ML20035F621

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Exam Rept 50-223/OL-93-01 on 930329-31.Exam Results:Both Candidates Passed Exams
ML20035F621
Person / Time
Site: University of Lowell
Issue date: 04/09/1993
From: Caldwell J, Doyle P
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20035F620 List:
References
50-223-OL-93-01, 50-223-OL-93-1, NUDOCS 9304220098
Download: ML20035F621 (38)
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{{#Wiki_filter:I O ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-223/0L-93-01 FACILITY DOCKET NO.: 50-223 FACILITY LICENSE NO.: R-125 FACILITY: University of Massachusetts - Lowell EXAMINATION DATES: March 29 - 31, 1993 EXAMINER: Paul Doyle, C ief E m ner SUS:tITTED BY: Y'7-93 4'ul Doyle, igfT[dininer Date l APPROVED BY: hm9 I Ja.e~s L. CaTdwell, Chief Date N n-Power Reactor Section C erator Licensing Branch Civision of Reactor Controls and Human Factors Office of Nuclear Reactor. Regulation

SUMMARY

During the week of March 29, 1993, the NRC administered operator licensing examinations to two reactor operator candidates. Both candidates passed the examinations, t i r Z 6 f b 9304220098 930410 PDR ADOCK 05000223 V PDR

I REPORT DETAILS 1. Examiners: Paul Doyle, Chief Examiner 2. Results: R0 SRO Total (Pass / Fail) (Pass / Fail) IPass/ Fail) NRC Grading: 2/0 0/0 2/0 3. Written Examination: The NRC administered written examinations to two Reactor Operator j candidates. Both candidates passed this portion of the examinations. l 4. Operating Tests: l The NRC administered operating tests to two Reactor Operator candidates. i Both candidates passed this portion of the examinations. l 5. Exit Meeting: [ l Paul Doyle, Chief Examiner, NRC i Marvin Mendonca, Observer, NRC i Dennis Martineau, Acting Reactor Supervisor, U. Mass. -- Lowell Mary Montesalvo, Senior Reactor Operator, U. Mass. -- Lowell Dr. Gunter Kegel, Facility Director, U. Mass. -- Lowell I During the exit meeting the chief examiner stated that he found no t generic weaknesses on the part of the candidates. The chief examiner t also mentioned the fact that the candidates seemed well prepared and thanked the facility for their support in administering the l examinations. j ~ l 6 l f I 1

= _. -.. t I ENCLOSURE 2 Facility Comments on Written Examination l Section B Question 5 t Which ONE of the following materials is NEVER allowed in the reactor containment building? j a. Alcohol i b. Liquid Nitrogen j i c. Mercury d. Cadmium Facility Comment: The UML Standing Order #1 states that a mercury thermometer used during temperature calibrations is ar. acception [ exception] and mercury (in element form) is prohibited, therefore per our Standing Order #1 there is no correct answer. I NRC Resolution Comment noted. The NRC will correct this question. Because the most correct answer was c, no grading change is warranted. Section B Question 6 i The allowable limit for pool water conductivity averaged over a month is: i ~ a. 0.5 pmho/cm I b. 5.0 pmho/cm c. 50 pmho/cm ~ d. 500 pmho/cm 1 ~ Facility Comment: Answer b 5.0 pmho/cm as per Technical Specification 3.8 Coolant System. NRC Resolution: Agree with comment. The answer key for this question has been modified to recognize choice 'b' as being correct. t t

i ! Facility Comments on Written Examination j Section C l Question 11 Match the radiation detectors listed in Column "A" with its corresponding detector type from column *B". (2 points, 0.5 each) l a. Continuous Air Monitors 1. BF detector 3 b. Stack Effluent Monitor (Gaseous) 2. Geiger-Muller detector l c. Stack Effluent Monitor (Particulate) 3. Scintillator detector f ~ d. Bridge Monitor 4. Ion Chamber t Facility Comment: i The answers to parts b and c should be 2 and 3 respectively vice the NRC's 3 and 2. l HRC Resolution: Agree with comment. The answer key has been change to reflect the answers for i this question as: a. 2, b. 2, c. 3, d. 4. s I i l i l 1 i [ f 1 h t l I 'r

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r t i i l l U. S.. NUCLEAR REGULATORY COMMISSION WON-POWER REACTOR LICENSE EXAMINATION f I FACILITY: Univ. of Mass. -- Lowell l t REACTOR TYPE: GE MTR DATE ADMINISTERED: 1993/03/29 i f REGION: CANDIDATE: i INSTRUCTIONS TO CANDIDATE: t Answers are to be written on the answer sheet provided. Attach the answer 3 sheets to the examination. Points for each question are indicated in paren-theses for each question. A 70% in each section 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 TOTAL SCORE VALUE CATEGORY 20.00 33.3 A. REACTOR THEORY, THERMODYNAMICS AND FACILITY OPERATING i CHARACTERISTICS 20.00 33.3 B. NORMAL AND EMERGENCY OPERATING PROCEDURES AND RADIOLOGICAL CONTROLS i 20.00 33.3 C. PLANT AND RADIATION MONITORING SYSTEMS 60.00-TOTALS FINAL GRADE I All work done on this examination is my own. I have neither given nor i received aid. t Candidate's Signature [ i i 1

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. r

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 i

received or given assistance in completing the examination. This must be i 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.

