Text

Exam Rept 50-297/OL-91-01 on 910603-04.Exam Results:Both Applicants Passed Exam
	ML20217C669
Person / Time
Site:	North Carolina State University
Issue date:	07/08/1991
From:	Eresian W, Szymanski T; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20217C665	List: ML20217C659; ML20217C669;
References
	50-297-OL-91-01, 50-297-OL-91-1, NUDOCS 9107180068
	Download: ML20217C669 (64)
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{{#Wiki_filter:_ 4. ENCLOSURE 1 U. S. NUCLEAR REGULATORY COMMISSION OPERATOR LICENSING INITIAL EXAMINATION REPORT REPORT NO.: 50-297/0L-91-01 FACILITY DOCKET NO.: 50-297 FAClllTY LICENSE NO.: R-120 LICENSEE: North Carolina State University EXAMINATION DATES: June 3-4, 1991 EXAMINER: Warre' Eresian, ret) Examiner SUBMITTED BY: <W A.'~ 7& / Warerfres)4n,Ch~ +eminer Date APPROVED BY: [ /wr MNch 18 / Throdore L. Spfmanski, Chief ft1 Date Non-Power Reattor Section Operator Licensing Branch Division of Licensee Performance and f)uality Evaluation, NRR SUMMARf: NRC administered written and operating examinations to two Senior Reactor Operator (Instant) applicants. Both applicants passed the examinations. 9107180068 910708 PDR ADOCK 05000297 V PDR

l REPORT DETAILS 1. Examiners: Warren Eresian, Chief Examiner 2. Results: R0 SR0 Total (Phss/ Fail) (Pass / Fail (Pass /faill NRC Grading: 2/0 2/_0 3. Written Examination: See comments and resolutions on attached sheet. 4. Operating Examinations: Both candidates passed the operating examination. 5. Exit Meeting: Present at the exit meeting were: Warren Eresian, NRC Garry Miller, NCSU Stephen Bilyj, NCSU Mr. Eresian thanked both Mr. Miller and Mr. Bilyj for their efforts in support of the examination. Mr. Eresian noted thst both applicants demonstrated a lack of understanding of principles of radiation detection.

-6 ENCLOSURE 2 RESOLUTION TO COMMENTS FROM THE NORTH CAROLINA STATE UNIVERSITY EXAMINATION A 013 Correct answer is (C), not (B). NRC:- Typographical error. Comment accep.ad. A.018-No answer is correct, but the "most" correct answer is (D). NRC: Comment accepted. B.001 There is no correct answer. NRC: Comment accepted. Question will be deleted. C.003 There-is no correct answer. NRC: Comment accepted. Question will be deleted.

ENCLOSU3E 3 NRC Official Use Only f Nuclear Regulatory Commission Operator Licensing Examination This document is removed from Official Use only category on date of examination. NRC Official Uce Only

4 l4-IU, S. NUCLEAR REGULATORY COMMISSION NON-POWER REACTOR LICENSE EXAMINATION-North Carolina-State Univ FACILITY: REACTOR TYPE: PULSTAR l 1 DATE ADMINISTERED: 91/06/03 2 REGION: CANDIDATE: J LICENSE APPLIED FOR: ,TNSTRUCTIONS-TO CANDIDATE: Answers are to be written _ on the exam page itse.tr, or the answer sheetAttac Write answers one : side-ONLY. Points for_each question are indicated in parenthes proviaed. examination. (3) hours after the examination-starts. ?cach question. Examinations will be' picked up three % OF = CATEGORY % OF ' CANDIDATE'S CATEGORY CATEGORY-VALUE. TOTAL SCORE VALUE REACTOR THEORY, THERMODYNAMICS i A. 20.00 -- 3'3.33. AND FACILITY OPERATING CHARACTERISTICS NORMAL : AND EMERGENCY - OPERATING B. i

20.00 33.33

'FROCEDURES AND-RADIOLOGICAL-CONTROLS PLANT AND RADIATION MONITORING C. 20.00' =33.33 SYSTEMS TOTALS

60.00 FINAL GRADE I_have neither given nor AllLwork done on this' examination.is my own.

rscaived aid.. Candidate's Signature

j Page 2-A. PX THEOPY, THE.FXO & FAC OP CHARS ~ ANSWER SHEET Multiple Choice (Circle'or X yo" ,oice) If you change your answer, write your selection in the blank. } MULTIPLE CHO1CE 001 a b c d 011 a b c d 002 a b c d 012 a b c d 003 a b c d 013 a b c d 004 a b c d 014 a b c d 005 -a b c-d 015 a b c d 006 a b c d 016 a b c d 007 a b c d 017 a b c d 008 a b c d-018 a b c d 009 a b c d 019 a b c d 010 a b c d 020 a b c d A *****) (***** END OF CATEGORY w y e 4-+ ie a v- + -e e. y .--.5 em-- a-V ? --PW

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Page 3 B. NORMM 'EMEFG PFOCEDURES & RAD CON 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 011 s b c d 002 a b c d 012 a b c d 013 a b c d 003 a b c d 004 a b c d-014 a b c d 005 a b c d 015 a b c d 006 a b c d 016 a b c d 007 a b c d 017 a b c d 008 a b c d 018 a b c d 009 a b c d 019 a b c d 010 a b c d 020 a b c d B *****) (***** END OF CATEGORY

e I Page 4 J PIR;T AND RAD MO!!ITOPJJ'G SYSTEMS C. A N S-W E R SHEET (circle or X your choice) Multiple Choice k. If you change your answer, write your selection in the blan 011 a b c d 001 a b c d 012 a b c d 000 a b c d 013 a b c d 003 a b c d 014 a b c d 004 a b c d 015 a b c d 005 a b c d 016 a b c d 1 006 a b c d 017 a b c d 007 a b c d 018 a b c d 008 a b c d 019 a b c d 009 a b c d 020 a b c d 010 a b c d C *****) (***** END OF CATEGORY (********** END OF EXAMINATION **********) l t

15 NRC_ RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During-the administration of this examination the following rules apply: Cheating on the examination means an automatic. denial of your appl-ication and could result _in more severe penalties. I. i ~2. After the examinatie.1 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 _ j This must be done after you complete the the examination. examination. Restroom trips are to be limited and only one candidate at a 3. You must avoid all contacts with anyone time may leave. 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. 5.. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet. Print-your name in the upper right-hand corner of each answer 6. sheet. Partial credit.may be given. Therefore, ANSWER-ALL PARTS OF NOTE: partial 7. THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. credit will NOT be given on multiple choice questions. i Proportional grading will NOT be given on multiple chtice B. questions. 9.-If the' intent of a question is unclear, ask questions of the examiner-only. When turning in your examination, assemble the completed examination aids and

10. examination with examination questions, In addition, turn in all scrap paper.

answer sheets. 70% in each

11. To pass the examination, you must achieve at least-category.-

12. There is a-time limit of (3) hours for completion of the examination.

13. 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.

