
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Chief Examiner: .
/ $ A/f GaiPy 9. Johnston, Date Signed Operator Licensing Examiner Accompanying Personnel: s
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P. Isaksen, Contract Examiner, EG&G-INEL Date Signed
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Approved: 'b r /((N (1. F. Miller,'dr.,/ Date Signed Chief, Operations Section Summary:
Examination on July 26 - 27, 1989 (Report No. 50-228/0L-89-01)
Written and oral examinations were administered to two Senicr Reactor Operator candidates. One SR0 candidate passed both the written and operating examinations.
One SR0 candidate failed the written examination and passed the operating examination.
8909110356 DR 890823 HDOCK 05000228 FDC _______________-____-_a
r_______ ,__ _ _ _
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REPORT DETAILS .
I
- 1. Examiners G.Johnston,RV(ChiefExaminer)
P. Isaksen, EG&G - INEL
- 2. Persons Attending the Exit Meeting G. Johnston, RV P. Isaksen, EG&G - INEL H. Simens, President and CEO I. Lamb, Reactor Supervisor
- 3. Written Examination and Facility Review
.The written examinations were administered to two SR0 candidates on July 26, 1989.
At the conclusion of the written exam, the facility staff was provided a copy of the examination and were instructed to provide written comments within five working days.
The facility provided written comments within the time restraints. The resolution of those comments are detailed in attachment I to this report.
- 4. Operating Examination The examiners administered the eperating examinations on July 27, 1989.
No specific concerns were identified relating to the examinations.
- 5. Facility Observations The examiners did inform the facility staff of two areas that require some attention. The High Radiation Area posting for the area above the radiography installation is not immediately viewable to a person climbing the stair steps. The Chief Examiner pointed out that it should face toward an individual who may be climbing the stairs.
The other item has to do with the liquid waste receiving tanks on the south side of the main building. The tanks are presently empty, and therefore do not require posting The sample valve for the tanks is a standard hose bibb with the valve handle removed, and is unmarked as to what function it provides. The Chief Examiner informed the facility staff th6t the valve should be marked clearly so as to avoid confusion as to the purpose of the valve.
- 6. Exit Meeting The Chief Examiner met with the facility representatives denoted in Paragraph 2 on July 8,1989. The Chief Examiner discussed the findings to that point and the examination process.
l U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR 'oERATOR LICENSE EXAMINATION RcGION S FACILITY: Aerotest_ggerationst_Inc.
P '-
N (% ; . REACTOR TYPE: _T _R _I_ _G A _ _ _ _ _ _ _ _ _ _ _ _ _.._ _ _ _ _ _
' " W DATE ADMINISTERED: @9f97fg6_________________
CANDIDATE:
1 INSIBUCIlgNS_IQ,CBNp1991Et i Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points f or each question are indicated in parentheses af ter the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__YBLUE_ _IQI@L ___SCnRE___ _y@LUE__ ______________C@lEGQ6Y_____________
s d t99__ _d!dh'g ___________ ________ H. REACTOR THEORY
_dht99__ _db I'9 ___________ ________
I. RADIOACTIVE MATERIALS HANDLING DISPOSAL AND HAZARDS
_29t99__ _ fg ___________ ________ J. SPECIFIC OPERATING CHARACTERISTICS s 199__ _29tgg ___________ ________
K. FUEL HANDLING AND CORE PARAMETERS ADMINISTRATIVE PROCEDURES,
_29 99__ _hhhb ___________ ________
L.
CONDITIONS AND LIMITATIONS c;7
________% TOTALS 199199__ ___________
FINAL GRADE AII work done on thi s examination is my own. I have neither given nor received aid.
Candidate's Signature j
MAS 3CTY l
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- j NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examinat4 on the f ollowing rules appl y:
- 1. Cheating on the examination means an automatic denial of your appl i cati on and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the. cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination. This must be done after you complete the examination.
- 3. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 4. Use black ink or dark pencil only to f acilitate legible reproductions.
- 5. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 6. Fill in the date on the cover sheet of the examination (i f necessary).
- 7. You may write your answers on the examination question page or on a separate sheet of paper. USE DNLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
B. If you write your answers on the examination question page and you need more space to answer a specific question, use a separate sheet of theDO NDT paper provided and insert it directly after the specific question.
WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 9. Print your name in the upper right-hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Ini ti al each page.
- 10. Bef ore you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
II. If you are using separate sheets, number each answer as to category and number (i . e. 1.04, 6.10) and skip at least 3 lines between answers to allow space f or grading.
- 12. Write "End of Category " at the end of your answers to a category.
L 13. Start each category on a new page.
( 14. Write "Lart Page" on the last answer sheet.
- 15. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transpositica error r esul ti ng in an incorrect answer. Write it out.
- 16. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page i s NDT an indication of the depth of answer required.
o 1Y. Show all calculations, methods,.or assumptions used to obtain an answer.
.18. Partial credit.may be given. Therefore, ANSWER ALL PARTS OF THE DUESTION AND DD NOT LEAVE ANY ANSWER BLANK.. ' NOTE: _ parti al credit will NOT be given on multiple . choice questions.
19.. Proportional grading will be applied. Any additional wrong inf ormation that is provided may count against you. For example, if a question is worth one point and asks for four responses, each of which is worth O.25
. points, and you give five responses, each of your responses will.be worth O.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of'
- 1.00 even though you' got the f our correct answers.
- 20. If the intent of a. Ques. tion i s uncl ear , ask questions of the ex aminer only.
21..When' turning in your examination, assembl e the compl eted examinati on wi th ex ami nati on questions, examination aids and answer sheets. In. addition, turn in'all scrap paper.
- 22. To. pass the examination, you must achieve an overall grade of D% or greater and at l east 70*/. 'i n each category.
- 23. There is a time limit of (6) hours for completion of the examination.
(or some other time if less that the f ull examination is taken. )
- 24. When you are done and have turned in your ex ami nati on , l eave the examin-ation area as defined by the examiner. If you are f ound in this area while the examination is still in progress, your license may be denied or revoked.
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' QUESTION H.01 (1.00)
MULTIPLE CHDICE
'Which-DNE of the f ollowing statements concerning Xenon-135 production
'and removal is correct?
p a...At full power, equilibrium conditi ons, about half of the Xenon is produced by Iodine decay and the other half is produced as a direct fission product.
b '. - Following a reactor trip f rom equilibrium conditicas, Xenon peaks l because delayed neutron precursors continue to decay to Xenon while neutron absorption (burnout) has ceased.
c.- ' Xenon production and removal increases linearly as power level increases; i.e., the value of 100% equilibrium Xenon is twice that of 50% equilibrium Xenon.
- d. At low power levels, Xenon decay is the major removal method.
At high power levels, burnout is the major removal method.
QUESTION H.02- (1.00)
MULTIPLE CHDICE After operating at 50% power for several days, reactor power is increased to 1 0 0*/.. Ini ti al l y, reactivity changes over the next 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will bet
- b. CONSTANT - due to the 6.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> half life of Iodine 135.
- c. POSITIVE - due to the faster burnup of Xenon at higher neutron flux levels.
- d. NEGATIVE - due to the increased production of Xenon et the higher ~ fi ssi on rate.
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~ QUESTION H.03 (1.00) lI FILL IN1THE BLANK The neutron source provides a significant number of neutrons to ____
and thereby permits controlled startups. (Note: more than one word responses per blank are required)
QUESTION- H.04 (1.00)
MULTIPLE CHOICE Which ONE of the f ollowing correctly describes the observed reactor response f or the same small addition of reactivity, one positive and one negative?
- a. The response will be faster for the nega.tive sddition at all times in core li f e.
- b. The response will be f aster fcr the negative addition at end of core li f e.
- c. The response will be faster for the positive addition at all times in core life.
- d. The response will be the same f or both the positive and negative addition at all . times in core lif e.
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! DUESTION H.05 (1.00)
Assume ,the plant is operating at 50 watts with normal system lineup. Indicate how the f ollowing changes in plant conditions would affect DNBR (increase, decrease, remain the sane). Con si der each case separately.
- 1. Pool temperature increases 20 degees during power operations.
- 2. Power is raised to 100 watts.
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" QUESTION H.06 (1.00)
! MULTIPLE:CHDICE
'Which DNE of the f ollowing f actors plays the most important role' in
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determining the-worth of a control rod?
