Text

Forwards Forms a & B W/Answers for Generic Fundamentals Exam Section of Written Operator Licensing Exam Given on 891004. P in Final Grade Column Indicates Passing Grade for Exam
	ML19325E520
Person / Time
Site:	Sequoyah
Issue date:	11/01/1989
From:	Peebles T; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Lorek M; TENNESSEE VALLEY AUTHORITY
References
	NUDOCS 8911070340
	Download: ML19325E520 (78)
	v • d • e

{{#Wiki_filter:' '

f Ulelf 8") 81 Af ts aseg Nucts AM Cs',,ULAT0nY C00MCl0N l

Cl00e1 al l { .n 1911AARIETT A ST Altf ItN. l l ATLAlvT A,GIoa01& 30893 November 1, 1989 I l Docket Nos. 50-327 and 60-322 I - i Tennessee Valley Authority i b, ATTNt Mr. M. J. Lorek i Training Manager Sequoyah Nuclear Plant l P. 0, tox 2060 Soddy-Daisy. TN 37379 j i GENTLFMEN: f On October 4,)1989, the NRC administered the Generic Fundamen Section (GFES of the written operator licensing examination to employees of f Enclosed with this letter are copies of both forms of the l your facilit;t. examination including answer keys, the grading results for your facility, and j e l copies of the individual answer sheets for each of the examinees from your facility who took the examination. Please forward the results and answer sheet to the examinees. A 'P" in the column labeled Final Grade indicates a passing grade for this examinations passing grade for the GFES is 80 percent. in accordance with 10 CFR 2.790 of the Comunission's Regulations, a copy of (- this letter and Enclosures 1 and 2 will be placed in the NRC's Public Document Room (PDR). The results for individual examinees are exempt from disclosure, therefore. Enclosures 3 and 4 will not be placed in the POR. Should you have any questions concerning this examination, please contact Mr. Paul Doyle at (301) 492-1047. l l Sincerely, { ..M j's-ThomasA.Peebles, Chief / Operations Branch i Division of Reactor Safety Enclosures 1. Examination Fom "A" witu Answers 2. Examination Fom "B" with Answers , 3. Examination Results SusInary for Facility 4. Copies of Candidates Individual Answer Sheets f D h $h h.>0 27 PNV y f i 9 w +- .,,r., .--,,w-- ..--,--r-w.--,.,. .-,..,,--.-,.c a.~ -, - -, - -.-.n- ,-,,.--,-.-..s

} ,t r i ANSWER KEY j PWR GTE (FORM A) ? 1. C. 26. A. 51. D. 76. B. 2. D. 27. D. 52. C. 77. D. 3. A. 28. D. 53. B. 78. D. I L 4. D. M 54. D. 79. B. 5. B. 30. A. 55. A. 80. C. E 6. B. 31. B. .46,-=4, 81. C. 7. D. 32. C. 57. B. 82. C. 8. C. 33. A. 58. D. 83. A. 9. C. 34. C. 59. B. 84. D. 10. B. 35. A. 60. B. 85. B. t L 11. B. 36. D. 61. B. 86. D. I 12. D. 37. C. 62. D. 87. C. 13. C. 38. C. 63. D. 88. A. h 39. B. 64. A. 89. B. 15. C. 40. D. 65. D. 90. D. 16. D. 41. B. 66. D. 91. D. i 17. D. 42. B. 67. B. 92. A. 18. C. 43. A. 68. C. 93. A. I 19. B. 44. B. 69. B. 94. B. 20. B. 45. A. 70. D. 95. A. 21. C. 46. A. '/1. C. 96. B. i 22. C. 47. C. 72. C. 97. B. 23. B. 48. A. 73. D. 98. A. 24. B. 49. D. 74. A. 99. A. 25. D. 50. A. 75. D. 100. D. Pressurized Water Reactor Aeneric Fundamentals Examination administered October 4.1989. Questions 14, 39 and 56 l were deleted. F I I l l l l 1 i 1

i s i { i ANSWER KEY l WR GFE (FORM B) i 1. D. 26. A. 51. B. 76. A. 2. A. 27. A. 52. B. 77. D. i 3. D. 28. D. 53. D. 74. A. 4. B. 29. C. 54. A. 79. D. 5. D. 30. D. 55. D. 80. C. 6. D. 31. A. 56. D. 81. B. i 82. D. 7. B. 32. D. 8. C. 33. B. 58. A. 83. A. 9. C. 34. B. 59. B. M 10. C. 35. D. 60. C. 85. B. 11. A. 36. C. 61. A. 86. D. I 12. D. 37. C. 62. C. 87. B. 13. B. 38. B. 63. A. 88. B. 14. D. 39. B. 64. D. 89. B. 15. C. 40. D. 65. C. 90. D. 16. A. 41. C. 66. C. 91. D. 17. B. M 67. B. 92. A. 18. D. 43. C. 68. D. 93. D. 19. D. 44. D. 69. B. 94. D. 20. A. 45. D. 70. B. 95. B. 1 21. A. 46. C. 71. A. 96. C. 22. B. 47. B. 72. B. 97. B. 23. A. 48. B. 73. A. 98. D. 24. B. 49. C. 74. A. 99. C. 25. B, 50. C. 75. C. 100. C. Pressurized Water Reactor Generic Fundamentals Examination administered October 4, 1989. Questions 42, 57 and 84 were deleted. i 6 b t i

0 '8 C t. UNITED STATES NOCLEAR REGULATORY COMMIS$10N PRESSL'RIZED VATER REACTOR CENERIC PUNDAMENTALS EXAMINATION I [ Please Print: Name: Facility: I ID Number: i INSTRUCTIONS TO CANDIDATE Use the answer shewt provided. Each question has equal point value. The passing grades require at least 80% on this part of the written licensing examination. All examination papers will be picked up 2.5 hours after the examination starts, i SECTION Questions % of Total Score COMPONENTS 1 43 REACTOR THEORY 44 72 THEP.M0 DYNAMICS 73 + 100 TOTALS 100 All work done on this examination is my own. I have neither given nor received aid. Candidate's Signature i l i l r i FORM A

u .s RULES AND CUIDELINES FOR THE GENERIC FUNDAMENTALS EXAMINATION f During the administration of this examination the following rules apply F (1) Print your name in the blank provided on the cover sheet of the i examination. l (2) Till in the na, of the fatiggty you are associatd O (3) rill in the ID Number you were given at registration. i i (4) Three handouts are provided for your use during the exanination, an Equations and Conversions sheet, instructions for filling out the answer sheet, and Steam Table booklets. j (5) Une only the answer sheet provided. Credit will only be given for f answers marked on this sheet. Follow the instructions for filling out the answer sheet. 6 (6) Scrap paper will be provided for calculations. (7) Any questions about an item on the examination should be directed to the examiner only. l (A) Cheating on the examination will result in the automatic forfeiture of i this examination. Cheating could also result in severe penalties. (9) Restroom trips are limited. Only ONE examinee may leave the room at a f time. In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room, i t (10) After you have completed the examination, please sign the statement on l the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination. (11) Please turn in your examination materials answer sheet on top followed by the exas booklet, then examination sids. steam table booklets, handouta and scrap paper used during the examination. (12) After turning in your examination materials, leave the examination area, as defined by r.he examiner. If after leaving you are found in the examination area while the examination is in progress, your examination l may be forfeited. i

.... - _ ~.. -. -.. I l .,s I GENERIC rWDMETAIJ EIAKINAT10N 88CT10N l SQUATIONS AND CONVI3LS10NS MANDOUT SMRET V MTIMS 4................ Cycle Efficiency = Met Werk fout) = mc AT p Emrp (in) ) 0 5 Ah SCR $/(1 K,gg) = ? I 4 UA AT CRg (1 K,gg)g CR I1

Koff)2

= = 2 St'R = 26.06/t M 1/(1. K,gg) CR /CR = = g 0 r i i 26.06 (1,gg p) (1 K,gg)n j SyR = M = i (#. p) (1 K,gg)g r i sm(t) P,10 sDM r (1. X,gg) Aeff = i r,.(t/') W i r Pwr = = g i o (1*/s) + [ d p)/A

I 1 /(# * #)

] t = eff (X,gg. 1)A,gg 1* 1 x 10 5.econd. [ p = Ax,g,/x,gg A,,, = 0.1..cond. 1 = r l i CONTERS10NS l 10 2.21 lba 1 Curie 3.7 x 10 dps 1 kg = = 1 i 3 6 l 1 hp 2.54 x 10 STU/hr 1 Mw 3.41 x 10 STU/hr = 1 BTU 778 ft.lbf 'F 9/5 'c + 32 = = o 'C 5/9 ('F - 32) = .. m. m

c-o i-e FRESSUR11ED WATER REAC1tIR CDIERIC FUNDAMDf7AIA EXAMINATICII FORM A QUESTION: 1. The primary purpose of a pressure relief valve is to: A. maintain system flow. 8. maintain system pressure. C. maintain system integrity. D. maintain system temperature. QUESTION: 2. When a discharge valve is opened to atmosphere, the pressure on the upstream side of the valve will: A. remain the same, and the pressure on the downstream side will increase. B~ increase, and the pressure on the' downstream side will remain the same. C. remain the same, and the pressure on the downstream side will decrease. D. decrease, and the pressure on the downstream side will remain the same. QUESTION: 3. The function of a valve backseat is to: A. isolate system pressure from the packing and stuffing box to minimize packing leakage. 8. isolate system pressure from the packing and stuffing box for the purpose of valve repacking. C. provide a backup means of flow isolation in the event c! primary seat leakage. D. provide a backup means of flew isolation in the event of a pipe break." i FORM A Page 1 of 35 (

', 7 c , e PRES $URIEED WATER REACTOR CDfERIC PVNDANDf7A1.8 RlKANIMATION i FORM A i i QUESTION: 4 After manually positioning a motor. operated valve, how is the valve actuator i re engaged? r A. Actuation of the torque switch l l 5. Manually pulling up on the manual declutch lever C. Actuation of either the full.open or full closed limit switch D. Actuation of the valve actuator motor in either the open or close direction i QUESTION: 5. To verify the position of a closed manual valve, the operator should operate the valve: A. to the fully open position, then reclose it using normal force. l B. in the closed direction using normal force, i C. in the open direction until flow sounds are heard, then close the valve using manual force. t D. in the closed direction until it stops, then close it an addist<..nal one. half turn using normal force. QUESTION: 6. l l D3nsity compensation is used in flow instruments to change _ to A. mass flow rate, volumetric flow rate f B. volumetric flow rate, mass flow rate l C. fluid pressure, volumetric flow rate D. differential pressure, mass flow rate L f FORM A Page 2 of 35

