ML20246F453
| ML20246F453 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/17/1989 |
| From: | Casto C, Ernstes M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20246F451 | List: |
| References | |
| 50-424-OL-89-01, 50-424-OL-89-1, NUDOCS 8908300344 | |
| Download: ML20246F453 (200) | |
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g ;, ' EXAMINATION REPORT!- 50-424/0L-89-01 i-O4 _ Facility Licensee: ' Georgia Power: Company-m- ;40 Inverness Center: Parkway L/ ' . P. O.' Box 1295 [ ' ; Birmingham, AL 35201 P . -
- Facility-Name: I- :Vogtle Electric Generating Plant t '
[O . Facility Docket'Nos.:- 50-424.end 50-425 h't,[ , , y ,
. . , Facility License Nos.:
NPF-68 and NPF-81
. Examinations were administered at: the Vogtle.-Electric Generating Plant near_
Waynesboro, Georgia.. , o k' Chief Examiner: @N5c .* [ O-/7-69 f
. Michael E. Ernstes Date Signed 7 Approved By:: #72[ M M
. Charles K.'Casto; Chief .
y-n--s 9
) ate Signed Operator Licensing Section 1 Division of Reactor Safety SUMNARY Examinations were administered on Jane 12-15,;1989.
Written examinations and operating tests were administered to 'seven R0
! applicants ' and two SR0 applicants. A writter, test was administered to two n : additional SRO applicants. A simulator test wa's administered to one M additional SRO applicant. Sev e R0s and five SR0s passed these examinations.
Unit 2 ' operating testst were administered to one 'R0 applicant and two SR0
- .. . . applicants. - Two SR0s passed the examination, the R0 failed.
,7 c naa% v Ban BUSSdS' .
REPORT DETAILS
- 1. Facility Employees Contacted:
*K. Holmes, Plant Training and Emergency Planning Manager
*R. Dorman, Operations Superintendent of Training
*H. Butterworth, Operations Superintendent Administration
- Attended Exit Meeting
- 2. Examiners:
*M. Ernstes, NRC, Region 11
.R. McWhorter, NRC, Region 11 L. Sherfey, PNL R. Vinther, PNL R. Pugh, PNL
- Chief Examiner
- 3. Exit Meeting:
At the conclusion of the site visit, the examiners met with representatives of the plant staff to discuss the results of the examinations. The examiners made the following observations concerning your training program: Areas of generic weaknesses were found in tne knowledge of power supplies for the MG sets, failure modes of thermocouple, location of headsets used for local operation of the ARVs, and general familiarity with the Emergency Plan among R0s. The' exam team expressed concern over the inadequacy of the simulator's capability of modeling certain plant conditions. The operators are trained under conditions which do not accurately reflect the plant response that would be experienced during operation of the real plant. This negative training, as detailed in the Simulation Facility Report, could lead to improper use of the EGPs under actual conditions in the real plant. 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 material provided to or reviewed by the examiners. L _- __ _ - - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ i
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l U. La NUCLEAR REGULATORY COMMI ON l
-' REACTOR OPERATOR LICENSE EXAMINATION l FACILITY: Y0GTLj_1&3_______________
REACTOR TYPE: PWR-WEg4_________________ DATE ADMINISTERED: @9[g6f12_________________ IN@l6UCllgN@_IQ_C@NQ19@IEL Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__YeLUE_ _191@( ___SCg6E___ _y@(UE__ ______________C@lEGggy_____________ _22:00__ _22t2g ___________ ________
- 1. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) _2Z 99__ _2Z ZZ . ___________ ________ 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) yQ.::
-07700- 47.47 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
'iE
-99.00- % TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
- 3 .- g NRC RULES\ wdD GUIDELINES FDR LICENSE NOMINATIONS
]
~During the administration of this examination the f ollowing rules apply
.1.- Cheating on the examinati on means: an automati c ' deni al of your application and could result in more severe penalties.
J-2.- Restroom trips are to be. limited and only one candidate at a time may leave. You'must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 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 examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided f or answers. "
- 7. 'Pri ; your name in the upper right-hand corner of the first page of each section of the answer sheet.
S. 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.
l 11. Separate answer sheets from pad and place finished answer sheets face l down on your desk or table.
- 12. Use abbrevi ations only if they are commonly used in facility literature.
- 13. The point value f or each question is indicated in parentheses after the question and can be used as a guide f or the depth of answer-required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
I 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE l QUESTION AND DO NOT LEAVE ANY ANSWER BLANK. NOTE: Partial credit will not i be given for multiple choice questions.
- 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 compl eti ng the ex ami nati on. This must be done af ter the examination has been completed.
u______________________________ _ _ - . _ _ __ . - - __ _ __. .
o. O
.18.. .Wh0n ' you comploto ' your exami nati on, you chc11:
- a. Assemble your examination as f allows:
(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 use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
ci-L_BEAGI96 EBINg1ELES 7. ) THERMODYNAMICS Pega' 4 b) . (77,) AND COMPONENTS
?. 7,) (FUNDAMENTALS EXAM) ()
* .. i
;+
QUESTION 1.01 (1.00) Which ONE of the f ollowing correctly defines Dif f erential Control Rod j
' Worth 7
- c. .The amount of reactivity change.resulting from a change in rod position of one unit r
- b. The total amount of reactivity change resulting from a change in rod '
' position of neveral units
- c. The difference ~in reactivity change resulting from a change in rod I position of one unit by a center rod compared to an outer rod
- d. The difference in reactivity change resulting from a change in rod position of one unit by a rod at BOL compared to EOL i
l i l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
l i- REACTOR PRINCIPLES ( 77,) AND COMPONENT 7J' THERMODYNAMICS p- Pogo 5 11%)- (FUNDAMENTALS EXAM) U QOESTION- 1.02 (1.00) Which DNE of the f ollowing correctly describes - how and why Modero. tor Temperature Coefficient (MTC) changes with increased Boric Acid concentration?
- a. MTC increases (less negative) as Boric Acid concentration increases due to the effects of Boron on the Thermal Utilization Factor (f)
- b. MTC decreases (more negative) as Boric Acid concentration increases due to the effects of Boron on the Thermal Utilization Factor - (f )
- c. MTC increases fless negative) as Boric Acid concentration increases due to the effnets of Boron on the Thermal Non-Leakage Probability (L-th)
- d. MTC decreases (more negative) as Boric Acid concentration increases due to the effects of Boron on the Thermal Non-Leakage Probability (L-th)
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
1.,_ REACTOR PRINCIPLES- %) THERMODYNAMICS 'gq Paga 6
-(7%) AND ggMPQNENI 11Zl_JEyNQ@d[NI@LS_gl@dl V
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QUESTION 1.03 (1.00) Given ttie f ollowing initial conditions:- Keff = 0.957 All Rods In Boron Concentration = 1242 ppm Source Range Indication = 150 cps
' Shutdown Bank Worth = 4.2% delta'K/K Total (All Rods) Bank Worth = 7.1% delta K/K Calculate the source range count after withdrawing the shutdown banks.
-(Sel ec t the best answer below.)
c.- 300 cps
- b. 1100 cps
- c. 2200 cps
- d. 60f0 cps l
l l l J
-(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
h-1e__BE@ gigs _E61NglE(ES g'.l_IUg8DQQYN@ Dig @: 1("y Pago -7
,(7%) AND CQUEQNgNIN__11Z1_JEQNQ@dgNI@(S_[f@dl \.J .
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. QUESTION 1.04 (1.00)
Unit 11 trips early i n'11fe'after operating at 100% power for 37 days. Xenon in the core will peak approximately __________ hours after the' trip, 1cnd during that time, approxi matel y __________ pcm reacti vi ty wi l l be added
'to the core.
(Select - the ONE answer below which best fills in the blanks)
- c. 6. hours; -2100 pcm b ." 6 hours; -3200 pcm
- c. B hours; -2100 pcm
- d. O hours; -3200 pcm e
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
.I
~
A6 P N - -E F LS-EXAM) j 1 QUESTION 1.05 (1.00) Which ONE of the f ollowing best describes how and why the average delayed
-neutron fraction.(Beta-bar) changes with increasing core age?
- a. Decreases, since as core ~ age increases, a higher percentage of fissions come from Pu-239.
- b. Decreases, since as core age increases, a lower percentapa'of fi ssi ons come from Pu-239.
- c. Increases, since as core age increases, a higher percentage of fissions come f rom Pu-239.
- d. Increases, since as core age increases, a lower percentage of f i ssi ons come from Pu-239.
l l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) w_----_-__-_-__-__-____-___-_-_____-_-___-_-----____-___-__-___-___-___-_ _ - _ _ _ _ - _ _ _ _ _ _ _ - - _ _ _ _ - _ _ _ - _ - _ - _ _ _ _ _ _ _ - - - _ - _ - _ _ _ _ .
- 12. REACTOR' PRINCIPLES Y.)' THERMODYNAMICS Pags 9
.(77.) ANQ_QQMPQNENT_ _1*f1_JFQNQAMgNTALS_EX AM) -
QUESTION 1.06 (1.00) 30 minutes ago it was discovered that- two rods are. stuck at 228 steps, and
- a. power reduction was commenced i n preparati on f or ' shutdown. Given the f ollowing conditions, _ calculate 'the new available Shutdown Margin using the
~
attached Data Sheet 1 and associated plant curves. 50% power Boron-concentration = 1200 ppm
' Control Bank D at 220 steps 100% equilibrium Xenon prior to downpower Tavg = Tref Beginning of Core Life (Select the ONE best answer bel ow. )
.a. 0.7% delta'K/K b.- 2.9% delta K/K
- c. 3.8% delta K/K
- d. 4.7% delta K/K 1
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
D E .. . . .
.1..
- REACTOR PRINCIPLES %) THERMODYNAMICS m .Pc93 10
- ( 7'/ ) AND COMPONENT IIEI~IFUUDEMEUTMLS EXAM) h l
QUESTION 1.07 (1.00) Fill in the blank below wi th thw ONE '1etter. f or the curve which best illustrates Axial' Flux. Distribution for that condition. (Assume rods'are fully withdrawn with equilibrium-Xenon.):
-Curve Letter Condition l '. ____________
BOL, 0% power
- 2. ____________
- BOL, 100% power
- 3. ____________ - EOL, 0% power
- 4. ____________
EOL, 100% power CURVE "a" CURVE "b" 100% --- 100 % - - - - -- h h
- E h PEAK I E Sow- PEAKS W 50%-
* / W
.5o o o
I AxlAL OAXIAL i CURVE "c" CURVE "d" 100 % - -- poog ._ _ ___ h is b etAK g , g W Sow- .--etat E Sow. I U I o o O O AXIAL ,
$ggggg *
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
l1,,h_ REACTOR PRINCIPLES 7.) THERMODYNAMICS :Pcg3.11
- ( 7f},_ ANQ_QQDPQNENig 131,1E(INQ@dgNI@65.Ef@M1 hg.
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- QUESTION 1.08? : ( 1. 00 )
. Which DNE.of:the_following categor'ies of transients does NOT have a significant risk of. Pressurized Thermal Shock?
' Loss of' Coolant' Accident.
.a. -
~
b.' Steam Generator Tube Rupture
.c. . Secondary Depressurization d.- . Anticipated Transient Without Trip V'
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
12.c_BE99198_EBINQlELES_f?hl_IhgBDQQyN8dlQS, Pcga 12 (7%) AND COMPONENT [ 1131_lE6)NQgD[NI66@_EX@dl Q - QUESTION 1.09 11.00) l Referring to the attached figure for the Reactor Core-Safety Limits, match labela psi a curve - segments in Column I with their bases in Column (Fill in the blank in Column I with the letter in Column II) Column I Column II
- 1. ________ - Segment I a.. Prevents exceeding 15% quality of coolant at core exit 2.. ___ __ - Segment II b. Prevents exceeding DNBR less than 1.3 anywhere in core, from W-3 correlation
- c. Prevents T-hot from reaching-saturation
- d. Prevents exceeding fuel centerline-temperature of 2200 deg F.
l l l l l l l-(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
( Q 'Page 12A 680 e- l UNACCEPTABLE
, OPERATION 2400 pela 0 -
% x m
% 3
- 2m @
2000 paia - E 620 -
\
1775 pois
- i. N \\
8 N \' N ^ B e 580 T 3
~
ACCEPTABLE OPERATION 560 i i l 540 I O 0.2 0.4 0.6 0.8 1.0 1.2 FRACTION OF RATED THERMAL POWER FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT V0GTLE UNITS - 1 & 2 2-2
kf ,; "
) THERMODYNAMICS: (' ' Pcgo 131 0 jli_;Rg@gTQR_ PRINCIPLESN__1 c ('77) ANp_QQDPQNgNI _
g ,1Zl_JEyNQ@DENI@(g_gX@M1 ' i:;T . , , h o . QUESTION '1.10 ( 1 '. 00 ) Given the inf ormation bel ow, calculate core thermal power. (Disregard heat l4 cdditions or losses.from other. sources, and assume the feedwater is a l .caturated li quid. ) 1 S/G-k S/G-B 5/G-C. S/G-D Steam press. (psig) 1035 1035 1035 1035 Steam flow (Ibm /hr) 1.9X10^6 1.9X10^6 1.9X10^6 1.9X10^6 Feed temp. . (deg F) 450 450 450 450 } l Feed flow (Ibm /hr) 1.9X10^6 1.9X10^6 1.9X10^6 1.9X10^6. (Select the ONE best answer bel ow. )
- a. 1445 MWt
- b. 1695 MWt
- c. '2465 MWt d.. 5781 MWt
(***** CATEGDRY 1 CONTINUED ON NEXT PAGE *****)
g g; , _ - -__ - S I f-[ A .'(.,['. n' _i . . . ' [i. . 'l u . L e Pogs.14 P14.' REACTOR PRINCIPLES- 7. ) THERMODYNAMICS'.
- (7Y,) ' AND ' COMPONENT 1 17, ) - (FUNDAMENTALS EXAM)
- 4' p
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' QUESTION .1.11 ' . ( 1. 00) -
' Gi ven. the f all owi ng post-LOCA condi ti ons, c al cul at'e : RCS subcool i ng.
iNatural circulation flow' verified satisfactory-- Al'1 RCP's: secured-RVLIS upper range.=,95%- Pressurizer empty Average. core exit thermocouple.='300 degF RCS pressure.= 255 psig
' Containment pressure = 0 psig (Select the ONE best' answer below.)'
- c. . .17 degF
- b. .23 degF
- c. 28'degF'
- d. 34 degF t***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
U! F1 [li REACTORcPRINCIPLES'(7%) THERMODYNAMICS' Pcgo 15 L: ' '"EIY5_I_75U_h_~C_yb@ U(Ult ~l._I_I5_i_~_If[ishdb(U__TE_($_g_X AM_) , q 3 v _ __ __ N,.
- =
-QUESTION. 1.12. ( l'. 90 )
.Which ONE of the following best describes the EOP-19001, "ES-0.1, Reactor
-Trip Response", requir ements f or RCS temperature when verifying natural circulation flow?
-- a . - RCS cold leg temp at saturation temperature for steam generator pressure
- b. RCS cold leg temp at' saturation temperature for RCS pressure
- c. ~ RCS hot leg temp at than the saturation temperature f or steam generator pressure
- d. RCS subcooling monitor indication greater than 2 degF
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
L 1;* ' REACTOR PRINCIPLES (7%) AND COMPONENT 3)' THERMODYNAMICS 11%) (FUNDAMENTALS EXAM) (} Pago 16. J
.q t
1 QUESTION ~1.13 (1.00) , i Which~ONE of the f ollowing correctly defines cavitation in a pump?
- a. The formation and collapse of vapor bubbles formed where local fluid pressure drops below saturation pressure.
- b. The formation and collapse of air bubbles f ormed where local fluid pressure drops allowing entrapped air to come out of solution.
- c. Pump noise and vibration caused by high pump discharge pressure reducing local fl ow ' rates.
- d. Pump noise and vibration caused by low pump discharge pressure increasing local flow rates.
i f (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) - - - _ - - _ - - - _ --_ _. _ 1
r
J 1/ ! REACTOR PRINCIPLES g %)~ THERMODYNAMICS . P -- Pcga 17-
- ( 7 /. ) AND CQUEQNgNI N__1131_JEQNQ95gNI@(g_EX@di_
' QUESTION 1.14. ( 1. 00 ) .
" Which ONE of ' the' f oll owing i s NOT one of the MAJOR causes of water hammer 7 n
.c. Valve operations-
- b. Pump operations-
- c. Steam-water mixtures in piping d.. Entrapped air'in fluids-(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
L- ---- - . - - . - . - _ - - - _ - - - _ - - - - - _ - - - - - - - - - - - . _ _
ig,__ REACTOR PRINCIPLES X) THERMODYNAMICS- .- s-Pcga 18 3,i q JZZ.l_ANQ' COMPONENT, 11 */ ) (FUNDAMENTALS EXAM) , . QUESTION- 1.15 (1.00) l.
' Which ' ONE of the Lf o11owing correctly states the purpose of loop seals :
upstream.of safety, valves such as the Pressurizer Safety Valves?
- c. Prevent safety valve damage due to high temperature l b. Prevent inadvertent opening by mitigating pressure transients L
- c. Prevent water hammer d._ Prevent gasses f. om leaking through the valve seat
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) I - - - - _ _ - _ _ _ - - _ _ _ _ - 8
II ,__86@CIOg_g61gg1E(g@j'q31_Ibg6dggyN9Digg- Pago 19 ( 7 /. ) AND COMPONENT! J11Z,1_fFUNQAMENTAL@_gXAM1 ((s l . QUESTION 1.16 (1.00) EWhich DNE of the following is correct concerning manual operation of motor-operated valves?
- a. 'The valve power supply breaker must first be opened before declutching i the motor and manually operating the valve.
1' !. b. The valve motor will automatically re-engage and reposition the valve if remote operation is attempted while the motor is declutched for manual operation.
- c. The valve torque limiting mechanism will continue to prevent overtorquing of the valve on its main or back seat during manual operation,
- d. The remote valve position indication will not accurately reflect valve position when the valve i s manually operated.
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
a
~l'a R"7CTOR PRINCIPLES,, 731_ THERMODYNAMICS .
Pcgp 2D
. - 51 9ND_QQMPQNENT 117.) (FUNDAMENTALS EXAM)
QUESTION 1.17 - (1.00) Which ONE of the f ollowing correctly describes the ef f ects of post-transient core voiding on Source Range Detsctor response?
'o. Source range level increases proportionally with increasing void fraction.
- b. Source range level decreases proportionally wit n increasing void fraction.
- c. Source range level initially decreases as void f raction increases, and
.then increases when void fraction becomes exceptionally large.
- d. Source range level initially increases as void fraction increases, and then decreases when void f raction becomes exceptionally large.
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) E______________________ _ __
Ig;g;REACTORiPRINCIPLES %) THERMODYNAMICS Pcgo 21-(7%) ANQ (QMPQNgNI 1131_fEQNQ95ENI@(@,gf@dl(gs). ,
~
QUESTION 1.18 (1.08) F'orf the f ollowing types of thermocouple f ailures in Column I, select the resulting effect upon_ indicated temperature from Column II.
.(Fill in the blank.in Column 1 with the ONE best l etter f rom Column !!).
Column I Col umn II
- 1. _____ - Short circuit a .' Indicated temperature would read erroneously HIGH l > ;. 2. _____ - Water in thermocouple b. Indicated temperature would insulation read erroneously LOW
- c. Indicated temperature would-NOT CHANGE
- d. Indicated temperature would be.the SAME AS THE TEMP AT THE POINT OF THE FAILURE p (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
l _ _ _ _ _ _ - __ . _ - _ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ - _ _ _ - _
I
'12 _BEeGIDB_EBING1BLEE El_IMEB5DDYUe51GE -- Pcos 22.'
u-
.(7x) Aug_GguegsgNI 11}{_fE(leeeeEuletE creer O u .
H lGUESTION'- 3.19= (1.88) , If run at shutoff head f or extended. periods of' ti me, a' centrifugal pump will'be damaged by:- (Select-the-DNE'best answer below) O. Excessive c'urrent
- b. Runout.
- c. Overheating .
1
- d. -Cavitation
)
J i o (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
- 1. ' REACTOR PRINCIPLES /*7*/.) THERMODYNAMICS Pcg3 -23 ,
' 22n_ese_cgrousufL.2nn_1Eweemselets_Esent O, 4' ..
i l
- DUESTION .1.28 -(1.99) i
., Which DNE of the- f dllowing f actors will. INCREASE the Net Positive Suction p .. . j Head'(NPSHE available to a centrifugal pump?
- o. Increased suction pressure
- b. Increased fluid temperature c.- Increased fluid velocity (f l owr ate) d.- Increased pump speeld 4
,l J
i l l (***** CATEGORY 1 CONTINUED ON NEXT PAGE sas**)
II .. REACTOR PRINCIPLgg %1_ THERMODYNAMICS- . Pego 24 l (7%) ANQ_CQMPQNENT, 11*f1_fFUNQAMgNTALg_gXAM1 - 4 QUESTION. 1.21 (1.00) Which DNE of the f ollowing is correct concerning the operation of the Electronic Direct Reading Dosimeter (EDRD)?
- o. The EDRD can display total dose or dose rate.
- b. The EDRD chirper chirps f or each 0.5 mrem tot al integrated dose,
- c. The EDRD is the primary official record for exposure received in a high radiation area.
l' c:1. The 'EDRD is a scintillation type of radiation detector. 1 l l l l l l e (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
t-1.+' REACTOR PRINCIPLES g'.) THERMODYNAMICS p Pega 25 IZZl_9NQ_CQDEQNENI N___1131_1EyNQ@DENI@6S_gl@D1 v i QUESTION 1.22 (1.00) Whicn ONE of the f ollowing correctly describes the f unction of the 13.8 KV and 4.16 KV bus breaker " maintenance / normal" switches?
- a. The " maintenance / normal" switch bypasses the electrical auxiliary board handswitch to allow local operation.
- b. The " maintenance / normal" switch bypasses the f ast bus transf er f unction to allow testing of the residual transfer function,
- c. The " maintenance / normal" switch bypasses the overcurrent time delay relay to allow an instantaneous trip during an overcurrent condi tion.
- d. The " maintenance / normal" switch bypasses the sych check relay to allow closing on a dead bus.
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
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, ~ 1-( 1.' ,Pcgg 2$
[ , REAGIQR_ERINQ1P(ggl:-l(731_THgRMQQYif3Migg'l1131_fEyNp6DENI66S_
,(7%) AND COMPONENT p . ; .t .:
lCUESTION- 1.23 (1.00) L , Operation of a Positive Displacement. Pump with insuf ficient Net Positive Suction Head..(NPSH) will probably cause which DNE of the f ollowing to J. cccur? (Bel ect the ONE best answer below)
- a. Excessive slip
. b". Decreased pump speed
" . "iz:;;it / 1 err
- d. Air binding
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) i
ig_ REACTOR PRINCIPLES %) THERMODYNAMICS Pago 27-( 77,) ANQ_ COMPONENT 11%)- (FUNQAMENTALg_gXAM1 l.: . .
}
QUESTION 1.24 (1.00) Which GE of the f ollowing correctly describes how the letdown domineralizer is prevented f rom - diluting . RCS boron concentration?
- o. By' limiting' the letdown flow rate through the demineralized
- b. By running borated water through the domineralizer prior-to usage
- c. By limiting letdown temperature through the demineralized
- d. By constant. addition of borated water downstream of the domineralizer i
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1z;__BE69198_EBINCIE6E5_1731_IBEBdQQyN9digg Pago 2B (77)-ANDCOMPONENT[jl131_JEUNQ@d[NI@(g_g!@dl() 'a .>
-QUESTION 1.25 (1.00)
Which ONE of the f ollowing correctly describes why some pumps have precautions limiting the number of pump starts in a given time period?
- a. Prevent damage to pump bearings due to axial starting forces
- b. Prevent damage to pump electrical components due to overheating
- c. Prevent damage to breaker trip devices due to repeated cycling
- d. Prevent damage to downstream piping due to water hammer i
(***** END OF CATEGORY 1 *****)
l- 21- EMERGENCY AND ABNO L PLANT EVOLUTIONS f~ pegg 29
-(27%) '.
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,gtu_ EMERGENCY AND'AgNO R g PLANT EVOLUTIQN@ .
Pcg3 30 W
'4 J2Z31
~
QUESTION. 2.01 (1.00)
.If reported by chemistry, which DNE of the f ollowing values would require cetion in accordance with Technical . Specifications?
Dc. Dose equivalent I-131 = 9.2X10E-1 uCi/ gram
~
b.. . Dose equivalent I-131 = 6.2X10E-1 uCi/ gram
- c. Gross radioactivity l = 107/E-bar uCi/ gram d.- ' Gross radioacti vi ty = 62.5/E-bar uCi / gram l
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. 7 2[Y_ D Pcg3.31. :.
ENCy_8Np_89N9g_P69NI_Eitg6LJIl@Ngl I
~ QUESTION 2.62 (1.00)
WhichL ONE' of ~ the f ollowing is NOT an indication. which might occur during a ') Loss. of Secondary Cool ant? I
. . l Jo.. Outward rod motion
. j b., Containment. sump level increasing l
.c. Steam line radiation monitor alarm (s) d.' Feed . flow - steam flow mi smatch -
l l 1 i l 1
'l i
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Pcgo 32 nm 2___EMEBGgNQY_@NQ_@@NQB6(_P(@NI_Eyg6UIlgN@ _0
-QUESTION 2.83 (1.88) r Which ONE of the .f ollowing correctly describes why SG's are depressurized at the maximum rate to (ul ti matel y) atomspheric pressure during the q oxecution of EDP 19221, " Response to Inadequate' Core Cooling"?