- a. The rod speed.-
- b. >The: delayed neutron fraction.
.c.; The flux , shape.
B <d. The. reactor power.
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.3.a' DUESTION H.07 (1.00)
MULTIPLE CHDICE Which one of the f ollowing correctly completes the sentence!d ::ribin;-
zwby"The thermal flux is depressed in the center of the core when a
- fuel element is. installed in the A-ring. Because the installation of a fuel element causes the. center of the core;.....
- a. to-be highly undermoderated.
- b. to'be highly overmoderated.
- c. to act as a reflector,
- d. to increase in critical mass.
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fGUESTION- H;OB (1.00)
MULTIPLE'CHDICE
' Reactor power increases from'40 to 60 watts in 20 seconds. What is E the reactor period associated with this power increase?
- a. : 8.1' seconds -
- b. 4.93 seconds
- c. 49.3 seconds
- d. 81.1 seconds ~
QUESTION. H.09. ~( 2.00)
What are the THREE components / effects which comprise the prompt negative temperature coefficient?
QUESTION H.10 (1.00)
MULTIPLE CHDICE Which one; of the f ollowing correctly describes the Bath temperature coefficient?
- a. Whenever the reactivity and the temperature change in the same direction, the Bath coef ficient is negative.
- b. The experimentally measured Bath coef ficient has been determined to be slightly positive in the room temperature region, becoming negative at higher temperatures.
- c. The Bath coef ficient is a f unction of position in the core,
- d. Rapid transient behavior of the reactor is determ .ned by the
. magnitude'of the Bath coef ficient.
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di__BgpgTQ3_THEgRY Page B QUESTION H.11 (3.00)
The reactor is shutdown by 5% delta k/k with a countrate of 10 cps.
From the choices (1-4) below select the correct value of + or -%
delta k/k for a. and b. (Multiple choice)
- a. How much positive reacti vity woul d have to be added to double the original countrate? (1.0)
- b. How much negative reactivity would have to be inserted to reduce the countrate to 1/2 of its original value (of 10 cps)? (1.0)
- 1. 1.0
- 2. 2.5
- 3. 5.0
- 4. 10.0
- c. Why is there a difference in the values obtained in a. and b., above? (1.0)
DUESTIDN H.12 (1.00)
MULTIPLE CHOICE Which one of the f ollowing correctly describes why rod adjustments are required to maintain a steady state power level of 20 kW after a power reduction from 200 kW to 20 kW?
- a. Xenon and void coef ficient effects.
- b. Fuel temperature and del ayed neutron effects.
- c. Rod shaddowing and fuel temperature effects.
- d. Source neutrons and Xenon effects.
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L QUESTION. H.13 - ( 1 '. 00 )
p MULTIPLE' CHOICE' Which onk'of'the following correctly describes how delayed neutrons affect reactor control?
- a. Increase the fast fissions of U-23B contributing. to the prompt neutrons in the. chain reaction and results in a shorter reactor period.
- b. Increase the neutron generation lifetime which causes the reactor period to be longer.
- c. Decrease the leakage which causes the -Bef f /B ratio to be less than unity'resulting in a longer reactor period.
- d. Decrease'the average neutron energy causing a smaller fast neutron leakage probability resulting in a Beff/B ratio <1 and-a shorter-reactor period.
QUESTION H.14 (1.00)
MULTIPLE CHOICE Which one of the f ollowing statements concerning the moderating properties of Zirconium Hydride is correct?
a..The probility that a neutron will return to the fuel element bef ore being captured elsewhere is a f unction of the temperature of the hydride.
- b. The ratio of hydrogen atoms to zirconium atoms affect the moderating properties for slow neutrons.
- c. The . hydride mixture is quite ef f ective in slowing down neutrons with energies below 0.025 eV.
- d. The elevation of the hydride temperature increases the probability that a thermal r.eutron will escape the fuel-moderator el ement bef ore . being captured.
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QUESTION H.15 (1.00)
FILL IN THE BLANK' Graphite is-'a better reflector than, water because graphite has a significantly lower neutron ________________ .
QUESTION H.16 (2.00)
LThe reactor-trips from 100%' full power operation.
a.fWhat causes'the constant negative. period 10 minutes after the reactor trip? (Calculations are NOT required.) (1.0)
- b. Wnat causes the power to stabilize several hours after the reactor trip, assuming no operator action is taken? (1.0) l l
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- 1. - RADIOACTIVE MATERIALS HANDLING DISPDSAL Page 11-BND_HSZ@RDS 1
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QUESTION 1.01 (1.00)
MULTIPLE CHDICE The dose rate at 6 feet from a small (1 cubic centimeter), irradiated sample is 40 mr/hr, what would be the dose rate at 1B inches from the sample?
- a. 4.44 mr/hr
- b. 160 mr/hr
- c. 360 mr/hr
- d. 640 mr/hr QUESTION I.02 (2.00)
Match each of the equations given in Column A to its description in Column B. (Note: descriptions in Column B may be used once, more than once or not at all.)
Column A Column B
- a. lambda = In 2 / t 1. Relationship of source activity (1/2) after some decay time.
- b. DR = 6 CEn
- 2. Relationship between threshold
- c. TVL = 3.32 x HVL value limit and exposure time,
- d. A = A(o)e[exp(- lambda t)3 3. Relationship between source acti vity and measured dose rate.
- 4. Relationship between source activity and gamma energy.
- 5. Relationship between decay constant and half-life.
- 6. Relationship between layer value thicknesses for shielding.
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I. RADIOACTIVE MATERIALg_HANpkIN@_pIgPpgAL Page 12 BNp_H9]@Bpg' 4
GJESTION I.03 (1.00) .
MULTIPLE CHDICE Which one of the f ollowing statements concerning the control of access to a High Radiation Area is allowable in accordance with IOCFR20'!
- a. High Radiation Area signs must be posted only when an i ndi vi dual has made an entry into the area, and the access point will remain unlocked at all times.
- b. High Radiation Area signs must be posted at all times, and the access point must be maintained locked at all times except during periods of access,
- c. High Radiation Area signs must be posted only when an individual has made an entry into the area, and the access point must be maintained locked at all times.
- d. High Radiation Area signs must be posted at all times, and no further controls are required for the access point.
QUESTION I.04 (1.00)
MULTIPLE CHDICE In accordance with Technical Specifications for the ARRR, the Glory Hole Facility is purged with carbon dioxide gas for the purpose of:
- a. preventing the buildup of fission product gases Xe and Kr due to seepage into the glory hole.
- b. preventing the f ormation of radioactive nitrogen due to the activation of oxygen in the glory hole,
- c. preventing the f ormation of excessive amounts of radioactive argon due to activitation in the glcry hole.
- d. preventing the f ormation of an explosive atmosphere due to activation of gases in the glory hole.
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- d. ' RADIOACTIVE' MATERIALS HANDLT.NG DISPDBAL , Page 13 BND_H@l@BDS
-QUESTION I.05 (1.00)
MULTIPLE CHDICE A technician perf orming radiography receives a quarterly dose' of 19-Rems on his finger rings and a quarterly dose of 1.1 Rem on his film badge. Which of the f ollowing correctly describes reporting requirements to the NRC due to the above exposures?
- a. No report is required since both exposures are within 10CFR2O all owabl e 1i. mi ts.
- b. A report is required because the finger exposure exceeds the 10CFR2O allowable limits f or exposure to the hands and f orearms.
c.
A report is required because .the whole body exposure exceeds the 10CFR2O allowable limits f or. exposure to the whole body.
- d. A report is required because both the finger exposure and the whole body exposure exceed the 10CFR2O allowable limits.
. QUESTION I.06 (1.00)
MULTIPLE CHDICE Which one of the f ollowing phrases completes the description of the method by which the low-level liquid waste is processed when the primary storage tank is full?
The li quid waste water' i s treated, if necessary, and the water is then ____________.
- a. directed to the sanitary sewer system.
- b. routed to the water makeup system for the pool.
- c. shipped by tanker truck to the disposal site.
- d. transf erred to the temporary storage tank prior to releasing.
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I. RADIOACTIVE MATERIALS HANDLING DISPDSAL Page 14 BND_H916BDS QUESTION I.07 (1.00)
MULTIPLE CHDICE Water in the pool is swirled into a spiral by the return from tne primary cooling loop. Which of the following correctly describes the purpose of this spiralling ef f ect?
