ML20245A770
| ML20245A770 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 04/17/1989 |
| From: | Hare E, Jordan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20245A754 | List: |
| References | |
| 50-123-OL-89-01, 50-123-OL-89-1, NUDOCS 8904250378 | |
| Download: ML20245A770 (41) | |
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- U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-123/0L-89-01 j Docket No. 50-123 License No. R-79 i Licensee: University of Missouri - Rolla Nuclear Reactor Rolla, M0 65401-0249 Facility Name: University of Missouri, Rolla Examination Administered At: Rolla, Missouri Examination Conducted: March 22-23, 1989 RIII Examiner: E. A. Hare cAk l{ ,O Date h
Approved By: M. J. Jordan, Chief #
Y 7/f7 Operator Licensing Sectio 1 Date '/
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Examination Summary Examination administered on March 22-23, 1989 (Report No. 50-123/0L-89-01)).
Examination was administered to one Reactor Operator candidate.
Results: The candidate passed.
8904250378 890417 PDR ADOCK 05000123 PDC V
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. REPORT DETAILS
- 1. Examiner E. A. Hare
- 2. Exit Meeting On March 23, 1989, a meeting was held to discuss generic findings made during the course of examination. Since only one candidate was examined, generic findings are not appropriate.
Overall, the facility was clean. However, the examiner noticed storage containers labeled as if containing radioactive material sitting in ground water that had leaked into the basement from a rainstorm the previous day. When questioned about the contents of the container, l the facility representative stated that they were empty. Containers of this type should be stored away from these areas since this appears to be a repetitive problem whenever it rains.
- 3. Examination Review Question A.04 Facility Comment should have given value for prompt neutron lifetime, 1*.
NRC Response Disagree with comment. Prompt neutron lifetime is value a candidate should know. The question and answer key remain unchanged.
Questien A.08 Facility Comment Question is very unclear and probably taken out of context. Recommend rephrasing to state "When is the ' system' reactor source critical."
NRC Response Comment noted. Question will be changed to "When is the reactor considered source critical" when it is uploaded into the main exam question bank.
Question 8.03 Facility Comment We have only half front and half rear fuel elements, which could be meant c with this question. They are used to " fine-tune" the excess reactivity.
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. NRC Response .
Question will.be deleted due to it confusing nhture. The word " fuel" was not meant to be included, thus the intent of the question was unclear.
Question B.06 Facility Comment The term " control element" is rather ambiguous SAR refers to it as
" control rod fuel element."
NRC Response The question is directly quoted from your facility's SAR. It was unclear ,
to the examiner if the two terms were in fact identical. The question I will be changed prior to uploading into the main bank exam question. We l recommend you update your SAR to eliminate ambiguous t.erms of this type.
Question C.04 Facility Comment Your answer is correct, but its not the only reason, another being to ensure a proper draw (flow) rate of chemicals.
NRC Response Facility did not reference any material to substantiate their comment.
The examiner could not find any. The answer key remains unchanged.
Question C.06 Facility Comment Actually, the purpose 2. (in your key) is implied in purpose 1 (in your key).
NRC Response Comment noted. Reference notes three specific uses for the single water purification system. The answer key will not be changed.
l Question C.09 Facility Comment l The reason 2. can also be formulated as ". . . to prevent build-up of_ radioactivity . . ." which is tantamount to activate impurities by neutron irradiation.
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, NRC Response l Comment noted.
Question G.03 Facility Comment All samples are meant: solid and liquid.
NRC Response The referenced material o,ily discusses liquid sample. Facility comment is noted.
Question G.09 Facility Comment Actually there are five criteria and the question should be such as:
"What are four out of five criteria . . ." (see your key).
NRC Response Agree with comment. Both the question and answer key will be i changed when uploaded to the main question bank. The candidate will only be required to answer four criteria.
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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION REGION 3 FACILITY: _UDiYz_Si_diEEQuci_______
REACTOR TYPE: BESEeBDH_________________
DATE ADMINISTERED: 692D2222_________________
INSIBUDIIDUS_ID_D8UDID8IE1 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 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
__VeLUE_ _IDI6L ___SDDBE___ _VaLUE__ ______________D8IEGDBX_____________
.16t50__ _1dtid ___________ ________ A. PRINCIPLES OF REACTOR-OPERATION h 3.OO
_idtLE__ _12tBe ___________ ________ B. FEATURES OF FACILITY DESIGN
_16160__ _1st2a ___________ ________ C. GENERAL OPERATING CHARACTERISTICS
_12tDD__ _12 TBS ___________ ________ D. INSTRUMENTS AND CONTROLS
_latDD__ _ lated ___________ ________ E. SAFETY AND EMERGENCY SYSTEMS
_16tDD__ _15tHe ___________ ________ F. STANDARD AND EMERGENCY OPERATING PROCEDURES
_16t5D__ _16143 ___________ ________ G. RADIATION CONTROL AND SAFETY
_1DDid__ ___________ ________% TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature i
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe 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. l
- 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.
