ML20196D602
| ML20196D602 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/16/1988 |
| From: | Arildsen J, Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20196D574 | List: |
| References | |
| 50-424-OL-88-02, 50-424-OL-88-2, 50-425-OL-88-02, 50-425-OL-88-2, NUDOCS 8812090142 | |
| Download: ML20196D602 (274) | |
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b-4' ENCLOSURE 1 EXAMINATION REPORT 424 and 50-425/0L-88-02 Facility Licer.st.a: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Facility Name: Vogtle Electric Generating Plant Facility Ded E No.: 50-424 and 50-425 Written exeminations and opereting tests were administered at Vogtic Electric Gene ating Plant near Waynesboro, Georgic.
1 Chief Examiner: ed J _ 'e.r id .j
/6 Nov 88 Date Signed
! /38[ f -
dW M/WM Approved bhJohn F. FrutTro,' 051ef, Operator LicensingDate Signed Section 1 Suma ry:
Examinations on September 19-22, 1988.
Written and Operating tests were administered to 9 candidates; all candidates passed. Based on the resu'its described above. 6 of 6 R0's passed and 3 of 3 SRO's pass;d. 4 of 11 (36%) of the changes made to the written examination as a result of facility comercs were due to inadequate or incorrect reference material supplied by the facility to the examiners for examination prepar-tion, keference material submitted to *'n* MC should accurately reflect the current plant configuration so that post-examination modifications to the examination are minimized, s
G010090142 s:3 g g;r, y
{DR cocN 05000424 PDC l
7 REPORT DCTAILS
- 1. Facility Employees Contacted:
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- Paul Rushton, Plant Training and i
Emergency Planning Panager
- R. Donnan, Operations Superintendent l of Training
- H. Dutterworth, Operations Supervisor l
- Attended Exit Meeting
- 2. Examiners:
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- J. Arildsen R. Baldwin l M. F.rnstes S. Roesener i
- Chief Examiner
- 3. Examination Review Meeting At the conclusion of the written examinations, the examiners provided Mr. Dorman, with a copy of the written examination and answer key for review. The NRC Resolutions to facility comments arc listed below.
1 l a. R0 Exam I
(1) Question 1.0?c NRC Resolution:
Coment not accepted. Facility coment is incorrr.ct. In accordance with the Technical Specification Definition, the shutdown margin is either, "the instantaneous amount of reactivity by which the reactor is subcritical OR would be suberitical from its present condition assuming all rod cluster aassemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reectivity worth which is assumed to be fully withdrawn." In other words, the defined shutdown margin does NOT assume a stuck rod if the reactor is subcritical with all rods inserted.
Facility lessen plan LO-LP-33510-01 specifically states in a note following a suberitical calculation of shutdown margin that "there is not actually a stuck rod, so calculated SDM does not equal defined SDM."
However, since the question does not state whether defined or calculated SDM is to be used when answering *,he question, the answer to part C could be either INCREASE or NO CHANGE. Therefore, part C is deleted from the test.
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2 (2) Question 1.10a NRC Resolution:
Comment acknowledged. Question is graded to allow credit for answers describing the operational effects of MTC vice simply stating MTC.
(3) Question 2.16(6.17)
NRC Resolution:
Comment not accepted. In accordance with the CVCS training next (VEGP Chapter Sa, page 8) the safety grade cold shutdown letdown flowpaths discharge to, "The PRT through isolation valves (HV0442A and/or HV04428), or to the excess letdown flowpaths, upstream of the excess letdown hnt exchanger, through a motor-operated isolation valve (HV8090)." The corrent answer may include RCDT, VCT, charging suction header or seal return but MUST include excess letdown system for creult.
To clarify grading, both the R0 and SRO examination answer keys are changed to state:
l "2. Excess Letdown System."
I (4) Question 4.03 NRC Resolution:
- Comment acknowledged. Due to the lack of the appropriate standing order the question is deleted from the exam. The facility is cautioned that Administrative Procedures should never reference material that is
' not written, i
- b. SRO Exam
- - (1) Question 5.03b
. NRC Resolution:
! Coment accepted. Part b is deleted from the examination. Question worth is changed to 2.00.
i (2) Question 5.16a NRC Resolution:
Comment accepted. Tolerance is changed from "+ or 0.05 F" to "+ or
- 1.0 F."
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(3) Question 5.18b NRC Resolution:
Coment acceoted. Changed "3E-6" to "SE-6". > .cility needs to include the value SE-6 in written reference material.
(4) Question 6.04 NRC Resolution:
Coment accopted. Added additional answers as follows:
"6. Breaker "Local-Control Room" selector switch in the "Control Room" position. ;
- 7. Breaker control room in "AUTO."
l Facility lesson plan, LO-LP-01401,Section III, C.2, should be revised l to include the additional permissives. ;
(5) Question 6.07 l NRC Resolution:
- Comment not accepted. A decrease in the value of the flux penalty WILL result in an increase in the value of the OT Delta T setpoint.
The facility is cautioned to screen examination coments more carefully for validity. ;
(6) Question 6.17 NRC Resolution:
See Question 2.16/6.17.
(7) Question 8.02 NRC Resolution:
Coment acknowledged. Answer "d" is totally correct. However, confusion may exist due to the phrase "continuous operation is ,
desirable..." Therefore the question is deleted. !
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(8) Question 8.09 NRC Resolution: !
t Comment accepted. Second part of answer is placed in parentheses and l the associated points are deleted. The question value is changed !
to 0.50. j (9) Question 8.12 j NRC Resolution: ,
B Comment acknowledged. Grading allows non-repetitive specific examples [
in place of any generic answers. Added the following to the answer [
key: [
"0R - one example of any given type of recorded activity." j r
(10) Question 8.14 !
NRC Resolution ,
Coninent accepted. Deleted "(including downgrading and teminating)" f from part 1 of answer. l Deleted "and content of messages" from part 2 of answer, j Added the following:
"7. Reclassifying the emergency OR downgrading OR teminating" i I
- 8. Approval of Emergency Message content."
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The facility should consider revising Emergency Response Procedure, f 91102-C, section 2.3, p. 2, to include a comprehensive and well f organized list of nondelegable responsibilities. ;
(11)Qeostion8.17 (
NRC Resolution: f r
Comment accepted. Answer changed to include:
"0R
- 1. HOLD tag the handswitch in the closed position.
- 2. Mechanically or hydraulically gag the valve in the closed position [0.25) and HOLD tag the gagging device [0.25)
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The following changes were made to the examinations as a result of final rwiew and/or candidate questions during exam administration. All significant i changes to the question statements were announced to all the candidates during the exam by the exam proctor. Additional typographical errors were corrected.
ANSWER 1.19/5.13 Added:
"0R - Examples of each cause."
QUESTION / ANSWER 1.22c Deleted part C following exam completion. Changed point value to 1.50.
14000 series procedures should be included in material provided for future NRC examinations.
I i ANSWER 2.03 Changed RMWST from "Nomal" to "Alt. nate" Water source and changed Demineralized Water from "Alternate" to "Normal" source.
NRC COMMENT:
- The reference had been updated but not supplied to the NRC. It is expected i that correct and clearly typed reference material will be provided in future NRC examination packages.
ANSWER 2.04(Q i
i Added:
"0R - to limit AFW flow to a depressurized SG."
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! ANSWER 2.05b Rewritten as follows:
"h. Any three of the fcilowing at 0.50 point each:
- 1. Temperature increase in the AFW discharge piping as indicated on j temperature instrumentation.
l 2. Pressure increase in the AFW discharge piping.
Vapor escaping through the vent or drain lines.
- 4. AFW pump starts but fails to develop adequate discharge pressure.
- 5. Temperature increase in the AFW discharge piping as indicated by touching the piping.
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NRC COMMENT:
Accepted alternate answers. l ANSWER 2.07b Changed to read:
l "Water flows ftom the standpipe side of the #3 seal past the seal in two l directions [0.25):
A. To the #3 seal leakoff (OR containment sump) [0.25]. I B. To the #2 seal leakoff (OR RCOT) [0.25].
The static head of the standpipe is higher than the pressure in the two leakoffflowpaths[0.25),"
NRC COMMENT:
Completed answer to the question.
QUESTION 3.10 Changed question statement and answer to the following:
"The following question concerns the operation of the steam dump control system.
State what parameter responds proportionally to a change in steam dump demand for:
- a. Unit 1
- b. Unit 2 Answer:
- a. Valve stem movement
- b. Steam flow 0.50 for each correct concept, 0.50 total for correct unit matchup for a totsi of 1.50 points."
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7 NRC COMMENT:
Training on this subject did not use the words "EQUAL % CAMS" or "LINEAR
% CAMS." Reference material was inadequate.
ANSWER 3.16a(6.06a)
Changed to read:
"a. Any four of the following at 0.25 point each:
- 1. OT Delta-T trip
- 2. OT Delta-T trip
- 3. P-12 circuitry (or Lo-Lo Tavg signal).
- 4. Feed water isolation C'rcuitry (or la Tavg signal to FWI).
! 5. OT Delta-T rod stop and Turbine runback.
- 6. OP Delta-T rod stop and Turbine runback.
l QUESTION / ANSWER 3.2J DELETED following the examination.
NRC COMNENT:
1 Incorrect reference material. It is expected that clearly typed and correct reference material will be provided in future NRC examination packages.
ANSWER 3.22c Changed "1870" to "1885".
, NRC COMMENT:
Incorrect facility reference material.
ANSWER 4.06(2)
DELETED, changed question value to 1.50 NRC COMMENT:
i While 4500 mrem /yr is a V0GTLE administrative limit, it can not be achieved i without special authorization. The question asked for only thoto limits
! which did r.ot require authorization.
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8 ANSWER 4.09c Changed from "3" to "3 or 4".
HRC COMMENT:
The entire range of 10% to 15% is acceptable.
ANSWER 6.11a(3)
Added:
"(Turbinetrip)"
' ANSWER 6.13 l
Added:
"SG blowdown isolation [0.3]
SGsamplevalveisolation[0.3]"
Changed all "O 5" values to "0.3".
QUESTION / ANSWER 6.14d DELETED following the examination. ;
Changed question value to 1.50. '
ANSWER 6.16a Added:
"0R - normal modulation of control values". -
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QUESTION 7.02 I
DELETED during the examination, nNSWER 7.15 (
Changed to "(any 5 0 0.4 each)"
Added: i "6. At the end of each calendar year.
- 7. Not used for six days."
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. . _ _ _ _ _ _ = . _ _ _ - _ _ .._ _ ______ - .
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9 MSWER7.19 Deleted:
"When critical [0.5]" and "when suberitical [0.5]".
Changed question worth to 1.00.
ANSWER 8.12 Added:
"10. Containment entry when a control point has not been established."
ANSWER 8.18 Place in parentheses "when the exposure margin is less than or equal to 200 mrem."
ANSWER 8.20c Added:
"0R - Indicated level change of 7% (67 gallons)"
- 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 three generic weaknesses noted during the operating examination. The areas of below normal performance were:
- 1. Candidates were unfamiliar with the magnitudes of I!CP's normal and starting currents, and the location where they could be monitored in the control room.
- 2. Candidates were unfamiliar with the fail position of ARV upon loss of power.
- 3. Candidates were unfamiliar with the master key locations.
Much of the reference material provided by the facility for examination preparation was handwritten and difficult to read. This resulted in many of W connents listed in enclosure 3. The facility is reminded that all reference material provided must be correct and legible.
The cooperation given to the examiners and the effort to ensure an atmosphere in the control 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.
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U. S. NUCLEAR REGULATOFjY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY. YQQILE_2__(_1_____________
REACTOR TYPE: EWB-WEGi.________________
f DATE ADMINSTERED: QQLQ2/12_________________
EXAMINER: E lGEgBi_ D t_____________ ,_
CANDIDATE _________________________
INSIBUGI1QUS_ID_COUDIDGIEL Use separate paper for the answers. Write answers on one side only.
Staple question shoot on top of the answer sheets. Pointu for each question are indicated in parentheses after the question. The passing grade requiren at least 70% in each category and a final grade of at least 80%. Examination papsrs will be picked up six (6) hours after the examination starts.
% OF CATEGORY. % OF CANDIDATE *S CATEGORY
__YeLUE_ _IDIGL ___SGOBE___ _Y869E__ ______________G61EQQBY_____________
29.00 25.6l
________ 5. THEORY OF NUCLEAR POWER PLANT f_22mE2_. 12Em2O ___________
OPERATION, FLUIDS,AND THERMODYNAMICS 29,'7s %fe 39
________ 6. PLANT SYSTEMS TESIGN, CONTROL, f_22sEi__ O2E_22 ___________
AND INSTRUMENTiTION 27,50 24.2 8 7'_22s3-__ A25:_2 ___________ ________ 7. PROCEDURES - NLPMAL, ABNORMAL, EMERGENCY AND RADaOtOGICAL -
CONTROL 28.co 24.72
________ O. ADMINISTRATIVE PROCEDURES,
[_22&Ei__ E2Eu22 ___________
CONDITIONS, AND LIMITATIONS l l 3.1F r 11Gx___ ..__________ ________X Totalu Final Grade All work done on this examination is my own. I have neither given nor recuived aid.
Candidate's Signature y[q 75
b NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS I J
During the administration of this examination the following rules applyg I L
10 Cheating on the examination n,eans an automatic denial of your application ,
.and could result in more severe penalties. t
- 2. Restroom trips are to be limited and only one candidate at a time may 6 leave. You must avoid..all contacts with anyone outside the examination ,
room-to avoid even the appearance or possibility of cheating. l
- 3. Use black ink or dark pencil only to facilitate legible reproductions.
- 4. , Print your name in the blank provided on the cover sheet of the ex ami nat i on.
- 5. ' Fill in the date on the cover sheet of the examination (if necessary).
- 6. Une only the paper provided f or answers.
7.. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
D. 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.
- 10. Skip at least three lines between each answer,
- 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.
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- 13. The poirit value for each question is indicated in parenthesen after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methode, 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 00 NOT LEfNE ANY ANSWER DLANK.
- 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 exami nation has been completed.
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, 10.'When.you complete your examination, you shall:
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, a. Assemble your exemination au followns (1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
- 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 une 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.
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- Mi__IBCOBY_QE_NUGLEBB_EDWEB_ELONI_9EGB9Il082 Pcgo 2 ELUIDDieUD_IUEBdODYueb1GD i
OUESTION 5.01 ,(1.00)
Which one of'the following would NOT have an offect on the Axial Power Distribution of the reactor'coro? ,
- a. Fuel enrichment
- b. Control rod position
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-______________________-__________________________-_______________________a
QUESTION 5.02 (1.00)
Which one of the following statements describes the change in count rate resulting from a short rod withdrawal with Keff at 0.99 au compared to an identical rod withdrawal with Keff at 0.95.
- a. LESS time will be required to reach steady-state following the rod withdrawal and the count rate will be GREATER with Keff at 0.99.
- b. MORE time will be required to reach steady-state following the red viithdrawal and the change in count rate will be LESS with Keff at 0.99.
- c. LESS time will be required to reach steady-state following the rod withdrawal and the count rate will be LESS with Keff at 0.99.
- d. MORE time will be required to reach steady-state following the rod withdrawal and the change in count rate will be GREATER with Moff at 0.99.
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)>Co OUCSTION 5.03 (W Compare the calculated Estimated Critical Position (ECP) for a startup to be performed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after a trip from 100% power, to ACTUAL control rod position if the following events / conditions occurred.
Consider each independently. (State your answer as Actual position is HIGHER THAN the ECP, the Actual position is LOWER THAN the ECP, or the Actual position is the SAME AS the ECP)
- a. One reactor coolant pump is stopped two minutes prior to criticality.
'b_
The 9/U 11 conducted ^ !wn cae-lir- t4 mewmmh---. f>m e tro
- c. The s t s _... uump prenuure setpoint is reduced to 950 psig,
- d. Condenser pressure is reduced from 7 psia to 2 psia.
- c. All G/G 1evels are allowed to decrease by 5% as the rod withdrawal ccurs during the startup.
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i QUESTION 5.04 (1.00)
Which one of the following statements best describes the change in ;
' moderator temperature coefficient (MTC) from DOL to EOL7 l i
. a. The MTC becomes more negative due to increasing baron i concentration, decreasing fission product inventory. and axial '
flux redistribution toward the edges of the cero.
- b. The MTC becomen more negative due to decreasing baron j concentration, increasing fission product inventory, and radia. [
flux redistribution toward the edgns of the core.
I c. The MTC becomes lens negative due to increasing boron concentration, increasing fission product inventory, and axial flux redistribution toward the edges of the core.
- d. Tho MTC becomen lusa negative due to decreasing boron concentration, decreasing fission product inventory, and axial
> flux redistribution toward the edges of the core.
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r QUESTION 5.05 (2.00) ,
A beginning-of-lif e core has been operating with all rods f ully '
withdrawn at 100% power for 1 week. The bank D control rods are inserted 100 steps with sufficient boron dilution to offset the i reactivity added by the rods. Answer the following questions f about the resultant xenon transient IN THE RODDED REGION OF THE CORE.
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- b. Why does indirect production of xenon change during this
. transient? (1.00) ,
- c. The final uteady-state xenon concentration will be ________(LESS THAN, GREATER THAN, EDUAL TO) the original concentration. (0.C0) -
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DOEST 10N 5.061 (1.00)
Which one of the fo?Aowing is the definition of'the term reactivity? l
- a. The rate of change of reactor power in neutrons per second. l
- b. The ratte betwcon the populations of two successive neutron g en er a'. i on s .
- c. The difference between critical rod position and all control ,
rods withdrawn for a given core condition. ,
- d. The measure of a reactor's departure from criticality. f I
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i QUESTION 5.07- (1.00)
<> Which one of the f ollowing defines the . term NUCLEATE DOILING7.
- a. . Boiling that renuits ir, the bulk fluid temperature reaching saturated conditions.
- b. Boiling that resu!ts in a thin layer of steam at the heated surface.
- c. Doiling that occurs when small bubbles are formed at the heated surface and move off in'so'the liquid.
- d. Dailing that occurs when the critical heat flux is reached.
(***** CATEGORY 5 CnNTINUED ON NEXT PAGE +****)
.DUESTION 5.08 (2.00) r Will the Departure from Nucleate Boiling Ratio (DNBR) INCREASE, DECREASE, '
or REMAIN THE SAME if the following plant parameters are measurably REDUCED during power operation? Consider'each parameter separately. ;
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- a. Reactor Coolant System (RCS) Pressure i.
- b. RCS Tavg-Temperaturo }
- c. Reactor Power ;
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- d. RCS Flow i
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.OUESTION 5.09 (1.30) !
i True or False? ,
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.a. -The NPSH required to prevent cavitation is independent of pump ;
speed. i
- b. One of the pump laws for centrifugal pumps states that_the volumetric flow rate in proportionL1 to thu speed of the pump.
- c. Pump runout is the term used to describe the condition of a :
centrifugal pump running with no resistance to flow'at the i discharge. !
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Q' UESTION 5.10' (1.00)'
- What are*the TWO major factors affecting the Fuel Temperature Coefficient over coro age?
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1 m- ---c., -_.. . . . _ . -..._%w- -w-,., .-------,-w-- _ - - , - - , - . - _ ----w=+w.-ww,y,,
-I it t OUESTION 5.11 (2.00)
- a. List.the THREE components which combine to produce the Pos.- ,'
- Coefficient. (1.50) 4
- b. How does total power coefficient vary (Becomes MORE NEGATVE or LESS .
NEGATIVE) as the core ages? (0.50) ;
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I QUESTION 5.12 (2.00) r List the:TWO major factors that affect differential baron ~ worth over core life AND indicate how (MORE NEGATIVE or LESS NEGATIVE) thuy affect differential baron worth. .
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~ QUESTION 5.13 (1.50.1 List THREE major causas ei Water Hammer.