- a. It reduces the amount of Ar-41 created by activation,
- b. It delays the dissolution of fission gases Xe-131 and Kr-85 as the water passes upward through the core.
- c. It reduces the filtration requirements for the water by channeling the radioactive particulate of Co-60 and Cs-137 to the bottom of the pool.
- d. It increases the time for incuted radioactivity, primarily N-16, to reach the top of the pool.
QUESTION 1.08 (2.50)
- a. What is the definitica of a High Radiation Area as given in 10CFR20. (1.0)
- b. What are the TWO continuing high radiation areas at the ARRR Facility which are posted as High Radiation Areas. (1.5)
QUESTION I.09 (3.00)
List THREE of the f our events, including setpoints, that would be classified as a Radiological Emergency in accordance with the Emergency Plan at the ARRR.
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- .S ?C I.. RADIOACTIVE MATERIALS HANDLING DISPOSAL -Pcgs 15 BND_H8]@BDS
, QUESTION. I.10 (3.00) !
For.each of ' the portable survey instruments listed below, . identif y the type of detector used AND the type of radiation each is designed te measure..
- 1. Cutie Pie.
- 2. Pancake counter.
3.-NEMD Rem meter.
- DUESTION- - I .1'1 (1.50)
- a. What is the maximum quarterly whole body dose permitted, according to 10 CFR 20? ( 0. 5 ) -
- b. What TWD conditions must be satisfied, according to 10 CFR 20, to permit this' radiation exposure? (1.0)
-1 GUESTION I.12 (1.00)
During conditions f ollowing an accident it may be necessary to allow an exposure in excess of the maximum whole body quarterly limit. What is the ' allowable accidental exposure limits tot
- 1. Correct an emergency situation?
- 2. Save a life?
DUESTION I.13 (1.00)
FILL;JN THE BLANK Liquid special nuclear material contained in en experiment shall be limited to ___(1).___ grams and shall be ____(2) ____, according to ARRR
. Technical Specifications.
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GUES' TION ;J.01 (1.00) c.
.7- M'ULTIPLE CHDICE Which one ' of Ethe f ollowing is the approximate core -reactivity associatediwith-a period of 10 seconds?. Use the attached figures from the critical' assembly and power calibration' procedures.
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- a. $ 0.10
- b. $0.35 L c.,60.50
- d. $0.75 QUESTION- J.02' (1.00)
' MULTIPLE CHOICE Which. one of the f ollowing correctly describes' the. response to the safety-rod "DN"' light bulb burning out during reactor power operation?
- a. .The-safety rod cannot'be moved any'further in the outward L di recti on from its original position.
- b. The saf ety rod cannot be driven 'in- either direction f rom its origina1' position.
- c. The safety rod will' scram due to an interruption of power to
.the magnet coil.
- d. Th'ere is no af f ect of the bulb being burned out other than a loss of indication.
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OUE!fi 1DN J.03 (3.00)
The SCRAM ci r cui tr y provides mul ti pl e prat ett i ve f estures,.
- a. What two (2) SCRAMS are provided by Nuclear Instrumental 2 on Channel 17 (No set points required. ) (1.04
- b. What two (2) SCRAMS are provided by Nuclear inntrumentetion Channel 2? (No setpoints r equi red. ) ( .l . 6 )
- c. Besides water level, what are the two (2) other SCRAMc from
- instrumentation other than Nuclear Instrumentation? (No setpoints required.) (1.0)
ANSWER
- a. Low Count (0.5)
Fast Period (0.5)
- 6. 90% of Vol t age (O.5)
Fast Period (0.5)
- c. Earthquake (0.5)
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Water Temperature (0.5)
REFERENCE ARRR D1M, Vol 1, sec IX, Figures IX-4 and IX-5.
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J__h5Egl@lg_QBg5311N@,g@$5@glggl5119@ Pego 17 QUESTION 'J.03 (3.00) 66 F^- ==-" 0 2 t"r Ec!!e"inc c r - . m. m 2 -ivrsecondiLivii. i.uiu.in h:ther OE, me@--iico UR NO) an automatic scram is associated wi ts. . . . 21 r- _
c na di t i nn - rn-rie:7 ;;c;, ,,,, ,,y,rg;;;y,_
'a rter Irvel !~
a ._ . _ _ _
b .__. W a + = r dis.wwiv2ty nign.
c.J*z u-I t ;;; cr. chcr 21 2.
d.-Low inm+r'==-t ::di,,y w.i d . .. . o ri 3.
- e. Evarmat i nn .
4_ Chnet reactor Deriod.
QUESTION .J.04 (1.00)
MULTIPLE CHOICE The reactor primary pumps are inadvertently turned "off" during normal reactor operation. Which one of the f ollowing correctly describes the effect on cooling tower f an operation? The cooling tower fans
- a. is.also-deenergized.
- b. will operate if the water temperature in the sump is above setpoint.
- c. will only run in the manual "on" position.
- d. is prevented f rom operating without primary pump flow.
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-QUESTION J.05 (1.00)
. MULTIPLE CHDICE.
Whichfone of the f ollowing correctly states how long the reactor can be: operated without the reactor cooling system in operation. Assuma an initial pool temperature of 74 degrees-F.
- a. several seconds.
.b. several' minutes.
- c. several hours.
- d. several days.
QUESTION J.06 (1.00)
MULTIPLE CHDICE Which one of the f ollowing correctly describes how the makeup system
' is designed to prevent the. overflow of water in the reactor pool?
- a. The .f l oat switch shut's off the makeup water pump.
- b. A float valve diverts the makeup water to the East Bay.
- c. Two - float valves operate, one shuts to stop flow to the pool and one opens to divert the water to the East Bay.
- d. Two float ' valves in series will shut, once pool level -is restored to a preset value.
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- 7. __SEEg]Elg_gEg@@]}N@_CHSB991gBl@l}C@ Paga 19-L QUESTION J.07 (2.50)
Match the- events in Column A t- the correct response of the Denalect~
automatic alarm system in Column B. (Example f. 6, Note: the
. responses in Column B may be used once, more than once or not at all)
Column A Column B
- a. Unauthorized entry. 1. Automatic alarm - notification of AD personnel and Sheriff.
- b. Earthquake.
- 2. Automatic alcrm - notification of
- c. Fire. AD personnel, Sheriff and Fire Dept.
- d. Evacuation. 3. Automatic alarm - notification of AD personnel and Fire Dept.
- e. Radiation.
- 4. No automatic alarm or notification.
QUESTION J.OB (2.00)
- a. What is the purpose of the check valve on the suction of the primary cooling loop?
- b. How does the design of'the primary coolant loop prevent siphoning the pool l evel below the Technical Specification level limit, in the event of a break in the return line external to the pool?
QUESTlDN J.09 (1.00)
MULTIPLE CHDICE Which one of the f ollowing is the normal / expected delta-T across the heat exchanger if the reactor is operating at 250 kW and the pool outlet temperature is 90 degrees-F?
- a. 2.5
- b. 6. 0
- c. 9.5
- d. 13.0
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
, , ,7 ,
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i-l~ - . i
' SPECIFIC OPERATING CHARACTERISTICS- Paga 20
-2
' QUESTION J.10' ' ( 1. 50 ) -
- a. What is the setpoint" of the water temperature. alarm? ( 0. 5 ) '
- b. . What i s .the basi s/ reason .f or. the Technical Specification temperature limit? ( 1. 0 ) .
-QUESTION' :J.11 (3.00) a.f What ;..'is 'the interlock associated with the saf ety' rod? (1.0)
- b. . What is .the interlock : associated with the Shim-Reg rods? (1.0)
- c. What is . the purpose /f unction - f or the above interlocks? (1.0)
. QUESTION J.12 (2.00)
. List FOUR of the five dif f erent ventilation equipment components that are controlled by the " Emergency shut-off".
(***** END OF CATEGORY J *****)
- = - - - . _ - . _ - . _ . _ ___
P C s- m;
- n. i,..,-
JN Page 21 5:__EuE6_deNP6199_eNP_COBE_EeBSDETER@'
r
~ QUESTION :K.01 <
(1.00)
MULTIPLE CHOICE Which one of1the f ollowing correctly states the purpose. of the triangular spacer blocks on the upper ends of_the fuel el ements?
- a. They permit insertion of. wires 'into the core to obtain flux measurements.
.b. They ' minimize the weight of the f uel el ement s.