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~~-__ Page 10 THERMO & FAC OP CliARS A. HX THEORY, I^ l QUESTIO!1: 001 (1.00) DPM. asing irom 65 MWT on a SUR of 0.5 Reactor power is inu nds? Which OliE of the following is the reactor power after 120 seco A. 550 MWT B. 650 MWT C. 750 MWT D. 850 MWT QUESTIO!1: 002 (1.00) 0.946. In a suberitical reactor, Keff is increased from 0.861 to h t was Which ONE of the following is the amount of reactivity t a added to the reactor cere? A. 0.086 delta K/K B. 0.104 delta K/K C. O.125 delta K/K D. 0.220 delta K/K QUESTION: 003 (1.00) l is most Which OllE of the following terms of the six factor formu a affected by " Poisons"? Fast Fission Factor A. Thermal Non-Leakage Probability B. C. Reproduction Factor Thermal Utilization Factor D. A CONTINUED ON NEXT PAGE *****) (***** CATEGORY

Page 11 RX THEORY, THERMO 6 FAC OP CHARS A. OUESTION: 004 (1.00) Which ONE of the following best describes the difference betwenn a reflector and a moderator? Reflectors slow down neutrons while moderators A. decrease core leakage. Reflectors shield against neutrons while B. moderators decrease core leakage. Reflectors shield against neutrons whiled moderators decrease plutonium production. C. Reflectors decrease core leakage while D. moderators thermalize neutrons. QUESTION: 005 (1.00) Which ONE of the following is the reactivity coefficient that will turn power when the regulating rod has been withdraan to increase (Assume no other actions are taken.) power? Pressure coefficient A. B. Void coefficient Moderator temperature coefficient C. Fuel temperature coefficient D. A CONTINUED ON NEXT PAGE *****) (***** CATEGORY

Page 12 A. 'RX THEORY, THERMO & T'AC OP CHARS QUESTION: 006 (1.00) Which ONE of the following is the reason for the -80 SEC period following a reactor scram? The ability of U-235 to fission with source A. neutrons. The decay constant of the longest-lived group B. of delayed neutrons. The amount,f negative reactivity added on a o trip being greater than the Shutdown Margin. C. The doppler effect adding positive reactivity due to the temperature decrease following a D. scram. QUESTION: 007 (1.00) l Which one of the following is the reason for operating with therma noutrons instead of fast neutrons? Increased neutron efficiency since thermal neutrons are less likely to leak out of the A. core than fast neutrons. Heutron absorption in non fuel material increases exponentially as neutron energy B. increases. The fission cross section of the fuel is much higher for thermal energy neutrons than fast C. neutrons. l Doppler and moderator temperature coefficients become positive as neutron energy increases. D. A CONTINUED ON NEXT PAGE *****) (***** CATEGORY . t ~.

Page 13 A. RX 7HEORY, THERMO 6 TAC OP CHARS QUESTION: 000 (1.00) Which ONE of the following is the description of a thermal neutron? A neutron possessing thermal rather than A. kinetic energy. The primary source of ther al energy increase B. in the reactor coolant du' ng reactor operation. A neutron that has bes, produced in a C. significant time (on the order of seconds) after its initiating fission took place. A neutron that experiences no not change in D. energy after several collisions with atoms of the diffusing media. QUESTION: 009 (1.00) R3 actor power increases from 10 watts to 800 watts in 4.2 minutes. (Assume a positive step change in reactivity.) Which ONE of the following is the approximate doubling time? A. 0.36 minutes B. 0.66 minutes C. 0.72 minutes D. 0.95 minutes A CONTINUED ON NEXT PAGE *****) (***** CATEGORY

Page 14 A. EX THEORY, THERMO & TAC OP CHARS QUES'110N : 010 (1.00) Which ONE of the following describes the relationship between and integral rod worth (IRW)? differential rod worth (DRW) is the slope of the IRW curve at that A. DRW location. is the area under the IRW curve at that B. DRW location. DRW is the square root of the IRW at that C. location. D. DRW is not related to IRW, QUESTIO!!: 011 (1.00) Which ONE of the following describes the PULSTAR operating values and the for the Temperature Coefficient of Reactivity (pcm/deg F) power defect (pcm) respectively at IMW? A. -3.9 pcm/deg. FT -330 pcm B. -3.1 pcm/deg. Fi -270 pcm C. -2.3 pcm/deg. F; -220 pcm D. -1.7 pcm/deg. F ; -160 pcm l (***** CATEGORY A CONTINUED ON HEXT PAGE *****) -~,,

Tage 15 & EAC OP CHARS A. 'RX THEORY, 1HERMO QUESTION: 012 (1.00) is following describes the reason why Xenon-135 poison during Which ONE of the fission-product the most inportant Xenon-135 has an exctptionally small absorption cross section for thermal neutrons and small A. rate of production. Xenen-135 has an exceptionally large absorption cross section for thermal neutrons and small B. rate of production. Xenon-?35 has an exceptionally large absorption cross section for thermal neutrons and large C. rate of production. Xenon-135 has an exceptionally small absorption section for thermal neutrons and large D. cre 3 ret of production. QUESTION: 013 (1.00) following describes the expected response of the Whi.h ONE of thereactor if any Linear Power Channel indicates 74%7 The reactor scram will automatically scram A. followed by a loss of magnet power. The reactor will continue to operate at theintervened present power level until manually B. by the operator. The control rod drives automatically initiate reverse drive action until the operator C. depresses the ACK/ RESET pushbutton.. The control rod drives automatically initiate partial reverse drive action until reactor D. power is less than 70%. A CONTINUED ON NEXT PAGE*****) (***** CATEGORY

