ML20214M503
| ML20214M503 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 09/08/1986 |
| From: | Burdick T, Dave Hills, Ridgway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20214M461 | List: |
| References | |
| 50-116-OL-86-01, 50-116-OL-86-1, NUDOCS 8609110144 | |
| Download: ML20214M503 (61) | |
Text
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U.S. NUCLEAR REGULATORY COPMISSION REGION III Report No. 50-116/0L-86-01 Docket No. 50 b - License No. R-59 Licensee: Iowa State University Ames, IA 50010 Facility Nane: Iowa State UTR-10 Reactor Examination Administered At: Ames, IA Examination Conducted: August 19, 20 and 21, 1986 i
Examiners: $df$)kgs)
K. R. Ri way 7/3/f/
Diti
- h. $.
D. E. Hills 9/MJ's Date Approved By: . . urdick, Chief Operating Licensing Section fk/k
,Dite Examination Summary Examination administered on August 19, 20, and 21, 1986 (Report No. 50-116/0L-86-01)
Examinations were administered to one senior operator and two operator candidates.
Results: All three candidates passed these examinations.
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REPORT DETAILS
- 1. Examiners K. R. Ridgway D. E. Hills, Chief Examiner
- 2. Examination Review Meeting An examination review meeting is no longer conducted. Specific comments concerning written examination questions, followed by NRC responses, are enumerated in Attachments 1 and 2. Other question / answer changes noted following the examination are shown in Attachment 3.
- 3. Exit Meeting At the conclusion of the examination an exit meeting was held. The following personnel attended this exit meeting:
Facility Representatives:
R. A. Hendrickson, Reactor Manager NRC Representatives: ,
4 D. E. Hills, Chief Operator Licensing Examiner '
K. R. Ridgway, Operator Licensing Examiner The following observations and generic issues were discussed:
- a. The examiners noted a general weakness of the RO candidates in the radiation protection area.
- b. The examiners noted that during the startup examinations that repeated spurious trips of the dump valve occurred just as the core tanks were reaching their operating level thus delaying the examinations.
- c. The examiners noted two discrepancies between the wording used in i the facility procedures and that used in the Technical Specifications (T.S.). These were brought to the attention of the licensee by telephone following the examinations.
(1) T.S. 4.2.3.c states the operability of the control rods and dump valve shall be tested daily when the reactor is operating.
Due to safety interlocks, there is presently no way of operational testing the control rods without the dump valve being closed and the core tanks being filled. Other interlocks prevent the withdrawal of the rods out of sequence.
(2) T.S. 3.8.3.c specifies that the reactivity worth of any experiment or group of experiments installed in the core shall be limited to -0.75$ to +0.22$. The normal operating procedure E.6.a implies that experiments greater than 0.22$ can be placed in the reactor.
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ATTACHMENT 1 Resolution to Iowa State University's Coments on NRC R0 Examination of August 19, 1986 Facility Coment on Answer A.07:
In addition to the graphite that surrounds the core tanks, the water above and below the fuel in the core tanks acts as a reflector. I don't believe that concrete plays a significant role as a reflector in the UTR-10.
Examiners Resolution:
Agree: Answer key was changed to also include water above and below the fuel.
Facility Comment on Answer B.03:
The worths of the rods are not correct (they are taken from a table from the Startu) Report,p.4-4,SAR). Use the values given in the sheet
" Selected Reactor Data" (found under General Information in Volume II of the Training Manual) since they are current measured values.
Examiners Resolution:
Agree: Correct values were inserted in the answer key and the reference added.
Facility Coment on Question / Answer C.03:
Question: There are only two operational conditions that need to be satisfied to use the automatic power controller. They are (1) power of at least one watt and (2) the regulating rod is above 5%. (Operations procedure.)
l' Answer: The b., c., and d. answers were taken from Design Considerations and Descriptions, p. 4-33, SAR. They are criteria that were adopted in the implementation of the design; they are all satisfied if the operating
- procedure conditions are followed. The down-limit switch is not closed if the rod position is 5% or more, the startup sequence is satisfied if the reactor is at one watt or above, and according to our experience, the power level signal is reasonably stable if the power is one watt or above.
Examiners Resolution:
Agree: The question and answer have been revised to include only two conditions for automatic operation.
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Facility Comment on Answer C.05:
Question / Answer: There is only one way you can verify that the source has been withdrawn--by seeing that the power increase is briefly retarded. The cable can be withdrawn but the source may not be attached to it. This issue is strongly emphasized during training. Why is the "0.775" in the answer?
Examiners Resolution:
Agree: The question and answer have been reworded and the "0.775" has been removed.
Facility Comment on Answer D.04:
Question: The question is vague since we have two " linear power channels." They are (1) multirange linear power and (2) linear percent power.
Answer: If the applicant chooses the linear percent power channel, then the parts to the answer are--(a) fission counter / chamber and (b) local meter signal and high power scram signal.
Examiners Resolution:
Agree: The question has been changed to specify the multirange linear power channel; therefore, the answer was not changed.
Facility Comment on Answer D.05:
Question: There are only two rod withdrawal inhibits (or prohibits).
They are the first two given in your answers. Also, the question asserts that there is a TS setpoint for each of three prohibits; this is misleading since a switch can have no setpoint, and the applicant has to invent an answer that fulfills the setpoint criterion.
Answer: If you use Table 4.6-11 of the SAR, the entry "Any nuclear or process calibrate or test switch not off" shows a rod prohibit in the footnote. Actually that footnote is not entirely correct since each calibrate switch is connected to a scram condition and when the wide-range drawer "ssfety trip" control is on, it disconnects power to the rod drive motors. The applicants found this cut by trying out those switches on their own initiative. In the training program, I covered the two conditions with real setpoints.
Examiners Resolution:
Agree: The question and answer have been revised to specify only two prohibits and the point value changed from three to two.
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Facility Comment on Answer E.01:
Question: The questien states that there are "eight trip circuits. . .".
This is a false statement and confuses the applicant. There are eleven trips listed in the nuclear group of Table 3-1 of the TS. The question should have read. . . Name (eight of) the nuclear instrumentation channels that generate trips and give the minimum number required for '
operation.
Examiners Resolution:
Agree: The question has been changed to specify the eight nuclear instrunentation channels only.
Facility Comment on Answer F.05:
Answer to (b): The Operations procedure should list one more record--
Shutdown Checklist.
- Examiners Resolution
Agree: The Shutdown Checklist was added to the answer and the note "Any four out of five" was added.
Facility Comment on Answer G.02:
Answer: The question asks for the. . . average annual concentration. . .
so the only method that applies is to limit the energy release to 4760 kWh per year.
Examiners Resolution:
Agree: The question has been changed to methods and the annual deleted.
The point value was changed from one to two.
Facility Comment on Answer G.03:
(a) Do you mean for gamma rays? s (b) Do you mean whole-body dose?
Examiners Resolution:
Agree: The question was revised to specify gamma dose rate and whole body dose.
The above resolutions and the changes made in Attachment 3 either did not affect the applicants answers or werc taken into account when assigning point value to the applicants answers.
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ATTACHMENT 2 Resolution to Iowa State University's Comments on NRC SR0 License Examination of August 19, 1986 Facility Comment on Question I.06:
The question asks ". . . is it possible that personnel may be injured and unable to exit, . . .". The answer given does not coincide with the question. The question continues with ". . . what guidelines exist to determine what action . . .". This last part is hopelessly vague.
Examiners Resolution:
Agree: The first part of the question was changed to a statement ". . .
it is possible" Facility Comment on Questions I.08 and K.09:
I.08 Choose the equivalent question K.09 and drop this one.
K.09 Question: The points assigned to the question are excessive.
No other question has more than three points assigned to it.
The nine criteria for approving experiments are intended for the Reactor Use Committee to use when it considers approval of an experiment proposal. The approval of experiments does not fall within the scope of the SR0s list of duties or responsibilities. In other words, I don't train a SR0 to nemorize the criteria but to understand them and implement them. Once the RUC approves the experiment, the SR0 implements the conditions associated with the experiment. The operating conditions for each approved experiment are provided on the form " Operator Instructions for Experiments."
Examiners Resolution:
Agree: By error these two questions were identical except for point count. The question and answer to I.08 was deleted, the applicants response for 1.08 was used as the response to question K.09 and question and answer I.09 were renumbered to I.08. While the area covered by this question may not be specifically required to be in the ISU training program, the applicant's responses generally covered the criteria quite well and the question remains in this examination. It will not be included in the NRC question bank.
