ML20248D374
| ML20248D374 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/01/1989 |
| From: | Baldwin R, Brockman K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20248D372 | List: |
| References | |
| 50-302-OL-89-01, 50-302-OL-89-1, NUDOCS 8908110014 | |
| Download: ML20248D374 (286) | |
Text
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' # ** UNITED STATES y g- 3 g NUCLEAR REGULATORY COMMISSION -
! o,, f REGION li 101 MARIETTA ST., N.W.
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ATLANTA, GEORGIA 30323 -
1 ENCLOSURE 1 l EXAMINATION REPORT 302/0L-89-01 Facility Licensee: Florida Power Corporation '
P. O. Box 1240 Crystal River, FL 32629 Facility Name: Crystal River Nuclear Plant Facility Docket No.: 50-302 Written examinations and operating tests were administered at Crystal River 3
Nuclear Plant near Crystal River, Florida.
Chief Examiner: MAWM YJo/#f Richard S. Baldwin Date Signed Approved By: 9 gd 6 // /89 Date Signed Ken . Broc Man.4 hief Op ator Licensing Section 2 l Di ision of Reactor Safety Summary:
Examinations were administered on April 17 - 20, 1989. I Written examinations and operating tests were administered to eight candidates; -
seven of whom passed. ;
Based on the results described above four of five R0s passed and three of three SR0s passed.
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j V {}g 890003 G5000 PN )p
I REPORT DETAILS 1
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- 1. Facility Employees Contacted:
- W. Marshall, Operations Superintendent
- J. Smith, Licensed Operator Training Supervisor
- J. Lind, Licensed Operator Manager
- P. F. McKee, Director, Nuclear Plant Operations
- L. Kelley, Director, Nuclear Training
- G. Boldt, Vice President, Nuclear Production
- J. Owen. Instructor
- Attended Exit Meeting
- 2. Examiners:
- R. S. Baldwin B. Picker N. Jensen T. Morgan
- Chief Examiner
- 3. . Examination Review Meetino At the conclusion of the written examinations, the examiners provided J. Smith with a copy of the written examination and answer key for review.
The NRC Resolutions to facility comments are listed below.
- a. R0 (SR0) Exam (1) Question 1.07 NRC Resolution: Comment accepted. The reference will be changed as requested.
(2) Question 1.08(4.08)
NRC Resolution: Comment accepted. The answer key will be <
changed to "A" as reqcested.
I (3) Question 2.01 (5.01)
NRC Resolution: Comment not accepted. This question does not require the candidate to memorize Technical Specifications Limiting Conditions for Operations. It requires the candidate to recognize a correct Technical Specification Limiting Condition of Operation when provided incorrect information related to Technical Specification Limiting Conditions for Operations.
2 This knowledge is consistent with NUREG 1122, " Knowledge and Abilities Catalog for Nuclear Power Plant Operators:
Pressurized Water Reactors," in the area of System Generic K/A
- 5, Knowledge of limiting conditions for operations and safety limits. The answer key remains unchangert.
(4) Question 2.03 NRC Resolution: Comment accepted. Since this was not a verbatim extraction from the precedure referenced in the question, the question will be deleted and the point values adjusted accordingly.
(5) Question 2.18 NRC Resolution: Comment accepted. The answer key will be changed to accept either "C" or "D" as correct answers.
(6) Question 2.22(5.22)
NRC Resolution: Comment accepted. Since the question does not elicit all of the desired answers as written, the answer key will be changed to delete " Depress reactor trip pushbutton."
(7) Question 2.23 NRC Resolution: Ccmment accepted. The answer key will be changed to allow either answer "A" or "C" as correct answers.
(8) Question 2.25(5.14)
NRC Resolution: Comment accepted. Since the make-up flow rate is not consistent with the rest of the conditions provided in the question, the transient in progress can not be determined.
The question will be deleted from the exam, and the point value i adjusted.
(9) Question 3.19 ;
NRC Resolution: Comment accepted. The answer key will be changed to allow either answer "A" or "C" as correct answers.
(10) Question 3.20 NRC Resolution: Comment accepted. The question will be i deleted from the exam. The facility is reminded that reference I material should be labeled sufficiently to preclude j i inaccuracies in the examination. >
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(11) Qestion 3.26 NRC Rt. solution: Comment accepted. Based on the information provided and the facility not being able to determine what actually w1il occur on the transient described, the question will be deleted from the examination and point value adjusted.
(12) Question 3.38 NRC Resolution: Comment accepted. The answer key will be modified to allow "the prevention of saturated conditions in the RCS due to draining the pressurizer as a second correct answer.
(13) Question 3.41 NRC Resolution: Comment accepted. The question will be deleted from the examination, and the point values adjusted accordingly.
(14) Question 3.48 NRC Resolution: Based on post-examination grading it has been determined that this question is SRO based knowledge; therefore, the question will be deleted from the examination, and the point value adjusted accordingly.
- b. SR0 Examination (1) Question 5.18(b)
NRC Resolution: Comment accepted. The answer key will be modified to allow " positive reactivity" as the only correct answer.
- 4. Exit Meeting At the conclusion of the site visit the examiners met with representatives of the plant staff to discuss the results of the examination.
There were no generic weaknesses noted during the oral examination.
The cooperation given to the examiners and the effort to ensure an atmosphere in the centrol room conducive to oral examinations was also noted and appreciated.
The licensee did not identify as proprietary any of the material provided to or reviewed by the examiners.
U. S UCLEAR REGULATORY COMMIS N l
REAC ;
OPERATOR LICENSE EXAMIN- ON REGION 2 FACILITY: Crystal River 3 REACTOR TYPE: PWR-B&W177 DATE ADMINISTERED: E9/04/17 INSTRUCTIONS TO CANDID &lEl Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
M, ASIBCOPY
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE _VALUE CATEGORY 2r.vc 24.00 _43-94 "5 1. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) 24.co zr. s W
--29-00 4 B&-94* 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
l 4v. 2.0 n or l 50-Efv M 40.12 *' 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
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- 94. zf I
Wr** % TOTALS FINAL GRADE l
All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature .
START TIME STOP TIME Candidate's Name (please print) i l
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NRC RULES O GUIDELINES FOR LICENSE I"fiINATIONS V V During the administration of this examination the following rules apply: l
- 1. Cheating on the examination means an automatic denial of your application l E
and could result in more severe penalties.
l 2. Restroom trips are to be limited and only one candidate at a time may I leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 3. Use black ink or dark pencil only to facilitate legible reproductions. )
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- 4. Print your name in the blank provided on the cover sheet of the i examination. !
'5. Fill in the date on the cover sheet of the examination (if necessary). ,
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'6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of'the first page of each 4
- section of the answer sheet.
. 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write only on one side of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
l 10. Ship at least three lines between each answer.
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- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the
' question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the examiner only.
- 17. You must sign the statement on the cover . sheet that indicates that the work is your own and you have not received or been given assistance in completing the examination. This must be done after the examination has been completed.
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- 18. Wh:n you complete youb-6xaraination, you shall:
- a. Assemble your examination as follows:
l (1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
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- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions,
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
a
- 1. REACTOH PRINCIELES (7%) THERMODYNAMICS Pcga 4
~N (7%) AND COMPONENTS^ %) (FUNDAMENTALS EXAM) /]
\.
QUESTION 1.01 (1.00) MULTIPLE CHOICE A reactor startup to full power is being performed 5 hours after a trip from full power equilibrium conditions, using a 5%/ min ramp. How would the resulting xenon transient vary if a 2%/ min ramp was used instead?
- a. The xenon dip would be smaller and occur sooner.
- b. The xenon dip would be larger in magnitude and occur later.
- c. The xenon dip would be smaller and occur later.
- d. The xenon dip would be larger in magnitude and occur sooner.
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T7%) AND COMPONENTS ^1%) (FUNDAMENTALS EXAdl /^;
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l QUESTION 1.02 (1.00) l The reactor trips from full power, equilibrium xenon conditions. l Six hours later, the reactor is brought critical and power is raised to 10E-8 amps on the intermediate range. l If power level is maintained at 10E-8 amps which one of the following i statements is CORRECT concerning subsequent control rod motion?
- a. Rods will be withdrawn since xenon concentration increase is greater than the xenon burnup rate.
- b. Rods will not move because the xenon concentration increase equals the xenon burnup due to the core flux.
- c. Rods will be rapidly inserted because the critical reactor will cause a rate of xenon burnout higher than the concentration increase.
- d. Rods will be inserted due to xenon concentration decay and burnout associated with the power level.
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- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS Paca 6 (7%) AND COMPONENTS g %) (FUNDAMENTALS EXAM)
QUESTION 1.03 (1.00) Which one of the following statements concerning the power defect at 100% power is correct?
- a. The power defect is the difference between the measured power coefficient and the predicted power coefficient.
- b. The power defect increases the rod worth requirements necessary to maintain the desired shutdown margin following a reactor trip.
- c. The power defect is more negative at beginning of core life because of the higher boron concentration.
- d. The power defect necessitates the use of a constant Tava program to maintain an adequate Reactor Coolant System subcooling margin.
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1,...' REACTOR PRINgIELES (7%) THERMODYNatilQS Page 7 (7%) AND COMPONENTS PA%) (BLNDAMENTALS; EXAM 1 A i %J %)
-QUESTION 1.04 (1.00)
Which one of the following will result in an increased calculated Shutdown Margin assuming all other conditions remain unchanged?
- a. Reactor Coolant Temperature decreases.
- b. RCS boron concentration decreases.
- c. Fuel burnup is nearing End of Life. ,
- d. Xenon concentration increases.
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~ 1. REACTOR PRINCIELES (7%) THERMODYMMICS Page 8 (7%) AND COMPONENTS /1%) (FUNDAMENTALS EMM1 s_- (J" l'
l QUESTION 1 05 (1.00) l Select the parameters below which BEST describes the specific group of parameters which must be controlled and monitored during the apprcach
.to criticality, in accordance with OP-210, " Reactor Startup."
- a. PZR level, Source Range counts, Intermediate Range amps, Boron I concentration, RCS temperature.
- b. 'RCS temperature, Source Range counts, Startup rate, rod position.
- c. Startup rate, Intermediate Re.nge amps, control rod positions, RCS flow rate.
- d. Reactor Shutdown Margin, ECS flow rate, RCS temperature, Intermediate Range amps, Rod position.
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QUESTION 1.06 (1.00)
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How will the reactivity addition rate to the RCS change, due to a 10 ppm boration at the Beginning of Core Life vs. the End of Core Life? Assume the same feed concentration, same flow rate to RCS and same temperatures.
- a. Remains constant over core life.
- b. Not enough information is pro"ided. l l
- c. Decreases as the core ages. i
- d. Increases as the core ages.
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- 1. RE_6CTOR PRINCIPLES (7%) THERMODYNAlilGS (7%) AND QQUEONENTS_g%) (FUNDAMENTALS EXAti).
{') QUESTION 1.07 (1.00) FILL IN THE BLANK According to Technical Specifications Shutdown Margin is defined as: The amount of reactivity by which the reactor is suberitical or would be subcritical from its present condition assuming:
- 1. No change in axial power shaping rod position, and
- 2. control rod assemblies (safety and regulating) are fully inserted except for the rod assembly of the reactivity worth which is assumed to be fully withdrawn. ]
WRITE ANSWERS BELOW IN ORDER OF THE BLANKS:
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~ 77%FANDCOMPONENTSgl%) (F,U@bMENTALS EXAM) ()
i QUESTION 1.06 (1.00) Which one of the following describes the chances to the stear that occurs accross the throttle block (nozsles) of a real (not ieleal) turbine, but prior to impinging on the turbine blades?
- a. Enthalpy decreases, quality constant.
- b. Enthalpy increases, quality constant.
- c. Enthalpy constant, quality decreases.
- d. Enthalpy decreases, quality decreases.
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1 REACTOR PRINCIPLES (7%) THEBdQDYNAMICS Pcga 12 (7%) AND COMPOhENTS &l%) ( F.U @ R IE N T A L S E X A M ) ; '3 W x/ l QUESTION 1.09 (1.00)
.Which one of the below requ$ es the most heat removal during condensation? Assume steam is of equal quality.
- a. one pound of steam at 1 psia, b, one pound of steam at 300 psia.
- c. two pounds of steam at 600 psia.
- d. two pounds of steam at 1200 psia.
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- 1. ' REACTOR PRINCIPLES (7%) THEBdQDJ.H6MLGE Page 13 (7%) AND COMPONENTS & l%) (FUNDAMEHIakS_EXAtil /^\
W U QUESTION 1.10 (1.00) Which one of the following statements is CORRECT concerning a secondary calorimetric?
- a. If feedwater temperature is read erroneously high, then the calculated reactor power will be higher than actual.
- b. The calorimetric equation includes the heat added by the reactor coolant pumps as a negative factor and the heat lost to the containment atmosphere (ambient losses) as a positive factor.
- c. Mass flow rate of the secondary system is determined by totaling the average steam flows from each of the steam generators.
- d. The results of the secondary calorimetric may be used as the basis for calibration of the power range nuclear instrumentation provided indicated power is greater than 75%FP.
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1 ., REACTOR PRLlLQlELES (7%) THERMQDllibdiqS Paga 14 (7%) AND COliPONENTS g 11) (FUNDAMENTALS EK6til (] ) I l QUESTION 1.11 (1.00) Given the following data: , RCS flow ...... ..... 1.5 E8 lbm/hr : Thot ................ 606 des F j Teold ............... 554 deg F Tave ................ 580 deg F ; Superheat ........... 35 deg F OTSG pressure ....... 850 psig Feedwater Temp ...... 480 deg F Feedwater Flow ...... 1.3 E7 lbm/hr OTSG level .......... 88 % l Cp ............. .... 1.25 BTU /lbm des F ! I Select the value below that most closely matches the calculated cole power. l
- a. 2300 MW i d
- b. 2500 MW t
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- c. 2700 MW l
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- d. 2900 MW s
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~~ ~ Tf/% ) AND COMPONENTS " 1%) (FUNDAMENTALS EXAll ( )
W (_/ QUESTION 1.12 (1.00) Which one of the following is NOT an example of conditions which can rosult in water hammer?
- a. Sudden closure of a valve in a system in which there is water flow,
- b. Cavitation occurring at a flow orifice in a closed system.
- c. Rapid pressurization of a properly filled and vented system.
- d. Starting a pump on a partially empty system.
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- _ , _ , = -- . . . 11!' E R 4 EACTOR PRINCIPLES (7%) THERMODYNAMICS . .
Paga 16-c.!r . . (7%) AND COMPONENTS ^1%) ~ (FUNDAMENTALS' EXAM)- . I, t= ,
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- QUESTION ~' .1 13. (1.00)
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;Which factor below,has a direct.effect en Hot Channel Factor?.
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- a; ' Reactor.~ power- .
ib. RCS average temperature ..
- c. 'RCS: flow
.d. 'RCSl pressure rl i
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(7%) AND COtiEQ 1%) FUNDAMENTALS EXAtil ( ') l QUESTION 1.14 (1.00) j Which one of the following situations best describes a condition in which pressurized thermal shock concern exists. Refer to Enclosure 2 of l 1 EP-390, attached, if desired, j A small break LOCA has occurred: 1
- a. HPI has initiated, all RCP's are operating, the RCS )
temperature is 530 F and the RCS pressure is at the PORV l setpoint. ; (
- b. HPI has initiated, all RCPs are shutdown, the RCS temperature is at 490 F and the RCS pressure is at the PORV setpoint.
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- c. HPI has initiated, all RCPs are operating, the RCS temperature is at 450 F and the RCS pressure is at 1900 psig, l
- d. HPI has initiated then stopped, all RCPs are shutdown, the RCS 1 temperature is at 400 F and the RCS pressure is at 1700 psig. j i
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21.< REACTOR'PRlHQIPLES (73) THERMQDYNAMICji Page'18~ (7%)- AND QQtRQNENTjijs/N1%)- (FUNDAMENTALS EX6ti). A-I t
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( .. I QUESTION- 1.15 (1.00) l .. I: -Which one of the following statements about pump Net Positive Suction l HeadL(NPSH) is CORRECT? I: ji a. NPSH is the amount by'which the saturation pressure is greater l. than the euction pressure for'the' water being pumped. ,
- b. When a pump is started, the NPSH will decrease by the amount Lof the pressure drop in the suction piping.
- c. NPSH is essential for. operation of. centrifugal pumps but not for positive displacement pumps.
'd.. NPSH can be. calculated by subtracting the suction pressure from the discharge pressure.
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L 11 -REACTOR PRJNCIPLES-(7%) THERMODYNAMIC . Paga 19 (7%) AND-COMPONENTS 1%) (FUNDAt9EIALS. EXAM) i
,UESTION' Q 1.16 (1.00)
-Which orie of the following best describes the steam relief capacity
.of the Main Steam System?
L a. The code safeties must be combined with the atmospheric dump valves to have a capacity of 100%, with relief settings from-l p- 935 psig to 1010 psig. 1
- b. The. code safeties must be combined with the atmospheric dump y valves to have a capacity of'100ti, with relief settings from L 1010 psig to 1150 psig.
- c. The code safeties do NOT hase-to be combined with the atmospheric dump valves to have a capacity of'100%, with l relief settings from.1050 psig to 1100 psig.
- d. The code safeties'do NOT have to be combined with the
! atmospheric dump valves to have a capacity of 100%, with relief settings from 935 psig to 1025 psig. i i
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- li IPJtACTOR PRINCIPLES (7%F THERMODYNAMICS
.Pego 201
* , (7%)"AND COMPONENTS ^ 1%) (FUNDAMENTALS EXAM)
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t 1 QUESTION 1.. '17 . ' (1. 00 );
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cAn operator drops his/her self-readinE' pocket dosimeter (SRPD)' . rasulting in-no. physical ~ damage but only a1 partial discharge of.the- '
.SRPD.
The SRPD'will then:
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-a. ' Read. lower than actual exposure. y
'b. . Read higher than-. actual exasure.
- c. ' Fail as is.
- d. . _ Read equal to actualLexposure.
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- _ _ - . _ _ - . _ _ - ,. -_ _ - = _ _ _ . _ _ _ _ _ _ _ . _ .
F Y1. : REACTOR \ PRINCIPLES (7%iiTHRMODYNAMICS .. :Pega 21: [.. e.~--(7%)"AND CQtiPONENTS ^1%) 4 FUNDAMENTALS' EXAM) Q, 7 d' i K iQUESTION: 1.18 ' - (1.00) E% .
,Tho: plant'has experienced a loss-of-coolant. accident:(LOCA)'with. degraded
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. 1 safety. injection flow. The reactor coolant pumps are manually tripped and. L'7thel':;resultingphaseseparationcausesthe. upper'portionof'the:coreto
. uncover.
p lWhich'one of the'following: describes Excore Source Range (BF3) neutron level ~ indication as'the core begins to uncover. The detector count' rate ~should:
- a. . increase as the cora uncovers. .
- b. decreases as the core uncovers.
- c. remainsLfairly. constant as the core uncovers.
- d. ' oscillate severely as the core-uncovers.
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- 1. REACTOR PRINCIPLES (7%1_ THERMODYNAMICS Paga 22 (7%) AND COMPOHEMIS_ % JMHDAMENTALS_EXAMA O.
m-3 l QUESTION 1.19 (1.00) f Which one of the following best describes the safety procedures and/or I precautions for positive displacement pumps.
- a. Like the reciprocating pump, to protect a rotary pump from damage it should be provided with a relief valve in the discharge line and should never be run without an open discharge path.
- b. Unlike the reciprocating pump, to protect a rotary pump from damage it should be provided with a relief valve in the suction line and should always be started with a closed discharge path,
- c. Like the reciprocating pump, to protect a rotary pump from damage it should be provided with a relief valve in the suction line and should alwa;rs be started with a closed i discharge path.
- d. Unlike the reciprocating pump, to protect a rotary pump from damage it should be provided with a relief valve in the discharge line and should never be run without an open discharge path.
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- REACTOR ~ PRINCIPLES (73) THERMODYNAMICS -
Pasa 23 '-1 (7%)-AND COMPONENTS - %) (FUNDAMENTALS EXAM) .A~ =l V i, 4 , s d 4 El 1
; QUESTION-. l'.20. . ( 1. 0.0 ) ;
iWhich one of1the following most accurately ~ describes.:the effects'on a .j
. heat exchanger whenEa tube failure-(leak)toccurs. Assume the high
. pressure side:is the hot fluid, it is a counter flow' heat exchanger- j]
and'both mediums are' vater. The hea't transfer rate: , decreases because the flow rate out.of the-high pressure side 'I
- a. <
< of the heat-exchanger effectively decreases. ,
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- b. . increases-because:the surface area of the.he'at exchanger ~,
' effectively decreases...
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- c. increases-because the-thermal conductivity (heat transfer coefficient) . of the heat exchanger effectivel:- increases.
- d. decreases because.the thickness of the metal separating'the two mediums effectively decreases.
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L REACTOR PRINCIPLES (7%) THERMQDYNAMICE Page 2 (7%) AND COMEQEKl q 1%) LFUNDAMEETALS EXAtn l l l l QUESTION 1.21 (1.00) l l Which one of the following is a correct statement regarding the ! op3 ration of a 480 volt non-ES load center feeder breaker? l l l l
- a. If the ccntrol power fuses are blown, the load may still be operated using the local handswitch, l
! b. The load center feeder breakers can be closed without the I respective 4160 V supply breakers being closed. l
- c. With the local-remote switch in local, the control room l maintains breaker indication and tripping control.
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- d. When operating a breaker locally, placing the local-remote switch in local bypasses the breakers tripping circuits.
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l 1. -REACTOR PRINCIPLES (7%) THEEdQDYN&dlCE Page 25 17%) AND COMPONENTS ('Q%) (FUNDAMENTALS EX601 l I QUESTION 1.22 (1.00) Which one of the following BEST describes why successive starting cycles on large motors, such as RCPs, are strictly limited?
- a. Large motors have large inertia problems to overcome causing excessive wear and heat on bearing surfaces, due to the weight of the motor.
- b. The switchgear supplying these motors is susceptible to overheating and insulation damage, causing flash-over on the bus work.
- c. The cooling systeras for the switchgear are not adequate to maintain the switchgear cool, when such motors are started multiple times in quick succession.
- d. The motor windings are more susceptible to overheating and inuulation breakdown due to the large current draw on start, and minimal cooling air flow on initial rotation.
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- 1. REACTOR PRINCIELES (7%) THERMODYNAMICS Paga 26 (7%) AND COMPONENTS g l%) (FUllDAMENTALS EXAtil ]
QUESTION 1.23 (1.00) In procedure OP-402, Section 3.2, " Makeup & Purification Systen " there is a caution which states, " Exercise caution when placing the demineralizers in service." WHAT is the purpose of this precaution?
- a. Reactivity changes can result causing undesired power changes from the removal of boron from the coolant,
- b. Pressure changes can result if the demineralized has not been properly filled and vented causing cavitation in the Makeup pump.
- c. Large amounts of Lithium will be removed from the primary causing a change in pH and an increase in primary activity.
- d. Temperature change on the demineralized inlet can damage the resin esusing chemistry problems and release of resin to the makeup system as the resin breaks up.
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! - t/ QUESTION 1.24 (1.00) 1 Complete the following statement from the choices below. When para 12eling an AC generator to the commercial power grid, the i voltages must be in phase at the instant of paralleling otherwise the difference can damage: j
- a. Ioads on the grid because of the instantaneous shift in the voltage sine wave.
- b. the generator because it will act as motor with little or no reverse current through the breaker.
- c. the grid transformers because of the instantaneous shift in the current cosine wave.
- d. tne generator because of the high currents induced by the voltage potential between phases.
(***** END OF CATEGORY 1 *****) I
~2.
EtiERGEl4CY AND ABN PLAliT EVOLUTIONS Pa:;;a 28 ( 27<q ('s
<-)
lS a e et er) bio"!AN SLd
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l 2 .~ GENCY-AND~ABNORMA PLANT' EVOLUTIONS Page 29 [, QUESTION- 2.01 (1.00) L. s . . . Which one of the following.is a Limiting Condition for Operations concerning Movable Control Assemblies Technical Specifications?
- a. 'All-safety, regulating and axial power shaping control reed
-switch position indicator channels and pulse stepping position l-
. indicator channels shall be operable and capable of determining the control, rod position within +/- 2%.
l b. All safety: rods shall be operable and positioned within +/- 9%
-(indicated position)'of their. group average heicht.
- c. The individual safety and regulating rod drop time from the fully withdrawn position shall be less than or equal to 2.1 seconds from power interruption at the control rod drive breakers to 3/5' insertion with Tave greater than or equal to 525 FLand all RCPs operating.
- d. All axial power shaping rods (APSR) shall 1xr operable and shall be positioned within +/.- 6.5% (indicated position) of their group average height.
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- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pcg3 30 (27%1 g ( ']
l QUESTION 2.02 (1.00) Which one of the following is the IMMEDIATE ACTION step of AP-580, "R:; actor Trip", that requires the operator to concurrently perform EP-140, " Emergency Reactivity Control", if the step is not satisified?
- a. Ensure CRD group 1 through 7 are fully inserted.
- b. Ensure Intermediate range flux is decreasing.
- c. Is Shutdown margin less than 1%.
- d. Verify TVs and GVs are closed.
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l2 . EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Pega 31 (27%) g (' t QUESTION 2.03 (1.00) Which one of the following is a required method of providing boron to the core when " Emergency Reactivity Control' is require by procedure EP-140?
- a. Borate to Makeup Tank using the Batch Controller for a 50 ppm boron change.