4. Use black ink or dark pencil only to facilitate legible reproductions.

l S. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.

6. Fill in the date on the cover sheet of the examination (if necessary).
7. Print your name in the upper right-hand corner of the first_page of each section of your answer sheets.

l l

8. The point value for each question is indicated in parentheses after the question.

l

9. Partial credit will NOT be given.

l I

10. If the intent of a question is unclear, ask questions of the examiner only.
11. k' hen you are done and have turned in your examination, leave the examin-ation 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 j revoked. -l I I + t

EQUATION SHEET 2 0 = m c, AT P. k N" = f - 39 y sec k = 96 8 - 0.007 a = 1.26 x 10 f Q = m Ah SCR - S/(1-Keff) Q = UA AT CR, (1-Keff), = CRz (1-Keff)z l 26.06 (A,,,p) (1-Keff)o (B - p) (1-Keff), i SUR = 26.06/r M = 1/(1-Keff) = CR /CR 3 o P=P 10 * " SDM = (1-Keff)/Keff o W P=P e"#" Pwr - W, m o B(1-0) t P= P, f, = 1 x 10'5 seconds B-p (l*/p) + [(iT-p)/A,,,p] r - f*/(p-fP t= i p = (Keff-1)/Keff A,,, = 0.1 seconds ~' p - AKeff/Keff 0.693 B = 0.0070 A 2 DR D - DR 0 DR = DR,e'" 33 z2 6CiE(n) DR = DR = R/hr, Ci a Curies, E = Mev, R = feet 1 Curie - 3.7x10'" dps I kg = 2.21 lbm 3 6 I hp = 2.54x10 BTU /hr 1 Mw - 3.41x10 BTU /hr l 1 BTU = 778 ft-lbf

  • F = 9/5*C + 32 i

1 gal H O = 8 lbm

  • C = 5/9 (*F - 32) 2 l

l

Section A Rc Theory. Thermo & Fac. Operatino Characteristics Page 4 f i

  • QUESTION (A.1)

You are performing a reactor startup and have just pulled out the source. If you were to continue the startup by pulling out the regulating rod adding 50.30 reactivity to the reactor, what would be the resulting reactor period? .l a. - 60 seconds l b. - 30 seconds c. - 20 seconds d. - 10 seconds i i

  • QUESTION (A.2)

[1.0) Thereactorhasbeenrunforashorttimeat1Mwattbeforebeingshutdown i (Equilibrium Xenon conditions). An experiment worth - 2.0 x 10~ AK/K is REMOVED from the reactor. When the reactor is restarted two days later pool l temperature is 5'C COOLER. What will be the difference in the rod height when the reactor is returned tc 1 Mwatt (equilibrium Xe conditions)? (a, -3 x 10'5 AK/K/*F) a. 0.175%6K/K less rods must be withdrawn b. 0.224%6K/K less rods must be withdrawn c. 0.056%6K/K more rods must be withdrawn d. 0.119%oK/K more rods must be withdrawn

  • QUESTION (A.3)

[1.0) Which ONE of the following statements desc"ibes why installed neutron sources are used in reactor cores? a. To increase the count rate by an amount' equal to the source contribution. b. To increase the count rate by 1/M (M - Subcritical Multiplication Factor). c. To provide neutrons to initiate the chain reaction. d. To provide a neutron level high enough to be monitored by instrumentation.

Section A FL Theory. Thermo & Fac Operatino Characteristics Page 5

  • QUESTION (A.4)

[1.0] What is the K,,, for a reactor shutdown by 0.0455 AK/K? a. 0.957 b. 0.855 [ c. 0.786 d. 0.0455

  • QUESTION (A.5)

[1.0] At the beginning of a reactor startup, K,,, is 0.90 with a count rate of 30 CPS. Power is increased to a new, steady value of 60 CPS. The new K,,, is: a. 0.91 b. 0.925 c. 0.95 d. 0.975

  • QUESTION (A.6)

[1.0] The reactor is operating at 900 Kwatts (90%) and the scram setpoint is set at 125%. What will be the resulting peak power if an experiment inserted into the reactor causes a 100 millisecond period and the scram delay is 0.1 second? a. 1.4 Mwatts b. 2.8 Mwatts c. 3.4 Mwatts d. 5.0 Hwatts i L

Section A R; Theory. Thermo & Fac. Operatino Characteristics Page 6

  • QUESTION (A.7)

[1.0] Beta and Beta-effective both describe the total fraction of delayed neutrons. The difference between the two is: a. Beta-effective is smaller than Beta since delayed neutrons are born at a lower energy level than prompt neutrons. i b. Beta-effective is larger than Beta since delayed neutrons-are born at a lower energy level than prompt neutrons. c -, Beta-effective is smaller than Beta since delayed neutrons are born at a higher energy level than prompt neutrons. d. Beta-effective is larger than Beta since delayed neutrons are iirn at a higher energy level than prompt neutrons. i i

  • QUESTION (A.8)

[1.0] Which of the following characteristics of a material would result in the most efficient thermalization of neutrons? a. LQW atomic mass number and HIGH scattering cross section. b. HIGH atomic mass number and LOW scattering cross section. l c. LOW neutron absorption and LOW scattering cross section. d. LOW neutron absorption and HIGH atomic mass number.