Page 16 A. 7tX THEORY, THERMO & TAC OP CHARS QUESTION: 014 (1.00) Which ONE of the following if changed, will NOT affect the Effective Multiplication Factor (K-off)? Neutron contribution from neutron sources A. B. Control rod worth ) C. Puel enrichment Shutdown margin when the reactor is suberitical D. QUESTION: 015 (1.00) f A reactor startup is in progress. Which ONE of the followin wh0n taking the reactor critical? The nuclear instrumentation will take longer to stabilize at each new suberitical lovel. A. will be critical when the period The reactor with no B. and power level remain constant, further rod withdrawal. Each completed control rod withdrawal will result in the same amount of change in C. suberitical power level. Each control rod withdrawal results in an D. initial negative period followed by a strong positive period. A CONTINUED ON NEXT PAGE *****) (***** CATEGORY w m w r r w-ww-

Page 17 A. RX THEORY, THERMO & TAC OP CHARS QUESTION: 016 (1.00) Which ONE of the following describes how the effective delayed nautron fraction varies over core life? Increases due to the burnup of U-238. A. Decreases due to the buildup of PU-239. B. Increases due to the buildup of PU-239. C. Decreases due to the burnup of U-230. D. QUESTION: 017 (1.00) Which ONE of the following describes how the magnitude of the Fuel Tcmperature coefficient of reactivity is affected over core life? It becomes more negative due to the buildup of A. PU-240. IT becomes less negative due to the buildup of B. fission products. It becomes more negative initially due to C. gadolinium burnout, then less negative due to fuel depletion. D. It remains essentially constant. (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 20 & P.AD CON B,* NORMAL /EMERG PROCEDURES -QUESTION: 001 (1.00) In accordance with PULSTAR OPERATIONS MANUAL Section 2, which ONE of the following Reactor ADMINISTRATIVE CONTROLS, Op3rator actions is NOT permitted during automatic reactor operation? j Observe reactor instrumentation f rom rear of A. console in the interest of reactor safety. instrumentation on temperature control ) B. Obse rve panel in the control Room. f Obtain replacement chart recorder paper stored C. in Control room. Observe status of Control Room Electrical D. Distribution Panel, t QUESTION: 002 (1.00) Which ONE of the following lists the personnel who may close a RED tag-out? Reactor Operators and Reactor Operator A. Assistants Reactor Operations Manager and Reactor B. Operators Chief of Reactor Maintenance and Reactor C. Operations Manager Designated Senior ReactorsOperator and Chief D. of Reactor Maintenance. B CONTINUED ON NEXT PAGE *****) (***** CATEGORY - ~.

Page 18 A. RX THEURY, THERMO & FAC OP CHARS QUESTION: 01B (1.00) While withdrawing control rods during a reactor startup, the count If the SAME amount of reactivity that caused the first doubling in added again, which ONE of the following describes reto doubles. whet will happen? i The count rate w'ill doubic and the reactor will A. be subcritical. The count rate will not double and the reactor B. will be critical. The count rate will nore than double and the -f C. reactor will be suberitical. The count rate will more than double and the D. reactor will be critical. l i QUESTION: 019 (1.00) Which ONE of the following accidents is considered by the PULSTAR Safety Analysis to be a "Non-excursion Accident"? A. Experiment Failure B. Tuel-Loading Accident C. Control Rod Failure D.- Loss of Primary Flow A CONTINUED ON NEXT PAGE *****) (***** CATEGORY

Page 19 1 RX THEORY, THERMO & EAC OP CHARS A. QUESTION: 020 (1.00) Which ONE of the following describes the behavior associated with WATERL.GGING? in the fuel cladding which would permit Leak in-leakage of water during low power operations A. or at shutdown. Leak in the fuel cladding which would permit B. out-leakage of fission products into the water during low power operations or at shutdown Leak in the Primary coolant heat exchanger C. which would permit in-leakage of fission products into the secondary coolant system during power operations or at shutdown. Leak in the Primary coolant heat exchanger D. which would permit out-leakage of raw water into the primary coolant syster.during power operations or at shutdown. I ,, cA,...,

Page 22 B. NORMAL /EMERG PRC CEDURES & RAD CON QUESTION: 003 (1.00) level Which ONE of the following positions represents the minimal irradiated of authority required to approve the release of materials to off-campus users? A. Any NRC licensed operator B. Designated Senior Reactor Operator Reactor Supervisor / Associate Director C. 9adiological Protection Office / Reactor Health D. Physicist i QUESTION: 004 (1.00) Which ONE of the following are the required signatures for a Radiation Work Permit once it is initiated and signed by the i i Reactor Health Physicist? Reactor operator on watch and the Designated A. senior Reactor operator. B. Reacter operstor on watch and the Reactor operations Manager. Person in charge of the job and the Reactor C. Operations Manager. Person in charge of the job and the Designated D. Senior Reactor operator. l (***** CATEGORY B CONTIFUED ON NEXT PAGE *****)

~ l ( l Page 22 NORMAL /EMERG PROCEDURES & RAD CON D. QUESTIOll: 005 (1.00) One of the immediate action steps for a reactor scram is to " Ensure Reverse action of control rod position indicators." Which ONE of the following is the action to be taken if the reverse action fails to take place? Move the Ganged Insert switch to the "In" A. position. Initiate a Manual SCRAM D. Turn "Off" Reactor Keyswitch C. Inform Designated Senior Reactor Operator D. QUESTION: 006 (1.00) Which ONE of the following conditions would prevent the initiation of the Automatic Control System? Regulating Rod has been withdrawn to 15 inches A. Servo deviation is 0.3% B. The MODE switch is in the " Square Wave" C. position Gang Drive switch is in the neutral position. D. B CONTINUED ON HEXT PAGE *****) (***** CATEGORY ~ - - - - ~ -. - - - _ _ _ _ _ _ _ _ _ ___

