IR 05000020/1988002
| ML20155J419 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 10/19/1988 |
| From: | Eselgroth P, Yachimiak E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20155J402 | List: |
| References | |
| 50-020-88-02OL, 50-20-88-2OL, NUDOCS 8810260104 | |
| Download: ML20155J419 (115) | |
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U.S. NUCLEAR REGULATORY CCVJilSSION P.EGION I OPERATOR LICENSING EXAllINATI0h IEPORT EXAMINATION REPORT NO. 50-020/88-02 (OL)
FACILITY DOCKET NO.50-020 FACILITY LICENSE NO. R-37 LICENSEE: Massachusetts Institute of Technology 138 Albany Street Cambridge, Itassachusetts 02139 FACILITY: Itassachusetts Institute of Technology Reactor (MITR-II)
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EXAltlNATION DATES: September 12 & 13, 1988 CHIEF EXAMINER:
bIM f
/ / Ob Edward Yachimiak,(Operations Engineer
~Date
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78/<//
////f/88 APPROVED BY:
(fPeterf. Eselgrott144hief PWR 5ection Date SUtiltARY: Written and operating examinations were administered to One (1)
Senior Reactor Operator (SRO) candidate and One (1) Reactor Operator (RO) candidate. Both candidates succesfully completed their respective examinations and were granted licenses.
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REPORT DETAILS TYPE OF EXA41 NATION:
Replacement EXAMINATION RESULTS:
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CHIEF EXAMINER AT SITE:
E. Yachimiak, USNRC OTHER EXAMINERS:
D. Silk, USNRC 1.0 Generic Strengths The following generic strength was noted during the administration of the operating examinations. This information is being provided to the licensee in recognition of the efforts of the Nuclear Reactor Laboratory (NRL) staff to adequately train and qualify their NRC license candidates.
Both candidates displayed a thorough knowledge of the security plan which has been implemented at the MITR-II.
Each candidate briefed the examiners on the confidentiality of the security plan and explained the limited "need to know" nature of the security system.
Each candidate was familiar with the immediate and follow-up actions for security violations, as specified in the procedures, and was able to discuss each action in detail, 2.0 Personnel present at the Exit Meeting J. Bernard, Director of Operations, MITR-II 0. Harling Director of Nuclear Reactor Laboratory K. Kwok, Superintendent, MITR-II
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l Attachments 1. R0 Written Examination and Answer Key 2. SRO Written Examination and Answer Key
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3. Facili*u Comments on the Written Examination 4. NRC Response to the Facility Consents
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i ATTACHMENT 1
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U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION P
i Facility:
MITR-II
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Reactor Type:
kesearch
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Date Administered:
88/09/12 Examiner:
Gordon Robinson Candidate:
'N 00 fM INSTRUCTIONS TO CANDIDATE Use separate paper for the answers.
Write answers on one side only.
Staple
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question sheet on top of the answer sheets.
Points for each question are indi-cated in parentheses after tne question.
The passing grade requires at least
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70% in each category.
Examination papers will be picked up six (6) hours after
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the examination starts.
Category % of Candidate's
% of j
Value Total Score Cat. Value
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A.
Principles of Reactor Operation
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14.0 14.0 B.
Features of Facility Design 14.5 14.5 C.
General Operating Characteristics
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l 14.5 14.5 D.
Instruments and Controls
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j 14.0 14.0 E.
Safety and Emergency Systems L
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14.5 14.5 F.
Standard and Emergency Operating f
Procedures
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14.0 14.0
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Radiation Control and Safety
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Final Grade
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i All werk done on this exam is my own.
I have neither given nor received aid,
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS Buri ng the administration of this examination the f ollowing rules apply:
B.
Choating on the examination means an automatic denial of your application cnd could result in more severe penalties.
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@.
Rootroom trips are to.be limited and only one candidate at a time may 10Cve.
You must avoid all contacts with anyone outs,ide the examination ecem to avoid even the appearance or possibility of cheating.
9.
Uno black-ink or dark pencil gnly to facilitate legible reproductions.
Print your name in the blank provided on the cover sheet of the cxcmination.
-3.
Fill in the date on the cover sheet of the examination (if necessary).
Uco only the paper provided for answers.
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Print your name in the upper right-hand corner of the first page of eacn
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ccetion of *he answer sheet.
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Ccnsecutively number each answer sheet, write "End of Category __" as copropriate, start each category on a new page, write gniv gn gne side of the pacur, and write "Last Page" on the last answer sheet.
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Nunber each answer as to category and number, for example, 1.4, 6. 3.
o. Skip at least thtra lines between each answer.
\\1. Scaarate answer sheets from pad and place finished answer sheets face Gewn on your desk or table.
,2 U:o abbreviations only if they are commonly used in facility li3etatutg.
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.3.
Tho point value for each Question is indicated in parentheses after the qu;stion and can be used as a guide for the depth of answer required.
L4 Show all calculations, methods, or assumptions used to obtain an answer to mathematical prontems wnether indicated in the cuestion or not.
,5. Pcrtial credit may be given.
Therefnre. ANSWER ALL PARTS OF THE QUESTION AND DC,NOT LEAVE ANY ANSWER BLANK.
6. If parts of the examination are not clear as to intent, ask questions of tho examiget only.
7.
You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
This must be done after the examination has been completed.
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I l(18. WhCn you complete your examination, you shalls o.
Assemble your examination as followsg.
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Exam questions on top.
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Exam aids digures, tables, etc.
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(3)
Answse pages including figures which are part of the answer.
l D.
Turn ir your copy of the examination and all pages used to answer
the examination questions.
c.
Turn in all scrap paper and the balance of the paper that you did
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I not use for answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after (
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leaving, you are found in this area while the examination is still
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in progress, your license may be denied or revoked.
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A.
ARINCIALES OF REACTOP OPERATION
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QUEST!Q4 A.01 (2.5)
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(n.)
Yoye reactor i s subcri tical by 4 percent delta V/M.
t Your startup channel reads 30 cps.
When the count l
rate has incre ased to 300 cp s., WHAT is the new t
K-effective.
SHOW ALL WORK.
Useful equations are i
nopended to the end of the exam.
(2.0)
(b.)
TRUE or FALSE?
For a given amoun t et positive reactivity insertion while the reactor is sub-
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cr i t ic al, the closer the reacter i s to cri tical the larger the change in countrate.
(0.5)
QUESTI ON A.02 (2.0)
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Two minutes after a scram cf your reactor from full power,
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a significant number of neutrons are still present in the core.
List the major sources of these neutrons and state the crigin of each source.
(2.0)
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OUESTICN A.03 (2.0)
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Indicate whetner the following statements concerrs.ng
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j ftasion product poi soning ar e TRUE or FALSE f or the
MITR-!!.
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The amount et Dos 6tive reactiv64v neeced to over-i ccme the equilibrium value of xenon-135 poisoning l
at 100 percent of full ocwer is twice that needed to over ccme equilibrium xenon-135 at 50 percent l
cower.
(0,5)
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b.
Upon s hu t t i ng cown the reactor after an extended
run at full power, tne xenon concertration peaks
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(0.!)
c.
When increasing power fece 50 percent power (siter
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extended operation) to 100 percent pcwer, the
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x+non-125 concentration initia'.lv decreknes and t
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then increases.
(0,5)
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Shutting cown the reactor frem full ocuer causes
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j the samarium-149 concentration to change.
(0.7)
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CATEGORY A C Ct 4T I NU E D CH N EXT F A G E * * * * * )
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4 PP!NCIPLES OF REACTOR OPEF ATi cti
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OVESTION A404 (2.0)
l During a normal startup to tuli pcwer kiter several weekn l
of maintenance. the ce&ctor is placed on n 60 second
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period.
The ini ti al pcwce In 100 watts.
Wi th no red
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movemen t, woul d thi s re 6c tor per i od be sus tained for 3
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Thow your c 61 cul at i ons knd JUST!FY your answer.
(2.0)
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i QUEST!Cet A.05 (2.0)
k In a suecri tical reactor. If a reactivity of 0.003 delta I
K/K is added to the reactor, will it take longer to conch
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a equillbelum if the in;tiki K-effective is 0.95 or if l
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K-e+fective is 0.9957 Briefly Justify your choice.
L'2.05
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i OVESTION A.06 (2.0)
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A cri ti c al renctor is pi nced on a stable reactor Deriod 6t t
icw power.
When measured with n stop watch, the doubling i
i time was 35 seconds.
WHAT is the approximate r e & c t i t' i t >'
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which has been inserted?
SHOW ALL WORK.
Use+ul equktiens i
j tre appended to the end of the exam.
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j QUESTION A.07 (2.0)
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Indicate whether the f oli cwing s t a temen t s tr e TRUE cr FAL3E.
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j In generkt as shin blades are raised:
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The ax i ni spitial location of the point et maximum (
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flux will be higher.
(0.Si f
i b.
The magnitude of the flus (in Part n.) will be
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(0.5)
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The magnitude of the ttermal neutron flux tunilable
- t the beam cort reentt6nt tnimble ties increktes.
( 0. 5
d.
Power density decrettes in the A Dnd B ting 3.
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P.
53 TURES OF F.:.01 L ! TY DEilGN
OVE5 TION B.01 (2.5)
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Drhw a sim le schematic of the Heavy Water Reflector Clean-s up System.
Include the f ol l owi ng t l
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All major ccmoonents.
Indicate direction of flow
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(1.5)
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Location of outlet from the reflector t6nk and l
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(0.!)
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Location of *11 ficw, temperature. and conductivity
measuring devices.
(0,5)
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OVESTICN B.02 (2.0)
Consider the Heavy Water Helium Gas $/ stem.
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Give TWO (2) reasons WHY. helium is used instead of j
air in thi s system.
<!.0)
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D.
WHAT B40 (2) operating conditions of the reccebiner, i
if met. assure that the deuterium c;ncentration in j
the cover gas will not exceed 6 percent by volume.
(1.0)
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OUESTION B.03 (2.0)
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Eriefiv describ, HOW normal shutdown cooling is obtkined and WHAT oper a t or actions must be taken to obtain ma=imum
l flew.
(2.0)
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OUE5 TIC 4 E.04 (2.0)
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.' e n s i d e r the Reactor Eullding Vent il at 6 on Sys tem.
I n.
WHY is it important to place the switch that
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in the "Weekend-open" position whenever the builc-i ing i s le+t unattenced?
(1.0)
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Erietiv describe HOW the reactor building l
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(1.0$
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CEATURE? 0F FACILITY'DE?tGH l
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QUESTIC4 8.05 (1.5)
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Eriefly describe the THREE (3) step process used to sett l
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(1.5)
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OUESTION B.06 (2.0)
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Consider the reactor core configuration, n.
Eriefly explnin the method used to number the
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iuel element positions in the three rings et the
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(1.0)
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WHY Are the fuel elements designed to be axin11v i
s ynee t r i c ?
(1.0)
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OVE5 TION B.07 (2.0)
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In accordance with your technichl Decitichtions, indickte L
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the folicwing l
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Minimum primprv c ool an t system flow rate at full i
oower operation.
(0,5)
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tia x imum ocwer level with no ortmarv cociant ovmos t
in oper> tion.
(0.5)
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Maximum allcwaele bulk ocol temper kture dur ing f ull (
pcuer operation.
(0.*)
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tii n imum wa t er level above core (you may use the
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overficw pipe >s a reference point it sov wish).
(0.!)
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END OF CATEGCRY E +++++)
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C. GENEPAL OPERATING CHAEACTERi? TICS
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OVEST! Ct4 C.01 (2.0)
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j WHAT influences the magnitude of the negative j
reactivity inserted when the heavy water retlector is dumped during a major scram?
Briefly explain WHY this
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(2.0)
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OUE 5TI Ot1 C.02 (2.0)
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enc omp as s e s D40 ( 2) distinct phencmena.
Both insert nega-i
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tive reactivity with an increase in temperature.
Srtefl.
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describe the reason for this reactivity change for EACH i
j Dhenomenon.
(2.0)
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Indicate whether the folicwing statements concerning j
primary system water chemistry are TRUE or FALSE.
Con-j lider +ach statement separately.
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It i s permi ssible to operate the reactor if the i
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pH value is in excess of 7.0 if the cause of the l
high DH is kncwn.
