ML20236X607

From kanterella
Jump to navigation Jump to search
NRC Operator Licensing Exam Rept 50-166/OL-98-01 for Test Administered Week of 980706.Candidate Failed Section a of Written Exam
ML20236X607
Person / Time
Site: University of Maryland
Issue date: 07/28/1998
From: Isaac P
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20236X601 List:
References
50-166-OL-98-01, 50-166-OL-98-1, NUDOCS 9808100135
Download: ML20236X607 (42)
v • d • e


Text

{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ i U. S. NUCLEAR REGULATORY COMMISSION l OPERATOR LICENSING INITIAL EXAMINATION REPORT l REPORT NO.: 50-166/OL-98-01 l FACILITY DOCKET NO.: 50-166 FACILITY LICENSE NO.: R-70 FACILITY: University of Maryland EXAMINATION DATES: July 7,1998 i EXAMINER: Patrick Isaac, Chief Examiner SUBMITTED BY: et cI 7!2 8 !96 s-Pa

Isaac, Examiner

[ ate / i

SUMMARY

During the week of July 6,1998, the NRC administered Operator Licensing Examinations to one Senior Reactor Operator Instant (SROI) candidate. The candidate failed section A of the written examination. ) l l 9808100135 980804 PDR ADOCK 05000166 V PDR l j

! REPORT DETAILS i 1. Examiners: Patrick Isaac, Chief Examiner 2. Results: RO PASS / Fall SRO PASS / FAIL TOTAL PASS / FAIL Written N/A 0/1 0/1 Operating Tests N/A 1/0 1/0 Overall N/A Ol1 0/1 1 ) )

o NRC RESOLUTIONS -WRITTEN EXAMINATION QUESTION iB.09) An experiment is being planned. The experiment requires the modification of the normal configuration of the sample handling tool. An experiment of this type has not been previously performed in the course of the reactor program. Which one of the following is the classification of this exp;;; ment? a. Routine Experiment b. Modified Experiment c. New Experiment d. Special Experiment ANSWER: d Facility Comtrg This question could have two answers dei ending on how the applicant read the question. The question states "an experiment of this type has not been performed in the course of the reactor program". If the applicant decides that "this type" only referes to modifying a sample too1, then this experiment could be considered a Modified Experiment (b). If the applicate decides that "this type" refers to changes in both the sample tool and the sample then it would be a Special Experiment (d). The definition for Modified states: Modified routine experiments are those which have not been performed previously but are similar to routine experiments in that the hazards are neither greater nor significantly different than those for the corresponding routine experiments. Therefore, if the only change is to the sample handling tool, there would most likely be no change in the hazards. NRC Resolution: Comment Accepted. The answer key will be modified to accept both "b" and "d" as correct i answers to question B.9. l ENCLOSURE 2 f ( o

1 1 QUESTION (B.13) Which one of the following requires the notification of " Unusual Event"? A reactor operator received a localized dose of 27 rems to his feet. a. b. The reactor operator initiated a manual reactor scram when he felt a tremor that was caused by an unexpected earthquake. A radical group of students is marching toward the Reactor Facility. c. d. The reactor operator notices the pool level is decreasing due to a leak in the pool outlet pipe ANSWER: d Facility Comment: This question has three correct answers: (b), (c), (d). From the E Plan Section 4.2, unusual events include: a) Threats to, or breaches of sectirity, of the reactor building, such as civil disturbances.. This is answer (c). b) Official report or observation of existing or imminent severe natural phenomena in the immediate local area that might cause structural damage to the reactor building. Answer (b), a perceivable earthquake would quaiify as a natural phenomena which could darnage the reactor building. c) Significant or continuing loss of pool water from the reactor tank... This is answer (d). NRC Resolution: Comment Accepted. Question B.13 will be deleted from the examination.

U. S. NUCLEAR REGULATORY COMMISSION NON-POWER INITIAL REACTOR LICENSE EXAMINATION FACILITY: University of Maryland REACTOR TYPE: MUTR DATE ADMINISTERED: 07/08/98 REGION: I CANDIDATE: INSTRUCTIONS TO CANDIDATE: Answers are to be written on the answer sheet provided. Attach all answer sheets to the examination. Point values are indicated in parentheses for each question. A 70% in each category is required to pass the examination. Examinations will be picked up three (3) hours after the examination starts. % OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE .IDIAL SCORE VALUE CATEGORY 20.00 JL1 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING CHARACTERISTICS 19.00 R B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS 18.00 E C. FACILITY AND RADIATION MONITORING SYSTEMS 57.00 TOTALS FINAL GRADE l All work done on this examination is my own. I have neither given nor received aid. l l l Candidate's Signature l ENCLOSURE 3

A. RX THEORY. THERMO & FAC OP CHARS ANSWER SHEET Multiple Choice (Circle or X your choice) If you change your answer, write your selection in the blank. MULTIPLE CHOICE t 001 abcd 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 a b c d 011 abcd 012. a b c d 013 a b c d 014 abcd 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 "*")