[ l'e' PRESSURIF.ED WATER REACTOR CENERIC PUNDAMENTt.iA EKANIMATION PURN A j V i + QUESTION: 7. i-If the liquid flowing through a liquid flow rato sensor contains entrained voids (gas or stean), indicated flow rate will be: A. erroneously high. l B. erroneously low. t C. unaffected. j t D. fluctuating. t QUESTION: 8. [ If the equalizing line on a differential pressure (D/P) flow detector is I opened, the flow detector indication vill: [ ,A. increase slightly, i B. decrease slightly, 1 C. 30 to zero. l D. not change. l i i QUESTION: 9. l I Flow detectors (such as an orifice, flow nozzle, and venturi tube) seasure i flow rate using the principle that flow rate is: j A. D111CTLY proportional to the dif ferential pressure. B. INVERSELY proportional to the differential pressure. [ I I. P C. DIRECTLY proportional to the square root of the differential pressure. [ l I l-D. INVERRE12 proportional to the square root of the differential pressure, t 1 l +. ? t t F f b FORM A Page 3 of 35 t

r-PRESSURIED WATER REACTOR CDtERIC WNDARDfTALS EKANIMATION FOP,M A 's QUESTION: 10. The pressure differential between a reference leg and a variable les is: A. DIRECTLY proportional to the htight of the variable leg. B. INYtt1ELY proportional to the height of the variable leg. C. Dill &ILY proportional to the density of the reference leg. l D. INVIRSELY proportional to the temperature of the reference leg. i QUESTION: 11. i I If the reference leg of a differential pressure level indicator experiences high ambient temperature, indicated level will: l E A. read less than actual level. B. read greater than actual level. C. equal the actual level. D. slowly decrease to zero. l QUESTION: 12. The level indication for a reference leg differential pressure level l instrument will fail ]AW as a result of: A. a break on the reference leg. l B. a rupture of the diaphragm in the differential pressure cell. C. the reference leg flashing to steam. D. a break on the variable leg. FORM A Page 4 of 35

4 d PRES $URIEED WATM REACTOR CMRIC PUNDMLENTALS ERANIMATIOlt i PORN A l QUfSTION: 13. A resistance temperature detector (UTD) operates on the principle that the j change in electrical resistance of. I A. two dissimilar metals is p11ECTLY proportional to the temperature change neatured at their junction. B. two dissteilar metals is INVERSELY proportional to the temperature change [ measured at their junction. C. a metal is PIRECTLY proportional to its change in temperature. D. a metal is INVERSELY proportional to its change in temperature. t QUESTION: 14. i Two differential pressure level transmit';ets are installed in a large tank. If transmitter I is calibrated at 200 'F and transmitter II is calibrated at 100 'F, then at 150 'F' l A.' transmitter I will read greater than transmitter II. -y B. transmitter II will read greater than transmitter I. C. transmittar I and II will read the same. D. it is impossible to predict how either transmitter will respond, i I QUESTION: 15. Scintillation detectors operate on the principle of: A. photodisintegration. B. photokinesis. C. photomultiplication. D) photoionization. u FORN A page 5 of 35

[ i L l M FRESSUll1EED WATER REACTTML CENERIC MDtDAMENTALS EXAMINATION FORM A l f !i QUESTION: 16. 1 A BF3 proportional counter detects both neutrons and gammas. Which of the i following best describes the method used to eliminate the gamma contribution l' from the detector output? l A. Two counters are used, one sensitive to neutron and gamma and the other f sensitive to gamma only. The outputs are electrically opposed to cancel i p the gamma. induced currents and yield a neutron only signal for indication l use. l i B. The BF3 proportional detector records neutron flux of sufficient l intensity that the gamma signal is insignificant compared to the neutron l' signal and yisids a neutron on1;r signal for indication use. f C. Camma induced detector pulses are of insufficient width to generate a si nificant los. level amplifier output. Neutron pulses are the only ones B ? with sufficient. width to yield a neutron.only signal for indication use. D. Neutron induced current pulses are significantly larger than those from { gamma. The detector signal is applied to a circuit which filters out the smaller gamma pulses yielding a neutron only signal for indication use. QUESTION: 17. 1 The difference between the setpoint and thw measured parameter its an automatic flow controller is called: A. gain. B. bias. C. feedback. D. error. QUESTION: 18. Y A controller's output is typically insufficient to accurately drive a valve actuator. To overcome this problem, a control loop normally employs: A. a lead /la5 unit. B. a regulator. C. a positioner. A D. an aeplifier unit. 8 FORK A Page 6 of 35

c PRESSURIEED WATR REAC1tlR CBRIC FUWhMUMTALS RAMINAT10h PORM A I QUESTION: 19. f I a Why must an operator pay particular attention to auto / manual valve controllers l 1 eft in the manual mode? t A. The manual valve control is usually not stable compared to the automatic mode. [ B. The valvo position will no longer respond to changes in system parameters. l C. The controlled parameters will no longer be controlled by the valve Y position. D. the valve can only be operated locally during this time. f QUESTION: 20. Whe.t precautions sust be observed when transferring a valve controller from the sutomatic mode to manual mode of control? A. Ensure that the proper offset is established between the automatic mode and manual mode. B. Ensure that the valve controller output signals are matched between automatic mode and manual mode. l Ensure that the valve controller stabilizes in the automatic mode before f C. i [ completely transferring to the manual mode of control. l D. Ensure that the automatic valve controller signal is increasing before transferring to manual woda of control. l l QUESTION: 21. l An indication of centrifugal pump cavitation is: L l A. pump motor amps pegged high B. pump discharge pressure indicating zero. l C. pump motor amps oscillating. D. pump discharge pressure indicating shutoff head. O l FORM A Page 7 c.f 35

e PRESSURIZED WATER REACTOR CDfERIC PUNDMENTA1A EKAMINATION FORM A QUESTION: 22. The ters shutoff head' for a centrifugal pump indicates that it is pumping at: A. maximum capacity and minimum discharge head. 9 B. maximum capacity and maximum discharSe head. C. minimum capacity and maximum discharge head. D. minimum capacity and minimum discharge head. QUESTION: 23. Operating a motor driven centrifugal pump for extended periods of time with no flow through the pump will cause: A. pump failure from overspeed. B. pump failure from overheating. C. motor failure from overspeed, j D. motor failure fr'on overheating. 4 i .\\ QUESTION: 24. SHUTTING the discharge valve on an operating centrifugal pump will cause the NO10R AMPS to and the pump DISCHARGE PRESSURE to A. increase, increase i i B. decrease, increase C. increase, decrease D. decrease, decrease l 1 l FORM A Page 8 of 35 -. ~, _.

Lo '4 c 1 E PRES $1RIEED WATER REAC70R CENERIC FUNDMENTALS EKANT4AT10N j L PORN A l l [ QUESTION: 25. .If the speed of a positive displacement pump is increased, the available net i positive suction head (NPSH) will and the probability of cavitation will i l' A. increase, increase I B. decrease, decrease [ l C.- increase, decrease I D. decrease, increase i i QUESTION: 26. Reactor' coolant pump motor amps will if the rotor is LQGEED and [ g the motor speed will if the rotor AHEARI. i A. increase, increase-i B. increase, decrease C. decrease, increase D. decrease, decrease f I I i L QUESTION: 27, 1-p -If the generator bearings on a motor generator overheat then: 1 l A.. the generator voltage will increase, s B. the generator windings will overheat. C. the motor current will decrease. i' D...the motor windings will overheat. t 1 4 i FORK A Page 9 of 35

' O~ L be ,o 1. PRESSURIEED WATER REACTOR GENERIC FUNDAMENTALS EKAMINATION PORM A r l . QUESTION: 28. If the speed of a variable speed centrifugal pump is increated to cause pump j ,'L.. flow rate to double, pump motor current will: i or. A. remain constant. n B. increase two. fold (double). C. increase four fold. D. sneroase ei ht. fold. S QUESTION: 29. The starting current in an A.C. motor is significantly higher than the J full load running current because: ) A. ' starting torque is lower than running torque, j 1 B. starting torque is higher than running torque. i C. rotor current during start is higher than running current. I D. rotor current during start is lower than running current. ] l [ l .i QUESTION: 30. i t The number of starts for an electric motor in a given period of time should be limited because: l A. overheating of the windings can occur. 1 t-B. excessive torque is generated during motor start. C. running current is such higher than starting current. D. motors are normally started under full load conditions. ) v l FORM A Page 10 of 35

FRESSURIEED WATER REACTt* CENERIC FUNDAMENTALS EXAMINATION FORM A QUESTION: 31. i Sevete stress in a mechanical component, induced by a sudden, unequally I distributed temperature reduction is a description of: 1 A. heat stress. j B. thermal shock. i C. thermal strain. i D. heat strain. ) j QUESTION: 32. Tube fouling in a heat exchanger causes heat transfer to decrease by: 1 A. reducing fluic' velocity on the shell side of the exchanger. B. increasing flow rate through the tube side of the exchanger, i C. reducing the overall (total) heat transfer coefficient. D. increasing the overall (total) heat transfer coefficient. ) QUESTION: 33. j t j Borated water is flowing through the tubes of a heat exchanger being cooled by fresh water. The shel.1 side pressure is less than tube side pressure. What will occur as a result of a tube failure? I A. Depletion of borated water inventory. 1 B. Depletion of cooling water inventory, q C. Dilution of the borated water system. 1 D. Shell pressure will decrease. i M*M A Page 11 of 35

. = _ t y PRESSURIZED WATER REACTt* CDilRIC PWDAMENTALS EKAMINATION f l FORM A l F QUESTION: 34. j What in the reason for bypassing a desineralizer due to high temperaturet i A. Resins expand and restrict flow through the desineralizer. B. The demineralizer decontamination factor is dramatically increased, t C. Organic compounds used as resins will decompose. l D. The creation of preferential flowpath through the demineralizer will f occur. QUESTION: 35. In the event of a system crud bur st, what adverse effect does the crud burst I have on domineralizer operation? A. Increases pressure drop across uenineralizer B. Increases flow rate through desineralizer C. Increases desineralizer outlet conductivity ) D. Increates domineralizer inlet pH i QUESTION: 36. Boron concentration in the reactor (primary) coolant system has been decreasing steadily at approximately 10 ppa per hour while using the deborating denineralizer. After several hours, the rate decreases to 2 ppa per hour. What is a possible cause for the change in deboration rate? l A. Temperature of the coolant passing through the desineralizer has decreased. B. pH of the coolant has increased significantly. C. Flow through the deborating resins has increased sharply. l D. Deborating resins have become boron saturated. L FORM A Page 12 of 35

c* PRESSURIEED WATER REACTOR CDIERIC FVWDAMENTA12 EKAMINATION FORN A QUESTION: 37. To de.energine a component and its associated control and indication circuits, the component circuit breaker should be: A. racked in and tagged in open position. L B. racked in and tagged in closed position. C. racked out and tagged in racked out position. D. in the test position and tagged in test. [ QUESTION: 38. l' To ensure reliable local breaker indication is being provided the __ l must be reset after breaker operation. A. OPEN/ CLOSED mechanical flag B.. OPEN/ CLOSED indicating lights C. Overcurrent trip flag D. Spring CHARGE /DISCRARGE flag i QUESTION: 39. A circuit breaker thetaal overload device: L l A. compares actual current to a fixed overcurrent setpoint that is equated i to temperature and actuates a trip relay. B. when subjected to 1.igh current, overheats and actuates a circuit interrupting device. C. senses operating equipment temperature and trips protective circuits at preset limits. l D. is an induction coil that produces a secondary current proportional to the primary current. i t l l FORN A Page 13 of 35 i