- c. They provide access for fuel handling equipment.
d.. They allow water to flow out'of the core through the top grid plate.
QUESTION K.02- (1.00)
MULTIPLE CHOICE.
' From the choices below select the ones that correctly complete the f ollowing statement regarding personnel requirements f or movement of fuel ar.d ' graphi te elements wi thin the reactor pool.
At least __(1) __
person (s) shall be present at the facility and at least __(2)__ shall be senior reactor operator licensed.
a.. One
_ b. Two
- c. Three
- d. Four
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
_-_-__2___ . _ _ _ _ - _ -__
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4
' ' s[__[ugL_egNpLINg_gNp_CQ3g_Pggggglgg) Paga-22 E
' QUESTION K.03 (1.00)
MULT3PLE CHOICE.
Which one.of the following prevents the. control rods f rom slamming into'the bottom of the guides on a reactor trip?
-a. dashpot and piston. arrangement.
b'. coil spring.
4
- c. magnet. armature fiel d.
d.7 1ength of the guides is longer .than rod travel.
QUESTION :
K.04 (1.00)
MULTIPLE CHOICE
- Which one of ' the following is the reason f or loading fuel n on-symmetri c al l y?
- a. Due to the positioning of the glory hole.
- b. To balance the control rod worths.
- c. To allow f or f uel burnup considerations.
- d. To increase the flux near the radiography beam tube.
($$4** CATEGORY K CONTINUED ON NEXT PAGE *****)
1
- - - - __--__.___.m.__ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ , , _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ , _ _ _ ___ _ _ _ ____ _____ _
Page 23 K. FUEL HANDLING AND CORE PARAMETERS QUESTION K.05 (1.00)
MULTIPLE CHOICE From the choices below select the one that correctly completes the following:
The Keff for any storage f acility filled with f uel elements shall be less than ______.
- a. 0.99
- b. 0.95
- c. 0.90
- d. O.80 QUESTION K.06 '(1.OC)
MULTIPLE CHOICE
( w c.A< 5 % h m &
The maximum number of fuel elements, allowed by TS, in each fuel storage pit located in the reactor reom floor i s:
- a. 15
- c. 19
- c. 21
- d. 20 i
(4**** CATEGORY K CONTINUED ON NEXT PAGE *****)
eym - x- -
'~
i
+ .
1 Page 24 Ei__EUEL_d3NpLJyg_3Np_Cp3g_P333Mg][33 QUESTION ~K.07 (1.00) l_
MULTIPLE CHOICE 4
Which one.of the f ollowing correctly describes. how the f uel storage j pits are required to be " secured", according to TS, except during :
actual fuel transfer operations? l
- a. Roped off. l i
- b. By posting signs.
.1 l' c. With a lock and chain.
- d. By a security guard.
-QUESTION K.OB (1.00) i MULTIPLE. CHOICE l 4
1 Which one of the f ollowing statements concerning instrumentation requirements f or ref ueling operations is correct, according to ;
Critical Assembly and Power Calibration procedures? l
- a. The daily ~ reactor checks are NOT required to be completed.
b.-Either the air OR water radiation monitors and the associated l
' chart recorder must be operational .
1
- c. ALL i' instrumentation required f or reactor operation must be operable and operating.
L d. Only Channel 4 must be operational since it is the channel that is normally used.
j p . QUESTION K.09 (1.50)
- a. What i s the maximum rate of reactivity addition f or the control (0.5) rods, allowed by TS?
- 6. What TWO design features of the control rod drive system ensures (1.0) this requi rement' i s met?
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
z_, _ .y . . _ _ _ -. _ _.
7--. .
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' Pagar 25 gi__Eggbjbyphlyg_byp_C9BE_BSB8DEIEBE-rn.:
GUESTION- 'K.10" (1.00)
-Why-is the. ideal arrangement one where the location of the. fuel.being.
added~ is between the neutron source and the detector during refueling operati ons? :
1 l
l
(***** CATEGORY K CONTINUED ON NEXT PAGE *****)
.s ,
.s
1
. :., j
- g___[ugg_g3ND(}N@_@ND_COBE_PS$3MgIgRg' Page 26 l
l I
QUESTION K.11 (3.00) q Ref erring ' to the data below and the Attachment Q-5 subcritical multiplication plot of that datas (For a, b, and c below) (Note:
a, and b are Multiple Choice) ;
TOTAL NUMBER M ' '# "
STEP OF ELEMENTS D TECTOR A DETECTOR B DETDCTOR C O O 100 ~75 50 1 30' 417 97 90 i
2 40 645 115 122 3 50 1,667 150 192 i
4 60 6,667 246 435 5 65 20,000 441 1,111~
6 66' 25,000 600 2,000' ,
l
- a. Which one of the f ollowing is the predicted f uel loading for !
criticality? (1.0) l I
i
- 1. 66
- 2. 68- ,
- 3. 70
- 4. 72 i
- b. Which detector (s) showed an "unconservative" criticality I
predi c ti on7 (1.0) l l
- 1. A
- 2. B l l
~3. C
- 4. A c-d C l C. Why does this data indicate that a procedural violation has (1.0) occurred 7
.(***** CATEGDRY K CONTINUED ON NEXT PAGE *****)
I
3 4t 's -
51-Page 27
' ': gi__ hug 6_gego61N9_eND_s06E_PSB9dEIEB@
.+
" QUESTION K'.12 (1.00)
L
= MULTIPLE CHOICE
~
The aluminum f uel element is similar to the stainless' steel f uel element except : f or.L which one of the following?.
- a. . The f uel ' length in the aluminum elements is 15 inches.
'b. >The graphite cylinders are approximately 3.4- inches long.
c.-The' stainless steel. elements, initially contain Samarium poison.
- d. The f aluminum' element end ' fittings- are not. contoured.
QUESTION K.13 (1.00)
-i.
MULTIPLE'CHDICE
.Which one of the- f ollowing is the method used to dif f erentiate between
- a. graphite' element ~and a fuel element?
- a. c Byi wei ght ; di f f erenti al .
-b. .
By the blue' color of the fuel. elements.
- c. By the difference-in shape.
- d. By the size difference.
QUESTION K.14 (2.50) a.. State FOUR of the different data items that must be recorded and documented f orf each of the f uel el ement moves, according to the (2.0)
Critical Assembly and Power Calibration procedure.
(0.5)
- b. Where' are' these records normally maintained?
m ,,
- )
(***** CATEGDRY K CONTINUED ON NEXT PAGE
V' Page 2B
. 5 __Eu!6_H3Np6]N@_@ND_CQ$5_P969MgTEB@
QUESTION K.15 (1.00)
MULTIPLE CHDICE 1 ,-
11,1 From the choices below, select the ones that correctly complete the fallowing statement.
The total time allowed by TS f or insertion of all the. control rods f ollowing' a scram ' signal shall be a maximum of __ (1) __ millisecond %
The ' actual scram time of the control rods is approximately __(2) __
- milli seconds. -
- 3. 150 b'.'300 c.=450
- d. 600 QUESTION K.16 (1.00)
MULTIPLE CHDICE Which one of the f ollowing correctly describes the minimum requirement that must be met in order to perform maintenance on more than one control rod guide sleeve, according to the Critical Assembly and Power Calibration procedure.
- a. All fuel must be removed from the reactor core,
- b. No more than 28 fuel elements may remain in the reactor core. _l
- c. Removal of 28 or more fuel elements f rom the reactor core.
- d. Only one control rod guide sleeve can be removed at a time.
(***** END OF CATEGDRY K *****)
? i
, .l 6: ' sn . . .
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Pag 2129J
, "4b ADMINISTRATIVE PROCEDURES2 _CQNp))JgNS
, AND LIMITATIONS t'
i
~
f
. QUESTION IL.01 (2.00)
.StateJthe_TWO reasons for personnel gathering in the control room in
- o
- the - event .of ' a ' fi ssion product releaseEf rom the core.
. QUESTION .L.02 (2.50)
Indicate the MINIMUM. license level required to be'present'at the 1f acility-l (RD, SRD, BOTH.RD and SRD, or NONE)'for EACH of the
..f ollowing situations, according to ARRR Operating procedures.
Consider each' case separately.
~
A
- a. DuringLinitial_'startup and' approach to power.
- b. During ' normal. operation.