- c. To reduce RCS pressure to allow the ECCS accumulators and' low pressure SI pumps to inject water -
- b. To reduce RCS pressure'to prevent the. formation of superheated steam in the~ core
- c. To reduce RCS temperature to' increase thermal driving head for natural.
circulation
- d. To reduce RCS temperature in order to collapse any steam void in the upper part of the reactor vessel i
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
Pogo 33
. Bc_RZ4LEDEBgENCL@NQ_Q@Ng3MS6_P69NI_gyg6911gNS- .7 iG' .
i..
'QUESTID'N 2.04 ( 3 . 00) '
~
Following a control room evacuation due to.. fire, control of all components has been.transfered to the shutdown panels. The shutdown panel switch for the 'B' SI pump i s "OFF" when a vali d SI signal is received. The pump.
. wills (Select the ONE best answer below)
- c. . Start, and remain running until SI is reset.
.b.' ' Start, and remain running until its associated breaker. is locally opened.
- c. Not start, butLthe operator may start the pump using.the shutdown panel switch without first resetting SI.
- d. Not start, but the operator may start the pump by first resetting SI-and then using the shutdown panel switch.
i l l I l l l 1 l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ _ _ _ _ _ . - - _______________J
2h EMERGENCY AND A" NORMAL PLANT'E00LUTIONS Pcgy 34 27%) . {]- QUESTION 2.05 (1.E%) With ' the pl ant in Mode 5 on RHR, an unisolable leak in the Component Cooling Water (CCW) train occurs on the.'A' header, placing the 'A' train.ofiCCW out of ~ train CCW pump service. .Whichcommon DNE of discharge the-Lf o11owing correctly describes the action ~ required by ADP 18020, " Loss of.
-Component Cooling Water", for affected loads?
- a. The A Train RHR pump must be secured to prevent RHR heat exchanger damage due:to loss of cooling water flow,
- b. The A Train RHR pump.must be secured to prevent ~RHR pump seal damage due to loss of seal cooling.
~
- c. The A Train Spent Fue1 Cooling pump must be secured to prevent SFC heat exchanger damage due to loss of. ccoling water flow.
.d. The A Train Spent Fuel Cooling pump must be . secured to prevent SFC pump seal damage due to loss of seal cooling.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
I;' 22, , EMERGENCY AND ABNO~*'L PLANT EVOLUTIONS r- Pcga 35 3.!2ZE (/ 's
-QUESTION. 2.26 (1.20)
! If the f ollowing indications are received in the Unit 1 control room while I ot full' power, which DNE of the following 120VAC vi tal - instrument _ panel s has probably been' lost? INDICATIONS:-
.All Channel'II Trip' Status. Lights energized Loss of Power Range Channel N-42 & Intermediate Range' Channel N-36
' Inverter 1BD112 Trouble Alarm at EAB
.' .a. IAY1A
- b. 1BY1B
- c. IBY2B
- d. 1CY1A
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2..' EMERGENCY-AND A?NOR""t PLANT EVOLUTIONS 7 g- Pcg3 36 (27%) . (,/ s,) t QUESTION 2.07 (1.00) Immediately following a loss of offsite and-onsite power (station blackout), the STA reports the status of Critical Safety Fuctions as: Subcriticality - Green Core ~ Cooling - Orange (go to EOP-19222-1/FR-C.2) Heat Sink - Red (go to EOP-19231-1/FR-H.1)
' Integrity - Green Containment - Green Inventory - Yellow (go to EOP-19263-1/FR-I.3)
Which ONE of the f ollowing best describes the correct procedure to use in rosponse to the transient.
- a. " Loss.of All AC Power", EOP-19100/ECA-0.0
- b. " Response to Degraded Core Cooling", EDP-19222-1/FR-C.2
- c. " Response to Loss of Secondary Heat Sink", EOP-19231-1/FR-H.1
- d. " Response to Voids in Reactor Vessel", EOP-19263-1/FR-I.3 1
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l I I
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4,- QUESTION '2.08 (1.00) Uponl a' loss of.. Auxiliary Component Cooling Water. ( ACCW), the affected RCPs must be secured within ________ minutes. (Fill 'in1the blank) l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l-- i
[; L2.4 EMER~ENCY'5AND'ABNOR - PLANT EVOLUTIONS Pcgo 33. [,I
.(27%)-
, *h.
J QUESTION: 2.09- ( 1'. 00 ) ' Which DNE of the following buildings'are NOT served by the fire. protection ecismic dry standpipe system? a.: -Containment Building l
- b. Fuel Handling Building
-c. Auxiliary. Feed Pump House d.. D3esel Generator Building-
- l
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
.- - ._. - _ _ _ . . __ _ __ _____.____---_____---___-______--_-_._--__-O
f: 2 .. EMERGENCY AND ARNO g L PLANT EVOLUTICNS. n Paga 39 1222Lt y U_
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l.
-QUESTION '2.10 (1.00)
'Which'ONE.of the f o11'owing procedures or corditions does NOT require L amergency boration? ,
1-
- c. " Response to Nuclear Power Gsneration/ATWT" (EOP-19211-1/FR-S.1)
- b. " SOURCE RANGE HI FLUX LEVEL AT SHUTDOWN" annunciator response
- c. Shutdown margin less than' required by Technical Specifications
- d. " Rod Control System Malf unction - Uncontrolled Continuous Rod Motion" (ADP-1BOOO3-1)1.
t (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
m 7 ....,.. . . . L Zi;__EDEB9ENQL,9NQ,@gNQBMA(_E(@NI_gyQ((lligNE ' Peg 7 4*) 12ZZL. (f , O..
. QUESTION. 2.11 ( 1. 00) .
D:; scribe the pref erred . emergency' boration 'f.lowpath up to the charging pump !
-cuction. - Include the borated water source, dri ving .f orce, remotel y.
/ operated. valve (s) and control room indication (s) .
l. i i i i i 1 l l 4
)
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- _- _-________2-_______-_____._--._-_- -. _. . _ . _ _. )
2a _gdgBGgyCy_gyD_ABNO L PLANT EVOLUTIONS Pcga 41 42Z31 - C7
~
QUESTION 2.12 (1.00) Which DNE of the f ollowing correctly lists annunciators which would be expected if the controlling channel of pressurizer pressure,(P-455) failed low? e.. "PRZR LO PRESS /P7 REACTOR. TRIP"-
"PRZR LC PRESS ALERT" "PRZR CONTROL LO PRESS'AND HEATERS ON" "PRZR PRESS LO PORV BLOCK"
- b. "PRZR PRESS SI REACTOR TRIP"-
"PRZR LO PRESS SI. ALERT" "PRZR CONTROL LO PRESS AND HEATERS ON" "OVERTEMP delta-T BLOCK ROD WITHDRAWAL"
- c. "PRZR LO PRESS ALERT" "PRZR LO PRESS SI ALERT" "A COLD OP ACTU VLV HV-8000A NOT FULL OPEN" "A RCS PRESS APPROACHES COLD OP LIMIT"
- d. "PRZR LO PRESS ALERT" "PRZR LO PRESS SI ALERT"-
"PRZR CONTROL LO PRESS AND HEATERS ON" "OVERTEMP delta-T ALERT"
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
- 2. 'EMERGENC'/ AND ABNO PLANT EVOLUTIONS Pega 42
.c J2ZZ1 pd QUESTION 2.13 (1.00)
Which DNE of the f ollowing correctly. describes why RHR flow is limited when RCS water. level is at, or less than, mid-nozzle l evel .
- a. Minimize the potential for loss of pump suction due to gas entrainment from vortex formation
- b. Minimize the potential for loss of pump suction due to steam binding from cavitation c .- Minimize the potential for. pump overcurrent trip from runout due to low discharge pressure d.. Minimize the potential for pump overspeed trip from runout due to low discharge pressure
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
!2--EMERGENCY AND ABNORM ' PLANT EVOLUTIONS-Pcg3 43 RZ 1 W -
O' y; . < -QUESTION .2.14 ( l '. 00 ) j.
~
-Which.ONE of.the fc11owing correctly lists conditions,which must be met to openLthe A. train RHR' containment sump suction valve (HV-0811A).
4 Both loop suction valves closed -(8701 A and B) lCCP.to RHR. suction: closed (8804A).
- b. One of two loop suction valves closed (8701A or B)
CCP to RHR suction closed (BB04A)
.c. - Both -- l oop . sucti on ' val ves cl osed (8701A and B)
'RWST suction closed (8012A)
- d. One of. two loop suction. valves closed '(8701 A or B)
RWST. suction closed (8012A) l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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- 2.* EMERGENCY AND A'ND% hL_ PLANT _EVQLUTIQNS ; Pcgo 44'
.(27%)
f- 1
- 4
-QUESTION 2.15 '( 1. 00 )
In accordance.with ADP 18007, " Chemical- and. Volume Control System .. Malf unction", duri ng . a l oss of makeup'and seal injection flow, special procedures to restore seal injection flow must_be used to prevent excessive
- thermal. stresses if'RCP #1 seal temperature has exceeded __________ deg F.
(Fill in.the blank.above.) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
p:. ~. . . . .w ( i 2 -:: EMERGENCY r AND ABNO PLANT'EVOLUTIONSi- .Pcgo.45 7j
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N ' P p- , F:. :l QUESTION 22.16- (1.00) ~ . ( i State the, definition'. of ~ the term::'?stabl e" as used in : the EDP's. [. L 'l :: L k I$ r' (? :\ . j_. -- e (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
12A 5 'Pcga.46 ENGY_eND_eBN9g_P(@NI,,,ENQLyllON@ - r-l q l
-QUkSTION- '2.17 (' 1. 00 )
- EOP,19001-C[ "ES-0.1, Deactor Trip Response," requires restarting:ene RCP:
-if;RCP's are not' running.- Which.RCP(s) are preferred for starting, and why?-;
i. O (*****. CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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p p o#cocoooooo ocooomooomo -- , -v- -
- p. s 1
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- 2.1B.
~
i - GUESTION ( 2. OS ) - List,'iniorder..the FIVE'immediate. actions required by EOP-19211, "FR-S.1,.
' Response to Nuclear! Power Generation / ATWT. " .. Do not . include substeps or R3sponse.Not.Obtained actions (RND's).
L. 1 1 er s (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
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- 2:l__EDEBEENgy_@NQ_@BNQ@_PL@NI_Eyg(yligNS f. Pega 43 e .!2Z4L
[ p 1 QUESTION 2.19- (1.00) Following ' a small break Loss of Coolant Accident, SI flow has been reduced i n ; accordance ori th EDP 19010-C, "E-1, Loss of Reactor or Secondary Cool ant", and EDP - 19011-C, _"ES-1,1, SI Termination". What are the TWO conditions (listed on the foldout page) which require SI to_be reinitiated? (Assume adverse containment DOES'NOT exist.) l . 1 l l l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
- 2_-__- ___ __ _- _ _ _ - . _ _ _ .
U?L 2U _gDg8@gNCy,999,9'Ng _ _P6@NI_Eyg6UllgNE- - Pc g > . 48P 12?3L GUESTIDN' 2.20 (1.00) Which : ONE; of1the f ollowing f actors. is; NOT used to enhance post-LOCA natural ci rcul ati on-- f l ow?
- a. -Maintain at least one. SG level in narrow range b.. Maintain PRZR pressure > 2000 psia
-c.. ~ Maintain PRZR level > 50 7.
Ld . . _ Maintain SG pressure constant or decreasing (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) t
2f__ELTBHNCy_ egg _esygg_eLeyI_gY26WIlgNS J2Z31
'Q Pcg3 50 QUESTION 2.21 (1.80)
'In responding to a Steam Generator Tube Rupture, af ter. the transition has .
been made from EDP-19000, "E-2, Reactor Trip or Safety Injection", to
.EOP-1903B, "E-3,' Steam Generator Tube Rupture", which DNE of the f ollowing is correct-concerning the usage of RCP trip criteria *?
- a. RCP's should be tripped anytime during EOP-19030 if the criteria are met.
- b. RCP's should be tripped'during EDP-19030 only if the criteria are met
' when the operator is specifically required to check the criteria at step 1.
- c. RCP's should be tripped during EDP-19830 only if the criteria are met bef ore isolating the ruptured SG(s) at step 3.
- d. RCP's should be tripped during EDP-19038 only if the criteria are met before initiating RCS cooldown and depressurization at step 14.
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s i [ 2[__gDgRGgygy_@yD_$*_NOQg6_PLANYi 42231 , t EVOLUTIONS () Pogo 51 QUESTION 2.22 (1.00) Following a. double-ended SG tube rupture, EOP-19030, "E-3, Stean. Generator Tube Rupture", has been successfully executed through the completion of RCS cooldown and depressurization, the securing of ECCS fl ow, and the restoration:of normal charging and letdown. As.RO, you note the f ollowing conditions: Ruptured SG Level - 60% and INCREASING Pressurizer Level - 55% and INCREASING Which ONE of the f ollowing correctly describes the action which should be token to establish equilibrium conditions (steady SG and PZR levels)?
- a. Reduce charging flow, decrease RCS pressure using PZR spray
- b. Increase charging flow, decrease RCS pressure using PZR spray
- c. Reduce charging flow, increase RCS pressure using PZR heaters
- d. Increase charging flow, increase RCS pressure using PZR heaters
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****>
,_=--_ -- _ _ _ - _ _ _ _ _ _ _ - - - - -- - -- _ _ _ _ - _ _ _ - - _ . -
2r.__EDEBGENCL@ND_@@NQBd@6_P6@NI_EygL(JllgN@ ' Pago 52. m zi o o.
. QUESTION 2.23 (1.00)
Which DNE of the following correctly completes the statement below describing the purpose for EOP-190127 EOP-19012 "ES-1.2, Post-LOCA Cooldown and Depressurization", provides guidance f or plant cooldown and depressurization ~ f ollowing ' ECCS actuation
.due. tot
- a. Small LOCA's where the SI termination criteria is c.itisfied
- b. Small LOCA's where the SI termination criteria cannot be satisfied.
- c. Large LOCA's where the SI termination criteria' is satisfied
- d. Large LOCA's where the SI termination criteria cannot be satisfied l
l (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2.*- EMERGENCY AND ABNO g PLANT EVOLUTIONS. C~ Pcg3 53
. ( 2 77. ) W .
4 QUESTION ~ ,2.24 (1.00) If. refueling operations were in progress.an Unit 2,.which.ONE of_the following. radiation monitor alarms would nrQUIRE containment evacuetion if
- o. valid 'high' radiation alarm was received?
I c. . . Containment' Personnel Access Hatch Area Monitor, 2-RE-0004. b .- ' Containment Vent Particulate Monitor, 2-RE-2565A
- c. Containment-Seal Table Room Area Monitor, 2-RE-0011 i 'd.. Fuel. Handling Building Area Monitor, 2-RE-0008
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) l
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2[__GOsBEENGY_eNQ,@@NQ["'6_E(@$1_[yQ(yligN@ Pago 54
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1 1 l
' QUESTION 2.25 (1.00) j While at 100% power, a sudden unexplained decrease in instrument air pressure occurs. Which DNE of the following' correctly describes when the reactor should be. tripped in accordance with ADP-18028, " Loss of Instrument Air"?
- o. The reactor should be tripped if instrument air pressure lowers to less than 70 'psig f ollowing isolation of the service Mr header.
- b. The reactor should be tripped if instrument air pressure lowers to less than 70 psig following isolation of the service air header and after ensuring all air compressors are running.
- c. The reactor should be tripped if instrument; air pressure lowers to less than 70 psig f ollowing isolation of the service air header and isolation of the turbine building instrument air header.
- d. The reactor should be tripped it instrument air pressure lowers to less than 70 psig following isolation of the service air header and establishment of an open instrument &ir header between units 1 and 2.
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
2[ EMERGENCY AND A~ nod hL_ PLANT _ EVOLUTIONS 12Z3L () Pago 55 QUESTION 2.26 (1.00) Which ONE of the f ollowing correctly lists the order in which maj or loads cre sequenced onto the 4.16KV ESF busses f ollowing a loss of normal AC cupply power (undervol tage condi ti on) WITHOUT the pressence of-a SI signal?
- c. 1. Component Cooling Water (CCW) Pumps
- 2. Auxiliary Component Cooling Water-(ACCW) Pumps
- 3. Nuclear Service Cooling Water (NSCW) Pumps
- 4. Centrifugal Charging Pump (CCP)
- 5. Auxiliary Feed Water (AFW) Pump
- b. 1. Centrifugal Charging Pump (CCP)
- 2. Component Cooling Water (CCW) Pumps
- 3. Auxiliary Component Cooling Water (ACCW) Pumps
- 4. Auxiliary Feed Water (AFW) Pump
- 5. Nuclear Service Cooling Water (NSCW) Pumps
- c. 1. Centrifugal Charging Pump (CCP)
- 2. Auxiliary Component Cooling Water (ACCW) Pumps
- 3. Component Cooling Water (CCW) Pumps
- 4. Auxiliary Feed Water (AFW) Pump
- 5. Nuclear Service Cooling Water (NSCW) Pumps
- d. 1. Component Cooling Water (CCW) Pumps
- 2. Nuclear Service Cooling. Water (NSCW) Pumps
- 3. Centrifugal Charging Pump (CCP)
- 4. Auxiliary Component Cooling Water (ACCW) Pumps
- 5. Auxiliary Feed Water (AFW) Pump I
(***** END OF CATEGORY 2 *****)
',g
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)
t I l e (***** CATEGDRY 3 CONTINUED ON NEXT PAGE *****)
2[__EbeNI_SygI(($g[J}g% h_D_E(gNI;Wigg_ GENE 51C .O e=ao 57
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j- QUESTION' 3.01- (2.00) Fill in the eight.(B) blanks below with. the applicable coincidence and setpoint for the-four listed automatic / manual rod stops. ROD STOP COINCIDENCE SETPOINT 2 1.- 'C-1, Intermediate Range. ___________ IR current equiv. to ______%
-2. C-2, Power Range ___________ _______%
- 3. C-3, DT delta'T ___________ _______% below trip setpoint 4.. C-4,.OPEdelta P. ___________ _______% below trip'setpoint
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) _-____-_--_--_______-______-___u
,. i L.i_ELONI_gygIgdg_Hg3 Q_E(9NI WlQg_Q{Ng81Q .gQ Paga 58 EEEEQNglgl(lll[g_11,21
- j. QUESTION 3.02 (1.00)
Which DNE of .the f ollowing correctly describes the f unction of multiplexing in.the Rod' Control System?
's.- Provide current sequence orders for the power cabinets
- b. Provide. control bank overl ap signals to the master cycler
- c. Prevent . logic - cabinet output when an urgent alarm is recieved
.d.. Prevent the power cabinet from moving more than one group at-a time l
l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) u _ _ _ - _ _ - _ _ _ _ _ _ - _ _ _ _
, . BEE S E le_ _I E. _ .
' QUEST I ON -'- 3 . 18 3 .' ' ( 1. 75 ) -
R ' Assuming the plant i s in Mode l', list ~ the. three automatic Saf ety Injection cctuation signals, . with the required coincidence and setpoints f or each. l' l~ l l l l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l
Ji__ELONI;@y@ igm @_1}@Z M D_E(SNI WlpE_QgNEBIC /] Pcg3 63 BEEEQN@l@l(lllE@_J1W,1 V 4.'. 9
- QUESTION 3.04 (1.00)
Which ONE of the f ollowing sets of RCS_ parameters is correct concerning the.
.sffects of restarting an idle RCP while at power?
- c. Unaffected loops Tave - DECREASE Affected loop Tave - INCREASE Unaffected loops delta T - REMAIN THE SAME Af f ected loop delta T - INCREASE-
-b. Unaf f ected loops Tave - INCREASE Af f ected loop Tave - DECREASE Unaf f ected loops delta T - REMAIN THE SAME Affected loop delta T - INCREASE
- c. Unaffected loops Tave - REMAIN THE SAME Affected loop Tave - DECREASE Unaffected loops delta T - REMAIN THE SAME Affected loop delta T --INCREASE
- d. Unaffected loops Tave - DECREASE Affected loop Tave.- INCREASE Unaf f ected loops delta T - DECREASE Affected loop delta T - INCREASE
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
3 * ' PLANT ~ SYSTEMI '(3'M) D PLANT-WIDE GENERIC ' Pcga 61
- BEEPQtggig16111gS_J1__1 }y
. QUESTION 3.05- (1.00)
Which- ONE of the f ollowing correctly . lists High Hrsad Saf ety ' Inj ection flowpath' components which are installed on BOTH LNITS 1 and 27
.'c. BIT outl et' i sol ati on valves - (HV-8801 A & B)
BIT inl et i sol ation vavl es -(HV-8803A & B)
- b. BIT outlet isolation valves.(HV-8801A & B)
BIT flow indication-(FI-0917)
- c. BIT inlet isolation valves (HV-8803A & B)
BIT discharge pressure. indicaton (PI-0947)
- d. BIT inlet isolation valves (HV-8803A L B)
BIT flow indication (FI-0917) 1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) V E..__ . _ _.___._._._________ ___._.__ _ ._.____._ _ _____...___._ _ .____ _ _ _ _ ____ __ _ _ _ __
, :liL_ELONI_gygIgdg_Hg3L/'lQ_EL@NI;W1Qg_QgygglQ: . pig-) 62:
BEEEQNE1916111Eg_11L_t (,} . s. j -- DOESTION: 3.26 ( 3 . 00 ) - Concerning the' Reactor Cool ant Pump #3- seal ,. describe L the source and moti ve - l- f orce f or injection, 'and - to where the leakof f flows.
- l. .
l~ li I (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l
7 --_7-
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5 I . Pcgo 63.
' - - - E t # ! D e i l B I C I I I sli n3MPLANTSYSTEMS-(3PM)kDPLAN
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- CUESTION" '3.87.: (1.98)< ..
When verif ying equipment L status, f oll owing ai FI ini tation, the containment. cool i ng syst em - shoul d have ; ____________ .- (number ) containment cooling. fan (s)- _
-running-in ___________'(speed).
(Fillzin the blanks 'above).
}
.6 6 !'
e (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
r; y
~4 iE68NI_gygIEM3_l EZ.1 D_EL$NI; WIDE _GENEBIC .
Pcga 63
.BEEEONgigl(lll[S_11@Z.1 1
' QUESTION 3.08' (1.00)
Concerning the operation of the. Containment Low Range radiation.. mon'itor (1/2-RE-0002.or 1/2-RE-0003), which ONE of the fo11 wing' actions will, with no other ' action,- initiate a containment venti 11ation ' isolation? a.. : Resetting the Saf ety Related Display Console s
- b. Loss'of power to the Digital Radiation Monitoring System minicomputer
- c. Calibration' with the Data Processing Module in " BYPASS"
- d. Loss of power to.the Radiation Monitor
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
m ND_E(@NI;WlDE_GENEBIC Pcg6 65 J31__ELONI_SYSIEMS_13]3
,BEEEONgig1(lll[@_11031_
())'
,4 i.
QUESTION 3.09 41.00) Which DNE of the f ollowing correctly lists the MINIMUM Auxiliary Feedwater (AFW) pump and SG configuration needed"to remove 100% of the design reactor-decay heat load?
- a. One turbine driven AFW' pump, or two motor driven AFW pumps supplying two intact'SG's L
b.. One motor driven AFW pump supplying two intact SG's
- c. .One turbine driven ACW pump, or two motor driven AFW pumps supplying one intact SG
- d. One motor driven 4Aw pump supplying one intact SG
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
Ici_ELONI_gy@IEd@_1}g31(fp_EL@NI:WlQg_GEdgB1C Pcg2.66' ' (BEEEQNgigl(llig@_110((_ (])' v . t QUESTION '3.10 (1.00) With Unit 1 at 100%, a periodic surveillance is being conducted from the control room on the A train Auxiliary Feedwater (AFW) pump. The pump is running with the miniflow recirc valve (1-HV-5155) open, and the discharge
' fl ow control. valves (1-HV-5137 and -5139) shut. Which ONE of the f ollowing correctly describes how the system will respond with no operator action if 2/4 - l ow l evel alarms are received on SG #1?
- o. There will be no motor driven AFW pump start signal generated because a second SG with 2/4 low level alarms is required, and the lineup will not change
- b. A motor driven AFW pump start signal will be generated, but the lineup will not change c.4 A motor driven AFW pump start signal will be generated, the discharge flow control valves will automatically go full open, and the miniflow valve will remain open
- d. A motor driven AFW pump start signal will be generated, the discharge flow control valves will automatically go full open, and the miniflow valve will go shut
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
!0 3 .,__ PLANT _@Y@TEMS (38% g)D PLANT-WIDE' GENERIC g ' Paga 67 RESPON@l@l(II1Eg_11w__1 l QUESTION 3.11 (1.00) Which DNE of the f ollowing correctly describes the flowpath for r el i ef of cn overpressure condition in Gas Decay Tank'(GDT) #17.
- a. The GDT #1 r el i ef valve discharges directly to the plant vent system downstream of RV-0014 (trip valve for RE-0014)
- b. The GDT #1 relief valve discharges directly to the plant vent system upstream of RV-0014 (trip valve for RE-0014)
- r. . The GDT #1 relief valve discharges to GDT #10, and the GDT #10 relief valve discharges directly to the plant vent system downstream of RV-0014 (trip valve f or RE-0014)
- d. The GDT #1 relief valve discharges to GDT #10, and the GDT #10 relief valve discharges directly to the plant vent system upstream of RV-0014 (trip valve for RE-0014)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
;3; ' PLANT SYSTEMS (38%)(s~T -
D PLANT-WIDE GENERIC y' E 3 Pcgp 68 R_ E_SP_ON_S_I __ _ _B_I L__I ___T_I E S_' __ _( 10_%_) . 9,
- v. .