B. NORMAUEMERG PROCEDURES & RAD CON ANSWER SHEET ~ Multiple Choice (Cire!e or X your choice) If you change your answer, write your selection in the blank. 1 i MULTIPLE CHolCE i 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 i 006 a b c d l 007 1 2 3 4 008 a - b c ' 'd 009 a b c d 010 a b c d 011 abcd 012 a b c d 013 a b c d 014 a.b c d 1 015 a b c. d 016 a b c d 017 a b c d l-018 a b c d 019.a b c d I ("*** END OF CATEGORY B "*")

C. PLANT AND RAD MONITORING SYSTEMS ANSWER SHEET Multiple Choice (Circle or X your choice) l If you change your answer, wite your selection in the blank. MULTIPLE CHOICE 001 aLcd 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 a b c d 011 abcd 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 (""* END OF CAT ~ GORY C ""*) (*""""* END OF EXAMINATION "****"**)

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. 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 neither received nor 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 contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating. l 4. Use black ink or dark pencil Qaly to facilitate legible reproductions. 5. Print your name in the blank provided in the upper right-hand corner of the examinatio,1 cover sheet and each answer sheet. 6. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE. l l 7.. The point value for each question is indicated in (brackets) after the question. 8. If the intent of a question is unclear, ask questions of the examiner only. l 9. When turning in your examination, assemble the completed examination with examination questions, examination aids and answer sheets. In addition turn in all scrap paper. 10. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet. Scrap paper will be disposed of immediately following the examination. 11. To pass the examination you must achieve a grade of 70 percent or greater in each category. 12. There is a time limit of three (3) hours for completion of the examination. 13. When you have completed and turned in you examination, leave the examination area. If you are observed in this area while the examination is still in progress, your license may be denied or revoked. w.

l t i EQUATION SHEET (p-0)* d = ic bT = a bH = UA bT p**

  • _

2a(k)f Q* = 5 x 10 seconds S S g g,. -P l -K,f f A = 0.1 seconds -1 CR (1 -K,ff ) = CR I 1 ~Ke f f, ) eff 1 2 CR (-p3) = CR I ~P ) 1 2 2 -- = 0. 007 1-K,ff* A p M=

  • ff 1-K S UR = 2 6. 0 6 e tf, p-p i

1 CR F=P 10 '"* h ' 1 n 1-K,[ CR 2 1 (1-K ") P=P e' SDM = eff S(1-p) p* P= Pn T= B-P p-g ~P e f f, eff T= + eff o f f, e f f, 0.693 ( K,ff-1) T P= = 9 A K,ff DR =DR e* DR,d,* = Dst,d,# n IP ~0) IP ~0) 2 l 6CIB(n) = DR =

Peak, Peak, 2

g I = I,e " ~ 1 Curie = 3.7 x 10 dis /tec 1 kg = 2.21 lbm 1 BTU = 778 ft-lbf F = 9/5 C + 32 1 gal (H O) = 8 lbm C = 5/9 ( F - 32) 2 cp = 1.0 BTUllbml"F c = 1 callsec/gml"C p

7 9 5 9 1 9 5 2 h 0 c 9 r 5 a 7 M 5 8 5 0 2 0 8 3 8 5 77 g 5 7 5 2 / 0 7 s e 5 7 e y 6 56 v 5 2 r g 0 6 6 u d / 5 7 o C R 55 /j 5 g 2 h n j 5 0 y 5 t it r a o l y 5 u 4 g e 5 W e / 4 0 R 4 5 d f 5 3 3 o y 5 R 0 3 /, 52 7 02 y5 1 01 1 5 O 0000G0000000000000000000000000O 098765432109876543210987654321 o 3222222222211111111 11 -{o3 mEeU

l!l\\ li!j1 l11 66 2 2 0 9 0 U 9 j 5 1 7 1 5 9 9 h 5 2 c 0 9 ra 9 5 ~ M 7 y 5 8 8 0 5 3 2 p 0 8 8 5 / 77 j 5 7 5 2 / 0 7 7 5 s r 76 e j 56 v j 5 i 2 6 - r -1 0 6 n u / 5 w 7 C g 5 5 a r 5 /

5. d h

2t 1 hm 5i a 0 5.W d 5 tirh n, t 7 n 5,4 e oS / 5 c 4 r W 2 e j ~ 0 4 P 4 j 5 a 7 d j 5 3 3 o /. 5 2 / 0 3 R 3 / 5 7 / 2 52 5 2 / 0 2 2 5 f -ii5 17 1 5 ,1 2 01 1 5 7 5 5 2 0000000000000000000000000000000'0 098765432109876543210987654321 iL 322222222221111111111 mea)UE po3