Page 23 NORMAL /EMERG PROCEDURES & RAD CON B. 1 QUESTION: 007 (1.00) Which ONE of the following events is considered an unanticipated cbnormal reactivity change?" Actual critical position is 80 pcm of the A. estimated critical position. Experiment reactivity varies significantly from B. that which was planned. Continuous withdrawal of safety number 2 rod. C. Continuous withdrawal of transition rod, l D. QUESTION: 008 (1.00) The N-16 Channel indication is A reactor startup is in progress. rocding stable at 900 kW. J Which ONE of the following is the allowable band of agreement for the Safety and Linear Channels at this power level? A. 800 - 1000 kW B. 850 - 950 kW -C. 850 - 1000 kW D. 800 - 950 kW B CONTINUED ON NEXT PAGE *****) (***** CATEGORY t' s ...--,,,.n. .. ~.,. -m..,

l Page 24 t B.

NORMAL /EMERG PROCEDURES & RAD CON QUESTION: 039 (1.00)

Tochnical Specifications state "The rate of reactivity insertion is not averaged over the length of the rods, of the control rods, groater than 0.1% delta h/k per second." Which ONE of the following events is associated with the basis that casures that the safety limit will not be exceeded? The flow reversal which occurs upon loss of A, forced convection coolant flow. B. A rod eject' ion accident in the steady state mode. An accidental withdrawal of a 0.3% delta h/k C. experiment in the pneumatic rabbit. A startup accident due to a continuous linear D. reactivity insertion. QUEt. ION: 010 -(1.00) Which ONE of the following is the Limiting Safety System Setting for the minimum height of water above the core? A. 20 feet, 0 inches B. 17 feet, o inches C. 14 feet, 2 inches D. 14 feet, o inches I (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page 25 B. NORMAL /EMERG PROCEDURES & RAD CON QLESTION: 011 (1.00) Which one of the following is the maximum exposure limits as set down by 10 CFR 20 section 20.101? (NRC Form 4 is on file.) A. Quarterly Whole Body - 3.0 rem Yearly Whole Body - 5(N-18) Quarterly Extremities (Hands & feet)-18.15 Rem Quarterly Skin of Whole Body - 7.5 Rem B. Quarterly Whole Body - 3.0 rem Yearly whole Body - 5(N-18) Qanrterly Extremities (Hands & feet) - 7.5 Rem Quarterly Skin of Whole Cody - 18.75 Rem C. Quarterly Whole Body - 1.25 rem Yearly Whole Body - 5 Rem - 7.5 Rem-Quarterly Extremities (Hands & feet) Quarterly Skin of Whole Body - 18.75 Rem D. Quarterly Whole Body - 1.25 rem Yearly Whole Body - 5 Rem Quarterly Extremities (Hands & feet) - 18.75 Rem Quarterly Skin of whole Body - 7.5 Rem QUESTION: 012 (1.00) Which ONE of the following NCSU Emergency Plan general guidelines apply if a search team needs to access the reactor building? Limit exposure to less than 100 mR / person. A. Limit exposure to less than 250 mR / person. B. Limit exposure to less than 500 mR / person. C. Limit exposure to less t.an 750 mR / person. h D. (***** CATEGORY B CONTINUED ON HEXT PAGE *****) 4 y

Page 26 ' NORMAL /EMERG PROCEDURES 6 RAD CON B. QUESTION: 013 (1,00) Which one of the following operations allows the over-the-Pool minutes? rodiation monitor to be bypassed for up :o tnree (3) During pulse mode operations A. During removal of experiments from the reactor B. pool Immediately after starting the pneumatic blower C. system. During square wave mode operation D. QUESTION: 014 (1.00) Which ONE of the following is the amount of time that the Reactormay be open while and Loading Dock Door (1105) Bay East Door (B118) the reactor is operating? A. One minute B. Three minutes C. Five minutes D. Seven minutes QUESTION: 015 (1.00) Which ONE of the following must review a temporary change to the Operations Manual within two months of its initiation? Nuclear Reactor Program staff A. Radiation Protection Council B. C. Independent Review Group Reactor Safeguards Advisory Group D. B CONTINUED ON NEXT PAGE *****) (***** CATEGORY e- ---w,e--- ~ - --- --,,,., - - >.

Page 27 JJORMAL/EMERG PROCEDUkES & RAD CON B. 4 i QUESTION: 016 (1.00) the following Emergency Classes is being described 7 Which ONE of " Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the rocctor." Notification of Unusual Events A. B. Alert Site Area Emergency C. D. General Emergency 017 (1.00) QUESTICN: i Which ONE of the following actions is required of the fuel handl ng crow in the event of an evacuation signal during fuel movement? shall be: The fuel assenbly in transit Lowered to the bottom of the pool at it present location and the and the fuel handling tool A. tied in place. Stored in a recorded location and the fuel handling tool disconnected from the fuel. B. Secured in its present location and the bridge C. crane de-energized. Placed in its designated mose location and bridge crane movement controls locked. D. B CONTINUED ON NEXT PAGE *****) (***** CATEGORY

Page as B[:N0kh31./EMERGpROCEDURES & RAD CON Ot1ESTIONt 018 (1.00) Which ONE'of the following is the amount of time a licensed l operator must perform his/her licensed duties to maintain -proficiency? A. Four hours per month -D. Eight hours per month C.- Four. hours per quarter-D. Eight! hours'per quarter-QUESTIONt 019-( 1. 0 0 ) -- Which'ONE of the following are the Technical Spe ification limits for irradinted. fuel storage? l 'Keff <0.80 delta-k/k and fuel element- -{ A. temperature <90 degrees C Xeff <0.85 delta k/k and fuel element B. temperaturer<85 degrees C- .Keff <i0.90~ delta k/k and fuel element. C.- temperature <80: degrees.C Keff_<0.95Ldelta k/k'and fuel element D.~ temperature <75 degrees C fQUESTION: 020 (1.00) Which ONE of the following terms is descriptive of a= qualitative verification of? acceptable performance-by. observation of channel behavior? -A. Channel Operation B.- Channel Calibration t C. Channel' Test t D. -Channel check (***** END OF CATEGORY B *****) _.. _ _.. -. _ __ _ _,-. _ - __._ _ _.-..._ _. _. - -. ~. _.. _ _.,.. _ _. _. - -...., _.. -

Page 29 ' LANT AND RAD MullITORING SYSTEMS P C. 7__ QUESTION: 001 (1.00) in the Which ONE of the following types of detectors is utilize l roloase during a reactor pulse? A Uranium lined Fission Chamber detector, gas and drive assently, high and low A. voltage power supplies, and pulse preamplifier.

filled, A Con.pensated Ion Chamber, gas filled, a high voltage and compensation voltage power supply.

