ML20249C225
| ML20249C225 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/22/1998 |
| From: | Curley V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9806260227 | |
| Download: ML20249C225 (1) | |
Text
._
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NOTE TO:
NRC DOCUMENT CONTROL DESK MAIL STOP 0-5-D-24 FROM:
1 e'e,*, f bog /
LICENSING ASSISTANT OPERgING LICENb BRANCH
~ REGION I Pets 9 kb W A # Yn/
SUBJECT:
OPERATOR LiCENS!NGdEXAMINATION ADMINISTERED ON honI I 199 f
__, AT Onlvut OliecA D0dKET Nd5. So-Jfr go,/ so.s/7 II Rd W
ON pnrff e 49 R' OPERATOR LICENSING %XAMINATION/ HElit ADMINISTERED ATEkREFEl(ENCEDFACILITY. ATTACHED YOU WILL FIND THE FOLLOWING INFORf1ATION FOR PROCESSING THROUGH NUDOCS AND DISTRIBUTION TO THE NRC STAFF, INCLUDING THE NRC PDR.
Item #1 a)
FACILITY SUBMITTED OUTLINE AND IHITIAL EXAM SUBMITTAL DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE A070.
I b)
AS G!7EN OPERATING EXAMINATION, DESIGNATED FOR DISTRIBUTION 44, pqw QNDERRIDSCODEA070.
I4 Item #2 EXAMINATIONREPORTWITHTHEASGIVENWRITTENEXAMINATIONI
' ATTACHED.-DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE IE42.
. w.y e
i NO 17 PDR I
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UNITED STATES y
g NUCLEAR CE2ULATORY COMMISSION 5
8 REGloN I 3
3 C.
475 ALLENDALE HoAD KING oF PRUSSIA. PENNSYLVANIA 19406 1415 May 7, 1998 Mr. Charles H. Cruse Vice President - Nuclear Energy Baltimore Gas and Electric Company (BG&E)
Calvert Clif t; Nuclear Power Plant 1650 Calvert Clifis Parkway Lusby, MD 20657-4702
SUBJECT:
CALVERT CLIFFS UNIT 1 AND UNIT 2 REACTOR AND SENIOR REACTOR OPERATOR RETAKE EXAMINATION REPORT NOs. 50-317/98-301 (OL)
AND 50-318/98-301(OL)
Dear Mr. Cruse:
This report transmits the findings of the senior reactor operator (SRO) written retake examination administered by your training department on April 1,1998.
This examination was administered to one Senior Reactor Operator (SRO) candidate who had failed the original written examination administered in October 1997. This individual passed the retake examination and was issued a license.
This examination addressed areas important to public health and safety and was developed and administered under Interim Revision 8 to the Examiner Standards (NUREG-1021). This examination was developed by the Calvert Cliffs training department, while the NRC provided oversight and final approval prior to the administration of the examination.
Calvert Cliffs training personnel subsequently administered the NRC approved written
- examination.
The quality of the exam submittal was an improvement over the previous examination, with relatively few changes required to adddress NRC comments.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosures will be placed iq the NRC Public Document Room.
' \\
l
/
l*
_ _ _ ~ -m
Mr. Charles H. Cruse 2
No reply to this letter is required, but should you have any' questions regarding this examination, please contact me at (610) 337-5183.
Sincerely, L
Richard J. Conte, Chief Operator Licensing and Human Performance Branch Division of Reactor Safety Docket Nos. 50-317;50-318 m
Enclosure:
Initial Examination Report No. 50-317/97-301(OL) and 50-318/97-301(OL)w/ Attachment 1 cc w/ encl: w/ Attachment 1:
C. Zapp, initial & Requalification Supervisor cc w/ encl: w/o Attachment 11 T. Pritchett, Director, Nuclear Regulatory Matters (CCNPP)
R. McLean, Administrator, Nuclear Evaluations J. Walter, Engineering Division, Public Service Commission of Maryland K. Burger, Esquire, Maryland People's Counsel R. Ochs, Maryland Safe Energy Coalition State of Maryland (2)
_______-m_______m
i
~
1 Mr. Charles H. Cruse 3
Distribution w/ encl: w/ Attachment 1:
DRS Master Exam File (V. Curley)
Nuclear Safety Information Center (NSIC)
PUBLIC
' Distribution w/ encl: w/o Attachment 1:
D. Screnci, PAO (2)
NRC Resident inspector Region 1 Docket Room (with concurrences)
J. Wiggins, DRS L. Nicholson, DRS R. Conte, DRS J. D' Antonio, DRS L. Doerflein, DRP R. Junod, DRP
. %fyESEli??
RS File Distribution w/ encl: w/o Attachment 1: (VIA E-MAIL)
B, McCabe, RI EDO Coordinator S. Stewart - Calvert Cliffs S. Bajwa, NRR
' A. Dromerick, NRR M. Campion, RI Inspection Program Branch, NRR (IPAS)
DOCDESK I
5
l U. S. NUCLEAR REGULATORY COMMISSION REGION 1 Docket Nos.:
50 317 and 50-318 Report Nos.:
98 301 (OL)
License No.:
Baltimore Gas and Electric Facility:
Calvert Cliffs Units 1 and 2 Location:
Lusby, Maryland Dates:
April 1,1998 Chief Examiner:
J. D' Antonio, Operations Engineer / Examiner Approved By:
Richard J. Conte, Chief Operator Licensing and Human Performance Branch Division of Reactor Safety i
TscGwuiW)
EXECUTIVE
SUMMARY
Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection Report Nos. 50-317/98 301(OL) and 50-318/98-301(OL)
Ooerations A retake written examination was administered to one Senior Reactor Operator (SRO) candidate who had f ailed the original examination administered in October,1997. This individual passed the retake examination and was issued a license.
ii i
1 l
Report Details
- 1. Ooerations 05 Operator Training and Qualifications l
l 05.1 Senior Reactor Operator Written Examination l
l a.
SCODO A written retake examination was administered to one SRO instant applicant.
b.
Observations and Findinas The applicant passed the examination and was issued a license.
The facility examination submittal was an improvement over the prior examination submittalin that far less revision was necessary for NRC approval. NRC comments resulted in changes to approximately 10% of the examination. The most common comment concerned one or more implausible distractors. No post exam comments were provided by the facility, c.
Conclusions
(
The facility had successfully remediated the applicant for the prior exam failure.
The examination submittal was an improvement over the October 1997 examination submittal.
V. Manaaement Meetina X1 Exit Meeting Summary An exit meeting was held by telephone on April 29,1998. The NRC summarized the exam review comments. Participants were the NRC Chief Examiner and the facility Supervisor of Initial License Training, John Hornick.
I Attachments: Calvert Cliffs SRO Written Exam w/ Answer Key l
l
r f r am - p s o, t e el 6
ES-401 Site-Specific Written Examination Form ES-401-7 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific Written Examination Applicant Information Name:
Rogion:
b/II/III/IV Date:
Iacility/ Unit: CLeJFP /$Z License level:
R0 / [Sh Reactor Type:
Finish Time:
Instructions Use the answer sheets provided to document your answers.
Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collect 3d four hours after the examination starts.
Applicant Certification All work done on this examination is my own.
I have neither given nor received aid.
Applicant's Signature Results Examination Value
/86 Points Applicant's Score Points Applicant's Grade Percent NUREG-1021 39 of 39 Interim Rev. 8, January 1997
= _ _ _ _ _
L Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK rese:1
- 1. AREA RAD Al. ARMS 002 Given the following:
. Unit.1 is at 50% power
- Maintenance is in progress on 11 Charging pump
- alarm at 1C17 " RAD MON PANEL 1C22" annunciated
- CRO reports that " UNIT 1.WP VENT" alarmed with 1-Rl-5410 reading 1000 cpm
- ABO reports that 11 Charging pump was inadvertently vented As CRS, select the proper response to these conditions:
A. Direct CRO to acknowledge the alarm and remove the monitor from service until completion of maintenance on 11 Charging pump.
l ~
B. Declare the 1-RI-5410 OOS due to alarm setpoint is set too low, have CRO refer to 1
Alarm Manual for compensatory actions.
C. Direct CRO to acknowlege the alarm and bypass 1-RI-5410 for duration of I
maintenance on 11 Charging pump.
- 4. Direct CRO to monitor for trends on 1-RI-5410 and notify Rad Safety and Shift Supervisor.
Correct answer is based on actions in Alarm Manual, distractors are inappropriate actions for an unplanned RMS alarm. The " unplanned RMS alarm" condition is inferred.
author:REN Modified question by complete change of stem and distractors KEY WORDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outline h00061K302 b.6 lAPPLIC-SRO EB-MODIFY NO 1-200 lCRO 122-1 l2.17.2 k1G2 l
DATES: Modified: Monday, March 16,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
Asa %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Time l 1l p(diff)l 0l rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l4l 0l 1
4 I
I I
l I
EXAM BANK DATA SHEET l
Question #: CRO-122-i-3-15 Task #:
020150301 NRC Category (s) :
B,B CRIEF: General Response to an Unplanned RMS Alarm l'KEYNORDS: 122 - 1/2C22 RADIATION MONTIORING QUESTION Which statement _ describes the general response to an unplanned RMS alarm?
A.
Declare the alarm OOS immediately and refer to appropriate plant procedures for followup action.
B..
Acknowledge the alarm and monitor RMS for trends once per shift.
C.
Declare the alarm OOS, monitor for trends, contact the appropriate group, and Shift Supervisor declares a radio-logical event if warranted.
D.
Acknowledge alarm, monitor for trends, contact the appropriate group, and Shift Supervisor declares a radiological event if warranted.
ANSWER D.
1 REFERENCE DATA Point Values 1.00
'Madia #: CRO-122-1-3 Enabling Obj #: 2.1.B
)
R: quired Ref: 01-35 Time: 2 min Question Type: MC l
K/A Catalog: 015A7.01.07,073000 GEN 8,3.3/3.3 Raf.: 55.41:10,12 55.43:5
/
OI-35
' 3GNIEW l
Author:
Date:
i Approved:
Date:
R; viewed by Program Development: No Rsv.
1, 12/03/96 Page 1 of 1
)
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page:2
- 2. KC Di5TR150 TION 002
~ ~
Given the following:
- Unit 1 and Unit 2 are at 100% power
- ESO requires P-13000-1 OOS for maintenance
- RO has been directed to shift Unit 1 RCP power supply to P-13000-2 Describe the proper method to shift an RCP power source to the opposite Unit:
A. RO starts oil lift pump, insert synch stick, observes no rotation of synchroscope at 1C01, close the breaker at 1C06.
B. RO starts oil lift pump, insert synch stick, observes no rotation of synchroscope at 1C19, close the breaker at 1C19.
C. RO inserts synch stick, observes no rotation of synchroscope at 1C01, close the breaker at 1C19
- 4. RO inserts synch stick, observes no rotation of the sychroscope at 1C19, close the breaker at 1C06.
Correct answer is based on Ol-1 A steps, distractors are permutations of incorrect synscope location, breaker location and use of oil lift pump, author:REN Modified question to change stem and distractors.
KEY WoRDs:
NRC KIA NRCImp Cog level Source Reference Less Plan Obj #
Outline b00062K503 b.6 l COMP kB-MODIFY lOI-1A lCRO 118-1 l4.7 k2G2 l
DATES: Modifed: Monday, March 16,1996 Used:
cTATisTICs:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o_
o As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Timel 1l p(diff)l ol rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol l
~
l l'
1 p
EEAM BANK DATA SHEET Question #: CRO-118-1-1-09 Task #:
?
NRC Category (s):
None CRIE!F: Transfer of Power to an RCP to the Opposite Unit KEYWORDS: 118 - 13'KV AND 4 KV ESSENTIAL FEEDER CONTROL QUESTION How is power to an RCP transferred to the opposite unit?
A.
Via an ABT if voltage degrades to less than setpoint, lift oil and CCW alarms are clear, and power from opposite unit is available.
B.
Opposite breaker is closed after starting the oil lift pump I
and inserting the sync stick.
C.
Opposite breaker is closed after taking RCP power supply j
selector switch to opposite bus.
D.
Opposite breaker is closed after inserting sync stick and ensuring CC low flow alarm is clear.
ANSWER D.
REFERENCE DATA Point Value:
1.00 M:dia #: CRO-118-1-1 Enabling Obj #: 4.7 Rcquired Reft None Time: 2 min Question Type: MC
-K/A Cataloa; ?
Ref;r
?-
REVIEW.
Author:
Date:
Approved:
Date:
Rcviewed by Program Development: No R;v.
2,'06/28/96 Page 1 of 1 r
L.
I I
l Tuesday, March !7,1998 @ 08:47 AM FINAL.BNK Page: 3
~ Th~CCID Gi S RECEX6E 001 3
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The Chemistry Tech has reported to the CRS that the weekly sample of #13 WGDT (onservice) has been completed. The analysis results are 9 curies of noble gas and 2
5% O by volume.
What are the required actions for the sample results per Tech Specs?
A. Isolate #13 WGDT, sample WG surge tank.
B. Maintain #13 WGDT in service, have RCS sampled for activity.
2 vC. Isolate #13 WGDT, reduce O concentration.
D. Maintain #13 WGDT in service, monitor letdown process rad monitor.
2 Tech Spec requires action for O reduction only, distractors have action for activity 2
results (none required by Tech Spec) or subsequent identification of O source.
author:REN KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l
lD00060G133 l4.0 hPPLIC NEW l TECH SPEC NRO-1341 l8.0 IT1G2 l
DATES: Modified: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o e
o o
o 3
Asa %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100 0 TimeI il p(diff)l 1l rpbl ol Values:1 l ol 2l ol 3 l ol4l ol l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 4
~d.XCCIDiiQhEEE4SE 001
~
A discharge of the Miscellaneous Waste Monitor Tank is in progress.
Which one of the following conditions would require entry into AOP-68, " Accidental Liquid Waste Release"?
A. Trip of a Circ Water Pump on the unit receiving the discharge with no corresponding reduction in discharge flow rate.
vB. LQD WASTE DISCH valves (2201 and 2202 CVs) OPEN with discharge RMS alarm.
C. Discharge activity exceeds the computer alarm high setpoint specified in the release permit.
D. Discharge activity decreases to less than the Discharge Permit background activity value.
correct answer is specified entry condition for AOP 68, distractors plausible occurences during a discharge that are not entry conditions for AOP 6B.
author:REN The question was modified to even out the length of the distractors (JB comment)
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00059A101 h.5 NEMORY l4!93 NRC h0P-6B hRO-134-1 l10.0 k1G1 l
DATES: Modified: Tuesday. March 17.1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o e
o o
o o
o o
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time]
p(difr)l 1l rpbl cl Values:1 l ol2l ol 3 l ol4l ol l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: S 5.AFVf001
~
During troubleshooting efforts on the Unit 2 Auxiliary Feedwater Actuation System, an inadvertent "AFAS A"is actuated. The "AFAS A ACTUATED" alarm is received in the Control Room. Which of the tielow listed combinations of component actuations should be expected to occur?
A. CV 4070s and 4071a OPEN to supply steam to the aligned steam driven pump.
B. CV 4070s and 4070 OPEi! to supply steam to the aligned steam driven pump and 23 AFW rump STARTS.
- 4. CV 40718 dnd 4071 OPEN to supply steam to the aligned steam driven pump.
D. CV 4070 and 4071 OPEN to supply steam to the aligned steam driven pump.
Correct answer is based on logic design, distractors are components from B logic.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b00061K302 l4.4 DOMP kB-MODIFY ESAR-7 DRO 34-1 l3.1 k2G1 l
DATES: Modified: Friday, March 13.1996 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
0 2
1 0
0 0
0 0
0 0
0 3
Asa %:
0.0 66.7 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 0.33333l rpbl
-0.381l Values:1 l 0l2l 0l 3 l 0l 4 l 0l L
i l
i 4
I L
l.
O l
EEAM BANK DATA SHEET Question #: CRO-34-1-3-t6 Task #:
020340445 NRC Category (s) :
None CRIEF: AFAS Channel A KEYWORDS: AFAS QUESTION During troubleshooting efforts on the Unit 1 Auxiliary Feedwater Actuation System,- an inadvertent "AFAS A" is actuated.
The "AFAS A ACTUATED" alarm is received in the Control Room.
Which of the below listed combinations of component operation should be expected to occur?
L A.
CV 4071a and 4070a open to supply steam to 11 AFW pump.
B.
CV 4070a and 4070 open to supply steam to aligned steam driven pump and 13 AFW pump starts.
C.
CV 4071a and 4071 open to supply steam to aligned steam driven pump and 13 AFW pump starts.
D.
CV 4070a and 4070 open to supply steam to 12 AFW pump.
ANSWER C.
REFERENCE DATA Point Value:
1.00 M:dia #: CRO-34-1-5 Enabling Obj #: 3.1 Rcquired Ref: None Time: 2 min Question Type: MC K/A Catalog: 02034K4.01,02034K4.02,061000K4.02 Raf.: 10CFR55.41:
7, 10CFR55.43:
5, SD-34 REVIEW Author:
Date:
Approved:
Date:
-Roviewed by_ Program Development: No rov.
6, 02/23/98 Page 1 of 1_
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 6
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6.~ RE4~MDVDHITdFUD01 The Control Room Ventilation High Radiation Monitor (RE-5350) fails high. Which of -
the following automatic component actions are expected to occur?
A. Main Plant Exhaust Fans STOP and Control Room Ventilation goes to RECIRC mode.
vB. POST-LOct Filter Fans START, Outside Air Dampers CLOSE and Toilet Area Exhaust Fan STOPS.
C. POST-LOCl Filter fan discharge dampers OPEN and Toilet Area Exhaust Fan STARTS.
D. NSR Chiller Unit STOPS and Control Room SR HVAC STOPS.
Correct answer is based on design, distractors have unrelated components (Mn PLT Exh Fan, NSR chiller) or reverse action.
- KEY WoRDs:
NRC K/A '
NRCImp Cog level Source Reference Less Plan obj #
Outline bOOO72K101 b.5*
l COMP EB-MODIFY ESAR-7 lCRo 1221 b.0 Ir2G1 l
DATES: Modified: Monday, March 16,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o e
o e
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l il p(diff)l 1l rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l 4 l ol l
l I
EXAM BANK-DATA SHEET Question #: CRO-122-1-3-25 Task #:
020150207 NRC Category (s) :
B,B ERIEF: 5 Automatic Actions Control Room Ventilation High Rad Alarm KEYWORDS:- 122 - 1/2C22 RADIATION MONTIORING QUE; TION State any 4 of the-5 automatic actions that occur on a Control Room Ventilation High Rad Alarm (RE-5350).
