ML20128C325
| ML20128C325 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 11/19/1992 |
| From: | Caldwell J, Eresian W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128C303 | List: |
| References | |
| 50-116-OL-92-01, 50-116-OL-92-1, NUDOCS 9212040340 | |
| Download: ML20128C325 (45) | |
Text
{{#Wiki_filter:, . _ __ - " ' " ~ ENCLOSURE 1 . U. S. NUCLEAR REGULATORY'COMMISSIDH
... OPERATOR LICENSING INITIAL EXAMINATION REPORT j
- REPORT NO : 50-ll6/0L-92-01 FACILITY DOCKET NO.: 116 FACILITY LICENSE NO.: R-59 FACILITY: UTR-10 Reactor EXAMINATION DATES: November 2 4, 1992 EXAMINER: Warren Eresian, Chief Examiner SUBMITTED BY: /% ///A7/92.--
arre. Eresian C ef Exariliner - DRe > APPROVED BY: ,4100 / / N Jam 1., Calckell, Eh ef~ Oate No -Power Reactor Stction 0ppratcr Licensing Branch Division of Reactor Controls and Human Factors, NRR
SUMMARY
NRC administered written and operating examinations to three Reactor Operator applicants =and one Senior Reactor 0perator (Instant) applicant. One Reactor Operator applicant passed the examinations. One Reactor Operator applicant failed the written examination, one. Reactor Operator failed the operating test, and.the Senior Reactor Operator applicant-failed the written examination. b 5 9212040340 921123 PDR ADOCK 05000116
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REPORT DETAILS
- 1. Examiners:.
Warren Eresian, NRC Richard Miller,' Sonalysts
- 2. Results:
R0 SRO Total IPass/ Fail) (Pass / Fail) IE1111 Fail) NRC Grading: 1/2 0/1 1/3
- 3. Written Examination:
Two Reactor Operator applicants passed the written examination, and one Reactor Operator and one Senior Reactor Operator failed the written examination.
- 4. Opt .61ng Tests:
Two Reactor Operator applicants and one SR0 applicant passed the operating test, and one Reactor Operator failed the operating test.
- 5. Exit Meeting:
The following personnel attended an exit meeting on November 3,1992 to discuss the examination: Warren Eresian, OLB Examiner, NRC John Adams, Reactor Manager, Icwa State Reactor Facility
. Mr. Eresian and Mr. Adams discussed the written examinatica, and Mr.
Adams provided facility commenta. n i
. The following are comments concerning the N.R.C. RO/SRO license exam administered on 11/02/92. The exam was reviewed by Richard Danofsky, Facility Director, and John Adams, Reactor Manager. Comments:
- 1. Problem A-005 None of the answers provided in question A-005 were correct. We feel the correct answer for this $1.11. This answer can be supported with the following calculations:
SDM = (1 Keft) / Keff Keffian ==> = 1/ (1-p an mm) p an == = (1.1 $) * (0.00763 Ak / k / $)
= -0.00839 Kef11en ==> = 1/ [1 - (-0.008393)]
= 0.99168 SDMAt = (1 - 0.99168) / 0.99168
= 0.00839 Ak/k SDMs = 0.00839 / 0.00763
= 1.10 $
- 2) Problem A-011 We feel the question was improperly written for the indicated answer. We think that the question should be written as follows for the given answer (D):
"Which ONE of the following is the expected momentajy response of the reactor when the -
source is withdrawn to its storage position? " Without the word "mementary" the correct answer should be "(B) The reactor period will become slightly longer and then stabilize." This assumes the reactor is critical at the time when the source is removed from the core. I wouie also like to point out that the section of the Rx Operation-Normal procedure referenced for this problem does contain the word " momentarsj". 3 Problem A-012 - We feel that the answer is correct, but Lamarsh, Introduction to Nuclear Engineering ,1975, is not used to train reactor operators at this facility. The affects of
control rods on the factors of the six factor formula was never coverd during the candidates training.
- 4. Problem A-015 We have no disagreement with the answer to this question, but the relative absorption cross-sections of the different poisons was never specifically covered in training. Boron is the only poison we specifically talk about in our training due to its use in our control rods. Xenon and Samarium are only mentioned briefly since our operation time is very restricted at higher powers (less than or equal to 10 kw-hr in any 7 day period) due to argon-41 production. Our normal operation is at less than 100 watts which does not result in significant amounts of xenon or samarium being produced in the core. ,
- 5. Problem A-019 We feel this is a good question with only one point of confusion. The IJfR-10 reactor would never operate for 5 consecutive days due stafravailability or argon-41 production. We would like to see the phra>e, "5 consecutive days ", replaced with, "8 ,
consecutive hours", if this question is used on future exams for this facility.
- 6. Problem B-012 We feel this is a good SRO question, but we do not require our RO candidates to know the Tech. Spec, basis. We would like to request that this question be removed from-the RO candidate's exams.
- 7. Problem B-018 .
We feel that the word "large" leads one to the emergency actions associated with a major fire not a minor fire. The key indicates that the correct answer for this question _was (A). This is the correct emergency response for a minor fire. We feel that the correct answer for this particular scenario is (D). (see also page 3 of the Operations-Abnormal and Emergency Procedures)
- 8. Problem C-020 We feel the answer in the key, (D), is incorrect. On page 14 of the Facility Information, the first sentence states, "The core needs 9 dummy plates to limit the calculated excess reactivity to 0.5% Ak/k, or less." For this reason we feel that selection (C)is the correct answer.
RESOLUTION OF FACILITY COMMENTS QUESTION A005: Comment accepted.- Question will be deleted from the examination. QUESTION A0ll: Comment accepted. "B" will be accepted as the correct answer. QUESTION A012: Comment not accepted. How control rod motion affects reactivity through the six-factor formula (and hence changes K eff) is fundamental. QUESTION A015: Comment noted. No action required. QUESTION A019: Comment noted. No action required. QUESTION B012: Comment not accepted. Facility procedures allow an R0 to operate the ' reactor without the direct supervision of an SR0 (who may be off-site),_ hence R0s should know Technical Specification bases. QUESTJON B018: Comment t.ccepted. Answer key typographical error. QUESTION C020: Comment accepted. Answer key typographical error.
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IOWA STATE UNIVERSITY 11/02/92
e: 4 U. S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION FACILITY: Iowa State University REACTO.1 TYPE: UTR-10 DATE ADMINISTERED'. 11/02/92 REGION: 3 CANDIDATE: INSTRUCTIONS TO CANDIDATE: Answers are to be written on the exam page itself, or the answer sheet provided. Write answers one side ONLY. Attach any answer sheets to ne examination. Points for each question are indicated in parentheses .or cach question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours af ter the examine. tion starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 20.00 33.33 A. REACTOR THEORY,THERMO-DYNAMICS, AND FACILITY OPERATING CHARACTERISTIC 20.00 33.33 B. NORMAL AND EMERGENCY PROCEDURFS AND RADIO-LOGICAL CONTROLS 20.00 33.33 C. PLANT AND RADIATION MONITORI!!G SYSTEMS 60.00 100.00 TOTALS FINAL GRADE All work d'19 on this examination is my own. I have neither given nor ceceived ala.