/ 1 h 5 / c 9 ra 0 M 9 0 5 3 8 0 8 f / 57 0 / 7 s p 56 e v / 06 r / a 5 C / 5 2 y 0 5 h m g tr 5 i l 4 o / S W 0 / 4 5 g 7 5 3 3 d 5 o / 03 R / 5 "e, 52 0 f 2 5 1 / 01 1 L / 5 0 0 0 0 G 0 0 G 0 0 0 0 0 0 0 0 O 't 0 8 6 4 2 0 8 6 4 2 0 8 6 4 2 3 2 2 2 2 2 1 1 1 1 1 )Ea)U h v

Page 1 Section A: R Theory. The,mo & Fac. Ooeratina Characteristics Question (A.1) [1.0) A reactor scram has resulted in the instantaneous insertion of.003AK/K of negative reactivity. Which one of the following is the stable negative reactor period resulting from the scram?

a. 45 seconds
b. 56 seconds
c. 80 seconds
d. 112 seconds Question (A.2)

[1.0) The count rate is 50 cps. An experimenter inserts an experiment into the core, and the count rate decreases to 25 cps. Given the initial K, of the reactor was 0.8, what is the worth of the experiment? a. Ap = - 0.42 b. Ap = + 0.42 c. Ap = - 0.21 d. Ap = + 0.21 Question (A.3) [1.0) Given the lowest of the high power scrams is 110%, and the scram delay time is 0.5 sec. Approximately how high will reactor power get with a positive 20 second period? a. 113 % b. 116 % c. 124 % d. 225%

Section At R Theory. Thermo & Fac. Ooeratina Characteristics Page 2 Question (A.4) [1.0) Which one of the following is the dominant factor in determining differential rod worth? a. Axial and Radial Flux. b. Total Reactor Power c. Rod speed d. Delayed neutron fraction Question (A.5) [1.0) Which one of the following is the MAJOR source of energy recovered from the fission process? a. Kinetic energy of the fission neutrons b. Kinetic energy of the fission fragments c. Decay of the fission fragments d. Prompt gamma rays Question (A.6) [1.0] l Which statement illustrates a characteristic of Suberitical Multiplication? a. As Keff approaches unity (1), for the same increase in Keff, a greater increase in neutron population occurs. b. The number of neutrons gained per generation gets larger for each succeeding generation. c. The number of fission neutrons remain constant for each generation. d. The number of source neutrons decreases for each generation. L___._______._____

Section A R Theory. Thermo & Fac. Ooetatina Characteristics Page 3 Question (A.7) (1.0) Control rod positions when the MUTR is at low power critical is 80.0%, 80.0% and 60.0% for Shim I, Shim 11 and the Reg. Rod respectively. Using the provided control rod worth curves, which one of the following represents the excess reactivity? a. $8.01 b. $6.45 c. $6.03 d. $1.56 Question (A.8) [1.0] Which one of the following statements describes Count Rate characteristics after a control rod withdrawal with the reactor subcritical? (Assume the Rx remains suberitical.) Count Rate will rapidly increase (prompt jump) then gradually increase to a stable value. a. b. Count Rate wi!! rapidly increase (prompt jump) then gradually decrease to the previous value. c. Count Rate will rapidly increase (prompt jump) to a stable value, d. There will be no change in Count Rate until criticality is achieved.

-= Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 4 Question (A.9) [1.0) Most nuclear text books list the delayed neutron fraction (S) as being 0.0065Ap. Most research reactors however have an effective delayed neutron fraction (p,, ) of 0.0070 Ap. Which One of the following is the reason for this difference? a. Delayed neutrons are born at higher energies than prompt neutrons resulting in a greater worth for the neutrons. i b. Delayed neutrons are born at lower energies than prompt neutrons resulting in a greater worth for the neutrons, l c. The fuelincludes U23e which has a relatively large p for fast fission. i d. The fuelincludes U23e which via neutron absorption becomes Pu which has a larger p i 238 for fission. Question (A.10) [1.0] Assume the following rod worths: Shim 1 $2.90 Shim II $3.10 Reg. Rod. $2.40 Core excess $3.20 I Calculate the Tech. Specs Shutdown Margin. a. $11.6 b. $8.4 c. $5.2 d. $2.1 l 2

Section A: R Theorv. Thermo & Fac. Operatina Characteristics Page 5 Question (A.11) [1.0) J Which one of the following is the reason for an installed neutron source within the reactor? A startup without a neutron source... is impossible as there would be no neutrons availahe to start the fission process. a. b. would be very slow due to the long time to build up neutron population from so low a level. could result in a very short period due to the reactor going critical before neutron c. population can build up high enough to be read on nuclear instrumentation. d. can be compensated for by adjusting the compensating voltage on the source range detector. Question (A.12) [1.0] An element decays at a rate of 20% per day. Determine its half-life. a. 3 hr. b. 75 hr. c. 108 hr. d. 158 hr. Question (A.13) [1.0] The reactor is operating at 150 KW. The reactor operator withdraws the Regulating Rod adding $0.50 of reactivity and allowing power to increase. The operator then inserts the same rod to its original position, decreasing power. In comparison to the rod withdrawal, the rod insertion will result in: the same period due to equal amounts of reactivity being added. a. b. a shorter period due long lived delayed neutron precursors. c. the same period due to equal reactivity rates from the rod, d. a longer period due to long lived delayed neutron precursors.

