ML20210G966
| ML20210G966 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/16/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20149F887 | List: |
| References | |
| 50-483-97-301, NUDOCS 9707220356 | |
| Download: ML20210G966 (6) | |
See also: IR 05000483/1997301
Text
{{#Wiki_filter:_
.
ENCLOSURE
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.: 50-483
License No.: NPF-30
Report No.: 50-483/97 301
Licensee: Union Electric Company
Facility: Callaway Plant
Location: Junction Hwy. CC and Hwy. O
Fulton, Missouri
-
Dates: July 7,1997
Inspector: H. Bundy, Chief Examiner, Operations Branch
Approved By: J. L. Pellet, Chief, Operations Branch
Division of Reactor Safety
ATTACHMENTS:
Attachment 1: Supplemental Information
Attachment 2: Final Written Examination and Answer Key
-
0 y go 3
,
i
.
2-
!
!
!
EXECUTIVE SUMMARY j
Callaway Plant
NRC Inspection Report 50-483/97 301
,
l
l
NRC examiners evaluated the competency of two retake reactor operator license applicants l for issuance of operating licenses at the Callaw w Diant facility. The licensee developed ; the initiallicense examination using NUREG 10J. ' Operator Licensing Standards for Power Reactors," Interim Revision 8. The initial written examinations were administered to ! both applicants on June 27,1997, by f acility proctors in accordance with instructions , provided by the chief examiner. The operating tests had been waived for these applicants. ! Both applicants displayed the requisite knowledge and skills to satisfy the requirements of i 10 CFR 55 and were issued reactor operator licenses. Operations
Both applicants passed the reactor operator written examination. No broad
knowledge or training weaknesses were identified as a result of evaluation of the
graded examinations.
The licensee submitted a satisfactory examination outline which was used for
examination development.
The written examination was acceptable for administration as submitted and of high
quality.
)
J
_
. . . . . . . . . . . . .
.
. .
. .. .
.
.
. .
. . . . . . ..
.
3
Reoort Details
1. Operations
04 Operator Knowledge and Performance
04.1 Initial Written Examination
1
'
a. Inspection Scone
On June 27,1997, the facility licensee proctored the administration of the written -
examination approved by the chief examiner and NRC Region IV supervision to two
individuals who had applied for initial retake reactor operator licenses. The licensee
graded the written examinations and the staff reviewed its results. These
individuals had previously passed the operating test portion of the examination and
it had been waived by Region IV. The licensee also performed a post-examination
question analysis, which was reviewed by the chief examiner. This inspection
consisted of in-office review and approval of the examination results supplied by the
licensee,
b. Observations and Findinas
The minimum passing score was 80 percent. The scores for the applicants
averaged 81.8 percent. Both' applicants missed Questions 23,42,53,61,62,72,
87,95, and 98. Pursuant to the licensee's request, Question 99 was deleted
because the proctors inadvertently failed to provide an attached curve, which was
necessary to answer the question. Also, pursuant to the licensee's request,
Choice C was allowed as a correct answer in addition to Choice D for-Question 32.
The examinations were regraded based on these determinations. No broad training
or knowledge weaknesses were identified. Reasons for missing the valid questions
appeared to be related to question difficulty and isolated knowledge weaknesses.
c. Conclusions
Both applicants passed the reactor operator written examination. No broad
knowledge or training weaknesses were identified as a result of evaluation of the
graded examinations.
05. Operator Training and Qualification
05.1 Initial Licensine Examination Develooment
The facility licensee developed the initiallicensing examination in accordance with
guidance'provided in NUREG 1021, " Operator Licensing Examination Standards for
Power Reactors," Interim Revision 8.
______ a
_ - _-_____-__ _ _-
4
.
* .
4
- 05.1.1 Examination Outline -
. a. Inspection Scope
The facility licensee submitted the initial examination outline on May 2,1997. The i
chief examiner reviewed the submittal against the requirements of NUREG 1021.
b. - Observations and Findinos
The initial examination outline was satisfactory as a guide for development of the '
examination. However, the chief examiner provided several minor enhancement
j suggestions which were incorporated by the licensee.-
c.. Conclusions
The licensee submitted a satisfactory examination outline, which was used for
examination development.
- 05.1.2 Examination Packsoe
a. Inspection Scoce
The facility licensee submitted the completed examination package on June 12,
~ 1997. The chief examiner reviewed the submittal against the requirements of
NUREG-1021.
!-
b. Observations and Findinos
. The draft-written examination contained 100 questions, of which 67 were new,
12 were modified licensee examination bank questions, and 21 were directly from -
the licensee's examination bank. This distribution satisfied NUREG-1021
. requirements. The draft examination was responsive to the knowledge and abilities -
sample plan submitted on May 2,1997, technically valid, and discriminated at the
proper level. It was considered adequate for administration. The questions were
generally of high quality. However, the chief examiner provided comments on
construction for 8 questions. The comments related to the suitability of question
distractors or construction of the question stem. :In response to the chief
examiner's comments, the licensee revised or replaced these questions,
c,. Conclusions
LThe written examination was acceptable for administration as submitted and of high-
quality.
s
.. . . . _ . . . .
. . . . . . .
_ . . . . .. . . .
.
.
. . . .. . . . . . . . . .
_ _.
_ .- _ - _______- - _ -
,
-6- l
l
l
l
- V, Manaaement Meetinas
X1 Exit Meeting Summary
The chief examiner presented the inspection results to Mr. Czeschin on July 9,
1997, and he acknowledged the findings presented.
Mr. Czeschin did not identify as proprietary any information or materials examined
during the inspection,
i i l
_ _ _ _ _ . -__-___
,
_ - -_ _______ ___ - _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ -
.
ATTACHMENT 1
SUPPLEMENTAL INFORMATION
PARTIAL LIST OF PERSONS CONTACTED
Licensee
F. Biermann, Operating Supervisor, Training
G. Czeschin, Superintendent, Training
R. Moody, Operating Supervisor, Training
R. Neil, Shift Supervisor Operations, Training
NHC
D. Passeht, Senior Resident inspector
! l 1
i -
.
.. .. .
.. . .
.. _ _ _ _ _ _ _ _ _ l
- - _ , . - - - . , . , - - - - , . , , - - - - - , - - . - - - - - , - - _ - _ , , _ , - - - _ _ _ - _ - - , , , _ . _ - _ , - - - - , - - - - , _ , - _ _ - - - - , _ _ . _ - - , , - , , _,
9
ATTACHMENT a
FINAL WRITTEN EXAMINATION AND ANSWER KEY
l l l l
. - __ ._
_ _ _ ,
l
CALLAWAY PLANT
EXAMINATION COVFR SIIEET
TitAINING del'AltTMENT
COURSE TITLE: RO INITI AL LICENSE EX AMIN ATION DATE: 6/27/97
N AME (Print): SCORING:
SIGNATURE: ,g# Points Possible: 4e$ ;
e b p' ,.y Points Missed:
DIRECT 10NS: DLACKOLTICORR1CT ANSWERS
[dgM \ E Grade:
l. E [I3] l C l [b] 26. l A l l B l % E St. l A l E l C ll D j 76. E l B l l C l l D j
2. l A l [Bj % E 27. E l B j l C l l D l 52. l A l l B l E l D l 77. l A l l B l E l D j
l 3. l A l E [dl [Dj 28 [h] E l C l l D l 53. l A l E l C l l D l 78. l A l E l C l l D l
4. W B E [DJ 29. l A l l B l l C l E 54. E y l C] ] D l 79. l A l l B l l C I M
5.lAl E W lDj 30. E l o l i c i l o l 55 l ^l M i cil o! so.1^11BI M iol
6. l A l B E [Ul 31.lAjjBl E %/ 56 l A l [5] l C l E 81 l A l l B l l C l g
7. [th [dl l D l 32. l A j j B l [ E 57 M i nil cIl ol 82. i A i i B i i C i E
8. E l B l l C l l D l 33. l A I N I C l l D 58.I^1FUl IDI 83 M inilCllDI
9. W [I3] E lDl 34. % l B l E l D l 59. l A l E l C l l D l 84.lAl l C l [b]
10. l A l E % l D j 35. E l B j [d] l D l 60. l A l E l C l l D l 85. W E l C l l D j
11. l A j [h] l C l E 36 l A l l B l E l D j 61lAll[ [C] E 86. E % l C l [Ul
12. l A l B C E 37 l A j j B l E [Ul 62. l A j j B l l C l E 87 l A l W l C l E
13. l A j W E l D j 38. E l B l l C l l D j 63. l A l [U] E [U] 88. E l B l l C l l D l
14. E B [d] [D] 39. E l B j [CJ l D j 64 l A j j B l l C l E 89. E [Ill l C l l D j
15. E [Bj l C l l D l 40. l A l E l C l [Dj 65. E l B l [CJ l D j 90. l A l E l C l [Dj
16. l A l [El E l D l 41. l A j W E l D l 66. l A l E [d] l D j 91. l A l l B l l C l E
17. [Ill l C l l D l 42. l A l l B l [k'] E 67. l A l E l C l l D l 92 l A l l B j E l D j
18. l A l E [dl [Bl 43. E l B l [C] l D l 68. l A l E l C l l D l 93. l A l l B l E [Dj
19. [h] [BJ [C] E 44. E l B l % l D l 69. E l B l l C l l D l 94 l A l l B l % E
20. E % l C l l D j 45. l A j j B l E l D j 70. l A l l B l l C l E 95. {Aj [,B] E l D j
21.{Al B lDl 46. l A l l B l E [Dj 71. l A l E l C l l D j 96. l A j [ E l D j
22. [k] E l C l l D j 47. l A j j B l j C l E 72. E l B j j C l l D j 97 g [5] l C l l D j
23. l A I M i c i l o l 48 l ^1 E l cIl ol 73 l ^ 1181 E 1 o 1 98 l ^ 11 B ll c l E
24. E l B j [CJ l D j 49. E l B jj C ll D l 74. l A j j B l E l D j
25. E [ % l D l 50. l A l l B l E l D j 75. l A l l B j j C l E '100. l A lj l C l [DJ
--
.