  • QUESTION (A.9)

[1.0] WhighONEofthefollowingisthetimeperiodinwhichthemaximumamountof Xe" will be present in the core? a. 7 to 11 hours after a startup to 100% power. b. 3 to 6 hours after a power increase from 50% to 100%. c. 3 to 6 hours after a power decrease from 100% to 50%. d. 7 to 11 hours after a scram from 100%. i i t i

Section A R Theory. Thermo & Fac. Operatino Characteristics Page 7

  • QUESTION (A.10)

[1.0) Each fission event releases approximately 200 Mev of energy. Which one of the following contributors to this energy is the LARGEST? a. Beta and gamma radiation (B-y) b. Prompt and delayed neutrons h c. Kinetic energy of the fission fragments d. Alpha radiation (a) i

  • QUESTION (A.11)

[1.0] As a result of beta (B) decay: a. The atomic mass number decreases by 1, and the number of protons remains constant. l b. The atomic mass number remains constant, and the number of protons increases by 1. c. The atomic mass number remains constant, and the number of protons remains constant. d. The atomic mass number decreases by 1, and the number of protons decreases by 1.

  • QUESTION (A.12)

[1.0] Integral Rod Worth is defined as the reactivity: a. change per unit of rod motion. b. due to control rod position. c. required f" shutdown with the most reactive rod withdrawn. d. available for shutdown _ after control rod withdrawal. ~ I i i i

Y Section A R Theory. Thermo & Fac. Operatine Characteristics Page 8

  • QUESTION (A.13)~

[1.0] The fuel temperature coefficient of reactivity is - 1 x 10AK/K/*F. When a control rod with an average rod worth of 0.1 %8K/K/ inch is withdrawn to 10 inches, reactor power increases and becomes stable at a higher level. Assuming the moderator temperature is constant, the fuel temperature has: a. increased by about 100*F b. decreased by about 100*F c. increased by about 10*F d. decreased by about 10*F

  • QUESTION (A.14)

[1.0] j Which factor in the six-factor formula is represented by the ratio: number of neutrons that reach thermal eneroy number of neutrons that start to slow down a. fast non-leakage probability (L,) b. resonance escape probability (p) c. reproduction factor (t;) d. thermal utilization factor (f) e

  • QUESTION (A.15)

[1.0) During a fuel loading, as the reactor approaches criticality, the value of 1/M: l a. decreases toward zero b. decreases toward one ^ c. increases toward infinity d. increases toward one i

Section A R Theory. Thermo & Fac. Doeratino Characteristics Page 9

  • QUESTION (A.16)

[1.0] Which conoition below describes a critical reactor? a. K - 1; M/K - I b. K - 1; M/K - O c. K - 0; M/K - 1 d. K - 0; M/K - 0

  • QUESTION (A.17)

[1.0] 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 (A.18)

[1.0] In a reactop at full power, the thermal neutron flux (p) is 2.5x10'2 neutrons /cm /sec. and the macroscopic fission cross-section I, is 0.1 cm. The fission reaction rate is: 2.5x10" fissions /sec. a. b. 2.5x10'3 fissions /sec. 2.5x10" fissions /cm /sec. 3 c. 3 d. 2.5x10'3 fissions /cm /sec. '.t b

Section A R Theory. Thermo & Fac. Operatino Chtracteristics Page 10

  • QUESTION (A.19)

.[1.0) K,,,,,,,,, di ffers from K,ini,, in that K,,,,,,iy, takes into account: in a. leakage from the core b. neutrons from fast fission c. the effect of poisons d. delayed neutrons. r

  • QUESTION (A.20)

[1.0) Which ONE of the following parameter changes will require a control rod INSERTION to maintain reactor power constant following the change? a. Samarium buildup b. Primary Coolant Temperature Decreases r c. Xenon buildup d. U concentration decreases (Fuel Burnup) 235 t i F i ) b 4 (*** End of Section A ***) 4

Section B Normal /Emero Procedures & Rad Con Page 31

  • QUESTION (B.1)

[1.0] The setpoints for the gamma cave radiation monitor are currently specified by Standing Order # 10. Which of the following choices is the correct setting for the high/ low set points for the gamma cave radiation monitor? a. 0.5 mR/hr - 0.3 mR/hr b. 1.0 mR/hr - 0.2 mR/hr c. 5.0 mR/hr - 2.0 Mr/hr d. 20.0 mR/hr - 2.0 mR/hr

  • QUESTION (B.2)