[. 25 EACH) 1.
2.
3.
4.
ANSWER ANY 4 of 5
[.25 EACH) 1.
Shuts fresh air intake damper 2.
Shuts exhaust damper 3.
Starts POST-LOCI Filter Fans 4.
Opens POST-LOCI Filter fan discharge dampers 5.
Secures kitchen exhaust fan REFERENCE DATA Point Value:
1.00 i
Media #: CRO-122-1 Enabling Obj #: 3.0 i
Raquired Ref: None Time: 2 min Question Type: SA
~K/A Catalog: 015K4.03,K4.04,073000K4.01,4.0/4.3 Raf.: 55.41:11 55.43:5
/
SD-15, ARP 1C22 REVIEW Author:
Date:
Approved:
Date:
Roviewed by Program Development: No Rav. 00,'08/04/92 Page 1 of 1 1
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Tue'sday, March 17,1998 @ 08 47 AM FINAL.BNK Page: 7
- 7. ^TisS'001
~
Given the following:
1 Unit 1 has received a Reactor Protection System input which requires a reactor trip.
The Reactor has not tripped.
The MANUAL reactor trip buttons have failed to actuate a reactor trip.
l l
WHICH ONE (1) of the following methods is used NEXT to shutdown the reactor per EOP-0, " Post Trip Immediate Actions"?
A. Trip the main turbine.
VB. De-energize the CEDM motor generator sets.
C. Commence RCS boration using BAST gravity feed valves.
D. MANUALLY drive the CEAs into the core.
Correct answer is altenate action for manual pushbuttons not working, distractors are unrelated actions for the particular condition described.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00029A112 l4.0 NEMORY l11/95 NRC EOP-0 E.RO-201-0 l1.0 klG1 l
DATES: Modified: Friday, March 13,1998 used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.o TimeU p(diff)l il rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol j
1 l
l I
l l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 8 8MIRC0EATlif(fWKTEiR'601
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You are the Unit 1 CRS. You are reviewing a Liquid Waste Discharge permit for discharging 12 RCWMT to Unit 1 Circulating Water System. The following plant conditions exist:
l Unit 1 Unlil
- Mode 5 90% power
Both SW Headers in service What action should you as the CRS direct?
A. Approve the discharge permit and give it to the Unit 1 CRO.
vB. Have Chemistry submit a new permit for discharge to Unit 2.
C. Pen and ink the permit to change to " Unit 2" and approve permit for discharge.
D. Have Chemistry hold the permit until 12 SW Header is returned to service.
Correct answer is the administrative action required for permit initial conditions not met, the distractors are conditions that contain inappropriate actions, i.e, permit must reflect actual conditions of discharge.
KEY WORDS:
NRC K/A NRCImp Cog level Source Reference Less Pian Obj #
Outline h00075K102 h.1 hPPLIC NEW l01-17C-4 hRO-113-1 l2.0 k2G2 l
DATES: Modified: Tuesday, March 17,1998 used:
I otal STATISTICS:
A B
C D
E F
G H
I J
Omits T
Responses:
0 2
1 0
0 0
0 0
0 0
0 3
As a %:
0.0 ss.7 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel il p(diff)l 0.ssss7l rpbl 0,381l Values:1 l 0l 2 l 0l 3 l 0l 4 l 0l l
1 i
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 9
~~~
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"9. COAD' IR RE910VE00T A CAR unit has been shutdown and the inlet CV has failed to shut. If the CAR is in the
" Holding Mode", describe the effect, if any:
A. Air will not leak into the condenser.
I B. Air will leak into the condenser via the seal water recirc pump.
C. Air willleak into the condenser via the hogging CV.
vD. Air will leak into the condenser via the three way valve.
Correct answer reflects the caution in the 01, distractors are based on no effect, or specific components which are not sources of air inleakage for a failed inlet CV.
KEY WORDs:
NRC K/A NRcimp Cog level Source Reference Less Plan Obj #
Outline h00055K301 N.7 l MEMORY MM BANK hi-13 hRO 202-7G l1.2 k2G2 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
1 2
o o
o o
o o
o 3
As a %:
0.0 0.0 33.3 66.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l o.66667l rpbl 0.381l Values:1 l ol2l ol 3 l 0l 4 l ol I
I l
J l
i
)
l l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 1I b7CORDUCT OFDPS 002
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~ ~
0 Unit 1 is in MODE 3 with Tavg at 532 F, when one CEA is declared inoperable. How long after the detection of the inoperable CEA must the shutdown margin be verified?
A. Immediately v8.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> l
C.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Correct answer is specified by Tech Specs, distractors are routinely mentioned action times from the Tech Spec.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference L'ess Plan Obj #
Outline l00002.1.11 b.8 NEMORY EXAM BANK ITECH SPEC lSRO 206-1 b.0 lT3 GEN l
DATES: Modifed: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
1 2
o o
o o
o o
o o
o 3
Asa %:
33.3 66.7 0.0 0.0 s.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(drff)l o.ssss7l rpbl
-0,991l Values:1 l ol 2 l ol 3 l ol 4 l ol l
I l
l
Tuesday, March 17,1998 @ 08:47 AM -
FINAL.BNK Pose: 12
- 12. CONDUCT OF OPS 003 Unit i reactor startup following a refueling outage is in progress. The Shift Supervisor has assigned you as the Dedicated SRO for physics testing that NFM has just commenced. Prior to the start of the physics test you had been assigned as the Operations Work Control Center Coordinator (OWC). Which of the following functions may be performed by the Dedicated SRO?
VA. Direct the immediate actions necessary to place the unit in a safe condition.
B. Make recommendations to the Shift Supervisor conceming the physics test data reduction activity.
C. Review and approve Maintenance Orders.
D. Approve emergent risk significant maintenance contingencies.
Correct answer is specific to the responsibilities of the postion, distractors are elements of prohibited unrelated activities.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference
. Less Plan Obj #
Outline h00002.1.2 l4.0 lAPPLIC-SRO NEW h0-1-200 lSRO 204-1 b0.0 Ir3 GEN l
DATES: Modified: Monday, March 16,1998 Used:
statistics:
A B
C D
E F
G H
I J
Omits Total Responses:
3 o
0 o
o o
o o
o o
o 3
Asa %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l sl p(diff)l 1lrpbl 0l Values:1 l 0l 2 l 0l 3 l 0l4l 0l l
l l
(
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 15
~~T57CCIA60CT dF OPS 506
~
~
given the following conditions for Unit-1:
- 1) PA912 = 2475 0
- 2) Th = 590.5 F
- 2) Tc = 546.5 9
- 3) ASI = +0.015
- 4) PZR pressure = 2250 PSIA Using appropriate Tech Specs, calculate actual Pvar and the resultant Ptrip value:
vA. Pvar 1797, Ptrip 1875 B. Pvar 1875, Ptrip 1797 l
C. Pvar 1875, Ptrip 1875 i
D. Pvar 1811, Ptrip 1797 Correct answer is from actual calculation and using 1875 as minimum setpoint in all cases as specified by TS. Distractors are reversal of proper values or use of -0.015 for ASI in ' calculation (transpositional error).
KEY WORDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outline h0002.1.12 l4.0 hPPLIC kB-MODIFY kECH SPEC DRO 59-1 l5.02 IT3 GEN l
DATES: Modrfied: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 0
0 0
0 0
0 0
0 0
0 3
As a %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl 0l Values:1 l 0l 2l 0l 3 l 0l4l 0l
EXAN BANK DATA SHEET Question #: CRO-59-1-5-28 Task #:
.020590501 NRC Category (s) :
B,B CRIEF: Calculating Pvar & Ptrip KEYNORDS: SD 59 - REACTOR PROTECTIVE SYSTEM QUESTION Using the Tech Specs The following conditions exist at U-2 1)
PA912 = 1475MW 2)
Tc = 542*F 3)
ASI = +0.02 Calculate Pvar & Ptrip
[.5 each]
A.
Pvar =
B.
Ptrip =
ANSWER A.
1140
[.5 EACH]
B.
1875 Answer dependent on T.S curves.
Verify calculation prior to using question.
1 l
REFERENCE DATA Point Values 1.00 Msdia #: CRO-59-1 Enabling Obj #: 5.02,3 l
l Required Ref: Tech Specs 2.2-2, 2.2-3 Time: 2 min Question Type: NP K/A Catalog: 059A4.02,012000K6.11,2.9/2.9 Raf.: 55.41:10 55.43:2,~5
/
Tech Spec 2.2.1 REVIEW Author:
Date:
1 Approved:
Date:
R0 viewed by Program Development: No l
R;v.
1, 07/14/93 Page 1 of 1 1
I l
Tur.sday, March 17,1998 @ 09:31 AM FINAL.BNK Page: 16 167 CONT' IN9lESTdOOf~D02
-~~
~
~
Following a design basis Loss of Coolant Accident the Containment Spray System fails l
to actuate as required.
As a result, the containment design pressure will be exceeded unless which of the following actions are taken as a minimum:
A. 2 Reactor Cavity Cooling Fans and 2 Containment Cooling Fans are started in SLOW speed.
vB. 3 Containment Coolers are started in SLOW speed.
C. 3 Containment Coolers are started in FAST speed.
D. 4 Containment Coolers are started in FAST speed.
Correct answer is FSAR design bases, distractors are inapprorpiate actions that will result in failure of containment coolers (fast speed) or running unanalyzed components (Cavity Cooling fan) author:REN The stem was modified based on comments from JB KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000022A102 h.5 IAEMORY l4/93 NRC ESAR-6.5 hRO7-1 l10.0 k2G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl ol Values:1l ol2l ol 3 l ol 4 l ol l
i
l Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 17 57M6WT iMslENTCODE063-
~~
Given the following:
- Unit 2 has implemented EOP 4 (Excess Steam Demand)
- 21 SG blowdown in the Containment has been completed 0
- Containment temperature is ~252 F 1
- Containment pressure is ~ 47 PSIG
- Pressurizer level indicates - 128 " and pressure is - 1000 PSIA i
As the Containment Cooling Systems remove heat from the containment atmosphere, what effect is expected on the indicated level in the Pressurizer compared to the actual j
i level?
A. Indicated level will be less than actual level due to decreasing containment temperature, it will always be lower than actual.
vB. Indicated level will be greater than actual level, and as the containment temperature lowers, it will approach actual level.
C. Indicated level will be greater than actual level and will stay higher due to reference
{
leg flashing as the containment temperature lowers.
j D. Indicated level will be less than actual level, and as the containment temperature lowers, it will approach actual level.
Correct answer is based on EOP attachment 17, distractors are permutations of incorrect trends from the attachment.
author:REN The question was modified to completely change the stem and distractors, plus add in the decalibrating effects of RCS pressure.
KEY WORDS:
NRC K/A NRCImp Cog level source Reference Less Plan Obj #
Outline h00022K302 h.3 lAPPLIC EB-MODIFY EuND lSRO-201-0 l8.0 lT2G1 l
DATES: Modified: Monday, March 16,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
e o
e o
o o
e o
o o
As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Time l 1l p(diff)l 0l rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l 4 l 2
)
i l
EEAM BANK DATA SHEET Question #: SRO-301-15-1-05 Task #:
?
NRC Category (s):
None CRIEF: Pressurizer Level Indication KEYWORDS: 301 - THERMODYNAMICS AND HEAT TRANSFER QUESTION As' containment temperature increases, pressurizer level indication is expected to be A.
Less than actual.
B.
Greater than actual C.
Fluctuating due to reference leg flashing D.
Tracking actual due to density compensation ANSWER B.
' REFERENCE DATA Point Value 1.00 M:dia #: SRO-301-15-1 Enabling Obj #: 8.1 Required Ref: None Time: 2 min Question Type: MC K/A Catalog: K15.07 l
Rof.: None REVIEW Author Date:
Approved:
Date:
Rsviewed by Program Development: No Rhv. 003 08/07/92 Page 1 of 1
I Tuesday,. March 17,1998 @ 08:47 AM FINAL.BNK Page: 19 15IC6AT INIUtERT5PMY 001 The Containment Spray System is designed to limit containment pressure to less than its design value during a design basis accident. The system is also expected to be effective for which of the following:
A. Collecting and processing containment penetration leakage.
B. Preventing fuel and cladding damage.
C. Maintaining hydrogen concentration below 4%.
l VD. Removing fission products from the containment atmosphere.
t l
Correct answer is based on description in FSAR, distractors are unrelated but plausible accident conditions.
KEY WORDS:
NRc K/A NRcimp Cog level Source Reference Less Plan Obj #
Outline h00026K406 h.2*
hlEMORY HEW ESAR-6 lCRO-7-1 l10.0 k2G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
i 2
o o
o o
o o
o 3
Asa %:
0.0 0.0 33.3 66.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 0.66ss7l rpbl o.381l Values:1 l ol 2 l ol 3 l ol4l ol I
i i
a
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK
. Page: 20
- 20. CONTAINMENT SYS 001 During the performance of STP O-78-2 on Unit 2 at 100% power, the CRO reports that the Containment RMS isolation valve 2-RE-5291-CV fails to close on the SIAS signal.
What action is appropriate for this condition:
A. Complete the STP, place the Containment RMS back in service, note the malfunction in the STP.'
- 4. Shut 2-RE-5291-CV, deactivate the valve within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per TS, note the malfunction in the STP.'
C. Shut 2-RE-5291-CV within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, verify position once per shift, note the malfunction in the STP.
D. Notify System Engineer, evaluate STP results, note the malfunction in the STP, Correct answer is based on TS and STP admin requirements, distractors are variations on TS requirement, not applying TS requirements or subsequent implementation of STP admin requirements.
re-entered question due to floppy disc problem.
KEY WORD 8:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00103K102 l4.1*
DOMP NEW kECH SPEC DRO 7-1 l25.0. 29.0 k2G2 l
DATES: Modified: Friday, March 13.1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o o
As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Time l 1l p(diff)l 1l rpbl 0l Values:1 l 0l2l 0l 3 l 0l 4 l 0l
r Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page:21
= g=-
6001 Due to a problem on 2-TIC-223,2-CC-223-CV fails shut cat itdown Heat Exchanger outlet temperature to increase. What effect does ibt v' ave on reactor l
l power and why?
l (Assume normal CVCS lineup)
A. Reactor power will decrease due to the increase in B-10 removal in the CVCS lon Exchanger.
vB. Reactor power will decrease due to the resultant increase in B-10 concentration in i
the VCT.
C. Reactor power will increase due to the resultant increase in B-10 concentration in the VCT.
D. Reactor power will increase due to the increase in B-10 removal in the CVCS lon Exchanger.
Correct answer includes the effect on the I-X to the downstream VCT, distractors are reverse action of effects on reactor or cycs components.
KEY WORDs:
NRc K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00004K306 h.6 l COMP NB-MODIFY NUND lCRO-113-5 h.0 IT2G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o e
o o
o 3
As a %:l o.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl ol Values:1 l ol 2 l cl 3 l ol 4 l ol L_-.--_________-..
EXAM BANK DATA SHEET Question #: CRO-113-5-5-12 Task #:
?
NRC Category (s) :
None ERIEF: Effect of Increase in Letdown Heat Exchanger Outlet Temperature KEYWORDS: 113 - SERVICE WATER AND MISCELLANEOUS STATION SERVICES QUESTION What effect does an increase in Letdown Heat Exchanger outlet temperature have on reactor power and why?
A.
Reactor power will decrease due to the increase in B-10 removal in the CVCS Ion Exchanger.
l B.
Reactor power will decrease due to the decrease in B-10 removal in the CVCS Ion Exchanger.
C.
Reactor power will not be affected.
D.
Reactor power will increase due to the increase in B-10 removal in the CVCS Ion Exchanger.
ANSWER B.
}
_ REFERENCE DATA Point Values 1.00 Mcdia #: CRO-113-5-5 Enabling Obj #: 3.0 Roquired Ref: None Time: 2 min Question Type: MC K/A Catalog: ?
Rof.: ?
REVIEW Author:-
Date:
Approved:
Date:
Rsviewed by. Program Development: No R3v. 00, 07/17/92 Page 1 of 1
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 22
- 22. CVCS 002 Unit 1 is operating @ 100% power. RCS boron concentration is 161 ppm. The RO is monitoring a 120 gallon DI water addition to the VCT. The following indications are observed:
Reactor thermal power at 2700 Mth and slowly increasing 0
Auctioneered Tc at 548 F 0
Highest RPS Tc at 548 F Which of the following actions should be performed first?
A. Trip the reactor and implement EOP-0.
B. Insert Group 5 CEAs to 105".
- 4. Stop any makeup to the RCS.
D. Perform a 10 second fast boration.
Correct answer is specified by AOP 1 A for RCS dilution, distractors are actions out of sequence or over compensation for the event.
j KEY WoRos:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000004A407 h.7 l COMP HEW h0P-1A lCRO-107-1 l2.17.2
[r2G1 l
DATES: Modified: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
o 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol l
l I
l L_________
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 23 2f DC DISTRlBUTID'A~60'1
~
The correct action to take to trip the Unit 2 turbine on a loss of 125 VDC Bus 11 is:
A. Use trip button on 2002, it is unaffected by loss of 125 VDC Bus 11.
B. Initiate turbine trip from either ESFAS logic cabinet by depressing either Turbine Trip Hi Level or RxTrip Bus Undervoltage bistable manual trip pushbutton, vC Station an operator at the front standard and when directed, manually trip the turbine using the trip lever.
D. Enter the HP turbine doghouse and flip the MSR High Level Trip Bypass Switch up and down which will trip the turbine.
Correct answer is specified in AOP 7J, distractors are unspecified actions which cause a turbine trip assuming DC power is available.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000063K404 b.97 NEMoRY MXAM BANK h0P7J lCRO 202-7J k.2 IT2G1 l
DATES: Modified: Tuesday. March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Totaf Responses:
o e
3 o
e o
e o
o o
o 3
Asa %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel 2l p(d@l 2lrpbl 0l Values:1 l 0l2l 0l 3 l 0l 4 l 0l i
l l
l 1
f f
L-
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page:24
~i4TDKDPp5[fWOD 001 Which one of the following describes the immediate effect on Shutdown Margin as.-
defined by Tech Specs for a dropped CEA?
VA. Shutdown Margin is unchanged.
l B. Shutdown Margin is reduced by the worth of the CEA.