PRI,$5URIZED WATER RFACTOR CDERIC WNDAMENTALS EKAN! NATION i PORN A l QUESTION: 40. Loss of circuit breaker control power will cause: A. breaker line voltage to be zero regardless of actual breaker position. l B. the remote breaker position to indicate closed regardless of actual breaker position. C. inability to operate the breaker locally and remotely. D. failure of the close spring to charge following local tripping of the i breaker. i f QUESTION: 41. If a de. energized bus is not unloaded prior to closing the output breaker of a three phase generator onto the bus, then: A. an overvoltage condition will occur on the bus. l B. an overcurrent condition will occur on the generator. C. an overvoltage condition will occur between generator phases. D. benerator undervoltage relay actuation will occur, i l i QUESTION: 42. l Which of the following statements is correct concerning the use of disconnect switches? I A. Disconnects should be limited to normal load current interruption. l B. Disconnects may be used to isolate transformers in an unloaded network. C. Disconnects are similar to oil circuit breakers, but are manually oporated. D. Disconnects must be closed with caution when under load because of l possible arcing. l l' FORN A Page 14 of 35 . ~

n' e .I f PRESSURIEED WATER REACTOR CENERIC FUNDAMENTA1J ERAMINATION l FORN A i ,.1 l' b l l QUErtION: 43. j t i Closing a generator output breaker with the generator frequency such aess than i-grid frequency will cause the generator to trip on: f -A. reverse power. S. ove rvoltage. C. overcurrent, j l' D. overspeed. t e r QUESTION: 44. The operator has just pulled control rods and changed the effective multipli. cation factor (K,gg) from 0.998 to 1.002. The reactor is: A. prompt critical B. supercritical C. exactly critical [ D. suberitical i 9 i t t i t i i L l-l' l-FORM A Page 15 of 35 1

I I PRESSURIEED WATER REACTOR C W Dt1C FUNDAN WTALS EKANIMATION f FORN A j QUESTION: 45. The ratio of the number of neutrons in one generation to the number of i neutrons in the previous generation is the: I A. effective multiplication factor B. fast fission factor C. neutron non leakage factor D. neutron reproduction factor QUESTION: 46. Reactivity is defined as the: A. fractional change in neutron population per generation. ] B. number of neutrons by which neutron population changes per generation. 1 C. rate of change of reactor power in neutrons per second. D.- change in the number of neutrons per second that causes a fission event. 1 QUESTION: 47. A given amount of positive reactivity is added to a critical reactor in the source (startup) range. The amount added is less than the average effective i delayed neutron fraction. Which of the following will have a significant effect on the magnitude of the stable startup rate achieved for this addition? l i A. Prompt neutron lifetime B. Fuel temperature coefficient C.. Average effective decay constant i D. Moderator temperature coefficient l FORN A Page 16 of 35

,1 ' '.. t.; i s FRESSURIEED WATER REACTOR CINERIC' PWDMtENTALS EKAMINATION FORM A l QUESTION: '48. t i Over core life the production of plutonium isotopes with delayed neutron fractions than uranium delayed neutron fractions will cause 'l reactor power transients to be near the end of core life, e l I A. less, faster l B. less, slower i 1 C. greater, faster D. greater, slower w QUESTION: 49. An' installed neutron source: i A. maintains the production of neutrons high enough to allow the reactor to j achieve criticality. B. provides a means to allow reactivity changes to occur in a suberitical reactor. i C. generates a sufficient neutron population to start the fission process I and initiate suberitical multiplication. l l- - D. Provides a neutron level that is detectable on the source range nuclear L instrumentation.- QUESTION: 50. Why does increasing reactor coolant boron concentration cause the moderator L temperature coefficient to become less negative? l A. Reactor coolant temperature increases result in a larger increase in the l thermal utilization factor. l B. Reactor coolant temperature increases result in an increase in the resonance escape probability. I' C.- Reactor coolant temperature increases result in an increase in the total l' non leakago probability. l D. The change in resonance escape probability dominates the change in the thermal utilization factor. 1 IVRM A Page 17 of 35

d s. \\ MtE55URIZED WATER REACEMt CENERIC FUNDAMENTALS EKAMINATION FORM A QUESTION: 51. Why does the fuel temper.iture (Doppler) coefficient becomes less negative at higher fuel temperatures? A. As reactor power increases, the rate of increase in the fuel temperature diminishes. B. Neutrons penetrate deeper into the fuel, resulting in an increase in the fast fission factor. C. The amount of self. shielding increases, resulting in less neutron absorption by the inner fuel. D. The amount of Doppler broadening per degree change in fuel temperature i' diminishes. QUESTION: 52. A reactivity coefficient measuras change while a reactivity defect (deficit) measures a change in reactivity due to a change in the measured parameter. A. An integrated, total B. A rate of, differential C. A differential, total D. A total, differential i QUESTION: 53. i During power operation, while changing power level, core reactivity is affected most quickly by: A. boron concentration adjustments. B. power defect (deficit), i t C. xenon transients. D. fuel depletion. FORM A Page 18 of 35

3 n.- t, ,g f-PRESSURIZED WATER REACTOR CENERIC IVNDAMENTALS ERAMINATION IDRM A QUESTION: 54. 1 As moderator temperature incresses, the magnitude of differential rod (CEA) worth increases because: A. decreased moderator density causes more neutron leakage out of the core. 1 B. moderator temperature coefficient decreases, causing decreased competition. C. fuel temperature increases, decreasing i.eutron absorption in fuel, j ~ D. decreased moderator density increases neutron migration length, j QUESTION: 55. i Control rod (CEA) bank overlap: A. provides a more unifora differential rod (CEA) worth and axial flux i distribution, B. provides a more uniform differential rod (CEA) worth and allow dampening i of Xenon. induced flux oscillations. C. ensures that all rods (CEAs) remain within the allowable tolerance between their individual position indicators and their group counters and to ensure rod (CEA) insertion limits are not exceeded. D. ensures that all rods (CEAs) remain within their allowable tolerance be tween individual position indicators and their group counters and to provide a more uniform axial flux distribution. t QUESTION: 56. The basis for the maximum power density (kw/ft) power limit is to: A. prevent fuel clad melt. i I l B. prevent fuel pellet selt. C. limit bulk coolant temperature. l D. prevent nucleate boiling. l FORM A Page 19 of 35

i g l PRESSURIZED WATR REAC1CR GENERIC PWDAMENTALS EXAMINATION FORM A i 1 QUESTION: 57. j h The control rod insertion limits are power level dependent because the asgnitude of: ) L i A. control rod worth decreases as power increases. l B. power defect increases as power increases. C. Doppler (fuel temperature) coefficient decreases as power increases. D. moderator temperature coefficient increases as power increases. QUESTION: 58. Fission products that have substantial neutron capture cross sections are: A. excited fission products. B. fission product daughter. C. radioactive fission products. D. fission product poisons. i QUESTION: 59. Following a reactor trip from sustained high power operation, Xenon.135 i concentration in the reactor will: A. decrease because Xenon is produced dirJctly from fission. L B. increase due to the decay of Iodine already in the core. C. remain the same because the decay of Iodine and Xenon balance each other out. decrease immediately, then slowly increase due to the differences in the D.. half lives of Iodine and Xenon. l l l 1 l l l l l l FORM A Page 20 of 35

i '*4, ^) PRESSUK1EED WATER REAC1tlR CDfBLIC FUNDAMENTALS EXAMINATION f FORM A i ' tu QUESTION: 60. l Following a steactor trip from sustained high power operation, the major i ^ Xenon.135 r',aoval process is. A. ion exchange, i n' beta decay. j i C. neutron capture. l D. alpha' decay. ) l h QUESTION: 61. j k j A reactor has been operating at 50 percent power for 7 days when power is l. ramped to 100 percent over a four hour period. The new equilibrium Xenon value will: A. be twice the 50 percent value. { t B. be less than twice the 50 percent value. l C, be more than twice the 50 percent value, j D. remain the same sit.ae it is independent of power. l QUESTION: 62. Slow changes in axial power distribution in a reactor that has operated at a t steady. state' power for a long time can be caused by: l A. , Xenon peaking. l' B. Xenon override. C. Xenon burnup. p l Xenon oscillation. D. L i y l P 1 l. FORM A Page 21 of 35

y .i i n .3 ., ;.l-- p s. 3 y PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKANINATION f N" [ 1 . 70RM A t sc, ' (' QUESTION: 63, g., f - T7 k*r .A reactor.that.has' bee' q. crating at rated power for about two weeks reduces i power to 50 percent. Xe t3f vill reach a new equilibrium condition in V hours. m. A. 8 to 10 hours- ? N

B.
20 to 25 hours q..

y 4-W; C. 30 to 35 hours s s F D. 40 to 50 hours. a QUESTION: 64. l EA The: reacter is near the end of its operating cycle..In order to stay . critical, power and temperature have been' allowed to "coastdown." Why is boron no longer used to compensate for fuel' depletion? A. 1Borou concentration. approaches zero and requires excessive amounts of water to' dilute. .B. The differential boron. worth has decreased below its useable point. The boron in the coolant has.been depleted due to neutron absorption. t j D. "Coastdown" is preferred due to fuel conditioning limitations, b -QUESTION: '65. While withdrawing control rods during an approach to criticality, the count .r rate doubles. What will occur if the same amount of reactivity that caused the first doubling is added again? 'A. Count rate will increase slightly. B.~ Count rete will double. C. The reactor will remain suberitical. D. The reactor will be critical or slightly supercritical. I t 4 iI L PORN A Page 22 of 35 < r$ 't .. ~

,a ,e 4, e M..i $ -{ O[ty $, [", PRESSURIZED WATER REACTOR CENERIC FWDAMENTALS EXAMINATION 1 - e FORM A kj'y " QUESTION:" 66. 1 i .In a reactor with a source, a non.changin5 neutron flux over a few minutes is [ g....i. ' indicative of criticality or: .a f y A,- the point of adding heat. h, , B.. supercriticality. .t 'C. .suberiticality. lj ..D... equilibrium suberitical count rate. 4 Ig, 'i S QUESTION:. 67. At EOL,. critical rod (CEA) position has been calculated for a reactor startup four hours after a' trip from 100 percent power equilibrium conditions. The t i actual critical rod (CEA) position will be 14WER than the predicted critical

rod (CEA)' position'if

r .A. the startup'is. delayed until eight hours after the trip. B. the steam dump pressure setpoint is lowered by 100 psi prior to reactor startup. ? C. ' actual boron concentration is 10 ppa more than the assumed boron { concentration. 4 D. 'one control rod (CEA) remains fully inserted during the approach to criticality. 1 I QUESTION: ' 68. L' criticIN - 0.985, how much reactivity must be added to make the reactor With k A. .1,480 pcm (1.48% delta k/k) B. 1,500 pcm (1.50% delta k/k) C. 1,520 pcm (1,52% delta k/k) D. 1,$40 pcm (1.54% delta k/k) 4 FORM A Page 23 of 35 m, N. - -, - - ~.. -,..