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QUESTION 5.14 (1.00)
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Describe-the conditiens in a fluid under which cavitation occurs.-
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' QUESTION S.15 (1,30) f VOGTLE 2 is near the beginning of its first fuel cycle VOGTLE 1, with an identical reactor and fuel leading scheme, is near the und of its ;
first cycle. Assume both plants have just started up following a 3-week l shutdown period. I
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- a. Critical data has just been taken at 10 E-8 amps at both plants and -
the operators have added small, equal amounts of reactivity to i enntinue the power ascension. Which plant, VOGTLE 1 or 2, will have the HIGHER steady startup rate from this equal reactivity I insertion and EXPLAIN WHY? (0.75) l l
- b. Shortly after 50 percent power is reached during these startups, i rod control is placed in manual at both plants. Shortly afterward,
- a shutdown bank control rod worth -150 pcm drops into the core !
at both plants. Assuming that no operator action is taken for [
these casualties and that neither reactor trips. Which plant, j VOGTLE 1 or 2 will stabilire with the HIGHER steady-state Tavo ;
and EXPLAIN WHY? (0.75) ;
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-QUESTION 5.16 (1.00)
Answer the following questions in reference to subcooling margin of the i plant. l i
- a. What is the ~ subcooling margin of the plant if the following conditions ;
exist: ,
Thot'= 587 F Tavg = 572 F Tcold ='557F :
Ppar = 2235 puig Psg = 1033 psig !
- b. If power is raised from 50% to 100X, why does the subcooling margin l decrease? i i
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. . QUESTION 0.~ 17 (2.00)
- Define the term "Hard Bubble" as relates to the Pressurizer and BRIEFLY !
ry~ explain the effects on pressure control in the. primary system if a "Hard Bubble" exist.
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,, - OtJISTION 5.10; (1.50) c- Following the.taking of critical data, in the intermediate range, a stable. l startup rate of 0.15 DPM at 0.1% of full power in established. 'The l reactor.is at no-load Tave, and the Boron concentration is 800 ppm. The plant.is below the point of adding heat.
- a. What will the reactor power be af ter 2 mirautes?
I
- b. At what power level does the point of adding heat.begir? l (No calculation required.) [
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QUESTION 5.19 (1.50) [
During a power ramp to 50 percent power with rod control in automatic $
an incorrect boron change _was calculated and made which rauulted in t the plant stablizing at the desired power but with control rods at the all out position and Tavg 5 degrees F be).ow the target value. Given the !
following initial parameters, PROVIDE the final RCS baron concentration needed to INCREASE Tavg by 5 degreen F while returning control rod bank D to the 100 step position. Assume turbine power stays constar-* i at 50 percent. ;
L Initial RCS boron concentration = 600 ppm t j
Total power coefficient = -20 pcm/ percent Moderator temperature coefficient = -15 pcm/ degree F j Differential baron worth = -10 pcm/ ppm i Control rod worth avg. (5- 80) = 8.60 pcm/ step t (95-170) = 4.16 pcm/ step ,
(185-228) = 1.095 pcm/ step 1
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, a-QUESTION 5.20. ( 1. 50 ) ~
What is "Self Shielding" in'the fuel, AND how doom it affect reactor !
i operations au power. increases? '
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6t__EL8HI_aYSIEdH_DESION2_GQUIBQL2_GUD_INDIBudENIBIlgN Pego 22 QUESTION 6.01 -(1.00)
Which one of the following electronic components would be found in the INTERMEDIATE RANGE nuclear instrument channel?
- a. Two unique loss of voltage alarm functions per channel
- b. Preamplifier
- c. SumminC and level amplifier
- d. Pulso shaper l
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QUESTION 6.02 (1.00)
Whi t.h one ' of the following is NOT a contaiment phase A isolation signal?
a.. ' Safety Injection signal- l
- b. Reactor low pressure trip !
E c. Manual- ;
- d. Containment area radiation c
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=m---
b QUESTION 6.03 (1.00)
Which one of the following statements correctly describes.the symptoms.
of a Train A Safety Injection.where Train B SI f ails to produce 'an SI ;
signal? <
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- a. Both emergency diesels start but only the train A sequencer !
operates. [
i j ,, b. The Train A diesels starts but the Train B diesel does not i start. g l t
- c. Both emergency diesels start, but the Train B components do not j start. l 1
- d. Both diesels start and both train 's components starts. I
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. QUESTION 6.04 (2.00)
, List FOUR permissives that,tmust be natisfied before the Diezol-Generator output breaker will shut following a start.by the Safeguards !
Sequencer.
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List EIGHT reactor trips which are BLOCKED or DISABLED during--a.startup l when reactor power in.at approximately 10E-6 amps. Do not include setpo.ints or coincidences. [
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9 QUESTION 6.06 (2.00) '
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- a. List FOUR unique control, protectivo, or permissive circuits which I use individual loop Tavg signals and NOT auctionthered.high or low Tavg. (1.0)
- b. Excluding the main control board wide-range temperature indicators, '
list FOUR other SYSTEMS that use RCS loop wide-rango temperature signals. (1.0) r f
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OUESTION 6.07 (1.50) ,
r How must each of the following parameters change to achieve an increase in the Overtemperaturo Delta Temperature Setpoint (OTdelta T)?
i Use INCREASE, DECREASE, REMAINS THE SAME.
- a. Tave
- b. Reactor Pressure ;
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- c. Delta Flux Penalty l l
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. QUESTION 6.08 (2.00) ,
List FOUR automatic responses of the NSCW system to an SI. I f
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4 OUESTION 6.09 (2.00) ,
- s. List the ECCS subsystem requ.irements of Technical Specifications when in mode'4, < 350 F. l i
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a W 4 DUESTION 6.10- (1.50) !
t p List the THREE signals that cause automatic main steam line isolation. l Also list the setpoints and coincidence associated with the signals. l i
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QUESTION 6.11 (1.79)'
?
- a. What components are actuated or tripped on a full feed water ;
isolation?
- b. 'What signals will provide a full feedwater isolation? !
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l QUESTION 6.12 (1.50) ;
Describe the purpose of each of the THREE DP transmitters (a, b, c) used j for one train of the Reactor Vessel Level Indication System. ,
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l QUESTION ,6.13 (1.50) g What AUTOMATIC actions would occui given the following Steam Generator ,
J . level indications? l S/G 1 S/O 2 S/G 3 S/G4 $ !
l 20% 24% 21% 22%
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I, nii d OUCST10N 6.14 er25)
For each of the following interlocks / components on the Fuel Handling Machine briefly describe their function or operation. Include the setpoint if applicable.
j
- a. Low Load Inhibit i
- b. Upper Limit
- c. Black Cablo
- d. Dircrt;ca pma,-Luiiun DO Ir r e 'l ,
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. QUESTION 6.15 (2.00) ' -k Describe the FOUR opening interlocks associated with the RHR suction .
valves.to the RCS (8701A/B and 0702A/B). ,
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QtlEST10N 6.16 (2.00) i L
What function does each of the four solenoid valves provide that are in l
. series with the pneumatic operators of the Steam Dump valves? j i
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-QUESTION 6.17 . (1.00)
State the locations where the TWO Safety Grade Cold Shutdown Letdown i Flowpaths discharge. (
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QUESTION 6.10 (1.90) l t
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During a slow pressure increase transient the RO reports PORV 455 opened I l to reduce the proosure but PORV 456 did not open. EXPLAIN the reason !
l for PORV 456 not opening to reduce the pressure along with PORV 455. i ASSUME that both valves functioned correctly, neither are stuck and the l l absolute setpoints of each valve are identical, i l I l
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'I OUESTION 7.01 (1.00)
Which-one of the following th MT correct concerning the use conventions [
associated with EOP'st I L
- a. Even after a transition to another procedure, the steps begun f before the transition was made must still be completed, but IMt !
I to delay the transition.
' Continuous actions contained in a caution (step) are NOT in f effect when an operator is referenced to a procedure to be l
'rf ormed concurrently with the EOP in ef f ect. )
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a caution statement oc:urs before step one of an EOP tt may j spply either to the whole procedure or just to the first step.
- d. Unless otherwise specified, a required task need not be fully ,
completed before proceeding to the next instructioni it is [
enough t *,egin the task and have some assurance that it is progressing satisfactorily. i t
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t QUESTION 7.02 (1.00) -
Which one of .r SI (
the following termination with VEGP 1900-1, statements E-0, describes Reactor Tr ip the or crituria)jection?
Saf ety n
- a. Core thermocouples < 1200 deg.F. total fee low to S/O's !
greater than $70 gpm, RCG pressure stabir or rising, and Pzr i level greater than 4%. }
- b. Subcooling greater than 20 deg. , Narrow range level in at l 1eant one S/G greater t h a n 4 , !
and P7R level greater tha d.RCSpressurestableorrising, f
- c. Subcooling greater tvar 20 deg. F, Steam Dumps not in f operation, RCE pr sure stable or lowering, Total deed flow t to G's great than 570 gpm, and PZR pressur=* utable. l
- d. Core ext l
thermocouples greater than 736 deg. 6 and RVLIS
[
full r W,e greater than 39%, Narrow range level in at least I on t> a/G greater than 4%, RCS pressure stable or rising, and [
R prosnuro utabte. j l
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QUESTION 7.03' (1.00)
Which one-of the following would be the correct use of E-0, "Reactor Trip or: Safety Injection procedure with a loss of.off-site
.." power and failure of'the Emergency Diesels to recover the vital buses 7
- a. 'Go immediately to ECA O.0, Loss of all A/C power.-
- b. Go'immediately to ECA O.0 from E-O after_ verifying reactor and turbine trip.
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- d. Complete E-0, Reactor-Trip or Safety Injection IMMEDIATE ACTIONS f then go immediately to ECA O.0, Loss of all A\C. power.
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- QUESTION. 7.04- (1.00) 4 When are'the procedures required by the Critical Safety Function Status
. Trees implemented during ECA-C.4 according'to the Westinghouse
. Background'Information Users G. je for the Functional Restoration Guides 7.
a.- Never implemenced when in ECA-0.0
- b. ~Upon entry to ECA-0.0
- c. Upon reaching step 5 of ECA-0.0
- d. Upon exiting to subprocedures of ECA-0.0 s
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QUESTION 7.05 ( 1. 00 ).
1 If an SI, signal is generated while perf orming steps .in ECA O.0, Loss of'A11 A/C power, which one of the actions below is' required by the procedure?
- a. Reset the SI to permit manual loading of equipment on an A/C ,
emergency bus. , ,
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d.. No-action is necessary as it has not effect on the equipment.
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Q, j' , f L) $0UESTION 7.06 (l.D ,
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lg.Which of ' t.hnsf oll oi- iormal Operating Procedures (1900 seriea).
l[;.,.:N'i:; . 1-!regliiros an d mmed ctor trip if the RESPONSE ?!3 NOT CSTAINED to tO. y :is IMMCDI ATEM ACTION ~ A .ON: More than one right answer may apply. ,
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^ ia .* Partial L' o of F1 4 (18005-1)
> b '. Or. cont' rolled Continuous Rod V 6 ion.(10003-1) 4
, .c: .y .c. Gecondary Coolant Luakage (18008-1) gp , '
'i ,' ' d. Reactor' Coolant System Leakage (19004-1) '
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-e.. . St.oam Generatnr Tube Leakage (18009-1) if. l.oss of Instrument Air (18028-1)-
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QU5STION 7.07 ' ('1. 00)
,, Which -one of the f ollowing symptoms would . require the initiation of a gianu al reactor trip AND safety injection if neither had. occurred automatically?
a.: Containment pretsure.= 2.7 psig
- b. A General. Warning alarm on the Solid. State Protection System B
- c. Pressurizer. pressure = 1950 psig, pressurizer level = 40%
- d. Power = 35%, and loss of flow in one loop i
- e. Power = 45%, pressurizer level 93%
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. QUESTION 7.08' (1.00)
Which one of the following symptoms would require initiation of ONLY a manual reactor trip if neither,a reactor trip or' safety injection had automatically occurred?
P
- a. Containment pressure = 2.7 psig
- b. A General Warning alarm on the Solid State Protection System B
- c. Pressurizer pressure = 1850 psig, pressurizer -level = 40%
- d. Power = 35%, and loss of flow in one-loop
- e. Power = 45%, pressurizer level 93%
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- QUESTION '7.09 (2.50)
What FIVE parameters listed in ES-0.1', Reactor Trip Response (19001-1),
are ured to indicate or support the existence of natural ~ circulation f l ow .' INCLUDE the way each would be trending or the parameters * ,
expec ted value, as applicable.
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I L QUESTION 7.10 (1.00)
'- Due to severe smoke and toxic fumes it becomes necessary to evacuto the f ~ control room according to Abnormal Procedure 18038-1, Operations From Remote Shutdown Panel, Which procedure is the operator cautioned NOT to use? -
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QUESTION 7.11 (1.00)
- What TWO conditions can occur, according to a caution note in Abnormal Procedure 18000-1, Secondary Coolant Leakage, if CST level falls below 70%7 n
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' QUESTION 7.~12 (1.50)
. -According to the Foldout Page of E-0, Reactor Trip and Safety In.iection '
what.TWO conditions require tripping of All Reactor Coolant Pumps?
Include'setpoints.
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). i r, 1 QUESTION 7.' 13 ' (1.00) i
< ' What is the ONLY' condition in which the Post-LOCA -Containment Hydrogen' Purge System wi'11 be operated according to a CAUTION note in the system Joperating procedure 7 ,
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< QUESTIO', 7.14 .(1.50)
List the THREE' methods of verifying a reactor trip according t e FR--S.1,
,- Response to Nuclear Power Generation /ATWT.
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r OUESTION 7.15. (2.00)
List the FIVE conditions when a Radiation Work Permit will be ;
terminated.
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QUESTION 7.16 (2.00)
What are the THREE methoQs-of regaining core cooling when using FR-C.1, Response _to Inadequate' Core Cooling, in order of priority?
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t QUESTION 7.17 (2.00)
The foldout page for. procedure E-0, Reactor' Trip or Safety Injection '
' lists TWO conditions, either of which requiro the operator to Actuate.
.SI. What are these TWO conditions? Include applicable normal '
containment setpoints.
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, s QUESTION 7.18 (1.00)
W' hat EXACT action is required, according to AOP'18031-C, "Loss of Class 1E Electrical' Systems", if the associated 4160V 1E bus powered by a diesel is lost, but the diesel continues to operate? ,
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QUESTION 7.19 (M)
List TWO conditions requiring baron changes to be stopped according to the precautions listed in System Operating Procedure, 13009-1, CVCS Reactor Makeup Control System?
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'" - OUESTION 7.20 (1.00)
Why'must the Hydrogen Monitor isolation valves remain closed except ,
during hydrogen; monitor operation, according to the' System Operating Procedure, 13130-1, Post-Accidctnt Hydrogen Control? j i
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l QUESTION 7.21 (0.50) ;
Who, by title, can authorize exemption of the 100 mrom administrative i' limit of involved personne.', on Radiation Work Permits for control filter changes, according to Health Physic Procedure, 43007-C, ,
Issuance,~Use and Control of Radiation Work Permits?
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$ ' QUESTION 7.22 ( 1.'00 ) - ,
hh'entheShiftSupervisor approves the issuance of a Radiation Work-Permit, WHAT does his signature signify?
? '
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'OUESTION 7.23 ( 1. 00 )- ,
List TWO' classifications of personnel, by title, who can be issued keys to High Radiation' Barriers?
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OUESTION 8.01 (1.00)
Which one of the following must the Shift Supervisor obtain permission from before issuing a clearance whir.h might affect _the load carrying capablility of the, unit?
- a. General Manager
- b. System Operator
. c. Manager Operations
- d. Plant Manager 4
(***** CATEGORY 8 CONTINUCD ON NEXT PAGE *****)
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e OUESTION O.02 (1.00) g'g /g 7 g h While operating in Mode 1, control power is lost to pressurizer power operated relief volve, which one statement low in CORRECT 7
- a. Technical Specifications requires n action provided another PORV is operable and all pressur er code safety valves are operable.
- b. Technical Specifications quires the power supply to be removed from che assoc' ed block valve after verifying it to to open, if the PORV s not operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,
- c. Technical Speci cations requires the asnociated block valve to be shut a its power removed if the PORV is not made operable w lin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and continuous operation in desirable,
- d. Tec hn' m al Specifications requires action restore two PORVs to ope able status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or bu in hot standby within
.x t 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and hot shutdown within following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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/ -' QUESTION 8;O3 (1.00) 1 (4hich one of the f ollowing can authorize the change in position' of a. l LOCKED valve, according to Operations Administrative Proc'edure, 10019-C,
- Control of Safety Related Locked Valves?' ;
- a. Reactor on-duty 4 b. Shift Supervisor i 1
Shift Technical Advisor m !
- c. ,
I d.'On-Shift Operattons Supervisor i
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QUESTION O.04 (2.00) ,
, What are the responsibliities of the Shift Supervisor regarding Temporary Jumpers and Lifted Wires? ,
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t QUESTION O.05 (1;O0) ;
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Who, by' title, assumes the position of Lmergency Director in the 4
'i control room until relieved b/ the designated Emergency Director AND (
who,.by title, is the backup if the initial person indicated becores ;
i incapacitated, before he/nhe is relieved by the designated Emergency Director? [
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QUESTION B.06 (1.50) i List the THREE methods used to provide cold over pressure protection ,
in.accordance with Technical Specifications. l i
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- l. s DUESTION O.07 (1.00) f WHO is allowed to a,1 rove ten porary ::hanges to operating procedures and l WHAT must be checked before the approval can be given?
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- QUESTION' O.08 (2.00) .
An operator perf orming a surveillance test on the turbine-driven au:<iliary I feudwater pump discovers that the procedure step he is starting does not apply to this condition of the test. The operator then asked you as .
the supervisor to mark this step.N/A. 1 I List FOUR considerations that'must be made before marking a step N/A as cited in Procedure OOO54-C, Rules for Performing Procedures. !
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- 4. QUESTION B.09 t+rO@ (d5h .
In accordance with VEGP 10003-C, "Manning the Shift", during WHAT modes must a SRO be present in the Control Room?-
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QUESTION 8.10 (1.00) t What must the OSOS ensure has taken place' prior to appointing a person [
~ as the STA before the beginning of the shift? !
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QUESTION. 8.11 , (2.00) !
List the FOUR conditions in which a Senior Operator is:authori od to i shutdown the reactor without prior approval, according to Plant- l
' Administrative Procedure, OO3OO-C, Authority to Startup and Shut Down l c , Reactors. i e
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QUESTION 8.12 (1.50) i List SIX types of activities which are recorded in the Shift f
^ '
Supervisor *s log except for the time when the activities occurred.
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t lOUESTION. 8.13~ (1.00)
What TWO conditions must be met.before a Reactor Trip Report is S , REQUIRED, a'ssuming a' trip has occurred, accordirig to Operations l Administrative Procedure, 10006-C, Reactor Trip Review?
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, OUESTION'. 8.14 ( 2. 50 )' ,
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' Listi FIVE duties of the Emergency Directot* which are NON-DELEGABLE according to Emergency Response Procedure, 91102-C, Dutten of the l Emergency Director? '
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l QUESTION' O.15 ~(1.50) .
What'THREE classes or group of personnel are not iequired to get [
permi'asion to enter the "At-The-Controls" area of the control room? j
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4 QUESTION O.16 (2.00) f What are FOUR rules of conduct that will be observed by every person (
, entering the Control Room Area according to Plant Administrative !
Procedure,.00301-C, Main Control Room Access and Personnel Conduct? i
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' OUESTION 8.17 (1.00).
4 What is the Clearance Policy used when placing a clearance on a FAIL OPEN Air-Operated Valve (What must be done to Tag the valve closed)?
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4 QUESTION 8.18 (1.00) i What limitation (s) are placed on an individual who has a NO ENTRY" Exposure Margin, in accordance with VEGP 00920-C, Radiation Exposure limits and Administrative Guidelines?
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QUESTION. 8.19 (1.50)
Assuming.a plant licensed operator worked the following schedule, DETERMINE if any violation of Plant Administrative Procedures or ,
Technical Specifications occurred. STATE which limits were violated, if
- any, and SPECIFICALLY IDENTIFY each time period. involved. Note: Shift '
turnover time has not been included in the times indicated.
f Monday Tuesday Wednesday Thursday Friday Saturday Sunday I O 16 12 8 16 12 O l I
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~ . . - - - - . , - - ,- ,.,- ,,, - ,~_ , , , , _ . , _ . . - , .
