IR 05000020/1990003
| ML20062H735 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 11/26/1990 |
| From: | Eselgroth P, Maier W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20062H732 | List: |
| References | |
| 50-020-90-03OL, 50-20-90-3OL, NUDOCS 9012060004 | |
| Download: ML20062H735 (74) | |
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,. NOV 2 71990 U.S. NUCLEAR REGULATORY COMMISSION REGION 1 OPERATOR LICENSING EXAMINATION REPORT j EXAMINATION REPORT N /90-03(OL) l l FACILITY 00CKET N FACILITY LICENSE N R-37 LICENSEE: Massachusetts Institute of Technology ;
'I38 Albany Street !
Cambridge, Massachusetts 02139 l
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FACILITY: MIT Research Reactor EXAMINATION DATES: October 15 - October'I6,_1990
' EXAMINERS: W. Maier, Operations Engineer D.-Silk, Senior Operations' Engineer i
CHIEF.. EXAMINER: ! W. A. Maier, Operations Engineer
// ,2 (c f ' Date APPROVED BY:~
/ Peter dff/f 4(d4 Eselgropfvf Chief m/' n8/te
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a d- g i t,gPWR S tion,:0perations Branch
, Division of! Reactor Safety q Examination Summary: Written 1 examinations:and operating tests werecadmini-:
stered .to two (2) instant senior reactor operator-(SRO) candidates. One section o# the written examination was re-administered.to an upg'rade SRO.candi-date, All; candidates passed all sections of the examinations that were admini-
-stered;to the The candidates' demonstrated -weakness in their. personal knowledge of radiation protcction procedures. .This was~due-_to a tenuous' applicability,of thelproce- I -
dures-to the duties of licensed operators at the Nuclear Reactor Laborator x {
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i A procedural-inconsistency was identified by-the facility during the' review of j the written examination. Stay time calculations were not consistert oetweenl f
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two different Emergency Procedures. This discrepancy prompted =a facility
'commentLon a question of the written examinatio j '
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' . I'. 0 INTRODUCTION AND OVERVIEW The NRC examiners administered initial examinations to two (2) Senior l- Reactor Operator (SRO) instant candidates. The examiners also admini-stered the retake of one section of the written exam to a SRO upgrade .
candidate. The exams were administered in accordance with NUREG 1021, ' Examiner Standards, Rev 5, dated January 1, 1989, with revisions dated -i
~ June 1, 1990. The results of the examination are summarized belo :
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:2.0 PERSONS CONTACTED I-2,1='U.S. Nuclear Regulatory Commission' ; . . s 1 i . * W.;Maier,10perations Engineer- . . *
D.- ' Silk, - Seni_or. 0perations Engineer '
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B. Wetzel,~ReactorfEngineerT x
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} ^*JJ. Bernard, Director of React'or Operations ;
* K. Kwok',' Reactor. Superintendent
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* F. McWilliams, Reactor. Radiation Protection :0fficer:
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* Denotes those=present at the' exit: interview on>0ctober 17, 199 '
13.0 EXAMINATION-RELATED FINDINGS AND CONCLUSIONS
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j-3.1! - The following is-a summary'of the-strengths'and~ deficiencies noted ,
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during the administration ofJthe operating: tests. This information-
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is being provided to aid.the licansee in upgrading license and' ., requalification training programs. No licensee response is required.- I
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1-i Strengths
, , Knowledge and use of abnormel operating and emergency ;
procedure ! Knowledge of facility emergency plan and ability to make emergency classification . Knowledge of pre-start-up checklists and associated equipmen !
' Deficiencies Knowledge of Technical Specification limits on reactivity worth of movable experiment , Knowledge of radiation protection procedures contained in I Appendix A of the Procedure Manua .2 Training Program Comments i
OneLweakness -observed was in the candidates' knowledge of Appendix A , of the Procedure Manual (Radiation Protection Procedures).' The 41-observed weakness was due to a tenuous applicability of these proce- j
.dures1 to the Nuclear Reactor Laboratory (Nii). Both. candidates were "
unfamiliar with the quarterly discharge limits for effluents ard the dose limits for. storage of radioactive materials. With difficulty, one candidate was able to locateithe correct reference. The other-' 4 candidate-was: unable to locate-the-correct reference in the Procedure
. Manua Two written 1 examination = questions were deleted from the q Eexamination.because:of-a broad interpretation:ofnthe Radiation
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iProtect' ion' procedures as practiced.at:the NRL.- ' c' The examiners discussed -these problems ~ with'the .facil.ity at 'theLexit; +
/i ntervi ew.~ The facility: pointed out thatLthe responsibility:of_ .
controlcof effluents and- stored -radioactive: materials wasia function i
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, of 'the Radiation : Protection ~ Office._ - The document incorporated as
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Appendix A'of_the Procedure.Manualiis a generic; E campus-wide procedure and not specific;to'thelNRL=. . The' facility identif.ied a need for a,
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" reactor-specific: set of radiation . protection procedures and . policies s .