QUESTION 3.12 (1.00) Match the f ollowing Solid State Protective System (GSPS) power supply failures in Column I with the appropriate effect upon the plant from Column II.
'(Fill'in the blank in Column I with the ONE best' answer from Column II.)
' Column'I Column II
- 1. ______ Loss of one 48 VDC power- a. Train (s) remain (s) operable; supply in Train A No reactor trip
-2. ______ Loss of one 48 VDC power b. Train (s) remain (s) operable; supply in both Trains A Reactor trip occurs and B
- c. Trai n (s) is/are inoperable; No reactor' trip
- d. Train (s) is/are inoperable; Reactor trip occurs
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
.. n-It__EL@NI_SYSIEMS_1}gZ.lbgND_EL@NI;WlDE_G[NEBIC .
Pago 69
..- .RggEQN$lgl(lllgg_11gfl_
7 .-
' QUESTION 3.13 (1.00)
Which DNE. of the f ollowing is correct concerning operation of the ESF
~ Feedwater Isolation signal?
- a. A Feedwater Isolation initiated by:a Reactor Trip with Low.Tavg signal snuts the FW isolation valves and trips the Main. Feed Pumps
- b. A Feedwater. Isol ation manually ini ti ated ' shuts the FW i sol ation val ves and trips the Main Feed Pumps
- c. A Feedwater Isol ati on initiated by a SG Hi-Hi Level signal' shuts the FW isolation valves and trips the Main Feed Pumps d.. A'Feedwater Isol ati on initiated by a Reactor Trip with Low Tavg signal requires both clearing-the P-4 signal and operating the Feedwater Isol ation " Reset" to clear i
<***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
)
t._ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ J
,,l 3[ : PLANT. SYSTEMS ('38Z1 D PLANT-WIDE GENERIC; Pcga 7D
,, . RE_SPON_ S_I _B_I L_ _I _T_I ES__( 1_07_._)
I, s i
, :' QUESTION 3.14' (1.00)
/
.A Fuel Handling Building Ventilation system isolation . signal can be 7~
generated by a high radiation signal on a minimum of (coincidence) detectors, and starts ________ (number) post accident filterL g -units. (Select ' the ONE answer below which best fills in the blanks)
- c. .1/2 ; ONE-i:. b. 2/2 ; ONE
.c. 1/2 ; TWO
-d.. 2/2 ; TWO I
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1 3.. PLANT SYSTEMS-(3"*X g)D PLANT-WIDE GENERIC Pago 71
- RggPONHIBIL11155 (13
(]) '. QUESTION 3.15 (1.00) Which ONE'of the f ollowing statements is correct concerning Rod Insertion
. Limits?
-a. .The Rod-Insertion Limit Computer Comparator calculates Rod Insertion Limits using auctioneered Tavg and Nuclear Power as inputs.
- b. The Rod Insertion Limit Computer Comparator provides an automatic rod stop at the ROD BANK LO-LO LIMIT alarm to prevent automatic rod motion
-from exceeding the Rod Insertion Limits.
c, Technical Specifications allow rods to be below the Rod Insertion Limits for up to two hours.
- d. Technical Specifications for Rod Insertion Limits do not apply during critical Mode 2 operation.
l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
'3p;_P(ANT SYSTEMS (30%)hDPLANT-WIDE 1 GENERIC (" Pago 72 BEEEONgl@lL111EE_11Ff1- _
QUESTION. 3.16 (1.00) Which DNE of-the following correctly describes the effect'of-undercompensating an Intermediate Range Nuclear Instrument detector (s)?
- a. If a minimum of 1/2 IR channels is undercompensated, the IR detector may' prevent automatic re-energizing-of the source range following reactor shutdown
- b. If a minimum of 2/2 IR channels are undercompensated, the IR detectors may prevent automatic re-energizing of the source range following reactor shutdown
- c. If a minimum of 1/2 IR channels is undercompensated, the IR detector may prevent receiving P-6 before the source range reaches the trip setpoint during reactor startup
- d. If a minimum of 2/2 IR channels are undercompensated, the IR detectors may prevent receiving P-6 before the source range reaches the trip setpoint during reactor startup l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- -- -- - ~ - - - - - - -
/o m 'g .-. +
p t3;.= PU*".17 SYSTEMS'(3%Y. h p_P(@NI; WIDE _GENEBIC /~C Pegof73 " FJbv., > R5eE9N$lg16111gg_Jlyg .V: p . ,. Pi , j-] _ , M h4 L;, . QUESTION. 3.17 ( 1. BB)l
; Whi ch DNE~'of - the f ol'1 owi ng DOES1' NOT occur 'upon recei pt of l an "SI" si gnal b'y.
l the Nuclear Service Cooling Water (NSCW)' system?-
.a . - .Two NSCW pumps perLtrain start
- b. 1 NSCW cooling tower bl owdown isolates -
.c. Containment auxili ary. cooler NSCW isolation valves shut.
- d.. NSCW tower bypass valves shut:
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) .- m_m_ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ _ _ . _ . _ _ _ _ . . _ _ _ _ . _ . _ . _ ___ __ __ _ _ _ . . _ __ _._ .)
- P;f '. .
l: h _ i E L O N I ,jjb'g l g d p _ 1 3 g 3 b ; N Q _ P L A N T - W I D E G E N E R I Q. A Pcgo.'74 _
;;BE9E9N$lgl(lligg_fl@H
- a. ;. 1 1, j
; QUESTION 3.18- (1.BB) -' .
Descri be . the fl owpath. used f or cooling the . Pressuri z er . Reli ef -- Tank',
. including' tank suction and return. locations, driving f orce, ano. source of
-cooling; 1
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) L---__-___--_-___. . - _ _ _ _ - - _ ._ _ _ _ _ _ .
__ PLANT' SYSTEMS (38%)h_D' PLANT-WIDEGENERIC i 'Pcg2 75
- 1- . JEEEON@lgl(ll}[$_ fig 31 A
1 l o I 'GUESTION -3.19 (1.BB)
LThefpressurizer and pressure control system are' designed to allow f or l oadi ng and unl oadi ng at ________% per minute, or step load changes of
+ 'or _____,.__%, with rods in automatic, without. causing a reactor trip.
1. 1. l l 1 l l . l-l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) U-_a_ _ __-__ _ _ _ _ - - - _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _
Is__P(@NI_$y@lgMQ_J}$3) NQ_E(@N1W1pE_GENg819 Pcg3 76 RESPONSIBILITIES ( ) () , QUESTION 3.20 (1.00) j Which ONE of the following is correct concerning the design of'the Pressurizer Level Control System and its associated charging pump controlers?
- o. The Centrifugal Charging Pump flow controller, FK-121, has a low flow limit set at 25 gpm which affects both automatic and manual operation l of the Charging Flow Control Valve, FV-121.
b.- The Centrifugal Charging Pump flow controller, FK-121, uses actual charging flow for feedback, but the Positive Displacement Pump speed controller, SK-459A, does not.
- c. The Positive Displacement Pump will fail to minimum speed upon loss of the electric control signal.
- d. The Pressurizer Level Master Cont r ol l er , LK-459, is a Proportional plus Integral plus Derivative (PID) type of controller.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
.,7-------
if,- ? I f.3) PLANT SYSTEMS (3't% D PLANT-WIDE' GENERIC . Pigg 77. f;g,. BtBED951a16111Es 11 a _. __
'GUESTION: 3.21 ( 1 ; 99)
; Whi l e l at ,: 192% . power , a steam generator Atomspheri c Reli ef' . Val ve _( ARV)~ fails
- f ul'1 ' open. Which ONE of . the f ollowing correctly lists the expected increase in -total ' steam flow,7 assuming no' automatic reactor ~ protective or --
control action occurs?
- o. 2%
.b.- 4%
- c. 6%
- d. - 8%
l l' l-l (***** CATEGORY 3 CONTINUED ON NEXT PAGE **ss*)
=__--____-___--__-___-__--___--_--_
31.
- ' LE'._E($N _EYEIEEE_ME3 M_Q,E(@NI WJpg_@gNggig. ' ' '
/T pegg 73
;BEEEDNgig1(111gg,,i}g 1_ V y
j GUEST!DN- 3,22 (1.Og)
' Describe the f eature that prevents suppl ying 120 VAC vital b'usses wi th dual power supplies simultaneously.
i l l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE ***ss)
t "4
- 23r PL'NT' SYSTEMS-(38'ff"^ND' PLANT-WIDE GENERIC r Pcgo 79; k.
BEEP 9Ngigl(lligg_,[kjl Q QUESTION- 3.23' (1.99) The 125 VDC_ESF system.(2AD1 1BDI, ICD 1 & 2 DD1 )' batteries'are sized to: last f or ' __________ hour s - at full load during a loss of; AC power to the battery charger -(s) .
-(Select - the DNE answer below which best f a lls in the blank. )
- o. 1.50- ?
- b. 1.75 ,
- c. 2.08
- d. 2.75.
s W l (***** CATEGORY 3 CONT 3NUED ON NEXT PAGE *****)
;Ir_iPLANI_Sy@IEDS_l}@Z A)ND_ PLANT-WIDE _ GENERIC Pago CO RESPONSJgILITIEg_f1W_;l
.e .-
4 QUESTION 3.24 (1.00)
.Which DNE of the f ollowing correctly describes the flowpath f rom the 2A-Residual Heat Removal (RHR) pump discharge to the 2A Safety Injection (SI) pump suction during post-LOCA recirculation operations?
- a. Flow goes f rom the 2A RHR pump discharge directly to the suction of-the 2A SI pump
- b. Flow goes from the 2A PHR pump discharge, through the 2A RHR heat exchanger, and then to the suction of the 2A SI pump
- c. Flow goes f rom the 2A RHR pump discharge, through the Centrifugal Charging pump suction header, and then to the suction of the 2A SI pump i
- d. Flow goes from the 2A RHR pump discharge, through the 2A RHR heat exchanger, through the Centrifugal Charging pump suction header, and then to the suction of the 2A.SI pump l
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
_,,'.;" fa L ,.g) e . .. .
- f. ': 3. - PLANT " SYSTEMS '(3"?/.f~..LND PLANT-WIDE GENERIC . V- - Pcg3 B1'-
t -*BEEEQNglgl(lll@@_11gfl t ., QUESTIDN. '3.25 (l ' .58)~ Fill in.thelfollowing blanks'with"the. correct parameters for the Safety
; Injection Pumps.
1.. l' : Design shut off: head _____________.'psig in..the RCS.
. Design runout heads" ____________ psig Rat ed f l ow s ____________ gpm i.
<ws
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- - _..m._ _ . _ _ _ _ _ _ . _ _ _ _m__.__-____._ _m__._________
.y. ,
5 A__EbeNIifygI[$@,Hg3 f NQ_P(ANT;W1pg_EgNgRIGl f Pcg3 C2 BE9EQNgig1(lligg_( -
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$ n. :-
~
-QUESTION .3.26 - ( 1. 90 )' -
l -The' Emergency Diesel Generator.(EDG) Fuel 011 Storage. Tanks.. (FOST) are . DESIGNED to provide:at least __________. days:of EDG operati'on with.ESF: loads under accident c ond i t i er. s. (Sel ect the , ONE answer bel ow which best' f ill s in .- the- bl ank/ above. )
'c. 3-
- b. 7
- c. 14.
d.- '31 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
V .a p
-3; PLANT' SYSTEMS ' (3"78ND' PLANT-WIDE GENERIC ( Pcga B3 p .,L , S E g E O t!S l B 1!:l l l E E _ 1 1 B 1 g,
- QUESTION 3.27 s i . EEt- C) .OO ich DNE of . the f ollowing correctly describes syste response if operator-
.cr causes an inadvertent Train "A" SI signal-to e sent to the Safe rds Sequencer (s) during surveillance test' g7
- c. Onl y (he Train A- di esel will start
. Onl y th'a Trai n A sequencer will operate No loads W 1' sequence on
.b. Only the Trai diesel will s rt Only the Train sequencer w) 1 operate Only Train A loads ill seguence on
- c. Both the Train A and EJ/ (esels will start Only the Train A sequ'enceNwill operate
~
Only Train A load /will seqdence on
- d. Both the Traip and B diesel 41 start Both the Tr in A and B sequencers'w(11 operate Only Trai A loads will sequence on N' O. Both he Train A and B diesels will start B
the Train A and B sequencers will oper gs th Train A and B loads will sequence on E R., m (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) ____-_-___-__-_-____-_____D
l} __Ek6MI_EYEIEUS LEEd*l D_E6@NI ylDE_ GENE 61C' Pcgo C4
'4- 'B53E0N31BlbJTigg 113 1
. QUESTION 3.28 (1.00) ihich 'ONE of .the f ollowing correctly describes the correct Digital Rod
. Posi ti on 'Indi cation (DRPI) system alarm which would be generated by an open
-or shorted' detector-coil?
La. DRPI urgent Alarm
- b. ROD DEVIATION annunciator
.. c . DRPI Data A (or B) Failure alarm d.~ ROD.'AT BOTTOM annunciator o
l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- 3. PLANT' SYSTCMS - (38%) D PLANT-WIDE GENERIC -
Pcga 85 RESPONSIBILITIES ( ) QUESTION 3.29 (1.00)
. Which DNE of' the .f ollowing is correct concerning normal operation of Halon 1301 fi re protection systems?
- o. Two detector alarms in the area of coverage are required to activate a Halon system.
b.- ' Hal on injected into a space will be carried to other spaces through the plant venti 11ation system.-
- c. Halon system activation can be detected by observing the white color of the released Halon gas.
- d. Areas covered by Halon systems include the plant compter room, the communications room, the Technical Support Center, and the upper and lower cable spreading rooms.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) 1
~
0 1 2:__ELONI,$Y$lgM@_f3@31_@ND_E69NI;WIDg_Q$NSBig O Page 86
.BEEEON@l@l(lll@@,flO31 QUESTION 3.30 (1.C0)-
- Which DNE of' the: f ollowing correctly describes the MINIMUM coincidence
~which will cause a reactor trip from low RCS flow with the plant in Mode 1 at 30%_ power..
- a. 1/3 flow transmitters in ONE loop sense less than 90% flow
- b. '2/3 flow transmitters. in ONE loop sense less than 90% flow
- c. 1/3 f l ow transmi tters .in TWO loops sense less than 90% ' flow
- d. 2/3 ' fl ow transmitters in TWO loops sense less than 90% flow l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) _ __z _ ___________________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ___
!s__E68NI_@y@I@MS_f@BZ. Q Np_E69NI;Mlp@_@@N@RIC Paga 87 BEEEQN@lg161115@_J g l ()
fs k QUESTION 3.31 (1.00) Which ONE of the following i s correct concerning the effect a loss of instrument air _ or electric control power would have on Unit 2 with RHR Train A in service while in Mode 57
- c. The RHR Heat Exchanger 2A Outlet valve, 2-HV-606, would fail SHUT, and the RHR Flow Control val ve, 2-FV-618, would fail SHUT resulting in a total loss of RHR flow.
- b. The RHR Heat Exchanger 2A Outlet valve, 2-HV-606, would fail DPEN, and the RHR Flow Control valve, 2-FV-618, would fail DPEN resulting in maximum RHR flow and possible pump runout.
- c. The RHR Heat Exchanger 2A Outlet valve, 2-HV-606, would fail SHUT, and the RHR Flow Control valve, 2-FV-618, would fail OPEN resulting in nominal flow with no cooldown.
- d. The RHR Heat Exchanger 2A Outlet valve, 2-HV-606, would fail OPEN, and the RHR Flow Control valve, 2-FV-618, would fail SHUT resulting in nominal flow with maximum cooldown.
1 (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) L_ _ _ .- _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
g - - - - 3 3,_ PLANT' SYSTEMS - (38"/,) ND PLANT-WIDE GENERIC Pega 88 RESPONSIBILITIES (1 , ( ) QUESTION 3.32 (1.00) Which DNE of the f ollowing is correct concerning protection o+ the Auxili ary Component Cooling Water (ACCW) system from a RCP Thermal Barrier H3at Exchanger (HX) leak?
- a. Each RCP's ACCW return line has a motor operated isolation valve which shuts on high flow f rom that individual HX.
- b. Each RCD's ACCW supply and return lines both have motor operated isolation valves which shut on high flow from that individual HX.
~
- c. A common ACCW HX return line has a motor operated isolation valve which shuts on a high radi ation signal from the ACCW process monitor,
- d. Each RCP's ACCW return line has a relief valve which relives excess pressure to the PRT.
l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
E' 3[ -PLANT SYSTEMS (3"78ND' PLANT-WIDEGENERIC Pega 89 L-: .. RggPONgig1LITigg;J1E 1 g .. l-l_
-QUEST 17t? :3.33 .(1.00)
. State the source and train of the reactor trip signal which-shifts between the ~ Load Rejection Controller and the- Reactor Trip Controller in the Steam Dump-' Control'. system.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
. - . - -- -_-----_----__--_____-_ _ _ ___________ _ - _ - ___ a
,11_E69NI EYEIEdf_12EZ-
.y !!EEE9N@lgl(lllgg_fi _1 9_E69NI WIDE _@ENEBig Q
.' Pcqo 93
, QUESTION 3.34- (1.50)
What are:the-sources, setpoints,'and' coincidences for.the TWO-turbine trip inputs to the Solid State Protective System (SSPS) .for generating a reactor-
-trip when greater than P-97 l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) o________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
3 .- PLANT. SYSTEMS (3BZ ND PLANT-WIDE GENERIC Pcgo 91 BEEPQNgl@lblI1E5_f_ _1 1
'N .
- QUESTION 3.35 (1.00)
Which DNE of the f ollowing correctly states events which will occur on a decreasing instrument air pressure condition?
- a. At 80 psig decreasing, instrument air to the turbine building is isolated f rom instrument air to the auxiliary and containment buildings.
b._ At 70 psig decreasing, instrument air to the turbine building is isolated f rom instrument air to the auxiliary and containment buildings.
- c. At 80 psig decreasing, breathing air is isolated f rom instrument air to the auxiliary and containment buildings.
- d. At 70 psig decreasing, instrument air is realigned to separate Unit l's instrument air to the auxiliary and containment buildings from Unit 2's instrument air to the auxiliary and containment buildings.
l l l' l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
;;gg__e(ANT SYSTEMS T (}@Z},;_. AND PLANT-WIDE GENERIC -
Pega 92i
'BEEEQNgigl(ll1[@_l[ Q -
s_- < fs' -- U' l: + . ;i it t QUESTION, ~3.36' (1.00) Individual Pressurizer Code Safety Valve DIRECT valve position indication l: can be monitored at __________ and __________ (l oc ati ons) . (Fill.in the blanks.)= 1e b l l. ( w (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) i J l _ _ = _ _ _ _ _ = _ - _ _ _ . _ _ _ _ _ _ - - _ _ _ _ - _ _ _ _ __ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ ;
+[}[__P(MT_gYgT[MS (38YhNDPLANT-WIDEGENERI'C .
.Pego 93.
, ; ,7 ;R[gPQNgigl(111gg_J1Tfl s .. ,
- / , ,
QUESTION 3.37 (1.88)
'Which DNE of the -f ollowing correctly. describes, how an independent veri fi cation of. positi on - f or . a ma.nually operated throttle; valve: i s performed?
o . .: Move the valve slightly in the closed direction and then return it to. its required posi ti on.
- b. Completely close the valve and then reopen it to the required
. posi ti on.
- c. Inspect the last valve lineup sheet for verification' signature and
. compare recorded . val ve position wi th the required posi tion.
- d. ' Compare visual observation of stem or indicator position with the
. requi red posi ti on.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
1. p .
. 3 .'- . PLANT @YSTghs (307,[^ND PLANT-WIDg_@gNERIC -; pagg 94 BEEP 9tLSl@lLillg@_,ild1 S
.. QUESTION 3.38 (1.00)
)
- l. Authorization f or whole body exposure f rom 1001-1500 mrem / quarter requires
. written approval of which DNE of the f ollowing? !
- o. A Health Physics Laboratory foreman and the worker's foreman
~
- b. A Health Physics Laboratory supervisor and the worker's supervisor
~
- c. The Health Physics Superintendent and the individual's superintendent l d. Only a Health Physics Laboratory foreman
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
)_3t__EbeNLjjjyDIg!jS_J333 paga 95
, D_P6@NI WIDE _ GENERIC. -
;REgPQNg191(IT1[g_11 g QUESTION- 3.39 - ( 1. 00 ) -
. Reverification of procedural- initial conditions is required prior to restarting .- an evoluti on which has been . suspended f or greater- than-y .__________ _ hours.
(Select'the DNE answer-below:which best fills.in the' blank above.)' 1 D. B
- b . -- . 12
- c. 16-d.. 24
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
vc . . . . f72 EEL 9NIijyglggg_j}gg.4b'yp
' BEEE9Ngig1(lligg_,[g,p ,pk@NI hWlpg_ggNggig M
V
'phg3 96
' e
' ]_ J
-QUESTION ._ 3 . 4 18 (2.se) 15 tate FOOR' conditions. which, 'i f any. one occurs, . allow the on-shif t' reactor -
; operator..-to' shutdown'the reactor without prior approval.;
i f' . e (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
D /~ i 'Pcgo 97' [' (3 A PLCNT SYSTEMST(387. g)' D P L A N T - W I D E-' G E N E R I C '. RE32QNB191LIIIEE_11W 1 b [i j QUESTIDN 3.41 (1.BB)..
- l. .c L ,l Li st_ TWD. cases in whi ch Independent Verification requirements are.
.-ox empt ed / superceeded. ,e O
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
.i L--___-_-_-______-_-_____ _ _ _ - _ ______-
- p. - -
-Il__!%eNI_gyglgMg_f}g}
'l . ,BEBEQNgigibill[E_J1 ,d Q;E(gNI;W1Qg_QgNESlQ-Q Pago tiQ
; QUESTION- 3.'42- ( 2. 75 ) -
m Li st ' THREE. l ocati ons . where hold tags _ must ~ be. pl aced .to properl y . tag a Motor : Operated-Valve.as a. fluid. boundary. 1 l 1 Y
${'
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
4
. 3L PLANT SYSTEM 3 (37*/hNDPLANT-WIDEGENERIC.
Pcga 99
- / , EEEEQNg191LJIlgg_11g31 l
- QUESTION' 3.-43 (1.00) .q i . .
! Match the following unitized sound powered phone systems in Column I with their appropriate Jack color coding in ' Column II. l
- 1
'(Fill'in the blanks in Column I with the DNE-best letter f rom Column II . )'
Column I Column II
- 1. __________ The one l oop system a. Red used for-refueling L b. Drange 1 2.- __________ The one l oop syst em used for maintaining c. Green i cold shutdown f ollowing a control room evacuation d. Grey I,
4
,j i-l l
1 1 l' l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l l
?
p ,h.
.gc__ELeNI_gYSTEMS (393 g Np_E(gNT-Wlpg,@gN[61C; PcgalC3 M, BEEEQNgig1(111[g_1 3l51 V v ,
1.
' QUESTION .3.44- (0.50)
A fire team consisting of'__________ (number) members shall, be maintsined on site at'all times.
-(Fi'll'in the' blank.)
l r b l (***** END OF CATEGORY 3 *****) j (********** END OF EXAMINATION **********) j t - _ _ - _ - _ - _ - --. _ -_ - - .i
'"*,, . f ?l . QO Qq 1 3 0 THERMQQyggMlGE .
Pcg3101 g;j_REACTORPRINCIP6ESizn_ewn_codeoesuIng%)m_1EWD85ENI868 y ANSWER 1.01- ( 1. 00 ) '
's, c. ( 1. 0 )
REFERENCE LO-LP-33450-02, Objective 3. KA: 192005K105 (2.5) 192005K105 ..(KA's) ANSWER 1.02 (1.00)
$\, a. (1.0) i REFEREMCE
.LO-LP-33420-02, Objective 1, 5 L 7, pp. 10-12.
KA: 192004K106 (3,1) \. l 192004K306 ..(KA's) l ANSWER 1.03 (1.00) l
\ c. (1.0) l Present reactivity = (k-1)/k = (0.957 - 1)/0.957 = -0.0449 dK/K Reactivity af ter S/D bank withdrawal = -0.0449 + 0.0420 = -0.0029 dK/K Keff after withdrawal = 1/(1-rho) = 1/(1 + 0.0029) = 0.997 Count rute f = CRi (1-ki)/(1-kf) = 150 (1-0.957)/(1-0.997) = 2206 cps
(***** CATEGORY I CONTINUED ON NEXT PAGE *****) _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ __ }
Et ~~~ .. L1,.__BEOGIDB_EBINGIELEE_ m 1_INEBUDDYNed1GE- Pcga!C2'
, :1Z31_eUD_GDUEQNENI S 131_1EWeeUENIeLE_E!B51: O REFERENCE
_LO-LP-33310-02, Objective.11, p. 11. KA: 19200BK104 (3.8) I 192008K104 ..(KA's)
. ANSWER- 1.04 (1.00) l L c. -(1.0) 1 REFERENCE LO-LP-33430-03, Objective 9, pp. 7-12.
