ML20150D811
| ML20150D811 | |
| Person / Time | |
|---|---|
| Site: | Reed College |
| Issue date: | 06/22/1988 |
| From: | Elin J, Meadows T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20150D810 | List: |
| References | |
| 50-288-OL-88-02, 50-288-OL-88-2, NUDOCS 8807140154 | |
| Download: ML20150D811 (186) | |
Text
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Enclosure (1)
U. S. NUCLEAR REGULATORY COMMISSION REGION V EXAMINATION REPORT Examination Report No.: 50-288/0L-88-02 Facility Licensee: Reed Reactor Facility Reed College Portland, Oregon 97202 Facility Docket No.: 50-288 Facility License No.: R-112 Examinations administered at Reed College, Portland, Oregon Chief Examiner: J# ~
X W .~4 du// 7 Thomas R. Meadows Date Signed l
Approved by: _
/ @9 :
Joyh 0. Elin, Chief, Operations Section Fape Sig(1ed Sumary:
Written examinations were administered to six (6) R0 candidates and one (1) SR0 candidate on May 17, 1988. The operating examinations were administered May 18-19, 1988. The SR0 candidate passed all portions of the examination.
Three (3) R0 candidates passed all portions of their examinations. Two(2)RO candidates failed their respective written examinations, whila passing the operating portion of the examination. The other R0 candidate failed all portions of the examination.
8807140154 R 880623 y ADOCK 05000208 PNU
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REPORT DETAILS
- 1. Examiners:
Thomas Meadows, RV, Chief Examiner Leo Defferding, PNL
- 2. Persons Atter. ding the Exit Meeting:
NRC:
T. Meadows, RV t
Reed:
M. Pollock, Associate Director, Reed Reactor Facility Paul Terdal, Senior Reactor Operator (Supervisor, Reed Reactor Facility)
David Griffiths, Physics Professor (ROC Chairman)
- 3. Written Examination and Facility Review:
Written examinations were administered at Reed College on May 17, 1988.
At the conclusion of the examination, copies of the R0 and SR0 examinations and associated keys were provided to Mr. M. Pollock, Associate Director, Reed Reactor Facility to coordinate the licensee's formal review. The R0 examination was reviewed by Mr. Pollock, while the SR0 examination was reviewed by both Mr. Pollock and Mr. Terdal of the Facility staff. On May 20, 1988 the Chief examiner met with the Facility reviewers to consider the Facility coments that resulted from their review.
The review comments were endorsed by the Vice President / Provost, Dr. Marshall Cronyn, and subsequently forwarded to Region V. This document is included in this report along with the NRC resolutions of these comments for both the SR0 and R0 examinations, respectively (Attachments A and B). The SR0 and R0 master examination keys were revised, as described in Attachments A and B to this report, prior to grading the candidates responses.
- 4. Operating Examination:
The operating examinations were administered May 18-19, 1988. An improvement in the licensees operating procedures, primarily SOP's 70 and 71 (Completing the Weekly and Bimonthly Checklist) reflected in the overall improved performance of the Reactor Operator candidates during their oral examinations. The candidates were more familiar with equioment location and operation.
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However, it was also noted that many of the Facility's procedures still have not been upgraded since the last replacement examination cycle.
For example, S0P 01, "The Start UP Check List", is not a checklist at all. It reads like an academic text book that duplicates material covered in the Administrative Procedures, Health Physics Procedures, and Technical Specifications. The examination team noted that none of the candidates referred to this procedure during the actual reactor startups performed in the course of the examinations. This in itself is not contrary to safe operating techniques at a research facility, but does reflect on the inefficacy of some of Reed's procedures.
In the course of an oral examination, during an actual reactor startup on May 18, 1988, the Reed Reactor Facility experienced an actual "Station Blackout". Due to a rain storm and associated high winds all incoming electrical power was lost. The only lights that were available in the Reactor Facility came from emergency battery powered lanterns positioned in the reactor bay and exit corridor. All power was removed from the operating console and the control rods imediately dropped into the reactor core as designed. However, the Chief Examiner noted that the only licensed operator on shift (the SRO) imediately left the control room area to check the major electrical supply breaker in the Chemistry building (Room 7). It took approximately 15 minutes for the SR0 to return to the reactor bay and actually verify the control rods inserted. Although this action was not contrary to Reed's Emergency Plan, it would seem good practice to verify the reactor shut down before leaving the reactor area.
- 5. Exit Meetino:
At the conclusion of the site visit on May 20, 1988 the Chief Examiner met with representatives of the plant staff to discuss the examination.
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Attachment A Page 1 of 2~
NRC Resolutions of the Licceee Examination Reviets of the May 17, 1988 SR0 Written Examination, at Reed College.
Question H.04.
Coment:
See the attached Licensee's coment on Question H.04.
Resolution: Coment accepted.
After reviewing the new documentation supplied by the Licensee with their attached formal coments, the examiner agrees that answers "b" or "c" could be plausible answers. However, two (2) correct answers in a four (4) part multiple choice question reduces the knowledge determinant to a mere 50 f.
probability, therefore, this question is eliminated. The Examination and Answer Key have been appropriately adjusted.
Question I.15 Comment:
See the Attached Licensee's coment on Question I.15.
Resolution: Coment accepted.
The licensee points out that the Eberline E-140 could be used with a scintillation detector designed to operate at 900 volts. Although this is not the case at Reed, the examiner agrees that it is plausible. Therefore, tfie examiner agrees with the licensee's coment. However, two (2) correct answers in a four (4) part multiple choice question reduces the knowledge determinant to a mere 50% probability. This is not acceptable, therefore, this question is eliminated. The Examination and Answer Key have been appropriately adjusted.
Question L.01(c)
Comment:
l See the Attached Licensee's coment on Question L.01(c).
Resolution: Coment accepted. 1 The Licensee points out that the Reactor Health Physicist is "in practice" an "ex-officio, non-voting member of the RRC". The justification for this is {
given in the description of the Health Physicist duties, in accordance with i Reed's Administrative Procedures. Comensurate with this documentation 3
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{
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Attachment A Page 2 of 2 clarification, the examiner agrees with the Facility comment and will also accept "Health Physicist" as a valid answer for Question L.01(c). However, the total question worth will remain 1.0 point. The examination KEY has been modified per this evaluation.
Question L.01(d)
Comment:
See the attached licensee's coments on Question L.01(d).
Resolution: Coment not accepted.
The facility Administrative Procedures are vague and confusing, subsequently open to various "interpretations". Consequently, the question STEM does not directly quote the reference material. Therefore, it is not appropriate to say that the licensee's procedures were "misquoted". The examiner believes that the wording in the stem of the question clarifies the intent of the Referenced Procedures (and Technical Specifications), and subsequently makes the answer key response the only plausible answer.
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Attachment B Page 1 of 1 i
NRC Resolutions of the Licensee Examination Review of the May 17,1988 R0 L'ritten Examination, at Reed College Question A.08 Coment:
See the Attached Licensee's Coment on Question A.08.
Resolution: Ccment accepted, t
After reviewing the new documentation supplied by the Licensee with their attached formal comments, the examiner agrees that answers "b" 'or "c" could be plausible answers. However, two (2) correct answers in a four (4) part multiple choice question reduces the knowledge determinant to a mere 50%
j probability. This is not acceptable, therefore, this question is eliminated.
The Examination and Answer Key have been appropriately adjusted.
Question D.03(a)
! Comment:
i See the attached Licensee's comment on Question 0.03.
Resolution: Comment accepted.
- Although no supporting documentation was supplied by the Licensee, the examiner agrees with the Licensee's comment justification. The R0 candidates are college freshmen and sophomores and have no fonnal electrical-dynamics
, training. Therefore, question D.03(a) has been deleted from the examination and examination key.
Question E.02 l Comment:
See the attached Licensee's coment on Question E.02.
Resolution: Comment not accepted, i
The examiner understands that the setpoints for both the CAM and PAM must be i
changed to accommodate changes in detector efficiency and sampling flow rates, i However, since no new documentation was sent to support the licensee's coment justification and the fact that the R0 candidates must be familiar with the supplied Licensee's Emergency plan, the examiner believes that the question is valid. The question will remain unchanged.
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REED COLLEGE ' MUL4YdD l Oregon 97 o NRC
- 199% V RE ACTOR FACILITY 88 MAY31 P t : 03 24 May 1988 Robert J. Pate, Chief Reactor Safety Branch U. S. Nuclear Reguletory Commission 1450 hiaria Lane, Suite 210 Walnut Creek, California 94596-5368 Re: Licensing. examination conducted by hir. Tom hieadows at this site on 16 20 hiay 1988. Docl'et 50-288, License R-112.
Dear hir Pate:
I have reviewed and approved of the attached letters from Lawrence Ruby, Reactor Director, and J. hiichael Pollock, Associate Director, concerning the examination given by hir, hieadows.
Sincerely, hfarshall Cronyn Vice President / Provost I
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REED COLLEGE Po8Q3fgon97aoa ,
REGION V I meAcron neiury May 24,198 3
Robert J. Pate, Chief Reactor Safety Branch U. S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 5368 Re: Senior Reactor Operator licensing examination conducted by Mr. Tom Meadows at this site on 16 20 May 1988. Docket 50 288, License R ll2.
Dear Mr. Pate:
8 I have the following requests, referenced by question number, in regard to the Senior Reactor Operator's Exam: pt p/<*$
ret t-11.0 4. Accept answer "c" as equally correct. (Note: this was discussed on the RO ebm as well). Delayed neutrons are born at energies below the 12 MeV energy range, while prompt neutrons are born "fast."
Justification: Answer "c" is correct and is an even more precise description than is the key answer "b." Our Training Manual, on page 512, lists the delayed neutron energies as 250, 560, 405, and 450 kev, while the more recent reference, Glasstone and Sesonske 3rd ed. (see 1st attachment) lists the energies as 0.25, 0.46, 0.41, 0.45, and 0.41 MeV. Figure 2.26 on page 112 of the same reference, shows how the delayed neutrons arise from de-excitation of the precursor daughter nuclei, and so, such neutrons must be monoenergetic. On the other hand, answer "b" correctly describes both prompt and delayed neutrons as "fast" which is in accord with most characterizations of the fast group as beginning at 10 kev. In particular, it is the definition used in the RRF Training Manual (see attachment 2) and in Glasstone and Sesonske 3rd ed. (see attachment 3).
I.15 Accept either "a" or "d".
Justification: In fact, neither the Ludlum Model 177 nor the Eberline Model E 140 has ever been used with a scintillation detector at Reed, however, virtu:lly any Geiger counter can be used with a suitable scintillation detector. The Ludlum Model 177 is supplied with a variable high voltage supply which allows it to be used with a large selection of scintillation detectors and, hence, the Technical Manual discusses its potential use as a portable scintillation monitor. The Eberline E 140 could be used with a scintillation detector designed to operate at 900V, L01(c) Accept also !!ealth Physicist.
Justification: The Reactor IIcalth Physicist according to his duties described in the Administrative Procedures, serves as an ex officio, non-voting member of the RRC and, in practice, this means both subcommittees.
The Associate Director position is not required to be filled according to the !
Administrative Procedures. '
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Rcbert J. Pate May 24,1988 Page 2 L.01(d) Accept any number I through 4.
Justification: The examiner has misquoted the Administrative Procedures in the question c.nd this may lead to considerable confusion.
The Administrative Procedures (quoting requires "a minimum of four members of the facuhv andfrom the Technical Specifications)
(underlining added . facility staff "
examiners answerwould o)f "4"be obvious and correct.Had However, NRC the question included inspectors have inter committee member (s)preted this in the past to imply that there must be a Facility staff member.who is a Reed College faculty AND NOT a Reactor Since the Director, Associate Director (if this position is filled), and the Health Physicist are specified to be non voting rnembers, and die Supervisor must also be a member by virtue of the position, the 'true minimum total members is currently 5, of whom 3 are specitically non voting staff members (although only 2 of these are required), and one (the Supervisor) is a voting staff member.
Sincerely, -
/,-. y%-
J. dichael Pollock Associate Director I
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REED CULLEGE Port /a 97202 REQl0f093 V
aucm ucam 08 !.iAY 3l PI: 03 24 May 1988 Robert J. Pate, Chief Reactor Safety Branch U. S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 5368 Re: Licensing examination conducted by Mr. Tom Meadows at this site on 16 20 May 1988. Docket 50 288, License R ll2.
Dear Mr. Pate:
I have the following requests, referenced by question number, in regard to the Reactor Operator's Exam:
A.08 Accept answer "c" as equally correct. Dela energies below the 12 MeV energy range,yed neutrons while prompt are born neutrons are at born fast."
Justification: Answer "c" is correct and is an even more precise description than is the key r.awer "b." Our Training Manual, on page 512, lists the delayed neutron energies as 250, 560, 405, and 450 kev, while the more recent reference, Glasstone and Sesonske 3rd ed. (see 1st attachment) lists the energies as 0.25, 0.46, 0.41, 0.45, and 0.41 MeV.
Figure 2.26 on page 112 of the same reference, shows how the delayed neutrons arise from de excitation of the precursor daughter nuclei, and so, such neutrons must be monoenergetic. On the other hand, answer "b"
correctly describes bo'.a prompt and delayed neutrons as "fast" which is inataccord beginning 10 kev.with most chartacterizations of the fast group as In particular, it is the definition used in the RRF Training Manual (see attachment 2) and in Glasstone and Sesonske 3rd ed. (see attachment 3).
D.03 Disregard part a.
Justification:
Our trainees are freshmen or sophomores majoring in physics, chemistry, or mathematics. Such persons have no understanding of the descriptors "synchronous" or "nonsynchronous" in connection with metors. Rather, the information is of benefit only to management in replacing components to the original specficiations.
E.02 Accept as an equally correct answer "d.
Particulate Steck Monitor "
Justification. The informat!on for the key answer, i.e. the CAM, was obained from an appendix to our Emergency Implementation Procedures, which lists typical setpoints only is a guide to action in
emergency situations.
In ac_tuality, the setpoints change depending on detector efficiencies and sampling flow rates, both of which are subject to change at each calibration and at any intervening maintenance. The current setpoint for the CAM is 4000 cpm, and for the PSM is 3000 cpm.
The question implies current information, and makes no mention of the EIP document as a source. Thus, since neither the CAM nor the PSM is currently close to 2000 cpm, either should be acceptable.
Sincerely, Lawrence Ruby Professor Reactor Director l
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2.192)
F I 3.189) NUCLEAR REACTIONS AND RADIATIONS Ill E I 1:
TABLE 2.10. CilARACTERISTICS OF DELAYED FISSION NEUTRONS .
l IN THERM AL FIS$10N Nurnber of Fission Nevtsons Detsyed per Fission I-Approxirnate Half &e Energy l.
- beconds) U 233 U235 Pu 239 (MeV) 1 55 5.7 x 10** 5.2 x 10** 2.1 x 10** 0.25
' 23 19.7 34.6 18.2 0.46 f' 6.2 16.6
- 31.0 12.9 0.41 h 2.3 18.4 62.4 19.9 0.45 0.61 3.4 18.2 $.2 0.41 l;, t 0.23 2.2 6.6 2.7 - '
p l
Total dehyed 0.0066 0.0158 0.0061 Total fation neutrons 2.49 2.42 2.93 I
Fraction deh>ed 0.0026 0.0065 0 0020 l f
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trons are not appreciably different. It should be noted that the approximate energies j of the delayed neutrons, given in the last column of the table, are lower than for the 8 i
great maja.ity of prompt neutrons.
at 2.191. Most of the neutron rich fission products undergo beta decay (ll.49);in !
I a few cases, however, the daughter is produced in an excited state with sufficient en.
ergy to make possible the emission of a neutron. It is in this manner that the de-1 layed neutrons arise, the characteristic half 4ife being determined by that of the >
similer equa. parent (or precursor) of the actual neutron emitter. The (approximately) 55 s and ?
- 3 and pluto.
23.s groups have been definitely associated with bromine 47 and iodine 137 as pre- r i plotted as a cursors, respectisely, and krypton 47 and xenon.137 as the corresponding emitters.
Tave energies In each case, the nurnber of neutrons in the nucleus of the emitting species exceeds h a
of 10 MeV. a magic number by unity, viz., $1 and 83, respectively. This means that the last neu- r
! g:n of reactor l
tron has a low binding energy and is, consequently, easily emitted.
i 2.192. The rnechanism proposed to account for the SS s group of delayed neu. :
trons is shown in Fig. 2.26. About 70 percent of the beta decays of bromine 47 l }^
(half 4ife 55 s)leed to the formation of an excited state (or states) of krypton 47, o E
tutions have with excitatio:1 energy somewhat greater than the binding energy (B.E.) of the last j definite ex. .
neutron,i.e.,5.4 MeV,in that nucleus. This excited state can then immediately emit a neutron,leadwg to the fornation of stable krypton 46; the energy of the neutron y
e with each ey are close l is indi ated by E, ',i the figure. Although neutron emission is shown from only one fy excited state of krypton.87, there are probably sescral closely spaced statesinvolved; numbst of b hence, there is a small range of neutron energies. The observed rate of delayed neu.
>n neutrons (
tron emission is determined by the rate of formation of k.rypton47 and this depends 'E 3, uranium, on the rate of decay of bromine 47. The neutron emission thus occurs with a half- "
- ly fast neu. life of 55 s. '"
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k 3
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"Fast neutrons" are those with energies between 10 kev ;
and one MeV. From a radiation protection standpoint, these are the most hazardous neutrons. The velocity of fast ,
neutrons can be calculated in the same manner as was dcae l for thermal neutrons.
"Relativistic neutrons" are those with energies greater I
than 10 MeV. Tht energy is generally greater than the l binding energy a st nucleons, and they are thus par- !
i ticularly effee v.e at fragmenting nuclei with which they collide. The term relativistic comes from Einsteinian l
physics, which notes that, as the ve'".ity of an object ,
approaches the velocity of light, it 5. ~ heasier and l
heavier until, at the velocity of light, its mass becomes infinite.
The four energy group.e. are most useful in character-izing the types of nucitar interactions that predominate in each energy region. Thermal (also known as slow) neutrons are most commonly involved in nuclear reactions that result in their capture by a nucleus, usually with the emission of a gamma ray or most fission reactions.
The absorption or capture of intermediate energy neu-trons is marked by a series of peaks or poir.ts of high affinity for neutrons of a particular energy. These are known as resonance peaks, and hence intermediate neutrons are sometimes known as resonance neutrons and are target specific. This is of great utility in the analysis of 5 c h k & .2.
12-1-20 A. R f: Twh Med
2.135) 2.140) NUCLEAR REACTIONS AND RADIATIONS 89 nature of the reaction. In manyinstances,one reaction predominates,and this simpli- !
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Des the situation; the same is true when one particular isotope ha. a much larger cross l section than others of the same element. Most measurements have been made with naturally occurring materials, and the data are useful for calculations of the rates of processes occurring in nuclear reactors. For some elements, however, cross secuons have also been derived for individual isotopes, such as uranium 235, uranium 238, etc. ,
2.137. For many elements, especially those of mass number exceeding 100, an
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r examination of the variation of the absorption cross sections with neutron energy re-
<eals the existence of three regions.' There is, Orst. a low energy region, where the i l
cross section decreases steadily with increasing neutros, energy. The absorption cross f section o, then varies (approximately) inversely as the square root of the neutron energy, and since the energy is kinetic in nature, o, is inversely proportional to the
- neutron speed. This is caDed the 1/u region, and the neutrons are said to obey the 1/ulaw.
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2.138. Following the 1/u region for slow neutrons, the elements under considera.
tion exhibit a resonance treion, t.sually for neutrons of roughly 0.1 to 1000 eV en.
ergy. This region is characterized by the occurrence of peaks where the absorption EE cross section rises fairly sharply to high values for certain neutron energies and then falls again. Some elements, e.g., cadmium and rhodiurn, have only one high resonance peak, whDe others, such as indium, silver, gold, and uraruum 238, have two or more g ! peaks. The cross sections at the resonance peaks are sometimes very large,e.g.,more l !
G l a.n 2 X 10' b for cadmium ll3 at a neutron energy of 0.17 eV and 3.4 X 10' b for 1
xenon 135 at 0.7 eV energy. The total cross section of umaium 238 and the total and nssion cross sections of uranium 235, as functions / the neutron energy, are shown 4
uation that in Figs. 2.l? and 2.18, respectively. The marked resonance structure is apparent. .
able condi- 2.139. Immediately beyond the region of well defined resonances, minor resonance
- eutrons are peaks may occur, but they are difScult to resolve. Apart from these resonances,the
- ubstantial. nuclear cross sections decrease steadily with increaang neutron energy. At energies rgy in the in excess of about 10 kev, there is what is called the fast ncurron region. The cross instead of sections are usually Ic~. being less than 10 b in most cases and becoming even smaller
' ion factors for energies of the order of 0.1 MeV or more. The absorption cross sections are then
- ies are ob- similar in magnitude to the geometrical cross section of the nucleus, i.e.,2 to 3 b >
calculated (Q2.165). law and wide resonances, referred to as broad (or giant) resonances, are .
often observed at high neutron energies in the MeV range. They are, however, of little significance for nuclear reactor calculations. ,
4
'RGY 2.140. Not all elements show the type of behavior described in the preceding para-i graphs.
Most elements of low mass number, as well as several of high mass number, do not exhibit resonance absc ption in the region from 0.10 to 1000 eV,at least not L to any appreciable extent. There may be broad resonances at high neutron energies, i e jeutron i but these are usually not very important. The total neutron cross sections, including
. energy, t with the e$ince scatterina ctoss sections are usuaDy sinaD, the to'al cross section
, . ., lc absorptior plus scatterina, show s the sarne uend.
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U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: REED COLLEGE Reactor Type: TRIGA Date Ad.T.inistered: MAY 17, 1988 Examiner: THOMAS R. MEADOWS, RV Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parenthcses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value ,
/ v.z r / s. 9 l dh ih A. Principles of Reactor Operation sr. L 15 lh B. Features of Facility Design j s r. 2 :
15 lh C. General Operating ,
Cl,aracteristics I
/). [ /J 7 \
WA 4C - D. Instruments and Controls
/ y. 2.