/
/
- b. Open MUV-103, 107, 158 to bypass Batch Con' troller and then open CAV-60 (discharge from Boric Acid, pumps) to deliver boric acid directly to makeup tank for injection to RCS.
/
- c. Open MUV-73, (MakeuppumpsuctionfhomBWST) and charge at maximum flow. /
- d. Open MUV-103, 107, 158tobypa'$sBatchControllerandthen open WDV-38, 40, or 42 (RC Bleed Tank supply to makeup system) to deliver boric acid directly to makeup tank for injection to RCS. ,
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- 2. EMERGENCY AHD ABNORMAL Pk&EI EVOLUTIONS ,
Paga 32 l (27%1 , l l 1 QUESTION 2.04 (1.00) i i i Which one of the following is the reason for establishing Reactor Building cooling units on Service Water instead of Industial Cooling System, if there is a fire in the Auxiliary Building, according to AP-880, " Fire Protection?" ;
- a. The SW system routing is different than the normal Industrial Cooling system and thus better protected from fire.
- b. No automatic fire protection system exists for the Auxiliary Building.
- c. The Industrial Cooling flow is needed to provide cooling to the staging area for the fire fighting team.
- d. When the SW valves fail as is, a safe condition exists, in case of a safety system actuation.
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- 2. EMERGENCY AND AENORMAL PLANT EVOLUTIQllS Pcca 33 (27%) g ()
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I f I QUESTION 2.05 (1.00) q Which one of the following is the reason that the operator must ensure that the automatic bus stripping occurs as programmed during en undervoltage condition on the ES 4160 V bun, subsequent diesel cterting or energising with other sources according to AP-770,
" Emergency Diesel Generator Actuation?"
- a. To prevent the diesel from picking up the bus in a loaded condition,
- b. To prevent overspending of the diesel when picking up the load.
- c. To prevent arcing of the feeder breaker when closing, thus causing another undervoltage spike in the circuits.
- d. To prevent any fault on the system from feeding through and damaging the energising source.
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- 2. EMEltqENCY AND ABNORMA1_EldHT EVOLUTIONS Peca 34 Lgl%_), g 7 's, v.<
l l QUESTION 2.06 (1.00) Which one of the following is the reason most likely for evacuating tha containment when a spent fuel element is found to be laying ceross the top of the core at a 45 degree angle after removing the racetor head and upper internals.
- a. Radioactive gas leakage is probably occurring.
- b. Radiation levels are high due to the reduced refueling canal water level.
- c. Any additional movement in the canal will cause the fuel element to fall further.
- d. A critical condition exists with the fuel in this configuration and personnel exposure must be minimited.
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- 2. EMERGENCY AND ABriDRMAL PLnNT EVOLUTIONS Paga 35 (27%) g (')
v QUESTION 2.07 (1.00) Which one of the following valves must be verified by the operator as IMMEDIATE ACTION of procedure AP-460, " Steam Generator Isolation Actuation"? Assume the malfunction is occurring in "A" OTSG.
^
..utomatic closure of FWV-40, Main Feed Bypass Valve.
a.
- b. Automatic opening of FWV-35, Main Feed Bypass Isolation Va]ve.
- c. Automatic closure of FWV-28, A&B Feed Cross Connect Valve.
- d. Automatic opening of FWV-19, Main Feed Pump Recire Valve.
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. cJ21% Q 4 1 EQUESTION 2,08 L(1. 00 )- q""' . .,
- Which one of':the following is'the reason for the: expected level change'
;, 'of.,approximately'10%.on various instruments following a steam e J1cak inside the. reactor building according to a NOTE found in AP-460,
.e
" Steam Generator.Icolation. Actuation?"
- a. pressure increase in the containment.
b.' Temperature' increases in'the containment.
- c. . Humidity changes in.the containment.
d; Flooding of instruments in t'ne, lower containment. l-1
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Paga 37 !
- 2. EMERGENCY AND 6BNORMAblMNT EVOLUTIONS L22.%1 ()
a QUESTION 2.09 (1.00) Which one of the following is the most desirable method of fighting a high voltage electrical fire with water, according to EM-216, " Duties of the Nuclear Plant Fire Brigade?" 1
- a. Straight stream directly on fire from et least 50 ft.
- b. Wide pattern fog from at least 10 ft.
- c. Fog / stream combination from as close as possible.
- d. Narrow fog pattern from at least 40 ft.
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L EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 38 (27%) g ~ l } QUESTION 2.10 (1.00) i Which one of the following is the proper response of the Emergency Diesel Generator when control is transferred to the Remote Shutdown Panel following a Control Room Evacuation? 1
- a. The automatic control functions are unaffected except i automatic voltage control which is shifted to the generator j control panel. j
(
- b. The engine will be able to auto start, but must be loaded t manually by the operator.
- c. The engine must be manually stnrted using the e:nergency circuits, and will automatically load equipment afterward.
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- d. The automatic control functions are bypassed and the engine must be manually started and loaded from the remote panel and switchgear. !
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- 2. EMEB91NCY AE_AMQBMAL PLANT EVOLUTIONE Page 39 (27%) g ('"/3 s_
QUESTION 2.11 (1.00) Which one of the following is the reason that one Nuclear Operator should stay behind in the Control Room during an evacuation of the Control Room if conditions permit, according to AP-990, " Shutdown Outside Control Room?"
- a. To provide the SSOD early indication conditions which allow return to the control room following the fire.
- b. To operate controls that are not transferred to the Remote Shutdown Station, and provide untransferred indications to the remote stations.
- c. To direct fire fighting actions of the Fire Brigade, in an effort to minimize damage to' vital plant equipment.
- d. To perform channel checks with the operator at the Remote Shutdown Station and monitor the plant during the transfer.
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.a EMERGENCY AND ABNQBd L PLANT EVOLUTIONS Pa33 40 f27%)- /")
v QUESTION 2.12 (1.00) Which one of the following is NOT an IMMEDIATE ACTION of EP-290,
" Inadequate Core Cooling?"
- a. Ensure OTSGs are at 95% level.
- b. Ensure the Reactor is tripped.
- c. IF LPI is delivering flow THEN ensure full LPI flow.
- d. Ensure full HPI flow.
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'2. EMESQENCY AND.6BNORMAL PL6NT EVOLUTI.Q M Pcg3 41 j (27%) g (s) u i
i l i QUESTION 2.13 (1.00) { l Which one of the following is the retson that the OTSG pressure must { ba maintained above 100 psig if Emergency Feed Pump #1 is not j cynilable during execution of Emergency Procedure, EP-290, " Inadequate j Core Cooling?" 1
- a. To ensure enough steam pressure to operate Emergency Feed Pump
#2.
- b. To prevent flow from the Auxiliary Steam system to the j Emergency Feedwater Pump during the emergency. j
- c. To provide adequate flow through the tueline bypass valves for plant cooldown.
- d. To ensure the OTSG temperature stays high enough to maintain an adequate heat cink for the RCS.
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R. EMERGENCY AND ABNORMAL PLANT EVQhDTJONS Page 42 (27%) g ('] 1 QUESTION 2.14 (1.00) Which one of the following is the reason for closing or verifying the Main Turbine Throttle and Governor Valves are closed following a reactor trip per the IMMEDIATE ACTIONS of AP-580, " Reactor Trip?" 4
- a. To ensure the Main Generator is removed from the grid and ,
power is transferred to off-site for the Vital buses.
- b. To allow the Turbine bypass valves to control the OTSG pressure and plant cooldown rate.
- c. Stop overcooling leading to possible emptying the PZR and a saturated RCS. .
- d. To allow the rapid breaking of the condenser vacuum so plant temperature control can be transferred to the atmospheric relief valves.
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- 2. EMERGENCY AND ABNORMAL LANT EVOLUTIONS Pcga 43
-121%_1 (~'s
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) QUESTION 2.15 (1.00) What is the purpose of ensuring that Pressurizer Level is greater thnn or equal to 50 inches in the IMMEDIATE ACTIONS of AP-580, "R: actor Trip?"
- a. To prevent uncovering pressurizer heaters,
- b. To provide automatic pressurizer level control.
- c. To prevent loss of letdown from the RCS
- d. To provide the operator with a setpoint at which additional ;
action is required. L i i I I i l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i l l
! 2 EMERGENCY AND ABNOR@ b PLANT EVOLUTIONS Paga 44 l iRZll "'T } (V j QUESTION 2.16 (1.00) Which one of the following is an entry condition for AP-360, " Loss of Dacey Heat Removal?"
- a. Refueling is in progress with the core off-loaded to the' spent fuel area when a leak develops in the "A" RCP seal package.
- b. During cooldown at 250 F the "A" train DHR pump trips on overload leaving only the "B" train pump to continue cooldown.
- c. Cooldown to cold shutdown is continuing with both trains of DHR when DHV-42 sump suction valve is opened causing air binding of both pumps,
- d. Loss of off-site power during cold shutdown conditions prior to start of refueling and the failure of the "B" train EDG to start on an undervoltage condition.
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j i QUESTION 2.17 (1.00) l Which one of the following will be used to dictate the best alternate heat removal method required after a loss of Decay Heat Removal. according to a NOTE in AP-360 " Loss of Decay Heat Removal?"
- a. .The total flow rate to the RCS at the time of the loss. l
- b. The status of contaiment integrity. !
- c. The availability of incore temperatures and RCS conditions.
- d. The availability of makeup flow from normal injection.
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p"'2; ENrnar4CY-AND' ABNORMAL PLANT EVOLUTIONS' . Paco 46. [l , : ( 270 : g - (^g [: QdESTION-
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2.18 :(1.00) [-:: ,. .. j LAssuming a tube rupturelin on OTSG has occurred, which one.of the.... . following is the expected RCS verage te e hen ruptured OTSG at'1000 psig?' cA WW gettg05 15 * */O g<flli A the
- a. 531-F' f b; 537 F
- c. 543-F-
- d. 549 F' ,
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-QUESTION 2.19 (1.00)
LUning Enclosure 2 of.EP-390 attached to the rearLof the exam and the following plant conditions: RCS temperature: 425 F RCS pressure: 1100 psig
-No. of RCPs: 3 Tube Rupture in: OTSG A Cooldown rate: 55 F/hr Which one of.the following limits is being violated?
- a. NDT
- b. Fuel. pins'in compression
- c. Saturation
.d. Subcooling margin i
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i 2. EMERGENCY AND ABNORM > ELANT EVOLUTIONE _ Paga 48 l 127%) /~N l L) l l QUESTION 2.20 (1.00) ! AP-380, ES Actuation, step 3.14 states "IF, at any time while performing this procedure, RCS PRESS is > 2300 psig, THEN open the PORV to lower RCS PRESS to approx. 100 psig above OTSG PRESS." Which one of the following is the reason this action is taken?
- a. Ensures maximum HPI flow while ensuring maximum subcooling l margin. I
- b. Ensures adequate HPI flow along with minimizing releases to the reactor building.
- c. Ensures maximum HPI flow without allowing the OTSGs to become heat sources.
I
- d. Ensures the desired HPI flow and prov3 des assurance that the FORVs are operable.
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- 2. EMERGENCY AND ADtLQBliAL_ELANT EVOld!IlONS Page 49 (27%) j ')
p a I QUESTION 2.21 (1.00) Which one of the following is "the primary" reason for manual cctuation of Engineered Safeguards Actuation System?
- a. As a backup to the normal automatic actuation system.
- b. Ensure actuation prior to automatic system actuation when the operator knows it to be required,
- c. As a means of easily testing the function of the ES system.
I
- d. To provide an auxiliary method of actuation when normal actuation power is lost.
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'2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Paco 50 (27%)' r q )T e t ' QUESTION 2 22 (1.00)
What IMMEDIATE MANTIAL ACTIONS are required by the operator if the reactor control rods fail to insert on a Reactor Protection System Actuation according to AP-580, " Reactor Trip?" l l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i L _
if d V L QUESTION- 2.23 (1.00) L l Whichfone of the following is NOT an Entry Condition into AP-580,
'"R3 actor. Trip?"
l l' a .- Reactor Power'at 103.5% FP. L b. RCS Press at 1750 psig.
- c. RB pressure ~at 5 psia.
d'. Turbine Trip with Rx power at 55%. I l i i (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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-- o l ' .2i EMERGENCYJANDiABNORMAL PLANT' EVOLUTIONS-Pago.:52; -1 l
S :(27%)ru .
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, . QUESTION-- 2.24 (1.00)
, Which one of.theifollowing is the reason for bypassing'and throttling- 1 ithe'HPI flowito obtain equal flow to all four injection lines' according'to the CAUTION priortto~ step 3.6.of AP-380, " Engineered SafeguardsLActuation?" .
1 a.- To. Prevent overcooling condition in the reactor vessel.
.b. .To ensure ~adequat'e NPSH to the HPI pumps
- c. .To establish proper conditions for." piggy back" operations, a Ld. To prevent HP1 pump runout.
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l: 2. EMERGENCY'AND ABNORMAL PLANT EVOLUTIONS Page 53 l (27%) () l-l QU TION 2.25 (1.00) , i Assum Tag the following plant indication exist: l , l R Temperature: 579 F Tave ' RCS essure : 2100 decreasing at 100 psig/ min l~ PZR T rature: 643 F decreasing at 6 F/ min j
- j. PZR leve : constant with 2-3 gpm increase in makeup l- RCPs runni : 4 RB pressure : normal (no increase)
Reactor Power 40 RCP seal inj. :\co%rmal Which one of the following is he MOST probable situation developing? l-l a. Small break LOCA
- b. Stuck open PZR spray valve l ,f j c. PZR steam space leak i
- d. Letdown line leak i.
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- 2. EMERGENCY AND AlHipRMAL PLANT EVOLUTIONS Pcga 54 I
~(279Q .
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QUESTION 2.26 (1.00) Which one of the following is the reason why LPI, HPI and BS I will be shifted to the recirculation mode during a Small Break LOCA?
- a. The NPSH to the UPI pumps will be lost if suction is left on the BWST with level below 4 feet.
i
- b. The BS pump will begin cavitating unless its suction is )
shifted to the RB sump. 1 I 1
- c. To establish " piggy back" cooling mode the LPI must be taking {'
a suction from the RB sump.
- d. A more dilute boron concentration is allowed at this point in j the accident and therefore the shift is desirable. '
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~ RESPONSIBILITIES (lo g [ ,
FAis Paye Inbendiona lll ' B la k ) 1 l I i ( (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) f j
l 3 '. ELANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Peca 56 [ RESPONSIBILITIES (10gg (' '} l-l l i QUESTION 3.01 (1.00) Which one of the following BEST describes the reason that Emergency i Focdwater can have a proportionally larger cooling effect on the RCS ' then Main Feedwater, assuming the same flow rate and all RCP's are in op ration?
- a. EFW is injected into the steam space.
- b. Main Feedwater is NOT counter flow to the tubes.
- c. OTSG pressure is higher during EFW flow conditions.
- d. EFW is injected into the outer wrapper area of the OTSG.
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[- EBESZONSIBILITIES (1@r i > v/ U l l l QUESTION 3.02 (1.00) Which one of the following statements is accurate concerning the OTSG's?
- a. Primary and secondary side blowdown (during plant heatup) is accomplished by means of drain connections near the lower tubesheet,
- b. The startup range instruments will provide indication when the aspirating ports are flooded.
- c. The auxiliary feedwater header penetrates near the top of the OTSG shell and sprays the feedwater on the upper cylindrical baffle.
- d. The orifice plates, located in the lower downcomer section, are adjusted to balance the tube bundle and downcomer flow regions, thus preventing oscillations in OTSG level.
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A f32 ~ PLANT ' SYSTEMS : ( 3810 'AND PLANT-WIDE ' GENERIC - . .
. Pena 58-2 RESPONSIBILITIES (10 ' f% -
p y 1 V: L: L k " QUESTION '.03
~
(1.75)- L MATCH the actuation setpoint(s) value(s) in COLUMN B to Engineered
' Safety Features in COLUMN A. NOTE: ._ Items in COLUMN B may be used.
L Jmore than once, and' items.in COLUMN A may have more than:one
- corresponding match in' COLUMN B.
COLUMN COLUMN B o .___________________A _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . . __________________________
- 1. 500 psig-h l-
'a. :High Pressure Injection 2. 900'psig
- b. . Low Pressure Injection 3. 1500 psig
- c. Reactor' Building Isolation 4. 1700 psig
- d. ReactorTBuilding Spray. 5. '4 psig L 6. 7~psig g
- 7. 20psig-
- 8. 30 psig
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~~EESP.QNSIBILITIES(10g ( ')
i l QUESTION 3.04 (1.00) Which one of the following parameters is used to determine if the Main Feed Pumps have tripped, and thus enable the automatic start of tho EFW pumps?
- a. Low pump discharge flow.
- b. Low discharge header pressure and low lube oil pressure.
- c. Low lube oil pressure and low shaft RPM.
- d. Low control oil pressure.
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- 3. PLANT SYSTEMS (38%) AMD_ELANT-WIDE GEEERIC Page 60 RESPONSIBILITIES (10 -
(~ QUESTION 3.05 (1.00) Which one of the following is the purpese for shifting the Reactor Building Main Fans to slow speed following a Safeguards signal actuation?
- a. The fans are pumping a denser air mixture resulting in an excessively high motor load,
- b. The power required by the fans in fast is needed for operation of other safety equipment.
- c. The fan motor cooling is not functioning in fast speed after the Safeguards signal actuation.
- d. The cooling load is low and the operator can shift the fans high speed if required.
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RfSFCNSIBILITIKEi1CO O QUESTION 3.06 (1.00) Which one of the following is correct concerning HPI Safeguards Actuation?
- a. HPI Actuation Sequence is divided into four blocks for loading various equipment to its electrical buses.
- b. If HPI Actuation is bypassed prior to pressure falling below 1700 psig, then when a subsequent LPI Act tation takes place, the HPI would not actuate.
- c. Diverse Containment Isolation occurs at both the 1500 psig setpoint and the 500 psig LPI setpoint.
- d. Manual Actuation will result in the automatic Diverse Containment Isolation regardless of pressure.
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lim PLANT SYSIEMS (38%) AND PJdFT-WIDE GENERJ_Q P o 62 BESPONSIBILITIESf1qgg (]) QUESTION 3.07 (1.00) Which one of the following is NOT required to actuate the Rapid Feedwater reduction circuit?
- a. Reactor trip.
- b. One main feedwater pump turbine reset,
- c. Startup control valves in manual.
- d. All four feedwater control valves in automatic.
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- 3. PLbNT SX$1Eti3_138%) AND PLAHT-WIDE GENEBJS Page 63 BESD2HSIEILIIIES (ig Q l
l' QUESTION 3.08 (1.00) Which one of the following is the power supply to the Air Handling Fan AHF-1C for containmen.t cooling? I
- a. ES Bus 3B
- b. Reactor MCC-3A
- c. ES MCC-3AB
- d. Vent MCC-3B I
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3: PLAET SYSTEMS _L18%) AND PLANT-WIDE GENERIC P2;e 64 j REEEQN_EIplh1 TIES (10 ^ l w (~)i w l l QUESTION 3.09 (1.00) l i Which one of the following is the reason for providing 15 gpm { bypass flow around MUV-31, Makeup Control Valve? j
- a. prevent thermal stress on the RCS injection nozzle.
- b. ensure constant makeup flow if MJV-31 fails shut.
- c. prevent damage to charging pump due to loss of flow. j
- d. set the total operating range of MUV-31.
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RESPONSIBILITY 7ES(log } QUESTION 3.10 (1.00) Which cne of the following is a function of the Emergency Feedwater Isolation and Control System?
- a. Controle FWV-39 & 40 uben Feedwater is being supplied to the high nozzles,
- b. Terminata m in feedwater to prevent OTSG overfill.
- c. Control - t:.uspheric dump valves.
- d. Terminates heat load by tripping the reactor.
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- 3. PLANT SYSTEMS _(38%) 1.ND PLfNT-WIDE 3 GEHERig Pcg3 66 EESPO!?SIBJJ ,(];
QUES 710N 3.11 (1.00) Which one of the following is NOT a source of makeup throust primary food valve MUV-103, when the Feed Permissives are met?
- a. Borated Water Storage Tank l
- b. Deborating Demineralizers
- c. Normal Boric Acid Tanks
- d. Demineralized Water Tanks
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- 3. PLANT SYSTEMS (38%) AND PLANT-Wlp3_{$hTRLG. '
Peca 67 BESPOl@IBILITl ( ; QUESTION 3.12 (1.50) Whnt TWO radiation monitoring instruments are capable of causing automatic isolation of liquid discharge to the Plant Discharge Canal by shutting the Liquid Waste Discharge Isolation Valves? INCLUDE in your answer whether or not each monitor you list is related to a specific Technical Specification. Listing of the specific Technical Specification is not required. Setpoints NOT required. \ l { J (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- 3. PLANT SXSTEMS-(38%) AND PLAl{T-WIDE GENERIC Pcga 68 RESPONSIBILITIES (Ir" w
(~') u .. - i QUESTION 3.13 (1.00) < Which one of the following will cause automatic closure of the Latdown Isolation Valve, MUV-497
- a. High Flow i
- b. High Temperature !
- c. High Pressure
- d. High Radiation s
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1, ELANT SYSIEMS (38%) ANQ PLANT-WIDE GEEEBlQ Pcgs 69 ! RESPONSIBILITIES (10ggg {]) QUESTION 3.14 (1.00) Which one of the following, along with the radiation monitoring alarms will prevent the releace of liquid waste, if conditions are not proper to prevent exceeding the Federal Limits for liquid releases? {
- a. Discharge pump flow from the waste storage tank drops below the setpoint.
- b. Less the required Raw Water pumps are operating.
- c. Total circulating water flow does not exceed 1,300,000 gpm.
- d. The low level setpoint is reached in the storage tank.
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?3F LPLAhdTSYSTEMS'(38%) AND PLANT-WIDE'GENERICo '
P 70. RESPONSIBILITIES'(IP"' ' A' 1: - y N/
!';;: y k' {
$ q
- r .l QUESTION ':3.15 _-(l'.00).
.0-
$Whi:n jobLduties require work in and around'the HIC-resin.. fill and
'do-wateringisystem, WHAT is the primary knowledge an operator must '
have',<since?this-system is the-primary responsibility of.the Rad. Waste. tend Health Physics group?' a.: . If spilled, resin, beads are-extremely hard to pickup,
- b. Resin can be.a' slipping hazard if spilled on the floor. '
c, Spent resin is extremely " Hot"-radioactive wise and muut be
. controlled as such. ~ d.. . Once the resin is' dried-it.can not be reused in the plant demineralizers and should be marked accordingly.
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- 3. PLANT SYSTEMS (38%)-AND PLANT-WIDE GENERIC P ca 71
^ RESPONSIBILITIES (1F, T
- (~')
QUESTIONS 3.16 (1.00). Which -ne of the following conditions requires that the affected RCP be' tripped?
- a. RCP seal leakoff high and temperature at 162 F.
- b. Loss of seal injection flow to RCP for 5 minutes due to charging pump trip.
- c. SW surge tank level decreases to less than one foot.
- d. RCP cooling water temperature leaving the pump indicating 185 F.
I f s
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- 3. PLANT SYSTEtiS (190 AND PLANT-WIDE GENERIC Fage 72 1 RESPONSIBILITIES (1P] (]~ :
l QUESTION 3.17 (1.00) Which one of the following BEST describes the reason that RCS pressure must be greater than 400 psig any time RCPs are operating?
- a. To prevent reduction of RCP seal lifetime. ,
- b. To ensure adequate RCS pressure to support the RCP shaft.
- c. To allow for proper operation of the RCS with a bubble in the i PZR.
- d. To ensure proper positioning of the lower RCP radial bearing.
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3; PLAN.T SYSTEMS (38%) AND PLANT-WIDE GEHEBlO Paga 73 EEEPONSIBILITI Q l']) i i QUESTION 3.18 (1,00) Which one of the following is the actuation setpoint for Main Focdwater Isolation by the Emergency Fcedwater Isolation and Control Syntam?
- a. 300 psig
- b. 450 psig
- c. 600 psig
- d. 750 psig l
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3 PLANT SYSTJES (38%) AND PLANT-WIDE GENERIC Pagn 74 BEEPONSIBILITIES(log ('] QUESTION 3.19 (1.00) j Which one of the following is a reason EFW is preferred ove r Main Fesdwater when establishing Natural Circulation from extended operation at 100% power? ;
- a. Main Feedwater would result in a lower thermal center in the {
OTSG. j
- b. EFW produces a quicker overcooling effect on the OTSG to start Natural Circulation.
- c. Main Feedwater usage would require the full time coverage of an operator since automatic level control is not provided.
- d. EFW will result in a visible level in the OTSG of I approximately 2/3 the resulting level when using Main Feedwater.
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- 3. PLANT SYSIEl.iS (38%) AND PLANT-WIDE GEllE81Q Pace 75 RESPONSIBIJ41 TIES Ligh (~')
W u, QU TION 3.20 (1.00) Which o (of the following is correct concerning the Main Steam IsolationVaQes(MSIV)?
- a. Instrum air to the pneumatic operator is delivered through the valve po'sitioner controlling the volume booster valves.
Ns
- b. Local operation is'possible only with the manual handwheel operator. 'N s N
- c. The MSIV main disk is assisten) to open by the steam flow.
N ss
- d. Equalization of pressures across the MSIVs is accomplished by the opening of internal ports during'the first several inches of operator movement toward open. 'N N % >
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- p. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 76 RESPONSIBILITIES (log ,]
l 1 1 i QUESTION 3.21 (1.00) I Wr.fch one of the following is the reason for monitoring the five I highest in-core thermocouple when establishing Natural Circulation j conditions? j
- a. prevent the LOWEST from becoming the HIGHEST thermocouple.