- - -
..
. . .
. . _ _ .
Off . r /7
__- __ - _ - _ _ _ _ _ _ - -
.
CALLAWAY PLANT
EXAMINATION COVER SHEET
TRAINING DEPARTMENT
COURSE TITLE: RO INITIAL LICENSE EXAMINATION DATE:
NAME (Print)- SCORING:
SIGNATURE: Points Possible: 100
Points Missed:
Grade:
mxEenONs: BLACK OtTT CORRECT ANSWERS
1 W @ [CJlDl 26 l A l fBl l C l l D j 51 l A l l B l M [Ul 76 l A l l B l l C l Ibl
2 [lBllCllDj 27 l A l [ [Cl l D l 52 l A l l B l l C l Ibl 77
l All BllCl[
3 l A l W ( CJ [Dj 28 l A l l B l l C l [D] $3 WlBllCllDj 78 l A l l B l l C l [Ul
4
l A l l B l l C l IW 29 lAlfBllCllDj 54 l AllBllCllDl 79 lAllBllCl W
$ [lBllCllDl 30 [Il[bl W lDl 2 ! AllBllCllDl 80 I l l B l l C l [D]
6
9 9 LcJ f61 31 l ^ l l n i f cl f61 56 l^llallcllol si l ^ 11 B l fEl l o l
7 [Il l B l l C l [D] 32 h [Bj l C l l D l 57 lAl[bl[C]lDl 82 lAllBl C [D]
8 Bl % @ [Ul 33 W W l CllD j 58 [l [BjlC] W 83 WlBllCllDl
9
l AllBllCl[ 34 h [bl [CjlDj 54 lAllBllCllDj 84 [llBllCllDl
10 A l B l W IUl 35 l A ll B ll C ll D l 60 lAl[BjlCllDj 85 hllBllCl[Ul
11 lAl[Bj[CJlDl 36 l A l l B l W l D l 61 l A l [Bl l C l l D l 86 l A l l B j [El l D j
12 [hl (15] C lDj 37 lAllBl M lDl 62 l A l l B l l C l [_D] 87 h j B l l C l l D l
13 l A l [Bj l C l (DJ 38 W l B l l C l l D l 63 f l [bl C lDl 88 l A l l B l [El l D l
14 l A l [ l C l [Dj 39 [ ] [Bl [C] l D j 64
[Il[[El(DJ 89 [ lM W l D l
15 l A l l B j [Ul [Dj 40 l A l l B l l C l [D] 65 l A l l B l l C l l D l 90 l A l l B l l C l l D l
IC lAlfbl C D 41 [ [M lCllDl 66 l A l l B l l C l l D l 91 lAllBllCl[D]
17 A [5][hl(DJ 42 [ ] B [ [Dj 67 lAl B WD 92 l A l l B l l C l l D l
18 A lBllCllDl 43 l A l [5] l C l l D l 68 lAllBllCllDl 93 A (Bj[CllDl
19 lAl[BJ C [D] 44 l AlW C lDl 69 lAl\BllCllDl 94 l A l [bl l C l l D l
20 l A l l B l [Ul [Ul 45 l A l l B l l C l [Dj 70 l A l l B l [CJ @ 'M ld l B l l C l l D j
21 [Il l B ll C l [Ul 46 l A l l B l M l D l 71 lAl[BllCllDj 96 hA] l B l l C l l D l
22 @ [ Bj l C ll D l 47 lAllBl[CllDl 72 l All B ll Cll Dl 97 lAllBllCllDl
23 A IEl[C][Dj 48 l A l ( Bj ( C] l D l 73 l AllBllCllDj ,
98 [ \ C l (DJ
24 l A l l B l [El [D] 49 l AllBllCllDl 74 l All BllCllD j 9 ,.,!S! Ibl-
25 l A l [bl C lDl 50 l A l ( B] ] C l [ Dj 75 lAl(BjlCllDl 100 [ Aj [Bj l C l [ Dj
-_ _ _ _ _ _ _ _ _ _ _
QUESTION #1
A Safety injection has occurred due to a Steam Generator Tube Rupture. The crew has just
completed verifying that both NB01 and NB02 are energized per Step 3 of E-0, Reactor Trip or
Safety injection. Which one of the following describes the HVAC flowpath for the Fuel Building
at this time?
A. Fuel Building supply and normal exhaust stops; emergency exhaust dampers align to the
Aux Building.
B. Fuel Building supply and normal exhaust stops; emergency exhaust dampers align to
Fuel and Aux Building.
C. Fuel Building supply keeps running or starts; normal and emergency Fuel Building
exhaust isolates.
D. Fuel Building supply and exhaust keeps running or starts; emergency exhaust dampers
align to the Fuel Building.
! l
'
i
OUESTION #2
The plant is at 100% power, all systems lined up for normal operation with the NCF operatino
with 120 gpm letdown f!ow. A complete loss of uffsite power occurs without a saidy injection
signal. All plant systenis respond as designed except that 2 rods in the "C" Control C?nk ara si
200 steps withdrawn. .
Which ONE of the below describes the actions that will be performed during the initial response -
! to the above conoitions? l l A. Manually start either CCP, open suctions from RWST to CCP since immediate boration l flow from Boric Acid Transfer Pumps are not available. l '
B. Ensure NCP is running, open BGHV8104, Emergency Boration to CCP suction, and start
either Boric Acid Transfer pump.
C. Ensure either CCP is running, open suctions from RWST to CCP since immediate
boration flow from Boric Acid Transfer Pumps are not available.
D. Ensure either CCP is running, open BGHV8104, Emergency Boration to CCP suction,
and start either Boric Acid Tran;fer pump.
,
. - _ - _ . --
.
-QUESTION #3
Plant conditions are as follows:
. Safety Iniection occurred on low steam line pressure
. ECA-2.1 dncontrolled Depressurization of All Steam Generators
. ECA-2.1, Step 2, Control Auxiliary Feed Flow to Minimize RCS Cooldown, has AFW flow
- at 15,000 lbm/hr to each S/G.
- Level Pressure
'
A-SIG 20% WR - 355 psig stable
B SIG 15% WR 300 psig decreasing
C S/G 15% WR 290 psig decreasing
D SIG 25% WR 355 psig increasing ;
,
Which ONE of the following actions should be taken ?
A. Continue with performance of ECA-2.1, Uncontrolled Depressurizaton of All Steam
Generators
B. Transition to E-2, Faulted Steam Generator Isolation
C. Transition to FR-H.1, Response to Loss of Secondary Heat Sink
D; Transition to E-0, Reactor Trip or Safety injection
_
. _ _ _ _ _ _ _ _ _ _ _ _ _ -
.
.
1
l
QUESTION #4 )
You are the on-duty Reactor Operator. In accordance with plant policy, which one of the
following non-licensed individuals may you allow to start the 'A' Safety injection (SI) Pump from
Panel RLO17 in the Control Room?
A. Any system engineer authorized by the Shift Supervisor who is performing Si system
surveillances.
'
B. Any assistant equipment operator performing OJT on the SI system who is being
monitored by the Control Room Supervisor.
l C. Any individual who is in a license ti a.ning program under my direct observation.
D. Any electrical maintenance supervisor troubleshooting why the SI pump vibration
!- readings are abnormal. l
x
4
QUESTION #5' ,
-Tlie following plant conditions exist:
- Reactor power is 1 x 10E-8 amps-
L - - A reactor startup is in progress . .
i
! <
- N-35 Intermediate Range channel fails LOW ;
1
Which ONE of the following actions is' correct per Technical Specification 3.3.1, " Reactor Trip 4
System Instrumantation"?
A. Restore inoperable channel prior to exceeding P-6.
B. Restore inoperable channel prior to exceeding 5% power.
C. Restore inoperable channel prior to exceeding 10% power.
l' - D. Bypass the inoperable channel and continue with reactor startup.-
._
.,
t
t
.
.
. . ...
.
QUESTION #6 a
T:The plant is operating at 100% power with all equipment in its normal lineup. A spurious Si
occurs during some I&C testing. All equipment functions as designed.
y
- Which ONE of the following procedures will the CRS transition to upon completing ES-1,1, Si '
Termination?
A. OTG-ZZ-0001 A, Shutdown Bank Withdrawal
,
L B. OTG-ZZ-00002, Reactor Startup i.
C. OTG-ZZ-00005, Plant Shutdown 20% Power to Hot Standby
D. OTG-ZZ-00006, Plant Cooldown Het Standby to Cold Shutdown
.
- _ _ _ _ _ _ -
-
<
- QUESTION #7c
l The following plant conditions exist at 0400:- L . T avg 557'Fi
-
. PZR Press 2235 psig
l-
. _ Source Range Channel 31 indicates 19 cps
1 Source Range Channel 32 indicates 20 cps
'
The following plant conditions exist at 0409:
. Tavg 556'F
. PZR Press 2240 psig
. Source Range Channel 31 Indicates 39 cps
'
. Source Range Channel 32 indicates 46 cps
Which ONE of the following includes a plant response to the above conditions?