- 8. Consecutive 1/ number each answer sheet, write "End of Cetegory __" as appropriate, siert each category on a new page, write only on 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. l
- 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 DO 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. This must be done after the examination has been completed.
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- 18. When you complete your examination, you shall:-
- a. Assemble.your examination as follows:
C1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages. including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions,
- c. Turn in all scrap paper and the balance of the. paper that you did not use for. answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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. 8t_ EBINDIELES_DE_BEBRIQB_DEEBoI1QN Page 4 l
QUESTION A.01 (2.00) j l
In each of the following cases, STATE the preferred characteristics for a '
moderator. Briefly explain why for each answer.
- s. Absorb neutrons or scatter neutruos. (1.0) ;
- b. Have a high atomic weight or low atomic weight. (1.0)
QUESTION A.02 (1.00)
List two reasons why the neutron source is needed during startup of the reactor. (1.0)
QUESTION A.03 (1.00)
A person being trained on the reactor has developed a system for reactor ctartups. He noted that the last time he did a startup the reactor was critical at 5000 cps. He reasons that for his next startup (some months later) when he reaches 5000 cps the reactor will be critica). Explain why this system is not valid. (1.0)
QUESTION A.04 (2.50)
Calculate the reactor period for the given conditions: Beff = .007. (2.5)
- c. Keff = 1.0001 for a prompt critical reactor
- b. Keff = 1.0001 for a delayed critical reactor (Show all work)
QUESTION A.05 (3.00)
- a. What is the maj or fission product poison in your reactor? (1.0)
- b. How is it produced? (Include decay chain and pertinent half-life) (1.0)
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- c. How is it removed? (Include decay chain and pertinent half _ life)
(1.0) l
(***** CATEGORY A CONTINUED ON NEXT PAGE *****) 1
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l,'et__EBINCIELES_QE_BE6CIQB_QEEBoIIQN' Page 5 l
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. QUESTION. A.06 (2.00)
Briefly explain the difference between: '
- a. ' Fast and prompt neutrons (1.0)
- b. . Slow:aad delayed. neutrons (1.0)
OUESTION A.07 (2.00) c.. Explain what the difference is between k-inifinite and k-effective.
(1.0)
- b. K~ effective of a reactor is given as 1.0795 delta k/k.
What k-excess' does the r e'a c t o r h ave ? (0.5).
- c. What reactivity is associated with this k-effective? (0.5)
QUESTION A.08 (1.00)
When is a reactor source critical? (1.0)
(***** END OF CATEGORY A *****)
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. ~Bi_;EEeIUBES_DE_E6CIL111_ DESIGN Page 6
- QUESTION B.01 (3.00)
Facility ~ Technical Specifications specifies six control channels that will cause a rundown of the shim / safety rods if their set point is exceeded.
Name three of these control channels and if applicsble, its limiting set point. (3.0)
QUESTION B.02 (1.00)
Facility Technical Specifications require rod withdrawal prohibits for the pool water temperature,
- s. Why is this rod prohibit required and state its setpoint? (1.0)
QUESTION- B.03 (1.00) f_,
- What are the iwu spec 2al Tuel elemenim esed far' (1.0)
QUESTION B.04 (2.00)
- a. What is the purpose of the special adj ustment slip clutch-on the shim / safety rod drive? (1.0)
- b. How does the slip clutch insure there is no accidental lifting of a control element? (1.0)
QUESTION B.05 (1.00)
Why is the aluminum tube in the core access element curved under the water in the pool? (1.0)
QUESTION B.06 (2.00)
Describe two ways that movement of a shim / safety rod could inadvertently lift a cortrol element out of the core. (2.0)
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
Bi__EE6IUBES_DE_E6CILIIX_ DESIGN Page 7
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-QUESTION B.07 (3'00) .
From Figure 14, attached, MATCH the correct items (a through f);
- s. Control Element b.. Magnet
- c. Rod. Drive Assembly
-d. Magnetic Guide Tube e.. Control Rod.Stop Assembly f.- Extension Tube Aesembly QUESTION B.08 (1.00)
When the reactor is operating, N-16 is produced in the pool. How is the
'rodiation level at the pool water surface minimized. (1.0) 4 f
(***** END OF CATEGORY B *****)
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GA_..GENEBeL_DEEBoIINQ_CueBeCIEBISIIGS Page 8 QUESTION C.01. (2,00)
Facility Technical Specifications requires that " experiments shall not be positioned so as to cause shadowing of the nuclear instrumentation."
- e. Explain what is meant by shadowing. (1.0)
- b. 'Why is shadowing undesirable? (1.0)
. QUESTION C.02 (1.50)
Facility Technical Specifications required the shim / safety cod drop times to be measured semiannually. Following what other three circumstances must the drop times be measured? (1.5)
QUESTION C.03 (2.40)
State the location of the three Radiation Monitoring System monitors and what they are monitoring.