Unit 1 Plant Technical Data Book, Tab 1.4.1. l KA: 192006K107 (3.4) l' 192006K107 ..(KA's) l
' ANSWER 1.05 (1.00)
- a. 11.0)
REFERENCE LO-LP-33230-02, Objectives 13 and 11, pp. 11 L 12. KA: 192003K107 (3.0) 192003K107 ..(KA's) (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) = - _ _ _ - _ _ _ _ _ _ - . _ _ _ .
'lil_BE99196_PBINE1P(ggg*d,Iggggggygggigg. g .
- Pcen1C3 JZ11.9ND_GDEDNENIW1131_1EWD9NENIBLE_EX951 O' ;
ANSWER 1.06 ( 1. 00) -
- b. ( 1. 0 ) -
Cal cul ati ons * - 1A = 50 % 1B = 725 pcm 2A = 1200 ppm _ 2B = 2 pcm 3A = 220 step: 3B = 890 pcm
'4A =.890 pcm 4B = 1780 pcm
-5A = 2 5B = 6307 pcm IC = -2910 pcm REFERENCE LO-LP-33510-02, Objective 5, pp. 5 - 7.
, LO-1U-27101-00-001 KA 192002K114"13.8) 192002K114 ..(KA's)
A (*kSWER .1.07 (1.0@) (0.25 eachi
- 1. 'C.
- 2. a, 3.- d.
- 4. b.
REFERENCE LO-LP-33520-02, Objective 5, pp. B & 9. LO-TP-33520-011 & 012 KA: 192005K110 (3.6) 192005K110 ..(KA's) (***** CATEGORY 1 CONTINUED DN NEXT PAGE *****) I 1:
c- .i
.: 17 REACTQR_5 1LdQIPLES' ) . TL4[RMQQyNAMigg IZ31_9NQ,QQg&QN[N1,__11}l_lEWQgt![NI@(g_[lgt!1'
( Pag 31C4 L l --
- CNSWER 1.08 (1.00)
- d. ( 1. 0 )
REFERENCE LLO-LP-35204-04, Objective 6, pp. 11f . . KAs~ 193010K107 (3.8) 193010K107 ..(KA's)
' ANSWER 1.09 (1.00)
- 1. - c. (0.50)
- 2. - b. (0.50)
. REFERENCE LO-LP-34510-01, Objective 7, p. 31. j Tcchnical Specifications 2.1.1, p. 2-1 L 2-2; a-2.1.1, p. B-2-1. '
KAs . 193009K105 (3.1) 193009K105 ..(KA's) ANSWER 1.10 (1.00)-
- b. (1.0)
Steam enthalpy (1035 psi g + 14. 7 = 1050 psi a) = 1191.0 Feed-enthalpy (450 deg) = 430.3 Power = 4
- 1.9X10^6 * (1191.0 - 430.3) = 5701X10^6 Btu /hr 5781X10^6 Btu /hr / 3.41X10^6 Btu /hr/MW = 1695 MWt (4**** CATEGDRY 1 CONTINUED ON NEkT PAGE ****8)
' REACTOR PRINCIPLES - %)- THERMODYNAMICS '
~'
Pcg3185
,f!"{11,
~ 12%I_6SD_'C N SI-151:lfDSE5SisiER_Enet!1-(O 4
REFERENCE LO-LP-34310-01, Objective 4.b, pp. 13 --15. KA ' 193007K108 (3.1) 193007K108 ..(KA's) l 1*
-ANSWER 1.11 (1.00)-
- c. (1.0)
- l. Tsat (255 psi g + 14.7 = 270' psia) = 407 B degF Subcooling = 408:- 380;= 28 degF REFERENCE LO-LP-34110-04,. Objectives 5 L'14, pp. 13 & 21.
KA: _193003K117 (3.0) r
.1930/J3KI1'7 ' , .. (M A' c )
l i- SANSWER- 1.12 . .t . 00 )
- a. ' ( 1. 0 )'
l-l REFERENCE LO-LP-37012-04, Obj ecti ve 13, p. 6. Attachment D to EOP'19001 KA : 19300BK122 (4.2)
.19300BK122 ..(KA's)
ANSWER 1.13 (1.00) l S. . (1.0) l (***** CATEGORY I CONTINUED DN NEXT PAGE *****)
1r_ BE9EI95_PBINE1!1EE.d31_ItEB5991NMIEE ,- Pcco1Ci IZ119ND_G95!5PJENIF__1111_lEWND95ENI969_EE951 - 4
' ' REFERENCE, LO-LP-34410-03,- Objective'11, p. 18..
., i KA : . .193006K111 (3.1) 193006K111 ..(KA's) i l ANSWER. 1.14, (1.00) 1
- d. (1.0) l-REFERENCE LO-LP-34410-03, Obj ective 12, pp. 20 & 21.
KA: 193006K104 (3.4) 193006K104 ..(KA's) L ANSWER- 1.15- (!.00) d- (1.0)- l. REFERENCE LO-LP-16301-06-C, Objective B, p. 15. KA: 191001K301 (3.3) 191001K101 ..(KA's) ANSWER 1.16 (1.00)
- b. (1.0) l
(***ss CATEGDRY 1 CONT !tJUED ON tJEXT PAGE
- s***)
1
~
'1.
RIACTgRPRINCI%gg17R g Pcge107'
;, I_n_esD_GefDssIWun_TgRggpVNAMICg
_1E wneessleks_sueel v t REFERENCE. LO-LP-53130-04-C, Obj ecti ves 6 L 7, ' pp. 12 & 13. LO-IU-53112-00-C-201, pp. 1 L 2. KA: 191001K106 (3.3)
-191001K106 ..(KA's)
. ANSWER 1.17 .(1.00)
- d. (1.0)
REFERENCE LO-LP-36103-01, Objective 2, p. 9. KA: 191002K117 (3,3)
'191002K117 ..(KA's) l ANSWER 1.19 (1.30) l-P (E.50 each)
- i. 1. - d.
- 2. - a.
I REFERENCE-LO-LP-17401-05, Objective it, pp. 24 L 25 KAs 192002K114 (2.8) 191002K114 ..(KA's) ANSWER 1.19 (1.00)
- c. (1.0) 1~
(***** CATEGORY I CONTINUED ON NEXT PAGE ss***) i
g , ["- -id_BE9EI96_EBING1ELEf_JEl_IMEB599yN951GE .. ( .! Pcg31C3
' JZ31_9N9_G95E9NENIEW1131_1EWD95ENI969_E3951 A .
9..
.J:EFERENCE, LO-LP-53400-02, LObjective 10,.p. i t .'
7 ' KAs < 191004K104'(3.3) 191004K104 * ..(KA's) 5 i ANSWER 1.20 (1.00) o.. 41.0) REFERENCE. LO-LP-34410-03, Objective 11, p. 18. KAs ' 191004K106 (3.2) 191004K106 ..(KA's) ANSWER. 1.21 (1.00) O. (1.0) REFERENCE LO-LP-38401-02, Objective 12, pp. 25 L 26. KA: 191002K119 (3.1) 191002K119 ..(KA's) ANSWER 1.22 (1.00)
- c. (1.0) ;
(***** CM EGORY 1 CONTINUED CN NEXT PAGE *****)
- ~ ~
-~~~- ~ ~
lp_.; ','m t4 > y;:/;(:-
.10 ?HEACTOR' PRINCIPLES ) THERMODYNAMIC?. Pcg21C9 1131_1EWD95ENI9LE_ Ele 51 dp ,
f[.t ye;' ' .. ~~~?lfiE~ESE_~CQ6fDNENI [g';e .
' REFERENCE l
i LO-LP-01102-07-C,' Objective 4,.pp. 6 L 7.- E -'
- KA:- 191000K107.(3.0) h- . .
g -191008K107 ..(KA's) ANSWER 1.23- (1.00).
- d. (1.0)
!~ ..,.i: '?
- i. .
.~ REFERENCE LD-LP-53410-02, Objective B, p'. 9.
KA: 191004K124 (3.0) 191004K124 ..(KA's) ANSWER 1.24 (1.00) b.- (1.0).
' REFERENCE SDP 13006-1, para. 3.5,.p. 4; para. 4.4-10, p. 14 & 15 KAs . 191007K108'(3.0) 191007K108 ..(KA's)
ANSWER 1.25 (1.00)
- b. (1.0)
(***** CATEGDRY 1 CONTINUED ON NEXT PAGE. *****) u_________.____________-__________
(;;' ,
~
fib _BEeGI98_EBING1!NEEELIBEBD99YN951GE rvs PO p110.
> 1Z11_eU9 G95P9NENI W 1111_1EWDeUENIBLE_E1951 U E REFERENCE t
- LO-LP.-41601-01,- Obj ecti ves .4 & 10, pp. 12, 13 & 14.
(' SDP"13003-;, p.'2; 13826-1,'pp. 3.& 4. KAs , 191005K196 (3.0) 2 :1905K106 . . ( KA's )
\
(***** END OF CATEGORY 1 *****) 1
f 3-gi$gMERGENCYANDABNORhLPLANT-EVOLUTIONS:- L -
"Pcg3111'
- l , e.42ZEL . O.; 3-
;+
(< - i!
?'
1 ANSWER' ;2.01 -(1.00) l c ' ( 1. 0) : I , REFERENCE LO-LP-35106-02, Objective 1,-p. 4. " > -TGehnical' Specifications 3.4.8, p. 3/4-4-25. KA: '000076G011-(3.4) 200076G011' ..(KA's) ANSWER 2.02 ( 1. 00) '
'c.-(1.0)
REFERENCE. LO-LP-27121 -05, . ' Objectives 5 & 6,-pp. 5f. L 'KA: OOOO40G011 (4.1) 200040G01.1 ..(KA's) ANSWER- 2.03 (1.00)
- e. '( 1. 0 ) '
REFERENCE LO-LP-37061-02, Obj ecti ves 1 & 2, p. B. LO-IU-37061-00-001, Ques. 2a, p. 1-12.
'KA:. 000074K311 (4.0) 000074K311 ..(KA's)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) i
~ ~ ~ ~ ~ -~
~
kl . . .. .. . ? E3.s__EDEBEENGLONQ_@@NQ@jll@(_P(@NI EMQLWIl9NE -c 'Pcg3112.~ L
. ;- 4
' 12ZE W .. (v)'.
- p. , ,. 3 i: . ,
E'-
" ANSWER' 2.04 (1.00) c.' ( 1. 0 ) '
REFERENCE LO-LP-60327-00,. Objective 2'.k 3, p.16. KAs- 200068A121 (3.9)- p 00006BA122 ..(KA's) ANSWERi 2.05 - ( 1. 00) . 3
-b.. (1.0)>
REFERENCE
- LD-LP-10101-03, Objectives 2.d and 13.
AOP.18020-C, Caution prior to step 4, p. 2. KA: 200026K303-(4.0) 200026K303 ..(KA's) ANSWER 2.06 (1.00) b.. (1.0) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
- o. A__Et2E8EENGX 9NQ_ggNQQgg(_[L@$1_[ktQLyllQNg Pcg2113.
p' ,.
- RZ3L w ..O -
[ .: *D l.. . REFERENCE , h t LO-LP-01103-03-C, Objective.1 & 2b, p. 4.-
, 'LD-LP-68324-01,. Objective 3,-p. 4.
LD-IU-60324-00-001, p. 1-6. AOP 18032-1,- Secti on ~ C. KA: '800057K301 (4.1)
.000057K301 ..<KA's)
L ANSWER 2.07 (1.00)
~
c.- (1.0)
.t
. REFERENCE LO-LP-37031-04-C, Objectives 1, 6, 7 & 9, p. 5.
EOP-19100/ECA-0.0, Note prior to step 1, p. 2. KAs. 200055G011 (4.1)
'000055G011 ..(KA's) i ANSWER 2.08 (1.00) 10'(1.0) '(must be exact)
' REFERENCE LO-LP-04101-03-C, Objettive 9, p. 15.
SDP 13003-1 & -2, para. 2.2.12.5, p. 3. KA: 000015A210 (3.7) 000015A210 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
7, , , V -.: M4 F 2s__E5gR@gggLggg_ggggggg6_g(ggLgyg((JIlgNE ' m-f 'Pcto114 12Z31: W ~U p;- [ f 4};
+
* .i l
' ANSWER 2.09 ( 1. 00 )l c." (1.0) R REFERENCE-
- i. LO-LP-43101-04-C, Objective 6c, p. 17. l R : KA : 1000067A216 (3.3) {
i ~
- 000067A216 ..(KA's) I i
ANSWER. 12.10 (1.00) i
- d. ' ( 1. 0 )-
l 4 REFERENCE j LO-IU-09402-00-001, p. 1-2. 'l EOP 19211-C/FR-S.1, step 5, p. 3. ! ARP 17010-1 & -2, C01.
; Technical Speci f i cati ons 3.1.1.1 L 3.1.1.2, pp. 3/4-1-1 & 3/4-1-3.
KA: 000024K301 (4.1) ! i I 200024K301 ..(KA's) i i
'l
' ANSWER' 2.11 (1.00) l (0.25 each) l' l '. Boric Acid Storage Tank
'2.. Boric Acid Transfer Pumps
- 3. Boric Acid to Charging Valve (1/2-HV-8104)
- 4. _ Emergency Borati on Fl owmeter (1/2-FI-0183A)
I J l l l (***5* CATEGORY 2 CONTINUED ON NEXT PAGE *****) l
)
- Zs_IEDEBGENGY_9ND_9;UQB g6_P($NI.ggg6UIl995 _
7 Pcgo115 g
- .1 2 Z E . :J, .
CLEFERENCE : [LO-LFrB9401-03-C, Objective'th & 4, p. 16.
- LO-IU-09402-00-0011
' SOP-13009-1,> para. 4.6, p. 11.
.KA: 000024K302 ( 4. 2) '
200024K302 ..fKA's)- ANSWER 2.12 (1.00)
- d. (1.0)
. REFERENCE ARP 17011-1, 17012-1.
LO-LP-16303-04, Objectives 2 & 6. KA: 000027GG11 (3.6) 000027G011 ..(KA's) ANSWER 2.13 (1.00) aa- ( 1. 0) - REFERENCE LO-LP-12101-15-C, Objective 19.c, pp. 28f & 48. SDP 13011-1,- precaution 2.1.6, p. 2. KA: 000025K101 (3.9) l. L 000025K101 ..(KA's) (***** CATEGORY 2 CONTINUED ON NEXT PAGE *****) 1. 1. L - --- - - - - - _ - - - - _ _ ----- - - - _ _ _
W ~F;f , ~ 4_ _ _ . _
- 26_EDERQgNQY AND^ASNQRf*y_P(ANI;[yQLUIlgNE.: Pcep116i 0
7 l13Z%)- Q l c- ' ANSWER.' -2.14 (1.00). d.. .(1!B).
- REFERENCE LD'-LP-12010-15-C, Objective 7.e; p. 16.
[ j ,_._ - KA ~ '200025A110 (3.1): + . 000025A110 .~ . ( K A ' s ) ANSWER -2.15 (1.00)
+ or - 20 deg F) 220'deg F. (1.0; REFERENCE
-LD-LP-60307-01, Objective 6, p. 7.
ADP418007, Section B, step B.3, p. 5. KA: 000022G007 (3.0) 200022G007. ..(KA's) ANSWER- 2.16 (1.00)
.Within normal'conteel' band (0,5),-or outside normal contrel band, but
- rosponding 'as expected to a controlled condition (manual or automatic)
(0.5). t***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
~ - -
W7;9 .;i. . . . L ?2:2_'EDEBEENEXieNP_e!N9BM6_P69NI_[yg(QIlgN@; .
. . . :Pogn117,
; .!2ZR .,Q
!]
l-REFERENCE, l LO-LP-37011-03,. Objective 7, p. 13. KAs . BOOOO7K301.
;BOOOO7K301.. . '. (KA's ) .
ANSWER. 2.17 ( 1'. 00) - RCP(s).1 or.'4-(0.5 for e'ither.or both), in or' der to provide normal-pressurizer spray (0.5) REFERENCE LO-LP-37011-03, Objective 15. LO-IU-37011-01-001, Question 18, p. 1-15. KA: 000025A104 (3.6) 200025A104 ..(KA's)
. ANSWER 2.18 ' ( 2. 00) i:.: ..;, (o.5e~k vma m ;0.( cJ Cor carred or&)
- 1. Verify l Reactor Trip
-2. ; Verify Turbine Trip
- 3. Verify AFW pumps running 4.: Check' reactor power
- 5. -Emergency borate the RCS
. REFERENCE LO-LP-37041-03-C, Objective 7, p. B.
EDP 19211-C, p. 2. KA: 000029G010 (4.5) 000029G010 ...(KA's) I (***** CATEGDRV 2 CONTINUED ON NE4T PAGE *****)
c [; l2r__EDES9ENGX_9N9_99U96 5 _P69NI_[!@LWIlgNg- Pce:110 i
, - 12Z3L W- f-)v
(_ L ANSWER- 2.19 (1.00)
, 1. - RCS-subcooling:< 24'deg F (0.5) 2 PRZR level:cannot be maintained >9% (0.5) - REFERENCE LD-LP-37111-04-C,' Object'ive 10, p. 11.
KAs - 200009K328 (4.5)
-000009K328. ..(KA's)-
ANSWER 2.20 (1.00)' d.- . ( 1. 0 ); REFERENCE LO-LP-36101-01-C, Objective 7, p. 33.
. K A:l 000009K101 (4.2) 200009K101 ..(KA's)
ANSWER l2. 21 (1.00)
.d. (1.0)
REFERENCE' LD-LP-37312-06-C, Objective 10, p. 12. EDP-19030, Step 1 RND, p. 2. KA: 00003BK308 (4.1) 20003BK308 ..(KA's) (***** CA'TEGORY 2 CONT]NLJED ON NEXT PAGE *****)
l, ?l2 EMER[y[NCY ' AND' ABNDRMAL ' PLANT =- EVOLUTIONS. Pcg3119l k 12ZE (J Q q g-1[ s i
' ANSWER 2.22 I ( 1. 00 ) -
c.- (1.0) it
' REFERENCE.
^
LO-LP-37311-06-C, Objective 9, pp. 15-17. EDP-19030, Step,30,Ep.,24. KA: 20003BK306 (4.2) 200038K306- ..(KA's) ANSWER 2.23- (1.00)
- b. (1.0). . .
REFERENCE LO-LP-37112-02, .. Objectives 2 & 3, p. 4.
- LO-IU-37112-00-001, Self Test Question 2, p. 1-12.
KA: 200009K321 (4.2)
~
200009K321 ..(KA's) ANSWER 2.24 (1.00)
- b. (1.0)
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
12.e_'_EDEB9ENGY_9Np_89NQBg_PL9NI_[yQL(IllgNg _ n _Pcg312] ], c J.2ZM. W U , l) i REFERENCE l t "LO-IU-32101-00-03, Performance Objective, p. 3-1. 'l ARP-17100-2 and117102-2 j KA: 000061P.205 L (3. 5) - ! 000061A205- ..(KA's) ANSWER' 2.25- ( 1. 00) c.- - ( 1. 0) REFERENCE-LO-LP-60321-02-C, Objective 4, p .1 5. - LO-IU-60321-00-001, Self test question 7, p. 1-9. ADP-18028,. step A6 RNO, p. 5. KA: 000065A206 (3.6)
.000065A206 ..(KA's)
ANSWER 2.26 ( l '. 00 )
- c. (1.0)
REFERENCE LO-LP-01401-04-C, Objective 6a, p. 9. KA: 000056K301 (3.5) 000056K301 ..(KA's) L-l' (***** END OF CATEGORY 2 *****)
{7 ..
-Ir__EL9NI_Eygl[DE_13E} g)NR_E6dyl-Wigg,@[N[ Big. J ~ Pag;121 e>1 V9 BE9EQNgigl(lligg_flgl Qf i;;
,ANSWERi . 3. 01 - ' ( 2. kie )
- (0. 25. each) i 14 1/2; 20 ll 2. ~1/4 3 103 L 3. 2/4; 3-
'4. 2/4;c31 !
l l l l REFERENCE.
'LD-LP-27102-05, Dbjective 5, pp. 21 L 22. ')
KA: 001000K407 (3.7) , 001000K407 ..(KA's)
. ANSWER' 3.02. .(1.00) l
- d. (1.0) q l
REFERENCE i JLD-LP-27101-07, Dbjective 9,;p. 24.
-KA 001010K403 (3.5) ,;
001010K403' ..(KA's) 1 ANSWER 3.03 (1.75) l l
- 1. High Containment Pressure (0.25); 2/3 (0.1); 3.8 psig (0.2; +or- 0.2) i
- 2. Low Pressurizer Pressure (0.25); 2/4 (0.1); 1870 psig (0.2; + or - 20) ;
(Note: "1885 until veritrac accuracy verified" is also acceptabl e): ; 3.. Low. Steam Line Pressure (0.25); 2/3 (0.1) in 1/4 lines (0.1); 585 psig (0.2; + or - 20 psig) I I il (****4-CATEGORY 3 CONTINUED ON NEXT PAGE *****)
-. ._ __.-___-________________________m
7F= 2 us .-
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? . ac__ELONI_ESEIEDE_laE%1k;Q_PL@NI: WIDE _EENEBlG 'P g]122
;{
... . BEEEQNEIEILIIIEE_11L).
I' ) REFERENCE-L' O-LP-28103-06,[Obj ecti ve 4.h, pp. 5 & 6. KA 1 '013000K101 (4.2)
'013000K101 ..(KA's) l ,:
ANSWER 3.04 (1.00) d.- (1.0) i; REFERENCE'
.LO-LP-60305-01', Objective 9, p. 7.
KA: 003000K301 (3.7) 003000K301 ..(KA's) ANSWER 3.05- -(1.00)
-b. (1.0)
REFERENCE LO-LP-13101-05, Objectives 1 L 6,.pp. 6, 7, 13-15. PLID's IX4DB119 L 2X4DB119 KA: 004000K115 (3.8) 004000K115 ..(KA's) ANSWER 3.06 (1.00)
. Water flows from a standpipe (0.25) through the seal by static head (0.25)
(Tod seal leakoff goes to the containment sump (0.25)
.(Botto ) seal leakoff (joins #2 seal leakoff and) goes to the RCDT (0.25)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
. _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ - _ _ - _ - _ _ - _ - - _ - _ _ _ -___-_______-_____-____-a
g,- ,= - . . . ks 31 PLANT SYSTEMS ~(38%) Ng_P(@$1;WlQE_GENEBIC~ Pcg31231 a3 ,. essegnala161Ilta 1 O REFERENCE L. LO-LP-16401-03, Obj ecti ves 2. k 3, p.B.- KA: '003000K103 (3.3) 003000K103' ..(KA's)
. ANSWER 3.07 (1.00)
- Eight (0.5); Slow'(0.5).
REFERENCE LO-LP-29130-02, Objectives.1 k 2, pp. 6 L 7. KA: 022000K402-(3.1)
-022000K402 ..(KA's)
ANSWER- 3.00- (1.00)
- d. (1.0)
REFERENCE LO-LP-32101-07,- Objectsves 3, 5 and 12, pp. 10, 21-24. LER's 88-035, 88-039, 88-040, and 89-001. KA: 072000K401 (3.3) 072000K401. ..(KA's) ANSWER 3.09 (1.00) ,,
- d. (1.0)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) _ . _ _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
';3 3,
' 'IA2_EL9NI_EYEIEDE_IIE31E9_EL9NI;Wigg_@gNg81Q g- :POg3124 BEEEDNEIE161IIEE_1 5 (,)_
, , . :.c a ..
I REFERENCE. H ' LO-LP-20101-08,10bj ec ti ve 3, p. 48.
'KA: 061000K502 (3.2) 061000K502- ..(KA's)
GNSWER. .3.10 (1.00)
- d. : ( 1. 0 )'
; REFERENCE-LO-LP-20101-08, Objectives 4d, 4e, and Ba, pp. 50 & 53 KA: 261000K402 (4.5) 061000K402 ..(KA's)
ANSWER 3.11 ( 1. 00 ) ' c .. .(1.0) REFERENCE 1 LO-LP-46101-04,. Objective Sh L 51, p. 18. KA: 071000A209'(3.0) 071000A209 ..(KA's) l l 1 ANSWER- 3.12 (1.00) (0.5 each)
- 1. a.
- 2. b.
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
- i. .
l
'j.g='~-- - ~~
y , .y xi ~
. REFERENCES
[~ KALO-LP-28101-65?.'Dbj
. 013000G000 -(3. 8) -. ecti ves 3,17 b. 8, : pp'.-- 11,: 12,-&'27; l
213000G006 . . 't KA' s )' 9.-
' ANSWER 3.13 - ( 1. '00) :
1: . c.t (1.0). l-
REFERENCE:
LO-LP-28202-02, Objective l1a, 3 & 7a, pp. 5 & 6.
-K.A: 013000K115 (3.4) 013000K115 ..(KA's).
ANSWER -3.14 (1.00)
. .c.. .(1.0)
. REFERENCE .-
LO-LP-23301-06, Objective 8,: pp. 11.h 12.
'KA: 072000K403 (3.2)-
072000K403 ..(KA's) ANSWER 3.15 (1.00) c.- (1.0) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
. ,J 6 BEEA91ElElbilflES_$1 5 ;
W- W~ g;, ' n, . .LJ l ' REFERENCE' 4 LLO-LP-27102-05,. Objectives;5, 9 and 12, pp. 24 h 25. cTechnical Specification's 3.1.3.6,.p. 3/4 1-21. H KA: :001000G005-(3.7) m
?
F p 001000G005'- . . ('KA ' s ) .