Facility Comment on Questions J.04 and J.06:
Same comments as in C.03 and C.05 of the Reactor Operator part.
Examiners Resolution:
Agree: The same changes were made in these questions and answers.
Facility Comment on Question / Answer J.10:
Question: (b) The goal of this question is to see if the applicant will recognize the word " absolute: and add 14.7 psi to the gauge pressure. I prefer the psig values since they are the ones that are observable.
Answer: (b) The correct answer is found on page 1 of the Precritical Checks and Tests Procedure; it is 18 psig.
Examiners Resolution:
Agree: The answer was changed to the psig value as used in the above procedure.
Facility Comment on Answer J.11:
These answers are correct, but Table 4.6-11 in the Training Manual has a typo for the scram value for period; it gives ten instead of five seconds.
Examiners Resolution:
The discrepancy is noted. The examiners also noted other disagreements within the TS requirements, SAR and ISU procedures. These are noted in the Exit Meeting paragraph.
The above resolutions and the changes made in Attachment 3 either did not affect the applicants answers or were taken into account when assigning point value to the applicants answers.
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1 ATTACHMENT 3 Corrections or Clarifications on Iowa State University NRC R0 and SR0 Examinations of August 19, 1986 R0 Examination Answer C.02 Values was changed to value Answer C.07 Value of the moderator temperature coefficient was changed to -0..'054$
per degree F and the reference changed.
Answer D.02 b.
Was changed to the description of a comoensated ion chamber to agree with the question.
Answer D.06 The dump value interlock preventing its closure if the minimum inlet temperature is not satisfied was added to the functions of the inlet temperature instrument.
Answer G.07 The S curve feature of the rabbit tube thru the reactor shield to prevent radiation streaming was added and a note "any two" was added.
SR0 Examination Answer J.08 See C.07 change above.
O U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION Facility: Iowa State University Reactor Type: UTR-10 Date Administered: 86/08/19 Examiner: Ridgway, K.
Candidate:
INSTRUCTIONS TO CANDIDATE:
Ure separate paper for the answers. Write answers on one side only. Staple question sheet on top of answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in esch category and a final grade of at least 70%. Examination papers will be picked up six (6) hours af ter the examination starts.
C=stegory % of Candidate's % of Category Value Total Score Category Value 16.0 16.0 A. Principles of Reactor Operation 14.5 14.5 B. Features of Facility Design 13.5 13.5 C. General Operating Characteristics 13.0 13.0 D. Instruments and Controls 14.0 14.0 E. Safety and Emergency Systems 14.5 14.5 F. Standard and Emergency Operating Procedures 14.5 14.5 c. Radiation Control and Safety 100.0 100.0 Totals Final Grade %
All work done on this examination is my own. I have neither given nor received aid.
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Candidate's Signature
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ES-201-2 l l
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination reans an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
Consecutively nurber each answer sheet, write "End of Category " as 8.
appropriate, start each category on a new page, write on 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 sheet 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 DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only. ,
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NRC Rules and Guidelines for 2 ES-201-2 License Examinations
- 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. This must be done after the examination has been completed.
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Examination questions on top.
(2) Examination aids - figures, tables, etc.
i (3) Answer pages including figures which are a part of the answer.
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- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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o ICU REACTOR OPERATOR EXAMINATION OF AUGUST 19, 1986 A. PRINCIPLES OF REACTOR OPERATIONS CUESTION A.01 (3.0)
A maximum allowable excess reactivi ty is specified in the Iowa State University (ISU) UTR-10 Reactor Technical Specifications (TS) .
- a. What is the maximum all owable in TS? ( 1. 0 )
- b. Why is it necessary to have excess reactivity in an operating reactor? (1.0)
- c. How is it determined? (1.0)
DUESTION A.02 (3.0)
- a. Def ine del ayed neutron f raction. (1.0)
- b. How is i t r el at ed to the reactivity of a reactor? (1.0)
- c. Why are delayed neutrons important? (1.0)
QUESTION A.03 (1.0)
Reactor power is at 10 watts and increasing on a 10 second period. How long will it take the reactor to reach 12.5 1.i l owat ts? (Negl ect heati ng ef f ects) .
QUESTION A.04 (3.0)
The f ollowing terms sound similar but are very dif f erent.
Explain the difference between:
- a. Fast and prompt neutrons. (1.0) b Slow and delayed neutrons. (1.0)
- c. Acti vi ty and Reacti vi ty. (1.0)
QUESTION A.05 (1.0)
Give two reasons why the neutron source is needed during startup of the UTR-10.
(**** Category A continued on next page *++*)
h O!EB1 ION A.06 (2.O)
- a. U! . (< t is the purpow of the " moderator?" (1.0) 1,. E::p l e i n how the moderstar accomplishes its fuor. tion. 41.0)
D UI. b 1 I O N A . C (2.O)
Wlist malerials i ri your reactor f orn. tiie noderetor ar ici the ref 1 ec i.or '
DUES l10N A.OG (1.0)
If the a verage moder ator temperature increases in the UTR-10, tiie riumber of n e-u t r or is leaiing from the cot e decteases. True ot- False, e
( -* + + +: + Ei4D OF CA'IEGORi A *r+++)
b _ _. _. 1 E 6 1 0 5 5 E O r. _ E O C l!.;1 1 1 _ D E J 1 0 0 OtJE5 r 1 ON Fi . 01 (2.5)
Frow Figtu e 1, nane the conponnits whi tt i corr espond to nuniber4 3, 4, 5, o, 7, 10, 11, 15, 16, and 17. (O. d dl DUE51 1 ON Ic . O.-' (3.Oi The dung valve has two liniting conditions + or opert L > oo 2n the T5.
- a. Wi t a t er e i. h e two 1irititin conditions especi s i edT 1.C)
- 6. How long does it tate to drein the water from the core t en Fr? t1.O)
- c. Is t.h e neg a i. i ve eeectivity f rom drai ni rag the core t a i . L. s included in the re' wired shutdown margin? (1.0)
DUE.ElION i:.63 (3.G)
The UT Fe-) O r eactor is contr011ed by positianing con _ral rode. N + iw the control r o:s e , (1.0), give the parths of em ch (1.0) ,, and br icil y descr ibe how they operatc. (1. 0 )
e DUErfiION B.04 (3.O)
Provide the following information on the UTR-10 standby AC power systen.:
- e. lhe comnoner.t s oced. ( 1. 0 )
- b. ihe equipment it supplies. (1.0)
- c. The limiting conciitions of operations spccifiee in TC.
(1.0)
Culf.IIUN L: . LG (3.0; L i is i t i no cor.di t i one. 4or operation (LCO) for the primr"v cool an t system lists sevao ccnditions that must be met or the ieactor shall not be made critical. For the f ell cm n t h r er- i n s t r ug.er.t s , provide tiiei r limits (setpoint) and their aut oa:a t i c f u n c t i on E> .
- a. Fr i mar y coolant out1et temper atur e. (1.O)
- b. Primary cool ant ilow rate. (1.0)
- c. Frimcr y coolant conductivity. ( 1. O )
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C__ GEUE66L_DEEESIING_GUGE6GIEBJ SIICE QUESTION C.01 (1.0)
How is the moderator level maintained?
OUE57 ION C.02 (1. 0 )
How is the floo through the deionizer control l ed?
OUESTION C.03 (2.0)
What two conditions must be sat 2 sfied to place the reactor in the automatic control mode?
OUESTION C.04 (1.0)
Give the normal operating r ange f or each of the f ollowing parameters, including units,
- a. Pr i mar y coolant f)ow
- b. Primary coolent level OUESTION C.05 (1.5) e At what power level is the cource no longer needed? Dv what means is the source withdrawn and how can you verify that the cource has been withdrawn?
CUESTION C.06 (2.0)
Give the two l i rai t i ng conditions for oper ati on for confinement specified in the T5.
QUECTION C.De (2.0)
Define temperature coefficient (1.0). The UTR-10 teaiper ature c.oef f i c.i ent is ______. Give units. (1.00 OUESTION C.03 (3.0)
Nanse the three mast frequently used cmperimental facilitiu at the UTR-10 reac tor and brief1v describe how each is used.
(*++** END OF CATEGORY C+nn)
e D, _IN5TFiU,1jEUTG_6HQ_CDUT F O'ie DUESTION D.01 (4.0)
A. A corapensated i o:. t hembr-r (CIC) is used as ibn diiector for the mult1renge linear power channel. Why in Um CIC necesr ar y? (2.O)
- b. How it the CIC tested to verify that i ts ottt; wit ctirr ent eccurately f ollows the thenging neutron popul ati on over full range of oper at i ori? (1.0)
- c. Hcw rauch can the range of neutron detection be ext e:.ded uri rig a CIC in place of an uncompensated ion c.h emaer ?