QUESTION C.04 (1.00)
Why is it necessary to watch level when using acid and caustic tanks while doing demineralized regeneration. (1.0)
QUESTION C.05 (2.00)
Describe the two different arrangements possible when using the beam hole !
facility. (2.0)
QUESTION C.06 (1.50)
What are the three purposes of the single water purification system? (1.5) 1
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
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L, Ci_.QENEB8L_QEEB8IING_CU6BBCIEBISIICS Page 9 QUESTION- C.07 (1.00)
What.is'the reason for " vacuum breaks" in the purification piping? (1.0)
QUESTION- C.08 (2.00)
Fill in the Blank 4
- a. The minimum shutdown margin under any condition of operation with the
- h iginest worth control rod fully withdrawn shall.be no less than
_______ delta k/k. (1.0)
- b. . The-regulating rod.shall be worth no more'than _______ del:a k/k in reactivity. (1.0)
' QUESTION C.09 -(1.UD)
-State two reasons why the pool supply water is deionized prior to being
-supplied to the pool. (1.0)
(***** END OF. CATEGORY C *****)
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. Qx_alNSIBUbENIS_680 QQNIBQLS Page-10 1
i Q'UESTION. 0.01 (2.00).
- a. Describe the location (s) and type of sensor (s) used to measure the i pool water temperature. (1.0)
I L b. What automatic function is provided by the temperature. channel (0,5) 4 and what is the setpoint (0.5)?
l QUESTION D.02 (2.00)
Facility Technical Specifications require a maximum rod drop time of less than 600 msec.
- c. How does excessive magnet current affect the rod drop time? [1.0)
- b. What effects could low magnet current have on the shim / safety rods?
(1.0)
QUESTION -D.03 (1.50)
The drive system f or t he start-up channel is provided with a light indication system at the console. List the three positions the system will indicate. (1.5)
CUESTION D.04 (2.00)
From the log count r eit e recorder, two signals for the recorder i nt e r 1'o c k system are derived. Both signals prevent control rod movement. State the reason for each signal.
QUESTION , D.05 (1.00)
It is impossible to withdraw all four rods simultaneously. What prevents
.', this from happening? (1.0)
QUESTION D.06 (1.00).
-How often do the console instruments and safety system have to be calibrated? (1.0) 1 (****' CATEGORY D CONTINUED ON NEXT PAGE *****)
. Di_u1NSIBVdENIS_8ND_CQUIBQLS Page 11-
. QUESTION D.07 (1.S0)
Mstch the following reactor instrumentation (a through c) with the correct
. type of detector (1 through 3).
INSTRUMENT DETECTOR
- e. Startup Channel 1. Uncompensated Ion Chamber
- b. Linear Power Channel 2. Compensated Ion Chamber
- c. Log Power Channel 3. Fission Chamber
-QUESTION D.08 (2.00)
-nxplain how the servo-amplifier system is used to automatically control.the reactor power and describe how the system works. (2.0) 4-l l
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(***** END OF CATEGORY D *****)
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. Ei_2S6EEIX_6UD EdEBGENGX_SXSIEd1 Page 12
- QUESTION E.01 (2.50)
What five safety system channels are required to be operable before the i 1
reactor can be operated? (2.5)
QUESTION E.02 (1.50)
By what three indications can the leakage of water from the pool be detected? (1.5)
QUESTION E.03 (2.00)
-The Safety Channels sensing circuit contains two redundant circuits, each capable of actuating a r5ut off of magnet amplifiers in two different ways.
Describe how each of these two circuits operate. (2.0)
QUESTION E.04 (3.00)
For the'following situations (a through f), state the correct Protective Action (Scram, Rundown, Rod Withdrawal Prohibit, Safety Rod Withdrawal Prohibit, or Operator Response)
- a. Period < 30 seconds
- b. Bridge Motion
- c. Log N and Period Amp. Not Operative
- d. Effluent Pool Demineralized Conductivity high
- e. High Neutron Flux in Beam Room
- f. Safety _ Rods Below Shim Range QUESTION E.05 (2.00)
Whtn can the scram relay be reset and how is this accomplished? (2.0) l
(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
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IEit SoEEIY_oND_EbEBGEN91_SYSIEbH Page 13 6
' QUESTION E.06 (3.00)
Do' fine the'following terms: (1.0 each).
- 1. : Limiting Safety System Setting
- 2. Safety Channel
'3..
. Safety Limits t
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, IEi_ 1IoNDeBD_eUR_EdEBGEN91_QEEBoIIN9_EB0GEQUBES Page 14 QUESTION F.01 (2.00)
What precaution must be taken before a control rod is removed for inspection or maintenance? (2.0)
P-
. QUESTION F.02 (2.00)
Before an irradiation experiment can be performed, whet two forms must by completed and approved? (2.0)
QUESTION F.03 (2.00)
What four actions should the console operator take if a bomb threat is received by telephone while the reactor is operating? (2.0)
QUESTION F.04 (2.00)
What are the personnel staffing requirements for inspection.of control rods per1 SOP 302 " Inspection of Control Rods". (2.0)
QUESTION F.05 (0.50)
Who should be notified if a malfunction or abnormality of equipment is noticed? (0.5)
QUESTION F.06 (3.00)
The building evacuation alarm system has actuated. What six actions must be taken,by the Reactor Operator? (3.0)
QUESTION F.07 (1.50)
- u. State the time requirements for completing the Weekly Check. (1.0)
- b. If the reactor is not operable, which portion of the Weekly Check shall be performed? (0.5)
(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
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E r_ 1I6N D 680.6N D _ E t!E B G E NG L Q E E 86IIN G _ E 80 C E D U B E S Page ls
. QUESTION' F.08- (1.00)
During .the shutdown process'the' reactor operator notices that the control
- rods appear-to be jammed. What two actions must he-take?