- ANSWER' 3.16- (1.00)
- c. - ( 1. 0)
REFERENCE
. LD-LP-17201-03, ' .Obj ecti ve ' 10, . p. 13.
KAs, 015000A202 (3.1) 015000A202' ..(KA's)- ANSWER 3.17. (1.00)
- d '. (1.0)
REFERENCE
-LO-LP-06101-07-C, Objective.B.1, p. .15.
KAs 076000K116 (3.6)
). . 076000K116 ..(KA's)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) a---_-__- - _ - _ - _ _ - _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - _
h [31 " PLANT SYSTEMSL(387.) PLANT-WIDE GENERIC ~ . Pcg3127 18E829N91916111E5_118 _ L , ({} AN!WER 3.18 (1.00) (0.25'each) 1.. J Suction f rom PRT drain '(bottom L of PRT)
' 2. - RCDT' Pump (s) 3.; RCDT Heat Exchanger
- 14. PRT. Spray Header
> REFERENCE LO-LP-16301, ObjectiveL14d, p. 31.
KA: -010000G007 (3.4) 010000G007 ..(KA's)
. ANSWER 3.'19 (1.00)
. ( 0.' 5 . eac h')
- 1. . 5% per minute 2; 10%.
. REFERENCE LO-LP-16301-06, Objective 5, p. 1.
-KA: 010000K603 (3.2) 010000K603 ..(KA's)
LANSWER '3.20 (1.00)
- b. (1.0)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) p. E f L._____---___._______-.__.
SIS _IELONI_gygI[dg_f}gN1 Q[EL$NI;W1Qg[QgNg81Q Pcg3128- _.,f' BE9EDUEIRILIIIEE_11 ., (). REFERENCE LO-LP-16302-03-C, Dbjective 3, pp.-1'7,'19 L 21. LO-TP-16302-01-C-009
- KA: 011000K604' (3.1) 211000K604 ..(KA's)
LANSWER 3.21' (1.00) b., (1.0) REFERENCE. LD-LP-21102-04-C, Dbjective A.2,'p. 9 KA: -035010K602 (3.1) 035010K602 ..(KA's) ANSWER 3.22 (1.00)
. Mechanical (break-before-make) interlocks between breakers f or normal and c1 ternate . supplies allow only one of _ the supply breakers to be closed at a time. (1.0)-
l REFERENCE
.LO-LP-01103-03-C, Objective 3, p. 16.
KA: 062000K410 (3.1)
-062000K410 ..(KA's)
ANSWER 3.23 (1.00) l l d. (1.0) 1 (***** CATEGORY 3 CONTINUED DN NEXT PAGE *****) l [. L.- __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . _ . . _ _ . . - . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
p,---- a , 33d PLANT' SYSTEMS . (38% D PLANT-WIDE-GENERIC-
' Peg;129
;7--- R_E__5P_gug131LI_T_TE_E__7_1 _ __
"(])'
REFERENCE LO-LP-01201-04-C..Objectivef3,'p. ~4.
,.KA : 262000K303 (3.7) 062000K303 ..(KA's)
ANSWER 3.24 (1.00) 4 d.-(1.0) REFERENCE LO S LP-13201-C, Objective 6, p. 14.
'KA: 206000K605 (3.0) 006C00K605 ..(KA's)
ANSWER- 3.25 (1.50) (0.5 each).
- 2. 1540 psig (+ or -
100 psig)
- 2. ~75-pci s ' ^ cr- -
19 pr.igt 7 t o pst$v (+ ee - Soesg) 13, 425.gpm (+ or - 25 gpm)- REFERENCE LD-LP-13201-03-C, Objective 5, pp. 13 L'14. KA: 006000K603 (3.6) 006000K603 ..(KA's) ANSWER 3.26 (1.00)
'b. (1.0)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
n Ei__26eNI_gygIggg_f}g31j Jg_g($NI;gigg_@gNEBIG- f Pcg3130 j?.; BE9E9Nglgl(lligg_flg31 , h. REFERENCE-
~LO-LP-11101-03-C,- Objective-1, p. 25.
'KA:: 064000K609-(3.2)-
064000K608.- ..(KA's)' Y .WSWERl 3.27 . ( 1. S0) -
- a . 0 ), C_\6 Y E
~ REFERENCE.-
-LO-LP-01401-04-C, Objective 6, pp. 12 & 13.
KA: 64000K411 (3M B64000K411 ..(KA' ANSWER 3.28 (1.00)
- c. ( 1. 0 ) '
REFERENCE
.LO-LP-27201-03, Objective 6, pp. 10-13.
.KA: 014000K406 (3.4)
'01'4000K406 ..(KA's)
ANSWER '3.29 (1.00)
'a . . - ( 1. 0)
/
(***** CATEGORY 3 CONT INi)ED ON NEXT PAGE *****)
A T SYSTEMS 3 -WIDE GENERIC- Pcg3131. c 9
;--deersmcme(s:87.)d'PLA n ------------------
o
> REFERENCE
(-
. CO-LP-43101-04-C,- Obj ecti ves 7 & B, . pp. 21 & 22.
KAs- 086000K405-(3.0)- !. 086000K405 ..(KA's) ANSWER'
'3.30 '(1.00)
- d. (1.0)
. REFERENCE LO-LP-16103-02-C, Objective 6, p.'7.
KA: 016000K109 (3. 7 )- 216000K109 ..(KA's)- ANSWER' 3.31 (1.00)
- d. ( 1. 0) '
REFERENCE LO-LP-12101-15-C, Objective 7b, pp. 12 & 13. KA: 005000K410 (3.1)
.005000K410 ..(KA's)
ANSWER -3.32 (1.00)
- c. (1.0) l
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
~ ~ - --
@ l .
.n f~ .
1z_ P .A Pag 3132 j '. ' L:BESPQN$lgl(lll[$;,[lgR LeNITEIEME_Hfn_L.J_P($l$1;h!!Qg_QgNggig V REFERENCE l
'LO-LP-04101-03-C, Obj ecti ve B.d, p.-10.
KAs. - 200030G101 (3.0) 008030G301 ..(KA's) ANSWER 3.33- (1.00) Rsactor Trip 1 Breaker /P-4 (either for 0.5), Train B (0.5) REFERENCE LO-LP-21201-05-C, Objective C.2.c and A.6.f, p. 15. KAs- 041020K417-(3.7) 041020K417' ..(KA's) ANSWER 3.34 (1.50). 1, 4/4 (0.25) Turbine Stop Valves (0.25) not full open (<96.7%) (0.25)
'2. 2/3 (0.25) ETS hydraulic fluid pressures (0.25) less than 580 psig (0.25; + or - 30 psig)
REFERENCE LO-LP-28102-03, Objective 3, p. 10. KA: 045010K111 (3.6) 045010K111 ..(KA's) ANSWER 3.35 (1.00)
- b. (1.0)
(***** CATEGORY 3 CONTINUED DN NEXT PAGE ****4)
- m. . : . -- . ._
- x AANT t gYSTEMS'(39%) D PLANT-WIDE SENERICL .~ Pc;6133o
,-k}-- MEDEisIllunts_n L , t).
n iREFERENCE LO-LP-02110-03-C,. Objective 14 & 15,=p. 15.
.KA '.'078000K402 (3.2) 078000K402 ..(KA's)
ANSWER 3.36' (1.00) (0.5 each) -.oc E R F-1y SPDSc(Foxboro)4 computer display
- 2...PSMS (pl asma)' computer displ ay REFERENCE.
.LO-LP-16301-02, Objectives 49 & 9, pp. 16 & 25.
KAs ~ 194001A115 (3.1) 194001A115' .;(KA's) ANSWER 3.37 ~(1.00) d.' (1.0)
! REFERENCE VEGP Procedure'00308-C, p. 5.
KA: 194001K101 (3.6) 194001K101. ..(KA's) ANSWER 3.38 (1.00)
- a. (1.0) l l
l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
I~IN_EL9NI_EYEIEBE_IIE31b_EL9NI:NIDE_EENESIG O P gO134- i a mg. . BE9EQUEIE161I1EE_11931 d 6.: REFERENCE LO-LP-63920-00-C, Dbjective 14. VEGP Admin Procedure 90920, 4.4.6 l' KA: ' 194001K.104 (3.3) l 194001K194f ..(KA's) l-ANSWER 3.39 (1.00)-
- d. ( 1. 0 )-
REFERENCE LO-LP-63054-03-C, Obj ecti ve 1.d, p. 7. VEGP Admin - Procedure 2054-C, para. 4.2.3, p. 5. KA: 194001A102 (4.1) 194001A102 ..(KA's) ANSWER 3.40 (2.00) (0.5 each) 1.- When the safety of the reactor is in jeopardy
- 2. When a reactor protection trip setpoint has been exceeded and an automatic shutdown does not occur
- 3. When required to protect personnel and/or equipment
- 4. -When unusual circumstances warrant
' REFERENCE LD-LP-63300-03-C, Objective 3.
VEGP Admin Proc. 10000-C, para. 2.5, p. 10.
-KA: 194001A102 (4.1) 194001A102 ..(KA's)
(***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
77 - .-, 3
'34 PLANT SYSTEMS'(3SX) D PLANT-WIDE GENE 2IC.
-------~~-----------
Pcg3135 '- f- 8ti!EililCIIIti:II 2. Cf-
' ANSWER- 3.41: (1.02) 1.- .Inside containment af ter integrity is established
- 2. . Significant radiation exposure involved REFERENCE r
i.D-LP-63300-02-C, - Obj ect.i ve- 2, p. 7. KA: 194201A112 (3.1) 194001A112 ..(KA's) ANSWER 3.'42 (B.75) (0.25 each) ,
- 1. Handswitch
.2.1 Handwheel-
- 3. Motor breaker REFERENCE' LO-LP-63304-03-C, Objective 2, p. 9.
KA: 194001K102 (3.7) 194001K102 ..(KA's) ANSWER 3.43 (1.00) (0.5 each)
- 1. - b.
- 2. -
a. (****8 CATEGORY 3 CONTINUED ON NEXT PAGE ****8)
p1 i II_ELMI_EXEIEUE_laEE _PLMI:W1Qg_9ENgd1C .Pcgo136 y BEEE9NB191kII1EE_119 _ O REFERENCE' LD-LP-05110-03-C -Objective 7, p. 22.
'KA: 194001A104 ( 3. 0) -
194001A104 ..(KA's) ANSWER 3.44, (0.50)
'5 (0.5)
. REFERENCE VEGP-Admin Procedure 10003-C, p. 2.
KA s - 194001K116 ( 3. 51 - 194001K116 ..(KA's) (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION *******.***) I-
. ~
g L -; ~ i k M.o M
.T 4 (J~ 0- OrcuW EQUATION SHEET f = ma v = s/t w = ag 2 Cycle efficiency = * ~
{ s = v,t + at K = mC 2 a = (vg - v,)/t KE = hev vg A = AN
= v, + at A = A,e-AE PE = agh . - e/t 1 = In 2/tg = 0.693/t q W = va."
E
- I3148 tg(eff) = (t,,)(ts) _
Q=$ CST (g+g)
, P I . I IX Q = UAAT o I . I ,*VX Pwr = Wga g I = Ig'to**/ M y.y to SUR(t) TyL . 1,3/g y.y ,t/T EVL = 0.693/u SUR = 26.06/T T = 1.44 DT fA SCR = S/(1 - K,gg)
SUK = 26 1--g',f,o), w CR, = S/(1 - K,gg,) y T = D */p ) + [(i 'p)/1,ggo ] - CR (1 - Ken)3 = CR 2 (l ~ Xen)2 - T y 1*/ (p - D N
- I/II ~ Keff) = CR /CR 3 0 7 = (I - p)/ 1,gg p
# " (Eeff ~) g . (3 , geff)Df5I ~ Eeff)1 eff " #eff/Kaff SDM = (1 - K,gg)/K,gg c: f - Neff p= ~
[1*/TK,'gg -) + h/(1 + 1,ggT )) , t* = 1 x 10 seconds y = I47/(3 x 10 ) ~ 1,gg ? 0.1 seconds E=Na - Idlg=1d22 UATER PARAMETERS Idg =1022 1 gal. E 8.345 1ha 2 R/hr = (0.5 CE)/d (meters) I gal. = 3.78 liters 3 R/hr = 6 CE/d (feet) 1 fc = 7.48 gal. MISCEti,\NEOUS CONVERSIONS 3 Density = 62.4 lbm/f t 1 Curie = 3.7 x 1010dps Density = 1 gs/cm 3 1 kg = 2.21 1ha Heat of valorization = 970 Etu/lbs I hp = 2.f4 x 10 Bni/hr Heat of fusien = 144 Btu /lba 1 Hw = 3.41 x 10 Btu /hr 1 Atm = 14.7 Psi = 29.9 in. I'g. 1 Btu = 778 f t-lbf 1 f t. H2O = 0.4335 lbf/in 1 ' inch = 2.54 cm T = 9/5 C + 32 "C = 5/9 (*T - 32)
. i enOCEDURE NO. .
e REVISION e PAGE N$. T '
)
VEGF '14005-1 4 4 of 8 Sheet 1 of 1 DATA SHEET l: SHUTDOWN MARCIN CALCULATION-REACTOR CRITICAL
.1 DATE ~ TIME CURRENT CONDITIONS REACTIVITY BALANCE
'. l IA REACTOR POWER % IB POWER DEFECT + PCM (PTDB TAB 1.1) 2A BORON CONCENTRATION PPM 2B CURRENT ROD WORTH ,i 3A ROD POSITION STEPS (PTDP TAB 1.5.1) + PCM
{l BANK 3B ASSUMED STUCK ROD WORTH + PCM 4A MOST REACTIVE ROD WORTH PCM (value in 4A) i (PTDB TAB 1.5.2) I 4B ACTUAL S W Z ROD SA NUMBER OF STUCK RODS WORTH (4A times 5A) + PCM SB TOTAL ROD WORTH (HZP) (PTDB TAB 1.5.2) - PCM VERIFY IC IS A NEGATIVE NUMBER IC SUM 1B thru 5B () PCM INITIAL CALCULATED SHUTDOWN MARGIN % delta K/K (Divide absolute value of IC by 1000) REQUIRED SHUTDOWN MARCIN 1.3 % delta K/K (Tech Spec 3.1.1.t) COMPLETED BY / / SIGNATURE / DATE / TIME
'@e e *e
_ _____ _ ____ _ ___ l
.. -. " ~ " * *
,.,l
~
PTDB-1.T .0 3 O 2 of 22 TAB 1.1-F1 POWER DEFECT UNIT 1 CYCLE 2
's i i 4 '
400 -
. xw x-
A t W'*k 'A'*AN N
'b %'(' mNNNN m V- X% ?'s! 'A'(' NN &
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.'s
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, g_ ,( .
g % h ' k ' 2 's N
%. 'A 2000 -
s x 800 PM8 i N A
, 300 PPM
,, i e
N ' , x Et __ - __ E0L - - - - - - l l
= Paa 4 ; s I i I i
,,,,l 1 0 PMd i
2B *e Ep . Ep We POWER f5 of 3419 int) POWER DEFECT VERSUS POWER l BOL, MOL, EOL BOL MOL BORON DEFECT EOL BORON DEFECT BORON DEFECT (PPM) (PCM) (PPM) (PCM) (PPM) (PCM) - 1800 1129 900 1733 1700 1167 300 2503 800 1792 200 2580 1600 1206 700 1854 1500 1246- 100 2657 600 1918 0 2734 1400 1287 500 1985 1300 1330 400 2054 1200 1373 300 2125 1100 1417 1000 1463 900 1510 BOL BURNUP < 3000 MWD /MTU MOL EOL 3000 MWD /MTU < BURNUF < 11000 MWD /MTU 8A b/ .2/y/P1 BURNUP > 11000 MWD /MTU~ Reviewed By Date a
, Adh
renocsouns No. nev WON
' PAGENo.
-PTDB-1 TA .0' 3 16 of 22'-
TAB 1.5.1-F1 ROD WORTH HFP, EqXe, BOL & MOL UNIT 1 CYCLE 2 USE FOR BURNUP < 7500 MWD /MTU 2*w,,,, , , , i , , it IlI x W l/ \ ; 2M iV i l ll 1 ' TX l\ ! 10 j
) '\ T 1 1 1 m
I T T :
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*%m I
(
. \
l ' %
% m ')
'$ 113 25 o
118 I su o ass l BM C tis ses yg R00P051T1010(StepsWithdreen) DIFFERENTIAL AND INTEGRAL ROD WORTH VERSUS STEPS WITHD BANKS D, C, AND B MOVING WITH 113 STEP OVERLAP BOL & MOL, HFP, EQUILIBRILH XENON (1 D ? - l2/wlroj Reviewed By Date
- 3..s
. 1 PnOCEDURENO. g REWSON g PAGE NO.
PTDB-1 TAB 1.0 3 17 of 22 TAB 1.5.1-T1 i ROD WORTH I HFP,EqXe, BOL & MOL UNIT 1 CYCLE 2 USE FOR BURNUP <7500 MWD /MTU i i
. mPS m=8= .2=88mn zmsan i Coarr80L 84ME 800 bo8TE SCO WORTE ]
D /C / 8 (PCE/STU) (PCM) j 228 228 228 9.10 0 220 128 228 9.82 4 212 228 228 1,81 13 s 204 128 218 2.13 19 196 218 118 2.83 64 188 228 118 1.91 70 180 its its 3.06_ 94 171 228 228 3.17 118 166 128 228 3.26 148 156 118 228 3.31 171 148 218 128 ' 3.38 194 148 118 228 3.43 115 131 118 218 3.47 133 114 128 118 3.54 181 116 114 118 3.57 310 108 113 118 4.18 341 100 218 118 5.11 378 j 92 207 228 . 5.98 411 M 199 218 8.M 471 76 191 128 7.98 517 66 183 218 7.48 988 66 175 att 7.88 44 7 52 187 1as 8.15 111 44 159 128 8.44 777 34 15 1 118 8.58 844 28 145 128 8.55 914 le 135 128 8.13 981 12 it? 118 7.54- 1948 4 119' 118 4.M list 8 115 218 6.18 1117
. 8 108 113 5.93 1178
. S. 100 1H 6.88 1111 S' 91 197 7.54 1178 0 44 199 8.M IMS S. 74 131 8.93 1411 9 68 183 9.54 1445 t 64 175 10.05 U43 8 51 167 10.51 lue 4 44 159 18.95 1731 0 36 U1 11.14 1810 0 18 143 10.97 1999 0 10 135 18.16 19M e la 127 8.99 se71 0 4 119 7.M 11M e e tu s.53 2164 DIFFERENTIAL AND INTEGRAL ROD WORTH VERSUS STEPS WITHDRAWN BANKS D, C, AND B MOVING VITH 113 STEP OVERLAP BOL & MOL, HFP, EQUILIBRIUM XENON f/ O $$
Reviewed By I 2:- >> Date , we
PTD5-1 TAM.0 3' 18 of 22 TAB 1.5.1-F2-ROD WORTH HFP, EqXe, MOL & EOL UNIT 1 CYCLE 2 USE FOR BURNUP > 7500 MWD /MTU 2E' ;,; i l t t l l I4
'l l q l l t
)
- A f 1 9 ~-
ff 2000
,y , , ,
'I 103
/ % 1 '/NI
$ 1 V
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'N q
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\ p/
l' 4ha
\ '
.N 400 2
N i A ' o i 0 0 118 238 l l. BMet 0 0 118
- 25 l BMet C 114 ass BMel B R00 P051710ll (Steps eitheroen)
DIFFERENTIAL AND INTEGRAL ROD WORTH VERSUS STEPS WITHDRAWN B\NKS D, C, AND B MOVING WITH 113 STEP OVERLAP MOL & EOL, HFP, EQUILIBRIUM XENON
$D W Reviewed By I2k/rq Date
- 33
~
w, ~~ f 'e n o ce m m e m a : nrymon gs pagg no, PTDB-1 TAB- .0 V 3 19 of 22 1 TAB 1.5.1-T2-ROD WORTH HFP, EqXe, MOL & EOL UNIT 1 C7CLE 2 USE FOR BURNUP > 7500 MWD /MTU STEPS FITEDS&WN DIFFE8Erf1AL IWr848AL CONTROL SAME SOD WOSTE 80D WORTE D / C / 3 (PCE/ STEP) (PCN) 228 128 228 8.38 8 218 224 128 2.78 13 212 218 228 4.58 et 294 218 228 5.27 at 196 228 128 5.13 124 ISS 228 116 5.07 168 180 128 128 4.76 204 172 128 218 4.51 241 164 218 228 4.35 277 154 228 - 128 4.12 311 148 218 228 4.92 144 148 128 128 3.88 375 132 224 128 3.68 448 124 128 128 3.58 434
+
116 128 128 3.3F est les 213 128 5.57 498 1M 215 128 8.0F 553
. 92 201 128 9.81 811 84 199 128 9.31 895 74 191 118 9.01 769 68 183 118 8.79 844 64 175 128 8.48 910 51 167 118 8.49 979 44 159 114 4.H 1648 38 15 1 228 8.68 1117 18 148 128 8.68 118F 20 135 118 8.69 1854 11 151 118 8.18 1224 4 119- 228 7.33 1346' 9 115 118 8.54 1414 8 100 113 7.14 1642 0 180' 115 9.20 1814 8 98 207 9.99 1645 9 to 199 10.44 1687 8- 74 191 10.14 1776 9 68 183 18.12 1851 0 64 175 18.15 1934
-0 51 187 10.34 2017 9 44 159 10.44 litt 9 34 181 10.94 1189 0 18 143 11.06 1178 0 20 118 10.99 1864 8 la 11F 10.03 2450 0 4 119 8.15 1514 e e 115 7.13 assa DIFFERENTIAL AND INTEGRAL ROD WORTH VERSUS STEPS WITHDRAWN BANKS D, C, AND B MOVING WITH 113 STEP OVERLAP MOL & EOL, HFP, EQUILIBRIUM XENON
/ O N;[ 12/6]
Reviewed By Date ran
. 'anocsoungmo. neveon Paos no. 1 , , PTDB-1 TAB .0 3 20 of 22 TAB 1.5.1-F3 ROD WORTH HZP, NoKe UNIT 1 CYCLE 2 USE FOR ENTIRE CYCLE 1 1
3M tii siii ! i t i
'"' %dil i li IA i .
I 8 ' 2000 , ', 7, 14 l l 6 3
! \ l -
^(
2600 ', i 12 _ t
- N 1, '
Nm '
,.}
g ' i 4 5 5 /s \ \ R= 1
, 3 r s 1 *$g 1 i J \ l I'\
i i k 1 i .\ / '% g. gi= V y \ r s
\
1 l g 800 7
- ) g s
4 [ 'g 1 1 soo
)
l \ '%
\
t S
/ '
A 1
/ I I '% '
0 0 its tu l \ BMet 0 o 115 ass l BMet C e 15s 228 l BM4C 0 0 tis 238 t#0C A DIFFERENTIAL AND INTEGRAL ROD WORTH VERSUS STEPS WITHDRAWN BANKS D, C, B AND A MOVING WITH 113 STEP OVERLAP HZP, NO XENON
$d b I 2!w!!?
Reviewed 3y Date
- ms
7_ m - m n.=~-
,' pmocsountwo.
g neymon g PAos no.
.. PTDB-1 TAB r.0 3 21 of 22 ,
TAB 1.5.1-T3 l ROD WORTH HZP, NoXe UNIT 1 CYCLE 2 USE FOR ENTIRE CYCLE m Ps WITNDRAWW DImam14L IMGRE STEPS WITEDRAWN DI M RENTIE I M G ML CoirrROL BANK 300 votTE 800 WORTE
- CONTROL BANI BOD WORTE RCD WORTE D / C / B (PCM/ STEP) (PCM) C / 8 /4 (PCE/ STEP) (PCM) 228 228 228 0.19 9 52 187 228 9.85 1889 220 228 220 0.95 4 44 159 128 9.95 1669 212 228 228 1.96 16 36 15 1 228 9.78 1748 204 228 228 2.75 35 18 143 128 9.25 1824 196 228 228 3.24 59 24 135 128 8.41 1894 158 218 128 3.49 S8 12 127 128 7.44 1958 240 224 228 3.62 114 4 119 128 6.44 2013 172 228 228 3.68 143 0 115 228 6.04 1938 164 224 228 3.71 172 0 108 223 5.54 2079 136 228 128 3.75 202 8 ite 115 6.83 1125 148 128 228 3.79 232 0 92 207 6.54 1176 144 228 128 3.85 263 0 84 199 F.04 2138 132 12 & 224 3.92 194 8 76 191 F.53 2288 124 128' 228 3.98 3 25 6 64 183 7.95 2354 116 228 228 4.08 358 9 64 175 8.24 2415 108 223 228 4.39 391
- 9 52 167 8.44 1642 194 215 228 5.02 429 0 44 159 8.24 1544 92 30F 228 5.63 471 0 36 151 7.84 2412 M 199 228 6.14 518 0 28 143 F.16 1672 74 191 128 6.48 569 8 10 135 6.31 2724 68 183 228 6.88 622 8 12 127 5.42 2773 64 175 228 F.06 677 0 4 119 4.55 2813 52 167 128 T.29 735 e e 115 4.19 1831 44 159 228 F.41 793 0 8 los 3.M 1858 36 151 228 F.4F 853 e e 100 3.M 1887 28 143 228 .F.37 912 0 0 92 3.54 1914 28 135 128 F.11 970 0 0 M 3.39 2M4 12 12F 228 6.78 lets 8 8 76 3.14 1974 4 119 224 6.22 10FF e 2.48 e 68 19M 8- 115 224 6.42 1102 8 8 64 2.4F 3015 0 108 123 5.8F 1143 8 8 52 2.45 3013 e 100 215 6.48 1192 3 e 44 1.M 3M4 8 92 287 7.14 1147 8 e M 1.15 3844 0 84 199 F.48 1304 0 6 28 0.91 3064 0 - 76 191 4.48 1370 0 0 28 4.61 3074 0 68 183 8.93 1639 0 0 12 0.34 3678 0 60 175 9.M 1512 0 8 4 s.17 3088 O e e s.11 3081 s
- a a43E FULLY I M EIED DIFFERENTIAL AND INTEGRAL ROD WORTH VERSUS STEPS WITHDRAWN BANKS D, C, B AND A MOVING WITH 113 STEP OVERLAP HZP, NO XENON 61 o $$ 12/411 Reviewed By
/
Date v
,,.- PTDB-1 TAB t J 3 22 ef 22 TAB 1.5.2 ; ROD WORTH )
SUMMARY
UNIT 1 CYCLE 2 DE MEP Wo. Xenon NFP-EaIn l Red Bank Cumulative Bank Cumulativs Configuration M Werth M Werth a o.42 o.642 0.633 0.633 0+c o.953 1 595 0 972 1.605 0+c+e 0 901 2.496 o.906 2 511 0+c+pa o.585 3.o81 0 598 3 133 ARI 6.258 6'.307
\
s E% HIP
~
. lhLlanon REP-Isle Rod Bank CumuIative Bank Cumulative configuration M Worth M Worth o 0.647 o.47 c.41 0.ui 0+c 1.06.1 1 708 1.076 1 717 0+C+8 0.888 2 596 c.895 2.612 0+C+MA 0.638 3 234 0.46 3 258 ARI 6.633 6.68g
SUMMARY
OF CONTROL ROD WORTHS (Iao ) MOST REACTIVE ROD: CORE LOCATION K-6 WORTH 890 PCM (USE FOR ENTIRE CYCLE) f/.7) W / 2Nkt Reviewed By Date aus
, . . }1 Mrec
- O O DRAFT COPY U. S. NUCLEAR REGULATORY COMMISSION.