The; facility _ state'd an' intent to develop'such a documentito respond
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to the: problems observed. _This action would;betterLprepare? licensed: y operators: for_ their1 job-specific requirements in the area of radi-
!! ' , ,ation protectio With the. exception'of:theJabove' deficiencies,~the candidates were- J well prepared forithe licensing r examinations, ]
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;v " =5;0 ADDITIONAL FINDINGS u~ .
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'A' procedural inconsistency was identified by the facility during: The - '
review of the written exam. It was noted that two-different Emergency q
. Procedures direct operators to calculate stay times in the-Control Room ' ""
based on two different radiation exposures. This inconsistency prompted.
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a facility: comment to the written examination. The facility representa-tives stated an intention to resolve'the disparity in stay time calcula-tions by revising'one of-the procedure ,
;6;0 , EXIT INTERVIEW 4 , +
1Antexit meeting'was. conducted-on October 17, 199 The-licensee repre - sentatives-who attended the meeting are-listed in section 2.2 of this ! report, :The' strengths and deficiencies listed above and other-findings t discussed in this report were presented. -It was explained by the exami-
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ners.that the:results of:the examinations would be contained in the exami- ! _ nation report. Every effort would be madeLto send the applicants' result in approximately 30 days, a: !
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4 JAttachments:L
~ Master ~ Senior Reactor' Operator Examination =with Answer Key? :[
T ~ ' Facility CommentstonLInitial Written; Examination.and NRC Response.tcr
' , , Facility Comments ,y ,
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ATTACHMENT 1 Master Senior Reactor Operator Examination with Answer Key
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V. S. NVCLEAR REGULATORY COMMISSI0l' NON POWER REACTOR LICENSE EXAMINATION FACILITY: REACTOR TYPE: TANK DATE ADMINISTERED: 90/10/15
REGION: l CANDIDATE: i LICENSE APPLIED FOR: INSTRUCTIONS TO CANDIDATE: Answers are to be written on the exam page itself, or the answer sheet ! provided. Write answers one side ONLY. Attach any answer sheets-to the examination. Points for each question are indicated in parentheses for each question. A 70% in each section is required to pass the examinatio Examinations will be picked up three (3) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY VALVE TOTAL SCORE VALUE CATEGORY 3 , , 20.00 99+C REACTOR THE0RY, THEfM0 DYNAMICS ! 1FFHE3 AND FACILITY OPERATING 3 ' ' CHARACTERISTICS ,
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M-M " ' W c v . v u __ NORMAL AND EMERGENCY OPERATING S33 PROCEDURES AND RADIOLOGICAL-3227,W*- ' CONTROLS I9 00 "i ?h A 20.00 33.33 > PLANT AND RADIATIO.*; MONITORING' 1 SYSTEMS ta++ 5j, c c . ; l W -@-M % TOTALS FINAL GRADE All work done on this examination is my ow I have neither given nor received ai r Candidate's Signature
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: 1. Cheating on the examination means an automatic denial of your application and could result in more severe penaltie ; 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 examinatio . 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 cheatin . Use black ink or dark pencil only to facilitate legible reproductions, i 5. Print your name in the blank provided in the upper right-hand corner of the examination cover shee I 6. Fill in the date on the cover sheet of the examination (if necessary).
7. Print your name in the upper right-hand corner of the first page of each section of your answer sheets whether you use the examination question ; pages or separate sheets of paper. Initial each-pag . The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is : NOT an indication of the depth of answer require . If the intent of a question is unclear, ask questions of the examiner onl . When turning:in your examination, assemble the completed examination with l examination questions, examination aids and answer sheets. In addition, turn in all scrap pape ' l 11. To pass the examination, you must achieve at least 70% in each categor . There is a time limit of (3) hours for completion of the examination.
l (or some other time if less than the full examination is takcn.) i 13..When you are done and have turned in your examination, leave the examin-ation area as defined by the examiner. If you are found-in this area while the examination is still in pr%ress, your license may be. denied or-revoked.