(1.0)
QUESTION .F.09-; (1.00)
.What must the' reactor operator do if any interlock by pass key is required to be'used? .(1.0)
QUESTION F.10 (1.00)
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What are two circumstances when a reactor operator can disregard certain SOPS? (1.0) l l ,
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(***** END OF CATEGORY F *****)
Gi__'B6018IIDN_CQNIBDL_6UQ_SeEEIX Page 16 QUESTION G.01 (2.00)
- a. State the quarterly occupational dose limit for whole body, hands and feet, and skin of the whole body. (1.5)
- b. State the dose limit for individuals under the age of 187 (0.5)
QUESTION G.02 (1.50)
While working in en area marked "Coution, Radiation Area," en operator discovers his dosimeter is off scale and leaves the area. Assuming he had been working in the area for 45 minutes, what is the maximum dose he would have received? (Show all work and state any assumptions you have made.)
QUESTION G.03 (1.00)
Fill in the Blank A liquid sample can not leave the reactor pool unless the sample is
______________ on contact. Samples greater than this amount must be monitored by ______________. -(1.0)
QUESTION G.04 (1.00)
Which two people have the authority to extend a Radiation Work Permit? (1.0)
QUESTION G.05 (1.00)
What constitutes non-burnable radioactive waste? (1.0 QUESTION G.06 (1.50) )
1 Where is eating, drinking or smoking prohibited? (1.5)
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
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..- Dt_sB6016Il0N_cQUIBQL_6UQ_S6EEIX- Page 17 i LQUESTION G.07 (1.00)
To reduce exposure'to yourself and to others, what three factors should be considered?- (1.0)
QUESTION G.08 (1.50)
What does the term " SWIMS" stand for? (1.5)
QUESTION G.09 (2.00)
.What are the four criteria used when deciding who shall be the rescue personnel per SOP 603, " Guidelines for Emergency Exposures." (2.0)
QUESTION. G.10 (2.00)
Neme two features of the pneumatic sample transfer system design that are utilized to reduce overall radiation. ( 2. 0).
(***** END OF CATEGORY G *****)
(********** END OF EXAMINATION **********)
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2 2 Sphere A = 4 nr V = 4/3 (ur 3 Cube ///////////////////////////// V=S
o Page 5 of 5 DOI 6_SUEEI d1SCELLGUEQUS_1NEQBd8I1ON_1coctLauedl: ;
10 CFR 20 Appendix B Table I Table II Gamma Energy Col I Col II Col I Col II MEV per Air Water Air Water Msterial Half-Life Di si ntegrati on uc/ml uc/ml uc/ml uc/mi
-6 ~0 Ar-41 1.84 h 1.3 Sub 2x10 -----
4 10 ------
~# ~3 ~0 ~D Co-60 5.27 y 2.5 S 3x10 1x10 1x10 5x10
-10 ~#
I-131 8.04 d 0.36 S 9x10~ 6x10~ 1x10 3 10
~#
Kr-85 10.72 y 0.04 Sub 1x10~ -----
3x10 ------
~# ~0 Ni-65 2.52 h O.59 S 9x10 4x10~ 3x10 1x10~
-12 ~
~A -6 Pu-239 2.41x10 y 0.008 S 2x10 1x10 ^ 6x10 5x10
~0 ~1A ~#
Sr-90 29 y -----
S 1x10~ 1x10 3x10 3x10
~D ~#
Xs-135 9.09 h O.25 Sub 4x10 -----
1x10 ------
Any single radionuclides with T 1 > 2 hr which does not decay by alpha or/2 -9 -5 -10 3x10
-6 3x10 9x10 1x10 spontaneous fission Neutron Energy (MEV) Neutrons per em Average flux to deliver equivalent to i rem 100 mrem in 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> thermal 970x10 670 6
0.02 400x10 280 (neutrons) 6 30
- 0.5 43x10 --
3------
6 ,
17 cm x sec 10 24x10 l
Linear Absorption Coefficients p (cm~ ) !
Energy (MEV) Water Concrete Iron Lead l
O.5 0.090 0.21 0.63 1.7 1.0 0.067 0.15 O.44 L.