(0.5)
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It is permiasible to opeamte the reactoe if the
l concuctivitv exceeds 2.0 mieremhos when the i
i cause of the excess is known and is not related to
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(0,5)
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It i s f40T permi s si bl e to operate the *eacter if
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the chlor i ce r e ncing is in excess of 6 ppm.
<0.7)
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CATEGORY C CCNTitJUED Ct1tJEXT PAGE *****)
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C. GENERAL ODERATING CHARACTEOl5 TIC 9
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QUEST!G4 C.04 (2.0)
During full power operation of your reactor WHAT change in position of the regulating rod, if any, will be required to maintain a conttant p owe r level if reactivity changes occur by the f oll oaing means t (Assume each change occurs independently.)
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Light water leaks into the heavy water reflector.
(0.5)
b.
A large polyethelene s amp ! <> is injected into the reflector tank reentre.it t",imble using the pneumatic tube assembly 2PHl.
(0.5)
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c.
The heavy water blitter tank suddenly floods while i
operating with the medical therapy room in use with
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all shutters open.
(0.5)
i-d.
A larce piece of ca@viium is injected into the i
graphite re41ection region using the pneumatic
i tube assembly 1PH2.
(0.5)
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OVESTION C.05 (2.0)
j Give TWO (2) re asons WHY the regulating rod reactivity worth per inch withdrawn is greatest at the beginning of
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rod wi thdrawal (first inch withdrawn).
(2.0)
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i QUEST! Q4 C.06 (2.5)
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During the previous week the reactor was operated at full power f or six hours a day from Monday until Wednesday after-noon.
The f oll owing Monday an additional sample was loaded
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Briefly describe kHAT l
information is required to obtain an estimated critical
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position.' Assume no new fuel is added.
(2.5)
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QUESTION C.07 (1.5)
j The fuel management pattern at the MITR-!! usuall/ calls for refueling when the critical shim bank position reaches
16 inches.
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Approx ima tel y WHAT is the core excess reactivity (
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at this time?
(0,5)
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WHY is this excess reactivity necessary?
(1.0)
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GENEPAL OPERATING CNAPACTEPl? TIC 9
GUEST!Ct1 C.0S (1.0)
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Indicate whether the folicwing are TRUE or FALSE:
a.
If in the process of refueling, fresh fuel is plkced
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in the B-ring and partially-spent fuel is placed in the A and C-rings, the net result is to concentrate
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power in the center of the core.
(0.5)
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Reptacement of nn orifIced :ampie aseemblv with a fuel element increases the power density in she a
neeghboring elements.
(0.5)
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END OF CATEGORY C
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INiT Ut1ENTS AND CrflT CL3
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QUE5 TION D.0!
';2.5)
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Briefly describe HOW g fistion chamber detects
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neutrons.
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Briefly describe HOW unwanted signals from gtnaas
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and alphas tre removed trom the output signal of I
fission chamber.
(1.0)
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3UEIT!ON 0.02 (2.5)
During nytomatic coerttion, the regul ating rod a criv+n (
to the near-in oosition by a s l ewl y increasing reactroit-transient (i.e.
xenon burnout).
Explain the renctor contre!
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system's response it no coerator action is t& Ken.
(2.5i
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OVESTION D.03 (2.5)
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Indicate which of the following tre interlocks which must be satisfied in order to obtain initial blade motion
(withdraw - permit interlocks):
n.
Hold-dean grid 1ntched
'0,5)
b.
YWo out of three of the Pcwer Lev +1 Chennels I
(Channels 4
and 6) on sc al e (0,5)
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Main tank at ov e r f l ow
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Inner enc /or outer main lock gaskets pressur+
switches closed
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Primary coolant f l ow greater then !?00 ;cm 0.*,
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IN5TEUMENT9 AND CONTc0L5
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j The "SUB-CRITICAL POSITION" interlock circuit provides n
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convenient reference point at which the operator con
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cause t o m*K e a compl e t e instrument check before bring-
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ing the rea: tor to cri ticali ty.
List TWO (2) other l
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l reasons this ;nterlock is incorporated into the shim blade i
c on tr ol circuit.
( 2.0 )
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GUESTICM D.05 (1.0)
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(1.0)
!
!
I OUEST!CN 0.04 (2.5)
,
n.
Br i e fl y exoltin WHY the reactor must be held at l
constant p owe r twenty-four hours toe therm 41
.
equilibrium to be renched.
(3.7)
I i
.
c.
Once thermal equilitrium i s r e ac hed, WHmi informatich
{
i s neecec to calcul hte thermal power)
(1.3)
[
?
i I
!
OVEST!CN D.07 (1.51
!
Eriefly describe HOW the conductivity cell in the primarv coolant mensures the conductivity of the water.
- i. ! :'
,
t
[
l
!
)
!
!
l l
'
i i
!
!
s.....
END OF CATEGosy 0... *>
l
!
!
J
!
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a
I
!
!
t
!
+
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.
r
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!
!
E.
94FETY AND EMEPGENCY SYSTEMS t
I
-
OUE3 TION E.01 (2.5)
'
Indicate if the electrical loads listed belcw WILL or i
WILL NOT sutomatickily be supplied by the Emergency Power
'
Distribution System if normal pcwer fails.
!
i j
a.
St ar tuo channel No. 1 (0.5)
l
'
b.
Red control (0.5)
!
'
c.
Core purge blower
'0.5)
l d.
tiagn+ t ecwer (0.5)
j e.
Pr imar y coolant auxiliary pump (Mt12)
(0.5)
!
i l
I l
OUESTION E.02 (1.5)
l Indicate whether the tollowing questions concerning the l
]
Containment Pressure Relief System are TRUE or FALSE.
!
I i
n.
This system is intended to be used to relievt all
)
types of pressure buildur in the building ccntain-i ment.
(0,5)
I, i
b.
This system will au t cmh t i c al l y ce actuated if i
the containment pressure reaches 2.0 osig.
< 0. !
l
'
l c.
This system's charcoal filter is designed to absort
[
i most (aporoximately 90 percent) of the iodine (
I tant m6v be present in the exhaust air.
(0.!)
I
!
d l
I J
Ccnsider Emergency Cooling.
i l
.
floce 2 of Emergency Cooling assumes the level in j
the ccre tank cannot be maintained at the ov e r f i c+4 l
level, tut it has been determined that it is n>t dropping below the retctor inlet pene tr at ion.
J
m.
E r i e 41 < oescribe the ficw path through the
core.
s1.0)
,
i i
b.
Indicate the THREE (3) means by which hen *
i l.!)
!
8I removed fecm the primary system.
a
[
,
CATEGCKY E C;NT!NUE Ct4 NEXT FAGE
....)
( +++++
i
!
'
. -
- -
.
- -
.
-
-. - -
-
_.
.
-
_
-
__.
.
i
.
.
,
.
.
'
q L
,
E.
?ARETY AND EMEP0ENCY ?YeTEMS
,
t
!
!
f OVE5T10tl E.04 (2.5)
,
Consider the t1ain Core Tank Level Indi c ator s (ML-?A and i
i tiL-30).
l t
a.
Briefly describe the principle of operation and arrpngement used to produce the main core tank level
!
t
)
indications.
(1.5)
!
,
c l
'
b.
Indichte the differences in operation et these level j
'
j indicators.
t.0)
'
i.
,
i l
!
QUEST!Oti E.05 (2.0)
I
'
!
- I WHAT are the differences in circuitry, it any, between a
[
]
scram caused by 6 short period and a scram caused by low i
orimary coolant flow.
(2.0)
I QUEST!0t4 E.06 (l.5)
i
!
In addition to dropping the shim bl ades. li s t THREE (3)
L other automatic actions a t%JOR SCRAM initiates.
(1.5)
l I
<
r
'
i r
l OVEST!Ct1 E.07 (1.5)
i*
'
Indicate the SCPAt1 setooints for the followingi
[
i l
a.
Reactor D+riod
+0.!>
I
b.
Primar< coolant Icw flow
<Q.!)
J i
l c.
L c-w heavy water flew
<0.!'
l
}
!
I
'
i i
!
!
i
!
(*****
Et4D OF CATEGORY E * * * * * )
!
f
,
!
l
i
!
!
I I
i
'
!
'
.. _ _. _._ _,..~.,
_ _ _... _ _..... _ _.. _. _ _ _ _ _ _. _ _ _ _, _ _ _. _ _ _.. _ _, _. _
. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ -
____
- _ _ _ _
-
___
_ _ _ _ __ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ - _ _ - - _ _ _ _ _ _ _ _ _ _ _.
.
-
t
.
.
-
..
..
!
F, iT.:.tJtARD Atl0 EMER GENCY OPERATItJG ACOCEDURES i
,
I
.
'
OVE5TI0tt F.01 (2.5)
i
!
l i -
Consider the t e mi. or a r y bypassing of a satety function NOT l
reavired by Techn i c al Sovcifications.
t i
a.
If not part of an approved orocedure. Iisi the l
l THREE (3) people (by Job titie)
who shoulc! 6pprove i
the bypass.
a
< !.0)
!
i b.
- JHAT THREE ( 3) actiens must be tsken after the l
,
physical i nstallation et a jumper ?
(1.!)
i l
]
QUEST!ON F.02 (2.0)
-
l Other than radiation mer>6 tors and their alarms. Indicate (
TWO (2) Ilkely i ndications et a fuel element cladding
-
failure as given in ACP 5.S.2 ' Fission Product Detect-
.
i ton in the Primar.v Coolant".
(2.0)
.
,
,
't
,
<
i OUE5T!0t4 F.03 (2.5)
4 r
j For the belcw listec malfunctions indicate whether the t
metc e a t e ac t i on s e e su $ r e a r%JOR SCFAti. MINOR SCRAfi.
!
$HUTOClJ4 BY AR1, or NO SHUTDCot4 is required, assume the
!
,
reacter is operating at full ocwer and has not scrtmmec a
'
I autemetteally one that no other abnormal concitions have
,
c+en noted.
,
'
,
,
4.
A F+ Pied Channel Level Signal Of f-icale Al arm i
occurs.
(0.5'
,
e.
The Lcw Flcw Tr ans f er Pumo At arm cccur s.
(0.!)
f c.
The Lew Flcw ib i e l d Cool an t Al arm oc cu.'s.
(0.5)
>
c.
A L ew F i cw Au x 41 i
Pumo ??t2 Al arm occur s.
s0.!-
e.
Low Pr e s sure
,ot +ssec Air Alarm occurs.
(0.!;
'r I
,
I t
I
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j C AT E G O RY F C Cf 4T ! r 4U ED Ct1 N EXT FAGE + + + + + )
t+++++
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.
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,
'
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..
.F.
STANDARD AND EMERGENCY OPERATING PROCEDURES i
!
l
.
QUESTION F.04 (2.0)
,
t A "High Pressure Reactor Inl e t*
al arm occurs ( AOP 5.2.11)
,
while your reactor is at full power.
In addition to an l
increase in the heat exchanger outlet pressure, indicate l
FOUR (4) other conditions that, if any one<of them exist, require the operator to scram the reactor.
(2.0)
!
l i
'
OUESTION F.05 (2.0)
,
!
In accordance with your Technical Specification definition, (
list the FOUR (4) types of reactivity changes that con-l stitute variabla reactivity.
(2.0)
t
,
P
QLESTION F.06 (2.0)
!
t A serious fire occues in the control room while the i
reactor is at full power.
In accordance with AOP 5.7.8,
!
"Smoke Detector System", WHAT actions should the re ac tor j
operator. perform (if possible) prior to evacuating the t
control room?
(Assume all required personnel have i
been notified.)
(2.0)
l P
l OU6STION F.07 (1.5)
.
l
Indicate whether the f ol l owi ng st atemen ts concerni ng
'
l a normal hot weather reactor startup to full power (50F 2.3.1) are TRUE or FALSE.
l k.
If the reactor is not cri t ic al when the shim bank (
j
+xceeds the estimated cri tical position by 0.5 (
'
inches, the shim bank must be lowered to 1.0
inches or more belco the estimated critical position.
( 0. 5)
'
{
b.