[1.0] Gallontium has a biological half life of 15 days and a radiological half life of 2 days. What is the effective half life? a. 0.567 days j b. 1.765 days i c. 7.50 days d. 17.0 days Section B Normal /Emero Procedures & Rad Con Page 11

  • QUESTION (B.3)

[1.0] You are the react'or operator operating the reactor at 40% (900Kwatts). The auxiliary operator is preparing to temporarily deenergize the ventilation system for maintenance. Negative pressure will be maintained by temporary fans. What actions should you take? a. Shutdown the reactor. Technical Specifications do not allow operations of the reactor without a fully operating ventilation system. P b. Continue operation. The startup procedure (RO-6) states that reactor operations may continue based on the discretion of the Reactor Operator. c. Get permission from the Senior Reactor Operator. The startup procedure (RO-6) ~ states that reactor operations may continue based on the i discretion of the Senior Reactor Operator. d. Get permission from the Chief Reactor Operator. The startup procedure (RO-6) states that reactor operations may continue based on the discretion of the Chief Reactor Operator. t

Section B Normal /Emero Procedures & Rad Con Page 12

  • QUESTION (B.4)

[2.0]. MATCH the radiological term listed in column A with its corresponding limit listed in column B. (2 points / 0.5 per match) a. radiation area 1. < 0.5 mrem /hr b. area in an. unrestricted area 2. > 5.0 mrem /hr adjacent to a permanent storage area c. high radiation area 3. > 100 mrem /hr [ d. unrestricted area 4. s 2 mrem /hr i

  • QUESTION (B.5)

[1.0] l Which ONE of the following materials is NEVER allowed in the reactor l containment building? a. Alcohol b. Liquid Nitrogen c. Mercury d. Cadmium

  • QUESTION (B.6)

[1.0] The allowable limit for pool water conductivity averaged over a month is: I a. 0.5 pmho/cm b. 5.0 pmho/cm c. 50 pmho/cm d. 500 pmho/cm l t { J e., .t 1 c

Section B Normal /Emero Procedures & Rad Con Page 13 l

  • QUESTION (B.7)

[1.0] What is the 10CFR20 quarterly exposure limit for the skin of whole body?

a. 1.25 Rem
b. 3.00 Rem
c. 7.50 Rem
d. 18.75 Rem
  • QUESTION (B.8)

[1.0] Which ONE of the following scrams IS NOT required by Technical Specifications, while in NATURAL CONVECTION MODE 7 l a. Percent Power Level b. Seismic Disturbance c. Coolant Gate Open d. Detector High Voltage Failure I

  • QUESTION (B.9)

[1.0] Which ONE of the following describes the relationship between a Safety Limit (SL) and a Limiting Safety System Setting (LSSS)? a. The SL is a maximum operationally limiting value that prevents the LSSS from being reached during normal runs. b. The SL is a parameter that ensures the integrity of the fuel cladding. The LSSS initiates protective action to preclude reaching the SL. c. The LSSS is a parameter that ensures the integrity of the fuel cladding. The SL initiates protective action to preclude reaching the LSSS. d. The SL is a maximum setpoint for instrumentation response. The LSSS is the minimum number of channels required to be operable. i r

Section B Normal /Emera Procedures & Rad Con Page 14

  • QUESTION (B.10)

[1.0) In accordance with Technical Specifications, which pH of the following samples must be doubly encapsulated prior to irradiation? a. Explosive b. Corrosive c. Gaseous d. Radioactive f

  • QUESTION (B.ll)

[1.0) i In order to maintain an active R0 or SRO license, what is the minimum number e of hours per quarter must you perform the functions of an R0 or SRO? a. 2 i b. 4 c. 8

d. 12
  • QUESTION (B.12)

[1.0) A person is working 4 feet from a gamma point source emitting 8 R/hr at one foot. Which of the following is the length of time that the person can work' without exceeding the whole body QUARTERLY 10 CFR 20 dose limit. Assume no i previous exposure history is available.

a. 37 minutes 4
b. 1.25 hours.

i

c. 2.5 hours
d. 6.0 hours i

t I

Section B Normal /Emera Procedures & Rad Con Page.15

  • QUESTION (B.13)

[1.0) ~ A cobalt-60 source has been dropped in the reactor laboratory. Thirty (30) feet from the source a beta-gamma detector reads 100 mR/hr. What is the curie content of the source? (Assume a 1.2 and a 1.3 Mev gamma emission.) a. 90 curies b. 30 curies c. 6 curies d. 2.5 curies

  • QUESTION (B.14)

[1.0) An individual receives 100 mrem of Beta, 25 mrem of Gamma, and 5 mrem of neutrons. What is his total dose? a. 275 mrem b. 205 mrem c. 175 mrem d. 130 mrem

  • QUESTION (B.15)

[1.0) In accordance with Technical Specifications, under normal circumstances a senior reactor operator may be 'on call.' To meet the requirements this person must be: a. within the reactor containment b. within the Pinanski building -c. within the confines of the north campus d. within 15 minutes of the reactor facility ?