1 (p a, g,- A PRESSURIZED. WATER REACTOR CENERIC WNDAMENTALA < EKAMINATION 4 FORM A .c l QUESTION:- 69. If, during a reactor startup, the startup rate is constant and positive i without any further reactivity addition, then the reactor is. o A. critical.- B. supercritical. f-C. subcritical, D. prompt critical. c. 4 ' QUESTION:,70. Given a eritical' reactor operating below the point of adding heat. What J reactivity ~ effects are associated with reaching the point of adding heat? A. There are no reactivity effects since the reactor is critical, t ! B. The increase in fuel temperature will begin to create a positive s reactivity effect. C. The decrease 'in fuel te'aperature will begin to create a negative reactivity effect. 1 ;. D. The-increase in fuel temperature will begin to create a negative 4 reactivity effect. l y QUESTION:. 71. - Shortly after a reactor trip reactor power indicates 0.5 percent where a stable negative SUR is' attained. Reactor power will be reduced to 0.05 percent in approximately seconds. i. l ~. ' 360-A B. 270 I it-l',

C.

180 [y D '.- 90 FORN A Page 24 of 35

n 3

/'

Eg. zy . e' ..'o., T-c i .e> 5 g PRESSURIZED WATER REACTCR CENERIC FUNDAMENTALS EKAMINATION f-y; 3 FORN A t,:;:,' .i.. .-QUESTION: 72. I' The major reason boron is used in a reactor is to permit: l' 'l A. .a reduction'in the shutdown margin. .an increase in-the. amount of control rods (CEAs) installed. B. C. an increase in. core life. 1 L D. a reduction in..the effect.of resonance capture. i l :~ \\ H I i 4-t.. I I* l-

1. '

1l i i l il l-l s I t FORM A Page 25 of 35 s. 'O

i m.

' g

.y, !.., j y ',- - 1 \\ gm PRESSURIZED WATER REAC'!DR CENERIC FUNDANENTALS EXAMINATION L FORM A i QUESTION: '73. i f> } An atmospheric pressure of 15 psia equals: c m j A, -30 psig. F' .B. 15 psig. C. '5'psig. D. O psig. i s, e tc QUESTION: 74, Condensate depression is defined as: ,q'= .A.- cooling the condensate below its saturation temperature, u y 3 B. 'asintaining'the condentsate at a constant temperature throughout the sys tem.; + ? C.. ensuring that'the condensate is below the level of the hotwell pumps. l . 33-D. - cooling the condensate to the point of saturation, i QUESTION: 75. 1 What 1s the reactor coolant system subcooling for Tave - 400*F and pressurizer pressure: 1,000 psia? A. 75'F' .c B. .100'F-1, L' C. 125'F D. 145'F l l, l' l'.' l 1' 1. l: l l l FORM A Page 26 of 35 i<; -'I-' ..,,.,w..

El 3 PRESSURIZED WATER REACTOR CENERIC PtJNDAMENTALS EKAMINATION l FORN A n QUESTION:. 76. The plant ia maintained at 2,000 psia with' a pressurizer temperature of 636'F. 4 A pressurizer safety relief valve is leaking to a collection tank which is ' being held. at 10 psig. What is the temperature of the fluid downstream of the relief valve? q 1. 280'F B. 240*F .C. 190'F D. 170*F i-QUESTION: 77. j l l+ overall plant efficiency will DECREASE if: A. the steam quality is increased by removing moisture from the steam prior to entering'the turbine. B. the temperature of the feedwater entering the steam generator is increased. C. 'the amount of-condensate depression (subcooling) in the main condenser is decreased. U t D. the. temperature of the steam at the turbine inlet is decreased. [ QUESTION: 78. ~ J The possibility of a water hammer is MINIMIZED by: -A. changing valve positions as rapidly as possible. B. starting centrifugal pamps with the discharge valve fully open. C. starting positive displacement pumps with the discharge valve closed. D. venting systems prior to starting centrifugal pumps. FORM A Page 27 of 35 i. 1

I r Bn c

PRESSURIEED WATER react 0R CENERIC MINDAMF*fTA13 EXAMINATION

.j h/ ' ' ~ 4 l'- FORM A .P F ' QUESTION:'.79. p,

s ll Cavitation in an operating pump may be caused by:

f"' I-A.. lowering the suction temperature. 'l B. throttling.the pump' suction valve. ) j.. F F C. -throttling the pump discharge valve, j i s D. increasing the pump (3; i+ rge pressure. b i QUESTION: 80. ci. The piping system pressure change caused by suddenly stopping fluid flow is referred to'as: E A. cavitation. B. shutoff head, t. I C. . water hammer, D.

flow head, a

' 'g .g. [ S- -QUESTION: 81. If a flow measuring instrument is HQI density corpensated, then indicated mass L flow rate will be: u A the same as-actual mass flow rate with a change in temperature of the L fluid. ,V B. greater than actual mass flow rate with a decrease in temperature of the H J fluid. C. less than actual mass flow rate with a decrease in temperature'of the i> fluid. "4 D. less than actual mass flow rate with an increase in temperature of the fluid. l ', i FORM A Page 28 of 35 i,

F it. ) PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION t l FORM A QUESTION: 82. i J, Operating two pumps in parallel instead of operating a single pump will result in: A. a large increase in system head and the same flow rate. B. the same system head and a small increase in flow rate. C. a small increase in system head and a large increase in flow rate. D. a decrease in system head and a large increase in flow rate. QUESTION: 83. Excessive amounts of entrained gases passing through a single phase (liquid) heat exchanger is UNDESIRABLE because: A. flow blockage can occur in the heat exchanger. B. the laminar layer will increase in the heat exchanger. C. the heat transfer coefficient will increase in the heat exchanger, D. the temperature difference across the tubes will decrease through the heat exchanger. l QUESTION:

84..

In a two loop pressurized water reactor, feedwater flow to each steam l '. ' generator is 3.3 x 10 lba/hr at an enthalpy of 419 BTU /lba. The steam exiting each steam generator is at 800 psia with 1006 steam quality. Ignoring blowdown and pump heat, what is the core thermal power? l t i A. 3,411 MWt i, B. 2,915 MWt C. 2,212 MWt D. 1,509 MWt FORM A Page 29 of 35 .s.

(; s. i :.. g 9 h-PRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIJ EKAMINATION ' j FORM A QUESTION: 85. i Why does nucleate boiling improve heat transfer in the core? i A. The formation of steam bubbles at nucleation sites on the fuel clad l allows more heat to be transferred by conduction. L B. Heat is removed from the fuel rod as both sensible heat and latent heat of vaporization, and the motion of-the steam tubbles cause rapid mixing of the coolant. C. Heat is removed from the fuel rod as both sensible heat and latent heat L of condensation, and the heat is transferred directly to the coolant by radiative heat transfer, D. The formation of steam bubbles at nucleation sites on the fuel clad reduces coole.at flow in that area and allows more heat to be transferred k by convection. QUESTION: 86. Subcooled nucleate boiling is' occurring along a heated surface. The heat flux is then increased slightly. What will be the effect on the delta T between the surface and the fluid? A. Large increase in' delta T because of steam blanketing B. Large increase in delta T causing radiative heat transfer to become p significant C. Small increase in delta-T because of steam blanketing D. Small increase in delta T as vapor bubbles form and collapse \\ L l. QUESTION: 87. What parameter change would move the plant farther away from the critical heat flux? A. Decrease pressurizer pressure B. Decrease reactor coolant flow C. Decrease reactor power D. Increase reactor coolant temperature FORM A Page 30 of 35

i (?', '!* $1 PRESSURIZED WATER REAC'It)R CENERIC WNDAMENTALS U/MINATION 'I FORM A ) ^ QUESTION: 88. Film boilin6 is:. w,' A. heat transfer through a vapor blanket that covers the fuel cladding, h B. heat transfer being a:complished with no phase change. C. the most efficient method of boiling heat transfer. D. heat transfer through an oxide film on the cladding. QUESTION: 89. f The departure from nucleate boiling ratio (DNBR) is defined as: i A. the actual heat flux divided by the critical heat flux at any point along a' fuel rod. B. the critical heat flux divided by the actual heat flux at any point along [ a fuel rod. C. the core thermal power divided by the total reactor coolant mass flow rate. D. the number of coolant channels that have reached DNB divided by the r L number of coolant channels that are subcooled. 1 1 ,m QUESTION: 90. .The' reactor coolant subcooling margin vill be DIRECTLY REDUCED by: (Evaluate each change separately.) A. increased pressurizer pressure. B. increased pressurizer level. l C. increased reactor coolant flow. D. increased reactor coolant temperature. FORM A Page 31 of 35

PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA13 EXAMINATION' i FORM A l QUESTION: 91. 'i Maximizing the elevation difference botvsen the core thermal center and the steam generator thermal centers and minimising flow restrictions in the reactor coolant system (RCS) piping are plant designs to: -A. -minimize the reactor coolant system volume. jg. B. maxiafze the reactor coolant system flow rate during forced circulation. C. ensure a maximum RCS loop transit time. D. ensure RCS natural circulation flow can be established. O s., QUESTION: 92. i l' With the RCS subcooled and all RCPs stopped, the natural circulation flow rate will NOT be affected by an 1 eresse in the: A. reactor coolant pressurn increase. B. time after reactor trip. /< C. steam generator level increase. L D. steam generator pressure decrease. QUESTION: 93. If departure from nucleate boiling (DNB) is reached in the core, the surface l temperature of the fuel clad will: 6 - A. increase rapidly. B. decrease rapidly. C. increase gradually. D. decrease gradually, b FORM A Tage 32 of 35 s

m y -.. t s PRESEURIZED CATER REAC1VR CENERIC FUNDAMENTALS EIANIMATION T< FORM. A 4 r o QUESTION: 94. if the reactor.is operated within core thermal limits, then: 'A. plant thermal efficiency is optimized. g-B. fuel cladding. int *6rity is ensured. s C. Pres.7urized thermal shock will be preventsd. -D. Reactiv v,essel thermal stresses will be minimized. Yh. QUESTION: 9!. rast nedtron irradiation of the reactor vessel results in stresses within the vessel metal, thereby the Nil Ductility Transition-l Temperature. 1 A, increased.-incr$esing (k .s i B. increased, decreasing 1 C. decreased, increasing D. decreased, decreasing QUESTION: 96. The likelihood of brittle fracture failure of the reactor vessel is REDUCED 9 'by: A. increasing vessel age. B. reducing vessel pressure. C. reduaing vessel temperature. i D. reducing gamma flu.t exposure, j FORM A Page 33 of 35 't ~.e-- a