A. The "B" CCP suction valve from the RWST, BNLCV112E, opens.
B. ' The Containment Evacuation Alarm sounds.
C. The High Flux at Shutdown Alarm sounds -
D. "The reactor trip breakers open on high source range counts.
_ _ _ _ _ _ _ - .
;
QUESTION #8
Which ONE of the following describes the Flow Control Valves for the Motor Driven Auxiliary
Feedwater Pumps? :
A. The valves are motor operated and throttle close to limit runout flow under all secondary
side pressure conditions.
B. The valves are motor operated and throttle close automatically at high flow rates to limit
containment pressure increase caused by a steam line rupture in containment.
C. The valves are air operated and throttle close to limit runout flow under all secondary side
pressure conditions.
D. The valves are air operated and throttle close automatically at high flow rates to limit
containment pressure increase caused by a steam line rupture in containment.
I
.. . .. .. .
. .. .
.. ..
.
..
..
_ _ _ - _ ._ _--________ _ ___ _ _ _ _ - _ _ --
':-
--
,
t
- QUESTION #9 -
Fuel handling operations are in progress to support refueling. Both Fuel Building Radiation
- Monitors, GG-RE-27 and GG-RE-28 alarm, resulting in a Fuel Building Ventilation Isolation
Signal (FBVIS). Which of the following would be the correct immediate actions to be taken in-
l response to this event?
A. _ Store any fuel assembly in transfer h a safe location.
Ensure at least one personnel airlock door is closed.
Ensure the Fuel Building roll-up door is closed.
B. - Evaluate the need to evacuate the Fuel Building.
L Ensure at least one personnel airlock door is closed. l_ - Ensure the Fuel Building roll-up door is closed.
-C. - Evaluate the need to evacuate the Fuel Building.-
Store any fuel assembly in transfer in a safe location.
Ensure at least one personnel airlock door is cle.,ed.
D. Evaluate the need to evacuate the Fuel BtCding.
Store any fuel assembly in transfer in a safe location.
Ensure the Fuel Building roll-up door is closed.
-
M
,
.
QUESTION #10
The crew is responding to a plant transient and are currently in procedure ECA-1.2, "LOCA
Outside Containment"
i
Why should operators wait some amount of time during each valve repositioning per this procedure?
l A. Prevents overcurrent trips on valve motor breakers. l
B. Allows system pressure to respond to repositioning.
C. Prevent valve motor overheating due to excessive operation.
D. To allow check on indications of leak in auxiliary building.
.
_ _ - - _ - _ _ - _ - _ _ _ _ - _ - -
.
L- QOESTION #11 : -1
RCS activity is 50 microcuries per gram dose equivalent I-131.
l - Which ONE of the following is the Chemistry sampling requirements per OTO-BB-000057-
,
f A. Normal 3 day sample requirements are necessary.
'
B. - Once per day until activity decreases for 3 consecutive days.
C. Once per hour until activity decreases less than Tech Spec limit.
.D. Once per two hours until activity decreases on 3 consecutive samples.
'l
_ _- _
---_ L- ----
'
' - , - - + - , -
._ . - _
.
I QUESTION #12 i
Which one of the following instnictional communications between the Reactor Operator and the
!
. Primary Operator would be in accordance with the Callaway Plant Policy on verbal
l ,
communications?:
A. - Open the CCW heat exchanger A tube side drain, EGV0021.
B. Open the CCW heat exchanger alpha tube side drain, EGV0021.
C. Primary Operator, open the CCW heat exchanger A tube side drain, EGV0021.
D. Primary Operator, open the CCW heat exchanger alpha tube side drain, EGV0021.
- .
_
b
______ _ __ _ __ - __ _ ___ _ -
4
'
QUESTION #13 The plant is operating at 100% Power. An inadvertent Safety injection occurs when an l&C technician is performing a surveillance. WHICH ONE of the following will open and remain open until recovery from the Si is commenced? A. RCP DISCH PZR SPRY LINE ISO PCV, BBPCV04568 and BBPCV0455C. B. CVCS REGEN HX TO PZR AUX SPRAY ISO HV, BGHV8145. C. CVCS REGEN HX TO LOOP 4 OLD LEG ISO HV, BGHV8147. D. CVCS LTDN ORIFICE B OUT ISO HV, BGHV81498.
_____ _ _ _ - _ _ - _ _ - __ -
.-. . . . .
. .
.
QUESTION #14
,
Which ONE of the following describes the containment atmosphere radiation monitors
GT-RE-31 and GT-RE-327
A. They sample containment via the hydrogen control system and are isolated from
.
containment by a ClO A actuation.
l
B. They sample upstream of the containment isolation valves for the hydrogen control
system and are NOT isolated by a CIS A actuation.
C. They sample between the containment isolation valves on the mini purge exhaust line
and initiate a CPIS on high high activity.
- D. They sample from the containment purge exhaust line outside containment and initiate a
CPIS on high high activity.
.
-
- __ _ _
m
!
2
QUEST!ON #15
A loss of condenser vacuum is occurring due to unknown reasons, and power has been
reduced from 100% ta 75% over the last 5 minutes.
The following conditions exist:
. Auct High Tavg 593*F
. Reactor / Turbine Power 75% / 775 Mwe
. LP 'A' Condenser Pressure 5.8 Hga
. LP 'B' Condenser Pressure 6.2 Hga
. LP 'C' Coridenser Pressure 6.5 Hga
Which L E of the below describes the expected operation of the condenser steam dumps with
these conditions:
A. Less than 12 steam dumps are available and all available dumps are FULLY OPEN.
B. ALL 12 condenser steam dumps are available and all are FULLY OPEN.
C. Less than 12 steam dumps are available and all available dumps are PARTIALLY OPEN.
D. Less than 12 steam dumps are available and all are CLOSED.
_ _ _ .
-1
- QUESTION #16
-
-.
'
The plant is at 8% power preparing to synchronize the main generator to the grid when the
running main _ feed pump trips. As the Balance of Plant operator you observe the following
steam generator narrow range levels:
l -- A indicates 16%
B indicates 15%
C indicates 14%
D indicates 17%
--
All other plant parameters are normal.
Which one of the following correctly describes the status of the Auxiliary Feedwater (AFW)
System?
A. No AFW pumps are running
B. Only the turbine driven AFW pump is running
C. Only the motor driven AFW pumps are running
D. All the AFW pumps are running
--
- ;
-
.
- QUESTION #17 -
The following conditions exist:
l * PRZR Relief Tank Level Hi/Lo -- ALARMING on HIGH LEVEL '
* PRZR Relief Tank Pressure - ALARMING on HIGH PRESSURE
Which ONE of the below combinations contain sources, ALL of which should be monitored for
leakage into the PRT7 ;
I
A. RHR Pump Suction Reliefs (EJ8708NB), RCP Seal Leakoff Relief (BG8121), and CVCS
Letdown Relief (BG8117). 4 -
'
B. ECCS Accumulator Reliefs (8855A D), RHR Pump Suction Relief (EJ8708NB), and
CVCS Letdown Relief (BG8117). ,
~
C. RCP Seal Leakoff Relief (BGB121), CVCS Letdown Relief (BG8117) and
RHR Discharge Reliefs (EJ8856A/B).
D. Safety injection Pump Suction Reliefs (EM8858A), RHR Pump Suction Reliefs
_
(EJ8708A/B), and RCP Seal Leakoff Relief (BGB121).
. QUESTION #18
l l
Per ODP-ZZ-00310. WPA Tagging, which one of the following situations would require that a
- new tagout bo generated?
!
A. Tags need to be removed to perform rotation cher.ks following maintenanco.
B. Thare is a need for a sixth partial on an existing tagout.
C. Monthly audit identifies missing tags on an existing tagout.
D. Additional tags are needed after maintenance has been started on a component.
n -
~ X5b.4CLU/
y.a,j
. 4 b~.
QUESTION #19
The electric firo pump has started due to a rupture in the main fire header going into the
Radwasto Building. When can the pump be secured and returned to standby?
A. Any'imo from Panel KC008 in the main control room.
B. Anytime from the local control panel.
C. From Panel KC008 in the main control room after system pressure has boon restored.
D. From the local control panel after system pressure has been restorod.
.
..
-- ,
S': (
.
QUESTION #20
Callaway Plant is in Mode 4. "B" RHR is in service. A plant cooldown is in progress. The
Reactor Operator is directed to stop the cooldown. EGHV102, "B" CCW to *B" RHR heat
exchanger is CLOSED.
Which ONE of the following events occur?
'
A. "B" CCW flashes in the *B" RHR heat exchanger causing the "B" CCW surge tank lovel to
increase.
"
8. *B" ESW flashes in the "B" CCW heat exchanger causing water hammer in the "B" ESW.
C. "B" RHR flashes in the *B" RHR heat exchanger causing the "B" RHR suction rollef to lift.
i
D. "B" ESW flashes in tho *B' CCW heat exchanger causing the heat exchanger tube side
rollef valve to lift.
{
_ . . . s
-
.
. .
- . -
-
'
QUESTION #21
!
Plant conditions are as follows:
! e Mode 1
e 100% Reactor Power
l e All required Tech Spec and FSAR equipment is operable.
* An inadvertent CSAS occurs.
l-
-Which ONE of the following sets of valves will OPEN due to the CSAS?
A. RWST lsolation Valves, BNHV3 and BNHV4. I
B. Containment Sump Isolation Valves ENHV1 and ENHV7.
C. Containment Spray Pump Discharge Valves ENHV6 and ENHV12.
D. : Containment Spray Add Eductor Outlet Valves ENV5 and ENV11.
j
-_ _
. _ . . _ _ _ _ _ . _ _ _ _ . . _ _ . , _ _ . . . . _ _ _ . _ . _ . . _ _ _ _ . . _ . _ _ _ _ _ . _ . . - - _ _ _ _ . -
_
! I
l
i ;
> 4 . ) , .