(1. 0 )
OUEST I 014 L. 02 (2.O)
Nsmo the- two types of neutr on detectors used in the UTF-10 and g2 ve a brief descr I pti on of how each operates.
QUESTION b.03 (1.5)
What position inoication i s provided for the:
- a. Safety rodt. (C.5)
- b. Shim-safety rod. (0.5)
- c. Regulating rod. (0.5)
OUESTION D.04 (1.0)
For the multirance l i rieur power channe):
- a. What type detector is used? (0.5)
- b. What automatic f unc ti cu= does linear thannel pr ovi do?
(0. 5)
GUES inn D.05 (2.O)
Name two rod withdrawal prohibits and the TS setpoint f or them.
QUESTION D.06 (2.5, The inlet and ou t l et primary coolant temperatures are measured by what type detec. tors. What f unctions are man
e E. ,_f.6EE.Ti.l.iul2 Et_125.EUCY_SYEIEr.-!O CUEST101' E. 01 (2.0)
Name the ci giet nuclear instrumentation channels that generate trips of the safety system es requirec by TS Table 3-1.
QLiESTIOl4 E. 02 (1.5)
Dc-scribe the response sequence of the eu t en,et i c s c r a:- system following a hi gh power trip.
QUESTION E.O! ( 2. 0 :-
W! .a t is r:ic e n t by the one-out-oi-two scr am Jogic used lor the Ul R-10 reactor?
r OUECIION E.04 (1.51 Ey what three wayc can a fuel elen.ent cladding fcilure be determined?
, OUEST I O!J E.03 (2.0)
Er: pl ai n how a primary coolant l eal-: in the heat enchanger would be detected.
01JESTION E.06 (3.O)
What are the three safety limits specified in T5?
DUEST1ON E.07 (2. 0)
What at t i en should be teken if the regulating rod pneit2on indicator f ails during sutoinati c oper ation?
(+++++ EC OF CATEGORY E +++++)
E z_ _EI69D OE R _GU R _E tjEElE U C Y _Q EE B611BE _EEg G QUBES OUESTIOt1 F.01 (1.01 What opcr ator actions chould be tai:en following a scram other thsn for n ar coal shutdown?
OUEETION F.02 (2.0)
As the operator on duty, what four sctione do you t al:e to
" secure the reactor" following the anr.our. cement that the building is to be evccuated?
QUESTIOll F.03 (3.0)
What is the T5 definition of " Reactor Secured?"
OUESTION F.04 (3.0)
- a. Whet operator attione. theul ci t> e t a l:e n if a r adi ati en monitor alerm is reccived? (2.0)
- b. What is Lie arec eadiction aanitor cet p oi r. t L r equi r .ed .
by 15? (1.0) e OUESTION F.05 (4.S)
The reactor operator it responsible for i.eeping reactor records.
- a. Name f i ve types of i nf or mati on that ic requi red to be documented in the reactor log. (2.5) t_ . Name four other records that auct be i.ept b3 the reector operator. (2.0)
DUELT I ON F . 06 (1.0)
- Where is the Emergency Support Eenter located?
(***+e END OF CATEGORY F ++F++)
G._E01210IIRMl0BIE06_QUR.AGEEIY OLIESTION G.01 (1.5)
N a u:c three personnel moni tor ing devi cer.
O-jE51 ION G.02 (2.C)
W. i nt ar e the methodt used to avoid exceeding the l i c:i t on the a.oroge con.entratic. cf Ar-41 in unr estri c ted areec i r.
the reac tor building?
DUESTION G.03 (2.0)
- a. It the gamros cioce r ate ironi e coint so trec is 1.6 rem /br at 20 centimeters froa. the source, what is tr.e doce rate at 2 n,c ter s? Show ycur work. (1.O)
- b. Mcw lono could you remain at the 25 centimeter location wi thout e;.c cedino th 10 CFF 20 quar terly whol e L od s doce 11 mi t0'5h ow your werk. (1.0)
DUCGTION U.04 (1.0)
Who reviews all enperimente er classen ei experimentc that could affect r ea c t i v i t'. or result in thcr relcaco of radicactive materialc?
OUECTION G.05 (2.O)
- a. Define a curie. (1.0)
- b. Why is i t necc-2 2ary to use more shielding for e cet in of one materi al than what it required for a curat 0 --
enother material' OLIE51 ION G.06 (3.O)
What er e the 10 CFR 20 r egulationc f or posting the ial 3 oui < @
sigoc"
- a. Radiation Arca. il.0)
- b. High Rediation Area. (1.0)
- c. Ar e there eny additionel requirements fer cither cf ih.
above areas? (1.01
(++++ Category G continued on nent pcge *+**)
QUEET IO!4 G. 07 (1,0)
Give two design feature-; of the rabbit tube that cerve to limit the radiation hanai-d during use.
QUESTION G.05 (1.0)
The ISU Emergency Plan states that re-entry into the f acility with high radiation e::posurec will bc under t al:cn for only two rencons. What are they?
OUESTIOf 4 G.09 (1.0)
If/the reading on a cutic pie (i oni L at i on chamber) ic 140 mR/h without the end cap. and 125 mR/h with the end cap on, what is the appro:<imate exposure rate, in mR/h, due to gacema radiation?
(*+**+ END OF C ATEGOF:Y G ++*** >
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- g -1::: *<1 1,,1, 2 = 1,d,a -i t s---
g "=;a
- g 13d = lada - line source
(
5"I~ R/hr x time = R reduced for - turbine. SC pump, messle.
g cp3 o " I I"** * **** P**
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8
- Seren ' rod fuel ap ph a " APap hase x K
, Poisons) k = f(quality & Pressure) y,, g ,,, ,p,g , g g ,
D, = ka + Sk (speed)'s Pressure (speed)'s power bk a k-1 MATil Q = kAa? = hA&T = UAAT
, ,26.06 y a
=b N * * ')0 log b=a N " *A E6V y Q = co?
'- ~
log x" = c log x 3.1 x tone All = m.c.,AT log *Y- = log x - log y AU -mcAT v 3 - Ma log my - log a + log y 11 = U + pV De'-et = Coeff a A Parameter as = ST pV = nRT Eih = Eth Tt Ta .
CV + CaVa a C (V + Va)
ANSWERS - Iowa State University 86/08/18 Ridgway,N.
6_ _E E10GI EL E S_ gE _ B;6LI QB_9tEB6IJ gNS ANSWER A.01 (3.0)
- a. 0.781 (T S ) or 0.5% delta k/k (SAR) (1.0)
- b. To provide for loss of recctivity from tempere.turc.
voids, fuel depletion, and iission product build up and to have sufficient control s rods in the core for control. (1.0)
- c. Its value it cal cul ated by using the critical rod positions and the reactivity worth curves of each control rod not fully withdrawn from the core et e j ut.t critical level. (1.0)
Reference:
150 TS 3.1 ISU Irainsng Manual pg 20-21 ANSWER A.02 (3.0)
- a. Delayed neutron fraction = Deleyed neuteons/
Delayed neutrons + prompt neutrons (1.0)
- b. The del ayed neutron f racti on of 0.0065 for the UTF-10 fuel is defined as one daller of reactivity. (1.0)
- c. If the encess reacti vi ty exceeds the del eyed neutr or, fracticn, the reactor may not be controllable. (1.0)
Reference Bedi c Reactor Theory ANSWER A.O'. (1.0)
F= P* e >. p (l/T) 12,500 = 10
- exp (L/10)
In 1250 = t/10 t= 7.13 + 10 = 71 cec = 1.2 min. ( 1. 0)
ANSWER A.04 (3.0,
- a. Fast neutraris ref er to those al high energy l evel s; while prompt neutrons are those released at the time of f i sei on. (1.0)
- b. Slow rieutrons are neutr ons at low energy levele; w: a l t de eyed neutrons ar e those that are emitted from fim. ion fragments af ter the fi ssion event. (1.0)
- c. Acti,ity is t!e rate of radioactivity decay while reactivity is the amour.t of deviation c.f a r eactor f r csa, the just critical condition. (1.0)
Reference Besic Reactor Theory ANSWER A 05 (1.0)
To provide suffic>ent neutrons to get tiie c h es i n reactio.
going. (0.5) To aenerate a r eliable signal to the neutron detectors that monitor the startup range of pnwer. ( 0 . ".
