IR 05000331/1999301
| ML20207H677 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/13/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20207H672 | List: |
| References | |
| 50-331-99-301OL, NUDOCS 9907160080 | |
| Download: ML20207H677 (110) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION 111 l
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Docket No:
50-331
= License No:
DRP-49 j
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Report No:
50-331/99301(OL)
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Licensee:
IES Utilities Inc.
Facility:
Duane Arnold Energy Center
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Location:
- lES Utilities Inc.
200 First Street SE -
i P.O. Box 351 Cedar Rapidt, IA 52406-0351
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Date:
May 25,1999
Telephoned Examination Results June 4,1999 l
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Examiner:
M. Bielby, Chief Examiner, Rlli Approved by:
D. Hills, Chief, Operations Branch Division of Reactor Safety l.
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EXECUTIVE SUMMARY DAEC Nuclear Power P! ant NRC Examination Report 50-331/93301(OL)
A licensee developed and NRC approved initial operator licensing written retake examination wac administered by the licensee to one applicant requesting a reactor operator (RO) license to operate the Duane Arnold Energy Center.
Results:
The applicant passed the written retake examination and was issued an RO license to operate the Duane Arnold Energy Center.
Report Summary:
Based on the written retake examination score, the applicant's performance was
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satisfactory. (Section 04.1)
The high number of questions (21) submitted to the NRC that did not meet NUREG-
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1021, Operator Licensing Examination Standards for Power Reactors, Interim Revision 8, guidance demonstrated opportunities for improvement in the licensee's examination writing skills and knowledge. (Section 05.2)
The licensee administered the written retake examination in accordance with
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appropriate guidance and submitted the appropriate administration documentation. The examiner did not identify any examination compromise issues. (Section 05.3)
The licensee satisfactorily performed post examination activities including final grading
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and review of applicant clarification comments in accordance with appropriate guidance.
(Section 05.4)
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Report Details
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l l, Operationa 04: ' Operator Knowledge and Performance
04.1 Written Retake Examination Performance a.
Scope
. The licensee administered an initial operator license written retake examination to one
' Reactor Operator (RO) applicant. The NRC examiner evaluated the applicant's performance on the written examination.
b.
Qbaprvations and Findinas
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The RO applicant passed the written retake examination. The examiner determined that of the 18 questions answered incorrectly,11 were newly written questions not originally contained in the licensee's examination bank. Those questions reflected the discriminatory value of periodically refreshing the examination bank with new questions.
Because the examination was only administered to one applicant, the examinor could not draw any conclusions regarding generic knowledge and abilities weaknesses.
Howevar, eight of the 18 questions the applicant answered incorrectly were from the emergency and abnormal plant evolutions section of the examination. These eight questions are identified below for consideration as feedback into the licensee's
- Systematic Approach to Training based program. Based on the written examination score and question review, the applicant's performance was satisfactory.
Question #
Knowtedge Weakness
. RO#03 '
Abnormal plant evolutions, high reactor pressure - Ability to operate end monitor the reactor / turbine pressure regulating system.
RO#11 Emergency plant evokitions, SCRAM condition present and reactor power abwe average power range monitor
. (APRM) downscale or unknown - Knowledge of the operational implications of the reactor water level effects on reactor powe.c.
RO#13 Emergency plant evolutions, high drywell pressure -
Knowledge of the interrelations with AC distribution.
RO#15 Abnormal plant evolutions, loss of main condenser vacuum - Knowledge of the operationalimplications of the concept as it applies to loss of heat sink.
RO#17 Abnormal plant evolutions, partial or complete loss of DC power - Ability to interpret / determine the extent of power loss.
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RO#19 Abnormal plant evolutions, high drywell temperature -
' Ability to operate or monitor the drywell cooling system.
RO#20 Abnormal plant evolutions, high suppression pool temperature - Knowledge of the reasons for limiting heat additions.
RO#21 Abnormal plant evolutions, control room abandonment -
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Ability to operate or monitor AC electrical distribution.
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Conclusion Based on the written retake examination score, the applicant's performance was satisfactory.
Operator Training and Qualification
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05.1 General Comments The NRC approved written retake examination was administered by the licensee's
- training staff to one RO on May ^5,1999. The RO had previously demonstrated unsatisfactory results during the July 1998 written examinatien.
The licensee developed the written examination in accordance with guidance prescribed in NUREG-1021, " Operator Licensing Examination Standards for Power Reactors,"
Interim Revision 8 January 1997. An NRC examiner reviewed and approved the written examination prior to its administration.
05.2 Review of Written Examination Outline and Examination Submittal a.'
Scope
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The licensee developed the written' examination in accordance with the prescribed examination development guidelines in NUREG-1021, Interim Revision 8. An NRC
. examiner completed review and comments on the outline and written examination i
material on May 12,1999, b.
Observations and Findinas Examination Outie The licensee st,bmitted the proposed written examination outline based on the quantitative requirements of ES-201-2," Examination Outline Quality Assurance Checklist," in NUREG-1021, Interim Revision 8. However, the examiner identified that the facility licensee failed to provide the required quality assurance form ES-201-2,
" Examination Outline Quality Assurance Checklist" and the summary page of the examination outline. Form ES-201-2 documented appropriate management review of the examination. The examiner informed the licensee of the oversight and the licensee subsequently submitted the appropriate material. The examiner determined that the written examination outline met the necessary quantitative and qualitative requirements for an NRC examination.
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Written Examination The licensee's training staff developed the questions and used licensed operators to validate the written examination. The examiner identified that 21 of the 100 questions did not meet the written question development guidance stated in NUREG-1021, Interim Revision 8. The examiner also suggested enhancements for another 34 questions. The examiner informed the licensee of the needed improvements to the written examination which the licensee satisfactorily completed on May 21,1999. The identified deficiencies included:
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Eight questions were not at the appropriate knowledge level for an RO candidate
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per 10 CFR 55.41, " Written Examination: Operators" and required replacement.
For example, questions required the use of the Emergency Operating Procedure flowcharts to determine a correct answer.
Seven questions had two or more correct answers, in addition, one question
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stem provided a correct answer, one question stem required more specific clarification wording to make the distractors incorrect, and one question allowed elimination of two distractors making the question a "true-false" format which was contrary to guidance contained in NUREG-1021, Section ES 401. These questions required either rewrite of the stem or replacement of the distractor (s).
Three questions contained specific determiners and implausible distractors
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contrary to the guidance of NUREG-1021, Appendix B, Section C.2.m. These questions required either rewrite of the stem or replacement of the distractor (s).
A total of 34 questions had passive wording or symbols in their stems and
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distractors that required changes to reflect positive wording or specific numbers in accordance with the guidance of NUREG-1021, Appendix B, Section C.2.e.
For example: replaced "could" to "would"; replaced "should" to "shall" or "must";
replaced the statements or symbols of " appropriate" with specific numbers; and highlighted any necessary negative words, such as "NOT "
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Conclusion The high number of questions (21) submitted to the NRC that did not meet NUREG-1021 guidance demonstrated opportunities for improvement in the licensee's examination writing skills and knowledge.
O5.3 Written Examination Administrating a.
Scope The licensee's training stat' administered the written examination on May 25,1999, with approval from the NRC.
b.
Observations and Findinas The licensee administered the written examination in accordance with the guidance of NUREG-1021, Section ES-402. The licensee completed and submitted all appropriate
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do'cumentation for written examination administration to the NRC. The examiners did l
' not identify any examination compromise issues.
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_ Conclusions
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' The licensee administered the written retake examination in accordance with appropriate guidance and submitted the appropriate administration documentation. The examiner did not identify any examination compromise issues.
053 '. Post Examination Activities a.
Scope
~ The NRC examiner reviewed the written examination grading that was performed by the
~ licensee in accordance with Form ES-403-1, " Written Examination Grading Quality
Assurance Checklist," contained in NUREG-1021. The NRC examiner also reviewed F'
. the applicant's questions that were raised during the examination administration and
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comments submitted by the licensee,
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Observations and Findinos '
The post written examination grading submitted by the licensee included the necessary documentation as required per the guidance of NUREG-1021 ES-501. The examiner's independent grading agreed with that submitted by the licensee. The licensee also submitted a review of the comments made by the applicant during the examination. The 6pplicant asked a minimum number of clarification questions and there were no post 6xamination comments submitteo :sy the liansee.
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Conclusions
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The licensee satisfactorily performed post examination activities including final grading
and review of applicant clarification comments in accordance with appropriate guidance.
V. Manaaement Meetinas X1
' Exit Meeting Summary The examiner conducted a telephone exit meeting with members of the licensee's training
' management on June 4,1999, to discuss the examination results. The licensee acknowledged
- the findings presented and indicated that the materials reviewed were not considered
- proprietary.'
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l PARTIAL LIST OF PERSONS CONTACTED Licensee
' M. Hills, Operations Training Supervisor K. Young, Training Manager
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NBC P. Prescott, Senior Resident inspector INSPECTION PROCEDURES USED None
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ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None LIST OF ACRONYMS USED AC'
Altemating Current APRM Average Power Range Monitor CFR Code of Federal Regulations DAEC Duane Arnold Energy Center DC Direct Current DRS Division of Reactor Safety ES Examination Standards NRC Nuclear Regulator Commission NRR NRC Office of Nuclear Reactor Regulation OB Operations Branch OL Operator Licensing PDR Public Document Room RO Reactor Operator RWM Rod Worth Minimizer
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i ES-401 Site-Specific Written Examination Form ES-401-7 l
Cover Sheet
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NUREG-1021 39 of 39 Interim Rev. 8. January 1997 I
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Reactor Operator 50007 Topic: NRC 1998 ILC EXAM RE-TEST Exam Series A
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Rev. 0 - January 20,1999 ANSWER KEY DEVELOPED BY:.
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George Th'tillen, Instructor Date'
APPROVED BY:
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5/R<v #
I 9/98 Plant' Reviewer U
Da'te APPROVED BY:
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6 9/9f
@ ding Su%rvisor-Operations Dale
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Available Responses:
100 Number Correct:
SCORE:
%
Graded By:
Reviewed By:
Student's Name:
TDT 3.01 Re r Print Date:
LEAVE EXAM WITH INSTRUCTOR / PROCTOR PRIOR TO LEAVING EXAM ROOM.
f EXAM REVIEW SECTION - PLEASE SIGN IN BLACK INK I ACKNOWLEDGE THAT I HAVE PARTICIPATED IN THE REVIEW OF THIS DOCUMENT j
AND HAVE HAD AN OPPORTUNITY TO ASK QUESTIONS.
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Student's Signature
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TDT 3.01 l
Rev.2
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Objective: 93.21.01.03 (Revised from 1998 LOR exam.)
1 Point 11! ~ The plant is performing a shutdown'for a refueling outage. The following conditions exist:
One Condensate and Feed water pump are in operation.
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. Reactor power is 29%.
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Recire flow is at minimum
The crew is inserting control rods when a Turbine Trip occurs. The Turbine Bypass Valves j
respond as. designed.
~ Which of the following is the CORRECT concerning the plant and operator response to this event?
a.
The Bypass Valves will NOT be able to control Reactor pressure.
It will be necessary for operators to insert a manual Reactor Scram:
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b.
The Bypass Valves will NOT be able to control Reactor pre ssure.
_ lt will be necessary for operators to insert the cram group in accordance with Fast Power
Re' duction; c.
The Bypass Valves will be able to control Reactor pressure.
It will be necessary for operators to open all available steam line drains to assist Reactor pressure control.
d.~
The Bypass Valves will be able to control Reactor pressure.
No operator action will be necessary.
ANSWER: A'
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. REFERENCE: ARP IC07A, A-2; SD-693.1; TPOI 5 l
K/A System: 295005 K/A Number: AK2.07 K/A Value: 3.6/3.7 I
Cognitive Level:'3 i
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Note: IPOI 5 directs a manual scram if an auto scram is unavoidable. Turbine trip does not auto scram reactor < 30%, but an auto scram is unavoidable as RPV pressure increases. The SD say the Bypass Valve capacity is 25%; recent studies have show that, with the concurrent loss of
feedwater heating, BPV pressure control'would be inadequate > 22.5%. An RO should know this.
Distracter 1: "NOT be able" is correct but cram rod insertion is not. Fast power reduction allows the cram group to lower power to < 75% load line, after that a scram is required. At 29% power n the cram rods would already be inserted.
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Distracter 2: "Be able " is incorrect; Opening MSL drains will help but mosi, drains would already
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be open and this action will not make scram unavoidable.
Distracter 3: "Be able " is incorrect and a manual scram is necessary.
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Rev. 0 --
Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-1-Exam Series A
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Objective: 45.01.01.02 (NEW for 1998 ILC Retest)
1 Point 2.
An automatic reactor scram occurs from full power with the Master Feed Reg Controller in AUTO. As the IC05 panel operator during this transient you are roeponsible for restoring RPV level.
At which point are the following actions taken?
1) Depressing the pushbutton for " Manual Level Setback to 175", HS 4577, 2) Securing one of the two running feed pumps.
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a.
1) May be performed while RPV level still decreasing.
2) May be performed while RPV level still decreasing.
b.
1) May be performed while RPV level still decreasing.
2) Must wait until RPV level starts to increase.
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c.
1) Must wait until RPV level starts to increase.
' ) May be performed while RPV level still decreasing.
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d.
1) Must wait until RPV level starts to increase.
2) Must vvait until RPV level starts to increase.
ANSWER: B REFERENCE: IPOl 5 Rev 22, Step 3.2(3)
K/A System: 295006 K/A Number: AK3.04 K/A Value: 3.1/3.3 Cognitive Level: 3 Distracter 1: Trip a RFP when level starts to increase.
Distracter 2: Trip a RFP when level starts to increase.175" setback can be used immediately.
Distracter 3: 175" setback can be used immediately.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-2-Exam Series A
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Objective: 52.00.00.05 (NEW for 1998 ILC Retest)
1 Point 3.
See the EHC Pressure Regulator schematic on the next page.
The plant is at 90% steady state power with the EHC Pressure Regulators SFsT-UP AS SHOWN.'
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Assume that a steam leak were to occur on the sensing line for the B Pressure Regulator such that " Steam Thrcttle Pressure B" started to fail DOWNSCALE. Also assume that no operator action is taken.
Which of the following CORRECTLY describes the expected response of RPV pressure?
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a.
RPV pressure should not change.
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b. ' RPV pressure should stabilize 5 psig lower.
c.
RPV pressure should stabiliw 5 peig higher.
d.
RPV pressure should increase steadily until the reactor scrams on either high flux or high pressure.
ANSWER: C REFERENCE: SD-693.2, Figure 4 K/A SYSTEM: 295007 K/A NUMBER: AA1.05 K/A VALUE: 3.7/3.8 Cognitive Level: 3 Note: Figure shows B Regulator in control with a +5 psig on the A Regulator. As B throttle pressure lowers, the summer output goes from 0 to negative and TGVs start to close. As the A regulator throttle pressure increases, its summer output goes from -5 to 0 which will then provide the highest value through the HVG. If CVs continue to close, the A output goes >0 which opens the CV to lower pressure. Pressure thus stabilizes at a regulator set pressure which is 5 psig higher than B.' The setup is reversed from SD which has the A regulator in control (0 bias).
Distracter 1: = 5 psig higher.
Distracter 2: = 5 psig higher.
Distracter 3: = 5 psig higher.