,
J
!
i
-
QUESTION #22
The plant is operating at 100% power. The controlling PZR pressure transmitter, PT455, falls
j high. As a result of this failure, HOW will the following PZR components initially respond? j. (Select ONE of the following) !
PZR PORV's SPRAY VALVES . PZR 8/U HEATERS
j I A. Both will OPEN Will CLOSE Will Deenergize ! j B. One will OPEN Will OPEN Will Deenergize
I- C. One will OPEN Will CLOSE Will Energize l l D. Neither will OPEN Will OPEN Will Deenergize y
4 a i i
i 1 i
Y' l l 4
.J
. . . ..
. .
m ,
.
( QUESTION #23
FR H.1, Response to Loss of Secondary Heat Sink has just been entered. Plant conditions are
es follows:
I
e Total available AFW flow-200,000 lbm/hr
* A,B,D SIG levels 2% NR
* C S/G level 20% WR
* A,B,0 S/G pressures 950 psig
* C SIG pressure completely depressurized
e Containment temperature -190'F
e Conta!nment activity - 6E 2 microcuries per gram
o RCS pressure - 900 psig
* PZR level - off scale low -
'--
e RCP's - secured
Which ONE of the following actions should be taken in accordance with FR-H.1 ?
A.' Immediately initiate steps 10 through }6, RCS bleed and feed
B. Transition to E-1, Loss of Reactor or Secondary Coolant
C. Transition to E-2, Faulted Steam Generator Isolation
D. Return to procedure and step in effect when SIG level > 4%
.
4
_ . . _ - .- _ . . _ _ . _ - - _ .- . . . _ _ _ - - . _ - . _ . _ _ _ . -
,
.
l
l
QUESTION #24
Which ONE of the following electricallineups is a normallineup for the Switchyard?
A. ESF XFMR XNB01 energized by Safeguards XFMR 'B" via ring bus breaker 52-3.
B. MTGY-CAL 7 transmission line energized by the main step-up XFMR's via switchyard
breaker V53.
C. CAL BLAN-1 transmission line energized by 345 KV SWYD Gus "A" via switchyard
breaker V41.
D. 200 series site load XFMR's energized by Safeguards XFMR 'A' via ring bus breaker
52-4.
4
- - - - - - . . , ,
.
I
QUESTION #25
A reactor coolant system leak develops in the 'C' RCP thermal barrier. The CCW system is
designed for this failure by isalating the thermal barriors on HIGH CCW .
A. Flow
B. Radiation
! C. Pressure
D. Tank Level
.
d
i
i
*
l l
QUESTION #26
The plant has experienced a loss of offsite power. All equipment functioned as designed. Five
minutes later, N00111, *A" DIG output breaker, trips open. Which ONE of the following caused
NB0111 to open?
A. High lube oil temperature
B. Overcurrent
C. Low Jacket water pressure
D. Overspeed
i
)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
l l
.
,
- QUESTION #27
l e NCP is running,120 gpm letdown ! . BGFT121, CVCS CHG HDR TO REGEN HX FLOW XMTR, fails. '
. As a result, BGFCV124 closes.
'
. The NCP handswitch red light is lit
. BGHV8109, NCP Recirculation Valve, is open.
The following annunciators are received:
. CHARGING LINE FLOW LOW
e SEAL INJECTION TO RCP FLOW LOW
e NCP FLOW LOW .
1
Which ONE of the following actions should be taken immediately?
A. Take manual control of BGFCV124 and open it.
'
B. Start a CCP and secure the NCP.
-C. Open the sealinjection target rocks
D. Isolate allletdown
,
_______ - _-___ _ _ _ _ _ _
.__ .
.
. ..
?
t
QUESTION #28 l
Which ONE of the below NK01 bus electrical lineups meets the requirements for continuous
operation while in MODE 17
NORM CHARGER ALT CHARGER BATTERY
NK21 NK25 NK11
l
A. Connected Disconnected Disconnected
.
B. Disconnected Connected from NG bus Connected
C. Disconnected Connected from PG bus Connected
-
D. Disconnected Disconnected Connected
- -
-. -
U
.
QUESTlON #29
'
Compare the output of the reactor control unit, with rod control in auto, for the two conditions
listed below:
I
e A 2% step change in turbine load at 90%.
* A 2% step change in turbine load at 40%.
i'
Which ONE of the following describes the comparison of the signal output and the reason for
the difference?
A; Larger at 90% due to the response of the Variable gain unit.
B. Larger at 90% due to the response of the Non-Linear gain unit.
'
C. Smaller at 90% due to the response of the Non Linear gain unit.
D. Smaller at 90% due to the rosponse of the Variable gain unit.
I
h
-;
,
_
h
'
i.m .w.
'
--r--.s6._--- r . ..-,i ..,_.,.,,3-... - ..s .s . ,, , --.. J.--,- .-.r-.r. m m w .t- , - .. . ,_m ,-,m-_.m-.-----,em- , , .-
- - - - _ _ _ _ _ _ _ _ ___ __
.
QUESTION #30
l
The plant is operating at 100% power. l&C has determined the "A" train ESFAS has a bad
power supply ihat has to be replaced. The 'A' train ESFAS will be downpowered using
OTS SA-00001.
Which ONE of the following actions prevent an inadvertent actuation from the 'B" ESFAS train?
A. The cross trip block switch is placed in the BLOCK position.
D. The associated "B" bistables are placed in the BYPASS position.
l C. The dual voltage power supply,15 vde/ 48 vde, is placed in the OFF position.
D. The 48 vde power supply is placed in the OFF position.
;
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
QUESTION #31
i
l E-0," Reactor TriplSafety injection", defines RCP trip criteria. When stopping all RCP's in a
LOCA condition E4 directs that steam dumps be operated in the ' steam pressure" mode.
l
Which one of the following is also requ! red to be verified when stopping all RCP's por E-07
A. MSIV6 open.
B. Both CCP's in operation.
C. Either CCP or Si in operation.
D. AFW flow >300 Klbm/hi.
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ . ..
.
I i
'
!
QUESTION #32
,
Which one of the following posted areas must be deposted before plant personnel may be
i permitted to enter?
A. CHRA, Caution High Radiation Area D. DHRA, Dangor High Radiation Area C. DREA, Danger High Radiation Area Radiological Exclusion Area D. VHRA, Very High Radiation Area '
i
-
-
..
- _ _ _ - _ .
. .
..
.
.
QUESTION #33
Which ONE of the following statements correctly describes the purpore of the interlocks
associated with the RHR suction isolation valves (EJHV8701 A/B and BBPV8702A/0) while
l placing RHR in the shutdown cooling mode? l
A. Prevent draining the RWST to the containment sump.
l
l '
O. Prevent overpressurization of the RHR system.
C, Provents exceeding RHR system design temperature.
D. Provent contamination of the RWST.
. _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _
.
QUES flON #34
Plant conditions are as follows:
. At 0700, a loss of all offsite power occurred j
;
e At 0"10,6 01 occurred due to stuck open SIG Safety
e Ati MA:ip:< tent operated as designeci l
t
. flosit(ction of instrumeni air to Containmen' is in progress.
. EFHV43 and EFHV44, ESW to 'A' and 'B' as compressors are closed.
<
Which ONE of the following has caused EFHV43 and EFHV44 to close?
A. Blackout load shed
B. LOCA load shed
.
C. Loss of instrument air
D. High D/P
.
1
l
. QUESTION #35 A precaution and limitation in OTN-EG-00001, Component Cooling Water System, informs the
l operator that EGHV0069A/B (EG HS 69) and EGHV0070A/B (EG HS-70), CCW Supply / Return
to Radwaste, must be opened simultaneously. The reason for this requirement is to:
A. Satisfy the system high flow Interlock.
B. Satisfy the system low flow interlock.
C. Minimize potential of system water hammers.
D. Ensure proper flow is maintained to containment system loads.
<
)
.1
e
4
L~
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _
*
l
QUESTION #36
During a surveillance test with the plant at 90% power, an instrument technician removes the
instrument power fuses from N42 prior to bypassing channel N42 inputs. Assuming no operator
cetions the control rods will . (Select ONE of the following.)
A. drive IN at 72 spm then drive OUT as temperature DECREASES.
B. drive OUT at 72 spm then drive IN as temperature INCREASES. j
;
C. be blocked from moving OUT in AUTO and MANUAL. -l
D be blocked from moving OUT in AUTO only.
.
~ 4
, ! l
i
OUESTION #37
The following conditions eNst:
e "A" and *B" CCW Pumps are running,
. The Service Loop is being supplied by "B' CCW Train.
. 'A' Component Cooling Water Radiation Monitor EGRE0009 has exceeded the
Hi Hi ALARM setpoint.
!
Which ONE of the following automatic actions occur in addition to receiving an audible ALARM
:on the RM 117
A. EGRV0009, CCW SRG TK A VENT CTRL VLV remains OPEN, EGRV0010, CCW SRG l
'
TK B VENT CTRL VLV remains OPEN.
8. EGRV0009, CCW SRG TK A VENT CTRL VLV remains OPEN, EGRV0010, CCW SRG 4
TK B VF,NT CTRL VLV CLOSES.
C. EGRV0009 CCW SRG TK A VENT CTRL VLV CLOSES, EGRV0010, CCW SRG TK B
VENT CTRL VLV remains OPEN.
O. EGRV0009, CCW SRG TK A VENT CTRL VLV CLOSES, EGRV0010, CCW SRG TK B
VENT CTRL VLV CLOSES.