RW erence Ita si c Reactor Theory
, ANSWER A.06 (2.0)
- a. Neutrons of Iow energy have the highest probabi1ity cri causing fission of the fuel. Most neutrons are born at high energy levels. The moderator reduces the neutt o:s energy level. (1.0)
- b. Mat eri al s moderate neutr or., by colli ci ons between t!.e neutrons and the mod er a t oc- nuclei. (1.0)
Ref er once Ba:si c Reactor Theory ANSWEfi 4. 07 (2.0)
Moderator - water (graphite)
Reflector - Graphite (and wc.ter above and below ine fuel)
Feference Basic Reactor Theory ANSWER A.08 (1.0)
Fa1se Reference ISU Training Manual pg 32 )
E.__EEOIUEES_OE_EGGILlIY_([GlOU_
ANSWER D.01 (2.5)
- 3. Thermel Lolumn (.25)
- 4. Leed Gemma Curtain (.25)
- 5. Cor e (r e f l ec t or ) (.25)
- 6. Core Tank (.25)
- 9. Shield Exper iment Doct (.25)
- 10. Shield Experiment Tank (.25)
- 11. beam Por t (.25)
- 15. Radiation Cavity (.25)
- 16. Pneumatic Rabbit Tube (.25)
- 17. Source Fositioner (.25)
Reference ISU Trainir.g Manual AN3WER D.02 (3.0)
- a. Operability, 600 milliseconds (1.0)
- b. Appr oximately 4 + or - 1 second (1.0)
- c. No (becisup shutdown action) (1.0)
Reference ISU Technical Specifications ANSWER B.03 (3.0) 2 Safety Rods, 0.72$ each. (1.0) 1 Shim-Safety, 1.02$. (0.5) 1 Regulatory Rod, 0.194. (0.5)
The operation of the control rods 2s analogous to that of a window shade. A stainless cteel cpring connects 1. lie F:or el sheet wi th a motor-dr iven drum. A drive motor rotates the deum which winds the spring eround the drum withdrauing tlie control element. This action stores energy in the sprir.g which, . )le nented wi th gr avi ty i ar c. e n , drivec the controi e l enien t into t h t: reflector w' ien the rods are scrammed by detoupling the dr um f r oni the n.otor drive by suddenly I removinc the holding current applied to the magnetic clutch.
( 1. D)
Reference ISU SAR ISU Training menual Vol. 2 1
i
\
\
- s AtJ5WERi B. 04 (0.0)
- a. Two had-acid storage batteries, a charger tr dcin f er f '
'N ur ni t . and an inverter. (1.0)
, i
(
- b. It supplien sel ect ed area r adi ation moni tors orid (1.0) ' rV s al er ms. , >
k
- c. For reactor oper est i ur e , the Eysteaa shall l;c oper 61.l e wi th 8' hours operating tinie"without elarm activetsc w .
'b g and,two hours with al ei nis or . (1.0) i RefetenLe, IGU EARA3.4 3
~
ISU T3 J '.,6 i f'
AtJCWER B.05 (3.O) f -
- a. Les ts then. " 60 degr ees F , alarm.
(1.O) -
i
- b. Greeter tk hi 3 gpa., al at m. (1.O) u u ;, ~ t ,
- c. Lees than C ini crombos/cm, al e rni. (1,0)
Fvfcrente ISU TS 3.3.3 and 3.3.4 t
e i n
.h . , _
b i
r I i w
i 'l
- 1
'Y 5
+ .,
t l
I O
L
\
~) g
+:_ s
$ I C GENEEAL OPERATING CHARACTERISTICS t
ANSWER C.01 (1.0)
- Core tank levels ere contiolled by a f i .:ed over f 1 ow pipe io i, - each corc tani:. fLevel variea slightly with flow.
s / '
Referbnce :
7 ISU SAR 4. 5. 5 (b)
(
ANSWUT, C.02 (1.0)!t
,7 I
- 7.-
p f B3 adjto.Li r a hand, a operated valve in the pr ocecs pi t.
Reference ICU CAR 4.5.3(b) i M.LL;ER C. O! , (2.0) v.
- a. . Pos.:r love.T(il at least one watt and regulating rod is above US. . ' ( l' .'M )
~7 )e l
- b. Regulatinoftpntrol el en.ent doun-limit ewi tch it not
~
closed d- the P.a.;ul at i ng Rod is greater then 5% out.
- (1.0) I e
us Reference 't v -
~.
u ISU,Startup Cequence
< At45WE) C.04 (1.0) s ,
% i e e. d.5-9.5 gpm- (0.5)
- b. 491-92% or 49-50 in. (0.5)
- f. .
+ o
? Fef er ence '
10U Operatirig r rocedure, Table 1
's AUGWCR C.05 ( 1.' 5 i
,i 5 E-04% or (50 mW) (0.5) pa dicelly b y- cable (0.5) mornenter y power d c.c r eas e (0.5)
~
Re f er *. n ce IEU-T7 raining Manuel Operatang Frocedure
./
4 ANSWER C.06 (2.0) i t
,, a. Confinement boundary shall be operable whenever 11.0
- reactor is ^ operating. (1.0) a
+-- - _ _ . ,
- b. Confinement boundary shall be secured during fuel transfer operations. (1.0)
Fseference ISU TS 3.4 I A!J5WER C.07 (2.0)
The chenge in reactivity di vided by the change in c.oderatur temper a ture , (1.0)
- 0.00544 per degr ee F'. (i.0) fieference ISU Trai ni ng Manual. pg 33 und selected date ATJSWER C.03 (3.0)
Experimental facilities most it equently ust:d and exampl es of I
i ex pter i men t al apparatus employed are:
--Pneumatic irradiation facility (r abbi t tube): This I facility is used to irradiete small volume senples in all I forms, i . e. , solid, liquid, or gas. The system is equicped l with en ebsol ute filter to ren.ove particulates from tha exhaunt s t r ea ns. Samples wiiich produce small positi w reactivity effects, e.g., metallic disks of uraniua, enriched l
, to greater than 90% in U-235, have been irtadiated ior del e ved neutr on and fission product gamma emi ssi on studice.
(1.0)
--Vertical central stringer (internal reilector): With thie stringer removed, space equidistant between core tanks becomes avail abl e f or insertion of equipment ranging f r om large volume neutron detectors to a reactor oscillster and similar apparatus based on vibt stino or iotating rieutr on absorbing materials. (1.0)
--Horirontal centr al str inger (thermal column): Wi th thi s strinoer removed, space in line with one core tent: is e vai l abl e to accommodate equipment r anging f rc n neutron detectora to a collimatino tube for extracting a neutron beam for di f fi acti on measur ements. (1.0)
O Two beam ports Irradiation cavity Shield tank Reference ISU SAR 5.3.1
Dz__1BilButtuIs_sup_cggIBgL ANGWER b.01 (4. 0)
- e. Gam nn-r av emi sei ens do not vary 1inearly with p>*r, as does the neutron flux. At high power, the ratio cf neutr ons to gamma-rayc is so high that the gamme-rcyc contribute little to the detector output however at intermediate and lower power levels, the gamma-ray induced ionizations are a significant fraction ena must be compensated for to obtain the ioninction effectc of the neutron flux which varies linearly with power level.
(2.0)
- b. Dy (1) operating the reactor at high power 1cng enough to reach equilibrium, (2) scramming the reactor, (3) recording detector current data es a function of time after scram, and (4) plotting the data au the natural log of the detector cur r ent vercus time. (1.0)
- c. Two to three decades on the lower power end. (1.0)
Ref er er.ce ISU Tr aini ng 11anual . pg 27 ANSWER D.02 (2.0)
- Fi sti on chambers (n , f i ssi on) - Interior chamber wall it a.