14 +4 % E. Safety and Emergency Systems l
/ V* L 14 M._. F. Standard and Emergency Operating Procedures
//,2 13 E;: G. Radiation Control and Safety l
- n. ? r 1
-t V r-Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
.ca.a y :
(p M Q% ';,","," /*2& A 7-
[VAM gC& l / /.* ) $ / r=1 (u 17 CweroA W)
ES-201-1 Enclosure 2 ATTACHMENT 1 (continued)
Enclosure 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS 1.
A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel during the duration of the written examination.
should motel i ormake arrangements for the use of a suitable room at a local scho other building.
the licensee. Obtaining this room is the responsibility of 2.
Minimum by the chiefspacing is required to ensure examination integrity as determined examiner.
with a 3-ft space between tables. Minimum spacing should be one candidate per table, No wall charts, models, and/or other training materials shali be present in the examination r:om.
3.
Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above.
examiner and/or proctor. These arrangements shall be reviewed by the l
- 4. :
The facility staff shall be provided a copy of the written examination and !
answer key af ter the last candidate has completed and handed in his written examination.
vide formal written comments with supporting documentation tion and answer key to the chief examiner or to the regional office section chief.
5.
The facility licensee shall provide pads of 8-1/2 by 11 in. lined paper in The examiner shall distribute these pads to the candidates. unop All reference material needed examiner. to complete the examination shall be furnished by the i intc the examination room, and no other equipment or referen shall be allowed.
I 6.
Only black qu;stions. ink or dark pencils should be used for writing answers to Examiner Standards
[ ES-201-1 Enclosure 2 NRC RULES AND GUIDELINES FOR LICENSE EXA'ilNATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examinatioa.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer sheet, write "Er.d of Category " as appropriate, start each category on a new page, write only one side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
16.
If parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
been completed. This must be done after the examination has l
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Examiner Standards
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ES-201-1 f Enclosure 2
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer,
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this er < while the examination is still in progress, your license may b' enied or revoked.
Examiner Standards '. ' '
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- t. .
. ES-201-1 J Enclosure 3 ATTACHMENT 1 (Continued)
Enclosure 3 Requirements for Facility Review of Written Examination
- 1. There shall be no review-of the written examination by the facility staff before or during the administration of the examination. Following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key.
- 2. The facility will have five (5) working days from the day of the written examination is given to provide formal comment submittal. The submittal will be made to the responsible Regional Office by the highest level of corporate management for plant operations, e.g., Vice President for Nuclear Operations. A copy of the submittal will beforwarded to the chief examiner, as appropriate. Comments not submitted within 'ive (5) working days will be considered for inclusion in the grading process on n case by case basis by the Regional Office section leader. Should the comment submittal dead-line not be met, a long delay for finalization of the examination results may occur.
- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and reference,
- b. Facility comment and Evaluation
- c. Supporting documentation NOTES: 1. No change to the examination will be made without submittal of complete, current, and approved reference material.
- 2. Comments made without a concise facility recommendation will not be addressed.
Examiner Standards
_ q
[ EQUATION SHEET
- f = ma v = s/t w = mg 2 ** * ("
s = v,t + hat Cycle efficiency = "Energy (in)
E = mC a = (v, - y )/t KE = mv v g =v +a A = AN A=Aeg PE = mgh w = 0/t A = in 2/tg = 0.693/tg W = vaP B 'O [ ' ) 2 2 r t
i q(eff) = (t,)(t -
s
) ,
AE = 931Am ,2 .e
,Q = m A h j4 (c +e) b I.Ieo ~h 2
Q = $C AT
, P D: G C E sr1/g Q = UAAT I-Ie -ux Pur = Wf $ I.I lo -X/ M o
. P=P 10 SUR(t) TVL = 1.3/p P=P O e/
t M = 0.693/p SUR = 26.06/T T = 1,44 DT
/A
D)
SUR = 26 -g CR = S/(1 - K ff )
T = '(1*/p )+ {(g_*p)/x pg CR y (1 - Kegg)y = CR 2 (l ~ Keff)2 T = 1*/ (p - fy M = 1/(1 - K,gg) = CR /CR g 0 7 = (5 - 0)/ A egg P M = (1 - K,gg)0 0~ eff 1 p = (K,gf-1)/K,gg = AKeff eff /K SDM = (1 - K,gf) Meggc/-M*M p= [1*/TK,gg .] + [5/(1 + A egf d "1*
P = E4V/(3 x 1010) A,gg = 0.1 seconds I = No Idyy=Id22 WATER PARAMETERS Id =Id 2 g
1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters)
I gal. = 3.78 liters R/hr = 6 CE/d2 (gcet)
Ift = 7.48 gal. MISCELL\NEOUS CONVERSIONS ,
Density = 62.4 lbm/ft 10 1 Curie = 3.7 x 10 dps Density = 1 gm/cm 1 kg = 2.21 lbm Heat of varorization = 970 Etu/lbm I hp = 2.54 x 10 3BTU /hr Heat of fusicn = 144 Btu /lbm 0 1 Mw = 3.41 x 10 Btu /hr 1 Atm = 14,7 psi = 29.9 in. Ig. 1 Btu = 778 ft-lbf 2
1 ft. H 2O = 0.4333 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32 C = 5/9 ( F - 32)
5
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'O
/
SECTION A Principles of Reactor Operation
- QUESTION A.01 (3.0)
/ . -r s 'e a J ~
An & "- ly-Berylium souree for neutrons is used in Reed's reactor. There is a control rod safety interlock that is tested by manually moving this source near the start up detector before control rods are withdrawn upon startup at Reed.
- a. What is this safety interlock? (0.75 for i nterlock)
(0.25 for i nterlock setpt.)
(1.0)
- b. Why is an installed man-made neutron source necessary? (1.0)
- c. How are neutrons produced from this source (production equation not necessary)? (1.0)
- ANSWER A.01 (3.0)
- a. Interlock:
Control Rod Withdraw is prevented with less than (two) neutron
- induced cps (on the startup channel). (0.75)
Setpoint: (less than ) 2 cps (0.25)
- b. To ensure that nuclear power can be monitored (in the range of the star: tup (count rate) channel..V M <' er e /~."
(1.0)
,a a-s 6 um r;_ --
__ decays, m ;; m
- c. Radioactive A ,1 ; ., xo 2 ct i . '-. gr- - 1y - f !
,, , g, 2: - .o- ,is ng _13, m (pg 03
, +n y mj y , - ,., ,1 e ,- f / l Md is-u) . " , -~ (1.0)
- REFERENCE l Reed Technical Specifications: l RRF Tr at ning Manual, Module 12-1:
y ~
/~o sw"Jn mys < Y . s- " .- ypn Aa, l . rdu xx .~
- A a 4~2A a-
,n
- . J ,., pn ,dd- ~/ 'MlA s u/./p z , - L A x u -2
.2s' .
1
s c
L c'
- OUESTION A.02 (3.0)
Reed's reactor uses both moderators and reflectors to help maintain the neutron population in the reactor.
- a. What are the three(3) substances that are used as moderators in Reed's core? (0.5 pts. each) (1.5)
- b. What substance is primarily used as a reflector in Reed's core? (0.5)
- c. Why is moderation necessary in a TRIGA reactor? (1.0)
- ANSWER A.02 (3.0)
- a. (0.5 pts. each) (1.5)
- 1. Zirconium Hydride (ZrH)
- 2. Water (H2O)
- 3. Graphite
- b. Graphite
- c. A moderator is needed to slow down (thermalize) neutrons.
(1.0)
- REFERENCE RRF Training Manual, Module 12-6; 1
4 l
I l
l 2
i t
/
- QUESTION A.03 (0.75)
MULTIPLE CHOICE (Select the correct response) t When Reed's reactor i s operating at steady state 200 kW, the heat transfer from the fuel centerline to the fuel cladding is correctly characterized as:
- a. conduction
- b. Film boiling
- c. convection
- d. Nucleete boiling
- ANSWER A.03 (0.75) a.
- REFERENCE Thermo-Dynamics, Enrico Fermi
.r-e -+-,w. - - - -,=-e,--------e,-werer +-=,--esmew-,-wwwevem.---c.--=--.we- -w--enewc,-w,--.--.-wew.r.,.--7,m.ww.e-v . , e
4
/
- QUESTION A.04 (0.75)
MULTIPLE CHOICE (Select the correct response)
When Reed's reactor is undergoing refueling, the heat transfer from the fuel cladding to the rreactor pool i s correctly characterized as:
- a. conduction
- b. Film boiling
- c. convection
- d. Nucleate boiling
- ANSWER A.04 (0.75)
C
- REFERENCE Thermo-Dynamics. Enrico Fermi i
I i
i 1
4 i
l s
[
- QUESTION l A.05 (0.75) l MULTIPLE CHOICE (Select the correct response)
The safe control of Reed's reactor is possible because of the nature of the neutron production from the fission process.
Which of the following statements correctly describe the l influence of DELAYED NEUTRONS on the neutron life cycle? )
- a. Delayed neutrons increase the time required for PU-239 to moderate the fission process.
l
- b. Delayed neutrons decrease the time required for the neutron i population to change between generations.
- c. Delayed neutrons increase the time required for the neutron population to change between generations.
- d. Delayed neutrons decrease the amount of reflection possible with a steel reflector.
- ANSWER A.05 (0.75)
C.
REFERENCE:
RRF Training Manual, Modules 12-4 and 12-5 i
)
l 1
1 l
l 5
1 4
y i l
- QUESTION A.06 (0.75) i MULTIPLE CHOICE (Select the correct response) l The safe control of Reed's reactor is possible because of the i nature of the neutron production from the fission process. I Which of the following statements correctly describe how delayed neutrons are produced?
- a. Delayed neutrons are produced from delayed neutron precursor nuclei by beta decay sequence, each having a definite half life.
- b. Delayed neutrons are produced from the radiological disassociation of Samarium, under the influence of a neutron flux.
- c. Delayed neutrons are produced from delayed neutron precursor nuclei by alpha decay sequence, each having a defint.e half life.
- d. Delayed neutrons are produced from the radiological disassociation of U-240, under the influence of a neutron flux.
- ANSWER A.06 (0.75) a.
REFERENCE:
RRF Training Manual, Modules 12-4 and 12-5 l
l 6
a f
f
- OUESTION A.07 (0.75)
MULTIPLE CHOICE (Select the correct response)
The effective delayed neutron fraction (Beff) for Reed's reactor )
decreases over core life. The exact value of Beff depends on fuel enrichment, which in-turn, depends on core age.
Which of the following statements correctly describe the reason that Bet, decreases over core life?
- a. The isotope specific delayed neutron fraction (Bi) for U-235 decreases.
- b. The fraction of power produced by the fission of Pu-239 increases as Reed's reactor operating time increases.
- c. The isotope specific delayed neutron fraction (Bi) for U-238 decreases.
- d. The fraction of power produced by the fission of Pu-239 decreases as Reed's reactor operating time increases.
$ ANSWER A.07 (0.75) b.
REFERENCE:
RRF Training Manual, Module 12-5 l
l l
l
/
- OUESTION A.08 (0.75) t- LTIPLE CHOICE (Select the correct response)
For IGA cores the effective delayed neutron fraction (Beff) is not th same as the core effective delayed neutron fraction (B-core). Bef-f is slightly larger than B-core.
Which of thL following statements correctly describe the reason that Beff dif ers from B-core?
- a. B-core neut ns have a slight probability of leaking out of the core, whi e Beff neutrons always remain in the core.
- b. Both delayed and rompt neutrons are born as fast neutrons.
however, delayed r utrons are born at lower energy levels.
- c. Delayed neutrons are orn at energies below the 1-2 Mev energy range, while pr mpt neutrons are born fast.
- d. Both delayed and prompt n'utrons are born as fast neutrons, ;
however, delayed neutrons c. r e born at higher energy levels.
- ANSWER A.08 (0.75) l
- b. l
- REFERENCE RRF Training Manual, Module 12-5 l
- g. . -
/ /
/
o
/
- OUESTION A.09 (0.75)
MULTIPLE CHGICE (Select the correct response)
Which of the following statements correctly describes a "THERMAL NEUTRON":
- a. A neutron tnat experiences no net r.hange in energy after several collisions with atoms of the moderator.
- b. A neutron at reuonant epithermal energy levels that causes fission to occur in Pu-240 or U-238.
- c. The primary source of thermal energy increase in the reactor core during reactor operation.
- d. A neutron at fast energy levels that causes fission to occur in Pu-240 or U-238.
- ANSWER A.09 (0.75) a.
- REFERENCE RPF Training Manual, Module 12-6 o
T l
s 10UESTION A.10 (1.25)
During a refueling outage the state of the reactor pool changed to a condition of .120 DELTA-K (shut down margin) by the removal of spent fuel from the fuel storage racks.
What is the Keff of the spent fuel pool for this condition?
SHOW ALL WORK!
(1.0 for correct application)
(0.25 for value) (1.25)
- ANSWER A.10 (1.25)
Aoplication:
Keff = 1 - .12 (0.5)
Value: 1 1
I Keff = .88 (+/- .012) (0.25)
- REFERENCE RRF Training Manual, Modules 12-4 through 12-5 l
i I
1 i
10
e
?
e 1
- OUESTION A.11 (1.75)
The reactor is subtritical with 5 counts per second (CPS) !
indicated on the count rate meter. The reactor is hot, Xenon free, all rods inserted, with an initial Keff of 0.90. The regulating rod is withdrawn, establishing a new steady count rate of 100 (still subtritical).
What is the new Keff?
SHOW ALL WORK!
(1.5 for correct application)
(0.25 for correct value) 1 ANSWER A.11 (1.75)
Application:
CRo (1-Keff)o = CRi (1-Keff)i (0.5)
Koffi = 1 - ECRo/CRi](1-Keff)o (0.5)
Keffi = 1 - E5/100](1-0.90) (0.5)
Value:
Keffi = 0.995 (+/- 0.005) (0.25)
- REFERENCE RRF Training Manual, Module 12-4 i
l 11
]
4 l
1 1
- 1
- l
- OUESTION A.12 (0.75)
MULTIPLE CHOICE (Select the Correct Response)
The density of pure Water is "standar di zed" as 62.4 lbm/ft3, at a temperature of 25 degrees Celsius. Using the equation sheet provided:
What is this temperature in degrees Fahrenheit (F)?
- a. 60 degrees F
- b. 77 degrees F
- c. 46 degrt'en F
- d. 103 degrees F
- ANSWER A.12 (0.75) b degrees F = 9/5 degrees C + 32
= 9/5 (25) + 32
= 77
- REFERENCE Equation Sheet Physics, Resnick and Hallidy, Ch. 21 (Temperature)
END OF SECTION A 12
1 c
f SECTION B Features of Facility Design
- QUESTION B.01 (1.0)
The three(3) control rods used at Reed are of similar design. The powdered neutron absorbing material is sealed in a tube made from a corrosion resistant element.
- a. What in the name of this compound of powdered neutron absorbing materia 19 (0.5)
- b. What element are the control rod tubes made from? (0.5)
- ANSWER B.01 (1.0)
- a. Baron (carbide) (34C) (0.5)
- b. Aluminum (A1) (0.5)
l l
l 1.
i e
a
- DUESTION B.02 (1.5)
Reed's Technical Specifications and Safety Analysis Report 'SAR) identify the control rod drive system as important to the design of the core and safe operation. The G.A. TRIGA Mark I Maintenance and Operating Manual specifies the design features of this system:
- a. What is the vertical travel length (inches) of the control elements? (0.5)
- b. How does the design of the control rod assembly barrel for each control rod reduce the bottoming impact of the rods upon a reactor scram? (1.0)
- ANSWER B.02 (1.5)
- a. 15 (+/- 1) inches ( 0.Jdb
- b. (The control rod assembly barrel) has grated vents (hol en) in the bottom providing a dashpot (cushioning) action upon a scram. (1.0)
i i
1 l
l 'l
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20UESTION B.03 (1.0)
Reed's control rods are designed with an actual length that is longer than the distance that they can actually travel. Amon0 other design considerations, thits ensures that they are not withdrawn out of their "supporting components". These supporting components can fit in any of the 90 core fuel positions, and are fastened to the l o mr grid plate by a lacking device,
- a. What is the actual design length (inches) of the control rods? (0.5)
- b. What is the name of this "supporting component?" (0.5)
- ANSWER B.03 (1.0)
- a. 20 (+/- 1) inch (0.5)
- b. (control rod) guide tube (0.5)
l l
1 l
l l
1 l
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e
- OUESTION B.04 (3.0)
Attached Figure B.04 is an illustration of the Mark I TRIGA Reactor f rom Reed's Saf ety Analysi s Report (SAR):
- a. What is the system labeled "A"? (0.5)
- b. What is the tube labeled "B" used for? (0.5)
- c. What is the component labeled "C"? (0.5)
- d. What is the component labeled "D" used for? (0.5)
- e. What is the tank labeled "E" made of? (0.5)
- f. What is the component labeled "F" used for? (0.5)
- ANSWER B.04 (3.0)
- a. pneumatic transfer system (rabbit transfer). (0.5)
- b. isotope (specimen) removal tube. (0.5)
- c. rotary specimen rack (lazy Susan). - (0. 5 ) I
- d. neutron (reactor power) detection. (0.5)
- e. Aluminum (A1) (0.5) i
- f. reflector (moderator) (0.5) i
- REFERENCE Reed's SAR I
l I
i i
16
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- DUESTION B.05 (3.0)
Attached Figure B.05 is an illustration of the type of Fuel / Moderator element pin used at Reed. The component labeled "C" is the Fuel / Moderator. Assuming a freshly loaded fuel el ement that is fully loaded with it's primary fissile isotope:
- a. What is the Top End Fixture labeled "A" made of? (0.5)
- b. What material is the component labeled "B" made of? (0.5)
- c. What is the design function of the components labeled "B" and "D" (same function)? (0.5)
- d. What material is the "Moderator" part of the component labeled "C" made of? (0.5)
- e. What is the primary fissile isotope f or the component labeled "C"? (0.5)
- f. How many grams of the primary fissile isotope is loaded into the component labeled "C"? (0.5) ,
- ANSWER B.05 (3.0)
- a. Aluminum (A1) (0,5)
- b. Graphite (0.5)
- c. (axial; reflector (0.5) l L
- d. Zirconium-Hydride (ZrH) (0.5)
^
- e. Uranium-235 (U-235) (0.5) 37 (+/- 7) gra
- f. (0.5)
$ 17
d.
TOP END-FIXTURE
.3 y B SPACER Q
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- 28. 37 IN 14 IN.
)
- 1. 41 IN.
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~ 1. 47 IN.
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- 3. 94 IN.
/u EfBOTTOM END FIXTURE Fig. 8,05 Fuel-Moderator Element
_ . _ _ . . _ _ _ _ , _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ . . ~ . . -
ALUMINUM TOP END-FIXTURE 3
GRAPHITE h SPACER un
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- 1. 41 IN.
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- 3. 94 IN.
/u ALUMINUM BOTTOM END FIXTURE f
Fig. 6,05 Fuel-Moderator Element MY
- DUESTION B.06 (3.0)
One ( 1 ) way to determine the fuel loading content (% of fissile isotope) of a fuel element is to observe the cclar of the spacer (see Figure B.05). A "fully loaded" fuel element has a clear - l anodized finish. There are two(2) other spacer bicek colors for fuel elements with 1/2 and 1/4 normal fuel loading respectively. l Another way to determine fuel loading is to observe the machined grooves in the top end fixture of an individual fuel element.
These groove designs are illustrated on the attar.hed Figure B.06.
- a. What is the color of the spac7r block on a fuel element with -
only 1/2 of the normal fuel load? .
(0.5)
- b. What is the color of the spacer block on a fuel element with only 1/4 of the normal fuel load? (0.5) l l
- c. What is the fuel loading (f raction of normal) of a fuel i element machined with the design labeled "B" on Figure B.06? !
(0.5) ,
- d. What is the fuel loading (f raction of normal) of a f uel l element machined with the design labeled "C" on Figure D.OA7 :
(0.5) l
- e. What is the fuel loading (fraction of normal) of a fuel element machined with the design labeled "D" on Figure B.067 (0.5) ,
- f. What type of element is identified by the etched design labeled "E" on Figure B.06? !
(0.5) l
- ANSWER B.06 (3.0) i
- a. red (0.5) {
- b. orange [ reece- (0.5)
- c. 3/4 (75%) (0.5)
- d. 1/2 (50%) (0.5) i
- e. 1/4 (25%) (0.5)
- f. (graphite) Dummy (0.5)
- REFERENCE G.A. TRIGA Mark 1 Maintenance and Operating Manual 18
. . . . _. _ . . . . . - . . . .. . =. . .
w J
l i I i i A e c g g.
4 Figure B.06:
Fuel loading grooves machined in top end fixtures of fuel elements. 4 a
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I I I I I j j 1 Full 3/4 1/ 2 1/4 Graphite Dummy i
Figure B.06: l I -
Fuel loading grooves machined in top end fixtures of fuel elements.
t t
KEY-1 4
3 J
f
- OUESTION B.07 (2.5)
Dummy fuel elements occupy core grid positions not filled by fuel-moderator elements and other core components. Dummy element spacer blocks have a distinctive color for ease of identification.
- a. What is the material that the actual dummy element (not the cladding) made of? (0,5)
- b. What material is the dummy element spacer block made of?
(0.5)
- c. What is the color of the dummy element spacer block? (0.5)
- d. What is the material that makes up the cladding of dummy elements made of? (0.5)
- e. How much does a dummy element weight (pounds)? (0.5)
- ANSWER B.07 (2.5)
- a. graphite (0.5) '
- b. Aluminum (A1) (0.5)
- c. blue (purple) (0.5)
- d. Aluminum (A1) (0.5)
- e. 2.8 (+/- .5) pounds (0.5)
- REFERENCE G.A. TRIGA Mark I Maintenance and Operating Manual t
l l
l END OF SECTION B 19
l SECTION C l General Operating Characteristics
- OUESTION C.01 (2.5)
Attacned Figure C.01 illustrates a reactivity addition due to control rod withdraw at "time 0", t=0. Rod motion stops at "time 1", t=1. At t=0, the reactor is critical, in the source range, well below the point of adding heat (POAH) to the moderator.