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1 EQUATION SHEET l l
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k - In cp AT Cycle Efficiency , y 6 - In Ah SCR - S/(1 - K,gg) 6 - UA AT CR (1
K,gg)3 - CR2 (1 - K err)2 SUR - 26.06/r M - 1/(1 - K rr) e
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CR3 /CRo 26.06 (A err el (1 - Kerrlo H = 8R "
(# p) (1 g tt)t l P -
Po 10smt) SDM - (1 - K,gg)/Kerr P - Po e(t/') Pwr - Wg in l _ l _ r - (f */p) + ((# - p)/A.trp} r - A*/(p - #)- p -
(K rr - 1)/K rt e e 1 - 1 x 10 5 seconds i p -
AK,gg/K,gg - Aert - 0.1 seconds-1 i l l 1 Curie - 3.7 x 1010 dps- 1 kg~ - 2.21 lbm 1_ hp - 3 2.54 x 10 BTU /hr 1 Mw - 3.41 x 106 BTU /hr l 1 BTU - 778 ft lbf 'F - 9/5 *C + 32 l
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5/9 (*F - 32)
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.- .... s -. ' RX THEORY. THERMO & FAC OP CHARS Page 4 QUESTION: 001 (1.00)-
In which area of the Gas Filled Detector Curve (below) does a gamma-compnnsated ion chamber operate?
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L Area III Number of lens Detected versus Voltage ! Area IV for a Gas Filled chamber F QUESTION: _002 (1.00) Which one of the following defines the resonance escape probability, p, from the oi:t factor formula?
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l Total Number'of Thermalized Neutrons l Total Number of Fast Neutrons Escaping Leakage , Total Number of Fast Neutrons Escanino Leakace ' Total Number of Fast Neutrons Produced from Fast and Thermal-Fission , Thermal Neutrons Absorbed in Fuel Total Number of Thermal Neutrons Escaping Leakage L d .- Total Number of Thermal Neutrons Escanina Leakace Total Number of Thermalized Neutrons (***** CATEGORY A CONTINUED ON NEXT PAGE *****) l ,_ _ _
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QUESTION: _003 (1.00) What is the count rate in. a reactor that has a multiplication factor equal to - 0.7 and a neutron source emitting 600 neutrons per second?
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Which one of the following is the correct amount of reactivity added if the : multiplication factor, K, is increased from 0.861.to 0.9657 . .086 b.- 0.108 E .125 <
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QUESTION: _005 (1.00)
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zReactor: power is_ increased'at a steady rate from-500 watts to 100 Kw in t'wo minutes. ? What is the. reactor period during this interval? -1 a. -11 seconds- j ' e : seconds -
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> ' A '. RX THEORY. THERM 0 & FAC OP CHARS Page 6-QUESTION: 006 (1.00) Given a reactor period of 32 seconds, what is the doubling-time? . seconds seconds seconds-
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I 'l-QUESTION: 0'07 :(1.00) Given the.following information: . ' Ilmg . Power Rod Position :i 0- '50 w! 50. %
'351sec' 100 w- 55,% '
, Determine the DIFFERENTIAL ROD' WORTH between rod position of 50% and 55%; ' l m: (k = 0.1 sec-2, B-eff- = 0.00787)' i o a.. 0.0013 E o
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. .. .. . RX THEORY. THERM 0 & FAC OP CHARS Page 7 QUESTION: 008 (1.00)
The MIT Reactor is operating at 5 MW (100% full power) and the reactor scram is set for 110% of full power. What will be the power at the time of the scram if a nuclear excursion creates a 0.5 second period and the scram delay time is second after 110% is reached? MW MW MW , MW QUESTION: 009 (1.00) Which one of the following best describes the beta decay of a nuclide? The atomic mass number decreases by 1, and the number of protons remains constan The atomic mass number remains constant, and the number of protons-increases by The atomic mass number remains constant, and the number of protons remains constant, The atomic mass number decreases by 1, and the number of protons decreases by (***** CATEGORY A CONTINUED ON NEXT PAGE *****)
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... .< . , RX THEORY. THERMO & FAC OP CHARS- Page 8 QUESTION: 010 (1.00)
Which one of the following factors of the six factor formula is most easily varied by the reactor operator? thermal utilization factor reproduction factor fast fission factor fast non-leakage factor-QUESTION: 011 (1.00) ; Which of the following is accurate concerning control rod worth? j-a . Doubling the poison content of a rod doubles its wort l Rod worth increases as reactor coolant temperature increase t A rod located in the periphery of the core is worth more than one located near the center of the cor i i As void content in the core increases rod worth decreases, f QUESTION: 012 -(1.00) Whichione of the following'is the correct reason that delayed neutrons enhance control of the reactor?- 1
. More delayed neutrons are produced than prompt, neutrons ;
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Which one of the following statements correctly describes thermal neutrons? A neutron that experiences a linear decrease in energy as the temperature of the moderator increases, A neutron at resonant epithermal energy levels that causes fissions to occur in U-23 A neutron that experiences an increase in energy levels after collisions with larger atoms of the moderator, A neutron that experiences no net change in energy after several collisions with atoms of the moderator.