When 1 MW of reactor power ia reached. a tive
!
minute soak Deriod i s main tained to allcw the
'
reactor core and primary coolant to approach
.
l thermal equilibrium.
(0.5)
f c.
Between 50 kW and 300 KW k 30 to 40 second p+ricJ t
,
'
i s recemnended (0,5)
i i
"
(+++*+
END OF CATEGORY F *++++)
i l.
,
i
_.
.
..-.
.
.
.
.
.
.
..
..
G.
PADIATION CONTROL AND ?AFETY
.
-
QUESTION G.91 (!.5)
Does the biological effect of 10 Rem depend on whether it is a neutron or gamma dose?
Briefly explain your answer.
(1.5)
.
QUESTION G.02 (2.0)
A radiation survey meter is locSted one foot from k small single radiciostope sample and reads 100 mrem /hr.
Fifteen minutes earlier the re ading was 200 mrem /hr with t h t-meter in the s ame po'A l t i on.
HOW long must you wait until the radiation level drops to 10 mrem /hr?
SHOW ALL WORK.
(2.0)
OUESTIOtt G.03 (1.U)
In Accordance with the Required Procedures for Radiation Protection indicate whetlier the following are TRUE or FAL5 f~.
3.
Liquids are NOT allowed to be olaced into a co*!ection container designated ter solid weste.
t' G. 5 )
b.
It IS oermissible to elnce k smalI bottie contnining low level radioactive water into a
"Liquid Radicactive Waste" col 1 ec t i on con t m i ner.
(0.5)
c.
It !? permissible to disoose of R 3 pound slight 1.
rndicactive Diece of meth) in e collection c ntkiner designated tor solid waste.
(0.5)
(+++++ CATEGORY G CCNTINUED C44 NEXT PAGE +++++)
I
.
.
.
.
..
.
..
G.
PADIATIOtl CCtlTPOL AtlD SAFETY
.
QUESTION G.04 (2.0)
A por tabl e r adi a t i on moni tor indicates a reading of 60 mr/hr at a distance of 10 feet from what could be considered a radioactive point source (gamma emmitter).
You are required to work on a valve located 5 feet trem the source.
You estimate the Jo5 will take 10 minutes.
WHAT dose would you expect
- eive if you worked on the valve for 10 minutes?
,A ALL WORK.
(2.0)
'
,
OUESTION G.05 (2.0)
Consider the Core Purge Monitor, a.
WHAT type et detector is used in this moniter?
(0.5)
6.
Describe the automatic actions which occur if the
"High Radi a t i or. Core Purge" al arm is actuated.
(1.5)
QUESTION G.06 (1.0)
An operator enters an kre n that is posted as n "rkdiation
area" (as defined in 10 CFR 20).
He performs a job that takes him 40 minutes to complete.
WHAT is the MAXINUM dose he could expect to receive?
(1.0)
QUESTION G.07 (2.0)
According to 10CFR 20. an i nd i v i du al in a restricted tr e k may be alIowed to receive a whole body dose et radiktion grehter than 1.25 Rems Der calendkr quarter under certain conditiens.
Name the conditions.
(2.0)
GUESTION 3.08 (2.0)
Give the tollowing information concerning N-16:
1.
HOW i3 N-lo oroduced?
(9.5)
b.
IJHAT is the primary h a:: ar d kssociated with the oreduetion of N-16?
<0.5)
C.
Is N-lo b r*dihtion problem when the rencter i3 s hu t down ?
Briefly explain.
( 1. 0 '>
'
' +-+++ END OF EXAN +++++)
._.
..
_
.. _. _
_
_
_.
_ _ _ _ _.... _ _ _ _ _ _
_
_
-. _
_
_
_ _. _ _ _
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c.m m :,nc:. s
..,
fa ma y a s/t Cycle efficiency = (Networs
out)/(Energy in)
-
,
.
,
,
,
~
'
w.q s = V,t + 1/2 4t
E = ac
KE = 1/2 sv
,, (yr, y )fg 4, xg A,g,-At
'
c o
PE = agn Vf = V, + at w = e/t x = sn2/t1/2 = 0.693/t1/2 1/2*" " b5'in)(*h)3 t
-
y
,yg
((t1/2) * (*b)3
-
,
'
- 93I "
~
-e x g,g
,
.
.
Q = aCpat d=UA&t I9 It n
'
I = I,10** N L pwr. w e
TYL = 1.3/u
,
sur(t)
HVL = -0.693/s P o P 10
'
p = p,e /T
'
t l
50R=26.06/T SG = 5/(1 - Kdf)
G
= 5/(1 - K,ffx)
x SUR = 25o/ t* + (s - o)T G)(1 - Kdf1) " U II ~ kaff 2) '
Z l
.
T = (t*/s) + [(8 - s)/lo]
M = 1/(1 - X,g) = G)/G,
,
T = 1/(s - s)
M = (1 - Kgf,)/(1 - Kdf1)
l T = (s - o)/(la)
SDM = (1 - K,g)/K,g
,
t' = 10-5 3,c,,43
'
e = (K,g-1)/K,g = 4Kd/Xdf T = 0.1 seconds ~I
'
-
_
s = [(&*/(T Kgf)]+[igf(1+17)]
/
I d) = I d l
, P = (zeV)/(3 x 1010)
I d) 2 =2 2 Id j
g2
= eN R/hr.= (0.5 CE)/d (metars)
-
R/hr = 6 CE/d2 (feet)
'
Water Parameter _s Miscellaneous Conversions 1 gal. = 8.345 its.-
1 curie = 3.7 x' 1010
'
dps
!
l 1 ga;. = 3.78 liters 1 k9'= 2.21 1he
I ft- = 7.44 gal.
1 hp = 2.54 x 1 8tu/hr Density = 62.4 1 ft3 1 se = 3.41 x 1 Stu/hr
!
- Density = 1 gn/
lin = 2.54 cm
-
,
Heat of vaporizatica = 970 8tu/10e Y = 9/5'C + 32 i
Heat of fusion = 144 Stu/lbe
'C = 5/9 ( T-32)
l 1 AD= 1407 rni = 2 sos in Ha u
-
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-
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,
.
Dr tee lfl A*WetAo
'
74tl/
..
.
..
A.
PRINCIPLES OF REACTOR OPERATION ANSWERS -- MITRII - 88/9/12 - ROBINSON, G.
,
I ANSWER A.01 (2.5)
a.
(R2
=
1-(Keff1)
=10 CR1 1-(Keff2)
(0.75)
delta K/K =
1-(Kefft)
.04; (Keff1) = 0'.962 (Keff!)
(0,5)
Keff2 =.9962-1.962
=
1-(Keff2)
(0.75)
b.
TRUE (0.5)
REFERENCE Reactor Physics Notes:
Reactor Startup and Reactor Sub-
,'
cri ti cal Mul t ipl icat ion p.
8.
'
,
,
ANSWER A.02 (2.0)
,
Del ayed neu trons f r om f i ssi on f ragmen t decay f.e/
/
l (i.e. Br-87 with a 55 second half-life).
( 0. '" > -
Photoneu trons f rom gammas ( f rom f i ssi on f ragmen t decay)
!
which interact with deuterium (in the heavy water f.#/
reflector).
( CH-75r)
Neutron: ' om instel1+d source, psica;um, :nd bery!um.
( &r59 l
,
(CAE_+h!:
cur +
m.7 ii.v.
L,,n
, ymuv + d ci i, in.ig-
n i e t c n b.
If so, adjust point value to 1.0 each for above answers.)
NOTE: Information in parenthesis NOT required to receive l
full. credit for answer.
!
r REFERENCE i
Reactor Physics Notes: Reactor Startup and Reactor Subcritical (
Multiplication p.
7 and Reactor Kinet.ics p.
11.
i ANSWER A.03 (2.0)
,
!
a. FALSE (0.5)
i b. FALSE (0.5)
!
c. TRUE (0.5)
j d. TRUE (0.5)
REFERENCE l
Reactor Systems Manual 10.7 Reactor Physics Notes: Reactivity Feedback and Measurement of a Xenon Transient p.
24, 30, 32.
-
-
-
-
-
.
. -
- -
-
-
-
-
e
..
.
,
..
.
..
.
A.
PRINCIPLES OF REACTOR OPERATION ANSWERS -- MITRll - 88/9/12 - ROBINSON, G.
ANSWER A.04 (2.0)
P(t)
P(o) exp (t/ tau) = 100 watts exp (480/60)
(0.5)
=
'
P(t)
298 kw (0.5)
=
ye s
% increase in moderator temperature m id.JJ nw ii e p -- P
- *n dahl * E u m p,Y a e on e i M a',w. +t en o w y A s*d u r 4 *,g", N '
<1.0)
n+ac-t4v i t). -.. _
w * */
(Note: The temperature reactivity feedback effect becomes apparent at approximately 100 Kw, SOP PM 2.3 p. 3. ) seer * r8's
'#'**'"*
REFERENCE Reactor Physics Notes: Reactor Kinetics p.
i Reactor Systems Manual 10.8
.
ANSWER A.05 (2.0)
The case when K-effective is 0.995 will take longer to reach equilibrium.
(0.5)
/
The nearer K-effect is to one, the longer it takes to reach a new steady state, because of the increcsed number of generations which exist with the increased population.
(1.5)
REFERENCE Reactor Phys;cs Notes: Reactor Startup and Reactor Suberi tical Mul+1 plication p.
8, 9,
10.
ANSWER A.06 (2.0)
'
Period =
D.T
=
35 sec
= 50.5 sec (0.5)
!
.693
.693 Reactivity = beta /(1 + lambda x tau)
(0.5)
.00785/(1 +.08 x 50.5)
(0.5)
=
.00156 de1ta K/K
'O.5)
=
or 0.198 beta REFERENCE Reactor Physics Notes: Reactor Kinetics and Control Rod Calibration by Reactor Period Measurement p.
3, 4,
14, 18.
i k
.
-.
.
.
.
.
-
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.
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..
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,
...
.
.
,
...
.
,
..
.
A.
PRINCIPLES OF REACTOR OPERATION
!
ANSWERS -- MITRl!
88/9/12 - ROBINSON, G.
,
-
,
,
ANSWER A.07 (2.0)
f
.a.
TRUE (0.5)
^
b.
FALSE (0.5)
c.
FALSE (0.5)
d.
TRUE (0.5)
RERFERENCE Reactor System Manual 10.2
,
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8.
FEATl!EES OF FACli!TY DESIGN HNSWERS -- MITP II - 88/9/12 - ROBINSO4, G.
.
'
ANSWER B.01 (2.5)
See enclosed figure (3.3-1)
REFERENCE Reactor Systems Manual 3.7 and Fig. 3.3-1 Answer B.02 (2.0)
a.
Moisture entrained with the air would degrade the heavy water (D20 dilution).
(0.5)
Nitrous oxide formation from the presence of air in high radiation fields would cause corrosion.
(0.5)
b.
The tamperature of the middle of the recombiner must exceed a mi n imunt required value (50 degrees C.).
(0.5)
,
The flow rate through the recombiner must be between certain flow rates (1.o and 8.0 cfm.).
(0.5)
$he, grord ne+ssao& ens *$
4 e t * *r sed fved!/t * * * / * W'"
REFERENCE FL, Amp ** # of o'e s o s f e er* H 0, fe, A n eew kts k
.
heactor Systems Msnual 3.16
"
ANSWER 6.03 (2.0)
!
Normal shu tdown cool i ng i s prov i ded by air auxiliary pump (MM-2) and the cleanup loop heat exchanger (HE-2).
(1.0)
Maximum flow can be obtained by bypassing the ion column and the inlet 7.nd outlet filters.
<!.0).
REFERENCE Reactor Systems Manual 3.4
!
!
ANSWER B.04 (2.0)
4.
If the ven til ati on shoul d be lost, the int &Ke damper will close, thereby, forcing all air within the build-
,
i ng t o f l ow p as t the plenium monitor prior to being i
discharged.
(1.0)
b.
A manually operated exhaust control damper (located in the stack base) is used to throttle the overall f l ow of air through the ventilation system.
(0.5)
The opening of the damper is adjusted to maintain the building differential pressure between the intake and the exhaust.
(0.5)
REFERENCE Reactor Systems Manual 8.12, 8.16
,.