Sourca neutrons are not significant. (Assuming, Beff = 0.0073, and _d__ = 0.1);
- a. What is the value (in seconds) of the reactor period after rod motion stops, if the total positive reactivity insertion increased Keff to 1.001, as indicated on Figure C.017 SHOW ALL WORK!
(1.5 for correct application)
(0.25 for correct value) (1.75)
- b. What would a trace (shape only) of the resultant co-ar increase look like on the log power section of Figure C.01 after rod motion ends until the POAH?
10.75)
- ANSWER C.01 (2.5)
- a. Application:
i: = (Keff-1)/Keff (0.25)
= (1.001-1)/1.001 = 0.001 (0.25)
T = (b p)/2[_p (0,5)
=(0.0073-0.001)/0,1 x 0.001 (0.5)
Value:
= 63 (+/- 3) seconds (0.25)
- b. see attached Figure C.01 KEY (0.75)
- REFERENCE RRF Training Manual, Modules 12-3 through 12-6 20
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- QUESTION t C.02 (0.75)
MULTIPLE CHOICE (Select the Correct Response)
The Reed TRIGA reactor has been designed with a large "prompt" negative fuel temperature coefficient (FTC). There are three(3) principle effects that collectively achieve this negative FTC ;
Dcppler, the properties of the fuel element moderator, and Core l Leakage:
Which of the following statements correctly describe the reason that the properties of fuel element moderator effect the overall !
"prompt" negative FTC?
- a. The build up of the fission product, Samarium, causes the insertion of negative reactivity after long term reactor operation.
1 i b. With increasing fuel element moderator temperatures the thermal neutron population is hardened (increased energy) .
- c. The build up of the fission product, Samarium, causes the insertion of negative reactivity after short term reactor operation.
c/,hf2 With increasing moderator temperatures the thermal neutron population is softened (decreased energy).
- ANSWER C.02 (0.75) b.
- REFERENCE ,
Reed Reactor Physics, Module 12-6 i
f J
t
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P i
21
- OUESTION C.03 (2.25's Reed's fuel is designed with a large "prompt" negative fuel temperature coefficient (FTC). There are three(3) effects that collectively achieve this negative FTC ,
- 1. The properties of the fuel element moderator.
- 2. Core Leakage.
- 3. Doppler Effect
- a. Which one(1) of these effects is smallest? (0.75)
- 6. Which one(l) of these effects is largest? (0.75)
- c. Which one (1) of thene effects results from the broadening of the resonant neutron capture energy bands for U-238 and PU-240? (0.75)
- ANSWER C.03 (2.25)
- a. (2) core leakage (0.75)
- b. (1) The properties of the fuel element moderator. (0.75)
- c. (3) Doppler Effect (0.75) ,
- REFERENCE RRF Reactor Physics, Module 12-6 i
i i
l l
4
- 22
A 4
- QUESTION C.04 (1.75)
The Reed reactor is taken critical and maintained on a stable 30.
second period. ;
How long (seconds) will it take-to increase power level.100 times?
SHOW ALL WORK'
~
l (1.5 pts. for application) i (0.25 pts, for value)
- ANSWER I C.04- (1.75)
J Application:
P =.Po e^ t/T (0,5)
P/Po = 100 = e^ t/30 sec (0.5) tu In 100 (30) (0.5) i Value:
= 138 (+/- 2) seconds (2.3 minutes) (0.25)
- REFERENCE RRF Reactor Physics, Module 5 I
equation sheet 1
1 l
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l 23 l
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- QUESTION C.05 (1.0) '
During a reactor routine power increase in the power range, a student operator inadvertently turns the range switch in-the wrong direction. This results in a reactor scram and sharp power
. decrease followed by a stable negative period. For Reed's reactors
- a. What is the value (in seconds) of_this stable negative period? (0.5)
- b. How long (in minutes) can this stable negative period be observed (pegged law) on the reactor period meter? (0.5)
- ANSWER C.05 (1.0)
- a. 80 (+/- 5) seconds (0.5)
- 6. 17 (+/- 5) minutes (0.5) 4
- REFERENCE Reactor Physics, Module 5; 9
4 24
d
- OUESTION C.06 (2.0)
Attached Figures C.06a and C.06b are. illustrations of Reed's radial neutron flux without the reflector installed and with the reflector installed, respectively. A welded container (not shown) encases the entire reflector.
- a. What is the container that encases the reflector made of?
(0.5)
- b. What would a trace (shape only) of the radial neutron flux look like as it passes from the core (at_ point A) through the reflector (to line B)?
SHOW ALL WORK on Figure C.06b (1.5)
- ANSWER C.06 (2.0)
I.
i a. aluminum (0.5)
- b. see attached Figure C.06b - KEY (1.5)
- REFERENCE RRF Training Manual, Figure 12-4-3; RRF GA Manual i
I 1
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- QUESTION C.07 '(0. 75 )
MULTIPLE CHOICE (Select the Correct Response)
Reed's Mark I reactor is slightly undermoderated. ;
1 Which of the following statements correctly describe the reactor l operating characteristic, "undermoderated"?
- a.- The pool depth is not sufficient to cause an increase in water density.
- 6. There are less Hydrogen atoms than Plutonium atoms in the Core.
- c. A lowering of the core water density will produce a negative :
reactivity response?
- d. There are less Plutonium atoms than Uranium atoms in the core.
- ANSWER C.07 (0.75)
C.
1 i
- REFERENCE RRF Training Manual, Modules 12-6 and 12-7; i
I 1
4 I
l 1
i l
i 26
- QUESTION ,
C.08 (2.75)
There are three(3) control rods used to control Reed's reactor.
OnE(1) of these is the "regulating" rod. The "integral rod worths" of these control rods change over core life due to internal core changes within the fuel and the control rod elements, and other reactor operating characteristics. Therefore, before every reactor startup, the operator is required to check actual core excess reactivity using the control rods and calibration charts in the back of the operators log.
- a. What are the names of the other two(2) control rods used at Reed? (0.5 pts. each) (1.0)
- b. What is the other type of "rod worth" that changes for every axial position of rod height? (0.25)
- c. What are the current estimated reactivity worths (reactivity-$ only) for each of the three(3) reactor control rods as indicated on the RRF control room status board?
i (0.5 pts. each)(1.5)
- ANSWER C.OB (2.75)
- a. (0.5 pts. each) (1.0)
- 1. shim rod
- 2. safety rod /
- b. differential O '!# (0.25)
[e
- V f /
- c. (from current ARRF status board data, 0.5 pts. each) (1.5)
(only $ reactivity necessary) shim rod T._Jf (+/- .5) $
safety rod'df_(_(+/- .5) $
regulating rod / _7 E (+/-
.5) $
- REFERENCE RRF Control Room Status Board 27
- OUESTION '
C.09 (1.25)
Reed's primary coolant system is i mpor t ar.t for minimizing the corrosion of reactor components and reducing the radioactivity of the pool water. The attached Figure C.09 is an ectual pi<;ture of '
the major components of the primary coolant syst<rm:
- a. What is the component labeled "A" (0.25)
- b. What is the component labeled "B" (0.5)
- c. What is the component labeled "C" (0.5)
- ANSWER C.09 (1.25)
- a. demineralizer (0.25)
- b. filter (0.5)
- c. flow meter (0.5)
- REFERENCE RRF GA Manual Y
END OF SECTION C l 20 l
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-KEY-
t SECTION D Instruments and Control ;
QUESTION !
D.01 (2.0)
The electromagnet and other components that link the control rod elements to the piston assembly are below the mounting plate on the center channel. Attached Figu e D.01 is an actual picture of j the type of Rack-and-Pinion control rod drive used at Reed: j
- a. What is the name of the component labeled "A", which is spring loaded? (0.5)
- b. What is the name of the component labeled "B", which is connected.to the piston assembly? (0.5)
- c. What material is the component labeled "B" made oi? (0.5)
- d. What is the name of the component labeled "C"? (0.5)
- ANSWER D.01 (2.0)
- a. pull rod (0.5)
- b. armature (0.5)
- c. iron (0.5)
F
- d. connectinO rod (0.5)
- REFERENCE a
RRF GA Mechanical Maintenance and Operating Manual; 29
t.
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- lC b~ Y -
i
- QUESTION '
D.02 (2.25)
The drive assemblies for the control rods are fastened to a mounting plate on the center channel'above the reactor pool. ,
The previous Figure D.01 is an actual picture of the type of Rack-and-Piaion control rod drive used at Reed: i
- a. What is the name of the component labeled "D"7- (0.5)
- b. What is the name of the component labeled "E"? (0.5)
- c. What is the name of the componnnt labeled "F"7- (0.5)
- d. What is the component labeled "F" used for? (0.75)
% ANSWER D.02 (2.25) l
- a. (Drive) motor (0.5) :
- b. draw tube (0.5)
- c. putentiometer (0.5)
- d. Provides indication of rod position. (0.75) 1
- REFERENCE RRF GA Mechanical Maintenance and Operating Manual; I
I i
i l
l 1
l I 1 1 l
i 1 !
50
i 1
. )
I I
- QUESTION L _ %
D.03 Pi.rj ~
All three(3) control rod motors used at Reed are single phase, reversible AC motors. However, the motor used for the regulating rod has a servo "type" motor and is capable >of faster drive speeds. ,
f W h <. "t e" df e ngle hasi- ote is u f or eo le
+ o(2) conte rod rivesh .5)
- b. What is the maximum insert / withdraw speed (in. / min. ) that can be developed by the regulating rod motor? (0.5)
- c. What is the maximum insert / withdraw speed (in./ min.) that can be developed by the other two(2) rod motors? (0.5)
- d. What component mounted on all three(3) drive assemblies stops the respective rod drive motor at the top and bottom of rod travel? (0.5)
- ANSWER f. f D.03 (2. ) A
.// ndisytfctwdi# / odd
- b. 24 (+/- 4) in/ min (0.5)
- c. 19 (+/- 4) in/ min (0,5)
- d. limit switches (0.5)
- REFERENCE RRF GA Mechanical Maintenance and Operating Manual; i
l l
1 l
l l
\
l I
, T1 J
l
. 5 P
- OUESTION D.04 (1.5)
The console power switch (S1) controls primary AC electrical power to all circuits except the DC power supply. The DC power is ,
used to supply the consol e clock and one(l) important reactor system.
- a. What is the magnitude of the electrical voltage of this DC power supply? (0.5)
- b. What in the one (1) i rnpor t ant reactor system that the DC
' (0,5) source supplies?
- c. Where is the circuit breaker that controls the DC supply output located? (0.5)
- ANSWER D.04 (1.5)
- a. 25 (+/- 5) V DC h ' # # '* " ' (0.5)
- b. ion chamber power (nuclear instrumentation) (0.5)
- c. (rear center door of) operating console (0.5)
(s a to ,e ave *r ; e o,,a a n <Ltroom 7 ,
- REFERENCE -<<<- .
. ' &c-a nrx , % m o' - .da.
e a cre a o < wsect s m n cee ik m ec ~ o ~
- A'
RRF GA Instrumentation Maintenance Man)ual J
I 1
I I
I i
i l
l 12 i
i 4
4
- a c
i
- QUESTION l
D.05 (0.75)
MULTIPLE CHOICE (Select the correct response) ,
4 .
The types of nuclear instrumentation used at Reed vary to accommodate the wide range of reactor power that must be l monitored.to facilitate safe operations. l
}
Which of the following channels receives its input from a fission [
type neutron detector? (
- a. Period Channel :
- b. Count Rate Channel t
- c. Linear Power Channel
- d. Log Power Channel i !
- ANSWER >
l D.OS (0.75) i
- b. 1
- REFERENCE ;
- I RRF GA Instrumentation Maintenance Manual )
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- OUESTION D.06 (0.75)
MULTIPLE CHOICE (Select the correct response) l The types of nuclear instrumentation used at Reed vary to I accommodate the wide range of reactor' power that must be monitored to facilitate safe operations. ;
1 a .
Which of the f ollowing channels consist of a compensated ion i chamber typ> of detector, a recorder, and n 14 position range a switch? ;
L
- a. Period Channel i
- b. Count Rate Channel ;
1 4
j c. Linear Power Chminel i
! i i d. Log Power Channel i
4
- ANSWER D.06 (0.75) 3 C,
- REFERENCE ,
RRF GA Instrumeritation Maintenance Manual t h
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l *OUERTION D.07 (0. 7. :)
l MULTIPLE CHOICE (Select the correct response) l l
The types of nuclear instrumentation used at Reed vary to accommodate the wide range of reactor power that must be 1 monitored to facilitate safe operations.
Which of the f ollowing channels provides a reactor power scram signal?
- a. Period Channel
- b. Count Rate Channel
- c. Linear Power Channel I
r
- d. Log Power Channel
- ANSWER D.07 (0.75) ,
l l
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-
- REFERENCE RRF GA Instrumentation Maintenance Manual l l
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10UESTION D.08 (0.75)
MULTIPLE CHOICE (Select the correct response)
The types of nuclear instrumentation used at Reed vary to accommodate the wide range of reactor power that mest be monitored to facilitate safe operations.
Which of the following channels provides the operator with a continuous record of neutron flux from a power level of less than one watt to full power?
- a. Period Channel
- b. Count Rate Channel
- c. Linear Power Channel
- d. Log Power Channel
- ANSWER D.08 (0.75) d.
- REFERENCE RRF GA Instrumentation Maintenance Manual l
36
- . . .- - - . - ~ . - . ~ . - . . - - .- . . . . . . . .- . -. . . ... . . - - .. . . _
- QUESTION D.09 (0.75)
MULTIPLE CHOICE (Select the correct response)
The types of nuclear instrumentation used at Reed vary to accommodate the wide range of' reactor power that must be manito. ed to f aci1itate saf e operati ans.
Which of the f ollowing channels provides a bistable output that ,
prevents withdraw n' control rods when the neutron count rate is below a preset value?
- a. Period Channel
- b. Count Rate Channel
- c. Linear Power Channel
- d. Log Power Channel
- ANSWER D.09 (O.75) b.
- REFERENCE RRF GA I n st r'
- men t a t i or Maintenance Manual :
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37 !
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- QUESTION D.10 (0. 75)-
l MULTIPLE CHOICE.(Select-the correct response)
The types of nuclear instrumentiation.used at Reed vary to accommodate the wide range of reactor power that must be )
monitored to facilitate'sefe operations.
Which of the f ollowing channels provides the operator with indication of how much power is changing per second?
- a. Period Cha inel
- b. Count Rate Char.nel
- c. Linear Power Channel
- d. Percent Powe Channel
- ANSWER D.10 (O.75) a.
- REFERENCE RRF GA Instrumentation Maintenance Manual 38-
1
- DUESTION .
, D.11 (0,75)
MULTIPLE CHOICE ( Sel ec t the correct response)
The types of nuclear instrumentation used at Reed vary to accommodate the wide range of reacter power that must be monitored to facilitate safe operations.
Which of the fol1owing channel s recei ves its input frem an uncompensated ion chamber?
- a. Periad Channel b.
Count Rate Channel c.
Linear Power Channel k d.
Percent Power Channel
- AN5WER D.11 (0.75) d.
- REFERENCE s RRF GAonInstrumentation s.rs < < - e s ~n. - ~ < rs an Maintenance Manual
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- OUESTION D.12 (1.0)
The "compensated" ion chambers derive their names from the fact that their circuitry is designed to differentiate between the desired neutron flux generated signal and an erroneous signal, generated by another type of radiation that occurs during the fission process. However, at rel atively high power levels "urcompensated" ion chambers can be used to generate an accurate reading of reactor power.
- a. What in this other type of radiation that must be compensated for in nuclear instrumentation at low power levels? (0.25)
- b. Why can "uncompensated" ion chambers be used to generate accurate readings of reactor power at relatively high power levels? (0.75)
- ANSWER D.12 (1.0)
- a. gamma (Xray) (0.25)
- b. Gamma radi ati on and neutron radiation (all radiation forms) generate representative (linear) signals of reactor power at higher power levels. (0.75) also: (Because the signal generated by gamma is insignificant compared to the neutron generated signal).
- REFERENCE RRF GA Instrumentation Maintenance Manual; Detector Fundamentals 4
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- v*************************************** l END OF SECTION D 40 l l
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l SECTION E Safety and Emergency Systems l
- QUESTION E.01 (1.0) i Reed's Technical Specifications and Safety Analysis Report (SAR) identify the control rod drive system as important to the design of the core and safe operation. ,
l
- a. What is the maximum rate of reactivity insertion
( */. delta K/K per second) allowed by Technical Specifications associated with the movement of a control rod? (0.5)
- b. What is the maximum control element drop time (in seconds) allowed by Technical Specifications that a control element may have and still be considered "operable"? (0.5)
- ANSWER E.01 (1.0)
- a. O.12 (+/- .01) delta K/K per second (0.5)
- b. (l ess than) one(1) second (0.5)
TREFERENCE Reed SAR and Technical Specifications; G.A. TRIGA Mark I Maintenance and Operating Manual l
1 41
- DUESTION
-E.02 (O.75) i
' MULTIPLE CHOICE (Select the. correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the-evacuation alarm and/or ventilation confinement system.
Which of the following safety devices has an alarm setpoint of 2000 CPM ? .
i
- a. RAM :
- b. Gaseous Stack Monitor
- c. CAM
- d. Particulate Stack Monitor
- ANSWER E.02 (0.75) !
C.
l
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D 1 1
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. __ ~ . . . - . - . . - -. . .. . . . . . _ . . - . ~ ~ . _ -
- QUESTION E.03 (0.75)
MUL'IPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that ere capable of -
detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the -
evacuation alarm and/or ventilation confinement systens.
Which of the following safety devices is a scintillation counter, used to monitor gamma radiation levels in the .eactor room?
- a. RAM
- b. Gaseous Stock Monitor
- c. CAM
- d. Particulate Stack Monitor
- ANSWER E.03 'O.75) a.
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D l
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- QUESTION E.04 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their al aria setpoints, these monitors will initiate the evacuation alarm and/or ventilation confinement system.
DJhich of the following safety devices has an alarm setpoint that
, is usually set between 115 and 160 cpm?
- a. RAM
- b. Gaseous Stack Monitor
- c. CAM
- d. Particulate Stack Monitor
- ANSWER E.04 (0.75) b.
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D l
\
I
- OUESTION E.05 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the evacuation alarm and/or ventilation confinement system.
Which of the following safety devir.es has an alarm setpoint that is usually set between 1200 and 1800 cpm?
l
- a. RAM
- b. Gaseous Stack Monitor
- c. CAM l
- d. Particulate Stack Monitor
- ANSWER l E.05 (O.75) l d.
I
- REFERENCE RRF Emergency Implementatien Procedures, and Appendix D l
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- OUESTION E.06 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the evacuation alarm'and/or ventilation confinement system.
Which of the following safety devices has an alarm setpoint-that is usually set at 2 mR/hr?
- a. RAM
- b. Gaseous Stack Monitor
- c. CAM
- d. Particulate Stack Monitor
- ANSWER E.06 (0.73) a.
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D i
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- DUESTION E.07 (0.75)
MULTIPLE CHOICE (Select the correct response) l There are fixed radiation monitors at Reed that are capable of l detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the evacuation alarm and/or ventilation confinement system.
Which of the following safety devices will activate the l ventilation confinement system when tripped? i
- a. RAM
- b. Gaseous Stack Monitor l
- c. Bulk Water Temperature Monitor
- d. Particulate Stack Monitor
- ANSWER E.07 (0.75) b.
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D l
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- QUESTION i l
E.08 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed safety devices at Reed that are capable of detecting fuel failure, or other hazardous reactor conditions. As specified in Reed's Emergency Plans t Which of the following safety devices serves as a backup-measurement of the reactor primarv coolant radioactivity and is located on the North wall of the Mechanical Room?
- a. Secondary water low pressure monitor.
- b. Bulk water temperature monitor,
- c. Water conductivity monitor.
- d. Portable Survey Meter (GM)
- ANSWER E.08 (0.75) c.
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D r
l l
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. - - ._ . ~ . . ._. . . . . . . . . . . . . -. . ._ . .. - .- . - .. . .-. _
1 10UESTION E.09 (2.0)
Reed's Technical Specifications require that the maximum.
available core excess reactivity shall be a certain limited'value
(% delta K/K). This requirement: assumes that four(4) core operating conditions exist. One(1) of these is that the reactor is "cold".
- a. What is limiting value (% delta K/K) for'the "maximum available core excess reactivity" at Reed. (0.5)
- b. What are the other three(3) core operating conditions assumed by Technical Specifications when analyzing the maximum available core excess reactivity at Reed?
(0.5 pts. each) /,1. 5) l
- ANSWER E.09 (2.0)
- a. 2.25 (+/- .02) */. delta K/K -(t 5)
- b. (0.5 pts, each, any order) (1.5)
- 1. (reactivity) experiments are in place
- 2. Xenon free
- 3. critical
- REFERENCE Reed's Technical Specifications; 1
d 49
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. 1
- OUESTION E.lO (2.5)
Reed's Technical Specifications gives no credit for cooling of the spent fuel in the pool storage racks by the forced flow of 4
the primary coolant system. Technical Spec fications also identify a 1imit for the Keff for fuel storage that defines the "s,a f e geometry" for fuel storage,
- a. What is the Keff limit for f t el storage at Reed? (0.5)
- b. How is the adequate cooling of stored fuel elements ensured even without the forced cooling of the primary coolant system? (l.0)
- c. Why do spent fuel elements or fuel devices produce heat?
( 1. 0 )
- ANSWEF E 10 (2.5)
- a. ( l ess than) 0.8 (+/- 0.01) (0.5)
- 6. The fuel elements are (reqaired to be stored in a geometry) that promotes adequate natural convection (circulation) cooling (from the pool water? M. ( 1. 0)
- c. The heat from the irradiated fuel elements is produced from the radio-nucleid decay process (decay heat). (1.0)
- REFERENCE Reed's Technical Specificatians; RRF Reactor Operations Seminar material y ,< e .r s seces7 C s ym s w/~ f ,N yac
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- O fs s 'd-g- r o n s 6 c se s. c k i sA- F M t? M J G /- .