B. An Uncompensated Ion Chamber, gas filled, a high voltage power supply and a picoammeter. C. An Uncompensated Ion Chamber, under a high vacuum, associated power supply, a current D. amplifier, and an electrometer current integrator. 002 (1.00) QUESTION: h Which ONE of the following events will occur due to a loss of t e Recctor Air Supply? A Low Primary Flow condition will be sensed, the Flapper will open causing a Flapper Open A. Scram. An Abnormal Pool Level Alarm will annunciate due to a High pool level indication, No Reactor B. Scram will result. A Low Primary Flow Alarm will annunciate and a Low Primary Flow Scram will be initiated. C. A Low Primary Flow condition will be sensed, and the Pulse Rod will drift in shutting down D. the reactor. C CONTINUED ON NEXT PAGE *****) (***** CA7EGORY

Pcge 30 C.

PLANT AND RAD MONITORING SYSTEMS QUESTION: 003 (1.00) fan damper-verification lights on the

'If the confinement Radiation-Monitoring Panel are illuminated, which ONE of the cause? following conditions describes the Power is available to the c';ntrolled dampers A. Negative air pressure in the Reactor Building B. The main H & V supply and exhaust dampers are C. fully open The main H'& V supply and exhaust danpers are D. fully closed QUESTION: 004 (1.00) Which one of the following pairs of numbers correctly completes the following statement? four fuel pins from two different pulsed fuel elements chall be inspected whenever a group of __?__ pulses of greater than At least __7__ pcm have been accumulated. A. 2001 100 B. 10; 100 C. 1001 1000 D. 101 1000 C CONTINUED ON NEXT PAGE *****) (***** CATEGORY

Page 32 PLANT AND RAD MONITORING SYSTEMS C. QUESTION: 005 ( 1. 0 0) Power is being supplied by the Auxiliary E1cetrical System when Commercial power is restored. (LTC) Which ONE of the following gives the Load Transfer Controlinstantly the Transfer Switch position when commercial power is restored? that will A. Confinement Fan No. 1&2 B. The running Confinement ran Confinement ran No. 1 & Control Room C. Distribution Panel Control Room Distribution Panel D. QUESTION: 006 (1.00) Which ONE of the following describes how the Auxiliary Generator cupply breaker is closed following a loss of commercial power and the generator is started from the control Console? As the generator comes up in speed and voltage the generator voltage works against the spring A. to close the switch. As the generator comes up in speed and voltage B. reaches 80% of rated it automatically closes the switch. As the generator comes up to rated speed a time C. delay times out applying power to the closing relay to close the switch. As the generator comes up to rated voltage a D. contact loses applying power to the closing relay to close the switch. (***** CATEGORY C CONTINUED ON NEXT PAGE *****) '~ w-,

Page 32 C. ' PLANT AND RAD MONITORING SYSTEMS i QUESTION: 007 (1.00) Which ONE of the following Area Radiation Monitors will automatically shift to battery power upon the loss of Il5VAC7 A. Control Room B. Reactor Bridge C. Over Reactor Pool D. Reactor Bay West Wall f QUESTION: 006 (1.00) Which ONE of the following Air Radiation Monitoring systems constitutes an off-line isokinetic sampling system? Filter GM monitor & Reactor Day Cam A. Stack Particulate monitor & Auxiliary GM B. monitor Auxiliary GM monitor & Reactor Bay Cam C. Filter GM monitor & Stack Particulate monitor D. QUESTION: 009 (1.00) following monitors utilizes a gamma sensitive Which ONE of the ocintillation detector? A. Control Room Area Monitor Personnel Hand and Feet Monitor B. C. Waste Tank Monitor D. Stack Particulate Monitor C CONTINUED ON MEXT PAGE *****) (***** CATEGORY ,-.,..,..,,eJ w

Page 33 t - C. PLAllT 'AllD RAD M0111 TORI!1G SYSTEMS _ QUESTIOll: 010 - (1.00) Which OllE of__the following monitors, when in an ALARM condition, causes-an evacuation? West Reactor Bay Wall Monitor A. B.- Primary Dominerilizer Monitor -c. Exhaust Filter Bank Monitor D.- Reactor Bridge Monitor t QUESTIO111- 011-(1.00) A tube primary / secondary heat exchanger tube leaks develops. Which OllE of the following conditions will result in a loss of roactor coolant to the secondary-cooling system? ? Reactor operating at 1.'O MW, primary-and A. secondary pump. running. . Reactor secured, primary pump running:and. -B. secondary pump secured. Reactor at-50 kW in natural circulation with C. secondary pump' secured. Reactor at-125 kW in natural circulation with D. secondary pump running. (***** CATEGORY C CONTINUED ON NEXT PAGE *****) ryv.--+- rr.em,y.-3,---rw--a-re- ,y., ,,,,v.m.wn-,,w_.,,-4 y.,_~ ,m,,,ss,,_.,__.,,, _... _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _., _ _ _ _ _