l QUESTION: 014 (1.00) Suppose a control rod is to be withdrawn until 50 millibe:a is added to a critical reacto If the blade speed is such that the re activity addition rate is_10 millibeta/second, what will the reactor period be immediately before rod motion stops? (Assume delayed neutron decay constant is 0.1 sec~l) . a.- 30 sec l ! sec l l = sec d.- 100 sec
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- RX THEORY, THERMO & FAC OP CHARS Page 10 QUESTION: 015 (1.00)
Following an increase in reactor power from sustained operation at 100 kilowatts to 5 megawatts, in what direction will the regulating rod move for the next half hour? (Reactor is on auto control.)
'c.; It would drive i It would drive ou It would not move, because the reactor is at equilibrium, It would move in response to signal noise with no net movement.
i QUESTION: 016 (1.00) The term ' Xenon-precluded' means that: The reactor is critical on xenon-produced neutrons alon The worth of the control absorbers is decreased because of xenon, The reactor is on a long period because of the excess xenon in the cor The reactor cannot be started because of the presence of too much xenon.
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' -QUESTION: - 017 (1.00)
What type of reactivity effect will occur if pure, uncontaminated D 0_ 2 leaks into either the' light water reflector above the top of the core, or the light
.w ater reflector in the-annular space-between the core and the sides and bottom of the core tank? Positive Negative c .- Positive then negative Negative then positive (***** CATEGORY A CONTINUED ON NEXT PAGE * * * * *)
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What type of fuel is used in the MIT Reactor? Plutonium-239 Uranium-238 - low enriched Thorium-233 high enriched Uranium-235 QUESTION: 019 (1.00) Select the list that gives the order of types of radiation from the MOST penetrating to the LEAST penetrating (ie. travels the furthest in air). alpha, beta, neutron, gamma beta, alpha, gamma, neutron gamma, neutron, beta, alpha neutron, gamma, alpha, beta QUESTION: 020 (1.00)
-Xenoa concentration reaches its peak approximately _ after shutdown at-the MITR.- hours
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-c .f- ~e'- . NORMAL /EMERG PROCEDURES & RAD CON Page 12 <
QUESTION: 001 (1.00) If you are working in a radiation zone where the general background is 50 mrem /hr gamma radiation, how long can you stay in that zone before you would exceed the MINIMUM 10 CFR 20 whole body quarterly limit? hours
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QUESTION: 002 (1.00) The dose rate at a distance six inches from a point source is 5000 mrem /hr. At: 4 What~ approximate distance from the source is a "High Radiation-Area" sign , Lrequired to be posted, per 10 CFR 20 regulations? .5 feet-p ' b; : 3.5 feet - L !