Candidate's Signature
NRC RULES AND GUIDELINES FOR LICENSELEXAMINATIONS , -During~the administration of this examination'the following rules apply:
- - 1. Cheating on the examination-means an automatic deniallof your
-application and.could result.in more severe penalties.
- 2. After the examination _has been completed,-you must sign-the statement on the cover sheet indicating that the work is your'own .
and you have not-received or given assistance in completing-the examination. This must be done after you complete the examination. ,
- 3. Restroom trips are to be limited and only one candidate at-a-time may leave. You must avoid all ccatacts with anyone outside the examination roomito avoid even the appearance or possibility of cheating.
- 4. Use black ink or' dark = pencil only to facilitate legible reproductions.
- 5. -Print your~name in the blank provided.in the upper right-hand corner of the examination cover sheet.
'6. Print your name in the upper'right-hand corner of the answer sheets.-
- 7. The-point value for each question is indicated in parentheses-.after the question,
- 8. Partial' credit may be given. Therefore, ANSWER ALL PAkTS OF THE.
-QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.- NOTE:: partial credit
, ~will NOT be given on multiple choice-questions.-
- 9. If-the intent of a question is. unclear, ask' questions of the examiner only.
- 10. When= turning in your examination, assemble:the-completed examinat. ion with examination questions,. examination aids and-answer sheets. In addition,-turn in-all scrap paper.
i
- 11. When you are done.and have turned in-your examination, leave the, .
examination area as defined by the examiner.- If.you are found;in this area while the examination is still'in progress, your license may be denied or revoked. 1
A. . REACTOR THEORY, THERMO AND FAC OP CHARS Page 4
-QUESTION: 001 (1.00)
Which ONE of the following indicates when the reactor is exactly critical during a reactor startup? , a. Reactor power level is constant with the source removed and no control rod motion,
- b. Reactor power level is constant with the source installed and no control rod motion.
- c. Reactor power level increases slightly when the sturce is removed with no rod motion. -
- d. Reactor power level decreases slightly when the source is removed with no rod motion. <
QUESTION: 002 (1.00) Of the approximately 200 Mev of energy released per fission event, the largest amount appears in the form of:
- a. beta and gamma radiation
- b. prompt and delayed neutrons
- c. fiscion fragments
- d. alpha radiation QUESTION: 003 (1.00)
A reactor is critical with the following conditions: The shim-safety rod has been withdrawn 70%. The regulating rod is fully inserted. Which ONE of the following is the excess reactivity-loading of the core? (Shim-safety and regulating rod worth curves are attached).
- a. 0.14 $
- b. 0.20 $
- c. 0.34 $
d, 0.82 $ (***** CATEGORY A CONTINUED ON NEXT PAGE*****) _ _ _ _ _ _ - _ - _ i
- A. REACTOR TilEORY, TilERHO Ante FAC OP CilARS Page 5 QUESTIO'4 004 (1.00)
Which ONE of the following describos the otract on the worth of safety rod #1 if the shim-safety rod is fully inserted?
- a. Safety Rod worth decreanos due to the reduction in the thermal neutron flux surrounding the safety rod.
- b. Safety Rod worth increases because the safety rod now controls half of the core's thermal neutron flun instead of only one-quarter.
- c. Safety Rod worth will remain the same because the diffusion length of thermal noutrons is loss than the distance separating the rods,
- d. Safety Rod worth will remain the samo because the reflector will maintain an oven ois&.ribution of neutrons in the core.
QUESTION: 005 (1.00) Reactor conditions are as follows: Reactor is exactly critical. Coro is Xenon froo. Primary inlet temperature is 80 dog. F Reactivity added by rods to achievo criticality in 1.). S. Regulating rod is fully inserted. Which ONE of the following is the SHUTDOWN MARGIN if the reactor is scrammed? (Assumo ALL rods are fully inserted.)
- a. 1.32 $
- b. 1.17 $
- c. 0.99 $
- d. 0.85 $
(***** CATEGORY A CONTINUED ON NEXT PAGE*****) 4
A. REACTOR TilEORY, THERMO AND PAC OP CHARS Page 6 QUESTION: 006 (1.00) A compensating ion chamber (CIC) is used to monitor reactor power. Which ONE of the following describes the response of the meter i indication following a reactor scram, as the post-scram period cAproaches infinity,-if the CIC is UNDERCOMPENSATED7
- a. Indicated iseutron flux will be llIGilER than actual neutron flux.
- b. Indicated neutron flux will be LOWER than actual neutron flux.
- c. Indicated neutron fir" will be the SAME as actual neutron flux.
- d. Indicated neutron flux will be either llIGilER or LOWER than actual neutron flux depending on reactor power.
QUESTION: 007 (1.C Reactor conditions are as fc11ows: ,
- Reactor power is 5 watts and steady.
- Primary coolant temperature is 80 deg. F.
Regulating rod is 20% withdrawn. Which ONE of the following is the new position to which the regulating rod must be withdrawn to attain a 70 second period? (Assume the offectivo delayed neutron fraction-is 0.00763 and the effective delayed neutron decay constant is 0.1 sec'3
- a. 24%
- b. 41%
- c. 54%
- d. 66%-
1 (***** CATEGORY A CONTINUED ON NEXT.PAGE*****)
A. REACTOR THEORY, THERMO AND FAC OP CHARS Page 7 QtSSTION: 000 (1.00) The reactor is operating at power when an uncontrolled rod withdrawal occurs. Which ONE of the following describes the response of the reactivity coefficients? (Assumo primary coolant temperature control is in manual.)
- a. The doppler coefficient will add negative reactivity to the core first due to the time delay required to transfer heat to the coolant.
- b. The doppler coefficient will add negative reactivity to the core first due to the larger magnitude of the doppler coefficient,
- c. The moderator temperature coefficient will add negative reactivity to the core first due to the timo delay required for .
a significant fuel temperature change to occur.
- d. The moderator temperature coefficient will add negative .
reactivity to the core first due to the time delay required for the delayed neutrons to begin slowing down. QUESTION: 009 (1.00) Which ONE of the following describes the PRIMARY reanon that an increase in the primary coolant temperatura changes the reactivity of the-reactor core?
- a. The resonance escape probability for fission neutrons DECREASES.