~ Page 34 PLANT AND RAD MOla TO'nitui SYSYEMS .C. \\ i QUESTION: 012 (1.00) Which OllE of the following describes the Three-Wcy Divertingfinal posi actuator fails due to a loss of control air pressure? Valve's (S-5) S-S will divert all secondary flow to the A. cooling towers. flow. B. 5-5 will lock up maintaining pre-failure S-5 will cycle between full flow to the cooling C. tower to zero. S-5 will divert all secondary flow back to the D. pump suction. QUESTION: 013 (1.00) Which ONE of the following rods has the highest worth? A. Regulating B. Safety 42 C. Safety $1 D. Pulso QUESTION: 014 (1.00) Which ONE of the following elements is utilized in the PULSTAR Startup Neutron Source? Plutonium - Beryllium A. B. Antimony - Beryllium Polonium - Beryllium C. Americium - Berylliuu D. C CONTINUED ON HEXT PAGE *****) (***** CATEGORY

Page 35 PLANT AND RAD MONITORING SYSTEMS C. l __ l QUESTION: 015 (1.00) Which ONE of the following is the purpose of the Nitrogen Purge System? in the acts as a backup motive force It Pneumatic Transfer System should the air / vacuum A. supply blower fail. It provides a nitrogen purge gas to the Pl.sumatic Transfer System to reduce the B. formation of Argon-41. It acts with the BT&TC exhaust system to supply a continuous nitrogen gas blanket to the Beam C. formation. Tubes to minimize Argon-41 is used as a source of nitrogen gas for moisture removal and humidity control within It D. the Beam Tubes while in use as a specimen chamber. QUESTION: 016 (1.00) Which ONE of the following Nuclear Instrumentation System detectors l i failure and ,ould provide the FIRST indications of fue -p n w leakage? SEMIRAD burst detector A. B. Compensated ion chamber C. Gamma sensitive, xenon filled ionization chamber D. Uranium lined, fission chamber C CONTINUED ON NEXT PAGE *****) (***** CATEGORY ~ - ~ - - ---.. _ _ _ _ _ _ _ _ _

Page 36 PLANT AND RAD MONITORING SYSTEMS - l fC. g QUESTION: 017 (1.00) on overpower Which ONE of the following prevents a reactor scram during pulsing operations? The Linear and Safety Power channels are placed in " bypass" prior to pulsing the reactor. A. The overpower scram instrumentation setpoints time out have a 10 second time delay that must B. before a scram will occur. Depressing'the " Pulse" pushbutton provide. bypassing a C. The nuclear instrumentation channels used for overpower scram protection do not react fast D. enough to see the pulsed power. QUESTION: 018 (1.00) ts is required to Which ONE of the following control rod magnet curren be used prior to fuel movements. A. 40 mA B. 60 mA C. 80 mA D. 100 mA QUESTION: 019 (1.00) NT the " PULSE Which one of the following conditions will PREVE INTERLOCKS CLEAR" light from illuminating? 1500 pcm of the Pulse Rod is in the core. A. Reactor power is 120 kW. B. Pulse accumulator air pressure is 45 psig. C. Primary coolant flow is 425 gpm. D. C CONTINUED ON NEXT PAGE*****) (***** CATEGORY

Page 37 PIANT AND RAD MONITORING SYSTEMS C. QUESTION: 020 (1.00) in the steady state mode, which ONE of thetic sample? When operating -following is the reactivity worth limit for a pneuma A. 100 pcm D. 300 pcm C. 600 pcm D. 1000 pcm f C *****) (***** END OF CATEGORY (********** END OF EXAMINATION **********)

Page 38 A.* RX THEORY, THERMO & FAC OP CHARS ~ ANSWER: 001 (1.00) B.

REFERENCE:

Fundamentals of Nuclear Reactor Engineering, Equation 3-14,

DPC, page 94 ANSWER:

.002 (1.00) B.

REFERENCE:

DPC Fundamentals of Nuclear Reactor Engineering, Equation 3-41,page 121 ANSWER:- 003 (1.00) D.

REFERENCE:

DPC Fundamentals of Nuclear Reactor Engineering,page 72-73 ANSWER: 004 (1.00) D. (***** CATEGORY A CONTINUED ON NEXT PAGE * * * * * )

Page 39 A. 'RX THEORY, THERMO & FAC OP CHARS

REFERENCE:

52-53 Fundamentals of Nuclear Reactor Engineering, pg.

DPC, ANSWER:

005 (1.00) D.

REFERENCE:

Fundamentals of Nuclear Reactor Engineering, pg. 146

DPC, ANSWER:

006 (1.00) B.

REFERENCE:

Fundamentals of Nuclear Reactor Engineering,pg.40 & 106

DPC,

~ ANSWER: 007 (1.00) C.

REFERENCE:

Fundamentals of Nuclear Reactor Engineering,pg.73-75

DPC, ANSWER:

008 (1.00) D. (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 40 A. 'RX THEORY,-THERMO & FAC OP CHARS

REFERENCE:

1 Fundamentals of Nuclear Reactor Engineering,pg.57

DPC,

- ANSWER:. 009 (1.00) B.

REFERENCE:

Fundamentals of Nuclear Reactor Engineering, Equation 3-14, 'DPC, page 94 ANSWER: -010 (1.00) A.

REFERENCE:

137-139 Fundamentals of Nuclear Reactor Engineering,page

DPC, ANSWER:

011 (1.00) 'A.

REFERENCE:

1-11 NCS PULSTAR Ops. Manual, Section 1.4.6 p. -ANSWER: 012 (1.00) C. (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 41 - A. ' 10( THEORY, THERMO & FAC OP CilARS

REFERENCE:

- DPC, Fundamentals of Nuclear Reactor Engineering,page 159 ANSWER: 013 (1.00) B.

REFERENCE:

NCS PULSTAR Operations Manual, Section 4.4.3, page 4-22 ANSWER:

014 (1.00) A.

REFERENCE:

Fundamentals of-Nuclear Reactor Engineering,page 56'

DPC, ANSWER:

015 (1.00) A.

REFERENCE:

i I DPC, Fundamentals of Nuclear Reactor Engineering,pg 116-119 ANSWER: 016 (1.00) B. (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 42 A.* RX THEORY, THERMO & FAC OP CHARS

REFERENCE:

DPC, Fundamentals of Nuclear Reactor Engineering,pg 39 ANSWER: 017 (2.00) A.