C. Shutdown Margin is increased by the worth of resultant power change.
D. Shutdown Margin is unchanged by the offsetting Xe reactivity effects.
Correct answer is based on the TS definition for SDM, distractors are effects on SDM which do not account for the TS definition.
l
' author: REN ~
KEY WoRDs:
NRC K/A NRCIr:q Cog level Source Reference Less Plan Obj #
Outline b0003AK107.b.9 l COMP hdEW l TECH SPEC lCRO-2061 b-lT1G1
]
DATES: Modmod: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
1 1
1 0
0 0
0 0
0
-0 0
3 As a %:
33.3 33.3 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 0.33333l rpbl -0.381l Values:1 l 0l 2 l 0l 3 l 0l4l 0l i :-
i'
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 25
- 25. EMER BORATION 001 On a loss of MCC-214, which boration flowpath would be available?
A. RWT outlet and a charging pump.
vB. 22 BA pump, BA direct m/u valve and a charging pump.
I C. 21 BA pump, BA flow control valve, VCT to a charging pump.
D. 21 or 22 BAST gravity valves and a charging pump Correct answer is from effect specified in AOP 71, distractors are based on 1 component that has no power that prevents flow, author: REN KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b00024K201 l2.7 NOMP kB-MODIFY h0P71 DRO-107-1 k.15 k1G1 l
DATES: Modified: Friday', March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 2
0 1
o o
o o
o o
o 3
Asa %:
0.0 66.7 0.0 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)I 0.66667l rpbl 0.s1l Values:1 l 0l 2 l ol3l ol4l 0l
~
(
EEAM BANK DATA SHEET Question #: CRO-107-1-3-29 Task #:
020060210 NRC Category (s):
B,B ERIEF: Boration Flow Path Availability-KEYWORDS: 107 CHEMICAL AND VOLUME CONTROL BOARD QUESTION On a loss of 11 4KV Bus, which one of the below listed boration flow paths would be available?
A.
RWT outlet valve and a charging pump B.
12 BA pump, BA direct M/U valve, and a charging pump C.
11 BA pump, BA flow control valve, VCT M/U valve, VCT outlet valve, and charging pump D.
11 or 12 BAST gravity drain valves, and a charging pump ANSWER B.
L REFERENCE DATA Point Values 1.00 l-M:dia #: CRO-107-1-3 Enabling Obj #: 2.15.2
[
R: quired'Ref: None Time: 2 min Question Type: MC l
K/A Catalog: 006K2.02-3,004000K2.01,2.9/3.1 Rof.: 55.41:7-55.43 REVIEW Author:
Date:
Approved:
Date:
.Roviewed by Program Development: No Rav.
3',.02/20/98-Page 1 of 1
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 26 i
I67nsle[CDREl:IO6flNG 001
~
~
A major transient occurred a short time ago on Unit 2. You are the Unit 2 CRS and you are directing the implementation of EOP-0. The following conditions exist:
RCS pressure 1130 psia and lowering Pressurizer level 35" and lowering 0
RCS subcooling 42 F and lowering Containment pressure 1.5 psig and rising The RO is performing the RCS Pressure and Inventory Safety Function. He reports that SIAS actuation has been verified but there is no HPSI flow indicated. 21 and 23 HPSI Pump amps and discharge pressure are low. What action would you recommend to the Shift Supervisor?
A. Start 22 HPSI.' ump.
B. No action necessary, the flow indicators must have failed.
C. Stop, then restart 21 and 23 HPSI Pumps.
vD. P! ace all operating ECCS Pumps in PTL, verify valve lineup, vent pumps.
Correct answer requires inference that a common mode failure has occurred on all pumps sharing a suction with 21 and 23 HPSI (LPSI and CS pumps) are in jeopary of failure due to inadequate suction head.Distractors are unrelated or partial actions that will not account for common mode failure for all affected pumps.
i KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000006A204 h.8 hPPLIC-SRO HEW EOP-0 lCRO-7-1 h.0. 36.0 lT2G2 l
DATES: Modified: Tuesday, Maren 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
0 0
0 3
0 0
0 0
0 0
0 3
As a %:
0.0 0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 2l p(diff)l 1l rpbl 0l Values:1 l 0l2l 0l 3 l 0l4l 0l
Ic Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Pagei27 27755iERlRf602 Given the following:
- Unit 1 is at 100% power
- The 1B DG is running unloaded for post maintenance testing, Electric Shop and Mechanical maintenance personnel are standing by in the 1B DG Room -
- CRO reports a"1B DG" alarm is received at 1C188
- OSO reports a " START FAILURE" alarm is received at the 1B DG Alarm panel
- Electricians suspect blown fuses, requesting to replace them immediately.
Using the provided electrical schematic, determine which fuses have resulted in the indicated response on the 1B DG and will provide direction from you the CRS for replacement:
l_
- A. Fuses FU7 and FU8 due to the start failure alarm that was annunciated from the loss of control power.
l
- 4. Fuses FU1 and FU2 due to the start failure alarm that annunciated from the loss of
. control power.
C. Fuses FU3 and FU4 due to start failure alarm from the engine running with the air
. start solenoids failed close.
C. Fuses FU5 and FU6 due to the start failure alarm from the loss of power to the low speed and auxiliary stop relays.
Correct answer is based on the schematic for loss of fuses FU1 and FU2, distractors are different fuses in the circuit which do not effect the start failure circuitry (T2A relay).
author:REN The question was modifed by complete change of the stem and use of different fuse combinations.
KEY WORDs:
NRC K/A NRcImp Cog level Source Reference Less Plan Obj #
Outline h00064K203 l3.6 lAPPLic EB-MODIFY l1E86 SH13 lCRO 48-1 l11.0 lT2G2 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Timel il p(diff)l ol rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol
EXAM BANK DATA SHEET Question #: CRO-48-1-2-10 Task #:
020480501 NRC Category (s) :
None ERIEF: Loss of DG control power KEYWORDS: DG ALARM QUESTION The "1B DIESEL" alarm window has actuated in the control room.
Investigation has. determined that fuses FU2 and FU3 are blown.
What is the effect on 1B DG?
(refer to drawing 1E-86 sheet 13-provided)
ASSUME IB DG IS IN A STANDBY CONDITION WHEN ALARM RECEIVED A.
The exciter field flash control power is lost, the air start solenoids fail open, and the DG starts.
B.
.The air start solenoids fail closed and a start failure has occurred.
C.
None, the DG is still operable as its power is being maintained by fuses FUi and FU4.
D.
The field is flashed, the air start solenoids fail open, and the DG starts.
. ANSWER B.
REFERENCE DATA Point Values 1.00 M:dia #: CRO-48-1-2 Enabling Obj #: 16.0 R quired.Ref: 61-086-E sht 13 Time: 3 min Question Type: MC K/A Catalog: 02 04 8 K1'. 01, 02 04 8 K11. G 5, 02 04 8 K11.10 Raf.: 61-086-E sht 13 and Alarm Manual REVIEW Author:
Date:
Approved:
Date R3 viewed by Program Development: No
-Rbv.. 2,.-11/08/94 Page 1 of 1
Tueulay, March 17,1998 @ 08:47 AM FINAL.BNK Page: 28 25.~5slEWPR6CEbURE5 601
~
~
Which one of the following parameters would absolutely differentiate a steam line rupture inside containment from a LOCA inside containment?
A. Containment Sump Level.
B. Pressurizer Level.
C. Containment Temperature.
vD. Subcooled Margin.
Correct answer is based on the response of the ESDE which causes a large cooldown with RCS pressure maintained by safety injection. The LOCA results in a rapid pressure decrease from the loss of inventory, resulting in subcooled margin going to 0 0. The other distractors are parameters that are affected by both accident conditions.
F KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b00002.4.4 l4.3 NEMORY l4/93 NRC ESAR-14 lSRO 2014 l1.0 IT3 GEN l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o 3
o o
e o
o o
o 3
As a %:
0.0 0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l il p(diff)l 1l rpbl ol Values:1 l ol 2 l ol 3 l ol4l ol l
l l
I o________
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 29
~ 6.~EslEDRD6EdOR55004 2
Given the following:
- Due to a loss of all AC power, EOP 7 (Station Blackout) was implemented ~20 minutes ago
- Unit 1 is meeting the intermediate SFSC but Unit 2 is not meeting the intermediate SFSC for Core and RCS heat removal as a result of sabatoge
- The interim RAD estimates that a release of 2E6 uCl/sec is occurring and will continue for at least 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- Wind direction from the DRDT screen is from the North What Prompt Protective Action Recommendation should be made?
A. Shelter 10 mile EPZ B. Evacuate 10 mile EPZ
- 4. Evacuate zone 1 and 3 and shelter the remainder of 10 mile EPZ D. Shelter zone 1 and evacuate remainder of 10 mile EPZ Correct answer is based on ERPlP actions, distractors are permutations of the correct
' answer, author: REN The question was modfied by complete change of stem and change required action due to wind direction change. Outline needs change to to change in K/A from 2.4.28 KEY WoRDs:
NRC K/A -
NRCImp Cog level Source Reference Less Plan Obj #
Outline h0002.4.44 - l4.0 hPPLIC-SRO kB-MODIFY ERPIP 3.0 lSRO 217-3 l11.0 IT3 GEN l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
Asa %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Time U p(diff)l ol rpbl ol Values:1 l ol2l ol 3 l ol4l ol l
i l
l l
l
EXAM BANK DATA SHEET Question #: SRO-217-3.0-2-19 Task #:
032170414 NRC Category (s) :
None ERIEF: Protective Action Recommendations (PARS)
KEYWORDS: ERPIP QUESTION Sabatoge has caused a major plant accident. As the Shift Supervisor you decide to call a General Emergency.
What Protective Action Recommendation should be made given the following conditions?
A release of SE6 uCi/sec is occurring via main vent stack and'is expected to last for next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> DRDT screen indicates wind direction from the west c.
Evacuate 10 mile EPZ b.
Shelter 10 mile EPZ c.
Evacuate zone 1 and shelter remainder of 10 mile EPZ d.
Evacuate zones 1, 2 and 3 and shelter remainder of 10 mile EPZ ANSWER c.
Evacuate zone 1 and shelter remainder of 10 mile EPZ REFERENCE DATA Point Values 1.00 M3dia #: SRO-217-3.0-2 Enabling Ohj #: 11.0 Required Ref: ERPIP 3.0 Rev. 17 Time:
3 min Question Type: MC l
K/A Catalog: 194001Al.16,3.1/4.4,03217PA3.18 I
Raf.: ERPIP 3.0 Rev. 17 l
REVIEW.
j Author:
Date:
L l-Approved:
Date:
Rsviewed by Program Deveicpr.3nt: Yes Rsv.
5,.08/27/97 Page 1 of 1 Li-. --
1
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 30
~~ ~ TeMER PR6CEDURES'005
-~
30
~
Given the following:
- Unit 2 has implemented AOP 7H (Loss of Plant Computer) l
- DAS is not available Select the more restrictive limit which, when exceeded, requires a power reduction within the specified time interval:
A. Less than DNB limits within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
B. Less than Linear Heat Rate limits within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
C. Less than DNB limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
v'D. Less than Linear Heat Rate limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
j Correct answer is based on AOP 7H actions, distractors are permutations of incorrect actions within AOP 7H.
author: REN The question was modified by complete change of the stem and adding incorrect time limits (removed Tq and Frt distractors)
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l00002.4.11 k8 NOMP EB-MODIFY h0P 7H NRO 202 7H l2.0 k3 GEN l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
Asa %:
00 0.0 0.0 00 00 00 00 00 00 00 00 00 Time d p(diff)l ol rpbl ol Values:1 l ol2l ol 3 l ol4l E
1 i
EXAM BANK DATA SHEET Question #: CRO-202-7H-5-05 Task #:
020590301 NRC Category (s):
B,B ERIEF: Power Reduction KEYWORDS: 202 - AOP QUESTION why must a power reduction, if necessary, be commenced within 60 minutes of a sustained loss of the plant computer?
A.
DNB Tech Spec B.
Azimuthal Tech Spec C.
Total Planar Radial Peaking Factor Tech Spec D.
Linear Heat Rate Tech Spec ANSWER D.
1 l
REFERENCE DATA Point Values 1.00 M;dia #: CRO-202-7H-5 Enabling Obj #: 2.1 Rcquired Ref: None Time: 2 min Question Type: MC K/A-Catalog: PK3.01,010000 GEN,3.4/3.9 Raf.: 55.41:10 55.43:2
/-
REVIEW j
Author:
Date:
Approved:
Date:
R3 viewed by Program Development: No Rev.
3, 05/08/95 Page 1 of 1 Iw
l l
l Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 31
- 31. ECiUiPslERT"CDNTFfDL 601
~
1 An immediate change to an STP, that is not a change of intent, requires the approval of how many members of plant management staff, and who must one of these members be?
A. Two, Test Coordinator.
B. Three, General Supervisor or above.
vC. Two, a Senior Reactor Operator.
D. Three, GS-NPO Correct answer is based on admin procedure requirements, distractors are variations l
based on specific titles, not SRO license requirements.
l KEY WORDS:
l NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00002.2.6 l3.3 NEMoRY k.XAM BANK ER 1101 lSRO 204-PR l3.0 k3 GEN l
DATES: Modified: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
o 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time d p(diff)l il rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol l
l 1
l I
i
)
I o.________
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page:32
~52~$dOIPWl5NT~CdNTRDL 002
~
~
~
Refer to the attached Unit 1 Technical Specifications Core Operating Limits Report (COLR).
Unit 1 reactor power is 70% when a continuous CEA withdrawal occurs. When the withdrawal is stopped, indicated Axial Shape Index (ASI) is -0.29 and reactor power peaks at 79%. Unit 1 is using Excore Monitoring for LHR and DNB surveillance monitoring.
.Which, if any, axial flux offset control limit (s) is(are) being exceeded?
l vA. Linear Heat Rate only.
B. DNB only.
C. Both Linear Heat Rate and DNB.
D. Neither Linear Heat Rate nor DNB.
Correct answer is based on the TS requirements, where the DNB requirement is very n close to the TS limit due to the resultant power increase. Distractors are different possible combinations of 2 items of concem.
provide TS section 3/4.2 and COLR MEYWoRDs:
NRC K/A NRCimp.
Cog level Source Reference Less Plan Obj #
Outline b0002.2.25 b.7 NEMORY l4/93 NRC kS COLR lCRO 212-3 E.1 h3 GEN l
- DATES: Modifed: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 0
0 0
0 0
0 0
0 0
0 3
Asa %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l il p(diff)l 1l rpbl 0l Values:1 l 0l 2l 0l 3 l 0l 4 l 0l 1:
I
=__-_2_____.
_ Tueuiay, March'17,1998 @ 08:47 AM FINAL.BNK Page:33
~53T5dUIPNiERT CfCiHTKOL 003
~
11 and 12 Heater Drain Pump Chiller Units are scheduled to be taken out of service for scheduled maintenance. The chiller units will be out of service for 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />. The maintenance order describes only the inspection that the shop will be performing. You
. have directed the Principal Plant Operator (PPO) to place two " heat killer" fans in operation at the Heater Drain Pump motors. What additional controls, if any, are required by plant procedures?
A. Initiate a Troubleshooting Control Form.
- 4. Have the Shift Supervisor perform an evaluation and initiate a Temporary Alteration.
C. Place the temporary fans in service, no additional action is required.
D. Initiate a Procedure Controlled Temporary Plant Configuration Change.
Correct answer is based on admin procedure, distractors are possible administrative actions for equipment failures or operating procedure requirements.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline -
. h0002.2.14 b.0 l COMP-SRO NEW IAD-1-100 lSRO 204MN b.0 k3 GEN l
DATES: Modined: Tuesday, March 17,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel il p(diff)l 2l rpbl ol Values:1 l ol2l ol 3 l ol4l ol l
l l
l i
l e
':_-_-a_--
__2.___---
Tuesday, March 17,1998 @'08:47 AM FINAL.BNK Pa8e:34
~MTE60iPMEAT 66ATRdi_~604
~
~
You are performing the function of the Operations Work Control Center Coordinator (OWC) when the Outside Operator reports that the 2A DG Standby Lube Oil Pump is making an unusual noise. The System Engineer and Mechanical Maintainence Supervisor recommend that the pump be replaced immediately as Priority 2 -
maintenance. What action, if any, should the OWC initiate per plant procedures?
vA. Ensure completion of an Operational Risk Assessment.
B. Authorize the Maintenance.
C. Direct the Outside Operator to secure the lube oil pump.
D. Direct the CRO to perform a breaker line-up verification Correct answer is the required action per admin procedure, distractors are variations of routine operator actions that are inappropriate for the condition.
KEY WORDs:
' NRc K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b0002.2.17 b.5 l COMP-SRo NEW NN-1-202 lS-201MN101 l1.1 k3 GEN l
DATES: Modified: Tuesday, March 17,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 o
o o
o o
o o
o o
o 3
Asa %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel il p(diff)l 1l rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol L,
h i
i
________r_-__________._
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page:35
- 35. EQUIPMENT CONTROL 005 STP M-212A-1 is in progress on Channel A RPS. Trip Units 1,2,7,8 and 10 are bypassed. Instrument Maintenance personnel discover an out of tolerance voltage for the high power trip unit. They suspect a bad power supply and request permission to commence troubleshooting the problem. Who must authorize the Troubleshooting Control Form?
A. RMGS and CRS.
B. RMGS, GS-Instrument Maintenance, and CRS.
D. RMGS, SS, and GS-NPO.
Correct answer is based on admin procedure, distractors are various approval chains.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b0002.2.20 h.3 l COMP-SRO HEW hN-1-110 lS-204MN110 h.1 k3 GEN l
DATES: Modified: Friday. March 13,1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
o
_1 As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time d p(diff)l 1l rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol t
i
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 36
~ [EfQUjPhisWTDUNTFiD~L 066 3
A Unit 1 startup is in progress following a 7 day forced outage to replace an RCP seal.
You are performing the functions of the Dedicated SRO for the plant startup. The following conditions exist:
RPS Delta-T power 14%
Plant computer thermal power 17%
STA reports that RCS loop Th-Tc is consistent with a power level of ~18%.
l l
You notice that the " LOSS OF LOAD CH TRIP BYP" alarm is still in alarm at 1C05.
When should this alarm clear, when is the trip required to be enabled, and what is the design basis of the trip?
l A.12%,214%, helps avoid lifting the main steam line safety valves.
L B.13%,214%, protects the RCS from overpressurization.
vC.14%,215%, helps avoid lifting the main steam line safety valves.
D.13%,215%, protects the RCS from overpressurization.
Correct answer is based on Tech Spec bases description, distractors are variations on the setpoint and trip purpose.