- b. The resonance escapo probability for fission neutrons INCREASES.*
- c. The nonlaakage probability for fission neutrons DECREASES.
- d. The nonicakage probability for fission neutrons INCREASES.
QUESlION: 010 (1.00) The 1/M plot from four different neutron detectors is attached. Each neutron detector.is located at a different core position. Which ONE of the following curves represents the 1/M plot that would result if the neutron dettetor is located too close to the source?
- a. Curvo A
- b. Curve B
- c. Curve C
- d. Curve D
(***** CATEGORY A CONTINUED ON NEXT PAGE*****) _ _ _ . - . , _ . ._u._.___._. ._ _ __ a-_. -2, -
- ._ . .._. . . - _ = -
A. RE70 TOR THEORY, THERMO AND FAC OP CHARS Page 8 QUESTION: 011 (1.00) R3 actor conditions are as follows:
- A reactor startup is in progress.
- A stable reactor period of 80 seconds has been established.
- Reactor power is 5.5 E-4% increasing. ;
- Startup source is fully inserted.
Which ONE of the following is the expected response of the reactor when - the source is withdrawn to its storage position?
- a. Reactor period will become continuously shorter at an exponential rate approaching 0 seconds.
- b. Reactor period will become slightly longer and then stabilize.
- c. Reactor period will become shorter and stabilize at approximately +30 seconds,
- d. Reactor period will become longer and then become slightly negative.
QUESTION: 012 (1.00) A factor in the six-factor. formula which is most affected by control rad position ist
- a. resonance escape probability
- b. fast fission factor
- c. neutron reproduction factor
- d. thermal utilization factor
( * * * *
- CATEGORY A CONTINUED ON NEXT PAL ' ****)
t
, , , - . - , - ..n.- , , - - - . . . - - = , , - , - - n---
4 A. REACTOR THEORY, THERMO AND FAC OP CHARS page 9 ' QUESTInN 013 (1.00) Which ONE of the following stateme7ts describes the subcritical reactor rocponse as Keff approaches unity for a given addition of 0.01 $ of reactivity? :
- a. A LARGER change in neutron level results and a SHORTER period of time is required to reach the equilibrium neutron level.
- b. A LARGER change in neutron level results and a LONGER period of
- time is required to reach the equilibrium neutron level. I
- c. A SMALLER change in neutron invel results and a SHORTER period of time is required to reach the equilibrium neutron.
- d. A SHALLER change in neutron level results and LONGER period of time is required to reach the equilibrium neutron level.
' QUESTION: 014 (1.00)
Which ONE of the following elements will slow down fast neutrons most
.quickly, i.e. produces the greatest energy loss per collision?
- a. Oxygen-16
- b. Uranium-238
- c. Hydrogen-1
, d. Boron-10 QUESTION: 015 (1.00)
Which ONE of-the following elements has the highest thermal neutron l absorption cross-section?
- a. Uranium-235
- b. Samarium-149
- c. Boron-10
- d. Xeno" 135
(***** CATEGORY A CONTINUED ON NEXT PAGE*****) 1. {.
A. REACTOR THEORY, THERMO AND FAC OP CllARS Page 10 QUESTION: 016 (1.00) A power calibration is to be done on a pool reactor containing 6000 gallons of water. The pool P9ats up at a rate of 3 degrees F por hour. The power of the reactor ist
- a. 5.3 kW
- b. 14.7 kW r
- c. 44.0 kW
- d. 329.1 kW QUESTION: 017 (1.00)
A reactor startup is in progress. Reace9" povy ?.h , watt and the reactor operator has just established a ScF.t.j +33 cacend period. Which ONE of the following is the arount of timo that is required-to reach rated powor? (Assume prit.ary coolant temperature is constant.)
- a. 81 seconds
- b. 140 seconds
- c. 322 seconds
- d. 420 seconds QUESTION: 018 (1.00)
The equations which describe the UTR-10 startup neutron source are
- a. Pu-239 -> alpha + U-235 Be-9 + alpha -> C-12 + neutron
- b. Pu-239 -> alpha + U-235 B-10 + alpha -> N-13 + neutron
- c. Pu-239 -> beta + U-239 Be-9 + beta -> Li-8 + neutron
- d. Pu-239 -> beta + U-239 B-10 + beta -> Be-9 + neutron
(***** CATEGORY A CONTINUED ON NEXT PAGE*****)
A. REACTOR Ti!EORY, TilERMO AND FAC OP citARS Page 11 QUESTION 019 (1.00) Following a reactor scram from 5 consecutive days of power operation, tho decay heat in the reactor core is generated from , but cooling of the core with the primary coolant is not required because the
- a. photo-neutron reactions; fission product inventory is insufficient to provido a significant number of photons.
- b. photo-noutron reactions; onergy level of the gammas and botas are too low to induce a significant number of photo-neutron reactions.
- c. fission product beta and gamma decay; fission product inventory is insufficient to provido a significant heat source.
- d. fission product beta and gamma decay; onergy level of the gammas and botas are too low to generate heat during interaction with the reactor materials.
QUESTION: 020 (1.00) A reactor is operating at a steady-stato power level of 1.000 kW. Reactor power is increased to a now steady-state power level of 1.004 kW. At the higher level, X off ist
- a. 1.004 i
- b. 1.000
- c. 0.004
- d. 0.000
(*****END OF CATEGORY A*****)
D. NORMAL /EMERG PROCEDURES AND RAD CON Page 12 , QUESTION: 001 (1.00) A reactor startup is in progress. The safety rods have-boon fully withdrawn. Which ONE of the following describes the proper method to be used by the reactor operator to attain critica3ity? , i
- a. Fully withdraw the shim-safety rod, then withdraw the regulating rod to the estimated critical position and pause to chock the porlod.
- b. Fully withdraw the shim-safety rod, then withdraw the regulating rod to establish a 30 second period.
- c. Fully withdraw the regulating rod, than withdraw the shim-safety rod to the estimated critical position and pause to check the period.
- d. Fully withdrhw the regulating rod, then withdraw the shin-safety rod to establish a 30 second period.
QUESTION: 002 (1.00) Which ONE of the following states when the primary deionizer must be isolated &,_d the reason for isolating the dolonizer?
- a. When the dolonizer inlet temperature exceeds 140 dog. F; to provant separation of the mixture of H+ and OH- resins.
- b. When the deionizer inlet temperature exceeds 140 deg. F; to prevent chemical breakdown of the H+ and OH- resins.
- c. When the primary coolant outlet temperature exceeds 160 deg. F:
to prevent separation of the mixture of H+ and OH- iesins.
- d. When the primary coolant outlet temperature exceeds 160 deg. F; I to prevent chemical breakdown of the H+ and OH- resins.