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.. .. " NORMAL /EMERG PROCEDVRES & RAD CON Page 13 STION: 003 (1.00)
Handling s, or a suitable remote-handling device MUST b sed for handling a source or co iner which emits a dose rate, at cont , in excess of . .25 rem /hr .50 rem /hr .0 rem /hr .25 re ' Dc{cted- $u (Ac l y Comment 5 (m~- QUESTION: 004 (1.00) Which one of the following is the definition of a Rem? A measure of the sum of the products of the dose equivalent to the organ-or tissue and the weighting factors applicable to each of the body organs or tissues that are irradiated, A quantity of radiation absorbed, per unit of mass, by the body or by any portion of the bod A measure of the dose of any ionizing radiation to body tissue in terms of the energy absorbed per unit mass of the tissu d. ' A measure of dose of any ionizing radiation to the body tissue in terms of its estimated biological effect relative to a dose of 1 R of x-ray (*'*** CATEGORY B CONTINVED ON NEXT PAGE *****)
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Which o' he following actions is required in the event of a amination incident ca orized as a localized, non-volatile liquid e ' l? Survey the ea, then drop absorbent mate on the spill, assemble potentially co minated persons in o to arrive, ocation and wait for Radiation Protection personn Rope off the area, assemb otentially contaminated persons in one location and monitor for tamination and wait for Radiation Protection person to arrive, Place abso ent material on the spill, a 'ce all persons to leave the immedi area and wait for Radiation Protect personnel to arrive, urvey the area, rope off the area, monitor all perso el near the spill and wait for Radiation Protection personnel to arri . Delded- SCe (ach Commed$ p th \ QUESTION: 006 (1.00) What is the MINIMUM crew complement whenever the reactor is HOT shutdown, in cddition to the required Radiation Protection Officer or his alternate being onsite or on call, per Technical Specifications? Two persons onsite, at least one of which is a licensed senior operator, Two licensed ope ators onsite, one of which is in the control roo Two licensed operators onsite, at 1 cast one of which is a licensed senior operator and one of which is in the control room, Three persons onsite, two of which are licensed operators and one licensed individual must be in the control roo (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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QUESTION: 007 (1.00) How often are Nuclear Instrument Scram Times Tests required to be performed, per Technical Specifications? Quarterly Semi-annually Annually Biannually QUESTION: 008 (1.00) During the performance of an Abnormal Operating Procedure, a tempcrary change to'the procedure is required. Select the minimum complement of personnel required to approve this temporary change, Two' members of the reactor staff, at least one of whom holds a Senior Reactor Operator License, The Duty Shift Supervisor and an appropriate group Supervisor.
!. c. A 1icensed Senior Reactor Operator and a member of the Reactor Safeguards i l , Committe Two licensed Senior Reactor Operators and the Director of Reactor 0perations.
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. .. .. . NORMAL /EMERG PROCEDURES & RAD CON Page 16 QUESTION: 009 (1.00)
What Emergency Classification would a bomb threat be categorized as? Unusual Event Alert Site Area Emergency General Emergency QUESTION: 010 (1.00) According to the MIT Emergency Plan, who has the authority to direct the MIT Campus Police to evacuate portions of the campus? Radiation Protection Officer b.- President of MIT Supervisor Off-Site Emergency Director QUESTION: 011 (1.00) ;i Thm< reactor is operated at full 9ower for 8 hours and subsequently shutdown and 1 unnttended for 8 hours. The rer.ctor is going to be started up and operated at
a power of 3 M Which of the, following Startup Checklists =is required to be-performed? ~ One Loop Startup, Shutdown < 16 hours Two Loop Startup, Shutdown < 16 hours
' . Restart Following an Unanticipated or a Brief-Duration Shutdown . Non-Routine Reactor Startup (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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During reactor operation, there is an unanticipated nega ve reactivity addition to the core from an unknown source. What are the required immediate acti9ns, per the appropriate Emergency Operating Procedure? Assume the reactor is in Aut Manually scram the reactor, b.- Take manual control of the reactor and maintain steady powe Take manual control of the reactor and do NOT add any positive reactivity, Allow the reactor to scram automatically on power-set / actual power deviatio ,
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QUESTION: 013 (1.00) In the event of a Building NW12 evacuation, due to.a radiological emergency, what location-is used as the Assembly Area?