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Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
- 5799NRCA.
3-Exam Series A
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Objective: 45.01.01.01 (NEW for 1998 ILC Retest)
1 Point 4.
The plant is at 100% power in a normallineup when annunciator IC05A, D-1, " REACTOR VESSEL HI/LO LEVEL RECORDER ALARM" actuates.
The following indications are observed at 1C05 and 1C06:
RPV level is at 185" and slowly lowering.
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The Master Feed Reg Valve Controller remains in AUTO and set at 190.
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A Feed pump amps are 700 and slowly increasing.
- A Feed Reg valve position is 65% and slowly opening.
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B Feed pump amps are 400 and slowly lowering.
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B Feed Reg Valve position is 40% and slowly closing.
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Which of the following is the CORRECT, LONG TERM operator response for this situation?
a.
Adjust the Master Controller in AUTO to a higher setpoint.
b.
Shift the Master Controller to MANUAL and adjust the A and B Reg Valves further open.
I c.
Adjust the bias on the A and B Reg Valve Controllers to balance flows.
d.
Shift the B Feed Reg Valve Controller to MANUAL and adjust the B Reg Valve further open.
ANSWER: D REFERENCE: ARP IC05A, D-1; SD G44 IUA System: 295009 IUA Number: AA1.02 IUA Value:4.0/4.0 Cognitive Level: 3 Note: B Feed Reg Valve controller is failing in AUTO and driving the B Reg valve closed.
Distracter 1& 2: This will open A Reg Valve and may recover level but the A Feed pump will eventually trip on overcurrent.
j Distracter 3:This would be appropriate for a small mismatch at steady state conditiona.
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l Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-4-Exam Series A l
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g Objective: 89.02.01.01 (NEW for 1998 ILC Retest).
1 Point
' 5. : Due to increasing Drywell leakage appearing in the Floor Drain Sump, the reactor i.s being shutdown. Reactor poweris 40% with the downpower progressing normally. Operators are
watching Drywellleakage very closely..
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Equipment Drain Sump IDENTIFIED leakage has remained constant at 2.0 gpm for 8 weeks.
Floor Drain Sump UNIDENTIFIED leakage has risen steadily over several days from 1.5 gpm to 2.5 gpm.
At 1200 this day, operators pumped the Drywell sumps and obtained the following readings on the Floor Drain Sump TIME COUNTER GALLONS GPM 1000 0092230 295 2.5 1200 0092825 Has a Technical Specification operational leakage limit for the Reactor Coolant System been exceeded?-
a.
No; unidentified leakage has remained at = 2.5 gpm.
-4 b.
No; Totalleakage has remained less than 5 gpm.
c.
. Yes; unidentified leakage has increased by more than 2 gpm.
d.
Yes; Totalleakage has increased to more than 5 gpm.
ANSWER: C REFERENCE: T.S. 3.4.4 -
K/A System: 295010 K/A Number: AA2.01 &
K/A Value:3.4/3.8 Cognitive Level: 3 Distracter 1: 2.48 gpm if RO incorrectly uses the usual 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> /240 minutes for calculation.
Approximation sign (=) is necessary for realism. The correct calculation is 4.90, which cannot be considered % 2.5 gpm".
' Distracter 2: 2.48+ 2.0=<5.0 if RO incorrectly uses the usual 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> /240 minutes for calculation.
Distracter 3: 4.9+2.0= >5.0 gpm, but totalleakage limit is 25 gpm.
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-5'-
Exam Series A
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Objective: 94.03.05.02 (From 1998 LOR exam.)
1 Point U.
The on shift crew is holding power during load increase following successful post-outage startup.
Plant conditions are as follows:
Reactor power:
65%, stable Reactor level:
189", stable Generator output:
350 MWe, stable Without warning, the NSOE reports the following indications, with no operator action:
Reactor power:
Rising steadily on all APRM channels Reactor level:
180", dropping slowly Generator output:
Rising steadily
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Which one of the following is the most plausible explanation for these indications?
a.
One or both of the feed regulating ve.lves is failing closed, lowering feed flow and collapsing voids in the core.
b.
One or both of the Recire controllers has failed, causing reactor Recirculation flow to increase.
c.
The EHC system is malfunctioning, and is acting to raise reactor pressure.
d.
The reactor has just experienced a control rod drop accident.
ANSWER: B REFERENCFs: AOP 255.2 K/A System: 295014 K/A: AA2.03 K/A Value: 4.0/4.3 Cognitive Level: 3 Distracter 1: If feed flow was lowering, voids would increase and power drop.
Distracter 2: If EHC was faihng in this manner, MWe would drop.
Distracter 3: A control rod drop accident would increase voids (raising level). Also, changes in power and level would be abrupt, not slow / steady.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-G-Exam Series A
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' Objective: 95.06.01.08 (NEW for 1998 ILC Retest)
1 Point 7.- - During full power operation on the Mid Shift (when no extra personnel are available), a
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reactor scram occurs which cannot be immediately reset. The following indications are j
present at 1C05:
..When the Rod Select Power is tuned OFF and then ON with the Mode Switch in Refuel, the_ white Refuel select Permissive light remains OFF.
l On the Full Core Display, the Blue Scram lights are ON for all 89 rods.
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.On the Full Core Display, the green FULL IN lights are OFF for four (4) control rods.
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All LPRM downscale lights are ON.
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When the IRMs are fully inserted, they read between range 3 and 4 and are lowering.
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RPV pressure is 900 psig and lowering very slowly with the Main Steam Line Drains open.
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SBLC was not injected.
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1) Per the ~ATWS EOP, is the reactor considered SHUTDOWN or SHUTDOWN UNDER ALL CONDITIONS WITHOUT BORON 7 And'
2) What is the CORRECT basis for the nnswer to part 1 of this question?
.a.
1) SHUTDOWN 2) Only four (4) rods do not indicate FULL IN.
b~
1) SHUTDOWN-
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2) The reactor is suberitical and below the point of addin;; heat.
c.
1) SHUTDOWN UNDER ALL CONDITIONS WITHOUT BORON 2) All 89 blue Scram Lights are ON.
d.
1) SHUTDOWN UNDER ALL CONDITIONS WITHOUT BORON 2) The IRM readings indicate that all rods have inserted to at least the Maximum Suberitical Banked Rod withdrawal position.
ANSWER: B-REFERENCE: ATWS EOP & Bases '
K/A System: 295015
- K/A Number: 2.4.17 K/A Value: 3.1/3.8
- Cognitive Level: 2-
' Note: SDUACWB cannot be determined until rod positions are known. DAEC POAH is IRM range G-7.
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Distracter 1: Shutdown is correct but not because only four rods are out.
Distracter 2: Scram lights are and inadequate indication of rod positions.
Distracter 3: IRM readings cannot be correlated to rod positions.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
- 5799NRCA-7-Exam Series A
p-Objective: 95.59.03.01 (NEW for 1998 ILC Retest)
1 Point 8. ~ A large Recire line break Loss of Coolant Accident has occurred while at power.
The OSS directs you, the 1C03 operator, to initiate Torus Sprays and he is trying to determine if Drywell Sprays can be initiated per EOP 2, Graph 7, "Drywell Spray Initiation
Limit".
Which other parametric value, in addition to Average Drywell Air Temperature, will the OSS need to make this determination?
a.
RPV Pressure b.-
Drywell Pressure c.
Torus Pressure
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-d.
Torus Level ANSWER: B REFERENCE: UFSAR Table 6.2-1, EOP 2 K/A System: 295024 K/A Number: G 2.4.0
- K/A Value: 3.1/4.0 Cognitive Level:.1 Note: Pressur'e response is modeled after UFSAR Fig. G.2.50 and revised values of Table G.2-1 and should therefore be considered normal.
Distracter 1: Value would be needed to determine Graph 1 (Sat Curve) entry, but not DW Spray permissive.
Distracter 2: Similar to DW pressure but not part of Graph 7.
Distracter 3: OSS will also verify T/L <13.5 ft. before spraying DW, but this is not part of Graph 7.
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Reactor Operator, 50007 4 -
01/20/99 Topic 1999 NRC Retest 5799NRCA-8-Exam Series A
Objective: 8.03.01.03 (From 1998 LOR Biennial Exam)
1 Point i
9.
The plant was at full power when a Turbine Building steam leak caused a Group 1 isolation to occur 10 minutes ago. MSIV closure successfully isolated the leak. RPV pressure exceeded 1120 psig on the initial transient. SRVs are the only pressure control system in operation.
The following plant conditions exist:
All control rods are fully inserted.
RPV levelis 190" and stable.
RPV pressure is 875 psig and lowering.
Based on the SRV indications below, select the answer which CORRECTLY describes the statue of the Low-Low Set SRVs. (Note: The shaded indicating lights are ON.)
G G G )a A
.
E,9 w
.,$
. o\\.,y...[
PSV-4401 PSV-4407 a.
The LLS Logic failed to give PSV-4401 a close signal.
b.
The LLS Logic failed to give PSV-4407 an open signal.
c.
The LLS SRVs are operating as designed.
d.
The LLS SRVs are operating as designed but PSV-4401 is mechanically stuck open.
i ANSWER: A
{
REFERENCE: SD-183.1 K/A SYSTEM: 295025 K/A NUMBER: EK3.09 i
K/A VALUE: 3.7/3.7 l
Cognitive Level: 3 l
Note: The amber light comes from 2/3 SRV Tailpipe pressure switches >25#.
j Distracter 1: RPV pressure is < PSV-4407 closing pressure of 905 psig.
l Distracter 2: PSV-4401 should have closed at <900 psig but the red light indicates that it is still
,
getting a LLS open signal.
!
Distracter 3: PSV-4401 should have closed at <900 psig but the red light indicates that it is still getting a LLS open signal. There is no way to tell if the SRV is stuck open.
Rev.O Reactor Operator, 50007 l
01/20/99 Topic 1999 NRC Retest 5799NRCA-9-Exam Series A
Objective:48.03.01.03'(NEW for 1998 ILC Retest)
1 Point 10. A smallline break LOCA occurs while at power. The Primary Containment responds as designed and EOP 2 parameters are under control.
Four control rods fail to fully insert and actions are taken per ATWS EOP including.
installation of Defeat 15 "MSIV and MSL Drain Rx Lo Lo-Lo Level Isolation Defeat".
l
, Available high pressure systems are not able to maintain RPV level. The following plant conditions exist:
. ' RPV Level 60", slowly lowering RPV Pressure 700 psig, slowly lowering
.
At this point, operators get all control rods fully inserted. The OSS briefs the crew that the
)
ATWS EOP is being exited and that Alternate Level Control (ALC ) is being entered.
)
Assuming that Defeat 15 removal WILL BE DELAYED, i
1) May the MSIVs REMAIN OPEN or must they be manually CLOSEDhv the 1C03 operator?
2) What is the CORRECT reason for part 1 of this question?
a.
1) REMAIN OPEN -
2) The open MSIVs would keep the Main Condenser available for eventual plant cooldown.
b.
1) REMAIN OPEN 2) The Main Steam system can be used to help expedite RPV depressurization so low pressure systems can inject, c.
1) CLOSED 2) Closing the MSIVs will conserve RPV inventory.
d.
1) CLOSED 2) Closing the MSIVs is necessary to protect the Main Condenser from overpressure.
ANSWER: C REFERENCE: EOP Bases ALC pg.20; SD-683 K/A System: 295031 K/A Number: EK2.12 K/A Value: 4.5*/4.5* Cognitive Level: 3 Note: A Group 1 MSIV closure at 04" would have occurred if not defeated for ATWS, which is no
' longer applicable. This isolation is designed to conserve inventory.
Distracter 1: Keeping condenser available is a true statement but MSIVs should be closed.'
Distracter 2: Depressurizing RPV is a true statement but depressurizing to anticipate ED is not
,
allowed and MSIVa should be closed.
Distracter 3: Closed is correct: BPVs would still close on high backpressure and the MSL drains return under water in the condenser. Also, EOP-1 allows Defeat 17. Not a concern.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
. 5799NRCA
- 10 -
Exam Series A
_
_
r
,
l t
-
..
'
Objective:- 95.51.02.09 (NEW for 1998 ILC Retest)
1 Point
- 11. A Group 1 Isolation and ATWS have occurred from full power.
[
'.
Reactor Power was 15% after the Recire pumps were tripped.
The SRVs have lifted and have stabilized RPV Pressure.
'.
The Torus temperature is increasing rapidly.
.
Drywell pressure remains normal.
..
The OSS has~ directed that RPVinjection be terminated for Level / Power Control.
.-
As the 1C05 operator, you close the Feed Reg Valves monitor critical parameters.
The following point is reached as RPV Levellowers:
. RPV level is at 150".-
.
Reactor power is at 2%.
'.
At this point the OSS directs you to reestablish injection with feedwater.
Is this direction correct? (YES or NO)
If YES, identify the reason it is correct.
If NO, identify the additional considerations necessary to reestablish injection.
a.
YES; injection may be reestablished when power lowers to <5%. There is no restriction on RPV Level.
b.
YES; injection may be reestablished when power lowers to <5% and RPV levelis <158".
c.
NO; injection must remain terminated until RPV levellowers to less than +119.5".
d.
NO; injection muat remain terminated until RPV levellowers to less than +87".
.
ANSWER: D REFERENCE: ATWS /L 1 & 2 K/A System: 295037
' K/A: EKLO2 K/A Value: 4,1/4.3 -
Cognitive Level: 2 Note: This is a recent change to the Level / Power control strategy. A IC05 operator should know that level must be lowered to < +87" in this situation.
Distracter 1: Reactor Level must be < +87" power <5% to re-establish injection.
Distracter 2: Reactor Level must'be < +87" power <5% to re-establish injection. Operators are L
- often directed to maintain level at 158" during an ATWS scenario.
[
Distracter 3: Reactor Level must be < +87" power <5% to re-establish injection. When in an L
ATWS but not 11P control, operators often use the Lo-Lo level as a limit.
-
l-
- Rev.O'
Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 11 -
Exam Series A y
..
.
.
..
.
.
. -_---
__
Objective: 95.11.01.01 (NEW for 1998 ILC Retest)
1 Point 12. Noble metal addition to the reactor coolant system can affect the Containment Hydrogen and Oxygen analyzers during a Loss of Coolant Accident.
1) Is this a problem for ANY LOCA or for only a LARGE BREAK LOCA?
and 2) How could noble metals affect the analyzers?
a.
1) ANY LOCA 2) Noble metals could cause He and 02 to recombine in the sample line which would tesult in LOWER readings.
,
b.
1) ANY LOCA 2) Noble metals could react like H2 and 02 in the analyzers which would result in HIGHER readings.
.
c.-
1) LARGE BREAK LOCA 2) Noble metals could causc H2 and O2 to recombine in the sample line which would result in LOWER readings.
d.
1) LAnGE BREAK LOCA 2) Noble metals could react like H2 and O2 in the analyzers which would result in HIGHER readings.
ANSWER: C REFERENCE: EOP Defeat 16 K/A System: 500000 K/A Number: EA2.01 K/A Value: 3.1/3.5 Cognitive Level: 1 Distracter 1: Lower reading is correct, but a concern only on a DBA LOCA.
Distracter 2: A concern only on a DBA LOCA; A possible misconception that readings would be higher, but Defeat 16 says they would read lower.