. v.
, ' QUESTION 8.20 (1.30)
As reported in VOGTLE i LER 88-007 a personnel error Inad to missing a !
Technical Specification surveillance on #2 RCS Accumulator Tank. The i error was caused by failure of control room personnel to complete ,
procedure steps of sampling after refilling the accumulator. j L i 4
- a. WHAT sample must be taken? i
- b. WHERE must the information be logged regarding the sample? I
- c. WHAT in the volume change allowed bef ore sampling must be done I according to Technical Specifications? f, i
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OUESTION G.21 (1.50) l' VOGTLE Licensee Event Report 88-012 reported that the weekly [
surveillances were minsed for seven items involving CVCS, High Pressure Injection systems and Power Distribution Limits.
What is the normal frequency for a weekly surveillance and the allowable ti me interval allowed for completion'in days? i I
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ELUIDS400D_IUE6dODXUGUIGH ANSWER 5.01 (1.00) '
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REFERENCE VEGP Lesson Plans, LO-LP-33520-01, p. 5 Lesson Objectives, LO-LP-33520-01, #3 192005K110 192OO6K108 ..(KA's)
ANSWER 5.02 (1.00) d REFERENCE Westinghouse, Fundamentals of Nuclear Reactor Physics, 1993, p. 0-54.
VEGF Lennon Plans, LO-LP-33310-01, TP-13 Lesson Objectives, LO-LP-33310-01, #11 19200GK103 ..(KA*s) i 3.00 e ANSWER 5.03 +Wt
- a. SAME AS
- t. u ! cor p__TgAg_ oc, e re o
- c. LOWER THAN
- d. SAME AS
- e. SAME AS i
REFERENCE VEGP Lesson Plan, LO-LP-33510-01 Learning Objective #14 1 001010A2'/1 001000K534 001000K104 ..(LA's)
(***** CATEGORY 5 CONTINUED ON NEXT PA'it! ++**+)
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ANSWER 5.04 (1.00s b
i REFERENCE ;
VEGP Lesson Plan LO-LP-33420-02 -
unsson Obje:tive.LO-LP-33420-02, MO j 192004K106 ..(KA's) i i
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ANSWER 5.05 i?.00)
- a. INCREASES (0.5)
(1.0) !
decreasing.
r
- c. LESS THAN (0.5) (
i REFERENCE VEGP Lesson Plan, LO-LP-33530-00, Soc. II-D, pp. 7L0 LO-LP-33430-02, Sec. II-D, p. 7 5
, 192006K100 ..(KA's)
ANSWER 5.06 (1.00)
, t d I I
, REFERENCE r i
- VEGP Lesson Plans, LO-LP-33210-02, p. 15 Lesson Objectivos, LO LP-33210-02, #5 [
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ANSWER 5.07 (1.00)
REFERENCE VEGP Lesson Pl an, LO-LP-34210-OO, p.9 Lesson Objectives, LO-LP-34210-00, #4 i
193000K103 ..(KA's) s ANSWER 5.08 (2.00) .
l (0.5 each)
- a. DECREASE l INCREASE l b.
- c. INCREASE [
i
- d. DECREASE i
REFERENCE ;
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WEST T-H PRIN PG 13-23,24 VEGP Lesson Plan, LO-LP-54510-00, pp 11-13 j i
193000K105 ..tKA's) (
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- ANSWER 5.09 (1.50)
- a. False [
i l b. True ;
- c. True (0.5 each] !
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ELUlQD40ND_IUE6dQDYued1GQ-
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REFERENCE Westinghouse Thermal Science, Chapter 10, Pp. 41-49 ,
General Physics HT & FF, Pp.319-326. -
LO-LP-34410-OO-C ,
t 191004K105 191004K112 191004K106 ..(KA's) !
n ANSWER 5.10 (1.00)
- 1. Decrease in U230 atoms. ;
- 2. Increase in resonant absorbers (PU240) .
REFERENCE j i
VEGP Lesson Plan, LO-LP-33410-01, p.9 192OO4K107 ..(KA*s) l e
i ANSWER 5.11 (2.00)
- a. (3 0 0.5 each)
- 1. Doppler-only power defect ;
- 2. Moderator-only power defect j
- 3. Void-only power defect !
- 4. Pressure-only power defect (1.50) t
- b. Decomes more negative. (0.50)
L REFERENCE [
L i VEGP Lennon Plan, LO-LP-33420-02, p. O (
Lesson Objective, LO-LP-33420-02, #14 001000K549 .,(KA's) ,
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ANSWER 5.12 (2.00) i I
- 1. ' Boron Concentration Decreases (0.53 - MORE NEGATIVE CO.53 r
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- 2. Fission Product Buildup to.53 - LESS NEGATIVE CO.53 f f
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Qx__IUE0BY_DE_UUGLEOS_EDWEB_ELOUI_DEEBBI1QU2 Pcgo 88 ELVIDS200D_IUE6d9DXU001GS REFERENCE Westinghouse Nuclear Training Operations, p. 1-5.31 !
VEGP Training Vol. 2, Chapter 4, pp 122-124 Lesson Plan, LO-LP-33440-01, pp 5&6 i 192005K105 ..(KA's)
ANSWER 5.13 (1.50) I (0.5 each)
- 1. Valve operations -
- 2. Pump operations
- 3. Steam / water interface l O$ ench ca u se Cf- En ef es REFERENCE ,
VEGP Lesson Plan, LO-LP-34410-00-C, pp 26 L 27 193006V104 ..(KA'u) .
ANLWER 5.14 (1.00)
Cavitation occu-u when the pressure of the fluid is reduced to a pressure below CO.53 that of its saturation pressure for a given ;
temperature which will allow botling to occer C0.53.
i REFERENCC :
L VEGP Lesson Plan LO-LP-34410-00-C, p. 22 Lesson Objective, LO-LP-34410-00-C, #10 i
193006K111 ..(KA's) l l
ANSWER 5.15 (1.50)
- a. Vogtle 1 (0.25) oue to a smaller Beff value (0.50) l l
- b. Vogtle 1 (0.25) due to a more negativo NTC value (0.50) f i
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ELVID2400D_IUE6dQDYU001CE -
L REFERENCE WEST Fund of NRP PG 7-33 WEST RCC for Large PWRs PG 3-23 l e
f.
192000K124 192OOOK114 ..(KA's) i
- ANSWER 5.16 (1.00) l
- a. Tsat for 2250 psia (2235 psig) [;
= 652.67 F (0.50) i, o Subcooling margin = Tsat - Thot = 652.67 - 507 = 65.67 F + nr - 444Mb F l (0.50) <
- b. Subcooling margin decreases because That vill increase as power l increases (0.50) j REFERENCE J VEGP Lesson Plan, LO-LP-34110-03 t
001000K556 ..(KA's)
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ANSWER 5.17 (2.00)
A Hard Bubble is a vapor volume such as the pressurizar steam space !
where there is a mixture of steam and non-condensable gases present I (1.0) I A Hard Bubbin causes the response of the pressurizer to diminish due j to the reduced volume expannien during outsurges and lack of ;
condensation during insurgen. (will accept other wording conveying similiar processes. (1.0) j 1
REFERENul i
VEGP Leoson Plan LO-LP-34310-00, p. 17 Lesson Objective, LO-LP-34310-00, #Se 010000K501 ..(VA's) [
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ANSWER 5.10 (1.50)
- a. P = Po10exp(SUR)(t) (0.5) -
l
= (0.1) 10ex p (0.15 ) (2) :
r
= 0.';99526% (0.5) I Round off to 0.2 % is acceptable.
- h. 1E-6 to E-6 amps or 1% to 2% of full power. (0.5)
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VEGP Lesson Plans, LO-LP-33230-01, P. 6 Lesson Objectives, LO-LP-33230-01, #3 [
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3 192OOBK114 ..(KA's) i ANSWER 5.19 (1.50)
PCM change duo to temperature = 5 F * -15 pcm/ degree F = -75 pcm j CO.253 :
Reactivity change required by rods = 228 step to 180 steps = 40 steps [
CO.253 ,
43 stepu
- 1.095 pcm/ steps = -43.8 pcm (inward rod movement) i CO.253
-75 pcm ( t emp or.a tur e ) & -43.0 pcm trods) = -110.8 pcm reactivity change. f
[0.253 l
-110.0 pcm / -10 pcm/ ppm = 11.08 ppm boron change. l CO.253 600 ppm - 11.80 ppm = 500.12 ppm final concentration. [0.253 I
REFERENCE (
l WEST RCC for Largo PWRs pg 3-21/22, 5-33 j VEGP Lesson Plan, LO-LP-33420-02, pp 1-5 l LO-LP-33440-01 j
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OO4000A404 ..(KA's) [
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-ANSWER 5.20 (1.50) f r
The large pellet diameter (relative to the resonance peak energy path) results in the first layer of fuel "shielding" the second layer of f f uel . . As fuel pellet temperature rises the off-resonance neutrons (f or the most part that would previously pass entirely through the pollet) are more readily absorbed. [1.03 Causes negative reactivity to be added as power increases. C0.53 ,
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RErRRENCE t DVPS Reactor Theory Manual Chapter 6 p 33 VEGP Training Vol. 2. Chapter 4 pp 31-37 {
Lesson Plan. LC LP 33410-02, pp 7 (4 0 j Lesson Objectivo. LO-LP-33410-02, #6 l
l 192OO4K105 . 3 j
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62__ELOUI_DYDIEd3 DES 1064_QQUIBQL4_00D_1USIBVdEUISIlDU Pcg3 92 ANSWER 6.01 (1.00) l I
a l REFERENCE VEGP Lesson Plan LO-LP-17201-00 TP-005 }
.015000N603 ..(KA's) ,
i ANSWER 6.0 (1.00) j i
b I REFERENCE {
Safeguard Actuation System Fig. 7.2.1-1 (Sheet O of 20) !
l 013000K402 ..(KA's) ;
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I ANSWER 6.03 (1.00) ,
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VEGP Lesson Plan, LO-LP-1401-01 t i
064000K411 ..(UA's) [
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. ANSWER 6.04 (2.00) i
^
(any 4 0 0.5 each)
- 2. Preferred incoming breakere open.
- 3. No bus faults as indicated by no bus lockouts on preferred bus. [
- 4. DG close permissive from sequencer. l
- 5. No lockouts on Diesel engine or generator. '
e '"* ~ ' " " * ' L * *'. , F * * ' ' ' ' l f, 3 e . s , ' s , . . r - 4 . r e ., o s'. . , ' s e lra w r ursk y, g,s w a., r.sI u.o- s :res . h, he uv."
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REFERENCE ,
3 VEGP Lesson Plans, LO-LP-01401-01, p. 0 ,
i (3.5/4.0) j 064000K411 ..',KA*n) i 1
ANSWER 6.05 (2.00) -
1 I
- 1. Source range high flux !
- 2. RCP low voltage
- 3. RCP underfrequency j
- 4. Pressurizer low pressure <
f
- 5. Pressurizer high level
- 6. Single-loop low flow
- 7. Two-loop low flow
- 0. Turbine trip (0.25 each) t REFERENCE i
VEGP Training Text, fig 7.2.1-1 sh 2 f 012OOOK406 ..(KA's) l 5
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6t__EbeUI_SYSIEdD_DE21004.GQUIBQL4_0ND INDIBudEUIGIIOU Pcgo 94 ANSWER 6.06 (2.00) O ; ;)
- a. 1) OT Del ta--T c 21:u!:t ar rd;' (0.25)
- 2) OP Del ta-T sai cu! &LE T r'/' (0.20)
- 3) P-12 circuitry (or Hi Steam Flow SI permissive, Steam dump block, and Lo-lo Tavg signal) (0.25)
- 4) Feodwater isolation circuitry (or Lo Tavg signal to FWI) (0.25)
- 5) OT Och'f r ed .nop .n .,,4 w M n can h<< L , g ,, , , _
- b. 1) RVLIS c) op N l . - r c . .I s r.j. 4 a ./ rv,b e r a8..,L. >
- 2) COPPfl
- 3) Core subcooling monitor ,
- 4) Retote Shutdown System
- 5) Gaf ety Parameter Disrt.ay System
- 6) Plant Computer
- 7) Plant Safety Monitoring System (Any 4 0 0.25 each)
REFERENCE VEGP Training Text , Chapter 25, pp 17,10 Lesson Plans, LO-LP-16701-00, pg 5 and LO-LP-16501-00, pg 5 00'?000K512 OO2000K410 000000K107 002000A403 000000A104 i
. . O: A 's )
ANSWER 6.07 (1.50)
- a. Decreason (0.5 each) I
- b. Increase
- c. Decreases i
r REFERENCE VEEP Training Text , Chapter 25 Logics sheet 5. ,
012000A101 . . O: A 's ) f I'
I i
\ ,
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) ;
l ?
6t__ELOUI_SYSIENS_DED10Sa_GOUI69La_0ND_IUSIBudEUISI1QU Pcgo 95
+
l P
ANSWER 6.08 (2.00) l Accept any 4 0 0.5 each
- 1. Two NSCW pumps starts per train. ,
- 2. Containment cooler isolation valves open.
- 3. Containment aux, cooler and cavity cooler isol. valves shut. [
- 4. NSCW blowdown valves shut. !
- 5. If either of the primary NSCW pumps in a train fails to start, the j associated train standby NSCW pump will start
)
REFERENCE VEGP Lessen Plan, LO-LP-0601-05-C Lesson Objective, C.3 i 076000K403 076000K402 076000K401 ..(KA's)
ANSWER 6.09 (2.00) l (0.5 for each item indicated) !
4 one operable flow path f rom RWST with manual transfer to co 'A4 ent f sump during recirc.
t REFERENCE ,
VEGP Lesson Plan, LO-LP-13001-01-C, p. 17 !
Lesson Objective 9 l 006000G005 ..(KA's) !
t L
ANSWER 6.10 (1.50)
(0.3 for each signal, 0.1 for each setpoint, and 0.1 for each coincidence for a total of 1."On
- 1. H1-2 containment pressure, 14.5 psig, 2/3 ,
- 2. Steam line pressure low, 505 psig ( >P-11 or < P-11 but not j l '
blocked), 2/3
- 3. Steam line pressure rate high, <= 100 pst with a 50 see time I constant ( < P-11 and blocked), 2/3
)
t t
[
(++++* CATEGORY 6 CO$TINUED ON NEXT PAGE *****) [
I i
l .
l
\
\
f
<$x Pego 96 EL9dI.SKDIEdD DE0196a_CQUIBQLa_6dD INSIBudEUIGI190 REFERENCE VEGP Technical Specification, Table 3.3-J l 013000K403 ..(KA's)' i
'l ANSWER 6.11 (1.75) L
- a. 1. Trips both MFP's (0.253 l
'2. (Shuts) Feedwater Isolation valveng !
- a. Main (0.253 [
- b. Bypass CO.253
( r.e wie 7 <.j ) ,
- b. 1. Safety Injection Signal (0.25) ;
- 2. S/G Hi-Hi level (2/4), ( 7 0 */. ) , (P-14) (0.25) i f
REFERENCE i l
VEGP LO-LP-19101-00-C l 059000A306 ..(KA's) ;
t
[
L i ANSWER 6.12 (1.50) l l I j (0.5 each) [
DPa - meanures static narrow range level of the vessel from hot leg to -
top of head.
DPb ~ measures static' wide range level from bottom of vessel to top of vessel.
DPc - measures differential pressure of RCS flow ae,ross the core.
I REFERENCE VEGP Training Text, Chapter Id, p. 5 i l
I (3.1/3.6) {
002OOOK603 ..(KA's) l
?
i l
(***** CATEGORY 6 CONT 1 HUED ON NEXT PAGE *****) !
i I
t b..___._________________.-_____________________
bi__Et0UI_DYDIEUD_DED1002_CQUIBOLi_0UD_10DIEVDEUIGI1QN PLga 97 l
ANSWER 6.13 (1.50) p, '
, _ , , ' . ; L ': ;- m a ,= ' es.' usa Rx trip C O.M 3 3 Starts MDAFW pumps ( 0. ;i) ,
St vts TDAFW pump C O . ,W 3 '
Mk Is. /... is./.gi... re.31 s l .w y o s ,<l. < is. k r,,* ' E o. % 3 REFERENCE VEGP Lesson Plan, LO-LP-18301-00-01 p.7 035010K401 . 4:A 's )
>.S0 ANSWER 6.14 (M'v )
- a. Prevents bridge or trolley movement (0.33 Setpoint 1407 lbs (0.23
- b. Stopu hoist withdrawa) [0.253 and clears low load inhtbit interlock (0.253.
- c. Stops downward motion of hoi t.t (0.33 Setpoint 200 lbs. Co.23
( nc ,M, ge s runuires t ., r. n g _,_ t n en 'v3 briagn int-rish m angagat b r-Ae-4 0, ;f,4.-.w+d e e c e n d pud selects direction md e==e f ra -
!'"tid ^ [ 0 Y 1. (P (*yf tl l REFERENCE VEGP Training Te>t, Chapter 1Ea, p. 16 034000V403 034000V402 034000V401 . . O: A 's )
ANSWER 6.15 t2.00)
(0.5 each)
- 1. Rf.'T RVILS pr essur e (is less than 377 psig).
- 2. RWST suct'.cn valve for the train (0912A/B) is closed.
- 3. ECCS rect rculation valve for the train (OD04A/lO is closed.
- 4. Containment sump tuolation valve (0011A/D) is closed.
REFEREPCE VECP Training Text, Chapter 10a, p. it, Da'.a Tables.
005300N407 ..(VA's)
I
(****+ CATEGORY 6 CONTINUED ON NEXT FAGE *****)
i
i .6___E66MI_SYSIEdS_QEQ1GN2_QQNIBQL2_6NQ_INSIBQUENIGI1ON Pcga 98 I
ANSWER 6.16 (2.00)
(0.5 each) .
- a. Trip open bistable acti on. CR " uor A t ,- Chapter 1.c, p.
(3.8/4.1) (4.0/3.9) .
j OOOO27A101 010000K403 ..(KA's) i
't
(***** END OF CATEGORY 6 *****)
~
Zm__EB9GEDUBEE_:_UQBd662 0HUQBd862_EDEBOEUGY Pcga100 GUD_88D19690lGOL_G9dIB96
' ANSWER 7.01- (1.00) b REFERENCE VEGP EOP Training Text, Vol 1, Ch I-B, pp I-2-6, 7& 11 194001A102 ..(KA's) pelerecI ANSWER 7.02 ( .00) b hEFERENCE VEGP 900-1, Reactor Trip or Safety Injection 00 000G001 ..(KA's)
ANSWER 7.03 (1.00) b
~
REFERENCE VEGP fi-0 19001-1, Reactor Trip or Safety Injection
- 2CA 0.0 entry conditons tr4001A107 ..(KA's)
ANSWER 7.04 (1.00) a
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
cZz__EB9GE99BES_ _N9Bd862_0BN9Bd862_EdEBGENGY Pcgo101
-ONQ_B8 Dig 69Q1G86_GQUIBQL REFERENCE Westinghouse Background Information for ECA O.0 Users Guide for ERG's and Background Documents p. 17/18 OOOO55K302 ..(KA's)
ANSWER 7.05 (1.00) a REFERENCE VEGP 19100-1, ECA O.O p.5 013000G001 ..(KA's)
ANSWER 7.06 (1.50)
(0.5 each) b, d, e REFERENCE VEGP Abnormal Procedures, 18003-1, 18004-1, 16009-1 4
0000G7G011 000022G011 OO1050G015 ..(KA'n)
ANSWER 7.07 (1.00) e REFERENCE VEGP Emergency Procedure, 19000-C, p. 1 OOOOO7A202 ..(KA's)
(***** CATEGORY 7 CONTINUED ON NEXT PAGE ****+)
L -Zz__EB9GEDUBES_:_N9Bd862_8EU9Bd862_EUEBOENGY Pcgo102
[1 ,
8ND_8091969G1986_G9 NIB 96 '
ANSWER 7.08 (1.00) e REFERENCE VEGP Emergency Procedure, 19000-C, Attachment A, item 11 OOOOO7A202 ..(KA's) ,
' ANSWER 7.09 (2.50) 29
- a. RCS subcooling monitor indication CO. 253 greater than 4MT deg. F CO.253
- b. RCS hot leg temperatures CO.253, stable or lowering CO.25]
- c. Core exit thermocouples [0.253, stable or lowering CO.253
- d. RCS cold leg temperatures CO.253, at saturation temp. for S/G pressure CO.253
- e. S/G pressures E0.253, stable or lowering CO.253 REFERENCE VEGP LO-LP-34110-OO p.6 ES-0.1, 19001-1 p.16 193008K122 ..(KA's)
ANSWER 7.10 (1.00)
EOP 19000-C, E-O Heactor Trip and Safety Injection
- REFERENCE VEGP Abnormal Procedure, 18938-1, p. 2
- OOOO60K318. ..(KA's)
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
I.