Jc. During: operation past normal . working hours to accommodate a
-customer ^ waiting for their parts.
d.,During recovery from an unplanned shutdown.
'e. During significant power reductions.
- QUESTION: L 03 (1.00)
N i MULTIPLE CHDICE Which one of' the f ollowing actions is required by ARRR Operating procedures,.if after the Safety rod is withdrawn to its f ull out position there. is NOT a significant increase 1in countrate, during
~
l a' reactor startup?
l t,
- a. Insert the Safety rod and initiate corrective action.
- b. Adjust the Shim and Reg. rods to obtain the desired power level ..
1 1
- c. Adjust the output of the Log Count Rate Meter and continue the startup.
- d. Dbtain permission _ f rom the Reactor Super vi sor to continue the startup and make a log entry to that effect.
(***** CATEGDRY L CONTINUED ON NEXT PAGE *****) i b -______________________b
L.' ADMINISTRATIVE'PROCEDURESg_CQNp1T1QNg Pogo 30 tj ANp_(JMilAllgNg l
b -QUESTION L.04- (1.00)
MULTIPLE CHDICE
-Which one of the f ollowing listed personnel is required by the-General Emergency. Procedures to authorize a re-entry of the ARRR Facility f or the initial inspection of the area f ollowing an evacuation 7
- a. The SRO in charge,
- b. The Reactor Supervisor..
- c. The Radiological Safety Officer.
- d. The NRC..
-QUESTION L.05. (1.00)
MULTIPLE CHDICE Which one of the f ollowing . listed personnel is required by the-General. Emergency' Procedures to inform the San Ramon Fire Department in the event of-a fire that cannot be controlled by the fire fighting equipment within the facility?
- a. The SRO in charge.
- b. The Reactor Supervisor.
- c. The Radiological Safety Officer, d.- The' person discover ing the fire.
QUESTION L.06 (2.00)
- a. Who (by job position / title) makes the determination to evacuate the reactor building in the event the fire al arm i s sounded, according to General Emergency procedures?
- b. Where are personnel normally directed to evacuate to?
(***** CATEGORY L CONTINUED DN NEXT PAGE *****)
y
- Vl
, .A .-
+
ADMINISTRATIVE PROCEDURES z _CgNp]IlgNS Page 31
-(.
p ANg_ LIMITATIONS E
p QUESTION: L.07' (1.00)
MULTIPLE-CHOICE Which one of the f ollowing is the primary purpose of the ARRR Security system?
a..To prevent sabotage,
- b. To prevent inadvertent facility operation.
c.-To prevent' unauthorized radiation exposures.
i d.1To prevent theft of special nuclear material.
' QUESTION L.OB (2.50)
FILL IN THE BLANKS According to ARRR Administrative procedures, temporary c:nanges to procedures may be authorized by a ___ (1) ___ and ___(2) ___, provided
.that the changes are in compliance with TS 12.2.2. Such changes shall be documented on a ___(3) ___. Temporary changes become void after (4) ___ days unless submitted to the ___(5) ___ for approval as permanent' changes. (Note blanks may require more than one' word responses)
QUESTION L.09 (1.50)
FILL IN THE BLANKS According to-ARRP Operating procedures, a minimum of ___ (1) ___ nuclear.
safety channel (m is/are to be on line at all reactor power levels.
The console key i all be ___(2) ___
whenever the console is unattended by.___(3) ___. (Note blanks may require more than one word responses)
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
_________ _ - _- -__- - ___ _ _ _ Q
- c ..
ik. ADMINISTRATIVE PROCEDURES g _CgNp}ll@NS Page 32 ONp_LIMil@llgNSL QUESTION- 'L.10 (1.00)
. MULTIPLE CHOICE-
!' Which one of the f ollowing statements correctly describes the method used to ensure 'the operability of the._ Denalect Alarm System 7 a.~ The system is tested weekly..
- b. TheLsystem self-check monitors. operability..
- c. The system status: lights are energized.
'd. The system 'f ailure status . lights are ' not energized.
! ' QUESTION L.11 '(1.50)
Match the surveillance in Column A' to the allowable deviation' time (grace) periods f or compl eti on in Column B, according to'ARRR Maintenance procedures. (Notes. choices in Column B may'be.used once,
'more than once or'not at all.)
Column A Column B
- a. Quarterly 1. I day
- b. Semi iAnnual 2. 1 week c.EAnnual 3. 1 month
- 4. 3 months
(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
_ - _ _ -. . _ _ - _ _ =
Page 33 bL g_ ADMINISTRATIVE PROCEDURES2_CgNp]TJgNS ANp_LJMJIATJQNS
' QUESTION' L.12 (2.00)
MULTIPLE CHOICE Which one of the f ollowing emergency descriptions is associated with at Class I emergency? (1.0) a.
(1.0)
- b. . Class III emergency?
- 1. Of a localized nature requiring no evacuation, outside assistance or significant distruption of normal operation.
- 2. Of a s localized nature requiring no evacuation, or outside assistance but distrupts normal operation.
- 3. Of such magnitude and extent to require evacuation of the reactor building, the assistance of the San Ramon Fire Dept., and be a possible threat to. facilities in the immediate vicinity.
- 4. Of such magnitude and extent that other facilities and areas are af f ected and major emergency procedures are involved.
Control of the situation requiresLiu11 activation of the San Ramon Fire Dept. and area wide emergency units.
QUESTION L.13 (1.00)
FIuL IN THE BLANKS The individual explosive devices shall be li mi ted to ___ (1) ___ grains equivalent TNT encased in metallic sheathing, and the maximum quantity of explosive material allowed at one ti me is li mited to ___(2) ___
pounds equivalent TNT, according to ARRR TS.
1
(***** END OF CATEGORY L *****)
(********** END OF EXAMINATION **********)
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l . l nl: n r. .... O.;: en un g.:..h U""l!k: n. up . e:. : il- lh"i nNun .:n :; " - l e" :. . .. im up- .... t h-
. . :..l. l , :n: .' .l;l m n m .
r.:! .lpl !!! :n. 81.! . !. :.ll! !. .g t. i.<hn. n. n.l.H! n.. n. .. h. u u. n l
. . h.!!. ! ,, . . i. h. l. j h. n .
30 un .!!. :.). j1u
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si" r.. d .3 ci in ti.i l. an l p. . -
..! h.. . .p n n. . .p. . ,..:.
-t. a y "I u . . . - .o .
m :.. .:.= m ;. .
.!.::To
- n nn I"JiT% di nn :n.
nu tph - un y: . n. n. t u p- nn n "; .-
^
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~
11l1m[ nr " i e2 0 :,,, a,: n;; ;n, ,,q y; i:.. un ip. h: .";H.. ::n ;;p: n. ,..
!:!n: a: ' :: 1:. .!:t ...! '
- !L: !.n :... ....
' l:; . ! li
. .a . . ....
.. p-tr*
. . . - M:
..- . . . .. p.. . . . .
>".r
.,t.
... u. . n.:. p. . p. a. i. n - .n" n..r ..
.g pi. n. .. m.. . p. . .
- r. H.
i nc .: n. i .: . m _ ,F_ _ ;:;_ t
.f O h' n t sp;::n.[ ;g .n !ju n. ln en n n:. n o g .n -
- .:: ::p: . . i. :::;. : ::.
F u ur! .:t !. :::. l... --ut.- .n h.. .h: h '. .'. :n! h. nn .- . m ...---- m ...."- y p' ". .;. v n~:- - tri- m -
- ~r :-- r - --- - --
m t -- Hij l;i!i. i!"r d' :n lui Ha ~" " w Ji n:. l .