1.5 0.057 0.13 0.40 0.57 2.0 0.048 0.11 0.33 0.51 2.5 0.042 0.097 0.31 0.49 3.0 0.038 0.088 0.30 0.47 I
! l l
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!- j i
.et_.,EBIUQlELES_QE_BEeCIDB_DEEBel10U Page 18 1
. ANSWER A.01 (2.00)
- n. Scatter, so neutrons are lowered in energy rather than lost. (1.0)
- b. Low atomic weight so the fewer scattering collisions,are required (1.0)
REFERENCE i
Introduction to Nuclear Engineering section 6.5 b
ANSWER A.02 (1.00)
To provide sufficient neutrons to get the chain reaction going. (0.5)
To. generate a reliable signal to the neutron detectors that monitor the
'startup range of power. (0.5)
REFERENCE SOP 102 Introduction to Nuclear Engineering section 7.1 ANSWER A.03 (1.00)
The count rate at critical is e function of starting count rate (source) and the shutdown margin. Also several months later burnup, poisons, and ;
any changes in experiments will have some effect (1.0)
REFERENCE Introduction to Nuclear Engineering section 7.1 JAASTER COPY .
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
Tet__EBINQlELES_QE_BE6CIQB-QEEB611Q8 Page 19 ANSWER A.04 (2.50) p = Keff - 1/Keff
= (1.0001 - 1)/1.0001
= 0.0001 dk/k [0.53
- a. Reactor period T = 1*/p [0.5)
= (1 x E -4 sec)/(1 x E -4 dk/k)
= 1 sec [0.5)
- b. T= (Beff - p)/(Lp) [0.5)
= (.007 - 0.0001)/((0.1) (0.0001))
= 690 sec [0.5)
REFERENCE Introduction-to Nuclear Engineering section 7.1 ANSWER A.05 (3.00) s.- Xenon 135 (1.0)
- b. (1) Directly form fission. [.25]
(2) From beta decay of fission product-iodine-135 and te11urium-135.
[.375) .Te-135 decays to I-135 (11 second half-life) which then decays to Xe-135 (6.7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> half-life). [.375)
- c. (1) Burnout by neutron absorption. [.333)
(2) Beta decay to Cesium-135 [.333) with a 9. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> half-lif e.
[.333)
(Exact half-life not required, must be within 20% of actual)
REFERENCE Introduction to Nuclear Engineering section 7.4 ANSWER ,
A.06 (2.00) i
-a. Fast neutrons refer to those at high energy levels. [0.5)
Prompt neutrons refer to those released at the time of fission. [0.5)
- b. Slow neutrons are neutrons at low energy levels [0.5)
Delayed neutrons are neutrons are those which appear at some time after the fission event due to fission product decay. [0.53
(***** CATEGORY A CONTINUED ON NEXT PAGE *****)
D. .
- ^*/
m let__EBINCIELES_QE_BE8GIQB_QEEBoIIQU Page.20 REFERENCE Introduction to Nuclear Engineering section 7.1 ANSWER A.07 (2.00)
- a. K-infinite is the multiplication constant for a theoretical reactor
- with zero leakage. K-effective takes into account neutrons lost due
- to slow and fast leakage (k-eff = k-inf
- slow and fast non-leakage-probability.) (1.0)
(exact wording not required) b.= k-excess = keff - 1 = 1.0795 - 1 = 0.0795 delta k (0.5) l
- c. Reactivity = (keff -
1)/keff = (1.0795 - 13/1.0795 0.0736 delta k/k (0.5)
REFERENCE Introduction to Nuclear Engineering section 6.5
. ANSWER A.08 (1.00)
When it has a Keff = 1.0 with a neutron source present (1.0)
REFERENCE Introduction to Nuclear Engineering section 6.5 i
I 1
(***** END OF CATEGORY A *****)
I
! .- .sj . ,s n
1
. LEz__EE8IUBER_DE_E6CILIIX_ DESIGN .Page 21-ANSWER' B.01 (3.00)
. Linear ~ power (0,5), 120% (0.5)
Reactor period ~(0,5), 15 seconds- (0.53-Low-CIC voltage- (0.5), 80% (0.5 Radiation: Monitors (0.5), 20 mrem /hr (0.5)
Log power (0.5), 120%' (0.5)
Reg rod on insert' limit, in auto (1.0)
(any three)
. REFERENCE Facility Technical Specification. Table 3.1 l
' ANSWER B.02 (1.00)
Pool. water temperature: to protect demineralized resins (0,5), 135 degrees F (0.5) l REFERENCE Facility Technical Specifications Table 3.1 s ;-
ANSWER B.03 (1.00)
- 1. Irradiati }{)g.\gsfga
- 2. Isoto ' Production Purpose (2 at D. = 1.0)
REFERE E l
S 375 A
(Y)
- ANSWER B.04 (2.00)
- a. Insures that excessive loading on the shim / safety rod drive will cause the clutch to slip, thereby preventing movement of the shim / safety rod. (1.0)
- b. The force available to insert the shim / safety rod is always greater than that available for withdrawal. (1.0)
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
.. 4
..Hi _EE61MBES_DE_EeGILIIX_ DESIGN Page 22 REFERENCE SAR.3-16 ANSWER B.05 (1 00)
To prevent neutron [or gamma streaming (out the upper portion of the pipe).