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- OUESTION E.11 (2.5)
Reed's Technical Specifications require that the steady state operation of the reactor shall not exceed a certain kilowatt value (maximum shermal power per Reed's license) utilizing the three(3) scrams listed in Table I and two ( 2) interlocks listed in Table II of the specifications. One(1) of these scrams is the Manual Scram function.
- a. What is the value of the maximum steady state thermal power limit (kilowatts)? (0.5)
- b. What are the other two(2) scrams listed in Table 1 of Reed's Technical Specifications?
(must include initiating channel and setpoint)
(0.5 pts. each)(1.0)
- c. What are the two(2) interlocks listed in Table II of Reed's i Technical Specifications? (0.5 pts. each)(1.0)
- ANSW2R j E.11 (2.5) i
- a. 250 (+/- 2) kilowatts [2 7 7 T ^ (0,5)
- b. (0.5 pts. each, any order) (1.0) i l
- 1. Linear 110% of full power (275 kW)
- 2. Percent Power (l og ) 110% of full power (275 kW)
- c. (0.5 pts. each, any order) (1.0)
I
- 1. Control element withdraw prevented with less than(2 cps) on the nuclear instrumentation (start ap channel).
- 2. Preventien of the simultaneous manual withdraw of 2 l control rod elements. i l
- REFERENCE Reed's Technical Specifications l
51
_ . m _ . _ . _ . _ _ ._- __ _ _. ~. . _ -. _ _ . . -- -
- QUESTION E.12 (0.75)
MULTIPLE CHOICE (Select the correct response)
In-core experiments usually effect core reactivity parameters.
Furthermore, if not conducted properly, these experiments could present a radioloc,ical hazard to-the general public. Therefore, Reed's Technical Specifications impose specific limits and administrative requirements when conducting experiments. As required by Reed's Technical Saecifications:
Which of the following responses is the maximum reactivity worth limit o^ any i ndivi dua.1 in-core experiment?
a
- a. 2.25% delta K/K
- b. 3.0 $
- c. O.12% delta K/K
- d. 1.35 $
- ANSWLR E.12 (0.75) d.
- REFERENCE Reed's Technical Specifications i
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END OF SECTION E 52 l
_ ._... _ _ . . . . _ . _ _ . . . . . ._._._,_____ _ -..._ _._ ._.__..._. _ _._,a
SECTION F Standard and Emergency Operating Procedures
- QUESTION F.01 (2.75)
The Reactor Review Committee (RRC) basically has two f unctions; to review and to audit. There are two(2) subcommittees that make up the RRC.
- a. How often must each RRC subcommittee meet? (0.25)
- 6. What is the title of the person advised by the RRC? (0.5)
- c. What are the names of the two(2) subcommittees?
4 (0.5 pts. each) (1.0)
- d. Who arg the two(2) persons (by title) that must serve as non-voting membern of the RRC and all subcommittees?
(0.5 pts. each) (1.0)
- ANSWER F.01 (2,75)
- a. twice a year (0.25)
- b. President of Reed College (0.5)
- c. (0.5 pts. each) (1.0)
- 1. Reactor Operations Committee (ROC)
- 2. Radiation Safety Committee (RSC)
- d. (0.5 pts. each) (1.0)
- 1. Director of the RRF
- 2. Associate Director of the RRF
- REFERENCE Reed Technical Specifications RRF Administrative Procedures 53
- QUESTION F.02 (2.5)
The Rabbit Operator retrieves an irradiated specimen of PU-239 rrom the reactor during an experiment. While removing it from the receiver he slips, breaking the specimen tube and knocking himself out. The air containment isolation system activates and you, the Reactor Operator, initiate the evacuation alarm.
Commensurate with Reed's Emergency Implementation Procedures (EIP's), all persons in the RRF operations area are correctly evacuated to the assembly area. You are authorized reentry to save the life of the unconscious student.
- a. Where did the Facility personnel assemble? (0.5)
- b. What is the maximum area exposure rate (R/hr) that limited reentry can be made to save a life per, Reed's EIP's? (0.5)
- c. What is the ruaximum dose (rem) that personnel may receive to save a life, per Reed's EIP's? (0.5)
- d. Where are the two(2) places that the evacuation alarm can be sounded? (0.5 pts. each) (1. 0)
- ANSWER F.02 (2.5)
- a. Reactor pw xxug area (0.5)
- b. 100 R/hr (0.5)
- c. 25 rem (0.5)
- d. (0.5 pts. each, any order) (1.0)
- 1. control console (red button, right side)
- 2. Reactor bay (scath wall)
- REFERENCE Reed's Emergency Implementation Procedures 54
- QUESTION F.03 (1.5)
You were the Reactor Operator during the emergency evacuation outlined in the previous question (F.02). The personnel in the Reactor Bay and Control Room correctly exited through thei r specified pathways per Reed's Emergency Implementation Procedures (EIP's).
- a. What is the correct exit path for personnel in the Reactcr Bay, per Reed's EIP's? (0,5)
- b. What is the correct exit path for personnel in the Control Room, per Reed's EIP's? (0.5)
- c. Where is the emergency grab bag stored? (0.5)
- ANSWER F.03 (1.5)
- a. Through the (North East corner) emergency exit door in the Reactor Bay. (0.5)
- 6. Through the evacuation (e>:i t ) corridor. (0.5)
- c. evacuation (exit) corridor (0.5)
- REFERENCE Reed's Emergency Implementation Procedures 55
.___. . - . . _ - . _ _ _, _ - - _ . _ _ . , ._ _ . - ~ . - - . _ _ . _ . . ,
~ ,
- DUESTION F.04 (1.75)
During the emergency outlined in the previous questions you were authorized reentry to save the life of the unconscious student.
While you were evacuating the injured student you noticed that the red jewel light was illuminated on the front of-the GSM readout-in the. Reactor Bay:
- a. Who (by EIP title) has the sole authcrity, at the scene, to authorize you reentry to save a life? .( 0. 5).
(0.5) '
- c. Wnat abnormal Facility condition is indicated by the .
illuminated red jewel light? (0.75)
- ANSWER F.04 (1.75)
- a. Emergency Coordinator (0,5)
(accept any person authorized to act as Emergency Coordinator, if so identified)
- b. 75 rem (0.5)
- c. Air confinement set (air confinement system activated)(0.75) .l 1 REFERENCE Reed's Emergency Implementation Procedures 10CFR2O 1
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- QUESTION F.05 (2.75)
Reed's Emergency Implementation Procedures (EIP's) authorize three(3) individuals (by job title) to act as the Emergency Coordinator. One(1) of these persons is "the senior member of the ENCL present." Reed's EIP's Tabl e I, classifies three(3)
"credible" Emergency Action Levels (EAL's).
- a. What do the letters, "ENCL", stand for? (0.25)
- b. Who are the other two(2) individuals on duty (by job ti tle) authorized to assume the duties of Emergency Coordinator?
(0.5 pts. each) (1. 0)
- c. What are the three(3) credible EAL's for Reed?
(0.5 pts. each ) ( 1. 5)
- ANSWER F.05 (2.75) i
- a. Emergency Notification Call List (0.25)
- b. (0.5 pts. each) (1.0)
- 1. RO (on duty or present)
- 2. SRO (on duty or present)
- c. (0.5 pts. each) (1.5)
- 1. Non-Reactor Safety Related Event
- 2. (Notification of) Unusual Event (NOUE)
- 3. Alert
- REFERENCE Reed's Emergency Implementation Procedures; RRF Emergency Plan; i
57
.~. _._ _ . . . _ . _ . - . .. - - , - - , _ , . _ _ . . - - . . . . , _ , . . _ , . . . . - , . _ , - ~ _ , - , , . . _ _ - , - , _ , _ , , , _ , . - . ~ . -
- OUESTION F.06 (1.75)
During a fire emergency, Reed's Reed's Emergency Implementation Procedures (ElP's) direct you to to secure the main facility circuit breaker in case of an electrical hazard. Furthermore, in any accident injury involving radiation or radioactivity, the ambulance with the affected individual is to be directed ONLY to one(1) speci fi c hospital.
- a. Where is the main facility circuit breaker (room No. cr accurate description of room location)? (0.75)
- b. Where are the keys kept that would allow access to the main f acility ' circuit breaker (specific location)? (0.5)
- c. What is the name of the hospital identified for victims of a radiological accident? (0.5)
- ANSWER F.06 7 (1.'5)
- a. Room No. 7 (room across from the entrance to the Chemistry Stock Room) (0.75)
- b. emergency grab bag (0.5) )
- c. Good Samaritan (Hospital) (0.5)
- REFERENCE l
Reed's Emergency Implementation Procedures !
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- OUESTION F.07 (1.0)
Reed's Standard Operating Procedures SOPTO (Completing the Weekly Checklist) and Change Notice PCN# 87-03 ,dentify'two(2) specific ways of checking that pool water level i s at "nominal level".
What are the two(2) ways of verifying normal reactor pool level?
(0.5 pts. each)
- ANSWER F.07 (1.0)
(0.5 pts. each)
- 1. Water level is[+/-1 cm)of the nominal scribe mark.
- 2. Water level iswithin[1 inch)of the top U-bolt on the (Count Rate) Detector support.
- REFERENCE Reed's Standard Operating Procedures SOP 70 (Completing the Weekly Checklist) and Change Notice PCN# 87-03 I
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- l END OF SECTION F
- 59
SECTION G Radiation Control and Safety
- QUESTION G.01 (2.5)
A point source of GAMMA radiation measures 64 roentgen /hr (R/hr) gamma, at a distance of 2 feet. Assuming 100% detector efficiency for gamma radiation:
- a. What is the radiation dose (R/hr) f rom the GAMMA source at a distance of 16 feet? SHOW ALL WORK!
(1.25 for application)
(0.25 for value)- (1.5)
- b. What is the "Quality Factor" necessary to convert this dose rate from R/hr to Rem /hr? (0.5)
- c. What would be the "Quality Factor" necessary to convert this dose rate from R/hr to Rem /br if the dose rate resulted solely from a fast neutron radiation field 7 (0.5)
- ANSWER G.01 (2.5)
- a. Application.
(dose rate inversely proportional to distance sauared) (0.5)
D2 = (64 R/hr) (2/16)^2 (0.5)
= 64 (1/64) (0.25)
Value:
l
= 1.0 (+/- .02) R/hr (0.25) !
i i
- b. (OF => one ( 1 ) (0.5) I l
- c. (OF =) ten (10) (0.5)
- REFERENCE i RRF Training Manual, Chapter 2 l 1
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1 60
_ , _ _ _ . . - . _ . , . . - - _ , . - . _ . - , _ . . , _ , . - - - _ . . . . , _ - - ~ -
- QUESTION G.02 (2.0)
The Code of Federal Regulations, part 20.101 (10CFR20) specifies three(3) occupational radiation dose standards for individuals in restricted areas for the period of one(1) calendar quarter for the following parts of the body:
- 1. "Whole body; head and trunk; active blood forming organs; lens of the eye; or gonads."
- 2. "Hands and forearms; feet and ankles."
- 3. "Skin of whole body."
10CFR2O regulates that, "a licensee may permit an individual in a restricted area to receive a total occupational dose to the whole body greater than that permitted" for the above three(3) standards, provided three(3) criteria are met.
- a. What is the 10CFR2O occupational quarterly done standard for the part of the body identified by number (1) above? (0.5)
- b. What is the 10CFR2O occupational quarterly dose standard for the part of the body identified by number (2) above? (0.5)
- c. What iE[the 10CFR2O occupatinnal quarter 1.y dose standard for the part of the 'ady identified by number (3) above? (0.5)
- d. How much are the three(3) 10CFR2O occupational quarterly dose standards required to be redur.ed by (percent %) for
" e >: p osu r e of minors?" (0.5)
- ANSWER G.02 (2.0)
- a. 1.25 rem (0,5)
- b. 18.75 rem (0.5)
- c. 7.5 rem (0.5)
- d. 10% (0.5) l 4 REFERENCE 10CRF20 61
l a
i d
- DUESTION G.03 (0.75)
MULTIPLE CHOICE (Select the correct response)
Which of the following correctly describes neutron type radiation?
- a. Radiation that has less penetrating power than alpha radiation.
- b. Radiation that is usually ' classified as having a positive charge.
- c. Radiation that has more penetrating power than beta radiation.
- d. Radiation that is usually classified as having no matter., or substance.
- ANSWER G.03 (0.75) c.
- REFERENCE Reed Training Manual, Chapter 1; i
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1 62 ,
- OUESTION G.04 (0.75)
MULTIPLE CHOICE (Select the correct response)
Which of the following correctly describes alpha. type radiation?
i a. Radiation that has more penetrating power than fast beta radiation.
- b. Radiation that has more penetrating power than gamma l radiation.
- c. Radiation that is usually classified as having a positive charge.
l
{ d. Radiation that is usually class 4fied as having a neutral charge.
4
- ANSWER G.04 (0.75) l l c.
- REFERENCE Reed Training Manual, Chapter 1; 1
i l
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i i
e i
i I
i I
- QUESTION G.05 (0.75)
MULTIPLE CHOICE (Select the correct response)
Of particular concern when handling radiologically contaminated materials is the ingestion _of radiation inside the body. Given the same curie amount of ingestion and neglecting the chemical hazards:
Which of the f ollowing types of radiation will cause the most inturnal biological damage?
- a. Beta
- b. Gamma
- c. Alpha
- d. Xray
- ANSWER G.05 (0.75) c.
- REFERENCE RRF Training Manual, Chapter 1 l
l f
. . . )
.* QUESTION G.06 (2.0)
Attached Figure G.06a is an illustration of the ficar plan of the Reed Reactor Facility. The general background radiation levels are indicated for the. Reactor room, the Laberatory, the Methanica) room, and the Counting room. Radioactive sourceu are kept~in the Laboratory for instrument calibration and.certain
' experiments. Radioactive Chlorine-36 gas bottles are.being stored at the Facility to conduct Department of Defense experiments under contract. 10CFR2O requires specific types of "CAUTION" l signs for each of these four(4) areas, for the specific t conditions identified. Using Figures G.06a and G.06b (10CFR2O Appendix B):
i
- a. What must the "CAUTION" sign read that is hung over the counting room? -(0.5)
- b. What must the "CAUTION" sign read that is posted on the reactor room door? (0,5)
- c. What must the "CAUTION" sign read that in posted on the cabinet containing radioactive sources in the lab? (0.5) r
- d. What must the "CAUTION" sign read that is posted on the mechanical room door? (0.5) -
- ANSWER G.06 (2.0)
- a. (CAUTION / DANGER) HIGH RADIATION AREA (0.5)
- b. (CAUTION / DANGER) RADIATION AREA (0.5) ,
- c. (CAUTION / DANGER) RADIOACTIVE MATERIAL (S) (0.5)
- d. (CAUTION / DANGER) AIRBORNE (RADIOACTIVITY) AREA (0.5)
- REFERENCE 10 CFR 20 l
. 1 l .
l l
1 65 l
twe G,0 6 b Nuclear Regulatory Commission Part 20, App. B APPENDIX B-CONCENTRATIONS IN AIR AND WATER ABOVE NATL >RAL BACKGROtlND-Continued' (See footnotes at end of Appendix B)
Isotope 8 Table i Table 11 Element (atomic number)
Col. b M Col. 2- Col.1-M Col. 2-(#UM) (p l) (#UM) (p NI) i 2x 10" 1 x 10-8 6x10" 4 x10" Calcium (20) . . Ca 45 .. S 3 x 10-' 3 x 10-* 1 x 10" 9 x 10" I 1 x 10" 5 x 10- 8 4 x 10" 2 x 10-*
Ca 47 .- S 2 x 10-' 1 x 10-8 6 x 10" 5 x 10" I 2x 10" 1 x 10" 6x 10" 3 x 10" Califomium (98) . Cf 249 S 2 x 10"8 1 x 10-i 5 x 10- 8* 4 x 10-
- 1 1 x 10"' ~ 7 x 10-* 3 x 10-'8 2 x 10" Cf 250 S 5 x 10"8 4 x 10" 2x 10-'8 1 x 10-*
1 1 x 10- 8' 7x 10" 3 x 10"8 3 x 10" Cf 251 __ . S 2x 10"8 1 x 10" 6x10"* 4 x 10-8 1 1 x 10"' 8 x 10-* 3 x 10-'8 3 x 10" Cf 252 . - S 6 x 10"8 2 x 10-* 2 x 10-" 7 x 10-*
I 3 x 10-" 2 x 10-* 1 x 10- 88 7 x 10" Cf 253 ' S 8 x 10"' 4 x 10-8 3 x 10-" 1 x 10" l 8 x 10"' 4 x 10-8 3 x 10-" 1 x 10" Cf 254 - S 5 x 10- 88 4 x 10-* 2x 10"8 1 x 10" l 5 x 10-'8 4 x 10*
- 2 x 10"8 1 x 10" Carbon (6) .. C 14 .
S 4 x 10" 2 x 10-8 1 x to" 8 x 10-*
(CO )_ Sub 5 x 10" .
1 x 10-* _
Cerium (58) , Ce 141 S 4 x 10-' 3 x 10-
- 2 x 10-' 9 x 10" 1 2x 10" 3x 10-s 5x10" 9x10-8 Ce 143 . S 3 x 10-' 1 x 10" 9 x 10-' 4 x 10" l 2x 10" 1 x 10-8 7x 10" 4 x 10" Ce 144 ~ S 1 x 10" 3 x 10" 3 x 10"' 1 x 10" l Sx10-' 3 x 10" 2 x 10"' 1 x10" Cesium (55). Cs 131. S 1x10" 7x 10-8 4 x 10-' 2x 10.s 1 3 x 10-8 3 x 10-8 1x10-' 9 x 10" Cs 134m S 4 x 10" 2x 10" 1 x 10-' 6x 10-8 1 6 x 10-8 3 x 10-8 2 x 10" 1 x 10-s Cs 134 -. S 4 x 10" 3 x 10" 1 x 10" 9x 10" 1 1 x 10" 1 x10" 4 x 10"' 4 x 10" Cs 135 S 5 x 10" 3 x 10-s 2x 10" 1 x 10" l 0 x 10" 7x 10" 3x10" 2 x 10" Cs 136 3 4 x 10" 2 x10-8 1x10" 0 x 10" i 2x 10" 0x 10-8 6x 10" 6x 10" Cs 137 . S 6x 10-e 4 x 10" 2x 10" 2 x 10" i 1 x 10-8 1 x 10-8 5x10"' 4 x10" Chlorine (17) Q 36 . S 4 x 10" 2 x 10" 1 x 10- 8 8 x 10" i 2 x 10" 2 x 10-8 8x10"' 6 x 10" Q 38 S 3 x 10-* 1 x 10" 9x 10" 4 x 10" I 2x 10" 1x10 8 7 x 10-' 4 x 10" Chromium (24)- Cr 51 S 1 x 10" 5 x 10-8 d x 10-' 2x 10" 1 2 x 10-8 5 x 10" 8 x 10" 2x 10-8 Cobatt (27) . Co S7 . S 3 x 10" 2x 10-8 1 x 10" 5x 10" l 2x 10" 1 x 10-8 6 x 10" 4 x 10-*
Co S8m .. S 2 x 10" 8 x 10- 8 6 x 10" 3 x 10-8 I 9 x 10-' 6x 10-8 3x10" 2x 10-8 CoS8 S 8 x 10" 4 x 10- 8 3 x 10" 1 x 10" l 5 x 10" 3 x 10-8 2 x 10" 9x10 8 Co 60. S 3 x 10" 1 x 10-8 1 x 10" 5 x 10-'
I 9 x 10 ' 1 x 10-8 3 x 10"' 3 x 10" Copper (29)- Cu 64 S 2x 10"
~ ~. . 1 x 10-8 7x 10" 3 x 10" 1 1 x 10" 6x10" 4 x 10" 2 x 10" Curium (08.' _ Cm 242 ~.._.. S 1 x 10-" 7 x 10-* 4 x 10"8 2x to" l 2 x 10"' 7 x 10-
- 6 x 10"' 2 x 10" Cm 243 . S 6 x 10"8 1x10" 2 x 10"8 5 x 10-*
1 1 x 10"' 7 x 10-
- 3 x 10"8 2x10" Cm 244 ; S 9x10"8 2 x 10" 3 x 10"* 7 x 10-'
i 1 x 10"' 8 x 10" 3 x 10"8 3 x 10" Cm 245.. S 5x10"8 1x10" 2x10"8 4 x 10" I ivin"* o v e rs-
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9
- DUESTION G.07 (0.75)
MULTIPLE CHOICE (Select the correct response)
Which of the following instruments, used at Reed, is portable and is used to detect extremely high rangen of beta-gamma radiation in an emergency situation?
- a. RAM
- b. Victoreen CDV-715 Model 1B
- c. PSM
- d. Eberline Model E-140 TANSWER G.07 (0.75) b.
- REFERENCE RRF Documentation Volume 3-Health Physics, Section 3 j
i 1
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_ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ ._ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ___l
c1
- OUESTION G.08 (0.75)
MULTIPLE CHOICE (Select the correct respanne)
Which of the following instruments, used at Reed, is portable and can be used to discriminate BETA radiation?
- a. PAM
- b. Eberline Model RO-2
- c. Victoreen CDV-715 Model 18
- d. GSM r
- ANSWER G.08 (0.75) b.
- REFERENCE RRF Documentation Volume 3-Health Physics, Section 3 i
1 1
b?
,1 e
4W
- OUESTION G.09 (2.75)
A radioisotope with a half life of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> has just been removed from the reactor. This isotope decays by 0.5 Mev gamma emission.
The measured radiation level at i foot in initially 200 mR/hr, solely from the isotope. The detector used to measure the radiation is 1 0 0*/. efficient for 0.5 Mev gamma.
- a. How long (hours) will you have to wait until the radiation has decreased to 2 mR/hr? SHOW ALL WORK!