~
"Z2__EB9GEDUBES_ _U9Bd862_Gh30Bd862_EUEB9EUGY Pcg3103 00D_B09196991G86;G9UIB96 ANSWER 7.11 (1.00)
- 1. Vacuum. drag capability is lost.
s
' REFERENCE VEGP Abnormal Procedure, 18008-1, p. 2 039000G010 ..(KA's) r ANSWER 7.12 (1.50)
- 2. RCS pressure [0.53 less than 1375 psig CO.2"J.
REFERENCE VEGP Emergency Procedure, 19000-C, fuldout page, p. 26 000007K301 ..(KA's)
ANSWER 7.13 (1.00) ]
The containmere. hydrogen concentration cannot be maintained below 4% by other means.
4 REFERENCE i i VEGP System Operating Procedure, 13130-1, p. 14, caution noto 029000K301 ..(KA's)
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
'It__BBggggyBgS - NQBd863,_8BNgBd862_EMERQgdGY PcgalO4 8N9_B09196991G86_G9dIB96 f
' ANSWER 7.14 (1.50)
(0.5 each)
- 1. Neutron flux lowering
- 2. Reactor trip and bypass breakers - OPEN
- 3. Rod bottom lights - LIT r
REFERENCE i
VEGP FR-S.1,C19211-13, Response to Nuclear Power Generation / ATWT OOOO29EK31 ..(KA's)
ANSWER. 7.15 (2.00) 5" c1 (any jV O $>f$ each)
- 1. Job is completed.
- 2. when c1ncelled.
- 3. whenevtr a significant change in radiological conditions occurs.
- 4. when work scope changes.
H 5.
(r .
as determingd
,} , , g,, a. , ) s. -wby's<P supervision.
f*. der ye's<. ,
?, y,r c., , ,.,t 4;, .. 3lu ).y s .
F.EFERENCE VEGP Health Physic Procedure, 43nO7-C 5 p. 19 194001N103 ..(KA's)
}
l ANSWER 7.16 (2.00)
(0.5 unch pluu O.5 f or correct ci der)
- 1. Reinitiation of high pressure safety injection
- 2. Rapid secondary depressurization
(***** CATEGORY 7 CONTINUED ON NEXT PAGE *****)
, - -- - - --- --. y_-, -- ------- -.
_r- v---
Zs__EBQGGDUBES_:_NQBdebi_8ENQBd862,gdEBQENGY Pcgo105 GND_BORIQLQ91G86_GQUIB96 REFERENCE VEGP. Lesson Plan, LO-LP-37061-01, p. 5 Lennon Objective, LO-LP-37061, #2 OOOO74K311 OOOO74K103 ..(KA's)
ANSWER' 7.17 (2.00)
- 1. Pzr level CO.53, 9% CO.53
- 2. RCS subcooling CO.53, lenn than 24 degreen F CO.5]
REFERENCE Procedure 19000-1, LO-LP-37002-02-C pg 6 OOOOO9K303 ..(KA's)
ANSWER 7.18 (1.00)
~
(Trip the affected Train Diesel Generator) by depressing both EMERGENCY STOP Push-buttons.
r REF2RENCE VEGP Abnormal Procedure, 10031-C, p. 2 064050G014 064000K102 ..(KA's) ;
L j.C C ANSWER 7.19 (0. r4N j
- 1. Control bank movement in in wrong direction CO.53 "en c.-itical-f 0. 5 2 -- t
- 2. Count rate increason at an unexpected rate [0.5] wh T r"h rr 4 + 1 c al I O . " ? --
l
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r
. 'Z2.__E89CEDUBES_:_N9Bt!8bi_8BU9Bd864_EdEB95URY ' Paga10
? 8dD_B89196991G86_G9BI696 ,
REFERENCE s
VEGP System Operating Procedure, 13009-1, p. 1, precautions OO4020G014 ..(KA's)
P ANSWER 7.20 (1.00) iS hnPJre containment integrity is maintained.
t t
, REFERENCE f VEGP System Operating Procedure, 13130-1, p. 4 j l
028000A101 ..(KA's)
-ANSWER 7.21 '(0. 50 )
HP Superintendent 4
REFERENCE VEGP Health Physics Procedure, 43OO7-C, p. 3, precaution and
. limitations i
1940v1K103 ..(KA's)
[
1 ANSWER 7.22 t' 1. OO ) :
1 The SS in aware of t h re work evoltitions and the impact of and on other l work evolut4.ons its the area.
L If t-REFERENCE !
i VEGP HP procedure 43OO7-C, p. 16 f 194001K103 ..(KA's)
I f
L
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~
Zi__EBRGEDUBES_:_N9Bd862_8DU9Bd862_EMEBQENGY Pcga107 j ' 809_B8D19L991G8L_GQUIB96 t
1 ANSWER 7.23 (1.00)
(0.5 each) ~
1.. Qualified HP-personnel
- 2. Qualified Operations personnel REFERENCE VEGP Health Physics Procedures, 43101-C, p. )
194001K103 ..(KA's) l 4
d a
i !
1 i
i j
(***** END OF CATEGORY 7 *****)
e L'_
at__0Dd1NISIB8IIYE_EBgCgDUBES2_G9691I19dS2 Pcgm108
- OND_LidlI8IlQNg t
I.
ANSWER 8.01 (1.00) b REFERENrE VEOP Plant Administrative Procedure, OO304-C, p. 6 194001A102 ..(KA*u)
. ANSWER 8.02 (1.O(f d
DGvCTCO REFERENCE VEGP T S. 3.4.4 ,
01 00A203 ..(KA'u)
ANSL.ER B.03 (1.00)
< b REFERENCE VEGP Operation ~ Administrative Prccedure, iOO19-C, sec. 4.0, p. 1 194001K101 ..(KA's)
ANSWER 8.04 (2.00)
(0.5 each)
- 1. Control of jumpers and lifted wires.
- 2. Final approval of jumpers and lifted wires.
- 3. Determination involvement in safety related system.
- 4. Review of log to ensure proper transfer operating information from one shift to the next.
i
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L __ _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ . . _ _ _ _ _ _
, at__8Dd1NISIB8I1YE_EB9GEDWBESi_G9BD1I1ONH2 Paga109 0N9_L1d110I196S i
REFERENCE' VEGP Administrative Procedure, 00306-C, sec. 3.2.1, p. 4 194001A106 ..(KA's)
ANSWER 8.05 (1.00)
- 1. On Shift Operatiens Supervisor
- 2. - Shift Supervisor REFERENCE VEGP Emergency Response Proceduren, 91102-C, p.1 194001A103 ...(KA's)
ANSWER 8.06 (1.50)
(0.5 each)
- 2. Two recidual heat removal suction relief volves each with a set point of 450 psig,.
- 3. The reactor coolant system depressurized with an RCS vent
+ capable of relieving at lear,t 670 gpm water flow at 470 puig.
REFERENCE VEGP T.S. 3.4.9.3 p. 3/4 3-4 002000G007 ..(KA's)
ANSWER 8.07 (1.00)
- 1. Must be approved by two members of plant management staff (0.25) least one of whom holds a Senior Operator license. (0.25)
! 2. Check - intent of original procedure is not altered. (0.5) 1
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
i
1
'at__09d1NISIBOI1YE_E80GEQUBESi_GQUD111QU@3 Page110 OND_ Lid 1IGI1ONS REFERENCE Tech Specs 6.7.3 194001A101 ..(KA's)
ANSWER 8.08 (2.00)
(4 0 0.5 each)
- 1. Will not violate step-by-step performance.
- 2. Will not result in omission of required work.
- 3. Will not violate intent of the procedure
- 4. Will not create an unsafe plant condition REFERENCE VEGP Plant Administration Procedure OOO54-C, Step 4.2.2.3 194001A102 ..(KA's) o.*50
, ANSWER 8.09 (-h-ee)
Modus 1 to 4 CO.51 [f or either uni t) O'. 5 2.
REFERENCE VEGP Operations Admini-Atrative Procwdure, 10003-C, p. 1 19400tA103 ..(KA's)
ANSWER O.10 (1.00)
(0.5 nach)
- 1. The person has performed chift functions within 30 day OR
- 2. Person has been briefed in accordance to Licensed Operator Requalification Program.
I i (***** CATEGORY O CONTINUED ON NEXT PAGE *****)
r- ,
- ;9z_.8Dd1NISIBOI1YE_P8QQEQQ8ES2_QQUQlI1QUS2 Peg 3111 8MD_L10110I1965 REFERENCE VEGP Operations Admin Procedure, 10003-C, p. 2 194001A111 ..(KA's)
ANSWER 8.11 (2.00)
(0.5 each) 1.
Safety of_the reactor is in jeopardy.
- 2. Reactor operating parameters exceed reactor trip netpoints and automatic shutdown did not occur.
- 3. It is required to protect personnel and equipment.
- 4. Unusual circumstances warrant it.
REFERENCE VEGP Plcnt Administrative Procedure, OO3OO-C, sec. 3.3, p. 2 194001A103 ..(KA's)
- ANSWER B.12 (1.50) 4 (any 6 0 0.25 each)
- 1. The name and position of each operator on shift.
- 2. Major equipment status changes.
- 3. Major system and equipment testing.
- 4. Personnel injuries.
- 5. Entering and exiting a Technical Soecificet ton act7 on strtument.
- 6. Significant events, such as reactor tripu or unexpected power changes.
- 7. Implementing the Emergency Plan. {
O. Significant security incidents. ,
h id, ** , a u ,ra.1 pirhs .o . r h
- e * =* n ~ ' h ' V A '
?,*b*i.'ae.*r*h"fc.<y +f ~
CR- one e<s ' a 4 y } lr t r, re re clod A c r.viry REFERENCE VEGP Operations Administrative Procedure, 10001-C, sec. 2.2.1, p. 1 i 194001A106 ..(KA's) ,
l I
i
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l I
c_-_. .
t Os__0DUINISIBOIIL'E_EB9GEQWBES2_GQNDlIlONS2 Pago112 OND_tIdlIGI1QNS ANSWER 8.13 (1.00)
(0.5 nach)
- 1. More than one control rod withdrawn
- 2. Fuel in the vessel.
REFERENCE VEGP Operation Administrative Procedure, 10006-C, tec. 3.2.1, p. 1 194001A106 ..(KA's)
. ANSWER 8.14 (2.50)
(any 5 0 0.5 each)
- 1. Classi f ying and decl arir.g the emergency. -+ ice +t*ds g d own gr a dittg a^d t : -- - i . m L i v . )
5 2. Recommending protective actions to of f-site authorities, and-con 4ent-me m e sgeg.
- 3. Authorizing personnel radiation exposures in excess of 10CFR2O limits. g, ,
- 4. Deciding to evacuate non-essential personnel 4oem uite at Alert C1assification.
- 5. Deciding to request assistance from federal support groups.
- 6. Deciding to notify off-site authorities responsible for emergency measures.
- 7. Re < w:l yiny tho t ~') * "? M d~^y 'lhJ OE " ~ h ') -
t'. 12 cen u. n r.
REFERENCdpfcnl o f E.<eryt,ey Al? t.s < <;c VEGP Emergency Response Precedure, 91102-C, sec. 2.3, p. 2 194001A116 ..(KA's)
ANSWER O.15 (1.50)
(0.5 each)
- 1. On--Shi f t Operationn Personnel
- 2. Operations Chain of Command
- 3. NRC resident inspectors f***** CATEGORY O CONTINUED ON NEXT PAGE *****)
s . . -
is az__8DdINISIB8I1YE_EBOGEDUBES2_GQNQ1IlgNQ2 Pega113
- / GNQ. bid 1I6II963
}l ~
ll REFERENCE UE,GP Plant Administrative Procedure, OO301-C, sec. 3.2, p. 1 194001A1.11 ..(KA'r.)
ANSWER 8.16 (2.00) i (any 4 0 0.5 each)
- 1. Keer noise levels to a minimum.
- 2. Maintain an attitude of alertness.
- 3. Keep area in a clean and orderly condition. *
- 4. Obtain operations supervisory approval prior to performing any activity that would be disruptive or affect operations.
- 5. Do not take food and/or drink to the control panels, r
REFERENCE VEGP Plant Administrative Procedure, OO301-C, p. 2 194001K105 ..(KA's)
- ANSWER 8.17 (1.00)
(0.5 each)
- 1. HOLD tag the handswitch in the CLOSED position.
- 2. HOLD tag the handwheel in the CLOSED position.
0,,R Ma o r< h**d*'I' I* ' '*
- A " A P s ; c'; * ' - . .
2, me h< hr.r h eib or Arcles.lic'Ik v
- l* *~ l llo v cl fo 3
- T'J 1 [c.).2 f]
RGYERENCE t< c !I$e j<)
de vTbt
- . ,+ [ o 2 T.3 , TI, e ta r'd h ot o rey 3 VEGP-00704-C, p. 8, Equipment Clearance and Tagging 194001K102 ..(KA's)
ANSWER- 0.18 (1.00)
The individual shoule NOT be allowed to enter a Radiation Control Area (wh3ntheexposuremargin is less than or equal to2OOmrem) [1.003 (Unless granted permission by a Health Physics Laboratory Supervisor or above)
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
,: O___69d1NIDIBOI1YE_EB9GEDUBES2_GOUDII19NS2 Page114 689_L101I0I1983
' REFERENCE p_ .VEGP Administrative Procedure, 00920-C, sec. 4.3, p. 4 s 194001K104 ..(KA's)
ANSWER 8.19 (1.50)
Tuesday / Wednesday worked > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> CO.53 Friday / Saturday worked > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> CO.53 Monday-Sunday worked > */2 hours in seven days to.53 i
REFERENCE VEGP Plant Administrative Procedure, 00005-C, sec. 3.2, p. 1 VEGP Technical Specifications, 6.2.2, p. 6-2 194001A103- ..(KA's) e ANSWER 8.20 (1.50)
(0.5 each)
- a. Sample for Boron concentration
- b. Logged in Control Room Log
- c. > 1% volume change I hy *b *%
h.,); e.ml l#<< l c he rey CJ 1 j *t .
REFERENCE VEGP Licensee Event Report,88-007 194001A111 ..(KA's) f ANSWER 8.21 (1.50)
(0.5 each) :
7 DAYS !
7+ 1.25 = 0.75 DAYS for any one week period. I 7
- 3.25 = 22.75 DAYS for any three consecutive surveillance periods.
L i
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Si_ _8 DM IN1HIB 8I1YE _EBOG E DU BE S 2_GOU D1Ilg NS 2 Pcgs115; 4
869_ Lid 1I8Il0US REFERENCE j l' - VECP Licensee . Event Report , 88- 012 Technical' Specification, 4.0.2 OO4020 GOO 5 ..(KA*s)
,l' t
4 r
I F
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I 6
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r U. S. NUCLEAR' REGULATORY COMMISSION !
REACTOR OPERATOR LICENSE EXAMINATION ,
FACILITY: VgGTLg,2,,__k__1,,,______,,,,,
REACTOR TYPE: P W R - Wg g 4_, _ __ _ _ ,, _ _ ,, _ _ _ _ _ _
DATE ADMINSTERED: ggf99fj,9,,,___,,____,____,,,,,_ l 1
CANDIDATE _ _ _ _, ,,,_ _ _ _ _ _ _ _ ,,,,_ _ _ _ _ _ _ _ _
l INSleggIlgNS,Ig_geNQ}QSJh Use separate paper for the answers. riieanswerson 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 I grade requires at least 70% in each category anti a final grade of at ,
least 80%. Examination papers x1.1 be picked up six (6) hours after the examination starts. ;
i
% OF i CATEGORY */. OF CANDIDATE'S CATEGORY
__V0695_ .19IGL ___SCgeg___ _yeLug__ ______________Celggger_________,___
29,50 M. 'l 9
/ 12sEE_ [_2i_Z2 _ _ _ _ _ _ . . , _ _ _. . .. 1. PRINCIPLES OF NUCLEAR POWER .,
PLANT OPERATION, THERMODYNAMICS, i HEAT TRANSFER AND FLUID FLUW b 25',8 4
.29 29 _8 2$125 . ____ . . ..... . _ 2. PLANT DESIGN INCLUDING SAFETV ,
AND EMERGENCY SYSTEMS ,
19.15 14. 58 t
[_E2:2E_'., O tISP _______. -. __-.___ 3. ' 3TRUMENTS AND CONTRCLS l 29.5'o 14.79 i I_211:s_. Edir.El
- 4. PROCELUREG - NORMAL, ABNORMAL, t EMERGENCY AND RADICLOGICAL !
CONTROL t i19.00 i
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Tcgats j r z::: _. -------_
Finai--__- ,--__f'cade l t
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Al1 wark done on thio examtnation is my own. I have notther givon f nor received aid.
Candidate's Signature >
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MAEl@Y t
s NRC RULES AND GUIDELINES FOR LICENCE EXAMINATION 3 J During the administration of this examination the following rules apply
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only ono candidate at a time may leavs. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or oossibility of cheating. 1
- 3. Use black ink or dark pencil only to facilitate legible reproductions. l 4 Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
- 8. Consecutively number each answer s+ t, write "End of Category __
as appropriate, start each category c new page, write only on one side of the paper, and write "Last Pagt n the last answer sheet.
- 9. Numoer each answer is to category and number, for example, 1.4 6.3.
- 10. Skip at leaat three lines between each answer.
- 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 es 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 i n t'6e question or not.
- S. 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 questio7s 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 examinstion has been corpleted.
1 - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
_____--__-v--_-- . _ _ _ . _ _ _
18. Wh:n you ccmploto your oxcmination, ycu challs
- a. Assemble your examination as follows:
(1) Exam questions on top. l 6
., (2) Exam aids - figures,. tables, etc. ,
(3) Answer pages i ncluding 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 exaatnation questions. .
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- d. Leave the examination area, as defined by the examiner. If after ,
leaving, vou are found in this area while the examination is still !
in progress, your license may be denied or revoked.. t i
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Pcgo 2 IUESD99XN$D1QSg,,0{@l 169NgEgg,@N9,E(Ulp,E69W QUESTION 1.01 (1.00)
TRUE or FALSE?
- a. Delayed neutrons are LESS likely to escape resonance capture than prompt neutrons. ,
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- b. Ef f ective delayed neutron f raction changes over core lif e due to the buildup of Plutonium and the depletion-of U-235.
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QUESTION 1.02 (Z/
State how each of the following will affect shutdown margin. Limit your answer to INCREASE, DECREASE, or NO CHANGE. Consider each case separately. Assumu EOL.
- a. Boron concentration is decreased 20 ppm while maintaining constant power and no rod motion.
- b. Bank D rod height is increased from 125 steps to 200 steps while maintaining constant power and boron concentration.
pg)GTED
- c. Pj $tcr t r i ;: . ch: i n s er t ,-
- d. While shutdown, the RCS is cooled down Oy 40 degrees.
l (ss*** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
OUESTION 1.03 (1.00)
TRUE or FALSE 7
- a. For a constant boron concentration, differential boron worth will decrease over core life because of the buildup of fission products.
- b. For a constant power level, differential boron worth will increase over core life because of the decreasing baron concentration.
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QUESTION 1.04 (1.00)
Multiple Choice Delayed neutrons play a major role in the operation of the core because they ... (Choose the ONE correct answer)
- a. are born at (thermal) slow energy levels (less than 1 ev) and therefore are more apt to cause a fission as compared to being absorbed by a poison.