REFERENCE:

DPC, Fundamentals of Nuclear Reactor Engineering,pg 146-149 ANSWER: 018 (1.00) D. REFlRENCE: DPC, Fundamentals of Nuclear Reactor Engineering,pg 89 ANSWER: 019 (1.00) D.

REFERENCE:

DPC, PULSTAR Safety Analysis, Section 13.1.1,pg 1 (***** CATEGORY A CONTINUED ON NEXT PAGE *****)

Page 43 .RX THEORY, THERMO & FAC OP CHARS A. ANSWER: 020 (1.00) A.

REFERENCE:

DPC, PULSTAR Safety Analysis, Section 13.2.1.3,pg 3 (***** END OF CATEGORY A *****)

- ~ ~ - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ Page 44

NORMAL /EMERG PROCEDURES & RAD CON B.

ANSWER: 001 (1.00) B.

REFERENCE:

NCS Administrative Controls Section 2,Sub 2.3.3.3 page 2-6 ANSWER: 002 (1.00) C.

REFERENCE:

Sub 2.9.3 Page 2-20 NCS Administrative Controls Section 2, ANSWER: 003 (1.00) D.

REFERENCE:

Sub 2.10.4 page 2-24 NCS Administrative Controls Section 2, ANSWER: 004 (1.00) C.

REFERENCE:

Sui. 10.2.1 page 2-22 NCS Administrative Controls Section 2, (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page 45 'B,:*HORMAL/EMERG-PROCEDURES & RAD CON ANSWER: 005 (1.00) A.

REFERENCE:

NCS Reactor Operating Procedures Section 3 Sub 3.4.1.2 page 3-56 ANSWER: 006 (1.00)- C.

REFERENCE:

NCS Reactor Operating _ Procedures Section 3, Sub 3.2.1.4.1.c, page 3-46 ANSWER: 007 (1.00) B.

REFERENCE:

l NCS Reactor Operating Procedures Section 3, Sub 3.4.5.2 page 3-62 ANSWER: 008 '( 3. 00). C. (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page 46 e B.- NORMAL /EMERG PROCEDURES & RAD CON ~

REFERENCE:

NCS= Reactor Operating Procedures Section 3, Sub 3.2.1.3.4 page 3-44 ANSWER: 009 (1.00) D. REFEREs!CE: NCS Tech Spec 3.2.c Bases, page 15 ANSWER: 010 (1.00) C.

REFERENCE:

NCS Tech Spec Section 2.2.1, page 10 ANSWER: 011 (1.00) A.

REFERENCE:

10. CFR 20 Section 20.101(a) (b) (1) (2), " Radiation Dose Standards for Individuals in Restricted Areas."

page 297. ANSWER: 012 (1.00) A.- (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Page 47 .B._,NoddAL/EMERG PROCEDURES & RAD CON

REFERENCE:

NCSU Emergency' Procedures 1.3.8, page 6 ANSWER: 013 (1.00) B.

REFERENCE:

NCS Tech Spec Section 3.5.2.c, page 22 ANSWER: 014 (1.00) C.

REFERENCE:

NCS Standing Order #48 ANSWER: 015 (1.00) B.

REFERENCE:

NCS Administrative Controls Section 2, Sub 2.4.3 page 2-13 -ANSWER: 016 (1.00) D. l l B CONTINUED ON NEXT PAGE *****) (***** CATEGORY l f l

o Page 48 B.*- NORMAL /EMERG PROCEDURES & RAD CON

REFERENCE:

LNCS PULSTAR Emergency Procedure Section 4.3.1.b page 1 ANSWER: 017 (1.00)- B.

REFERENCE:

NCS-Special Procedure 3.3 Fuel Handling Procedures Section 4.15 page 4 ANSWl'R: 018 (1.00) C.

REFERENCE:

NCS Special Procedure 2.6 Pulstar Operator Requalification Program Section-12.0.page 8 ANSWER: 019 (1.00) -A.

REFERENCE:

NCS Tech Specs 5.3 page 35 ANSWER: 020 (1.00) D. (***** CATEGORY B CONTINUED ON NEXT PAGE *****)

Pago 49

NORMAL /E!!ARG PROCEDURES & RAD CON

.Be -REFERENCE; NCS-Toch-Specs Section 1.14 page 2 4 (***** END OF CATEGORY D *****)

~~ ~' Page 50 PLANT AND RAD MONITORING SYSTEMS C. ANSWER: 001 (1.00) D.

REFERENCE:

Instrumentation and Control Subsection 4.1.6 page 4-9 NCS Section 4 ANSWER: 002 (1.00) C.

REFERENCE:

NCS Operating Manual Section 4 Instrumentation and Control Subsection 4.2.1 page 4-12. ANSWER: 003 (1.00) D.

REFERENCE:

NCS Operations Manual Section 8 Confinement - Heating & Ventilation System Subsection 8.2.3 page 8-6 ANSWER: 004 (1.00) C. (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

Page 51 C.' PLANT AND RAD M0llITORING SYSTEMS REFERE!1CE: NCS Special Procedure 3.4 Section 1.0 page 1 ANSWER: 005 (1.00) D. REFERE!1CE: NCS Operating Manual Section 6 Auxiliary Electrical System Section 6.2 page 6-8 ANSWER: 006 (1.00) A.

REFERENCE:

HCS Operating Manual Section 6 Auxiliary Electrical System Section 6.2.2 page 6-9 . ANSWER: 007 (1.00) B.

REFERENCE:

7 Radiation Monitoring and Radioactive Drain System NCS Sectio.1 Subsection 7.2.1 page 7-2 ANSWER: 008 (1.00) B. (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

Page 52 PLANT AND RAD-MONITORING SYSTEMS C,.

REFERENCE:

NCS Section 7 Radiation Monitoring and Radioactive Drain System = Subsection 7.2.2 page 7-2 ANSWER: 909 (1.00) C.

REFERENCE:

NCS Section 7 Radiation Monitoring and Radioactive Drain System Subsection 7.2.3 page 7-3 ANSWER: 010 (1.00) A.

REFERENCE:

NCS Section 7 Radiation Monitoring and Radioactive Drain System Table 7-1 ANSWER: 011 (1.00) B.