i i l ) l Section A: R Theory. Thermo & Fac. Ooeratino Characteristics Page 6 Question (A.14) [1.0] Which statement best describes Xe-135 behavior following a Rx Scram? a. Xenon concentration decreases due to production rate from fission stops. b. Xenon concentration decreases due to production rate from l-135 decay increasing. c. Xenon concentration increases due to production rate from Pm-149 increasing. 1 l-d. Xenori concentration increases due to 1-135 decay exceeding Xe-135 decay. Question (A.15) [1.0) l As power level increases, the Prompt Negative Temp. Coefficient (PNTC) causes: 238U to absorb neutrons over a wider range, thus decreasing the number of neutrons a. available for fission with 235U. b. Doppler resonance effects to decrease. c. The hydrogen atoms in the ZrH2 to slow down more neutrons. d. More thermal neutron absorption by the moderator. Question (A.16) [1.0) l During a fuelloading, if the fuel elements are loaded to the core one by one starting near the ( source and proceeding toward the detector, which one of the following statements describes the effect of this loading sequence on the 1/M plot? a. The sequence has no effect on the 1/M plot. b. The 1/M plot will have a less angular slope, predicting criticality for a larger number of eternents. c. The 1/M plot will have a steeper slope, initially predicting criticality for a fewer number of l elements. i d. The 1/M plot will approach infinity. Predicting criticality would be difficult. l l

I Section A: R Theory. Thermo & FLc. Ooeratina Characteristics Page 7 l Question (A.17) [1.0] Why does the effect on reactivity by the Fuel Temperature Coefficient (FTC) decrease as fuel temperature increases? The water density decreases, causing the neutron resonance escape probability (p) to a. decrease. b. The neutron thermal utilization factor (f) predominates in its effect on the neutron life cycle. The neutron energy resonance absorption peake broaden less for the same degree of c. fuel temperature change. d. More neutrons leak out of the core. Question (A.18) [1.0] Select me of the following statements which correctly describes the influence of delayed neutrons, on the neutron life cycle. Delayed neutrons: decrease the period of a reactivity addition oecause they thermalize more quickly than a prompt neutrons. b take longer to thermalize because they are born at higher energies than prompt t,.utrons. cause the length of the average neutron generation time io increase and reactor period c to increase, d increase the value of D., because the are born at higher energies than prompt neutrons. Question (A.19) [1.0] Which one of the following accounts for generation of a majority of the heat One HO118 after a reactor scram following an extended period of operation? a. Fission product decay b. Delayed neutron fissions c. Stored heat energy in t eactor components d. Spontaneous fissions

Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 8 Question (A.20) D.0] A mixed beta-gamma point source measures 200 mrem /hr at one foot and 0.1 mrem /hr at 20 feet. The beta emissica has an energy of 1.0 MeV. What is the fraction of betas in the source? a. 10% b. 20% c. 80% d. 90 % I t I

Section B: Normal /Emero. Procedures & Rad Con Page 9 Question (B.1) [1.0] A small radioactive source is to be stored in the reactor building. The source is a 0.5 curie and emits a 1.33 Mev gamma. Assuming no shielding was to be usea, a Radiation Area barrier would have to be erected from the source at a distance of approximately: a. 28 feet b. 22 feet c. 17 feet d. 2 feet QUESTION (B.2) [1.0] A room contains a source which, when exposed, results in a general area dose rate of 175 millirem per hour. This source is scheduled to be exposed continuously for 35 days. Select an acceptable method for controlling radiation exposure from the source within this room. Post the area with the words " Danger-Radiation Area" a. Equip the room with a device to visually display the current dose ! ate within the room. D. Equip the room with a motion detector that will alarm in the control room. c. d. Loc' ihe room to prevent inadvertent entry into the room. Question (B.3) [1.0] Which one of the following does NOT need to be submitted to the NRC when modified? a. License b. Requalification plan c. Emergency implementation Procedures d. Emergency Plan

Section B: Normal /Emera. Procedures & Rad Con Page 10 Question (B.4) [1.0) Consider two point sources, each having the same curie strength. Source A's gammas have an energy of 1 MEV whereas Source B's gamma have an energy of 2 MEV. You obtain a reading from the same Gegar counter 10 feet from each source. Conceming the two readings, which one of the following d atements is correct?

a. The reading from Source B is four times that of Source A.
b. The reading from Source B is twice that of Source A.
c. Both readings are the same.
d. The reading from Source B is half that of Source A.