- b. provide 70% of the fission neutron inventory and have higher importance factors associated with them as compared to prompt neutrons.
- c. are considered an thermal neutrons and therefore they etill not travel far enough to leak out of the core.
- d. are born so much later than the prompt neutrons and provide controllability during steady state operations and power transients.
2
(***** CATEGORY l CONTINUED ON NEAT PAGE *****)
QUESTION 1.05 (1.00)
Multiple Choice Which one of the following statements is correct?
- a. With all other conditions constant, the reactor responds LESS QUICKLY to a given reactivity change at EOL than at BOL, because the value of Beta-bar effective is GREATER.
- b. With all other conditions constant, the reactor responds MORE QUICKLY to a given reactivity change at EOL than at BOL, because the value of Beta-bar effective in LOWER.
- c. With all other conditions constant, the reactor responds LESS QUICKLY to a given reactivity change et EOL than at BOL, because the value of Beta-bar effective is LOWER.
- d. With all other conditions constant, the reactor responds MORE QUICKLY to a given reactivity change at EOL than at BOL, because the value of Beta-bar effective is GREA15R.
(***** CATEGORY i CONTINUED ON NEAT PAGE *****i
i QUESTION 1.06 (2.00) i t
A beginning-of-life core has been operating with all rods fully withdrawn at 100*/. power for 1 week. The bank D control rods are inserted 100 steps with sufficient boron dilution to offset the reactivity added by the rods. Answer the following Questions about the resultant xenon transient IN THE RODDED REGION OF THE CORE.
- a. How does the xenon level change at first (INCREASES, DECREASES, STAYS THE SAME)? (0.50)
- c. The final steady-state xenon concentration will be ________(LESS THAN, GREATER THAN, EQUAL TO) the original concentration. (0.50) l l
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s QUESTION 1.07 (1.00)
Multiple Choice The reactor has been operating at 100% power for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, reactor power is then lowered by baron addition to 80%. Which ONE of the following statements nest describes Xenon behavior during the first hour following the power decrease?
(NOTE: CXe3 denstes xenon concentration.)
- a. Direct CXe3 decreases, indirect CXe3 decreases, total CXe3 decreases.
- b. Direct CXe3 decreases, indirect CXe3 increases, total CXe3 increases.
- c. Direct CXe3 increases, indirect CXe3 decreases, total CXe3 decreases.
- d. Direct CXe3 increases, indirect rie3 increases, total CXe3 increases.
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(***** CATEGORY 1 CONTINUED ON NEXT PAGE ess**)
QUESTION 1.08 (2.00)
- a. List the THREE contributors to total power coefficient. (1.50)
- b. How does total power coefficient vary (Becomes MORE NEGATVE or LESS NEGATIVE) as the core ages? (0.50)
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(***** CATEGORY 1 CONTINUED ON NEXT PAGE *e es)
i QUESTION 1.09 (1.50)
Indicate whether each of the following will make the moderator temperature coefficient (MTC)-LESS NEGATIVE, MORE NEGAT 1'/E, or have NO EFFECT.
- a. INCREASING moderator temperature.
- b. DECREASING boron concentration.
- c. INCREASING core age.
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( _ __. _ _ _ _ _ . _ _. . __
i
.,. QUESTION 1.10 (1.00) [
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If the UNIT 2 reactor were to operate ccntinuously at approximately 100%
power for the entire first fuel cycle, describe how the axial flux peak i
1 would move or behave over ccre life as follows: (
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- a. State why the axial flux peak is initially' located below the core
- centerline.
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- b. What causes the axial flux peak to move upward over core .
! life? !
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QUESTION 1.11 (2.00)
A Xe-free reactor startup is in progress with power leveled out at 10 - '
amps for critical data. Describe the effects, if any, on the parameters listed below if rod D4 (control bank D) drops to the bottom. Include in your description both the transient behavior and the final steady state condition. Initially Tave = 546 F and Primary Pressure = 2235 psig.
- a. Tave (0.50)
- b. Primary Pressure (0.50)
- c. Reactor Power (1.00) l l
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QUESTION 1.12 (1.00)
Multiple Choice l
During a reactor startup, you have just verified a constant positive startup rate on the Source Range Nuclear Instruments, without any rod motion or boron dilution. The ACTUAL condition of the core with this indication ist l a. Subcritical l
- b. Prompt Critical
- c. Critical
- d. Supercritical I
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QUESTION 1.13 (1.00)
Multiple Choice The reactor is critical at 10,000 cps when a Steam Generator PORV fails open. Assuming BOL conditions, no rod motion, and no reactor trip, choose the ONE answer below that best describes the values of Tavg and nuclear power for the resulting new steady state. (POAH = point of adding heat).
- a. Final Tavg greater than initial Tavg, Final power above POAH.
- b. Final Tavg greater than initial Tavg, Final power at PDAH.
- c. Final Tavg less than initial Tavg. Final power at POAH.
- d. Final Tavo less than initial Tavg. Final power above POAH.
(assse CATEGORY 1 CONTINUED ON NEAT PAGE 44444)
QUESTION 1.14 (2.00)
Given the following initial conditions:
Keff = .943 All rs;s in Boron 900 ppm Total rod worth of 7.5%
Shutcown bank worth of 4.11%
Source' range indication of 100 com Calculate the source range count rate after withdrawing the shutdown
! bank. Show all work. State any assumptions.
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(essee CATEGORY 1 CONTINUED ON NEXT PAGE 44444) i i
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l QUESTION 1.15 (1.00)
Multiple Choice In order to maintain a 150 degree F. subcooling margin in the RCS when reducing RCS pressure to 1600 psig., Ste:m Generator pressure must be reduced to approximately _____________.
- 4. 435 psig
- b. 445 psig
- c. 455 psig
- d. 465 psig i
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I QUESTION 1.16 (2.00) 1 Will the Departure from Nucleate Boiling Ratio (DNBR) INCREASE, DECREASE, or REMAIN THE SAME if the following plant parameters are measurably REDUCED.
during power operation? Consider each parameter separately.
- a. Reactor Coolant System (RCS) Pressure
- b. RCS Tavg Temperature
- c. Reactor Power
- d. RCS Flow l
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QUESTION 1.17 (1.00) i TRUE or FALSE 7 -
- a. One of the pump laws for centrifugal pumps states that the i volsmetric flow rate is proportional to tne speed of the pump.
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- b. Pump runout is the term used to describe the condition of a centrifugal pump running with no resistance to flow at the [
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QUESTION 1.10 (1.50)
- a. At normal hot standby condi+1ons, in which direction will the pressurizer level i n d i c a t i oni change as a result of the following transients? <!NCREASES. DECREASES. STAYS THE SAME).
Consider each transient separately. Assume the letdown and I charging flows are eQuallZed and the pressurizer level control ,
system i s in manual, j
- 1. The reference leg heats-up from 120 F to 200 F due to the I relocation of a ventilation duct. (0.50) (
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from normal operating temperature to 590 F. (0.50) {
f D. For case 2 above, following the cooldown. is the indicated level GREATER THAN, LESS THAN, or EQUAL TO equal the actual level?
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QUESTION 1.19 (1.50)
List the THREE major causes of Water Hammer.
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QUESTION 1.20 (1.00)
Mul tiple Choice Choose the ONE correct answer. The 2200 degrees F maximum peak cladding temperature limit is used because:
- a. a rircalloy-water reaction is accelerated at temperatures above 2200 degrees F.
- b. it is 500 degrees F below the fuel cladding melting point.
- c. any clad temperature higher than this correlates to a fuel center line temperature at the fuel's melting ooint.
- d. the cladding Decomes weaker, Decause of a ricconium phase change at temperatures above 2200 degrees F te.g., zirconium goes from a close packed hexagonal structure to one that is body-centered cubic).
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QUESTION 1.21 (1.00)
What are the TWO parameters that are controlled to reduce reactor vessel stress during heatup and cooldown?
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QUESTION 1.22 +ETMt Indicate whether the following will cause the power range instrument to be indicating HIGHER, LOWER, or the SAME AS actual power, if the instrument has bes.1 adjusted to 100% based on a calculated calorimetric. Consider each case separatel y.
- b. The reactor coolant pump heat input used in the calorimetric was omitted
- e. The-s t ea.e 21cx usse ia twe-cel sr; astr; c we3-1 ewer--then-actust-()tterco
- d. The f eedwater flow rate used in the calorimetric was lower than actual feedwater flow rate e'
(esses END OF CATEGORY 1 seaso)
23,,6b9dI,pgg!gy jygbyp}yg,gGEg]y,999,[ygRGgNCy Pcgo 24 515I50b i
i QUESTION 2.01 (1.00) .
During refueling operations the RHR pumps may lose flow with the reactor ,
vessel level visible above the bottom of the RCS piping nozzles, althougn !
that level is well above both the RHR pumps. ;
I Assuming that the valve lineup is correct and that the RHR pumps do NOT l lose power, explain how the RHR pumps can lose flow with reactor vessel ,
level visible at nearly a foot above the bottom of the RCS piping i noz:1es.
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QUESTION 2.02 (2.00)
List the DESIGN capacity (gals) or f l owe r.t o (gpm) and associated discharge pressure (psig) for each of the ECC5 water injection systems listed:
- 1. Centrifugal Charging Pumps
- 2. Safety Injection Pumps
- 3. Residual Heat Removal Pumps
- 4. Accumulators i
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w QUESTION 2.03 (1.25)
State the THREE sources of makeup water to the Spent Fuel Pool that use only installed equipment (that use NU portable equipment). Identtiy which one is "Normal Makeup" and which one is "Alternate Makeup."
( eeae CATEGORY 2 CONTINUED ON NEAT PAGE seoes>
_-__________-_-a
QUESTION 2.04 (1.00)
State the TWO reasons wny flow testr?ctors are installed in the AFW lines to each steam Generator.
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QUESTION (2.00)~
- a. State' the most probable cause of steam binding of' the AFW pumps.
(0.50)
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- b. State'THREE indications of the potential for steam binding. - The three indications'do NOT all have to be available in the control ,
room. (1.50) (
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. . t QUESTION 2.06 (l.OOL Multiple Choice Choose the ONE answer which best describes the reason that the anti-reverse rotation device is included on the reactor coulant pumps.
To prevent reverse rotation of an idle reactor coolant pump (i mpel l er, shaf t ,
and motor) which could lead tot i
- a. damage of the seal package.
- b. excessive core bypass flow. l
- c. thrust bearing degradation.
- d. excessive starting currents.
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QUESTION 2.07 (1.50) i Answer the fol1owing questions as applied to the #3 RCP seal.
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- a. 'What is the purpose of the #3 seal? (0.50)
- b. Describe the normal flow path through the #3 seal including what causes the pressure differential across the seal. (1.Q0) l tsss
- CATEGORY 2 CONTINUED ON NEAT PAGE *****)
QUESTION 2.08 (1.00s
- a. Explain the purpose of the check valve around the normal c h a r g i tig valve (HV-8146).
- b. Why is the check valve around the normal charging valve spr i ng-l oad ed ?
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(***** CATEGORY 2 CONTINUED ON NEAT PAGE **sse) 4
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l QUESTION 2.09 (0.75)
List the THREE loads cooled by the Component Cooling Water (CCW) system.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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. QUESTION' 2.10- . ( 13 25 )- ,
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List; FIVE components /spstems that-discharge to the Pressurizer Relief Tank.
o', IDENTICAL' PARALLEL COMPONENTS COUNT AS ONLY ONE SOURCE!
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QUESTION 2.11 (1.50)
- a. Explain the means of preesure control when the plant is being operated in 'a solid water condition. (1.00)
- b. List TWO components which provide overpressure protection when the plant is solid? IDENTICAL PARALLEL COMPONENTS. COUNT AS ONLY ONE OF TWO. (0.50)
(s.**** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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-QUESTION 2.12 (1.50)
- a. Give TWO reasons why NaOH is added to containment spray
water to control the pH. (1.00)
.b. How is the NaOH transferred from its storage tank to the containment spray stream? (0. 50) <
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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- )GUESTION-' 2.13 - (0. 50 f
,,, - Why 'i s the . posi tive .displ acement ' charging pump provided wi th a' low speed stop?
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1 QUESTION 2.14 (1.50)
List THREE major sources of hydrogen generation in containment during ,
I a LOCA.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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'5~ QUESTION 2.15 (1.25) a.- What is the purpose of the Unit 2 auxiliary containment cooler NSCW isolation valve interlock? (0.50) -
- b. Explain the sequence of operation for opening of both inlet and outlet NSCW isolation-valves on the Unit 2 aux 111ary containment [
cooler. (0.75) (
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QUESTION 2.16 (1.00)
State the locations where the TWO SAFETY GRADE Cold Shutdown Letdown Flowpaths discharge.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
i QUESTION 2.17 (1.00)
- a. Why do the Unit.1 RHR Temperature Control valves at the heat exchanger outlet (HV-6060 &607). stroke open only a limited amount?
- b. .What is different about Unit 2 that makes the stroke limit on the RHR Temperature Control valves unnecessary?
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[ . QUESTION 2.18 ~(2.00)
< T.S. 3.5.3.1, "ECCS:Subsytems," requires that one OPERABLE subsystem be available in MODE 4 with Tavg < 350 F. 11denti f y the FOUR minimum ,
conditions that must'be satisfied to have an OPERABLE ECCS subsystem. ,
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,T) Y QUESTION 2.19 (1.00)
The containment cooler fans have both a high and a low speed.
- a. Under what' condition is the low speed intended to be used?
- b. What 'i s the purpose (design intent) for ha'ving the-fan run in slow speed as opposed to high speed?
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QUESTION 2.20 (0.50)
State the TWO 480 vac power supplies to the Unit #1 rod control motor l a
generator sets. !
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QUESTION 2.21 (1.00)
State TWO design purposes of the Feedwater Isolation Valves.
(4 sea
- CATEGORY 2 CONTINUED ON NEXT PAGE *****)
QUESTION 2.22 (1.50)
- a. State the normal and alternate sources of water to the Auxiliary feed pumps. (0.50)
- b. What components must be operated to switch from normal source to alternate source in Unit 2 AND from where is the manual part of this operation normally performed? (1.00) a i
l (esses CATEGORY 2 CONTINUED ON NEXT PAGE 4444s)
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QUESTION 2.23 (1.50)
- a. The following sets of RCS penetrations'both extend into the coolant l loop flow path. State for each the reason why an extension is used.
- 1. Spray inlet connections.
, , 2. Sample taps. (1.00) ;
- b. St' ate the TWO sets of RCS instrumentation which have penetrations that extend into the coolant loop flow path? (0.50) t t
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i 4____________._____
QUESTION 2.24 (1.25)
State the FIVE functions that compressed air performs in the Emergency Diesel Generating system.
(aeaea CATEGORY 2 CONTINUED ON NEAT PAGE 4aeas)
)
-QUESTION 2.25 (1.00) i:
What are the TWO design purposes for warming the Eniergency Diesel Generator lube oil while in standby status?
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(44ses END GF CATEGORY 2 s4aas) r
E, s__IN@IByDENI@_@ND_CQNIBQ6S ' Pcgo 49 GUESTION 3.01 (0.75) s
- a. What is the purpose of the O to 1.5 F dead band in the' rod control unit? (0.50) ;
- b. The rods are stepping in due to a temperature deviation of 3.5 F, at j what level of . deviation will the rods stop moving? (0.25) l l
(sesas CATEGORY 3 CONTINUED ON NEXT PAGE ssess)
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CUESTION 3.02 (2.00)
- a. An urgent failure occurs in a power control cabinet causing a "Lock-Up" in that cabinet. State the level of current (FULL, t REDUCED or ZERO) supplied to each of the THREE groups of coils in 1 the cabins't. (1.50) ,
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- b. When the "ROD CONTROL URGENT FAILURE" annunciator sounds, how should .
it be determined if the failure'is in the Power Cabinet or the Logic ;
Cabinet? (0.50) ;
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GUESTION. 3.03 (1.00) t i
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- a. During a normal rod withdrawal, you notice that only every )
i other digital rod position light is illuminating for DNE of the I rods as it travels. Give one example of what might cause this ,
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indication?
b '. State the accuracy of the affect d rod's digital rod position indication system. (dither of the two possible accuracies ,
j constitutes a correct answer.) {
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QUESTION 3.04 (1.75)
- a. What in the upper limit of indication for the in-core thermocouples?
(0.25)
- b. Following an accident involving a large steam release in containment, millivolt readings are taken at the in-core o! splay panel AND at tne Remote Processing Unit. How is the temperatere of of the in-core thermocouple developed from these two millivolt readings. (1.50) l L
teeeae CATEGORY 3 CONTINUED ON NExT PAGE oaees) l 1
QUESTIGN 3.05 (0,50)
What is the function of the High Flux At Shutdown switch on the :$$
range drawer?
i (s.eeae CATEGORY 3 CONTINUED ~)N NEXT PAGE seees) ;
QUESTION 3.06 (1.00)
How do germissives P-6 and P-10 provide protection against damage to the Source Range Detector. Consider each permissive separately.
Setpoints are not desired.
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tsaes* CATEGOR( 3 CONTINUED ON NEXT PAGE sesa )
QUESTION 3.07 (1.00)
- a. State the purpose of the reactor trip breaker auto shunt trip coil.
- b. Which reacter trip breakers are operated by the auto shunt trip coils?
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ted*ea CaTEGOftv 3 CONTINUED ON NEXT PAGE 8e4*e)
QUESTION 3.08 (1.50)
- a. State FOUR conditions that will cause a General Warning signal.
- b. State the consequences of receiving a Genera. Warning signal from both trains simultaneously.
1.
(ssses CATEGORY 3 CONTINUED ON NEXT PAGE sasse)
Y QUESTION 3.09 (2.25)
State the names and coincidences and y,etpoints of all the reactor trips,
.nterlocks (Cs) and permissives (Ps) associated with the Intermediate Range Nuclear Instrument.
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, QUESTION 3.10 (1.50) f r
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- c. Ee:1O!r t he aruran i r-^ue d i f f er.._a ence between--the _..m,_,.___ m.__
r espe"_-- + n rm_ . lat
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- /. CAMS and, g pg
- - - - - - - - - - ---- ---- .i._ i. .m. _
w u ry,p __ g, y, ,7 p m-a_1 .._1..__
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- O= N bI '4"00 kM *#, C^".3[S_%hMftg g.M ggq Q Qgg fhe (allon,%) co s < t r o ; y tre en p;p o [ 7 j, e f L t* 2 r-EO.n cony owl S Ten m du, yo sy si een .
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(***** CATEGORY 3 CONTINUED ON NEXT PAGE 44448) s_.
QUESTION 3.11 (1.25)
- a. List the THREE arming signals for the steam dump control system.
(0.75)
- b. What ONE additional signal must be present to energize the arming solenoid? (0.25)
- c. What interlock must be satisfied in conjunction with the arming signals to allow control of ALL steam dump valves? (0.25)
(stess CATEGORY 3 CONTINUED ON NEXT PAGE stess)
QUESTION 3.12 (1.00)
How is a reactor trip on tu*bine trip prevented from occurring even when four-cut-of-four turbii.e throttle valves are shut? Include INSTRUMENT, SETPOINT and COINCIDENCE in you answer.
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QUESTION 3.13 (1.00)
State the FOUR signals that will automatically start the standby i CCW pump.
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QUESTION 3.14 (1.50) l l
List the THREE categories of Liquid Radi& tion Monitors AND give the name of DNE monitor in each category. 1 j
(***ss CATEGORY 3 CONTINUED ON NEXT PAGE *****)
' QUESTION 3.15 (2.00)
List TWO pressurizer level conditions (INCLUDING setpoints) under which the pressurizer level control system actuates the pressurizer heater control system AND explain why each level / heater interlock is installed.
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QUESTION 3.16 (2.00)
- a. List FOUR unique control, protective, or permissive circuits which use individual loop Tavg signals and NOT auctioneered high or low Tavg.
- b. Excluding the main control board wide-range temperature indicator s, list FOUR other SYSTEMS that use RCS loop wide-range temperature signals.