REFERENCE:

NCS Section 5 Water and Reactor Air Systems Subsection 5.1.3.5 page 5-7 ANSWER: 012 (1.00) A. l '(***** CATEGORY C CONTINUED ON NEXT PAGE *****) 1

Page 53 C.

PIANT AND RAD MOllITORING SYSTEMS

REFERENCE:

NCS Section 5 Water and Reactor. Air Systems Subsec 5.2.3.4 pg 5-16 AllSWER: 013 (1.00) A.

REFERENCE:

Control Rod NCS Volume TI Reactor Operator's Data Section II, Worth,page 4 ANSWER: 014 (2.00) A.

REFERENCE:

NCS Pulstar Operations Manual, Section 1, " General Information", Page 1-9 ANSWER: 015 (1.00) B.

REFERENCE:

NCS Pulstar Operations Manual, Section 9, "Experi. mental Facilities", Page 9-5 (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

Page 54 C.. PLANT AND RAD MONITORING SYSTEMS 4 ANSWER: 016 (1.00) C.

REFERENCE:

NCS Pulst r Operations Manual, Section 4, " Instrumentation and Control", Page 4-8 ANSWER: 017 (1.00) C.

REFERENCE:

NCS Pulstar Operations Manual, Section 4, " Instrumentation and Control", Page 4-18 ANSWER: 018 (1.00) B.

REFERENCE:

" Fuel Handling NCS Pulstar Special Procedures Manual, SP 3.3, Procedures", Page 3 ANSWER: 019 (1.00) D. (***** CATEGORY C CONTINUED ON NEXT PAGE *****)

r Page 55 C.' PLANT AND RAD MONITORING SYSTEMS

REFERENCE:

NCS Pulstar Operations Manual, Section 4, " Instrumentation and Control", Page 4-21 ANSWER: 020 (1.00) B.

REFERENCE:

NCS Pulstar Operations Manual, Section 9, " Experimental Facilities", Page 9-19 (***** END OF CATEGORY C *****) (********** END OF EXAMINATION **********)

t A. RX THEORY. THERMO & FAC OP CHARS Page 1 ANSWER KEY 001 B 008 D 015 A 002 B 009 B 016 B 003 D 010 A 017 A 004 D 011 A 018 D 005 D 0~2 C 019 D 006 B 013 B 020 A 007 C 014 A (***** END OF CATEGORY A *****) B. NORMAL /EMERG PROCEDURES & RAD CON [ 1 001 B 008 C 015 B l 002 C 009 D 016 B l 003 D 010 C 017 B 004 C 011 A 018 C 005 A 012 A 019 A 006 C 013 B 020 D 007 B 014 C l i (***** END OF CATEGORY B *****) l l

~ t l Page 2 PIANT AND RAD MQNITORING SYSTEMS C. ANSWER KEY 001 D 008 B 015 B 016 C 002 C 009 C 017 C 003 D 010 A 004 C 011 D 018 B 005 D 012 A 019 D 006 A 013 A 020 B 007 B 014 A (***** END OF CATEGORY C *****) (********** END OF EXAMINATION **********) 1

4 I

o

. TEST CROSS REFERENCE Page 1-S R O-E-x a m- ??? Reactor Orq anized b-y Question Number QUESTION VALUE REFERENCE 001 1.00 9000737 002 1.00 9000738 003 1.00 9000739 004 1.00 9000740 005 1.00 9000741 006 1.00 9000742 007 1.00 9000743 003-1.00 9000744 009 1.00 9000745 010 1.00 9000746 011 1.00 9000747 1 i 012 1.00 9000748 013 1.00 9000749 014 1.00 9000750 015 1.00 9000751 016 1.00 9000752 017 1.00 9000753 018 1.00 9000754 019 1.00 9000755 020 1.00 9000756 20.00 i 001 1.00 9000757 002 1.00 9000758 003 1.00 9000759 004 1.00 9000760 005 1.00 9000761 006 1.00 9000762 007 1.00 9000763 008 1.00 9000764 009 1.00 9000765 i 010 1.00 9000766 011 1.00 9000767 r 012 1.00 9000769 013 1.00 9000770 014 1.00 9000771 015 1.00 9000772 [- 016 1.00 9000773 017 1.00 9000775 018 1.00 9000776 019 1.00 9000777 020 1.00 9000778 20.00 001 1.00 9000779 002 1.00 9000780 003 1.00 9000781

IWClEAR 1RA!NotJG

1.'r*tt Cwc>! na State vn:,casy ESA

-~

==.---

Equation Sheet n S J,

C=

('F-32) g, ng: 4 1; 2 ' BE = ( Am) 932 J 4}2,ya g2); NOV 3

r=

9'C432 b-amu Rem = rad

DF N
No e'nt 6 = th c,h T IE I (t 1) 3t:

t,,,,,,= m t 2 ig

tg N=

w y* Y

UA ( h T,,,)

GAW 0.093 Y = In h h ' A

AN A'",

t,,;,,, T ,,Ae.,, T, = T,,,, h

A e ' '" '

c E, = b hE

XE bT DCFe c Dore :a t e > 7jpg s

=T ~ e 2 E = No DR

6 CE T,
T p,54 1)

= DR; ( d, ) 2 c T>= 1 1 = Jo e*Z* (Deutrons) M d, = DR; d, 1 E* y, y g.p, PH * -309IN C*] 3 2 ,,

p y, J*Jo(0.3) M gz g, N*N(k,fj)I a

o m I = I (0,5) 'un P

3, P = P (k,,,) 1 c

o 1 k,ff -2 6k oft

= No ( O. 5 ) '">

p= ett A,ff x, 2n2 SUR p,,, o, 3 4 g p, 1 F 3/2 "H' UN 26 1 SUR = A = 18 1 6 P, Prin,; - pi,,,,,,, DT dt 1 heft' P Pfinal

Pin,ej,3-b p T
ytit P k -k s

2 AP= 26.11'HP k, k* SVR = E ctt - P 3 p 8

,,=

P = P 3 Om t ,11 o CR 1 - k,f g, p, p g$ }_, o u M CR, 1-k,,,, a- ,,}}

ML20217C669

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