_ _ _ _
'
_ _ . _ . . _ _ _ . . _ - _ . _ . _ _ _ . _ _ _ . . _ _ _ _ _ _ . . _
1
:
i
QUESTION #38 ; Which ONE of the following will result in a shift of Auxiliary Feedwater (AF) System suction from the Condensate Storage Tank to the Essential Service Water System ? A. AFW pump suction pressure of 20 psia coincident with a loss of offsite power. B. AFW pump suction pressure of 22 psia coincident with Lo Lo levelin ALL steam
generators.
C. AFW pump suction pressure of 20 psia coincident with Pressurizer pressure of 1850 psig.
D. : AFW pump suction pressure of 22 psia coincident with a phase B isolation.
__
. . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . ._ .. .
.
QUESTION #39
Plant conditions are as follows:
.100% Rx Power
e 588.3*F Tavg Loop i
e 588.1*F Tavg Loop 2 ,
l e 588.4*F Tavg Loop 3 l L e 588.2'F Tavg Loop 4
e 585,4'F Tref ~ ;l
Which ONE of the following would occur if the Rod Control Selector Switch were placed in
AUTO? <
Rod speed Rod movement direction
A. 8 spm IN
- D. 48 spm IN <
C. 8spm OUT
D. 48 spm OUT
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _
.
t
QUESTION #40
, Plant conditions are as follows:
. A LOCA outside of containment has occurred.
l . No fluid is collecting in the containment recirc sump. '
. The RWST is empty.
. All ECCS pumps have been stopped.
Which ONE of the following can be used to provide water to tb ECCS pumps per ECA 1.1 ?
A. Condensate Storage Tank
.
B. Reactor Makeup Water Storage Tank
C. Spent Fuel Pool
D. Waste Collection Tank
m
_ _ _ - _ _ _ _ _ _ - _ _ _ _ - _ - _ _ _
t
l
QUESTION #41
. Given the following conditions:
. The plant was operating normally at 100% power
. - SIG A narrow range level rapidly decreases to 2%
e SIGs B, C, and D narrow range levels are at 50%
e The reactor and turbine do NOT trip
e Auxiliary Feedwater pumps do NOT start
. An Anticipated Transient Without Trip [ATWS) condition is announced
:
. Control rods are manually inserted
.
*- Power Range instrumentation is decreasing at 10% per minute due to rod insertion
Which ONE of the following is the_ expected response of the ATWS Mitigating System
(AMSAC)?
A. AMSAC will automatically trip the reactor which then causes a turbine trip.
,
8. AMSAC will trip the turbine and automatically start all AFW pumps.
C. AMSAC will not actuate since the required SIG low level logic has not been satisfied.
D. AMSAC is blocked from actuation since power level will be less than 30% power before
the AMSAC time delay expires.
9
;
,
'
l
l
QUESTION #42 Which ONE of the following describes the functional relationship between the Feed Hdi/ Steam Hdr AP, FW Reg Valve Position, and the FW Reg Bypass Valve Position, while increasing power from 10 - 20%?
FRV
BYPASS
Feed Hdr / Steam Hdr AP FW REG VALVE VALVE
A. Maintained constant at 150 psid Throttled OPEN Throttled OPEN B. Slowly lowered to 90 psid Throttled OPEN Throttled CLOSED C. Maintained constant at 150 psid Remain CLOSED Throttled OPEN D. Slowly lowered to 90 psid Throttled OPEN Throttled OPEN
,
4
QUESTlON.#43
'
The following conditions exist:
l e Reactor Power is'60%
. 'A' RCP #1 Seal AP is 170 psid and decreasing 1 psid per minute
. 'A' RCP #1 Seal Leak-off flow is 3 gpm
. 'A' RCP Frame Vibration is 3 mils and increasing 1 mil /hr
- - Which one of the following is the proper operator action per OTO-BB-00002, Reactor Coolant
-
Pump Off-Normal?
'
l
A. Reduce power to <48% and trip the affected RCP. +
B. Trip the reactor and turbine, then trip the affected RCP.
: C. Trip the affected RCP and be in Mode 3 wl thin the next 6 hours.
D. Continue to monitor vibration on 'A' RCP.
.
. . . . . . .. .. . . .
. _ .
. _j
-_- - ____ -
.
QUESTION #44 j
:The plant is responding to a safety injection and the crew is currently in E-1, Loss of Primary or
' Secondary Coolant, with the following plant conditions:
. RCS Pressure 1700 psig - Stable i
e Core Exit TC 560*F Stable i
. ECCS systems All Actuated as Required
. CTMT Pressure 10 psig Stable
!- . CTMT Temperature 195'F Slowly Decreasing
. - CTMT Radiation SE2 R/HR-
. S/G Aux Feedflow 100 Kibm/hr to each S/G
. S/G Pressures 1100 psig - Stable
. RCPs All off
With these conditions the core decay heat is being removed primarily by:
A. Heat transfer from the RCS to the S/G's due to natural circulation.
B. Heat transfer from the RCS to the S/G's due to reflux boiling.
C. Injection of water from the RWST and removal of steam / water out from the break.
D. Injection of water from the RWST and removal of steam / water out the pressurizer PORV,
,
-
. QUESTION #45 Which one of the following would violate the Technical Specification Safety Limit concerning Reactor Coolant System pressure? A. Mode 1 - 2550 psig B. Mode 2 - 2350 psig C. Mode 3 - 2750 psig D. Mode 4 - 2450 psig
l l
..
. . . . . .
.. . . . . . .
.
.
.
. . - .. .
.- - . . - - - . - - - - . - -
-
.
QUESTION #46
NE01 ('A' Emergency Diesel) Room Supply Fan is being placed in the Pull-to-Lock position.
Which ONE of the following is correct for the operability of NE01 while the Room Supply Fan is
under the control of the Reactor Operator?
- A. - Placing NE01 Room Supply Fan in Pull-to-Lock will have NO effect on the operability of.
NE01.
! B. NE01 should be declared inoperable when the Reactor Operator places it's supply fan in !- Pull-to-Lock.
i
l C. NE01 should be declare. . inoperable if outside air temperature exceeds 65'F.
D. NE01 should be declared inoperable if NE01 room temperature increases to 100 F.
__.
.
. .
.
i
.
QUESTION #47 -
- A truck in the switchyard backs into the "B" Safeguards transformer causir.g a loss of the entire
switchyard. ."A" and "B" D/G's fail to start.
Which ONE of the following power supplies would be unavailable?
A. "A" MFP emergency oil pump power
B. RLO1-RLO6 board power
C. PA01 breaker control power
D. Main Turbine turning gear oil pump
l\
;
<
\ -
- . . _ . - - . - . . - . . _ . _ . - . ._._._. -
_ . _ _ - . . _ _ . _ . _ _ _ . . _ _ _ _ . _ . . _ _ . . . _ . . _ _ _ _ . . .
1
'
p ->
i
p QUESTION #48 . "
The Containment Fan Coolers are running in fast speed when an SIS occurs. Which one of the-
following describes the expected response of the Fan Coolers? <
!. ! A. They continue to run unless containment spray is initiated. - 1 .
-- .
! B. .-They trip and are restarted in slow speed by the LOCA sequencer, ,
,
1
C. They shift to slow speed after a 60 sec, delay.
4
D. - They trip and are manually restarted in slow speed.
4- I j- l 2 . 3 + . <
'
s !
i 4 1 j '. 4
_
, d i
;
<
3
..
4
i
!.
_ . _ - - - . _ - - , _ . - - - _ . _ - - - - - . - _ , - ,_
. - - . .- - - ... .._ _ - . . . - - - - _ _ . . - . . . . - . . . .
i
1
!
*
.!
L QUESTION #49
The plant conditions are as follows:
. 'A' SIG Tube Rupture
. Manual Safety injection
. All equipment functioned as designed
. 'A' S/G atmospheric is OOS
. 'A' S/G pressure 1240 psig-
.
. :'A' S/G level > NR level indication
_
.
'
B', 'C', 'D' SIG levels < NR level indication
. RCS pressure 1240 psig
* PZR level 40%
.
Which ONE of the following should be implemented when the STA makes a pass through the
CSF's ?
. ' A. - FR-H.2 Response to Steam Generator Overpressure
B. FR-H.3 Response to Steam Generator High Level
C, FR-H.4 Response to Loss of Normal Steam Release Capabilities -
D. FR-H.S Response to Steam Generator Low Level
4
l
!
)
_____
.
_.
QUESTION #50 '
Assuming 100% power and 75 gpm letdown.- Which ONE of the following failures will result in
; a loss of makeup capability AND cause a reduction in Reactor Power if the Reactor Makeup
.. Control system is in AUTO and NO operator action is taken?
A. : Loss of instrument air to BGLCV112A
-. _
l B. BGLT0112 fails high
C, BGLT0149 fails high
L l
D. BGLT0185 fails high
,
_ _ - _ _ _ _ - - _ _ _ _ _ _ __-
.
-- QUESTION #51
Plant conditions are as follows:
. Mode 1 )
100% Reactor Power l
. Tavg 588.4*F
,
. NCP is running with BGFCV124 in Auto
.
l . Letdown flow is 125 gpm
. PZR level controller, BBLK459 is in Auto
.
. BBLT459 is the selected channel
l '
BBLT459 fails HIGH. NO operator action is taken.
Which ONE of the following occurs in the plant due to BBLT459 failing?
A. The Reactor will immediately trip on PZR high level.
B. The Reactor will, after a period of time, trip on high PZR level.
C.- - The Reactor will, after a period of time, trip on low PZR level.