( * * * *
- CATEGORY B CONTINUED ON NEXT PAGE* * * * *)
B. NORMAL /EMERG PROCEDURES AND RAD CON Page 13 QUESTION: 003 (1.00) Which ONE of the following describes the release of the Argon-41 that is produced by the irradiation of air surrounding the reactor?
- a. The discharge rate of irradiated air is uncontrolled due to the dissolved air in the primary coolant, and the Argon-41 release rate is uncontrolled due to the air pathways in the biological shield.
- b. The discharge rate of irradiated air is uncontrolled due to the dissolved air in the primary coolant and air pathways in the biological shield, but the Argon-41 release rate is controlled by the reactor's usage pattern,
- c. The discharge rate of irradiated air is controlled by the design of the air pathways in the biological shield, but the Argou-41 release rate is uncontrolled since the reactor facility has no dedicated ventilation flitration system.
- d. The discharge rate of irradiated air is controlled by the design of the air pathways in the biological shield and the limited amount of dissolved air in the primary coolant, and the Argen-41 release rate is controlled by limiting reactor full power hours of operation each year.
QUESTION: 004 (1.00) Whenever the Beam Port plugs are removed, personnel radiation exposure protection is provided by a.' a 1-1/2 inch thick lead curtain paramanently inatalled on the exterior of the graphite reflector.
- b. the thickness of tFs core reflector which is designed to provide an infinite reflector,
- c. temporarily installing beam catchers.
- d. the biological shield.
(***** CATEGORY B CONTINUED ON NEXT PAGE*****) i H
. I B. NORKAL/EMERG PROCEDURES AND RAD CON Page 14 F
QUESTION: 005 (1.00) Which ONE of the following states the log entry required by the operator for the installation of an experiment?
- a. Estimated critical control rod position, anticipated reactivity ;
changes during tho experiment, and experiment identification and location.
- b. Estimated critical control rod positiol., any supplemental i shielding that is required, and the experiment limits.
- c. Date of approval by the Reactor Use Committoo, anticipated reactivity changos during the experiment, and the experiment limits.
- d. Experiment identification and location, any displaced reactor parts, and the installation of required supplomontal shielding.
QU 36 (1.00) A x actor startup is in progress and no special operator instructiono for experiments are in offect. Which ONE of the following describes a precaution that must be adhered to when withdrawing a safety rod?
- a. Stop withdrawal by rolcasing the UP switch when the "up light" goes OFF.
- b. After the rod is fully withdrawn, if the rod's withdrawal time is NOT betwoon 9 minutes and 10 ainutes, discontinue the startup, fully insert the rod, and notify the SRO.
- c. After the rod is withdrawn and power is steady, if the multirango power channel roads above its range on the operator Paramotors Table, discontinue the startup and notify the SRO.-
- d. Stop withdrawal if any period channel decreases to loss than 300 seconds.
(***** CATEGORY B CONTINUED ON NEXT PAGE*****)
l B. HOPMAL/EMERG PROCEDURES AND RAD CON Page 15 i QUESTION: 007 (1.00) ! Which ONE of the following is the definition of a CHANNEL CHECK in cccordance with Technical Specifications?
- a. The comparison of a channels behavior to another independent channel measuring the same parameter to verify acceptable performance,
- b. The introduction of a signal into a channel indicator for verification that it is operable.
- c. The introduction of a signal into a channel's sensor, line, amplifier, and output devices for verification that it is ;
operable.
- d. The adjustment of a channel so its output corresponds accurately to known values of the paramotor neasured by the channel.
QUESTION: 008 (1.00) Following reactor power operations for i day, the reactor is placed into the following condition The reactor is subcritical. The multirange power channel indicates normal at 9 E-4 watts. The log-percent power channels indicate normal at 8 E-6 %. The primary' coolant inlet temperature is 80 deg. F. Safety rod #1 is fully withdrawn. All other rods are fully inserted. Which ONE of the following is the condition of the reactor?
- a. Hot shutdown
- b. Hot Standby
- c. Cold Shutdown
- d. Reference Core Condition
(***** CATEGORY B CONTINUED ON NEXT PAGE*****)
0 B. NORMAL /EMERG PROCEDURES AND RAD CON page 16 QUESTIOil 009 (1.00) Tn AUTOMATIC power control, the power level may be adjusted by moving the powur demand setpoint provided: a, the shim-safety rod is NOT driven to the full "up" position.
- b. the regulating rod and the shia-safety rod are NOT both driven to the full "down" position,
- c. the shim-safety rod is NOT driven to the full "down" position.
- d. the regulating rod is NOT driven to the full "down" position. . ,
GUESTION: 010 (1.00) Roadings of the instruments that are listed on the Operating Log Sheet must be recorded:
- a. after each power change of one decade during a reactor startup.
- b. hourly if the previous reading was outside of its normal range,
- c. atsleast hourly when the reactor is operating at a constant power.
- d. after each manual rod movement for a change in power greater than or equal to 5%.
QUESTION: 011 (1.00) Technical Specifications limits the maximum negative reactivity worth of any single or group of experiments that may be installed in the core tot
- a. -0.17% dk/k (-0.22 $)
- b. -0.35% dk/k (-0.46 $)
- c. -0.48% dk/k (-0.63 $)
- d. -0.50% dk/k (-0.65 $)
(***** CATEGORY B CONTINUED ON NEXT PAGE*****)
D. NORMAL /EMERG PROCEDURES AND RAD CON Page 17 QUESTION: 012 (1.00) Technical Specifications limit the maximum positive reactivity worth of any single or group of experiments to +0.14% dk/k (0.18 $). Which one of the following is the basis for this reactivity limit? (Assume the experiment fails and causes a step reactivity addition of
+0.14% dk/k to the reactor.)
- a. the resultant period would be 3 seconds, which is easily controlled by an automatic reactor scram,
- b. the resultant period would be 30 seconds, which is easily managed by control rod movement.
- c. reactor excess reactivity loading for the core would not be exceeded, allowing safety rods to shutdown the reactor.
- d. reactor excess reactivity would change to +0.02% dk/k, an amount sufficient to maintain criticality and continuo operation.
QUESTION: 013 (1.00) Reactor is operating normally at 10 KW, when the REACTOR COOLANT LOW FLOW RATE ALARM is received and primary coolant flow rate indicates 4 gpm. Which one of the following are the actions that the operator must take per the Abnorma) and Emergency Operations Proceduro?
- a. Immediately deprest the MOD pump pushbutton and depress the reactor scram bar when power has decreased to 1 watt or less. '
- b. Immediately depress the MOD pump pushbutton and then reduce reactor power to 1 KW or less,
- c. Immediately reduce power to 1 watt or less and depress tho MOD pump pushbutton,
- d. Immediately reduce power to 1 KW or loss and depress the MOD pump pushbutton.