KEY WORDs:
NRC KIA NRCImp Cog level Source Reference Less Plan Obj #
Outline l00002.2.22 l4.1 l COMP HEW k.S. LSSS lCRO-59-1 l1.02 k3 GEN l
DATES: Modified: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H l l J
Omits Total Responses:
o o
i 2
o o
o o
o o
o 3
Asa %:
0.0 0.0 33.3 66.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 0.33333l rpbl 0.991l Values:1 l 0l 2 l 0l 3 l 0l4l 0l
J Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK' Pase: 37
- 37. ESFAS 002 Which of the following components under expected conditions will have Salt Water
. isolated to it during a SIAS?
A. SRW heat exchanger.
. 4. CCW heat exchanger.
C. Circ water pump seals.
D. ECCS pump room coolers.
Correct answer is based on design described in the FSAR, distractions are various salt.
water system loads that get SIAS signal (non-isolating) or no SlAS effect.
KEY WORDs:
NRC K/A.
NRCImp Cog level Source Reference Less Plan Obi #
Outline
' h00013K502 b.3 bEMORY EXAM BANK bSAR-9.5 lCRO 113-2 b.0 k2G1' l
DATES: Modified: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F-G H
I J
Omits Total Responses:
0 3
0 0
0 0
0 0
0 0
0 3
As a %:
0.0 100.0 0.0 0.0
- 0. 0' O.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 2l p(diff)l 1l rpbl 0l Values:1 l 0l 2 l Ol3l 0l 4 l Ol' l
l' l
$m.
_m.___'_____.U
___<_1.__
Tuesday, March 17,1998 @ 08:47 AM
. FINAL.BNK r se:38
~ 7E5FAS 603 38
~
Given the following:
- Unit 1 is in Mode 3-
- SIAS Pressurizer Pressure Blocked on both logic channels
- RCS pressure being reduced to 1500 PSIA /
- PZR Spray valves fail shut and RCS pressure starts to increase Select the expected system response as pressure increases:
A. SlAS Pressurizer Pressure Block will be manually removed when the RO goes to
" NORMAL" at 1800 PSIA with the keyswitch for SIAS Block A at 1C10.
- 4. SIAS Pressurizer Pressure Block will be automatically removed when ZE and ZF
. SIAS Pressurizer Pressure sensors clear C. SIAS Pressurizer Pressure Block will be manually removed when the RO goes to
" NORMAL" at 1800 PSIA with both keyswitchs for SIAS Block A and B at 1C10.
D. SlAS Pressurizer Pressure Block will be automatically removed when ZD SIAS '
Pressurizer Pressure sensor clears.
Correct answer is based on FSAR description, distractors are permutations of wrong.
status (manually removed) or 1 out of 4 logic, author:REN this is a new question for an Exam Bank question replacement KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b00013K401 l4.3 l COMP NEW ESAR-7 lCRO 63-1 l1.7 lT2G1 l
DATES: Modified: Tuesday, March 17,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o e
o o
o o
o o
As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0
'o.o 0.0 0.0 Time l 1l p(diff)l ol rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol.
l-1.
1 i
p I
iL
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 39
- 39. EXCESSIVE RCS LEAK 001 Given the following:
- Unit 2 is at 80% power
- Unidentified RCS leakage is.5 GPM
- No SG leakage is identified
- RO reports that VCT trace indicates an increase in RCS leakage As the CRS, you direct the implementation of AOP 2A (Excessive RCS leakage).
Which of the following conditions would require Unit 2 to be shutdown per T.S. 3.4.6.2?
A. 5 GPM leakage identified from body of 2-CVC-500 (VCT Diversion).
B. 5 GPM leakage identified from the packing gland on PORV-404.
- 4. 5 GPM leakage identified from RCP intregral heat exchanger, D. 5 GPM leakage identified from seat of SI-652-MOV.
RCP intregral heat exchanger is considered pressure boundary leakage, distractors are non-pressure boundary leakage for the RCS or system connected to RCS.
author:REN KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
outline hCEA16AK13h.5 l COMP HEW kECH SPEC lCRo-202-2A k.0 k1G3 l
DATES: Moddied: Friday. March 13,1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
2 1
o o
o e
o o
o 3
Asa %:
0.0 0.0 ss.?
33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 i
Tirnel il p(diff)l o.ssss7l rpbl o.381l Values:1 l ol 2 l ol 3 l ol 4 l ol I
i l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 40 40EFUEGI^MdilA6661 During refueling a new fuel assembly has just been inserted in its specified core location when the FHS observes that the mast detent is at "0" vice "180" as required by the fuel handling procedure. Choo'3e the answer that represents the applicable actions to be taken:
A. Withdraw the fuel assembly from the core, FHS and Shift Supervisor shall evaluate, and obtain written approval from the PE-NFM to resume core alterations.
B. Leave the assembly grappled and exit the refueling machine, the RCRO and FHS shall evaluate, and obtain verbal approval from the Shift Supervisor to resume core alterations.
l VC. Leave the assembly grappled and notify the Shift Supervisor and PE-NFM l
immediately.
l D. Withdraw the fuel assembly from the core, rotate mast to the correct detent, and reinsert the assembly.
Correct answer is based on FH-210 requirements, distractors are prohibited actions.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000034A203 l4.0 hPPLIC-SRO kB-MODIFY EH-210 lCRO 113-6 l7.2 lT2G2 l
DATES: Modifed: Monday, March 16.1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
o 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 l rpbl ol Values:1 l ol2l ol3l ol4l ol Time]
p(diff)l i
1
EXAM BANK DATA SHEET Question #: CRO-113-6-4-13 Task #:
022090105 NRC Category (s) :
None CRIEF: Refueling KEYWORDS: 113 - SERVICE WATER AND MISCELLANEOUS-STATION SERVICES QUESTION During refueling, two source range NIs indicate a sustained rising count rate after a fuel assembly has been inserted.
Choose the answer that represent s the applicable actions to be taken:
A.
Withdraw the fuel assembly from the core, FHS and Shift Supervisor shall evaluate, and obtain written approval from the PE-NFM to resume core alterations.
B.
Leave the assembly grappled and exit the refueling machine, the RCRO and FHS shall evaluate, and obtain verbal approval from the Shift Supervisor to resume core alterations.
C.
Notify the Shift Supervisor and Fuel Handling Supervisor immediately.
D.
Initiate boration, NI system engineer and Shift Supervisor shall evaluate, and obtain written approval from the GS-NPO to resume core alterations.
ANSWER C.
1 REFERENCE DATA Point Values 1.00 Mndia #: CRO-113-6-4 Enabling Obj #: 2.0B Rsquired Ref: FH-210 Time: 2 min Question Type: MC K/A Catalog: ?
Raf.: ?
' REVIEW Author:
Date:
Approved:
Date:
Raviewed by Program Development: No R3v.
3, 03/23/95 page 1 of 1 t
j
I Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK rage: 41
- 41. FU56RECid9ERYCY
~
Given the following:
- "CNTMT RAD LVL HI" at 2C10 is received and verified as valid by the CRO, What procedural actions are required?
A. Parallelimplementatica of EOP-5(LOCA) concurrent with EOP-4.
v8. Implementation of EOP-8 (Func Recovery) due to EOP-4 Cont Env SFSC not met.
C. Implementation of EOP-8 (Func Recovery) due to EOP-4 Rad levels SFSC not met.
D. Parallel implementation of AOP-6A (abnormal RCS activity) concurrent with EOP-4.
Correct answer is based on the specific parameter (rad alarm) contained in the containment envoimment safety function status check. Distractors are various combinations of parallel actions that are not appropriate or wrong SFSC referenced.
author:REN KEY WORD 3:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline bCE009EK12 l4.0 hPPLIC-SRO HEW EOP4 hRO-201-8 h.1 lT1G2 l
DATES: Modified: Tc esday March 17,1998 Used:
{A STATISTICS:
B C
D E
F G
H I
J Omits Total _
Respo.7sec 8 o
3 0
o o
o o
o o
o o
As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpb[
ol Values:1 l ol 2 l ol 3 l ol4l ol I
1 w--_--_-______._______________-___________________
Tuesday, March 17,1998 @ 08:47 AM F1NAL.BNK Page: 43
~ fHi~RECDWiBINEFf601 4
WHICH ONE (1) of the following is the MAXIMUM hydrogen concentration allowed inside Containment before the Hydrogen Recombiners are required to be placed in service?.
VA. 0.5%
B. 2%
C. 3%
. D. 4%
Correct answer is based on EOP5 actions, distractions are variations up to the design 2
2 limit of 4% containment H (H Recombiner design)
KEY WORDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outline l000028A101 b.8 NEMORY l11/95 NRC EOPS kRO 7-1 l28.9 k2G2 l
DATES: Modified: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
0 2
0 1
0 0
0 0
0 0
0 3
As a %:
0.0 66.7 0.0 33.3' O.0 0.0 0.0 0.0 0.0 0.0 00 100.0 Timel 1l p(diff)l 0l rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l 4 l 0l l
l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK
.Page: 45 l
457HIRCS ACTMiT ~002
~
~
l Given the following:
- Specific activity of the reactor coolant has exceeded 1.0 microcurie / gram DOSE EQUIVALENT l-131 for greater than 100 continuous hours interval.
0 Which one of following is the basis for the requirement to cooldown below 500 F I
within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />?
VA. Prevents the release of activity should a SG tube rupture.
l B. Increases reliability of the data collected for Piiual lodine determination per ODCM.
C. Minimizes the expected lodine spiking pnenoma from the large change in thermal power due to plant shutdown.
D. Increases the coolant density to enable self-shielding to reduce on-site exposures.
Correct answer is based on Tech Spec bases for trip, distractors are RCS activity related concepts or variations of reactivity concepts (self-shielding).
KEY WORDs:
l NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline lD00076A202 h.4 NEMORY l11/95 NRC kS BASES DRO.212-1 b.0 klG1 l
OATEs: Modified: Saturday, March 14,1998 Used; l
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 o
o e
o o
o o
o o
e 3
As a *A:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl ol Values:1 l ol 2 l ol3l ol4l ol u___
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 47
~D7lSCiDRe~TEslFsiOHliO1 Which of the following provides a possible indication of a failed incore detector?
l:
VA. CECOR/BASSS display on the Plant Computer.
B. " Selected Computer Point" alarm at C06.
l C. Incore detector computer point in alarm below the limit on Plant Computer.
l D. Small variations in reactor thermal power (PA 911 2 Mwth).
Correct answer is based on AOP conditions, distractors are unrelated effects or conditions which do not denote failed indications for incore detector (detector in alarm below Plant Computer limits).
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00017K101 b.2 NEMORY kB-MODIFY h0P 7H lCRO 64-1 N.0 hG1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 0
0 0
0 0
0 0
0 0
0 3
As a %:
100.0 0.0 0.0 0.0 0.0 0.0, 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l il rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l4l 0l l
EXAM BANK DATA SHEET Question #: CRO-64-1-4-04 Task #:
020690514 NRC Category (s) :
B,B CRIEF: Failed Incore Detector Identification KEYWORDS: SD.64 - ICI QUESTION-How is a failed incore detector initially identified?
l A.
Tg surveillance will display failed detectors B.
CECOR/BASSS failed detectors display on plant computer C.
Fr surveillance will display failed detectors D.
"XD" labeled point will alarm on the plant computer ANSWER.
B.
l REFERENCE DATA Point Values 1.00 Madia #: CRO-64-1-4 Enabling Obj #: 2.0 Raquired Ref: None Time: 2 min Question Type: MC K/A Catalog: 064K1.02,015000K6.01,2.9/3.2 Rof.: 55.41:2,7 55.43:5 REVIEW Author:
Date:
Approved:
Date:
Rsviewed by Program Development: No R v.
2, 01/21/98 Page 1 of 1
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK P.ge: 49
~~i9.lARGE'BREAKlOC^~002~ ~ ~ ~ ~ ~ ~ ~ - ~ ~
~~~'
~~~
Which one of the following is the reason that core flush is NOT established before 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following a LOCA?
A. Boron precipitation is not a problem due to large steam flow through the break, vB. Avoid entrainment of Si flow in the steam being released from the core.
C. Maximize cold leg injection due to high decay heat load.
D. Allow for Rx vessel head cooling to minimize void formation in the head.
Correct answer is based on EOP5 bases for core flush, distractors are reasons for core flush not required to start immediately per bases.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000011K312 l4.6 NEMORY l11/95 NRC kOPS BASIS lSRo-2015 b.0 k1G1 l
DATES: Modered: Monday, March 16,1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
2 1
e o
o o
o o
o o
o 3
Asa %:
66.7 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time U p(diff)l o. 3333 3l rpb
.o.3sil Values:1 l ol 2 l ol 3 l ol 4 l ol l
i L
1 Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 50
~
~s6.~0dOIDMDW STE 001 The Miscellaneous Waste System receives liquid waste from which of the following major sources?
A. Containment tendon galleries, vB. Contair. ment normal sump and pumped sumps.
l C. Waste Gas Decay Tank condensate.
D. Evaporator distillate.
Correct answer is based on system design per FSAR, distractors are sources of waste l
that are handled locally via drums, go to other system components or RC Waste system.
KEY WORDs:
l NRc K/A NRcimp Cog level Source Reference
!.ess Plan Obj #
Outline h00068K401 l4.1 NEMORY HEW ESAR-11 l CRC 134-1 b.0 k2G1 J
DATES: Modified; Saturday, March 14,1998 Used:
l STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
Asa %:
00 100 0 00 00 0.0 00 00 00 00 00 00 100.0 Time]
p(diff)l 1l rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol
I
~
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 51 l
=
The 4 major actions of EOP-2, Loss of Offsite Power are designed to:
A. Protect the condenser from overpressure, restore forced circulation, restore RCS pressure, and restore affected electrical buses.
v8. Protect the condenser from overpressure, verify shutdown sequencer loads operating, establish inventory control and restore affected electrical buses.
C. Restore affected electrical buses, maintain natural circulation, commence plant cooldown to shutdown cooling entry conditions and determine appropriate ERPIP actions.
D. Minimize inventory losses, isolate the affected steam generators, depressurize and cooldown to shutdown cooling entry conditions.
Correct answer is based on EOP2 basis and EOP2 procedure block steps, distractors are based on other EOP block steps mixed with EOP2 block steps.
KEY WoRDs:
NRC K/A NRcimp Cog level Source Reference Less Plan Obj #
Outline h00056K302 l4.7 IAEMORY EXAM BANK EOP2 Basis lSRO-201-2 h.0 k1G3 l
DATES: Modiried: saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total l
Responses:
o 3
o e
o o
o o
o o
o 3
i As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l d
p(diff)l 1l rpbl ol Values:1 l ol 2l ol 3 l ol 4 l ol l
i
/
(
r
I l
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 52
~52105S CDSTIATElf601
~
Which condition is requires entry into the LCO per Tech Specs for Containment isolation Valves in Mode 17 A. Pressurizing the safety injection tanks with nitrogen.
B. Filling the safety injection tanks from the RWT.
- 4. Hot leg sample valve, PS-5467-CV, fails open after completion of sampling.
D. Quench Tank vent. RC-400-CV, fails open after venting Quench Tank.
Correct answer is from Tech Specs, distractors are TS items that require administrative control, or no LCO action statement needed.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00069A201 l4.3 NEMORY EXAM BANK IrECH SPEC kRO7-1 b3 lT1G1 l
DATES: Moddied: Monday, March 16,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 1
2 0
o o
o o
o o
o 3
Asa %:
0.0 33.3 ss.?
o.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l o ssss7l rpbl os1l Values:1 l ol 2 l ol 3 l ol4l ol
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK r a 53 u
53.I_DSYNTlC 5RVI{sV7[liO1
~
~
Given the following:
- Unit 1 is in Mode 3, NOT and NOP
- Both SRW heat exchangers were cleaned last shift
- Alarm "11/12 SRW HX SRW OUT TEMP Hi" annuciates at 1C13
- CRO responds and reports that 11 SRW Heat exchanger outlet temperature reads 0
98 F and steady.12 SRW heat exchanger outlet temperature is normal
- CRO reports that 11 SW header pressure is 30 PSIG and 12 SW header pretsure is 20 PSIG q
As the CRS, you direct the CRO to take actions per the Alarm Manual. The CRO reports that adjustment of the output on 11 SRW heat exchanger SW control valve had no effect on lowering outlet temperature.
Select the direction required by you to respond to this condition:
A. Direct implementation of AOP 7A (Loss of SW) to determine if a SW system rupture exists.
l B. Direct implementalon of AOP 7B (Loss of SRW) to determine if a SRW system rupture exists, vC. Direct implementation of AOP 7A (Loss of SW) to determine if SW system flow blockage exists.
D. Direct implementation of AOP 78 (Loss of SRW) to determine if SRW system heat loads are excessive.
1 Correct answer is based on a stuck 1-SW-5210-CV, distractors are actions for other unrelated conditions.
author:REN I
I KEY WoRDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
outline l000062A101 l3.1 lAPPLIC-SRO HEW h0P 7A lCRo-202-7A l2.0 h1G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
e o
3 o
o o
n o
o e'
o 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 a. 0-0.0 0.0 0.0 100.0 Time l 3l p(diff)l 1l rpbl 0l Values:1 l 0l 2 I 0l 3 l 0l 4 l ol l
l w-_.
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 54
~ 4.TOSYNOC SRW(SWOO2 5
~
A rupture occurs downstream of 22 GRW Heat Exchanger SW control Valve, 2-SW-5212. What actions per AOP-7A (Loss of Salt Water) would allow for continued operation of the SW System?
L A. Manual start of 23 SW pump on 22 SW header.
VB. Lineup 21 SW header as an emergency overboard flowpath.
C. Lineup 22 SW header as an emergency overboard flowpath.
. D. Manual start of 23 SW pump on 21 SW header.
Correct answer is based on actions in AOP 7A for specified rupture conditions, distractors are incorrect design functions (22 SW header) or unrelated actions (23 SW pump starts),
author:REN
' KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000062A201 b.5 NEMORY EB-MODIFY lAOP 7A DRo-113-2 (7.0 Ir1G1 l
DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G l
'H I
J Omits Total Responses:
o 2
i o
o o
o o
o o
e 3
As a %:
0.0 ss.?
33.3 0.0 0.0 0.0 0.0 0.0 0.o _ 0.0 0. 0, 100.0 Time l 3l p(diff)l o.ssss7l rpbl o 3d Values:1l __
ol 2l ol 3 l ol 4 I ol l
I
EXAM BANK DATA SHEET Question #: CRO-113-2-5-21 Task #:
?