\\- w. PRESSURIZED WATER REACTOR CENERIC R)NDAMENTAIE EXANINATION q e h QUESTION:,97. g. )$ 'J ' Pressure strehs on the reactor vessel wall is: A. cospressive across the entire wall. B. tensile across the entire wall. o '( 'C. tensile at the inner wall, compressive at the outer wall. D, compressive at the inner.all, tensile at the outer wall, t -QUESTION: 98. j. The nil-ductility temperature is that temperature: l L A. - below which the probability of brittle fracture significantly increases. s where failure stress becomes greater than the yield stress of the metal. B, C. below Ehich the probability of plastic dnformation significantly. increases. D. below which the yield stress of the metal is hi her than the critical B ' fracture stress. i k -QUESTION: 99. Pressurized thermal shock could most. likely'bo, a concern during: A. an uncontrolled cooldown followed by a rapid repressurization. B. an uncontrolled depressurization followed by a rapid repressurization. I an uncontholled cooldown foiloved by a rapid depressurization. V C. D. an overpressurization from a low temperature, low pressure cordition. } i, \\ s FORM A Page 34 of 35 t.

c. ,g i- - l, 7 f., *.' .s y PRESSURIZED WATER REACTOR CENERIC FUNDAMENTA1J EKAMINATION j FORM A. ) I t QUESTION: 100,- f. Iy During a ' severe overcooling transient, a major concern to the operator is: i 9.l A. accelerated zirconium hydriding. B. loss ~of reactor vessel water level. C.. loss ofc reactor coolant ptump net positive suction head. { s D. brittle fr'acture of the reactor vessel. L t a s, - s P -.s. i \\, g o

\\

, y' ", 1\\ I l', 1 y 4 ~- l e l' l i l 1. ' \\'. .\\' \\\\ FORM A Page 35 of 33 y

67.-- y j f.'N '.T... ., s ' t 1 1 UNITED STATES NUCLEAR REGUIATORY COMMISSION. ] PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION i.

.,, 1,s V.

t b' t 'Please Print: Name: t ' Facility:. 5 3' ID Number: -s ' INSTRUCTIONS TO CANDIDATE Use. the; answer sheet provided.,Each question has equal point value. The passing grades require at least.80% on this part of the written licensing l examination. All examint. tion papers will be picked up 2.5 hours after the examinationistarts. c< SECTION Questions !. 4 of Total-Score THERMODYNAMICS-1 ; COMPONENTS 29 .71. REACTOR THE0EY 72 100 .4,.. + ,,s TOTALS 100 l I \\ 1 E All. work done on this s.ramination is my own. I have neither given nor g received aid. i. Candidato's Signature P PORM B /' ~ 4 -.m--- .-e .m-,, _.,,, .u~,

K + 6. E 5 K \\ RULES AND CUIDELINES FOR THE GENERIC FUNDAMENTALS EXAMINATION h.' , During the administration of this examination the following rules apply: T 3 VJ (1) Print your name in the blank provided on the cover shaet of the [ . examination. (2) Fill in the name of the facility you are associated with. (3) Fill'in the ID Number you were given at registration. (4).Three handouts are provided for your use' during the examination, an Equations and Conversiona sheet, instructions for filling out the answer sheet, and Steam Table booklets. (5) Use only the answer sheet provided. Credit will only be given for answere marked on this sheet. Follow the instructions for filling out the answer sheet. (6)' Scrap paper will-be provided for calculations. (7) Any quest'ons about an item on the examination should be directed to the examiner on%'. (8) cheating on the exc71r.ation will result in the automatic forfeiture of this examination. Cheating could also' result in severe penalties, f ,(9) Restroom trips are limited. Only ONE examinee may leave the room at a time. In order to avoid the appearance or possibility of cheating, avoid all contact with anyone outside of the examination room. (10) After.you have completed the examination, please sign the statement on the cover sheet indicating that the work is your own and you have not received or been given any assistance in completing the examination, l' (11) P16tse. turn in your examination materials answer sheet on top followed by the exam booklet, then examination aids steam table booklets, handouts and scrap paper used daring the examination. E I. (12) After turning in your examination materials, leava the examination area, ) as defined by the examiner. If after leaving you are found in the L examination area while the examination is in progress, your examination l; may be forfeited. l i. l, l

_.(.

Jeg

'fr \\-

.,Y.

OENERIC PtBIDANETA12 EIANIl% TION SECTICII f ' D,, N BQUATICIIS AND 00NVERSI0ftS HANDOUT SHRFI I M ^ g3 cycle Efficiency Nat Work (outi m' a c AT p Energy (in) i 4 ' = a' Ah SCR S/(1 K,gg) j = k ' ' UA'AT CRg (1 K,gg)g CR2 (1. K,gg)2 = ..s ti' q, SUR = 26.06/r N 1/(1. K,gg) CR /CR = g 0 26.06'(1,gg p) (1. K,gg)0 SUR =' N = () ~p)' (1 K,gg)t ' P, 10 " I") 'P (1. K,gg)/K,gg SDN = = P e(t/r)' Pwr 'P~ 'W e = = n o. f (1./p) + [(#. p)/A,gg ) e 1 /(p A) t = p f = I (K,gg 1)/K,gg 1* 1 x 10 5 seconds p' = j. I [. p' AK,gg/K,gg 1,gg = 0.1 seconds *g = P l' yy CONVERS10EIS 10 e 1 Curie - 3.7 x 10 dps 1 kg 2.21 lba = 3 6 1 hp-2.54 x 10 87U/hr 1 Mw 3.41 x 10 BTU /hr = l - 1 BTU 778 ft.lbf 'F $/5 *C + 32 = =

C 5/9 (*F - 32)

= u; e l h; -[: ?

r t { p:l# y ' ~ *.' .,. ' PRESSURIZED WATER REACTTIR CDIERIC FUNDAMENTALS EKANINATION ' gg. p.-; QUESTION: 1. . An atmospheric l pressure of 15 psia equals:

A'.1.30 psig.

a. 3 1 <( q. - B(l 15 psig. .g. ' C', 5 psig.. p -- 0, 0 psig. I i QUESTION:' 2. j U . Condensate depression is defined as r y

A.

. cooling the condensate below'its saturation temperature. [ 1r , L B.< maintaining-the. condensate at a constant temperature throughout the w system. C. ensuring that the condensate is below the level of t$e hotwell pumps. ~ D.'- cooling the condensate to.the point of saturation. [ QUESTION: 3. What is the. reactor coolant system subcooling for Tave - 400'F and pressurizer l. pressure - 1.000 psia? ? I 1' h - A. 75'F lQ, .t B '.- 100'F 11 1: L C. 125'F D. 145'F Is c,'\\ E i 1: l 1;c 1 FORM B Page 1 of 34 1. 1' Ii V I, L, ......., ~...

o e s ',8 ,%'e} ~t' t ' PRESSURIZED WATER REACTOR CENERIC 7tJNDAMENTAIJ EXAMINATION FORM B 7 -QUESTION: 4 The plant is maintained at 2,000 psia with a prossurizer temperature of 636'F. A pressurizer safety relief valve is leaking to a collection tank which is l ibeing held at 10. psig. What is the temperature of the fluid downstream of the relief valve? A. -280'F B. 240'F g, C. 190'F 'D. 170*F. . QUESTI0ti: 5. j_:s L Overall plant efficiency will PECREASE if: t the stoaa quality is increased by removing noisture from the steam prior A. to entering the turbine. ) B.- ' the temperature of the feedwater entering the steam generator is increased. j C, the amount of condensate depression (subcooling) in the main condenser is decreased. + D.. .the. temperature of the steam at the turbine inlet is decreased. f QUESTION: 6. The possibility of a water hammer is KINIKIZED by: [ A. changing valve positions as rapidly as possible. B. ' starting centrifugal pumps with the discharge valve fully open. C. starting positive displacement pumps with the discharge valve closed. . D.' venting systems prior to starting centrifugal pumps. PORN B Page 2 of 34 . ~...

10 h.... FRESSURIZED WATER REACTOR CENERIC FUNDI.NENTALS. EXAMINATION FORM B

J.

. QUESTION: 7. Cavitation in an operating pump may be caused by: A. lowerin5 the suction temperature. B. throttling the pump' suction valve. C.. throttling the pump discharge valve. D. increasing the pump discharge pressure. QUESTION: 8. The piping system pressure change caused by suddenly stopping fluid flow is i~ referred to as: A. cavitation. B. shutoff head. C. water hammer. D. flow head, i QUESTION: 9. If a flow measuring instrument is HQI density compensated, then indicated mass 7' flow rate will be: A. the same as actual mass flow rate with a change in temperature of the fluid. B. greater than actual mass flow rate with a decrease in temperature of the fluid. C. less than actual mass flow rate with a decrease in temperature of the fluid. D. less than actual mass flow rate with an increase in temperature of the fluid. FORN B Page 3 of 34

b 1 e 4 s..

m i

PRESCURIZED WATER REACTOR GENERIC FUNDAMENTALS EKANINATION PORN B

QUESTION:

10, i . operating two pumps in parallel instead of operating a single pump will result in: ) A. a large increase in system head and the same flow rate. B.. the same system head and a small increase in flow rate. C. a small increase in system head and a large increase in flow rate. D. a decrease in system head and a large increase in flow rate. QUESTION: 11. L Excessive amounts of entrained gases passing through a single-phase (liquid) I heat exchanger is UNDESIR431E, because: A. flow blockage can occur in the heat exchanger. B. the laminar layer will increase in the heat exchanger. C. the heat transfer coefficient will increase in the heat exchanger. D. the temperature difference across the tubes will decrease through the heat exchanger. l. 1 1' QUESTION: 12. In.a tva-loop pressurized water reactor, feedwater flow to each steam generator is 3.3 x 10 lbs/hr at an enthalpy of 419 BTU /lba.'The steam exiting each steam generator is at 800 psia with 100% steam quality. Ignoring blowdown and pump heat, what is the core thermal power? A. 3,411 NWt B. 2,915 MWt C. 2,212 NWt D. 1,509 NWt FORM B Page 4 of 34

p ' i.Q, i c. I' PRESEURIZED WATER REACTOR CENERIC FUNDAMENTALS EKANIMATION FORM B QUESTION: 13. 1 Why does nucleate boiling improve heat transfer in the core? ] A. The formation of steam bubbles at nucleation sites on the fuel clad allows more heat to be transferred by conduction. B. Heat is removed from the fuel rod as both sensible heat and latent haat i of vaporization, and the motion of the steam bubbles cause rapid mixing of the coolant.. ] C. Heat is removed from the fuel rod as both sensible heat and latent heat i of condensation, and the heat is transferred d'irectly to the coolant by radiative heat transfer. y D. The formation of steam bubbles at nucleation sites on the fuel clad reduces coolant flow in that area and allows more heat to be transferred i by convection.- T-i 'f. QUESTION: 14 Subcooled nucleate boiling is occurring along a heated surface. The heat flux is then increased slightly. What will be the effect on the delta T between c the surface and the fluid? A. Large increase in delta T bee,ause of steam blanketing B. Large increase in delta T causing radiative heat transfer to become significant C. Small increase in delta T because of steam blanketing D. Small' increase in delta T as vapor bubbles form and collapse L l l QUESTION: 15. L What parameter change would move the plant farther away from the critical heat I flux? A. Decrease pressurizer pressure I. B. Decrease reactor coolant flow C. Decrease reactor power D. Increase reactor coolant temperature l l 1 FORN B Page 5 of 34

s i en ;i, ni _i FRRSSURIZED WATER REACTOR CENERIC FUNDAMENTALS'EIANINATION 1 s, Y FORM B i~!! QUESTION: 16. Film boi'.ing is: A. heat transfer throu6h a vapor blanket that covers the fuel cladding, f -B. heat transfer being accomplished with no phase change. C. the most efficient method of boiling heat transfer, !D. heat transfer through an oxide film on the cladding. s ' QUESTION: 17. The departure from nucleate boiling ratio (DNBR) is defined as: A. the actual heat flux divided by the critical heat flux at any point along a fuel rod. B. the critical heat flux divided by the actual heat flux at any point along a fuel rod.' 3 I' C. the core thermal power divided by the total'reactar coolant mass flow . rate. -D. the number of coolant channels that have reached DNB divided by the l number of coolant channels that are subcooled. QUESTION: 18. The reactor coolant subcooling margin will be DIRECTLY REDUCED by: (Evaluate each change separately.) A. increased pressurizer pressure.

B.

increased pressurizer level. C. increased reactor coolant flow. D. increased reactor coolant temperature. FORN B Page 6 of 34

s. . 'p FRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EXANINATION FORM B QUESTION: 19. Maximizing the. elevation difference batween the core thermal center and the steam generator, thermal centers and minimizing flow restrictions in the . reactor coolant system (RCS) piping are plant designs to: A. minimize the reactor coolant system volume. B.. maximize the reactor coolant system flow rate during forced circulation. C. ensure a maximum RCS loop transit time. D. ensure RCS natural circulation flow can be established, l m QUESTION: 20. l' With the RCS subcooled and all RCPs stopped, the natural circulation flow rate will MgI be affected by an increase in the: A.. reactor coolant pressure increase. B. time after reactor trip. C. steam generator level increase. D. steam generator pressure decrease. l ~ j QUESTION:' 21. i. If departure from nucleate boiling (DNB) is reached in the core, the surface j temperature of the fuel clad will: A. increase rapidly. l-B. ' decrease rapidly. C. increase gradually. l-l. D. decrease gradually. 1-1' L l-1 l' 1 L PORM 3 Page 7 of 34

g ai Sh. .Lo ~ .W; 3 :... J- ' n; PRESSURIZED WATER REACTOR CENERIC FUNDAMENTAIA EKANIMATION w-s n ' ' FORN 5 ) u s t ' QUESTION:- 22. If the reactor:is' operated within core thermal limits, then: A. plant thermal efficiency is optimized. ' ':n B- ' fuel. cladding integrity is ensured. C. pressurized. thermal shock will be prevented. o. D. reactor vessel thermal stresses will be minimized. t i 1 QUESTION:- 23. Fast neutron. irradiation of the reactor vessel results in stresses within the. vessel metal, thereby the Nil-Ductility Transition E Temperature. P I A, increased,-increasing i B.' increased, decreasing 'C. decreased, increasing i D. ' decreased, decreasing h ' QUESTION: 24 L I;. The likelihood of brittle fracture failure of the reactor vessel is REDUCED L by: / lc A. increasing vessel age.. i 'B. reducing vessel pressure. C. reducing vessel temperature. 1; D. reducing gamma flux exposure. L ( 1 l: 1-l ln ' 1' l

I l

K FORM B Page 8 of 34 i: ) {

7 y. 9.,1 '.'.c. 'i. PRESSURIZED WATER REACTOR CENERIC FUNDAMENTALS EKANINATION - y r, 'l PORM B , 01 3 -QUESTION: 25.. Pressure stress on the reactor vessel wall'is: ' -)

J " ) ;Y '

f A.'. compressive across the entire' wall. y .l =v 3 B. tensile across the entire wall. [ i 'C. tensile at the inner wall, compressive at the outer wall. ' }! ' D. compressive at the inner all, tensile at the outer wall. QUESTION: 26. l

The nil-ductility, temperature is that tasperatuis:

s A. below which the probability of brittle fracture significantly increases. .M B. where failure stress becomes greater than the yield stress of the metal. C. 'below which the probability of plastic deformation significantly i' increases. + a D.. below which the yield stress of the metal is higher than-the critical' l 3 ' fracture stress. t F 1 U ~ QUESTION: 27. E Pressurized thermal shock could most likely be a concern during: A. 'an uncontrolled cooldown followed by a rapid repressurization. B.- an uncontrolled'depressurization followed by a rapid repressurization. C.- an uncontrolled cooldown followed by a rapid depressurization. 'D. an overpressurization from a low temperature, low pressure condition. QUESTION: 28. During a severe overcooling transient, a major concern to the operator is: i A. accelerated zirconium hydriding. B. loss of reactor vessel water level. C. loss of reactor coolant pump net positive suction head. D. brittle fracture of the reactor vessel. FORM B Page 9 of 34 y m, ,,. - =. _,,..,, - _., ,,4m _.,.,_.,.,_,..._e-

j t +e. j pp W .PRESSURIEED WATER REACTOR CENERIC FUNDAMENTAIJ EKAMINATION t i:;i' pogM g l, n: i' QUESTION: 29. p. The. primary purpose of a pressure relief valve is to: ( p f" A. maintain system flow. 'B. maintain system pressure. i .C. . maintain system integrity. K D. maintain system' temperature. ( !?, QUESTION: ' 30. l: When a discharge valve is opened to atmosphere, the pressure on the upstream p side.of the valve will:- i A.L remain'the same, and the pressure on the downstream side will' increase. B.- increase, and the pressure on the downstream side will remain the same. C. remain the same, and'the pressure on the' downstream side will decrease. .D. ' decrease','and the pressure on the downstream side will remain the same. y., l' . QUESTION:. 31. F The function of a valve backseat is to: l A '. isolate system pressure from the packing and stuffing box to minimize H packing leakage. B. isolate system pressure from the packing and stuffing box for the purpose of valve repacking. C.- provide a backup means of flow isolation in the event of primary seat leakage. D. provide a backup means of flow isolation in the event of a pipe break. ^ j i' J FORM B Page 10 of 34 x .m

E, 1 i '.z i. T-PRESSURIEED WATER REACTOR CENERIC FUNDAMENTAIS EXAMINATION FORM B QUESTION:

32. '

j I Af ter manually positioning,e motor operated valve, how is the valve actuator ) g .re engaged? A. Actuation of tho' torque switch 4 B. Manually pulling up on the manual declutch lever C. Actuation of either'the full-open or full closed limit switch D. Actuation of the valve actuator motor in either the open or close direction -QUEST 10N: 33, 4 To verify the position of a closed manual valve, the operator should operate the valve: A. to the fully'open position, then reclose it using normal force. B. in the closed direction using normal force. l C. in'the open direction until flow sounds are heard, then close the valve using manual force. D. .in the closed direction until it stops, then close it an additional one half turn using normal force. 4 QUESTION: 34. Density compensation is used in flow instruments to change to A. mass flow rate, volumetric flow rate B. volumetric flow rate, mass flow rate C. fluid pressure, volumetric flow rate D. differential pressure, mass flow rate FORM B Page 11 of 34 = -

i ) i PRESSURIEED WATER REACTOR CENERIC FUNDAMENTAIA EXANIMATION PORM S I QUESTION: 35. l 1 If the liquid flowing through a liquid flow rate sensor contains entrained voids (gas or steam), indicated flow rate will be: l I A. erroneously high. B. er5oneously ' low. C. unaffected. I i.' D. fluctuating. I QUESTION: 36. If the equalizing line on a differential pressure (D/P) flow detector is i' opened, the flow detector indication will: A. increase slightly, 8. decrease slightly. C. go to zero. D. not change. I QUESTION: 37. Flow detectors (such as an orifice, flow nozzle, and venturi tube) measure i flow rate u61ng the principle that flow rate is* t i L A. DIRECTLY proportional to the differential pressure. 1 INVERSELY proportional to the differential pressure. i. B. L L C. P1kECTET proportional to the square root of the differential pressure, j 1 D. INVERSELY propertional to the square root of the differential pressure. ll' 1 t I i P FORM B Page 12 of 34 .~.. J

$J, i I MLEsstat1EED WATE3t REACNR GENER3C FUNDAMENTALS EKANIMATION j FORM B { i QUESTION: 38. 1 The pressure differential between a reference it[ thd a variable leg is: A. D11ECTLY proportional to the he1 ht of the variable leg, i 3 i B. INVERSELY proportional to the height of the variable leg. A C. DikECTLY proportional to the density of the reference leg. i D. INVERSELY psoportional to the temperature of the reference leg. l QUESTION: 39. l i If the reference leg of a differential pressure level indicator axperiences l high ambient temperature, indicated level vill: A. read less than actual level. i B. read greater than actual level. C. equal the actual level. D. slowly decrease to zero. t QUESTION: 40. l The output for a reference leg differential pressure level instrument will [ fail LQ2 as a result of: l A. a break on the reference leg. B. a rupture of the diaphrags in the differential pressure cell. C. the reference leg flashing to steam. l. D. a break on the variable leg. 1 V l r l' I l FORM B Page 13 of 34 l l