REACTOR OPERATOR LICENSE EXAMINATION REGION 2 FACILITY: Vogtle 1 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 89/06/12 INSTRUCTIONS TO CANDIDATE: Use separate ;. paper.for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing grade requires at least.70% in each category and a final grade of at
.least 80%. Examination papers.will be picked up six (6) hours after the examination starts.
% OF.
. CATEGORY %.0F CANDIDATE'S CATEGORY VALUE TOTAL SCORE- VALUE- CATEGORY x1.73 23.50 2340- 4. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 33.83 33.50- 3k50 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) 42 00' ##
.Ah00' 43dr0' 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)
77.00 10G:0~ % TOTALS FINAL GRADE All~ work done on this examination is my own. I have neither given nor received aid. P' Candidate's Signa;ure DRAFT COPY
b , _ . b i l L4. REACT 0P PRINCIPLES-(7%) THERMODYNAMICS Page- 2 j ) (7%) AND COMPONENTS-(10%)-(FUNDAMENTALS EXAM)~ QUESTION 4.01' -(1.00) i Given the following initial conditions:- l Keff = 0.957 All Rods In- ! Boron Concentration = 1242 ppm Source Range Indication.='150-cps I Shutdown Bank Worth = 4.2% delta K/K
. Total (All. Rods) Bank Worth = 7.1% delta K/K j
, WHICH ONE:(1) of the following representsithe source range. count trate after withdrawing the shutdown banks? (1.0) ;
(a.) .300 cps
-(b.) 1100 cps !'
a
/ (c.) ~2200 cps j
-(d.) 6000 cps ANSWER. 4.01- (1.00)
-(c.) {+1.0] -) 1 Present reactivity = (k-1)/k = (0.957 - 1)/0.957 = -0.0449 dK/K j Reactivity after S/D bank withdrawal = -0.0449 + 0.0420 = -0.0029 dK/K- i Keff after withdrawal = 1/(1-rho) = 1/(1 + 0.0029) = 0.997 j Count rate f = CRi (1-ki)/(1-kf) = 150 (1-0.957)/(1-0.997) = 2206 cps ;
I REFERENCE
- 1. :Vogtle: LO-LP-33310-02, Obj. 11, p. 11. ,
l
-192008K104 ..(KA's) i 1
1 (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) ___- -__ ____--_____-_-___________D
& y
- 4. REACTOR PRINCIPLES'(7%) THERMODYNAMICS-- Page : 3 (7%) AND COMPCNENTS (10%)-(FUNDAMENTALS' EXAM)
L 1,- QUESTION 4.02 -(1.00) Using the attachment' on the following page, WHICH'ONE' (1) of the following represents: values of MTC for a core at'E0L with 0 boron concentration? (1.0)
,(a.) Curve A
-(b.) Curve B l(c.)_' Curve C.
-(d.) Curve D ANSWER- ~4 .02 (1.00)
(a.) [+1.0] REFERENCE
- 1. . 'Vogtle:
LO-LP-33420-03, Obj. 7. 192004K106 ..(KA's) QUESTION 4.03 (1.00) WHICH ONE-(1) of the following initial plant conditions would require the'LEAST change in boron concentration for a 50 pcm reactivity change? , (1.0)_
- (a.) Tavg.68 deg 1000 ppm boron (b.) Tavg.68 deg 200 ppm boron (c.)- Tavg 557 deg 1000 ppm boron (d.) Tavg 557 deg 200 ppm boron
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
= _ _ - - - ---_- _
v .- . _. . _ . . , _ _ _ _ -. _ . _ . _ . - . _ . . . . . . _ _ _ _ . , _ , _
..___,.__,__--._-_.,__q
. _i,.
V ' ' h F 4. REACTOR PRINCIPLES:(7%)' THERMODYNAMICS Page~ 4
-(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER 4.03 (1.00)
, .(b.) .
[+1.0] m. REFERENCE 1.- .Vogtle: LO-LP-33440-02-C.
.192007K105 ..(KA's)
QUESTION. 4.04: (1.00)' ASSUMING equal amounts of' reactivity addition,' WHICH ONE. (1) of the following statements describes the reason for a higher SUR at core E0L than at BOL7 (1.0) (a.) A-decrease in B-eff due to a buildup of Pu and burnout of U-235.- (b.) An increase in B-eff due to a buildup of Pu and burnout of U-235. (c.) 'A decrease in B-eff'due to depletion of boron concentration. (d.) An increase in B-eff due to depletion of boron concentration. ANSWER 4.04 (1.00) (a.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-33230-02.
192003K106 ..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
[.: '.l v V : Page 5
- 4. / REACTOR ~ PRINCIPLES ~(7%) THERMODYNAMICS
- (7%) AND COMPONENTS (10%) (FUNDAMENTALS ~ EXAM)'
l-i: QUESTION 4.05 (1.00)~ H WHICH 0NE (1) of the following statements defines differential control rod worth? (1.0)
'(a.) Amount of reactivity change resulting from a unit change in, rod position.
(b.)- Total reactivity. change resulting from a change in rod position over'.several units of. rod travel. (c.) The difference in reactivity change resulting from movement of a center rod compared to an outer rod. (d.) The. difference in a control rods worth at BOL and EOL. ANSWER 4.05' -(1.00)~ (a.). [+1.0] REFERENCE-
- 1. Vogtle: 'LO-LP-33450-02, Obj. 3.
192005K105 ..(KA's)
- l. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
- %' ' ..~- -
J 4. - Page' 6 I
^
REACTOR PRINCIPLES (7%) THERMODYNAMICS 1 L , (7%) AND COMPONENTS (10%) (FUNDAMENTAL.S EXAM) g i
.i
; QUESTION' . 4.06 (1.00), l, The following plant conditions exist: l
. Boron Concentration -!1100 ppm Shutdown Margin'- 2% delta-K/K Sourcri Range Channel Indication - 10 cps. .
Differential Boron Worth - 10!pcm/ ppm q If boron concentration:is REDUCED by 100 ppm, WHICH ONE ~(1) of the following represents the final Keff? (1.0). i (a.)- .970 j r (b.) .985 , i' (c.) .990.
'(d.) 1.00 l ANSWER- 4.06 (1.00)
(c.) [+1.0] -{ i 1
-REFERENCE l 1.- Vogtle: LO-LP-33510-02, Obj. 4 & 5.
'192002K114 ..(KA's)
I l l l (***** - CATEGORY 4 CONTINUED ON NEXT PAGE *****) z_.___________________-_--_.------______---_--.-_-_-_-----________---____---------___----_-_---.-__-------____a
!, . y; 1 t O O
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS' Page 7 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 4 QUESTION 4.07 (1.00)
- A reactor startup is performed five (5) hours after a. trip from-full power equilibrium conditions. 1he reactoris then taken to full. power using a.5% per minute ramp. WHICH ONE (1) of the following describes how the resultant xenon transient would vary if.a'2% per minute ramp is used instead?. (1.0)
(a'. ) .The xenon dip would be smaller in magnitude and occur sooner. (b.) The xer;on dip would be smaller in magnitude and' occur later. (c.). The xenon dip would be-larger in magnitude and' occur later. (d.) The xenon dip would be larger in magnitude and occur sooner.
' ANSWER - 4.07 (1.00)
(b.) [+1.0] REFERENCE-1
- 1. Vogtle: LO-LP-33430-03, Obj . 9.
192006K107 ..(KA's)- (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
C( w' , C
~
O O
'4. ' REACTOR PRINCIPLES-(7%) THERM 0DINAMICS Page 8 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
.. QUESTION. 4.08 (1.00)
- ASSUME a calorimetric power calculation is performed under each of
- the following conditions. WHICH ONE (1) of the following conditions
'would result in a CALCULATED-power. HIGHER.than ACTUAL power? (l'.0)
(a.) Indicated feedwater temperature is 10 degrees lower than actual feedwater. temperature.
~
(b.) Indicated steam generator pressure is 30 psig higher than actual steam generator pressure.
-- (c . ) . Indicated feedwater flow is 1E5 lbm/hr lower than actual feedwater flow.
.(d.) Indicated feedwater header pressure is 30 psig higher than actual feedwater header pressure.
' ANSWER' 4.08 (1.00)
(a.) [+1.0] REFERENCE
- 1. Vogtle: LO-IV-17301-00-003 193007K106 ..(KA's) i QUESTION 4.09 (1.00)
WHICH ONE (1) of the following plant parameter changes would result in a. decreased DNBR7 (1.0) (a.) increased RCS Tavg (b.) increased RCS pressure (c.) increased RCS flow (d.) decreased reactor power (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
'f}
- 14. : REACTOR PRINCIPLES (7%) THERMODYNAMICS Page' 9 (7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM)
- u. ,
p is ANSWER- '4.09= ._ (1.00)! (a'. ) [+1.0]'
. REFERENCE-I :1l- Westinghouse, Thermal Hydraulics Principles and Applications,
-pp. 13-23'& 24..
F 193008K105 ..(KA's) QUESTION 4.10 (2.50).
" State the RPS trips which provide protection from exceeding the
;following thermal limits:
, -a. - DNB less than 1.3 =(3 trips required) (1.5)
- b. Peak Clad Temperature greater.than 4700 degrees F-
-(2l trips required) (1.0) 4.10 (2.50) i'd # ### * /'
ANSWER 2.) x.a e n n n 7 *y
- a. 1. OT Delta-T Trip [+0.5] .s.) A Waa' Nr u d a v* V
- 2. Loss of flow trips F+0.5' <.; it c p an
- 3. Low pressure trips +0.5' r,ec7 3n uh n,&*7~>'a k~ <
,' y,, . <w
- b. 1. High' neutron flux tri [+0. 5]
- 2. OP Delta-T trip [+0.5 REFERENCE
- 1. Vogtle: LO-LP-36001-03-C.
193009K105 ..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
k L . . O (3
\._) U L 4.- REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 10 (7's) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) l QUESTION 4.11 (1.00)
The following plant conditions exist: RCS Pressure -.1330 psig Core Outlet Temperature - 550 deg F WHICH ONE (1) of the following represents the subcooling margin using the above parameters 7 (1.0) (a.) 27 degrees F subcooled (b.) 29 degrees F subcooled (c.) 32 degrees F subcooled (d.) 34 degrees F subcooled ANSWER 4.11 (1.00) (c.) [+1.0] (Pressure = 1330 psig + 14.7 = 1344.7 psia from steam tables: 1300 psia --> 577.42 deg F 1350 psia --> 582.32 deg F Delta-P 50 psia --> 4.9 deg F Interpolation: 4.9 deg F/50 psia 44.7 psia = 4.41 deg F 577.42 deg F + 4.41 deg F = 581.83 Subcooling Margin: 581.83 deg F - 550 deg F = 32 deg F REFERENCE
- 1. Vogtle: LO-LP-34110-04, Obj. 17 & 19.
193003K125 ..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
m ,f EQ- ]. rl
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 11 h (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
( QUESTION '4.12; (1.00) A system containing saturated vapor at 585 psig is leaking-via a-
- crack'in a pipewall. The pressure downstream of the crack is 285 psig. ASSUMING ideal throttling characteristics, WHICH ONE-(1)-
of the following represents the condition of the fluid downstream of the' crack? (1.0) (a.) . wet vapor /100% quality (b.) wet vapor /60% quality. (c.) superheated vapor (d.)- saturated liquid ~ ANSWER 4.12 -(1.00) (c.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-34110-04, Obj.12,15,16, & 19.
193004K115 ..(KA's) QUESTION 4.13 (1.00) Using the attachment on the following page, WHICH ONE (1) of the following illustrates the operational curves of two centrifugal
. pumps operating in parallel? (1.0)
(a.) Figure a. (b.) Figure b. (c.) Figure c. (d.) Figure d. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
+ , , ,
W g , v. [ 4. ! REACTOR PRINCIPLES (7%) THERMODYNAMICS- .. Page 12 T (7%) AND COMPONENTS-(10%) (FUNDAMENTALS EXAM) r ANSWER 4.13 :- (1.00).. (c;)- [+1.0]1-4 REFERENCE' L 1.: Vogtle LO-LP-34410-03-C Obj. 7. 191004K109- ..(KA's) , QUESTION' 4.14 (1.00).
- CONSIDER a main feedwater pump operating under normal conditions..
'WHICH ONE (1) of the follcwing parameters.will_ INCREASE the-available Net Positive Suction Head (NPSH)- for the main -feedwater -
- pump? (1.0)
(a.)- system static pressure is lowered (b.) system flow rate is raised-(c.). system head loss is increased
~(d.) system fluid temperature is lowered ANSWER 4.14 (1.00)
(d.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-53400-02, Obj. 7.
191004K106 ..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
.u : , , ,
.(}
,.gs Q. 4; ' REACTOR PRINCIPLES'(7%) THERMODYNAMICS .. ~Page 13 i (7%) AND COMPONENTS-(10%) (FUNDAMENTALS EXAM) QUESTION. 4.15- (l'.00) l
'The average. STARTING current for an alternating. current motor !
thatprovidespowerforapumpisapproximatelyWHICHONE~(1) 1 of the' following; relative to its normal RUNNING current? -(1.0)
-(a.). the same as (b.). _
two' times
'(c.) five. times'- ,
(d.) ten times 4.15 {
' ANSWER _ (1.00)
~(c.) [+1.0] ;
i REFERENCE ; i
- 1. .Vogtle: LO-LP-41601-01, Obj. 13.
191005K105 ..(KA's) i QUESTION.- 4.16 (1.00) l The number-of starts over short periods on large motors is limited
~
to prevent which one of the following? (1.00) .l (a.) damage to motor bearings (b.) damage to motor windings l (c.) damage to motor mountings ) 1 (d.) damage to motor / pump coupling i i (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
K (q r
~!
O .O;
? y.c ' +
1 [ , . . , . . . . . . . . .. . 1 "m L4.
.. ~ REACTOR-PRINCIPLES-(7%)-THERMODYNAMICS- Page"14' (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)- -!
' l
.l l
LANSWER i .4.16 L (1.00)- (b'. ) [+1.0]: , n
'l p REFERENCE' ,
1
- 1. .Vogtle:-~LO-LP-41601-01. .;
191005K106.- . .' ('KA ' s ) '{
- )
QUESTION ~4.17 (1.00)L
- Operating la motor-driven centrifugal pump for extended periods of I time-with the dischar
' result in WHICH ONE'(ge_ valve and' recirculation valves shut will
- 1) of the'following?. (1.0)
(a.). No damage,'.since the ump and motor are designed to operate - with.the-discharge va ve shut. ! 4 (b.) The pump overheating,' cavitation, and ultimately pump failure. .l j (c.) Excessive' motor current, damage to motor windings, and !
. ultimately motor failure.
l L(d.) Pump and motor overspending and tripping on high motor overcurrent. I ANSWER 4.17 (1.00)
-(b.) [+1.0] l
.l ;
REFERENCE j
-1. LO-LP-53400-02, Obj. 10. j
,1
- l. I L
191004K104 ..(KA's) i i o (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
9 9 E4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 15
;(7%) AND COMPONENTS.(10%) (FUNDAMENTALS EXAM)
. QUESTION-- 4.18 (1.00)
WHICH ONE-(1) of the:following correctly describes the effects of. q L post-transient: core voiding on Source Range Detector re:;ponse? (1.0)
.'(a.) Source' range. level increases' proportionally with_ increasing void fraction.....
~
. (b.) . Source range level decreases proportionally with increasing-void fraction.
(c.) Source range. level initially decreases as void fraction increases, and then increases when void fraction becomes exceptionally large. (d.). ' Source range level initially increases as void fraction increases, and then decreases when void fraction becomes
. exceptionally-large.
ANSWER. :4.18 (1.00) (d.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-36103-01, Obj. 2, p. 9.
191002K117- ..(KA's) (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
o
^ '
o u l
. c.
>4. REACTOR PRINCIPLES-(7%) THERMODYNAMICS' Page 16- l (7%) AND COMPONENTS-(10%) (FUNDAMENTALS EXAM) l QUESTI'ON 4.19 (1.00) !
l The.following plant conditions exist: l Plant Power'- 100%- i '
,Tavg - 587 deg F
, Steam Pressure - 980 psig No plugged S/G tubes ;
If 10% of the' tubes:in each steam generator are subsequently plugged, WHICH ONE,(1) of the following values of Tave will be required to , maintain a steam pressure of 980 psig at 100% power? (l'.0) , -l
,(a.) '583' (b.) 587' l
- (c . )' 592 .
(d.) 598
.1 ANSWER 4.19 (1.00) {
i (c.)' [+1.0]- l l REFERENCE-1.- Westinghouse, Thermal Hydraulics Principles and Applications, l- p. 5-47 and Steam Tables. , l l- 191006K113 191006K112 ..(KA's) I l (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) . E___________________--__---_.__--__----_____________a
O O-41 ' REACTOR PRIWCIPLES-(7%) THERMODYNAMICS Page 17 (7%) AND COMPONENTS (10%)-(FUNDAMENTALS EXAM) F r QUESTION 4.20 (1.00)
.WHICH ONE (1) of the following describes the single-acting diaphram actuator and valve shown in the attachment on the following page? - (1.0)
(a.)' _ Air' to open - spring 'to close' (fail open).
;(b.)- Air to close - spring to open (fail closed)
(c.) Air _to ciose - spring to open (fail open). (d.)' Air to_open - spring to close (fail closed). ANSWER 4.20 (1.00)_
~(c.) [+1.0]
REFERENCE
- 1. Vogtle: LO-LP-53130-04-C, Obj. 3, 12, 14, & 15.
191003K110 191001K104 ..(KA's) QllESTION 4.21 (1.00) WHICH ONE (1).of the following parameters determines the MAXIMUM level that can be' indicated by a PZR level instrument? (1.0) (a.) the level of the differential pressure cell. (b.) the level of the variable leg condensing chamber.
.(c.) the level at which the reference leg penetrates the pressurizer.
(d.) the level at which the variable leg penetrates the pressurizer. (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
y - j
, n 10:
p< f 4.s REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 18 _(7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) r (.-
' ANSWER 4.21' (1.00)
(c.)' [+1.0] L REFERENCE ~
- 1. Vogtle: LO-LP-53210-02-C.
1 191002K107' ..(KA's)- is QUESTION 4 12 (1.00)
.WHICH'ONE(1)<ofthe.followingconditionswouldcauseindicatedPZR'
- le<el.to'be GREATER:than actual level?. (1.0)
-(a.). A rupture-in the detector variable leg.
,(b.)- A. rupture in the detector' reference leg.
-(c.) Reference . leg. temperature less than PZR. temperature.
.(d.) Reference leg head pressure equal to variable leg head, pressure.
ANSWER- 4.22 (1.00) (b.) [+1.0] REFERENCE
- 1. -Vogtle: LO-LP-53210-02-C.
191002K109 ..(KA's). (***** END OF CATEGORY 4 *****)
l J. Ol L! 5.. EMERGENCY AND ABNORMAL PLANT' EVOLUTIONS Page 19 L (33%) o , i QUESTION' ;5.01 (2.00) According to.19001-C, "ES-0.1,' Reactor. Trip Response", Attachment D,-
- LIST.FOUR-(4) conditions that-indicate Natural Circulation Flow.
STATE both the parameter ANO its expected condition. ASSUME that containment conditions are normal. ' (2.0) s
' ANSWER 5.01 (2.00)
- 1. RCS.subcooling monitor indication greater than 24 deg F.
- 2. . S/G pressures - stable or lowering.
- 3. RCS hotleg temperatures - stable or lowering.
~
- 4. Core exit thermocouple - stable or lowering.
- 5. RCS cold leg temperature - at saturation temperature for S/G pressure.
Any 'four . (4)' [+0.25] for parameter, [+0.25] for condition; max. [+2.0]
. REFERENCE
- 1. Vogtle: ES-0.1, " Reactor Trip Response."
'2. Vogtle: LO-LP-37011-03, Obj. 12.
000015A121 000056K101 ..(KA's) QUESTION 5.02 (1.00)
- a. During a Loss of ALL A.C. Power event, WHAT component failure is. assumed to result in an RCS LOCA? (0.5)
- b. A note in 19100-C, "ECA-0.0, Loss of All A.C. Power" directs action to be taken which results in the cooldown and depressurization of the RCS. WHAT action is taken to accomplish this cooldown and depressurization? (0.5)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
. : \
~
?,.
- 0! O 1 l
-5.= EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 l (33%) {
.i j
' ANSWER- 5.02 (1.00). !
a.- Failure of RCP. seals: [+0.5]: l 1 b.. Depressurization of the Steam Generators.- [+0.5] i I REFERENCEL j i 1.: Vogtle: ECA-0.0. ! c z. Vogtle: LO-LP-37031-04, Obj. 2. : i 000055K302-_ ..(KA's) !
]
QUESTION- 5.03 (1.00)_ STATE the Technical Specification basis.that refers to EACH of the following:
- a. Uncontrolled withdrawal of a rod. - (0. 5) -
'b.- Uncontrolled withdrawal of a bank. (0.5) d i
i 1 i ANSWER 5.03 (1.00) )
- 1. - (Uncontrolled withdrawal of a rod) will be no more l severe than accident analysis. [+0.5] 4
- 2. (Uncontrolled withdrawal of a bank of rods) will not i result in a peak power density that exceeds centerline
- melting criterion. [+0.5] j 4
l
)
l (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ;
p:gp ;., c r p
.q .q
-Q. 4g h '5; EMERGENCY =AND ABNORMAL PLANT-EVOLUTIONS Page 21:
if (33%) is : REFERENCE-p .
- 21. . Vogtle:: Technical Specification B 3/4.1-4..
f 2. Vogtle:' LO-LP-39205-04-C, Obj. 4. p 000001G004 ..(KA's)
.e
. QUESTION 5.04 (1.00)-
Technical = Spec'fications' place specific tem on-boric acid flow path lines. . WHICH ONE. (perature
- 1) of requirements--
the following t
-describes the consequences of failure to meet-these temperature requirements? (1.0)-
(. _ a' ) A pH in.the range outside assumed in accident analysis. (b.) Degraded boration flow capacity. 1 (c.)- : Thermal shock to~CVCS and RCS components. (d.)- Conversion of- the boric acid from a tri-borate to a monoborate. form.
' ANSWER 5.04- -(1.00)'
- (b.) [+1.0]
REFERENCE-
.1. Vogtle: Technical Specification B 3/4.1.2.1 and 3/4.1.2.2
- 2. Vogtle: LO-LP-09402-02-C p. 13 000024K104 ..(KA's)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
i
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 22 (33%)
QUESTION 5.05 (1.00) Emergency operating procedure 19010-C, "E-C, Loss of Reactor or Secondary Coolant," is entered by symptoms of loss of inventory from either the RCS or the secondary. State FOUR (4) indications which could be used to differentiate a steam-line break and LOCA. (1.0) ANSWER 5.05 (1.00)
- 1. high steam flow
- 2. low steam pressure
- 3. steam line delta pressure
- 4. steam generator level decrease
- 5. Tavg decrease
- 6. Containment radiation increase Any four (4) [+0.25] each; max. [+1.0] 4 i
. REFERENCE
- 1. LO-LP-34610-01-C Obj.10 000040A203 000011A213 000009A236 ..(KA's)
QUESTION 5.06 (1.00) Following a reactor trip caused by a loss of offsite power, steam dump operation is immediately inoperable. DESCRIBE HOW the steam
' dumps are made to be inoperable following a loss of offsite power. (1.0)
ANSWER 5.06 (1.00) CWP breakers trip on U.V. 0.5 steam dump control system ;+0.5;?whichbreakscontactC-9inthe
+ .