_ _ _ _ _ _,,, _,
-,.. _. _ _ _
,,
_ _ _, _,
_
r
_
,. _ _. _ _. _ _ _ _ _ _
_ _..
-
.-
.
..
.
..
B.
FEATURES Oc FACILITY DESIGN
ANSWERS -- MITR 11 - 88/9/12 - ROBINSON, G.
ANSWER B.05 (1.5)
1.
A plug is placed in the port.
(0.5)
2.
Gas seal s are made by bolting a ring against the aluminum flange of the liner.
(0.5)
3.
A gasket cover is bol ted over the beam port's opening.
(0.5)
REFERENCE Reactor Systems Manual 2.4 ANSWER B.06 (2.0)
a.
Fuel element positions in each ring are numbered sequentially in the clockwise direction from the regulating rod position.
(1.0)
b.
The elements are axially symmetric so that they can be inverted in order to equalize any peaking in axial burnup.
(1.0)
REFERENCE Reactor Systems Manual 1.4, 1.5 ANSWER B.07 (2.0)
a.
1800 gpm (0.5)
b.
100 Kw (0.5)
c.
60 degrees C (0.5)
-
d.
4 inches below the overflow pipe (0.5)
(CAF for actural height above core)
REFERENCE Technical Specifications p.
2-5
.
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C.
GENERAL OPERAT7NG CHAPACTERISTICS
.*
88/9/12 - ROBINSON, G.
ANSWERS - MITRI!
-
.
'
ANSWER C.01 (2.0)
The amount of negative reactivity added is dependent on the position of the shim blade bank.
(1.0)
This effect can be considered as being due to the
[
'
Shadowing influence that the blade bank inserts on the reflector.
(1.0)
REFERENCE
'
l Reactor Systems Manual p.
10.6 I
i ANSWER C.02 (2.0)
I a.
An increase in the light water temperature will insert i
negative reactivity by causing the hardening in the
,
neutron spectrum.
(1.0)
i b.
An increase in the heavy water reflector temper-
'
ature will insert negative reactivity by al l owi ng more
neutron leakage.
(1.0)
!
REFERENCE j
!
Reactor Systems Manual p.
10.8
'
'
h
.
]
ANSWER C.03 (1.5)
i
!
l a.
FALSE (0.5)
i b.
TRUE (0.5)
'
'
!
c.
TRUE (0.5)
i
REFERENCE Operating Procedure Checkilst FM 3.1.1.1 p.
l
,
ANSWER C.04 (2.0)
a.
OUT (0.5)
b.
IN (0.5)
i c.
M l#
-(0.5)
i d.
NO EFFECT (0.5)
REFERENCE I
Reactor Systems Manual p.
10.10 i
i
.
.,_
_
-n
- _. - _ _. _,, _., _ _.. _ _.....
- _ _,.,.
..,,. _ _ _, - _ _,. - _. _ _,,. - - _,,, _.
._,_,- _,_.,, _
,.,-
.
..
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,
,
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'
C.
GENERAL OPERATING CHAPACTEPl? TICS
.
88/9/12 - ROBINSG4, G.
ANSWERS - MITRII
-
ANSWER C.05 (2.0)
a.
The full-in position for the regulatory rod is six inches above the bottom of the fuel elements.
(1.0)
b.
Once the regulating rod is withdrawn any appreciable amount, it is heavily shadowed by the adjacent shim blades.
(1.0)
REFERENCE Reactor Systems Manual p.
10.6 ANSWER C.06 (2.5)
a.
The delta K due to temperature change or the change in average temperature and temperature coefficient.
(0.5)
b.
The delta K due to the additional sample.
(0.5)
c.
The delta K due to burnup or MWH and delta K per MWH.
(0.5)
d.
The previous critical rod positions.
(0.5)
,
e.
Rod worth curves.
(0.5)
REFERENCES Operating Procedure Checklist PM 3.1.1.2 p.
ANSWER C.07 (1.5)
a.
Approximately 2 beta of excess reactivity.
(0.5)
b.
In order to be able to override the xenon shutdown transient.
(1.0)
REFERENCE Reactor Systems Manual p.
10.8 ANSWER C.08 (1.0)
a. TRUE (0.5)
b. TRUE (0.5)
REFERENCE Reactor Systems Manual p.
10.5
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D.
INSTRUMENTS AND CONTPOLS
-
ANSWERS - MITR!! - 88/9/12 - ROBINSON, G.
ANSWER D.01 (2.5)
l a.
A neutron entering the chamber causes a uranium atom t
(in the uranium oxide coating) to fission.
(0.75)
The resulting fission products create a large neg-(
ative ionization pulse in the counting gas.
(0.75)
'
b.
A pulse height selector is used to distinguish the
'
large negative pulses created by neutron-induced f i ssions f rom the small er pul se produced by the ganma rays and al pha par t i c l es.
(1.0)
i REFERENCES Reactor Systems Manual p.
5.3 ANSWER D.02 (2.5)
The automatic control circui t can no longer keep reactor i
power at the set power level and power would start to
[
increase.
(0,5)
The au t omat i c run-down c i rcu i t causes a visual al arm.
(0.5)
'
-
After 30 seconds delay, the circuit transfers reactor i
,
'
control to manual mode.
(0.75)
,
The circuit then drives in the selected shim rod.
(0.75)
REFERENCE Reactor Systems Manual p.
4.5
!
ANSWER D.03 (2.5)
a.
must be satisfied (0.5)
!
'
i b.
need not be satisfied (0.S)
l l
c.
must be satisfied (0.5)
I
,
I d.
must be satisfied (0.5)
'
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}
be sa t i sf i e d $< /** ## ##) h[
e.
need not (0.5)
l mas 4 ec rehs Aed & A.// g e"'44 *#
(Acceptable answer therefore i s a, c, and d.)
i 4./ e
REFERENCE Reactor Systems Manual p.
4.1 and 4.2
-
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D, INSTRUMENTS AND CONTPOd
.
.
ANSWERS - ti!TRII - 88/9/12 - ROEINSON, G.
ANSWER D.04 (2.0)
ammed at a uniform 1.
To maintain the shim bl ade bank pr 4.
height during the f i nal approach * c. c r i t i c a l i t y.
(1.0)
2.
To establish a level, be l ow the critical position, to which the shim bl ades may be individually withdrawn in one step.
(1.0)
REFERENCE Reactor Systems Manual p.
4.3 ANSWER D.05
<!.0)
Depressing the " al l -absor be r s-in" pushbutton will give the scram alarm but will not scram the reactor.
(1.0)
REFERENCE Reactor Systems Manual p.
4.5 ANSWER D.06 (2.5)
a.
The graphite reflector has a large heat capacity and is slow to attain an equilibrium temperature distribution.
(0.7)
6.
Primary f l ow r a t e, core temp. rise, and heat capacity. (0.6)
Heavy water reflector flow rate, temp. rise, and heat capacity.
(0.6)
Shi el d cool an t ficw rate, temp. rise, and heat capacity (0.6)
REFEkFNCE Reactor Systems Manual p. __
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D.
It4STRUMENTS AND CCt4TPOLS AN SWE P.S - M I TR ! ! I 88/9/12 - ROBINSON, G.
ANSWER D.07 (1.5)
Two conc en tr i c c yl i ndr i cal electrodes, measures the resistivity of the water.
(0.5)
A potential voltage applied across the cell produces a current that is inversely pioportional to resistivity.
(0.5)
Resistivity varies inversely with conductivity.
(0.5)
(Also acceptable is - conductivity is directly proportional to current flowing through the cells.)
REFERENCES Reactor Systems Manual p. 6.1
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E.
SAFETY AND EMERGENCY SYSTEMS
-
ANSWERS - MITRII - 88/9/12 - ROBINSON. G.
,
ANSWER E.01 (2.5)
a.
WILL NOT BE SUPPLIED (0.5)
6.
WILL BE SUPPLIED (0.5)
c.
WILL NOT BE SUPPLIED (0.5)
d.
WILL BE SUPPLIED (0.5)
e.
WILL BE SUPPLIED (0.5)
REFERENCE Reactor Systems Manual p.
8.34
!
ANSWER E.02 (1.5)
a.
FALSE (0.5)
6.
FALSE (0,5)
c.
TRUE (0.5)
REFERENCE Reactor Systems Manual p.
8.23 ANSWER E.03 (2.5)
a.
The ficw goes up through the core and dcwn through the flow We+ud c h e c k v al v e s (by natural circulation). (1.0)
q w ide,
b.
i.
Heat lost to ambient (0.5)
f li.
Heat lost to the reflector Sank (0.5)
ill.
Heat lost to the off gas system (0.5)
REFERENCE Reactor Systems Manual p.
3.5
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E.
SM ETY 4.ND EMEPOENCY ?YSTEM5 ANSWERS - MITRII - 88/9/12 - ROBINSON, G.
- ANSWER E.04 (2.5)
a.
Both emplov differential pressure transducers that measure the difference between static pressurt in the air gap area (above the outlet plenum) and the pressure developed by a reference leg that extends into the core tank to a point immediately above the top of the fuel.
(1.5)
6.
ML-3A is e l ec t r i c al l y-dr i ven (piezo-electric differential pressure transducer) and is su,mplied (0.5)
by emergency power.
ML-3B is pneumatically-driven (transmitter)
and is supplied by instrument air.
(0.5)
i REFERENCE Reactor Systems Manual p.
6.8 ANSWER E.05 (2.0)
A period scram is fast acting, that is it is coupled directly to the magnet-current amplifiers and upon a preset scram signal interrupts the current to the magnets of the six shim blades.
(1.0)
A low primary c ool an t flow caused scram is initiated by a rel ay wh i ch opens the withdraw circuit, thereby, causing the current to the magnett to be cut off.
(1.0)
REFERENCE Reactor Systems Manual p..
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E.
SAFETY AND EMEPGENCY SYSTEMS 88/9/12 - ROBINSON, G.
ANSWERS - MITRll
-
ANSWER E.06 (1.5)
1.
Secures the ventilation system (0.5)
2.
Seals the containment shell (0.5)
3.
Dumps the top part of the heavy water reflector (0.5)
REFERENCE Reactor Systems Manual p.
9.8 ANSWER E.07 (1.5)
a.
10 second period (0.5)
b.
1975 gpm (0.5)
c.
M gpm (0.5)
REFERENCE Reactor Systems Manual p.
9.9
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F.
STANDARD AND EMERGENCY OPERATING PROCEDUPES ANSWERS - MITRl!
88/9/12 - ROBINSG4, G.
-
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ANSWER F.01 (2.5)
I a.
Reactor Superintendent (0.34)
]
Duty Shift Supervisor (0.33)
!
The Electronics Supervisor (0.33)
(or designated alternates)
.
l b.
Two responsible people must check the jumper after (0.5)
i
j installation.
The Jumper must be tagged for identification.
(0.5)
(
A record of the authorizer's initials must be i
recorded on the bypass log sheet.
(0.5)
<
REFERENCE
'
J Administrative Procedure PM 1.9 p.
!
i
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i
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i ANSWER F.02 (2.0)
l, i
High Primary Cool an t Conduc t ivi ty ( al arm)
(1.0)
!
!
!
Increase in results of the weekly analysis of the
.
l primary c ool an t.
(1.0)
'
REFERENCE Abnormal Operating Procedure PM 5.8.2
i j
!
{
ANSWER 5.03 (2.5)
!
e
,
a.
MINOR SCRAM (0.5)
I i
b.
NO SHUTDOWN REQUIRED (0.5)
c.
,g,,ggio o (0.5)
l j
d.
- *W##,
(0.5)
.... -.,
,,n.
e.
NO SHUTDOWN REQUIRED (0.5)
!
.
i REFERENCE I
I Abnormal Operating Procedures PM 5.1.4, PM 5.2.1, Pm 5.3.2,
]
.
i i
I
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I
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-_
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...
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,
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r
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a
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F.
STANDhRD AND EMEPGENCY OPERATING PROCEDURES j
ANSWERS - MITRII 88/9/12 - ROBINSON, G.
-
L
"
ANSWER F.04 (2.0)
'
r Any four (4) of the f ol l owing t
i 1.
Any change in reactivity 2.
Any decrease in primary coolant flow 3.