Distracter 3: Large Break is correct; A possible misconception that readings would be higher, but Defeat 16 says they would read lower.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA 12 -
Exam Series A l..
.
..
...
...
.. _ _ _ _
Objective: 95.28.01.04 (NEW for 1998 ILC Retest)
1 Point 13. There are two motor operated containment vent valves; INBD DRYWELL VENT MO-4310A and INBD TORUS VENT MO 4309A.
Which one of the following CORRECTLY describes a situation and reason for throttling closed one or both of these motor operated containment vent valves?
- a.
During an outage Integrated Leak Rate Test (ILRT) while depressurizing the containment from 40 psig, MO-4310A and/or MO-4309A should be throttled closed to control the depressurization rate.
b.
During performance of SEP 301.1, " Torus Vent Irrespective of Rad Release", MO-4309A should be throttled to protect the SBGT suction piping from overpressure.
c.
During performance of SEP 301.1, " Torus Vent Irrespective of Rad Release", after the rupture disc has been burst while using the Hard Pipe Vent, MO 4309A should be throttled fully closed as necessary to sceure the vent flow.
- d.
During performance of SEP 301.2, "Drywell Vent Irrespective of Rad Release", while maintaining Drywell pressure 45-53 psig, MO-4310A should be throttled fully closed at 45 psig to help minimize offsite radioactivity release.
ANSWER: A RLFERENCE: STP 3.6.1.1-02; SEP 301.1;SEP 301.2
. K/A Systemi 295024 K/A Number: EK2.10 K/A Value: 3.5/3.5 Cognitive Level: 2 Note: The RO is not expected to know the ILRT procedure, but he/she should know that these
.MOs are never closed in an emergency because they are from non-essential busses. See P&L.
Distracter 1: It would prevent SBGT overpressure but it is not allowed.
Distracter 2: It would isolate one vent path but it is not allowed and CV 4357 is closed to stop the vent flow.
Distracter 3: This would close a valve or -
vpass vent line but CV-4310 already performs this y
function and it is not allowed.
'
Rev.O Reactor Operator, 50007 01/20/99-Topic 1999 NRC Retest 5799NRCA
- 13 -
Exam Series A
P
~
!
Objective: 12.00.00.07 (NEW for 1998 ILC Retest)
1 Point 14. The plant was operating at full power when an electrical fault tripped the B Recire MG set.
The B Recire pump has been properly secured and the B Recire Pump Discharge Valve re-opened after 5 minutes.
Total Core Flow indication on IC05 will now be derived by subtracting the B Loop Flow from l
the A Loop Flow rather than by adding them.
.
.
Which of the following is the signal used to initiate this change?
i a.
Differential pressure between the two Recire loops.
b.
Interlock with the B Recire Generator Field Breaker.
.
c.
Interlock with the B Recire MG Drive Motor Breaker.
d.
Interlock with the B Recire RPT Breakers.
ANSWER: B.
REFERENCE: 01264 K/A System: 295001 K/A Number: AK3.06 K/A Value: 2.9/3.0 Cognitive Level: 1 Note: The Total Core flow indication uses two summers, one for 2 loop operation and one for SLO.
These summers transfer depending on the position of the Recire MG Field breakers.
Distracter 1: LPCI Loop select uses pump AP to determine if a Recire pump is running.
Distracter 2: I"ausible but incorrect.
Distracter 3: Plausible but incorrect.
Rev.O Reactor Operator, 50007 01/20/99-Topic 1999 NRC Retest 5799NRCA
- 14 -
Exam Series A
g.
Objective: 32.05.02.07 (NEW for 1998 ILC Retest)
1 Point j
15. The plant has been operating at full power for several days.
Operators notice that, over the last several hours, Condenser Backpressure has risen from 2.5 "Hg to 3.5"Hg. Over this same period, Offgas system flow has decreased from 20 scfm to 18 scfm. There have been NO ALARMS associated with this probleni.
' Which of the following could be the cause of these indications?
)
{
a.
Cooling tower outlet temperature increase.
b.
Air leak into the condenser.
c.
One or more blown Offgas loop seals.
.
d.
Offgas premature recombination.
ANSWER: A REFERENCE: ARP IC07, D 9; AOP 672.3 K/A System: 295002 K/A Number: AK1.03 K/A Value: 3.6/3.8 -
Cognitive Level: 3 -
Distracter 1: ' Air leak would cause Backpressure to increase but Offgas flow to increase.
- Distracter 2: Blown loop seals would cause Offgas flow to decrease but not Backpressure increase.
There would also be radiation alarms associated with this problem.
Distracter 3: Premature recombination would'eause Offgas flow to decrease but not Backpressure increase. There would also be several alarms associated with this problem.
Rev.0'
Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 15 -
Exam Series A q
Objective: 19.01.01.03c (NEW for 1998 ILC Retest)
1 Point 16. The plant is in normal full power operation with no LCOs on January 1, 2000, when massive grid instabilities result in the loss of offsite power for the foreseeable future. The plant responds as designed including both Standby Diesel Generators (SBDGs) which have started.
- Diesel fuel oil deliven is uncertain due to infrastructure problems.
Assume the following in your answer:
The Diesel Oil Storage Tank,1T-35, is at its Tech Spec low limit of 30,317 gal.
.
The Auxiliary Boiler Fuel Oil Storage Tank, IT-34, level is 37,000 gal.
.
Power will be'available for necesnry transfer equipment.
.-
Select the answer which CORRECTLY describes how long the SBDGs will be able to operate
- FULLY LOADED if no more fuel can be delivered.
.
a..1 SBDG for 7 days This is at the design fuel consumption rate for the Diesels and IT-35 only; The Boiler fuel in IT-34 is normally too low quality for transfer to IT-35.
b.
2 SBDGs for 7 days This is at the design fuel consumption rate for the Diesels and IT-35 only; The Boiler fuel in IT-34 is normally too low quality for transfer to 1T 35.
c.
2 SBDGs for 7 days
'
This includes an additional 37,000 gallons of Boiler fuel transferred from 1T-34 with fuel being used at the design fuel consumption rate for the Dicaels and IT 35.
d.'
2 SBDGs for'14 days This includes an additional 37,000 gallons of Boiler fuel transferred from IT-34 with fuel being used at the design fuel consumption rate for the Diesels and IT-35.
ANSWER: C REFERENCE: SD-324; 01324 K/A System: 295003:
~ K/A Number: AK2.02
' K/A Value: 4.1*/4.2*
Cognitive Level: 2 Note: =37,000 gal supplies 1 SBDG for 7 days by design.
Distracter 1: This is correct for IT-35 only; However,1T-34 fuel can be transferred.
Distracter 2: This is not correct for IT-35 only; 1T-34 fuel can be transferred.
Distracter 3: This is not correct for IT-35 + 37,000 gal.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 10 -
Exam Series A
l
)
Objective: 94.06.01.02 (NEW for 1998 ILC Retest)
1 Point 17. The plant is operating in a normal full power lineup when annunciator 1C08, A-9,125 VDC SYSTEM 1 TROUBLE activates concurrently with a number of other annunciators which
]
confirm a loss of DC power.
As the BOP operator at 1C08 you identify that 4KV breaker control power has been lost to busses 1A1 and 1A3.
The loss of which one of the following 125 VDC busses would account for this indication?
)
a.
1D10
.
)
b.
1D11 c.
1D13
,
d.
1D14 ANSWER: A REFERENCE: AOP 302.1 K/A System: 295004 K/A Number: AA2.02 K/A Value: 3.5/3.9 Cognitive Level: 3 Note: A DAEC operator would be expected to diagnom the extent of the 125 VDC problem by observing 4KV control power availability.
Distracter 1: Would result in the loss ollAl control power only.
Distracter 2: Would result in the loss of 1A3 control power only.
Distracter 3: Homogenous distracter. Supply to RCIC; no affect on control power.
i Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA 17 -
Exam Series A
Objective: 95.85.04.03 (NEW for 1998 ILC Retest)
1 Point 18. The crew is performing RPV Flood actions in response to a design basis LOCA that has been complicated by equipment problems.
Which of the following is NOT A CONCERN when raising RPV level?
a.
Thermal shock damage to the hot metal of the steam lines.
b.
Exceasive loading on MSL hangers not designed for the weight of water.
c.
Induction of water and subsequent damage to the Main Turbine, d.
Two-phase flow damage to the open SRVs.
ANS% 2R: D
.
REFERENCE: RPV/F-15 & 16; EOP Program Manual, RPV/F section, rev. 3; 01 183.1 P&L 4 K/A System: 295008 K/A Number: AK2.11 K/A Value: 3.1/3.3 Cognitive Level: 2 Note: Two-Phase flow is a concern during manual SRV operation, but not when directed by EOPs.
Distracter 1: Paraphrase of one of the three bases for closing the MSIVs during RPV/F.
Distracter 2: Paraphrase of one of the three bases for closing the MSIVs during RPV/F.
Distracter 3: Paraphrase of one of the three bases for closing the MSIVs during RPV/F.
Rev.0'
Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 18 -
Exam Series A
,
Objective: 95.14.01.04 & 07 (NEW for 1998 ILC Retest)
1 Point 19. The plant was in normal full power operation when a large line break LOCA occurred. The
)
plant responded as designed and operators have restored RPV level to +40".
-
Operators have also initiated containment sprays to reduce Drywell pressure and temperature from their maximum values of 24 psig and 300 F (average). The OSS directs that EOP Defeat 4 "Drywell Cooler Isolation Defeat" be installed in order to be able to secure i
Drywell sprays.
The Balance of Plant operator verifles that two Well Water pumps are running and then, at panel 1C-25, places both Defeat 4 keylock handswitches in the OVERRIDE position. He then j
verifies that the Drywell Cooling Well Water Supply and Return valves, CV 5718A&B and
'
CV-5704A&B, reopen.
1) Will the Drywell Cooling fans automatically restart in fast speed? (YES or NO)
and 2) Has Defeat 4 been properly installed? (YES or NO)
'
-
a.
1) YES
'
2) YES b.
1) YES 2)NO c.
1)NO 2) YES d.
1) NO 2)NO ANSWER: D REFERENCE: EOP-2; EOP Defeat 4; SD-700 K/A System: 295012 K/A Number: AA1.02 K/A Value:3.8/3.8 Cognitive Level: 3 Distracter 1: Fans will not start with DW Sprays on. Manual Well Water isolation valves must be closed and reopened slowly to avoid water hammer if Drywell temperature was s280 F.
Distracter 2: Fans will not start with DW Sprays on.
Distracter 3: Manual Well Water isolation valves must be closed and reopened slowly to avoid water hammer if Drywell temperature was >280 F.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest l
5795NRCA -
- 19 -
Exam Series A
,
r Objective: 99.28.01.08 (NEW for 1998 ILC Retest)
1 Point 20. The plant is in normal full power operation with no LCOs when the annunciator activates for i
l SRV/SV TAILPIPE HI PRESS OR HI TEMP (IC03A, C-5). Operators confirm that a Lo-Lo l
Set SRV is partially open.
They complete a fast power reduction to < 75% power and cycle the handswitch with no result. They also start RHR in the Torus cooling mode at maximum cooling capacity. Torus average water temperature was increasing slowly but has STABILIZED at 85 F since Torus cooling.was placed in service.
Must the reactor be SHUTDOWN or can the plant CONTINUE OPERATION?
If SHUTDOWN, identify the CORRECT means of performing the shutdown.
If CONTINUE OPERATION, CORRECTLY identify how long operation can continue.
a.
SHUTDOWN
.
Reduce core flow to 24 Mlb/Hr. and manually scram the reactor.
b.
SHUTDOWN Perform a controlled power reduction per IPOI-3 and shutdown per IPOI-4.
c.
CONTINUE OPERATION For up to 7 days (the length of the LPCI inoperability LCO) and then a controlled power reduction per IPOI 3 and shutdown per IPOI-4.
d.
CONTINUE OPERATION Indefinitely as long as average Torus water temperature remains < 110 F.
ANSWER: A REFERENCE: ARP 1C03A, C-5 K/A System: 295013 K/A Number: AK3.02 K/A Value: 3.6/3.8 Cognitive Level: 2 Note: A DAEC RO would be expected to know that a scram is directed if SRV cannot be closed.
Distracter 1: Plausible since temp has stabilized, but ARP directs immediate scram.
Distracter 2: Plausible since temp has stabilized, but ARP directs immediate scram.
Distracter 3: Plausible since temp has stabilized, but ARP directs immediate scram.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
-
5799NRCA
- 20 -
Exam Series A
i n
!
Objective: 94.28.06.01 (NEW for 1998 ILC Retest)
1 Point i
21. See the 480 VAC schematic on the next page.
A series of electrical switching operations take place when energizing the Inboard Shutdown Cooling Isolation valve, MO-1908, for establishing Shutdown Cooling from 10-388.
l LWhich of the following CORRECTLY outlines the breaker manipulations to' accomplish this?
i a. ~ Open' 1B4401.'
Open 1B3400.
_
Reclose 1B4401.
Close IB3401 to energize the bus for MO 1908.'
Leave in this alignment after MO-1908 has been operated.
.
b. ; Open IB4401.
Open IB3400.
Open 1B3401 -
Reclose 1B4401 to energize the bus for MO 1908.
Leave in this alignment after MO-1908 has been operated.
~.
Open 1B4401.
c Open IB3400.-
Open 1B3401.
Reclose IB4401 to energize the bus for MO-1908.
'
. Reopen IB4401 after MO-1908 has been operated.
i
d.'
Open IB3400.
' Open 1B340L Close 1B4401.
,
!
Reclose IB3400 to energize the bus for MO 1908.
' Reopen IB3400 after MO-1908 has been operated, i
ANSWER: A --
REFERENCE: AOP 915
,
K/A SYSTEM: 295016 K/A NUMBER: AA1.04 K/A VALUE: 3.9/3.9 Cognitive Level: 2 Distracter li Possible misconception that MO-1908 is from 1B34A.
.
Distracter 2: Possible misconception that MO 1908 is from 1B34A. Reopening 1B4401 would deenergize IB34A &lB44A, the swing bus for LPCI inject valves.
Distracter 3:Possible misconception is that IB34 is reenergized through IB3400.
This is wrong because 1C388 is entirely Div 2 and this outline relies on a Div 1 power source.
!
Rev.' 0 -
Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest
'
5799NRCA'
- 21 -
Exam Series A
M'.
.
-
Objective: 95.00.00.22 (Revised, from a 1998 Quad City ILC exam.)
1 Point 22. Which of the following is the MINIMUM Emergency Plan event classification for entry into EOP-4, " Radioactive Release. Control"?
EOP-4 is entered when the offsite radioactivity release rate is above the rate which requires the declaration of...
a.
an Unusual Event.
b.
an Alert.
c.
a Site Emergency d.
a General Emergency.
ANSWER: B
'
REFERENCE: EOP-4 K/A System: 295017 K/A Number: Generic 2.4.1 K/A Value: 4.3/4.6 Cognitive Level: 1 l
Distracter 1: Homogeneous distracter; EOP-4 entered at Alert.
Distracter 2: Homogeneous distracter; EOP-4 entered at Alert.
I Distracter 3: Homogeneous distracter; EOP-4 cntered at Alert.