QUESTION (8.5) [1.0] Which one of the following is the definition for " Annual Limit on Intake" (All)? The concentration of a radionuclides in air which, if inhaled by an adult worker for a year, a. results in a total effective dose equivalent of 100 mill! rem. b. 10 CFR 20 derived limit, based on a Committed Effective Dose Equivalert of 5 rems whole body or 50 rems to any individual organ, fer the amount of radioactive material inhaled or ingested in a year by an adult worker. c. The effluent concentration of a radionuclides in air which, if inhaled continuously over a year, would result in a total effective dose equivalent of 50 millirem for noble gases. d. Projected dose commitment values to individuals, that warrant protective action following a release of radioactive material. QUESTION (tiG) [1.0) l l In order to ensure the health and safety of the public,10CFR50 allows the operator to deviate from Technical Specifications. What is the minimum level of authorization needed to deviate i from Tech. Specs? a. USNRC b. lieactor Supervisor c. Licensed Senior Reactor Operator, l l d. Licensed Reactor Operator. l t

Page 11 Section B: Normal /Emero. Procedures & Rad Con Question (B.7) [1.0] Match the requirements for maintaining an active operator license in column A with the correct time period from column B. Column B .Qolumn A a. 1 year 1. Renewal of license 2. Medical Examination b. 2 years 3. Requalification Written examination c. 4 years 4. Requalification Operating Test d. 6 years Question (8.8) [1.0] In accordance with Technical Specifications, which One of the following statements is TRUE7 Each fuel experiment shall be controlled such that the total inventory of lodine isotopes a. 131 thru 135 in the experiment is no greater than 1.5 curies. The reactivity worth of any individualin-core experiment shall not exceed $3.00. b. Experiments containing materials corrosive to Rx components shall not be irradiated in c. the Rx. d. Explosive experiments shall be doubly encapsulated. Question (B.9) [1.0] An experiment is being planned. The experiment requires the modification of the normal configuration of the sample handling tool. An experiment of this type has not been previously performed in the course of the reactor program. Which one of the following is the classification of this experirnent? a. Routine Experiment b. Modified Experiment c. New Experiment d. Special Experiment

SL; ,n B: Normal /Emera. Procedures & Rad Con Page 12 Question (B.10) [1.0] A point source of gamma radiation measures 50 mr/hr at a distance of 5 ft. What is the exposure rate (mr/hr) at a distance of 10 fL a. 25 mr/hr b. 12.5 mr/hr c. 6.25 mr/hr d. 17.5 mr/hr Question (B.11) [1.0) Which one of the following statements describes why radiation levels in the Reactor Bay may be elevated during performance of SP 202, Reactor Power Calibration? a. Reactor will be operated at higher than normal power. b.- The Diffuser pump is not in operation. c. The pool water temperature is elevated. d. The pool level is lower thar

  • srmal.

Question (8.12) [1.0) Which one of the following defines the basis for the Safety Limit applicable to fuel temperature? a. Excessive gas pressure may result in loss of fuel cladding integrity b. High fuel temperature combined with lac.. of adequate cooling could result in fuel melt c. Excessive hydrogen produced as a result of the zirconium-water reaction is potentially explosive d. High fuel temperature could result in clad melt l (

Section B: Normal /Emera Procedures & Rad Con Page 13 Question (B.13) [1.0) Which one of the following requires the notification of " Unusual Event"? A reactor operator received a localized dose of 27 rems to his feet. a. i The reactor operator initiated a manual reactor scram when he felt a tremor that was b. caused by an unexpected earthquake. A radical group of students is marching toward the Reactor Facility. c. The reactor operator notices the pool level is decreasing due to a leak in the pool outlet i d. pipe. Question (B.14) [1.0] A system or component is defined as " operable" by Technical Specifications if: a channel check has been performed. a. b. it is capable of performing its intended function. c. it has no outstanding testing requirements, d. a functional test has been performed. Question (B.15) [1.0) Per the Safety Evaluation Report, which one of these hypothetically conceivad accidents could result in a breach or rupture of the fuel cladding? a. Loss of coolant b. Fuel-Handling c. Rapid insertion of reactivity d. Metal-water reactions