a. .across the street from the NW12 Albany Street entrance reception area in NW13 campus police headquarters
' machine' shop in NWl3
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l QUESTION: 014 (1.00) What is meant by the term " chronic radiation exposure?" j a lar e dose received in a short period of time that could possibly be letha a one time dose to an unborn fetus, which may cause developmental abnormalities ; small doses received repeatedly over long periods of time, which may cause delayed effects a small dose received by a large population, which statistically could cause genetic damages
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QUESTION: 015 (1.00) A reactor containment evacuation is require The Reactor Operator performs the Immediate Actions necesstry to evacuate personnel from Containment. He then
.eust calculate his own 'Stcy Time' in the control room. If the radiation level in the control- room is 150 mrem /hr, what is the Reactor Operator's MAXIMUM stay time?- minutes I hour,'40 minutes hours i
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QUESTION: 016 (1.00) Which statement is HQI a violation of Technical Specifications? Operating with one inoperable shim blade fully inserte Reactor power is 2 MW, one primary pump in. service, and the total coolant flow rate is 1000 gp Reactor pow 6r is 150 kW with the emergency cooling system inoperable. . Reactor power is 100 kW and emergency power is not availabl QUESTION: 01.' (1.00)
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Wh;n is the regclating rod withdrawn during a reactor startup? After the B-10 counter is secured and the power range instrumentation is on scal . When reactor power reaches 10 watt After the third control blade in withdrawn to subcritical positio After all control blades are withdrawn to the subcritical positio . l QUESTION: 018 (1.00) H w is thermal power calculated? a.- By irradiating a gold foil and counting it to determine power level, t By performing a heat balance with the reactor at power and in equilibrium.
' By using channel #7 (a calibrated ion chamber) to read reactor power.
< By measuring the neutron flux in a beam port at powe (***** CATEGORY B CONTINUED ON NEXT PAGE *****)
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. .. . , NORMAL /EMERG PROCEDURES & RAD CON Page zu QUP.STION: 019 (1.00)
Wh;t is the maximum allowed power level if a Pu-Bo source is in the core, per T chnical Specifications? W W c. '100 kW kW
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QUESTION: 020 (1.00) Und:r what type of restrictions is an Experimenter who is wearing a Blue Film B2dge? He is required to be directly supervised when performing any action , involving radioactivity or-which could possibly influence reactor operation, He is allowed.to operate the experiment by himself, subject to the approval limitations which may have been impose ; He is allowed to operate the experiment by himself, with-the exception of the use of a spectrometer, He is required to be directly supervised when performing any action that could possibly influence reactor operation, but is allowed to perform experiment steps-on his own, including ones involving radioactivit .
(***** END OF CATEGORY B *****)
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. PLANT AND RAD MONITORING SYSTEMS Page 21 ;
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I Commtd5 ' De eted- 500 t4Cl / QUES 10N: 001 (1.00) > What is th nction of the "suberitical interlock?"
' It prevents ulating rod withdrawal until a the shim blades have reached their su tical position, i It limits the rate of wit of the regulating rod when the shim ;
blades have reached thei c ical position, It prevents ro hdrawal if the reacto oes critical before the shim 1 blades h eached their suberitical posit imits shim blade withdrawal to four inches after t im blades have I reached their-subcritical positio l
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'i non compensated ion chamber proportional boron counter d - fission chamber
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(***** CATEGORY C CONTINVED ON NEXT PAGE *****)
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., - . PL ANT AND RAD MON 110 RING SYSTEMS Page 22 QUESTION: 003 (1.00)
Why is blowdown of the cooling tower basins required to be secured whenever the reactor is shutdown? The secondary water monitors cannot detect leakage when the reactor is shutdown due to short-lived isotopes, Secondary system level cannot be adequately measured when shutdown due to thermal expansion during operatio Shutdown cooling system efficiency may be adversely affected due to blowdown . The cooling tower level detectors and automatic makeup system is not energized when the reactor is shutdow QUESTION: 004 (1.00) Which radiation monitor can be used for estimating reactor power because it's output is proportional to the fast neutron flux in the reactor? Core Purge Monitor Ar-41 Monitor N-16 Monitor Primary Coolant Monitor (***** CATEGORY C CONTINUED ON NEXT PAGE *****) _ _ .
. - _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ., , . PLANT AND RAD MONITORING SYSTEMS Page 23 QUESTION: 005 (3.00)
Match the facility conditions in Column I with the type of ai Mmatic response I expected to occur from the Reactor Safety System in Column 11. Items in Column I have only one correct answer and items in Column 11 may be used once, more l than once or not at all (0.50 points per response).
! Column I Column 11 (Condition) (Automatic Response) 1. Core tank level 2 inches a. Alarm ONL below overflow pip b. Rod withdrawal inhibited 2. Primary coolant flow by interloc equals 1990 gp c. S: ra . Reactor outlet temperature equals 48 degrees d -No safety system respons . Reactor building vacuum equals 1.2-inches water above atmospheri . Primary cleanup system temperature equals 52 degrees l , 6. D 20 flow equals 88 gp ! , QUESTION: 006 (1.00).