- b. ensure the core temperature is stable and not overcooling.
- c. provide the required delta T between the heat source and the heat sink.
- d. identify thermocouple which are properly tracking Teold.
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- 3. PLASI SYSTEMS (38%) AND_ELANT-WIRE _GEHE819 Pcg: 77 EEEEQHSIBILITIES.(Ig ]
QUESTION 3.22 (1.00) Which one of the following statements correctly describes plant bahavior during a reactor startup, when power is being raised above tha point of adding heat? Assume a linear reactor power increase to cbout 3% power.
- a. Tave will not rise above the corresponding saturation temperature of 532 degF,
- b. Tave will rise and the steam temperature will tend to follow Th.
- c. The OTSGs will remain at saturated conditions and no superheat will be added.
- d. The steam is superheated at zero power conditions and superheat will rise proportionally with power.
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Pega 78 O PMt!L?XfC'MfL Mh. LAND PLANT-WIDE GENERIC BESPON!.lbl,ddXE110/g (~.l v f l l ! QUESTION 3.23 (1.00) i
- Which one of the following is the correct reason for maintaining subcooling margin during Natural Circulation?
- a. The greater the subcooling margin the better the Reflux boiling cooling.
- b. The greater the margin of subcooling (large amount of subcoolind) the better the Natural Circulation flow rate.
- c. When steaming only one 01SG, subcooling margin is monitored in the steaming loop to ensure no voiding in that loop.
- d. Without subcooling Natural Circulation will be interrupted or stopped.
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- 3. ELANT SYSTEMS (36%) AND_ELANT-WIDE _GENEBlQ Page 79 RESPONSIBJJ,ITIES .LLg (]) l i
i R
. QUESTION 3.24 (1.00)
Select the answer below which correctly completes the following statement, regarding the Reactor Building Spray System. Fol_ wing a LOCA reactor building spray in designed t limit post-accident building pressure to:
- a. 30 psig, and then reduce building pressure to approxiraately 25 psig.
- b. 55 psig, and then reduce building pressure to approximately 25 psig.
- c. 30 psig, and then reduce building pressure to approximately 1 !
psig.
- d. 55 psig, and then reduce building pressure to approximately 1 psig. i I
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- 3. PLANT QYSTEMS (38%1_AND PLANT-WIDE GENERIC Pega 80 l RESPONSJJILITIES (Ig (],
i i, I QUESTION 3.25 (1,00) Which one of the following is supplied power directly from a Safety-related DC bus?
- a. ICS control cabinet 1 (ICS-X)
- b. DHP-1B Suction from Reactor Building Sump DHV-43. i l
- c. Fire Service Panel in control room.
- d. Emergency Diesel Generator Air Compressor Motor (EGM-2B).
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W i3i ' P $ A N T S Y S T E M S '- ( 3 8 % F A N D ' P L A N T - W I D E G E N E R I C : Pago,81 RESPONSIBILITIES (1r
'STION 3.262 (1.00')
.d the Emergency Diesel. Generator respond'to a Loss of 250/125.
~
'How'w lVDC'ES Digsel Generator Panel "B" in the EDG control-room (DPDP-6B)?
.a. The)nginewouldnotstart.
' b '. .The engine ould start, come up to speed..and the generator.
would not-en heize.
- c. The. engine would tart, come up to speed and voltage but not-tie >to-the AC bus.
.d. The engine would start a p on overspeed.
%Yq/
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. c3; 'PLANTLSYSTEMSof380 'AND PLANT-WIDE GENERIC .
.. :Paga-82f
% v ERAPONSIBILITIES (1r-((
p4 j >i i' l y 4 { QUESTION ~3.27 (1.00): o-m
.Which'onelof the following is.NOTLa close permit--function / relay.for.
'T ? tho Emergency Die:sel: Generator 3B. f eeder breaker to .the "B" 4160 V L: '
'ES. bus?:
3
.a.-.GeneratorLfieldrelayl, l ' b ',' Synchroscope switch.
- c. Cross-tie' blocking..
,.d. . Diesel ready matrix.
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PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Pasa 83 RESPONSIBILITIES '{}; I l QUESTION 3.28 (1.00) 1 l Which one of the following can be done when HPI is operating in the J
" piggy back" mode with suction from the Reactor Building Sump to reduce the chance of losing HPI?
- a. Maintain specified RB sump level. !
(
- b. Open the HPI discharge valves to full open. !
l
- c. Stop HPI pump every 30 minutes for 3 minutes. 1 l
- d. Throttle the LPI discharge to limit the pressure supplied to the HPI pumps. !
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- 3. ELANT SYSTEMS (38%) AND PLANT-WIDE GENE 8LQ Paga 84 RESEQNSIBILITIES ( I P'""
(_ ) u- '? QUESTION 3.29 (1.00) Whare do the Reactor Building Spray Pumps take their suction?
- a. The boric acid storage tank downstream of valve CAV-660.
- b. The decay heat pump common discharge through DHV-106. j 8
l
- c. Directly from the $WST downstream of MUV-58 suction line to Makeup pumps. i
- d. Downstream of DHV-34 and 35 on the common ECCS suction line. f l
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- i
L _ELANT SYSTEMS (38%) AHL ELANT-WIDE GEHEB19 Paga 85 < EEEE9ESIBILITIES11g [] i l { I QUESTION 3.30 (1.00) { Choose the statement below which BEST completes the following i statement, concerning the Pressurizer PORVs. I Tha Pressurizer PORV will open in automatic control mode when: i
- a. the RCS pressure setpoint is reached and the pilot solenoid energizes,
- b. the RCS pressure reaches the setpoint.
- c. the RCS pressure reaches the setpoint and the pilot solenoid de-energizes.
- d. a key operated switch or_ the main con ~crol board is placed in the LO position.
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- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GEHERIC Paca 86 RESPONSIBILITIES (1C^
- (~)'
w QUESTION 3.31 (1.00) Which one of the following PZR heater banks is controllable at the Remote Shutdown Panel?
- a. A
- b. B {
- c. C
- d. D
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- 3. PL_4NT SYSTEMS (38%) D PLAllT-WI]E GENEB19. Paga 87 RESPONSIBILITIES (10 (~)
s.s QUESTION 3.32 (1.00) Which one the following is correct concerning the Nuclear Services Closed Cycle Cooling System?
- a. Low level in the surge tank will trip the normal duty pump and initiate makeup.
- b. The normal duty pump will automatically shutdown 15 seconds after either of the emergency duty pumps are started.
- c. On an Emergency Safeguards signal (RBI & C) the cooling water supply valves to the Control Rod Drive Motors are closed and the booster pumps are automatically stopped.
- d. The selected emergency duty pump will automatically start based on low system pressure.
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I 3. _ELANT SYSTEMS (38%) AND Page 88 j RESPONSIBILITIES (10gg. PLANT-WJ.DEGENERIC (~})
~
I I l l l QUESTION 3.33 (1.00) 1 Which one of the following is the correct reason for ensuring there ic at least 2700 gpm flow through the Reector Coolant System during and after a boron dilution when shutdown and on the Decay Heat System?
- a. This flow ensures adequate mixing and stratification.
- b. 2700 gpm will cause the equivalent volume of RCS to be circulated completely in a 20 minute period,
- c. Any reactivity change rate associated with the dilution will be recognizable by the operator.
- d. Flow greater than the 2700 gpm prevents boron precipitation on the reactor internals.
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- 3. PMNT SYfETEtis (38%) At[D PMNT-WIDE GENERIC Page 89
]
RESPONS1RILITIES(10g {')
~ .
QUESTION 3.34 ( 1.'00 ) q Which one of the following is correct regarding the response of the I Nuclear Service Raw Water pumps after a LOCA event? I i
- a. Pump RWP-1 remains running and either RWP-2A or RWP-2B will 1 start. .
- b. Pump RWP-1 trips and either RWP-2A or RWP-2B start.
- c. Pump RWP-1 trips and both RWP-2A and RWP-2B start.
- d. Pump RWP-1 remains running and both RWP-2A and RWP-2B start. '
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- 3. PLANT _ SYSTEMS (SC%) AND PLANT-WIDE GENERIC Page 90 RESPONSIBILITIES (10g {)
QUESTION 3.35 (1.00) Which one of the following is correct concerning equipment that is cffected when a Reactor Building Isolation Actuation occurs?
- a. Isolates all Reactor Building penetrations execpt RCP controlled bleed-off.
- b. Starts the Reactor Building Spray pumps in recirculation mode.
- c. Sounde the Reactor Building Evacuation alarm when mode 5 or 6.
- d. Isolates CFV-29 (Core Flood Tank Vent) and CVF-12 (Core Flood Tank level equalizing Valve) 1
)
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- 3. PLANT SYSIggE 138%) AND PLANT-WIDE GENERLQ Pcge di EKEPONSIBILITIES (
(')
.i I
QUESTION 3.36 (1.00) i Which one of the following Decay Heat valves provides overpressure protection for the Decay Heat System?
- a. DHV-41 Outside containment suction isolation valve.
- b. DHV-91 Outside containment pressurizer spray isolation valve.
- c. DHV-3 Inside containment suction isolation valve.
- d. DHV-5 Outside containment return isolation salve.
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3, Pla\NT SYSTEMS (38%) AND PLAT 4T-WIDE GENERIC Page 92 RESPONSIE (] QUESTION 3.37 {1.00) Which one of the following conditions will result in the actuation i of the turbine bypass valves with the HIGHEST bias from its operating cetpoint7
- a. "he reactor is tripped as indicated by a trip CONF light on the diamond panel and decreasing reactor flux.
- b. The reactor is not tripped, and the main turbine is tripped,
- c. The reactor and turbine are not tripped. Steam header pressure deviation is 25 psig below setpoint.
- d. The reactor and turbine are not tripped, all turbine bypass valves are closed and ULD is greater than 15%.
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3- EAFL91SEMS (38%) AND_EAUT-WIDE GENERIC Page 93 EEsiPoNSInn,Ings noa ('~3 W t/
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QUESTION 3.38 (1.00) ! l State the reason the operator is require; to maintain pressurizer ! lovel in accordance with the attnched cur - " Figure 5 - Minimum f Pressurizer Level At Power." i WRITE ANSWER BELOW: i i l I (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l 1 l ) w_______
L PLAUT SYSTEMS (38%) AND PLANT-WIDE GENERIC Fage 94 l' BESPONSIBILLTlES_, , ; [.: I 1
- QUESTION 3.39 (1.00) i What are the TWO design factors which prevent (or reduce) the
- probability of the Reactor Building Sump water flowing to the BWST 1 during the injection systems swap-over to the Reactor Building Sump?
WRITE ANSWER BELOW: l l l-i i l-l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
BEEEQl1SIBILITIES(1rg 4 QUESTION 3,40 (1.00) i In accordance with RSP-101, " Basic Radiological Safety Information and ( Instructions for Radiation Workers", what determines if an area needs j to be a Locked High Radiation Area? l
- a. Greater than 1000 mrem in one hour at one foot.
- b. Greater than 1000 dpm on a swipe carvey of one square meter.
I
- c. Greater than 150 mrem /hr whole Lady and 2 Rem /hr to extremities.
- d. Greater than 0.1 Rem per hour on contact. f i
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- 3. PLANT S,JSIEMS (38Q_AND PLANT-WIDE GENEBIG Pcga 96 s . RESPONSIBILITIES (1g ()
QU$BT, ION 3.41 (1.00) l Which he of the following will cause the grestest biological damage to man?
- a. 1.0 rad of neutron
'N
- b. 1.0 rem df gamma s
- c. 5.0 rad of ta
- d. 0.05 rad of alpha x
'\ j f)
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l 3 '. PLANT SYSTEMS (38%1 Pago 97 l BEEEQF_SIBILITIE 4_AND PLANT-WIQE_GENERIG O l QUESTION 3.42 (1.00) l Which one of the following is a valid method of performing an independent verification for "In-plant Clearances and Switching Orders" according to CP-115?
- a. Two individuals observing the breaker for a component is in the correct position while working together.
- b. One individual observing that a valve is in the correct position LOCALLY, and another individual using a REMOTE indicator to verify valve position.
- c. Two individuals verifying valve position from a remote indicator ONLY.
- d. One individual actually placing a breaker in its required position, then the SAME individual verifying from a remote indicator that the breaker is in the correct position.
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- 3. PL&NT SYSIEMS (38%) . (D... PLANT-WIDE GENERIC Paga 98 -
BESPONSj])LITIES (10 (' ) f i QUESTION 3.43 (1.00) Which one of the following conditions is the most likely situation ' where control room access " lock out" system would be utilized in accordance with AI-500, " Conduct of Operations?"
- a. Large number of maintenance personnel in control room.
- b. Minor plant transients (i.e. shifting of HPI pumps).
- c. Surviellance testing (i.e. Diesel Generator operability test).
- d. ICS runback due to loss of RCP.
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32 PLAHI SYSTEMS (38%) AND Page 99 { ESEQHSIBILITIES_110g_EkbHT-WIDEGENERIC QUESTION 3.44 (1.00) Which one of the following is NOT a respeasibility of plant personnel in carrying out the ALARA program?
- a. Correcting the actions of co-worho s which are counterproductive to the ALARA concepts,
- b. Obtaining and using proper personnel dosimetiy and survey instruments when conducting area surveys.
- c. Knowing RWP requirements, radiation sources, and dose rates associated with their specific assignment.
- d. Tracking their whole body exposure.
)
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S. PLANT SYSTEMS (38%) AND PLANT-HIDE GEEEBIC Pcg3100 BESEQt1SIBILITIES(1g QUESTION 3.45 (1.00) Match the class of fates listed below (A - D) with the materials involved (1 - 4). CLASS OF FIRE MATERIALS INVOLVED
- a. Alpha 1. Flammable liquids, gases, or j greases {
- b. Bravo 2. Combustible metals
- c. Charlie 3 .. Ordinary combustibles (paper, wood, etc.)
- 4. Energized electrical equipment k
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~ ~ ~ BESfg!SIBILITIES(log r^';
\J QUESTION 3.46 (1.00)
Tha minimum site manning requirements of the Plant Fire Brigade is at least members, excluding members of the minimum shift ..:rew necessary for safe shutdown. l
- a. 5 I
- b. 7
- c. 9
- d. 11 l
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2 PLANT SY3TEMS (38%) AND PLANT-WIDE GENERIC Pcga102 BEEPONSIRELIlES_LHg ('] QUESTION 3.47 (1.00) Which one of the following must be available for use, by the confined space entry crew, for rescue operations in confined spaces that are considered Immediat_;y Dangerous to Life and Health 7
- a. Certified medical personnel for CPR.
- b. A charged fire hose for flushing rescuers if contaminated,
- c. Radio for communication with control room.
- d. Rescue personnel ready for entry with Air line respirator. f l
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- 3. PLANT: SYSTEMS (38%l . ANT-WIDE GENERIC
Psiso103
.RESPONDJJILJ11ES (1 V) l QUESTION 3.48 (1.00)
Which one of the following person-rem exposures would equire ALARA review by an ALARA specialist and an ALARA job review.
- a. 0.1 person-rem
- b. 0.5 person-rem
- c. 0.75 person-rem
- d. 1.0 person--rem
/
/
/
/
/
r V/
/
/
/
/
/
/
/
/
/
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- 3. PI&NT t SYSTEME (38%) PLANT-WIDE _ GENE 81Q Paga104 RESPOBSJ31LITIES . (10 ("T) q
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1 1 QUESTION 3.49 (1.00) j l Which one of the following is NOT an immediate action for an ) individual who discovers an emergency condition? i
- a. Notify Security via the nearest intra plant phone, i
- b. Take action to warn other personnel in the area.
- c. Stop machinery that is contributing to the severity of the emergency.
- d. Withdraw to a safe area. 1 I
/
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I i (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********)
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MINIMUM PRESSURIZER LEVEL AT POWER _---__-____-___-____-_O
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, cooldown curves 2600 2400 ADEQUATE SUSC00 LING MARGIN 2200 A 2000 NDT LIMIT
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- 2. 2 RCPs g 1200 3E 1000 / < 2 RCPs
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!=I 10-x/TVL n
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- Eeff)!
- CR 2 (I
- Keff)2 T = 1/ (p - j) M = 1/(1 . K,ff) = CR /CR0 g T
(j - p)/ A,ff, M = (1 . K,ffjo/(1 - K,ff;l p=(K,ff-1)/K,ff=AK,ff/K,ff SDM = (1 - K,ff)/K,ff p=(L*/TK,ff)+(j/(1+A,ff)) T L* = 1 x 10-5 seconds P = IdV/(3 x 1010) l eff A = 0.1 seconds *I I = Na l dg i = 1 d22
- v = s/t Igdf=1d 22 2
s = va t'+ 1/2at2- R/hr - (0.5 CE)/d (meters) a-(vf=v)/t R/hr = 6 CE/d 2 (f,,g) a vf = va + at u = f/t WATER PARAMETERS MISCEttANE005 CONVE0510NS 1 gal. 8.345 lhe 1 Curie = 3.7 x 1010dos lgal. 3.78 liters I kg 2.21 lbs I ft3 = 7.48 gal. I hp = 2.54 x 103 btu /hr Density = 62.4 lbm/ft 3' 1 Mw 3.41 x 106 Stu/hr Density = 1 gV cm3 1 8tu = 778 ft !bf Heat of vaporization = 970 Btu /lbe 1 inch = 2.54 cm Heat of fusion 144 Stu/lbe CF = 9/50C + 32 1 Ata - 14.7 pst - 29.9 in. Hg. OC = 5/9 (OF 32) 2 I ft. H O2 = 0.4335 lbf/in
. _ - - - ___-_--__ a
. 1. REACTOR PRINCIPkES F'Q THERMODYNAMIC f- Page10.5 LBl_ M P COMPONENTSi_jl%) (FUNDAMENTALS EXAM 1. C
.~ ANSWER 1.0'1 (1.00)-
C-REFERENCE CR ROT 1-10, pp 17 Lesson Objective'9 (3.4/3.4)' 192006K106 ..(KA's)
/ ANSWER- 1.02 (1.00) q a
REFERENCE 4 CR ROT.1-10, pp 19-20 l Lesson Objectives 5,6,7,8,9,10 { I (3.1/3.2) j 192006K110 ..(KA's) ANSWER' 1.03 (1.00) b 1 i REFERENCE CR ROT 1-8, pp 23-24 (2.9/2.9) l) l 192004K113 . (KA's) i l l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) ! __m______._.____.__. _i__ _ _ _ _ . . . _ _
f i 1'. REACTOR PRINCIPLES /"~) THE.EMO_pYNAM,I_GE .g, Pago106-
-(7%) AND COff?ONENTSJ _ fl%) (FUNDAMENTALS EXAM). U i
- ANSWER' 1.04 (1 00).
'd REFERENCE CR ROT 1-10, pp.17-20 (2.9/2.9) 192004K110 ' ..(KA's)
ANS"ER. 1.00 (1.00) 1
- b REFERENCE CR Operations Procedure, OP-210, pp 1-11 ,
l ROT 1-12, p. 42 No Facility Lesson Objective identified (3.4/3.5) J92008K101 ..(KA's) ANSWER 1.06 (1.00) {
. REFERENCE CR ROT 1-7, pp 26-28 Lesson Objective 16 Reactivity Worth Curves, OP-103C i
(2.9/3.1) i 192004K111 ..(KA's) j l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) A _ _ _ _ . _ _ _ _ _ _ _ _ . _ . _ . _ . -
-:12 1RE5CTOR PRIERLES (7N 'THEMQQYNAMICS Pago107. .
17%)-AND COMPONENTSi 11%) (FUNDAMENTALS EKg1 ((.)w s.
' ANSWER 1.07 (1.00) l[0.,25 each]'
instantaneous, all, single, highest
. REFERENCE CR' Technical Specifications,. Definitions 1.13, p. 1-3 Ne - Fae114ty Lessen-Objestrive-identified-a _
ROT 5-1 o s p ektoe. f (3.2/3.6) 192002K110. ..(KA's)
\
ANSWER 1.08 (1.00) p'M
%; A ' /> t
~s .
4 REFERENCE CR ROT 2-2, d 39-42 Lesson jective 15 (2p /2.8) J ..(KA's) f$3004K115 ANSWER 1.09 (1.00)
.c REFERENCE steam tables CR ROT 2-2, p. 18 Lesson Objective 8 (3.3/3.4) 193003K125 ..(FA's)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
- 1. REACTOR PRINCIPLES (2 1 THERMODYNAMIC.C_q n Pcgs108 )
(7%) AND COMPONENIS__y l%) (EREDAMENTALS EXAffl V l 1 i i i ANSWER 1.10 (1.00) j b j l REFERENCE CR ROT 2-3, p. 49 i Lesson Objective 18 Surveillance Procedure, SP-312, p. 1-14 ; (3.1/3.3) i 193007K106 ..(KA's)
)
{ l ANSWER 1.31 (1.00) { l d h ( REFERENCE CR ROT 2-4, Lesson Objective 9 (3.1/3.4) 193007K108 ..(KA's) ANSWER 1.12 (1.00) C l REFERENCE CR ROT 2-6, p. 24 Lesson Objective 7 (3.3/3.4) 193C06K110 ..(KA's) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) j l l < J L___________
Pago109 ! 4 1 REACTOR PRIiiQlELES_y"t) ..THEBMQDltMMICS
.f7%) AND COMPONENTS! (1%) (FUNDAMENTALS EXAM 1 () i i
j- ANSWER 1.13 (1.00) { L a, ! REFERENCE CR ROT 2-9, pp 6-8
' Lesson Objective 3 (2.9/3.3) 193009K107 ..(KA's)
ANSWER 1.14 (1.00) ; b REFERENCE CR ROT 5-73 and ROT-2-14 (3.8/4.1) 193010K107 ..(KA's) ANSUER 1.15 (1.00) b REFERENCE
~CR' ROT 2-8, p.-34-3d 1
(3.2/3.3) (3.3/3.5) 191004K106 191004K101 ..(KA's) ) 1 (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ i
~1. REACTOR PRINCIPLES (r"O THERMODYNAMICS Pego110 (7%) AND COMPONENTS L !1%) (FUNDAMENTALS EXAM 1 bs ANSWER 1.16 (1.00)
-C REFERENCE n CR ROT.4-5 chapter 8, p. 90 - 91, 93 - 95 Technical Specification section 3.7.1.1 (3.3/3.4) 191001K101 ..(KA's)
' ANSWER 1.17 (1.00) b I REFERENCE No Specific Facility reference identified.
(3.1/3.3) 191002K119 ..(KA's) ANSWER 1.18 (1.00) a i REFERENCE { J CR ROT 3-10, p. 17 l (3.3/3.5) 191002K117 ..(K4's) l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) I
l '. ' REACTOR PRINCIPLES __f M THERMODYNAMICS Page111
=(7%)-AND'COMPONENTSA (1%) (FUNDAMENTALS EK&dl (s y
. ANSWER' 1.19- (1.00) a
. REFERENCE
,CR ROT 2-8, p. 30 & 32 (2.8/2.9) .(3.0/3.1) 191004K123 191004K124 ..(KA's)
ANSWER 1.20 (1.00)- c REFERENCE-CR ROT 2-5, rp 7 & 8 (2.8/2.9)- 191006K113 ..(KA's) l ANSWER 1.21' (1.00) c l REFERENCE 1 i CR ROT 4-3, p. 57 l l (3.1/3.3) (2.9/3.1) 191^98K111 ~191008K103 ..(KA's) l i l i (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) l l
- l. RE&qTOR PRINCIPLES M~ O THERMODYNAMICS r3 Page112 ;
(7%) AND COMPONENTS T_L%) { FilEDMENI&hS_EKAM) V j ( ANSWER 1.22 (1.00) d ! l REFERENCE CR Operating Procedure, OP-302, p. 5 NO Specific facility training objectives identified (3.0/3.1) q 191005K106 .(KA's) ANSWER 1.23 (1.00) a REFERENCE CR Operating Procedure, OP-402, p. 8 (3.0/3.1) 191007K108 .(KA's) ANSWER 1.24 (1.00) d REFERENCE CR ROT 2-17 (3.3/3.5) 191008K108 .(KA's) (***** END OF CATEGORY 1 *****)
- 2. EMEEGENCY AND 4BNOBlM -PLANT EVOLUTIONS 7-) Pcgs113 j 122X1 W V l
-l ANSWER 2.01 (1.00) l c
REFERENCE CR Tech Spec 3.1.3.x, pp 3/4 1-18 through 3/4 1-37 I (3.1/3.6) l 000005G003 ..(KA's) f i ANSWER 2.02 (1.00) b 1 REFERENCE CR Abnormal Procedure, AP-580, p. 3 (4.1/4.4) 000024K301 ..(KA's) AMSWER 2.03 (1.0g) c j ['
/ p
/ LV REFERENCE r CR Emergency ~ Procedures, EP-140, p. 3 (4.2/4.4) 000024K302 ..(KA's)
/
l l ! (***** CATEGORY 2 CONTINUED ON NEXT FAGE *****) ) l t ____ 3
7_____. 1
- 2. EMEBGENCY'AND ABNORim PLANT EVOLUTIONS q Page114 LPJll W C/
I i ANSWER 2.04 (1.00) d } f REFERENCE CR ROT 5-69, p. 8 (3.3/4.1) 000067K304 ..(KA's) 7 ANSWER 2.05 (1.00) d REFERENCE ) } CR ROT 5-30, p. 4 1 (4.4/4.7) 000056K302 ..(KA's) J ANSWER 24 06 (1.00) l a . REFERENCE License Event Report, 86-012, Haddam Nech Power Plant No facility procedure or lesson plan identified l l (3.1/3.7) 000036K301 ..(KA*s) i 1 I (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) ) L_____- - - l
'R. ELtKRG_ENCY AND ABNO8 g _EI.dNT EVOLUTIONS Pcg2115 (27%) W (~)
ts l 4 l ANSWER 2.07 (1.00) , C l REFERENCE CR ROT 5-65, pp 4&S Abnormal Procedure, AP-460, p. 3 (4.5/4.7) 000040K304 ..(KA's) ANSWER 2.08 (1.00) b REFERENCE j CR RCT 5-65, p. 4 Abnormal Procedure, AP-460, various pages (3.4/3.9) ! 000040K306 ..(KA's) ANSWER 2.09 (1.00) b REFERENCE CR Emergency Implementing Procedure, EM-216, p. 2 (3.1/3.9) 000067K102 ..(KA's) l ( (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l
[ 2 E11F2GENCY AliD ABNORM & PLAN'LEVOLUT._IQHE ,m Page116 l L27%L W L) ANSWER 2.10 (1.00) a REFERENCE CR ROT 4-6, p 21 (3.3/3.4) 000068K207 ..(KA's) ANSWER 2.11 !1.00) d REFERENCE I CR ROT 5-31, p. 11 & 12 (4.2/4.5) 000DSSK318 ..(KA's) ANSWER 2.12 (1.00) b REFERENCE Ch ROT 5-19, pp 3 & 4 Lesson Objective 2 Emergency Procedure, EP-290, p. 3 (4.0/4.4) 000074K311 .(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
- 2. EMERGENCY AND ABNORMLL PLANT EVOLUTIONS r~s Paga117 L31%.1 - L..)