Rev.O Reactor Operator,50007
'
01/20/99 Topic 1999 NRC Retest 5799NRCA
- 22 -
Exam Series A
<,
Objective: 94.10.01.01 (NEW for 1998 ILC Retest)
1 Point 23. The plant had been operating at full power for several months with no inoperable equipment.
Within one hour of the end of the previous shift, a TOTAL LOSS of General Service Water j
occurred.
~ The operators manually scrammed the reactor and took appropriate actions to stabilize the plant. The Main Turbmc was placed on the Turning Gear when the rotor speed was less than 1.5 RPM. The relieving crew was called at home, told of the transient, and asked to report early for their shift.
Considering the effects of the loss of GSW on the plant, which one of the following will the relief Reactor Operator NOT FIND when he/she entered the control room?
The relief Reactor Operator WILL NOT FIND...
a.
both EHC pumps secured.
.
b.
HPCI and/or RCIC being used for RPV pressure control with the MSIVs closed.
c.
the RWCU system being used in the drain mode for RPV level control.
d.
Recire pump Mini purge secured for RPV thermal stratification concerns.
i ANSWER: C
,
l REFERENCE: AOP. 411; IPOI 5; OI 693.3 K/A System: 295018 K/A Number: AK2.02 K/A Value: 3.4/3.6
)
Cognitive level: 3 Note: AOP 411 directs shutdown of RWCU It is a large heat load on RBCCW which has lost its j
GSW cooling. The Non-regen heat exchanger uses RBCCW cooling. The AOP also direct i
shutdown of GSW loads that are not necessary with the Rx shutdown.
Distracter 1: Should be expected because the EHC system is not necessary with the Rx shutdown and the turbine tripped.
Distracter 2: Should be expected because the MSIVs would close on a Steam Tunnel high temperature Group 1 Isolation due to loss of GSW cooling. EOPs do not allow defeat of this isolation. HPCI and/or RCIC would then be used in CST-CST for pressure control.
Distracter 3: Should be expected because AOP 411 directs tripping of Recire pumps. IPOI 5 directs mini-purge isolation when Recire pumps are off and thermal stratification is a concern.
Rev.O Reactor Operator,50007-01/20/99'
Topic 1999 NRC Retest 5799NRCA 23-Exam Series A u
-
I Objective: 94.17.01.01 (NEW for 1998 ILC Retest)
1 Point l-24. The Instrument Air system is in normal operation with Instrument Air Dryer IT-265A in service.
If the NSPEO were to mistakenly place the power switch for IT-265A, HS-3046A, in the OFF
. position, would there be an immediate LOSS ofInstrument Air Header pressure?
(LOSS or NO LOSS)
l
!
If LOSS, identify the CORRECT effect on IT-265A and/or IT-265B and the operator action (s)
necessary to maintain Instrument Air Header Pressure.
IfIJO LOSS, identify the CORRECT reason that header pressure is maintained.
a.
LOSS; Both drying chambers of IT 265A isolate so the operator must open the manual bypass valve around IT 265 A & B. (Until IT 265A pressures can be equalized and the
_
drying chamber returned to service)
.
b.
LOS3,. ae Purge Exhaust Valves for both drying chambers on IT-265A fail open so the operator must close the manual Purge Exhaust isolation valves.
c.
NO LOSS; Loss of power to 1T-265A automatically places the standby dryer IT-265B in service.
d.
NO LOSS; Loss of power to IT-265A places both ofits drying chambers in service and closes the purge Exhaust valves.
ANSWER: D.
- REFERENCE: AOP 518; SD-518; OI-518 K/A System: 295019 K/A Number: AA1.02 K/A Value:3.3/3.1 Cognitive Level:.2 Distracter 1: Drying chambers do not isolate.
Distracter 2: Purge exhaust valves do not fail open.
Distracter 3: The standby dryer is in OFF and must be manually started.
l-
,
l-L Rev.O Reactor Operator, 50007
- 01/20/99 Topic 1999 NRC Retest 5799NRCA-
- 24 -
Exam Series A
-
Objective: 48.01.01.01 (Revised, from a 1998 Clinton audit exam.)
1 Point 25.' Given the following initial plant conditions:
i A reactor startup is in progress.
.
The Mode switch is in the START & HOT STBY position.
.
The Main Turbine is in shell warming.
.
.
At this point a VALID isolation signal causes a~ complete Group 1 Isolation.
.
.
.
The RPS system RESPONDS AS DESIGNED and does NOT scram the reactor because there i
'is no scram signal present.
l Which of the following Group 1 signals is the only one which could have generated the
' complete Group 1 Isolation described above?
.
- a.
Low Main Steam Line pressure b.
Low reactor water level
c.
- High Turbine Bldg. Ambient Temperature i
d.. High Main Steam Line Radiation ANSWER: C
'
i REFERENCE: ARP IC05B, A-2 & A-8 K/A System: 295020 K/A Number: AA2.06 K/A Value: 3.4/3.8 Cognitive Level: 2 Distracter 1: Mode Switch must be in RUN to enable this isolation.
. Distracter 2: The reactor would have scrammed at 170".
Distracter 3: This was a full Group 1 signal for 20 years but now only closes MSL drains and Recirc sample and trips the Mechanical vacuum Pump.
Rev.O Reactor Operator, 50007 01/20/99._
Topic 1999 NRC Retest 5799NRCA
- 25 -
Exam Series A
r)
l Objective: 10.01.01.01 (Revised from DAEC Exam Bank)
1 Point 26. EOP 1 has been entered during a loss of coolant accident. No CRD pumps are running and the reactor building is NOT ACCESSIBLE.
Which of the following CORRECTLY describe the 1C05 operator actions necessary to restart the first CRD pump for RPV injection?
I a.. OPEN the DRIVE WATER AP CONTROL, MO-1830, Adjust the CRD SYSTEM FLOW CONTROL, FC-1814, to O gpm in MANUAL, then start the pump.
!
b.
OPEN the DRIVE WATER AP CONTROL, MO-1830, verify that the CRD SYSTEM FLOW CONTROL, FC-1814, is in AUTO, then start the pump.
.
c.
CLOSE the DRIVE WATER AP CONTROL, MO 1830, adjust the CRD SYSTEM FLOW CONTROL, FC-1814, to 0 gpm in MANUAL, then start the pump.
d.
CLOSE the DRIVE WATER AP CONTROL, MO-1830, verify that the CRD SYSTEM FLOW CONTROL, FC 1814, is in AUTO, then start the pump.
ANSWER: C REFERENCE: 0I-255 K/A System: 295022 K/A Number: AA1.01 K/A Value: 3.1/3.2 Cognitive level: 3 Distracter 1: Both the MO and FC must be closed.
Distracter 2: Both the MO and FC must be closed.
Distracter 3: Both the MO and FC must be closed i
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-2G-Exam Series A
'
p Objective: 95.50.01.01 (Revised, from 1998 Hope Creek ILC exam.)
1 Point 27. During an ATWS transient in which heat is being added to the torus, Standby Liquid Control is initiated prior to reaching the Boron Injection Initiation Limit, Graph G.
Which of the following CORRECTLY identifies the basis for this action?
This action assures that the Hot Shutdown Boron Weight is injected before the Torus...
a.
heat capacity temperature limit is exceeded, b'.
dynamic load limit is exceeded.
,
c.
pressure suppression pressure limit is exceeded, d.
LOCA blowdown limit is exceeded.
,
ANSWER: A REFERENCE: EOP Bases K/A System: 295026 K/A Number: EK3.04
K/A Value: 3.7/4.1*
Cognitive Level: 1 Note: All distrac+ers are EOP concepts related to the Torus, i.e. homogeneous distracters.
Distracter 1: Formerly called SRV Tailpipe limit, has more to do with Torus level. This graph was recently deleted at DAEC.
Distracter 2: Indicates failure of containment response; water temp is not on this graph.
Distracter 3: A LOCA blowdown will add a great amount of heat to the Torus, but there is no limit associated with this.
Rev.O Reactor Operator, 50007 01/20/09 Topic 1999 NRC Retest 5799NRCA.
- 27 -
Exam Series A
Objective: 95.59.03.01 (NEW for 1998 ILC Retest)
1 Point 28. A loss of Drywell cooling occurred, causing the crew to scram (successfully) from 100% power.
L
. When Average Drywell Air temperature could not be restored and maintained <280 F the
'
crew Emergency Depressurized the RPV. The OSS has performed a crew brief to inform the crew that the Sat Curve (EOP-2, Graph 1) has been entered.
l l
The following applicable parameters are at these stable values:
. Both Recire pumps are tripped.
.
Indicated NR GEMAC RPV level 190"
.
Indicated WR Yarway RPV level 200"
.
Indicated WR GEMAC (Floodup) RPV level 200" h
.
i Indicated Fuel Zone RPVlevel 190"
.
Which value for RPV water level, if any, should be used for EOP decision-making purposes?
a.
107" i
'
b.
190" c.
200" d.
None, all RPV level indicators should be considered unreliable.
ANSWER: A i
REFERENCE: EOP-2; EOP-2 Bases K/A System: 295028 K/A Number: EK1.01 -
K/A Value: 3.5/3.7 Cognitive Level: 2
. Note: This strategy has changed drastically since the ILC exam. See training material for full
. explanation.
I
' Distracter 1: Indicators can be used but only with a 23" penalty.
Distracter 2: WR Yarway cannot be used after ED; WR GEMAC cannot be used until TSC evaluates.
Distracter 3: Possible misconception; this was the correct answer for 4 years until the last rev of EOP 2. Levelindication reliability should be questioned, but indications are stable, thus OK.
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 28 -
Exam Series A
F
,
Objective: 95.12.01.06 (NEW for 1998 ILC Retest)
1 Point 29.1) Which source of water is preferred for the HPCI suction during performance of EOP 1,
"RPV Control"? (CSTs or TORUS)
And
-
2) Identify a stated basis for the answer to part 1 of this question.
l i
a.
1) CSTs 2) Overrides can be installed to maintain a CST suction, which prevents disruption of HPCI operation during suction transfers, b.
1) CSTs 2) The CSTs provide higher quality water than the Torus, c.
1) TORUS 2) The Torus contains a large volume of water than the CSTs.
-
d.
1) TORUS 2) The Torus suction will be at a higher pressure than the CSTs during a LOCA.
ANSWER: B REFERENCE: EOP 1, SD152; ARP IC03B, D-9 K/A System: 295029 K/A Number: Generic 2.4.6
- K/A Value:3.1/4.0 Cognitive Level: 2 Distracter 1: CST is correct and Defeat 2 will prevent suction transfers, but this is not a stated i
basis.
Distracter 2: The Torus is a larger volume but the CSTs are preferred.
Distracter 3: The Toras suction may possibly be a + higher pressure during a LOCA but the CSTs are preferred.
,
t l
,
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA.
- 29 -
Exam Series A
Objective: 94.29.01.02 (NEW for 1998 ILC Retest)
1 Point 30. Can Torus water level be read at the following in plant locations? (Yes or No)
1) At 10-388, the Remote Shutdown Panel 2) At 1C-208, Reactor Bldg. North by CRD hatch.
3) At 10-142,in the Southwest corner of the 1A4 Switchgear Room.
a.- 1) Yes 2) Yes -
3) No b.
1) Yes 2) No.
3) Yes c.
1) No
,
2) Yes 3) No d.
1) No 2) No 3) Yes ANSWER: A REFERENCE: AOP-915; K/A System: 295030 K/A Number: EA2.01 K/A Value: 4.1*/4.2*
Cognitive Level: 1.
Note: Can be read from 10-388 and 1C-208.1C-142 holds the emergency fuses for Torus level and temp, but not levelindication. Each area is yes twice and no twice.
Distracter 1: 1C-208 is yes;10-142 is no.
Distracter 2: 10 388 is yes; Distracter 3: 10-388 is yes;10-208 is yes;10-142 is no.
l
,
l Rev.O Reactor Operator,50007 l
!
-.01/20/99 Topic 1999 NRC Retest
.5799NRCA
- 30 -
Exam Series A
!
Objective: NSPEO 48.02 (NEW for 1998 ILC Retest)
1 Point 31. A LOCA has occurred and you are being dispatched from the Control Room to take emergency action in the Reactor Bldg. You take a " Fast Entry" Electronic Dosimeter (ED) as you pass through Access Control.
Assume that, as an RO licensed Control Room operator, you would normally enter the plant on Radiation Work Permit (RWP) 10, Job Step 2, which sets the ED at a Dose Alarm of 50 mR and a Dose Rate Alarm of 90 mR/Hr.
Will the alarm settings on the " Fast Entry" ED be THE SAME or HIGHER than the normal settings?
a.
Dose Alarm THE SAME Dose Rate Alarm THE SAME
.
b.
Dose Alarm THE SAME Dose Rate Alarm HIGHER c.
Dose Alarm HIGHER Dose Rate Alarm THE SAME d.
Dose Alarm HIGHER Dose Rate Alarm HIGHER ANSWER:' D REFERENCE: RWP 30, Job Step 6 K/A System: 295033 K/A Number: EK1.02 K/A Value: 3.9/4.2*
Cognitive Level: 1 Note: RWP 30, Job Step 6 fast entry dosimeters are set at 100/2500. It is reasonable to expect that an RO would know this when taking a Fast Entry ED when responding to an emergency which involves abnormal rad conditions.
Distracter 1,2, & 3: Both settings are higher on Fast Entry EDs.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-31-Exam Series A
Objective: 94.25.05.04 (NEW for 1998 ILC Retest)
1 Point 32. AOP-913, " Fire", contains instructions for manual realignment of the discharge dampers of the CONTROL ROOM SUPPLY FANS, IV-AC-30A&B.
j Which of the following is A CORRECT USAGE of these instructions?
i IV AC-30A&B discharge dampers are overridden...
a.
CLOSED as part of the procedure to maintain the Control Bldg. at a positive pressure.
b.' CLOSED as part of the procedure to keep Cardox (CO2) out of the Control Room.
c.
OPEN
,
as part of the procedure to provide emergency cooling for the Control Room.
d.
OPEN as part of the procedure to provide emergency ventilation for the Battery rooms.
ANSWER: C REFERENCE: AOP 913 K/A System: 600000 K/A Number:. AK3.04 K/A Value: 2.8/3.4 Cognitive Leveh 1 Note: These dampers are overridden closed when damper control is lost and open when ESW cooling is lost. In either case, the purpose is to cool the control room.
Distracter 1: Not the purpose of these instructions. Maintaining the CB positive is a good thing but there are no emergency instructions to do this.
Distracter 2: CB dampers auto isolate when Cardox initiates. Not the purpose of these
. instructions Distracter 3: Emergency Battery ventilation is a concern during a fire, but it is not the purpose of these instructions.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA '
- 32 Exam Series A
l Objective: 94.01.01.02 (NEW for 1998 ILC Retest)
1 Point i
33. An earthquake has caused structural damage to the Reactor Building. A normal reactor shutdown and cooldown was performed. The plant entered MODE 4 four hours ago,32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> after Secondary Containment was declared inoperable. RHR is in the Shutdown Cooling mode in parallel with one Recire pump.
'
l At this point, a pipe rupture occurs in the Shutdown Cooling line between the Shutdown -
Cooling isolation valves, MO-1908 & MO 1909, and the RHR pump suctions.
'
The OSS directs the following:
Place RHR in the Torus Cooling mode.
.
. ' Verify the HPCI and RCIC Steam Supply valves closed.
Verify the Head Vent valves closed.
.
' Begin injection with the A Core Spray pump to establish SR Dow.