coated with uranium enriched in U-235 which produces fission fragments that, in turn, produce ion pai rs which are collected at the chamber electrodes. (1.C)
- b. Compensated Ion Chamber - One concentric region of the detector is filled with baron gas or coated with boron and detects neutrons indir ectly by the n olptia resction where the alpha particles ionize the fill gas, as well as gamma rays, and both p.oduce ion pair =. 1 l .e other concentric regica produces ion pairs from the gamme rays on1y. The resulting current i e sut.t r at ted f r om the current produced in the baron region and result'= in a current proportional to only the n population. ( 1. 0)
Reference ISU Training t%nual, pg 25-26
AtJ5WER D.03 (1.5)
- a. Up and down indication lights (0.5)
- b. Up and down indication lights and position transmitting potentiometers which indicale pos.ition es per cenLcae of full withdrawal (0,5)
- c. Jan.e at b. (0.5)
Reference IGU SAR pg 4-25 (d45WER D. 04 (1.0)
- a. Con.p en s a t ed ion chamber (0.5)
- b. Recorded power level and signal to the automatic poucr level control (0.5)
Reference ISU EAR pg 4-23 ANSWER D.05 (2.0)
Minimum count rate, Icon than 0.1 mW (1.0)
Moderator level, greater than 42 inches (1.0)
Reference ISU SAR Table 4.6-11 15U TS Tablen 3- 1 and 3-2 A!45WER D.06 (2.5>
Reuistance temper eture device, Rl D (0.5)
IN'_ET temper atur e , llc-3. Low temperature alerm. automatic control of secondery water flow, and dump valve clotute i nterl oc k 11i minimum inlet temperature i s not sMisfied
( 1. b )
Outlet temperature, TI-1, high temperature alarm (1.0)
Ez__@OEEll_6UM_EUEBGEUgy_EYElEUL ANSWER E.01 (2.0)
Two low power trips (source out) (0.5)
Two high power trips (0.5)
Two fant period trips (0.5)
Two high voltage loss to n-detectors (0.5)
Feference ISU TS Table 3-1 ANSWER E.02 (1.5)
Upon receipt of trip, power is cut off to the rod clutches of the two safety and the shim-safety rods. They are driven into the core by spring and gravitational forces. (. ~)
The reguleting rod is automatically driven into the ct -
(C.5) and the dunip val ve opens draining the core taril:n to the dump tank. (0.5)
Reierence ISU 54R 4.6.1 and 4.6.4(b)
AN5UER E.C3 (2.O)
There ere two safety circuits for each safety par enie t er but it takes only one of the two to trip the safaty system.
Re-f erence I5U SAR 4.6.2.(b)
AU5WER E.04 (1.5)
Rel ease of fission products will be detected by increanc- in thc coolant conductivity (0.5), the radiation dose r,te increase et the deionizer monitor (0.5), and coolant t a na l .e anal ysi s. (0,5)
. Re f er ence ISU SAR 6.1.2(b)
ANSWER E.05 (2.0)
The leak would be detected by a lots of coolant Iceel an the dump tank (1.0) and by lors of suction head to the pr : n.ar y pump. (1.0)
Reference ISU 5AR 6.1.2(c)
ANSWER E.06 (3.0)
- a. Power level, 15 kW. (1.0)
- b. Primary coolant flow not less than 3.5 gpm. (1.0)
- c. Pri mary coolant temperature not grcater than 180 degrees F. (1.0)
Reference ISU TS 2.1.3 and 2.1.4 ANSWER E.07 (2.O)
E!.ut off the automatic controller (1.0) Operation uv continue ucing the shim-safety rod for contiol. Otherwis.
, shutdown (1.0)
Reference ISU Training Manual - Operating procedure C.2
E__eIOUE.0BD_002_EUEEGEUEY_ESOCERUEgs ANSWER F.O! (1.0)
Type of scram and its cause chall be determined und rccorded in the Reactor Log. (0.5) Nati-fy the SRO. (G. D)
Ref er ence IEU Training Manuel - Oper. Procedure A ANSWER F.02 (2.G)
- a. Initiate scram by r en.ovi n g Lcy. (0. 5)
- b. Check rods are down and tal:e log book with you. (0.5)
- c. Activate evacustion bell. ( 0. 5 )
- d. Shut off circui t breai:ers. (0.5)
Reference IGU Tr aining Manual Oper ating Procedure D.3.a ISU Emergency Response Procedure pg. 10 ANSWER F.03 (3.0)
- 1. Reactor containt incuf fici ent f uel oc moderatcr or (1.0)
- 2. A combinatiori oi:
- a. niini rnuni number of control rods are inserted and (0.5)
- b. (1egnet power off with Ley removed and (0.G)
- c. No work involving core, c or e.- strccture, carit! ol rode, control r od dr ives (unless rode are decoupled) and (0.5)
- d. Na high reactivity experimento are bei ng moved. (0.5)
Geiarence ICU TS 1.0
ANSWEP F.04 (3.0)
- a. 1. Detcrnine location end magnitude of reading.
(0.5)
- 2. If reading it abovc 50 mrem /hr, manually screm reactor. (0.5)
- 3. If por table monitor confirms reading, initiale evacuation. (0.5)
- 4. If reading is between trip setting and 50 mrom/hr and confirmed with portabic monitor to be abnorms:1 from Operating I'arameters Table, pl ace reactor in hot standby or shut down, as apprcpriate. (0.5)
- b. 5 mrem /br. normal and up to 50 mrem /hr maximum depending upon local conditiatic. (1.0)
Reference ISU Training Manual - Oper ating Frocedure B.2 15U TS Table 3-3 nN6WER F.05 (4.5)
- a. Rcactor Log - Significant events (G.5), Stertup record format for each startup from cold shutdown (0.5) - identification and location of each inccre experiment (0.5), power level change and times including scrams (0.5) shutdown times and reactor cecured (0.5). (2.5)
- b. Pre-critical Chec t:l i st (0.5)
OperatIrig Log Sheet (0.5)
Ir r adi at i on Log (0.5)
Visitor Log (0.5)
Shutdowr. Log (0. U )
(Any 4 of 5)
Reference IGU Trainine Manual - Operating Procedure A.1 AN5WER F.CS (1.0)
Basement room ( Ro o n. 9) i .1 Sweerity Hall next door to reactor
G ._ _ _ BOD 10I l00_c.Ou1Eck _ sue._s.eEEIY ANSWER G.01 (1.5)
Film bedoes (0.5)
Pocket Ion Ch aaiber s , F'I Cs (C.5)
T her mol un.i nescent Dos 1 meter s or TLDs ( 0 . G 's Reference IEU Tr airiing Nanual - Radi ol ogi cal Safety ANSWER G.02 (2.0)
Fiestr i c t i ng the nurnbern of !!Wh of reactor oper ati on ps: wee l .
(100) or per year (4760)
Reference ISU TS 3.7.3 and 3.7.4 ISU SAR 4.5.4 AN5WER C.03 (2.0)
- a. (1.600 rem /hr.) (25 ca.) equered/(2GG tm) sauereJ c U.025 run./hr or 25 arem/hr. (1.0)
- b. Quer t.er l y whol e body dos,e = 1.25 rem or 1250 nirem (0. 3 )
1250 n. rem /16CO mrem /hr = 0.78 hrs or 47 mins.
(0.5)
Reference Bonic Theory 10 CFR 20.101 1
a ANSWER G.04 (1.0)
The Reactor Use Committee Rcference ISU TS 3. 8. 3. A and 6. 2. 3 (3)
AN5WER G.03 (2.0)
- a. Amount of radioactive material that enitc 2.22E12 duo or 3.7E10 dps (1.0)
- 6. Effectivenecs of shielding dependt upon the type of radioactivity emitted and the energy. (1.0)
Reference Basic Theory ANSWER G.06 (3.0)
- a. A dose in excess of 5 mrem in one nour or 100 mrum i t. 5 consecutive days.
- b. In excess of 100 mrem in one hour.
- c. High radiation areas are equipped with controls such as shielding, alarms, or locks. May use direct surveillance for less than 30 days.
Reference 10 CFR 20.202 and .203 ANSWER G.0~ (1.0)
Usco filtered compressed air (0.5)
Exhaust is f il tered thr u HEPA f il ter s. (0.5)
Rabbit tube is curved thru shield to prevent radietion str eami ng . (0.5)
(Any 2 of 3)
Reference ISU SAR 4.2.7 (e)
ANSWER G.G6 (1.0)
- a. Save a 1if e or search ior unaccount ed personnel . (O.5i
- b. Prevent an impending disaster. (0.5)
Reference ISU Emergency Plan 3.6.3
. ANSWER G.09 (1.0) l
Reference bat:i c Theory La-e
.1
W.S. NUCLEAR RECMATORY COI9815SION ED110R react 0R OPERATOR LICMSE ERAM1MATION Facility: towa State University Reactor Type: UTR-10 Date Administered: 86/08/19 Examiner: Ridgway. K.
Candidate:
D STRUCTIONS TO CANDIDATE:
Write answers on ane side only. Staple C e separate paper for the answers. Points for each question are indicated question sheet on top of answer sheets.The passing grade requires at least 70% in in parentheses after the question. Examination papers will be cach category and a final grade of at least 70%.
picked up five (5) hours af ter the examination starts.