(***** CATEGORY B CONTINUED ON NEXT PAGE*****)
.. .. .._...._._.m
B. NORMAL / EMERG PROCEDURES AND RAD CON Page 18 l QUESTION: 014 (1.00) Solect the choice that coepletes the following statement. l The reactor is operating at 5 KW when the rabbit in withdrawn from the 1 coro, the radiation level measured at 4 cm from the rabbit indicates 125 ! mr/ hour. The reactor operator shall and the rabbit facility operator shall .
- a. insert rods to Hot Standby; leave the rabbit in its present position and evacuate the area surrounding the rabbit,
- b. insert rods to Hot 6tandby; fully withdraw the rabbit from the core,
- c. manually scram the reactor; leave the rabbit in its present position and evacuate the area surrounding the rabbit.
- d. manually scram the reactor; fully insert the rabbit into the Core.
QUESTION: 015 (1.00) . The ISU Emergency Plan states that re-entry into high radiation environments will be permitted to but the dose of the individual entering must be limited to :
- a. save a life; 25 Rem
- b. prevent a disaster; 25 Rem
- c. save a life; 100 Rem
- d. prevent a disaster; 100 Rem QUESTION: 016 (1.00)
Which ONE of the following is the type of radiation detector that is used for the area radiation monitoring system?
- a. Beta and gamma sensitive Geiger-Mueller detector
- b. Gamma sensitive Geiger-Mueller detector
- c. Beta and alpha sensitive scintillation detector
- d. Gamma sensitive scintillation detector
(***** CATEGORY B CONTINUED ON NEXT PAGE*****)
.. - _ ~ ___ ,
4 B. NORMAL /EMERG PROCEDURES AND RAD CON Page 19
' QUESTION: 017 (1.00)
How would an accessible area be posted if the radiation level in the crea is 65 mR/ hour?
- a. CAUTION- RADIATION AREA
- b. CAUTION- HIGH RADIATION AREA
- c. CAUTION- RADI0 ACTIVE MATERIALS AREA
- d. CAUTION- RESTRICTED AREA 1
QUESTION: 018 (1.00) ; A large fire has broken out in the reactor console and the surrounding area. A reactor scram has occurred. Which one of the following describes the actions that the reactor operator shall perform?
- a. Notify the LED and combat the fire with a fire extinguisher.
- b. Notify EH&S and combat the fire with a fire ex'tinguisher. ,
- c. Notify the LED, call the fire department, and initiate an evacuation. -
- d. Notify EH&S, call the fire department, and initiate an evacuation.
QUESTION: 019 (1.00) In order for the measurement of-rod worth-to be performed, the reactor must initially be , and a poison must be inserted into the core prior to startup if the worth of _, rod is to be measured,
- a. slightly.suberitical, a safety
- b. exactly critical, a safety
- c. slightly subcritical, the shim-safety
- d. extetly critical, the shim-safety
(***** CATEGORY B CONTINUED ON-NEXT PAGE*****) ,
4 B.- NORMAL /EMERG PROCEDURES AND RAD CON Page 20 QUESTION: 020 (1.00) A cmall source (experiment) is being prepared for use. The experimenters are working in the same room as the experiment. The work is estimated to take 2 hours. The source radiation field measures 2.5 Rem /hr at 1 foot. Which one of the following is the MINIMUM dicta:1ce that must be maintained between the experimenters and the source to prevent the experimenters from obtaining a dose of 200 mrem?
- a. 25 feet
- b. 12.5 feet
- c. 5 feet
- d. 3.5 feet
(*****END OF CATEGORY B*****)
4 C. PLANT AND RAD MONITORING SYSTEMS page 21 QUESTION: 001 (1.00) Which ONE of the following describes the insertion of control rods when a scram signal is initiated? t,
- a. The safety and shim-safety rods are rapidly inserted into the core / core flood tanks by only gravitational forco.
- b. The safety, shim-safety, and regulating rods are rapidly inserted into the graphite reflector by spring and gravitational forces.
- c. The safety, and shim-safoty rods are rapidly insorted into the graphite reflector by spring and gravitational forces.
- d. The safety, and shim-safety rods are rapidly inserted into the graphite reflector by only gravitational force and the regulating rod is inserted by only spring forco.
Q 2STION: 002 (1.00) Which ONE of the following describes the response of the rod control circuitry if the operator depresses an illuminated control rod YELLOW pushbutton switch and then releases it?
- a. The rod clutch doenergizes, the rod falls into the coro, and-the clutch reenorgizes when the pashbutton is roloased.
- b. The rod clutch doonorgizes, the rod falls into the coro, and the
, claten remains doonorgized when the pushbutton is released.
- c. The rod drive motor doonorgizes, the rod falls into the core, and the drive motor roenergizes when the pushbutton is-roleased.
- d. The rod drive motor doonergizes, the rod falls into the core, and the drive motoi remains doenergi;:od when the pushbutton is released.
(***** CATEGORY C CONTINUED ON NEXT PAGE*****)
C. PLANT AND RAD MONITORING SYSTEMS Page 22 QUESTION: 003 (1.00) , Tho shim-safety and the regulating rods have "up" and "down" pushbutton switches for controlling rod motion. Which ONE of the following ' describes the responso of the shim-safety and regulating rods to the operation of those pushbuttons?
- a. When the shim-safety and the regulating rod "up" pushbuttons are simultaneously deprossed, both rods will be simultaneously withdrawn. i
- b. When the shin-safety and the regulating rod "up" pushbuttons are simultaneously deprossed, the shim-safety is withdrawn to full out and then the regulating rod will bo withdrawn.
- c. When the shim-safety and the regulating rod "down" pushbuttons are simultaneously depressed, both rods will be simultaneously insertad.
- d. When the shim-safety and the regulating rod "down" pushbuttons are simultaneously depressed, the shim-safety will be inserted to full in and then thu regulating rod will be inserted.
QUESTION: go4 (1.00) : Immediately following a reactor scrata, the scram signal clears and the scram annunciator light pushbutton is depressed. Which ONE of the following describes the response of the reactor protection system?
- a. The scram signal is immediately roset and the scram ciruitry is immediately roset. '
- b. The scram signal is immediately reset and the scram ciruitry is delayed from resetting for at least three seconds.
- c. The scram signal is dolayed-from resetting for at leact three seconds and the scram ciruitry immediately resets when the scram signal has reset.
- d. The scram signal is delatred from resetting for at least three seconds and the scram ciruitry must be manually reset after the scram signal in reset.
( * * * *
- CATEGORY C CONTINUED ON NEXT PAGE* * * * *)
w C. PLAllT AllD RAD H0141 TOR 111G SYSTEMS Page 23 QUESTION: 000 (1.00) Which 011E of the following describes the control rod interlock that is cetuated when reactor power by nuclear instrumentation is loop than 0.0001 watt?