.
How many SRVs must be opened and what is an appropriate RPV pressure control range for this plant condition?
a ' Open one (1) SRV and control pressure 50-60 psig.
b.
Open one (1) SRV and control pressure 120-130 psig.
c.
Open three (3) SRVs and control pressure 50-60 psig.
d. ' Open three' (3) SRVs and control pressure 120130 psig.
ANSWER: A -
REFERENCE: AOP 149 K/A System: 295021
. K/A Number: AA1.04 K/A Value: 3.7/3.7 Cognitive Level: 3.
' Nete: AOP 149 says to open one SRV and maintain RPV pressure 50 psig > Torus pressure (=1 psig).
- Distracter 1: Correct number of SRVs, but pressure from RPV Flood EOP and is too high.
' Distracter 2: Correct pressure, but number of SRVs is from RPV Flood EOP and is incorrect.
Distracter 3: Number of SRVe is from RPV Flood EOP and is incorrect. Pressure from RPV Flood EOP and is too high.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 33 -
Exam Series A
E l
Objective: 98.02.01.03 (NEW for 1998 ILC Retest).
1 Point 34. Refueling operations are in progress. The Cattle Chute is installed and core alterations have begun.
. Would there be any radiological control restrictions on personnel access inside the Drywell?
If YES, identify the CORRECT restriction.
If NO, identify the CORRECT reason that restrictions have been eliminated.
a.. YES; Access to the upper levels of the
'vellis restricted during fuel movement.
b.
YES; Access to the entire Drywellis ret ted during fuel movement.
c.
NO; there are no restrictions because the Cattle Chute is installed.
d.
NO; there are no restrictions because the refueling cavity is ilooded.
ANSWER: A REFERENCE: RFP 403 K/A System: 295023 K/A Number: AKl.01
,
K/A Value: 3.6/4.1 Cognitive Level: 1 Note: Access.to the entire Drywell was restricted before the Cattle Chute was implemented. It shields the cavity floor between the RPV and the Fuel Fool, which allows access to all but the upper levels of the Drywell during fuel and highly radioactive component movement.
Distracter 1: Yes, but only the upper levels of the DW.
Distracter 2: Even with the cettle chute installed access to the upper levels is restricted.
Distracter Si Possible misconception. Flood up does provide some shielding but not enough.
Rev.O Reactor Operator,50007
'01/20/99 Topic 1999 NRC Retest
. 5799NRCA 34 -
Exam Series A
Objective: 75.01.01.04 (NEW for 1998 ILC Retest)
1 Point 35.' Assume the following area high temperature' conditions were to occur while the plant was in normal full power operation.
In each case IC04B, B-4, STEAM LEAK DET AMBIENT HI TEMP should activate.
i Evaluate each case and identify the CORRECT response, if any, of associated PCIS isolation
'
)
. valves.: Would there be NO ISOLATION, a PROMPT (within a few seconds) isolation, or a DELAYED isolation?
Case 1) Ambient temperature above the TIP room exceeds 111.5*F.
Case 2) Ambient temperature near the Torus catwalk exceeds 150 F.
a.
1) PROMPT 2) NO ISOLATION
'
-
,
b.
1) PROMPT
<
2) DELAYED c.
1) NO ISOLATION 2) NO ISOLATION d.
1) NO ISOIATION 2) DELAYED i
l ANSWER: B REFERENCE: ARP 3 003C, A-8;1C040, A-7; IC05B, E-8; OI-358, P&L #3 K/A System: 295032 -
K/A Number: EK2.04 j
K/A Value: 3.6/3.8 Cognitive Level: 1 Note: RWCU isolates after a 3 second TD. Torus catwalk v ill isolate HPCI and RCIC but only after 15 min. and 30 min. time delays. EOP-3 is provided for another question but RO must recognize Max Normal setpoints are also high temp isolation setpoints.
Distracter 1: 2) is delayed.
Distracter 2: 1) is prompt; 2) is delayed.
Distracter 3: 1) is prompt.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA -
35-Exam Series A
>
L Objective: 95.70.07.02 (NEW for 1998 ILC Retest)
1 Point 36. The RHRSW pipe in the HPCI room develops a leak and the HPCI Room water level starts to
rise above floor level.
As HPCI Room level continues to increase, which of the following WOULD NOT be an
' expected indication of this problem in the Control Room? (Assume no operator action.)
i
a.
Increasing level indicated on a HPCI Room water level indicator.
b. -- Activation of annunciator 1C04C, A-2, REACTOR BLDG FLOOR DRAIN SUMP HI LEAKAGE.
c.
Activation of annunciators 1C14A, B-4, AREA WATER LEVELS ABOVE MAX NORMAL and A 4, AREA WATER LEVELS ABOVE MAX SAFE.
'
t DC electrical grounds and/or HPCI component breaker trips.
ANSWER: B REFERENCE: EOP-3 Bases; ARP 1014; ARP 10-147 K/A System: 295036
- K/A Number: EK3.04 -
K/A Value:3.1/3.4 Cognitive Level: 1 Note: Drain valves from individual equipment rooms, like HPCI, are normally closed and locked '
out to prevent cross flooding of unaffected rooms. The HPCI Room sump hilevel will alarm in Radwaste, but water will not transfer to the RB Floor Drain sump until the Radwaste operator takes action. A DAEC RO should know this. K/A tests knowledge of secondary containment sumps.
Distracter 1: Indicated on LI-3768 on 1C21.
Distracter 2: Activated by LS-3768 in HPCI Room.
Distracter 3: The definition of Max Safe levelimplies damage to safe shutdown equipment iflevel above this limit.
l (-
l Rev.O Reactor Operator, 50007 01/20/99 -
Topic 1999 NRC Retest
- 5799NRCA-36-Exam Series A '
i p
Objective:95.50.01.01 (NEW for 1998 ILC Retest)
1 Point l
37. As the Panel IC05 operator'during an ATWS, you are directed to perform RIP 103.2,
" Increase CRD Cooling Flow and Pressure".
-
.1)Is MO 1830, DRIVE WATER AP CONTROL, adjusted OPEN or CLOSED as part of this I
procedure?
l AND 2) What is the stated purpose of this action?
a.~ 1) OPEN 2) To cause the control rods to insert faster when manually driving them in.
b.
1)OPEN 2) To cause the control rods to drift in.
c.
1) CLOSED -
.
2) To cause the control rods to insert faster when manually driving them in.
d.
1) CLOSED 2) To cause the control rods to drift in.
ANSWER: B REFERENCE: RIP 103.2 K/A System: 201001 K/A: A4.04 K/A Value: 3.1/3.0 Cognitive Ievel: 2
- Note: This question reflects a recent change to the RIP. This step was not in place at the time of the 1998 ILC exam. The stated purpose of this action is to drift the rods in by increasing Cooling water flow and pressure (by opening the MO). Closing the MO increases AP and causes the rods to drive faster Distracter 1: Open is correct but rods will not drive faster if this is done.
Distracter 2: Closed is incorrect; rods will drive faster but this is not the stated purpose.
Distracter 3: The stated purpose is correct but Closed is incorrect.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 37 -
Exam Series A
..
.%
Objective: 72.03.01.08 (NEW for 1998 ILC Retest)
1 Point 38. It is late in core life. A reactor startup is in progress with power in the sourco range.
Operators have been using continuous rod withdrawal and have just completed withdrawal of the Group 2 control rods.
The Source Range Monitors have responded as follows:
SRM counts:
CSRM D SRM Initial:
60
60
'
Current:
300 350
'320 330
)
l
'
Which of the following describes the PROCEDURALLY CORRECT method of control rod
- withdrawalin this condition?
Continuous rod withdrawal until any SRM count rate increases to 500 cps.
a.
b.
Single notch rod withdrawal until any SRM count rate increases to 600 cps.
c.
' Single notch rod withdrawal until 50% rod density.
d.
Group notch rod withdrawal from this point on.
- ANSWER: D REFERENCE: IPOI-2, Step 22 K/A System: 201002 K/A Number: Generie 2.2.2 K/A Value:4.0/3.6 Cognitive Level: 2 Note: Group notch required when >75% density.
~
Distracter 1: Continuous was correct up to this point.
Distracter 2: Single notch would have been correct >600 cps but < 75% density.
l Distracter 3: Single notch would have been correct >600 cps but < 75% density.
l l
l
!
!
!
Rev.O Reactor Operator, 50007 j
01/20/99.
Topic 1999 NRC Retest j
~ 5799NRCA '
38-Exam Series A c
]
-
-
Objective: 12.00.00.03 (From a 1996 LOR exam.)
1 Point i
39. The plant was operating at 100% power with the following values on the Recire Pump Speed controls:
Weston (millivolts)= 49.8 Pump Speed (P) = 100 Speed Demand (S) = 100 A motor controllogic failure then caused the discharge valve on the B Recirc pump to go closed, causing a Runback. Select the set of B Recire Pump Speed control values that an operator would expect to find after such an event.
a.
Weston (millivolts)= 12.5 (20% signal)
Pump Speed (P) = 25.3 (20% speed)
Speed Demand (S) = 25.3
.
b.
Weston (millivelts)= 22.8 (45% signal)
Pump Speed (P) = 45.4 (45% speed)
Speed Demand (S) = 45.4 c.
Weston (millivolts)= 49.8 Pump Speed (P) = 25.3 (20% speed)
(
Speed Demand (S) =100 d.
We.w (millivolts)= 49.8 Pt _.i Spead (P)
=45.4 (45% speed)
Speed Demand (S) = 100 ANSWER: A
,
REFERENCE: SD 264, Figure 18 K/A System: 202002 K/A Number: K6.03 K/A Value: 2.8/2.8 Cognitive Level: 2 Notei RO must know that discharge valve closure is a 20% runback and that, unlike a 45%
runback, a 20% runback drives the controller speed demand back to 20%.
Distracter 1: 20% runback not 45%. Also, millivolts and (S) do not change on a 45% runback.
L Distracter 2: (S) and millivolts signals have not changed. Both would respond to a 20% runback.
I'
Distracter 3: 20% runback not 45%. Readings would be correct fue a 45% runback.
!
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
,
f 5799NRCA 39-Exam Series A r
E
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Objective: 2.02.01.02 (From 1998 LOR exam.)
1 Point 40. The plant was operating at 100% power, when a spurious turbine trip occurred. Shortly after the turbine trip, the dry well pressure rose to >2 psig due to a seal failure on the B Rer:,
Pump. The following plant conditions currently exist:
RPT Breakers Open
.
RPVlevel 189" steady
.
RPV pressure 940 psig steady
.
D/W pressure 2.9 psig rising slowly
.
Loop A Recire riser pressure minus Loop B Recire riser pressure = 0.5 paid
.
Which of the following statements concerning LPCI LOOP select is CORRECT?
a.
The "B" RHR loop will be selected.
,
b.
The "A" RHR loop will be selected.
c.
Neither RHR loop will be selected until RPV pressure lowers further.
d.
Neither RHR loop will be selected until RPV level lowers further.
ANSWER: C REFERENCE: 01149 Rev 58 K/A System: '203000 K/A Number: A3.07 K/A Value: 4.2*/4.G*
Cognitive Level: 3 Distracter 1: Neither loop will be selected until RPV pressure lowers to <900 psig Distracter 2: Neither loop will be selected until RPV pressure lowers to <900 psig Distracter 3: Loop select logic is already initiated, it still needs RPV pressure to be <900 psig Rev, O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-40-Exam Series A
'
Objective: 5.06.01.02 (Revised from a 1996 LOR exam.)
1 Point
,
41. The HPCI INBD and OUTBD STEAM LINE ISOL VALVES, MO-2238 and MO-2239, go
.
closed upon receipt of the signals listed below.
Which one of these signals DOES NOT seal-in?
a.
HPCI Equipment Room Ambient High Temperature
- b.
HPCI Steam Line Low Pressure c.
HPCI Steam Line High Differential Pressure d.
HPCI Exhaust Diaphragm High Pressure ANSWER: B
.
REFERENCE: SD 152;01-152 K/A SYSTEM: 206000 K/A NUMBER: A2.10 K/A VALUE: 4.0/4.1 Cognitive Level: 1 Distracter 1: This is a valid isolation signal which seals in.
, Distracter 2: This is a valid isolation signal which seals-in.
Distracter 3: This is a valid isolation signal which seals-in.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-41-Exam Series A
I Objective: 4.01.01.01 (NEW for 1998 ILC Retest)
1 Point 42. The RHR/ Core Spray Fill Pump,1P 70, becomes inoperable during power operations.01-151,
" Core Spray", provides several options for maintaining the discharge piping filled.
Which of the following IS NOT one of these options?
a.
Use installed Condensate Service connections directly into the Core Spray System as a pressure source, b.
Use Demineralized Water through a Mechanical Jumper (hose)into a Core Spray vent line as a pressure source.
c.
Use a running RHR pump crossconnected through the keep filllines as a pressure source.
d.
Use installed Condensate Service connections to the RHR system crossconnected tl. rough
- the keep filllines as a pressure source.
ANSWER: A REFERENCE: 01-151 K/A System: 209001 K/A Number: K1.03 K/A Value: 2.9/3.0 Cognitive Level: 1 Note: There are no installed Condensate Service connections to Core Spray, therefore, no procedure.
Distracter 1: Directed by Section 0.2 Distracter 2: Directed by Section 9.1 Distracter 3: Directed by Section 9.1 Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-42-Exam Series A
_
l l
i Objective: 6.00.00.03 (NEW for 1998 ILC Retest)
1 Point j
43. A transient has occurred while at power which has resulted in a hydraulic ATWS and a Bus 1A3 lockout. The 1C05 operator initiates Standby Liquid Control (SBLC) as directed.
,
i Which of the following CORRECTLY describes the expected condition of the SBLC Squib valves based on their respective power supplies?
a.
Both will have actuated; they ura powered from respective divisions of 125 VDC.
i b.
Both will have actuated; they are powered from Uninterruptible AC.
I c.
Only one will have actuated; it is powered from B RPS.
d.
Only one will have actuated; it is powered from its associated pump breaker on IB44.
'
ANSWER: D REFERENCE: ARP IC05A, F-3 K/A System: 211000 K/A Number: K2.02 K/A Value: 3.1/3.2 C gnitive Level: 1
Distracter 1& 2: No power to A SBLC pump / Squib valve due to 1A3 lockout; power supplies are 1B34 &lB44.'
Distracter 3: Power supplies are 1B34 &lB44.
l
Rev.O Reactor Operator, 50007 01/20/09 Topic 1999 NRC Retest 5799NRCA-43-Exam Series A
!
!
Objective: 22.00.00.07f (NEW for 1998 ILC Retest)
1 Point
44. A turbine trip from full power has caused a reactor scram. RPV levellowered to 110" during the initial transient but has been restored to the normal operating band for two minutes. The scram has NOT BEEN RESET.
Select the answer which CORRECTLY describes the status of the RPS Backup Scram valves in this plant condition.
Both Backup Scram valves should be...
a.
energized and OPEN b.
energized and CLOSED i
c.
deenergized and OPEN i
'
d.
deenergized and CLOSED i
ANSWER: A REFERENCE: SD-358 j
K/A System: 212000 K/A Number: A1.08 K/A Value:3.4/3.4 Cpgnitive Level: 1
'
Note: ARI solenoids would have also have energized to vent, but would reset after 45 seconds.