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
9 9 1
- 5. EMERGENCY AND ABNORMAL PLANT EVOLl'(IONS L Page 23. ;
( 33%) REFERENCE <
~ l'. Vogtle: LO-LP-21201-05.
- 2. Vogtle Text, Chapter 10g.
000051K301- ..(KA's)- , . QUESTION 5.07 (1.00) : WHAT action is~taken to stop leakage and re-establ.ish pump shaft l
, sealing after the'#1 RCP seal fails? (1.0).
l i j 5.07- 1
-ANSWER (1.00)
Closure of RCP #1 seal leakoff isolation valve. [+1.0] ! I REFERENCE. j 1.- 'Vogtle: LO-LP-60304-03-C. 000015A122 ..(KA's)
= QUESTION. 5.08 (3.00)
In reference to 19100-C, "ECA-0.0, Loss Of All AC Power," answer the > following.
- a. STATE the immediate action performed to assure a secondary heat sink. (0.5)
- b. STATE the FIVE (5) immediate actions performed to isolate the RCS. (2.5)
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
u-4 10 0
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS ~ Page 24
-(33%)
ANSWER 5.08 (3.00)
- a. ' Verify AFW flow greater than 570 gpm. [+0.5]
,-- b. 1. PZR PORVs shut [+0.5]- l 2. letdown isolation valves shut
.3. excess letdown isolation valves [+0.5]
shut [+0.5]
- 4. reactor vessel head vent' isolation valves shut [+0.5]
- 5. RCS sample valves shut [+0.5]-
REFERENCE
- 1. ECA 0.0 " Loss of All AC Power" 19100-C 000055K302 ..(KA's)
QUESTION 5.09- (1;00) Step 1 of 19211-C, "FR-S.1, Response to Nuclear Power Generation
/ATWT,". requires a manual trip of the reactor. STATE TWO (2) actions to be taken if the manual trip does not function? (1.0)
ANSWER 5.09 (1.00)
- 1. Manually open supply feeder breakers to rod drive M/G sets 480 VAC supply buses (open breakers to NB08 and NB09) [+0.5]
- 2. Manually insert control rods. [+0.5]
REFERENCE
- 1. Vogtle: E0P FR-S.1, 19211C.
000029G010 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
L .9 4- _
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 25 (33%) .- ,
QUESTION 5.10 '(1.50)
- a. WHAT is the Technical Specification SAFETY LIMIT for reactor !
coolant system pressure? (O'.5) ;
- b. .WHICH 0NE (1).of the following actions must be taken if l the RCS pressure safety limit has been exceeded? (ASSUME Mode 1 conditions.) (1.0)
(1.) Be in HOT standby with pressure in limits within one (1) hour. (2.) Be in ROT standby within 10 hours or have RCS I pressure less than limit in 5 minutes. (3.) Be in HOT standby with pressure in limits within 48 ! hours. (4.) . Reduce'RCS pressure below limit within 30 minutes I and be in HOT standby within 24 hours. l j ANSWER 5.10 (1.50) ]
- a. 2735 psig [+0.5] 1
- b. (1.) [+1.0]
4
. REFERENCE
- 1. Vogtle: Technical Specification 2.1.
000027G003 ..(KA's) QUESTION 5.11 (1.00) Procedure 19001-C, "ES-0.1, Reactor Trip Response," has a note that directs' operators to a specific procedure to establish charging and letdown in the event that instrument air is lost. WHAT flowpath (valves and flow destination) is used to establish letdown ;n this condition (valve numbers not required)? (1.0) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
Fq. ./ u ; (, , LOL O E 5. EMERGENCY AND ABNORMAL-. PLANT EVOLUTIONS Page 26 (33%) rANSWER. 5.11 (1.00) Letdown is established using reactor vessel head vent flow controi valves-[+0.5] to the PRT [+0.5]. 2 REFERENCE-
- 1'.. -Vogtle: -ES-0.1, 19001-C.
000065A208 000028K305 000028A210 ..(KA's) QUESTION 5.12 (1.50) Unit 1 is in progress of transitioning from Mode 5 to Mode 4. During this transition wide range pressure transmitter PT-408 fails high. t a. WHAT' automatic action associated with.the RHR system should occur? INCLUDE applicable setpoints.and/or interlocks. (1.0)
- b. WHAT is the purpose of this automatic action? (0.5)
ANSWER 5.12 (1.50)
- a. RHR suction isolation valves will close [+0.5] at indicated pressure of'750 psig [+0.5].
- b. Protect RHR from exceeding design pressure. [+0.5]
REFERENCE
- 1. Vogtle: LO-LP-12101-15-C.
000025A206 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 27 (33%)
QUESTION 5.13 (2.00) ASSUME initial condition of 100% reactor power, Tave of 588.5 deg F. a. A loop)1 ONE (1 ofnarrow range Tc the following failing sets low would result in WHICH of indications? (1.0) Tavg d-T Loop 1 OPd-T Setpoint OTd-T Setpoint Loop 1 Loop 1 Loop 1 (1.) decrease increase decrease decrease (2.) increase decrease decrease increase (3.) decrease increase no change increase (4.) increase decrease increase no change
- b. Utilizing the Technical Specification attachment on the following page, the inoperable channels of RPS must be placed in the tripped condition within WHICH ONE (1) of the following? (1.0)
(1.) 30 minutes (2.) 2 hours (3.) 4 hours (4.) 6 hours ANSWER 5.13 (2.00)
- a. (3.) [+1.0]
- b. (4.) [+1.0]
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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- g. ;o;
- 5. ' EMERGENCY'AND. ABNORMAL PLANT EVOLUTIONS Page 28-(33%)
i l REFERENCE 1
- 1. .Vogtle: ' Technical Specification 3/4.3.1.-
- 2. Vogtle: LO-LP-16101-02.
000007A103'- ' ..(KA's)
' QUESTION 5.14- (1.50)
During the first part of-Procedure 19030-C, "E-3, Steam Generator. Tube Rupture," RCS. temperature and pressure are changed, dependent
- on 'certain secondary )lant ~ parameters. STATE' the secondary .
parameters used AND w1ere'RCS temperature and/or pressure are adjusted.in relation to these parameters. (1.5)
-ANSWER 5.14 (1.50) p_ 9.N A Failed S/G t z;rature.-E+0dsb RCS- temperature is decreased belowsaturationtemperatureofthefailedS/G.[+0.5].
L --Failed-S/G-pressure-{*0,25}+ RCS pressure is '(then) reduced below the pressure of the failed S/G [+0.5]. htiFERENCE r
- 1. Vogtle: E-3, " Steam Generator Tube Rupture."
000038K301 ..(KA's) (***** CATEGORY :5 CONTINUED ON NEXT PAGE *****)
[? 3 L , -
- 30. O .
15! EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 29 (33%) 1 l l QUESTION 5.'15 .(1.00)
. PRIOR to-a ' reactor trip;' WHICH ONE (1) of the following would N0T l be considered indication of a steam generator tube rupture for the ,
affected steam generator 7 _(10) (a.) Increase-in steam generator level.
~ (b.)- ' Steam flow / feed flow mismatch.
(c.)' S/G pressure increasing: rapidly.
.(d.) High. level'on main steam,line rad monitor.
! ANSWER 5.15 -- -(1.00)
'(c.). [+1.0]
REFERENCE 11._ Vogtle:- LO-LP-37311-06-C. 2.'. Vogtle: E-3, " Steam Generator Tube Rupture." 000038A203- ..(KAfs) QUESTION 5.16 (1.00) Step 22'of Procedure 19000-C, "E-0, Reactor Trip or Safety Injection," has you STOP ALL RCPs if you have at least one SI or CCP running and RCS pressure is less than 1375 psig. WHAT are TWO (2) reasons for NOT running the.RCPs below this pressure? (ASSUME normal containment conditions exist.) (1.0) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
g , 9 9
/ i5.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS: Page 30.
L. -(33%) ANSWER 5.16' .(1.00)
- 1. . Reduces inventory loss [+0.5] (during small break LOCA) l
- 2. Restricts clad temperature increase [+0.5] (to lower values than if pumps were to trip later in accident)
REFERENCE
- 1. Vogtle LO-LP-37111-04-C Obj. 6 000009K323 ..(KA's)
QUESTION 5.17 (1.00) The following plant conditions exist:
. Reactor in Mode 5.
Core thermocouple' readings 150 deg F. Cooling medium RHR - midloop operations. . Hours since shutdown from full power - 40. Reactor shutdown was from the end of a fuel cycle after extended operation at high power. Hot leg dams 'are installed with the cold leg primary manway covers installed. As per a CAUTION in Procedure 18019-C, " Loss of RHR", if RHR cooling
'is lost, saturated RCS conditions and subsequent core uncovering will result within WHICH ONE (1) of the following? '(1.0)
(a.) 10 minutes (b.) one (1) hour (c.) 10 hours (d.) two (2) days (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) I
o
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'5. ' EMERGENCY,AND ABNORMAL PLANT EVOLUTIONS- 'Page-31
'(33%)-
4 LANSWER 5.17- '(1.00') (a.). [+1.0) REFERENCE
- 1. Vogtie: .LO-IU-60315-01-001'.
2.- Vogtle: -LO-LP-60315-03-C. ll 000025K101 ..(KA's)' l QUESTION- 5.18 (1.00) l
~
.WHICH 0NE L(1) of the following is NOT'an indication which might.
~
occur during a Loss of Secondary Coolant? (1.0) -l (a.) Outward:rodmotion (b.)- Containment sump level increasing l
.(c.) Steam.line radiation monitor alarm (s)' .i
~!
j
- (d.) Feed flow - steam flow mismatch i
' ANSWER- 5.18 (1.00) .
.(c.) [+1.0]
REFERENCE
- 1. Vogtle: LO-LP-37121-05, Objectives 5 & 6, pp. Sf. j i
000040G011 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ___ - --_ - __ _ - _ a
.5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 32
-(33%)
L g QUESTION- 5.19l (1.00) WHICH ONE (1)'of the following correctly-describes why SG's are depressurized at the maximum rate to (ultimately) atomspheric. L. pressure during the execution of E0P 19221, " Response to Inadequate Core Cooling"?- (1.0).
' (a.) To reduce RCS pressure to allow the'ECCS accumulators and low pressure SI pumps to inject water (b.) To reduce RCS pressure to prevent the formation of superheated.
' steam in the core-(c.) To reduce RCS' temperature to increase thermal driving head for natural circulation (d.) To reduce RCS temperature in order to collapse any steam void in the upper part of the reactor vessel-ANSWER ~ '5.19 _1.00).
( (a.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-37061-02, Objectives 1 & 2, p. 8.
- 2. Vogtle:. LO-IU-37061-00-001, Ques. 2a, p. 1-12.
000074K311 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
i ..
;5. EMERGENCY AND'ABNt/RMAL PLANT EVOLUTIONS- Page 33' )
(33%) .l l I
!- ' QUEST' ION ' 5.20 (1.00)i -l Following a control room evacuation due to fire, control of all l components;has been transfered to the shutdown panels. The shutdown i panel switch for the 'B' SI pump is "0FF" when a valid SI signal is j received. The pump will do WHICH ONE (1) of the' following'l (1.0) 1 t
.(a,). Start, and-remain running until SI is reset. l q
- (b'. ) ~~ Start, and remain running until its associated breaker is l locally opened. !
-(c.) Not start, but the o)erator may start the pump using the shutdown panel switc1 without first resetting SI. ;
(d.) Not start, but the operator may start the pump by first ; resetting SI and then using the shutdown panel switch. ! i ANSWER 5.20 (1.00) ; (c.) [+1.0]. l REFERENCE !
- 1. .Vogtle: LO-LP-60327-00, Objective 2 & 3, p. 6. !
000068A122 ..(KA's) i l l 1 4 I {: I i l- (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) ) i l _ _ _ _ - _ _ _ _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _
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- 15. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 34 (33%)
QUESTION 5.21 (1.00) With the plant in Mode 5 on RHR, an unisolable leak'in the Component Cooling Water (CCW) train occurs on the 'A' train CCW pump common dischar WHICH l0NE'(1)ge header, of the placing following the ' A'describes correctly train of CCW out of service. the action required by A0P 18020, " Loss of Component Cooling Water", for affected loads? (1.0) (a.) The A Train RHR pump must be secured to prevent RHR heat exchanger damage due to loss of cooling water flow. (b.) The A Train RHR pump must be secured'to prevent RHR pump seal damage due to loss of seal cooling. (c.) The A Train Spent Fuel Cooling pump must be secured to' prevent SFC heat exchanger damage due to loss of cooling water flow. (d.) The A Train Spent Fuel Cooling pump must be secured to prevent SFC pump seal damage due to loss of seal cooling. ANSWER 5.21 (1.00) (b.) [+1.0] REFERENCE
- 1. -Vogtle: LO-LP-10101-03, Objectives 2.d and 13.
- 2. Vogtle: A0P 18020-C, Caution prior to step 4, p. 2.
000026K303 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
KJ . . . ., ;,. , ,
'b. ':
n 5. " EMERGENCY AND ABNORMAL PLANT EVOLUTIONS- -Page 35- l y -(33%) , p E .-QUESTION 5.22 (1.00)- If the following indications are received in the Unit I control room while at full power, WHICH ONE (1) of the following 120VAC vital- 1 instrument panels has'probably been lost'l- -! , INDICATIONS: i
'Ali Channel-.II Trip Status' Lights' energized !
Loss of Power Range Channel N-42 & Intermediate Range Channel N-36 u Inverter 180112 Trouble Alarm at EAB (1.0) i
!(a.) 1AY1 A - ,
-(b.) IBY1B (c.); IBY2B (d.) ICY 1A- ,
l 1 i ANSWER 5.22 ( _1.00) j i (b.) -[+1.0] i i REFERENCE l
- 1. Vogtle: i 2.- Vogtle:, LO-LP-01103-03-C, Objective LO-LP-60324-01, Objective 1 - & 2b, p. 4.
3, p. 4. 3.- -Vogtle: LO-IU-60324-00-001, p. 1-6.
- 4. Vogtle: A0P 18032-1, Section C. ,.
j l 000057K301- ..(KA's) ] i j l l 1 1 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) j 1 _ -_ __-----___--__-___---__-__---_____-____L
7 -.., r '
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,15. ~ EMERGE'CY N AND ABNORMAL PLANT EVOLUTIONS- Page 36 ;.;
(33%)-
. . .I' / -
I QUESTION 5.23 (1.00) .- WHICH ONE (1) of the following buildings are NOT served by the fire j protection seismic dry standpipe system? (1.0)~ :! l (a.) Containment. Building j (b.)? Fuel Handling Building l (c;) Auxiliary Feed Pump House (d.) Diesel' Generator. Building l
-) .
ANSWER- .5.23 (1.00)
-i (c.) ' [+1.0] '
REFERENCE 1 ~. Vogtle: LO-LP-43101-04-C, Objective 6c, p. 17.- 000067A216. ..(KA's) i QUESTION 5.24 (1.00) WHICH ONE (1) of the following procedures or conditions does NOT l require emergency boration? (1.0) :) 1 (a.) " Response to Nuclear Power Generation /ATWT" (EOP-19211-1/FR-S.1) ) (b.) " SOURCE RANGE HI FLUX LEVEL AT SHUTDOWN" annunciator response (c.) Shutdown margin less t~an n required by Technical Specifications f(d.)- " Rod Control System Malfunction - Uncontrolled Continuous Rod Motion" (A0P-180003-1)1. 4 (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) , i
p e. . . 0 j') h. ,; 5.: EMERGENCY AND ABNORMAL' PLANT ~ EVOLUTIONS- Page 37 l (334) ! h- , m p l ANSWER- 5.24J -(1.00); l
. 1
'(d . ) - '[+1.0].
. REFERENCE .;
- 1. .Vogtle: LO-IU-09402-00-001', p. 1-2.
2.. Vogtle: EOP 19211-C/FR-S.1, step'5, p. 3.
-3. 'Vogtle: ARP 17010-1 & -2, C01.
4.. Vogtle: Technical Specifications 3.1.1.1 & 3.1.1.2,
.pp. 3/4-1-1:& 3/4-1-3.
j 000024K301 ...(KA's) i
' QUESTION- 5.25 (1.00)'- ;
E0P 19001-C, "ES-0.1, Reactor Trip Response," requires restarting one RCP if RCP's are not running. WHICH RCP(s) are' preferred _for .! starting, and WHY? (1.0) i ANSWER 5.25 (1.00)
- RCP(s) 1 or 4 -([+0.5] for either or both), in order. to provide q normal pressurizer spray [+0.5]. ;
~ REFERENCE 1
l '. Vogtle: LO-LP-37011-03, Objective 15. , 2.- .Vogtie: LO-IU-37011-01-001, Question 18, p. 1-15.
]
000025A104 ..(KA's) (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) , l _ -___-_a
- k W[
f,,, * ' h 1 J5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 38 [.. (33%) l s: ;
; QUESTION 5.26 (1.00). ;
.Following,a small break Loss of Coolant Accident, SI flow has been-reduced in:accordance with E0P 19010-C, "E-1, Loss of. Reactor or
, Secondary Coolant", and E0P 19011-C, "ES-1.1, SI Termination". WHAT 4 are the TWO (2) conditions'(listed on the foldout page)'which require. ' SI to be reinitiated? (Assumeadversecontainment.00ESNOTexist.) (1.0) , i 2 ANSWER' 5.26 (1.00) . j ('
- 1. RCS subcooling < 24 deg F [+0.5]
- 2. PRZR level cannot be maintained > 9 % [+0.5]
a REFERENCE j
-i
- 1. Vogtle: LO-LP-37111-04-C, Objective 10, p. 11.
]
000009K328 ..(KA's) 1
)
QUESTION 5.27 (1.00) In responding to a Steam Generator Tube _ Rupture, after the transition ! has been made from E0P-19000, "E-0, Reactor Trip or Safety Injection", ) to E0P-19030, "E-3, Steam Generator Tube Rupture", WHICH ONE (1) of the following is correct concerning the usage of RCP trip criteria? (1.0) ! (a.) RCP.s should be tripped anytime during E0P-19030 if the criteria are met. L (b.) RCPs should be tripped during E0P-19030 only if the cr;teria are met when the operator is specifically required to check the l criteria at step 1. (c.) RCPs should be tripped during E0P-19030 only if the criteria are met before isolating the ruptured SG(s) at step 3. (d.) RCPs should be tripped during E0P-19030 only if the criteria are met before initiating RCS cooldown and depressurization at step 14. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
g _ _ _ yW . w a; o
,a .
u ' E V i5. EMERGENC' YAND ABNORMAL PLANT EVOLUTIONS' 'Pagel39' (33%) al_;[ s' (ANSWER' ; 5;27l (l'.00)
? (d.) . [+1.0]'
REFERENCE 1.- Vogtle: LO-LP-37311-06-C, Objective 10, p.12..
. S 2. - Vogtle: E0P-19030, Step 1~RNO, p.E2.
'000038K308: ..(KA's)
' QUESTION 5.28: (1.00).
- WHICH ONE (1); of:the following.' correctly lists the~ order' in which major loads. are. sequenced onto the 4.16KV ESF busses following a loss of normal AC supply power.(undervoltage condition);WITHOUT the presence'of an SI signal? .(1.0)
(a;) 1. Component Cooling Water (CCW) Pumps
'2' . Auxiliary Component Cooling Water.(ACCW). Pumps 0 3. Nuclear Service Cooling Water (NSCW) Pumps
' 4 .-
- 5. .Auxiliary Centrifugal Feed ChargingWater (AFWPump)'(CCP) . Pump-(b.)- l '. Centrifugal Charging Pump (CCP)
- 2. : Component-Cooling Water (CCW) Pumps 3.- . Auxiliary Component Cooling Water (ACCW) Pumps 4.
L 5. Auxiliary Nuclear ServiceFeedCooling Water Water (AFW) Pump (NSCW) Pumps (c.) 1.. Centrifugal Charging Pump (CCP)
- 2. Auxiliary Component Cooling Water (ACCW) Pumps
- 3. Component Cooling Water (CCW) Pumps 4.
C 5. Auxiliary Nuclear ServiceFeedCooling Water Water (AFW) Pump (NSCW) Pumps
'(d. ) 1. Component Cooling Water (CCW) Pumps
- 2. Nuclear Service Cooling Water (NSCW) Pumps
- 3. Centrifugal Charging Pump (CCP)
- 4. Auxiliary Component Cooling Water (ACCW) Pumps
- 5. Auxiliary Feed Water (AFW) Pump l
l L , (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
[? /f* ~5. o;; EMERGENCY'AND ABNORMAL-PLANT EVOLUTIONS ~
;O Page.40-
, (33%).
p l-Vi
- ANSWERT .5.28 (l '.00) -
,:(c.) [tl.0].
' REFERENCE-1'. - Vogtle:. LO-LP-01401-04-C, Objective 6a, p. 9.
000056K301 ..(KA's) L (*****ENDOFCATEGORY 5 *****)
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I I? : 6. ' PLANT' SYSTEMS (30%)'AND PLANT-WIDE GENERIC' Page 41
- RESPONSIBILITIES.(13%)
I F . QUESTION; 6.01- (1.50) L b'
- MATCH the following systems with their respective loads. A response.
is needed for each load.-(Systems'may be used more than once or not
'at all.) .(1.5)
LOAD' SYSTEM
- a. 'CCP and: lube oil cooler 1. Component _ Cooling Water b.. : RCP thermal barrier HX. 2. Nuclear Service' Cooling Water c.- RHR-HX
- 3. Auxiliary Component
- d. Letdown Hx Cooling Water
.e. . Spent fuel. pit Hx 4. Circulating Water System
- f. Control building ESF Chiller
- ANSWER 6.01 (1.50)
.a. 2
- b. 3 -
- c. ~1
'd. 3
- e. I f.- -2
[+0.25] each; max. . [+1.5) REFERENCE
- 1. Yogtle: LO-LP-60316-01-C.
- 2. . Vogtle: LO-LP-60317-00.
- 3. Vogtle: LO-LP-60318-00.
008000K102 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE-GENERIC Page 42 RESPONSIBILITIES (13%)
QUESTION 6.02 (1.00) WHICH ONE (1) of.the following would be' considered a core alteration? (1.0) (a.) Lowering RCS level to slightly below vessel flange. (b.). The testing of the irradiation sample handling tool for proper operational (pre-use inspection). (c.) Loosening of vessel head studs. (d.) Withdrawal of a RCCA above vessel flange. ANSWER 6.02 (1.00) (d.) [+1.0] REFERENCE
- 1. Vogtle LO-LP-25201-06-C Obj. 2 034000G011 ..(KA's)
QUESTION 6.03 (1.00) STATE the associated Technical Specification bases for EACH of the ingtisolation signals. t F< u'uN (1.0)
- a. Shig i
- b. High-High steamas..erator level Q t)6 S T/d A' 06/6 $ O ANSWER 6.03 (1.00)
- a. Minimizes RCS cooldown frcm break of feed to steam' H .5].
- b. Protects turbine and prevents excessive cooldown [+0.5].
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- i. REFERENCE i1. Vogtle: 'LO-LP-18201-06-C.
059000K419 ...(KA's) L
' QUESTION- 6.04: -(1.00)
A' high activity / radiation level received by WHICH ONE (1) of the - following-area detectors-will result in a containment ventilation isolation?- (1.0)-
. (a.)- RE2562A Containment Particulate Detector
-(b.) RE005 Containment High Range Detector (c.) RE002' Containment Low Range Detector (d.) RE004 Containment Access Hatch Area Detector ANSWER 6.04 (1.00)
(c.) [+1.0] REFERENCE 1.. .Vogtle: LO-LP-32101-07-C. 072000K102 ..(KA's)
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-RESPONSIBILITIES (13%) j l
' QUESTION -6.05 (2.00)'
STATE the condition'and/or accident each of the following power-
- range tr ips provide protection' for as specified in Technical .
~
Specifications Bases.
- a. .High setpoint 109% !
(0.5)
- b. Low s'etpoint 25% (0.5)- i a
c.- +5% SUR Trip (0.5)
- d. -5% SUR Trip -(0.5) -)
s
-ANSWER- 6.05 (2.00) a.- reactivity excursion from all power levels [+0.5] I b., reactivityexcursionbeginningfromlowpower-[+0.5]
- c. ruptured CRDM housing (or rod ejection from'mid-power) l
[+0.5]l l
- d. control rod drop-accidents [+0.5]
REFERENCE
- i. 1. Vogtle: LO-LP-17301-03.
l l 2. Vogtle: Technical Specification Bases, B-2.2. 1 015000G006 ..(KA's) i i l i i (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1-( l: ____ _ ____ ______ -___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ o
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77 u; . [] .' t] < , i
- 6. ' PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 45 I
!.. RESPONSIBILITIES (13%)
l L j 6.06: 'l QUESTION (1.00) WHICH ONE (1) of the following conditions will stop-outward rod
' motion in the automatic mode but NOT in the manual mode? (1.0)
(a.)' 1/21R greater than current equivalent to 20%' reactor power !