Any increast in the core purge
,
4 Any increast in primary conductivity readings
'
l 5.
Any increase in the core outlet temperature 6.
Any increase in the core delta temperature (Notes Each response is worth 0.5 points.)
"
REFERENCE j
Abnormal Operating Procedure PM 5.2.11
?
'
J
'
,
ANSWER F.05 (2.0)
,
,
Xenon (0.5)
Fuel Burnup (0.5)
!
Sample changes made in operation (0.5)
Changes in experiments during operation (0.5)
[
I
.
REFERENCE i
l Technical Specifications p.
3-33
!
(
>
.
r i
I r
j A615MER F.06 (2.0)
(
j Scram the reactor.
(0.5)
Turn on the "D0 NOT ENTER * sign for the back personnel i
j lock.
(0.5)
'
Remove the reactor KEYS and (0.5)
'
l Console log (0.5)
l J
]
REFERENCE i
j Abnormal Operating Procedure PM 5.7.8
'
$
!
ANSWER F.07 (1.5)
s
]
a.
TRUE (0.5)
j b.
TRUE (0.5)
i c.
FALSE (0.5)
I i
REFERENCE
{
Standard Operating Procedure Fti 2.3 p.
2 and 3 l
I
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G.
RADIATIOf4 CONTPOL AND SAGETY 88/9/12 - ROBINSON, G.
ANSWERS - MITRII
-
ANSWER G.01 (1.5)
NO (0,5)
The unit Rem considers the different effects.
Rem is a biological unit, thus different radiation causing the same dose in Rem should have the same effect.
(1.0)
REFERENCE 10 CFR 20 RPO Notes and Memos p.
ANSWER G.02 (2.0)
A(t) = A(o) e *** - lambda t (0,5)
t=
15 minutes A(t) / A(o) =
100 / 200 = 0.5 (0.5)
lambda = -(In 0.5) / 15 min =.046 / min (0.5)
t = -(In 10/100) / (0.046/ min) = 50 minutes (0.5)
REFERENCE Nuclear Reactor Engineering, Gl ass tone and Sesonske p.
ANSWER G.03 (1.5)
4.
TRUE (0.5)
b.
FALSE (0,5)
c.
TRUE (0.5)
REFERENCE MIT Required Procedures for Radiation Protection p.
20 and 21
.
..
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,
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G.
PADIATION CONTPOL AND SACETY
.
ANSWERS - MITRll - 88/9/21 - ROBINSON, G.
ANSWER G.04 (2.0)
D2 X R2 X R2 (0.5)
D1 X R1 X R1
=
D2 =
(60 nir/hri v 10 4t v 10 4t
= 240 mr/hr (1.0)
5ft x 5ft 40 mr (0.5)
Dose =
(240 mr/he)v 10 min
=
(60 min /hr)
REFERENCE Nuclear Reactor Engineering, Gl as s tone and Sesonske p.
524 ANSWER G.05 (2.0)
a.
G-M "Pancake" detector (0.5)
4, k
...t y, In ( s s e'*A *~ )
b.
tf7=1!M3 automatically closes
" f" J (0,5)
s e /N #'/* b.
(0.5)
ttJ-64 automatically closes Core purge blower is turned off (0.5)
REFERENCE Reactor Systems Manual p.
7.12 ANSWER G.06 (1.0)
Max imum dof>e r a te i5 100 mr/hr (0.5)
(40 min /60 min) x 100 mr = 66.7 mr (0.5)
REFERENCE IV CFR 20.203
.
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l G.
RADIATION OONTPOL.:.ND SACETY ANSWERS - MITR11 88/9/21 - ROBINSON. G.
-
ANSWER G.07 (2.0)
a.
He/she does not exceed 3 Rem per quarter.
(0.5)
b.
His/her radiation histroy is known and recorded on the proper form (Form 4).
(0.5)
c.
The dose received when added to his/her radiation history does not exceed 5(N-18) Rem 2 where N = the person's age at his/her birthday.
(1.0)
REFERENCE 10 CFR 20.101 ANSWER G.08 (2.0)
a.
N-16 comes from 0-16 via a(n,p) reaction.
(0,5)
b.
Its primary h a:: Ar d is the high energy garrena r ay given off (0.5)
c.
NO, (0.25)
because of its short half life (7 sec)
(0.75)
REFERENCE Nuclear Reactor Engineering, Gl ass t one and Sesonske p.
402 i
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ATTACHMENT 2
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U. S. NUCLEAR REGULATORY COMMISSION I
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SENIOR REACTOR OPERATOR LICENSE EXAMINATION t
>
FACILITY:
MIT
,
,
!
]
REACTOR TYPE:
RESEARCH l
DATE ADMINSTERED:
88/09/12
EXAMINhR:
YACHIMIAK.
E.
,
f CANDIDATE CbO A
a i
'
INSTRUCTIONS TO CANDIDATE:
l
!
!
l Use separate paper for the answers.
Write answers on one side only.
'
Staple question sheet on top of the answer sheets.
Points for each i
question are indicated in parentheses after the question.
The passing i
grade requires at least 70% in each category.
Examination papers will
.t
'Je picked up six (6) hours after the examination starts.
f k
% OF i
CATEGORY
% OF CANDIDATE'S CATEGORY
'
VALUE TOTAL'
SCORE VALUE CATEGORY f
l 19.5 o
'
t-20.00-
_ZILD.D.
H.
REACTOR THEORY f
J4.So 20.00 I.
RADIOACTIVE MATERIALS HANDLING
-
x.-
<
DISPOSAL AND HAZARDS l
20.00 20.00 J.
SPECIFIC OPERATING l
CHARACTERISTICS l
16.60
!
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<
20_0^
20.00 K.
FUEL HANDLING AND CORE l
,
l PARAMETERS g
4fMHL 20.00 L.
ADMINISTRATIVE PROCEDURES, CONDITIONS AND LIMITATIONS
!
96.5 I
N
%
Totals Final Grade I
All work done on this examination is my own.
I have neither given i
'
nor received aid.
lD C
4 20
'J7M iO Gg6*
Candidate's Signature l
d'aa.
fu tts)ohkOM o
l Fa;Q3g cond,
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. _ -
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NRC RULES AND GUIDELZNES FOR LICENSE EXAMINATIONS
.
-
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During the administration of this examination the follow.ing rules apply:
'
'1.
Cheating on the examination means an automatic denial of your application i
and could result.4a more severe penalties.
i i
2.
Restroom tripe are to be limited and only one candidate at a time may i
t leave.
You must avoid all contacts with anyone outside the examination
,
room to avoid even the appearance or possibility of cheating.
Use black ink or dark pencil only to facilitate legible reproductions.
,
3.
-
i 4.
Print your name in the blank provided on the cover sheet of the examination.
'
!
5.
Fill in the date on the cover sheet of the examination (if necessary).
l
6.
Use only the paper provided for answers.
i 7.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
i l
l 8.
Consecutively number each answer sheet, write "End of Category __" as j
appropriate, start each category on a new page, write only on one side l
of the paper, and write "Last Page" on the last answer sheet.
l
]
9.
Number each answer as to category and number, for example, 1.4, 6.3.
10. Skip at least three lines between each answer.
I
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11. Separate answer sheets from pad and place finished answer sheets face
j down on your desk or table.
i l
12. Use abbreviations only if they are commonly used in facility litsrature.
>
>
l 13. The point value for each question is indicated in parentheses af ter the l
question and can be used as a guide for the depth of answer required.
,
,
!
14. Show all calculations, methods, or assumptions used to obtain an answer
to mathematical problems whether indicated in the question or not.
I
j 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE j
QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
'
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i 16. If parts of the examination are not clear as to intent, ask questions of i
!
the examiner only.
!
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17. You must sign the statement on the cover sheet that indicates that the j
work is your own and you have not received or been given assistance in
completing the examination.
This must be done o.fter the examination has been completed.
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When you complete your examination, you shall:
a.
Assemble your examination as follows:
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Exam questions on top.
(2)
Exam aids - figures, tables, etc.
(3)
Answer pages including figures which are part of the answer.
b.
Turn in your copy of the examination and all pages used to answer the examination questions.
c.
Turn in all scrap paper and the balance of the paper that you did not use for answering the questions, d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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AEACTOR THEORY Psge
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QUESTIO!1 H.01
'2.00)
a.
WHY is the value of Beta-effective greater than the value of Beta?
(1.00)
tr-WttY aoes the value of Beta-ef fev Livc decrcaou d~uring core 111ct--
'0.50)
c.
WHAT in the source of the neutrons that cause the characteristic-80 second period on a reactor scram?
(0.50)
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QUESTION H.02 (2.50)
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Given that the reactor is suberitical with a Keff of 0.9075 and a Start-Up
<
channel reading 2000 CPS:
a.
WHAT would Keff be after a reactivity addition causes the count rate to increase to 4000 CPS 7 SHOW ALL WORK.
b. Would the reactor be Suberitical, Cricical, or S1percritical if
,
1.59 Beta was added to the 0.9875 Keff core?
SHOW ALL WODK.
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e QUES'fION H.03 (2.75)
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Assume the reactor is on a stable 40-second period.
a.
HOW long (in minutes) will it take to change power level TWO (2)
decades?
SHOW ALL WORK.
(1.75)
b. HOW much reactivity (in Millibeta) has been inserted into the reactor in order to place it on this stable period?
Assume the reactor was just critical prior to this reactivity insertion.
SHOW ALL WORK.
(1.00)
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QUESTION H.04 (1.50)
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a. HOW (Incrersee. Decrease, No Change) does a DECREASE in reactor power affect the Capture Cross Section of U-238 at its resonance energies?
(0.50)
b. WHAT are TWO (2) reasons WHY a neutron whose energy is slightly above the upper limit of a U-238 resonance capture energy will still have a high probability for capture by a U-238 atom?
(1.00)
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QUESTION H.05 (4.00)
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a.
Briefly state the Production AND Removal mechanisms for Xe-135 AND Sm-149.
Include applicable elements and isotopes.
(3.00)
b. HOW (Increase, Decrease, No Change) would Xe-135 affect the the reactor's Actual Shutdown Margin TWO (2) hours after a reactor trip from continuous power operation at > 100 kW7 (0.50)'
c. HOW long does it take Xe-135 to build into a core that has been shutdown l for refueling?
Assume the reactor is run at rated power.
(0,50)
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QUESTION H.06 (2.00)
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a. WHY does the moderator temperature coefficient become MORE negative as the moderator heats up?
b. WHAT are the TWO (2) reasons for the negative reactivity effect associated with an IllCREASE in moderator temperature?
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QUESTION H.07 (2.00)
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a. WHY is D20 (heavy water) used in the MITR-II as a reflector instead of H207 b.
HOW does the D20 reflector produce source neutrons when the reactor is
suberitical?
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QUESTION li.08 (1.25)
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Calculate reactor pow er (in t4W)
Reactor Outlet TemperaturBeactor Inlet Temperature given the following operati ng conditions:
Reactor Primary Coolant Fl
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e 110 F.
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ow Rate -
130 F.
1800 gpm
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WUFSTIOtt H.08 (1.25)
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Calculate reactor power (in MW) given the following operating conditions:
Reactor Inlet Temperature
-
110 F.
Reactor Outlet Temperature
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130 F.
Reactor Primary Coolant Flow Rate -
1800 gpm
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QUE CIOil H.09 (2,00)
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Answer the following questions regarding the design of the MITR-II fuel elements:
a.
WHY must the fuel have a minimum cladding thickness of 0.008 inches?
b. HOW would a thicker clad affect the ability of a fuel element to transfer heat during power operations?
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,' RADIOACTIVE MATERfALS HANDLING DTSPOSAL Page 11
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AND HAZARQS
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QUESTION I.01 (2.50)
a. WHAT THREE (3) conditions would individually activate the "Waste Tanks" alarm on the control room scram par.el?
(1.50)
b, WHERE would water from the Waste Tanks vent to if both tanks were overfilled?
(0.50)'
c. WHAT administrative action prevents an inadvertant discharge from the Waste ".anks to the sewer system?
(0.50)
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QUESTI0ti I.02
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WHAT are the HffdE tei actions AND the Ot1E (1) control room indicatior, which are automatically initiated on a steadily increasing sump level in the equipment room?