Distracter 1: Backup scram valves would be energized and open.
Distracter 2: Backup scram valves would be energized and open.
Distracter 3: Backup scram valves would be energized and open.
l Rev.O Reactor Operator,50007 01/20/09.
Topic 1999 NRC Retest 5799NRCA
- 44 -
Exam Series A j
t
<
[
,
.
Objective: 94.12.01.05 (Revised from 1996 ILC Audit Exam.)
1 Point 45.' Which one of the following nuclear instrument failures would indicate a loss of 24 VDC?
a.
A aiated RBM level fails high b.
Associated LPRM levels faillow c.
Associated SRM levels fail high d.
Associated IRM levels faillow ANSWER: D i
REFERENCE: AOP 375 K/A System: 215003-
K/A Number: K2.01
. K/A Value:2.5*/2.7 Cognitive Level: 2.
Distracter 1: No affect. Powered by RPS.
Distracter 2: No affect. Powered by RPS.
I Distracter 3: Would faillow.
t
)
i
)
)
J
.
Rev.O Reactor Operator, 50007 01/20/09 Topic 1999 NRC Retest 5799NRCA-45-Exam Series A
)
,
.
Objective: 78.02.01.01 (NEW for 1998 ILC Retest)
1 Point 46. Operators are preparing to withdraw the first control rod for a reactor startup. All operable j
SRM detectors are fully inserted.
Given the following sets of SRM readings (in counts per second), would the SRM system be considered OPERABLE or NOT OPERABLE for startup?
SRM A
B C
D l
Set 1).
4
Set 2)
-4
3
a.
Set 1) OPERABLE for startup Set 2) OPERABLE for startup b.
Set 1) NOT OPERABLE for startup
-
Set 2) OPERABLE for startup c.
Set 1) OPERABLE for startup Set 2) NOT OPERABLE for startup
d.
Set 1) NOT OPERABLE for startup Set 2) NOT OPERABLE for startup ANSWER: D REFERENCE: IPOI-2
]
K/A System: 215004
- K/A Number: G 2.2.1 i
K/A Value: 3.7/3.6 Cognitive Level: 2 Distracter 1: Must have 3 operable channels reading >3 cps.
,
Distracter 2: Must have 3 operable channels reading >3 eps.
- Distracter 3: Must have 3 operable channels reading >3 cps.
l
!
I Rev.0 Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest
!
'
5799NRCA 46-Exam Series A
Objective: 81.01.01.03 (Revised from Clinton 1998 NRC exam.)
1 Point 471During full power steady state operations, the APRM Gain Adjustment Factor (AGAF) for
' A APRM is found to be 1.03 on the current printout of the 3D Monicore Periodic Log.
1) ' Under these conditions, is the operation of A APRM CONSERVATIVE or NOT CONCERVATIVE?
and 2)
What is the CORRECT reason for the answer to part 1 of this question?
a..1) CONSERVATIVE 2) A APRM is reading LESS THAN actual power.
b.
1) CONSERVATIVE l
2) A APRM is reading GREATER THAN actual power.
'
c.
1) NOT CONSERVATIVE
'
2) A APRM is reading LESS THAN actual power.
d.-
1) NOT CONSERVATIVE 2) A APRM is reading GREATER THAN actual power.
ANSWER: C-REFERENCE:
K/A System: 215005 K/A Number: A1.07 K/A Value: 3.0/3.4 Cognitive Level: 2
'
Note: AGAF is the ratio of actual thermal power over APRM indicated power. An APRM reading less than actual (AGAF>1.0) would be farther from its flow biased scram setpoint and therefore non-conservative.
Distracter 1: It is not conservative to have the APRM set < thermal power. AGAF of 1.03 indicates an APRM reading < thermal power.
Distracter 2: If APRM were set > thermalit would be conservative.
Distracter 3: AGAF of 1.03 indicates an APRM reading < then.al power
'
,
i Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-47-Exam Series A
,
i
I
\\
i Objective: 88.00.00.00 (From 1998 LOR exam.)
1 Point
'48. The plant is operating at power. In which direction (HIGHER or LOWER) would a 1C05 Yarway levelindication failif the following malfunctions or events were to occur?
(Consider separately) ~
1) A break occurs in the variable leg.
2) A rapid RPV depressurization occurs.
. a.
1) HIGHER 2) HIGHER b.
1) HIGIIER 2) LOWER c.
1) LOWER
,
2) HIGHER l
d.
1) IAWER 2) LOWER -
ANSWER: C I
'
REFERENCE: SD 880 K/A System: 210000 K/A Number:. A2.03 & 2.10 K/A Value: 3.0/3.1 & 3.3/3.5 Cognitive Level: 2 l
. Distracter 1: More AP on variable leg break; Level indication would decrease
.
Distracter 2: More AP on variable leg break; Level indication would decrease Less AP due to ref
)
leg flashing ; Level indication would increase.
l
= Distracter 3: Levelindication would decrease Less AP due to refleg flashing ; Level indication would increase.
]
Rev, O Reactor Operator,50007
'01/20/99 Topic 1999 NRC Retest 5799NRCA
- 48 -
Exam Series A i
l'
j
Objective: 3.02.01.05 (From 1998 LOR exam.)
1 Point 49. The following question is related to the three sets of RCIC indicating lights shown below, minus the associated handswitches. GRAY SHADED means the light is ILLUMINATED.
A plant transient has occurred which involved an automatic initiation and subsequent failure of the RCIC system. The only operator action taken with RCIC was to cycle the handswitch for MO-2405, RCIC Turbine Stop Valve, to the FULLY CLOSED position and then to hold it in the OPEN position for three seconds. (Assume that MO-2400 and MO-2401, steam supply isolation valves, are OPEN.)
What is the status of RCIC based on these indications?
O" RCIC STEAM SUPPLY MO-2404
.
O" On TURBINE STOP VALVE TURBlNE STOP VALVE MOTOR MO-2405 CONTROL MO-2405 a.
A RCIC Hi RPV Level trip has occurred.
The RCIC Turbine trip is RESET.
b.
A RCIC Hi RPV Level trip has occurred.
A turbine trip signalis still present and the RCIC Turbine trip is NOT RESET.
c.
A RCIC Hi RPV Level trip has NOT occurred.
The RCIC Turbine trip is RESET.
d.
A RCIC Hi RPV Level trip has NOT occurred.
A turbine trip signal is still prcsent and the RCIC Turbine trip is NOT RESET.
ANSWER: B REFERENCE: ARPs 1C040, A-5 and A-G; SD-150 K/A System: 217000 K/A Number: K4.02 & K4.04 K/A Value: 3.3/3.3 & 3.0/3.1 Cognitive Level: 3 Note: With a mechanical OS the motor control would not start to reopen.
Distracter 1: MO-2405 closed with motor control dual indicates that a trip signal, other than mechanical overspeed, is still present.
Distracter 2: MO 2404 closed indicates that a 211" trip is still present. MO 2405 closed with motor control dual indicates that a trip signal, other than mechanical overspeed, is still present.
Distracter 3: MO 2404 closed indicates that a 211" trip is still present.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-49 Exam Series A
Objective: 8.02.01.02 (NEW for 1998 ILC Retest)
1 Point 50. With the plant at full power and with HPCI inoperable, a small line break accident o:. curs inside the Drywell. Due to a slow transfer of the non-essential busses, Condensate and Feed are unavailable. All remaining ECCS systems respond as designed. RCIC is being used for high pressure injection, but RPV level is slowly lowering.
When the ADS timers initiate the OSS directs them to be locked out. With 30 seconds expired on the timers, the 1C03 operator DEPRESSES COMPLETELY and TURNS BOTH A and B LOGIC ADS TIMER RESET pushbuttons. However, the pushbutton for the B Timer does not hold in that position, and, unnoticed by the 1C03 operator, it immediately pops back out to its normal position.
1) When will ADS initiate?
and 2) How many ADS SRVs will open?
J a.
1) 90 SECONDS after the attempted lockout 2) 2 ADS SRVs will open i
b.
1) 90 SECONDS after the attempted lockout 2) 4 ADS SRVs will open c.
1) 120 SECONDS after the attempted lockout 2) 2 ADS SRVs will open d.
1) 120 SECONDS after the attempted lockout 2) 4 ADS SRVs will open ANSWER: D REFERENCE: SD 183.1; 01 183.1 K/A System: 218000 K/A Number: A4.04 K/A Value:4.1/4.1*
Cognitive level: 2 Note: RO must understand that depressing the pushbutton completely, even momentarily, resets the timer and that it should immediately restart. RO must also understand that, when either ADS logic is satisfied, it opens all 4 ADS SRVs.
Distracter 1: Timer resets to 120 seconds. 4 SRVs should open.
Distracter 2: Timer resets to 120 seconds.
Distracter 3: 4 SRVs should open.
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 50 -
Exam Series A
r-Objective: 42.00.00.041 (NEW for 1998 ILC Retest)
1 Point t
l 51. The plant is operating at full power when a complete loss of Well Water occurs. When the i
plant is scrammed, RPV lovel lowers to +160" before it can be restored to the EOP-1 control l
band.' All other plant systems respond as designed.
The OSS directs that the Drywell be cooled using an Air Purg,e per OI-573, " Containment Atmosphere Control System".
Which of the following statements is CORRECT in describing the operation of the AIR PURGE ISOLATION, CV 4317, when establishing a Drywell air purge?
During normal power operation, CV 4317 would be...
a.
OPEN.
It would not be affected by a Group 3 isolation and would be in position for an Air Purge, b.
OPEN, however, it would now be CLOSED due to a Group 3 isolation signal.
A Control Room operator must override or reset the Group 3 isolation in order to reopen CV-4317 locally for an Air Purge.
c.
CLOSED.
It would not be affected by a Group 3 isolation but it must be opened locally for icn Air Purge.
d.
CLOSED.
A Control Room operator must override or reset the Group 3 isolation in order to reopen CV-4317 locally for an Air Purge.
ANSWER: C REFERENCE: 01-573
' K/A System: 223001 K/A Number: KG.13 K/A Value: 3.2/3.4
'
Cognitive Level: 2 Distracter 1: No Group 3 isolation is correct, but valve is normally closed and not in position for an air purge.
Distracter 2: Valve is normally closed and not in position for an air purge. It would not receive a Group 3 isolation signal.
Distracter 3: Closed is correct, but it would not receive a Group 3 isolation signal.
'Rev.O Reactor Operator, 50007
- 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 51 -
Exam Series A i
J
.-
t Objective: 26.01.01.14 & 29.01.01.06 (NEW for 1998 ILC Retest)
1 Point 52. The plant is in a normal full power line up when a Loss of Coolant Accident occurs. RPV level lowers to +50" but the plant responds as designed and operators promptly restore RPV level i
to the +170"-211" band. Drywell and Torus pressure are at G psig and slowly lowering, i
NO EOP Defeats have been installed and NO actions have been taken to reset Primary Containment Isolations.
Which of the following CORRECTLY identifies the expected positions of the PCIS Group 7 isolation valves in this plant condition?
- 1) Drywell Cooling Well Water supply and return valves, CV 5718A&B and CV 5704A & B.
and 2) RBCCW Drywell Isolation valves, MO-4841A & MO-4841B.
.
a.
1) OPEN 2) OPEN b.
1) OPEN 2) CLOSED c.
1) CLOSED 2) OPEN d.
1) CLOSED 2) CLOSED ANSWER: B REFERENCE: SD-859.1, OI-700 K/A System: 223002 K/A Number: A3.02 K/A Value: 3.5/3.5 Cognitive level: 2 Note: Both sets of valves close at <+G4"; isolation logic resets when >+64"; DW cooling valves reopen, RBCCW valves must be reopened with the handswitch on 1C00.
L Distracter 1: RBCCWvalves remain closed.
Distracter 2: DW Cooling valves reopen. RBCCW valves remain closed.
Distracter 3: DW Cooling valves reopen.
Rev.O Reactor Operator, 50007
.01/20/99 Topic 1999 NRC Retest 5799NRCA'
- 52 -
Exam Series A
I h
l I
Objective: 42.01.02.01d (NEW for 1998 ILC Retest)
1 Point.
!
53.' See the Safety Relief Valve figure on the next page.
i Assume that the flexible material'of SRV component identified were to rupture
)
(fail completely) during power operation.
i l
l 1) Would there be an indication of this failure in the control room when it occurred?
And 2) Could the SRV.be opened manually from 1C03?
a.
1) A IC03A annunciator would activate which could be confirmed with IC21 indications.
2) The SRV could still be opened manually.
b.
1) A IC03A ~ annunciator would activate which could be confirmed with IC21 indications.
2) The SRV could NOT be opened manually.
.
,
c.
1) There would be no indication of this failure.
2) The SRV could'still be opened manually.
j
- d.
1) There would be no indication of this failure.
2) The SRV_could NOT be opened manually.
'
\\
. ANSWER: D ;
REFERENCE: SD 183.1, Figure 1; ARP 1C03A, C-9 i
K/A SYSTEM: 239002 K/A NUMBER: K5.01 K/A VALUE: 3.4/3.5 Cognitive Level: 2
,
Note: This was a plant event. Although no actual failure occurred, workers misapplied SRV
insulation causing overheating and severe degradation of these diaphragms.
Distracter 1:. No indications (may confuse this diaphragm with the bellows failure which is alarmed.)& SRV cannot be opened.
t Distracter 2: No indications.
.Distracter 3: SRV cannot be opened.
i
Rev.O Reactor Operator, 50007
- 01/20/99 Topic 1999 NRC Retest 53-Exam Series A
- 5799NRCA
-
i Objective: 93.07.01.04 (From 1998 LOR exam.)
1 Point 54. The Drywellinspection at 400 psig has just been completed during a normal (MSIVs open)
reactor startup.
Operators resume the startup by withdrawing one group of eight (8) Control Rods from position 10 to position 12. NO OTHER OPERATOR ACTION is taken.
What affect will this rod withdrawal have on the observable Heatup Rate?
i (HIGHER HEATUP RATE or NO AFFECT on Heatup Rate)
If HIGHER HEATUP RATE, identify the CORRECT coefficient of reactivity which counteracts the control rod reactivity addition. (Causes power to turn.)
If NO AFFECT, identify the CORRECT reason.
.
a.
HIGHER HEATUP RATE The Moderator Temperature Coefficient causes power to turn.
b.
HIGHER HEATUP RATF, The Fuel Temperature Coefficient causes power to turn.
,
c.
NO AFFECT The Main Steam Line Drains would be open to control RPV pressure.
d.
NO AFFECT The Turbine Bypass Valve (s) will open further to control RPV pressure.
ANSWER: D l
REFERENCE: IPOI-2
)
K/A System: 241000 K/A Number: K1.29 K/A Value: 3.4/3.4 j
Cognitive Level: 3
Distracter 1& 2: BPVs shormd be 20%-90% open at this point in the startup and will just open
'
further. Power increases r nd is turned by moderator temp and fuel temp increaces, but no change to HUR because pressurr, and therefore temperature, remain the same.
i Distracter 3: MSL Dra ns would have been open since 150 psig. The steam flow there wouhl be relatively constant, ard increased reactor power opens the BPVs. "No affect" is correct but not yj because the MSL' drains are open.
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 54 -
Exam Series A
,
Objective: 45.01.01'07 (NEW for 1998 ILC Retest)
1 Point
.
l 55. The plant is at power with ONLY ONE Reactor Feed Pump operating.
l.