NRC Category (s) :
None CRIEF: Design Feature of the SW System KElfMORDS:'113 - SERVICE WATER AND MISCELLANEOUS STATION SERVICES QUESTION A rupture occurs downstream of 12 SRW heat exchanger salt water outlet valves.
What design feature of the saltwater (SW) system would allow for continued operation of the SW system?
A.
Automatic start feature of 13 SW pump on 12 header.
B.
Use of 11 SW header as an emergency flow path.
C.
Use of 12 SW header as an emergency flow path.
D.
Automatic start of 13 SW pump on low system pressure.
ANSWER-B.
REFERENCE DATA Point Value 1.00 M2dia #: CRO-113-2-5 Enabling Obj #: 7.1,7.2 LRequired Reft None Time: 2 min Question Type: MC
'K/A Catalog: ?
l Ref.: ?
I ' REVIEW l
' Authors =
Date
- Approved
Date:
lRavf.ewed by Program Development: No
-Rov.
1,-11/18/94 Page 1 of 1
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 55 551DSSDF CCVT061
~
~
~
Given the following:
Unit 1 is operating at 100% power.
Alarm 1C13 CC PP(S) DISCH PRESS LO, has actuated.
WHICH ONE (1) of the following RCP conditions requires the operator to trip both the reactor and the reactor coolant pump?
0 VA. Upper thrust bearing temperature is 197 F, B. Controlled bleed off flow is 2.0 gpm.
0 C. Guide Bearing temperature is 193 F.
0 D. Component cooling water outlet temperature at the RCP is 135 F.
Correct answer is trip criteria from AOP 7C, distractors are below trip criteria or not a trip criteria (CCW outlet temperature).
KEY WoRDS:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00026A206 h.1*
NEMORY l11/95 NRC h0P 7C NRO-113-5 l10.0 IT1G1 l
DATES: Modified: Saturday. March 14,1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 o
o o
o o
o o
o o
o 3
As a W 100.0I 00 00 00 00 00 00 00:
00 00 00 100.0 Time U p(diff)l 1l rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol
)
3
)
l l
l Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 57
- 57. LOSS OF INST AIR 001 During a loss of instrument air during MODE 1 operation, when would the reactor and turbine be tripped and EOP-0 implemented?
A. If instrument air pressure decreases to less than 40 psig AND in the opinion of the SS or CRS continued plant operation may cause equipment damage.
vB. If instrument air pressure decreases to less than 40 psig OR in the opinion of the SS or CRS continued plant operation may cause equipment damage.
C. If component cooling containment isolation valves, CC-3832-CV or CC-3833-CV, begin to go shut AND low flow alarms received on the RCPs.
D. If component cooling containment isolation valves, CC-3832-CV or CC-3833-CV, begin to go shut OR in the opinion of the SS or CRS continued plant operation may cause damage to RCPs.
Correct answer is based on AOP 7D actions, distractors are conditions that may effect a trip, but are not specific actions in AOP 7D.
KEY WoRDs:
NRC KIA NRCimp Cog level Source Reference Less Plan Obj ni Oatline
' OP 7D lCRO-202-7D h..1 IrsG2 l
h00065K308 b.9 NEMORY MM BANK A
DATES: Modified: Tuesday, March 17,1998 used:
STATISTICS:
A B
C D
E F
G H
I 8
. Omits Total Responses:
1 2
o o
o o
o o
e o
o 3
As a %:
33.3 s6.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l o.ssss?l rpbl o.381l Values:1 l ol 2 l ol 3 l ol 4 l ol I
m Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 58
_g.
Given the following:
- Unit 2 is in Mode 2, EOL and at ~2% Reactor power with Main Turbine tripped
- 21 SGFP running with 22 SGFP lined up in STBY
- AFW system aligned for normal operation 4
0
- The RO reports that Tc is lowering, approaching 515 F Tavg and Reg Group 5 CEAs have being withdrawn from 125" to raise power and restore RCS Tavg
- The CRO reports that 21 SGFP overspeed and tripped on high discharge pressure
- Shortly thereafter, the RO reports Unit 2 is in Mode 1 with.5 DPM SUR As the CRS, describe the action (s) required and basis for the decision:
\\
A. Direct the insertion of Reg group 5 to return to Mode 2, start up 22 SGFP.
B. Direct a reactor trip due to positive reactivity excusion from excessive CEA motion.
C. Direct the insertion of Reg group 5 to maintain power at 5%, start 23 AFW Pump.
vD. Direct a reactor trip due to a positive reactivity excusion from excessive cooldown.
The event is due to excessive cooldown similar to LER 95-003 (Swapping of SGFP steam supplies). The determination of the correct answer requires analysis of data to realize that CEA reactivity is insufficient to result is a.5 DPM SUR at 5% power and the l
uncontrolled cooldown from the inferred overfeed will result in an automatic trip at l
~14% power. Distractors are actions which are assume the cooldown effect is controlled. The describe d conditions require a SRO judgement to prevent an automatic trip.
author:REN KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline lDCEE06EA12 h.0 hPPLIC-SRO HEW
.IER 95-3 lCRO-202-3G l8.1 k1G2 l
DATES: Modified: Tuesday. March 17,1998 used; STATISTICS:
A B
c D
E F
G H
I J
Omits Total Responses:
o 1
o 2
o e
o e
o o
o 3
As a %:
0.0 33.3 0.0 66.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.o Time d p(diff)l o.66667l rpbl o.61l Values:1 l ol 2 l cl 3 l ol4l ol
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 59 5i9. LOSSIDF RRRI5EiCJ~001
~
l Given the following:
- Unit 1 in in Mode 5, shutdown for 7 days 0
- RCS pressure is 200 PSIA and temperature is 180 F
The RO reports that the ABO noticed that 11 LPSI pump outer pump bearing is overheating. Shortly thereafter, The CRO r9 ports that 11 LPSI pump tripped and the TBO reported that the breaker tripped on overcurrent and the relay can not be reset.
l Which of the following actions is the first to be taken to restore core cooling?
A. Establish core cooling by bleeding steam from the SGs.
vB. Reduce RCS pressure and line up CS pumps on SDC.
C. Start a HPSI pump, open the PORVs to cool the core via RCS blowdown to the containment.
D. Start a charging pump, open PORVs to cool the core via RCS blowdown to the containment correct answer is based on action in AOP 3B, distractors are subsequent actions if the correct answer is unsuccessful.
minor modification to question REN KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l
l000025K303 l4.1 NEMORY MM BANK h0P-3B lCRO-71 l16.0 lT1G2 l
l DATES: Modified: Saturday, March 14,1998 Used:
l STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
j As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel 1l p(diff)l 1l rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol I
l l
l 1
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 60
~ 60.T6SS dVRHK{sbC) 002 What action is required to prevent a common mode failure during SDC operation per Operating Instruction 3B7 vA. STBY Pump H/S in "PTL".
B. Recirc SDC header prior to initiating SDC.
C. Running 2 LPSI Pumps.
D. MOV Jog limits.
Correct answer is contained in the general precautions of OI-3B, distractors are items contained within the Ol that will not result in common mode failure of the SDC flow to the core.
author:REN KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000025G128 h.3 l COMP HEW lol38 lCRO-7-1 l16.9 lT1G2 l
DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 o
o o
o o
o o
o o
e 3
Asa %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Tirne U p(diff)l 1l rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol l
l L_ --- _
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 62
-~
6216SS SR NIS 001 Given the following:
- Unit 2 is in Mode 2 with Shutdown Rods ARO and Reg Rods ARI
- Channel B WRNI indication failed low, CRO recommends declaring it OOS Select one of the following which describes the condition allowed by Tech Spec:
A. Trip or Bypass affected RPS bistables within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, repair Channel B WRNI, continue Plant start up.
vB. Trip or Bypass affected RPS bistables within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, continue with Plant start up.
C. Repair Channel B WRNI within 1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, continue Plant start up.
D. Repair Channel B WRNI within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, continue Plant start up.
Correct answer is based on Tech Spec actions, distractors are variations of the time limits contained in theTech Specs for unrelated LCOc.
author.REN The question was modified from a sequence of actions to specific TS time limits.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000032K301 h.6 l COMP EB-MODIFY l TECH SPEC lCRO-571 l8.1 lT1G2 l
DATES: Modified: Tuesday, March 17,1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
1 2
o o
o e
o o
o o
o 3
Asa %:
33.3 66.7 0.ol 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Tirne]
p(diff)l 0.66667l rpbl o,3eil Values:1 l ol 2 l ol 3 l ol 4 l ol I
I t______________
EXAM BANK DATA SHEET-Question #: CRO-57-1-5-23 Task #:
020570201 NRC Category (s):
B,B CRIEF: Reactor Startup KEYWORDS: SD 57 - NUCLEAR INSTRUMENTATION SYSTEM QUESTION Using Tech Specs:
U-1 is in mode-2 performing a reactor startup, when channel A WRNI is declared inoperable.
Is it permissible to allow the reactor startup to continue?
A.
Yes, provisions of T.S.
3.0.4 are not applicable and no other actions.
B.
Yes, provisions of T.S.
3.0.4 are not applicable and l
bistables must be tripped or bypassed within one hour.
C.
No, mode 1 cannot be entered without LCO compliance.
D.
Yes, provided inoperable channel is repaired within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
ANSWER B,
I REFERENCE DATA Point Values 1.00 Mndia #: CRO-57-1-5' Enabling Obj #: 6.1.1-2 Required Ref: Tech Spec 3.3.1.1 Time: 2 min Question Type: MC l
K/A Catalog: 057K8.2,K8.4,K8.1,015000 GEN 5,3.3/3.8 l
Raf.: 55.41:10 55.43:2 l REVIEW I
1 Author:
Date:
Approved:
Date:
R3 viewed by Program Development: No 1
Rsv.
3, 10/03/96 Page 1 of 1 I
Tuesday, March 17,1998 @ 08:47 AM FINAL.BNK Page: 64 "64XO5S VlT L AdV0E
~~
Given the following:
Unit 1120VAC bus 1Y01 has been lost.
Operators are being directed per AOP-7J, " Loss of 120 Vital AC Power," to shut Letdown isolation Valves (CVC-515, 516).
Which one of the following is the reason for closing these valves?
A. They have no control indication available and placing them in the shut position is a conservative action.
v8. They will eventually lose control air because instrument air to containment is lost.
C. To isolate any potential leakage flowpath while power is lost.
D. To minimize transients on the loop charging inlet nozzles when power is restored.
Correct answer is based on actions in AOP basis, distractors are actions that do not account for the loss of lA.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Leas Plan Obj #
Outline l00057AA106 b.5 NEMoRY l11/95 NRC lAOP BASIS lCRO-202-7J l1.0 lT1G1 j
, DATES: Modiried: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses; o
3 o
o o
o e
o o
o o
3 As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.o Time l il p(diff)l 1l rpbl cl Values:1 l ol2l ol3l ol 4 l ol I
I e
I
.j l
I i
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 66
~~667Ei^IS'FE$DW TEiR 001 What happens on a transfer from High Power to Low Power Mode if SG level rises to greater than +20" during the transfer?
A. The transfer continues at the same rate.
j B. The transfer continues at 1/2 the original rate.
VC. The transfer is suspended, the MFV returns SG level to normal in Auto, and the BFV is held at current position.
D. The transfer is suspended, the BFV returns SG level to normal in Auto, and the MFV is held at current position.
Correct answer is based on the automatic actions of the DFWCS. Distractors are based on the reverse (transfer from low power to high power) transfer or incorrect transfer actions.
)
KEY WORos:
NRC K/A NRCImp Cog level Source Reference Less Plan obj #
Outline l000059K104 k4 IAEMORY MM BANK hLM MAN lCRo 103-1 l1.4 k2G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
0 0
3 0
0 0
0 e
0 0
0 3
As a Yo:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0l 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l4l 0l
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 67 N7 hiKl'N TURBTnN 001
~
Which one of he following conditions is indicated when the LOAD CHANNEL light on the Unit 2 turune control panel is lit?
vA. Failure in the Impulse Pressure feedback loop has occurred and the EHC system is in the IMP OUT mode.
B. Failure in the impulse Pressure feedback loop has occurred and the EHC system is in the TURBINE MANUAL mode.
C. Failure of the Turbine Actual Reference counter has occurred and the EHC system is in the TURBINE MANUAL mode.
D. Failure of the Turbine Actual Reference counter has occurred and the EHC system is in the IMP OUT mode.
Correct answer is based on system design, distractors are unrelated variations of other turbine control ciruits
- KEY WORDs:
' NRc K/A NRC imp Cog level Source Reference Less Plan Obj #
Outline b00045K439 l3.0 NEMORY l11/95 NRC lCRO 102-2 lCRO 102-2 l7.4 lT2G3.
l DATES: Modified: Saturday, March 14,19p3 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
2 1
o o
o o
o o
o o
o 3
Asa %:
66.7 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time U p(diff)l 0.6sss7l rpbl o.s1l Values:1 l ol 2 l ol3l ol 4 l ol i
A.
I Tuesday, March 17, !998 @ 08:48 AM FINAL.BNK Page: 68 687A'4TOMLDiffC d61
~
Given the following:
I
- Unit 2 is in Mode 3 with EOP-2 (Loss of Offsite Power) implemented
- Plant cooldown has commenced due to condensate inventory 0
0
- 21 loop Th 520 F and Tc 525 F 0
0
- 22 loop Th 535 F and Tc 520 F 1
l Which of the following is the required action for this condition?
A. Increase steaming from 22 SG via TBVs.
v8. Increase steaming from 21 SG via 21 ADV.
C. no action required, this is a normal condition.
D. Restart RCPs when power is available.
Correct answer is based on actions for an inverted d/t condition during natural circ, distractors are conditions which will not restore the normal d/t on 21 SG.
author:REN The question Th and Tc for 21 SG was modified to put the inverted d/t within 22 SG parameters to avoid confusion (comment from WPB) after question validation.
KEY WoRDs:
' NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline hCEA13G132 l3.8 l COMP-SRo EB-MODIFY EoP-2 lSRO-201-2 l7.0 lT1G1 l
DATES: Modified: Saturday, March 14,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
omits Total Responses:
o 3
o o
o o
o o
o o
o 3
As a %:
0.0 100.0 0.0 0.c 0.0 0,0 0.0 0.0 0.0 0.0 0.0 100.0 TimeU p(diff)l il rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol I
l i
EEAM BANK DATA SHEET Question #
SRO-201-2-1-09 Task #:
022010603 NRC Category (s) :
B,B BRIEF: Corrective Action KEYWORDS: 201 - EMERGENCY OPERATING PROCEDURES (EOP)
QUESTION An inverted delta T (Th less than Tc) is observed on the 12 S/G during the performance of EOP-2.
The best corrective action for this.condit;on is:
A.
Increase cooldown via the 11 S/G i.
B.
Initiate cooldown of 12 S/G l
C.
No action necessary, this is a normal occurrence D.
Restart RCPs ANSWER B.
REFERENCE DATA Point Value:
1.00 M dia #: SRO-201-2-1 Enabling Obj #: 7.0 Required Ref: None Time: 2 min Question Type: MC K/A Catalog: ?
Ref.: None REVIEW Author:
Date:
Approved:
Date:
R; viewed by Program Development: No Rnv. i 1,r'11/02/95 Page 1 of 1 1
-______.._-________-_-________a
1 Tuesday, March 17,1998 @ 08:48 AM
' FINAL.BNK Ps8e:69 697ADDLEkR INSf663
~~
Instrument Maintenance Shop plans to pefform troubleshooting activities on Reactor Regulating System (RRS) Channel X & Y per MN-1-110. RRS Channel Y is selected.
Trouble-shooting activities will begin on Channel X first. Which of the following actions may also be necessary?
A. Calculate and set the Power Ratio Calculator potentiometers per AOP-7H.
B. Fail the temperature instrument input to RRS.
- vC Remove Reactor Regulating NI inputs to the Digital Feedwater System.
D. Calibrate RRS Nis per 01-30.
Correct answer is based on Ol 7 actions, distractors are unrelated actions.
l KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline i
b00016K106 b.4 l COMP HEW lO1-7 lCRO-58-1 b.4 k2G1 l
DATES: Modified: Tuesday, March 17.1998 Used; STATISTICS:
A B
-C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
e 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 TimeU p(diff)l il rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol s
t
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 70
- 76. NUd[E iflR~5T dO4
~
Given the following:
- Unit 1 is at 100% power
- various alarms annunciate
- CRO reports that 12120 VAC Vital Bus (1YO2) indicates 0 volts at 1C24A Select the indication that is effected :
A. Channel B WRNI at 2C43 v'B. Channel B LRNI at 1C15 C. Channel A WRNI at 1C43 D. RRS Channel X LRNI at 1C05 Correct answer is based on design, distractors failure effects are wrong or not powered from 1YO2.
author: REN The stem and distractors were completely modifed KEY WORD 8:
NRC K/A NRCImp Cog level Source Reference Lass Plan Obj #
Outline l000015K201 b.7 NEMORY NB-MODIFY ES13 kRO 202-7J l1.0 j.'2G1 l
DATES: Modifed: Tuesday, March 17,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
Asa %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 n.o 0.0 0.0 0.0 Time l 1l p(diff)l ol rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol l
L____.
l EXAN BANK DATA SHEET Question #: CRO-57-1-5-05 Task #:
020570201 NRC Category (s) :
3,B CRIEF: NI Indication KEYWORDS: SD 57 - NUCLEAR INSTRUMENTATION SYSTEM QUESTION Which NI power indication is lost on a loss of 120VAC bus 2YO2?
A.
1C15 channel A wide range B.
1C15 channel B linear range C.
2C43 channel B aux excore wide range D.
1C43 channel B aux excore. wide range ANSWER D.
I REFERENCE DATA Point Values 1.00 M3dia #: CRO-57-1-5 Enabling Obj #: 2.1 Required Ref: None.
Time: 2 min Question Type: MC K/A Catalog: 057K1.01,K2.01,015000K2.01,3.3/3.7 Raf.: 55.41:2,7 55.43 REVIEW Author:
Date:
Approved:
Date:
RGviewed by Program Development: No Rav : '3,.10/03/96 Page 1 of 1
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 71
^ff~PLANTMRE 001
~
A fire is reported to the Control Room in Unit 1 12 foot turbine Building at 1000. The Fire Brigade responds at 1004 and reports that 11 SGFP pump oil has leaked out and ignited. Due to the oil leaking out, it flows down to the bowser room in the condenser
. pit and ignites the lube oil bowser. The fire in the 12 foot is extinguished at 1008 and the fire in the lube oil bowser room is extinguished 5 minutes later.