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FRSTION I.03 (1.50)
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In accordance with operat,ing procedure 3.12.2. "Procedure for Cell Entry,"
a.
WHAT preventative action must be taken to protect persons from exposure to high radiation levels whenever the LEFT cell is not on use?
(1.00)
b.
WHOSE approval is required prior to entry into the RIGHT cell?
(0.50)
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QUESTION I.04 (2,50)
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Given a gamma source which has a measured dose rate of 100 mR/Hr at 10 feet'
from the source:
a. Calculate how much time must pass (in minutes) until the dose rate at 1 foot will be 100 mR/Hr.
Assume a source half-life of 15 minutes. (1.50)
'
b.
Instead of waiting for the source to decay further, calculate HOW MUCH lead shielding (in centimeters) would have to be used in order to lower
'
the dose rate from 100 mR/Hr to 1 mR/Hr at 1 foot.
Assume a mass attenuation coefficient of 0.189 ?gm/._m0) and a density of 11.34 (gm/cm3).
a (1.00)
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QUESTION I.05 (3.00)
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An irradiated component is surveyed with a portable instrument.
The open window indication is 2.00 R/Hr while the closed window reading is 1.50 R/Hr both at a distance of 18 inches.
a. WHAT is the Beta dose rate at 18 inches from the component?
b. WHAT would be the maxinium time that you could remain at the survey distance without exceeding your 10CFR20 quarterly WHOLE BODY limit?
Assume you are without a Form NRC-4 and have no current exposure this quarter.
Also, assume that you are wearing the appropriate protective clothing / articles.
c. WHAT would your 10 CFR 20 limit for quarterly AND lifetime dose be with a completed Form NRC-47
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WHAT are THREE (3) gases that are removed by the Core Purge (Off-Gas)
System?
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QUESTION I.07 (2.00)
a.
HOW do the gamma-sensitive scintillation detectors detect Tritium leakage into the Secondary Water System from the D20 reflector heat exchanger?
b. WHY must blowdown of the cooling tower basins be secured whenever the
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reactor is not operating?
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QUESTION I.08 (3.00)
a.
In order to receive radioactive material ordered for delivery to the NRL. a member of the operations staff must possess WHAT TWO (2)
qualificatinn 't (1.00)
b. WHAT FOUR (4) actions need to be taken by the individual receiving a radioactive material package?
(2.00)
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QUESTION I.09 (2.00)
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a.
WHAT are the TWO (2) reasons for which an individual may be authorized to incur radiation exposures in excess of the 10 CFR 20 limits?
b.
If time permits. WHAT TWO (2) people should nake the above authoriza-
"
tions?
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QUESTION J 01 (2.25)
Describe the operation of the pneumatic tube system including both the rabbit insertion and ejection processes.
Identify ALL major components in your description.
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QUESTION J.02 (1.50)
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a. WHAT are TWO (2) reasons for having a CO2 purge maintained to the water-cooled, vertical sample thimbles?
(1.00)
b. WHY is it necessary to water-cool the vertical thimbles which are used for sample irradiation?
(0.50)
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QUESTI0!i J.03 (2.50)
a.
Explain the operation of the Anti-Syphon valves (both open and closed positions), specifically addressing HOW tne valve would prevent the complete drainage of the core tank on a coolant pipe break.
b.
Explain the operation of the convection valves during both normal and loss of coolant flow conditions.
Include in your explanation a decription of the coolant flowpaths involved.
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QUESTION J.04 (2.50)
'
Deecribe the operation of a compensated ion chamber AND explain WHY compensation is necessary.
Include in your explanation the power levels at which this detector is used to detect neutrons.
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QUESTION J.05 (2.75)
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a. WHY in 125 volt D.C.
storage battery power needed to prevent simultan-eous closure of the two (2) main 13.8 KV circuit breakers?
(0.75)
'
b. Describe the operation of the emergency electrical power distribution system, including the 5 KVA motor-generator (M/G) set, during both the loss and susequent restoration of normal power.
(2.00)
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QUESTION J.06 (2.00)
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WHAT FOUR (4) actions occur when a major scram pushbutton in depressed?
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QUESTI0tl J 07 (1.50)
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a. When operating at full power. WHAT could result if secondary system temperature dropped to less than 6 degrees C.?
(0.60)
B. WHAT are TWO (2) actions that could be taken to reduce the rate of
secondary system heat removal WITHOUT decreasing reactor power?
(1.00)
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QUESTION J.08 (1.00)
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During a reactor atartup, WHY is reactor power held constant for FIVE (5)
minutes after each 1 MW increase in power level?
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QUESTIO!1 j.09 (2.00)
WHAT are the FOUR (4) requiremento imposed by the "automatic-control-i permissive" circuit which must be met before the reactor can be shifted to
.
automatic control?
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WHAT are 4he FOUR (4) functi a of the Cleanup System?
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,l 5m / FUEL HANDLING AND CORE PARAMETERS Pego 30
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QUESTION K.01 (2.00)
,
During performance of a spent fuel transfer:
a. WHY is the inner door of the main personnel lock left open?
(0.50)
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b. WHAT are TWO (2) locatione in the core tank from which fuel elements may j
be transferred to the transfer cask?
(1.00).
c. WHY in the retlector dumped prior to fuel movement?
(U.50)t
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QUESTION K.02 (3.50)
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a. Describe the construction of the storage racks currently ins';alled in the spent fuel storage pool.
Include in your description the rack's material composition AND the reason for the material's use.
(2.50)
b. WHAT are TWO (2) reasons for using high purity deionized water in the spent fuel storage pool?
(1.00)
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QUESTION K.03 (1.50)
a.
HOW much time must elapse between a reactor shutdown and the removal of fuel from the core if the reactor had previously operated at power levels in excess of 100 KW7 (0.50)
b. WHAT is the Technical Specification basis for the above time constraint?
(1.00)
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QUESTI0ti K.04 (1.00)
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Bolt Cutters are required for the removal of WHAT TWO (2) reactor reactivity control components?
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QUESTION K.05 (2.00)
.
In accordance with PM-3.3.2, "Spent Fuel Removal."
a.
WHAT precaution must be taken by individuals whenever they are performing physical work activities on the reactor top with the reactor top shield lid removed?
b.
WHAT action must be performed on Nuclear Instrumentation Safety Channels 5 and 6 before a full power startup may be initiated?
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CATEGORY K CONTINUED ON NEXT PAGE *****)
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QUESTION K.06 (3.00)
.
Give the basis for each of the following Technical Specifications:
a.
The reactivity worth of the regulating rod connected to the automatic control system is less than 1.8 % delta k/k.
b. The maximum controlled reactivity addition rate is no more than:
-4 5 X 10 delta k/k/second, c. The reactivity worth of the D20 reflector dump is greater than the reactivity worth of the most reactive shim blade.
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WHAT are FOUR (4) conditions that could actuate a Spent Fuel Storage Pool (SFSP) alarm?
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QUESTIOt1 K.08 (1.50)
.
In accordance with PM-1.15
"Refueling,"
a.
WHAT TWO (2) individuals must sign the Fuel Loading Verification record and Fuel Loading Permission Form?
(1.00)
b.
Prior to exceeding WHAT power level must the Fuel Loading Verification record be signed by the two above individuals?
(0.50)
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QUESTION K.09
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a.
WHAT Fuel Element Assembly design characteristic enables the fuel to achieve a more complete burnup?
(0.50)
b.
For a Fuel Element Assembly which has-4eaded witn an incressed amount of U-235, a.:pla in tion of a Burnable Poison limits
'
the initial incre:r er e reactivity worth associated with the f)
element t '. ' allows for an increase in the element's overall b
(1.50)
.
c.
HOW does the loading of Hafnium, fixed, neutron-absorber plates on the absorber spider assembly affect the core's nuclear flux / power?
List TWO (2) effects.
(1.50)
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QUESTION L.01 (2.50)
a. WHAT are THREE (3) reasons wny all positions in the core tank must be filled and secured with either a fuel element or another approved unit before operating at full power is allowed per Technical Specificationo?
(1.50)-
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b.
In accordance with Technical Specifications WHY are at least FIVE (5)
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operable shim blades required to be within 2.0 inches of a banked (average shim blade height) position when the reactor is at power levels; of greater than 100 kW7 (1.00)1 l
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QUESTION L.02 (2.50)
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a. WHAT THREE (3) reactor parametere have indication which is taquired to be supplied by emergency power whenever the reactor is operating? (1.50)
b. WHAT are the TWO (2) reasons that the use of eAerge.ncy power is probably not necessary for the MITR-II7 (1.00)
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QUESTI0ti L.03 (1.50)
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a.
WHAT reactor building pressure relief system interlock must be satisfied before a reactor startup can be conducted?
(0.50)
b. The reactor building overpressure scram is installed to scram the reactor at less than 3.0 inches of H20.
WHAT is the basis for the value of this setpoint?
(1.00)
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QUESTI0t1 L.04 (3.50)
a.
WHOSE permission is required before a warning tag can be posted AllD WHO may post a warning tag?
(1.00)
b. WHAT are FIVE (5) requirements which must be observed when "locking out" facility equipment AFTER permission is granted?
(2.50)
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QUESTIO!1 L.05 (1.50)
In accordance with 10 CFR Part 50.54(x), under WHAT conditions can an operator take reasonable action that departa from a license condition or a Technical Specification?
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QUESTI0t1 L.06 (1.00)
WHOSE approval is required before Temporary Changes to Class B or C procedures may be made?
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QUESTION L.07 (2.00)
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a. Whenever jumpers are used to bypass safety functions. WHERE must,a warning tag be placed so that the reactor is not started until the l
bypass is removed?
!
b.
In WHAT condition can the reactor be in when Safety Functions, which are required by Technical Specifications as a Limiting Condition for Operation, are to be bypassed for testing purposes?
c. HOW many individuals are required to check the physical installation of
.
a jumper after it has been installed?
'
d. TRUE or FALSE:
Safety Functions which are bypassed during a normal startup by key
,
switches on the scram panel are logged onto the Bypass Log Sheet?
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QUESTION L.08 m
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a.
Using Attachment 2, classify, i f applicable, each of the' events listed below in accordance with PM-4.4, "Emergency Classification System."
y9 nn)
(/ oo)
1. An experiment using bottled hydrogen gas beycomaa an====A vaaniting in!
l
_
the unenn+-ellcd seiease of the gas from its container.
/q 4 c'
2. A train derailment ra-ulte-lu che complete rupture or both liquid A durage tanks whien. were full at the time of the accident.
3. The MIT Campus Police inform you that an anonymous caller has just
,
threatened to damage the reactor building.
4. An automatic reactor scram from full power occurs due to the tripping-of a primary coolant pump.
b. Within HOW many hours after an Alert is declared must the NRC be notified?
(0.50)
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Page 48
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QUESTION h.60)
WHAT H.01
,'2.00)
the{
safe Tune of the greater relativa nhi 14 +y M dalaved neutrons to cause
-
Fael fi UJ due to their lower birth energies (0.50]
.
probability for fission)
mniu: buildup [ 0. SG-]
11no-87 (longest lived neutron precursor) [0.50]
a. Gec-
&Ca J x d w>w Race O'
- Reactor Physica Hotes v & hG - s s h a d fo &> y M a y & m itw>w y.Qrei/nf H.02 (2.50)
,
'CR1 = 1-Kef f1/1-Kef f 2 (0.25]
1/2000 = 1-0.9875/1-Keff2 (0.50]
MO8
%wed.
.
C2 = 0.99375 (0.50]
= 1.59 (Beta) * 0.00786 [0.50]
ha<pVJ Co.Sp]
= 0.0124974 F' = 0.9875 + Rho f = 0.9999974 (0.25]
- oximately critical (0.50]
>
t r Reactor Physics Notes H.03 (2.75)
l Po * 10 - (SUR* time) (0.25]
= 26.06/T [0.25]
= 26.06/40 = 0.6515 (0.50]
100 (0 25]
i=
i
= 10 * (0 J515*t)
i = 2/0.6515
= 3.07 minutes (0.50]
(Bata - Rho)/(Rho *1ambda) [0.25]
=
i = (1.0 - Rho)/(Rho *0.1) (0.25]
[
= 200.0 Millibeta (0.50]
,
Roactor Physics Notes
!