D. The Reactor does not trip due to PZR level.
,
.
QUESTION #52
Which one of the following actions occur on a high' rad alarm (red) on the SG sample monitor,
SJ-RE-027 = j
- .
.
l
- A. BM-FV-54, SG Blowdown Surge Tank Outlet Valve closes
B. BM-HV-65 thru 68, SG Sample Isolation Valves close
L .C. BM-HV-1 thru 4 SG B/D Containment isolation Valves close
D. PBM01 A, SG Blowdown Discharge Pump trips
,
_ _ _ __ __ ______ ______ _ - -
*
,
QUESTION #53
E-3," Steam Generator Tube Rupture", performs RCS depressurization to refill the pressurizer.
Which ONE of the following shows the preferred order for depressurization.
A. Normal Pressurizer Spray, Auxiliary Spray, Pressurizer PORV
B. Normal Pressurizer Spray, Pressurizer PORV, Auxiliary Spray
C. Pressurizer PORV, Auxiliary Spray, Normal Pressurizer Spray
D. Pressurizer PORV, Normal Pressurizer Spray, Auxiliary Spray
l l
- - _ __
,
.
QUESTION #54
Using tt 3 attached graph, select the temperature combination at which the cooling tower
bypass > 'ves should be open.
Basin Temperature Ambient Dry Bulb Temperature
A. 40 F 25*F
4
B. 50 F 25*F C. 70*F 10*F D. 75*F 10 F
. - _ - _ _
.
_
"
,
>
'
- QUESTION #55 -
J
A high high shell level occurs in the 1 A heater Which ONE of the following is the response of
Main Feedwater due to the high high level?
A. Main Feedwater temperature goes up.
B. Main Feedwater temperature goes down. !
;
l C. Main Feedwater flow goes up._ !
. .
D.- Main Feedwater flow goes down.
l
6
# -
l'
.
. . , .
.
. . . . .
.
. __ ,
. _
.
. . . . .
_ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _
,
.
. QUESTION #56 4
, Callaway is in MODE 1. All systems are lined up in their normal configuration and operating
properly. A component cooling water system leak has occurred.
The following conditions are noted by the Reactor Operator:
l . The CCW surge tank level is 53% and DECREASING
. VCT levelis 65% and INCREASING
. :
Which ONE of the following leakage sources would result in these conditions?
A, CCW heat exchanger
l
. B. -Letdown heat exchanger
C. RHR heat exchanger
D. Seal water heat exchanger
.
__ . _ _ _ _ - _ _ _ . _ _ - _ .
:
-
'
'
- QUESTION #57
Main Control Board annunciator window 62C, AREA RAD MON FAIL, has alarmed. The BOP -
determines it was caused by SDRE0035, New Fuel Storage Area Rad monitor. The CRS
- directs you to source check the monitor for a response,__
_Which ONE of.the fo!!owing will you use to perform.a source check?
- A. - The green button
B.- The yellow button -
C,- -
The red button
,4
'
D. The white button
.
.
-)
iT
'.s j
i
._--__-__ - -_ _-___-_-_
.
QUESTION #58
The plant is being cooled down per EF s.2, Natural Circulation Cooldown, due to a sustained
loss of all offsite power following a tornado.
The cooldown rate will be limited to less than 'F/hr while the RCS subcooling will be
maintained greater than _ F more subcooled than instrument error.
A. 50,50
B. 100,100
C. 50,100
D. 100, 50
I
,, . . -
. - . .
. .J
!
i
l
l
t
-
-
QUESTION #59
The Control Room is being evacuated due to a fire in Panel KC008. You are the Reactor ,
Operator and have been directed by the Shift Supervisor to perform your immediate actions.
Which of the following locations _will you initially go to when you leave the Control Room?
'
A. Front standard on the main turbine.-
!
B. - South (Train B) ESF Switchgear Room (CB-2000).
- C. -North HVAC Room (AB 2047)
O. Auxiliary Shutdown' Panel-
.
.
.g'
fl
.. .,., .
- _ _ _ _ .____-__ _ _ - _ _ _ _ -
:
QUESTION #60 1
The following plant conditions exist:
.; Reactor power 23%
. Gen MW 208-
. CB D rods - 130 steps -
l . Rod Control Automatic
. MFP Speed Control- Automatic
. Main FRV Automatic
if turbine impulse pressure controlling channel, PT-505, falls HIGH, the rods in control bank D
' will . (Select ONE of the following.)
'
A. be inserted into the core (tripped) by a turbine trip signal
B. move in the outward direction
- C. move in the inward direction
D, not move
_. _
-,
.
. .
-. -
-
- ,- -... .-
___)
_ _ _ - _ _ _
i
\ OUESTION #61 Plant conditions are as follows:
l -. Mode 1
e 100% Reactor Power
. All Automatic controls in their normal condition
. BBTY411, Loop 1 Tavg, fails at 588.5'F
l
. A Reactor Trip occurs.
l~
NO Operator Actions are taken. Which ONE of the following occurs in the plant?
'
A. Steam dumps will be o, n. The RCS will cool down until main steam pressure reaches
l-
615 psig. Then the MSIVs will CLOSE and the RCS will heat up again.
l
B. Steam dumps will be open. The RCS will cool down until main steam pressure reaches
f- 1092 psig. Then the steam dumps will throttle to maintain this pressure.
C. Steam dumps will be open. The RCS will cool down until Tavg reaches 557'F. Then the
steam dumps will throttle to maintain this temperature.
D. Steam dumps will be open. The RCS will cool down until Tavg reaches 550*F. Then the
steam dumps will cycle closed and open to maintain this temperature.
,
I
_- ____ - __ _ _ __ _ ___ - __ - - _ - _ - . . _ _
*
.
QUESTION #62
A turbine runback can be caused by high stator cooling water temperature or low
stator cooling water flow.
A. inlet; inlet
B. inlet: outle!
C. outlet; outlet
D. outlet; inlet
.-
,
-:.) !
_ _
. QUESTION #63 ,
All reactor coolant pumps secured with the following conditions:
_
. RCS WR Pressure (BBPl405) 400- ,
e RCS NR Pressure (BBPl406) 350
.
* Charging Header Pressure (BGP1120) 550
l . _ VCT Pressure (BGP1115) 50 psig .
Using the attached graph,
1 i Which ONE of the below #1 seal leak-off flowrates is the MAXIMUM flow that would still allow .<. 1
starting reactor coolant pumps?
A. - l1.0 gpm
8, 1.5 gpm
i
C. 2.0 gpm
,
D. 2.5 gpm
.
-
-
. _ _ _ - _ _ - _ - _ _ - - _ _ - _ _ _ _ _ =?
l
.QUESTION #64
_
LThe following conditions exist:
'
"-
. - Safety injection - - Actuated
.: Procedure in Effect E-1 Loss of Reactor.or Secondary Coolant
'
'. RCS Core Exit Tc 580'F
, :. = RCS Cold Leg Temp 560*F l L . CTMT Pressure - 9 psig -
. CTMT Temperature . 190 F ,.
. CTMT Radiation- 1E3 R/HR
Using the provided attachment 2 from E-1, determine which ONE of the below combinations of -
RCS pressure and temperature would satisfy subcooling requirements.
RCS WR Pressure Core Exit TC
A. 1800 psig 590'F-
B. 1500 psig 570'F
C. 1200 psig 550'F
D. 1000 psig .500'F-
s
. -_ _ . _ . _ _ . _ _ _ _ _ . . . _ _ _ . . - . . . _ _ . - _ _
,
e '
._
3 - 4- , i? -
QUESTION #65 -
,m : Plant cor,ditions are.as follows:
i.
i t . 'A' Cire Pump lockouti
.
4-
- .- Setback in progress
"
. MCB annunciator 81D, Rod Bank Lo lit .
. - .;MCB annunciator 81C, Rod Bank Lolo lit
Which ONE of the following indications will meet the requirements for current plant conditions ? ,
<
- - .
.
- 1 A. 40 gpm flow indicated on BGi 1183A, EMERG BORATE TO CCP A & B HDR FLOW
~ n IND A.
-
B. 40 gpm flow indicated on BGFY1108, BA TO BA BLENDING TEE FLOW BATCH
, COUNTER. .
C. BGHISSA, A BORIC ACID XFER PMP PBG02A HAND IND SW, red light lit.
i D. . BGHV8104, EMERG BORATE TO CCP A & B HDR ISO HV, red light lit
- -.
I > ' .
*
, 7 , i < $ l
,
*
1,
,
d
'
_________._.______,___,o -
- .,, . , , . - , . . . . . --
, . , . _ . . , ,
. _ _ _ _ _ _ .. _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _
.
i
QUESTION #66-
Which one of the folic wing conditions would require action to be taken within 15 minutes to
: avoid violating the plant Technical Specifications?
A The plant is at 40% power with AFD outside its specified target band.
B. . The plarit is at 2% power with Tavg at 550 . ,
C. The plant is at 40% power when 120-volt AC bus NN01 loses power.
D. The plant is at 2% power when SR channel N31 fails.
-
'
_U
._ . _ . . . . _ _ _ . _ _ . ~ . _ _ . . - . _ . - _ _ _ . . _ . . _ . . _ _ . _ . . . . . _ > . . . _
-
. . _ . _ _.. _ _ ._..
.
! LQUESTION #67 . $ - A reactor startup is in progress with IR power at 3x10-11 amps. The source range High Flux
~
'
- Trip has NOT been blocked. Which ONE_of the following describes the Reactor Protection
3
- System response if a CONTROL POWER fuse blows on N-31 with the source range Level Trip
J- Bypass Switch in the positions indicated? I Level Trip Bypass: NORMAL Level Trip Bypass: BYPASS i - A. no trip no trip !