1 of Candidate's % of Category Category Category Value Value Total Score R. Reactor Theory WA1VED
- 1. Radioactive Materials 15.0 20.0 Bandling. Disposal and Bazards y 26.7 J. Specific Operating Characteristics K. Fuel F.sndling and y 26.7 Core Pcrt-c:crs L. Administrative Procedures.
26.6 Conditions end Licitations
.20.0 Totals 75.0 100.0 Final Grade %
I have neither given nor received sid.
All work done on this examination is my own. 1 Candidate's Signature
l l
l
- ES-201-2 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. Re* troom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. Print your' name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first- page of each section of the answer sheet.
i
- 8. Consecutively number each answer sheet, write "End of Category as appropriate, start each category on a new page, write on only one side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category ano 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 sheet face down on your desk or table. ,
i 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.
l
5
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NRC Rules and Guidelines for 2 ES-201-2 License Examinations
- 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. This must be done after the examination has been completed.
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows:
(1) Examination questions on top.
(2) Examination 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 arswering 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.
2 i
l_ E6DIO6 Ell 2E__dOIE,B1865J;jBURLlUez_QlEEOSOL2_6UQ_UOMEQE QUESTION I.01 (3.O)
- a. la CFR 20.10)(a) specifies limits on the occupativi.al doce: that on individual may receive in each calendar quar ter . What are they? (1.5)
- b. The sane section also permits individual s to eaceed the whole body limit. Give the thi ee conditione unde:
which this is permitted. (1.5)
GUESTION I.02 (2.0)
A TS Liniiting Condition of Operation res,tricts the r c at or operation to 4760 KU-l!RL per year and 100 KW-ilR3 per wi.r .. k .
Whv? (1.0/1.0)
QUESTION I.C3 (1.5) 10 CFR 19.11 r equ2 res each liccnsee to pont or mal.e reada l y available five specific documents, name three of these.
QUESTION I.04 (2.0) e
- e. If the doce rate from point source is 1. 6 ren./hr et 2b centimeters from the source, what is the dose rate at 2 meters? Show your wark. (1.0)
- b. How long could you remain at the 25 centimeter location without exceeding the 10 CFR 20 quarterly des.e lin.it?
Show your work. (1.0)
DUEDTION 1.05 (2.5)
Wlic t cor r ccti su actions ar e spec.i ii eci in the ICU En orcn nci P l u. Alert for a largc fire?
. QUEET101t I.06 ( 2. O)
- a. Followiiia an incident at the ISU facility, it is postib1e that personnel may be injured and unable te enit, what ISU guidelinen enist for rescuers to deter mi ne what action should bc taken? (1.0)
L. Who can authorize exceeding 10 CFR 20 dose 11m t s '
(1.C)
(**** Categor y I continued on ncut page *+++)
W DUEST ION 1.07 (1.E)
If a smear exceeds ________, additional measuremer:ts ta l l be'porformed. Fill in the blant:.
QUES 110N 1.08 (1.0)
Give two design f eatuees of the rabbit tube that serve to limit the radiation he:ard during use, e
I
(+++++ END OF CATEGOfiY I ++++H
J.__.EEEGIElG_9EE BellUE_GU686EIE BlEIlgs OUESTION J.01 (2.0)
- a. Explain why tiier e i s a TS limiting conditi on of opcration for the primary coolent inlet temperature.
(1.0)
- 6. Ilow is the limit n.aintained? (1.0)
QUESTION J.02 (1.0)
Ho.w is the moder etor levtl mai ntai ned?
GUESTIGN J.02 (1.O)
How is the flow through the deionizer contr alledi OUESTION J.04 (2.O)
What two ceridi t iont muct be ceticfied to p1 ace ihe reacto; in the autometic contr el mode?
OUEST10N J.0:> (1.5)
Give the normal operatirig ranc.e f or each of the f ollowi rig parameters, including units.
- a. Frimary coolent fIow L. Primary coulant levtl
- c. Pr i mar y ccolant Lonductivity GUESTION J.06 (1.5)
At wnel_powcr l ev el is the sour ce no longer needed? Dy whet means is the source withdrawa and hou can you verify that the cource has been withdrawn?
OUEST1ON J.07 (2.O)
Give thc two lin.iting conditionc for operation for confinument specifled in the T5 and give the basen for these 1imito.
(+*** Category J continued on next page +++r>
QUESTION J.03 (2.0)
Def ine temperatur e coe f f i ci c,t ( 1. 0 ) . The UTR-10 temperature coefficient is _____. Give units. (1.0)
DUESTION J.09 (3.0)
Name the three mont f requently used expcrimental 4 acili ties at the UTR-10 reactor and briefly describe how each ir, used.
OUEST10N J.10 (1.0)
(4 s su mi ng primary coolant flow is normal.
- a. How much time is required to fill the core tani.e to normsl operating level? (0.5)
- b. What is the presture drop through the system in pouridt per squere inch gage? (0.5)
DUESTIDN J.11 (3.0, 0. 5 Ef.Cil)
Na nic si of the eight condi ti on s that will cause a scran?
e
( m *+ END OF CATEGORY J +****)
9 E __EUE t=_UBUE I US_03D_GOBE _COEGUEIECS QUESTION K.01 (2.0)
The fuc1 trensfer procedure states:
Fuel shall be transferred into or out of the reactor cor c with the control rods ________ __________
(1.0) and with the moderator _________ ______ (1,0). Fill in the blanks.
OUESTION K.02 (1.0)
The fuel transfer procedure states:
A __ _______ shall be present at the reactor consol e and nioni t or the nuclear instrumantation system whenever fuel i t, being moved. Fill in the blank.
QUESTION K.03 (3.0)
The UTR-10 TS permits the bypassing of certain channels pr ovi ded appi opr i at.e corcipensati on ia empioyed. What are the bypasset per mitted? (1.0) Why? (1.0) What ar^e the
, compensations employed? (1.0)
DUESTION I;.04 (1.0)
When moving low-activity fuel, the f uel handlisig tool <na y b r:
used if the SRO approves. True or Fa1se.
QUESTION I:.DD (1.O)
What instrumentation is used to follow a fuel (nov en'en t. into or out of the reactor?
DUE511ON K.06 (3.O) l Provide the following i nf or mation on the UTR-10 star.dby AC power system:
- a. The components used. (1.0)
- b. The equipment it supplien. (l.O)
- c. The limiting conditions of operation =s sp ec t -f i ed in is.
(1.0)
n DUESTION K.07 (2.0)
Fill in the blanks.
- a. The encess reactivity shall be measured on an ________
frequency end f allowing _______________. ( 1. J )
- 6. The shu t dc.wri mer gin shall be meacured on an___________
frequency and f o l l o w 2 n g _ _ ____ _ _ _ _ _ ,,, . (1.0)
DUE 5110lJ K.00 (1.0)
Whet is the survei11at.cc required i or coniinement? (0,5!
At what frequency? (0,5)
DUEGlION K.09 (6.0)
The ISU SAR lists nine coreditions that must be satisfied before an experiment can be conducted. Give six of these.
e
(++*n END OF CATEGORY K ++++*)
L. ,_ __ _60Sl U I_5 IB 611'i k,f Eg C E L!!jBE S1_GOULlllOUi!z_6UE 61t11T6110U5 DUESTION L.01 (3. 0 )
What i t- the T5 deiinition of " Fse s c t or Secured?"
QUE51JON L.OZ (1.C#
What is ihe mi riiriom staf f irig requi r ed by the 15U 7 5 w'wn the r eac toi- is not secur ed':
OlEST1DN L. 03 (2.G)
Wh.n is the direction of a licensed senior reactor operatur rcquirnfi DUi:ST 1 JN L. 04 (1.5)
What i s n ecnt L: y "r eadi l y available cn call" at defintd 2n the 15U '15' OUE5110N L.05 (1.0)
- e. Temporary de vi at i ori from procedurec. mcy b e iriad e bv the on-duty F>f:0 in order to deel with sp ec i c.1 c i r c u m s t ,-, n c e r:
or cor.di t i on e . 1 rue or False. (0. 5)
- b. The operebility of the control rods and the dump valve shall be tested daily when the reactor is operetin(.
True or Fa1se (O.5)
DUEG1 ION L C/, (2.Oi ISU TC requirs four cpectfic actions to be tal eii in cow 0 e Sefety L2 mil violattun. Neue them.
h
&+*4 Category L coiitinued on rien t panc **t* )
DUE51 ION L.07 (1.G) 10 CFR 55. 31 (e) . Operators Licenses, Conditions of the Licenste, states thal a licensee shall regularly activel y perforni the operating functions of an operator or serii or operator. If they have not operated for a period of
___,._____, he shall, prior to retuming licensed duti er ,
dea.onstrate to the _ _ _ . _ _ . _ . _ , _ ,
that his knowledge and understanding of facility operation and administration ere sati sf actor y. Fill in the blanPs.