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1,11 * REACTOR THEORY Pago 49
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ANSWER H.04 (1.50)
a.
Increase (due to less broadening) [0.50]
b.
- the neutron will loose very little energy in its collision which will place it right at the resonance capture energy (0.50]
- the neutron is in the fuel where most of the material is U-238 atoms which makes them more likely targets for collisions (0.50]
REFERENCE MITR-II Reactor Phyoics Notes ANSWER H.05 (4.00)
a.
Xe production:
directly from fission (0.50]
(Beta) decay from I-135 [0.50]
Xe removal:
(Beta) decay to Cs-135 [0.50]
neutron absorption (burnout) to Xe-136 [0.50]
Sm production:
(Beta) decay from Pm-149 (0.50]
Sm removal:
neutron absorption (burnout) to Sm-150 [0.50]
b. Increases [0.50]
c. 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> (0.50]
REFERENCE
'AITR-II Reactor Physics Notes ANSWER H.06 (2.00)
a.
because the rate at which water expande (0.50] increases with temperature (0.50]
b.
increased leakage (0.50]
neutron spectral shift (0.50]
REFERENCE MITR-II Reactor Physica Notes ANSWER H.07 (2.00)
a, because of its lower thermal neutron absorption cross-section (1.00]
b. photo-neutron production (0.50] by gamma rays (0.25]
from fission product decay (0.25]
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- RE%CTOR THEORY Poco 50
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REFERENCE MITR-II Reactor Physics Notes ANSWER H.08 (1.25)
Q = M*Cp*(T2 - T1) [0.25]
1800 * 8.345 * 60 * 1.0 * 20 (0.50]
=
= 1.8025 E+7 (BTU /Hr) / 3.42 E+6 Q = 5.286 MW [0.50]
RFFERENCE MITR-II Technical Specifications ANSWER H.09 (2.00)
a.
to prevent the release of radioactive fission gas into the reactor coolant [1.00]
b. it would increase the delay time for heat removal [0.50] on rapid power increases [0.50]
REFERENCE MITR-II Technical Specifications 5-4 (*****
END OF CATEGORY H *****)
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a
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j a. fitm 900 eper-a leak from the tank
[3 X 0.50]
!
ambient temperature <= 32 F.
b. the stack (0.50]
l c.
the final valve in the discharge path is kept locked closed (0.50)
REFERENCE
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,
({.60
^
I ANSWER I.02 F2. 0 04
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h pump one starts (0.50]
j r :p tu: eterte (0.50)
inlet city water isolates (0.50]
"Leak Primary D20 System" annunciator alarms (0.50]
,
REFERENCE
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!
}
a. door must be closed (0.50] and locked (0.50]
b. MITR Radiation Protection Officer (0.50]
2 REFERENCE l
i PM-3.12.2 pages 1,2
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If. * RADIOACTIVE MATERIALS HANDLING DISPOSAL Page 52
&BD HAZARDS
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ANSWER I.04 (2.50)
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a. D1 * (R1)'2 : D2 * (R2)'2 (0.25]
l 100 (mR/Hr) * 10'2 (ft2) = D2 * 1 2 (ft2)
D2-10,000 mR/Hr (0.25]
A = Ao * e (-lambda * time) [0.25]
lambda = In2 / half-life (0.25]
lambda = 0.04621 (1/ minutes) (0.25]
100 (mR/Hr)
= 10,000 (mR/Hr) * e (-0.04621 * time)
time : 100 minutes (0.25]
,
b. I = Io * e (-mu * X) (0.25]
mu =,5/ mass attenuation coeficient * 11.34 (gm/cm3) (0.25]
,
mu : 00 (1/v=) [G.2G]
g,f y ggc gg} (gg
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i =
100 * e (,etr * X ) g
X = 0.0?"S ( c;. )
(^ 25]
2' lb (6*) CP'25-]
REFERENCE
,
MITR-II Reactor Physics Notes i
I ANSWER I.05 (3.00)
- !
t
!,
a. open window - closed window (0.50]
2.00 - 1.50 = 0.50 R/Hr (0.50]
l j
b. 1.25 R/Qtr (0.50]
!
1.25 / 1.50 = 50 minutes (0.50]
c. 3 R/Qtr (0.50]
5(N-18) R (0.50]
J.
REFERENCE 10 CFR 20.104 l
!
]
ANSWER I.06 (1.50)
!
N-16 I
j Ar-41 (3 X 0.50]
!
l Hydrogen i
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j REFERENCE i
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RSM-3.2.5 a
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I.* ' RADIOACTIVE MATERIALS HAFJLING DISPOSAL Pago 53
AND HAZARDS
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ANSWER I.07 (2.00)
a.
by detecting the presence of H-16 [0.50] and F-18 [0.50]
b. because of the short lived half lives of the detector sensitive isotopus which are used for tritium detection [1.00]
REFERENCE RSM-7.4.1 ANSWER I.08 (3.00)
a. NRC SRO license [0.50]
shift supervisor qualifications [0.50]
b.
- notify the Radiaction Protection Officer
- check package for DOT compliance
[4 X 0.50]
- perform a survey
- check shipping papers against purchase order REFERENCE
'
PM-1.10 page 18 ANSWER I.09 (2.00)
a. to save a human life [0.50]
to ensure nuclear safety [0.50]
b. Director of Reactor Operations [0.50]
MITR Radiation Protection Officer [0.50]
REFERENCE PM-4.3 page 14 I
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'Sp2CIFIC OPERATING CHARACTERISTICS Page 54
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ANSWER J.01 (2.25)
When a rabbit is inserted, solenoids (0.25] operate in such a manner that a vacuum (0.25] is channeled betwaen the inner and outer tubes (0.25]
Because there are perforations in the end of the inner tube, (0.25]
the opening of a solenoid which applies atmospheric pressure to the outer tube (0.25] causes a differential pressure to exist across the rabbit, (0.25] propelling it to the in-pile limit (0.25]
.
The operation is reversed by another set of solenoid valves in order to eject the rabbit [0,50]
REFERENCE RSM-2.10 ANSWE9 J.02 (1.50)
4.
reduce Argon-41 production (0.50]
prevent nitric acid formation (0.50]
b. gamma heating (0.50]
REFERENCE RSM-2.9 ANSWER J.03 (2.50)
a. During normal conditions, the valves are closed by hydraulic pressure lifting the balls upward (0.25]
On a pipe break, the balls drop by gravity opening the valve (0.25]
Water then flows out of the core tank and out the break (0,25]
This continues until the water level drops to
,
the top of the valves, (0.25] when the flow of water is stopped by air intrusion into the valves (0.25]
b. During normal conditions, the valves are closed by hydraulic pressure lifting the balls upward (0.25]
When core flow stops, the balls drop by gravity [0.25] allowing cold water (0.25] to flow downward through the valvns (0.25] and up through the core (0.25]
REFERENCE
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)
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f ANSWER J.04 (2.50)
B10 (n, alpha) Li7 (0.75)
!
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the charged products create ion pairs (0.25)
{
'
in the counting gas (N2) (0.25) which are seen as pulses l
by the detector (0.25] the detector also detects gamma rays (0.25]
[
'
so these must be compensated for by another ion chamber without
~
!
the B10 lining (0.25] this signal is then. subtracted from the i
!
B10 lined ion chamber's signal (0.25)
l the detector is good for intermediate (0.25] and full power levels (0.25)
i r
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i REFERENCE l
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RSM-5.3 i
"
!
i ANSWER J.05 (2.75)
j a.
'
because it supplies power to operate a motor-driven interlock (0.75)
t i
b. the emergency lighting panel transfer switch immediately connects to
'
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battery power (0.50)
the M/G set starts immediately (0.25] but is delayed from loading
}
through a transfer (0.25] for 12 seconds (0.25)
';
on restoration of power all transfer switches return to their normal
!
positions (0.50) and the M/G sct is stopped (0.25)
!
i REFERENCE
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RSM-8.31,8.32
,
!
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i ANSWER J.06 (2.00)
f
.
- the ventilation is secured I
- the containment shell is sealed
- the top part of the D20 reflector is dumped (4 X 0.50)
?
- the withdrawal permit circuit is interrupted l
caursing the shim blades to drop
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RSM-9.8
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,J. * SFECf FfC OPERATING CHARACTERISTICS Page 66
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ANSWER J 07 (1.50)
a.
D20 freezing could occur [0,50]
b.
- shift cooling tower fans to low speed
- adjust cooling tower slats
[2 X 0.50]
- bypass flow to basins REFERENCE PM-5.4.6 ANSWER J.08 (1.00)
to allow the reactor core and primary coolant to approach thermal equilibrium [0.50] thereby reducing stress on the fuel element and cladding [0.50]
REFERENCE PM-2.3.1 l
.
ANSMER J.09 (2.00)
- all shim blades must be above the suboritical interlock position
- the deviation between power-set and actual power must not exceed 1.5%
- the regulating rod control switch must be in the neutral position
- the regulating rod must be withdrawn beyond its near-in position
[4 X 0.50]
REFERENCE BSM-4.4
'
ANSWER J.10 (2.00)
.
maintain the purity of the primary H2O
-
t
- maintains core level by means of a continuous overflow
[4 X 0.50)
provides for a nurge volume
-
provides cooling flow through the H2O medical shutter tank
-
f/tO t <C b p
& C d UMUd
~
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K '. ' FUEL HANDLING AND CORE _2ns. ct"EE Pago 58
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ANSWER K.01 (2.00)
a.
to prevent personnel entry into the reactor building (0.50]
b.
fuel storage ring (0.50]
transfer basket (core flow guide) [0.50]
c.
ensure adequate shutdown margin (0.50]
REFERENCE PM-3.3.1 page 2 PH-3.3.2 pages 3,4 ANSWER K.02 (3.50)
a. five by five (seven by seven) matrix of open-ended boxes (0.50]
in an aluminum frame (0.50]
OA Ca cl>we lft4 M made of aluminum-cadmium-aluminum sandwich (0.50] cA. CC4%twn b. [
,
,
used for corrosion resistance (aluminum) (0.50]
neutron absorption characteristics (cadmium) (0.50]
b, decay heat removal (0.50]
shield personnel from gamma radiation (0.50]
REFERENCE RSM-8.38 ANSWER K.03 (1.50)
a.
four (4) days (0.50]
b.
prevent melting from afterheat (1.00]
REFERENCE HITR-II Technical Specifications 3-39 ANSWER K 04 (1.00)
regulating rod absorber (0,50]
control (shim) blade (0.50)
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K '. * FUEL MANDLING AND CORE PARAMETERS Pago 59
,,
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, REFERENCE PM-3.4.1.3.4.2 ANSWER K.05 (2.00)
a.
check that there are no loose or unattached items in their clothing (affix loose iteme with tape) (1.00)
b.
low power safety amplifiers must be replaced by full power safety amplifiers [1.00)
REFER 3NCE PM-3.3.2 ANSWER K.06 (3.00)
the t>tal worth of the rod is to be limited such that the complete a.
althdrawal of the rod will not 4aab the re-+ne-prompt Q,1)
cause fuel damage (1.00]
b.
in the event of an accidental continuous insertion of react $vity at the above maximum rate, the response of the reactor safety system period and level trips will adequately protect the reacter [1.00)
c.
the additicnal independer, apability for reactivity control provided by the D20 reflector dump gisis added assurance that the reactor can be made suberitical under an adverse condition of fuel loading or control blade malfunction [1.00)
REFERENCE MITR-II Technical Specification 3-32 thru 3-35 ANSWER K.07 (2.00)
- loss of power to the SPSP control and alarm panel-a leak from the pool
- low SFSP water level.
(4 X 0.50)
- low flow thru the SFSP ion exchanger REFERENCE PM-5.7.12. "Spent Fuel Storage Pool,' page 1 (*****
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ANSWER K.03 (1.50)
a.
senior reactor operator [0,50]
,
.aperintendent [0.50]
!
b.' /.0 KW [0.50]
!
REFERENCE j
PM-1.15
!
'
10C
!
ANSWER K.09 Af. 50 }-
I a.
it is axially symmetric [0.50]
b. The burnable poison has a high abas, t.4 -
r s-section for thermal
!