PRESSURIEED WATER REACTOR CENERIC FUNDAMENTALS EXAMINATION j FORM S i I QUESTION: 41. A resistance temperature detector (RTD) operates on the principle that the change in electrical resistance of-4 1 A. two dissimilar metals is DIREcrLY proportional to the temperature change measured at their junction. B. two dissimilar metals is /,HfELSELY proportional to the temperature change measured at their junction. ) i C. a metal is PIRECTLY proportional to its change in temperature. ] D. a metal is INVER$ZLY proportional to its change in temperature, i J QUESTION: 42. Two differential pressure level transmitters are installe1 in a large tank. If transmitter I is calibrated at 200 degrees F and transmitter II is L calibrated at 100 degrees F, then at 1L0 degrees F: A. transmitter I will read greater than transmitter II. B. transmitter II will read greater than transmitter I, f i C. transmitter I and II will read tha same. D. it is impossible to predict how either transmitter will respond. i QUESTION?. 43. l i Scintillation detectors operate on the principle of: A.- photodisintegration. B. photokinesis. C. photomultiplication. D. photoionization. i l l i PORN B Page 14 of 34

t FRESSUR11ED WATER REACTOR CFJtERIC FUNDMENTALS EXAMINATION FORn B j k QUESTION: 44 t A BT3 proportional counter detects both neutrons and gammas. Which of the following best describes the method used to eliminate the gamma contribution from the detector output? A. Two counters are used, one sensitive to neutron and gamma and the other sensitive to gamma only. The outputs are electrically opposed to cancel the gamma. induced currents and yield a neutron.only signal for indication

uso, i

B. The BF3 proportional detector records neutron flux of sufficient intensity that the gamma signal is insignificant compared to the neutron signal and yields a neutron only signal for indication use. C. Camma. induced detector pulsee are of insufficient width to generate a significant log level amplifier output. Neutron pulses are the only ones with sufficient vidth to yield a neutron only signal for indication use. D. Neutron. induced current pulses are significantly larger than those from gamma. The detector signal is applied to a circuit which filters out the smaller gamma pulses yielding a neutron only signal for indication use. I t QUESTION: 45. The difference between the setpoint and the measured parameter in an automatic flow controller is called: A. gain. B.

bias,

_t C. feedback. [ l D. error. i QUESTION: 46. A controller's output is typically insufficient to accurately drive a valve l actuator. To overcome this probles, a control loop normally employs: l t [ A. a lead / lag unit. B. a regulator. C. a positioner. D. an amplifier unit. l l l FORM B Page 15 of 34 L

l s PRES 3URIEED WATOL REACTOR CDfERIC FWDAIFJf7ALS EXAMINATION l Porn B 1 QUESTION: 47. l Why must an operator pay particular attention to auto / manual valve controllers left in the manusi mode? F A. The manual valve control is usually not stable compared to the automatic mode. l B. The valve position will no longer respond to changes in system i parameters. { C. The controlled parameters will no longer be controlled by the valve l position. j D. The valve can only be operated locally during this time. QUESTION: 48. What precautions must be observed when transferring a valve controller from the automatic modo to manual mode of control? A. Ensure that the proper offset is established between the automatic mode and manual mode. B. Ensure that the valve controller output signals are matched between automatic mode and manual mode. C. Ensure that the valve controller stabilizes in the automatic mode before completely transferring to the manual mode of control. D. Ensure that the automatic valve controller signal is increasing before transferring to manual mode of control. QUESTION: 49. An indistion of centrifugal pump cavitation is: A. pump motor amps pegged high. B. pump discharge prensure indicating zero. C. pump motor amps oscillating. D. pump discharge pressure indicating shutoff head. L i FORM B Page 16 of 34

"T T-'" >.t f. i. PRES $URIEED WATER REACTOR CENIlRIC W'fDAMENTA1A ERAMINATION FORM S QUESTION: 50. The term " shutoff head' for a centrifugal pump indicates that it is pumping at: A. maximum capacity and minimum discharge head. B. maximum capacity and maximum discharge head. C. mint.tum capacity and maximum discharge head. D. minisue espacity and minimum discharge head. QUESTION: 51. Operating a motor + driven centrifugst pump for extended periods of time with no flow through the pump will cause: A. pump failure from overspeed. B. pump failure from overheating. C. motor failure from overspeed. D. motor failure from overheating. QUESTION: 52. SHUTTING the discharge valve on an operating centrifugal pump will cause the 321gt AMPS to and the pump DISCHARCE PRESSURE to A. increase, increase l B. decrease, increase 1 I C. increase, decrease D. decrease, decrease l FORM B Page 17 of 34 -w v z m

l

PRESSURIEED WATML REACTOR GWrERIC FUNDMEDf7ALS EXANIMATION h

FORM S ( t QUESTION: 53. l i If the speed of a positive displacement pump is increased, the available net j positive suction head (NPSH) will and the probability of j cavitation will i, 5 A. increase, increase j r S. decrease, decrease ( C. increase, decrease l t D. decrease, increase [ 33 QUESTION: 54 Reactor coolant pump motor amps will if the rotor is LQ&EED and the motor speed will if she r9 tor EH56ER. l A. inertase, increase { 3. increase, decrease f C. decrease, increase l D. decrease, decrease t QUESTION: 55. If the generator bearings on a motor generator overheat then: { A, the generator voltage will increase. B. the generator windings will overheat. C. the motor current will decrease. D. the motor windings will overheat. .( f i t FORM a Page 18 of 34

3 j o FRESSURIEED WATER REACTOR GENutIC FUNDAMENTA1A EEANIMATION j FORN & QUESTIDN: 56. If the speed of a variable speed centrifugal pump is increased to cause pump Rt flow rate to double, pump motor current will: i A. remain constant. l S. increase two fold (double), i l. C. increase four fold. ( i D. increase eight fold. o L QUESTION: 57. I i The starting current in an A.C. motor is significantly higher than the full load running current because: ) I A. starting torque is lower then running torque, i i startin5 torque is hit er than running torque, i h B. C. rotor current during start is higher than running current. D. rotor current durin5 start is lower than running current. 1 QUESTION: 58. a Tne number of start; for an electric motor in a given period of time should be limited because: l A, overheating of the wir. dings can occur. I L,' B. excessive torqua is generated during motor start. j C.. running current is such higher than starting current. L D. motors'are normally started under full load conditions. L i l ? \\ l i t i 1 FORM B Page 19 of 34 1. i l ~

1 4 FRESSURIEED WATER REACTOR CEMRIC FUNDMWrTALS EIANIMM' ION FORN S f QUESTION: $9. Severe stress in a mechanical componant, induced by a sudden, unequally distributed temperature reduction is a description of: A. . heat stress. 5, therral shock, hg C.. thermal strain. l L D. heat strain, fin QUESTION: 60. Tube fouling in a heat exchanger causes heat transfer to decrease by: I. A. reducing fluid velocity on the shell side of the exchanger. B. increasing flow rate through the tube side of the exchanger. C.- reducing the uverall (total) heat transfer coefficient. D. increasing the overall (total) heat transfer coefficient. QUESTION: 61. Sorated water is flowing through the tubes of a heat exchanger being cooled by fresh water. The shell side pressure is less than tube side pressure. What ^ will occur as a result of a tube failure? A. Depletion of borated water inventory. P B. Depletion of cooling water inventory. I C. Dilution of the borated water system. D. Shell pressure will decrease. l e l' FORM B Fage 20 of 34 $~

J i L PRESSURIEED WATER REACTOR CENERIC FUNDAMENTA1.8 EKANIMATION FORM S j QUESTION: 62. What is the reason for bypassing a demineralizer due to high temperature? l A. Resins expand and restrict flow through the domineraliser, j B. The demineralizer decontamination factor is dramatically increased. C. Organic compounds used as resins will decompose, j u D. The creation of preferential flowpath through the domineralizer will occur. l QUESTION: 63. In the event of a syrten crud burst, what adverse effect does the crud burst l I have on demineralizer operation? [ l l A. Increases pressure drop across domineralizer i B. Increases flow rate through domineralizer C. Increases domineralizer outlet conductivity l D. Increases domineralizer inlet pH QUESTION: 64. l i ) Boron concentration in the reactor (primary) coolant system has been de-creasing steadily at approximatei ' 10 ppa per hour while using the deborating dominera1. f.ze r. After several hours, the rate decreases to 2 ppa per hour. What is a possible cause for the change in deboration rate? A. Temperature of the coolant passing through the domineraliz6r has decreased. B. pH of the coolant has increaswd significantly. L l C. Flow through the deborating resins has increased sharply. D. Deborating resins have become boron saturated. l t l FORN 5 Page 21 of 34 t s

l ] 4.. L MLES$URIEED WATR REACNR CWFRIC FUNDt.IUOtTALS EKAMINATION - l FORN 3 i +' i QUESTION:. 65. lt l j b. To de. energize a component and its associated control and indication circuits, the component circuit breaker should be: ,7 A. racked in and tagged in open position. I B. racked in and tagged in closed position. C. racked out and tagged in racked.out position. 1 D. in the test position and tagged in test. 1 j o QUESTION: 66. j To ensure reliable local breaker indication is being provided the i p must be reset af ter breaker operation. ] l A. OYEN/C1hSED mechanical flag B. OPEN/C1hSED indicating li hts S L C. Overcurrent trip flag D. Spring CHARGE /DISCHARCE flag i QUESTION: 67. l A circuit breaker thermal overload device: A. compares actual current to a fixed overcurrent setpoint that is equated to temperature and actuates a trip relay. r B. when pojected to high.*urrent, overheats and actuates a circuit-l- interrupting device. J C. senses operating equipment temperature and trips protective circuits te i preset If.mits. i 1 D. is an induction coil *, hat produces a secondary current proportional to j I i the primary current. l \\ l l' l l. l l l l-FORN 8 Page 22 of 34 c l.'

b. M PRESSUR17.ED WATER REACTOR CDIERIC FUNDAND'TALS EKAMINAT'.ON i PORM B QUESTION: 64. i i a# Loss of circuit breaker control power will cause: A. breaker line voltage to be zero regardless of actual breaker positten. I i B. the remote breaker position to indicate closed regardless of actual breaker position. i -C. inability to operats '

breaker locally and remotely.