- B. reactor trip no trip
C. no trip reactor trip
D. reactor trip reactor trip
,
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ -
QUESTION #68
The plant is at-100% power with the following conditions:
1
"
- . - C" CCW pump OOS i
. "A" CCW Train in Service, "B" CCW Train in Standby
l . NCP in Service with 120 gpm Letdown Flow
The "A" CCW pump trips due to unknown reasons.
Which ONE of the below includes required immediate actions?
A. Restart the "A" CCW pump, if pump fails to restart, then stri either "B" or "D" CCW
- pump and transfer the service loop to the "B" CCW Train.
B. Start either "B" or "D" CCW pump then transfer the service loop to the "B" CCW Train.
C. Trip the Reactor Coolant Pumps and the Reactor, enter E-0, Reactor Trip / Safety
injection, then transfer the service loop to the "B" CCW Train,
- D. ~ Verify "B" CCW pump starts automatically then transfer the service loop to the "B" CCW
Train.-
,
s
_ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ ____ - _
.
QUESTION #69
A steam line has ruptured inside containment resulting in a reactor trip and safety injection.
E-0, Reactor Trip and Safety injection has been entered and the operating crew is in the
progress of transitioning to E-1, Loss of Reactor or Secondary Coolant. While monitoring the
CSF status trees, you deterrnine that an ORANGE path exists for SUBCRITICALITY.
Which one of the following actions should be performed by the crew:
A. Continue current pass through the status trees, if no RED path is encountered then
implement FR-S.1.
B. Complete the actions of E-1, then implement FR-S.1.
C. Immediately implement FR-S.1, then continue current pass through the status trees.
D. Implement FR-S.1 at the discretion of the Shift Supervisor.
,
_____ _ _ - . _-__-_- .
.
QUESTION #70-
l
The plant it, operating at full power when a Loop 1 Wide Range Tc RTD fails HIGH. This event
u
will have which one of the following effects on indicated subcooling on the 'B' Train Core
l Subcooling Monitor? - l- A. No effect since only core exit thermocouples provide input. ,
B. No effect since the Subcooling Monitor is bypaesed with the reactor trip breakers closed.
C. Small decrease since the Subcooling Monitor uses the average of the Wide Range RTDs
and the core exit thermocouples.
-
D. Large decrease since the Subcooling Monitor uses the highest reading Wide Range RTD
or core exit thermocouple.
,
i
N
4
.
2
OUESTlON #71 The plant is operating at 50% steady state power, with Tavg and Tref matched. Rods are withdrawn in manual continuously for 20 steps. Which ONE of the following combinations includes indications that would be received in the control room?
Tref /Tauct Rod Control Temp
Annunciator E:ror Indication Turbine Load
A. HI Positive Decreasing 8. LO Positivo increasing , C. HI Negative Increasing
D. LO Negative Decreasing
j
,
I
.
1
QUESTION #72
A LOCA has occurred. ES1.2, Post LOCA Cooldown and Depressurization is in progress. Just i
prior to initiating the RCS cooldown, the low steamline pressuro Sl is blocked.
Which ONE of the following is the reason for blocking the low stearnline SI ?
A. To provent the MSIVs from auto closure on low steamlino SI.
B. To unblock the steam line isolation from high rate signal.
C. To provent any Sl equipment from actuating.
D. To allow manual operation of SI equipment.
! r
i,w c y ,-,- - +,. p , -----e.
. - _ _ - _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ .
1
i
.
,
QUESTION #73
Which one of the following actions must be performed if the plant computer is down for
15 minutes?
;
I
l A. Perform a heat balanco.
D. Perform control room computer down logs.
C. Perform AFD monitor alarm inoperable surveillance.
D. Verify locally that area room temperatures are within specifications.
.
,
,
__ . _ -_ ._ _ _ - _ _ _ _ _ _ _ . _ _ _ . . _ . . - _ .
_ _. __
.
QUESTION #74
Callaway Plant is in Mode 3 cooling down for a Refueling outage. The Reactor Operator has
boon directed to decreaso RCS pressure to 1950 psig. Which ONE of the following would the
Reactor Operator have to set the Pressurizer Prossure Master Control, BBPK455A, to maintain
the RCS at 1950 psig in Auto? Narrow Rango PZR pressuro range is from 1700 to 2500 psig.
.
A. 1.77 turns
B. 2.55 turns
C. 3.13 turns
D. 4.41 turns
.
-
.
QUESTION #75 The plant is operating at 100% power. The instrument air lino to tho 'A' SIG FRV ruptures. The plant trips on S/G low level. Which ONE of the following causod both main food pumps to trip? A. MFP dischargo pressure high high 0. Trip of all condensato pumps C. MFP overspood D. FWIS
.
QUESTION #76
During post LOCA cooldown and depressurization CCP's and Si pumps are stopped on
' citernate ECCS trains when possible. t
Which one of the following describes the reason for alternating the ECCS trains?
f
A. Increase the probability of RCS injection flow if one ECCS train becomes inoperable.
B. Equalize flows on ECCS trains to maintain pump suction head.
C. ~ Minimize primary leakage while ensuring adequate subcooling.
D. Equalize loading on the NB busses, since it is assumed that the diesels are supplying !
power,-
,
.
_ . _ - _ - . _ . _ . . _ - - . ._ ___ ._ ___ _ . _ _ _ __ _ ___ _ _ _ . __ _ . _ _ _ _
l
.
QUESTION #77
The plant exporlonced a Si on low PZR pross. RCS pressure is 1750 psig and decreasing. E 0,
Reactor Trip or Safety injection, Step 21 is in progress. PZR spray valvo BBPCV455B is
partially open and will not closo in manual.
1 Which ONE of the following is the action to perform por E-07 f
A. Trip the B RCP
B. Trip the D RCP
C. Trip the A and D RCP's
D. Trip the B and D RCP's ,
4
*
l i l
QUESTION #78
The plant is in MODE 6 with core reload in progress.
Which ONE of the below sets of conditions will allow fuel movement to continue with both Boric
Acid Storage Tonks (BAT) drained?
RWST RWST RWST
Level Boron Temperature
A. 96,500 gal 2585 35'F -
B. 77,500 gal 2750 55'F
C. 59,350 gal 2320 75 'F
_ _ . _
D, 38,300 gal. 2100 95'F
1
QUESTION #79 Plant conditions are as follows:
e Rod H-8 in CB D was misaligned low. . Rod H 8 was withdrawn 15 steps to align it with the other rods in CB D. e The P/A converter AUTO / MAN switch is broke in the Auto position.
Which ONE of the following conditions occurs because of the P/A converter being in AUTO when rod H 8 was recovered?. A.- Rod Control Non Urgent Failure alarm when CB D rods initially moved in. B. Rod Control Urgent Failure alarm when CB D initially moved in. C. Rod Bank Lo alarm will be received with CB D actually above setpoint. D. Rod Bank Lo alarm will be received with CB D actually below setpoint.
1
.
-
. _ _ - _ _ _ _ - - _ _ _ . - . . . _ _ _ - _ __. ___ _ . _ _ _ _ _ . _ _ _ _ . . _
.
l
QUESTION #80 During the performance of ECA-3.2, SGTR with Loss of Reactor Coolant Saturated Recovery Desired, the current pass through the CSF's indicate a yellow path on Core Cooling requiring consideration of performing FR C.3, Response to Saturated Core Cooling. 1
i
Which ONE of the following actions should be performed 7 A. Proceed immediately to FR C.3. B. Perform FR C.3 in parallel with ECA-3.2. C. Finish performing ECA-3.2. D. Proceed immediately to ES-0.0, Rediagnosis.
- - _ . . ._.
:
QUESTION #81 The following conditions exist:
1
. SPENT FUEL POOL HilLO Level Annunciator is received.
. The plant is at 100% power. l
'
. Makeup to the SFP is required due to ovaporation.
. SFP boron concentration is 2450 ppm.
Which ONE of the below sourcos would be used for makeup? A. Blonded Flow via CVCS B. Refueling Water Storago Tank C. Recycle Holdup Tanks D. Reactor Makeup Water
.
. - _ . . . _
__ - _ .. _. .
I
OUESTION #82
Radwaste is discharging DMT 'A' HBFV866, LRW DISCH FCV, automatically CLOSED.
Which ONE of the following could have caused HBFV866 to CLOSE automatically.
A. Servico Water Radiation Monitor Hi Hi
B. Liquid Radwasto Discharge Flow High
C. Liquid Radwaste Discharge Flow Low
D. Dilution Water Flow Low
i ,
4
-w -. -.. -- , -.. -- .- , .,
. ._. - -. _ _ _ . _ . _ - _ _ _ ._. __ -
_ _ _ _ __.__ _ _ . __ _ .
l !
,
!
!
*
l -l ! ! t i ! - QUESTION #83 l
> t
l '
!
Plant conditions are as follows: l
l ! e RCS large break LOCA occurred j l e Safety injection on low pressurizer pressure ! l
* All equipment function as designed
l - e Cold Leg Recirculation in Progress ;
e RCS Temperature is 325'F !
*
l e RCS Pressure is 35 psig l
e. E 1 Step 15 isolation of accumulators is in progress ;
'
-1
~Which ONE of the following actions is the preferred order of isolating the 'B'secumulator?
l
I
A. Close the isolation vslve, open one of the vent valves, open the other vent valve
B. Open one of the vent valves, open the other vent valve, close the isolation valv9 !
!
C. Close the isoletion valve, open the vent valve l
I
.
-- }
L !
D. . Open the vent valve, close the isolation valve
.
i.