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l QUESTION 3.17 (2.25)
With level in the Volume Control Tank (VCT) at 40% and reactor makeup water control in automatic, VCT level detector LT-112 fails HIGH, Assume reactor is operating at 100 percent power.
i
- a. List THREE automatic control functions which are either initiated OR prevented as a result of LT-112 failing high. (0.75)
- b. If NO operator action is taken f or this failure, the reactor will trip. Explain why the trip will occur by listing, in SEQUENTIAL order, FIVE major CVCS or RCS events that will occur leading up to the trip. (1.50) 484884 CATEGORY 3 CONTINUED CN NEXT PAGE eesse)
f QUESTION 3.18 (0.75)
List the THREE inputs used to control the feedwater BVPASS valve.
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QUESTION 3.19 (1.00)
List the FOUR automatic start signals for the Motor Driven Auxiliary Feedwater Pumps. Setpoints NOT required.
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QUESTION 3.20 (1.00)
An undervoltage condition occurs such that the normal incoming breaker from offsite power to the 4160VAC bus trips open. The Diesel Generator (DG) starts as it should, but the DG output breaker fails to shut.
Shortly thereafter. offsite power is determined to be available again.
What is the primary difference in the unit i and 2 procedures for reclosing the normal incoming breaker?
(ssses CATEGORY 3 CONTINUED ON NEXT PAGE sesso)
QUESTION 3.21 (1.50) DCLdTGD A nuclear service cooling water tower f dios on high vibration.
- a. State TWO locations from ch the trip can be reset.
- b. Which unit do 54 trip apply to?
- c. Wh revents a vibration trip from occurring on every fan start?
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QUESTION 3.22 (2.25)
List the THREE signals that cause automatic safety injection. Also list the setpoints and coincidence associated with the signals.
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ft__E6995QU6gg_;_NQ6[@6t_@@NQ60@62_EdESGENQY Pcgo 71 ONQ_6@Qlg6QQ1Q@6,QQN1696 i
QUESTION 4.01 (1.00)
Under what conditions could an individual with a valid RO license be designated to assume the Control Room command function?
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QUESTION 4.02 (1.00)
State the color and shape of the valve / instrument label plates for each plant.
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F QUESTION 4.03 (1.50)
_ ogsgrep In accordance with t he St ariek419-OrdWM , state SIX operations procedures th = t :y-tTW-'Fer f ormed without having the procedures in hand.
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QUESTION 4.04 -(1.50)
What THREE classes or group of personnel are not required to get permission to enter the "At-The-Controls" area of the control room?
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QUESTION 4.05 (1.00)
In accordance with 10001-C. "Logkeeping," state FOUR events that are required to be entered in the UNIT CONTROL LOG.
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l.60 QUESTION 4.06 42.00' State the FOUR VEGP administrative limits for external exposure to a radiation worker. Assume no increases have been authorized. Include in your answer the numerical limit and the effected portion of the body.
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j QUESTION 4.07 (0.50)
TRUE or FALSE 7 While sur'veying yourself upon exit from a cJntami.'At 19' rea, you find that you exceed the limit of 100 cpm greatse than .. c.< ground on the skin of your elbow. You should attempt tc t'econtaminate your elbow with a luke-warm wet wipe and then survey it % gain. If the result of the second survey (after decontamination uttemp*.) is still greater than 100 com above background, then Health Physic.% should be notified.
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l QUESTION 4.09 (1.00)
Match the power levels in Column D to the procedural actions of Column A. Assume that Column A actions are performed in accordance with UOP 12004-1, "Power Operations." Each Column A action has only one Column B response. Column a responses may be used more than once.
COLUMN A COLUMN B
- u. Roll main turbine to operating speed. 2. 4 */.
- c. Place steam dumps in Tavg mode. 3. 10 to 12%
- d. Transfer the station electrical loads 4. 12 to 15%
to UATs.
- 5. 20 to 25%
- 6. 30%
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QUESTION 4.10 (0.50)
The precautions section of Reactor Coolant Pump Operation pr ocedure 13003-1 states that a RCP should NOT be started if the pump but is being supplied from the same Reserve Auxiliary Transformer through which a diesel generator is paralleled to the system. What is the reason f or thi s precaution?
l tsses* CATEGORY 4 CONTINUED ON NEAT PAGE se*e8)
QUESTION 4.11 (1.00)
In accordance with the limitations section of 13003-1, "Reactor Coolant Pump Operation." state FOUR of the seven criteria that necessitate the stopping of a RCP.
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OUESTION 4.12 (1.50)
Step 2 of AOP 18012-1, "Turbine Runback / Setback," requires the !
operator to "Verify that a runback has initiated". According to the rest of this step, state the THREE items that must be checked AND wtate their expected condition. e l
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- QllES T 10t) 4.13 t1.25)
State the immediate actic is for AOP 10005-1. "Partial Loss of Flow."
Include in your answer all actions, verifications and expected values, u RNO actions are NOT dosi< Lei.
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E E _ -- __ - - - - _ - - --
QUESTION 4.14 (1.25)
State tne IMMEDIATE response, i.e. action or verification, to each of the following instrumentation abnormalities. Include condition of item (s) checked if applicable. The actions in the response not obtained column are NOT desired.
- a. Failure of reactor coolant loop narrow range temperature instrumentation (0.50)
- b. Failure of pressurizer pressure instrumentation (0.75)
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QUESTION 4.15 (1.00)
The immediat's action of ADP 18031-1,~"Loss of. Class 1E Electrical Systems",'is to' trip the affacted. train Diesel Generator.
'I
- a. How is the affected train Diesel Generator ~ tripped?
- b. 'Why.must the'affected train Diesel Generator be tripped?
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h-t- o GUESTION 4.16 (2.00) ,,
- a. Which DNE of the'following' symptoms would require.the Reactor Operator to initiate a manual reactor trip AND a manual safety.
injection ifcneither had occurred automatically?.
, 1. A General Warning alarm on Train B of the Solid State Protection {
System
- 2. Power = 30%, loss of flow in one loop l 3.- Power = 48%, pressurizer level 9 3*/.
i
- 4. Pressurizer pressare = 1850 psig i
- 5. Containment pressurn = 2.6 psig
- b. Which ONE of the above symptoms would require the Reactor Operator to initiate ONLY a manual reactor scram if neither reactor scram or a safety injection had automatically occurred? .,
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l QUERTION 4.17 '(2.00)
During a loss of"all AC powse, Procedure ECA-0.0 has the operator i cooldown and depressurize the RCS using steam generator Atmospheric Relief Valves (ARV). l l
.a. ;Why must the RCS be depressurized?
- b. Why shouldn't the Steam Generator be depressurized below 165 psig?
- c. With RCS pressure at 750 psig and decreasing during the depress.wization, how should the operator resoond if pressurizer level is lost (SECURE DEPRESSURIZATION or CONTINUE DEPRESSURIZATION)? l
- d. What plant conditions MUST be established before Procedure ECA-0.0 can be exited?
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QUESTION 4.18 (1.50)
List THREE conditions, including setpoints, that constitute "adverse containment".
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1 -d QUESTION 4.19 ~ ( 1. 00)~
. . , , 1v
., W hat are the FOUR methods for tripping the reactor.outside of the control: room.according to AOP 18038-1, Operation From Remote Shutdown Panels?" '
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(**ss* CATEGORY 4 CONTINUED ON NEXT l' AGE e**ss) l I
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-- - - _ , . . . _ . , . , , , . . , ~ ~ - , . , - . - _ . - - . - _ . . , . . . _ _ _ , . . . _._, ,- =,,.,-m-
. - . , ,-. - -- - -. - - - - - r-- - . ,
p 4 I
. QUESTION 4.20 (2.50) .
s a. State the-conditions of EOP 19231, "FR-H.1, Response to Loss of Secondary Heat Sink,". which require immediate initiation of primary fwed and bleed. ( 2.00)
- b. Why are,the RCPs tripped if either'of the'above conditions exist?
(0.50)
(**ss* CATEGORY 4 CONTINUED ON NEXT FAGE **sas)
{
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f.-
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~
QUESTION 4.21 ~(1.50)
The. foldout page for EOP 1900-C, "E-O Reactor Trip or Safety Injection,"
lists TWO conditions, either.of which require the operator to Actuate SI. What are these'TWO conditions?- Include applicable normal '
setpoints. Adverse-containment setpoints are NOT required.
~
s l
t I
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I i
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(*s*** CATEGORY 4 CONT INUED ON NEX T P A'iE * * * * * )
{
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s L
QUESTION 4.22 (3.00) l 'The following questions apply to the immediate action steps of EOP 19000-C, "E-O Reactor Trip or Safety Injections" >
- a. State all the valve groups that are verified shut to confirm ';
feedwater i sol ati on . ;
- b. Containment spray is required (containment pressure is 23 psig)'but was not automatically initiated. How does the operator verify proper operation after manually initiating spray?
c.; ESFAS was not, properly actuated, state what pumps must therefore be verified as running.
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i r
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(es**s CATEGORY 4 CONTINUED ON NEXT PAGE ssssa) f, t
u - - -
fr e t ObESTION 4.23 (1.50)
Step'4 of the immediate actions'for EOP 19100-C, "ECA-0.0 Loss of 411 AC ,
Power," has the operator verify AFW flow greater than 570 gpm. 14 the flow is less than 570 gpm, what operator actions are required as stated ,
in the RNO column? Include in your,. answetr all items to be !
ensured / checked and the expected conditions. <
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' (***** END OF CATEGORY 4 *****)
(********** END OF EXAMINATION **********) {
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1
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~ - - - - - - - - - - - - - - - - - - - - -
{ T - -- ,
L11. 2i"61991EhES_9E_NUg(g@@,bghgg,[(@NT_Q[gg@llgN t Pcgo 94' I
i TH[Rh0 DYNAMICS 2 HEAT TRANGFER AND FLUID FLOW a
Y 1 1 j
' ANSWER 1.01 (1.00)
- a. FALSE
- b. TRUE REFERENCE VOGTLE LO-LP-33230-01, Objs. 13 & 14. '
2.4/2.5 192OO1K102 ..(KA's)
I so e ANSWER 1.02 (7/60)
- a. DECREASE -
- b. NO CHANGE p et ere o
- c. I REASE
- d. DECREASE REFERENCE VOGTLE LO-LP-33510 Objs. 1, 5 & 6.
3.2/3.4 3.5/3.7, 3.8/3.9 192OO2K114 192OO2K113 192OO2K110 ..(KA's) l 1
ANSWER 1.03 (1.00)
- a. TRUE l
l b. TRUE i
1
)
to**** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
t .
1 PRINgIPLES'OF NUCLEAR POWER PLANT OPERATION g Pcgo 95
-IME BDQQy N@d1C S z _ dE 91_I69N S E E B,',@NQ_ E 6 pi p_ E(QW r
REFERENCE VOGTLE LO-LP-33440-01, Objs.,'6 & 7.
3.8/3.8 5 192OO7K104 ..(KA's)
ANSWER 1.04 (1.00) i d.
REFERENCE VOGTLE LO-LP-33230-01, Obj. 9.
3.0/3.0 I'
192OO3K107 ..(KA's)
ANSWER 1.05 (1.00) b.
REFERENCE VOGTLE LO-LP-33230-01. Objs. 9& 12.
3.2/3.3 192OO3K106 ..(KA's)
ANSWER 1.06 (2.00)
- a. INCREASES (0.50)
- b. Because the concentration of iodine (the Menon precursor) is decreasing. (1.00)
- c. LESS THAN (0.50)
(s**** CATFGORY 1 CONTINUED ON NEXT PAGE *****)
1:__EBjNgighEp_gF_Nyg(E@g_ggWEg_P(@NI_gPE6@llgNt 'Pcga 9a IbE6DggyN8DICgz_bE9I_I68NSEEB_8ND_E(y]Q_E69W REFERENCE VOGTLE LO-LP-33430-02, Obj. 17.
3.3/3.4 192OO6K108 ..(KA's)
ANSWER 1.07 (1.00) b.
REFERENCE VOGTLE LO-LP-33430-02, Obj. 8.
3.4/3.4 192OO6K106 ..(KA's)
ANSWER 1.08 (2.00)
- a. Any three of the following at O.50 point each.
- 1. Dopplar power 'or fuel temperature) coefficient
- 2. Moderator temperature coefficient
- 3. Void coefficient
- 4. Pressure coefficient (0.75)
- b. Decomes more negative. (0.50)
REFERENCE VOGTLE LO-LP-33420-02. Objs. 14 & 15.
3.1/3.1 192OO4K108 ..(KA's)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
__ ( . ,. .
w m ,,
7.- 1. PRINQIPLEN'OF' NUCLEAR POWER PLANT'DPERNTION g Pcgi 97 g+i.
THERMODYNAMICSg__HESI_IR9N_EER_SNQ_ELUIp_ELQW s s
. !!' 'v; '
1 k ~ ANSWER ^ .1.10 9 . (1.50) t
' a '. MORE. NEGATIVE;
, :; r , L ' '
- J'"
, 4 b.iMORE' NEGATIVE.
l
, 2
- c. MORE NEGATIVE.
V' i .e REFERENCE VOGTLE LO-LP-334'20-02, Objs. 6, 8.& 9. '
3.1/3.1 1
- I
~
192OO4K106 ..(KA's) t
. ANSWER 1.10 (1.00)
- a. The lower core inlet-temperature CO.253 in combination wi th the negative MTC CO.253 result in more power being generated in the bottom half of the core, r
- b. Fuel depletion in lower regions of'the core.
i REFERENCE ,
VOGTLE LO-LP-33520-01, Obj. 3. .
2.9/3.1 l
192OO5K112 ..(KA's) !
ANSWER 1.11 (2.00) [
i
- a. Temperature is unaffected by the dropped rod. (0.50) l t
- b. Pressure is unaffected by the dropped rod. (0.50) l t
- c. The reactor power will initially drop promptly (0.253 and then slowly f decrease CO.253 to a new steady state level as supported by [
suberitical multiplication CO.503. t f
l t
t
(***** CATEGORY 1 CONTINUED ON NEXT PAGE ***ss) ;
i i
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w--
1 5 d
1,' PRINCIPLES'DF-NUCLEAR POWER PLANT OPERATION t 'Pcgo 98 ISEBUQQYUed1GEt_SEeI_IBONSEE6_@NQ,E(ylQ,E(QW ,
I
' REFERENCE VOGTLE.LO-LP-33230-01, Obj. 20.
VOGTLE LO-LP-33420-02, Sec. E.3, p. 8.
l 3 . 5 / 3 .' 6 , 3.5/3.6 192OOOK112 192OO5K103 ..(KA's) .
ANSWER 1.12 (1.00)
- d. l REFERENCE VOGTLE LO-LP-33210-02, Obj. 4.
3.8/3.8 192OOOK111 ..(KA's)
ANSWER 1.13 (1.00) d.
I REFERENCE l VOGTLE.LO-LP-33530-OO, Obj. 2.
4 3.6/3.8 ,
6 i
i 192OOOK121 ..(KA's) i i
i I
t I
, I i
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
i i
b I
i I
1 I
- 1. PRINCIPLES ^OF NUCLEAR POWER PLANT' OPERATION t Pcgo 99 ,
IBEBdQQyN@dlC@t_bE91_IB9N@EEB_9NQ,E691p_E(gW ANSWER 1.14 (2.00)-
Present reactivity = (k -
1)/k = (0.943 - 1)/.0943 = .060 CO.50J-Reactivity after withdrawal of shutdown bank = .060 + .0411 = .019 CO.503 Keff after withdrawal = 1/(1 - p) = 1/(1 + .019) = ' . 9811 CO.503 Count rate after withdrawal = CR (1 -k )/(1 - k ) =
1 1 2 100 (1 -
.943)/(1 .981) .= 300 CO.50]
REFERENCE VOGTLE LO-LP-33310-01, Obj. 7.
3.9/4.0 3
192OOBK103 ..(KA's) j ANSWER 1.15 (1.00)
.,1 REFERENCE i
- j. VOGTLE LO-LP-34110-OL. Obj. 14.
3.3/3.4 3.1/3.2
- 193OO3K117 193OO3K125 ..(KA's)
I ANSWER 1.16 (2.00)
I
- a. DECREASE
- b. INCREASE
- c. INCREASE i
. d. DECREASE t
I (es*** CATEGORY 1 CONTINUED ON NEXT PAGE ess**)
11__EBINQlP(Eg_gF_Ngg(E@@_EgWEg_P(@N]_gfgg@IlgNt Pcgo100 IUEBd99yb60195 1 _UgeI_IgeNSEE6_9N9_ELy19_EL9W REFERENCE VOGTLE LO-LP-34510-OO, Obj. 1.
3.4/3.6 193OOOK105 ..(KA's)
ANSWER 1.17 (1.00)
- a. True
- b. True RGFERENCE i
VOGTLE LO-LP-34410 OO-C. Obj. B.
2.5/2.7. 2.3/2.4 15'1004K 105 191004K112 ..(KA's)
ANSWER 1.18 (1.50) a.
- 1. INCREASES
- 2. STAYS THE SAME (1.00)
- b. GREATER THAN (0.50)
REFERENCE VOGTLE LO-LP-16302-02-C. Obj. 6.
2.6/2.6 193OO1K103 ..(KA's)
(esses CATEGORY 1 CONTINUED ON NEXT PAGE ss***)
, 1:__EBINcIE6gs_gE_syCLE96_EgME6_E69NI_ GEE 68IIQNg Pcgo101-
- 10EBD991N8dlC@i_ME@I_I69NSEEB_8ND_E691D_E69W ANSWER 1.19 (1.50)
- 1. _ Valve operations.
- 2. Pump operations.
- 3. Steam / water interface.
OR - En ,pte s of ea ch cw>e .
REFERENCE VOGTLE LO-LP-34410-OO-C. Obj. 11. .
3.4/3.6 1
193OO6K104 ..(KA's)
I s
ANSWER 1.20 (1.00) i REFERENCE T
VOGTLE LO-LP-34510-OO, Sec. 3.a, p. 6.
3.1/3.5 l
193OO9K105 ..(KA's) i i
ANSWER 1.21 (1.00) l 1. Temperature (or cooldown rate).
l '
- 2. Pressure.
REFERENCE VOGTLE LO-LP-35205-01, p. 8 Obj. 1.
3.3/3.7 193OO9K105 ..(KA's)
L i
I' (esses CATEGORY 1 CONTINUED ON NEXT PAGE ***ss) 0 t
- 1. PRINCIPLEO OF NUCLEAR POWER PLANT OPERATION t Pcgo102
. IME8DppyN@dlCSg_b[@l_18@NCEE8_@Np_E6Ulp_E6pW
+
k
- l50'
- _ ANSWER 1.22 -4EM
.a. LOWER
- b. HIGHER s
. LOuca DE##
- d. . LOWER s
REFERENCE VOGTLE LO-LP-34310-00 Obj. 4.
3.1/J.4 193007K108 ..(KA's)
(sesse END OF CATEGORY 1 4444s)
~, ,
q 2t__PseNI_Q[Sl@N_JNC6UDINg_S@ Eely _@NQ_EDEB@[NCY Pcga103 '
SySIEDS
)Yleg 1 ,
t
'- 2.01 ANC.WER '(1.00) e Vortexing.(OR air entrapment) at the RHR suctions CO.503 causes air !
binding (OR loss of suction) in the RHR pumps CO.503. ,
REFERENCE r
VOGTLE LO-LP-12101-07-C, Obj. G2.
- 3. 6/ 3. 9,' 2.2/2.5 t
s OO5000K40'9 'OO5000K109 ..(KA's)
ANSWER 2.02 (2.00)
(Tolerances +/- 50 gpm, +/- 50 poig) l- 1. CCP: 300 gpm (150 cach) @ 2500 psig i- 1150
- 2. 51 Pumps
- 850 gpm (425 each) @ 4 7"O= psi g
- 3. RHR Pumps: 6000 gum (3000 each) @ 160 psig
- j. 4. Accumulators: 26,000 - 27,500 gals (approx. 6600 to 6850 each) l @ 650 psig 1
(0.25 ca. gal /gpm3 0.25 ea. psig)
I j REFERENCE
! VOGTLE LO-LP-13101-03, Obj. 6.
l VOGYLE LO-LP-13201-02, Obj. 5.