Section B: Normal /Emera. Procedures & Rad Con Page 14 Question (B.16) [1.0] Based on the Requalification Plan for operators at the MUTR, each licensed operator must complete a minimum of Reactor startups during each requalification cycle. a. 4-b. 6 c. 8 d. 10 Question (B.17) [1.0] Which one of the following is a prerequisite prior to inspecting any control rod? Perform a shutdown margin calculation to ensure the reactor remains shutdown during a. the r'od inspection. b. Move a mininium of 4 fuel bundles from the core and place them into the fuel storage bins. c. Perform a reactor startup to evaluate core excess, ) d. Perform the " Console, Instrumentation Check portion of the Rector Start-up Checkout to ensure the scram circuit is operable. Question (B.18) [1.0) The govemor requests radiation workers to clean up an accident at Calvert Cliffs. While helping out you receive a dose of 6 Rem.10 CFR 20 requires that this dose be tracked as a Planned Special Exposure. Who is responsible for maintaining a permanent record of this dose? a. Federal Emergency Management Agency (FEMA). b. University of Maryland Reactor Facility c. Nuclear Regulatory Commission. d. State of Maryland, (an agreement state). 1 i

l Section B: Normal /FJngrg. Procedures & Rad Con Page 15 Qdastion (B.19) [2.0] Identify each of the actions listed below as either a Channel Check, Channel Test, or Channel Calibration. Verifying overlap between Nuclear Instrumentation meters. a. Replacing an RTD with a precision resistance decade box, to verify proper channel b. output for a given resistance. Performing a calorimetric (heat balance) calculation on the primary system, then c. adjusting Nuclear Instrumentation to agree. d. During shutdown you verify that the period meter reads -80 seconds. (

Section C Plant and Rad Monitorina Systems Page 16 Question (C.1)' (1.0] CO, is used in the pneumatic transfer system instead of compressed air because: a. it is more compressible. h. it does not retain moisture. c. it minimizes Ar-41 production. d. it minimizes N-16 production. Question (C.2) [1.0] With the power control servo in the Automatic Mode, which one of the choices below completes the following statement? - The control servo willincrease reactor power at a maximum period of based on a comparison between the power demand signal and reactor power detected by a a. +30 seconds; compensated ion chamber b. +15 seconds; compensated ion chamber c. +30 seconds; fission chamber d. +15 seconds; fission chamber Question (C.3) [1.0] ~ The poison section of the MUTR control rods consist of: a. Boron-Aluminum alloy (Boral) b. powdered borated graphite. c. Boron Carbide mixed with Zirconium Hydride d. compacted and sintered Boron Carbide I

l Page 17 Section C: Plant and Rad Monitorina Systerns Question (C.4) [1.0) Which one of the following will NOT prevent outward rod motion? Safety Channel 1 test trip switch is turned on. a. Shim 1 UP switch is activated while Shim 2 UP pushbutton is depressed. b. Shim 2 UP pushbutton is depressed while in Automatic Mode. c. d. The log power channel fails low. Question (C.5) [1.0] The instrumented fuel rod will measure core temperature that is: equal to the average of all fuel rod temperatures, a. b. the highest fuel rod temperature during normal conditions. significantly lower than the temperature at the core hot spot. c. d. the highest fuel rod temperature during accident conditions. Question (C.6) [1.0] When a compensated ion chamber is used for neutron detection, how is the gamma flux accounted for? Pulse he:ght discrimination is used to cancel the gamma flux. a. b. The gamma flux is proportional to neutron flux and is counted with the neutrons. The gamma flux is cance!!ed by creating ar aqual and opposite gamma current. c. d. The gamma flux passes through the detector with no interaction because of detector design.

l 4 I Section C: Plant and Rad Monitorina Systems Page 18 Question (C.7) [2.0] Match the control red drive mechanism part in column "A" with its function from column "B". Column A Column B a. Pull rod 1. Provides rod bottom indication b. Push rod 2. Provides rod position indication when the electromagnet engages the armature c. Potentiometer 3. Provides rod full withdrawn indication d. Piston 4.- Works with dashpot to slow down rod travel near the bottom of its travel 4 l J Question (C.8) [1.0) Switching the REACTOR POWER RANGE switch to the ZERO position while in the automatic mode will result in which one of the following actions? a. regulating rod insertion b. regulating rod withdrawal c. reactor scram d. shim 1 insertion Question (C.9) [1.0) Which one of the following describes the action of the rod control system to drive the magnet draw tube down after a dropped rod? ] i a. Deenergizing the rod magnet initiates the rod down motion of the draw tube. l i b. Actuation of the MAGNET DOWN limit switch initiates the rod down motion of the draw tube. l c. Actuation of toe ROD DOWN limit switch initiates the rod down motion if the rod drive is withdrawn. d. Resetting the scram signalinitiates the rod down motion of the draw tube. l l 1 L

Page 19 Section C: Plant and Rad Monitorina Systems i Question (C.10) [1.0) Overflow from the pool goes: into the holdup tank in the water handling room sump through the pool overflow piping. a. directly into the wster handling room sump through the pool overflow piping. b. directly into the water handling room sump through the floor drain gratings around the c. base of the reactor, direct!y into the sewer system through the floor drain gratings around the base of the d. reactor. Question (C.11) [1.0} Which one of the following conditions will NOT esult in a reactor scram? a. Bridge Monitor = 50 mR/hr b. Loss of compensating voltage to the Compensated lon Chamber Loss of electrical power to the 120 Volt AC instrument bus c. d. Fuel element temperature = 420*C Question (C.12) [1.0] Air contamination greater than the setpoint has been detected by Lie exhaust air radiation monitor. VAich one of the following is the ventilation system response? The supply system will automatically stop, dampers will direct air through filters purging a. the room at 150 cfm. b. The supply system will automatically stop. The exhaust system will automatically stop, dampers iJj.lirect air through filters purging c. the room at 150 cfm. d. The exhaust system will be secured automatically.