'3 neutrons (0.50] co its negative cat T"
.rth initially compensates i
a i
for the raactivity wort e added JL,0.25]
.
g6 After the poiso r a a neutron, it is.nermanently removed from the
,'
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competi rocess [0.50]
!
T echanism delays the decrease in reactivity worth of the fuel
!
element, thus increasing its life (burnup) [0.25]
c. maximizes [0.25] flux and power (densitits) [0.25] in the lower half of l
the core (0.25]
!
minimizes (0.25] power (peaking) [0.2b]
in the top half of the core (0.25]
RSFERENCE RSM-1,3,1.4 PM-3.3.1 (*****
END OF CATEGORY K *****)
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l ff * ADMINISTRATIVE PROCEDURES, CONDf11QHE Page 61
MD LIMIMllQb3
,,
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ANSWER L.01 (2.50)
a.
prevent mechanical damage to the components (0.50)
prevent core reactivity changes due to movement (0.50)
assure proper flow distribution and cooling (0.50)
(ensure validity of safety limits)
b. so as r.ot to appreciably affect core power distribution (1.00)
(hot channel factor or peaking factor)
REFERENCE MITR-II Technical Specifications 3-41
.
ANSWER L.02 (2.50)
a.
neotron flux main tank coolant level
[3 X 0.50)
!
primery coolant outlet temperature i
b. loss of power automatically scrams the reactor (0.50)
coolant will still cover the core (melting will not occur) [0.50]
i REFERENCE
,
!
t
)
HITR-II Technical Specifications 3-23 i
a f
I
ANSWER L.03 (1.50)
I minimum negative differential pressure (0.50)
a.
i b. prevent reactor scram en momemtary low positive pressure (0.50) which may occur after a ventilation shutdown (0,50]
.
REFERENCE I
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L.
CONDITIONS Page 62 AND LIMITATIONS f
.
ANSWER L.04 (3.50)
a.
on duty console operator (0.50]
any member of the NRL/RPO staff [0.50]
b.
- SB0 will witness lockout i
- SRO will verify safe system condition (any 5 @ 0.50 each)
- person performing work will perform lockout
- person performing work will retain the key on his person
,
- a notation as to the system being locked out shall be made on the status board the system must be tagged out
-
REFERENCE I
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PM-1.14.3 ANSWER L.05 (1.50)
in an emergency (0.50)
.
when the action is neede.d to protect the public health and aafety,*[0.50]
,
and no other action is immediately apparent (0.50]
REFERENCE l
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ANSWER L.06 (1.00)
two (2) reactor staff members (0.50) one (1) of whom ehall hold an SRO license (0.50]
a
'
REFERENCE PM-1.5
t ANSWER L.07 (2.00)
,
a. on the shim blade control handle (0.50]
b. shutdown (0.50]
c. two (2) (0.50)
d. FALSE (0.50)
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AHD LIMITATIONS
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PM-1.9
/,5o)
ANSWER L.08
_
Rnt (9
a. f. n i e cx, _
kbD unw nrea
.
3. Unusual Event Q X 0.50)
f 4. No Classification i
b. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (0.50)
(
REFERENCE
!
!
PM-4.7.1 i
PM-4.4
-
i
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t ANSWER L.09 (3.00)
if the probability of occurrence or the consequence of an accident or l
-
malfunction of equipment important to safety previously evaluated in the
!
SAR may be increased [1.00]
i
-
if a possibility for an accident or malfunction of a different type than
any evaluated previously in the SAR may be created (1.00)
!
if the margin of safety as defined in the basis for any Technical
!
-
Specification is reduced (1.00)
!
t REFERENCE i
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ATTACHMENT 3
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Facility Comments on RO Exam. 12 Sept. 88
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A.02 Source is not installed.
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A.04 At 298 kW, the temperature change is still insignificant.
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The period would still be 60 seconds.
(Not e,:
PM 2. 3 p. 3
does give 100 kW as the point of adding heat.
We shift to
cooling towers at 250 kW and begin seeing temperature effects
on the approach to 1 MW.
PM 2.3 p.3 is in error.)
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j B.02(a) Also, avoid activation of argon, and Provide inert medium for transport of disassociated D /02 CO
recoebiner.
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C.04(c) Answer should be
'In'.
On floodin5 which would be with D 0, l
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(If light wate r
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flooded it, the answer is correct, but the blister tank is
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surrounded by heavy water.)
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D.03(c) Must have 1800 gpa for full power operation.
For 100 KW operation, not required.
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I E.03(a) Should be flow ' guide' not ' shroud'.
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E.03(b) Typo
' bank' should be ' tank'.
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E.07(c) Current setpoint is 95 gps.
It varies, but is always above
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minimum required of 75 gps.
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F.03(d) Refer to PM 5.2.1 and PM 5.5.4.
Neither requires an immedi-l q
F.03(e) ate shutdown.
Both allow time to investigate and both
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require shutdown by ARI if certain conditions exist.
Not
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c.05(b) MV-83 and MV-64 are referred to as the ' solenoid valves'.
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I Memorisation of valve numbers is not required.
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Facility Comct nts on SRO Exam. 12 Sept. 1988
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H.Ola Concur that I5 > 8 because of their lower birth energies.
As a result they have a lower probability of undergoing fast neutron leakage and to a lesser extent resonance capture.
So, we agree with giving credit for "lower birth energies".
We disagree with giving credit for 'cause thermal fission'
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because once thermalized both prompt and delayed have same
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probability of causing fission.
H.02b The MIT Reactor uses fully enriched fuel.
There is very (
little U-238 and hence little plutonium buildup.
Beta-effec-tive does decrease on the MITR-II with core life because the
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blades are withdrawn further making the effective core volume
larger.
Hence, there is less leakage of prompt neutrons.
l Recall that from fH.Ola, the principal difference between j
prompt and delayed neutrons is the leakage probability.
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thing that decreases leakage decreases that difference.
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Problem could be
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H.04a Reason given in answer (less broadening) is correct but the effect is to decrease (not increase as indicated in the i
answer) the capture cross-section.
Also, MITR fuel tempera-
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ture varies only over a range of 30*C from zero to full i
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So, the effect is quite small.
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ing out xenon.
So, the answer should be 'No Change'.
If the
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question meant "by how much would the reactor be shutdown",
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then the answer is ' Increase'.
(Notet Believe this point of
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l H.08 Question should provide value for specific heat of water.
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1.01a Typo in answer.
It should be ' level' not ' flow' greater than
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900 gallons (not gpm).
I.02 The sump system was recently modified. There is now only one pump.
I.04b Typo on units.
Shot:1d be 0.189 cm / gram.
Hence, in solu-tion, multiply by density instead of dividing.
Answer is about 2 cm.
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I.09b Note:
Director of Operations and Emergency Director may be the same person.
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J.05a The 13.8 KV breakers are the property of the Cambridge
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Electric Company.
The Reactor Staff is not allowei to operate them.
Hence, question is not relevant.
J.10 Also provides shutdown cooling (decay heat removal) when reactor is shutdown.
This is a fif th function of the cleanup system.
RSM 3.2.6.
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K.Olb Answer is correct but note that fuel must go from the storage
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ring to the basket.
It can not go direct from the storage ring.
K.02 Currently two types, of boxes.
One is aluminum-cadmium-aluminua, the other is cadmium-lined.
K.06a A 1.8% delta K/K insertion will acke the reactor prompt critical.
The answer should be that such an ir.sertion will not cause a transient that is beyond the capability of the safety systen to shut down the reactor before fuel damage occurs.
K.08 The answer is correct but the question's wording is confua-ing.
The safety and operating limits must be verified before going above 1 KW.
The SRO and Superintendent sign for doing that evaluation.
K.09a Also, radially symmetric.
K.09b The MIT Reactor does not use burnable poisons.
K.09c Answer is correct but inserts are currently made of boron stainless steel.
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L.02b Also, mh aum required equipment is provided by self-
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contained power supplies.
L.03 Answer given is correct.
However, please see also PM 5.5.7,
"Building Overpressure", which gives other f actors involved ia cilecting the set point.
L.06 Must be two licensed reactor staff members, one of whom holds an SRO license for Class B.
For Class C, could be two staf f members, one of whom has an SRO.
L.08 At tachment Two was PM 4.4 page 1-5.
These pages provide general advice and they are not the EALs given in the proce-dures. Hence, this question is diffie. ult te grade.
Comments are as follows:
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(1) An H release would be an event.
The probability of
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problem has been increased, but no radiation release has j
occurred.
(2) A waste tank rupture would be an alert.
A radiation release has occurred, it is limited in extent by the finite tank volume, and it is well below levels for site
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emergency.
Waste tank activity is never more than a few mil 11 curies, if that.
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(3) This is an event as per written MITR procedures (The EALs).
(4) Not classified.
Falls within scope of AOPs.
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ATTACHMENT 4 o
NRC Response to the Facility Coments A.02 Coment is valid and point count will be distributed as indicated in the answer sheet. The answer sheet anticipated this comment.
A 05 Coment is accepted. Answer key will be changed.
B.02a Coments are accepted.
Answer key will be changed to include these answers.
C.04c Coment valid. Answer key will be changed.
D.03e Comer,6 valid. Answer key will be changed.
E.03a Coment accepted. Answer key will be changed. Suggest change be made to Reactor Systems Manual p. 3.5.
E 03b Coment valid. Answer key will be changed.
E.07c Coment accepted. Answer key will be changed.
F.03d The question states that no other abnormal condition occurred, therefore F.03 (d) answer is NO SHUTDOWN REQUIRED (error in answer key).
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F.03e The question states that no other abnormal condition occurred.
l therefore F.03 (e) answer is NO SHUTDOWN REQUIRED (answer key is correct).
G.05b Coment is accepted. Answer key will be changed.
H.01a The answer key w[0.50] which results in fewer delayed neutrons from as changed to:
"because delayed neutrons have lower birth energies being]lostfromtheneutroncycleduringthethermalizationprocess l
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H.0lb The question was deleted due to the lack of a reference. The value of the question was reduced by 0.50 points.
H.03 Either method is acceptable and since the answer does not change, no change was made to the answer key.
H.04a No changes were made to the answer key. The answer is correct, j
(Increase), since at the resonance energies the capture cross section Increases at lower tenperatures. refer to Figure 4-2b.
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-2-o H.05b The answer key was not changed because the candidate was informed during the examination that Actual Shutdown Margin was "the amount by which the reactor would be shutdown."
1.01a The answer key was changed to: "level 900 gallons." Please revise
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RSit-8.20 to correct this error.
I.02 The answer key was changed and the value of the question was reduced by 0.50 points.
Please revise RSM-8.19 and any applicable drawings.
I.04b The answer key was changed to reflect the typo in this question.
The correct answer is 2.15 cm.
I.09b The answer key was not changed because the reference material indicates only two (2) individuals: the Director of Reactor Operations (DRO) and the Radiation Protection Officer (RPO).
However, if the full energency organization is activated, then the DRO is the Emergency Director.
J.05a The answer key was not changed because the 13.8 KV circuit breaker motor-driven interlock is one of the loads which is directly supplied off the 125 VDC battery supply.
J.10 The answer key was changed to include a fifth correct answer:
"provides for decay heat removal."
K.02 The answer key was changed to accept both answers for full credit.
K.06a The answer key was changed by deleting the non-required, bracketed portion of the answer. The answer is still correct since the SAR shows that a 1.8% delta K/K is the limit for a step reactivity insertion without fuel damage occuring.
K.09a The answer key was not changed because axially syrrnetric is the only answer which could be referenced.
K.09b The questien was deleted thereby reducing the value of the question by 1.5 points. Please revise RSM-1.4 to reflect this non-use of burnable poisons.
K.09c The question, if used in the future, will be revised accordingly.
L.02b The answer key was not changed because a reference for the alternate answer was unavailable.
L 03 The corrent was reviewed but all other alternate answers did not have adequate justification to qualify them as a basis for the scram setpoint.
The answer key was not changed.
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L.06 The answer key was not changed since the Class B criteria are more stringent.
L.08 The question should have included PM-4.5, "Emergency Action Levels."
L.08a and L.08b will be deleted because of inadeqaute informatien.
The value of the question was reduced by 1.00 points.
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