QUESTIGN L.CB (2.0)
- a. What time i n t er val since the last precritical cherls would require a full precritical check before reecter start? (1.0)
- b. What oper e t.i ons in the precritical checklist *are riot required in the short form checklist? (1.0/
OWESTION L.09 (3.O)
The U1 h--10 con Lr cl concole contains an interlock system thet prevents closi ng the dump valve end/or withdrewing anv control rods. Name itiree of the five requirements that mu s. L be satiefied.
OUESTIOt1 L.lO (1.0)
Wiial condi t.i on must be in effect when experiments worth l e s h.
than 0.224 are i n s er t.ed or removed from the reactor? (0.5)
For ex p er i men t s. worth 0.22.1 or greater? (0.5)
OUEST1ON L.11 (2.0)
What iour conditions, n,ut t be fulii11ed to per mit vi w t cr eccess to the control room which is a controlled eccess e r . ./-
&+>+* END OF CATEGLRY L +++>+)
j REACTOR THEORY RA3!AT10N ' -
Fl.UIDS/THER99/ NEAT TRANSFg * '
L P = Pg o"b = P,10 I ** N = N,e'
= AnpaVa = AspaV A = IN Q = AnVt = AaVa
'! O Ap le g . g ,-pu = 1 10 -x M g
- gp . .e w ,= 0..,3 2.E,=Z,,t+AB,g,,,4
= . + ,. . . + , . . . .
y- ,
R/hr e d feet = 7 og 3
]
- k<' 8 s Point source I kf 1dt 3 = lada ,
Inda - lada - line source b"g C
- _-1_k reduced for - turbine. SG pump, nossle.
'M
- R/hr x time = R
I I*h ' " E IP D e
l 3 _ #P0 Aad x QF = Rem flow e (dp lM cpo, gBio , gRed I g ya g T'1,g g = U ' I'**
- I , ** *** *
" net *A doppler * ' mod ' void nto + ThMad D 23 c head lose e ap
+e se+D.+a,+S P-h + P e, gent .k !'
28 c F=PA
< ' Boron + ' rod * ' fuel ap8 phase AE8 pheme a.
op ,g ,,) k = f(quality & Pressure)
Pump laus speed a flow i % - km + Sk (speed)8a Pressues
- c. . ~ &~ - 1 MATil
("I'*d)8' E'"'#
Q = kAAT = hAAT = UAaf
.,. . _ 26.0s y a . i, Q- ga?
log ba s Q = mah 16V y e Q = co?
y' , 3.1 x 1018 log x = c Leg x all = m.c. AT P
g, log x = log x - los y AU = m s,AT los my - log a + los y H = U + pV A5 =
Defect = Coeff x & Paramete.r
}
pV = nRT 1
n 'i. . a tv2.
l 71 Ta
! CV + Cavs = C (Vs + Vs) l I _ ___ _
I _ _ BO DI O6 GIli'E_ daI EE16L g_ U60p61gg,_ p] E E O g66,_6Bp_ U616 S p 5 ANSWER 1.01 (3.0)
A. Whole body - 1 1/4 rem (0.5), extremi ti es - 18 3/4 rem (0.5), skin -7 1/2 rem (0.5)
- b. Whole body - 3 rem (0.5), accumulated dose
< 5 (N- 18) (0. 5) , licensee has accumulated occupation;31 done on NRC Forn. 4. (0.5)
Refcrence 10 CFR 20.101(a) and (b)
ANSWER I.02 (2.0)
The specificat. ion provides a censervetive Iimit on tht generation and rel ease of argon-41 and is based on meaturementc at this f acilit y (SAR: 4.5.4). Argon-41 in the only significant radicactive effluent produced during normal op er at i oi s of the resctor, and the limits providcd meet the requirements of 10 CFR Fert 2C. The first part is based on the ascumption tliot the r eactor operatet continuous 1y a t. 10 UW for 476 hours0.00551 days <br />0.132 hours <br />7.87037e-4 weeks <br />1.81118e-4 months <br /> and that the diluiion f csc i.or from diffucion of the air in the enclosure it ca il y 10 for these conditions, the argon-41 concentration averaged over one year is about. 50% of the value. (1.0)
The second part uses the assumptions that the reactor operates continuously at 10 KW for 10 hourn for one 40- hcur week; these conditions yield an average concentration in thc enclosure of 50% of the val ue listed for rectricted areat...
(1.0)
Ref er er ce ISU SAR 4.54 ISU TS 3.7.3 and 3.7.4 AN3WCR I.03 (1.5) 10 CFR 19, 10 CFR 20, the liccone, prccedures, and Fora, NRC-3, any three. (0. 5 s esch Re f c- ent e 10 CFR 1 "-; . 1 1
ANSWER I.04 (2.0)
- a. (1.600 rem /hr.) (25 cm) squared /(200 cm) squared =
0.025 rem /hr or 25 mrem /hr. (1.0)
- b. Quarterly whole body dose = 1.25 rem or 12GC, n.r em (0.5) 1250 mrem /1600 mrem /hr = 0.78 hrs or 47 mins.
(0.D)
Reference Danic Theory
. ANSWER I.03 (2.3)
Terminate r eac t or oper ati or e (0.5)
Notify Radiological Ser v2 ces (0.5)
Noti f y occupar.ts. (Evat. elerm) (0.5)
Notify fire department (0.G)
Notify Security (0 D)
Ref er ence 15U Emergency P1an, Talle pg 3-6 AN5WER I.06 (2.0)
, s. Re-entry into very high radiation environment will t. e undertaken only for these reasons: (1) Se vi ng 11 2e (up to 75 rem) or searching for unaccounted percanisel (0.5) or (2) prever+ing an impending disaster (up to 25 rem) (0.5)
- b. The Radiological Advisor (1.0)
Ref er e nce ISU Emergency F'l ari 3. 4. 7 and 0."
1 AN5WER 1.07 (1.0i 200 dpm/100 sq. c a.
Reference SAR 4.5.4
AN5HER I.00 (1.0)
Uses filtered co.npressed air (0.5)
Extiacst is fillered thru HEPA filters (0,5)
Reference ISU SiiR 4.2.7 (e) e
s 4__SEEGIE1C_OEEB611NG_CUQB@;1EBISIlGL AN5WER J.01 (2.0)
- a. The limit is bat.e d upon maintaining prima > y coolani temperature to avoid exceeding the excess' reactivity li mi t of TS 3.1.3.6 (0.5) at:d the bigh temper at ure safety limit of 160 degrees F. (0.5)
- b. Automatic temper ature coritral on a steam heuter in the dump tank maintains minimum cool aint temperature during stai-t up and no. mal operation modes,ow temperature interlock on closing the dump valve, and a low temperature alarm. (0.5)
Automatic temperature control on yhe secondary water with outlet temperature alarm at 160 degrees F (0.U'r Reference 15U 15 3.3.4 ISU SAR 4. 5. 3 (b )
AN5HER J.02 (1.0)
Core tant levels are controlled by a f i xed o'v erf l ow pipe in each core tank. Level varies slightly with flow.
Reference ILU SAR 4. 5. 3 (b )
ANSWER J.03 (1.0) by adjusting hand operated valves in the process pit.
Reference ISU EAR 4.5.3(b)
ANSWER J.04 (2.0)
- a. Power l evc.1 it at least one watt and regul at i ng r cai is i
above 5%. (1.0)
- b. Regulating control element down-limit switch is riot closed, or Reg. Rod is greater than 5% out (1.0)
Reference ISU Startup Secuence
s e
ANSWER J.05 (1.5)
- a. 8.5-9.5 gpm (0.5) *
- b.91-927. or 49-50 in. (0.5)
- c. 0.7-1.G micro mho/cm (0.5)
Reference IS'J Oper ati ng Procedure , Table 1 ANSWER J.06 (1.5) 5 E-04%, (50 mW) (0.5) physically by cable (0.5) momentary power decrease (0.5)
Reference ICU Tr aining Menual Operating Procedure Ai45WER J.07 (2.0)
- a. Confinement boundar y chall be operable whenever the reector is operating. Doors and windows of the reactor buildingt may bas e to br clor.ed in case of an accidental release of radioactivity. (1.0)
- b. Confinement boundary r. hall be secured during fuel transfer operations. Based on the hypothetical fuel drup accideist (5AR 6.4) and the importance of having the confinement boundary secured during fuel transfers.