Section B Normal /Emero Procedures & Rad Con Page 16 i

  • QUESTION (B.16)

[1.0] Which ONE of the following experiments would require special authorization r from the USNRC? i a. Explosive b. Corrosive c. Gaseous d. Radioactive i

  • QUESTION (B.17)

[1.0] Which of the following is the LOWEST level of U. Mass - Lowell management who may authorize restart of the reactor following an automatic scram? a. Reactor Operator b. Senior Reactor Operator c. Chief Reactor Operator t d. Reactor Supervisor

  • QUESTION (B.18)

[1.0) The facility director assigns you to decrease the Dose Rate being emitted by a point source by a factor of 10. The Dose Rate is due to 1.5 Mev gamma. What thickness of lead will be required to decrease the dose rate by a factor of 10? ' GIVEN: Thp/ gram and the density of lead is 11.4 gram /cm mass attenuation coefficient for lead 01.5 ev - 0.051 cm a. 0.2 cm b. 2 cm c. 4 cm d. 8 cm j I l i I t

i Section B Normal /Emero Procedures & Rad con Page 17

  • QUESTION (B.19)

[1.0] Which ONE of the following persons is responsible for making the decision to downgrade an emergency classification? a. The Emergency Director. b. Radiation Safety Officer c. Reactor Supervisor d. Facility Director i i i i t h 1 i l i -l ) (*** End of Section B ***)

I Section C Plant and Rad Monitorina Systems Page 18

  • QUESTION (C.1)

[1.0] ? The auxiliary operator reports thick black smoke coming frem the primary pump. Where would you tell the auxiliary operator to go to deenergize power to the i pump? a. Motor Control Center 1 b. Motor Control Center 2 6 c. Emergency Distr. Swbd. (480V end) d. Hot Cell Power Panel i t What design feature is used to minimize the effects of radiation due to N{'1.0]

  • QUESTION (C.2) decay in the plant?

a. A tortuous path through the demineralizer slows down the flow of coolant allowing the N time to decay. b. A large decrease in tpe flow velocity of the coolant in the hold-up tank, allowing the N' time to decay. c. A large decrease in the flow velocity of the coolant due to its distribution through many U-tubes in the heat exchanger, allowing the N time to decay. d. A long pipe from the pool into the pump room along with a relatively slow flow rate, allowing the N time to decay prior to reaching the l room.

  • QUESTION (C.3)

[2.0] i You are in the process of performing the daily check on the radiation monitors per RF-5. Match the monitor (in column A) with the source (in column B) used i to test it. i Column A CokumnB a. Stack Particulate 1. Cobalt" [ 25z b. Cam 1/2 2. Californium j c. Fission Products 3. Argon" ( d. Gamma Cave 4. Nitrogen l t t 'I

I I Section C Plant and Rad Monitorino Systems Page 19

  • QUESTION (C.4)

[1.0) Which of the following is the gas that the stack gas monitor is calibrated to measure? i a. Ar" b. C'* c. Fe'3 d. K"

  • QUESTION (C.5)

[2.0] l Match the plant condition listed in column A with the correct response listed i in column B. COLUMN A COLUMN B a. Log-N period s 30 sec. 1. Prevent withdrawal of Control Blades ONLY. b. Picoammeter 1 reading > 110% 2. Prevent withdrawal of Regulating Rod ONLY. c. Picoammeter 2 reading < 5% 3. Prevent withdrawal of both Control Blades and regulating rod. t d. Startup Source in motion 4. No response l

  • QUESTION (C.6)

[1.0] l Which ONE of the following SCRAMS is a electronic SCRAM 7 l .a., Coolant Gates open b. Seismic l c. High Voltage Failure i d. Reactor Period < 3 sec 2 I l I

}. Section C Plant and Rad Monitorina Systems Page 20

  • QUESTION (C.7)

[1.0] Which ONE of the following safety system protective functions is NOT bypassed when the Power Level Selector Switch is in the 0.1 Mwatt position? a. SCRAM - High temperature Primary Coolant leaving core b. SCRAM - Primary coolant low flow rate c. SCRAM - Bridge Low Power Position d. SCRAM - Low Pool Water Level

  • QUESTION (C.8)

[1.0] The " TEST" position of the Master Switch allows: a) insertion of scram signals without deenergizing the scram magnets. b) control power and lamp indication operability testing. c) control blade drive motion without energizing the scram magnets, d) control blade drive motion with energized scram magnets.

  • QUESTION (C.9)

[1.0) How is the signal for Control Blade position on the console generated? a. As the lead screw moves out, the impedance of a pick-up coil changes generating a changing voltage, b. A mechanical position indicator connected via a chain to the drive motor generates the signal. c. A series of limit switches open and close as the lead screw moves pass. d. A circuit with input from switch 753 generates a signal proportional to rod travel for the time the switch is in either the RAISE or LOWER position.