Select one of the following that describes the ERPIP Emergency Action Level (EAL) for this event:
VA. An EAL is not required because less than 15 minutes has elapsed since fire fighting
_ began.
B. An EAL is not required because non-safety related equipment is involved.
C. An EAL event is required because the fire burned for greater than 10 minutes.
D. An EAL event is required because the fire affected Appendix R equipment.
Correct answer is based on ERPIP 3.0, distractors are variations of time and equipment purpose.
author:REN concept came from 93NRC exam question to test on ERPIP EAL time.
KEY WoRDs:
NRC KIA NRCImp Cog level Source Reference Less Plan Obj #
Outline h00067K101 b.9 lAPPLIC-SRO NEW ERPIP lSRO-217 l1.0 lT1G1 l
DATES: Modified: Saturday, March 14,1998 Used; statistics:
A B
C D
E F
G H
I J
Orrjjg,j, Total Responses:
2 o
1 o
o o
o o
o o
a 3
As a %:
66.7 0.01 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 0.ssss rj rpbl 0.3n1l Values:1 l 0l2l 0l 3 l ol 4 ol l
l l
l r.
I
l l
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 72 72 PZR Ln95GiDNTff6i~0 2
~~
I Given the following:
- Unit 2 is in Mode 1 at 10.5% power
- Main Turbine startup in progress per OI-43A
- DFWCS in automatic l
- LT-100X Pressurizer level channel selected
- HS-100 is selected in "X / Y" position Describe the effect on the RCS if LT-110X fails due to a leak in the reference leg:
A. No change in Pressurizer level due to LT-110Y will compensate with HS.100 switch position.
B. Indicated Pressurizer level will decrease as Letdown goes to maximum exceeding Charging pump capacity.
v C. Actual Pressurizer level will decrease as Letdown goes to maximum, PZR Backup Heaters energize.
D. Actual Pressurizer level will increase as letdown goes to minimum and backup Charging pumps start.
Correct answer is based on design, distractors are permutations of wrong actual le'iel i
response or wrong component actions.
author:CCZ and REN KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00011A103 h.2 kOMP HEW ESAR-7 NRO 107-1 l1.0 k2G2 l
DATES: Modified: Monday, March 16,1998 used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
As a %:
0.0 0.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Time l 1l p(diff)l olrpbl ol Values:1l ol 2l ol 3 l ol 4 l ol
g:
/~
Tuesday, March 17,1998 @ 08:48 AM '
FINAL.BNK ~
Pagei73
~73 PZRTSVEL MALF 001
~
~
Given the following:
Reactor power is at 100%
' A transient has caused pressurizer level to DECREASE 14 inches below the programmed level.
The Pressurizer Level Control System is in AUTOMATIC.
The Charging Pump operational mode selector switch is in the "13 + 11" position.
WHICH ONE (1) of the following describes the response of the Pressurizer Level Control System?
A. Charging pumps 11,12, and 13 will be running and letdown flow will be isolated.
B. ONLY the 13 charging pump will be running and letdown flow will be isolated.
C. ONLY charging pumps 12 and 13 will be running with letdown flow at minimum.
- 4. Cherging pumps 11,12, and 13 will be running with letdown flow at minimum.
Correct answer is based on FSAR description, distractors are variations on charging pump effects 'and isolation of letdc.wn, which does not occur.
KEY WORDs:
NRc K/A NRCImp Coglevel Source Reference Less Plan Obi #
Outline b00028A102 l3.4 MEMORY l11/95 NRC ESAR-7 lCRO-58-1 l4.1 k1G3 l
DATES: Modified: Tuesday, March 17,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o 3
o o
o o
o o
o 3
Asa %:
- 0. o '
O.o 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel il p(diff)l il rpbl ol Values:1 l ol2l ol 3 l ol4l ol
-w
_----------------_---,------u----
_..--,.-az___e_
w_a__
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 74
~"N.~P'ZR PFfE5S MALF 601
~
~
l Given the following conditions:
- Unit 1 at 80% power
- PZR backup and proportional heater control in auto
- 1-HS-100 (PZR pressure control) in the "Y" position
- 1-HS-100-3 (PZR htr cutoff) in the "X+Y" position
- 1-PT 100Y fails high l
Select the expected plant response prior to any Operator action being taken:
A. Letdown control valves will open due to common mode failure effect.
- 4. PZR heaters will deenergize and spray valves will open.
C. PZR heaters are unaffected and spray valves will open.
D. PZR heaters will deenergize and spray valves are unaffected.
Correct answer is based on FSAR description, distractors are incorrect system response or unrelated effect (tJD CVs open).
authorREN KEY WORDs:
NRC K/A NRCimp Cog level Source Roference Less Plan Obj #
Outline lD00027K203 l2.8 l COMP kB-MODIFY ESAR-7 lCRO-62-1 h.0 lT1G2 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
i Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl ol Values:1 l ol2l ol 3 l ol 4 l ol 1
l
I EXAM BANK DATA SNEET l
Question #: CRO-62-1-3-42 Task #:
020050330 NRC Category (s):
None CRIEF: PT-100X fails high KEYNORDS: SD 62 RCS INSTRUMENTATION QUESTION Given the following conditions:
1)
Unit 1 at 100% power 2)
HS-100 (PZR Pressure Control) in the X position 3)
HS-100-3 (PZR Htr cutoff switch) in the X+Y position 4)
PT-100% fails HIGH Assume NO operator action Explain plant response, including operation and setpoint of any cutomatic actions.
[3. 0]
ANSWER-PZR heaters will de-energize and the spray valves will open (1.0).
The plant will trip cn TM/LP(0.5) variable setpoint, minimum 1875 PSIA (0.5) i REFERENCE DATA Point Value:
3.00 M;dia #: CRO-62-1-3 Enabling Obj #: 6.0 Rsquired Ref: NONE Time: 5 min Question Type: ES K/A Catalog: 005K3.02,000028 GENS,3.1/3.2 Raf.: 55.41:7,10, AOD 4A, ICO6 E-33 REVIEN Author:
Date:
Approved:
Date:
R3 viewed by Program Development: No R3v.
1, 07/30/96 Page 1 of 1
= _ - _ _ _ _ = _ _ _ _ _
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK rage: 75 76.~PZWREU5F7QT dO1
{
~~
Bleed and feed operations to cool the Unit 1 Quench Tank have just been completed.
Given the following indications of the Quench Tank parameters:
1)
Pressure 3 psig 0
2)
Temperature 105 F 3)
Level 23.5 inches Determine if any off normal conditions exist.
A. All parameters normal.
B. Pressure is too low.
C. Temperature is too low.
- 4. Level is too low.
Correct answer is based on the procedural guidance in 01-1B, distractors are parameters in the normal range.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000007A101 b.1 NEMORY NB-MODIFY lOl-1B NRO 5-2 l15 k2G3 l
DATES: Modified: Monday, March 16.1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o 3
o o
o e
o o
o 3
As a %:
0.0 00 00 100.0 00 00 00 00 00 00 00 100.0 TimeU p(diff)l il rpbl ol Values:1 l ol 2 l ol3l ol 4 l ol i
EXAM BANK DATA SHEET Question #: CRO-5-2-3-38 Task #:
020050302 NRC Category (s):
B,B ERIEF: Data on Quench Tank KEYWORDS: SD 5 - RCS l QUESTION Given the following data on the Quench Tank:
1)
Pressure 5 psig l
2)
Temperature 105'F 3)'
Level 32 inches Analyze the quench tank parameters to determine if any off normal conditions exist.
A.
No concerns all parameters normal B.
Pressure is too high C.
Temperature is too high D.
Level is too high ANSWER D.
REFERENCE DATA Point Value 1.00 Madia #: CRO-5-2-3 Enabling Obj #: 16.1 Required Ref: None Time: 2 min Question Type: MC K/A Catalog:.005K5.08,007000K1.03,3.0/3.2 Raf.: 55.41:10'
-55.43
/
OI-1B REVIEW
. Author:
Date:
)
i Approved:
Date:
Roviewed by Progr&m Development: No Rav. 00, 07/16/92 Page 1 of 1 I
i i
I i
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 76
~76TRXbl4 TION CdRh(DL 001 The setpoint for the normal liquid effluent monitor is based on assumptions in the Offsite Dose Calculation Manual (ODCM).
Which one of the following would require the Plant Computer activity setpoint to be decreased?
A. Decrease in actual release rate from 120 gpm to 90 gpm.
B. Decrease in operating circ water pumps from 6 to 5.
vC. Decrease in monitor background radiation level.
D. Decrease in Bay level.
Correct answer is based on setup conditions for a liquid waste discharge, distractors are conditions which have no effect on the conditions specified in the permit.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan obJ #
outline
' h0002.3.11 l3.2 NEMORY l4/93 NRC lCRO 122-1 lCRO 122-1 k.0 lT3 GEN l
DATES: Modified: Monday, March 16,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Iomits Total Responses:
o o
3 o
o o
o o
o o
o 3
Asa %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl ol Values:1 l ol 2 l ol3l ol4l ol l
t Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 78
- 78. RCP MALFUNCTION 001 Given the following:
- Unit 1 completed heatup to Mode 3 at NOT and NOP on this shift
- 1C06 alarm E-59 "12A RCP SEAL / TEMP Hl/ PRESS" annunciated
- CRO reports CCW temperatures, pressures and head tank level normal at 1C13 l
- RO reports 12A RCP temperatures have slowly increased during the heatup of the RCS, parameters are normal for all other RCPs Select the action required for the apparent reason for the 12A RCP alarm:
A. Verify CC 3832 and 3833 open,one CC Containment isolation CV is shut.
B. Start a second CC pump, RCW evaporator in operation.
v'C. Check CC flow to 12A RCP, additional flow is needed for RCDT HX cooling.
D. Check RCS leakrate,12A RCP integral heat exchanger has a CCW leak.
Correct answer is based on the design of 12A RCP CC supplying both the RCP and RCDT heat exchanger. Distractors are unrelated cause and effect for this unique design difference for 12A RCP which would effect all RCPs.
author:REN KEY WoRDs:
NRC K/A NRcImp Cog level Source Reference Less Plan Obj #
Outline l000015K302 h.1 l COMP HEW kM 12ARCP lCRO-106-1 b.0 k1G1 l
DATES: Modified: Tuesday, March 17,1998 Used; STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
o 3
Asa %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0l 0.0 100.0 Time l il p(diff)l 2 l rpbl ol Values:1 l ol2l cl 3 l ol 4l ol
_ - _ - - _ _ _ _ - - _ _ _ _ _ = - -. _ _ - - - - - - - _ - _ _ _ -
Tuer, day, March 17,1998 @ 08:48 AM FINAL.BNK Page: 81
~~ 17REACVDR 660LANTWOO1 8
~
~
Which one of the following annunciator alarms also indicates the presence of an interlock which will prevent the start of 22A RCP7 t
A. " OIL RESVR LEVEL LO" 4.' " OIL LIFT PP PRESS LO" C. "CC TEMP Hl' D. "RCP BLDOFF FLOW Hl/LO" Correct answer is based on Alarm Manual response and RCP design, distractors are variations of unrelated RCP alarms.
l KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan' Obj #
Outline b00003K113 l2.5 NEMORY lW93 NRC l ALM MAN DRO 106-1 b.0 k2G1 l
. DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses
'o 3
o o
o o
o o
o o
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l
~ ilrpbl ol Values:1 l ol2l ol 3 l
'ol4l ol
l Tuewlay, March 17,1998 @ 08:48 AM FINAL.BNK Page: 82
~~527 RF.ACT6R CdDiXRTWOO2
~~
Given the following trend & alarms on the 12B RCP with Unit 1 at 100% power:
ANALOG TIME VIBRATION ALARMS 0000 14 mils 0100 18 mils - Alert "RCPs Vibration" alarm 0115 30 mils - Danger "RCPs Vibration" alarm 0130 36 mils 0135 0 mils What action should be taken?
A. Commence an expeditious plant shutdown, and then secure 12 B RCP.
v8. Trip reactor, implement EOP-0, perform Reactivity Control and secure 12 B RCP.
C.12B RCP must be secured within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with GS-NO concurrence.
D. Immediately Contact Performance Testing Unit and GS-NO, evaluate vibration data.
Correct answer is based on Alarm rnanual response, distractors are based on actions which ignore the " danger" alarm setpoint for vibration.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline lD00003A203 l3.1 l COMP EB-MODIFY hlM MAN lCRO 106-1 b.0 k2G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)I il rpbl ol Values:1 l ol2l ol3l ol4l ol
EXAM BANK DATA SHEET Question #: CRO-106-1-2-12 Task #:
020050331 NRC Category (s) :
B,B BRIEF: Action to be Taken KEYWORDS: 106 - REACTOR COOLANT SYSTEM CONTROL BOARD QUZSTION Given the following trend on the 11B RCP:
TIME VIBRATION ALARMS 0000 14 mils Alert - RCP vibration alarm 0100 16 mils Danger - RCP vibration alarm 0115 30 mils 0130 40 mils 0145 44 mils What action should be taken?
A.
Conduct a plant shutdown, and then secure RCP 11B B.
Trip reactor and turbine, and then secure RCP 11B C.
RCP 11B must be secured within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D.
Perform an Engineering Evaluation for continued operation.
ANSWER B.
REFERENCE DATA Point Value:
1.00 Mcdia #: CRO-106-1-2 Enabling Obj #: 8.0 l
Required Ref: None Time: 2 min Question Type: MC K/A Catalog: 005Kl.07,K5.02,K6.03,K6.04,000015EK3.03,3.7/4.0 Ref.: 55.41:10 55:43:5
/
CCI-302 REVIEW Author:
Date:
Approved:
Date:
Raviewed by Program Development: No
-Rtv.
1, 02/09/98 Page 1 of 1
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK.
Page: 83
" 53 ME DT6R COOLANT sYS 001
~
During a large break LOCA fuel cladding temperatures sharply rise within the first 20 seconds. Why does this occur? -
A. MTC and doppler add positive reactivity to the core, raising power and temperature.
- 4. RCS pressure drops to saturation pressure and the fue! rods are blanketed with -
steam.
C. RCPs trip due to SlAS and CIS and this results in no driving head for flow.
D. LPSI and SIT flows are blocked by the voiding in the reactor vessel downcomer region.
Correct answer is based on the immediate effects of a LOCA on the fuel temperature, distractors are incorrect effects on reactivity or flows.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b00002K302 l4.5 IAEMORY EXAM BANK lSRO 201-5 BRO 201-5 l1.3 lT2G2 l
DATES: Modifed: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 2
o 1
o o
o o
o o
o 3
Asa %:
0.0 66.7 0.0 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(difrjl o.66ss?l rpbl o.3s1l Values:1 l ol2l ol 3 l ol4l ol l
I 1
l
f Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 84
- 84. RE^dT6R PRDTE6TidR ~601
~
~
You have just completed watch relief as Unit 1 CRS. The off-going CRS had related two occasions during the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> where RPS Channel B Delta-T power had spiked high causing "Hi POWER RESET DEMAND" alarms. A short time later you receive the following alarms and indications from Channel A RPS:
HI POWER TRIP RESET DEMAND PROT CH TRIP POWER LVL HI CH PRE-TRIP l
(NOTE: Above alarms are annunciating, then clearing every 5 seconds) l Channel A RPS T/U #1 is tripped Delta-T power is steady N.I. power is steady l
Upper and lower linear range power is steady Th and Tc are steady
^ What actions would you direct?
A. Remove the three spurious alarm annunciators from service, no further action is necessary.
- 4. Bypass Channel A RPS T/Us 1,2,7,8 and 10 per Tech Spec C. IM troubleshoot the RPSICP drawer to determine what is malfunctioning.
D. Document problem on an lasue Report, no further action is necessary Correct answer is based on Tech Spec actions for an inoperable Channel A RPS from inferred erratic outputs, distractors are variations on actions assumming no operability concern.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline b00012A205 l3.2 l COMP HEW k.S. LCO lCRO-59-1 ba2.13.1 k2G2 l
DATES: Modified: Saturday, March 14,1998 Used:
statistics:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
As a W o.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time U p(difr)l il rpbl ol Values:1 l ol 2l ol 3 l cl 4 l ol l
1 l
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 86 75TjdTRiVSYABlLT601
~
l U-2 is operating at 100% with RCS boron concentration at 965 ppm when a reactor trip (no SlAS) occurs. The RO observes that 4 CEAs do not have their rod drop light energized but 3 of the 4 CEAs have their LEL (green light) energized.
Per EOP-0, what action (s), if any, are required for Reactivity Control Safety Function?
VA Monitor for drop in reactor power, a negative SUR and borate to at least 1165 ppm.
B. Monitor for drop in reactor power, a -1/3 DPM SUR and make a note to inform the CRS of CEA indication problems.
C. Inform CRS that Reactivity Control Safety Function is complete and you are checking CEAPDS to determine status of all CEAs.
D. Monitor for drop in reactor power, a negative SUR and borate to at least 2300 ppm.
Correct answer is based on EOP 0 specified actions, distractors are based on incorrect communication responses or final boration of RCS (1 stuck CEA).
KEY WORDs:
NRC K/A NRcimp Cog level Source Reference Less Plan Obj #
outline DCEE02EA22 l4.0
)AEMORY EXAM BANK EOP0 BASIS bro-201-0 h.0 lT1G2 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
2 o
o 1
o e
o o
o o
o 3
As a %:
66.7 0.0 0.0 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 2l p(diff)l o.ssss7l rpbl o.381l Values:1 l ol 2 l ol 3 l ol4l ol
= -_--
Tuesday, March 17,1998 @ 08:48 AM -
FINAL.BNK Page: 88 887SCfC 00'i
~
~
~~
A loss of instrument air has occurred while on SDC with purification in service. What effect does this have on valve position of SI-306 (SDC Flow Control), SI-657 (SD TemplFlow Cont.), and CVC-500 (VCT Diversion Valve)? (IN ORDIER)
A. Falls OPEN, fails OPEN, and fails to WPS position.
B. Falls CLOSE, fails CLOSED, and fails to WPS position.
vC. Fails OPEN, fails CLOSED, and fails to VCT position.
j D. Fails CLOSED, fails OPEN, and fails to VCT position.
l Correct answer is based on fail positions of the 3 valves, distractors are permutations on the resultant fait positions.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline lD00005A402 l3.1 NEMORY MM BANK h0P7D hRO7-1 l29.0 lT2G3 l
DATES: Modified: Tuesday, March 17,1998 Used:
~~
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o e
3 o
o o
o o
o o
o 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time d p(diff)l 1l rpbl ol Values:1 l ol 2 l cl 3 l ol4l ol l
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 89
- 89. SERVICE WATER 001 Following a Unit 2 reactor trip from 100% power the following plant conditions exist:
Pressurizer Pressure 800 psia Containment Pressure 4.5 psig
~
All automatic systems have acuatated as designed Which one of the following describes the automatic response of the Component Cooling (CC) System based on these conditions?