(1.5 for application)
(0.25 for value) (1.75)
- b. How many curies are in the sample? SHOW ALL WORK' (0.75 for applicacion)
(0.25 for value) (1.0)
- ANSWER G.09 (2.75)
- a. Application:
[
R=Ro e^ (-In2 x t/ t1/2) (0.5) 2 = 200 x e^ -tin 2/24 (0.25)
In 200/2 = In e^ t (.693)/24 (0.25) 4.6 = .693t/24 (0.25) t = 24/.693 x 4.6 (0.25)
Value:
t = 159 (+/- 10) hours (0.25)
- b. Aoplication:
D = 6CEn/R^2 (0.25) 200 = 6C (0.5)/1 (0.25)
C= 200/3 (0.25) l Value: j C = 67 (+/- 1) turies (0.25) 1 REFERENCE Reed Training Manual, Ch. 2
- l END OF SECTION G END OF EXAM 60
I
,/L f ,<e 3 f i<- ,,'(' - /('[ j' e ,, f "
/s U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION Facility: REED COLLEGE Reactor Type: TRIGA Date Administered: MAY 17, 1988 Examiner: THOMAS R. MEADOWS, RV Candidate:
INSTRUCTIONS TO CANDIDATE:
Use separate paper for the answers. Write answers on one side onig Staple question sheet on top of the answer sheets. Points for ecch question are indicated in parentheses after the question. The passing grade requires at least 70% in each category. Examination papers will be picked up six (6) hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value s v.z r i r. s v W .c. W; H. Reactor Theory aze n ev
-E&' r=- 40 en- 1. Radioactive Materials Handling Disposal and Hazards 2 c.) 0 20 h- J. Specific Operating Characteristics L s' 10 20 _4_O ~.e- K. Fuel Handling and Core Parameters z cs . J c' 20 -20~.en- L. Administrative Procedures, Ccnditions and Limitations e r. r C- 100 Totals Final Grade _%
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature tv- .ce c. i n : / s c' ' '
fxam {wy r .' 2 L P
- L__ A
s .
ES-201-1 Enclosure 2 ATTACHMENT 1 (continued)
Enclosure 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS 1.
A single room shall be prosided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor personnel curing the duration of the written examination. If necessary, the facility should or motel, make other arranpements for the use of a suitable room at a local school, building. Obtaining the licensee. this room is the responsibility of 2.
Minimum spacing by the chief is required to ensure examination integrity as determined examiner.
with a 3-ft space between tables. Minimum spacing should be one candidate per table, No wall charts, models, and/or other training materials shall be present in the examination room.
3.
Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above.
examiner and/or proctor. These arrangements shall be reviewed by the 4.
The facility staff shall be provided a copy of the written examination and answer key after the last candidate has completed and handed in his written examination.
The facility staff shall then have five working days to pro-vide formal written comments with supporting documentation on the examina-tion and answer key to the chief examiner or to the regional office section chief.
5.
The facility licensee shall provide pads of 8-1/2 by 11 in. lined paper in The examiner shall distribute these pads to the candidates. unope All reference material examiner. needed to complete the examination shall be furnished by the Candidates can bring pens, pencils, calculators, or slide rules into the examination shall be allowed. room, and no other equipment or reference material 6.
Only black ink or dark pencils should be used for writing answers to questions.
Examiner Standards
)
. Enclosure 2 NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of clieating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each e section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only one side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example,1.4, 6.3.
- 10. Skip at least three lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face '
down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
i
- 14. Shuw all calculations, methods, or assumptions used to obtain an answer '
to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK. '
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only, i
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination.
been completed. This must be done after the examination has Examiner Standards ~
I ES-201-1
. Enclosure 2
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are a part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in-this area while the examination is still in progress, your license may be denied or revoked.
l l
Examiner Standards .
ES-201-1 Enclosure 3 ATTACHMENT 1 (Continued)
Enclosure 3 Requirements for Facility Review of Written Examination
- 1. There shall be no review-of the written examination by the facility staff before or during the administration of the examination. Following the administration of the written examination, the facility staff shall be provided a marked-up copy of the examination and the answer key.
- 2. The facility will have five (5) working days from the day of the written examination is given to provide formal comment submittal. The submittal will be made to the responsible Regional Office by the highest level of corporate management for plant operations, e.g. , Vice President for Nuclear Operations. A copy of the submittal will beforwarded to the chief examiner, as appropriate. Comments not submitted within five (5) working days wiH be considered for inclusion in the grading process on a case by case basis by the Regional Office section leader. Should the comment submittal dead-line not be met, a long delay for finalization of the examination results may occur.
- 3. The following format should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and reference.
- b. Facility comment and Evaluation
- c. Supporting documentation NOTES: 1. No change to the examination will be made without submittal of complete, current, and approved reference material.
- 2. Comments made without a concise facility recommendation will not be addressed. ;
)
l Examiner Standards l- _
EQUATION SHEET f = ma v = s/t w = mg 2
- 2 s = v,t + hat Cycle eff.'ciency = E E = mC
, , (yg , y9)jt KE = uv v f = v, + a t A = AN A = A,e PE = mgh w = 0/t *
! h = 0.693/t g W = v4P AE = 931am O"O h')2 2 r 3-t q(eff) = (t,)(ts) j=4 ,2 #
4=mAh (t +e) b Q={nCLT
, P D r G C E m/g
- I=Ieo d*
Q = UAST I=Ie -ux Pwr = Wf $
Ie Io lo -X/ M
, P=P 10 SUR(t) TVL = 1.3/u P=P Oe ti HVL = 0.693/u SUR = 26.06/T i T = 1.44 DT SCR = S/(1 - K,gg)
/A eff pi SUR = 26 g i
CR x = S/(1 - Keffx} '
~
T = '(1*/o ) + [(6 ~ o)/A,ggo ] 1( eff)1 " 2 Il - Keff)2 !
l T = 1*/ (p - Fy M " 1/(1 ~ Keff) = CR /CR g 0
"( ~ #)! eff #
M = (1 - x,gf)0/II ~ Keff)1 eff"1)/Keff
- OKeffIKeff SDM = (1 - geff)IKeff ~ 'T##'I p=
[1*/TK,ff .] + [E/(1 + A,ggT )] ,
1* = 1 x 10 seconds
? = I$V/(3 x 1010) x -I eff = 0 I seconds E = No I>g
'2 d2 WATER PARAMETERS Idg =Id2 1 gal. = 8.345 lbm R/hr = (0.5 CE)/d (meters)
I gal. = 3.78 liters R/hr = 6 CE/d (feet)
I ft = 7.4 8 gal .
MISCELLANEOUS CONVERSIONS ,
Density = 62.4 lbm/ft 3 10 1 Curie = 3.7 x 10 dps Density = L gm/cm 1 kg = 2.21 lbm Heat of valorization = 970 Etu/lbm I hp = 2.54 x 10 BTU 3
/hr Heat of fusica = 144 Btu /lbm 1 Hw = 3.41 x 10 Btu /hr 6
1 Atm = 14.7 psi = 29.9 in. }'g. 1 Btu = 778 ft-lbf 2
I ft. H oy = 0.4333 lbf/in 1 inch = 2.54 cm F = 9/5 C + 32
- C = 5/9 ( F - 32)
l l
SECTION H Reactor Theory
- QUESTION H.01 (0.75)
MULTIPLE CHOICE (Select the correct response)
The safe control of Reed's reactor is possible because of the nature of the neutron production from the fission process.
Which of the following statements correctly describe the influence of DELAYED NEUTRONS on the neutron life cycle?
i
- a. Delayed neutrons increase the time required for ZrH to moderate the fission process.
s
- b. Delayed t. atrc+c decrease the time required for the neutron
, popula^icn te r.hange between generations.
- c. Delayed neutrens increase the time required for the neutron population 'o change between generations.
- d. Delayed neutrons decrease the amount of reflection possible with a graphite reflector.
- ANSWER H 01 (0.75) c.
REFERENCE:
i RRF Training Manual, Modules 12-4 and 12-5 l
l
'li l
I l
1
- OUESTION H.02 (0.75s MULTIPLE CHOICE (Select the correct response)
The safe control of Reed's reactor is possible because of the a nature of the neutron production from the fission process.
Which of the following statements correctly descr. e how DELAYED neutrons are produced?
- a. Delayed neutrons are produced from delayed neutron precursor
, nuclei t / beta decay sequence, each having'a definite half life.
- b. Delayed neutrons are produced from the radiological dissociation of Samarium, under.the influence af a neutron flux. ,
- c. Delayed neutrons are produced from delayed neutron precursor nuclei by alpha decay sequence, each having a definite half life.
- d. Delayed neutrons are produced from the radiological dissociation of U-240, under the influence of a neutron flux.
- ANSWER H.02 (0.75) i a.
REFERENCE:
RRF Training Manual, Modules 12-4 and 12-5 1
l i
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4 3
2
. _ . . . - _ - - .-_ . . ~ . , _ . - - _ . - . . _ _ _ _ . . . . . . . . . _ _ _ _ _ . _ _ . . . _ - . . . - - - _ - _ , . _ _ . . . . _ . _ , . . _ . . . - . - . ~ . . _ _ _ _ _ _ , . - -
- OUESTION H.03 (0.75)
MULTIPLE CHOICE (Select the correct response)
The effective delayed neutron fraction (Beff) for Reed's reactor decreases over core life. The exact value of Beff depends on fuel enrichment, which in-turn, depends on core age.
Which of the f ollowing staternents correctly describe the reason that Beff decreases over core life?
- a. The isotope specific delayed neutron fraction (Bi) for U-235 ,
decreases.
- b. The fraction of power produced by the fission of Pu-239 increases as Reed's reactor operating time increases.
- c. The isotope specific delayed neutr on f raction (Bi) for U-238 decreases. .
- d. The fraction of power produced by the fission of Pu-239 decreases as Reed's reactor operating time increases.
- ANSWER F H.03 (0.75) :
b.
REFERENCE:
RRF Training Manual, Modul e 12-5 L
1 P
1 4
I t
- .JESTION H.O (0.75)
MULTI E CHOICE (Select the correct response)
For TRIGt cores the effective delayed neutron f racti on (Deff) is ,
not the sa e as the core effective delayed neutron fraction (B-core). B ff is slightly larger than B-core.
Which of the 11owing statements correctly describe the reason that Beff diffe s from B-core?
- a. B-core neutr s have a slight probability of leaking out of the core, whil Beff neutrons always remain in the core,
- b. Both delayed and rompt neutrons are born as fast neutrons, however, delayed r utrons are born at lower energy levels.
- c. Delayed neutrons are born at energies below the 1-2 Mev energy range, while p ompt neutrons are born f ast.
- d. Both delayed and prompt leutrons are born as fast neutrons, however, delayed neutrons are born at higher energy levels.
- ANSWER H.04 (0.75) b.
- REFERENCE RRF Training Manual, Module 12-5 f;
h#
I a :
i
- OUESTION H.05 (2.0)
Attached Figure H.05 illustrates a reactivity addition due to control rod withdraw at "time 0", t=0. Rod motion stops at "time 1", t=1. At t=0, the reactor is critical, in the source radijo, well below the point of adding heat (PDAH) to the ZrH moderator.
Source neutrons are not significant. (Assuming, Beff = 0.0073, and )[_ = 0.1):
- a. What is the value (in seconds) of the reactor period after rod motion stops, if the total positive reactivity insertion increased Keff to 1.001, as indicated on Figure H.05?
SHOW ALL WORK!
(1.25 for correct application)
(0.25 for correct value) (1.5)
- b. What would a trace (shape only) of the resultant power increase look like on the log power section of Figure H.05 after rod motion ends until the PDAH?
(0.5)
- ANSWER H.05 (2.0)
- a. Application:
p= (Keff-1)/Keff (0.25)
= (1.001-1)/1.001 = 0.001 (0.25)
T= (b-p)/s2_p (0.25)
=(0.0073-0.001)/O.1 x 0.001 (0,5)
Value:
= 63 (+/- 3) seconds (0.25) b, see attached Figure H.05 KEY (0.5)
- REFERENCE RRF Training Manual, Modules 12-3 through 12 -6 5
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I L i
- QUESTION H.06 (2.25)
During a refueling outage the state of the reactor pool changed
- from a condition of .120 DELTA-K (shut.down margin) to a condition of 0.036 DELTA-K (shut down margin) by the placement of addi ti onal spent fuel in the fuel storage racks. Considering i i these two(2) shut down conditions:
- a. What is the Keff of the spent fuel pool for each of the ,
two(2) conditions given above?
SHOW ALL WORK!
(0.75 for correct application) '
(0.25 for each Keff) (1.25) i i
- b. How much positive reactivity (delta K/K) .was added to the.
reactor pool?
SHOW ALL WORK!
(0.75 for correct application)
(0.25 f or cor rect value) (1.0)
- ANSWER H.06 (2.25)
Applications
Keffi = 1 - .12 (0.25)
Keff2 = 1 - .036 (0.25)
Values Keffi = .88 (+/- .012) (0.25)
Keff2 = .964 (+/- .012) (0.25)
NOIE i Any values used for Keff will be acceptable in part "b" if. i they are applied correctly and are consistent with the final l numerical answer.
I
- b. Application: '
3 p = Keff - 1 / Keff (0.25) p1 = .88 - 1 / . 88 = (-) .137 (+/- .001) (0.125) p2 = .964 - 1 / .964 = (-) .036 (+/- .001) (0.125) p (added) = pl p2 = .137 - .036 (0.25)
Values l p (added) = 0.1 (+/- .016) delta K/K (0.25)
- REFEREN2E RRF Training Manual, Modules 12-4 through 12-5 l h
j 1 6
l j
)
- QUESTION H.07 (0.75)
MULTIPLE CHOICE (Select the Correct Response)
Reactivity varies with changes in fuel temperature. Therefore, the fuel temperature coefficient of reactivity -(FTC) is defined '
as the change in reactivity due to a one degree of fuel temperature change. The FTC for Reed is always aods negative reactivity with-increasing fuel temperature. ,
Which of the following responses correctly describe the reason that the value of FTC decreases at higher fuel temperatures?
- a. At higher fuel temperatures the resonance absorption peaks broaden less for same degree increase in fuel temperature, than at lower fuel temperatures.
- b. As the moderator temperature increases the thermal utilization factor (f) predominates in its effect on Keff over the resonance escape probability (p).
- c. At higher fuel temperatures the resonance absorption peaks
, broaden more for same degree increase in fuel temperature, than at Idwer fuel temperatures,
- d. As the moderator density decreases thermal neutrons can not ,
travel as far, causing the resonance escape probability (p) >
to decrease, i
- ANSWER +
i H.07 (0.75) a i
- REFERENCE j RRF Training Manual, Modules 12-6 through 12-7 9
1 i
i 7
- QUESTION H.08 (i.O)
The reactor is subcritical with 10 counts per second (CPS) indicated on the count rate meter. The reactor is hot, Xenon 4 free, all rods inserted, with an initial Keff of 0.95. The regulating rod is withdrawn, establishing a new steady count rate of 100 (still subcritical).
What is tte new Keff?
SHOW ALL WORK!
(0.75 for correct application) 2 (0.25 for correct value)
- ANSWER ;
i H.08 (1.0)
Application:
3 CRo (1-Keff)o = CRi (1-Keff)i (0.25)
Keffi = 1 - [CRo/CRi3(1-Keff)o (0.25) i Keffi = 1 -
E10/100](1-0.95) (0.25)
Value Keffi = 0.995 (+/- 0.005) (0.25) i
- REFERENCE ,
- RRF Tra;ning Manual, Module 12-4 l l
I
{
i j 1
1 i l
)
T s
8
m ._ _ . - . .. . ._ .._ .
- QUESTION H.09 (0.75) i MULTIPLE CHOICE (Select the Correct Response)
The density of pure Water is "standardized" as 62.4 lbm/ft3, at a temperature of 25 degrees Celsius. Using the equation sheet '
proJided: i What is this ternperature in degrees Fahrenheit (F)?
- a. 13 degrees F
- b. 77 degrees F a
- c. 45 degrees F i
- d. 103 degrees F j
- ANSWER H 09 (0.75) b i
degrees F = 9/5 degrees C + 32 ,
e
= 9/G (25) + 32
= 77 s
,
- REFERENCE Equation Sheet Physics, Resnick and Hallidy, Ch. 21 (Temperature) i e
i t
f i
f 1
i 9 +
1
- QUESTION H.10 (0.75) ,
MULTIPLE CHOICE (Select the Correct Response)
During an experiment a physics professor installed two test manometers to the RRF Demineralized Water Tank to determine tank level (Refer to attar.hed Figure H.10).
Which one(l) of the following response. correctly identifies the tank level?
- a. 12 feet
- b. 4 feet
- c. 7 feet
- d. 9 feet
- ANSWER H.10 (0.75) :
b.
- REFERENCE Equation Sheet; Physics, Resnick and Hallidy, Ch. 17 (Fluid Statics) i 1
I 1
10
S8 2
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N.-
Mx ,
N a
X
. X t x W L Q
x LL W
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6 I I tt it i MN s i i i i ~ L 7& 4 o '9*34w
. . . . - . . _ - . =. . .. . . . . -. . .. .
i r
r r
.
- QUESTION H.11 (0.75)
MULTIPLE CHOICE (Select the Correct Response) j i i During an experiment a physics professor installed two test ,
i manometers to the RRF Demineralized Water Tank to determine tank pressure (Refer to attached Figure H.10).-
Which one(1) of the following responses correctly identifies the tank pressure?
- d. 9 feet of water gauge pressure,
- b. 5 feet of water gauge pressure.
- c. 13 feet of water absolute pressure.
- d. 4 feet of water absolute pressure. i
- ANSWER .
H.11 (0.75) !
i
- b.
- REFERENCE Equation Sheet; i Physics, Resnick and Hallidy, Ch. 17 (Fluid Statics) l i
3 1
4 1 ,
7 i
F
-l 4
i 3
i.
0 4
I s
i 11
- OUESTION H.12 (2.5)
Source neutrons are important to reactor operations, especially upon a reactor startup after a long shutdown period. Source neutrons that are "man made" are produced from two(2) specific production categories
- Radionuclide reactions as.sociated with the irradiation of a
( )
light target nucleus, such as Lithium, an alpha-neutron reattion (a,n).
- 2) The decay of a heavy autleus, such as Pu-240 or Cm-244.
l
- a. What is the other type of radionuclide reaction associated with the irradiation of a light target nucleus that produces neutrons? (0.5)
- b. What is the name of the neutron production category associated with the t.pl'.tting of a heavy nucleus? (0,5)
- c. What type of installed neutron source (specific isotcpic composition) is used (or the Reed TRIGA reactor? (0.5)
- d. Why is it importa t to have neutron sources in Reeds' reactor core? (1.0)
- ANSWER H.12 (2.5) l l
4
- a. photo-neutron (0.5)
- b. SF (spontaneous f i ssi on ) (0.5) l
- c. Polonium - Beryllium (0,5) l l
( also accept Am-Be) l
- d. To ensure that nuclear power can be accurately monitored l 1n the range of the f1ssion counter count rate channels.
(also accept: Control Rod withdrawal is prevented with g less than two neutron induced cps on the etartup channel). (1.O)
- REFERENCE Reed Technical Specifitations, page 91 RRF Reactor Physicu, Module 12-1; Pued SAR, page 5-5
<~ <*~rn d
~ /~e s's e ve + r ,# m ' ' a esc *st' .e e sn a - ,,,,,,,,:,,,,, ,
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l
- QUESTION H.13 (0.75) l MULTIPLE CHOICE (Select the Correct Response)
Which of the following statements correctly detacribes a "THERMAL NEUTRON": .-
- a. A neutron that experiences no net change in energy after several collisions with atoms of the moderator,
- b. A neutron at resonant epithermal energy levels that causes fission to occur in Pu-240 or U-238.
- c. The primary source of thermal energy increase in the reactor core during reactor operation,
- d. A neutron at fast energy levels that causes fission to occur in Pu-240 or U-238.
- ANSWER H.13 (0.75) a.
- REFERENCE RRF Reactor Physics, Module 12-3; 13
_ ._= . _ - . _ . . . . . - - _ . . . _ _ _ .. . . . _ . . __ _ _ _ . , ,..- , . . - . . .
- OUESTION H.14 (2.0)
The Reed TRIGA reactor has been designed with a large "prompt" negative fuel temperature coefficient (FTC). There are three(3) principle effects that collectively achieve this negative FTC:
Doppler, the propertina of Zirconium-Hydride (ZrH), and Core Leakage:
- a. Which one(1) of these effects is largest ? (0.5)
- b. Which of one(1) of these effects is smallest 7 (0.5)
- c. How does the doppler effect achieve it's negative input to the overall negative FTC? (1.0)
- ANSWER H.14 (2.0)
I
- a. The properties of ZrH (Cell and Imhamageneities) (0.5)
- b. Core Leakage (0.5)
- c. With increasing fuel temperatures the resonance absorption bands of U-238 (& PU-240) broaden, increasing the probability of a non-fission capture. -( 1. 0 )
1 REFERENCE RRF Reactor Physics, Module 12-6 14
- . - . . - - - . - - . - .. ~ - . . - . . - . . . -
- DUESTION H.15 (0.75)
MULTIPLE CHOICE (Select the Correct Response)
The Reed TRIGA reactor has been designed with a large "prompt" negative fuel temperature coefficient (FTC). There are three(3) principle effects that collectively achieve this negative FTC:
Doppler, the properties of Zirconium-Hydride (ZrH), and Core Leakage:
Which of the following statements correctly describe the reason that the properties of ZrH effect the overall "prompt" negative FTC?
- a. The build up of the fission product, Samarium, causes the insertion of negative reactivity after long term reactor operation.
- b. With increasing ZrH temperatures the thermal neutron
, population is hardened (increased energy).
- c. The build up of the fission product, Samarium, causes the insertion of negative reactivity af ter short term reactor operation.
- b. With increasing ZrH temperaturen the thermal neutron
- population is coftened (decreased energy).
- ANSWER H.15 (0.75) b.