Section C Plant and Rad Monitorino Systems Page 21

  • QUESTION (C.10)

[2.0] For a power failure, describe the status of each of the following items in ~ column A with the correct choice from column B. (2 points, 0.33 each) Column A Column B a. 8 Instrumentation 1. Power Available I b. Stack Air Rad. Monitor 2. No Power Available c. Control Rods d. Ventilation Control l e. Reactor Air Compressors f. Gamma Cave Rad. Monitor

  • QUESTION (C.11)

[2.0] Match the radiation detectors listed in Column "A" with its corresponding detector type from column B". (2 points, 0.5 each) a. Continuous Air Monitors 1. BF detector 3 b. Stack Effluent Monitor (Gaseous) 2. Geiger-Mueller detector c. Stack Effluent Monitor (Particulate) 3. Scintillation detector d. Bridge Monitor 4. Ion Chamber

  • QUESTION (C.12)

[1.0] A joint downstream of the primary pump fails. What would stop the pool from draining? a. Closure of an automatic valve sensitive to pool level. ~ b. Siphon breaks located in the pool suction piping, c. Draining of the Hold-Up tank causing the Primary pump to lose Net Positive Suction Head. d. Loss of level below the bottom of the suction piping. L l l l l. 1

Section C Plant and Rad Monitorino Systems Page 22

  • QUESTION (C.13)

[1.0) Which one of the following isotopes is analyzed for when determining the integrity of the heat exchanger? a. Ar" 88 b. Kr c. N 24 d. Na

  • QUESTION (C.14)

[1.0] Which one of the following combinations of detector alarms cause you to activate the a " Limited Radiation Emergency Alarm"? a. Stack Monitor (A) and Bridge Monitor (K). b. Reactor Constant Air Monitor (C) and Fission Product Monitor (E). c. Facilities Exhaust Monitor (F) and Pump Room Monitor (P). d. Bridge Monitor (K) and Control Room Monitor (R).

  • QUESTION (C.15)

[1.0] If the reactor is operating at 1 Mwatt when the SECONDARY pump trips, which ONE of the following automatic scrams will shutdown the reactor? a. Low Coolant Flow b. Short Period c. High Flux d. High Primary Coolant Exit Temperature

  • QUESTION (C.16)

'[1.0] Which ONE of the followinc describes the purpose of the Slide Gate Valves in the Pneumatic Tube System? a. Provide the means for changing the direction of air-flow and thus the I means for determining rabbit direction. b. Provide the means for varying the vacuum, thus providing a means for controlling the rabbit's speed. l c. Provide the neans of breaking vacuum, thus preventing the draining of the 1 reactor pool if a leak should occur. j d. Provide the means for cooling the system, thus preventing thermal expansion of the rabbit and possible binding. (***-End of Section C ***) i b e-

l t Section A R Theory. Thermo & Fac. Operatina Characteristics Page 23 l

  • ANSWER (A.1) c GIVEN $1.00 - B ---> p = 0.3(B) f r-ll

-o 7 (A,,,,,p) A,,,,,,0. 3 ( 8,,,) g,lL _H - IO.3(B IO.71 0.7

0. 7 8_,

r 23 rn (A.,,B.,'vl__ 2.,, 0.3 0.03 Assume A,,, = 0.125

REFERENCE:

(A.1) REED ROBERT BURN, o 1982, f4.4, equation 4.15.

  • ANSWER (A.2) b p2;07F10%hK/(KJ-J)(?[2TOTiM0'
  • REFERENCE-A2 3.

kdede as e 'off 5?CO s f;eq'uival enth) WOO 7N7E$E28~ '~~' ~ ' '^~ / 'Cy~ S M S"'0!007 ~~i~^.YTempfreictivity;=h+$0035T: ET$0'~28 9:$40!O35 W 50;315 V.i::$0 327 NOTE- 'Neid'sffoF U. HassMFe11~' "

  • ANSWER- (A.3) d

REFERENCE:

(A.3) REED ROBERT BURN, o 1982, 55.2, p. 5-1

  • ANSWER (A.4) a

REFERENCE:

(A.4) REED ROBERT BURN, o 1982, 53.3.4, equation 3.8, p. 3-21 0.0455K = K - 1 1 = (1 - 0.4c-)K K,, - 1/(1-p) = 1/(1-(-0.0455) = 0.9565

  • ANSWER (A.5) f C

REFERENCE:

(A.5) REED ROBERT BURN, o 1982, 55.5, example 5.5(c)(a). j i /(1-K (CR /CR ) = (1-K*{i-)K,,,2),,,2) 2 (60/30)3 = (0.90) 1 K,,,2 = 0.95 t 1 i

Section A R Theory. Thermo & Fac. Operatina Characteristics Page 24

  • ANSWER (A.6)-

C

REFERENCE:

(A.6) Standard Power Equation P=Pe' P = 1.25 Mwatts e("" +'A' V o P = 1.25 Mwatts (2.72) P = 3.398 Mwatts - 3.4 Mwatts

  • ANSWER (A.7) b
  • REF.ERENCE:

_ (A.7). REEDiROBERTlBURN.iio11982R

  • ANSWER (A.8) a

REFERENCE:

(A.8) REED ROBERT BURN, o 1982, 9

  • ANSWER (A.9) d

REFERENCE:

(A.9) REED ROBERT BURN, o 1982, f 8.4, Table 8.4.