.(1.0)
. REFERENCE SAR 3-17 ANSWER B.06 (2.00) 1.. Disassembly of the rod drive. (1.0)
- 2. Deliberate omission of mechanical components. (1.0)
REFERENCE SAR 3-16 ANSWER B.07 (3.00)
- e. 6
- b. 4
- c. 1
- d. 3
- e. 5
- f. 2 REFERENCE SAR Figure 14, pg. 3-15 ANSWER B.08 (1.00)
(Two water) pumps are used to direct surface water downward to the top of l
t rie reactor core (to delay the eq>> of radioactive nitrogen). (1.0) l C6G l
(***** CATEGORY B CONTINUED ON NEXT PAGE *****)
. 1 l- .
B___EE81UBES_9E_E8CILIIX_DESIQU Page 23 REFERENCE SAR 3-44
(***** END OF CATEGORY B *****)
._ - - _ - - - - _ _ _ -----_-___________J
. i Gi__GENEB8L_QEEB811GG_Cd686CIEBIEIICS Page 24 ANSWER .C.01 (2.00)
.e. Materials placed in such a.way as to cause a change in neutron flux at the detector at a constant power:1evel. (1.0).
- b. The instruments would.be given an inaccurate power.or flux indication !
in that area'of the core. (1.0)
REFERENCE Facility Technical Specifications 3.7.3 ANSWER. C.02 (1.50)
Drop times must be measured following the relocation of a rod to a new core position (0.5) and if the magnet assembly has been removed and reinstalled (0,5) and after rod inspections (0.5).
REFERENCE Facility Technical Specifications 4.2.1 ANSWER C.03 (2.40)
- 1. On the Reactor Bridge (.4) to monitor radiation levels above reactor pool (.4).
- 2. Near the demineralized (.4) to check for buildup of radioactive ions.
(.4)
- 3. At the area near the thermal column and beam port (.4) to ensure that no increased radiation level is present before entry is made into basement level C.43 REFERENCE, SAR 3-45 ANSWER C.04 (1.00) l l To ensure that no air is drawn into the system when level is low. (1.0)
(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
w _ _ _ _ _ _-_ - -_ __-_-___-___ _ _ - _ _ _ - _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _
1
, .c 1
Page 25
. TCt_aGENEBoL_DEEB6IING_CB886CIEB111103
- REFERENCE
~ SOP 204 pg 1 +
- ANSWER lC.05 (2.00)
- 1. Operated dry with a sample or experimental set-up located in the beam
~
tube.-(The two shield plugs are inserted into the. rear stepped ~
section of the hole)
'2. The beam hole facility can be used for bringing a collimated beam of.
. neutrons through the shield wall for experimental work.
(2 at 1.0 each =-2.0)
REFERENCE SOP 113 pg l' l ANSWER C.06 (1.50)
- 1. fill the reactor pool.with high purity water 2.- to provide pool water make-up due to evaporation and leakage losses
- 3. to maintain pool water purity be recirculation.
REFERENCE SOP 301 pg 1 i
j ANSWER C.07 (1.00)
To prevent draining the pool (below approximately 16 feet above the core).
(1.0) .
REFERENCE SOP 309 pg 1 l
j
'(***** CATEGORY C CONTINUED ON NEXT PAGE *****)
r.r_-____ .
t i
. t Cz__GENEBBL_QEEBoI1UQ_CBeBBCIEBISIIGS Page 26 ANSWER C.08 (2.00)
- e. 1.0% delta k/k
- b. 0.7 delta k/k REFERENCE Technical Specifications pg 10 ANSWER C.09 (1.00)
- 1. Reduce fuel element corrosion
- 2. Prevent build-up of impurities in the reactor pool water (2 at 0.5 each = 1.0)
REFERENCE SAR 5-1 I
1 l
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[***** END OF CATEGORY C *****)
Qt__INSIBUDENI$_66Q_QQNIBQLS Page 27 3
1 ANSWER D.01- (2.00)
- n. By two core inlet temperature thermocouple placed below the core (0.5) and one outlet thermocouple about five feet above the core (0.5) b.- Trip points of 57 degrees C (135 degrees F)( on the two. inlet temperatures) (0.5) causes a rod withdrawal prohibit (0.5)
REFERENCE Facility SAR pg 3-35 ANSWER D.02 (2.00)
- 1. Greater. magnet current will delay rod drop _ (1.0)
- b. Less current may prevent lifting the control rod.(0.5) or give spurious rod drops (0.5.)
REFERENCE Facility SOP 810 pg 7 ANSWER D.03 (1.50)
- 1. Insert Limit
- 2. Top Half-Travel
- 3. Withdraw Limit REFERENCE SAR 3-32 l
~
ANSWER D.04 (2.00)
- 1. (First signal prevents control rod movement until a minimum count rate !
is obtained (> This insures that the fission chamber is operating (0.5)f2 andc/s)).
that an adequate signal is available to begin startup (0.5).
l
- 2. (The second signal) prevents control rod movement if the log count rate recorder is not turned on. (1.0) l l
(***** CATEGORY D CONTINUED ON NEXT PAGE *****) .