Section C: Plant and Rad Monitorina Systema Page 20 . Question (C.13) [1.0) Which one of the following completes the following statement? The fuel in the MUTR is a homogeneous mixture of uranium-hydride alloy containing % by weight of uranium enriched to <

a..

graphite, 20, 8.5 b. zirconium, 20, 8.5 c. graphite, 8.5, 20 d. zirconium, 8.5, 20 Question (C.14) [1.0) Limit switches mounted on each drive assembly provide switching for console lights. Which one of the statements is FALSE? a. The DOWN light indicates that the control rod and rod drive are at their lower limits. b. The UP light indicates that the control rod and rod drive are at their upper limits. c. When the CONT /ON pushbuttons are depressed, the ON lights are extinguished. d. The CONT side light of the CONT /ON switch goes off less than one second after a scram occurs. Question (C.15) [1.0) Which one of the folicwing is the MAXIMUM reactor pool level decrease that could occur from a failure of the primary water system piping downstream of Heat Exchanger 17 a. 12 inches - b. 24 inches c. 5 feet . d. 12 feet i

i I Page 21 E - Section C: Plant and Rad Monitorina Systems Question (C.16) [1.0] ~ 1 The thermocouple in the instrumented fuel bundle measure temperature at: a. the interior surface of the cladding b. the center of the zirconium rod c. the outer surface of the fuel d. the interior of the fuel Question (C.17) [1.0] h i the - Which one of the following pairs of elements would be expected to undergo ion exc ange n primary coc', ant demineralized 7 a. Xenon and lodine b. Boron and Carbon c. Nitrogen and Argon d. Calcium and Magnesium

f Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 22 l

  • ANSWER (A.1) j c

{

  • REFERENCE Bum, R., Introduction to Nuclear Reactor Operations, @ 1982, @ 4.6, p. 4-16.
  • ANSWER -

(A.2) a

  • REFERENCE SDM = (1 - K,)/K, = (1.0 - 0.8)/0.8 = 0.25 If counts decreased by 2, then distance to criticality was increased by 2. therefore added 0.25 negative CR, (I -K,g,)

50 (I ~ # s,) ~ CR, (1 - K,g ) 25 (1 -0.8) l -K,g =2 x '.02 = 0.4 Therefore K,, = 0.6 which implies K,g, - K,g, 0.6 - 0.8 _,. 0.2 = -0.41667 . K,gK,g, 0.8 0.6 0.48

  • ANSWER (A.3) a
  • REFERENCE P = Po " P, = 110% T = 20 sec. t = 0.5 P = 110 e"'2 = 112.78%

e

  • ANSWER (A.4) a
  • REFERENCE Standard NRC Theory Question
  • ANSWER (A.5) b
  • REFERENCE Standard NRC Reactor Theory Question
  • ANSVER (A.6)

-a

  • REFERENCE l.

' Standard NRC Reactor Theory Question I

s Section A: R Theorv. Thermo & Fac. Ooeratina Characteristics Page 23

  • AtiSWER -

(A.7) d

  • REFERENCE ENNU 320 pg. 7-7 ANSWER (A.8) a
  • REFERENCE ENNU 320 pg.9-2

' ANSWER -(A.9) b

  • REFERENCE Standard NRC Reactor Theory Question
  • ANSWER (A.10) d 1EFERENCE MUTR T.S. Definition 1.27 SDM = Total Rod Worth - Core Excess - Most Reactive Roc SDM = -($2.9 + $2.4 + $3.1)- $3.2 - $3.1 = $2.1
  • ANSWER (A.11) c
  • REFERENCE Standard NRC ReactorTheory Question
  • ANSWER (A.12) b REFERENCE d~

A = A, e A =.693/T2 In(A/A ) =.693t/T2 T2 =.693 24hr/in 0.8 = 75 hr l '

  • ANSWER (A.13) d
  • REFERENCE Bum, R., Introduction to Nuclear Reactor Operations, @ 1988, SS 4.5.

i l l

Section A: R Theory. Thermo & Fac. Ooeratina Characteristics Page 24

  • ANSWER (A.14) d
  • REFERENCE ENNU 320 pg. 9-7 Burn, R., Introduction to Nuclear Reactor Operations, e 1988, QQ 8.2 - 8.4, pp. 8 8-14.
  • ANSWER (A.15) a
  • REFERENCE MUTR FSAR Section 3.3.2
  • ANSWER (A.16) b
  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, 6 5.5, pp. 5 5-25.
  • ANSWER (A.17) c
  • REFERENCE I