VOGTLE LO-LP-13301-01-C. Obj. 8.
l VOGTLE LO-LP-13301-02-C.
2.8/3.1, 3.0/3.2 l
1,
! OO6020K603 OO6020K601 ..(KA's) i l
1 i
(esess CATEGORY 2 CONTINUED ON NEXT PAGE sosse)
\
l i
L-
- 2. ' PLANT DESIGN INCLUDING SAFETY AND riMERGENCY Pcgo104 )
EXHIEt!E
/
l ANSWER 2.03 (1.25)
Aircen e r e Reactor Makeup Water Storage Tank CO.253 .t-mel Makeup CO.253.
MormaI Domineralized Water CO.253 ^1t rmste Makeup CO.253.
, Refueling Water Storage Tank CO.253.
REFERENCE VOGTLE LO-LP-25102-02-C, Obj. 9.
2.7/2.8, 2.4/2.5 a
, 033OOOK107 033OOOK105 ..(KA's) s ANSWER 2.04 (1.00)
- 1. To ensure that adequate flow will be available to the intact steam generators CO.503 (in the event of a feed line break).
- 2. To ensure that the AFWS will not contribute to pressurizing the containment CO.503 (in the ever t of a steam line break).
OR - To luir Arv f/~ ro a depres s we o ed S 6.
REFERENCE 1
VOGTLE LO-LP-20101-07-C, p. 11 Obj. 3.
3.6/3.7 061000 GOO 7 ..(KA's) 4 l ANSWER 2.05 (2.00)
)
! a. Leakage of hot main feudwater (back through check valves) into the AFW system (with the water then flashing to steam). (0.50) f ny r l,r er rC% w' r t* *1 < k :
/d d*,(* f MI
- b. 1. T,emp <> f r kigee,.a n ,,- er, a. t ur
- e (v-s,ilveul.sh,,<i.n t h e,, A. W d i sc h a r g e p i p i n g
..,n . . .
- 2. Pressure increase in the AFW discharge piping.
i 3. Vapor escaping through vent or drain lines. (1.50)
NIS p , fN p r.,f steers hwr $s lls Tu de*elof adep *re 'JL ( " M *-
G, 7 r ,, tr. r e e o s c <6 et i1 T ke I' $
A f W ! * $ ! N * ') C frif 4) As]"ho'tetfl fy re v e h iny rhe f ife .
l (4:41s CATEGCitY 2 CONTINUED ON NEXT PAGE *****)
j
4 4 . ..r f ,
) ~. It__Ek6dI_EEE14.ilNC(yglNg_gggTY ANQ< EMERGENCY Pogo105 EY.EIEt!E ,
m r s
REFERENCE !
VOGTLE LO-LP-20101-07-C,.p.f56,-ObJ. 19.
3.4/3.7,.2.7/3.0
. l 061000A206 061000K102 ..(KA's) ,
ANSWER 2.06 (1.00)- '
- d. I REFERENCE .'
VDGTLE LO-LP-16401-01, Obj. If.
3.2/3.3, 2.3/2.7, 2.1/2.4 OO3OOOK608 .OO3OOOK405 OO3OOOGOO7 ..(KA's)
ANSWER 2.07 (1.50)
- a. Prevents leaktge of liquids and gases CO.253 from the RCS to the Containment CO.253.
' 1:w; frc
- b. Wtr th; s tedp-fpe-s ide-to-t he-# 2%ee l-s i d e C O. 501.-.-.-The .
y etebFe-heed-e+-the-stendpk;;; i : - hiathee-than-thesour-e-estmen-the 42-and #3-seale-&Or40 h REFERENCE VOGTLE LO-LP-16401-01, p. . Obj. 3f, 3g, 4c.
3.2/3.3, 3.2/3.4, 2.7/3.1, 2.8/2.8 OO3OOOA109 OO3OOOK602 OO3OOOK407 003000G007 ..(KA's) e, f the ".3 $**l T N ' ' ' l Q , ,c ,- ( tv ., f e sa., t h e. 4 t =' *' <lf
- f a . sis le f * ' 7~
jn rw a dhe e rlo,, Con J '
A. T- rh<- 3 se~l le~L f f Coi' '-~ M <<r s-o t ) L'o ' c ],
q, To ike "2 so I lesloM (oM Rc 0 1 ) [ o.2 Q Sr < r; e hesd d t ,e 1 s ra ,aly ij e.
Is h) fre e r 8, a a, r t, ., ,e, w, e rhe i n 'rhe. 140 la* e k o O (h - p<rh.s Ec a c].
(asste CATEGORY 2 CONT 1N'JED ON NEXT PAGE seass)
L _
- 2. ' PLANT DESIGN INCLUDING SAFETY AND EMERGENCY Pcgo10$
EYSIEME ANSWER 2.08 (1.00)
- a. Prevents overpressurization of isolated charging lines (due to thermal expansion in the regenerative heat exchanger).
- b. (The spring provides sufficient back pressure on the check valve) so that auxiliary spray will flow into the pressurizer (and not through the check valve into loop 1).
or To allow for proper operation of auxiliary spray.
REFERENCE VOGTLE LO-LP-09201-03, Obj 3f.
3.4/3.4, 2.4/2.5 004000K603 OO4000K117 ..(KA's)
ANSWER 2.09 (0.75)
SFP HX RHR HX RHR pump seal cooler REFERENCE VOGTLE LO-LP-10101-02. Obj. 2b.
L 3.3/3.4 000000K10*4 ..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE ess**)
2 1__PL9NI_DE@l@N_INCLyplNg_g8EEIy_8Np_EDE69ENCX Pcg]107 EXEIEdp ANSWER 2.10 (1.25)
Any five of'the followings
- a. PZR PORV'S (2)
- b. PZR Safety Valves (3)
- c. Reactor vessel head vent
- d. RHR suction reliefs (2)
- e. CVCS letdown relief
- g. Di s-harge from RCDT heat exchanger
- h. Discharge from RMWST pumps REFERENCE VOGTLE LO-LP-16301-04-C. Obj. 2a.
3.0/3.2 OO7000K103 ..(KA's)
ANSWER 2.11 (1.50)
- a. Solid pressure control is maintained throu;" the use of the RHR/CVCS letdown crossconnectto.503 and the CVCS letdown pressure control valve (PV-131).CO.50]
- b. RHR suction relief valves.
Pressurizer Power Operated Relief Valves (PORV's). (0.50)
REFERENCE VOGTLE LO-LP-16501-02-C, Obj. 2.
3.2/3.5. 2.2/2.4, 2.9/3.1.
005000K104 OO5000K102 OO5000K402 ..(KA's) ;
(sessa CATEGORY 2 CONTINUED ON NEXT PAGE sesse)
2 t._Eh@dl_EEE1Ed_1dEhEEldE E@EE11_@yg_[dERGENCy Pego108' SYSIEMS J i l
ANSWER 2.12 (1.50) ,
i i a. Any two of the following at 0.50 each l .
- 1. Ensures the .> . . '. . n . a d r e .o v a l of iodine by-sprayed fluid. ;
l
- 2. Retains the iodine in solution. {
f
- 3. Minimizes post-LOCA corrosion. [
t
- b. NaOH is added to the spray flow with a j et eductor pump. (0.50) !
! , REFERENCE
- VOGTLE LO-LP-15101-OO, pp. 7L 10, Obj. 9. 4 i 3.1/3.6 2.8/3.2 i i
- 4. ;
O26020K401 026000K402 ..(KA's) l f
4 ,
r i ANSWER 2.13 (0.50) ,
i To prevent the flowrate from falling below the minimum required for RCP I
- seals.
t
[
] REFERENCE j VOGTLE LO-LP-09201-03, Obj. 7. !
i 3/1/3.5 J
! OO4020K607 ..(KA's) i a i i i ANSWER 2.14 (1.50) fi ,
,, Any three of the following at 0.50 each: !
l r a
j 1. 2tec-water reaction. [
- 2. Radiolysis of core and sump solutions.
l j
- 3. Corrosion of metals and paints in containment. f g !
j 4. Hydrogen release from reactor cool ant and pretsurizer vapor space. i 4
I
'i (sette CATEGORY 2 CONTINUED ON NEXY PAGE essee) !
I r
9
[
- 2. PLANT DESIGN INCLUDING SAFETY +3ND EMERGENCY Pcgo109 SYSIEMj REFERENCE VOGTLE.LO-LP-29150-OO, Obj. 2.
2.9/3.6 02OOOOK503 ..(KA's)
ANSWER 2.15 (1.25)
- a. To reduce waterhammer. (0.50)
- b. 1. The outlet opens partially (strokes for three seconds).
- 2. After a (60 second) wait the outlet valve finishes opening. p
- 3. The inlet valve then opens. (0.75)
REFERENCE VOGTLE RQ-LP-60301-OO-C, p. 7, Obj. 3.
2.9/3.4 076000K403 ..(KA's) a ANSWER 2.16 (1.00)
- 1. PRT.
S y>re m
- 2. Ex c eas Let down Heat-Ewchanger-44 owpath-4ORwostreamaf-the-
- e*een; i e toewn-hee t-ew changer 4.
REFERENCE VEGP Training Text, CVCS, Chapter 5.4, p. O 3.6/3.4 t
Ov4010A307 ..(KA's)
(sasse CATEGORY 2 CONTINUED ON NEXT PAGE sess*)
+32___eseN1_PEOl@N_lygLuglN@,Shggly,@ND_[DgRQgNCy Pcgo110
~
~~
. f!EIEUE .
ANSWER 2.17 (1.00) t,
- a. To prevent pump runout.
- b. Unit 2 has properly sized flow orifices downstream of the RHR pumps.-
REFERENCE
- t VOGTL E RQ-l.P-60301-OO-C, p. 13, Obj. 3.
3.8/4.2 006020K404 ..(KA's)
ANSWER 2.18 (2.00)
- 2. One operable RilR heat exchanger CO.503.
REFERENCE VOGTLE LO-LP-13001-03-C, Obj. 8.
3.5/4.2 006000 GOO 5 ..(KA's)
ANSWER 2.19 (1.00)
- 4. During a Safety Injection.
OR When there is high density / moisture air in the containment.
- b. To' protect the fan motor (f rom overload) .
(esses CATEGORY 2 CONTINUED ON NEXT PAGE sosts) k_ -
. _ . ~. -, , . ._
. a' 'li__?6 ANT DESl@d_1NCLyplN@,39EgIy_9NQ,gdgR@gNCY ,Pdgo111 y
..- c SySIggg ;
4 i
i REFEREfi:E '
9 VD3TLE LO-LP-2913d-01, Obj 1. [
' 3.1/3.4'
- v 022000K402 ..(KA's)' ,
C ,
ANSWER 2.20 '(0.50)
[' 1. (400 vac) 1NBOB i-ci 2. (400 vac) 1NBO9 l REFERENCE o- l 4 VOGTLE LO-LP-27101-06-C, Obj. 4. , ,
3.5/3.6 I l
001000K2Vi ..(KA's) !
I -
3, .
- ANSWER 2.21 (1.00) l 1. To prevent uncontrolled blowdown f rom more than one Steam Generater (in the event of a feedwater ripe rupturo).
1 i 2. To limit cooldown (and to protect the turbine).
I.
REFERENCE 4- VOGTLE LO-LP 1410',-04, Ob;. 2.
i 3.1/3.2 1
Y \
l Of.9000G007 ..(KA's) e r
(..... cA1 ee . 2 ceN11 Nee,eN Ne , eAee .....,
)
g ,-
1
Pcgo112
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY
.fYgIEME l ~
'.o
' ANSWER 2.22 (1.50)
- a. 1. Normal source - Condensate Storage Tank 1.
3 2. Alternate source - Condensate Storage Tank 2. (0.50)
- b. The three isolation valves f rom the alterstate supply are opened CO.503 from the control room (0.503.
. REFERENCE YOGTLE LO-LP-20101-07-C, Obj. 11.
3.6/3.0, 3.9/4.2 061000K401 061000K107 ..(KA's)
. ANSWER 2.23 (1.50)
- a. 1. In order to use velocity head of coolant for a driving force.
- 2. In order to obtain more representative samples. (1.00)
L. 1. Narrow range temperature indication system.
OR !
Hot leg RTD loop bypass connections. !
- 2. Wide range temperature indication system. g f
l or ;
RTD detector wells, 40.50)
REFERENCE l
- VOGTLE LO-LP-16001-02. p. 29.
4.1/4.1, 3.4/3.4 l 1 1 016000K101 OO2OOOK109 ..(KA's) i i
l l
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) J 4
.-, - , , _ ~ _ . .
_ , , _ . , - - . . . - - - - . _ , - , . , - - _ . . . , ~ . , , - _ , . , , _ _ _ , - - , _ . _ . , __ m.- -,_ _ _ . . , - _ , - . . - -
o Is .tbeNI_REE19N_INGkWR1W9_fe6E'IY_eNk Ed{R@{Ugy Pcgo113 RYRIEUE ;
7 .-
1
- j ANSWER- 2.24 ( 1'. 25 )
- 1. Starts the' diesels.
f
- 2. Rolls the diesels without starting them.
- 3. Operates the barring device. l
- 4. Operates the pneumatic protective logic.
- 5. Boosts the governor servomotor (during start).
9EFERENCE VOGTLE LO-LP ?i;02-02-C, Objs. 1 & B. ,
3.4/3,9 l
064 f,00K 105 ..(KA's)
- I l
,s. ANSWER 2.25 (1.00) ;
i
- 1. To promote starting, i i
j 2. To prevent extreme oil vi scosi ti es.
REFERENCE i
VOGTLE LO-LP-11104-01-C, Obj. 1. :
3.4/3.6 f 064000G007 ..(KA's) !
l l
i i
i l
f I
(***** END OF CATEGORY 2 **444) l l
l q , W M Yw m=y-mmM"~ w-,v 'mm-Wey
31__10!IB9dEylg,90g_Cgyl69LS Pcgo114 l
ANSWER 3.01 (0.75)
- a. Prevents hunting (or oscillating). (0.50)
- b. 1.0 F. (0.25)
REFERENCE VOGTLE, LO-LP-27101-06-C, Obj. 81.
3.2/3.4 OO1000K408 ..(KA's)
ANSWER 3.02 (2.00)
- 4. 1. Lift coils CO.253 - zero current [0.253.
- 2. Stationary coils CO.253 - reduced current CO.253.
- 3. Movable coils CO.253 - reduced current CO.253.
- b. The two cabinets should be checked for the presence of an alarm light. (0.50)
REFERENCE VOGTLE, Training Tant, pp. 6-27a L 2Ba.
1 VOGTLE. LO-LP-27101-04, Obj. 8.
3.4/3.8 OO1050K401 ..(KA's)
I
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
I 3:__INSI6UDEUIS_99D_CgyI69(.S PcgD115 ANSWER 3.03 (1.00)
- b. +10/-4 or +4/-10. (0.50)
REFERENCE VOGTLE LO-LP-27201-02, pp. 9L 10, obj. 5.
3.2/3.6, 2.3/2.4 014000K601 014000A102 ..(KA's)
ANSWER 3.04 (1.75) ,
3200 F (0.25)
- a. 030C "
- b. The two millivolt readings are added together CO.503 the milivolt reading for the reference junction box temperature is subtracted from the sum CO.503 and the final total is converted to the temperature of the thermocouple using a conversion table CO.503.
REFERENCE VOGTLE, LO-LP-36102-OO-C, pp. 11-14 L Obj. 5. l 3.1/3.6. 3.1/3.3 017020K403 017020K402 ..(KA's)
ANSWER 3.05 (0.50)
Enables / disables (blocks) the high flux at shutdown alarm.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3 __ld!IBUDENI@,@NQ,CQNIQQLS Pcgglio REFERENCE VOGTLE, LO-LP-17101-02, p. 18, Obj. 10.
3/3/3.4 015000 GOO 7 ..(KA's)
ANSWER 3.06 (1.00)
- 1. P Allows manual removal of high voltage.
- 2. P Automatically removes high voltage.
REFERENLE VOGTLE, Training Text, pp. 3a-22 & 3c-16.
VOGTLE, LO-LP-17101-02, Objs. 7,11 and 14.
3.1/3.3 015000K401 ..(KA's)
ANSWER 3.07 (1.00)
- a. Serves as a backup to the UV coils (on and automatic trip signal).
- b. RTA and RTB.
REFERENCE VOGTLE, LO-LP-20101-OO-C, p. 16, Obj. 5.
3.7/3.0, 3.7/4.2 OO1000K603 012OOOK103 ..(KA's) l l
l 1
l i
(ssssa CATEGORY 3 CONTINUED ON NEXT Parit asses)
,EtO_INEIBWO(Nig,@NQCQUIBQLS Pcco117.
f ANSWER 3.08 (1.50)
- a. Any four of the following at 0.25 point eacht i
- 1. Loss of either of the two 48 volt DC power supplies. j
- 2. Loss of either of the two 15 volt DC power supplies. f
- 3. Any printed circuit card removed or not properly inserted. l (Except isolation cards). j i
- 4. INPUT ERROR INH!b1T switch in the INHIBIT position. ,
- 5. LOGIC A. PERMISSIVE, or MEMORIES switch not in OFF. !
- 6. MULTIPLEXER TEST switch in INHIBIT.
I
- 7. Slave relay tester OUTPUT MODE SELECTOR switch in the REST position. l
- 8. MASTER RELAY SELECTOR switch out of OFF. f
- 9. Loss of AC relays (K646 and K742).
OR !
l Loss of.120 vac to slave relays. ;
i i
- 10. Bypass breaker shut. (1.00)
- b. Reactor trip. (0.50) i
! REFERENCE i-
- VOGTLE, LO-LP-20101-OO-C, p. 25, Objs. 9& 10.
1 3.1/3.5 012OOOK603 ..(KA's) i h
i I
L i
e i
l >
I i t
[ (48888 CATEGORY 3 CONTINUED ON NEXT PAGE *****) !
I f
- - _ _ , _ _ _ . . , _ - , _ . _ , , . _ - _ . _ _ . , _ _ _ _ _ . . _ , _ , . _ , _ . . __ _ _ _._-,. _ __--_ -__. -._,_..#-~--
Pcgo110 E1._1UE1890EU15 0DE_b9U109hs ANSWER 3.04 (2.25)
- 1. High Flux Reactor Trip CO.253, 1/2 CO.253, (current equivalent to) 25% power CO.253.
. -11
- 2. P-6 (OR Source Range Permissive) CO.253, 1/2 CO.253, 10 amps CO.253. ,
- 3. C-1 (OR IR High Flux Rod Stop)' CO.25), 1/2 CO.253, (Current equivalent to) 20% power CO.253.
REFERENCE VOGTLE, Training Text, pp. 3b-10.
VOGTLE, LO-LP-17201-01, Obj. 9.
4.1/4.2, 3.1/3.1, 3.7/3.9, 4.3/4.5, 3.7/3.9 ,
1 I
015000K407 015000K405 015000K402 015000K103 01"OOOK101 1 4
..(KA's) f I'
l ANSWER 3.10 (1.50) >
(
Ecuel : r : ;r.t r ;! ;ucr. thet 7. Ceaand - % .iw m f row EO ^;-
{
! s linear % cams control such that % demand =* ve stem ,
i moverment 3.
N ?
OR i h !
With equal % ca e % steam flow is con d CO.503 whereas with linear % the % valve stem movement is contro 0.503.
_. Unit 2. 40.a0) l
. I i REFERENCE [
VOGTLE, RQ-LP-60301-OO-C, p. 15, Obj. 3.
2.7/2.9 j 4
1 041020K603 ..(KA's) !
[
- d. W. tve cre~ no. e ma nr. l Gre* a F/~. l
- 6. ~~w o so nnin' v~r~<Av j c>.go n eaa waa r co., cep r ,
l
(,r a 3 e . ./ r ~/ c/ / er c, fu s., r s , I L
(ssses CATEGORY 3 CO*dTINUED ON NEXT PAGE sesss; l t i I
1IINSIRyggNIg_gND_ggNIBQ($ Pcgo119 e
'].