(1.0)
Reference ISU TS 3.4 ANSWER J.00 (2.0) lhe change in r eactivit y di vided by the change in enod e r a t o:-
temperature, (1.C)
- C.OC541 per deurce F deurce F. ( 1. O)
Reference
. 15U Trainino Menual. pg 33 IEU SAR Table 4.1-1
s e
AN5WER J.09 (3.O)
Experimental f ecilities raost f requently used and enemp ec of experimental apparatus employed are:
--Fneumatic irr ediation f ecility (i nbbi t tube): Thit facility is used to i rr ad i e t ea small valume samples in all forms, i.e., solid, l i ciui d , or gas. The syt. tem i s equi ppt c; with an absolute filter to remove particulates from the exhaust stream. Samplen which or oduce sn.al l pot.itive reactivity effccts. e.g., metallic disks of urar.iun, enr a ched to greater than 90*4 in U-233, havc been i r r adi sted i or delaved neutron end Iisuion product gamme emission studiea.
(1.0)
--Verticel central stringer (internal reflector): With this stringer removed, spece equidictant between core tenks be omen availabl e f or i ns er t i on of equipment ranging from large voluma neutron detectors to a reactor oscillator und similar appar olus bat.ed ori vibrating or rotatinc; neu t r os i absorbing materialc. (1.C)
-Hor i z on t al central stringer (thermL1 column): LE t h t h i t; stringer removed, space in line with one core tank is a va i l ab l e. to acc ommodate equipment r anging f t om neutr on detectors to a c o l l i vr.a t i n g tube for extracting a neutron beam for di f f r action muscuren.ent t . (1.0) e Reference 15U SAR 5.3.1 ANSWER J.10 (1.O)
- a. 9 + or - 1 min. (0.5)
- b. 17-19 psig. (0.5)
Rcdercnce ICU Ope'ating f~rocedure, Pg. e ANSWER J.11 (3.O)
Powcr gr eater than 12.5 Fu (0.5)
Power greater then 1.0 W and closures not inet all ed or st ar tu;; cour ce not ctored (0.5)
Perlad less then 5 sm.onde (0.5)
L.ow hiah voltage to nuclear instruments ( 0. '?. )
High moderetor level (0.5>
Earthquale greetet than 1 R a f3 : (0.5) llanual Scram (3) cr key off (0.5)
Lo c c. of AC Power (0.5)
' A
% 15U LAR Table 4.6-11 o
L_ EUE6_.UOUD61Bg_6UD _GOBE_B6 Bet %TEBji A143WER l'.. C 1 (2.G)
Fully i rit t-r t e d (1.0) brained Out ( 1. O 'i Ref er ente 15U Oper ati ng Pr cicedur e - Fue1 Tr ein e,f er C ANSWER l'. 02 ( 1. C)
Reactor Operator or RO Reference 15U Oper atirio Procedure Fuel Tr ant.f er C A143WER i;.C3 (3.G)
Geouente of G6iety ficd withdrauel can be changed ( 0. E ) , to measure m a;; i mum worth of shim-safety rod (0.5) , if elepaud withdrawal times are obter ved et the rod that e:te.blishe_ .
critical 1ty in maneuvered. (C.5)
The cignal from the multirange linear power chanr.el neat; on detector may be used e.,clusively for measurement de te (0.5), for f l u:t indicetion during measurements of rcector thermal power or contrcl rod worth (0,5). If another detettor of equivelent theracteristicu iu ured an a substitute. (0.5)
Ricf er ente 15U IG 3.2.0.E and 3.24 AN5WER I. 04 (1.0)
Falso Reference ICU Oper ating l r ocedure - Fuel Tr er.s4 et C
0 A!'5WEfe I:.OS (1.0)
Two wide rance detectors set up for pulse counting and e fission chamber installed in the thermal column.
Reference IEU Oper atirig Pr ocedor e - Fue] Transfer, C A!15WER I.05 (3.0)
- a. T uc. l ead--ati d stor age b r.t t er i es , a charget- t r a n <. i n-uni t , and an inverter. (1.0)
- b. It supplies selected area radi ation n,oni tort and alarms. (1.0)
- c. For reactor operation, the system shall be o;.er able with 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> operating tino without al arm act i va ti on s and two hours with al er nis on. (1,0)
Rpfurence 151 t SAR . 4 IGU TS 3.6 Af 45WE R l',. 07 (2.0)
- a. Ar.nue l l y (0.S), significant core or control rod changes. (0.5)
- b. Annually (0.5), si gr.iii cant core or control rod changes. (0.5)
Referent.c ISU TS 4.1.0 AtibliER L. 00 (1.0)
- a. Con f i neinent doore and windows tested for nor nial c l e .iir e
- b. Oiico every quarter Feierence ISU TO 4.4.3 AtJLWL R I . 09 (6.0)
The de t i gn und condut t of experimer.ts must insure thot;
--- Ad d i t i on s or removals of meterials in the core rep en shc,uld not cauue l oc. e l heating to the entent thal fuel or cladding i s demaged ci thet the coolant boils.
3 o
--Additione or renioval e of materiele in the core regaon should not cause safety channel neutron detectors to generate f alee signals.
--Additions or r emoval s of mater i al s in the core rccaon should not ccuse a loss of worth of sa f e-t y-t ype con t.: ul el eine n t s .
--tiateriale capeble of exploding or reecting r api dl y , alone or with any other meterial, whether nor mally pr esent or not, shal1 not be used.
-M#tteri al c cepotel e- of eccelerating the corrosson o-i r ee;.t or components shall not be used in the reactor core region un1ecs offectisc enc 1 otoret, can b+. pr ovided.
--T he reactor does not achieve prompt criticality. No ex per i men L involving reactivity addtiiens i ri excern cf D . D', .
d e l 1.a L/L wi11 be al1 owed.
--Reactivity additions dur i ng oper ati on of experimcnty uh al l not produce positive periods less than 20 seconds.
--liat er i el t to be ac t i ve t ec' by neutron irradiation shall in:
enclosed in a munner a p p r o p r i a i. e for solid, liquid, or gabeovE eteles, at may Le r equired , to thet no uncontrol]et]
r el e s t e .- of radioactive natoriel will occur.
-Per s onn el shall not be ex pai.ed to exces c1 ve r adi ati on.
The methad of performing e,;periments shal1 be aJjusted whenever possible to comply with the "at low at r e e t o n e. b l y achievable" principle.
Any ei: of the nine Referenco SAR page 5-5, 6
s o
k 62'i. l IY_l L180ll W _EB9E!!_l Mb E S.s _ GD!q.i II.I OUS ,,,8UD__(JU,I .T [41_I Ot F AN E WE F- L.01 (3.0)
- 1. heector c ont ai r.c i re_.e f i 3 c j erit i uel or moderctor or (1.0)
- 2. A ccm.b i net A on ci:
- e. minimum riumber of control r o d r- ar e incer L d and ( ta . 5 )
Mtwie t power oti with key removed and (0.5)
~
b.
- c. Ila war.- involsing core, core structure, cor i tr al rods, contiol rod drives (unlens tads are decoupled) end (0.5>
- d. N. e high r eetti vi t y en per i ments are being navid. (0.5)
Prtorence 1 511 TO 1.0 Al Sv:i.R L. . O/. (l.5)
A RO in the control room. (0.5) e A SFO r eadi l y available on call. (0.5)
A Heelth Pliysi cs;- quel i f i ed i ndi vi dual readi1y ave i 1 etil e on cel1. (U.51 h e fq'.r tric o I bu l a o. l . :. ( 1 )
A!40WEh L . 01 ( 2. O 'i i, . L;e t or e a r et. over y 4 r oie en unp1onned or urmtint. .1+<i
<itivtd moi. (accumented verbel concurrence i-required) (b.b) l.. F os-1 trancfer op or < t i c.n .i (0.5)
- c. M a i n l + t u.h t e e t t ) v i l l e t, i nvol v) nct ihe safety E v 51 eni Llie t t.ould cause a
f.e4nreaco IOU Treinino Manual - Oper. Procedure, Normel, C.6 AW.,WER L.il (:.0)
- 1. Fuciegen, tool 1:1Ls, butt p a c k s. corried in r_
1nuptcted on entry and e;it (0.5)
- 2. Vicitor to eecor t ratio doce. not exceed 15:1:
nd vicual contact with visitors in maintairtud (0.5)
- 3. Vititor loo is signed, encept for NE studento.
(0,5)
- 4. A radiaticn monitoring dev2te in carrieJ. (0.5s