ANSWER 2.13 (1.00) a REFERENCE CR ROT 5-10, p. 5 l Lesson Objective 3 Emergency Procedure, EP-290, p. 5 (0.7/4.2) l 000074K302 ..(KA's) ANSWER 2.14 (1.00) e REFERENCE CR ROT 5-28, p. 4 Lesson Objective 3 (3.7/4.0) 000007K103 . (KA's) ANSWER 2.15 (1.00) d-REFERENCE CR ROT 5-28, pp 3-6 Lesson Objective 2 Emergency Procedure, AP-580, pp 3-5 i (4.0/4.6) 000007K301 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE ****~*)
- g. -- -- ---=---- --
nyL 'g;g .; Pase118 l!.oi L.1JMERGEEI A@._ABRQFN"tEkANT EYQhilI. LORE m. u, i- (27%) > L/ () em: I
,,p
/t
. ' ANSWER 2.16 -(1.00)
> i, c,
.c REFERENCE-j 4
CR ROT 5-62, p. 2 &.3 Lesson Objective 1 l Abnormal Procedure, AP-360, p. 1 l I (3.6/3.9) l
]
000025G011 ..(KA's)- l
/
ANSWER 2.17 (1 00) e
~ REFERENCE CR ROT 5-62, pp 8 & 9 Abnormal Procedure, AP-360, p. 5 ._,
-(3.1/3.4) 000025K301 ..(KA's) l1 ANSWER 2.18 (3.00) l c or D I
REFERENCE Stean. Tables (2.9/3.3) l fi 00003'? K101 .. . ( KA ' s ) l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i l l l' L ._ - - - .__
1,__ElfEBQRl[QY AND ABSOJit1 & fLANT EVOLUTJONS n Page119 lab.1 W U i ANSWER 2.19 (1.00) b REFERENCE i 35 CR Emergency Procedure, EP-390, p. (4.1/4.3) 000037A216 ..(KA's) ANSWER 2.20 (1.00) e REFERENCE CR ROT 5-63, p. 16 Lesson Objective #3 Abnormal Procedure, AP-380, Step 3.14 (3.6/3.8) 000009K327 ..(KA's) ANSWER 2.21 (1.00) a REFERENCE I No Facility Trsining Objective or material identified. (4.5/4.8) 000009K328 .(KA's) l 1 l (3**4* CATEGORY 2 CONTINUED ON NEXT PAGE *****) I o
- 2. EMERGEEQ.Y AHD ABNQEtd& lh6NT EVOLUITONS ,o Page120 (2711 W C)
ANSWER 2.22 (1.00)
%4-eachk Depress Ex-T-r4p-punh-butrtons [0.5] u Ensure CRD Groups 1 through 7 are fully inserted IF NOT FULLY inserted open breakers 3305 and 3312 t&@~
REFERENCE CR Abnormal Proceduro, AP-580, p. 3 ROT 5-28, p. 4 Lesson Objective 2 (4.5/4.5) 000029G010 ..(KA's) ANSWER 2.23 (1.00) a oc C REFERENCE i CR ROT 5-28, p. 1 Lesson Objective #1 Abnormal Procedure, AP-580, p. 1 (4.1/4.3) , 000007G011 . (KA's) l ANSWER 2.24 (1.00) d J l l l I (***** CATEGORY 2 CONfINUED ON NEXT PAGE *****) { - 1
2 EffEB9ENCY AND AREQB M_ ', MI EVOLUTIONS c3 Page121 L2131 w a i
, REFERENCE 1
dR ROT 5-63, p. 10 l Lesson Objective 3 Abnormal Procedure, AP-380, p. 9 (4.0/4.5) 000008K305 ..(KA's) ARSWER 2.25 (1.00) c N s s N REFERENCE 5 CR ROT 5-63, p. 1 j ROT 5-28, p. 1 \ Lesson Objectives #1 \ N . Abnormal Procedures, AP-380 and'A,P-580 j N (3.4/3.6) 000008A220 ..(KA's) i l ANSWER 2.26 (1.00) l l REFERENCE i CR ROT 5-63, pp 30-32 Lesson Objective 3 1 Abnormal Procedure, AP-380, p. 31 (4.3/4.4) j 000011K315 ..(KA's) j r (***** END OF CATEGORY 2 *****)
- 3. Ek&HI SYSTXMS (38%) En PL4HI-WIDE GENERIG -
73 Page122 RESEQFSIBlkITIES (10 e (_/ ANSWER 3.01 (1.00) e REFERENCE Generic: The B&W Abnormal Transient Operator Guidelines Technical Bases Document. j (3.6/3.9) 061000K501 ..(KA's) l ANSWER 3.02 (1.00) d- l 1 REFERENCE CR ROT 4-32, p. 5 (3.2/3.5) 035010K402 ..(KA's) i ANSWER 3.03 (1.75) [0.25 each] I
- a. 1, 3, 5 (500 psig RCS, 1500 psig RCS, 4 psig RB) {
- b. 1, 5 (500 psig RCS, 4 psig RB)
- c. 5 (4 psig RB) ,
- d. 8 (30 psig RB) !
I REFERENCE CR ROT 4-13, p. 76 Lesson Objective 6, rev. 1 (4.3/4.4) j l 006000K405 ..(KA's) ; i (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) I i l l i
I k '3. PLAtlI SYSlEMS (38%) En PLAFT--WIDE GENEClg x Pegn123 l L) l JLESPONSIBILITIES Q(t_m l , l l l ANSWER 3.04 (1.0C) i d REFERENCE CR ROT 4-15, p. 11
' ROT 4-12, p. 44 ,
(4.5/4.6) 2 061000K402 ..(KA's) AN3WER 3.05 (1.00) a REFERENCE CR ROT 4-6, pp 43 Lesson Objective 8 ROT 4-13, p. 13 (3.3/3.5) 022000G007 .(KA'c) ANSWER 3.06 (1.00) REFERENCE CR ROT 4-13, pp 11-14 Lesson Objective 12 (3.3/3.7) 013000K410 ..(KA's) { (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
l- '3. 'ELANT SYSTEMS (39%). D_]% ANT-V[lpJ GFAKRIR r s. Pada124 EESPONSIBlklHES (1L (./
.t ANSWER 3.07 (1.00) c REFERENCE
! CR ROT 4-14, p. 48 l (2.8/3.0) 059000K418 ..(KA's) I ANSWER 3.08 (1.00) c REFERENCE CR ROT 4-8, Chapter 1, p. 19 Drawing EC-206-017 (3.0/3.1) 022000K201 ..(KA's) ANSWER 3.09 (1.00) a REFERENCE CR ROT 4-1, Chapter 1, p. 99 (3.7/4.2) 004000K509 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3 P ip R I T__ S L S T Et1 S ( a a l ) ~ PLANT-WIPE GENERJ_Q _ r,, Paga125 BESPONSJ3JJdTIES t 2 (j l 1
' ANSWER 3.10 (1.00) l REFERENCE CR ROT 4-15, p. 11 Lesson Objective 7 (3.6/3.8) 1 061000G004 ..(EA's) l l
ANSWER 3.11 (1.00) a ( REFERENCE CR ROT 4-1, Chapter 2, p. 76 and Figure 17 & 20 (3.0/3.3) 004000K407 ..(KA's) k ANSWER 3.12 (1.50)
- 1. RM-L2 (Plant Discharge Line Prior to dilution) [0.5], is TS-related [0.25] (TS 3.3.3.8)
- 2. RM-L7 (Waste Neutralizer Tank) [0.5], is TS-related [0.25] {
(3.3.3.8) 1 ( ( l
\
l (***** CATEGORY 3 CONTINUZD ON NEXT PAGE *****) { l l L______ _ 2
- 3. PLAN'l SYSTEMS ( 38%) - _ELANT-WIDF GENEhlQ ,o Pcg3126 BF&E0hMBILITIES (10 t)
I REFERENCE CR ROT 4-25, Table 4 and Table 5 Lesson Objective 4 (3.6/3.6) 068000A302 ..(KA's) ANSWER 3.13 (1.00) b REFERENCE CR ROT 4-1, p. 71 Lesson Objectives 3, 14 ) (2.8/2.9) 004000K403 . (KA's) ' ANSWER 3.14 (1.00) b REFERENCE CR ROT 5-48, p. 11 Lesson Objective 4 (3.6/3.6) j 068000A302 ..(KA's) 4 I ANSWER 3.15 (1.00) c (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
--_ - i
1 2 ELANT SYSTEMS (38%) D PLANT-WIDE GEHERIG r s Page127 RESPONSIBILITIES (1' w__) I REFERENCE CR ROT 5-48, p. 4 No facility Lesson Objective identified (3.2/3.5) 068000K504 ..(KA's) I ANSWER 3.16 (1.00) d I REFERENCE CR Operating Procedure, OP-302, sec. 3.2, pp 5-7 i (3.8/4.0) 003000G015 ..(KA's) ANSWER 3.17 (1.00) a REFERENCE CR Operating Procedure, CP-302, sec. 3.2.8, p. 6 (3.2/3.4) 003000K407 .(KA's) ANSWER 3.18 (1.00) i l I i l { (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) k l l
- 3. - EMNT SYSTEMS (3MB%MNT-WIDE GENERIC p, Pags128 RESPONSIBILITIES (10W C/
[L REFERENCE
~CR ROT 4-15, p. 25 Lesson Objective 20
( 3. 2/3. 4. ) } _059000K419 . . ( KA ' t, ) f [ ANSWER 3.19 (1.00) c or o REFERENCE CR ROT 3-3, p. 5 Lesnon Objective 8 { z (3.3/3.7) 002020K513 ..(KA's) l AN"WER 3.20 (1.00) ! a l cl.4 , REFERENCE N / N ' CR ROT 4- 32, Figuzes 17, 18 & 10 (3.2/3.6) 035010Kc01 ..(r k ANSWER 3.21 (1.00) L l 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) { . - _ - . _ i
- 3. ELANT SlSIEMS (38%) M T) PLAUT-WIDE GENERIC c-s Pag 3129 !
BEfiP0NSIBILITIES (10- 't ) { REFERENCE l CR ROT 3-3, p. 9 : Abnormal Procedure, AP-530 : (3.7/4.2) 002020K514 ..(KA's) i ANSWER 3.22 (1.00) b l REFERENCE CR. ROT 4-32, pp 23-24 ROT 4-14, pp 69-75 q Lesson Objective 3 (3.8/4.0) 035010K109 ..(KA's) ANSWER 3.23 (1.00) d REFERENCE CR ROT 3-3, pp 9-14 (4.1/4.3) 002020K512 ..(KA's) ANSWER 3.24 (1.00) d (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
~
2 1 'PLART SYSTEMS-(38%) f"D PLANT-WIDE GENERLQ, f~ Pago130 RESPONSIBILITIES (1C /- id L REFERENCE CR ROT 4-1, p. 172 Lesson Objective 1 (3.7/4.1) 026000K404 ..(KA's) ANSWER 3.25 (1.00)
.d REFERENCE CR Operating Procedure, OP-700E (3.5/3.7) 063000K302 ..(KA's)
$W WER 3.26 (1.00) d REFERENCE g
CR ROT.4-6, pp 21 (3.7/4.1) 063000K301 ..(KA's) \ ANSWER 3.27 (1.00) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) _ - - - _ . _ _ - _ - _ . __ }
- 3. PLANT SYSTEMS (38%1_ D PLANT-WIDE GENERIC -s Page131 5
L RESPONSIRLLIIIES (1' %.)
-REFERENCE CR ROT 4-3, p. 45 Lesson Objective not identified (3.3/3.1) 062000A401 ..(KA's) j ANSWER 3.28 (1.00)
} ( REFERENCE CR ROT 4-1, p. 84 (3.9/4.2) 006000K406 ..(KA's) ANSWER 3.29 (1.00) d ) REFERENCE CR ROT 4-1, Chapter 5, p. 177 i P&ID FD-302-641 l (4.2/4.3) I 026000K401 ..(KA's) i i l ANSWER 3.30 (1.00) j I i (***** CATEGORY 3 CONTINUED ON NEXT PAGE **'***)
- 3. EL@T SYSTEliq_LaBXLMD PLANT-WIDE GENERIC ,e 3
-Pega132 4
BES_EONSIHILIILES (1(W_ _ V i REFERENCE CR ROT 4-1, p. 34 Lesson Objective 6 (3.8/4.1) 010000K403 ..(KA's) {
' ANSWER 3.31 (1.00) d REFERENCE CR ROT 4-1, p. 31 Lesson Objective 6 '
ROT 4-16, p. 74 (3.2/3.6) 010000K603 ..(KA's) ANSWER 3.32 (1.00) b REFERENCE CR ROT 4-2, Chapter 2, p. 25 Lesson Objective 3 (3.1/3.3) 008000K401 .(KA's) ANSWER 3.33 (1.00) c (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) } ) I 1 L_ ---_ _ \
- 3. PLANT SYSTEfS (_ LANT-WIDE GENERLQ x. Paga133 RESPONSIBILITIES (1 V l
i REFERENCE CR ROT 4-1, Chapter 3, p. 151 Tech Specs, 3/4.1.1.2, B 3/4.1.1.2, p. B3/4 1-1 Lesson Objective 5 (2.9/3.1) 005000K503 ..(KA's) ANSWER 3.34 (1.00) - c - REFERENCE CR ROT 4-2, Chapter 2 and 3, p. 29 and 39 respectively Lesson Objective 3 chapter 3 (2.9/3.2) 076000K402 ..(KA's) ) ANSWER 3.35 (1.00) fd REFERENCE CR ROT 4-13, Chapter 1, p. 19 Lesson Objective 4 (3.1/3.7) 103000K406 .(KA's) ANSWER 3.36 (1.00) i c
)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) {
L _EL6NT SYSTEMS (3DA.)_ 'Q_EIAtlL-WIDE _ GENERIC q Page134'
.EESPOUSIBI_hlILES (1 (_/
REFERENCE CR' ROT 4-1, Chapter 3, p. 121 Lesson Objective 12-(3.0/3.2) 005000K401 ..(KA's) l ANSWER 3.37 (1.00) { a REFERENCE CR ROT 4-14 Lesson Objective 3 (3.7/3.9) 041020K417 . (KA's) r ANSWER 3.38 (1.00) To prevent uncovering the pressur.irer heaters [0.5] on a reactor trip [0.5]. ee eweat a*uraled (cadibt ia thc. Rts,du. 4e ency,$ 4h &cCo.5) Cod 0 REFERENCE CR ROT 4-1, p. 40 No facility objective identified. (3.0/3.4) (3.3/3.7) (3.6/3.7) 010000K402 011000K401 011000G001 ..(KA's) ANSWER 3.39 (1.00) [0.5 each]
- 1. Check valves in line from BWST (allowing flow only toward sump)
- 2. Height difference between the sump and BWST. (BWST higher)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- 3. ELANT SXQTEtfS'(38 Q D PLANT-WTHE GENERlq ry Page135 BESEQUSIBILITIES (1 _ (/
REFERENCE CR P&ID, FD-302-641 sheets 1 and 2 (3.7/4.1) 026020K404 ..(KA's) ANSWER 3.40 (1.00) a REFERENCE CR RSP-101, Sect. 3.2.3, p. 21, rev 09 (2.8/3.4) 194001K103 ..(KA's) A ' WER 3.41 (1.00) a ( % REFERENCE ss - 10CFR20.4 & .5 Ns., CR Health Physics Prbcedure, HPP-100, Sect. 20.4, p. 23, rev 02 (2.8/3.4) N N 194001K103 ..(KA's) 'Ns ANSWER 3.42 (1.00) b (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l l L_ _
n !T ta. PLANT'SXSTEMS_ Lap %) f"O PLANT-WIDE GEliERIC ,m, Page136:
. , EESJONSIBlklUES (10 J Ul REFERENCE
~I
.CR' Compliance Procedures, CP-115 (3.7/4.1) 194001K102 _ . . ( KA ' s ) . i j.
ANSWER 3.43 (1.00) d. REFERENCE CR Administrative Instruction, AI-500, p. 26 (3.1/3.4) 194001K105 ..(KA's) ANSWER 3,44 (1.00)
.b REFERENCE CR Administrative Instruction, AI-1600, p. 14
.(3.3/3.5) 194001K104 ..(KA's) 1 ANSWER 3.45 (1.00) !
)
[0.33 each]
- a. 3
- b. I
- c. 4 l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l l _j
- j. PMNT SYSTEME_f 38%) /"3 PLANT-WIDE GREERIC g-) Paga137 RESPONSIBILITIES-(10_] V REFERENCE Plant Wide Generic (3.5/4.2) 194001K116 ..(KA's)
ANSWER -3.46 (1.00) a REFERENCE CR Technical Specification 6.2.2.f, p. 6-la l (3 5/4.2) 194001K116 .(KA's)
- ANSWER 3.47 (1.00) c-REFERENCE CR Administrative 7.nstruction, AI-1805, pp 8-11 (3.3/3.6) 194001K114 ..(KA's)
I ANSWER 3. 8 (1.00) d l l l l l \ l ! l L (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) j ! f L_______-- __ - -- I
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- 3. PLAMI_SXETEMS (1@%L 10 PI4NT-WIDE GREERLQ ( ,
Pcge138 EESEONSIBILLIJXS (1 . (> REFERENCE CRAdminb-trativeInstruction,AI-1600, pp 17-18 (3.3/3 S) ,y y)) 194001 Kid 4 ..(KA's) ANSWER 3.49 (1.00) a REFERENCE CR Emergency Plan Implementing Procedure. EM-201, pp 4-5 (3.1/4.4) 194001A116 ..(KA's) l (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********) I I
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l :. Nuclear Regul atory Commi ssi on Operator Licens,ing Ex ami nat i on l-h I This document is removed from Official Use Only category on date of ex ami n at i on . NRC Official Use Onl y I s
l (~'t P l-U. S. h. CLEAR REGULATORY COMMISSID REAC70R OPERATOR LICENSE EXAMINATION FAC1LITY: __ _ .CBY1TALRUIR _1._ __ _ _ _ _ _. REACTOR TYPE: F,)W R- p k W 1 Z Z_ _ _ _ _ _ _ _, _ , ,, _ _ _ _ 1 l' DATE ADMINISTERED: g 9f 0 4 /12_ _ _ _ _ _ _,, _ ,,, _ ,, _ _ _ _ _ IUDIgucIIQNg_Ig_G9yD1D9IE1 l Use spparate paper for the a;.swers. Wri te answers on one si de onl y,. Staple question sheet on top of the answer sheets. Points 4cr each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Exami nation papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CAND I D A~I E ' S CATEGORY - Y8LUE,, _19196 __,12Cg6E___ _y06 UE _ _ _ _ _ _ _ _ _ _ _ _ _ _ __G 91E Cjp@ L ,_ _ _ _ _ _ __ _ _ _
1 g3._QO_, _gl,,,[n___________ ________
- 4. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
-32. 50 2. h t i 3+:-b s * ------M-----------
2 C . ls - - - - . - - - -
- 5. EMERGENCY AND ABNORMAL PLANT l $$. 4C 4'0 Si m
! ' M. Ki,6 47.ub 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC 1 RESPONS]BILITIES (13%) l
-/ M . ;rf
_jik . JR'ht _ , , _ _ _ _ , , . , _ , _ _ _ _ _ ,,,_ _ _ _ _ % TOTALS FINAL GRADE All work done on this ex ami n a t i on is my own. I have nei ther given nor received al d. 1 Candidate's Signature l l l l l l l l _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ ._ _ _ _ _ _ _ _ i
~ -~- - ~ - ' - ~
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g .NRC RULES AN UIDELINES FOR LICENSE EXA AT I DNS - .j v a m:-p
,j DOhing[the administration oC this examination' the f ollowing rules appl y: .)
1ht ;. . . , ...' . . to 1.;; Cheating' on th'e ' examination meansTan automatic denial of your application-Q d { Land coul d resul tg in morelsevere penal ties.
!I
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'g., room to avoid even7the' appearance or possibility.of cheating.
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l l15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE l DUESTION AND DD NOT LEAVE ANY ANSWER BLANK. l l16. If parts ~of the examination are not clear as to intent, ask questions of L the, examiner on!y. l l17,.You'must sign the statement on the-cover sheet that indicates that the l . work is your own and you have not received or been.given assistance-in l ' completing the examinati on. This must be.done after the examination has
}been completed.
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u l, J i.- . .- - Exam questions on top. d1)- . 1
- yp 'Q) ' Exam aids -.~ figures, tables, etc.
f l ,.
, , (3): Answer pages including figures which are part of the answer.
p L ' ub. ' Turn in your, copy.of the ex ami nation . and all pages used to' answer
) the ' examination questions.
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4j M difjgSgTOR PRINCIPLES I 32% h HERMODYNA.MICS r-Page .4-f47%) ANQ;CQgQNgNI@jjlQ3bfEyNpAMgNT9@_gx8tj),
~
hl I: ' i.w ... L p pi q7' ' .; la- 1 P:p ,) W , QUESTION'r 4.01 -
-t 1 , ', 00 ) -i 1-I 1 R. MULTIPLE 7 CHOICE' .
W reactor startup',to full: power..is being performed 5. hours after a. t trip f rom f ul:1.. power .equili bri um condi tions,- usi ng a 5%/ min ' ramp. l How.'would the resulting' xenon: transient vary"if a . 2*f,/mi n r amp .- was , R 'used instead?' i
'a.- The : x emon di p. woul d ' be smal1 er and occur sooner.
1, . b.; .The xenon dip would be larger 'in magnitude ar.d occur
; ,1 at er . .
.'c. 'The xenon . dip woul d be small er. and occur l ater, 1:
'd. The; xenon dip.would be. larger.in magnitude and occur nooner..
l-h e a: l. i ll l l-j ,: l' l l f 9 (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) 1 " _x _= -__.
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j4. -REACIORLER11jCIELJSijZ3 C THERMODYNAMICS l Page' 5" [:il ' 4 i ( 77. ): AND ' COMPONEN'S ' (161.4 L (FUNDAMENTALS EX AM) U V. , <; in - !+ e t @y;g e q g ,, , f 'lf.f O
~n
-GtJESTIONi :ll . 00) :
4 . '0 2 . i a , H)Th'l e reactor trips. f rom; f ull power,.: equilibrium xenon condi tions. Six l Lhours"later, the' reactor i s brought critical and power is raised to
;l
, ' l10E-8 amps on .the intermedi atef range. p ,
- [.INpower del'is maintained at 10E-B amps which "ne of ' the f oll owi ng
, ,' statements 'k CORRECT concerning subsequent control rod motion? E .' a . Rods wihl be withdrawn since : xenon concentration increase is l greater than.the. xenon burnup rate. ]
. b. Rods will not move because the renon concentration , increase
- equals the xenon burnup due to the core flux. 1
'c. Rods will-l be rapidly inserted because the critical reactor will cause a rate.of: xenon burnout higher than the-
- concentration. increase.
,' ;d. Rods will'be. inserted due to xenon ~ concentration decay and burnout. associ ated wi th the power 'l evel .
L (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) L r. I. L l.
. m_.-m.m_a_um --____--2_. _- -
2 t, )'['* . ', (= ,+, u, l g s i , .. pr :+ - ,> . . _ . ,. > . ?v42' NEACTOR'P'RINCtPLES. . V d7.] THERMODYNAMICS'. . . Page 6. iy dZ*f) ' AND' COMPONENTS (16 : (FUNDAMENTALS EXAM) y { f. ' 3 0DOESTION '4.03' (1.00)
- 'Which ? one lof ; tho' f all owi ng statements.concer Ang the. power' defect at~-
(100%.(power el s correc t? -
- a. ;The power'defett is the difference between the measured. power
-coefficient;and tho' predicted power coefficient.
- b. . The power . def ect . i ncreases ' the rod worth 'requi rements l; T : necessary :to maintai n the desired ; shutdowr' eargin f ollowing a reactor'. trip.