- REFERENCE Reed Reactor Physics, Module 12-6 l
l l
1G
. . . , _ _ . . . . - - - _.. . --.-.- .... , - . _ ,~ . ._., _ ._ .. _ _ _-. .,- _ . - . - _ ,. -.. ~ .. _.__._. _. , , _ . - - . . . _ . _ . , _ .
- QUESTION l H.16 (1.0)
The Reed reactor is taken critical and maintained on a stable 30 second period.
How long (seconds) will it take to increase power level 100
' times?
SHOW ALL WORK!
(0.75 pts. for application)
(0.25 pts. for value)
- ANSWER H.16 (1.0)
Application:
P = Po e^ t/T (0.25)
P/Po = 100 = e^ t/30 sec (0.25) t= In 100 (30) (0.25)
Value:
= 138 (+/- 2) seconds (2.3 minutes) (0.25)
- REFERENCE RRF Reactor Pnfsics, Module 5 equation sheet i
{
u
,1 6
- QUESTION H.17 (1.75)
During a reactor routine power increase in L5e power range, a student operator inadvertently turns the range switch in the wrong direction. This results in a reactor scram and sharp power decrease followed by a stable nega' ive peri od. For Reed's l reactor:
- a. What is 'he
- value (in seconds) of this stable negative period? (0.5)
- b. How long (in minutes) can this stable negative period be j observed (pegged low) on the reactor period meter? (0.5)
- c. What causes this stable reactor period following a reactor scram? (0.75) i
- ANSWER H.17 (1.75)
- a. 80 (+/- 5) seconds (0.5)
- b. 17 (+/- 5) minutes (0.5)
W
- c. The (80 second) period is determined by the longest delayed neutron precursor hal f -l i f e ( 54.5 seconds for Br-87 ).
(0.75)
- REFERENCE Reactor Physics, Module 5; equation sheet k A t. s c : ( Ta avn s h < < r, s -ros<<*~$ stw n' <> c s ~- c ,. c r
-os.-r - nrce y s es- 7s en- /s sr~ rord o e o e or
() < '4 A t'PC was Y 7'At # W f ,
1 1
1 I
l END OF SECTION H 17
SECTION I Radioactive Materials Handling, Disposal, and Hazards
- QUESTION I.01 (1.5)
A point source of GAMMA radiation measures 50 roentgen /hr (R/hr) gamma, at a distance of 2 feet. Assuming 100*/. detector ef ficiency for gamma radiation:
- a. What is the radiation dose (R/hr) from the GAMMA source at a distance of 16 feet? SHOW ALL WORK!
(0.75 for application)
(0.25 for value) (1.0)
- b. What is the "Duality Factor" necessary.to convert this value from R/hr to Rem /hr? (0.5)
- ANSWER I.01 (1.5)
- a. Application:
(dose rate inversely proportional to distance squared) (0.25)
D2 = (50 R/hr) (2/16)^2 (0.25)
= 50 (1/64) (0.25)-
Value:
= 0.78 (+/- .02) R/hr (0.25)
- b. (QF =) one(1) (0.5)
- REFERENCE RRF Training Manual, Chapter 2 18
~ .
~
l
- OUESTION 1.02 (2.5)
The Code of Federal Regulations, part 20.101 (10CFR20) specifies three(3) occupational radiation dose standards for individuals in restricted areas for the period of one(1) calendar quarter for the following parts of the body:
- 1. "Whole body; head and trunk; active blood forming organ's; lens of the eye; or gonads."
- 2. "Hands and forearms; feet and ankles."
- 3. "Skin of whole body."
10CFR2O regulates that, "a licensee may permit an individual in a restricted area to receive a total occupational dose to the whole body greater than that permitted" for the above three(3) standards, provided three(3) criteria are met.
- a. What is the 10CFR2O occupational quarterly dose standard for the part of the body identified by number (1) above? (0.5)
- b. What is the 10CFR2O occupational quarterly dose standard for the part of the body identified by number (2) above? (0.5)
- c. What is the 10CFR2O occupational quarterly dose standard for the part of the body identified by number (3) above? (0,5)
- d. How much are the thrpo(3) 10CFR2O occupational quarterly dose standards required to be reduced by (percent %) for "exposure of minors?" (0.25)
- e. What are the three(3) criteria specified by 10CFR2O that would permit an individual to exceed the occupational dose standards for the whole body? (0.25 pts. each) (0.75)
- ANSWER I.02 (2.5)
- a. 1.25 rem (0.5)
- b. 18.75 rem (0.5)
- c. 7.5 rem (0.5)
- d. 10% [e'" e "" # d' # (0.25)
- e. (0.25 pts. each, any order) (0.75)
- 1. (may not exceed) 3 rem in calendar quarter.
- 2. accumulated whole body dose (not exceed) 5(N-18)
- 3. Licensee (facility) determine accumulated whola body dose on (Form NRC-4) or equivalent.
- REFERENCE 10CRF20 19
l l
. l
- OUESTION 1.03 (E.9$T 5f ' I sT The Code of Federal Regulations. part 20.105 (10CFR20) specifies permissible levels of radiation in unrestricted areas. It states that the Commission (NRC) will approve licensee proposed limits for unrestricted areas if the proposed limits are not likely to I cause an individual to receive a specified whole body dose limit in any period of one calendar year. This limit defines "unrestricted area". Part 20.105 also identifies two(2) specific dose limits that an individual may not exceed if continuously present in this defined "unrestricted area".
- a. What is the 10CFR20.105 specified whole body dose limit in any period of one calendar year that defines "unrestricted area"? (0.5)
- b. What are the two(2) specific dose limits that an individual may not exceed if continuously present in this defined "unrestricted area". (0.5 pts. each) (1.0)
- ANSWER I.03 (1.5)
- a. O.5 rem (0.5)
- b. (0.5 pts. each) (1.0)
- 1. 2 mrem in any one hour (2 mrem /hr)
- 2. 100 mrem in any seven consecutive days (100 mrem /wk.)
- REFERENCE 10CRF20 l
20
-_ _ , _ _ _ _ . _ _ ~ , . . . . - _ - . . - - - _ __ _ . . _ _ _ , . , _ _.
- QUESTION I.04 (0.75)
MULTIPLE CHOICE (Select the correct response)
Which of the f ollowing correctly describes neutron type radiation?
- a. Radiation that has more penetrating power than beta radiation.
- b. Radiation that is usually classified as having a positive charge.
- c. Radiation that has less penetrating power than alpha radiation.
- d. Radiation that is usually classified as having no matter, or substance.
- ANSWER I.04 (0.75) a.
- REFERENCE Reed Training Manual, Chapter 1; i
1 21
- QUESTION I.05 (0.75)
MULTIPLE CHOICE (Select the correct respont.e)
Which of the following correctly describes alpha type radiation?
- a. Radiation that has more penetrating power than fast neutron radiation.
- b. Radiation that is usually classified as having a positiva charge.
- c. Radiation that has more penetrating power ~than gamma radiation.
- d. Radiation that i s usually classified as_having a neutral charge.
- ANSWER I.05 (0.75) b.
- REFERENCE Reed Training Hanual, Chapter 1; ,
I i
j l
l l
l l
l 22 ;
I
_ _ _ _ _ - _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ . _ _ _ _ _ _ . _ . _ _ _ _ __ _-.-______________..______m_____-______._.____.____.______._._._______.____-______________...-_m.___m__ _ _ __ ___-.____. _ _ ___ _ _
- OUESTION I.06 (0.75)
MULTIPLE CHOICE (Select the correct response)
Of particular concern when handling radiologically contaminated materials is the ingestion of radiation inside the body. Given the same curie amount of ingestion and neglecting the chemical hazards:
Which of the following types of radiation will cause the most internal oialogical damage? l l
- a. Beta
- b. Gamma
- c. Alpha
- d. Xray
- ANSWER I
I.06 (0.75) c.
- REFERENCE RRF Training Manual, Chapter i l
l l
l l
l 2
- . . _ . _ . . . - , _ - , - . . , . - , _ _ . . _ ..,,.,.,- ._._ -.. _ . - . . , _ . . . - _ . . . - ~ , .
l l
1 1
i
- QUESTION I.07 (1.25)
You are irradiating a specimen in the Chemistry lab. The radiation source that you are using is a- sample. f rom the reactor, that is kept in a shielded container mechanism fitted with an open window. The source is transmitting a nattgw beam of 0.1 Mev.
gamma radiation at a negligible distance from the specimen. You would like to reduce the beam'c intensity by 50% using a Lead shield. Using the equation sheet provided with this examination, and Figure I.07 (Attached):
What is the thickness (cm) of the required lead shielding?
Show all work?
(1.0 pts. for correct application)
(0.25 pts. for correct value) (1.25)
- ANSWER I.07 (1.25)
Application:
I = lo e^-ux (0.25) 1/2 = e^- (59. 7 cm^-1) (x cm) (0.25)
In1 - I n2 = I n t e^-59. 7 (x ) ] (0.25)
O - O.69 = -59.7x (0.25)
Value:
x = 0.01 (+/- 0.001) cm (0.25)
- REFERENCE Reed Training Manual, Chapter 2, pp. 20-28; 24
Linear Attenuation Coefficients, CM -I Quantum Energy, MeV 3
p, g/cm 0.1 0.15 0.2 C 2.25 0'.335 0.301 0.274 Al 2.7 0.435 0.362 0.324 Fe 7.9 2.72 1.445 1.090 Cu 8.9 3.80 1.830 1.309 Pb 11.3 59.7 20.8 10.15 ;
Air ~ ~
1.29 x 10
~
1.95 x 10 " 1.73 x 10 " 1.59 x 10 "
HO2 1 0.167 0.149 0.136 Concrete 2.35 0.397 0.326 0.291 l r
i f* ; 5 y g 5 [,0 7 l
- QUESTION I.08' (1.0)
A sample of a radio-isotope X is obser ved to cause a ' radiation field of 0.5'R/hr at a distance of one(1) foot. This material.is known to emit a single 2.0 Mev gamma upon disintegration.
What is the curie ~ content of radio-isotope X?
Show all work!
(0.75 pts. for_ correct application)
(0.25 pts. for cor.ec. value)
- ANSWER I.08 (1.0)
Application:
Reed thumb rule: R/hr at one foot = 6 x Ci x nx E (0.25) 0.5 = 6 x Ci x 1.0 x 2 (0.25)
Ci = 0.G/i2 (0.25)
Value:
Ci = 0.04 (+/- .002) curies (0.25)
- REFERENCE Reed Training Manual, Chapter 2 3
l l
l l
25
l l
- QUESTION l 1
1.09 (1.5)
Attached Figure I.09 is a drawing of the Model E-140 counter used at Reed College.
- a. What is the equivalent exposure reading (mR/hr) '
that corresponds to the full scale indication with the range switch in the "x1" position? (0.5)
- 6. What does the indicator label marked "xx" on Figure H.09 / v. ,
(C.5i i, ,. - 'I actually say on the E-140's used.at Reed College?
i
- c. What are the two(2) specific functions of the "Reset" pushbetton? (0.25 pts, each) (0.5)
- ANSWER i I.09 (1.5) l l
(0,5) !
- a. O.5 mR/hr
- b. BATT OK (battery OK) (0.5)
- c. (any order, 0.25 pts. each) (0. 5 )- l l
- 1. Reset after full scale (alarm) '
- 2. Operational checks (calibration) ,
1 l
i
- REFERENCE Instruction Manual, Model E-140 l
l l
l 1
l I
l l
I 26
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- OUESTION I.10 (2.0)
Attached Figure I.10a is an illustration of the floor plan of the Reed Reactor Facility. The general background radiation levels are indicated'for the Reactor room, the Laboratory, the Mechanicsi room, and the Counting room. Radioactive. sources are kept in the Laboratory for instrument calibration and certain experiments. 10CFR2O requires specific types of "CAUTION" signs for each of these four(4) areas, for the specific conditions identified. Using Figures I.10a and I.10b (10CFR2O Appendix B):
- a. What must the "CAUTION" sign read that is hung over the counting room? (0.5)
- b. What must the "CAUTION" sign read that is posted on the reactor room door? (0.5)
- c. What must the "CAUTION" sign read that is posted on the cabinet containing radioactive sources in the lab? (0.5)
- d. What must the "CAUTION" sign read that is posted on the mechanical room door? (0.5)
- ANSWER I.10 (2.0)
- a. (CAUTION / DANGER) RADIATION AREA (0.5)
- 5. (CAUTION / DANGER) AIRBORNE (RADIOACTIVITY) AREA (0.5)
I
- c. (CAUTION / DANGER) RADIOACTIVE MATERIAL (S) (0.5)
- d. (CAUTION / DANGER) HIGH RADIATION AREA (0.5) l
- REFERENCE 10 CFR 20 j i
1 1
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e e-
W Nuclear Regulatory Commission Port 20, App. B APPENDIX B-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROU *
(See footnotes at end of Appendra B1 .
Isotopee Table 1 Table il Dement (atomac riumber) Col. 2-Col.1 g Col 1.-h Col 2-4Wml) g$k 4WW) gy{
loone (53) I125 S 5x 10" 4 x10" 8 x to-H 2 x 10*'
I 2 x 10" 6 x 10*:
1126 S 6 x 10** 2x10" 8 x 10*
- 5x10** 9 x 10 3 x10" l 3x 10" 3x10-s 1129 S 2x 10" 1 x 10*
- 9 x10" 1 x 10" 2x 10*H 6 x 10*
- I 7x10** 6x10" 1 131 2 x 10*
- 2x10" S 0x10" 6x104 1 x 10*
- 3 x 10" I 3 x10" 2x 10-a g.
1 132 -
1x 10** 6x 10" S 2x 10" 2x10" 3 x10" 8 x 10*
- I 0x 10" 1133 S 5 x10-e 3x10" 2 x10*
- 3 x 10** 2 x 10" 4 x 10"' 1 x 10*
- I 2x 10" 1x 10" 7x 10*' 4 x 10*
- 1134 S 5 x 10*' 4 x 10-8 6 x 10" 2x10" l 3 x 10" 2x10" i135 1x 10*' 6 x 10*
- S 1x10" 7 x 10" 1x 10" 4 x 10" l 4x10" 2 x 10*
- Iri&rn (771 Ir 190.. S 1 x 10*
- 7x 10" 1 x10" 6 x 10*
- 4 x 10" 2x 10" l 4 x10" 5 x 10" 1r 192 1x10" 2x10" S 1x10" 1 x10" 4 x10" 4x10" l 3x 10" 1 x 10*
- Ir 194- 9 x 10*" 4 x 10-8 S 2x 10" 1 x 10" 8x 10" 3x10" r
I 2x 10" ,
fron (26) Fe 55 S 9 x 10*
- 5x 10" 3x 10" 9x10" 2x 10" 3x10" 8xto" i 1x10" 7 x 10" 3x 10" Fe 59 S 2x10*'
. 1 x 10" 2 x 10*
- 5x10" ext 0" Krypton (36) - I 5 x 10*
- 2x10" Kr 85m - 2 x 10-' 5 x 10* *
- Sub 6 x 10*
- Kr85 1 x 10*'
Sub 1x 10" Kr 87 3 x 10" '
Sub 1 x 10" Kr SS Sub 2x 10" Larmarium (57) 1x10** 2x 10" La 140- S 2x 10" .
7 x 10" 5 x 10-* 2 x 10" i 1x10" 7x 10" Leed (82) Ft 203 S 4 x10" 2 x 10" 3x10" 1 x 10-s g x 10-e 4 x10" l 2x 10" 1x10" Pb 210 6 x10" 4 x10" S 1x10"' 4 x 10-8 4 x 10"8 1 x 10" l 2x10"' 5x 10" Pb 212 S 8 x 10"8 2 x 10" 2 x 10" 6x10" 6 x 10"' 2x t0** l Lutetun (71)-
1 2x10** 5x10" 7x10"' 2x10" '
Lu177- S 6 x 10" 3 x 10" 2 x 10*
- 1 x t0" l 5 x 10* ' 3 x 10* * !
Man 9 Anese (25)-- Mn $2 2 x 10*
- 1 x 10*
- S 2x 10" 1 x 10* e 1
i y x t o" 3 x10-e 1 x 10*' 9 x 10* * $x10*' 3 x 10*
- Mn 54 S 4 x 10" 4 x 10" 1x to" 1 x 10" '
1 4 x 10*
- 3x #8 1 x 10*
- 1 x 10" Mn 56 S 8 x 10*'
l 4 x 10* 8 3x 10" 1 x10" Mercury (50)-- 5 x 10 *' 3 x 10-a 2x 10" 1 x10" Hg 197m S 7x 10" 6 x 10" 3 x 10" 2 x 10" i 8 x 10" 5 x 10" I Hg197- S 3 x 10" 2x 10" 1 x 10" 0 x 10" ' 4 x 10" 3 x 10" i
l 3 x 10" 1x10" .
Hg 203 -- S 9 x 10*
- 5 x10" 7x 10" 5x10" 2x 10" 2x10 s Mo@denum (42)
, 1 1 x 10" 3 x 10" 4 x 10" 1 x 10" Mo 03 S 7 x 10"
,, 5x10" J x 10*
- 2 x 10" i 2 x 10" 1 x 10" Neo#wum (50) - Nd I44 S 7x 10" 4 x 10" 8 x 10"' 2x10" 3 x 10"8 7 x 10" l 3 x 10"' 2 x 10*
- Nd147 1 x 10 * " 8x10" S 4 x 10" 2 x 10*
- I 2x10" 1 x 10*
- 6x10" Nd 149 -- 2 x 10" 8 x 10" 6x10**
- S 2 x 10*
- 8 x 10" 1 1 x 10" 6 x 10*
- 3 x 10" Neptunium f)3) Np 237 _ 8 x 10" 5 x 10" 3 x 10" S 4 x 10"' 9 x 109 1xt0"s 3 x 10" I 1 x 10"' 9x10" Np 233 - S 4 x 10"' 3 x 10* *
- 6 x 10' 4 x 10" 3 x 10+ '
I 1 x 10*
- Nd e4 (28)- 7 x 10" 4 x 10" 2x 10" f4 59 3 5 x 10" 1 x 10" 6 x 10" 2x 10*
- 2x10" 0
f i r, n r .T . ' o b -
.0 m - -
. ~. -
- OUESTION I.11 (1.75)
A chemistry student trips and spills an irradiated sample of soluble Cabalt-60 into the lake behind the Reed Reactor Facility.
The next_ day a physics student unknowingly drinks some of.the lake water while swimming and accidentally drowns. An autopsy of the victim's stomach contents showed that he ingested 25x10^ uCi/ml of soluble Cobalt-60. 10CFR20, part 20.106 regulates the amount of "radioactivity in effluents to unrestricted areas."
' Using the attached Figure I.11:
- a. How many times did the victim's ingestion contents exceed the soluble Cobalt-60 limit for the lake, as specified by ,
10CFR20, at the time of the autopsy analysis?
SHOW ALL WORK!
(0.75 pts. for correct limit)
- b. Where do the 10CFR2O limits for "radioactivity in effluents to unrestricted areas" begin to apply at Reed College (for the requirements of Federal Regulations)? (0.5) l l
- c. What is the maximum time that isotopic samples of a radioactive concentration (uCi/ml) limited by 10CFR20, part 20.106 be averaged for purposes of determining compliance' !
I with the regulations? (0.5) l
- ANSWER l I.11 (1.75)
- a. Application and analysis: !
l Limit = 5 x 10^-5 uCi/ml (0.75) )
l Value:
25/5 = 5 times l
- b. The boundary of the restricted area i (also accept: RRF reactor bay and control room) (0.5) l
- c. one(1) year (or equivalent time) (0.5)
- REFERENCE 10CFR20; RRF Emergency Plan i
i
. 28
h c, M r .I . H Nuclear Regulatory Commission Part 20, App. B APPENDIX B-CONCENTRATIONS IN AIR AND WATER ABOVE NATURAL BACKGROUND-COntinU0d'
[Soo footnotes at end of Appendix 0]
lsotope ' Table 1 Table II Element (atomic number)
Col. M Col. 2- gg Col. 2-(pG/m0 W gpCi} I) 4Ci/ml) Wa; g (pg 1 2 X 10" 1X10-8 6 X 10" 4 X 10" Calcium (20) - Ca 45 S 3 X 10" 3 X 10-* 1 X 10-' 9X10-*
I I X 10" S X 10- 8 4 x 10" 2x10-8 Ca 47 S 2 X 10' 1 X 10- 8 6 X 10" S X 10" l 2 x 10" 1X10" 6 X 10" 3 X 10" Califomium (98).- Cf 249 S 2 X 10-" 1X10" 5 X 10- '* 4x10-*
1 1X10-" " 7 X 10" 3 X 10- " 2 X 10" Cf 250 - S S X 10- '8 4 x 10" 2 x 10-" 1 X 10-8 1 IX10-" 7 X 10" 3 X 10-" 3 X 10" Cf 251 S 2 X 10- u 1 X 10" 6 X 10-" 4 X 10-8 1 1 X 10-" 8 X 10-8 3 X 10-" 3 X 10-s Cf252 S 6 X 10-" 2 X 10" 2 X 10- " 7 X 10-*
I 3 X 10-" 2x10-8 1 X 10-" 7 X 10-8 Cf 253 S 8 X 10"' 4 X10-8 3 X 10- " 1 X 10" l 8 X 10- " 4 x 10- 8 3 X 10- " 1 X 10" Cf 254. S S X 10-" 4 x10-* 2 X 10-" 1 X 10" I S X 10- " 4x10-8 2 X 10* " 1 X 10" Carbon (6) C 14- S 4 X10-* 2X10-8 1 X 10" 8X10 8 (CO,)- Sub S X 10-' . 1 X 10-8 Cerium (58) ,, Co 141 S 4 X 10" 3 X 10-8 2 X 10" 9 X 10" I 2 X 10" 3 X 10- 8 SX10" O X 10-
- Co 143 S 3 X 10" 1X10-8 9 X 10" 4 x 10" l 2 X 10" 1 X 10-s 7X10" 4X10 s Co 144 S 1 X 10" 3 X 10-
- 3 X 10- " 1 X 10" l 6 X 10" 3 X 10" 2 X 10- " 1 X 10" Cesium (55)- Cs 131. , S 1 x 10-* 7 X 10-8 4 X 10" 2 X 10- 8 I 3 X10-8 3 X 10-8 1X10" 9 X 10" Cs 134m - S 4x 10" 2 X 10- 8 1 X 10-
- Cs 136 S 4 X 10" 2 X 10- 8 1 X 10-' 9 X 10-8 1 2 X 10" 2X10- 6X10-' 6 X 10" Cs 137- S 6 X 10- 8 4 x 10-
- 2 X 10-' 2 X 10" I 1 X 10" 1 X 10- 8 SX10-" 4 X 10" Chlorine (17) . Cl36 S 4 X 10" 2X10-8 1 X 10" 8 X 10" l 2x 10" 2 X 10- 8 8 X 10"' 6 X 10" Cl38 S 3 X 10- 8 1X10" 9 X 10" 4 x 10" l 2 X 10-* 1 X 10" 7X 10" 4 X 10" Chromium (24) Cr 51 - S 1 X 10" 5X10-8 4 X 10" 2 X 10" I 2 X 10-' S X 10" 8 X 10" 2x10-8 Cobalt (27)- Co 57x S 3 X 10" 2 X 10- 8 1 X 10" 5X10" l 2 x 10" 1 X 10" 6 X 10" 4 X 10" CoS8m . S 2 X 10" 8 X 10- 8 6 X 10" 3 X 10-s l O X 10- 8 6X10-8 3 X 10-' 2 X 10- s CoS8- -
S 8 X 10" 4 x 10-8 3 X 10-' 1 X 10" 1 S X 10" 3X10-8 2 X 10" O X 10" Co 60- .. S SX10" 1 X 10- 8 1 X 10-' S X 10" l 9 X 10" 3 X 10 "
Copper (29) 1 X 10 8 3 X 10" Cu 64-- S 2 X 10" 1 X 10" 7 X 10" 3 X 10" I 1 X 10" 6X10" 4 X 10" 2 X 10" Curium (96).. .. -
Cm 2 4 2 ....-....... S 1 X 10-" 7 X 10" 4 X 10 " 2 X 10-
- I 2 X 10-" 7v10-* 6 X 10 " 2 X 10" Cm 243 - .. S 6 X 10- " 1 X 10" 2 x 10-" S X 10" l I X 10-" 7 X 10" 3 X 10- " 2 x 10" Cm 244, S 9 X 10-" 3 X 10-"
2 X 10" 7 X 10" l I X 10- " 8 X 10-
- 3 X 10-" 3 X 10" Cm 245 - . . . . . S S X 10-" 1 x 10" 2 x 10- " 4 X 10" n s v e- n a.,.a-a 4.,*n"8 ,0,vn-a
. i
- QUESTION I.12 (0.75)
MULTIPLE CHOICE (Select the correct response)
The terms "somatic effects" and "genetic effects" are used to describe biological damage caused by ionizing radiation.