'0 : - . Jn ** - :
0 50 po 15e zoo 250 Joe 150 af o o M c geo sso goo s5o yob l PO SI TION I N O I C. AT O R
reo t cr 5
~
~ DATA SHEET _
~ REACTOR TEORY FORNUULS:
P=Poet/T P = Po10SLR(t) P. = I f {th V 3.12 x 1010 fissions /see
.kff p = _L, T
+ 1 + AT-T = _! *.-
p T = bff - p Ap Ap = inKK(initial (final) f p = K-1_ K
. SLR = 26.06 T
Keff = c Pr p Pth fr 2 2
-(s Lth )
3 1 + (B 2 Lth2 j 2 Pr = e-(g2 L7 ) , p=eE_N_,)[leff) IIs c1 (1- Keffi) = C2 (1 - Keff2) a= 1 TR = Cc (,(final) initial f l oy = 1 Af + 1 ap - a2 ( Ef2 + Eq) At At f At p At . , e h
- - ^ - - - - - - . . _ . _ _ _ _ _ _ _ _
Page 2 Cf 5
' gTASHEET
_ l g wooovNnNics Ae rturr>comwres roma.As. _ , 6=A&h . 6=2:LATIn R /R - + In RyR2 1 + 2 1 l 6=tR(AT) . K'
~ K K2 6 = ACp(AT} ,
6out-6==6A*R4 n = $1n 41n . n = (h n - hout) REAL , (hin - hout) IDEAL
~
np = WAcnmL W SLPPLIED P1Vi =PV' 22 T1 T2
#1AVI I * #2 AV 22 m = PAV
\
$ = KA / A Px p iNC = KAQ3/g
= KA AT & = KA Ap &
ATs = AT (IN) - AT (M) Ira ( AT 'AT(OLT (IN1 ) ) C* I ffth 8.8 x 1(# Gr2 TCL - Tp3 = Y i = MATT Ax 6=AATtotal _ AXA + AXB +'AXN I % % N
{} . - . -
' Pope 3 cf 5 DATA SEET
- p. .RIFUGAL PWF LAW 5s 1 (Speedi )2 Head1 . (Speedi )3 Powert Speed 1 Floel . -
=
= -- .
.. (Speed2)2 Head 2 ISpeed)3 2 Power 2 Speed 2 FLn'2 RADIATION AM) DOGSTRY FORKLAS:
Ix = Io se R 41r = [d m CVI1=CV22 t 1/2 = 0.dP3_ A C = Co e-Ct A = IN G = _ Dilution Rate Volume A = Age-1t I = Io( n. Density of water (20*C) = 62.4 lba/ft3 = Ig/cm3 1 gm/cm3 = 62.4 lbs/ft3 1 gal = 8.345 lba 23 Avogredo's Number = 6.023 x 10 1 ft? = 7.48 gal O 1 gal = 3.78 liters Heat of Vapor (H2 ))= 970 Btu /lba 1 lbe = 454 grams Heat of Fusion (IT = 144 8tu/lbe 1 M = 1.66 x 10-24 grams - e = 2.72 Mass of Neutron - 1.nna m M y = 3.1415 Mass of Proton = 1.007277 M 1 KW = 738 ft-lbf/sec Mass of Electron = .000549 M 1 KW = 3413 Stwtr One atmosphere = 14.7 psia = 29.92 in. Hg. abs. 1 HP = 550 ft-lbf/sec
*F = 9/5'C + 32 1 HP = .746 KW *R = 'F +.460 1 HP = 2545 StuAr *C = 5/7 (*F-32)
I BTU = 778 ft-lbf 1 EV = 1.54 x 10-16 BTU 'K = 'C + 273 h = 4.13 x 10-21 M-sec ge = 32.2 lba - ft_e IW = 3.12 x 1010 fissions /sec Ibf - sec C2 = 931 g y/AMJ 1 CAL./ TRAM = 1.8 8tu/lba C = 3 x 105 m/sec 1 in. = 2.54 CM e = 0.1714 x 10-8 Stu ._ hr fte 'R9 I
i [ 1. g ,g y ORTA SET AVENE TE*J?i COWUCTIVITY (K) BTUAr-ft *F Meterial - 0.025 Cork 0.028 1 Fiber Inrlatin0 Soard _ 0.0P6 Maple or Dek Wood . ~ 0.4 Building Brick 0.45 Window Glass 0.79 Evdete 25.00 1 Parcont Carbon Steel 35.00 1 Percent Chrone Steel- 118.00 Aluminum 223.00 Copper 235.03 Silver 0.392 Water (20 psia, 200*F) 0.046 Steam (1000 psia, 550*F) 1.15 Uranium Dioxide 0.135 Helium 10.0 Zircaloy MIP t# emf Iff0RPRTION:
. E = ac2 E = 1/2 mv2 PE = a@
Vr = yo + at AE = 931 he, AREA MM LitJure;,lMIC GECT A = 1/2 bh ////////////////// TRIANGLE A' = S2 ////////////////// W ARE A=LxW ////////////////// RECTANGLE A = sr2 ////////////////// CIRCLE A = 2(LxW + LxH + WO V=Lxwxh RECTANGULAR SOLID Y = rr2h
^
RIQiT Cigia AR CYLItE R A = (2 rr2)h + 2(wr2) A = 4 tr2 V = 4/5 rr3 SPERE 3 anE ///////////////////////i V = S 4
rage 5 ct 9
's :
- DLT4 MEET
' M1*N"WF IWORN4TkON QWTINLED:
10 u n 2D W 41x 5 Gemma Table I TabJe II - Energy Col I 0o1 II Col I Col 11 EV per Air Water Air Water
. Disintegration ucAni ucAmt uc/n1 uc/al Material Half-Life 1.3 Sub 2x10-6 4x104' Ar-41 1.83 h 5 3x10-7 1x10-3 1x104 5x10-5 0o-40 5.27 y 2.5
- 5 9x10-9 6x10-5 1x10-10 3x10-7 1-131 8.04 d 0.36 Sub 1x10-5 ---- 3x10-7 --- -
Kr-85 10.72 y 0.0L 0.5p S 9x10-7 4x10-3 3x10-8 1x104 N145 2.52 h 2x10-12 1x10-4 6x10-14 5x104 Pu-23P 2.41x104y O.G3B S S 1x10-9 1x10-5 3x10-11 3x10-7 29 y Sr-90 Stb 4x10-6 1x10-7 ----- 0.25 Me-135 9.0P h Any sin 0le radionuclides with T 1 /lp 2 hr 9x10-5 1x10-10 3x104 which does not decay by a or spontaneous 3x10-9 fission NeJtrans per cm2 Average flux to deliver Wron Energy (EV) 100 mram in 40 hours stuivalent to 1 ran 60 Thermal 970 x 106 400 x 106 280 (ElmtDNS) O.02 '"
==2 185 #*18! 19 LIEAR 4BSORPTION 00EFFICIENTS w (m-1)
Enerny (EV) Water C.wete Iron Lead 0.21 0.63 1.7 0.5 0.GPO 0.44 0.77 1.0 0.067 0.15 0.057 0.13 0.40 0.57 1.5 0.33 0.51 2.0 0.048 0.11 0.042 0.GP7 0.31 0.4P 2.5 0.30 0.47 3.0 0.038 0.088
q-_ - - _ - -
+
Pega 34 h__BE@Cl@$_lHEg5y ("T,"} P.{Y}
;. J L 3 ud I ANSWER H.01 (1.00) d.
REFERENCE ARRR, Operator Training Manual (OTM), Vol 4, pp 1-25 to 1-29. ANSWER H.02 (1.00) C. REFERENCE ARRR DTM, Vol 4, pp 1-25 to 1-29. ANSWER H.03 (1.00)
"give accurate instrument readings" A _ _ f - [= 7m.
-i p e6 6 ' -- M
- -- -- 1 --
REFERENCE
-ARRR DTM, Vol 4, p 1-17) $ @ S = =g W, 4W-IR 3, p HH ,
ANSWER H.04 (1.00)
._ W n CM i- f !-h , - ;:. : _ w n s+/-s "u =' .^ *'=}
REFERENCE ARRR DTM, Vol 4, pp 1-14 through 1-17. ANSWER H.05 (1.00)
- 1. DNBR decreases.
- 2. DNBR decreases. [0.5 each3 mr=S1 &&}Y
(***** CATEGORY H CONTINUED ON NEXT PAGE *****)
f"'. _y
< s-},-
t c
% __BE6CIQB_lHEggy Paga 35
, -.z-j
' REFERENCE ARRR DTM, Vol 4, pp 1-28 to 2-30. ;
GP HTFF,.pp 243-259.
. 1 ANSWER H.06 (1.00) l 1 c.
l REFERENCE l l ARRR DTM, Vol'4, Sec. 1.1.13. ANSWER H.07 (1.00) j a'. REFERENCE .
.)
i AGNIR Reactor Physics Tests, Sec VI.C. ;
.j ANSWER'. H.08. (1.00)
- c. ( T=t / Ln(n /n ) = 20 sec / Lo(60/40) = 49.3 seconds.)