4
.c. 'The power def ect i s enore .negati ve et beginning .cf core 1i f e , because of the higher boron concentration.
Ed. The power defect. necessitates the use of a constant Tavg
+, >, program to, maintain an. adequate Reactor Coolant System
- subcooling; margin.
lf l l l l L L l l. t l-l' (***** CATEGORY 4 CON TINUED ON NEX T P4GE * * * * * ) o________ _ _ _ _ _ _ _ . _ _ _ _
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' Rg CCMPpNENTS AC..T,.OR _
'(1 w - -(FUNDAMENTAL.S e f._R I_N_' EXAM)-
H_ _E .__ R M O .D. C.) P_l_.E.S. D.1.7.%._ _Y _N A _M I _C.S - . 4 6.N i -.
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i .1 , i t- 4: ,m. , 1 N[@:Which Done of ythe ' f ol'l owing. wl.11: resul t. I n .an 'i ncreased
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Cal cril atted . .,
.j
[unchinged? j Shu tdown j .Ma' ~gi n asudmi ng Lot her, . c andi ti ons remai n- .l i E a
..a'. L Reartor Cool ant Ternperature decreases, 1 < e. .g Wy /b . RCS boron'conewnthation. decreases. .- > ?,
- c. .F uel burnup is. nearing:End'of Li f e.
g.g, .d. Xenon concentration increases,
.+ ..
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.* f l*****lCA;EGORY 4 CONTINUED ON NEXT PAGE *****)
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=4< ' REACTOR' PRINCIPLES'(73 ' .' 'g. , .RMODYNAMICS.. . ' ' ' ,
.'1 'l E I 19, }.!?3r_.0N9_G9TDUENIS.J.Ld_!!E9N90MENTA6SJf 9!$ '
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? ', jCOESTION '4.05 .I 1'. 00 L
.f~ 'e SS$1ecti'the L1'ine below fwhich BE.ST: describes';the: specific group: of .
- parameters which must' be conteolled and monitored 'during the approach -
.{
DP-210, " Reactor Startup."
- g< ritd cel'ticali ty, fin accordance' wi th Ja, . PZR level,LSource Rangeccounts, Intermediate Range amps,. Boron 1 concentration,;RCS temperature. ']
- 6. .- RCS temperature, Source Range counts, Startup rate, rod O '
. p osi t.i on .
- p. . .
.c.. : Startup rate,. Intermediate Range ampc, centrol rod posi ti ons, 1 RCS' flow: rate. .
- d. Reactor.Shu'tdown! Margin, RCS flow rate, RCS temperature,.
Intermediate Range amps, Rod. position. l 4 4 1***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) L 1
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BE9CIDB E8113CIELES_ 12K'~TbEBdDDY!9BdlCD
. (7%) AND' COMPONENTS (lbud-(FUND $MEL(T9Lg;EX8M1 (] Pagel.9'-
H 0
- -OdESTION 4.06 ('I . OO i:
.o 1 1 j0 Noiwill' the reactivity addition- rate to th'e RCS: change, due- to a
-!O ppm bort. tion:at the Beginning'of Core Life vs. the End of Core Life?
- -; Assume the.same. feed concentration,;'same flow rate to RCS and same..
temperatures. J .'a.. Remains constant over core life.
'b.- .
Not.enough information.is'provided. c- Decreases as'the core ages; d.. ' Increases.as the care eges. .; 1 I* (***** CATEGORY 4 CONTIN'JED DN NEXT PAGE *****)
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M',hhg@hTOR'PRINCIELgS[JZp 4 JZZl_ BUR _G90E9NENI@_flhg__tjgROQQyN9digg JEUNp6DENIBL@_Ef8dl Q .' Page n10-y y. 10U$5TIDNs 4.07' ( l '.- 00 ) ' y a i FILL INITHE BLANKL
..According.'to Technical Specifications Shutdown Margin is defined as:
?The; , .. -
amount of reacti vi ty by which tho ' reactor is . , .subtri ti cal . or .would 'be' subtri ti cal from its'present condition. Lassumin'g' , 4 ll 'i.- NoLchange'ln' axial; power shapiog rod position, and- .
~
I '
- 2. , .._____ control rod assemblies _ (saf ety and regulating)' are f ull y. inserted except for'the.______ red-eesembiv of the
_g_____ reactivity' worth.which is assumed to be fully
- withdrawn, i
t J w (*****' CATEGORY 4 CONTINUED ON NEXT PAGE *****)
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[= Page 11-D$as.BE09198_EBIN91 1
. (7%) AND' COMPONENTS-(1 ELE-(FUNDAMENTALS b Z'1>wd 6EXAM)' HER!OUYNAMICS - V.
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QUEST 10N 4.08? , t 1. 00) .
' Shii:h one mf the f ol.lowi ng 'descri bes l the" changes. to the steam , that ioccurs across: the thratt1e block (noz;t 1 es ) of. a'real' (not ideal)
?.,y turbi.ne, .but prior. to i mpi ngi ng on the turbine' bl ades? a '. . Enthalpy" decreases,.. quality constant.
- b; ..
Enthalpy. increases,' quality constant. c c .' ' Enthalpy constant, quality decreases, p.
- ;d.-EEnthalpy'docreases, quality decreasen.
l' l: l-l l l l* l' (*****' CATEGORY 4 CONTINUED ON NEXT PAGE *****)
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.Page'12 1' (77.) ; AND . COMPONENTS ~ ( 1 bg -(FUNDAMENTALS' EXAM) -;
3-y '
-QUESTION' .4.09' ' ( 1.' 00 ) -
VWhichione-of the~below requires the-most heat removal during .
' condensation? Assume steam is of equal qual'i ty .
-a.: one pound'of' steam at 1 psia.
. b. one: pound of steam at 300 psi a'.
.t; two pounds of steam at:600 psia.
- w. . .
c a' d .- 'two. pounds of steam.~at 1200 psia.
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Lek _BEBGI981EBINCIPLES .(7% ^{ THERMODYNAMICS- ... Page 13, c(7%)'AND: COMPONENTS-(16.4 (FUNDAMENTALS EXAM)- L, ~~-~~~~ sf h.w - L. QUESTION .-4.10 ( 1. 00)'
< Whi ch one.. of the . f cll owing , statements i s - CDRRECT concerni ng a
.: sec ondary l c a l ori metr i t? '
, u a.l .If<feedwater: temperature.As. read erroneously high, then.the
! , ' Jcalculated reactor power will;be highet than actuali
.b. The calorimetric equation includes the ' heat.' added by the reactor. coolant' pumps ar a negative factor.and'the heat
'i est - t o the contai nment' c .mosphere '. (ambi ent l osmes) ' .as ' a
., posi ti ve. f actor..
;U
- c. .. Mass' flow rate of the' secondary system i s determined by .
~
c totalinge the average steam flows 'f rom each' of the:. steam . generators.
- d. The results of'the secondary calorimetric.may;be used as the basi s f or cali bration of - the power . range ' nucl ear y instrumentation:provided. indicated: power,'ls; greater than
~75%FP.
d (***** CATEGORY 4-CONTINUED ON NEXT PAGE *****)
7,.,,. , 4E.4 REACTOR PRINC PLES (7'IhHEMODyMMICS _ (Page !14 ..' ['.' %.'x -(7%)'AND' COMPONENTS (16 n - (FUNDAMENTALS EX AM) k ;,
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.. . - . . - , t j.: . Gi von U the 4o11 owl ng Jdata:
E ? RCS f l ow . . . . . . . '. . ' . . . . : 1;5 EB'1bm/hr-
. . 1Thot..................,606, dog F
-.Tcold ..'.......'.....-554.deg F:
' T a v e . .. . . . . . . . . .' . . . . .. ! 580 ; d e g . F
' S u p er h ea t ' . .. .. . . . . . . . . . 35-deg.F:-
,1 .OTSGfpressure ....... -850 psig-Feedwater Temp ......-480-iceg F' Feedwater Flow ...... 1.3 E'7'Ib'm/hr OTSG l evel . . . . .. . . . .. . - 88 %-
3 , Cp f...................f1.25' BTU /lbm deg-F Sel ect . the ,value .below thet' most . c1 osel y matches .; the calcul ated ' core - , :: power.: il' .,"(-'
; a '. . ,2300 MW'.
- b. -2500.MW:
. c. 32700=MW l d .' ;2900.'MW-i j
i i 1 l o 1 r (***** CATEGORY 4 CONTINUED ON NEXT PAGE ***t*) l
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'! 4 . - REACT 08' FRINCIPLES -(7%C h. Page 15
~~$lif.EENETc5RPUUE5T$' -(FUNDAMENTALS ~lIbw[ THERMODYNAMICS EXAM)- .d '
.S L
,DUESTIDN 4.12 -( 1. 00 )
'Wh! ch one ' of - the f ol1 owl.ng is NOT an example of conditions which'can
'- 1 result in water' hammer?
- a. . Sudden closure of .a valve in a system In which there i s water '
flow. tb. ' Cavitation occurring at a flow-od fice in a closed system. c.- Rapi d pressuri zati on of a properl y ' f a ll ed - and vented ' system, d.- Starting a pump on a partially empty system. e [ I' f. h 11 [ (***** CATEGDRY 4 CONTINUED ON NEXT PAGE *****)
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D_Y_N_A_M_ Pa9e:16-
<i.. -l-(7%)'AND COMPONENTS ( I L,A .(.F_U_N_
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,j l b. .. : P'.;Sl average temperature .,.. . i'
[y c. :RCS-ilowf cl . M S'p,*9ssure-L
; . f .. -
li i. i 1 I J 4 (***** CATEGORY '4 CONTINUED ON NEXT PAGE *****) i c- - - - - - _ - - . _- - - - - - -
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~~~~]; ~/hiIh56~E65PUUENTSl5 L----.-------------------
IlFUR5ERE T'EES EXAM 5: l(' . L > v :,jy A gi.
, s LQUESTION'- 14 ! .14 L .' ( 1. 00 ) :
J v ,, . .
,;Whichlone?offthe following situations best describes a condition in-whidh pressurized thermal shock- concern exists. LRefer.to Enclosure 2fof'
.EP-39011f desired.
,? Al small.'.- break s LOCA .has occurred:
a ^. HPI ? has 'i.ni_ti ated, all RCP? s are 'operati ng, the.RCS Temperature:is,530 Fiand the RCS pressure is at the PORV'.
's e t'p oi n t .
[ b. . HP!n has .i ni tiated, all RCPs'are.shutdorm, the'RCS temperature i s' at' 490 f F and the RCS ~ pressure. is- at' the PORV setpoint.
, (c.? ' HPI hankini ti ated, . all. RCPs are f.operati ng, - the RCS- temperature '
is at'450.F.and the RCS pressure is at:1900 psig. HPI has' initiated (then stopped, al l' RCPs . are shutdown, . the RCS -
.d..
temperature is at 400 F and ~- the RCS pressure 'i s at' 1700 psig. . J 1 < l 1 r. l (***** CATEGORY 4 CONTINUED DN NEXT PAGE *****) 5 3 1 i.
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,1_._RE ACTOR PfjI NC I PLES T!"ffT L4ER MODVL4 AL1],LS -
! f ' Page 18 L '(7%F AND' COMPONENTS '(1L.d .(FUNDAMENTALS' EXAM) .-
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}QUESTIONi :'4.15- ' (1. 00)
"c'.LWhi ch 1one, of' the.; f all
.. . 1 1.
owi ng ; st atements about pump Net . Posi ti ve Sucti on
,
- nHead ?- (NPSH) ..i s CORREC ['?
- a. ' NPSH 1-s . the . embunt ' by whi ct, -the saturati on presst re i s greater than<the suction. pressure for the water . bei ng pumped.
b.- When.a pump id started,1the NPSH wi1l' decrease.by.the amount-i> , of:.the pressure drop in the suction piping. c... NPSH<is essential for' operation'of4 centrifugal pumps b'utJnot
.l . f or' positive : di splacement=. pumps.
p< r
}: ' d.: ' NPSH can be' calculated . by, subtracting the suction pressure
{ jfrom the' discharge _ pressure.
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.'QUESTIONE 4.'16 (1.00) .
[ . ;Which. one of the. f ol,l owing best. describes the steam relief capacity '.lof_the, Main: Steam System? L ..a.: T'he code saf eties must be' combined with the atmospheric dump valvenEto:have a capacity of 100%,a wi th reli ef settings from-
- l. 1935 psig:to:1010'psig.
Lb. The code sa'feties:must-be combined with'the atmospher.ic dump-Eval ves.- to have . a capaci ty of 100%, with relief settings from o 1010 psig to 1150 psig.
- c. The code safeties do NOT have to be combined with the I
. atmospheric dump, valves to have a capacity of 100%, with relief . settings f rom 1050 psig to 1100 psig.
d.. .The. code saf eties do NOT have- to be combined with the atmospheric dump valves to have'a capacity of 100%, with. relief . settings f rom 935 psig to 1025 psig.
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(4) , REACTOR PRINCIPLES : (7%[^TijEPMDDYNAMICS . P a g e '.' 2 0 - j
~(7%) '
. . . AND COMPONENTS-(1ey?- FUNDAMENTALS' EXAM)-
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'QUE$ TION .: ( 1.' 00 )
- An'.' operator .-. drops hi s/her '. sel f-readi ng poc ket dosi meter (GRPD) .
j resulting?in no_ physical: dami3ge but onl y'. a partial discharge of..the s c SRPD. - l L , : .. . . -.s /
,:3The'SRPD will'then:~
-r L
- a. - Read lower than actual exposure.
'b.. ' Read; higher than actual exposure.
.c.. Fai1 as is.
'd. -Read equel tW actual; exposure.
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'TOUESTION 4.10 -(1,00) i LE .. . > i Thef pl ant'. has experi enced ' a l oss-of-cool ant accident (LOCA) with' degraded saf ety . i nj ecti on. f l ow..
~
The reactor' coolant pumps are. manually tripped.and- I
?the.resulting phase separation.causes the upper portion'of.the core to i uncover. ,
t.Which 'one'. of the f ollowing describes Excore Source Rar ;e (BF3):
. neutron' level indication as the-core.begins to uncover.
- The detector count" rate' Shou'Id:
a;' 1 ncrease as the cor e uncovers. , , b '. . decreases as the'. core uncovers. c.' ' remains Ef ai r'l y constan't as the core uncovers. .; b d. osc.111 ate severel y as -the core uncovers. h a
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J4i I REACTORSPRINCIPLES ^ ( 7 *4 HERMDDYNAMICS :h .Page.22-
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' QUESTION- 4 .' 19 ' (1.00).
dWhich one of the f o'llowing best.' describes the saf ety procedures and/or
- precautions f or positive displacement pumps.
La._ Li ke the': reciprocating pump, to protect a rotary pump from of damage-it should be provided with a relief valve'in the di scharge li~ne .and should never be~run without an;open discharge path. ib. 'Unlike the reciprocating pump, to protect'a rotary pump from damage i t-- should be provided with a relief valve i n the .suc ti on -
'line.and should always be started with a closed discharge path, i c ;- Like the. reciprocating pump, to protect'a' rotary pump from.
damage it should be provided^with a relief valve in'the suction line,and'should always be started with a cl osed discharge pathi-ld . Unlike'the: reciprocating pump, to protect a rotary pump from 4 damage it should be provided with a relief valve in the discharge line and shoul d. never be run without an open discharge path.
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'!I A." > r REACTORY PRINCIPLES -~ (7L ' THERMODYNAMICS -
'l iC'~3i7E.IEdbbICb5PBAE7Js~iiL< ~iFUUUd5EUThES. EXAM)'- 1
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DUESTION - 4720 -
. a ', . .. ;.. iTheL boiler-condenserJ.:or ' reflux; boiling ' method of the .RCS circul ati on "iM susceptible to blockage'by. buildup of.-non-condensibles.* Expla!n !
jjhyithisieffactsrefluxboiling llll;i-': (
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M il.BEOGTOM PRINCIPLES i(7%.DAERMODYNAff1 CS :
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- i. QUESTION- 4. 21 L ' ( 1. 00 ) . ,
i WSichf oneL of the. f ollowing is a . correct statement :regarding the j
.: operation of a 480 volt'non-ES-load center feeder breaker? o 1
, Ea t- If Ith'e control power fuses ~ are bl own, the load may- still , be
- operated 1using- thellocal- handswi tch,
- b. 'The load' center 'f eeder breakers. can ' be cl osed without the.
' respective 4160'Visupply breakers.being' closed. 'l l
- c. Wi th the: local-re' m ote switch in local, ' the control' room .j
' maintains breakerfindication and tripping control. .j i
- d. , } When operating ' a break'er ~1 ocall y,. placi ng the l ocal-remote ,
switch in' local bypasses the treakers tripping circuits. ;
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OUESTION 4.22 (1.00) Which one of the f oll owing BEST describes why suc c essi ve starting cycles on large motors, such as RCPs, are strictly l i mi t ed?
- a. Large motors have large inertia problems to overcome causing excessive wear and heat on bearing surfaces, due to the weight of the motor,
- b. The switchgear supplying these motors is susceptible to overheating and insulation damage, causing flash-over on the bus work.
- c. The cooling systems for the switchgear are not euequete to maintain the switchgear cool, when such motors are started multiple times in quick succession.
- d. The motor windings are more susceptible to overheating and i nsul a ti on breakdown due to the large current draw on start, and mi n i inal cooling air flow on i ni ti al rotation, i
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AQUEST10N 4.23. ( 1. 00 )-
. :4 p :In'. procedure OP-402, Section 3.2,
" Makeup & Purifi cati on System"
' there Lis a . caution which states, " Exercise caution when placing lthe demineralizers-in. service." WHAT'is the purpose of thi s precauti on?
-a. Reactivity changer can resul t causing undesired ' power changes e> from the removal of boron -f rom. the coolant.. l
- b. Pressure changes can result if the demineralized.has not been:
properly filled ' and vented causing cavitation in the Makeup pump.
. c .-
Large amounts of' Lithium will be removed from.the primary-caus! .a change in pH and an increase in primary activity. I I .
..d. :Tempe.ature change onLthe demineralized inlet can.:famage the resin causing chemistry problems and release of resin to the makeup system as the resi n breaks up.
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C-OOESTION' '4'. 2 4 (1.00) < ! y.ll' , [ .. ,
,: Complete ^the f ollowing statement f rom the choices. bel ow.
tWhen: paralleling-an AC generator .to the commercial power' grid, the voltages mustlbe-iniphase'at the instant of parall eling 'otherwi ss the
- 7 difference (can damage; *2-
- 'a.. Lloadsfon the grad'because of the instantaneous shiftsin the ivoltage sine. wave.
'b.- the generator because-it will act as motor ' wi th ' li ttl e or no Lreverse. current 1through the breaker.
- c. 'the, grid transformers because of'the instantaneous shift in.
.the current cosine wave, fd. .the. generator {because of-the high currents induced by the vo'1 tage potenti al .between phases. ;
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$ 'Page 28' g$.z [ENERGENCY AND ABNORMdd N,dNT'
----- ------- -------------EVOLUTIONS.
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,3%i_iEDEBGENCYJ8MD_8D9980SL('$8NI_Eyg(UIlgNg Page 291 14232..
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g; mOUESTION' 5.01 (1.00) lWhich one of the"following i s ' a Limi ti ng Condi ti on f or Operations concerning Movable Control - Assemblies Technical Specifications?
- a. All safety, c'egulating and axial power chaping control reed '
switch position indicator channel s and. pul se stepping posi tion indicator channels shall be operable and capable of H determining lthe. control rod. position within +/- 2%.
- b. All saf ety rods shall be'operab1n and positioned within +/-~9%
'(indicated- posi ti on) of their. group average height.
h The-individual saf ety' and regulating rod drop time .f rom the c. f ully withdrawn position shall be less than or equal to 2.1 seconds from power' interruption at the control. rod drive breakers to 3/5 insertion with Tavu greater than or equal to
.525-F and all RCPs operating,
- d. Alli axial p'ower' shaping rods (APSR) shall be operable'and shall be positi oned wi thi n +/- 6.55. (indicated posi ti on ) ci their group average. height.
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h, c. ,, < !' s [!l ' i: '. I [QOE'STION 5.' 02 - l l' . OO ) ' y l .p., . . .s g lWhi'ch1one:ofzthe in11owing i s the. IMMEDI ATE ACTION step.of.AP-5BO,
;'!Reac t or Tr i p '! , which requires.the operator to concurrently per :
ff orm EP-140 " Emergency Reacti vi ty Control", if the step is not {sati sfi ed. .
~
a.- ' Ensure'CRD group i through 7 ' are f ull y inserted.
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> b ;- . Ensure Intermedi, ate range' flux is decreasing. ,
- q. .
c'. Is . Shutdown mar' gin 'less than 1%.
'd~ , Verify TVs and GVs1are closed.
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-QUESTION ' Sl 03 ' t1.00)
>i -
- Which one of~the folloEing is the reason that'the operator.
must' ensure that the automatic. bus stripping occurs as programmed-
.;during: an undervoltage condition on the- ES 4160.V bus, ' subsequent
/ diesel . starting or ' energizing lwith other sources according to AP-770,
- Emergency Diesel: Generator Actuation?"
!a. To prevent the diesel from picking up'the' bus in a 1caded condi ti on.
'b.' ;To prevent overspending of the diesel 'when picking up the a.. ,: load,
- c. 'To prevent arcing'of the' feeder breaker when . cl osi ng, thus causing.another/undervoltage spike in the circuits.
- d.- :To -: prevent any .f aul t- on the system f rom feeding through and
. damaging: the energizing source.,
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- . .lIMERGENCY ' AND A.BNORN L.----- N ANT'EVD.L.UTIONS,
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" QUESTION - -
- % O'4 : (2.00)- -i 1 1
'.' Whi ch .one of' the f ollowi ng valves : must. be veri'f i ed by the operator as>
IMMED'IATE; ACTION;of procedure AP-460, " Steam Generator Isol ati on , ! : Ar.tuati orf?? Assume.the. malfunction.ir occurring in "A" OTSG. 1 a.- Automatic c1osure.'of.FWV-40,. Main' Feed Bypass Valve. !
.b. Automati c . opening ..of FWV-35, Main Feed Bypass Isolation Valve. .l i8
, l lc. Aut omati c - cl osure . of FWV-28, ALB Feed Cross Connect. Valve. ll o
d.' : Automatic opening of'FWV-19, Main Feed Pump Retire Valve. - .; 3 ,
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'QUESTIDN 5.05 i1.00)
.Which one of the f ollowing is,the most desirabl e. method of fighti1g a
' high voltage el ectri cal fire with water, according to EM-216, "Duti's e of the Nucl ear Pl ant Fire Brigade?"
- a. Straight stream directly on fire from at least 50 ft.
- b. Wide pattern fog from at least 10 ft.
- c. Fog / st r eata combination f rom as close as possible,
- d. Narrow f og pattern from at least 40 ft.
. a 1
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g' m t: . ,. EDUESTIONT ' 3. 06' . ( 1.-00 b LL ,
' iWhich 'ene .nf L the f ollowing -i s. the' reason ' that one Nuclear. Operator
- shoul d : . stay behind in the: Control Room during"an' evacuation of the '
Controll Room i f . condi ti ?qs. permi t, ' accordi ng to AP-990, Shutdown p EOutside Control". Room?" - a
'a. - ;To provide. the SSOD earl y.' indication conditions which allow return to ' the . control. room f oll owing the . fi re.
- b. To, oper ate controls that are not transferred to:the Remote
-Shutdown Station, and provice untransf erred indications to the
(
. remote' stations.
c.. 'To di rect f ire' fi ghting acti ons!. o f '.the Fi re Bri gade, in an
' effort to minimize damage to vital plant equipment.
1
. .d . To perform-channel cher;ks wi th the ' operator at'the Remo'te !
a 'Shutoown Station.and monitor the plantduring the transfer.. q
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ADESTION~ S . '0 7. - _(1.000 ., ; Which one'of the,following'.is NOT an IMMEDI ATE ACTION: of. EP-290,- {., M.'.1 riadequat e i Core - Cool i n g?"- a.- - Ensure 0TSGs are at 95% level. k:J: ' b.,' Ensure the Reactor.is tripped., .I-g., t:
- L c . . 3 F.:. LP.I i s' del i ver i ng . f 3 ow ' THEN ensure f ull - LPI - f 1 ow. .
id. . . Ensure full HP1 flow.' ' 3 k q 1 i
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"iDUESTION
; 'S.09: (i 00):
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.d.Whi chi one of thef..f all owi ng i s J the .. reason.'f or cl osi ng' or ' veri f ying the
'; Main :. Turbi ne 'Throttl e and Governor ' Val ves are closed f oll owi ng .a .
rissctob trip,per;the;IhMEDIATE-ACTION 0 of AP-580, '" Reactor Tr.i p ?." Lai Tosensure theLMain' Generator is removed from the grid and "7 .. power ; i s ;transf erred ' to of f-si te -f or the Vital buses.- aj
- q. 1
- ..- Ib,- ToLallow the Turbine bypass valves to control the OTSG
" pressurenand planticouldown rate.
c.'/ ' Stop ' overcooli ng' l eading /to possi ble emptying . the PZR and a
-saturated'RCS.
- d. ' To ' all ow the rapid breaki ng of the condenser vacuum so plant
'U temperature control.can be-transferred'to the atmospheric ,
J - r el i ef . val ves.
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QUESTION' :5,09^ (1.00) l Nhich. one ok the' f oll'owing i s . an entev condi ti on f.or. AP-360, " Loss of. '" (Decay ~ Heat !temoval ?" W a. - Ref ueli'ng. i s ' i n . progreas ' wi th the core - of f -3 caded ' to ' the spent
' fuel.-area when a leak develops ~in the "A" RCP aeal package.