Which of the following statements correctly describe the genetic effects of radiation damage?
- a. The effects of radiation damage on the "ckin of the human body."
] b. The effects of radiation damage on the "sperm or egg. cells
! of the human body."
- c. The effects of radiation damage on the "head and trunk; active blood forming organs of the human body."
- d. The effects of radiation damage on the "hands and forearms; feet and ankles of the human body."
l
- ANSWER I.12 (0.75) b
- REFERENCE RRF Training Manual, Chapter 2 4
29
. .. _ _ . _ _ _ . . . _ _ . _ . . _ . . . _ , ~ . . __ __.__. . _ ,_..- ..._ ,.,_. . . _ . - _ . _ _ _ _ _ . - . . , _ _ _ _
1
- QUESTION I.13 (0.75) l Mt'LTIPLE CHOICE (Select the correct response) i Which of the following instruments, used at Reed, would you use to-detect extremely high ranges of beta-gamma radiation in an emergency situation? j l
- a. Ludlum Model 177
- b. Eberline Model RO-2
- c. Victoreen CDV-715 Model 1B i
- d. Eberline Model E-140 i
- ANSWER I.13 (0.75)
C.
- REFERENCE RRF Documentation Volume 3-Health Physics, Section 3 i
l 1
l 1
I i
1 ,
, i l
i 1
so
l l
l
- OUESTION '
I.14 (0.75) i MULTIPLE CliOICE (Select the correct response) l 1
Which of the following instruments, used at Reed, is portable,and l can be used to discriminate BETA radiation?
- a. Ludlum Model 177
- b. Eberline Model RO-2 i
- c. Victoreen CDV-715 Model 18
- d. Eberline tiodel E-140
- ANSWER I.14 (0.75) ,,
b.
- REFERENCE ,
RRF Documentation Volume 3-Health Physies, Section-3 l
F 6
31
- QUESTION 15 (0.75)
MUL LE CHOICE (Select the correct response)
Which a the following instruments, used at Reed, uses GM or scintilla 'on detectors?
- a. Ludlum , del 177
- b. Eberline Mo el RO-2
- c. Victoreen CDV- 5 Model 1B
- d. Eberline Model E-1 O
- ANSWER 1.15 (0.75) a.
- REFERENCE RRF Documentation Volume 3-Health Pnyct s e Section 3
/
,, ,w" 32
- QUESTION I.16 (1.75)
Fuel and "Special Nuclear Material" is at all times the property of the United States Department of Energy (DOE). In accordance with RRF procedures the Reactor Oper ator has the responsibility for the proper shielding and containment of radioactivity, as well as the proper labeling of radioactive materials. The radioactive material remai s the responsibility of the reactor operator until transferred in a suitable shipping container:
- a. How far from the surface of a shipping container must the required dose rate (f or shipping purposes) be determined? (0.25)
- b. Who (as far as DOE is concerned) has primary accountability for special nuclear material leased to the Reed Reactor Facility? (0.5)
- c. Where is the off-site radioactive waste disposal area currently being used by the facility? (0,5)
- d. What federal document must accompany a request for radionuclide production at Reed under contract from other NRC licensed facilities? (0.5)
> ANSWER I.16 (1.75)
- a. one(1) meter (or equivalent) (0.25)
- b. Director (of the RRF) (0.5)
.k
- c. Handford (Site) (or U.S. Ecology, Inc.) (0.5)
- d. (A copy of) the license (covering the radionuclide requested). (0.5)
- REFERENCE RRF Administrative Procedures- Reactor Experiments, pp. 13; RRF Administrative Procedures- Handling, Storage, and Dicposal of Radioactive Material, pp. 15.
k .4 s .1 s a c c en .- s8vesms&r ,, ste -t-o f~ ' ' M .
- E*************************************************************
END OF SECTION I 33
SECTION J Specific Operating Characteristics
- QUESTION J.01 (1.75)
Attached Figures J.Ola and J.Olb a 3 trations of Reed's '
radial neutron flux without the retA=-.ar installed and with the reflector installed, respectively. A welded container (not shown) encases the entire reflector.
- a. What is the container that encases the reflector made of?
(0.5) l
- b. What is the reflector made of? (0.5)
- c. What would a trace (shape only) of the radial neutron flux look like as it passes from the core (at point A) through the reflector (to line B)?
SHOW ALL WORK on Figure J.01-o (0.75) i i
- ANSWEP J.01 (1.75)
- a. al umi num (0.5) l
- b. graphite (0.5) ,
- c. see attached Figure J.01b - KEY (0.75)
- REFERENCF.
RPF 1 raining Manual, Figure 12-4-3; ,
RRF GA Manual, pp. 7-8.
l l
l i
~
34 ,
1
CENTERLINE OF CORE l
I I
NEUTRON I i
FLUX l l
I
'l. !
.' l I,
Figure'7,OI4 is&r C 8)
/ CENTERLINE OF CORE I
I I
I NEUTRON I FLUX ,I y> i w .
/ l
\ ,
/ l \
/ I \.
i i O
Figurc 7, O /6, 6
l 9
4 CENTERLINE OF CORE I ,
I I
NEUTRON I FLUX l l
1 I
l
. I I
Figure 7. OIct 1:::. . . .
I:::.:
": 8:::
. CENTERLINE OF CORE E,.!!.
..: j
. :.:4 j :.
g... .
t
.:........ 9 g.:. ......
!!!!f! ..!! '
{iii !!!Ni '
. . . . l
- . .,'.i.mi:!..
.:.9'. ..
I NEUTRON :.:. .:liiiilii9u:::i.
g.:. :.:m.: .!:iMiii.:.
FLUX
- !!,i
- ii;ql!l :. ,
J gjij ijin.ji:,
i::. .:.%*.:, . l .; :.: ,
!::i liilgi:i .' l jii:.:i:q.:.
$!!.!!!!Ki!.!..
.. l !.!!.! !!.!.d:i:iM. . .!!.E
. . ' .'...). :.
l I. .
h..
f
- .. l ::::.
'.:.:.::::p..yM.
vf.. .:.. . .
.:,G. . / l l \ :.;. .:]L::.::.::: ....
.:.y.v.
.Y .. (
n -
l \ w,..
[
3 g.:. . . :.: .:..
t:::.:::s:::::::::.
- .. . ...:.:.:y. . :.:
l ....,..
. l ,
- : t , c - r .r - c ;
@ (b @ (are. 'sco ~r mnirne m
- m.rm.:.,)
Figure d, O / b -
6 C P' g g , ,, , f p ,,.f , ;
t
@ u @ = o.u err. .
Q r c Q : p. s J' f ff -
- o. 7 r s ty. Torn
J
- QUESTION-J.02 (0.75)
I MULTIPLE CHOICE (Select the Correct Response)
Figure J.02 (Attached) illustrates tne behavior of Xenon concentration (Nxe) as a function of reactor power and ti.ne.
Which of the following responses correctly describe the reason that Nxe dipped at point "B" on Figure J.027
- a. As power is increased, less Xenon is produced-directly from fission.
- b. As power is increased the burn out of Nxe by the higher -
neutron flux becomes predominant over the next 4 to 6 nours.
- c. As power is increased, less Iodine'is produced directly from fission. 1
- d. As power is incruased the build up of Iodine by the higher neutron flux beccmes predominant over the next 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- ANSWER J.02 (0.75)
-b
- REFERENCE RRF T; aining Manual, Module 12-7 l
l l
l l
l a
1 l
i t i i 35 -
l
a ,
C
=
. to 9'O O
. =v 0=e 1
Vt > .
O n
9=G C
N m
C
= m P9 4 h C
O m
o hun
=
O Q
- D 4 O
T E r-me o C N
s
- C h G v
W D
C0 w ,
- C
% 1 u1 C
=?
- C
- 1 O
M N .
O O u3 O Q
- e. & W3 W3 N c o
O M
W W
M n em 4J C
$ G Q Q .
d D Ce ."5 E o O
$ M ,,*a o
-- , - , - . - - - - - - - , - - - - , - - - ....,-~,.----,.,-,,-------.-,-.-..--,,,cm.---n----,------ , - . , - - - , - - - - , , - - - - - , - - . , .
- OUESTION J.03 (0.75)
MULTIPLE CHOICE (Select the Correct Response)
Figure J.02 (previous) illustrates the behavior of Xenon concentration (Nxe) as a function of reactor power and time.
Notice that (on Figure J.02) as power is increased by a factor of four(4) at time = 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, the corresponding Nxe DID NOT increase by a factor of four(4) at point "C". It would appear that Nxe equilibrium is not a linear function of reactor power.
Which one(1) of the following resnonses correctly describe this Nxe behavior?
- a. Since neutron flux is directly proportional te power level, the burnout of Nex becomes more significant as power is increased,
- b. At higher fuel temperatures the resonance absorption peaks for Nxe narrow, releasing more Xenon over the next 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />,
- d. At higher fuel temperatures the resonance absorption peaks for Nxe broaden, trapping more Xenon over the next 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />.
- ANSWER J.03 (0.75)
A
- REFERENCE RRF Training Manual, Module 12-7 36
e
- DUESTION J.04 (2.25)
J Reed's reactor i s operating at 200 Watts in MANUAL mode when a
- large air bubble is introduced-into the core causing a minor power change. - The oper ator observes power change a f ew Watts, _
then return to its initial value as the bubble leaves the core.
Assuming negligible fuel usage or fission product poison concentration change:
- a. What is the predominant' reactivi hy coef ficient that i s causing this power change? (0.5) 1
- b. What direction would reactor power initially respond when j the bubble entered the core? (0.75)
- c. Why did power return to its i nitial value when the bubble left the core? (1.0)
- ANSWER J.04 (2.25)
- a. void reactivity coefficient (0.5)
- b. Power would decrease (0.75)
- c. The original reactivity balance (equilibrium conditions) for ,
the rod (core) configuration was reestablished. (original ,
moderation condition reestablished for that core configuration). (1.0)
- REFERENCE ,
i RRF Training Manual, Modul e 12-7 RRF SOP's - section 1 4
h f
i 2
37
. , , - ,--n--, . . - , --,.w,, ,.,,,, -,--. ,,, ,,,.,,,-,.,,g..--,._.,_nmn-,..,_n~,-,,,v,,.,,,..,...,,,-m, --.,-,c, ,-.e ,-- m,,,n
l I
- OUESTION J.05 (2.25)
Reed's reactor is operating ~at 200 Watts in AUTOMATIC mode when a large slug of cooler water is introduced into the core causing one(1) of the three(3) control rods to move. The operator observes that power does not significantly change as pool temperatures stabilize. Assuming negligible fuel. usage or fission product poison concentration changet
- a. What is the name of the control rod that responded to this reactivity effect? (0.25)
- b. What are the names of the other two(2) control rods?
(0.25 pts. each) (0.5)
- c. What is the name of neutron absorber'(poison) used in these control rods? (0.25)
- d. Wnat is the material used to clad the control rod poison made of? (0.25)
- e. What direction did the one(1) control rod move to maintain i reactor power stable when the cooler water was introduced into the core? (0.5)
- f. What is the predominant reactivity coefficient that is causing this rod movement? (0.5) !
- ANSWER I
J.05 (2.25)
- a. regulating rod. (0.25)
- b. (0.25 pts, each, any order) (0.5) l
- 1. safety rod 2 shim rod
- c. boron (carbide) (B4C) (0.25) I l
- d. aluminum (0.25)
- e. into the core (down) (0.5) i f. Moderator Temperature Coefficient (MTC) (0.5)
[ p rH c<.c f ric ia-w r) ,
- REFERENCE e I RRF Training Manual, Module 12-7 ;
RRF LOP's - section 1 l l
l l
38
4
- *OUESTION J.06 (3.0)
Core Excess checks are performed as the first reactor _ operation.
on each calendar day in accordance with Reed SOPOT -(Startup and core excess check). Before withdrawing the control rods the 1 operator first calculates the approximate rod settings for low power criticality using the calibration charts kept in the control room.
- a. W5at are the two(2) types of rod worth curves?
(0.25 pts. each) (0.5)
- b. What is the specific control room location of the calibration charts used at Reed? (0.5)
- c. What is the name of the first control rod to be withdrawn upon a core excess check? (0.25)
- d. What is the range switch scale selection (in Watts) when.
beginning a core excess check? (0.25)
- e. What are the three(3) reasons that cause-the reactivity effects of the fission product paiton Samarium to be insignificant when compared to those of Xenon?
(0.5 pts. each) (1. 5)
- ANSWER J.06 (3.0)
, i
- a. (0.25 pts. each, any order) (0.5)
I
- 1. differential
- 2. integral l
- b. (Inside the back cover of the) logbook (0.5) !
l
- c. regulating rod (0.25)
! d. O.1-W s.1 Watt) scale (0.25) l l
- e. (0.5 pts. each, any order) (1.5) )
l
- 1. relatively low production rate l
- 2. relatively stable isotope j j 3. not burned out by neutron flux (only removal via nuclei decay)(small absorption cross section) '
t
- REFERENCE -
i l Reed SOPO3; l RRF Training Manual, Module 12-7 l l
39 l 1
i'
- QUESTION l J.07 (3.25)
Core Excess checks are performed as the first reactor operation on each calendar day in accordance with Reed SOPO3 (Startup and core excess check. The procedure specifies three(3) control room instruments that should be monitored upon approach to low power criticality. Two(2) of these are the Period Meter and the Linear Channel. After a certain "steady power level" is established and "defined equilibrium" is reached the critical rod positions are recorded.
- a. What is the other control room instrument that should be monitored upon approach to low power criticality? (0.25)
- b. What is the minimum percent ( 7. ) of full linear power scale that range switching should occur while increasing power?
(0.25)
- c. What is the power level (Watts) at which "equilibrium conditions" are established? (0.25) l
- d. How long (minutes) must a "steady power" level exist before-the condition can be considered in equilibrium? (0.5)
- e. How is a symmetric flux profile achieved after tno first control rod is withdrawn to 50% of its range? (1.0)
< f. How is Excess Reactivity calculated after equilibrium conditions are established? (1.0)
- ANSWER J.07 (3.25)
- a. Count Rate Channel (0.25)
- b. 50 (+/- 2)% ( O .T.5 )
f
- c. 5 (+/- 1) Watts (0.25)
- d. 2 (+'- .25) minutes (0.5)
- e. The (shim) and (safety) rods are raised (withdrawn) to equal levels. (1.0)
- f. (Using the calibration charts) the remaining reactivity worths the control rods are determined and added together.
(1.0)
- REFERENCE i Reed SOPO3; 40
.m_ _ _ - . .
- QUESTION J.08 (3.0)
Reed operating procedure SOPO4 (Reactor Operations) applies following the establishment of criticality and the measurement of core excess reactivity as specified in SOPO3. SOPO3 states that core excess should be consistent with recent past values with the same condition of prior power 51stnry and the history of one(l) other type of operation perf or ned at Reed. SOPO3 also states that-the reactor must be i mmedi at el y shutdown if a certain core excess reactivity limit is exceeded. SOPO4 specifies an operating power limit to ensure that fluctuations do not take power above the license limit.
- a. What is the other condition (operation), besides power history, that can effect the core excess reactivity at Reed? (0.5)
- b. What is the core excess reactivity limit (in 5) cpecified by SOPO3? (0.5) ;
- c. What is the power limit (kW) specified by SOPO4? (0.5)
- d. How many range scales may be switched at any one time when going up in power in the manual mode? (0.25)
- e. What is the reactor period (seconds) limit specified by SOPO3 and SOPO4 when going up in power? (0.5)
- f. When can the reactor be placed in the "Automatic Mode", !
after core excess checks have been completed? (0.75)
!
- ANSWER 4
J.08 (3.0)
- a. experiment loading (0.5)
- b. 3.00 (+/- .1)$ (0.5)
- c. 240 (+/- 5) kW ( 96*'. 250 ) (0,5)
- d. one(1) (0.25) l J
- e. 10 (+/- 2) seconds (0.5)
- f. Any time the regulating rod is partially withdre n. ( 0. 75 ',
- REFERENCE RRF SCPO3, SOPO4 l
l 1
4 1
, l
! 41 l 1
- OUESTION J.09 (1.5)
What are the current estimated reactivity worths (in $) for each of the three(3) reactor control rods t i.tu s t identify rod) as indicated on the RRF control room status board?
(0.5 pts. each)(1.5)
- ANSWER J.09 (1.5)
(spr/sof9/f/) G/ " ,/
(from currentg RRF status board data, 0.5 pts. each, any order) shim rod v_.if_ (+/- .5) $ (0.5) safety rod v-j;[ (+/- .5) $ (0.5) regulating rod f r_4 (+/- .5) $ (0.5)
- REFERENCE RRF Control Room Status Board l
l l
l 41'
l
- OUESTION 3
J.10 (1,5)
Reed operating procedure SOP 51 (Performing Rabbit Irradiations) cautions that while perf orming Rabbit Irradiations it is possible for a specimen to alter the reactivity configuration of the core.
SOP 51 specifies two(2) conditions that the reactor operator could identify during irradiation operations that constitute "unreasonable core alterations". If these conditions exist the reactor should be scramed.
What are the two(2) conditions that would constitute an "unreasonable core alteration" while performing Rabbit Irradiations?
(0.75 pts. each)
- ANSWER J.10 (1.5)
(0.75 pts, each) (1.5)
- 1. A reactivity change of 10%.
- 2. A (sudden) change (increase or decrease) of 100 (+/- 5) control red positions.
- REFERENCE Read SOPS 1 i
I g .t *
- g g
- g * *
- g g g g * * *
- g * * * * * * * *
- g g s t s g g g g g g g g g g g g g g g g g g g e g g g g g g g g g g g END OF SECTION J 43
-s l
SECTION K FUEL HANDLING AND CORE PARAMETERS
- DUESTION '
K.01 '(2. 5 )
Reed's Technical Specifications and Safety Analysis Report (SAR) identify the control rod drive system as important to the design of the core and safe operation. The G.A.-TRIGA Mark I Maintenance and Operating Manual specifies the design features of this system:
- a. What is the vertical travel length (inches) of the control elements? (0.25)
- b. What is the maximum design-rate of insertion and/or withdraw (inches per minute) that can be developed by the automatic control rod drive motor? (0.25)
- c. What is the maximum rate of reactivity insertion ,
(7. delta K/K per second) allowed by Technical Specifications associated with the movement of a control rod? (0.5) t I
- d. What is the maximum control element drop time allowed by Technical Specifications that a control element may have and still be considered "operable"? (0.5)
- e. How does the design of the control rod assembly harrel for' each control rod reduce the bottoming impact of the rods ,
upon a reactor scram? (1.0)
- 4NSWER K.01 (2.5) i
- a. 15 (+/- 1) inches (0.25) l l
- b. 24 (+/- 1) in/ min (0.25)
- c. O.12 (+/- 61) delta K/K per second (0.5) i
- d. (less than) one(1) second (0.5) '
i 4
- e. (The control rod assembly barrel) has grated ventu (hol es) in the bottom providing a dashpot %ushioning) action upon-a scram. (1.0) l j
- REFERENCE i !
i Reed SAR and Technical Specifications; 4 J
G.A. TRIGA Mark I Maintenance and Operating Manual I
- 44 I
- .,, .__,,m, ._.-.m._m_ ., . . _ . - . _ _ . _ . . , _ _ _ - _ , , , . , . - - ,. ._._,....,_,_,_,__%-,.-___,,_-
- QUESTION K.02 (1.O)
Whi1e handling fuel elements with the fuel handling tool the operator should never coil the control cable in a circle with a diameter of less than about two(2) feet.