- a. Provents the withdrawal or insertion of any control rod except by a reactor scram.
- b. Provents the withdrawal of any control rod but allows the insertion of any control rod.
- c. Provents the withdrawal and insortion of the shim-safety c.nd regulating rodo except by a reactor scram.
- d. Provento the withdrawal of only the ohlm-nafety and regulating roda but allows the insortion of any control rod.
QUESTIOll: 006 (1.00) Which O!1E of the following in the bases for the automatic reactor scram due to high moderator levol?
- a. To provent flooding of the graphite reflector and the uncontrolled loss of coolant.
- b. To provent erroneous nuclear instrumentation indications caused by the increased fast neutron moderation,
- c. To provent power operation of the reactor with a loss of forced circulation when the dump tank emptics.
- d. To ensure that the core tanks can be emptied within 6 seconda after a sexam signal is received.
(***** CATEGORY C CONTINUED ON NEXT PAGE*****) t 1 ____-_-__--_-______.__.___-_--_----_____-----_---_--__s
_ - - - - . . - . - . . -~ - . - . - .. - .-. - . _ . - . - . - l I
.- 1 C. PLANT AND RAD MONITORING SYSTEMS Page 24 l
QUESTION: 007 (1.00) Primary coolant instrumentation provides an interlock that prevents the I opsrator from closing the dump valve. Which ONE of the following is the initiating condition and the reason for this interlock?
- a. The primary coolant inlet temperature must be at least 80 deg. i F. to ensure the minimum shutdown margin is available and total !
core excess reactivity is within limits, i
- b. The primary coolant inlet temperaturo must be above its determined minimum value to ensure the minimum shutdown margin is available and total core excess reactivity ir within limits.
- c. The primary coolant outlet temperaturo must be below 160 deg F; to provent excessive fuel plate cladding corrosion and to provent exceeding the dump tank design temperature.
- d. The primary coolant outlet temperaturo must be below its determined maximum value; to prevent excessive fuel plate cladding corrosion and to prevent exceeding the dump tank design i
temperature. QUESTION: 008 (1.00) The primary coolant moderator IcVel is affected by the primary coolant flow rate. Which ONE of the following describes the effect of varying the primary coolanc flow rato during power operation?
- a. If coolant flow rato decreases below 25_gpm the core tank level will gradually decrease to 42 inches.
- b. If coolant flow rato decreases below 25 gpm the core tank level will continuously increase until it overflows.
- c. If coolant flow rate increases above 25 gpm the core tank level will gradually decrease to 42 inches.
- d. If coolant flow rato increases above 25_gpm the core tank level will continuously increase until it overflows.
(***** CATEGORY C CONTINUED ON NEXT PAGE*****) _ ~ _. _ _ - - . _ _ _ _ _ -_ _ _ -__ ,- -- -
f C. PLANT AND RAD MONITORING SYSTEMS Page 25 QUESTION 009 (1.00) The primary coolant temperature c> trol syhtem utilizes a flow control valve to control the flow through . ,o primary heat exchanger. Which ONE of the following is the location of this flow control valvo?
- a. The secondary (cooling) side feed line to the primary heat exchanger.
- b. The secondary (cooling) sido discharge line from the primary heat exchanger.
- c. The primary side feed line to the primary heat exchanger.
- d. The primary side dischargo line from the primary beat exchanger.
QUESTION: 010 (1.00) Which ONE of the following will result in a reactor scram?
- a. Reactor period equals 10 seconds in one channel and 7 seconds in the other channel,
- b. Reactor power equals 11.5 KW in one channel and 11 KW in anotner channel.
- c. Roactor power is 0.001 watt on the Compensated Ion Chambor and the startup source is not stored.
- d. Reactor period equals 4 seconds in one channel and reactor power' is less than 0.0001 watt in both channels.
QUESTION: 011 (1.00) Which ONE of the following describes the operating limits and design for coolant' flow through the primary system during power operation?
- a. Forced convection flow must be mainteined at bli times whenever the reactor is critical.
- b. Primary coolant flow rate must be maintained as necessary to limit the rate of fuel temperature increase tr 10 dog. F per hour.
ce The primary circulating pump can be secured.for experimental measurements if reactor power is less than 1 KW,
- d. The reactor can be operated in the natural convecticq mode as long as the prinary coolant inlet-to-outlet differe..cial temperature is limited to 10 deg. F.
(***** CATEGORY C CONTINUED ON NEXT PAGE*****)
I 1
. \
C. PLANT AND RAD MONITORING SYSTEMS page 26 QUESTION: 012 (1.00) Which ONE of the following is the PRINCIPAL purpose for maintaining the i primary dolonizer in service during reactor power operations exceeding 7 days?
- a. To maintain conductivity below 2 micromhos/cm and to remove the soluble aluminum hydroxide corrosion products from the primary coolant. i
- b. To maintain conductivity below 10 micrombos/cm and to remove the soluble aluminum hydroxide corrosion products from the primary coolant.
- c. To maintain conductivity below 2 micrombos/cm to provent the excessive loss of fuel cladding thickness due to corrosion.
- d. To maintain conductivity below 10 micromhos/cm to prevent the-excessive loss of fuel cladding thicknoss due to corrosion.
QUESTION: 013 (1.00) Which ONE of the following is the type of neutron detector used by the two nuclear instrumentation log power channels?
- a. compensated ion chamber
- b. uncompensated ion chamber
- c. fission chamber with gamma compensation
- d. fission chamber without gamma compensation QUESTION: 014 (1.00)
Which ONE of the following describes the response of the Dump Valve if power is lost to the motor operator?
- a. Fails in its current position because no power is available to operate the motor operator.
- b. Closes in approximately 6 seconds because current to the holding magnet is interrupted.
- c. Opens in approximately 6 seconds because no power is available to hold the motor operator in position,
- d. Opens in only a few milliseconds because current to the holding magnet is interrupted.
I***** CATEGORY C CONTINUED ON NEXT PAGE*****)
Y (' i C. PLANT AND RAD MONITORING SYSTEMS Page 27 ' QUESTION: 015 (1.00) ; Which ONE of the following describes the supply and the discharge path .of the secondary (cooling) water side of the primary heat exchanger ' during reactor power operation?
- a. Supplied from the city water supply and discharges to the process pit sump.
- b. Supplied from the city water supply and discharges to the dilution tank.
- c. Supplied from the domineralized water supply and discharges to the process pit sump.
- d. Supplied from the domineralized water supply and discharges to the dilution tank.