_ . _ - - _ - _.___m__ .__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
' t.- .
.1Dt__INSIBubENIS_6ND_CQUIBQLS Page 28 REFERENCE-SAR 3-32
' ANSWER D.05 (1.00)
(There is an interlock system such that when the shim / safety rods are
. moved,-) power to the AC drive mechanism of the regulating rod is disconnected. (1.0)
REFERENCE.
SAR 3-35.
ANSWER D.06 (1.00)
Twice a year (not to exceed 8 months) (1.0)
REFERENCE SOP 803 pg.1
-ANSWER D.07 (1.50)
- a. Fission Chamber b.. Compensated Ion' Chamber
- c. Compensated Ion Chamber (3 at 0.5 = 1.5)
REFERENCE SAR 3-33
~
ANSWER D.08 (2.00)
When the reactor is at steady state power, the servo system may be energized to automatically maintain power level. The servo system is interlocked so that the power level must be within +/- 2% of the selected power level setting before the system may be engaged. (2.0)
(exact wording not required) l 1
(***** CATEGORY D CONTINUED ON NEXT PAGE *****)
1 1
. 1 Dz__INSIBUDENIH_oND_CONIB0L3 Page 29 REFERENCE SAR 3-36
(***** END OF CATEGORY D *****)
-3 4
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,L Ei;_S6EEIX_6ND_EUEBGENQX_SXSIEda Page 30
- ANSWER E.01 (2.50)
-Manuali seram Reactor period Log N and Period M o p m b e-Reactor Power Bridge motion I n e ; r e + 1 ue- -
Cany five at 0.5 each = 2.5)
REFERENCE Facility Technical Specifications Table 3.2 l
ANSWER _ E.02 (1.50)-
Increase in reactor bridge RAM ( 0. 5 ), increase in basement sump with alarm (0.5), and daily pool level readings (0.5).
REFERENCE Facility.SAR'pg g-7 ANSWER E.03 (2.00)
- 1. The first (master) circuit provides a fast scram which is obtained by applying cutoff bias directly to the grids of the magnet amplifiers. (1.0) i
- 2. The second (slave) circuit provides a backup scram by cutting off the i
AC power supply to the magnet amplifiers. (1.0)
REFERENCE SAR 3-37 l
L
(***** CATEGORY E CONTINUED ON NEXT PAGE *****)
E_____________________________ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
j
,,Et__S6EEIX_6NQ_EdEBGEUCX_SYSIEd3 Page 31
' ANSWER- E.04 (3.00) .
L a. Rod Withdrawal Prohibit
- b. Scram
- c. S c. r am
- d. Operator Response
- e. Operator Response f '. Rod. Withdrawal Prohibit
- REFERENCE SAR 3-40, Table IX ANSWER E 0S (2.00)
After.the condition causing a scram has been removed. (1.0) The reset relay' energized by manually pushing the reset button. (1.0)
REFERENCE SAR'3-42 ANSWER E.06 (3.00) i
- 1. Settings for automatic protective devices related to those variables having significant safety functions !
- 2. A measuring or protective channel in the reactor safety system. 3
- 3. Limits on important process variables which are found to be necessary to reasonable protect the integrity of certain physical barriers which guard against the uncontrolled release of radioactivity (3 at 1.0 each = 3.0)
(exact wording'not necessary)
REFERENCE Technical Specifications pg 4 and 6 i
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(***** END OF CATEGORY E *****)
i
______________________.,._________________________.____,__________g
.. w
- Page 32
.. Et__SI68DaBQ_eND_EdEBGENQ1_QEEBoIING_EBQQEQUBES l
ANSWER F.01 (2.00)
All fuel elements.necessary to insure the loading is below 50%'of a
-critical mass when all rods are removed (2.0)
REFERENCE Facility SOP 302 AN9WER F.02 (2.00)
- 1. A Request for Reactor Projects Form (1.0)
- 2. A Request for Irradiation Form (1.0)
REFERENCE Facility SOP 701 and 702 ANSWER F.03 (2.00)
'1. Obtain as much information from the caller as possible'(.5) 2.' Notify the SRO on duty and the campus police (.5)
- 3. Secure the reactor (.5) l 4 .- . Initiate evacuation (.5)
(0.5 each = 2.0)
REFERENCE l Facility S0P 506 ANSWER F.04 (2.00)
An SRO on duty (0.5) one R0 (0.5) and one assistant with some fuel handling experience on the bey. area (0.5) also a health physicist (or his representative) (0.5) l l
1 (r**** *****)
CATEGORY F CONTINUED ON NEXT PAGE
g , ,
p a. A u
1 u- ,
L ' .Er_5IoNQeBR_oNQ_EUEBGENQLQEEB6I1NG EBQQEQUBES -
- Page 33 REFERENCE
. SOP 302'pg 1
' ANSWER F.05 (0.50) <
SRO on duty '(0.5)
REFERENCE
. SOP 308 pg 1
-ANSWER F.06 (3.00)
- 1. ' scram'the reactor
- 2. ' remove magnet power key 2
- 3. obtain radiation instruments the. permanent, log
- 4. turn'off the exhaust fans
- 5. obtain the keys to the Physics Building where emergency equipment is kept-
- 6 ~. . evacuate the building himself (6 at.0.5'each = 3.0)
REFERENCE 1
. SOP 501 pg 3 ANSWER F.07 (1.50)
- a. It w il l tut completed on the first working day, but no later than the third working day of.each week.- (1.0)
- b. Only the Physical Security system test portion. (0.5)
RE F E RENC E. . l
. SOP 810:pg 1 ANSWER F.08 (1.00)
- 1. Stop driving in tne rods
- 2. Inform the SRO on duty.