What automatic action occurs when a high radiation alarm is received on the Sewer Radiation Monitor? Assume that the Sewer Monitor is in its normal mode i
.of monitoring liquid radioactive waste being pumped from the sumps to the waste tanks, The Radioactive Liquid Waste Systen' Containment Isolation valve closes, The Inlet City Water Solenoid valve closes, j The Sump pumps tri ;
l l The on line Sewer pump trip (***** CATEGORY C CONTINUED ON NEXT PAGE *****) l '
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. PLANT AND RAD MONITORING SYSTEMS Page 24 i
QUESTION: 007 (1.00) i What is the reason for cooling the cleanup system flow to less than 50 'C7 i So that the conductance probes will have an accurate readin b. To prevent liquification of particulates in the coolant thereby enhancing 1 the efficiency of the filters in removing impuritie l So as not to damage the heat-sensitive resin be To prevent corrosion of the system component QUESTION: 008 (1.00) Rod control is in automatic during a Xenon burnout transient which drives the regulating rod to its near-in position. What will. happen if no operator action is taken?
' The automatic run down circuit activates a red light and buzzer as a uarning, then after 30 seconds of no action a reactor scram occurs, The reactor will be immediately shifted back into manual control and an annunciator will alarm to notify the' operato c. 'The automatic run down circuit activates a red light and buzzer as a l warning,' then after 30 seconds of no action it transfers control to l manual mode and drives in the selected shim blad The reactor will be immediately shifted to manual mode and an annunciator !
will alarm, if no operator action occurs within 30 seconds a reactor scram occurs.
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(***** CATEGORY C CONTINUED ON NEXT PAGE *****) [
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QUESTION: 009 (1.00) l Using the attached figure of the MITR Core Section, select the correct fuel element position label for the position which is indicate , A3 A6
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What facility feature promotes decay heat removal when shutdown with primary i' pumps off? Anti-syphon valve Natural convection valve Heat exchanger outlet valve MV- l Slots in which the shim blades are inserte ' l
QUESTION: 012 (2.00) i Hatch the location or feature from Column I with the gas from Column 11 which i is used as a cover or operating fluid. Items in Column I have only one correct j answer and items in Column 11 may be used once, more than once or not at all l (0.50 points per response).
Column I Column 11 1. Void in the top of the Rx a. Carbon Dioxide- , Containment T&,as 1 b. Argon 2. Pneumatic Tube Operating Gas c. Air 3. Vertical Thimbles ,
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_ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ ___ _________________-____ -__-_ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ - __ .
., .. . PLANT AND RAD MONITORING SYSTEMS Page 27 ,
QUESTION: 013 (1.00) A reactor startup is underway, and the " Reactor Ready" light has energized; which one of the following accurately describes plant operation? If the reflector tank level decreases, such that the reflector tank is not at overflow, a minor scram will resul The regulating rod can be moved to any position of trave Shim Blade withdrawal motion is unlimite The "subcritical-bypass" pushbutton should be depressed to continue a normal startu , QUESTION: 014 (1.00) Th3 Emergency Power Distribution System batteries have the capacity to supply i p:w r to selected instruments and pumps for a maximum period of und:r optimum conditions, hour hours
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QUESTION: 016 (1.00) Which of the following indications will be automatically actuated outside of I ths control room when the " trouble NW-12 gamma monitor" scam alarm actuates? A red light and a warning horn in the operations office, A blue light and a bell at the reception are A siren and backlighted signs in the containment buildin A horn in building NW12 and backlighted signs at entrance QUESTION: 017 (1.00) If during an accident the Containment Building begins to approach its design pra:Oure of 2.0 psig, what design feature provides for containment protection? c. A pressure relief blower automatically initiates at 2.0 psi A containment relief valve will automatically open at 1.75 psi A containment relief valve may be manually opened to protect containmen , The main damper will cycle open and closed to maintain containment pressure betwoon 1.5 and 2.0 psig.
l l .. l l l l (***** END-OF CATEGORY C *****) '
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only. -Questlon will be modified in the exam bank for future us ! Fac111tycComment: Section A, #011 f e Answer. (b) is correct. .But, answer (c) might also be correct l depending on ; where thermal.fluxfpeaks. (Note:-This question is not being conteste '
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a 1 Comment:provided here is?for information only). , O .. i. Reference: S.'Glasstone & A. Sesonske, " Nuclear. Reactor Engineering," " i LVan-'Nostrand Reinhold, 1981, p 296-29 '
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y NRC' Response: Comment.note M :t
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No change' ma'deLto; answer key since camentiis 'being made -for:information-- .[ only; -Question will be~ modified in the exam bank 4 forLfuture us '
-Facility'Cbmment: Section'B, #003E
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(Bothianswers.(a).an'd-(c)arecorrect. LThe. answer ~(c);is; takenifrom MIT ,
'a JRadiation Protection Guidelines. !But'the policy at.the reactor is.to use.