I D. failure of the close sprin8 to charge following local trippin5 of the breaker. QUESTION: 69. t If a de. energized bus is not unloaded prior to closing the output breaker of a three. phase generator onto the bus, thent [ A. an overvoltage condition will occur on the bus. 8. an overcurrent condition will occur on the generator. C. an overvoltage condition will occur between generator phases. D. generator undervoltage relay actuation vill occur. 4 QUESTION: 70.- Which of the following statements is correct concerning the use of disconnect switches? A. Disconnects should be limited to normal load current interruption. B. Disconnects may be used to isolate transformers in an unloaded network. C. Disconnects are similar to oil circuit breakers, but are manually 4 operated. D. Discennects must be closed with caution when under load because of l possible arcing. t M FORM B Page 23 of 34 s e a

k '1-I m .i '1/ %'l HLESBURIZED WATER REAC1tIR CENIOltfC FUWD90NTA1A EXANINATION l \\ \\- FORW'8 \\ l s I QUEST 10M;. 71. \\ f u Closing a ganerator output breaker with the 'generaser (Fequency much less then grid frequency will cause the generator to trip on; i i as A. reverse power. tu i viu. i B, overvoltage. 4V l w C, overcurrent. D, ovrispeed. 't s l QUEST 10Nt-72. i 8 The operator.has just pulled control rods and changed the effective multipli. i cation far.cor (Keff) from 0.998 to 1.002. The reactor ist i i A. Prompt critical f B. supercritical t .C. exactly critical D. suberitical t 1 I t L \\ i 6 . y. i g P r i s i ,yv .vk. 5 FORM B Page 2fs of 34 \\1,

.r., cb. (, FRESMIRIEED WATER REACTOR CENERIC FUNDM0lNTALS DANIMATION 1 FORH,6 i QUESTION: 73. The ratio of 'the nkeber of neutrons in one generation to the number of f nortrons in the previous generation is the: i A. effective multiplication fattor 3. fast fission factor f 3 t ' C. neutron non leakage factor .. uton reproduction factor l ~ r 4 1 QUESTION: 74. i b Reactivity is defined as the: l A. fractional change in neutron population per generation. U i 1 it. number of neutre.ss' by which neutron population changes per generation. O \\ C. rate of-change of reactor power'in neutrons per second. D. thange in the number of neutrons per second that causes a fission event. f i QUESTION: 75. A given amount of posivf.ve reactivity is added to a critical reactor in the [ l source (startup) range. The amount added is less than the average effective l delayed neutron t'raction. Which of the following wf.11 have a significant l 4 effect on the magnitude of the stable startup rate achieved for this addition? t L A. Prompt neutron lifetime g' 4 l UB.. Fuel ' temperature coeffichnt 1 t i C. Average effective decay constant [ I &v e{ l D. Mo(erator temperature coefficient C. l. 4 i A 4 i s ls- %.g, t 1 b L , \\$ i I FotM B Page 25 of 34 s s L, ' I e m

F' .o PRESSURIEED WATER REAf'1th CDIERIC FUNDANDffA1A EIANINATION i PORM &- QUESTION: 76. Over core life the production of plutonium isotopes with delayed neutron fractions than uranium delayed neutron fractions will cause reactor power transients to be near the end of core life. A, less, faster B. less, slower C. greater, faster D. greater, slower QUESTION: 77. An installed neutron source: A. maintains the production of neutrons high enough to allow the reactor to achieve criticality. B. provides a means to allow reactivity changes to occur in a suberitical reactor. C. generates a' sufficient neutron population to start the fission process and initiate suberitical multiplication. D. provides a neutron level that is detectable on the source range nuclear instrumentation. l QUESTION: 78. Why does increasing reactor coolant boron concentration cause the moderator 1-temperature coefficient to become less negative? A.. Reactor coolant temperature increasec result it s larger increase in the thermal utilization factor. l: I B. Recetor coolant temperature increases result in an increase in the [i resonance escape probability. t C. Reartor coolant temperature increases result in an increase in the total I non leakage probability. D. The change in resonance escape probability dominates thi chenge in the L thermal utilization factor. i FORM B Page in o^ 34 r r A js

PRESSURIEED WATER REACT 00t GDilJt1C IVNDAMENTAIJ EIANIMATICII PotM B QUESTION: 79. Why does the v.'oel temperature (Doppler) coef ficient becosee less negative at higher fuel temperatures? A. As reactor power increases, the rate of increase in the fuel temperature diminishes. B. Neutrons penetrate deeper into the fuet, resulting in an increase in the fast fission factor. C. The amount of self shielding increases, resulting in less neutron absorption by the inner fuel. D. The amount of Doppler broadening per degree change in fuel temperature diminishes. QUESTION: 80. A reactivity coefficient measures change while a reactivity defect (deficit) measures a change in reactivity due to a change in the sessured parameter. A. an integrated, total B. a rate of, differential C. a differential, total D. a total, differential QUESTION: 81. During power operation, while changing power level, core reactivity is affected most quickly by: A. boron conventration adjustments. B. power defect (deficit). C. xenon transients. D. fuel depletion. FORM B Page 27 of 34 1

i PRESSUR1EED nlNfE3t ILEACTOR CtWtPit FUNDMtENTALS ERAN! NATION ) FORN O i i [ QUESTION: $2. As moderator temperature increases, the magnitude of differential rod (CEA) l worth increases because' A. decreased moderator density causes more neutron leakage out of the core. B, moderator temperature coefficient. decreases, causing decreased l competition. C. fuel temperature increases, decreasing neutron absorption in fuel. D. decreased moderator density increases.eutror migration length. QUESTION: 83. i Control rod (CEA) bank overinp: A. provides a more ut.iform differential rod (CEA) worth and axial flux distribution, i B. provides a more uniform differential rod (CEA) worth and allows dampening i of Y.enon dnduced flux oscillations. C. ensures that all rods (CEAs) remain within the e.llowable tolerance between their individual position indicators and their group counters and ensures rod (CEA) insertion limits are not exceeded. ? i D. ensures that all rods (CEAs) remain within their allowable tolerance between individual position indicators and their group countets and provides a noce uniform axial flux distribution. QUESTION: 84 L I The be. sis for the maximum power density (kw/ft) power limit is to: t t ( A. prevent fuel clad selt. 8. preveat fuel pellet selt. O. limit bulk coolant temperature. D. prevent nucleate boiling. 1 1 !DRM B Page 28 of 34

L. o. PRESSURIEED WATER REACTOR CENERIC PVNDAMENTAIJ EKANIMAT10ll PORN 5 QUESTION: 85. The control rod insertion limits are power level dependent because the ) assnitude of: A. control rod worth decreases as power incroaces. 5 power defect increases as power increases. C. Doppler (fuel temperature) coefficient decreases as power increases. 1 D. moderator temperature coefficient increases as power increases, i l QUESTION: 86. Fission product:. what have substantial neutron capture cross sections are: 1 A. excited fission products. 5. fission product daughter. C. radioactive fission products. ? D. fission product poisons, i QUF.STION: 87. Following a reactor trip from sustaine,d high power operation, Xenon 135 concentration in the reactor will: l A. decrease because Xenon is produced directly from fission. B. increase due to the decay of lodine already in the core. C. remain the same because the decay of lodine and Xenon balance each other out. l l j; D. decrease immediately, then slowly increase due to the differences in the i half lives of fedine and Xenon, o f l l l L FORM B Page 29 of 34 e +- ~.. _ _.

o,*o' PRR$5URIEED WATR REACTOR CarERIC FUlt0MEDf7ALS ERANINATICII PORN 5 L QUESTION: 48. Followins a reactor trip from sustained high power operation, the major Xenon [ 135 removal process is: ( i-A. ton exchange. l t B, beta decay. 1 C. neutron capture. 1 ~ f D. alpha decay. t 99. { QUESTION: A reactor has been operating at 50 percent power for 7 days when power is ramped to 100 percent over a four hour period. The new $quilibrius Xenon value vill: g i A. be twice the 50 percent value. B. be less than twice the 50 percent value. C. be more than twice the 50 psreent value, j D. remain the same since it is independent of power. l l t c 6 QUESTION: 90. l' Slow changes in axial nower distribution in a reactoc chec has operated at a t i steady. state power for a long time can be caused by: ) A. Xenon peaking. 5 8. Xenon override. I C. Xenon burnup. l D. Xenon oscillet. ton. t 1 i t l l-l k l FORM a Page 30 of 34 li

l PRESSURIEED WATER REACTOR CENERIC PUNDAMENTAIJ EIANIMATION FORM B QUESTION: 91. A reactor that has been operating at rated power for about two weeks reduces power to 50 percent. Xe.135 will reach a new equilibrium condition in hours. i A. 8 to 10 hours I B. 20 to 25 hours c. 30 to 35 hours i D. 40 to 50 hours i i QUESTION: 92. The reactor is near the end of its operating cycle. In order to stay critical, power and temperature have been allowed to 'coastdown." Why is boron no longer used to compensate for fusi depletion? l A. Boron concentration approaches sero and requires r".cessive amounts of water to dilute. B. The differential boron worth has decreased below its useable point. C. The boron in the coolant has been depleted due to neutron absorption. l D. 'Coastdown" is preferred due to fuel conditioning limitations. I ~ i QUESTION: 93. t While withdrawing control rods during an approach to criticality, the count t l rate doubles. What will occur if ths saes amount of reactivity that caused L the first doubling is added again? A. Count rate will increase slightly. l B. Count rate will double. I C. The reactor will remain suberitical. 1 t l. D. The reactor will be critical or slightly supercritical. 1 I i L t PORN B Page 31 of 34 s .m

~ FRESSURIEED WATER REACTOR CENERIC PUNDMEENTALS ERANIMATION FORN 5 i QUESTION: 94. [ i In a reactor with a source, a non changing neutron flux over a few minutes is { indicative of criticality or: l A. the point of adding heat. l S. supercriticality. C. suberiticality. i D. equilibrium suberitical count rate. f QUEST 10N': 95. At EOL, critical rod (CEA) position has been calculated for a reactor startup l four hours after a trip from 100 percent power equilibrium conditiont. The actual critical rod (CEA) position will be thWER than the predicted critical rod (CEA) position if: A. the startup is delayed until eight hours after the trip. 8. the steam dump pressure setpoint is lowered by 100 psi prior to reactor startup. r r C. actual boron concentration is 10 ppe more than the assumed boron i concentration. D, one control rod (CEA) remains fully inserted during the approach to criticality, i QUESTION: 96.- With keff - 0.985, how much reactivity must be added to make the reactor j critical? A. 1.480 r,cm (1.48% delta k/k) i B. 1,500 pcm (1.50% delta.k/k) C. 1.520 pcm (1.52% delta k/k) D. 1,540 pea (1.54% delta.k/k) i i ) I FORM B Page 32 of 34 ~_ _.... .-.c. ,._.,.m. _...._.,.m s m ~- sh-----w-

E . PRES $URIEED WATER REACTOR CENERIC FUNDANFJfTALS EXANINATION roan 8 QUESTION: 97. l l 1 l If, during a reactor startup, the startup rate is constant and positive i without any further reactivity addition, then the reactor is: i- 'A..

critical, i

B. supercritical. I C. suberitical. i D. prompt critical. l i QUESTION: 98. i Civen a critical reactor operating below the point of adding heat, what reactivity effects are associated with reaching the point of adding heat? A. There are no reactivity effects since the reactor is critical. B. The increase in fuel temperature will begin to create a positive { reactivity effect. C. The decrasse in fuel temperature will begin to create a negative reactivity effect. t t D. The increase in fuel temperature vill begin to create a negative { reactivity effect. t ll QUFSTION: 99. i i Shortly after a reactor trip, reactor power indicates 0.5 percent where a stable negative SUR is attained. Reactor power will be reduced to 0.05 percent in approximately seconds. A. 360 e B. 270 C. 180 D. 90 i 6.y I~ FORM B Page 33 of 34

c o 4 ;k g FILES $UIt1EED WATR REACTOR CENI3t!C MSIDANDITALS ET. ANIMATION i POItM S t QUESTION: 100. t The major reason boron is used in a reactor is to permit: l j A. a reduction in the, shutdown margin. B. an increase in the amount of control rods (CEAs) installed. 4 i f C. an increase in core life. i D. a reduction in the effect of resonanco capture. l t t t i i ' ) ( ? t I t I t i t ) i 't t t r FORM B Page 34 of 34 . -}}

ML19325E520

Text

Navigation menu

Search