1) Will there be feedwater flow through ONE or TWO High Pressure (IE-GA/6B) -
AND 2) Will there be feedwater flow through ONE or TWO feedlines to the reactor?
a.
1) ONE 2) ONE b.
1) ONE 2) TWO c.
1) TWO 2) ONE
,
d.
1)TWO 2) TWO ANSWER: D REFERENCE: P&ID Bech M-107 K/A System: 259001 K/A Number: K1.01 K/A Value: 3.0/3.7-Cognitive Level: 1 Note: The feedwater header is crossconnected after the Reg Valves which results in flow to both HP heaters. The feedwater headeris crossconnected u ain after the HP heaters which results in s
flow to both feedlines.
Distracter 1: Selected if neither crossconnect is understood.
Distracter 2: Selected if Reg valve crossconnect is not understood.
Distracter 3: Selected if the Reg valve position before the HP heaters is not understood.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 55 -
Exam Series A
Objective: 45.05.01.05 (NEW for 1998 JLC Retest)
1 Point 56. Operators have just taken The Mode Switch to RUN during a reactor startup. Feedwater level control is on the Startup Feed Reg Valve operating in AUTO.
Which of the following CORRECTLY describes the initial response of the Startup Feed Reg Valve if the A Feedwater Flow instrument were to fail LOW?
The Startup Feed Reg Valve will...
NOT MOVE because the loss of the feed flow signal would result in a Reg Valve lockup, a.
b.
NOT MOVE because the feed flow signal would not be an input to automatic level control.
c.
OPEN because indicated feed flow would be less than actual feed flow.
d.
OPEN because indicated feed flow would be less than steam flow.
ANSWER: B REFERENCE: IPOI.2, SD-644 K/A System: 259002 K/A Number: K4.09 K/A Value: 3.1/3.1 Cognitive Level: 3 Note: RO must know that the Mode switch transfer occurs at =10% power and that the transfer to 3 Element control occurs at =35%.
Distracter 1: Not Move is correct but loss of feed signal is not a Reg valve lockup.
Distracter 2: Mismatch is correct but not used in 1 Element; valve does not move.
Distracter 3: Mismatch is correct but not used in 1 Element; valve does not move i
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
. 5's 99NRCA-56-Exam Series A i
v Objective: 7.00.00.02b (NEW for 1998 ILC Retest)
1 Point 57. The plant is in full power operation with no LCOs.
What'would be the affect on Standby Gas Treatment System (SBGT) operability if the Control
Building Ventilation Air Compressor 1K-3 were to become inoperable?
a.
There is no affect because SBGT air operated valves are normally supplied with Instrument Air.
b.
There is no affect as long as the backup air receivers for SBGT remain fully charged.
l c.
There is no affect if Air Compressor 1K 4 is operable and crossconnected to the 1K-3 ' air i
system, d.
The A SBGT train is dependent on 1K-3 and must be declared inope,rable.
'
)
ANSWER: D REFERENCE: 01 170 P&L #6 K/A System: 261000 K/A Number: Generic 2.1.10 K/A Value: 2 7/3.9 Cognitive Level: 2 Note: This operability interpretation changed last year with the incorporation ofimproved Tech Specs and the Safety Function Determination Program. The revision was incorporated into P&Ls in SBGT and Control Bldg. HVAC OIs and ROs should know about it.
Distracter 1: SBGT is normally supplied by Inst. Air (not a Safety Related system); A SBGT is inop Distracter 2: Possible misconception about air receivers; A SBGT is inop Distracter 3: Possible misconception about 1K 4 (Division 2 system); A SBGT is inop Rev.O Reactor Operator, 50007 01/20/09 Topic 1999 NRC Retest 5799NRCA-57-Exam Serica A e
(
[
l Objective: 19.00.00.02 (NEW for 1998 ILC Retest)
1 Point 58. The plant is in normal full power operation with surveillance testing in progress on the B SBDG.
During initialloading, a failure occurs in ONE OF THE THREE Lube Oil Pressure switches. This switch activates as if a low oil pressure condition has occurred even though oil pressure is normal.
Which of the following statements CORRECTLY predicts the affect of this failure on the B l
SBDG?
l
'
I a.
There would be no operationalindication of this problem.
b.
B SBDG would continue to operate and the following annunciators would be received:
IC94, B-4, LUBE OIL PRESSURE LOW J
IC08B, C-2, B DIESEL GEN 1G 21 PANEL 1C94 TROUBLE I
c.
B SBDG would trip and the following annunciators would be received:'
IC94, B-4, LUBE OIL PRESSURE LOW IC08B, C 2, B DIESEL GEN IG 21 PANEL IC94 TROUBLE.
IC08B, D-2, B DIESEL GEN IG-21 ENGINE SHUTDOWN If properly secured, the B SBDG would automatically restart on LOOP or LOCA signal.
d.
B SBDG would trip and the following annunciators would be received:
IC94, B-4, LUBE OIL PRESSURE LOW 1C08B, C-2, B DIESEL GEN 1G 21 PANEL IC94 TROUBLE.
IC08B, D 2, B DIESEL GEN IG-21 ENGINE SHUTDOWN j
Even if properly secured, the B SBDG WOULD NOT automatically restart on LOOP or LOCA signal.
'
ANSWER: B i
REFERENCE: SD 324, Rev.1, ARP 1C 94 B 4; 1C08 C-2, & D 2 K/A System: 264000 K/A Number: K4.01 K/A Value: 3.5/3.7 Cognitive Level: 2
' Note: There are 3 low pressure switches. Any 1/3 will yield a 10 94 alarm. It takes 2/3 to trip the SBDG.
Distracter #1: Selected if RO thinks that it take 2/3 to get the alarms.
I Distracter #2 :It takes 2/3 to trip the SBDG. It is correct that, if properly secured, the B SBDG would auto restart with this failure in affect.
Distracter #3: It takes 2/3 to trip the SBDG. If properly secured, the B SBDG would auto restart with this failure in affect.
.
'
Rev, O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 58 -
Exam Series A
_
p
-
,
Objective: 81.01.01.0Gd (NEW for 1998 ILC Retest)
1 Point 59. The plant is operating at full power when the hold down assembly fails on Jet Pumps #1 & #2.
This allows the Jet Pump nozzle assembly (commonly called the Rams Head) to separate from the B Recire Loop piping inside the RPV.
- At IC05, the annunciators for APRM FLOW UNIT ' UPSCALE, INOP OR COMPARE ERROR and ROD OUT BLOCK are also received. At IC04, Recire Pump Discharge Flow indicators, which normally read =28,000 gpm, are found to be reading 28,500 gpm for A Recire and 32,000 gpm for B Recire.
Which of the following CORRECTLY describes how the APRM Flow Units will respond in this situation?
l a.
~ Compare Error trips from only two (2) Flow units.
.
b.
Compare Error trips from all four (4) Flow units.
c.
Upscale trips from only two (2) Flow units.
d.
Upscale trips from all four (4) Flow units.
ANSWER: D REFERENCE: SD-264, SD 878.3 K/A System: 215005 K/A Number: K5.05 K/A Value: 3.6/3.6 Cognitive Level: 3 Note: A dedicated flow transmitter on each loop goes to every flow unit where they are summed.
Therefore, all four Flow Units would read the same high flow (no compare Error).
Distracter 1: RO may think that the flow units ccmpare A to B Recire and that B&D flow units
.would not compare with A&C.
Distracter 2: RO may think that the flow units compare A to B Recire Distracter 3: RO may think that only B&D flow units would be upscale.
l l
l l
Rev.O Reactor Operator,50007
.01/20/99 Topic 1999 NRC Retest 5799NRCA-59-Exam Series A
Objective: 2.03.01.04 (NEW for 1998 ILC Retest)
1 Point 60. A LOCA occurs during power operation with RHR in its normallineup. RPV pressure is 600 psig and lowering steadily but RPV level is being maintained by Condensate and Feed. The B RHR Loop has been' selected and operate v. :nt to throttle MO 1904, (LPCI) OUTBD i
INJECT ISOL, to control RPV level.
l Select the statement which CORRECTLY describes the purpose and use of(keylock
. handswitch) HS-1904C, MO-1904 LPCI OPEN INTLK OVERRIDE.
HS-1904C is used to...
a.
close MO-1904 BEFORE reaching 450 psig RPV pressure by overriding an interlock which holds it open for 5 minutes, b.
close MO 1904 AFTER reaching 450 psig RPV pressure
,
by overriding an interlock which holds it open for 5 minutes.
.
l c.
close MO-1904 BEFORE reaching 450 psig RPV pressure
)
by overriding an interlock which holds it open for 10 minutes, j
d.
close MO 1904 AFTER reaching 450 psig RPV pressure by overriding an interlock which holds it open for 10 minutes.
ANSWER: B REFERENCE: OI-149; APED E11 <007> & <016>
'
K/A System: 203000 K/A Number: K3.01 K/A Value: 4.3*/4.4*
Cognitive Level: 1
'
. Note: 10 min. is the interlock which prevents opening the inject valve on the non-selected loop.
The seal-in feature that keeps MO 1904 closed does not work until <450 psig.
Distracter 1: 5 minutes is correct, but MO 1904 will reopen at 450 psig if overridden closed when
'
>450psig.
Distracter 2: 10 min. is wrong and MO-1904 will reopen at 450 psig if overridden closed when
>450psig.
Distracter 3: Closing valve once it has opened is correct but 10 min. is wrong.
!
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA 60-Exam Series A
i i
Objective: 3.02.01.08c (NEW for 1998 ILC Retest)
1 Point 61. RCIC hae automatically initiated and is injecting in response to a LOCA.
. How would RCIC be expected to respond if an oil leak were to occur which cause a lowering of RCIC oil pressure to 1 psig? (HV 240G is the RCIC TURBINE CONTROL VALVE.)
a.
RCIC will trip at a lube oil pressure of <3.0 psig, b.
RCIC system flow will increase when HV-2400 drifts open.
c.
RCIC system flow will decrease when HV-2406 drifts closed.
d.
RClO will show no response until one or more bearings fail.
j ANSWER: B
'
,
REFERENCE: ARP 1C04C, D-9 K/A System: 217000 K/A Number: A2.07 K/A Value:3.1/3.1 Cognitive Level: 3 Distracter 1: The low oil pressure alarm is set at 3 psig, but there are no auto actions.
Distracter 2: HV-2406 is normally full open and closes as RCIC initiates and builds up oil pressure.
Distracter 3: RCIC may sustain bearing failure but HV 2406 should drift open first.
I Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA 61-Exam Series A
v Objective: 8.01.01.02e (NEW for 1998 ILC Retest)
1 Point 62. The plant was in full power operation when an accident occurred which necessitated transfer of control to the Remote Shutdown Panel,1C388. When the transfer is complete, will the safety relief valves operate automatically in the Low Low Set (LLS) mode and in Automatic Depressurization (ADS) mode?
The SRVs will...
a.. not operate in either the LLS mode or the ADS mode.
b.
operate in the' LLS mode only, c.
operate in the ADS mode only, d.
operate in both the LLS and the ADS modes.
ANSWER: A
'
REFERENCE: SD 183.1
. K/A SYSTEM: 218000 K/A NUMBER: K1.05-K/A VALUE: 3.9/3.9 Cognitive Level: 2 Distracter 1: Neither mode is functional from 10388.
~Distracter 2: Neither mode is functional from 1C388.
Distracter Si Neither mode is functional from IC388.
l
..
I L
Rev.O Reactor Operator, 50007 01/20/99
. Topic 1999 NRC Retest i
5799NRCA :
- 62 -
Exam Series A j
L Objective: 94.11.01.01 (NEW for 1998 ILC Retest',
1 Point 63. During normal power operation, the B RPS Motor Generator trips due to a mechanical fault.
' After identifying the cause of the loss of RPS, operators place the B RPS ALTERNATE
,-
POWER TRANSFER switch in the ALT XFMR position. Operators then reset the 1/2 scram l
and momentarily depress PCIS DIV 1 RESET and DIV 2 RESET pushbuttons on 1C05.
Can the B Standby Gas Treatment lockout relay, LR-5830B, be reset at this point?
l (YES or NO)
l
- If NO, identify the action necessary before successfully resetting it.'
)
a.
YES b.
NO; wait for the B and D Main Steam Line Radiation monitors, RM-4448B & D, to warm up. (Associated annunciator will clear.)
,
c.
NO; Reset the Carbon Vault Rad Monitor, RM-4138, d.
NO; Reset the B Fuel Pool Exhaust Rad Monitor, RM 4131B.
ANSWER: D REFERENCE: AOP-358 K/A System: 212000 K/A Number: K3.01 K/A Value: 3.0/3.2 3 Cognitive Level: 2 Distracter 1: Will not reset until the Fuel pool monitor Group 3 signal is reset.
)
Distracter 2: This is part of the recovery of RPS power but it does not affect the Lockout relay.
'
Distracter 3: This is part of the recovery of RPS power but it does not affect the Lockout relay, i
Rev.O Reactor Operator, 50007
_01/20/99 Topic 1999 NRC Retest
,
5799NRCA-63-Exam Series A l
Objective: 5.00.00.02 (Revised, from Exam Bank.)
1 Point
- 64.= The plant is at power and operators are performing post maintenance testing on the HPCI turbine in order to exit the HPCI LCO.
.,.
HPCI has been manually started in the CST-CST mode using the TEST POT for control. The system is stable at 3500 rpm and 2000 gpm.
At this point, the operator throttles open CV 2315, TEST BYPASS, to achieve 3000 GPM.
Which of the following CORRECTLY describes the response of HPCI Discharge Pressure and HV 2200, TURBINE CONTROL VALVE, position to this valve manipulation?
. a.
HPCI Discharge Pressure INCREASES-HV-2200 position REMAINS THE SAME
.
b. ' HPCI Discharge Pressure INCREASES HV 2200 position THROTTLES OPEN c.
HPCI Discharge Pressure DECREASES HV-2200 position REMAINS THE SAME d. : HPCI Discharge Pressure DECREASES
,
HV 2200 position THROTTLES OPEN ANSWER: O REFERENCE: 01152; SD-152 K/A System: 206000
K/A Number: A1.07 K/A Value: 3.7/3.6
- Cognitive Level: 3 Note: RO must know that the test pot controls HPCI speed, not flow, so HV-2200 will not change position. Pump laws dictate that a pump at constant speed will have a decreased discharge pressure at higher flow.
Distracter 1: Discharge pressure will decrease.
Distracter 2: Discharge pressure will decrease. HV-2200 will not change position.
Distracter 3: HV-2200 will not change position.
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Rev.O Reactor Operator, 50007 01/20/99
_
Topic 1999 NRC Retest 5799NRCA '
64-Exam Series A
Objective: 94.02.01.01 (NEW for 1998 ILC Retest)
1 Point
.
l-65.' Control Rod Drive friction testing is in progress following refueling operations.
A control rod which was overhauled during the outage does not move from its full in position when a withdra=w signalis applied.
The following indications are seen at 1C05:
)
CRD Pump flow (on the flow controller)
40 gpm
.
CRD Charging Water pressure 1500 psig
.
CRD Drive Water header pressure 200 psid
.
There are no Rod Out Blocks in effect.
.
Which of the following CORRECTLY explains why this rod is difficult to withdraw?
l a.