A. Only the CC Heat Exchanger Salt Water (SW) outlet valves shut.
Both Shutdown Cooling (SDC) Heat Exchanger CC outlet valves open.
- All CC pumps start.
B. Only the CC Heat Exchanger Salt Water (SW) inlet valves shut.
CC Containment Isolation valves shut.
Both 21 and 22 CC pumps start.
Both SDC CC outlet valves open.
CC Containment Isolation valves shut.
CC supply to Liquid Waste Evaporators shuts.
Both 21 and 22 CC pumps start.
D. Both CC Heat Exchanger SW inlet and outlet valves close.
Both SDC CC outlet valves open.
CC Containment Isolation valves shut.
CC supply to Liquid Waste Evaporators shuts.
All CC pumps start.
Correct answer is based on FSAR description, distractors are 1 incorrect component response on SW valves or pump response.
KEY WORDs:
NRC K/A NRCImp Cog level Source Referenca Less Plan Obj #
Outline bOOO76A302 b.7 NEMORY l4/93 NRC ESAR-7 DRo 113-5 b.0 lr2G3 l
DATES: Modified: Tuesday, March 17,1998 Used:
sTATisTK:s:
A B
C D
E F
G H
I J
Omits Total Responses:
0 0
3 0
0 0
0 0
0 0
0 3
Asa %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l il rpbl 0l Values:1 l 0l 2 l 0l 3 l 0l4l 0l l
l<
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 90 l
9'075FF66IOLING 002 The most serious failure for the Spent Fuel Pool Cooling System is the loss of SFP j
l Water. What feature of the system is designed to prevent this?
A. Piping interconnection to either RWT.
B. Cask Handling Crane modified to meet single failure criteria.
C. Two channels of remote level indication with alarm function.
vD. SFP pipe connections with siphon breakers, above the water level in SFP.
I Correct answer is based on the FSAR description, distractors are design features that are not credited by FSAR loss of SFP water.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00033G128 l3.3 NEMORY HEW ESAR-9.4 hRO-113-4 l1.0 k2G2 l
DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total k
Responses:
o o
o 3
o o
o o
o o
o As a %:
0.0 0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.o f 0.0 100.0 TimeU p(diff)l 1l rpbl ol Values:1 l ol 2l ol 3 l _
ol 4 l ol l
l I
l
Tuesday, March 17,1998 @ 08:48 AM FLN \\L.BNK Page:91
- 91. SFP COOLING 003 Given the following:
- Unit 1 is defueled and Unit 2 is in Mode 5 l
- Alarm "SFP TEMP Hi" annunciated at 1C13 Select the cooling mechanisms in preferred order per AOP 6F (SFP Cooling 1
Malfunctions):
A. Line up Unit 1 SDC to SFP system, place second SFP cooler in service, add makeup to SFP as water boils off, vB. Place second SFP cooler in service, line up Unit 1 SDC to SFP system, add makeup to SFP as water boils off.
C. Line up Unit 2 SDC to SFP system, place second SFP cooler in service, add makeup to SFP as water boils off.
D. Place second SFP cooler in service, line up Unit 2 SDC to SFP system, add makeup to SFP as water boils off.
Correct answer is based on AOP 6F actions, distractors are permutations in the wrong order or prohibited lineup (Unit 2 SDC).
author:REN The question was developed as an extra question.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline l000033K303 h.3 l COMP HEW hop 6F lCRO 113-4 l4.0 Ir2G2 l
DATES: Modified: Monday, March 16,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 l
Time l il p(diff)l ol rpbl ol Values:1 l ol 2 l ol 3 l ol4l ol l
l 1
l i
{
l i
l L
l l
\\
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 93
~ f~SsiX~LL BR$4KLdCA 001 9
The plant has experienced a small break LOCA. Using the following plant conditions calculate the subcooled margin.
l 0
Core exit thermocouple read 600 F.
All RCPs are stopped.
Pressurizer levelindicates 300".
0 Thot indicates 590 F.
0 Tcold indicates 560 F.
l Pressurizer pressure indicates 1545 psia (lowest channel) 0 A. 5 F subcooled 0
v8. 0 F subcooled.
0 C. 5 F above saturation temperature.
0 D.10 F above saturation temperature.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h00009K102 l4.2 NEMORY EXAM BANK EOP ATTC lSRO-201-5 k.0 lT1G2 l
DATES: - Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
e o
o o
o 3
Asa %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time U p(diff)l 1l rpbl ol Values:1 l ol2l ol3l ol 4 l ol l
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 94
- 94. SMALL BREAK LOCA 002 There are 3 basic types of LOCAs the safety injection system is designed to compensate for. However, operator response must vary depending on the actual size of the break. If RCS pressure has reduced to 1320 psia strictly due to a LOCA event the focus of operator actions should be to:
A. verifiy that SIAS, CIS and CSAS have properly initiated and realign safety injection to a recirculation mode upon receipt of a RAS.
1 VB. establish and ma:ntain core and RCS heat removal via forced or natural circulation.
C. establish and maintain natural circulation flow while adjusting HPSI flow to provide j
inventory control.
i D. maximize charging, throttle SRW flow to CACs, and monitor Core and RCS heat j
removal for further degradation.
I Correct answer is based on EOP 5 basis and procedural guidance, distractors are variations of unrelated basis which do not meet ESFAS setpoints or ignore expected system response.
KEY WoRDS:
NRC K/A NRcimp Cog level Source Reference Less Plan Obj #
Outline l000009K203 h.3 NEMORY EXAM BANK hops BASIS lSRO-201-5 h.0 k1G2 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total j
Response 4:
0 1
0 2
0 0
0 0
0 0
0 3
Asa %:
0.0 33.3 0.0 66.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 0.33333l rpbl 0.991l Values:1 l 0l 2l 0l 3 l 0l 4 l 0l
Tuesdupfarch 17,1998 @ 08:48 AM FINAL.BNK Page: 95 j
- 95. STATIO.N AIR 001 As the Plant Watch Supervisor you are conducting a tour of the Turbine Building.11 Plant Air Compressor is in service and you notice the following indications on the microcontrollers:
j Alarm light is blinking
" SURGE" displayed in the function display What direction from the PWS, if any, is necessary?
A. Depress the ACK/ RESET pushbutton twice.
)
B. No action is required, j
- 4. Place the MODE OF OPERATION handswitch to UNLOAD.
D. Place the MODE OF OPERATION handswitch to MODULATE.
Correct answer is based on OI-18A response, distractors are unrelated actions for the l
specified condition.
KEY WoRDs:
NRC K/A NRCImp Cog level Scurce Reference Less Plan obj #
outline h00079G127 k.9 l COMP HEW lOl-18A lCRO-113-7 l1.0 lT2G2 l
DATES: Modified: Tuesday. March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
omits Total Responses:
1 o
i 1
o o
o o
o o
o 3
As a %:
33.3 0.0 33.3 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 3l p(diff)l o.33333l rpbl -o.381l Values:1 l ol 2 l ol 3 l ol4l ol
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 97 97, STMfD5RdMTDR 002
{
Given the following:
]
- Unit 's is at 10% power with a Plant startup in progress
- Alarm "12 SG CONTR CH LVL" annunciated at 1C03
- RO reports that 12 SG level by 1-LT-1106 indicates +63.5" and remaining SG level indications are at 0" Describe the effect on the Plant and action required:
A.12 Bypass Feedwater Valve will go SHUT requiring a manual Reactor trip and implementation of EOP 0.
vB.12 Bypass Feedwater Valve will continue to maintain level, the downcomer selector switch at 1C36 should be placed in the LT-1106 failure position to provide LT-1121 input to the control channel indication.
C.12 Byg.ss Feedwater Valve will go SHUT, requiring manual operation by placing its associated handswitch in the BYPASS FAIL position.
D.12 Bypass Feedwater Valve will continue to maintain level, a manual transfer from LOW to HIGH power of the DFWCS will be required for 12 Feed System.
Correct answer is, required action for failure of LT-1106 (CPU sensed failed output and shifted control to LT1121). Distractors are permutations on incorrect BFV action author: REN the question was developed as new due to STM GENERATOR 002 was used in Audit Exam for CRO 96.
KEY WORDs:
l NRc K/A NRCImp Cog level Source Reference Less Plan Obj #
outline lD00035A203 h.6 hPPLIC HEW lCRO 103-1 lCRO 103-1 l1.9 Ir2G2 l
DATES: Modified: Monday, March 10,1998 Used:
STATISTICS:
A B
c D
E F
G H
I J
Omits Total Responses:
o o
o o
o o
o o
o o
o o
As a %:l 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Time l 1l p(diff)l ol rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol L
l:
Tuesday, March l'7,1998 @ 08:48 AM FINAL.BNK Page: 98
- 98. STM LINE RUPTURE 001 With Unit 2 at 850 MWE, all MSR's in service, a reactor trip occurs. What operator action (in the Control Room) must be taken to prevent an overcooling of the RCS per EOP-07 A. Press "Close Valves" button on the turbine control panel.
- 4.. Press " Reset" button on the MSR control panel.
C. Observe that MSR source valves go shut.
D.~ Press the "MSR Trip" button Correct answer is based on Unit 2 specified actions for EOP 0, distractors are variations of Unit 1 features or unspecified Unit 2 features.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline bCEE06EK22 l4.2 NEMORY-bXAM BANK BOP O BRO-201-0 l1.0 lT1G1 l
DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
'o o
o 3
As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l il p(diff)l ilrpbl 0l Values:1 l 0l 2 l 0l 3 l 0l4l ol l
l l
)
1 i
_.U__._._._._
.m__m-__._
m___
]
Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 99
~99."SMUNE RilPTURE 602
~
~
~
Given the following:
An Excessive Steam Demand Event (ESDE) has occurred and BOTH steam generators are affected.
WHICH ONE (1) of the following parameters should be used to determine the steam generator to be isolated?
A. The steam generator with the highest Teold.
B. The steam generator with the lowest steam pressure.
C. The steam generator with the lowest AFW flow.
D. The steam generator with the highest level.
Correct answer is specified by EOP4, distractors are incorrect parameters.
KEY WoRDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outline lDOCE05EA21 l4.0 NEMORY l11/95 NRC EOP4 lSRO-2014 h.0 lT1G1 l
DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
e 3
Asa %:
00 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time d p(diff)l il rpbl ol Values:1 l ol 2 l ol 3 l ol4l ol
l Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK Page: 100
~I66.~5s ~STE'GXS 001 l
~
As CRS, the CRO reports that the ABO noticed the Waste Gas Surge Tank pressure had lowered from ~4 PSIG to O PSIG. The CRO is concerned that if a vacuum is 2
reached, air could mix with the H and result in an explosive mixture.
What direction is appropriate for the CRO to verify:
2 vA. N Control Valve opens at 0 psig.
B. Waste Gas Surge Tank relief to Waste Gas header OPEN.
C. Waste Gas Discharge Isolation Valves 0-WGS-2191-CV and 2192-CV OPEN.
D. Waste Gas Surge Tank drain trap aligned to Waste Gas Compressors.
4 Correct answer is based on Alarm manual response, distractors are incorrect design features.
author: REN Modified to add system equipment as new distractors, changed stem after validation.
KEY WORDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outline lD00071G128 h.3 l COMP EB-MODIFY l ALM MAN lCRO 134-1 b.0 IT2G1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total l
Responses:
o 2
0 1
0 o
o o
o o
o 3
l Asa %:
0.0 66.7 0.0 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timo d p(diff)l ol rpbl ol Values:1 l l 2l ol 3 l ol 4 l ol
,o l
EXAM BANK DATA SHEET Question #: CRO-219-1-0-02 Task #:
0214A0202 NRC Category (s) :
B,B
'CRIEF Waste Gas Surge Tank KEYWORDS: 219 - CHEMISTRY PROCEDURES QUESTION What prevents a vacuum from being drawn in the waste gas surge tank?
.A.
Nitrogen control valve opens at 0 psig B.
Nitrogen control valve opens at 1 psig C.
Waste gas compressors automatically stop at 0 poig D.
Waste gas compressors automatically stop at 1 psig ANSWER A.
j REFERENCE DATA Point Value 1.00' l
M2dia #: CRO-219-1-0 Enabling Obj #: 1.0 i
-Raquired-Ref: None Time: 2 min Question Type: MC K/A Catalog: 14AK1.04,071000K4.01,2.6/3.0 Rof.: 55.41:13 55.43
/
SD-14A
' REVIEW Author:
Date:
- Approved:
Date:
l Rsviewed by Program Development: No
'R;v.,30, 08/06/92 Page 1 of 1
- O
p.
weaisy, Med 17, l'99s e os,W7 As _.
'.Page!1.0' FINAL.BNK ~.
- 10. CONDUCT Of OPS 001 Which condition would require notification of the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of occurrence?
A. Performance of an STP that does not result in discharge to the RCS.
v9. SlAS initiation due to operator error which did not result in ECCS discharge to the C.
or initiated manual reactor trip during a preplanned physics test.
D. Pressurizer spray valve opening due to high RCf3 pressure.
Correct answer is specified in the admin procedure, distractors are elements of exceptions to the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reporting requirement or rxin-reportable conditions KEYWORDS:
NRC K/A NRCimp Coglevel Source Reference Laos Plan Old 8 Ouane hrmn,1.1 b.8 b4EMoRY kXAM BANK M 1101 b 71 b.0 k3 GEN l
DATES: N: Frkley, Med 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
omils Total Responses o
1 2
o o
o o
o o
o o
3 Ase %:
0.0 33.3 66.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel il p(diff)l 0.33333l rpbl 0.3s1l Values:1 l 0l 2 l ol 3 l ol4l Ol I
i i
I i
l i
j l
\\
^
Tuesday, March d,1998 @ 08:47 AM
. FINAL.BNK :
Pase: 13 l
- 13. CONDUCT OF OPS 004 Unit 1 core omond is scheduled to begin within the next week. The Unit 1 Refueling Machine shall be demonstrated operable by performing the required surveillance within
- -hours prior to the start of fuel movement, including demonstrating that the automatic overload cutoff functions when main hoist load exceeds pounds.
vA.73,3000 B. 72,1550 C.24,3000 D.24,1550 Correct answer is specified by Tech Specs, distractors are related RFM overload setpoints not specified by TS (1550 points) or wrong periodicity (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).
KEYWORDS:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outhne b0002.1.10 b.9 l COMP M
WCHSPEC lCRO-1134 l4.0 MN l
DATES: Modsed: Friday, March 13,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses 3
o o
o o
o o
o o
o o
3 As a %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel 2l p(dif0l 1lrpbl ol Values:1 l ol 2 l ol3l ol 4 l ol
,s'
- j*
i__1__________
-'. ~...
,,.. r.,
.,,. :..;. 3
, 7 :.".
'FBIEBNK-res.: 14
~
Tusaday,Merch 17,19Ng es:47 AM
- 14. CONDUCT OF OPS 005 You are the Unit 2 CRS and you have directed the CRO to shift EHC Pumps to allow the System Engineer to observe pump performance. The Unit 2 Turbine Building Ope,T.w, System Engineer, and Mechanical Maintenance Supervisor are standing by at the EHC Unit. What additional actions, if any;.are required by Operation's prodtdures?
A. Shift EHC Pumps as requested, no additional action required.
B. Announce start of the EHC Pump over the plant page prior to EHC Pump start.
C. Have TBO evacuate unnecessary personnel from the area around the EHC Pumps.
Correct answer is specified by admin procedure, distractors contain incen4',/ actions Or no actions.
MEYlllf0RDs:
NRC KAA NRCimp Coglevel source Reference Lees Plan Obj #
Ouane bOOO2.1.26 l2.6 l COMP M
5 1-100 DRO 204-1 I7.0 Ir3 GEN l
1 DATES: Modited: Fddey, Mardi 13,1696 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses.
o o
1 2
o o
o o
o o
o 3
Asa %:
0.0 0.0 33.3 ss.7 0.0 0.0 o.0 0.0 0.0 0.0 0.0 100.o Timel sl p(dill)l o.scss?l rpbl o.stl Values:1 l cl 2l ol 3 l ol 4 l ol m
W'"
.y.-
r d 'y,venis n'7,1,9s e os:4i As FkNNBNK,;.
. Pese:is
- 18. CONTAINMENT PURGE 002 Given the following:
- Unit 1 is in Mode 6
- Fuel Harviling is in progress
- Containment Purge is in operation
- GRO reports that he will be performing a functional test of RMSs at 1C22 per 01-35 As the CRS, what monitor should NOT be tested (per 01-35) that provide AUTOMATIC ACTIONS during a fuel handling incident in the Containment?
A. Fuel Handling Area Monitor (RI-5420) v6. Containment Area Radiation Monitor (Rl-5316A-0)
C. Wide Range Noble Gas Monitor (R!C-5415)
D. Containment ICI Area Monitor (RI-7006)
Conect answer is based on 01-35, distractors have no auto action to Containment Purge.
author: REN The question had the stem cravii. d/ changed and changed 1 distractor (Criticality Monitor), modifed to exclude cri'.icality and hi range monitors heed on question review, additionally, change stem and answer to be in singular.
KEYWORDS:
NRC KIA NRCimp Coglevel source Reference Laos Plan Obj s Ouane b00029K103 b.s l COMP kB440DIFY l0636 lCRO 1341 l4.1 Ir2G2 l
DATES: Modified: Tuesday, Merdi17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses o
o o
o o
o o
o o
o o
o As a %:
0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TimeU p(diff)]
ol rpbl
.ol Values:1 l ol 2l ol 3 l ol 4l oj 4
. ~.
- s..
y
.s..,
. 'nseaday,M l'7,1998 @ 08:47 AM FINAL.BNK 4 1
/ress:44 -
- 44. HI RCS ACTMTY 001 Which condition will cause 1(2)C07 alarm F-21 " RAD MON LVL Hl" to alarm AND a dose rate change in the Letdown line?
A. L Ch inside the Containment resulting in a crud burst when RCPs are stopped a ter CIS actuation.
B. L' X:A outside the Containment resulting in activity in the 27' West Penetration Room.
- 4. RCP pump start up after Loss of Offsite Power resulting in a crud burst D. Starting additional Charging pumps in response to an RCS leak.