-(2 at 0.5 each = 1.0)
.(***** CATEGORY F CONTINUED ON NEXT PAGE *****)
1 .
.% y ,
+ : !,
" Yeti _SIeNDeBD_eUD_EdEBQENGX_QEEB811NG_EB90EDUBES Page' 34.
REFE'RENCE,
[ SOP.105 pg.II ANSWER F.09- '(1.00)
A permanent log entry for' insertion'and removal shall be made.- . ( 1. 0 ) -
REFERENCE-
'SOPL101 pg 3 l
. ANSWER F.10 (1.00)
Authorization by SR0'on duty No safety requirements are violated (2 at 0.5 each = 1 '. 0 )
REFERENCE' LSOP 101 pg 3
_e I
p l
)
(***** END OF CATEGORY F *****) .
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-- * : ysp .
c:*~ 'g
> A2_h8016IIQU_QQNIBQL_6NQ_S6EEIl' Page 35 a
ANSWER G.01 (2'.00)l
.(3't 0.5 each.= 1.5) i
'b. 10% of the-above limits (0.5)
REFERENCE 10LCFR 20.101 and'104
.' ANSWER G.02 (1.50)
A radiation area is > 5 mrem /hr af high radiation area is >100-mrem /hr The maximum dose rate in a' properly ~ marked radiation area is 100 mrem /hr.
The maximum dose is calculated is as follews:
45/60 x 100 = 75 mrem (1.5).
REFERENCE' g
'10 CFR 20 ANSWER G.03 -(1.00)
<100 mrem /hr Health Physics
-(2 0.0.5 each)
. REFERENCE ,
1 ROLLA SAR pg 7-5 l
' ANSWER G.04 (1.00)
- 1. . Reactor Manager
- 2. Reactor Director (2 at 0.5 =1.0) ,
(***** CATEGORY G CONTINUED ON NEXT PAGE *****)
- .aa s
, Gt;J48Q18I1QU_CQNIBQL_88Q_18EEIr
- Page 36 i
REFERENCE
.ROLLA SOP 615 pg 2'
)
1 1
ANSWER G.05- (1.00)
-lc Those contaminated wastes reading greater than 0.1 mr/hr above background (0.5)1or glass, metal, and liquids (0.5).
REFERENCE ROLLA S0P 600 pg 1 ANSWER G.06 (1.50)
Reactor Bay :
Counting Rooms I any area posted as prohibited (3!st 0.5 = 1.5)
REFERENCE ROLLA S0P 600 pg 1 l
l ANSWER G.07- (1.00)
Time, distance, shielding (3 at 0.333 each = 1.0)
REFERENCE ROLLA SOP 600 pg 3 l l
ANSWER G.08 (1.50)
- 1. Stop the release
- 2. Warn reactor personnel
- 3. Isolate the area
- 4. Minimize your exposure
- 5. Secure .the building ventilation fans ,
L (5 at 0.333 each = 1.5) !
I
(***** CATEGORY G CONTINUE 0 ON NEXT PAGE *****)
u - - - - - - - - --
.o .e t p
=
-t
'n p . ,
Page 37
,J2t_.J6DI611DN_GQNIBQL_6HD_18EElf
!- " REFERENCE
-ROL'LA SOP 600 pg 3' ANSWER G.09 (2.00) 1.- Shall be' volunteers
- 2. Broadly familiar with the consequences of exposure
'3.' . Women capable of reproduction should not take part
- 4. Volunteers above the age of 45 (4 at 0.5 = '2.0)
- s. Ceo $ hdhkd W
REFERENCE ,gt gyLc4. m CL dth ROLLA SOP 603 pg 2 t
ANSWER G.10 (2.00)
- 1. Nitrogen gas is used as the transport medium
- 2 . Exiting gases are vented thru a high efficiency filter
~3. Rabbit tubes are curved thru the pool water.to prevent radiation streaming (any two at 1.0 each = 2.0) 3 REFERENCE' Facility SAR 4.3 l
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(***** END OF CATEGORY G *****) l
(********** END OF EXAMINATION **********) !
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