1 O i i REFERENCE ARRR:DTM,-Vol 4, Sec. 1.2.5. , 1 ANSWER H.09 (2.00)
' 1.. Cell "(and inhomogeneities) l
- l. 2. Doppler !
L 3. . Leakage t0.66 each3 .; REFERENCE : 1 ARRR DTM Vol 4, p 1-22. I i I (***** CATEGDRY H CONTINUED ON NEXT PAGE *****) i
= . _ - _ . . _ - _ . _ _ _ _ _ _ _ - _ _ _ _ - - - _ - - _ - _ _ _ _ - _ _ _ _ _ _ _ - - _ - _ _ _ - _ - _ - - _ - - _ - _ - _ _ _
',Q'
? . th__BEACI98 IHEggy Pcgs 36 T ANSWER H.10 (1.00) b. REFERENCE ~
'ARRR OTM, Vol'4, pp 1-24,-25.
ANSWER H.11 '(3.00)
-a.
2 b . f) II.O each3
- c. The closer.to (f urther away f rom) criticality .the smaller - (larger) increment of reactivity is required to increase (decrease) the multiplication a~given amount, also acceptable to explain that the relationship is an exponential f unction. E1.03 REFERENCE ARRR OTM, Vol 4, p 1-17; test #7 question 17.
ANSWER' H.12 (1.00)
'b.
REFERENCE ARRR OTM, Vol 4, Sections 1.2 and 1.33 Univer. of Maryland OP-104, p 3. ANSWER H.13 (1.00) b. REFERENCE ARRR DTM, Vol 4, Sec 1.2.5 and Appendix A. (***** CATEGORY H CONTINUED ON NEXT PAGE *****)
o . , ,
- 44 .
'6__B5eCI95_IBEgBy Page 37~
ANSWER '. H .14 ' -( 1. 00 ) d. REFERENCE
- ARRR-DTM, Vol'4, Sec.1.3.2.
JANSWER H.15- (1.00) absorbtion crossection. (deff cf
- 4 M S I
'#- +h A = 6c.+
- REFERENCE'
'ARRR OTM, Vol 3, Sec RT-5.11.c.
ANSWER. H.16 ( 2. 00 ) '-
- a. The decay. of' the longest' lived delayed neutron precursor.(Br-87)
- b. Subtri t' ital mul tipli cation; (of source neutrons).
REFERENCE ARRR'OTM,.Vol 4, Sec 1.2.5 and 1.2.7. t 1 (***** END OF CATEGORY H *****)
1 RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 3B 1. BND_b@l@BDS ANSWER 1.01 (1.00)
-d.
REFERENCE ARRR Reactor Operation Training Manual (DTM), Vol 5, Sec. 9.3. ANSWER I.02 (2.00)
- a. 5
- b. 3
- c. 6
- d. 1 00.5 each3 REFERENCE ARRR DTM, Vol 5, Secs. 10.2 through 10.5.
ANSWER I.03 (1.00) b. REFERENCE 10CFR20.203(c.) ANSWER I.04 (1.00) C. REFERENCE ARRR DTM, Vol .1, Technical Specifications, Sec. B.3.2 ANSWER I.05 (1.00) b. (***** CATEGORY I CONTINUED DN NEXT PAGE *****)
?I. RADIOACTIVE MATERIALS HANDLING:DISPDSAL Page-39 BND_H918RDS l-b l~ ' REFERENCE 10CFR20.101 and'10CFR20.405.a.
ARRR DTM, Vol . ' 1, Sec. VI.C.1.a. l' l l: ANSWER 1.06 (1.00)
,g y JA..Aka;;G ? + :L%^^= A & '^% '^ &
REFERENCE ARRR DTM[ Vol. 2, Sec. VI.4. ANSWER- 1.07 (1.00) d. REFERENCE ARRR DTM,.Vol. 2, Sec. V.2. ANSWER I.08 (2.50)
- a. High Radiation Area means any area, accessible to personnel, in which there exists radiation...at such levels that' a major portion of ~ the body could receive in any one hour a dose in excess of'100 mrem. [1.003
~b. 1. The-top of the reactor.
- 2. The demineralized. [0.75 each3 REFERENCE 10CFR20.202.(b).(3)
ARRR DTM, Test No. 3, Ques. 111.1. (***** CATEGDRY I CONTINUED DiJ NEXT PAGE *****)
1 Ig RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 40 J BND_HSZ9RDS 1 ANSWER I.09 .( 3.00)
&N j,4 y .
[Any 3, at 0.50 points each for the event and for the setpoint]
- 1. Smearable surface contamination > 100 mR/hr per 100 sq.cm.
1
- 2. High ' Radi ation Level > 100 mR/hr (monitored in the control r oom) . G oWM
- 3. High Water Radioactivity > 200 mR/hr (measured by the water monitor). (.2o W4y 4 High Air Radioactivity > 20 mR/hr (measured by the air monitor).C.2 N A,[
- c. =ft && &m*:* = & d==-.=_A=q; M Q )
ARRR DTM, Vol.1, Emergency Plan, Sec. IV.C. ANSWER I.10 (3.00) [0. 5 f or each of the detector types and type of r adi at i on]
- 1. (Cutie Pie) - ion chamber - Beta-gamma
- 2. (Pancake counter) - scintillation - alpha
- 3. (NEMD Rem meter (B-Ball)) - scintillation - neutron REFERENCE ARRR OTM, Vol 5, p 8 and Test No. 4, Dues. 18.
ANSWER I.11 (1.50)
- a. 3 Rems per quarter [0.53
- b. 1. Lifetime dose less than S(N-18)
- 2. Accumulated occupational exposure is documented on NRC Form 4
[0.5 each] REFERENCE 10 CFR 20.101, p 20-3; ARRR OTM, Vol 5, pp 6,7; Vol 1, Radiological Saf ety procedures, pp 2,3. (***** CATEGORY I CONTINUED ON NEXT PAGE *****)
4-u .,. 1 '
- 1. RADIOACTIVE MATERIALS-HANDLING DISPOSAL Page.41
, - eND,,H@l@BD@
1 i j ANSWER I.12 (1.00) :
.J
-- 1. .25. Rom '
- 2. 100. Rem [0.5 each3 ;
REFERENCE
- 10.CFR 20.101, p.20-3; ARRR DTM, Vol 5, pp 6,7; Vol 1, Radiological .4 Safety procedures, pp 2,3.- !
i l
. A N!.,W E R - I 13 . (1.00) .:
'1. '3 l
- 2. doubly encapsulated IO.5 each] !
-1 REFERENCE
ARRR' Technical Specifications (TS), 9.9. I l l
'l II j
i i 1 l l l
~I i
l 1 (***** END OF CATEGORY I *****)
- 2.__EdEG1Elg_QEE6811N@_gd@@@CIE61@ llc @ Pago 42 L
LANSWER J.01 . ( 1. 00)
.b. ..
'REFEREN'CE ARRR Reactor ' Operator Training - Manual ,' Vol 1, Sec.-IV, Figs. II & III.
ARRR DTM, Vol-4, . Sec. 1.2.5. ANSWER J.02 (1.00) C. REFERENCE ARRR OTM, Vol 2, F1g IX-4,-5.
-ANSWER J.03 (3.00) a.
b. c. Y N Y
*gr
((
/* w
. Y CO.5 each]
"AEFERENCE ARRR DTM, Vol 1, Sec III, p 1.
. ANSWER J.04 (1.00) b.
REFERENCE ARRR'OTM, Vol 2, p.V-5.. ANSWER J.05' (1.00)
- c. :
(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
[ ' ' .., IJ__EdEEIEIE_9EEBBIIN@_gy@80 gig 8]@Ilgg Pega 43-
-REFERENCE ARRR DTM, Vol;2, p V-1.
ANSW5R- J.06 (1.00) d. REFERENCE-ARRR.OTM, Vol 2, p.V-3.. ANSWER J.07 .( 2.50) a .- 1
- b. 4
- c. 3
- d. 4
- e. 2_ [O.5'_each3 CAF REFERENCE ARRR OTM, Vol. 1, Emergency Plan , p 7; Test bank.
ANSWER 'J.OB (2.00)
- a. To prevent to loss of prime when the primary pump is not operating.
- b. No point in the return line is more than one f oot lower /below the normal water level. [1.0 each]
REFERENCE-- ARRR OTM, Vol 2, p V-3. ANSWER J.09 (1.00) c.