  • ANSWER (A.10) c

REFERENCE:

(A.10) REED ROBERT BURN, o 1982, s 3.2.1, Table 3.2.

  • ANSWER (A.11) b

REFERENCE:

(A.II) REED ROBERT BURN, o 1982, 5 2.2, Fundamental Particles and 5 2.3 The Atom and the Atomic Nucleus.

  • ANSWER (A.12) b

REFERENCE:

(A.12) REED ROBERT BURN, o 1982, Chapter 7 5 7.3

3 t Section A R Theory. Thermo & Fac. Doeratino Characteristics Page 25 l

  • ANSWER

-(A.13) a i

REFERENCE:

(A.13) i REED ROBERT BURN, o 1982, 5 6.4.4, example 6.4.4(e) 1 Reactivity added by control rod = +(0.001 Ak/k/ inch)(10 inches) = 0.01 ok/k. fuel temperature change - -Reactivity added by rod / fuel temperature i coefficient i Fuel temperature change - (-0.01 Ak/k)/(-9.6 x 10'5 Ak/k/*C) - 104*C.

  • ANSWER (A.14) b

REFERENCE:

(A.14) REED ROBERT BURN, o 1982, 63.3.1, p. 3-16

  • ANSWER (A.15) a i

REFERENCE:

(A.15) l REED ROBERT BURN, o 1982, 55.4, pp. 5-15 through 5-18. i

  • ANSWER (A.16) b

REFERENCE:

(A.16) REED ROBERT BURN, o 1982, 63.3.4, example 3.3.4(b), p. 3-23 l i

  • ANSWER (A.17)

~ C

REFERENCE:

(A.17) i REED ROBERT BURN, o 1982, f 2.5, Table 2.3, pp. 2-40 throu9h 2-42. j s i

  • ANSWER (A.18) l C

REFERENCE:

(A.18) { REED ROBERT BURN, o 1982, 52.6.2, equatjon2.15,p.2-50. l R - p I, - (2.5 x 10' ) x 0.1 - 2.5 x 10 '

  • ANSWER (A.19) j a

REFERENCE:

~(A.19) REED ROBERT BURN, o 1982, G 3.3.1, Neutron Multiplication. t

  • ANSWER (A.20) b l

REFERENCE:

(A.20) J REED ROBERT BURN, o 1982, 5 7.7.4. (*** End of Section A ***) l

Section B' Normal /Emero Procedures & Rad con Page 26

  • ANSWER (B.1)

[ a

  • REFERENCE (B.1) i U. Mass - Lowell, Standing Order #10.

i

  • ANSWER (B.2) b
  • REFERENCE (B.2) l TL, =[ product / sum i

(15) x (2)] + (15 + 2) l = 30/17 - 1.76 i

  • ANSWER (B.3)

C

  • REFERENCE (B.3)

U. Mass - Lowell, Startup Procedure i

  • ANSWER (B.4) a 2, b 1, c 3, d 4
  • REFERENCE (B.4) i (a) 10 CFR 20.202.b(2)

(b) 10 CFR 20.105(b) (c) 10 CFR 20.202.b(3) (d) 10 CFR 20.105(a) f

  • ANSWER (B.5) c j
  • REFERENCE (B.5)

Standing Order #1.

  • ANSWER (B.6) e b (Arawer chansed to correct per f acility coiment.)

l

  • REFERENCE (B.6)

U. Mass. - Lowell Technical Specifications, f 3.B COOLANT SYSTEM i

  • ANSWER (B.7)

C. l

  • REFERENCE (B.7) 10CFR20.101
  • ANSWER (B.8) c
  • REFERENCE (B.8)

U. Mass. - Lowell, Technical Specifications s 3.3 REACTOR SAFETY SYSTEM i i

Section B Normal /Emero Procedures & Rad Con Page 27

  • ANSWER (B.9) b
  • REFERENCE (B.9)

U. Mass -- Lowell, Technical Specifications, s 2.2.2

  • ANSWER (B.10) b
  • REFERENCE (B.10)

U. Mass -- Lowell Technical Specifications, 6 3.6.1 through 3.6.8.

  • ANSWER (B.ll) b.
  • REFERENCE (B.11) 10CFR55
  • ANSWER (B.12) c.
  • REFERENCE (B.12) 10CFR.101
  • ANSWER (B.13) c.
  • REFERENCE (B.13 DR-{6CiE(n}}+R}

First find E (1.2 + 1.3) + 2 - 1.25 DR = {6Ci(1.25)(2)] + (30)2 900 (DR) - 6(2.5) Ci 900(0.1R/hr) - 15 Ci 90 - 15 Ci 6 curies - Ci i

  • ANSWER (B.14) d.
  • REFERENCE (B.14) 10CFR20 rem - rem
  • ANSWER (B.15) b
  • REFERENCE (B.15) l U. Mass. -- Lowell, Technical Specifications 6.0 EDMINISTRATIVE CONTROLS. 6.1 ORGANIZATION AND MANAGEMENT f 6.1.5 c
  • ANSWER (B.16) 5 a
  • REFERENCE (B.16) l U. Mass. -- Lowell Technical Specifications, 9 3.6 LIMITATIONS OF EXPERIMENTS t