MUTR FSAR Section 3.3.2 Standard NRC Reactor Theory Question

  • ANSWER (A.18) c
  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, @g 3.2.2 - 3.2.3
  • ANSWER _

(A.19) a

  • REFERENCE Burn, R., Introduction to Nuclear Reactor Operations, @ 1982, 9 4.9, pp. 4 4-26.
  • ANSWER (A.20) c REFERENCE At 20 feet, all measured radiation is from gammas.

l D,r 2 u D a 202r* 3 l D, (1)2 = 0.1 mr (20)2 j Ds = 40 mrem /hr gamma Ratio of beta to total = 1 -(40/200) = 80% l L~

) Section B: Normal /Emera. Procedures & Rad Con Page 25 i

  • ANSWER (B.1) a REFERENCE Glasstone & Sesonske,9.41, p 525.

DR= 6CE/x = 0.005 = 6(1/2)(1.33)/x, x = 798, x = 28.25 feet 2 2 2

  • ANSWER (B.2) d REFERENCE 10CFR20.1601(a)(3)
  • ANSWER (B.3) c
  • REFERENCE 10CFR50.54; ANSWER (B.4) c REFERENCE GM is not sensitive to energy.

ANSWER (B.5) b REFERENCE 10CFR20.1003 ' ANSWER (B.6) c REFERENCE 10CFR50.54(y) ANSWER (B.7) 1_d_ 21 31 4_a. REFERENCE 10CFR55 ' ANSWER (B.8) d ' REFERENCE Tech Specs 3.5 1

Section B: Normal /Emera. Procedures & Rad Con Page 26

  • ANSWER (B.9) d, b
  • REFERENCE OP 105 Section 3 0
  • ANSWER (B.10) b
  • REFERENCE DR,D,2 = DR D ' " DE4Rd = DR DR " 50 mr/hr x 5 ft2 = 12.5 mr/h.

2 2 2 2 D,2 1042

  • ANSWER (B.11) b
  • REFERENCE SP 202 pg. 2
  • ANSWER (B.12) a
  • REFERENCE Technical Specifications Section 2.1 1
  • ANSWER (B.13)

DELETED l d

  • REFERENCE E-Plan Section 4.0, Emergency Classification System
  • ANSWER (B.14) b
  • REFERENCE T.S. Definition 1.14
  • ANSWER (B.15) b
  • REFERENCE SER Section 14. 7
  • ANSWER (B.16) d

' REFERENCE MUTR Requalification Program; Operator Requal. Program Progress Checklist I

's Page 27 Section B: Normal /Emera. Procedures & Rad Con

  • ANSWER (B.17) b
  • REFERENCE SP-201, Control Rod inspection,3.0
  • ANSWER (B.18) b REFERENCE 10CFR20 1
  • ANSWER (B.19)

(2.0) a, check; b, test; c, calibration; d, check REFERENCE Tech. Specs, Definitions 1.2 l 1-

Section B: Normal /Emerg. Procedures & R9d Con Page 28

  • ANSWER (C.1) c
  • REFERENCE ENNU 320, Section 5.4
  • ANSWER (C.2) b
  • REFERENCE FSAR Section 6.3.2: OP-104 Step 6.6
  • ANSWER (C.3) b
  • REFERENCE FSAR Section 3.2.1
  • ANSWER (C.4) c
  • REFERENCE FSAR Sect. 6.1.3
  • ANSWER (C.5) c
  • REFERENCE ENNU 320, Section 6.1.3.2.
  • ANSWER (C.6) c
  • REFERENCE ENNU 320 Vol. 2 Section 3.3.5.3
  • ANSWER (C.7) a 1

b 3 c 2 d 4

  • REFERENCE FSAR Section 3.2.3
  • ANSWER (C.8) b
  • REFERENCE OP 104, Page 5
  • ANSWER (C.9) c
  • REFERENCE FSAR, Page 6-8

Smetion B: Norma'JEmera. Procedures & Rad Con Page 29

  • ANSWER (C.10) a-
  • REFERENCE-1

. ENNU 320, Sect. 8.1

  • ANSWER (C.11) b
  • REFERENCE FSAR Table 6.1

' ANSWER. (C.12) d

  • REFERENCE FSAR SEction 2.2 OP-101 pg. 7
  • ANSWER (C.13) d
  • REFERENCE ENNU 320 Vol. 2 Section 3.1,1
  • ANSWER (C.14).

b -* REFERENCE ENNU 320 Vol. 2 Section 6.2.1

  • ANSWER (C.15) b
  • REFERENCE FSAR SEction 4.1

'* ANSWER (C.16) d.

REFERENCE:

FSAR Section 3.1.2 '* ANSWER (C.17) d

  • REFERENCE ENNU 320 MANUAL VOL. 2, Page 4-2 s

.}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20236X607&oldid=3928825"