7 t
(4NSWER 3.11 (1.25) I n l
,' a. 1. P-4. (reactor trip) f g 2. C-7 (load rej ection)
- 3. (Mode selector switch in) Steam pressure mode. (0.75)
- j. b. C-9 (condenser available) (0.25)
- c. P-12 (lo-lo Tavg interlocks) (0.25) o REFERENCE f.
VOGTLE LO-LP-21201-03, pp. 18 . , objs. 5 & 6.
2.7/2.9 1
041020K603 ..(KA's)
ANSWER 3.12 (1.00)
' Reactor trip on a turbine trip is prevented (disabled) when three-out-of-four (0.253 power ranges CO.503 are less than 50% CO.253.
5 OR Reactor trip on a turbine trip is only possible (enabled) when
, two-out-of-four CO.253 power ranges (0.S03 are greater than 50% CO.253.
REFERENCE
? VEGP Technical Specifications, Sec. 2, p.6, & Sec. 3/4, pp. 3-4 & 5.
3.6/3.9 ii 5
045000K411 ..(KA's) i 1
(***** CATEGORY 3 CONTINUED ON NEXT PAGE essse)
3:__!ysIgggENIS,gyg,ggNiggLS , PcOo120 t .
ANSWER 3.13 (1.00)
- 1. Safety Injection
- 2. . Loss of Power
- 3. Low discharge header pressure
- 4. Running pump trips (anticipatory)
. REFERENCE VOGTLE LO-LP-10101-02, pp. 13 L 14, obj. 8.
3.1/3.3 000000K401 ..(KA's)
ANSWER 3.14 (1.50) i
- 1. Ef fluent Monitors - Waste liquid af fluent (RE-0010)
OR Nuclear service water process (RE-0020 A L B)
OR Turbine b1dg. drain liguid effluent (RE-0048) 1 2. Leak Detector Monitors - Component cooling water process (RE-0017 A & B OR Steam generator sample liquid (RE-OO19) 1 OR l Aux. steam cond. return liquid (RE-0025) l OR
! Aux. CCW process (RE-1950)
OR Control b1dg. sump effluent (RE-17646)
- 3. Process Monitors - Boron recycle liquid process (RE-0016)
OR Steam generator blowdown liquid (RE-0021) 1 l
(esses CATEGORY 3 CONTINUED ON NEXT PAGE seass)
]
e
h__1UNIBWtgN]f,,$NQ,,C961BQbf Pcg0121 REFERENCE-VOGTLU LO-LP-32101-03, Obj. 5.
3.6/3.V 073000K101 ..(KA's)
ANSWER 3.15 (2.00)
- 1. Turns all heaters off CO.253 at 17% level CO.253 to prevent heater burnout (0.503.
- 2. Turns on backup heaters (0.253 if' actual level varies above program' by 5% CO.253 to minimize the pressure transient during an outsurge after a subcooled insurge (OR to heat subcooled insurge water, thus' minimizing subsequent pressure transients) CO.503.
REFERENCE VOGTLE 16302-02-C, pp. 14 and 15, obj. 4.
3.3/3.7, 3.3/3.4 011000K402 011000K401 ..(KA's) i
( *sae CATEGORY 3 CONTINUED ON NEXT PAGE se4es)
I
l st__INsIRygsyIg_eyg_CgyISQLS Pcg3122
'l l
ANSWER 3.16 (2.00) I 1,e fulhsrl 4T I
&y f.,veOTe 4Delta-T cely 6
1sterH[ f W ' * * ;
- a. 1. _2 ' r 'P 1
- 2. OP Delta-T c !:u!:ter Trf
- 3. P-12 circuitry (or Mi Etrer "1:n 5: p:rmi;;ivav-steem-dump.
bleek, 2nd Lo-lo Tavg signal) t
.* o rFgyg6*at er, ,i s,o{af i,on ,c i r,cu(tjy (or Lo Tavg asignal'to FWI) y o f o<lus -r e.d n , r s L
- b. Any four of t h e [,ol. .)l owIng.%c aka.O.so35 point each t
- 1) RVLIS
- 2) COPPS
- 3) Core subcooling monitor
- 4) Remote Shutdown System
- 6) Plant Computer
- 7) Plant Safety Monitoring System 1
i REFERENCE 1
l VEGPTT pg' 25-17/18, LO-LP-16701-OO prs 5, LO-LP-16501-OO pg 5 1 3.9/4.1, 4.3/4.4, 3.5/3.7, 4.2/4.4 l
l OO2OOOK410 OO2OOOK107 OO2OOOA403 OO2OOOA104 ..(KA's) l l
(tes** CATEGORY 3 CONTINUED ON NEXT PAGE seass)
It._INglgyD{NI{_gNQ_QQNIRQ(S Pcgo123 l
.f I
. ANSWER 3.17 (2.25) ,
i
- a. 1. Letdown divert valve (or LV-112A) diverts to HUT. t i l Auto makeup prevented'(or auto makeup stopped).
) -2.
4 3.' Charging pump suction prevented from shifting to RWST on actual !
4 low VCT level. !
4
- b. Any five of the following at 0.25 each, also 0.25 total for logical !
4 sequences {
t
- 1. VCT 1evel drops. [
i 2. Charging pump loses suction when VCT drained.
1
- 3. Charging pump overheats (due nn flow) and trips.
- 4. Charging flow is lost. f l
- 5. CVCS letdown isolates (or pressurizer heaters shut off) on low ,
pressurizer level . f i
j 6. RCP seal leakoff continues (or pressurizer level still (
j dropping).
- 7. Reactor trips on low pressurizer pressure. !
I
{ REFERENCE ;
i i i LO-LP-09201-03, p. 10, objs. 3h 14 i i LO-LP-09101-01, p. 15, obj. 3. )
i VOGTLE. Training Text, pp. Sa-57 & 58. t 3.1/3.1 !
I
- t
- i. 004010A211 ..(KA's) !
i 3: t 5
1 1 !
i [
1 ANSWER 3.10 (0.75) i i
l 1.Auctioneered high Co.103 nuclear power CO.153.
i.
1 l 2. Actual steam generator level. [
l
- 3. Program level (or turbine impul se pressure) . (
< t i i I
i I i
i 4
! (asses CATEGORY 3 CONTINUED ON NEXT PAGE esses) 1
- I i !
- t f,
,cv ---.-, -'
- 3. INSTRUMENTS AND CONTROLS Pcgo124, i ,
i REFERENCE -
VOGTLE LO-LP-18501-OO-C, Obj. 3h.
3.6/3.8
- t 035010K401 ..(KA's) ,
ANSWER 3.19 (1.00)
- 1. S!S !
e f f
- 1. 2. Blackout [
i
- 3. Lo-Lo level in any.S/G ,
(
- 4. Both main Jeed pumps trip. l
} r
- REFERENCE
- s
! VOGTLE LO-LP-20101-07-C, pp. 18 7'19, obj. 8. !
d 4.5/4.6 t
b 1 .
! 061000K402 ..(KA's) l- !
ANSWER 3.20 (1.00)
I For unit 1 a circuit card must be pulled CO.503 as compared to unit two where i t is only required that a reset button be pressed CO.50). ;
j REFERENCE [
t
]
i VOGTLE RQ-LP-60301-OO-C, p. 10, Obj. 3.
1 3.5/4.0 3.3/3.1, 2.8/3.1 i' i j 062OOOK403 062OOOA401 064000K410 . . (KA's)
I t I
l, I l t i
t i
[
I i f
i (esses CATEGORY 3 CONTINUED ON NEXT PAGE *
- 884) 'l I
i i
1 e,-. n--,. - .-nn.,,,.,,,e -.nn,-,,,,--,..n,,-,_,n,. ,---,7.,mn ,n,.n, n-mn-,,.- _w,--v,--w,e,-
lIt_ INRISW5ENIl eN9 G96189bf Pago123 b .
Q&LCT&O ANSWER 3.21 (1.50)
- a. At the fan bre er.
Locally.
- b. Unit 2.
- c. A (30 m ond) time delay.
REFERENCE VOGTLE Q-LP-60301-OO-C, p. 7, Obj. 3.
2.8/2 O76000 GOO 9 ..(KA's) j ANSWER 3.22 (2.25)
- a. Hi-1 containment pressure, 3.8 psig, 2 of 3
- b. Low steam line pressure, 585 psig ( > P-11 or < P-11 but not blocked), 2 of 3 channels in 1 of 4 steam generators.
~
t98f
- c. Low pressurizer pressure, be%G-psig ( < P-11 but not blocked),
2 of 4 channels.
(0.25 for each signal, 0.25 for each setpoint, and 0.25 for eaco coincidence)
REFERENCE VOGTLE LO-LP-28103-04-C, p. 5, Obj. 1.
4.2/4.4 013OOOK101 ..(KA's)
(esses END OF CATEGORY 3 seass)
$1_.009EEEUOE3 ~_U90Dbh1_OEU90UOhi_ggggGgNCY Pcg3123 eNQ,6@ pig (QGlC@6_Cg61696 ANSWER 4.01 (1.00)
During an absence of the SS from the Control Room CO.503 while the unit is in Mode L or 6 CO.503.
REFERENCE ,
VOGTLE 10003-C , "Manning the Shift," step 3.6.
2.7 194001A109 ..(KA's)
ANSWER 4.02 (1.00)
- 1. Unit 1 - WHITE CO.253 Rectangular CO.253.
- 2. Unit 2 - BLUE CO.253 Circular CO.253.
REFERENCE VOGTLE RQ-HO-60301-OO-OO1, p. E2-8.
3.6 194001K101 ..(KA's)
D es e re n ANSWER 4.03 (1 0)
CAF REFERENCE VOGTLE St nding Order, # CAF.
VOGTLE O 054-C, "Rules for Performing Procedures," step 4.2.4.1.
4.1 194 01A105 ..(KA's) l l
(**s** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
. = _ ._.--. _ . - _ . . _ _ _ _ _ - _ _ _ _ ._ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ - _ _ _ _ _
-- 4. PROCEDUR{g, ,NQR % g,AgNQRMALg,EM{RG{NCy Pcgo127 10Ng,8991969919@(,ggNJ8Q( ,
t t
e ANSWER ~4.04 (1.50) !
- 1. On-Shift Operations Personnel 2.' Operations Chain of Command a
- 3. NRC resident inspectors [
t REFERENCE j VOGTLE OO301-C, "Main Control Room Access and Personnel Conduct," step 5 3.2. !
3.1 ,
194001K105 ..(KA's) f e
ANSWER 4.05 (1.00)
~
l Any four of the following at 0.25 point each
- 1. Mode changes. f
- 2. Load changes. .
4 3. Reactivity changes. t 1 i
, 4. Equi p ment status changes. [
- 5. Performance of surveillance testing.
- 6. Releases of radioactive effluents (including start and stop times). j
- 7. Out-of-specification chemistry results.
REFERENCE r
. VOGrLE 10001-C, "Logkeeping." step 2.3.
3.4 f
)
194001A106 ..(KA's) .
r r
I i
I I
i f
1 I v
i (ssssa CATEGORY 4 CONTINUED ON NEXT PAGE *****) '
I i i' 4
{
- 6. ~ PROCEDURES - NORMAL t ABNORMAL EMERGENCY Pcgo12J
~~~~bbh5bbhihEh!1hbE~Nhd!bhE~~~~~g~~~~~~~~~~
l50 ANSWER 4.06 42.00;
- 1. 1000 meem/qtr CO.253 - Whole body Co.253
- 2. '"^^ r r ' ;t r !^.2": - L" . ; 1 ; = , 0. 2". ;
- 3. 7500 mrom/qtr CO.253 - Skin [0.253
- 4. 19750 mrem /qtr CO.253.- Extremity C0.253 REFERENCE VOGTLE 00920-C, "Radiation Exposure Limits and Administrative Guidelines," p. 8.
2.8 194001K103 ..(KA's)
ANSWER 4.07 (0.50)
FALSE REFERENCE VOGTLE 00930-C, "Radiation and Coatamination Control," p. 15, 2.0 194001K103 ..(KA's)
ANSWER 4.08 (0.50)
To prevent crud infiltration into seal chambers.
REFERENCE VOGTLE 13006-1, "CVCS Startup and Normal Operation," step 2.1.1.
2.7/3.1 1
003000K602 ..(CA's)
(ssess CATEGORY 4 CONTINUED ON NEXT PAGE 8488s)
ex. ES9GEDWBEf. N9BD A _CRW980 & 5BEB9{NGy Pcgo120 9N9_Be91%991G%_G9NIBA I
. ANSWER '4.09 (1.00)
- a. 2
- b. 3
- c. 3 Cr 5/
- d. 4k- 6 ~
REFERENCE VOGTLE 12004-1, "Power Operation," step 4.1. ,
4.1 194001A102 ..(KA's)
ANSWER 4.10 (0.50)
(The pump starting current) may trip the diesel generator breaker.
REFERENCE VOGTLE 13003-1, "Reactor Coolant Pump Operation," step 2.1.1.
3.3/3.6 003000G010 ..(KA's) i
($$444 CATEGORY 4 CONTINUED ON NEXT PAGE 94848)
A. PROCEDURES - NORMAL _AB@ORMAL t g, EMERGENCY : Pcgo130 9NQ,Rggig(QQ1Q96 QQNIBQ(
[
P t
I ANSWER 4.11 (1.00)
Any four'nf the following at 0.25 each [
- 1. Motor bearing > 195 F.
- 2. Motor stator >311 F. t
- 3. Pump bearing > 230 F. !
- 4. Seal water inlet > 230 F. l
- 5. Total loss of ACCW for a duration of 10 minutes.
- 6. RCP shaft vibration of > or equal to 20 mits.
f
- 7. RCP frame vibration of > or equal to 5 mils.
REFERENCE VOGTLE 13003-1, "Reactor Coolant Pump Operation," step 2.2.12. !
3.3/3.6 l i
-003000G010 ..(KA's) !
i
[
t ANSWER 4.12 (1.50) !
L
- 1. Turbine Control Valvest.253 - Cleming C.253
(
- 2. Generator Loadt.253 - Lowering C.253
- 3. LOSS OF TURBINE LOAD INTLK C7 Status Lightt.253 - Energizedt.253 [
-REFERENCE VOGTLE 18012-1. "Turbine Runback / Setback." step 2.
4.1 ,
i i
194001A102 ..(KA's) [
f I
i 1
(seass CATEGORY 4 CONTINUED ON NEXT PAGE seses) }
}
t
!s. 6699E ddE9 ~_U9606bt_6EU9600ba.gdgBGENQY Pcgo131 609.669196991C66.9901696 ANSWER 4.13 (1.25)
- 1. Stop any power changes in progress CO.503.
- 2. Verify affected loop SG 1evel CO.503 trending to 50*/. C O. 25 3.
REFERENCE VOGTLE 18005-1, "Partial Loss of Flow," steps 1 & 2.
3.4/3.4 l 000017G010 ..(KA's)
ANSWER 4.14 (1.25) ;
4 Place the rods in manual CO.503.
- b. Verify RCS pressure CO.503 - stable (or rising) CO.253.
, REFERENCE VOGTLE 18001-1. Primary Systems Instrumentation Malfurction."
3.8/3.6, 3.5/3.4 i.
j 016000G014 010000G014 ..(KA's) ,
t 1
ANSWER 4.15 (1.00) t
- a. By depressing both EMERGENCY STOP push buttons. l
- b. To prevent operation of the Diesel Generator without NSCW. !
I REFERENCE VOGTLE 18031-1. "Loss of Class 1E Electrical Systems." step 1. ,
3.1/3.6 3.9/3.9 l
I l
064000A406 064000K102 ..(KA's) [
t I
4 (esess CATEGORY 4 CONTINUED ON NEAT PAGE sesse)
l- . < . ;
4 '. PROCEDURES - NORMAL t_(ENORMAL ,tEMERGENCY Pcgo132 9N9 899194991Geb_G9NIBQ6 i
I ANSWER 4.16 -(2.00)
- a. 4 l
- b. 3 l REFERENCE VOGTLE 19000-1, "E-0, Reactor Trip or Safety Injection," pp. 1, 17 & 19.
4.3/4.6 OOOOO7A202 ..(KA's)
'i ANSWER 4.17 (2.00) [
t
- a. To minimize RCS ' inventory loss via the RCP seals. i OR f To allow accumulators to inject. ,
h OR 1 To maximize time to core uncovery. j
- b. To prevent injection of accumulator nitrogen into the RCS.
- c. Continue depressurizing.
5
- d. Power must be restored to at least one ESF bus.
i l REFERENCE i
VOGTLE Emergency Operating Procedure 19100-1 p.12
! VOGTLE LO-LP-37031-01C p.43 LO-LP-37002-02-C p.12 3.6/3.7 t
OOOO55 GOO 7 ..(KA's) l' i
l i
l l
(asssa CATEGORY 4 CONTINUED ON NEXT PAGE sesse) t I
l I
a - - ,-. - . - - _.
41_ 6699E99 BEE _ _U96066A 6EU9606bx_gdggggggy Pcgo133 609_B69196991966_990IB96 ANSWER 4.18 (1.50) e
- 1. Containment Pressure C0.253 >/= 3.8 psig CO.253.
- 2. Containment high radiation level CO.253 >/= 100.000 R/hr C-). 25 3.
- 3. Containment integrateu dose CO.253 >/= 1,000,000 Rad C O . 2'J 3 .
REFERENCE VOGTLE LO-LP-36104-OO-C. p. 6, Obj. 5.
A.5/4.5 OOOO11G010 ..(KA's)
ANSWER 4.19 (1.00)
- 1. Use the Trip switch on Shutdown Panel A.
- 2. Use the Trip switch on Shutdown Panel B.
L
- 3. Locally trip the reactor trip and bypass breakers.
- 4. Locally trip the rod drive MG circuit breakers.
l REFERENCE i
VOGTLE 18038-1. "Operation From Remote Shutdown Panels " step 6. 4 4.3/4.4 i
OOOO60A123 ..(KA's)
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l i
ANSWER 4.20 (2.50) i
- a. 1. If WR level in any 3 S/G's is (25*4 CO.503 (40% adv. cont.) with !
I no feedwater established CO.503.
- 2. If par. pressure >/= 2330 poig CO.503 due to a loss of secondary heat sink CO.503.
- b. Increases the recovery time'available CO.253 before SGs lose !
inventory CO.253.
OR i
Removes the heat input of the pumps CO.503. p i
REFERENCE VOGTLE LO LP-37051-02-C, PP. 5 & 6, Objs. 2 and 12.
4.4/4.6 OOOO54K304 ..(KA's)
ANSWER 4.21 (1.50) j 1. RCS subcooling monitor indication CO.503 - Less then 24 F CO.253.
- 2. PRZR level CO.503 - cannot be maintained greater than 9% CO.253.
REFERENCE VOGTLE 19000-1, "E-0 Reactor Trip or Safety Injection," p. 26.
4.1/4.3 OOOOO7G011 ..(KA's)
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ANSWER 4.22 (3.00) .
.i . 1. MFIVs
- 2. BFIVs
- 3. MFRVs
- 4. BFRVs (0.25 each)
- b. 1. Verify containment spray pumps running CO.253.
- 2. Verify containment spray additive flowrate CO.253 of approximately 40 gpm (0.253 per operating CS pump CO.253.
- c. 1. AFW pumps
- 3. CCW pumps
- 4. NSCW pumps (0.25 each) ,l REFERENCE VOGTLE 19000-C. "E-O Reactoc Trip or Safety Injection," pp. 3 - 6.
VOGTLE LO-LP-37011-02-C. Obj. 4.2 4.2/4.1 i
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ANSWER 4.23 (1.50)
- 1. Ensure the (DAFW pump (0.253 is running CO.253 by checking open CO.253 one MS supply valve (HV-3OO9 o* 3019) and the common MS supply valve (HV-5106) CO.253.
- 2. Ensure the AFW throttle valves CO.253 are open CO.253.
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C1__0099EE90EE ~_U96U9ht_9Eb90UO6L EUE0_[ygy PcgD133 eU9_Se9196991Ge6_C901696 CEFf.RENCE VOGTLE 19100-C. "ECA-0.0 Loss of All AC Power." p. 4 VOGTLE LO-LP-37031-02-U, Obj. 7.
4.1/4.3 OOOO55G010 ..(KA's)
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