Correct answer is based on Alarm Manual description, distractors various activity producing wente M no activity reaching the process rad monitor in the letdown portion of CVCS.
author.REN KEYWORDS:
NRC WA NRCImp Coglovel Source Refwenos Lees Plan Obl#
Ouane h00078K201 b.0 M
EB-MODIFY l ALM MAN DRO-1071 k.7 Ir1G1 l
DATES: Modifiet Tuoedey, Merdi17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Totel Responses.
o o
3 o
o o
o o
o' o
o 3
Ase %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l 2l p(diff)l 1l rpbl el. Velues:1 l ol2l ol3l ol 4 l ol c
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se l
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. S 42 t,, -
. FDIAL.BNK
.v.
- 42. FUNC RECOVERY 002 EOP-8 has been implemented on Unit-1, due to a single event diagnosis was not possible. Assume no safety functions are cumently being met.
1 Select the conect success paths in order of implementation based on the safety funcp hierarchy:
VA. RC, VA, PIC, HR, CE, RLEC B. RC, Plc, HR, VA, CE, RLEC C. RC, HR, Plc, VA, CE, RLEC D. RC, VA, HR, PIC, CE, RLEC Conect answer is based on EOP 8 usage instructions, distractions variations in the wrong hierarchy.
author:REN MEYWORDs:
NRCK/A NRCimp Coglevel Source Reference Lees Plan Obj #
OuWne bCCE00EA22 l4.0 l COMP IdEW BOP 8 lSRO.2018 l2.6 lT1G2 l
DATES: ModlSed Monday,Merch16,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Tolol Responses 2
o o
o o
o e
o o
o o
3 Ase %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel 5l p(difnl 2l rpbl ol Velues-1l ol 2 l ol 3 l ol4l ol l
i 1
i 1
)
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Thy, Mardi'17,1993 e os:47 AM :
FINAL.BNK'. ' s.
't.de: 4
- 48. LARGE BREAK LOCA 001 l
Which one of the following indicates adequate' core cooling exists via natural circulation during small break LOCA?
I l
l
~
0 A. RCS Tc is less than 10 F superheated.
B. RCS Th and average CET temperatures are superheated.
0 vC. RCS loop Th minus Tc is 10 F.
0 D. RCS subcooling is 20 F.
Correct answer is based on EOP 5 conditions, distractors are below established limits j
(subcooling < 25 F) or indications of inadequate core cooling (superheat).
{
0 KEY WORDs:
J NRCK/A NRCImp Cog level Source Reference Less Plan Obj #
Outhne b00011K101 l4.4 khf.[5' li1/95 NRC kop 5 BRO 2015 b.0 k1G1 l
DATES: ModlSed Saturday.Marum14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
3 o
o o
o o
o o
o 3
Asa %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Timel il p(dimi ilepbl 01 vaiues:11 0121 01 a l 0141 01 i
I
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4 i
I I
4
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- 3.. :
2-y
..,.. 46. ~
.~
~
Tuesday) March 17,1998 @ 0$:4i' M.
FINAL.BNK.
. Page:
j A
1
- 46. INADEQUATE CORE CLG 001 Given the following:
- Unit 2 event resulted in implementation of EOP-3 (Total Loss of Feedwater) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago
- dnce-thru-Core Cooling in progress
- RCS pressure is 700 PSIA
\\ c is 505 F, CETis 507 F 0
0 T
- Total HPSI flow is 340 gpm Which of the following describes the condition of Unit 2 and required action:
VA. Reactor core is partially uncovered, immediately increase HPSI injection.
B. Reactor core is covered, immediately increase cooldown via SGs.
C. Reactor core is partially uncovered, immediately lower RCS pressure via Aux Spray using charging pumps.
D. Reactor core is covered, immediately lower RCS pressure via Aux Spray and charging pumps.
Correct answer is due to superheat indications from RCS pressure and Temperatures and HPSI flow is below required by EOP attachment 10 which requires 369 gpm minimum. Distractors are actions which, if used, would result in additional increase in the superheat condition or no change. Additionally, determination of the core inventory condition is basis for question.
l author:REN provide steam tables, EOP attachment 10 KEY WoRDS:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline h0074EK104 l4.1 lAPPLIC-SRo HEW h0P ATTC lSRO-201-3 h.0 lTIG1 l
DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
3 o
o e
o o
e o
o o
o 3
As a %:
100.0
- 0. 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 TimeU p(diff)l al tpbl 0l Va'ues:1 l ol 2l ol 3 l ol 4 l ol
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- p.es'56 -
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'W FINAL.BNK'
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- 56. LOSS OF COND VAC 001 Given:
Both_ Units 1 & 2 are at 100% power A Loss of Offsite Power occurs All DGs start and load as expected EOP-0 is implemented for both units j
Condenser vacuum is 22" HG on both Units Select the expected response on steam dumping capabilities for both Units:
l A. Unit 1 TBVs are operable, Unit 2 TBVs are operable.
v6. Unit 1 TBVs are inoperable, Unit 2 TBVs are operable C. Unit 1 TBVs are inoperable, Unit 2 TBVs are inoperable.
D. Unit 1 TBVs are operable, Unit 2 TBVs are inoperable Correct answer is based on difference of Unit 1 and 2 nominal setpoints (Unit 1 is 20",
Unit 2 is 25 ") contained in the Main Turbine trip logics, distractors are permutations around the setpoints.
KEYWORDS:
NRC K/A NRCimp Coglevel Source Reference Less Plan Obl#
Outline BOO 51AK301 b.1*
MY NEW h0P-7G BRO 2027G7 l1.3 lT1G1 l
DATES: Moddied Monday, March 16,1996 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
i i
i o
o o
o o
e o
o 3
As a %:
33.3 33.3 33.3 0.0 o.o o.c o.o 0.0 0.0 0.0 0.0 100.o Timed p(dtff)l o,33333l rpbl
.o. 3 eil Values:1 l ol 2l ol 3 l ol 4 l ol j
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Tuesasy,kah 11,199p's os:41d, FINAL.BNK
~
- 61. LOSS RC M/U 001 A charging header leak would be identified by which one of the following per AOP-2A (Excssive RCS leakage)?
A. Decreasing PZR level with minirnum letdown flow.
B. C@arging header pressure greater than RCS pressure.
C. C 1arging header flow < 44 gpm with one charging pump.
Correct answer is specified in AOP 2A, distractors are normal conditions or unrelated conditions for excessive RCS leakage.
KEY WORDs:
NRC K/A NRCimp Coglevel Source Reference Less Plan Obj #
Outline han29AA201 b.8 NEMORY W BANK lAoP-2A lCRO 202-2A b.0 Ir1G2 l
DATES: Modified. Saturday. March 14,1996 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o e
o 3
o o
o e
o o
o 3
Asa %:
00 00 00 100.0 00 00 0.0 0.0 0.0 0.0 0.0 100.0 Time d p(diff)l 3lrpbl ol Values:1l ol2l ol 3 l ol 4l ol l'
yt
1 i
i:
Tanday,udeh 17,199 ' dos:47AM
FINALBNK. ' '.
c,.
- Pagei.63' "#
~
- 63. [.OSS VITAL AC 001 Given the folkming:
- Unit 2 is at 100% power
- various alarms annunciate indicating possible loss of power
- CRO reports 0 voltage indication for 2YO9 at panel 1C24A As tb CRS, you direct the implementation of AOP-71 for the loss of 2YO9. A few minutes later, the RO mports that Reactor power is slowly rising.
Select the direction required by you to mitigate this effect and th0 basis:
A. Reduce reactor power and turbine load due to ircreased steam flow through MT InterceptorValve.
B. Trip the Reactor, implement EOP-0 due to a dilution event in progress.
C. Secure Charging and Letdown due a dilution evoid in progress.
v0. Reduce reactor power snd turbine load due to feedwater system cooldown.
Correct answer is based on AOP 71 actions for the effects of FWH hi level dumps failing open upon loss of 2YO9. Distractors are actions for components effected by loss of 2YO9 with opposite effect on the reactor or a non existent dilution event.
author.REN The question was modified after validation due no discrimination and make more cognitive actico required to discem the correct response.
KEYWORDS:
NRC K/A NRCImp Coglevel Source Reference Less Plan Obj #
Outline h00057K301 ld.4 lAPPLic-SRO NEW lAoP 71 lCRO-202 71 l3.0 k1G1 l
DATES: Modified Monday, March 16,1996 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
- o 3
o o
o e
o o
o 3
As a %:
0.0 0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.o Time l 1l p(diff)l 1l rpbl ol Values:1 l ol 2l ol 3 l ol 4 l ol l
l l
l I
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.' ?-
.P.seds A
FINAL.BlVKf
'/ -
meday,urch17,199 @osi47 AK.
- 65. MAIN AND REHEAT STM 001 Unit 1 had been operating continuously for 340 days, when a small RCS leak developed a short time ago. You are the Unit 1 CRS dimeting a rapid power reduction per OP-3 to pMee Unit 1 in hot standby. Unit 1 load is at 570 MWe. Reactor power is being lowered at the rate of 35% per hour. Tc is +2 degrees F from program Tc. The RO {eports that Tc is beginning to rise suddenly.' What has occurred and what effect willthere be on core reactMty?
(Note: Consider each condition separately)
A. TBV-3940 begins to shut, adds (+) reactivity.
B. S/G blowdown flow raised to 150 gpm, adds (-) reactivity.
4 MSR 2nd Stage High Load MOVs shut, adds (-) reactivity.
D. Low Pressure Feedwater Heater High Level Dump valves open, adds (+) reactivity.
Correct answer is based on the auto close design of the MSR MOVs, with action specified in OP-3. Distractors are unrelated manual actions with varied reactivity effects.
KEY WORDS:
NRC K/A NRCimp Coglevel Source Reference Less Plan Obj #
Outline h00039K508 b.6 lAPPLIC NEW DP-3 lCRO-102-3 b.0 lT2G2 l
DATES: Modified. Saturtisy. March 14.1996 used:
STATISTICS:
'_ A B
C D
E F
G H
I J
Omits Total Responses:
o e
3 o
o o
o o
o o
o 3
As a %:
0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 TimeU p(diff)l 1l rpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol 9
.h i
w
.FMIL.BN,';.
'Page: 77
~... >.
. fuesd y, Mardi 17,199:gos:4 AM..
~
'. ' '.77. RAblATION CONTROi. 002
~ '
An operator,is assigned a task to monitor a resin transfer line for blockage. The operator's current dose for the year is 850 mrem. The task is expected to result in a dose of100 mrem.
Describe the procedure, if required, for extending the administrative dose limit:
A.ho administrative dose limit extension is needed.
B. Dosimeter record review, Shift Supervisor and GS-NO approvals.
vC. Dosimeter record review, GS-NO and GS-RS approvals.
D. EPD functional revient, RadCon S/S and Shift Supervisor approvals.
Correct answer is based on admin requirements for dose extensions, distractors are variations on positions or reviews not specified.
KEY WoRDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obl# -
Outime lUQQQ2.3.4 b.1 l COMP b3NRC MOD hP 1-100 lGOT b2.0 Ir3 GEN l
DATES: ModlSed. Salurday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
2 0
2 0
0 o
o o
o o
o 3
As a %:
33.3 0.0 ss.?
o.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.o Time l 1l p(diff)l o.ssss?l rpbl o.s1l Values:1 l ol2l ol 3 I ol4l ol suu s
i.' O, Mar
- it,19'9s e oss: AM FINAL.BNK. '-
. l-
: P.se: s5'.
?8b7RdlTDlTsifiDN IND 001 The Control Element Assembly Position Display System'(CEAPDS) uses a rea'ctor power signal (Omet) to generate Which of the following functions?
~
A. Sequential Permissive signal.
B. Shutdown Group Exercise limit.
C. DEA Withdrawal Prohibit (CWP)
- 4. Secondary PDIL and PPDIL setpoints Correct answer is based on component design, distractors are unrelated outputs to the CEAPDS and incorrect use of Omet signal from RPS.
KEY WORDs:
NRC KIA NRCimp Cog level Source Reference Less Plan Obj #
Outline h00014K102 h.3 NOMP HEW DRo 601 BRO 401 h3.2 IT2G1 l
DATES: Modded: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o o
o 3
e o
o o
o o
o 3
As a %:
0.0 0.0 0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 TimeU p(diff)l ilrpbl ol Values:1 l ol2l ol 3 l ol 4 l ol V'
Tusaday, Mard 17,1998 @ 08:48 AM FINAL.BNK:
Page m
- 79. RCP MALFUNCTION 002 Given the following:
- Unit is manually tripped due to Loss of instrument Air
~ irached.
n
- The RO reports that Loop flow d/p parameters on C06 panel decreased to ~0
% PSID soon after RCPs were secured.
Which of the following is the required actions per EOP-2:
- 4. Monitor RCS loop temperatures for 5-15 minutes for thermal driving head development.
C. Immediately increase the Steaming rate from both SGs by opening all TBVs to establish natural circulation conditions.
D. Immediately shut ADVs and TBVs to establish natural circulation conditions.
Correct answer is based on EOP basis for natural circulation development, distractors are unrelated actions for the basis or actions which will impede natural circualtion development.
author: REN MEYWoRDs:
NRC K/A NRCimp Cog level Source Reference Less Plan Obj #
Outime h00015A112 l3.1 NEMORY h3NRC440D EOP BASIS lSRO-201-2 l2.0 lT1G1
_l DATES: Modhied: Tuesdey, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Responses:
o 3
o o
o o
o o
o o
o 3
As a %:
0.0 100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time U p(diff)l 3l rpbl ol Values:1 l ol2l ol 3 l ol.4 l ol l
Y
/S 4
h
Tuesday, March 17,1998 @ 01:48 AM FINAL.BNK
^
p.ge:so
- 80. RCS OVERCOOLING 001 During a main steam line break event (ESDE), unaffected S/G temperature must be 0
maintained within 25 F of CET temperature while blowdown of the affected S/G is in progress. Which one of the following is the basis for this limitation?
v'A. Prevents an excessive RCS heatup after blowdown of the affected S/G is complete.
B. delps to minimize the RCS cooldown from the blowdown of the affected S/G.
C. Conserves unaffected S/G inventory for core heat removal after blowdown.
D. Prevents the formation of tube voids after blowdown of the affected S/G is complete.
Correct answer is based on EOP4 basis and procedural guidance, distractors are unrelated basis.
KEY WORDs:
NRC K/A NRCImp Cog level Source Reference Less Plan Obj #
Outline hCEA11AA21 h.3 NEMoRY EXAM BANK HOP 4 basis bro-2014 b.0 k1G1 l
DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A-B C
D E
F G
H I
J omits Total Responses:
3 0
0 0
0 0
0 0
0 0
0 3
As a %:
200.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 100.0 Time l 1l p(diff)l 1l rpbl 0l Values:1 l 0l 2l 0l 3 l 0l4l 0l l
weeday, March 17,199: g os:4 AM FINAL.BNK
. Page: 87
- 87. RX TRIP STABIL 002 Given the following:
- Unit 2 tripped from 100% powor
- EOP-0 " Post Trip immediate actions" are being performed
- Tis Main Turbine did not trip as expected.
Whiqh one of the following actions should be performed per EOP-0 to trip /stop the turbihe?
l VA. Manually close both MSIVs.
B. Manually open the Generator output breakers.
l C. Manually trip the Generator exciter field breaker.
D. locally trip the Turbine from the front standard.
Correct answer is based on EOP O actions, distractors are unsecified actions which will result in turbine trip or equipment damage.
KEYwoRos:
NRc KIA NRcimp Cog level Source Reference Less Plan Obj #
Outhne hCEE02EA12 h.9 NEMORY l11/95 NRC kOP-0 BRO-201-0 l10.0 lT1G2 l
DATES: Modired: Saturday, March 14,1998 Used:
sTATISTIOs:
A B
C D
E F
G H
I J
omits Total Responses:
3 o
o o
o o
o o
e o
o 3
Ass %:
100 0 00 00 00 00 00 00 00 00 00 00 100 0 Timed p(diff)l 1l rpbl ol Values:1 l ol 2l ol 3 l ol4l ol
.s
.l 4
g
.. d I
i Tuesday, March 17,1998 @ 08:48 AM FINAL.BNK P.se: 92
~~
g2. SG TUBE RUPTURE 001 During implementation of EOP 6 (SG Tube Rupture) procedural guidance is given to maintain subcooling at a different value than EOP 0.
Select the proper value and the basis for the procedural requirement:
VA. daintain subcooling >25 F to minimize the RCS leak rate.
0 0
B.' Maintain subcooling >30 F to ensure adequate NPSH for RCPs.
)
C. Maintain subcooling > 25 F to minimize excessive Safety injection flowrate.
l 0
0 D. Maintain subcooling > 30 F to minimize backflow from the affected SG.
Correct answer is based on EOP 6 basis and procedural guidance, distractors are variations on limit and unrelated reasons.
author:REN KEY WoRDS:
NRC K/A NRCimp Coglevel Swrce Reference Less Plan Obj #
Outline b00037K102 b.9 l COMP kB-MODIFY EOP6 BASIS BRO-2016 b.1 lT1G2 l
l DATES: Modified: Saturday, March 14,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Omits Total Roeponses.
3 o
o o
o o
o o
o o
o 3
Asa %:
100.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 Time l il p(dsff)l 1lrpbl ol Values:1 l ol 2 l ol 3 l ol 4 l ol l
s
Tuesday, Mard I7,1998 @ 08:48 AM FINAL.BNK rsse:96
- 96. STATION BLACK OUT 001 Given the following:
- Unit 2 tripped
- EOP-5 (Loss of Coolant Accident) is implemented "a concurtsnt loss of AC power occurs What is the MAXIMUM design time available to restore power to the affected battery chabers?
l VA. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from initialloss of power B. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from initialloss of power C. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from time of ReactorTrip l
D. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from time of ReactorTrip Correct answer is based on FSAR description and Tech Spec LCO time, distractors are unrelated times or conditions.
KEYWORDS:
NRc K/A NRcimp Cog level Source Reference Less Plan Obj #
Outline l00055EK301 h.4 l COMP h5NRc-MOD ESAR4 lCRO-54-1 h.1 IT1G1 l
I DATES: Modified: Tuesday, March 17,1998 Used:
STATISTICS:
A B
C D
E F
G H
I J
Ornits Total Responses 1
1 1
o e
o o
o o
o o
3 As a %:
33.3 33.3 33.3 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 100.0 TimeU p(diff)l o,33333l rpbl
_o. 3 81l Values:1 l ol2l ol 3 l ol 4 l ol
,,,) t
_ _ - - _ _ - _ _ _ _ _ _ _ _ _.