.Section B Normal /Emera Procedures & Rad Con Page 28

  • ANSWER (B.17) f b
  • REFERENCE (B.17)

U. Mass - Lowell procedures (RO-7) Reactor Shutdowns, note following section 5 7.2.3(d).

  • ANSWER (B.18)

C

  • REFERENCE (B.18) l find y - (0.051cm*/g) X 11.4 g/cm - 0.5814 cm" 3

l -l e'"" o 0.1 -e in(0.1) - -(0.5814)x -2.3026 - -0.5814 (x) ~ x - 2.3026/0.5814 - 3.9672 = 4 i

  • ANSWER (B.19) a
  • REFERENCE (B.19)

U. Mass. - Lowell, E-PLAN, 6 3.3 Termination of an Emercency i t i '9 ? l i (*** End of Section B ***)

Section C Plant and Rad Monitorino Systems Page 29

  • ANSWER (C.1) a
  • REFERENCE (C.1)

U. Mass. -- Lowell supplied Reactor Electrical Distribution Sheet.

  • ANSWER (C.2) b
  • REFERENCE C.2)

QiMassJ--;;;.Liipe())

  • ANSWER (C.3)
a. 1,
b. 1,
c. 2
d. 1
  • REFERENCE (C.3)

U. Mass. -- Lowell, RF-5.

  • ANSWER (C.4) a
  • REFERENCE (C.4)

CA[

  • ANSWER (C.5) a, 2; b, 1; c, 1; d, 1.
  • REFERENCE (C.5)

U. Mass -- Lowell Instrument drawings. Also

  • ANSWER (C.6) d
  • REFERENCE (C.6)

U. Mass -- Lowell FSAR 6 4.4.15.

  • ANSWER (C.7) d
  • REFERENCE (C.7)

U. Mass -- Lowell Technical Specifications s

  • ANSWER (C.8)

C

  • REFERENCE (C.8)

U. Mass -- Lowell, FSAR Table 4.3.

  • ANSWER (C.9) b
  • REFERENCE (C.9)

U. Mass. -- Lowell, FSAR S 4.1.7. r r

i Section C Plant and Rad Monitorina Systems Page 30

  • ANSWER (C.10) a.

I b. I c. 2 d. I e.. I f. 1

  • REFERENCE (c.10)

U. Mass - Lowell, Electrical Distribution Diagram

  • ANSWER (C.11) a.

2 b. 3 2 cAncwer chansed to correct per facility comment.) C. B 3 canswer ch.noed to correct per f citity comment.) d. 4

  • REFERENCE (C.11)

U. Mass - Lowell, FSAR Appendix 10, pp. 10-18 and 10-19.

  • ANSWER (C.12) b
  • REFERENCE (C.12)
  • ANSWER (C.13) d
  • REFERENCE (C.13)

U. Mass - Lowell, FSAR s 7.4.3, Samplina

  • ANSWER (C.14) d
  • REFERENCE (C.14)

U. Mass - Lowell, FSAR Appendix 10. l

  • ANSWER (C.15) d
  • REFERENCE (c.15)

U. Mass - Lowell, FSAR, f 4.4.15, pp. 4-72 & 4-73. i.

  • ANSWER (C.16) c
  • REFERENCE (0.16) l U. Mass - Lowell, FSAR 5 4.3.3.5, page 4-35 i

a 1 i (*** End of Section C ***) l l'

Section A R Theory. Thermo & Fac, Operatina Characteristics Page 31 A.01 c A.02 b A.03 d A.04 a A.05 c A.06 c A.07 b A.08 a A.09 d j A.10 c A.11 b i A.12 b i A.13 a A.14 b A.15 a A.16 b i A.17 c A.18 c i A.19 a .l A.20 b i (*** End of Section A ***) i i l l 1 l

Etetion B Normal /Emera Procedures & Rad Con Page 32 B.I' a B.2 b i B.3 c j B.4

a. 2
b. I
c. 3

[

d. 4

'l B.5 c j B.6 0 b (Answer changed to correct per facility consnent.) { B.7 c B.8 c B.9 b i i B.10 b i B.11 b B.12 c 7 B.13 c l B.14 d B.15 b B.16 a B.17 b B.18 c B.19 a t i l i I (*** End of Section B ***) I ~

Section C Plant and Rad Monitori_ns Systems Page 33 n C.01 a C.02 b C.03

a. I
b. I
c. 2
d. 1 C.04 a

C.05

a. 2
b. I
c. I
d. 1 C.06 d

C.07 d C.08 c C.09 b C.10

a. I
b. 1 C. 2
d. 1
e. 1
f. 1 C.11
a. 2
b. 3 2 canswer changed to correct per facitity conenent.)

C. 2 3 (Answer changed to correct per facitity conenent.)

d. 4 C.12 b

C.13 d C.14 d C.15 d C.16 c (*** End of Section C ***) I i i}}

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