@' ' tongs lfor any sampl This islin accordance with;ALARA. -(Notes: , L
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f(1)' Confusion 'oni this : question is- the ,f acility's Lfault. ; (2) Answer -(a);
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.isebest ch'oicesin.. view'ofLALARA). 1 J
g' . Reference: l(1), Procedure Manual App. A: MIT' Required Procedure for Radiation,
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q ' Protection,"Section7III, Subsection C, Item . :{
' ' :(2)JProcedure Manual Chapter.2, Section 2.1,.first paragraph ~. (3)l Procedure Manual Chapter 1, Section 1.14.2.2(2).
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Attachment 2 3 NRC Response: Comment accerted and question deleted from exa Accepting choice (r) as a correct answer makes all four choices correc Facility Comment: Section B, #005 Request that this question be deleted because of three possible correct answer (B) is correct per the reference cited. But (c) and (d) are also reasonable responses and would be used at the reactor dependirg on circumstance Reference: A0P 5.2.14 NRC Response: Comment accepted and question deleted from exa Facility Comment: Section B, #007 Reactor Operators (R0/SR0) are riot required to memorize test and calibra-tion schedules. (Note: This question is not being contested. Comment provided here is for information only).
NRC Response: Comment note No change made to answer key since commer.t is being made for information onl . Facility Comment: Section Bt #015 Step 9 of PM'4.4.4.12 specifies e maximum dose of 300 mrem. But, Step 10 of PM 4.4.4.15 specifies a maximum dose of 1000 mrem So, the answer could be either. 2 hours (c) or 6.6T hour The facility needs to resolve the conflict between the two procedure NRC Response: Comment not accepte Examination question provides specific conditions that direct the operator' to the containment evacuation procedure (PM 4.4.4.12) and nec the proce-dure for release of radiation from containment (PM 4.4.4.15). This ques-tion is asking for information that is contained in the i'.imediate actions of the containment evacuation procedur Facility Comment: Section C, #001 None of the given answers are correct. The answer key is (d) which implies a total blade withdrawal of 8 inches (4 inches to reach the sub-critical interlock and 4 more after reaching that interlock). Suggest change (d) to "It limits shim blade withdrawal to four inches."
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o _ s ' Attachment 2 4 lE k i NRC Response: Comment accepted and question deleted from exa . Facility suggeuien to change the wording of choice (d) cannot be made e f ter the exam has been edministered. The wording of choice (d) will be changed in the exam bank for future use of this question, r FacDity Coce:nt: Saction L FOC'5-1 Answer is (a) if reactor 1's crhttal; (a) and (b) if ' shutdow Reference: RSM pp 4.3, 9.6, 9.10.
E NRC Response: Comment accept 9c and answre key changed to r.ccept either (a) or 6 (b) as cor ect answers.
":- Facility Comment: Kection C, #005-3 -
-. ! Given enswer is incorrec Should be (d). (Get an alarm at 53*C., scram at 55 C)
Reference: RSM p 9.4, r NRC Response: Comment accepted and answer key charged to accept (d) as the correct answer.
- Facility Comment: Section C, #005-4
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_ " Answer is (a) if reactor is critical; (a) and (b) if shutdown.
V Reference: RSM pp 4.3, 9.3, 9.1 ~NRC Response: Comment accepted and answer key changed to accept either (a) or (b) as correct answer Facility Comment: Section C, #012-1 Question is confusing. There is no ' reactor containment tank.' There is a ' reactor tank'= and a ' containment building.' The cover gas for the tank is air under forced convection. So' answer should be (c).
' Re fe rence : RSM Section 3.2.5, p 3.3- NRC Response: Comment accepted and answer key changed to accept (c) as the correct answe . . . . . . _ . . . _ _ _ . . . _ _ . _ _ . .- - - .
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