QUESTION: 016 (1.00) The Reactor Safety System senses the position of tro of the reactor closures for a reactor scram signal. Which ONE of the following lists. these two closures? ;
- a. Shield tank and rabbit closure
- b. Shield tank and operating closures
- c. Thermal column and rabbit closure i
- d. Thermal column and operating closures QUESTION: 017 (1.00)
Tol continuously monitor the conductivity of the primary coolant a conductivity cell is installed downstream of the primary . The p.fimary coolant _ conductivity meter indication provides a conductivity reading that is .
- a. deionizer; uncouponsated
- b. heat exchanger; uncompensated
- c. deionizer; temperature compensated
- d. heat exchanger; temperature-compensated
(***** CATEGORY C CONTINUED ON NEXT PAGE*****)
4 C. PLANT AND RAD MONITORING SYSTEMS page 28 QUESTION: 018 (1.00) Which ONE of the following describes the panel indicating light response to the position of the Dump valve?
- a. The light comes ON when the dump valve is FULLY CLOSED, and the '
light goes OFF when the valve reaches the FULLY OPEN position.
- b. The light goes OFF when the dump valve is FULLY CLOSED, and the light comes ON when the valve reaches the PARTIALLY OPEN position.
- c. The light comes ON when the dump valve in FULLY OPEN, and the ,
light goas OFF when the valve reaches the FULLY CLOSED position.
- d. The light goes OFF when the dump valve is FULLY OPEN, and the light comes ON when the valve reaches the PARTIALLY CLOSED position.
QUESTION: 019 (1.00) Upon a loss of Normal AC power, the radiation monitoring system is transferred to the standby power supply, and when the Normal AC , power source is restored, the radiation monitoring system is transferred back to Normal AC power.
- a. automatically; automatically
- b. automatically; manually
- c. manually; automatically 1
- d. manually; manually QUESTION: 020 (1.00)
Which ONE of the following is the roason that DUMMY FUEL PLATES must be loaded into the co' '
- a. To improve the moderation of fast neutrons in the core,
- b. To increase the fast neutron flux in the fast flux experimental facilities.
- c. To achieve the desired amount of core exceso reactivity.
- d. To provide samples for monitoring the corrosion rate of the fuel cladding.
(*****END OF CATEGORY C*****) (*****END OF-EXAMINATION *****)
a A. REACTOR THEORY, THERMO AND FAC OP CilARS ANSWER: 001 (1.00) A.
REFERENCE:
Racctor Operations Training Projecta r page 14 ANSWER: 002 (1.00) C.
REFERENCE:
Lamarch, Introduction to Nuclear Engineering, 1975, page 74
+
ANSWER: 003 (1.00) 4 C.
REFERENCE:
Reactor Operations Training Projects, pages 21, 45, 46 n v.u... - E ( p..., a - p e,,. ) i=1 where: n = number of control reds in core p.., = full out reactivity of rod - p.,p = reactivity added to core by the rod at critical rod position From Rod Worth Curves p .u.. . - (p..,. .u. p.,,, .si.) + (p..., ,.. - p.,,, ,..)
=
(0.76$ - 0.62$) + (0.20$ - 0) a 0.34$ - ANSWEP: 004 (1.00) A.
REFERENCE:
Reactor Operations Training Projects, page 46
+
.e ~ c. < - , ._ ._--c . , . _ . . , , - ,.
e
'2 ANSWER: 005 (1.00)
B. REFERENOE
.R::ctor Operations Training Projects, pagen 46 and 49, and Equation 3hect SDM = (1-X.tr) /X.tr X.c:c.,t. ... > = 1/ ( 1-0.rt., ..,.)
p.gt.,,,,. = (-1.1$) * (0.00763 dk/k/$)
= -0.00839 K.triert.: ser.) = 1/(1-(-0.00839))
= 0.99115 SDMan = 1-0. 99115 = 0. 00893 dk/k O.99115 SDMg = 0.00093/0.00763 = 1.17$
ANSWER: 006 (1.00) , A.
REFERENCE:
Rocctor Operations Training Pr>jects, pages 27, 28 ANSWER: 007 (1.00) D.
REFERENCE:
Reactor Operations Training Projects, page 21 T= (# p)/Xp); 70 = (1$-p)/0.1p; 7p = 1-o; p = 0.125$ From Reg Rod Wo th curve Reg rod worth at 20% = .04$
.04$ + 0.125$ = Final Reg Rod Worth = .165$
Final Reg Rod Position from Reg Rod Worth Curve = 66% ANSWER: 008 (1.00) A.-
REFERENCE:
Reactor Operations Training Projects, page 32.-
ANSWER: 009 (1.00) C.
REFERENCE:
ROCetor Operations Training Projects, pages 32, 33. ANSWER: 010 (1.00) B.
REFERENCE:
Ratctor Operations Training Projects, page 39. ANSWER: 011 (1.00) B.
REFERENCE:
R02ctor Operations Procedure - Normal, page 5 (Step E.1.1). ANSWER: 012 (1.00) D.
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 1975, page 272 ANSWER: 013 (1.00) B.
REFERENCE:
Rc:ctor Operations Training Projects, pages 12, 13. ANSWER: 014 (1.00) C. s
REFERENCE:
L2 marsh, Introduction to Nuclear Engineering, 1975, page 57 ANSWER: 015 (1.00) D. ,
REFERENCE:
Lamarsh, Introduction to Nuclear Engineering, 1975, App. II ANSWER: 016 (1.00) C.
REFERENCE:
Lanarsh, Introduction to Nuclear Engineering, 3975, page 310 Q = M cp6T; e Q = (6000 gallons) (8.34 pounds / gallon) (1 Btu /pouna-deg F) (3 deg F/ hour) Q = (150,120 Btu / hour) (1 kW/3413 Btu / hour) = 44.0 kW i
i' ANSWER: 017 (1.00) C. ; REFERENCEt j Racetor Operations-Training Projects, page 7. j P = P ,u " ; t t = In (P/P ) *T t = (in (10,000 watt /1 Watt))
- 35 = 322 sec. '
J ANSWER 018 (1.00) A. REFEREllCE Facility Information, page 16 ; ANSWER: 019 (1.00) , C.
REFERENCE:
Facility Information, page 56 ANSWER: 020 (1.00) , n.
REFERENCE:
Roactor Operations Training Projects, page 12
)
P k-i
A ^ NORMAL /EMERG PROCEDURES AND RAD CON ANSWE's 001 (1.00)
.C.
REfERENCF'. Optrationu Procedure, page S i ANr"ER: 00? (1.00) 8.
REFERENCE:
Facility Information, page 28 ANSWER: U03 (1.30) B.
REFERENCE:
Facility Information, page 51 ANSWER: 004 (1.00) C.