, b. (During'cooldown at 250 F-the "A" train DHR pump trips on.
love!-l oad 'l eavi ng oni.y. the "B" trai n pump .. to conti nue cool dowri,
- c. Cooldown 'to cold shutdown is continuing with both trains of '!
..DHR when DHV-42 cump suction valve . i s . opened causi ng air binding of both-pumps.
- d. Loss.of off-site l power during. cold shutdown. conditions prior..
to start of. refueling and the failure of the "B" train EDG- i to Luart.'on;an'undervoltage condition. -- if i I t 1 l i
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l % e gy . I..GOESTION'
; : S.' 10 ( 1 ; 00).
ll- t. . > L > Which one of> the f all owing: will be used to dietate the best: alter-j lnate ^ heat removal -method required af ter 'a loss of Decay Huat Removal l according to a NOTE in AP-360, " Loss of Decay _ Heat Removal?"
- 1. .
<a. The total'-' flow rate to the RCS at the.ti.me of the loss.
'b. The status.of cont ai nment i nt egri ty. : .
I
- c. The aval_l abili ty. of intore tcmperaturescand RCS conditions.
5
.d . . The - availability of makeup: flow f rom normal injection.
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'[$hMEMERGENCY AND ABNDRMALCANTLEVOL, UT_],OrjS: .h .Page 39 V v 1M'6M t p DUlsSTION. 5.11 11.00)-
! AP-3DO,-ES' Actuation,. step.3.14 states '"IF,'at any' time while
[ performing. thi s' pr.ocedure, RCS PRESS i s > 2300 psig,1 HEN open "the PORW tac 1 ower :RCS PRESS to J.pprox . 100 psig above'OTSG' PRESS."
- 3],gg'eg ggg gg- the ' f cllowing is the reason this :attion is taken?-
~
- a. Ercures maximum HPI flow ' whi1 e ensuring maximum subcoollng margin.
- b. Ensures adequate. HPI . f l ow along wi th minimizing releases to the' reactor. building.
'c. Ensures maximum HPI , flow without, allowing the. OTSGs .to become heat sources.
-d. Ensures the desired HP1 flow and provides assurance that the PORVs are operable.
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[ ii y - q.C t00ESTIDN; '3.12 : ( l',00 ) - . 1 W h'a t:51MMEDIATE MANUAL ACTIONS are. required by the-operator.if the ~ N.reactorL control rods f ail to insert on a Reactor. Protection System Actuation according to AP-5BO,: " Reactor Trip?" p
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{S .'. JOUESTI'ON: ~5.13 (1.00) SWh'i ch ? one' of - the f ollowi ng- i s ~ the reason l f or.: bypassing and throttling.
. "the' HPI . flow 'to obtain equal fhow to'all-four injection' lines-
[according to-the CAUTION prior to. step 3.6.of AF-380, " Engineered -
- Ssfeguards? Actuation?"
La . . .To prevent' overcooling condition in. tho reacter vessel.
<l .
'b ; - .To ensure adequate _NPSH to the HPI. pumps
- i;;
;p it. . - To sestabli sh proper condi tions f or " piggy back" operations.
- d. : Toiprevent.HPI pump. runout.
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.Page 42' '
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-QUESTIDN '5.14 (1.00)
Assuming. the f ollowing' plant indication exist:
'RCS Temperature: 579'F Tave RCS'Presmre : 2100 decreasing at 100 psig/ min PZR Temperature: 643 F decreasing at 6'F/ min 4 .P2R level : constant with 2-3'gpm increase in makeup RCPs' running- : 4
'.fRB pressure 't. normal (no' increase)
Reactor Powr1 : ~40% PCP' seal inj. : nor:aal o . .. . . 7 J Whi ch - one of' the f ollowing Li s the MOST probabl e si tuation developi ng? Ja. : Smal ,' break LOCA b.- Stuck' open PZR spray val ve
- c. PZR steam space-leak-d.- Letdown li ne ll eak .
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E.d_gdEgggggLpNp_9pyQBUGLQ @NI_ Ek'96LJI1999 - p ; cssz)t
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.QUEST3ON '. 5.15 - ( 1. 00):
Which one of.the follosing is:the reason why, LPI,' HPIand BS J willEbe shifted to the recirculation mode-during.a Small Break'LOCA?-
-ai The'NPSH'to the_.HPI. pumps will' be lost-ii suc ti on is.left on.
';the'.BWST with l evel below 4 feet, y b. .
The' BS . pump will begin ..cavi tati ng unl ess - i ts sucti on - i s shifted to the RB' sump. c.- To establish " piggy back" cooling mode the LPI must be taking-a suc ti on f rom - the Rt3 sump. Ld. -A more dilute boron concentration is allowed r,t this. point in'
'the accident and.therefore.the shift is desirable. -
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35.5 -EMERGENCY @g_AgNg GAL 4' (33%).
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o. h,dbESTIDN - 5.16- . y( 1. 00 ) . 1't > ,
. ~ .
'\
li c in :'accrirdance wi th . AP-525, " Continuous Control Rod Motion", there isL a
'NOTELthat states:
i"Tavg: error may go . to FW ~when Di amend 'i s selected to manual" g What signi fi cance- woul d L thi s have:-if Tavg error was the '-( * 'nti ng
^
- 4 cause of' continuous rod'.' motion?-
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wwwgy- -- i . . . . . . . . 'e . .. .. .. . Page 45:~ 7, 7
"<hkiEUEBOENCYi9ED 9pNgBb8L BULgygkyllggy -
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n , ,-. N- , g i . ,o g[',' , lH Ed6EsTIbN ' 5 [ 1.7 - t1.00)' 9 Which foneiof.:,the f ol)owing Would NOT be used to. determine the.cause'of icontinuous Control:< Rod: Moti on, . In accordance wi th . AP-525, . "Conti nuous
~
ulConteol'. Rod Hotson?" 1..r
'a. NIfpowerftrends.
g;y n ...'. b},
- Neutron-error
- c. Turbine' Bypass valves opening
-d.- LRCS Th..Tc, and-Tavg
- a. -
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b:i i i s,. < NE:_ ;EdERQgNQyiANDi ABNOF MAL ANT,gygl,1)TIQN@. .g
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- ( 1 '. 00 4, ~
- $nfaccordance with the ,Immediate D'erator p ac ti ons _of. EP-140,.
?' Emergency Roacti vi ty sontrol",~ fill in the~ blanks:
91 - ,. ; 3, , ;I F i n . Mcd e ' 6, THEN . st o; j a n y _,,,___ A__,___ o.' _____B_____. changes AND l.Estart'.boration at g r eat;er than.or equal-to _____C_____;gpm from: __D_ ,___.. h.
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DUESTION- :I 5,19- ( .1'. 00 s .
+ .
What4is:the basis for concurrently performing.VP-SBO, P1 ant Safety -
-lVerificationiProcedure", awhile performing.EP-140, " Emergency Reactivi ty Control?":'
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~ . 51 " _ ENGLONQ,,$BNQBOS6Q.$NI_EVQ(:LJIlgNS: .l -
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e; QUESTION: LS 20.: - ( 1 .~ 00) .
, 'A " Not e i ri s VP-5BO,: '"P1 ant. - Saf ety - Veri f i cati on Procedur e",-
[ hi. .: Th and.I Tc indications' may become. uneeliable 24 hours af ter a - i LOCA, " l whi ch' one of ' the 'f ol-l owi ng' i s the basi s .f or this note?
~
, a. f.high humidity; condi ti ons
.l ow ' cool ant fl ow > condi ti ons-
'. . b. l
- c. . "hi gh ' radi hti on coredi.ti ons
- d. high conta'inment' pressure conditions
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.i; 7.13_3%_
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1 2 a . , . , . , DUESTION: 5.21: (1.00) y
- Duringlaldropped Control. rod casualty,-the plant.is runback.to 60% FP.
STS 3.1.3.1' places speci fic' time requirements and power l evel . j f restri c ti onsL wi th one . rod mi sali gned > ' 6. 5% ' f rom i ts. group .' average. Wili ch : on e / of : the f allowlng i5 NOT the basis;for power 1evel
- restrictions?
a.- . acceptable power' distribution limits ara maintained.
;b.'. overpower trip setpoint. reducti on ~ ensures that DNBR 'is maintained above 1.30 during normal and ' transi ent conditions.
- c. minimum shutdown margin. is maintained, i ,
- d. the potenti al. ef f ect of a rod ej recti on' acci dent i s limi ted.
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.,.,,EMERGENCYANDABNORMA[Q1ANLEVQLUTIgNSl iE ' . t 3 3, %_ _) .
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,.9' ():" lp ljDUESTION 5.22- - ( 1. 00) . i r. , i[5InjiaccordanceLwith AP-545,'"P1 ant. Runback" Step 3.14 rec.11res the
':coperatorita notify the'.' Reactor: Specialist;if.a' runback was due to an
~
jasymmetric rod. What i s the basi s f or -. requiring thi s noti f i cation? j{(See. attached)
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.Page 51 (DU_ ,EEdd.Y_BND._GBNQBdhLQ9,NI,,ghg6QIJQNS.
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! QUESTION;' -
5.23 (1.00) . g IWhich ' one.of the '.f ollow'ing i s an entry condi tion into procedure AP-545, " Plant Runback?" 1-
~
- a. Cross . l imi .ts to f eedwa'ter p , .
- b. BOTh' output' breakers 1661/1662. tripped c'. : Loss of .' 1 RCP
- d. Low RCS flow-f-
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b 1 q. [ QUESTION '5. 24 - ( 1. 00) .
! Li s't thel. two ' entr y ,ndi ti ons that woul d requi re entr y i nto AP-990, i "7huttlown J f rom' Outs 4 de the ' Control' Room. "
n-i w 'I s N-I,'- ; 2 P l I I 1: l, 1 1 1
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!QO5STIDN- ' Si25 - ( 1. 00) .
;In accordance':with : AP-330, ' "Loss of Nucl ear . Ser vi ce. Water , " step 3. 7 s (see; attached)-requires the operator-to secure all nuclear service fwater,". raw water. and > booster- pumps When . service . water . surge tank level i t s t 0. '1 ;f oot , what 1.5 the-basis for'this action?.
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' 5;'26 DUESTION ;;
(1;Oor U In.accorcance.with.AP-770, " Emergency Diesel Generater Actuation",.
.what, actionsishould=be taken i f f ollowing - an undervol tage'. condi tion on
,lthe 4160vL ES busses, . the ' Emergency Diesel l Generators f ail to -start and
.! energize : the' busses? .
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B /~ Page 55 LDisdbEBDdWGY_GUD1baNDBdskfi M NI_EYDLUIIDUS . L) (33%). 7'-' i
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' QUEST I DN:. .' S . 71 (1.00)
.Which one'of: 'the f ollowi'ng represents the f our critical safety.
'f unctionw in order : of ; priori ty as monitored in Verification Procedure; VP-580?!
i i
- a. ~ Reac ti vi ty ' Control , Thermal Cont r ol , Radi oactive JInventory Control, Equipment Availability,
- b. Reacti vi ty ' Control , ' Radi oacti ve Inventory Control , Equipment
-Availability, Thermal. Control.
sc. -Reactivity Control, Thermal Control, Equipment Availability, a Radioactive ~In'entory v Control.
- d. 8eac t i vi t y ' Cont'rol , Equi pment Availability, Thermal . Control ,
Radioactive. Inventory Control. l l 1 i 1 l~ l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l a l L L i
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<iOUEST ON I 5.28 -( 1. 00)' '
l: . .
'Which one'of the.'fol1owing.is NOT;an entry-' condition for'EP-390, ,
l
"" Steam Gener at or Tub e,,~-Leak ?" -
t.
"1 a.- ; Main --Steam Li ne radi ation' Moni tors al armi ng -
g .. . . ._
- b. RMA-12 alarming .l 3c. Primary' leak rate' calcul ations
- d. ~Localfradiation surveys of Main Steam lines
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7,.. , 6 l' .. :-i ,
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s h ' EMERGENCY ~AND'ABNORMALP(ANT EVOLUTIONS. 2
- . P a g e ' 5 7 '-
3 ,- ~ ~_ ~. _5_5 _ __ 9 - - - - - - - - - - - - - - - - y - - ~ ~ - - - --- -- - - - . 4 l 1:.DUESTION: . S . 29 .; (1.50) L ..
~
T 'Iri; accord &nce wi th 4 EP-390, , " Steam Generator. Tube Rupture"', ' fill in the l? tblanksti 1
; "IF! RCP's have NOT - been. stopped wi thi n _____Ai____- mi nutes f rom. the
- ;.7 ti me
- t h a t _____,B_ _ __ _ __ ___C____ _ . wa s .1 o st then RCP's must _____D_____
l;j ____;E_____ to, prevent',,____F_____' damage. 1 l. p y. lr l' ( i' l-(***** ' CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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l5L_iEMERGENCY-ANDABNQMAlf'( MT__EVQ W ilQNS 2 Page'581
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-QUESTION' 5.30 (1'.00)
- Whi ch -. o.ne of L the ; f oll.owi ng, i s ' the Immediate-Operator. actions to'bre Lverifled if a RMA-3 alarm is recolved-in'accordance with AP-250, "Radi'ati on Moni tori ng Actuati on'?" .
> a.. .
AHF-11A,-AHF-11B are stopped.
?
b '. - AHV-1A,lAHV-1B AHV-1C, AHV-1D are all'cic3ed.
- c. 'AHF-10 is stopped..:
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- d. 'AHF-17A,.AHF-17B,-AHF-19A, AHF-19B,-.AHF-30 are all stopped.
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-l i, 5i_;F,MERGENCY J AND 'ADNDRMAL[d ; jT_pggtJT],0NS .
t 7,_ ( 3_3_%__) .: ,' r, , ., l:
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,l PDUESTION I
.S.31 (1.00) a l
- Whi'ch : one oF the 'f all owi ng i s thp1 CORRECT Irnmedi ate Operator Ac tion i n -
g:accordance wt th - AP-450i " Emergency Feedwater : Actuation"' f all owi ng ' a . lld]ossLo{,both, s Main'Feedwater Pumps? . j ir/;, ' i I
~ a. Trip the Reactor. ,
1 l , i l b.. Ensura that Both Emergency,Feodwater pumps start. E
- c. Attempt'to Restart 1 of the 2 tripped Main feedwater. pumps.
l 1:, i + d.: Ensure a.. runback is'ln. progress reducing power to 75%. i' ' l; .c ' 1
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34 . . . . .
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1 fr.%=.._m_'E_M_E_R_G_E_N_C_Y__A._N_D__'A_B_N_D_R_M_A_L _ A_N__ T_E..V_D_6U_ T._ _I 'O_N_ S_ ' ./ "Pa9e"60-4; i 1 n., #s. 11H'4L -4.c3 f .,s
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.j hp Nll ' ' DUESTION 'S.32
( 1. 00 ) ~ iy. , . 1 n' In f accordance. wl th AP-530, " Natural Circul at' ion"' Tabl e 2i 'Why' should 1RC. booldown NOT excoed 10: deg. ' F.= per hour'. f or Tc. greater than 280 # , id eg .( F . 7,- 3
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- h. E U 6 8 @ g N C L O N D ,,9 9 9 0 6 0 9 6 Q 9 6 L E i'0 6 (!I J O U S 13331
-QUESTION 5.33 (1.00)
In accordance with AP-1080, " Refueling Canal Level Decreace", Step 3.7 directs the operator to stop the RB purge if in progress. What is the basi s for this step? (See attached sheet) l l l l l l l l l l l (***** END OF CATEGORY 5 *****) l l l b______________________________________
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'6.01 (1.00)"
4
.[Whi ch "one' of the N ollowing':- will' NOT cause the ICS to enter'. the ' 5
' 6 TRACKING rnode j of ! operat ion 7 o' %
# ' " O "*" '
hn ;A ' ,' "; b . ul , n P1acingIBOTH Main'Feedwater Valves in Manual control. '! 1
> ,V y' -
c , .: P1 aci ng the.. Reactor Dernand Stati on .in Manual .
. 1 l- M M d. ' Feedwater Cross 1 Li mi t s in~ eH ect .
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1 o ($r -Ofll%gil. . .s . . . . - . 3EnEU8dl_SY3160SdA2931_9N . LONI-l41pg_QgNEBJG _ Page 64 ; J qJSEEE9991B16111EH_.!1231U - f2- .;y pp. 1 s MNESTION 6 ~. 02 ! ( h 00)
. . + .
Wbigh[one of.tiie fallowing purposes'is-correct-for the Control Rod I
< Dri.1.ve l mec hani sm Lead Screw?
- a. Provides coupling between the rotor assembl, and,the control -j
- r od.;
i'
;, < tr. - Determines the absolute position of the. drive.
Y n" ' c. Prevents radial motion of the upper portion of the' rotor.
.. ~
Jd. Slows the rari du_ ring the last - (12) inches of travel.to prevent damage to the torque tube.
?
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IMA.fEkbNbSYSIEUS3MNI_.GNOLANT-WIDg_QgNgSJ,C! :
' (m,,-;.,. REGFDNSI BILITIES (137.)
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- . 1 QOESTION 6.03 (l'. 00):
WhAch one of E the f ollowing sets of conditions. would directly cause the LEFICj system to ini tiate Emer( ency Feedwater'?- (assume all controls are ls;n'autot
- a. .A'itrip of one.M-in Feedwater pump at,907 power.
) I
' b' , - 1 A . ! ow 1 evel (<6") . in "A" TSG wi th HPI ' actuati on on both l channels. j c.. While' .at ' power 'anJoperator depresses the ". Trip 1" button at the local panel.
.d. An operator has placed the,SG BYPASS /RF.5El switches for Channel s ' A- D in the BYFASS'(up) position with main steam.
~~ pressure, at 700: psig, a DTSG low pressure (< 600 psi g) .
signal is subsequently received. i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1 ,
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> JcPEANTUSYSTEMS :130%)j${~'?
~ RESPONS I B 1 b_I _T_I ES__( 1._3_%. Vd. L9NI-L41pg_GgNERIC J :
Page,66: 3 k I l 1, IL. QUESTION " 6 '.' 0 4 (1200)'
;Whi'ch Lonse off. the ' f oll'owi ng oil .' pumps hat, as a' purpose to." supply oi1-toithecspeed:Lincreaser; gears ancFbearings when'the Makeup and !
Puri f i cati on .. Pump; i s ' STARTED?" e" - Mei n Gsear' .' Di'l . Pump
;a.-
Lb'. Shaft. Driven Gear ~D11l Pump
- c. Mai n .. Liaba 0111 Pump
- d. , Shaft Driven Speed Increaser Dil Pump il.
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QUESTION 6.OS (1.00) Which,.one.of. the f ollowing is correct concerning the limi ts and .
- precautions of: the CA system?
fa. Of system components that contain a boric acid solution of'
.5% wt. or, greater , . o nl y tanks need to be _ maintai ned . at n' . greater than.(105 dog. F.)
[" .b. While draining. the r3AMT ensure the heaters automatically - de-onergi.ze at the appropriate tank 'l evel .
' c. Hydeazi ne addi ti on. ta the RCS rfori nej ' operati on of makeup-demineralizern prevents release of chlorides,
- d. Sufficient water shall be available to dilute a- spill to a (100:1) ratio when handling NaOH, LiOH, or'hydrazine.
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. 6. N?LANT SYSTEMS'A30%) AN D LANT-WIDE GENERIC i -
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< RESPONSIBILITIES ( 13% Eb>" -
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_ QUESTION 6.06 (1.00) H1 WNich 'one of the statements below correctl y describes the ~ operati on' of , the.. Low Load Control' Valve (LLCV) and the Main-Feedwater Block Valve-(MBV),during a power. decrease from 100% to 15%, assuming both [ valves are in Automatic?
- a. .The MBV starts to cl ose as : Loop FW Demand : drips bel ow 80%
and the LLCV starts to close~ when the NBV reaches the fully-closed position.
.b. The MBV starts.to cicae as Loop FW Demand drops bel ow '50%
and the LLCV starts to'close when the MBV reaches the 80% caen position. . o c, -The MBV startsfto close.as Loop FW Demand drops bel ow 45% -
-and:the LLCV starts to close when the MBV reaches the 50%
open' position,
- d. The 'MBV starts to, close as Loop FW Demand drops below 45%
and the LLCV starts to close when the'MBV reached the fully closed posi t i on. I i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l
t.d[hl,A!gT_QY STEMS D Q9' f )iGWNL.9rq-L4 I pg_ggNggig _ [ Pag'e 69
.,RE.S.PONSI
. -------------------.B I L I T I ES (137. N
.DUESTION .6,07 .(1.00) l Whien one statement below correctly. describes how the .ICS. determines -
.th'a RCS flow . signal' f or determining. Whether a runback i s required?
Da. .ICS cal cul aten La 'fl ow ' signal based on RCP' breaker status. c:b. ICS calculates a flow signal based on input from RCS' loop f l ow. D/P' transmi tters. c.- 'ICS cal culates.- a - fl ow signal based on input.from RCS loop. 4 fluw tubes. sj .
- d. ;It.S calculates a flow signal based on a selectable input i-
.-usi.ng'a patch cord from the RPS cabinet.
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' " RESPONSIBILITIES - (13%) A2(At T-L41Dg_GENERig -
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1i QUEST 10N! .6.08- (1.50)
,: Fi l'l~. i n 'the bl anku s'-
<-a.-
Atl. -l ea s t' ,,,____ ____ _ c h a nn el ( s ) of excore nuclcar' instrumentation-
- mustu tse 'on scal e . wi th f uel in'the vessel. I
')
.b. .At least __________
Source Range channel (s) must be.operabin ~.
'during;the refuel.ing. operations.
r ,> . . f e
. . A .mi ni mum ' o'f _______ __ d ec ad e i s ) overl ap 'i s -requi red between the source and. intermediate range.
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(' g ':R i Pa9e 7'1 h _z_ _k__ A.bjT_f @_YS.TE_!1_S_._j 30%_) __A,FTPL AN_ _T__W I .DE_
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r; , . p ! p '! 6,09- (l.00) LQUESTION f. h ,
$ b '
l - i nterloc ks :' that 2 are NOT. bypassed? l. b'
- h. ,
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l o .: i l t***** CATEGORY 6 CONTINDE.D ON NEXT PAGE *****)
m . . _ . lL '.'. };, ; ; , if< 7 , 1 :.. ;
!R__Ei ANp SYSTgtjg_j}g31]t '06hNT-hllDE' f GENERIC ~- , 'Page.72
.BESE90H191LIIIEg_J1}3 M ' b-({?.. '
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l;' Q, UESTION ~ 6.10 . ( 1. DO E l5 Whathare the power supplies f or the fallowing equipment?
- a.-Reactor,Buil' ding Spray Pump 14 L 'b. Reactor Building Spray Pump 1B- -
L_ (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) - m____._______________ _ _ _ . . _ . _ _ _ _ _ _ _ _ _
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j6. .. PLANT" SYSTEMS' :(30$liAW'JLANT_,WlDE_GE)JERIC - - A.
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Page.73: RESPONS.I -------B I L I T I ES--( .13%_ M. '.
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iQUESTION-l :. 6.'11 :. (1.50) , Wiill e' depressuri zi ng- the ' pl ant,. i t in desired to bypass:the HPI and-
' . LPI "attuati on/ si gnal s;; T How ' and when is this accomp1ished? (Setpoints
- ,are r equi red) ir.
iI s a m 6 f '. (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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lf;.I.'. Q,iiPLANT35VSTEMS . , -' ,(30%)" . - -- j . %' A!!L 8 N I d W 11) g j g N g S 1 Q _
.Page.74}
lv ;. RESPONS I B I L I TJgg_J13Z.),, . . . ea i, ! c s ( I 6.12 ( 1. 00 ) - lIQ ESTION'
' ' -,...L . . ,
lj Wh.i chi one- of,;: the ': f oll owi ng' represent when the.. Matri x ' Rel ay Status l; J.1'arnpsion': the; ES ' Ac t uati on Relay Cabinets are:us.ed? J7 w ' a. L, Testing Only- , 1. 1, I
- b. Normal; operations On1y.
1 c. . Testing, ESF actuation i i:' d. Normal operations, ESF' ac'tuation 1
;; c.
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Page 75 l'f-J 3h;lEL9NIiSYSIE0D_l3931_9[h^PL9NI:
.BEEE9ESID161IIEg_,11g3 d WIDE Q. _9ENEBIG -
.?
i K DOESTION' ' 6.' 13 (1.
. . Match *the processfin column A wi th .the. appropriate defini ti on in i
' LColumn ~ B~ Column A Column B li 1. -Channel Check .a. The inj ection of ~a~ simul ated signal into the~ channel to
. verify proper response.
2h Channel Calibration b. Verification of acceptable channel performance by.. , observation of other available indications.
- 3. Channel Funct i onal Test c. The test of: logic elements in a prot <etive channel to verify thei r associated trip action.
- d. The adjustmentoof a channel.
such that it responds
' accurately to known ,
value. i-13 l
.(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
53, . i;'i! t.i - l ') kM -PLANIigy@T_gd@j (N'f L@y'Pk6N1;WlDE_@@$EBIC - ? .
-Page.76 p; " ' :.85@P,0N51BILITIES -(13%) V v
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\f , R1 ; r*. ' [ QUESTION' 6.14-. - (1.25) !.(There?are:twc' Lamber-lights associated with the Pressurizer Spray l: ~ valve. . : What .' .ndicati on. concerning these ember lights would be observed 11f the valvehwas: (consider each situation; separately) i . ( a. Ful'ly clased t
- b?- 30% open- 1 1
' tc . 40% open id. 'L70%.open
.e.- f ul l y. open.