.(b.) 1/4 PR greater than 103%~
(c.). 2/4 OT delta-T 3% below trip setpoint r. (d.) CBD at 223 steps.as detected by the P/A converter l l
< ANSWER 6.06 (1.00) 'l (d.) - [+1~.0] ' .l l
REFERENCE-l l
- 1. .Vogtle: 'LO-LP-27102-05. j l
001050K401 ..(KA's) l l
-QUESTION 6.07' (1.00)' )
l The following conditions exist: l Reactor plant at 70% power i
- a. Using the Rod Insertion Limit graph attachment on the following page,.WHAT is the Bank D rod position setpoint for rod bank LO-LO limit alarm? (0.5)
- b. What is the setpoint difference in rod steps between I actuation of the LO-LO limit alarm and the LO limit alarm? (0.5) 1
)
I I (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) I L _ . ._ -_ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____- ___O
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC- Page 46-RESPONSIBILITIES (13%)
ANSWER' 6.07 (1.00)
- a. ! 92 +/-- 2 steps.- [+0.5]
b.- 20. steps'[+0.5]
.. REFERENCE-
- 1. . Vogtie: LO-LP-27102-05.
014000A103 ..(KA's) QUESTION 6.08 (2.00) Safety Injection has been inadvertently activated.
- a. .WHAT.TWO-(2) conditions and/or signals must exist before the' block / reset circuit will function? (1.0)
- b. After RESETTING the SI signal, WHAT action must be performed to allow automatic actuation of SI? (1.0)
ANSWER; 6.08 (2.00)
- a. 1. 60 see time delay timed out [+0.5]
- 2. P-4 signal present [+0.5]
- b. Reactor trip breakers must be closed (cycled) [+1.0]
REFERENCE 1.. Vogtle: LO-LP-28202-02.
- 2. Vogtle Text , Chapter Ba, p. 72.
013000K401 ..(KA's)
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O i6.. PLANT SYSTEMS (30%)'AND PLANT-WIDE GENERIC Page 47
. RESPONSIBILITIES-(13%)-
l 1 QUESTION .6.09l-(1.00)' TWHICH_0NE (1) of the followi 3 statements is NOT CORRECT in reference to the turbine driven AFW pump steam supply isolation .
, : valve HV-51067 (1.0) p (a.)' ;Normally shut, will auto open on a TDAFP start.
-(b.)- AC operated valve (1 ABB).
-(c.)' Receives both train A and B open signals.
'(d.) Fails'as is, can be manually. operated.
ANSWER 6.09 (1.00)
-(b.) [+1.0]
REFERENCE.
- 1. Vogtle: LO-LP-20101-08-C.
061000K201 ..(KA's)
-QUESTION 6.10 (1.00)
Using the attachment on the following page, WHICH ONE (1) of the following parameters would initiate an automatic SI actuation if sensed values were as indicated? (1.0) (a.): Containment Pressure (b.) Pressurizer Pressure (c.)- Power Range High Flux (d.) _-Steam Line Pressure (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) . I h - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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RESPONSIBILITIES (13%) l' j J LANSWER 6.10 (1.00).
~
(d.) - [+1.0] . ; i
- REFERENCE l
.1. .Vogtle: LO-LP-28103-06-C.
)
; . 013000K101'. ..(KA's) .l i
.l i
.i
' QUESTION: 6.11 (1.00) l 1
e cto own Tave < 350 deg F. . ; Both trains of cold over pressure protection armed.- ;
.i If_ loop.1 Tc wide range RTD develops a short circuit and results 1
'in minimal resistance, WHICH ONE (1) of the following represents .;
system response? (1.0) ! (a.)' Train B PORV opens due to pressure setpoint_ decreasing below .j actual RCS~ pressure as-a result of low Tc indication. .I (b.)- Train B PORY remains closed as-a result of high-Tc indication. ! i (c.). Train A PORV opens due to pressure setpoint decreasing below actual RCS pressure as a result of low Tc indication, j
.I (d.) Train:A PORV remains closed as a result of high Tc indication. !
j l , . ANSWER 6.11 (1.00)
-(a.) [+1.0] !
-l I
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- 6. PLANT' SYSTEMS (30%)~AND PLANT-WIDE GENERIC' Page 49 RESPONSIBILITIES (13%)
.REFERENC21
.1. Vogtle.LO-LP-16501-02-C
- 2. . Vogtle LO-IV-16501-00-001 Ol0000A203 ..(KA's)
QUESTION ~6.12 (1.50)
- a. Describe the generic normal power supply flowpath to a 120 V AC IE vital bus. (0.5) i
'b. Describe the generic alternate power supply flowpath to' a
.120 V AC IE vital bus. (0.5)
- b. WHAT allows only one (1)l power supply to provide power at' any one time? (0.5)
ANSWER: 6.12 (1.50)
- a. 125 VDC bus through invertor (normal) [+0.5] ,
- b. 480VACMCCthroughtransformer(alternate) [+0.5)
- c. mechanical interlocks between breakers [+0.5]
- REFERENCE
- 1. Vogtle: LO-LP-01103-03-C.
062000K410 ..(KA's) QUESTION 6.13 (1.50)
' ASSUME ONE of the two 17% bistables in the pressurizer level
. control. circuit failed low /off. NAME THREE (3) automatic
' functions, other than alarms, that occur as a result. (1.5)
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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6;. PLANT SYSTEMS (30%)- AND PLANT-WIDE GENERIC Page 50 RESPONSIBILITIES (13%) l; I ANSWER 6.13~ (1.50)
- 1. All'PZR' heaters _de-energize [+0.5]
'2. - One letdown isolation valve shuts [+0.5]
- 3. . All' orifice isolation' valves.close '[+0.5]
- REFERENCE-
- 1. Vogtle: LO-LP-16302-00-C.
' 011000K301' ..(KA)
s QUESTION' 6.14 (1.75) Where in the reactor coolant system are each the'following penetrations located? SPECIFY loop (1, 2, 3, 4) AND hot, cold, or intermediate.
- a. normal letdown line (0.25)
- b. pressurizer surge line (0.25)-
c, normal and alternate charging lines-(2 locations required) (0.5) d.- excess letdown line (0.25)
- e. pressurizer spray lines (2 locations required) (0.5) 9 L
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 1
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p. l1 LANSWER. 6.14 (1;75)
- a. Loop 3' cold leg [+0.25]- .l F'
N Loop 4 ' hot leg' , [+0.25] H
- c. Loop 1~ cold-leg- ;+0.25;! l Loop4 cold. leg +0.25,:
d.. Loop:4 intermediate [+0.25] s.- Loop 1 cold ;+0.25 Loop 4-cold ,+0.25; . I REFERENCE' 1.. Vogtle:; LO-LP-16001-01.. ,
- i u
002000K106- ..(KA's) ] QUESTION- 6.15 (1.00) l l The following conditions exist: l An undervoltage trip of reactor trip breaker A.
~ An undervoltage trip of bypass reactor trip breaker B. l A shunt trip of reactor trip breaker A. j u
WHICH ONE (1) of the following trip inputs would have resulted in .j
.the conditions stated above? (1.0) )
(a.) Hi pressurizer level train A. ~j (b.) Simultaneously shutting both bypass reactor trip breakers. l I
- . (c.) : Manual SI~on main control board. 1 (d.){ Manual reactor trip on main control board.
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- 6. PLANT SYSTEMS (30Ss) AND PLANT-WIDE GENERIC- Page 52 RESPONSIBILITIES-(13%)
' ANSWER 6.15 (1.00)
(a.) .[+1.0] REFERENCE
- 1. Vogtle: LO-LP-28001-01, Obj. 4, 5, & 6.
012000K603 ..(KA's) QUESTION 6.16 (1.00) WHICH ONE (1) of the following statements is NOT CORRECT 'in regards to the operation / design of the emergency diesel fuel oil storage tanks? (1.0) (a.) Designed and maintained.to provide a seven (7) day post LOCA demand. l l (b.) Fuel oil storage tank from opposite train may be lined up to supply operating DG day tank. (c.) Storage tank can be filled through manway if normal method < not available. (d.) Fuel oil day tank overflow path is to opposite trains fuel oil storage tank. ANSWER 6.16 (1.00) l (d.) [+1.0] l REFERENCE
- 1. LO-LP-11101-03-C 064000K608 ..(KA's)
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-PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%).
I QUESTION' 6.17 (2.50) J '
- a. STATE SIX (6) conditions that will trip an emergency diesel generator after a normal start that are DISABLED on an emergency start. (Trip values not required). (1.5) j
- b. STATE the FOUR (4) conditions that will trip an emergency l diesel after an emergency start. (Trip values not required), (1.0) :
ANSWER 6.17 (2.50) ; r
- a. 1. High lube oil temp R Pb W"" i 9' w ,( F/&M
- 2. engine bearing high temp
- 3. crankcase pressure high " *' #' g :
- 4. turbo charger oil pressure low p, 4W,e d ;
- 5. Jacket water pressure low pg 1 6.- engine high vibration ". #ia-~ / WV 3
- 7. . turbo charger high vibration ;
Any six (6) [+0.25] each; [+1.5] max
- b. 1. generator differential trip (187 A,B or C / 186 A LOR set) ;
- 2. low lube oil pressure l
- 3. high' jacket water temp
- 4. overspeed
[+0.25] each REFERENCE i
- 1. Vogtle LO-LP-11201-03-C Obj. 7 064000K402 ..(KA's) l QUESTION 6.18 (1.00)
Per the Basis of Technical Specification 3.4.9.3 " Cold Overpressure j Protection System", there are two (2) postulated plant transients I which could cause overpressurization of the RCS in modes 4, 5, and 6. DESCRIBE ONE (1) of these two transients. (Answertoinclude pertinent primary and secondary conditions and/or parameters). (1.0) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 54 RESPONSI81LITIES (13%)
ANSWER 6.18 (1.00)
- 1. The start of an idle RCP [+0.25] with the secondary water temperature of the steam equal to 50 deg F [+0.25] generator above the RCS[+0.25]
coldleg less than or temperature [+0.25].
- 2. Thestartofallthreechargingpumps[+0.5]andsubsequent injection into a water-solid RCS [+0.5 .
Either answer [+1.0] Max REFERENCE
- 1. Vogtle: LO-LP-16501-02-C, Obj. 7.
010000G006 010000K403 ..(KA's) QUESTION 6.19 (1.00) l l The following conditions exist: Reactor power 100%. l Steam dumps - Tavg mode. 1/P transducer for Bank 1 steam dump valves failed to 4 mA output. A load rejection of 15% in two minutes occurs producing a Tavg/ Tref mismatch of 20 deg F. WHICH ONE (1) of the following statements is correct? (1.0) (a.) Bank 1 steam dump valves fail closed due to blockage of control signal by I/P transducer. l (b.) Bank 1 steam dump valves will respond to the trip open I bistable signal and go full open. (c.) Failure of I/P transducer will cause control air to be vented off, preventing steam dump valve movement. J (d.) Bank I steam dump valves fail open due to the reverse action of the I/P transducer. ; (*****CA1EGORY 6 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 55 RESPONSIBILITIES (13%)
ANSWER 6.19 (1.00) (b.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-21201-05.
041000G007 ..(KA's) QUESTION 6.20 (1.00) The Train A CCW system is in normal operation with two pumps running. WHICH ONE (1) of the following conditions will cause the standby CCW pump to automatically start? (1.0) (a.) safety injection signal (b.) undervoltage on vital bus (c.) running pump breaker trip (d.) low CCW surge tank level. ANSWER 6.20 (1.00) (c.) [+1.0] REFERENCE
- 1. Vogtle: LO-LP-10101-02.
008000K401 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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g- 4 ;.c 1 L'L- O .o > 1
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- SYSTEMS'(30%) AND PLANT-WIDE GENERIC Page 56 RESPONSIBILITIES (13%) l 4
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. QUESTION 6.21 (1.00)
] '
WHICH ONE-~(1.0) of the following. correctly describes the function .
'of multiplexing in the Rod Control System? (1.0)
(a.) Provide. current sequence orders for the power cabinets
.(b.) Provide Lcontrol bank overlap signals .to the master cycler (c.) Prevent' logic cabinet output when an urgent alarm is recieved' .j
-(d.)
Prevent the power cabinet from moving more than one group at a time .{ ;
; ANSWER- 6.21 (1.00) -
1 (d.) [+1.0] ! l
-l REFERENCE '
- 1. Vogtle: LO-LP-27101-07, Objective 9, p. 24.
001010K403 ..(KA's) QUESTION- 6.22_ (1.00) When. verifying equipment status following a SI initation, the containment cooling system should have (number) containment cooling fan (s) running in (speed). q
-(Fill in the blanks above) (1.0)
ANSWER- -6.22 (1.00) Eight'[+0.5]; Slow [+0.5] (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i ___________________________Q
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 57-RESPONSIBILITIES (13%)
REFERENCE
- 1. Vogtle: LO-LP-29130-02, Objectives 1 & 2, pp. 6 & 7.
022000K402 ..(KA's)
' QUESTION 6.23 (1.00)
WHICH ONE (1) of the following correctly describes the flowpath for relief of an overpressure condition in Gas Decay Tank (GDT) #17 (1.0) (a.) The GDT #1 relief valve discharges directly to the plant vent system downstream of RV-0014 (trip valve for RE-0014) (b.) The GDT #1 relief valve discharges directly to the plant vent system upstream of RV-0014 (trip valve for RE-0014) (c.) The GDT #1 relief valve discharges to GDT #10, and the GDT #10 relief valve discharges directly to the plant vent system downstream of RV-0014 (trip valve for RE-0014) (d.) The GDT #1 relief valve discharges to GDT #10, and the GDT #10 relief valve discharges directly to the plant vent system upstream of RV-0014 (trip valve for RE-0014) ANSWER 6.23 (1.00) (c.) [+1.0] REFERENCE 1
- 1. Vogtle: LO-LP-46101-04, Objective Sh & Si, p. 18.
071000A209 ..(KA's) l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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- 6. PLANT-SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 58 ;
RESPONSIBILITIES (13%) t QUESTION 6.24 (1.00) : While at 100% power, a steam generator Atomspheric Relief Valve (ARV) fails full open. WHICH ONE (1) of the following correctly lists the i expected increase in total steam flow, assuming no automatic reactor- j protective or control action occurs? (1.0) (a.) 2%
.(b.) 4%
(c.) 6% (d.) 8% ANSWER 6.24 (1.00) (b.) [+1.0] REFERENCE )
- 1. Vogtle: LO-LP-21102-04-C, Objective A.2, p. 9 035010K602 ..(KA's) l I
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PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 59 RESPONSIBILITIES (13%) t I QUESTION 6.25 (1.00) l WHICH ONE (1) of the following states events which will occur on a DECREASING instrument air pressure condition? (1.0) (a.) At 80 psig decreasing, instrument air to the turbine building is isolated from instrument air to the auxiliary and containment buildings. (b.) At 70 psig decreasing, instrument air to the turbina building i is isolated from instrument air to the auxiliary and containment buildings. ; (c.) At 80 psig decreasing, breathing air is isolated from instrument air to the auxiliary and containment buildings. (d.) At 70 psig decreasing, instrument air is realigned to separate Unit l's instrument air to the auxiliary and containment buildings from Unit 2's instrument air to the auxiliary and containment ! buildings. i ANSWER 6.25 (1.00) (b.) [+1.0] ] REFERENCE l
)
- 1. Vogtle: LO-LP-02110-03-C, Objective 14 & 15, p.15. i 078000K402 ..(KA's)
J l QUESTION 6.26 (1.00) l STATE TWO (2) conditions, EITHER of which, will satisfy the minimum administrative SRO control room manning requirements during modes 1, 2, 3, and 4. (1.0) 1 (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) 4 I J
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; +
o 91 6.- PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC ~Page.60 RESPONSIBILITIES (13%)- t .. ANSWER .6.26- (1.00)
. 1. .- One-(1)SRO.withlicenseonbothunits.[+0.5]
- 2. One- (1)' SRO at each unit [+0.5]
i-REFERENCE
- 1. Vogtle:' Procedure 10003-C.
194001A103 ...(KA's)-
, -QdESTION 6.'27.' ' (1.00)
If while performing an independent verification on a valve lineup an
' operator. finds a valve mispositioned,.he should perform WHICH ONE (1) of.'.the following? (1.0)
(a.) position the valve as required (b.) notify shift supervisor (c.)- position valve as required, and then inform shift supervisor of action taken (d.) submit a deficiency card in compliance with (00150-C)
" Deficiency Control."
ANSWER 6.27 (1.00) (b.) [+1.0] REFERENCE 1 l
.1. Vogtle: VEGP 00308-C.
194001K101 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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K w
. QUESTION: _6.28- (1.00) 1 lWHICH ONE (1). of the following'is a required entry item'in' the 7 Unit Control Log,. per procedure 10001-C, " Log Keeping"7.
(1.0);
.(a.): : Personnel injuries
~
(b.). Significant security incidents (c~ )' ' Out-of-specification . chemistry- results. g . (d.), The name and position of each operator on shift. t ANSWER 5 6.28' (1.00)
'(c.) :[+1.0]
REFERENCE
- 1. 'Vogtle: Administrative Procedure 10001-C.
194001A106 ..(KA's) LQUESTION: 6.29 (1.50)
-ASSUME a clearance is to be installed on a Fail OPEN A0V used as a boundary valve. If this valve is without a handwheel, HOW is the. valve tagged? (1.5)
- ANSWER 6.29 (1.50)
-1. HOLD tag the handswitch in the closed position [+0.5]
- 2. (Mechanically or hydraulically HOLD tag the gagging device [y) Gag valve closed [+0.5] and
+0.5].
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' 6;.--PLANT ~ SYSTEMS'(30%) AND PLANT-WIDE GENERIC .Page 62
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( REFERENCE 1... 'Vogtle: .EGP 00304-C, p. 10. . ' 194001K102 ..(KA's) QUESTION '6.30 .(2.00)- STATE FOUR (4) conditions which,.if any one occurs, allow the on-shift reactor operator'to . shutdown the reactor without' prior approval.- (2.0)
; ANSWER 6.30 (2.00) 1.- When _the safety of the reactor is:in jeopardy.
. [0.5]
.2. When a reactor )rotection trip setpoint has been exceed-and-automatic-slutdown does not occur. [+0.5]
- 3. When required to prot'ect personnel and/or equipment. [+0.5]
- 4. When unusual circumstances warrant. [+0.5]
REFERENCE
- 1. Vogtle: Administrative Procedure 10000-C.
194001A103 ..(KA's) (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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'6; PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC. Page 63 RESPONSIBILITIES (13%)
i l (;I l 1: j QUESTION 6.31- (1.00) ) J
, Authorization for whole body exposure from 1001-1500 mrem / quarter requires written approval from WHICH 0NE (1) of the following? (1.0)
(a.) a Health Physics Laboratory foreman and the worker's foreman. 1 (b.) a Health Physics Laboratory supervisor or above and the . worker's supervisor.
' (c.): both the individual's superintendent and Health Physic's ,
' superintendent. l (d.) the Health Physics Laboratory foreman. i 1
l' ANSWER 6.31 (1.00)- (a.) [+1.0] 1 REFERENCE !
- 1. VEGP 00920-C 4.4.6
- 2. Vogtle LO-LP-63920-00-C Obj.14 q l
194001K104 ..(KA's)
. QUESTION 6.32 (0.75) ,
A fire team consisting of at least (a.) members shall be maintained on site at all times. The (b.) shall designate the fire team captain and members at the beginning of each shift.
.The fire team may be reduced by one (1) person for a period not to exceed- (c.). -hour (s). (0.75)
);
(***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) _ _ _ _ _ . __________-_-_____-__-____-_a
py , cm,e s L1i 10 o
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- 6. PLANT' SYSTEMS-(30%) AND PLANT-WIDE GENERIC Page 64 RESPONSIBILITIES (13%)
ANSWER- 6.32 (0.75)' u a.: l5- [+0.25]
- b.- On-Shift Operations Supervisor- [+0.25]-
c.- 2 [+0.25] REFERENCE
- 1. Vogtle: 10003-C, p. 2.
194001K116- ..(KA's). QUESTION '6.33; (1.00). In: reference to personnel monitoring when exiting a RCZ, WHICH
.ONE (1) of the following statements is NOT CORRECT? (1.0)
(a.) A full ~ whole body frisk shall be performed by all personnel when exiting the RCZ access control points. (b.)- Personnel exiting contaminated areas shall, as a minimum, ! frisk their hands, arms, forearms, face, and feet. (c.) Hand carried tools and materials shall be frisked by HP personnel when exiting contaminated areas.
'(d.) 'In certain exceptions, individuals may perform self decontamination without HP personnel present.
ANSWER 6.33 (1.00) (d.) [+1.0] (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) !
( . -. - _ , _ - - - - _ _. .. _ _ o - ij ..- , f} 't }_ .
'6.' PLANT SYSTEMS'(30%? AND PLANT-WIDE GENERIC. Page 65 RESPONSIBILITIES ( 3%) ,
R jREFERENCE 1.- VEGP 00930-C
- 194001K103' ..(KA's);
' QUESTION 6.34: ;(2.00)
- The Emergency Director is responsible for classifying' and declaring
, .an emergency, including up rading, downgrading or termination of the'
' declaration'. . STATE FOUR 4 (g) additional responsibilities of the
- Emergency; Director which CANNOT be delegated. (2.0)
.. ANSWER .6.34 (2.00).
- 1.. -Recommending protective actions t'o offsite authorities.
- 2. ' Authorizing personnel _ radiation exposures in excess of 10 CFR 20 limits.
3._ Deciding-to' evacuate non-essential personnel at alert level. 4.. . Deciding _to request assistance from federal' support groups. 5.- Deciding to notify offsite' authorities responsible for emergency measures.
- Any four (4) [+0.5] each; max. [+2.0]
REFERENCE
- 1. VEGP '91102-C
- 2. Vogtle: LO-LP-40101-09-C.
19a001A116 194001K116 ..(KA's)
-)
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- 6. PLANT SYSTEMS (30%)'AND PLANT-WIDE GENERIC Page 66 RESPONSIBILITIES (13%)- !
L. (. . I i QUESTION '6.35 (1.00) ! i WHICH ONE (1)'.of the following correctly. describes how an independent i verification of position for a manually operated throttle valve is ! performed? (1.0) !
. (a.), Move the valve slightly in.the closed direction-and then return i it to its required position. l i
'- ( b '. ) Completely close the. valve and then reopen it to the required
' position.- !
i l(c.)' Inspect the:last valve lineup sheet for verification signature i and compare recorded valve position with the required position. j i . : (d.) . Compare' visual observation of stem.or indicator position with the !
. required position. I i
i ANSWER 6.35 (1.00) (d.') [+1.0] ) REFERENCE
- 1. Vogtle: VEGP Procedure 00308-C, p. 5. I 194001K101- ..(KA's) l
)
l lI (***** END OF CATEGORY 6 *****) (********** END OF EXAMINATION **********)
(v') (3 m) ( TEST CROSS REFERENCE Page 1 I OUESTION VALUE REFERENCE 4.01 1.00 90002 4.02 1.00 90003 4.03 1.00 90005 4.04 1.00 90006 4.05 1.00 90007 4.06 1.00 90011 4.07 1.00 90012 4.08 1.00 90004 4.09 1.00. 90008 4.10 2.50 90009 4.11 1.00 90010 4.12 1.00 90013
'4.13 -1.00 90001 o 4.14 1.00 90014 4.15 1.00 90015 4.16 1.00 90016 4.17 1.00 90017 4.18 1.00 90018 4.19 -1.00 90019 .
4.20 1.00 90020 4.21 1.00 90021 4.22 1.00 90022 23.50 5.01 2.00 90023 5.02 1.00 90024 5.03 1.00 90025 5.04 1.00 90026 5.05 1.00 90027 5.06 1.00 90029 5.07 1.00 90030 5.08- 3.00 90031 5.09 1.00 90032 5.10 1.50 90033 5.11 1.00 90035 5.12 1.50 90036 5.13 2.00 90037 5.14 1.50 90038 5.15 1.00 90039 5.16 1.00 90040 5.17. 1.00 90041 5.18 1.00 90069 5.19 1.00 90070 5.20 1.00 90071 5.21 1.00 90072 5.22 1.00 90073 5.23 1.00 90074 5.24 1.00 90075 5.25 1.00 90076 5.26 1.00 90077 5.27 1.00 90078 5.28 1.00 90079 33.50
7 3
.i ..
t 6.01~ 1.50, 90028 'j
- TEST CROSS REFERENCE .Page 2. -l i
QUESTIOND VALUE ' REFERENCE 6.02' 1.00. 90034 ! 6.03~ 1.00- 90042- l 6.04- 1.00- ~90043 6.05: 2'00
. 90044 t 6.06' :1.00: 90045 6.07- 1.00 '90046 ;j
.6.08 2.00 90047- l L6.09- 1.00 90048 l 6.10- 1.00 90049 !
6.11- 1.00: 90050 i
< .6.12 1.50 90051 1
.6.13 1.50 90052 !
6.14 1.75 90053 1 6.15 11.00 .90054 1 6.16 1 00
. 90055 I
6.17' 2.50 90056
.6.18- 1.00 90057
'6.19 1.00 90058 6.20 1.00- 90059 !
6.21 1.00 90080 l 6.22- 1.00 90081 i 6.23 1.00 90082 6.24 '1.00 90083 6.25 1.00 90084 ) 6.26 -- 1.00. 90060- q 6.27 .1.00 90061 i 6.28- 1.00 90062 ! 6.29 1.50 90063 1 6.30- 2.00 90064 6.31 1.00 90065 6.32 0.75 90066 6.33 1.00 90067 6.34 2.00 90068 6.35 1.00 90085 43.00 n..... 100.0 ,
)
)
_ _ _ - - _ _ - _ _ _ . - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _}}