-(***** CATEGORY J CONTINUED ON NEXT PAGE *****)
f:1' [' v ' Pego 44 K-i J 2__EEEGIEIE_DEEBSIJNg_gH33391gBJgIJgg l I REFERENCE
'ARRR OTM,.Vo3 1, Suc 4, p 8.
ANSWER J.10~ - ( 1. 50') . La. '125. degrees-F. ~ (+1 -2) [0.5] b '. To prevent 1 damage to the demineralized. resin. ' C 1.OJ REFERENCE-ARRR' Annunciator 1 Settings and Test No 1, Ques V-2. LANSWER J.11: (3.00) a.oThe safety rod must be f ully withdrawn bef ore it is 'possible- to withdraw either the shim or reg rod (f rom their down position).
- b. If both."up" switches of the reg and shim rod are depressed, only the. shim rod will withdraw from the core.
c..To prevent wit'hdrawing two rods at. once. C1.0 each] REFERENCE 1 ARRR'OTM, Vol 2,. p IX-7 and Test No 1, Ques V-3. ANSWER- J.12 (2.00) C4 required, 0.5 each3
- 1. High bay air conditioner.
. .f 2. High buy heaters.
- 3. N-Ray ~ set-up room air conditioner.
- 4. Chemical laboratory hood.
5.' Rest room vent fan. REFERENCE ARRR DTM, Vol 2, pp~11-3 & 4. (***** END OF CATEGDRY J *****)
7,_ 6 ,._gUE(_h3NpblNg_3Np,CgBg_E333Dg][B)' Pegs 45 u., l - ANSWER- K.01- ( 1.' 00 ) _. , I d .'
" REFERENCE'-
'ARRR'DTM,'Vol 2, p' III-6.
ANSWER 4 K.02 (1.00)
.1. -c'
- 2. .a, CO.5 each]
- REFERENCE ARRR DTM', ' Vol' .1, . Sec IV, .9 1.
- ANSWER- K.03 (1.00) la.
+:- -REFERENCE.
ARRR DTM,'Vol.2, p.20. ANSWER. K.04 .(1.00) L REFERENCE ARRR Test No 6, Gues 29.
'ANSW$R'. K.05 -(1.00) d.
(***** CATEGDRY K CONTINUED ON NEXT PAGE *****)
I i ~
,Ki__Ehh_0$ND6]NG_SND_C9BE_P@BS!1EIEBE Paga 46- ; :-i '
i
. REFERENCE
~ARRR-DTM,.Vol 1,-Sec IV,.p'1.
t i . . ANSWER K.06~ (1.00)- y* -b. REFERENCE , F . A R R R '.T S ,. 1 1 . 1 . .
' ANSWER K.07 (1.00) c.
- REFERENCE.
ARRR TS,'11.1. ANSWER. K.OB (1.00) c. REFERENCE
'ARRR OTM, Vol.1, Sec IV, p 1.
ANSWER :K.09 (1.50)
- a. 11 cents /second.CO.5J.
- b. Speed of the control rod drive motors CO.53,. and rod control interlocks CO.53.
' REFERENCE
'ARRR TS, 5.3.2 and.' Hazards-Summary Report, p 62.
i' l l~ (*****-CATEGORY K CONTINUED ON NEXT PAGE *****) m.
p.(.; G L.; Lir b'
' Ti '
Page 47-
"Ki__FUE6_HANDQNG;AND_COREJ ARAMET_ERS j
I!- ANSWER. K.10 (1.00) L It offers'the greatest amount of multiplying medium for source 1r.eutrons to travel prior to detection-(making the detector'most r. sensitive to increases in' count rate as f uel is added. ) 'C1.03 s REFERENCE. R .
.PSBR Training Manual,-Chapter 2,'Section A, p..2-12. CAF F
ANSWER K.11 (3.00)
- a. 2 (68)
- b. 2.(B).
-c. .More than half the number of fuel. elements projected to be-required to reach criticality were added in many steps C1.03.
REFERENCE' ARRR Training ~ Guides and Tests, Test #5, Questions 20 and 21. ANSWER K.12 (1.00)
- d. M "'" C # -
b -
^# " '
REFERENCE ARRR OTM, Vol 2, p III-13. ANSWER K.13 (1.00) a. I REFERENCE-ARRR OTM, Vol 2, p 111-13.- (***** CATEGORY K CONTINUED ON NEXT PAGE *****)
= _ s,. .- a <, L__E956_beNp(jN@,SNp_CQBE_BBBBDEJEB@. Page.48'
. f i
4 ANSWER K.14 (2.50)
- a. . [4 required, 0.5 each3
- 1. El ement #-
- 2. Type of el emen t --
'3. Starting' location-4.-Date'of-move 5.' Time of move
- 6. New location :
-- 7. Reacti vi ty- change (if' required)
- b. The control room' reactor files to.53 REFERENCE ARRR DTM, Vol 1,.Sec IV, p l';. Test No 4, Ques #6.
. ANSWER' K.15- (1.00)-
- 1. d.-
- 2. c. EO.5 each3
' REFERENCE
.ARRR TS, 5.3.3; Test No.6, Gues #B.
ANSWER K.16~ (1.00)
'C.
REFERENCE ARRR-DTM, Vol 1, Ser T V, p 11. l W (***** END OF CATEGORY K *****)
- s. .. ,.
s - ;,
- L= .- . ADMINISTRATIVE PROCEDURESz _COND]TJgNS Page 49 l OND_LJd11@IlgNS l
[
-l ANSWER 'L.01 (2.00) l '. ITo-facilitate a head count (personne1' accountability) [1.03.
- 2. . Because . the control room . i s pressuri z ed ' wi th clean air f rom <
.outside-[1.03.
REFERENCE
'ARRR,_ Test #4, Ques 29; Emergency Pl an, . Gec. E; OTM, Vol. 2, Sec II.1.
. ANSWER- L.02 (2.50)
. ;;: a. SRO
'b...RO c.-RO
'd. SRO
- e. ' SROl.
' REFERENCE-ARRR Operating Procedures, Sec. C.2; TS, Sec 10.
ANSWER .L.03 (1.00) a. REFERENCE ARRR,- Operating Procedures,.p:3. ANSWER L.04 - ( 1. 00 ) C. REFERENCE ARRR,LGeneral Emergency procedures, p 4. l (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
K < q,
;Pags 50 lL . . ADMINISTRATIVE'PROCEDURESz_CQNQITlQNS ONp_(1MlI@IlgNS l'
l-1 i-ANSWER L.05- (2.00) a. REFERENCE ARRR, General Emergency procedures, p 4. ANSWER L.06 (2.00)
- a. SRD in charge -DR- the'RSD C1.03
- b. The facility parking lot C1.03 CAF REFERENCE ARRR, General Emergency procedures, p 2.
ANSWER- L.07 (1.00). x d. REFERENCE-ARRR. Test No 3, Ques VIII-2.
. ' ANSWER L.OB (2.50) y
.1 . SRO
- 2. other qualified individual
- 3. PCN (procedure change notice)
- 4. 30
- 5. 'RSC - (reactor saf eguards committee)- CO.5:each]
REFERENCE ARRR Admini strative procedure, p 6. 1 (***** CATEGORY L CONTINUED ON NEXT PAGE *****)
.a v .:.
4 " '" L a__B901Ni@lB@llVE_PBQCEQQBESt _CQNQlligNQ, Page 51 BNQ_LidlI@llgNS: ANSWER L.09 (1.50) l '. ' 2
- 2. secured (in the key cabinet)
- 3. a licensed operator.- CO.5 each3 REFERENCE ARRR, Operating' Procedures, o 1.
ANSWER L'.10 -(1.00)
.b. ~
REFERENCE ARRR1 Test.No 3, Ques VIII-1.
-ANSWER L.11 (1.50)
- a. 2
- b. 3-
- c. 3 CO.5 each3 i REFERENCE ARRR OTM, Vol 1, Maintenance procedure, p 4. -
ANSWER L.12 (2.00) 4
- a. 2
- b. 01.0 each3 REFERENCE ARRR-Test No 1, Ques VI-3.
'(***** CATEGORY L CONTINUED ON NEXT PAGE *****)
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CO.5 each3 i; / REFERENCE ARRR{TS,c 9.11.1,-9.11.2. I a
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(***** END OF CATEGORY L *****) (********** END OF EXAMINATION **********)
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