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n ~E 6 I _[3 r f-b s ' b Iig b .. . !; QUESTION.
'6.15 .(3.00)-
JAfter using'the PORV to prevent a reactor trip'fromL100% power on RCS fpressure - high, indications lead you to suspect that the automatic
' reset ~of:the'PORV is out of cali brati on at . 02OO hours. You request a Ocali b'rati onEof the . PORV li f t setpoint'AND' reset setpoints.to verify (pPDRV operability. The calibration procedure requires removing power.
to the PCRV's solenoid valve which occurs at 0230 hours. Answer the f ollowi ng for.this situation. See Technical Speci ficati ons ~ attached. l fa. By what clock time must the block valve be closed to avoid being-in Hot; Standby withinE6 hours? Explain your decision, b .' - ' Attempts.to close.the. block val ve at 0245 are unsuccessful. ILC technicians determine that the pressure bistable must be replaced which may.take upfto B hours. Since the PORV i s .already closed and power removed .- f rom the. sol enoi d , can operation in Mode 1
-continue? ' Explain-what must be done,
- c. While in HotLStandby, the pressure bistable is replaced, thus returning the PORV to operability; however; the block valve remains; inoperable' in the open posi ti on. Can the unit return to-powerLoperations? Ex pl ai n your answer.
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f6[;_ELANT SYSTgMS .(30%)"AN.^?LANT-WIDE GENERIC" , Page 78- LBESEON@JylL11155l,J1331\ [ ( i; i
.- QUEST I ON . :6.16 ( 1. 50 ) - " fin '. accor'd anc e > wi t'h : DP-209, " Plant Cooldown" -f ill in the table concerning. Reactor plant cooldown rates.
RCSLTemperaturo. Allowable cooldown rates
,>,270 deg.:F. _____A_____ deg. F/hr
-270 deg. F. .
-?170 deg. F ,,_ ,.,_ _ B ,_ _ _ _ d e g . F/hr.
-i 4170 deg. F. _____C_____ deg. F/hr n-P I'
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/NA AEl 6U150YElEL1E_E9' .. . A h.GN'%9NI;Wlpg,ggyg51C :
'_ .Page.79, a,JRESPONSIBILIT IES -(13%)\/ :-
je
-QUESTION. 6.17.., (1.00)c
;Whats twat automatic f actions' woul d .be . expected to occurwhen receivitig a HighiRadiation' alarm from'RML-27'
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<fg.:: PLANT.SYSTEMSi M Q'fhAN269N1-Wlpgl,@gNgRIC- Page 80
, ily;Rgg@NSIBILITIES ' (13'4M -
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f (' IbOdSTIONL 'h .'18 ' , .i1 00) i Whil e r.ortducti ng a - tool down in' Mode 5, i f both di esel generators t'become : i noperabl e._ 1 a.- 'no technical specification attion statement i s.' entered. . H b) technical speci fications require that immediate actions
- should be taken ' to estabi t sh Mode' 6, o
I c i- Litechnical~ specifications require that positive, reactivity changes be stopped,
- d. : technical ' speci f i cati ons req.ti re i. hat = 0TSG's must remain
., operable as a means o f . heat.. rt,emoval .
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RESPONSIBILITIES'-(13%) d
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, i t, f-QUESTION: -6;19. , (1.00) ur,
,According.to.the technical specifications,'whi3e operating'in Modes'1
- -thru 3;-the maximum' level allowed in the DTSG'.s on the operatingDrange Lisa a.- 83%
i
- b. B7%
.c.. ' (?5%
. d .~ .98% 2l, f
b
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dNh:iPANIL SVGTEMS'(30%) AN 7 LANT-Wi:n ~ GENERIC Page 82. bbbbbbb b b Ibb.3 bb - p j_ w
-DUESTION 6 . '.2 0 (1.00)'
- h. DG A', .whi ch .nuppli es ES 4 KV bus : A is ~i noperabl e, LPI pump B. supplied byLthe ES 4 KV bus B i s inoperabl e. .Which one statement below.is
- correct concerning' continued operationiin Mode 17 Refer.to Technical SpecificationsJattached at the end of the ' ex ami nat i on ,
a, The acti on . statements f or both the LPI pump and the DG are E' applied i n d ep en d en t '. y , each must be restored to operable status in172 hours, b ,' Since tNe DG is required in Mode 4_and the LPI pump is not, th? unit'must be taken'to Mode 4?within 72 hours.
.i'
-c. T.S. 3.0.3 applies; i t requires acti on- to place -the uni t hin-a mode.in which the specification does not apply within l' R
' hour. j Ed. T.S. 3.OiS applies;-it". requires <ction to place the unit in a mode'i,'which the specification does not apply within 2 hours.
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i (***** CATEGORY 6 CONTIN lED DN NEXT PAGE *****) L-1 _ _ .I
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9 e.._E.R_I 83 C_ .
' J! RE.S. P_O.N.S, _I _B_I L_ _I _T_I _E S_'_( 1_3%_)'d _ _ __ ___ _' .
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. , . .6', 21 -
,( l'. 00 )
cQUESTION' - t; LIST (tije'4;. areas protected by the Lo.4 Pressure Cardox system. 1
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Page'84c 7., LANT-WIDE GENERIC-p"lu . PL ANT J SYSTEMS: (30%) ' AN.
,r ; RESPONSIBIL'ITIES -(13%)_ ..' -
w .l r . 3 DUESTIDN- : 6.22. (1.00)' ;
; IWhihh'one"of the f allowing is NOT a pri' mary' f unction of the Spent Fuel L. ! Coo 11 ng '. (EF) syst em7 :-
M: a. . Provide for' storing spent fuel assemblies. 7 ..
- b. Rai se' and ~1ower .the Water l evel l'n the spent fuel pools and the cask ~ loading area.
. Remove the Decay. Heat generated by stored spent fuel
. assemblies.
L ).
'd. Provide purification of t.he spent f uel= cool ant for. chemistry-purposes and to ; maintain water clarity during f uel handling operations, y,;
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..;h,_;EhNNT! BYSTEMS T ( 307.) , ,- Page'85
't i,R_E_S.PON_S_I __ B..I.L
_ _ _I T__I E__S ( .137. ) V' @NT-WJ.Dg.,,gENERJ,5.
- - . ~
v ' t j. dOVESTIdN: 6.23 (1200)
' Refer tio Figure 13, attached.
~
" Whi ch one. of.. the f o11 owi ng' correctl y represents the correct system ialignment.as shown~in.: figure 13.
La . . SFLcooling with.the. DH' system. 5 h- b. SF. pumps / valves operability checks.
- c. .DHR-with the SF pumps.
' Ld . Filling the' spent fuel pool with the SF pumps.
i. 1. l l 1 l
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r, . y 9 .. ' L %.,_ _ _- _: _P L_ A_ N _T _' S_ _Y _S7'_( _T E3_0%_)_A_N M_ _S ___ _ _L A_ _ _ N _T - W I D E ' G E N E R I C '
'Page'O6'
;:-RES m.
1 - _ _P_ON__S_I .B..I-- L I _T _I. E. S__( _13%_) I , .i, f' lll QUESTION: 6'.24.' i -( 1. 00 ) L Concerning steam production in the DTSG, at what: percent' power does
,the amount.:of superheat'rnach its. peak? (choose one).
I, l- y'
.a. 64%
.',6. 71%
' 78%'
!:-i. . c. j . s. U 'd. 85% l 1 i j (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1 l l i J
._. . , _ _ - .f - _ _ - _ . _ _ - - . _ _ _ - -
.J . -
- 2. 180 deg. F and; s until.' reactor' power. exceeds 5*/. full power, a continuous minimum il f eedwater flow of at.least _____A_,__,,, gpm to the OTSG main. f f eedwater nozzles 'should- be established. 1 l3) [The ma91 mum steam generator heatup rate'iy __,______ deg. F./hr.
k
- 14. : ~' h ' * . i a ;,. . steam generator operating l evel in> _ _ _ _,,,,,,,_ i n c h e s .
i, 1 l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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QUESTIDN' - 6.26 '(1.75)
- Complete -the f ollowing ' table dealing with reactor ' operating condi tions j
!perqTechnical Specifications. .
.4
'; hod e ' Rea c t i vi t y' Tave Power l-COLD SHUTDOWN (a) . (b) -
; HOT SHUTDOWN. (c) (d)- .-
.1 (g)'
'HDT:-STANDBY -
.(e) (f )
.l a
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gj ,_PL, ANT SYSTEMS ~(30%) AN ' LANT-WIDE GENERIC Page 89'
- BEgt*0Ng!pjy111Eg,J1331
\ QUESTION 6.27 (1.00)
. Answer the follps':ing cc.',cerning the Decay Heat R e;;-" * ! Tustem:
E1. What i s the reason f or delaying the opening of DHV-5 and DHV-6 (containment i sol hti on val ves) during a loss of c ool an t accident until reactor pressure decreases to 500 psig? {
- 2. Why is it necessary when placing the Decay Heat removal system in operation t.w M3ke-up pumps must be red tagged out?
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- 4. T e.RQSP_O_N_S_I de
_B_I L I T _I E_ _S _, ( 13_ _% ) ,%./._
. , - - - - - - - o qi p:
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ff QljEST ION - . 6.28'
' ('1. OO L , ,
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' v~ . , . . . .
v . . LWhich ; oneJof y.thelf o31owing i s' NDT cool ed by the.-' Decayf Heat Closed
; DCycl e' Cool i ng "t DC) ' system? .-
,;p l v , l?' , . . . .
,l a . .' " .Make up pump'1B-and motor l'
j '>
- 3. Lb., -Decay Heat.. removal ~ heat'exchangerrr
,. .{t 4
.c. Reactor BuiIding Spray pumps.and motors
- d. DC pump motor air. handling-units'(AHF 15A/B)
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6: > % f_' tp ROUESTION.; ..6/29. 1.1. 00 ', l a ,. . :I ' < .. . .- pfWhen runni ngl RW pumps, 3A. or. 3E, . why,1 s : i t necessary .: to - have = the - !: corresponding DC . loop. operating?
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gLi ,, 4 i k '[f' ;', ( .,\,l ill ' p: P r.:D. UEST I ON ' 6.30 ' ( 1. '00 ) g
. '.. 4 .
[! . . .,l Accor' ding ( t a:'.AliSOO,: ..which'onelof the following_must'be used.for.
; proper ' tracking" of _ "speci al val ve line-ups?"
4
-- a . lPiacing an' entry l1'n the operator'.s log, j W. - .
- Listing on the' shift re)i ef check 11st.
c.- Pl aci ng ':an ~ entry i n the shi f t supervi ser 's log. .: - d ,- Making a temporary procedure. change. l-r ll
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I('*****-CATEGORY 6 CONTINUED DN NEXT PAGE *****) a -----_____m._. _ _ - _ . _ _ _ _ _ - _ _ . _ _ . . , _ , _ _ _ . , . . _ _ _ _ _ . _ , _ . . _ _ _
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n, ,y I i', J . , f f : 'i y ,. . . . . . . .. 2 . , . . . ' l A N_:Y^ANT y m WIDE' GENERIC'- fi g_ _..i P E_ A_ N_ T_ _? S_ _Y S_._T E.. M_ S _' _1 f P a g e . 9 3-'- _ _3_, 0_ _% _-)-' g W __ fh @ E EPgl4Slp16111Eg_ H T H , j :, .. , L. ' l-i' = YOOE$iTION 6.31 ,(1.00) m- - Ii ' LjilI4h$se T'aut' hor fr ati on, by title, is required toyallow a " Radiation' 's., . ? Weir ker"- who l har. ' compromi sed " Radiological Saf ety" re-entry into the. li. L R C A ? :
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QUESTION > .6.32 '(1.50)
- [What are the.three times that a Self-reading Pocket Ion Chamber (PIC)
MUST-be-re-zerced? .z
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'k DUESTION c6.33 ' : ( 1. 00) fWhat are the : requirements in accordance with CP-115, " In-pl ant. .
(Equ'ipmont; Clearance ~and Switching. Orders, when.using Air Operated
' valves in clearances f or system isolation? (Address DOTH ccses of Air.
J/Opeeated Valves, . iei ones that f all . open and those that f all closed)'
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Page'96 jESPONDIDlb111ES_jlH1N 3 j .i k h, ' # '
- QUESTION' - 6.~ 3 4 (1.00)
,g Concerning-the use'of. Blue Tags answer the - f oll owi ng:
. 'a . e .
'Whose. permission is required t o c l l ow a p er son , otlh er than the:
A person that the Blue tag was issued, operation of the tagged I
- n. ,
' device?' -
- b. When per mi ssi'an 'i s' granted to allow other ,than the person issued
-the Bluo. tag,.how many times can it-be operated? .
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{? N. _ll 3; J N'.;* j' , z( *': GkJ ', Oli a L-QUEST!DNl 6.35'. ( 1. 00 )' l . LWhich'oneiof the' f ollowing is' correct concerning the use of' Dlue Tags.
.h. can.befused~with:another Blue. tag..
b.. : can be used with .a Red tag.
;cs. can be used.with a White tag..
- d. can be used wi th .a Red and Whi t e tag.
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,OUESTION- '6.36 . I 1. 00) ' ; .0$:the f ollowing whose responsibi'llty Is it'Lto ensure that all .
J.twelding, cut ti ng, or spark-producing" work done'at CR-3. complies with H CR-110, ' " Fire Pet. venti on Work Permi t ; Procedure?" (Choose One)
-a.. Nuclear Fire. Protection' Specialist
,i 4 b.. ~ Senior fduclear Fire. Protection Speciali st T;
m -c.- On-Duty Nuclear Shi f t Supervi sor-g d.. ~ Plant Manager l J 1 (***** CATEGORY .6 CONTINUED ON NEXT PAGE *****) _ . o.. . .- .- _ _ _ _ _ i
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l;s;f," 3 1 ./! , .. , P a g e :9 9 '.1 2, I"61h_ELONI;3ygIgdg,, c ' , RESPONSIBILITIES (137.A/ j307.) - AN96 ANT-W I Dg,GENER I C : ' ("\#]; .]
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'i Ip. QUESTION' l
. 6.37' - ( 1. OO P I.' ' When ,perf orming . procedural ac t i ons , Wor ki ng Copy" procedures =shall .be L used, what is the only exception to this?
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$N 2_ELONIb@y@lgtl5'Y30%$ AN[d @NI$ Wipe _QENEB1G -Q ._ WW RESPONSIBILITIES-(13%) ' (Q - H lgh;l4 , i ti l liOUESTION.:L 6.38. '(1.00) Uc I [.: Operating procedures can be cl assified ' as ei ther a) Step-by-step or b)
~
What l di stingui shi';ig f eature l's requir"ed by the Step-by-step [* l =. Gui dance. th'atlis n'ot required by the. Guidance type Operating rprocedure I 4,4 procedure?
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ROU.ESTIONl- '6.39 -(1.00)
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'.Duringf periods L when the shi f t J compl ement i s',l ess'. than normal , what
-: makimum . grace peri od exi sts, . providing immediate. action has been taken byithe. Nucl eahf Shi f t: SUpervi sor - to restore'. shi f t complement - to Minimum tTechnicaliSpecifications requirements? -(Choose'One) I
'a.-
-60 minutes
=
f.) <! ts . ~90 minutes , 4
' c .- /120' minutes y-
.d . . . 150 minutes:
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- QUESTION- 6.40 (1.00);
In'accordance with Al-500, '" Conduct,of-Operations",_during: ,l reactor'startups, scheduled' shutdowns and recovery f rom' reactor 'I !\'.; trips, '.how many.. li censed : reactor ' operators 'are required to : be at the Li \ =1 c c msin contral board? . [ij i I i, tf 1 l- 1
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;OUESTION.: 16.41' . (1.50F p )Duri;ng ~ Abnormal'~',or. Emergenc9. condi ti ons whi ch would <equire the f Nuclearf Shif ti. Supervi sor . to assume a " Command" position,.who are the
~
/three other indi vidual s, ~ by title, that are authorized to relieve the h(Nucl ear Shi f t Supervi sor. of " Command" duties?
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i- Q U E S T I O N ' 6'42l ~ ( 1. 00 )l
" Whi ch l one:- o f the' follow 2ng i s'NOT. required to-be done when replacing Jcd removing, a ' chart 1f rom a' recorder?
' ' a '. - ' record the date on;the chart paper.
- b. ..recorri ~ the recorder i den ti f i cation Enumber ' on the chart paper.
.. c . ' record'the parameter'being recorded on.the chart paper. _
<d.' .
record'the'name of: the. i ndi vi dual . changi ng the. chart paper. a;
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,J. RESPONSIBILITIES (13%) Y '
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- . QUESTION L6,43'- L ( 1 :.~ O O )
Iniaccordance with Al-500, Con duc t of Operations, 4.12 Work'ir) systems that'.could trip the Unit", whi ch one of the .f ollowing, does NOT
~
l require. pri or,Japproval' bef ore ~ perf ormi ng 'mai ntenance?
- 1
-'a . - Nutiear Instrumental 1on
' ' b; Turbine EH Control System l
- c. ~500KO Pratective Relay
'd . Emergency Feedwater I ni t i ati on and Control' System l
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- I 4:,g iQUESTION.- '6.44 -(2.00)
' v. 4 ,, , . i gj What,.. are.t the'. three Immedi at e Acti ons' i n accordance wi th ' AP-513,'" Toxi t.
'eGas?"- '( I f NO,T , . Then.-statements are;NOT_ required) 2, h
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-(********** END OF EXAMINATION **********)
l .
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? REFERENCE 4
.CR' ROT i l-10.'pp '17-20 i Lesson ' Obj ecti've '9.
,192006K106' ..(KA's) y, J. ANSWER 4.02 , (1.00)-
REFERENCE
'CR ' ROT 1-10, pp 19-20
' Lesson Objectives c 5,6,7,8,9,20- _
(3.1/3.2)' l 192OO6K110 . . '( K A ' s ): H ANEbiER , '4.03 ,(l.00)
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l;. REFERENCE
'CR ROT 1-9, pp 23-24 i
-(2.9/2.9) .j
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__ MOD _Y_N AM_I C_S r Page108'. '< K ' OZZdLON9_G9dEQNEyl[j,,,{l,!pjl_,[EyNp8dgNI96Lgf 9D1 ' - - - - - t j L , .4 .:. , , i
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- 192OO4K110' .'. (KA's) 3., \L Ky, <
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' REFERENCE- ' I
. p \;
TI'li Operations Procedure,LDP-210, pp 1-11 _.
. <:.t(ROT (1-12,,p. ' ~
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ANSWER: - 4.06- l' ( 1.' 00 )
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"REFERENUE-. , ;
i CR RDT;1-7, pp 26-28 1espon 3 Objective 16 Reaqtivity'Warth Curves, OP-103C i
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{T HESDRDYN@DlGS cANSWEN 4,07 - ( 1. 00) ~
E0.25 Leach 3'
- .i n s t an t an eou s , all, si ngl e, highest
> 4 T' REFERENCE CR Techni c a1' .. Spec i f i c at i on s, Definitions'1.13, p. 1-3 No Facility- Lesson Objecti ve identi fied
- ( 3. 2 / 3. 6 ) -
fl92OO2K110 ..TKA's) J
-ANSWER 4;.08 (1.00) il h
i REFERENCE
-CR ROT 2-2, . 39-42 (
Lesson ' O! .,ecti ve '15 (2.8/2.8)
~193OO4K11S ..(K4's)
ANSWER 4.09 (1.00) C
-REFERENCE i
steam tables
~CR ROT 2-2, p. 18 Lesson Objecti ve 8 (3.3/3.4) 193OO3K125 ..(KA's) f***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
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(REF RENCE "CR RDT 2-3,"p.[49' L:esson ' Obj ec t i ve 18:
= Gur ~veill Grice Procedure,L SP-312, p.~:,.1-14
., (3.1/3.3); 1 t 193007K106' . . ' ( K A n ) ' I 3 ANSWER- 4.11- (1.00) i Ja; i, - 1 INEFERENCE' 1: $'CRiROT.2-4', Lesson .Obj ective 9
.- ( 3. '1/ 3. 4 )':
'193007K108 ..(KA's)
ANSWEH '4.12' (1.00)
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- . REFERENCE-1
- 'CR; ROT-2m6,:p. 24 '
! -Lt.4 son Objective 7 j' '. ( 3.' 3 / 3. 4 ) L l~ L 193006K 110' . . '( K A ' s ) i< l I' l h; ($**** CATEGORY 4 CONTINUED ON NEXT PAGE *****) p
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, A.
- REFERENCE
~ CR; ROT : 2-9, pp- 6-8.
-Lesson' Obj ecti ve 3 ,
1 ( 2. 9 /3'. 3h
- -193009K107'- 4 .(KA"s)
.. ANSWER'- ~ 4.14. . (1.00)
.i b
'. REFERENCE CR' ROT:5-73"and ROT-2-14
- (3.8/4.10
' 193010R107 : . . (KA' m):
. ANSWER 4.15 '(1.00)
,b.
REFERENCE
'CR' ROT 2-8, p. 34-38 (3.2/3.3) (3.3/3.5)
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(***** CATE60RY 4 CONTINUED ON NEXT PAGE *****)
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I 4(? REACTOR'PRJNG1P_LE@_12%hdE_R_MQDYljAMig@! Page112
' ' 1Z'f) AND .- COMPONENTS - ([L,d (FUNDAMENT ALS__EX, AML .
a l ': ANSWER < :4.16L '(1;00) g~ C
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PREFERENCE l1 ((CRLROT.4H5 chapter'er p. 90 -.91,.93;- 95
. Tec tin i c al Specification.section 3.7.1,.1
'( 3. 3/ 3. 4 ) -
E [- 191'OO 1 K 101 - ..(KA'si !r r
ANSWER 4.17 <1.00)
\~ b 1 o .. . 1' LREFERENCE-1 l L ; No ' Specifi ci Facili ty 'ref ereiice identi fi ed. (3.1/3.3) ,
.'191002K119. ..<KA's)
LANSWER 4:.18 (1.00)
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'fREFERENCE' CRJROT 3-10, p. 17 (3.3/3.5) .! 191002K117 ..(KA"s). ) 1 i (***** CATEGDRY 4. CONTINUED DN NEXT PAGE *****) 1
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1-(7*/.) 'AND' COMPONENTS
----------..----------------- ------- (1------ ..) (FUNDAMENTALS EXAM) -
7 k* b IANSWER. 4.19 (1.00)
! REFERENCE CRiROT 2-8, p. 30'& 32 1
-(2.8/2.9) (3.0/3.1) 191004K123 191004K124 ..(KA's)
. ANSWER 4.20 (1.00)
LThi potential exi sts that non-condensible gases coul d coll ect on the h11t transfer surface of the primary side of the OTSG tubes. If
- thi. were to occur, non-condensibl e gases of sufficient quantity could shut off the boiler condenser process due to the increase in r Di tance to heat transfer. (1.00)
REFERENCE
'CR ROT 3-5, p. 6 L.D. #2 (2.4/2.6) 191006K114 ..(KA's)
ANSWER- 4.21 (1.00) C' REFERENCE
~CR ROT 4-3, p. 52 l (3.1/3.3) '2 'r/3,1) b 19100GK111 19100BK103 ..(KA's)
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4 4. . - REACTOR'PRINC1PLES ( 7 7. THERMODYNAMICS j Page114 IZ31.6MD_CODEONENIS_1132L_1EUND8 DEN 186S_Ef8dl ->
' ANSWER 4.22 (1.00) d REFERENCE CR Operating Procedure, OP-302, p. 5 NO Specific f acility training objectives identified (3.0/3.1)
I 191005K106 ..(KA's) f ANSWER 4.23 (1.00) . 1 l O REFERENCE CR Operating Procedure, OP-402, p. 8 (3.0/3.1) j 191007K108 ..(KA's) ANSWER 4.24 (1.00) d REFERENCE CR ROT 2-17 (3.3/3.5) 791008K108 ..(KA's) (***** END OF CATEGORY 4 *****) 1 l9 mm..._ . . . _ _ _
-e Si-- EMERGENCY AND'ASMORMAL N dNT EVDLUTIONS /^ 4 Page115' p ,0 q337.) ~~~~~~~~~~(./~~~~~~~~~~~'~~~'
s, lI ANSWER 5 5'.'01 ,
-11.00)
.At ,
LREFERENCE
' CR Tech'-Spec 3.1.3.x, pp'3/4>1-18 theough 3/4.1-37
..(3.1/3.3)
OOOOO5 GOO 3 . .' (KA's );
'.' ANSWER , - 5.02- ( 1. 00)'
1 b l REFERENCE
;CR Abnormal' Procedure, AP-5BO, p. 3 1
1: :(4.1/4.4) l'
- OOOO24K301 ..(KA's) 1' 1
l' ANSWER 5.03 (1.00) l t, d. 1. l\ ., c . REFERENCE 1 1' i_ CR ROT ~5-30, p. 4 L (4.4/4.7) 1. 1 OOOOS6K302 ..(KA's) L. L L g l' L- (*****'CAlFGORY 5 CONTINUED ON NEXT PAGE *****) ___ -__ m_m.-____-___.,__ _ ___._m__.._._.___.-..._-_._______.._______.m. _ . _ _ _ _ _
p ., .-.- e , ; , 52;: W c Pagell'6.
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ANT EVOLUTIONS 5 5;).
'-- dEMERGENC'YidND~ ---------- ABNORMAL! -- m ------------- .