REFERENCE:
Facility Information, page 17 l -ANSWER: 005 (1.00) D. l
REFERENCE:
Operations Procedure, page 4 l ANSWER: 006 (1.00) c.-
REFERENCE:
Ope. rations Procedure, pagE b l [ ANSWER: 007 (1.00) l A. l
REFERENCE:
l Technical Srecification D9finitions, page 1-1 L ANSWER: 008 (1.00) l .B.
REFERENCE:
' Operations Procedure, pag;.s 1, 7, 9 -Tochnical Specifications Definitions, page 1-3 --4.. ,
9
-ANSWER: 009-(1.00)
D.
REFERENCE:
Op3 rations Procedure, page 7 ANSWER: 010 (1.00) C.
REFERENCE:
Operations Procedure, page 7 ANSWER: 031 (1.00) C.
REFERENCE:
Technical Specifications, 3.8.3.c, page 3-16 ANSWER: 012 (1.00) B.
REFERENCE:
Technical Specifications, 3.8 Bases, page 3-17 ANSWER: 013 (1.00) u.
REFERENCE:
Abnormal and Emergency Operatir>ns Procedure, Sect. 5, page 3. Training-Manual for Reactor Opr'ators, Iowa State UTR-10, page 61 ANSWER: 014 (1.00) D.
REFERENCE:
, Abnormal and Emergency Operations Procedure, Sect.-11, page 4 , ANSWER: 015 (1.00)
-B.
REFERENCE:
- Emergency Plan Procedure, page 18.
ANSWER: 016-(1.00) B.
REFERENCE:
Facility Information, paga 34 ANSWER: 017 (1.00) A.
REFERENCE:
Radiological Safety, page 2 h .
s 9- -ANSWER: 018 (1.00) D.
REFERENCE:
Fccility Information, page 16 ANSWER: 019 (1.00) D. REFERENCE Maintenance Procedure, Rod worth Measurement, Sect. C and C.1, page 4 ANSWER: 020 (1.00) C.
REFERENCE:
Equation sheet Dose rate limit = 200 mrem / 2 hr = 100 mrem /hr I (d ): " Iz (da)
- 2 3 2500 mrem /hr (1 ft)2 = 100 mrem /hr (da)*
d2 = 5 ft HP Instrumentation and Methods, Point Source, page 4 and Demonstration, pngos 6, 7
F C. PLANT'AND RAD MONITORING SYSTEMS ANSWER: 001 (1.00) .C.
REFERENCE:
.Fccility Information, pages 11, 59 ANSWER: 002 (1.00)
A. REFERENCE Facility Information, page 59 ANSWER: 003 (1.00) C.
REFERENCE:
Facility Information., page 60 ANSWER: 004 (1.00) B.
REFERENCE:
Facility Information, page 57 ANSWER: 005 (1.00) B.
REFERENCE:
Facility Information, page 61 ANSWER: 006 (1.00) A.
REFERENCE:
Facility Information, page 61
. Technical Specifications 3.2.4 Bases, page 3-3 ANSWER: 007 (1.00)
B.
REFERENCE:
Facility Information, page 61 Technical Specifications Table 3-2 and bases, pages 3-8 and 3-9 Technical Specifications 3.1.3 (A&B) and bases, page 3-1 Technical Specifications 2.2.3, page 2-2 ANSWER: 008 (1.00) D.
REFERENCE:
Facility Information, page 48
ANSWER: 009 (1.00) A.
REFERENCE:
. Facility Information, page 27 ,
ANSWER: 010 (1.00)- D.
REFERENCE:
Facility Information, pages 57, 61 ANSWER: 011 (1.00) C.
REFERENCE:
Facility Information, page 25 ANSWER: 012 (1.00) C.
REFERENCE:
Facility Information, page 48 ANSWER: 013 (1.00) D.
REFERENCE:
Facility Information, page 31 Reactor Operations Projects, page 27 ANSWER: 014 (1.00) ,
-D.
REFERENCE:
LFacility Information, page 26
- ANSWER:' 015 (1.00)
-B.
REFERENCE:
Facility Information, pages 27, 29, 52 ANSWER: 016..(1.00) D.
REFERENCE:
Facility Information, page 34 ANSWER: 017 (1.00) l; .D.
REFERENCE:
l 'Facilly Information, page 33 l l l r
ANSWER: 018 (1.00) B.
REFERENCE:
Fccility Information, page 34-ANSWER: 019 (1.00) A.
REFERENCE:
Fccility Information, page 35 ANSWER: 020 (1.00) .C.
REFERENCE:
Pccility-Information, page 14
i A. RX THEORY, THERMO & FAC OP CHARS Page 1 ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank. 001 a b c d, 002 a b c d W3 a b c d 004 a b c d M5 a b c d 006 a b c d M7 a b c d 008 a b c d 009 a b c d 010 a b c d 011 a b c d 012 a b c d 013 a b c d
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014 a b c' d 015 a b c d 016 a b c d 017 a b c d 018- a b- c d 019 a -b c d 020 a. b c d (*"** END OF CATEGORY A *****)
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? B. NORMAUEMERG PROCEDURES & RAD CON Page 2 ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank. 001 a b c d 002 a b c d 003 a b c d 004 a b c d 005 a b c d 006 a. b c d 007- a b c d__ 008 a b c d 009 a b c d 010 9 a b c d 011 a b c d 012 a b c d 013 a b c d 014 a b c d 015 a b c d 016 a b c d 017 a' b c d 018 a b c d 019 a b c d 020 a b c d (***** END OF CATEGORY B ***")
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C. 'PLA NT AND RAD MONITORING SYSTEMS Page 3 ANSWER SHEET MULTIPLE CHOICE (Circle or X your choice) If you change your answer, write your selection in the blank. 001 a b c d
@2 a b c d 003 a b c d 004 a b c d M5 a b c d M6 a b c d
%7 a b c d M8 a b c d 009 a b c d 010 a b c d 011 a b c d 012 a b c d 013 a b c d 014 a b c d 015 a b c d _
016 a b c d 017 a b c d 018 a b c d 019- a b c d (***" END OF CATEGORY C *****)
EQUATION SHEET SUR = 26.06/t M = 1/ (1-Kef f) = CR /CRo 3 P = Po 10 8 **) -SDM = (1-Keff)/Koff P = Pc e N') DR = 6CiE/R 8 r = (t*/p) + [ (#-9) / A.trP 3 Y " l*/ ( A-0) p= (Koff-1)/Keff h.tr = 0.1 seconds'1 DR3D3 8 = DR 2D2 8 DR = DRoe Q = M CAT 'C = 5/9 (*F - 32) 1 BTU = 778 ft-lbf 'F = 9/5'C + 32 1 Curic = 3.7x1020 dps 1 gallon water = 8.34 pounds 1 hp = 2.54x10 8 BTU /hr 1 MW = 3. 41x10' BTU /hr
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