'
I
t
i
.
.
=
f
,
s
t
'emg n m w.--o.-,.vm-v'. -- g ,vo +e ,+m + o-.-o- m e we, r sv - -v,-,ve--><.<wr--sw.,e ww---e-~-w~r--ww-r~-we-,.~.se-o,noeray-,ww w -wasem-:-en,, ,u,aw,, e-mm,s-w->g4,- + m > wese , vns'
I
1
,
i
!
'
! '
f
!
>
!
f
- QUESTION #84
!
!
! The following plant conditions exist; . (- 1 ' . ANNUN 30A,- NF039A LOCA Seq Actuated, LIT :
e ANNUN 31 A, NF0398 LOCA Seq Actuated, LIT !
- e ANNUN 880, Hi Ctml Press Si Rx Trip, LIT
e Reactor Power
_
97 % l
e Gen MW 1200
* LCPGi9 Open i
e LCPG20 Open ,
e Control Rods Being manually bserted by the RO ;
* Turbine Stop Valves Open j
!
As the Balance of Plant operator, which one of the following would be the first action you would ;
'
take?
r
A. Manually runback the main turbine. ;
-8. Manually trip the main turbine.
C. Manually open switchyard breakers V53 and V55.
'
D. Fast close the MSIVs.
!
t
:
!
.
>
._.
_-
.
QUESTION #85
A largo steam lino break occurs insido containtnent. A Safety injection occurs on Containment
Pressuro. Containment pressure is 30 psig when step 14 of E-0, ' Chock if CTMT Spray is
Required', is performed.
Which ONE of the following is the reason for stopping all four RCP's ?
A. They are an unnecessary addition of heat to Containment.
B. All RCP cooling water flow is automatically isolated.
C. Air is too dense for the motor cooler fans to koop the motor cool.
D. Containment structural failure is imminent.
. . .
. . . _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _
-
,
QUESTION #8G
Which ONE of the following willinitiato a Blowdown and Sample Process isolation Signal
(BSPIS)?
A. Blowdown surge tank level high.
B. Undervullago on olther NB bus.
C. High temperature at non regon heat exchanger outlet.
D. Blowdown derninoralizer high differential pressure.
_ _ _ _ ._. _ .
. ..
.
. .. .
*
I
QUESTION #87
An inadvertent SIS accurs. All cystems actuato as designed.
Which ONE of the following can be roset by itself with no other signals being resot?
l
A. CPIS
B. CRVIS
C. SGBSIS
D. CISA
. _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ __
l l
.
QUESTION #88
A slowly increasing RCS lovel during mid loop operations could be a symptom of .
A. air entrainment into the RHR system.
B. nozzlo dam leakby into the RCS system.
C. high differential pressuro between the Containment and Fuel Building.
i
D. pressurizer nitrogon overpressure too high.
.
A
_ _ _ _ - _ _ _ _ _ _ - - - - - - -
l . !
QUESTION #89
The plant is in Modo 1 at 25% reactor power. Which one of the following would be cause to
ontor E-0, Roactor Trip or Safety injecticn?
A. 'A' Steam Generator level is at 10% on all channels and the reactor has not tripped. I
l
B. The main turbino stop valvos have closed and the reactor has not tripped.
C. Pressurizer level channel 459 is at 98% and the reactor has not trippod.
D. 'C' RCP breaker has just tripped open and the reactor has not tripped.
_
1 l
OUESTION #90
The plant is in Mode 6 with refueling in progress.-
Which ONE of the following is tho ventilatior. lineup for Containment?
A. Mini purge supply and exheust in service.
B. Shutdown purge supply and exhaust in service.
C. Mini purge exhaust in servlee with supply through the equipment hatch.
D. - Shutdown purge exhaust in service with supply through the equipment hatch.
1
h
- _ _ _ _ _ _
- __ _ _ _..-_._. .. _ . _ . _ - . _ _ _ _ _ -
.
.
.-
.
d Yt i !
-
1
1
QUESTION #91' :
i
'
j. Which ONE of the below sets of valve positions would maintain their associated systems
OPERABLE to perform their intended function for MODE 1 operation? -
I
.
:
'
EMHV8814A BNV8717 . EJHV8840
S1 Pump A RHR to RHR Train A/B
_Recirc Iso . RWST Hot Leg Recirc
j.
-
A. CLOSED CLOSED CLOSED- *
4
B. CLOSED OPEN OPEN !
,
C. OPEN OPEN OPEN -
'
i- D. OPEN CLOSED CLOSED
4 i 5- r y
' i
i .k
+
0
' 1
I J
- ! -
i
f
f
a
i
i
i : , a
) }- 4
+aram +++ g w ge- ww - v me ,s - - d-m,9.g,y 1+ me-,-yew-..--.,wtr , we ,.,r- 7a v r w n-m yr - n y = p- <-+ w m ,-+ w e ww-s e r ---*-- w H v tt -wwer eweg ew' e ss w ++ m-* ev> w vsw w- e y- T - er = T'
_ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ - _ _ -
.
QUESTION #92
The plant is responding to a loss of offsite and onsite power.
During implementation of ECA-0.0, Loss of All A.C., the AC supply breakers to the ESW pumps
Cre:
A. Placed in Pull to-Lock on the MCB so they are under positive operator control.
B. Manually closed locally since there is no closing power to the MCB handswitch.
C. Placed in Normal-After-Stop on the MCB for start when the DG is started locally.
D. Verified closed locally prior to starting DG or reenergizing the NB bus.
i
N
._ ._. _ . _ _ _ _ _ _ _ _ _ _ _
-_ _ _ _ _
l
.
'
QUESTION #93
A plant startup is in progress. Power level is 1E-7 amps. The Reactor is tripped wh n PA02 is
doenergized by Relay Test.
Which ONE of the following is the approximate length of time before the Source Range NI's
automatically energize ?
A. 2 minutes
B. 5 minutes
C. 10 minutes
D, 15 minutes
.
1
.
QUESTION #94
With the plant in MODE 3 the MCB handswitch for the Reactor Trip Breakers is rotated to the
CLOSE position.
Which ONE of the below conditions would prevent the reactor trip breakers from closing?
A. Pressurizer Level at 95%
-B. RCS Pressure at 1800 psig
C. Pressurizer Level at 17%
D. -RCS Pressure at 2400 psig
4
i
4
as
- .- .--
4
1
QUESTION #95 I
i
l
The reactor is exactly critical at 10E-8 amps when the 'A' SIG PORV fails open. Assuming NO l
operator action and NO renctor trip, which ONE of the following best describes the values of ;
Tavg and nuclear power for the resulting new steady. state conditions? l
A; Final Tavg is greater than initial Tavg. Final reactor power is above the POAH.
B. Final Tavg is greater than initial Tavg. Final reactor power is at the POAH.
C. Final Tavg is less than initial Tavg. Final reactor power is above the POAH.
D. Final Tavg is less than initial Tavg. Final reactor power is at the POAH.
9
. _ _ _ _ _ _ _ . _ _ _ - _ -
9 i
i
QUESTION #96 The plant is in MODE 2 commencing warmup of the main turbine. Which ONE of the following could be a direct result of a loss of Vital AC Instrument Bus NN02. A. Charging Pump Suction Swaps to the RWST.
! B. Source Range Hi Flux Reactor Trip.
! C. Intermediate Range High Flux Reactor Trip.
I ,
D. Idle Component Cooling Water Pump Start.
.
_a
. _ _. . _ . _ _ _ _ . _ _ _ - . - _ _ . - . _ . . .__ .__ ___ _ ___.__ _ .
_
'
.
!
QUESTION #97
I
Which ONE of the following parameters can be used to distinguish between a primary and
secondary leak?
A. RCS Tavg l
l
l
B. Pressurizer Level
C. Containment Pressure
D. Pressurizer Pressure
. 4
i
_ . . . _ - - . .
-.m - . - , - . _.- . , _ , .
_ _ . . _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _
t l
QUESTION #98
l . FR-C.1 is in progress. ,
. S/G's have boon depressurized to 120 psig. j
e All RCP's are stoppod.
Which ONE of the below is the reason for stopping the RCP's?
A. Roduce the heat input to the RCS. l
l
B. Normal PZR spray flow is unnecessary.
C. Prevent cavitation from N2 from the occumulators.
D. Prevent damage to Number 1 seal.
.
n
. _ . _ . - _ - . . _ . _ . . _ _ . _ ._ . _ _ _ _.. _ . _ . _ .. .. _ _ _ _ _ ._ ._ ___ _ _ _ _m . . . . . ,
1
!
l . . !-
QUESTib. #99-
f
[ FR P.1, Resp se to Imm:nent Pressurized Thermal Shoc ondition, is in progress due to a
steam leak whi has been isolated.
Which ONE of the llowing conditions is accept e using Attachment 7 for RCS Post-Soak
Cooldown Limitation during recovery from th TS condition ?
[ ,
A. RCS cold legs = 2 F. RCS wid ange pressure = 0 psig,
4 '
B. RCS cold legs _= 250' RC ide range pressure = 300 psig
i Ci RCS cold legs = 300 F. S wide range pressure = 400 psig,
D. RCS cold legs = 0 F. RCS ide range pressure _= 300 psig.
f i
A
s.
! 4
&
i . b
:-
-. - _ - -. -. -
i
l
*
l
,
'
QUESTION #100
A fire is reported in PG24, Pressurizer Variable Heater, Load Center.
This is an example of a fire and would be extinguished
A. Class B, by pre-action sprinklers.
B. Class C, by halon.
C. Class B, by halon.
D. Class C, by pre-action sprinklers.
, t
4
}}