7 , 3 3.,, 3 . g i 1 l .s f ILANSWERT .5. d4. (-1. dO ?- U.c: l -
> REFERENCE.
CR ROT 5-65, pp 4LS
~
Abnormal-Procedure,.AP-460, p. 3
, (4 . 5 / 4'. 7 ).
- -f OOOO40K304 ..(KA's)
, ANSWER '5. 05 - '(1.00)
, b
-' REFERENCE CR Emergency Implementing Procedure, EM-216, p. 2 (3.1/3.9)'
OOOO67K102 ..(KA's)
' ANSWER- 5.06 (1.00) ld'
.' REFERENCE CR RDT 5-31, p. '11 L 12 (4.2/4.5)
.OOOO68K318 ..(KA's)
(***** CATEGORY 5 CONTINUED DN NEXT PAGE *****>
hi ' 1 gh @ENgn9Np_SDNQBUS6' ..ANI y g6QI19Ng: Page11'7
?
L y i.!.ANS'WER- 5.07 -(1.00) b1 ,
'. REFERENCE' t
- (
'CRJROTl5'-19, pp.3 & 4 J '
_ Lesson Objective 2' Emergency Procedure, EP-290, p. 3
-(4.0/4.4)
OOOO74K311 ..(KA's) 1,
. ANSWER 5.08 (1.00) c {
REFERENCE CR'. ROT 5-28,'p. 4 Lesson. Obj ecti ve ' 3 - (3.7/4.0)
.OOOOO7K103: ..(KA's) 1
^ANSWERJ 5.09 (1.00) i C-(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
1
.};d[i $ EMERGENCYT AND ABNDRMALCLANT;gygLLJTJgNS .Page118 , V b ( 337. ) , ,
, - 1
- 26 6:: \'
,iREFERENCE. I 1.!::LCRE RDTJ5-62,1p. 2 & 3 , L" "Lessom Objective 1
- Abnor mal ~ Procedure, AP-360,'p. 1 K L(3. 6/3. 9) -
y . . .
;OOOO25G011:. ..(KA's) -ANSWER- 5.10 (3.00)
C
.A REFERENCE
'CR RDT.5-62,'pp 8 & 9-Abnormal: Procedure, AP-360, p. 5 (3.1/3.4)
OOOO25K301 ..(KA's)
' ANSWER 5.11 ( 1. 00') -
t.. c
- REFERENCE CR.RDT 5-63, p. 16 Lesson Objective #3 Abnormal Procedure, AP-3BO, Step 3.14
-(3.6/3.8)
OOOOO9K327 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
5, EMERGENCY AND ABNORMAL ANT EVOLUTIONS Pag e 11'r e-} 133^d1 ANSWER 5.12 (1.00) ( M b e o Lil7
& netactsi,_4Q c }r ip p u sii-b u L L ur15 LU.DJ Ensure CRD Groups 1 through 7 are f ull y inserted g,o IF NOT FULLY inserted open breakers 3305 and 3312 In.53,r#<
REFERENCE CR Abnormal Procedare, AP-580, p. 3 ROT 5-28, p. 4 } Lesson Objective 2 (4.5/4.5) OOOO29G010 ..(KA's) ANSWER 5.13 (1.00) d REFERENCE CR ROT 5-63, p. 10 Lesson Objective 3 Abnormal Procedure, AP-380, p. 9 (4.0/4.5) OOOOOBK305 ..(KA's) ANSWER 5.14 /I .00)
/
/p /
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l l
3- EMERGENCY AND ABNORMAt ANT EVOLUTIONS )
\
Page120 13331 REFERENCE CR ROT 5-63, p. 1 ROT 5-28 1 Lesson tives #1 J)h' ec. j Abnor al Procedures, AP-380 and AP-580
.4/3.6) 000008A220 ..(KA's)
I ANSWER 5.15 (1.00) a REFERENCE CR ROT 5-63, pp 30-32 Lesson Objective 3 Abnormal Procedure, AP-380, p. 31 (4.3/4.4) 000011K315 ..(KA's) ANSWER 5.16 (1.00) Would result id a feedwater perturbation (When diamond is placed in manual ) (1. 00) REFERENCE l i AP-525 p. 5 CR-ROT 5-67 p. 2 NO L.O. 4 (3.4/3.7) 000001K114 ..(KA's) j ANSWER 5.17 (1.00) c. l l (***** CATEGORY 5 CONTINUED ON NEXT PAGE ***4*) i } l 1
- 5. EMERGENCY AND ABNORM:AL ANT EVOLUTIONS Page121
(~') 1222'1
~REFERENCE f
CR-ROT 5-67 p. 2 AP-525 p.5 (4.4/4.6) OOOOO1A205 ..(KA's) ANSWER 5.18 (1.00) A 4pg3 al ter ati ons (0.25 each) Bhreactivity changes C 2700 gpm D BWST REFERENCE CR ROT 5-16 L.O. #2 EP-140 (4.0/4.0) OOOO24G010 .. (KA's) ANSWER 5.19 (1.00) Provides a means of guiding the user through all four sections of the VP thus ensuring that each critical parameter is observed. (1.00) REFERENCE CR-ROT 5-16 p. L.D. 43 EP-140 (4.2/4.4) OOOO24K302 .. (KA's) ANSWER 5.20 (1.00) C (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) l l
- 5. EMERGENCY AND ABNORMA gANTEVOLUTIONS r'~ Page122
\~'
.3E}Z1 REFERENCE VP-5BO P. 6 CR-ROT 5-75 p. 13 L.D. #3
.:4.4/4.6)
OOOO11K312 ..(KA's) ANSWER 5.21 (1.00) b REFERENCE CR-ROT 5-74 p. 5 L.O. #3 STS 3.1.3.1 p. 3/4 1-18 B 3/4 1-3 (3.3/3.7) ODOOO3K302 ..(KA's) ANSWER 5.22 (1.00) l (Recent events (AND-1) have proven that) A mi sali gned or dropped control rod with subsequent incorrect recovery acti ons can lead to drastic conneauences, (thus the requi rement of contacting the Rx Specialist) REFERENCE AP-545 p. 9 CR-ROT 5-68 p. 10, L.D. 43 3.8/4.1 OOOOO3K304 ..(KA's) ANSWER 5.23 (1.00) l 4 { l l { (***** CATEGDRY 5 CONTINUED ON NEXT P(4GE *****) l I i l 1 L__--._. _ -.
Page123 Sz__E9EgGEggy_egp_eggggyelq ge9I_Eyg6gIlggg (~} N_s ( 3_3 /. ) REFERENCE AP-345 p.1 CR-ROT 5-68 p. 1 L.C. #1 (3.5/3.6) OOOO15G011 ..(KA's) ANSWER 5.24 (1.00)
- 1. Control room uninhabitable due to fire (0.5 each)
- 2. Fire in the cable spreading room which affects control room cont rol s. f REFERENCE AP-990 . 1 ND L.O.
(4.0/4.1) 000068G011 ..(KA's) ANSWER 5.25 (1.00) these are secured to prevent damage t o the pumps (0.5) and to ensure availability once servi ce water inventory has been restored (0,5) REFERENCE AP-330 p. 7 CR-ROT 5-61 p. 11 L.O. M2 (4.0/4.2) OOOO62K303 ..(KA's) ANSWER 5.26 (1.00) Ensure all feeder breakers to the affected busses are open (0.5) then close the feeder breakers from units 1 and 2 (3211 and 3212) by(0.35) hol di ng in the cl ose posi ti on for approx. 10 sec. (0.15) i i 1 (***** CATEGORY 5 CONTINUED DN NEXl PAGE *****) l E _ _ _ _ _ _ _ _ _
'5 __ RGENCy_@ND_@@NOBU@!q g8NI_EyOLUILONS ~}
Page124 REFERENCE { CR-ROT 5-30 L.O. #2 AP-770 p. 3 (4.3/4,6) OOOO55K302 ..(KA's) ANSWER 5.27 (1.00) a REFERENCE CR-ROT 5-14, p. 9/10 L.D. 10 (3.8/3.9) OOOOO7G012 ..(KA's) ANSWER 5.28 (1.00) C' REFERENCE CR-ROT 5-20 . 2 L.D. #2 EP-390 p. 1 (4.2/4.3) OOOO38G011 ..(KA's) ANSWER 5.29 (1.50)
- a. 2 minutes
- b. subcooling
- c. margin (0.25 each)
- d. remain
- e. running
- f. core I l
(***** CATEGORY 5 CONTINUED DN NEXT PAGE *****) i l l l I 1
5- EMERGENCY AND ABNORMAL ANT EVOLUTIONS /~S Page125 _( _3 3_ _ */. _) k-) REFERENCE EP-390 P.13 1.o. #3 (4.1/4.2) OOOO38K308 .. (KA's) i ANSWER 5.30 (1.00) a. REFERENCE CR-ROT 5-60 p.2 L.O. #2 AP-250 p. 2 FD-302-751 (3.3/3.3) OOOO61G010 ..(KA's) ANSWER 5.31 (1.00) b REFERENCE AP-450 p. 3 CR-ROT 5-64 p. 4 L.O. #2 (3.2/3.2) ! 000054G010 .. (KA's) ANSWER 9.32 (1.00) To prevent steam bubble formation in the reactor vessel head. (1.00) REFERENCE CR-ROT 5-25 LO.O *t3 p.B AP-530 (4.2/4.7) OOOOO9K101 .. (KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) I - - -__ _
5- EMERGENCY AND ABNORMAL ANT EVOLUTIONS /~'i Page126 , (
.3.3%)-- U !
1 t- { ANSWER 5.33 (1.00) { prevents the spread of any airborne contamination (0,5) j c.
- b. helps eliminate any di f f erenti al pressure between the AB and the RB. (0.5 )
REFERENCE AP-1080 p. 9 CR-ROT 5-72 p. 3 L.D. #3 (3.7/4.11 , OOOO36K303 ..(KA's) l I l l (***** END OF CATEGORY 5 *****)
Page127 l hi_ _P699I_ Syg IEL1S_13931_9[Q'69NI;W J DE_ GENg g] C (~)T BEgPONSJg]LJIJEg_f1}31 j I l l ANSWER 6.01 (1.00) ; i
- b. (1.00) i t
i REFERENCE j i I OP-OC-SPS-IC-ICS P 23/24 LO IH l CR-ROT- 4-14 L.O. 2d p. 11 4 (3.2/3.2) j C59000K107 ..(KA's) ANSWER 6.02 (1.00)
- a. (1.00)
REFERENCE i CR-ROT 4-27, L.D. 1 p. 7 (3,4/3.6) OO1000K103 ..(KA's) AMSWER 6.03 '.1. 00 )
- b. (1.00)
REFERENCE l CR-ROT 4-15 L.O. 15 (4.5/4.6) 061000K402 ..(KA's) ANSWER 6.04 (1.00)
- a. (1.00) i
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I
- - - _ - _ _- i
i 6; PLANT SYSTEMS ( 307. ) A! (LANT-WIDEGENERIC
/~') Page128 l BESPONglB161115@_J13Z.1 ks' )
i REFERENCE j i CR-AND-82 i (2.5/2.6) f i I OO4020K618 ..(KA's) i ANSWER 6,05 (1.00) j i REFERENCE CR-ROT 4-2 CH. 4'L.O. 4
.( 3 . 1 / 3 . 4 )
OO4000G010 ..(KA's) ANSWER 6.06 (1.00) d. REFERENCE ANO 96 L.D. #6 i CR-ROT-4-5 CH. 4 L.O. 46 (2.4/2.6) 059000K401 ..(KA's) ANSWER 6.07 (1.00) REFERENCE CR-ROT-4-14 L.O. 42 p. 10 0590GOK107 ..(KA's' (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i
ca < .u
- 61hkl] NIiSYSIgtig_jjghh8@^fPLS!!I:!!!Dg_GENEBIC : :Page129; RESPONSIBILITIES (137.)hs -
'3 '- y Ws ,
TANSWER.' 6.08 - (1 50)
- a.. ons, (0.5 each) b.1 t'wo
= .* c . r > on e..
[ REFERENCE CR iROT-4-10 L.O..4, p. 37/40
'.(3.3/3;5)
;015000G010
..(KA's). ,
ANSWER 6.09 ,(1.00)
- a. 111ftl oil pressure-(0.5) ib. . cooli ng . water f l ow (0.5)
REFERENCE CRLROT-4-1 CH. 1.0 p. 36 s . ( 2. 6 / 2.' 9 )
,003OOOK6f4, . .. ( K A. ' s )
ANSWER 6.10. (1.00)
- a. 4160 VAC ES bus 3A' (0.5)
- b. 4160 VAC ES bus 3B ' ( 0. 5 )
REFERENCE CR-ROT-4-1 CH. S'L.O. 2a,
-(3.4/3.6)
'026000K201' ..(KA's)
(***** CATEGORY 6 CONTINUED ON NEX1 PAGE *****)
f{ q:: :'
""a" E55E!!!f!!! ids !Is!D -
JOL
':y
' ANSWER: 6.11 (1.50)
' . Manual 19 done~for each channel (0.5)
) HPI: signal may be bypassed.'when RCS pressure is'less'than or equal to
;1700 psig. (0.5)
;;LPI signal .'may be bypassed when RCS pressure is loss than or equal to, 900 psig. (0.5)
-REFERENCE J CR-ROT-4-- 13, L.O.#6 p. 10
.(3.7/3.9) 013OOOK412 ..(KA's)
- ANSWER 6.12- (1.00) a.
REFERENCE
'CR-RDT-4-13'- p. 32 L.D. 14
.(3.7/3.9) 013OOOA301 ..(KA's)
- 1. sb ANSWER 6.13 ( 1 rOO+-
- 1. B 1:2. D~
3.'A (0.50 EACH) l
. REFERENCE-CR Technical . Specifications (3.3/3.6) 015000G013 ..(KA's)
I l (***** CATEGDRY 6 CONTINUED ON NEXT PAGE *****) i
. [-__ _--_-___..-__m.__ - - - - - . _ . . - ..__
$[bPLANT= SYSTEMS (30%> ' ANP 7L ANT-WIDE- GENERIC- <Page'131 1
--~~REEE5ssisiEiiiEs ii33.I V ----~~~~~-~ ~~~~~' -' O-? u
.)
i 1 ANSWER .,6.14 (1.25) c a .I both wou'Id.~be off-Mbi 'one'would be'on i: "c.- I both would be on
- d. both would be'on
- e. one on.
' REFER'ENCE h
-CR-RDT-4-l' CH. 1 L' . D . #7,
- p. 32 (3.2/3.6). l I010000K603 ..(KA's) i ANSWER: '6'. 1 5 , (3.00)
- a '. - 1) If .the' SS decl ares the . PORV. i noperabl e 9 0200, then 0300, or 2)-If the SS does not declare the PORV inoperable 'at O200, -then 0330.1 (1.00)
-b. No, Hot Standby within 7 hours from the t i mre stated ~i.n p rit-t a,(1.00)
'c.. Yes, Provi si or t of 3. O'. 4 are not applicable. (1.00)
REFERENCE-CR,:TS-3.4.3.2,,.'p3/4 4-4a J010000 GOO 5 ..(KA's)
-ANSWER 6.16 (1.50)
- a. 100 (0.5 each).
- b. 50 c'. 10 REFERENCE CR-RDT 4-1 CH. 1 L.D. #9
.:CR TECHNICAL'GPECIFICATIDMS 3.4.9.1 p. 3/4 4-24 1 002000G005 ..(KA's)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ .1
c ... . ,. . . , f E, ' , . . . m _ . . ..
......"'. ...F. ., .
W
': :Page132:
$64 - PLANT'SYSTEMSF(30%).AN LANT-WIDE. GENERIC LBESE9N@l@lLJIlg@,,[1Ffl .' [b y 1 tc
.f; a,
Lp
- ANSWERL .6.L17- '( 1. 00 );
1, . h ; WDV'-G91 ' (ai r ' operated li qui d rel ease -i sol ati on); and l WDV-892 .(MOV li qui d rel ease : i solati on) both close.- ~ ( 1. 00 ) 1 $ REFERENCE. t-: ((CR-RDT4-25'1c.p.'31 L '. D . 4 ' [ . , :. (4. 0/ 4. 3) -
~
l: 673OOOK401 -. . (K A's ); i:
-ANSWER: 6.18 (1.00)-
C
' REFERENCE CTDTlS. 3. B.1.'2 p 3/4 8-6
- ( 3. 4 / 3. 9 ) -
'064000 GOOS. ..(KA's)
ANSWER - 6.19- ( 1. 00 ) - c. REFERENCE C5 T.-S. 3.4.S p. 3/4.4-6 035000 GOO 5 ..(KA's) ANSWER 6.20 (1.0C) d. l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l
. . . . . . _ _ _ _ _ _ _ _ _ _ _ . _ __ _ }
~
. _____N___..________ .._._
L r KREFERENCE'- a ! CRLTS 3.'5.2,' 3.8.1.1, 3.0.5 i
' (3'. 5 / 4 ; 2 ) -
(3.4/3.9). OO6000 GOO 5 064000 GOO 5 ..(KA's) r [ ANSWER,. 6.21: (1.00)
'1. . Main-Turbi'ne Generator' bearings 1-5 (0.25 each) f
'2. . Main Turbine Generator b ear i n g s .1 &;&d (e-7 '
- 3. Feedwater pump 3A
- 4. Feedwater pump 3B REFERENCE' CR. ROT- 4-7 p. 31 L.D. #~9
' ( 3. 0/3. 3 ) .
.086000K406 ..(KA's)
. ANSWER 6.22 (1.00) b REFERENCE RDT-4-29 L.D. 1,.2 P. 10 ,
'( 2. 5/ 2. 9 )
0330000004 ..(xA s> ANSWER 6.23 (1.00) i c l L ( l i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1 l L--___:-____________-_____. _ - - - _
p ,, m -
, . 3 , . .,
I- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . ' REFERENCE'
% y\ , :l:_ ,
> LCR-ROT,;4 29: L.O. 15
- .(2. 5/ 2. 7 ) '
TO33OOOK102' :..(KA's)
- l. .
['ANS'WER' '6~24-
- . (1.00)
C
*t i REFERENCE-l.
.CR-ROT 4-32 p. .
12..L.D. . #2 ' (4.0/3.9). 035010A301 ..(KA*s) 1 ANSWER 6.25 -( 1. 25) l,
- 1. 'a 237 psig (0.25 each) b.'110 deg.
F. 2.- a.:32..gpm
. ' 3 '. '100 d'g. e F./hr:
- 4. 18 inches
. REFERENCE'
'CR-ROT-4-32, L.O. #3, p. 21, OP-202 (3.2/3. 4 )-
IO35000G010 ..(KA's) l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l l l l 1 <
\
7 m 6A_UELBUliEYSIEUSIlE9$1_SUP~IS6dIr@lpEigggg81C _Page135: ' [W ?BEEPgygl@lL111Eg_j]3Z.l(.) j, y a-( 1. 75)' LAN5WER- - 6 '. ~2 6 -
'a .' 1< Oi991 (0.23 each)
.b.' <or'= toL200 deg. F' c.- :<'O.99-l ld . - 280 deg.FL> Tavg > 200 deg. F.
i.. e. . --< . O . 9 9 L cJf. s .> or = .
'to 280.deg.
..g..
O%
- -REFERENCE r CR.'.T,S.-p.
1-9 i b LOO 2000 GOO 1 ..(KA's) I'
. ANSWER 6.271 (1.00)
- 1. Thi's el i,*. nctes ' the .possi bi l i ty of the DH system f rom being overpressurized'by opening the valves at 1500 psig. (0.5)
,2. To' prevent inadvertent overpressurization of the DH system due to HPI actuation.
REFERENCE CR-ROT-4-1, L.D. #6, p 129, 136
'OO5000K401- OO5000G010 . . (KA's) J
.' ANSWER 6.28 -(1.00) a
[ REFERENCE
'CR-ROT-4-2 p. 3 L.D. #2 (3.3/3.4)
OO9000K102 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) c_1___ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ _ _ i
!6A PLANT f SYSTEMS .:(30%)' ANP7LANT-WIDE" GENERIC ~~~ (G Page136 hhhh0hh}h}(lI}hh}}}h5[ U ~-ANSWER-- 6.29 (1.00) i Because the RW pump motor ~ windings are cooled by its respective DC .1 cop. .(1.00)
REFERENCE CR-ROT-4-2, .p. 41-L.D. 46 6
'(2.7/2.9) 076000G010 ..(KA's)
ANSWER 6.30 (1.00) d REFERENCE CR AI-SOO-(3.6/3.7) 194001K101- ..(KA's) l l: ANSWER 6.31 (1.00) Plant manager (1.00)
- .: REFERENCE ND* ,
.RSP-101 P 7 -(3.5)
I 1 194001K104 . 4KA's) 1 1'
- l. 1 i
I '
- i. ANSWER 6.32 (1.50) l
( < 1.. as. directed by Health physics personnel l 2.. as specified by appropriate RWP prior to reaching 3/4 scale 3. I 1 l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I l I l 1 l
t 4: c 7.-- ,
~
6 __.____J _ -_________3__ _ 3 S. '
- REFERENCE-
- RSP_-01 P. 9'
? t 3. 5) .
'194001K104 ..(KA's)
I pANSWER 6.33 ( 1. 00' , l '. : l '. ' valves that'fai3 open must'not be used as clearante i sol ati ons unless.a mechanical gag is installed. (0,5) l 2.: . valves that fail closed may be used provided that the motive ~ air i s. i sol at ed - and vented of f .- (0.5) l. 1'
REFERENCE:
l~ CP-115 p. 12 I (4.1) 1. I 194001K102 ..(KA's) ' ANSWER 6.34. (1.00)
- a. The clearance holder - ( 0. 5)
- b. One. time,on1y (0,5)
REFERENCE CP-115 p.16 l- .(4.1) l- . 194001K102 ..(KA*s) l l ANSWER l 6.35 (1.00) l 1 l REFERENCE CP-115 p. 16
;(4.1) 194001K102 ..(KA's) l 1.
I (***** CATEGDRV 6 CONTINUED DN NEXT PAGE *****)
y 16'.D J PL ANT ' SYSTEMS"'(30Y.)" ANf']LANT-WIDE ' GENERIC' Page138~
", [tggPONSI BIL ITIES - ( 137.) v.' \
y., tv
+l g
(I-ANSWER- 6.36 ~'( 1. 00 ) I
- c~
'; REFERENCE
'CP-1381 p.2-M.1 ) '
194001K116 '. . '( K A ' s )
. ANSWER' 6.37 (1.00)
When perf orming routine actions of CP's that are frequently repeated j (1.00) 1 REFERENCE AI-500 p'.7. (3.9)- 194001A102 ..(KA's) ANSWER- 6.38 (1.00) c Step-by-step reouire signature or initial s of the person performing
.the procedure et each Etep, (1.0)
REFERENCE AI-500 p. 7 ! (3.9) l' l 194001A102 ..(KA's) l l l ANSWER 6.39 (I.00) l- 1 l: C-L l' l l (***** CATEGDRY 6 CONTINUED DN NEXT PAGE *****) r I'.
p'. - . . . . Ni j ANY/5VgTgtigi (30%)~ Ay'*7 @ H-W pg_ggNgRIC Page139 RESPONSIBILITIES,(13%) d b
,+
J
' REFERENCE-o iP ,
' Al-SOO~ p B l
;(3. 4 ) .-
394001A103- ..(KA's) I
- ANSWER. 6.40 . (1.00) 2-REFERENCE
A1-500 p. B 194001A103: .. . ( K A' s )
' ANSWER 6.41 (1,50) a.. another Nuclear- Shif t Sup ervi ser b.. an Assistant Nuclear Shiit Supervi ser (0.5.each) c, Nuclear Operations Superintendent l
REFERENCE AI-500- p. 10' (3.4) 194001A103 ..(KA's) l l 6.42 (1.00) l' ANSWER l' d l. l REFERENCE l L.AI-500 p. 12 ! - ( 3. l. ) 194003A1C'6 ..(KA's) u l L t
's l
l (***** CATEGORY 6 CONTINUED ON NEXT PAGE ***4*) 1
.. w. _ _ _ _ , _ - _ _ _ _ _ _ - - - - . . - _ _ _ _ -
g '
'~61 -I ANT?SfSTEMSt1130%)"AN 7 LANT-WIPE GENERIC
~~k' .Page140' RE5P6U5Isi[ ITIS 5^~i39. M ~~~~~~~ "i~~~~~~~ -
- 1. r L- ,
l; W. l" NSWER 6.43 (1.00). l
^ 'a .
l-REFERENCE l: ((AI-50d p. 21' !' (3.9) pl{3.9) 194001A109 194091A130 ..(KA's) ANSWER' 6.44 (2.00)
- 1. (If Toxic Gas Actuation has NOT occurred, Then sel ect
" Isolate / Reset switch to 150.)
I- I2 Verified c1osed- [- ~4HD-1/3D (O.25)
-4HD-2 (0.25)
-A; campers on the " Emergency Vent: 1 ation Dammer Pasi tion" Panel (O.25)
- i. 3. Verify Damper'AHD-3 is tpened (O.25)
- 4. Ensure stopped-AHF-20A/20B (0.25)
- AHF-21A/218 (0.15)
- AHF-44A/44D (0.25)
- AHF-30 (O.25)
> REFERENCE AP-513' p. 3'- (3.5) , 19400!K111 . . (Ke 's ) l l (***** END OF CATEGDRY 6 *****) ' i (*****4*it* END OF EXAMINATION **$44*****) 1 L __-_ - _ _ _ _ - - _ . _ - - -}}