What is the reason for this precaution for fuel handling?
- ANSWER K.02 (1.0)
A tight coil could pull the inner wires of the control cable, releasing the fuel element. (could drop the fuel element)
- REFERENCE G.A. TRIGA Mark I Maintenance and Operating Manual D
I
- QUESTION K.03 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the evacuation alarm and/or ventilation confinement system.
Which of the following safety devices has an alarm, and will also activate the ventilation confinement system?
- a. RAM
- b. Gaseous Stack Monitor
- c. Portable Survey Meter (GM)
- d. Particulate Stack Monitor j
- ANSWER ;
K.03 (0.75) 6.
- REFERENCE RRF Emergency Implementation Procedures, and Appendix D 1
i i ,
5 I
e
,I l
l 4 l i
1 i
1 l l i
46 .
i
e
- OUESTION K.04 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the i evacuation alarm and/or ventilation confinement system.
Which of the following safety devices is a scintillation counter, used to monitor gamma radiation levels in the reactor room?
- a. RAM
- b. Gaseous Stack Monitor
- c. CAM
- d. Particulate Stack Monitor i
- ANSWER K.04 (0.75) a.
- REFERENCE PRF Emergency Implementation Procedures, and Appendix D
'I 4 ~/
l l
- QUESTION K.05 (0.75)
MULTIPLE CHOICE (Select the corrnet response)
There are fixed radiation monitors at Reed that are. capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm sutpoints, these. monitors will initiate the evacuation alarm and/or ventilation confirement system.
i Which of the following safety devices.has an alarm setpoint that is usually set between 115 and 160 cpm, which will also activate the ventilation confinement system?
- a. RAM
- b. Gaseous Stack Monitor
- c. CAM
- d. Particulate Stack Monitor
- ANSWER j K.05 (u.75) i b. ,
tREFERENCE l
RRF Emergency Implementation Procedures, and Appendix D f
f 1
t F
I 4
i f
1 2 4G i ._ . _ . _ . . _ _ _ _ _ _ . . . _ , _ . _ . . . _ __._ _,. - . _.._-_.~._.-.__.._.,..___._,.-._,m,.__,,...--__,,...._.,..-- ,
._ . . .-- . - - - -~. . _ - . - -.
l
- OUESTION i- K.06 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed radiation monitors at Reed that are capable of detecting fuel failure, or other hazardous conditions. Upon reaching their alarm setpoints, these monitors will initiate the evacuation alarm and/or ventilation confinement system.
Which of the following safety devices has an alarm setpoint that is usually set between 1200 and 1800 cpm?
L
- a. RAM
- b. Gaseous Stack Monitor
- c. CAM
- d. Particulate Stack Monitor
- ANSWER K.06 (0.75) d.
- REFERENCE RRF Emergency implemyntation Procedures, and Appendix 0 5 l l
l
, l 49
- QUESTION K.07 (0.75) ;
MULTIPLE CHOICE (Select the correct response)
There are fixed safety devices at Reed'that are capable of detecting fuel failure, or other hazardous reactor conditions. As specified in Reed's Emergency Plan Which of the following safety devices serves as a backup measurement of the reactor pool water radioactivity and is located on the North wall of the Mechanical Room?
- a. Secondary water low pressure monitor,
- b. Bulk water monitor.
- c. Water conductivity monitor.
- d. Portable Survey Meter (GM)
I
- ANSWER l K.07 (0.75) c.
- REFERFNCE RRF Lmergency Impl ementation Procedures, and Appendix D 6
"l l
l 1
i i
50 I
.- . . _ - = .-.~ . . - . .. = . - . -. .- .
I 1
- QUESTION K. '0 8 (0.75) i MULTIPLE. CHOICE (Select the correct response) 4 There are fixed safety devices at Reed that are capabla of detecting fuel failure, or other hazardous reactor conditions. As specified.in Reed's Emergency Plant s Which of the following safety devices alarms with a high frequency audible alarm and flashing red light, and is located on a panel on the North wall of the Reactor Room?
- a. Secondery water low pressurc monitor.
- b. Bulk water monitor. ,
- c. Water conductivity monitor. .
- d. Portable Survey Meter (GM) ,
- ANSWER i K.08 (0.75) ;
' a.
I i
- REFERENCE RRF Emergency Impl emer.t n .un Procedures, and Appendix D 1
1 J
1 l
l i
i
)
i l
l l
l i
Si l
._.,. _ -,._ _ _ _ ,,._ _ ___ __.., _ _ ____ _ _ _,_..__,,_ __. _ _ , ___, _ .,,.. _ ,_,,_,.,_.._, _ 1
' e 4
- QUESTION K.09 (O.75)
MULTIPLE CHOICE (Select the correct response) . ,
There are fixed safety devices at Reed that are capable of detecting fuel failure, or other hazardous reactor' conditions. As-
- specified in Reed's Emergency Plan Which of the following safety devices activates a warning light on the control console and audib.te buzzer in the control room?
t
- a. Secondary water l ow pressure moni tor. ,
I b. Bulk water monitor. ;
- c. Water conductivity monitor.
i
- d. Portable Survey Meter (GM)
)
- ANSWER K.09 (0.75) b.
i
- REFERENCE i
j RRF Emergency Implementation Proceduren, and Appendix D l
a i
e i
i i
i 6
4 S2
__--_.__-_.__,,--_-,_.-,,,__,_._....,....,__-_,.__..,4.,___._.
' i
.e
- OUESTION '
K.10 (0.75)
MULTIPLE CHOICE (Select the correct response)
There are fixed safety devices at Reed that are capable of detecting fuel. failure, or other hazardous reactor conditions. As.
specified in Reed's Emergency Plan Which of the f ollcwing saf ety devices normally reads about 0.1 mR/hr when the reactor is operating and is located at the Reactor Room door, in the control room? l
- a. CAM
- b. Bulk water monitor. ,
I
- c. RAM l
- d. Portable Survey Meter (GM) i i i
- ANSWER K.10 (0.75) 1
- d. 1
- REFERENCE ,
i ,
RRF Emergency Implementation Procedures, and Appendix D i
l t
t l
)
i I
i I i l
l 53
f i
I
- QUESTION K.11 (3.25)
A float device monitors the water in the reactor tank and provides the operator with three(3) warning alarms for-high or low level conditions. One ( 1 ) of these is a red warning light '
l mounted above the chemistry building roof. Reed's Technical Specifications and Operating Procedures provide specific limits for reactor pool water temperature and level.' Reed's Technical Specifications specifies the minimum water level at which corrective actions must be taken at a certain level above the top grid plate.
I
- a. Where are the other two(2) warning alarms for high or low level conditions located? (0.5 pts each) (1.0)
- b. What is the reactor pool temperature limit (degrees F) that j would require reactor shut down if exceeded, as specified by.
Reed's Technical Specifications? (0.25)
- c. What is the minimum water level (i n feet) above the top grid plate, at which corrective actions must be taken?
(0.25) !
- d. How can the low level alarm be manually activated for testing per Reed SOP 63 (Testing the Low Water Level Alarm)7 ;
(1.0)
- e. How does the operator know when to fill the reactor pool i under normal conditions per Reed SOP 70 (Completing the Weekly Chechlist)? tu.75) "
4
- ANSWER K.11 (3.25)
{ a. (0.5 pts each, any order) (1.0) ,
I
- 1. evacuation corridor l j 2. (buzzer) in the control room
- b. 120 (+/- 1) degree F (0.25) i c. 16 (+/- 1) feet (0.25) I
! \
l 1 d. Depressing the plunger undarneath the bridge (on the far
! North side of the pool). (1.0) ,
I e. (By observing) the pool water level to be (an inch or more) J l
below the top U-bolt on the count rate detector support. ]
i also accept: Water level observed within 1 cm of ("nominal" level) scribe mark. (0.75) f
- REFERENCE l Reed SOP's 63 and 70; j Reed's Technical Specifications; S4
i a
l 1
I
. 1 l
1
)
- OUESTION j I
K.12 (3.5)
Reed's Technical Specifications require that the maximum ;
available-core excess reactivity shall be a certain limited value l
(% del ta K/K) . This requirement assumes that four(4) core j operating conditions exist. One(1) of these is that the reactor i is "cold". Technical Specifications also identifies a limit for the Keff for fuel storage under "all conditions of moderation."
This defines a "safe geometry" for fuel storage. Technical Specifications gives no credit for the cooling of irradiated fuel ;
elements or fuel devices by the forced flow of the water system. ;
- a. W'at is limiting value (% delta K/K) for the "maximum available core excess reactivity" at Reed. (0.25)
- b. What are the other three(3) core operating conditions
- assumed by Technical Specifications when analyzing the maximum available core excess reactivity at Reed?
(0.5 pts. each)(1.5)
- c. What is the value of the Keff limit that defines a "safe '
geometry" for fuel storage? (0.25)
, d. Why do irradiated fuel elements or fuel devices produce -
heat? (0.75)
- e. How is the adequate cooling of stored fuel elements or fuel devices ensured, as required in Technical Specifications?
(0.75) iAN5WER K.12 (3.5)
- a. 2.25 (+/- .02) % delta K/K (0.25) !
L
- b. (0.5 pts. each, any order) (1.5) j 1. (reactivity) experiments are in place ,
- 2. Xenon free
- 3. critical
- c. (l ess than) 0.8 (+/- 0.01) (0.25) i .
i
- d. The heat from the stored (irradiated fuel elements or fuel) devices is produced from the radia-nuclide decay process (decay heat). (0.75) 1 >
l e. The stored (irradiated fuel elements or fuel) devices are j required to be stored in a geometry that promotes adequate 2
natural convection (circulation) cooling (f rom pool water).
i s e s e s e r e s t ,- : .ere tw as areps',e rco 7 .a , , , ,,,,nts , ,L, (O.75)
- REFERENCE 'c # N d *' * "I a me- e vo< ",
i, Reed's Technical Specifications;
- J RRF Reactor Operations Seminar material 5b
-, - ~- - _ - - . _ ,. _._.,_ _ , , ,_ _ ,__,__,,_, ~ _ _ ,.,. ,,._ . - _ . . , _ _ _ _ _ _ _ _ . _ _ , _ . _ , _ , , . _ _ _ _ _ _ , _ , _ _ , _ . _ _ , . .
- OUES ,
K.13 (2.5) .
Reed's Technical Specifications require that the steady state operation of the reactor shall not exceed a certain kilowatt value (maximum thermal power per Reed's license) utilizing the three(3) strams listed in Table I and two(2) interlocks listed in Tablo II of the specifications. One(1) of these scrams is the Manual Scram function. However, for the_ purposes of testing these safety circuits, reactor power is allowed to exceed this maximum full power limit for the testing period, up to a higher maximum testing limit.
- a. What is the value of the maximum steady state thermal power limit (kilowatts)? (0.25)-
- b. What is this maximum testing thermal power limit (kilowatts)? (0.25)
~
- c. What are the other two(2) scrams listed in Table I of Reed's Technical Speci f icati ons?
__3, (must include initiating channel and setpoint) (0. 5 pts. i
- / each) (1.0)
- d. What are the two(2) interlocks listed in Table II of Reed's a Technical Specifications? (0.5 pts. each)(1.0) 1 1
L l
- ANSWER K.13 (2.5)
- a. 250 (+/- 2) kilowatts (' t t ' l' # # (0.25)
- b. 287.5 (+/- 2) kilowatts (0.25)
- c. (0.5 pts. nach, any order) (1.0)
- 1. Linear 110% of full power (275 kW)
- 2. Percent Power (log) 110% of full power (275 kW)
- d. (0.5 pts. each, any order) (1.0)
- 1. Control element withdraw prevented with lessthan(2 cps) on the nuclear instrumentation (startup channel).
l 2. Prevention of the simultaneous manual withdraw of 2
- control rod elements.
j'
- REFERENCE
, Reed's Technical Specifications I
i l 56
- OUESTION K.14 (1.25) ;
i
- In-core experiments usually ef f ect core reactivity parameters. ;
Furthermore, if not conducted properly, these experiments could present a radiological hazard to the general public. Therefore, Reed's Technical Specifications impose specific limits and i administrative requirements when conducting experiments. As required by Reed's Technical Specifications
- a. What are the three(3) types of experimental materials that must be doubly encapsulated? (0.25 pts.each) (0.75)
- 6. What is the maximum reactivity worth (dollars-$) of any individual in-core experiment? (0.5)
- ANSWER ,
K.14 (1.25)
- a. (0.25 pts.each, any order) (0.75) ;
- 1. materials reactive (chemically) with water
- 2. materials corrosive to (reactor) components
- 3. materials that are fissionable (l i qui d s)
- b. 1.35 (+/- .02) $ (0.5)
- REFERENCE j Reed's Technical Specifications ,
1 l
d H
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- l END OF SECTION K si ,
4 i
i i SECTION L P Administrative Procedures, Conditions, and Limitations
- QUESTION L.01 (3.5)
I The Reactor Review Committee (RRC) is established to provide for the independent review and audit of reactor facility operations and to advise a specific individual. The RRC may meet as a single committee or in two(2) subcommittees. One(i) of these subcomitteen is called the Reactor Operations Committee (ROC).
4 The ROC is composed of specified number of the facility staff, including two(2) individuals that are specifically identified by title. In accordance with Reed Administrative Procedures
- a. What is the title of the individual advised by th> RRC7 (0.5) ,
i l
- b. What is the name of the other subcommittee? (0.5)
- c. Who are the two(2) individuals (by title) that serve as non-voting members of the RRC and all subcommittees?
(0.5 pts. each) (1.0)
- d. What is the minimum number of facility staff required to compose the ROC (number onl y)? (0.5) ,
- e. Who are the two(2) individuals (by title) that must serve as members of the ROC? (0.5 pts. each) (1.0) r
- ANSWER L.01 (3.5)
- a. President of Reed College (0.5)
- b. Radiation Safety Committee (0.5)
- c. (0.5 pts. each, any order) (1.0) i
- l. Director of the RRF
- 2. Associate Director of the RRF
[,. a r.:. s <wr wa-aw s%rric n r " ss .n a sa a er -p.y rr. [<.s m x)
- d. four(4) (0.5)
- e. (0.5 pts. each, any order) (1.0)
- 1. Reactor Supervisor
- 2. Health Physicist l l
j
- REFERENCE Reed Administrative Procedures 58 l
. _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ __________.______.___.________________________________________._________.___________________..______.J
.. . - ~. .. . .- - _ - _ . . -- . ----
4 i
- QUESTION r
L.02 (2.5) i i The Reactor Review Committee (RRC) basically has two functions; to-teview and to cudit. In accordance with Reed Administrative f Procedures: f i
- a. How often must each RRC subcommittee meet? (0.5)
-b. What are four(4) of the eleven (11) items that the ROC subcommittee must review? (0.5 pts. each) (2.0) ;
- ANSWER '
L.02 (2.5)
- a. twice a year (0.5)
- b. (any four, 0.5 pts. each) (2.0)
J
- 1. (10CFR59.59) unreviewed safety questions
. 2. SOP's ,
4
- 3. All new experiments
] 4. Proposed changes to Technical Specifications j 5. Violations of. Facility License (or Tech. Specs.)
- 6. Violations of internal procedures (or instructions)
~
- 7. Fuel Movement (or Core Changes)
- 8. Reportable Occurrences l
- 9. Operator Training Program ;
' 10. Operator Requalification Program 1 11. Unexplained SCRAMS
- REFERENCE [
Reed Administrative Procedures i
t t
l
+
1 I
r 4 I 4
i i l 1
) l 1
[
4 09 !
- CUESTION L.03 (3.5)
The Rabbit Operator retrieven an irradiated specimen of PU-239 from the reactor during an experiment. While removing it from the receiver he slips, breaking the specimen tube and knocking himself out. The air containment isolation system activates and the Reactor Operator immediately initiates the evacuation alarm.
Commensurate with Reed's Emergency Implementation Procedures (EIP's), all persons in the RRF operations area are correctly evacuated to the assembly area. You are not on duty, but are the "senior member of the ENCL present", subsequently acting as the Emergency Coordinator Cone (1) of the three(3) persons authorized by Reed's EIP's to act as Emergency Coordinator]. You authorize reentry to save the life of the unconscious student. Per Reed's EIP's:
- a. Where did the Facility personne' '.s u emb l e? (0,5)
- b. Wha:. in the maximum area exposure rate (R/hr) that limited reentry can be made to save a life? 0.5)
- c. What is the maximum done (rem) that personnel may receive to save a 1i+e? (O.5)
- d. Who are the other two(2) individuals on duty (by title)
- authortred to act as Emergency Coordinator?
(0.5 pts. each) ( 1. 0)
- e. Where are the two(2) places that the evacuation alarm can be sounded? (0.5 pts. each) ( 1. 0)
- AN5WER L.03 (3.5)
- a. Reactor parking area (0.5)
- b. 100 R/hr (0.5)
- c. 25 rern (0.5)
- d. (0.5 pts. each, any order) (1.Oi
- 1. SRO (on duty or present)
- 2. RO (on duty or present)
- e. (0.5 pts. each, any order) (1.0)
- 1. control console (red button, right side)
- 2. Reactor bay (south wall) 1REFEhENCE Reed'n Emergency Implementation Procedures j l
60
i
- QUESTION L.04 (2.75)
During the emergency evacuation outlined in the previous.
question (L.03), the personnel in the Reactor Day and' Control Room correctly exited through their specified pathways per Reed's Emergency Implementation Procedures (EIP's). While the evacuation team was removing the injured student they noticed the red jewel light illuminated on the front of the GSM. eadout in the Reactor Bay,
- a. What is the correct exit path for perr.onnel in the Reactor Bay, per Reed's EIP's? (0.5)
- b. What is the correct exit path for personnel in the Control Room, per Reed's EIP's? (0.5)
- c. What abnormal Facility condition is indicated by the illuminated red jewel light? (0.75)
(0.5)
- e. Where is the emergency grab bag stcred? (0.5)
- ANSWER L.04 (2.75)
- a. Through the (North East corner) emergency exit door in the Reactor Bay. (0.5)
- b. Through the evacuation (exit) cor ..or. (0.5)
- c. Air confinement set (air confinemen system). -(0.75)
- d. 75 rem (0,5)
- e. evacuation (exit) corridor (0.5)
- REFERENCE Reed's Emergency Implementation Procedures 10CFR2O 61
1 -
- QUESTION L.05 (1.75)
During a fire emergency, Reed's Reed's Emergency Implementation Procedures (EIP's) direct you to to secure the main facility circuit breaker in case of an electrical hazard. Furthermore, in any accident injury involving radiation or radioactivity, the ambulance with the affected individual is to be directed ONLY to one(1) specific hospital.
- a. Where is the main facility circuit breaker (room No. or accurate description of room location)? (0.75)
- b. Where are the keys kept that would allow access to the main facility circuit breaker (specific location)? (0.5)
- c. What is the name of the hospital identified for victims.of a radiological accident? (0.5)
- ANSWER L.05 (1.75)
- a. Room No. 7 (room across ivom the entrance to the Chemistry Stock Room) (0.75)
- b. emergency grab bag (0,5)
- c. Good Samaritan (Hospital) (0.5)
- REFERENCE Reed's Emergency Implementation Procedures 62
.. ~. . ._- _ _ _. _ . _ . -
i
't
- OUESTION L.06 (3.0)
There.are three(3) individuals, identified by title, that must ' be on the Emergency Notification Call List (ENCL). They are included as part of.the minimum number of licensed operators on the lict.
- a. What i- 'he minimum number of licensed operators required to be t the ENCL? (0.5)
- b. Who (by title) is responsible for maintaining the ENCL current? (0,5)
- c. Who are the three(3) individuals, identified by title, that must be on the ENCL 7 (0.5 pts. each)(1.5)
- d. Who (by title) has the ultimate authority over on-site activities and personnel during an emergency? (0.5)
- ANSWER L.06 (3.0)
- a. five (5) (0.5)
- b. The Director of RRF (O.S)
- c. (0.5 pts, each, any order) (1.5).
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- 1. The Director of RRF
- 2. Reactor Supervisor
- 3. Health Physicist
- d. Emergency Coordinator (accept any person authorized to act as Emergency Coordinator, if so identified) (0,5)
- REFERENCE Reed's Emergency Plan i
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- OUESTION L.07 (1.0)
In accordance with Reed's Administrative Procedures a certain number of individuals must be present within the Reactor Facility when the reactor is not shut down as defined in Technical Specifications. At least one(1) of these individuals must be an NRC - licensed operator. The Senior Reactor Operator of record must be present in the Reactor Facility or one(1) other place.
- a. What is the minimum i. umber of individuals mtst be present within the Reactor Facility when the reactor is not shut down as defined in Technical Specifications? (0.5)
- b. What is the other place that the Senior Reactor Operator of record may be? (0.5)
- ANSWER L.07 (1.0)
- a. two(2) (0,5)
- b. Chemistry Building (0.5)
- REFERENCE Reed's Administrative Procedures l
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- OUESTION I L.08 (2.0) 1 Reed's Administrative Procedures identify two(2) major experimental areas, "in-core" and "near-core". There are three(3) specific reactor components that are apart of the "in-core" i
classification. There are two(2) specific reactor areas that are l
apart of the "near-core" classification. One(1) of the two(2) 1 "near-core" areas is:
l "Pool irradiations near core".
- a. What is the other reactor area (component) that is classified as "near-core" ? (0.5)
- b. What are the three(3) specific reactor components that are classified as "in-core" experimental areas?
(0.5 pts each) (1.5)
- ANSWER L.08 (2.0)
- a. Rotating Specimen Rack (lazy Susan) (0.5)
- b. (0.5 pts each, any order) (1.5)
- 1. Pneumatic transfer system (rabbit-in core)
- 2. Central thimble
- 3. Fuel Element Peplacement (Empty Source Holder)
- REFERENCE Reed's Administrative Pracedures i
- 4**********************
END OF SECTION L END OF EXAM 65
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