The overhauled dMve mechanism will have new internal seals and will require more Drive Water Differential pressure to operate.
b.
The drive mechanism will have reduced internal clearances at low RPV temperatures and will require more Drive Water Differential pressure to operate.
The overhauled drive mechanism will have pockets of air that willimpede operation until,
c.
worked out of the drive.
d.
The drive mechanism will be at its overtravel in position after overhaul and require double clutching to operate the first time.
ANSWER: C REFERENCE: AOP 255.1 K/A System: 201003 K/A Number: Generic 2.4.11 K/A Value: 3.4/3.0 Cognitive Level: 2 Note: AOP says to not re-insert the rod fully until all air is worked out of the drive.
Distracter 1: Concern not mentioned in AOP. Newer seals would need less DP.
Distracter 2: Concern not mentioned in AOP. Reduced clearances would need less DP.
Distracter 3: Concern not mentioned in AOP. Drive would not be OT in and, ifit were, double-clutching would not help.
Rev.0.
Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-65-Exam Series A
l l
l Objective: 84.00.00.05 (From 1998 LOR exam.)'
1 Point 66.
A plant start up is in progress per IPOI-2. The IC05 operator is withdrawing control rods to continue heatup to 400 psig. The operator notes the 4-rod display for the selected rod goes blank.
What type of block, if any, will exist on the RWM if the RPIS probe for that rod is giving NO rod positions?
The RWM will...
enforce an Insert block, but not a Withdraw block, due to loss of rod position.
a.
b.
enforce a Withdraw block, but not an Insert block, due to loss of rod position.
c.
enforce both an Insert and a Withdraw block due to loss of rod position.
,,
d.
continue to operate with no rod blocks; the RWM receives the necessary rod position inputs from the PPC.
ANSWER: C REFERENCE: SD-878.8 K/A System: 201006 K/A Number: K1.02 K/A Value: 3.4/3.4'
Cognitive Level: 2 Distracter 1: Causes both types of blocks Distracter 2: Causes both types of blocks.
. Distracter 3: Information for PPC also comes from RPIS.
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l Rev.O Reactor Operator,50007 l'
01/20/09 Topic 1999 NRC Retest l
L5799NRCA-66-Exam Series A j
l
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Objective: 12.00.00.03c (NEW for 1998 ILC Retest)
1 Point
' 07. See the Channel A RPT logic drawing on the next page.
~
The plant is in normal operation at 75% power.
'
~ Assume that an operator were to simultaneously depress the TEST pushbuttons for the Turbine Stop Valve #1 and #2 (at 1C07) until the valves were 80% open.
. What affect would this have on the Recire Pump Trip (RPT) breakers for the A and B Recire
..
pumps?
a. - ONE breaker to the A Recire Pump would open.
There would be no affect on the B Recire Pump breakers.
b.
TWO breakers to the A Recire Pump would open.
There would be no affect on the B Recirc Pump breakers.
.
c.
ONE breaker to the A Recire Pump would open.
ONE breaker to the B Recire Pump would open.
'd. ' TWO breakers to the A Recire Pump would open.
TWO breakers to the B Recire Pump would open.
ANSWER: C REFERENCE: SD264 K/A System: 202001 K/A Number: K5.05 K/A Value: 3.5/3.6 l
Cognitive' Level: 2 Distracter 1: Selected if RO thinks that A logic activates only one A pump breaker.
Distracter 2: Selected if RO thinks that A logic activates only the A pump breakers.
Distracter 3: Selected if RO thinks that either logic trips all four breakers.
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l Rev.O Reactor Operator, 50007 l'
01/20/99'
Topic 1999 NRC Retest 5799NRCA-67-Exam Series A
,
___________
Objective: 11.01.01.01 (NEW for 1998 ILC Retest)
1 Point 68. The plant has been operating steady state in a normal full power lineup for several weeks.
The following plant conditions exist:
3D Monicore Core Megawatts Thermal (Mwth):
1657.0
.
Feedwater Flow:
7.0 Mlb./Hr.
.
Final Feedwater Temperatures (outlet of GA&B Heaters):
420 F
.
,
RWCU System flow:
140 gpm
.-
RWCU to Reactor temperature:
435"F
.
Assume that the Reactor Water Cleanup (RWCU ) system is then isolated.
Which of the following statements is CORRECT concerning the plant and operator response to securing RWCU?
.
The change to core thermal power would...
a.
NOT BE NOTICEABLE.
No further operator action would be necessary.
b.
BE NOTICEABLE.
Operators may need to adjust the gains on the APRMs.
c.
BE NOTICEABLE.
Operators may need to substitute the computer point value for RWCU flow.
d.
BE NOTICEABLE.
Operators must limit the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> average thermal power to 1657.5 Mwth and contact Reactor Engineering.
ANSWER: C REFERENCE: 0I-261, P&L 16 K/A System: 204000 -
K/A Number: K3.04 K/A Value: 2.6/2.0 Cognitive Level: 2 Note: The plant is operating very close to the Rated Mwth limit of 1658 so operators should verify an accurate 3D Monicere periodic log. Heat balance values are given to make the change appear insignificant for Distracter 1.
Distracter 1: Definitely noticeable, and operators should substitute RWCU flow value.
Distracter 2: Noticeable is correct and adjusting GAFs is a good thing, but if thermal power has
- actually changed adjusting GAFs would not be necessary.
Distracter 3: Noticeable is correct but this action would be taken if Mini Purge flow to Recire pump seals is increased to >5 gpm. Not correct for RWCU isolation.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-68-Exam Series A
.........
.....
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....
...
...
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.
.
.
..
Objective: 2.03.01.05 (NEW for 1998 ILC Retest)
1 Point 69. The plant is Mode 4 with Shutdown Cooling (SDC) in service.
Assume that the Plant Manager's approval has been given as necessary. Which of the following combinations of RHR Flow, Recire Pump operation, and RPV level would NOT BE ALLOWED?
a.
RHR Flav.
2500 gpm
'
Recire Pumps
' 1 Pump (minimum speed) in parallel with SDC RPV level '
Maintained in the green band b.
RHR Flow 2500 gpm Recire Pump Both pumps secured RPV level Maintained 215" 220"
.
c.
RHR Flow 6000 gpm Recire Pump.
Both pumps secured RPVlevel Maintained in the green band
,
d.
RHR Flow 6000 gpm Recire Pump 1 Pump (minimum speed)in parallel with SDC RPVlevel Maintained 215"-220" ANSWER: D REFERENCE: 01-149 K/A System: 205000 K/A Number: A 4.09
' K/A Value: 3.1/3.1 Cognitive Level: 3 Distracter 1: Allowed; RHR Flow control band in parallelis 2000 4000 gpm.
Distracter 2: Allowed; RHR Flow may be lowered to 2000 gpm with RPV level >214".
Distracter 3: Allowed; RHR Flow must be >4000 gpm and procedure allows start of second RHR pump.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 69 -
Exam Series A
_
E
'l Objective: 74.00.00.04 (Revised from 1998 Hope Creek Exam)
1 Point
- 70. Given the following:
The plant has just scrammed from full power.
.
Rod 22-27 was selected just prior to the scrum.
.
No operator action has been taken.
.
The 1C05 operator observes that the "FULIrIN" light is illuminated for rod 22-27 on the Full Core Display while the Four Rod Display Selected Rod is not indicating "00".
Which of the following best describes the reason for this observation?
e a.
The scram must be reset to allow the rod to settle to position "00".
-
b. ; RPIS is providing faulted data to the Four Rod Display.
'
c.
RPIS Rod Drift logic bypasses the Four Rod Display.
d.
A selected rod is automatically deselected on a scram.
ANSWER: A REFERENCE: SD 856.1 K/A System: 214000 K/A Number: K1.05 K/A Value: 3.3/3.3 Cognitive Level: 2 Distracter 1: Common misconception. Rods overtravelin to reed switch 51 on a scram.
Distracter 2: Common misconception. Rods overtravelin to reed switch 51 on a scram.
Distracter 3: Common misconception. Rods overtravelin to reed switch 51 on a scram.
Rev.O Reactor Operator, 50007
- 01/20/99-Topic 1999 NRC Retest
. 5799NRCA 70-Exam Scrice A m
Objective: 82.00.00.04 (Revised, from a 1996 LOR weekly exam.)
1 Point 71. The plant is in normal full power operation.
Which one of the following WOULD NOT rcoult in c rod block from the Rod Block Monitor (RBM) system when a control rod is selected?
40%'of the assigned LPRM inputs to an RBM channel become inoperable.
a.
b.
A select matrix self check failure occurs.
c.
The function switch on one RBM channelis taken to the STANDBY position.
d.
The gain change unit is unable to achieve a balance between the averaged LPRM signal
,
l and the reference APRM signal.
'
'
ANSWER: A REFERENCE: 01-878.5; SD 878.5 K/A System: 215002 K/A Number: K4.01 K/A Value:3.4/3.5 i
'
. Cognitive Level: 1 Note: A Rod Block occurs if only 50% of assigned LPRMs are operable.
Distracter 1:. Rod block occurs.
Distracter 2: Rod block occurs. Paraphrase of" function switch out of OPERATE" Distracter 3: Rod block occurs. Paraphrase of" failure to null".
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Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest
- 5799NRCA 71-Exam Series A
~
Objective: 99.01.01.02 (Revised, from 1998 LOR exam.)
1 Point 72. A HPCI STP is in progress during normal power operation. Torus Cooling is maximized per the STP.
At this point, a degraded voltage condition occurs. The standby diesel generators re-energize the essential buses as designed. The non-essential buses close transfer to the startup transformer when the turbine trips. RPV level can be maintained in the green band with Feedwater. The HPCI STP is suspended.
The 1C03 operator reports that there are no EOP 2 entry conditions but that average Torus water temperature has stabilized at 93 F. The OSS directs that Torus Cooling be re-established.
Assume that A&B RHR Loop Discharge pressures on 1C03 (PI-2032/1962B) indicate 25 psig.
Which of the following describes the CORRECT actions for restarting RHR pumps in this situation?
a.
Pressurize and refill RHR loops with condensate service water and re-vent both loops IAW the RHR operating instruction,01 149, then restart RHR pumps.
b.
Close the associated HX INLET valve, MO-2029/1939, and HEAT EXCH BYPASS valve, MO-2030/1940, then restart RHR pumps.
c.
Close the associated HX INLET valve, MO-2029/1939, HEAT EXCH BYPASS valve, MO-2030/1940, and RHR CROSSTIE valve, MO 2010, then restart RHR pumps.
d.
Close the OUTBD TORUS CLG/ SPRAY valves, MO 2005 & MO-1932, and the TORUS COOLING / TEST valves, MO-2007 & MO 1934, then restart RHR pumps.
ANSWER: A REFERENCE: ARP 1C03B, C-3 & A-2 K/A System: 219000 K/A: K4 07 K/A Value: 3.0/3.1 Cognitive Level: 3 Distracter 1: This action is allowed only during an emergency and an emergency does not exist by the given conditions.
Distracter 2: This action is allowed only during an emergency and an emergency does not exist by the given conditions AND closing the RHR croas-tie valve is not required.
Distracter 3: A low pressure condition exists and this action will not prevent water hammer.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 72 -
Exam Series A
Objective: 30.01.01.01 (NEW for 1998 ILC Retest)
1 Point 73. The plant is operating at full power with HPCI inoperable when a Loss of Offsite Power occurs.
The grid cannot be promptly restored and the Standby Diesel Generators re-energize the essential buses as designed.
During this transient, a Safety Valve partially opens and does not rescat. RPV level and pressure are lowering slowly with available high pressure systems in service. Operators have responded to elevated Drywell pressure and temperature by establishing containment sprays on both loops of RHR per 01 149.
Which of the following sets of A Loop Core Spray, RHR and RHRSW pump operating status would be an ACCEPTABLE LINEUP for this plant condition?
a.
A Core Spray Pump Running A RHR Pump Running C RHR Pump Running A RHRSW Pump Running
.
C RHRSW Pump Running b.
A Core Spray Pump Running A RHR Pump Running C RHR Pump Running A RHRSW Pump Off C RHRSW Pump Off c.
A Core Spray Pump Off A RHR Pump Running C RHR Pump Running A RHRSW Pump Running C RHRSW Fump Running
. d.
A Core Spray Pump Running A RHR Pump Running C RHR Pump Running A RHRSW Pump Running C RHRSW Pump Off I
ANSWER: D REFERENCE: 01-149; 01410 K/A Syetem: 220001 K/A Number: A1.10 K/A Value: 3.0/3.2 Cognitive Level: 3 Distracter 1: Selected if RO does not recognize SBDG loading limitation with a LOOP.
Distracter 2: Selected if RO does not recognize the need to start RHRSW pump (s) in Cont. Spray mode.
Distracter 3: Selected if RO thinks that securing a Core Spray pump allows 2 RHRSW pump operation, which was formerly allowed by procedure.
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 73 -
Exam Series A
, _ _
Objective: 94.10.01.03 (NEW for 1998 ILC Retest)
1 Point 74. The plant is at 98% power at the end of an operating cycle. An edge rod is selected.
Operators are responding to a CRD ACCUMULATOR LO PRESSURE OR HI LEVEL annunciator.
At this point an electrical transient occurs accompanied by multiple alarms which the crew is trying to diagnose. As the 1C05 operator you notice that the reactor has not scrammed but there are no FULL-OUT lights and the wldte ROD SELECT light is off. The orange ACCUMULATOR light is still illuminated.
The loss of which of the following electrical systems would account for these indications?
a.
Uninterruptible AC
.
b.
Instrument AC c.
RPS d.
125 VDC ANSWER: A REFERENCE: AOP 357; AOP 317 K/A System: 202002 K/A Number: K3.06 K/A Value:2.8/2.9 Cognitive Level: 1 Note: Stem information about end of cycle and edge rod selected is necessary to establish that there are no full.in rods and that there is at least one rod selected.
Distracter 1: Common misconception; Accumulator and Rod select lights are from Inst AC; the loss of UP$ deenergizes the Rod Select matrix.
Distracter 2: Possible misconception; conditions indicate a loss of UPS.
Distracter 3: Possible misconception; conditions indicate a loss of UPS.
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Rev.0 Reactor Operator, 50001 01/20/99 Topic 1999 NRC Retest
- 5799NRCA
- 74 -
Exam Series A j
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Objective: 01.00.00.08 (From 1998 LOR exam.)
1 Point
!
73. The plant is at 74% power with a 92% loadline during a planned down power.
l l
During scheduled MSIV testing, one MSIV is declared inoperable and operators isolate that steam line. All other plant equipment is operating as designed.
(Evaluate separately)
1) _ Are operators allowed to perform STP 3.3.1.1-13," Turbine Control Valve EOC RPT Logic
'
' and RPS Instrument Functional Test", in this plant condition? (YES or NO?)
2) Is it allowed to raise reactor power above 75% in this plant condition?
L(YES or NO?)
- -
a.
-1) YES 2) YES
~
b.
1)NO 2) YES
'
c.
1) YES 2)NO l
d.
1)NO
,
2) NO l
,
ANSWER: B-
'
REFERENCE: IPOI-3,6.0(2)(a) & (f); Plant Event K/A System: 239001 K/A: A2.10 K/A Value: 3.8/3.9 Cognitive Level: 2 Distracter 1: Must be < 55% power for turbine testing.
Distracter 2: Must be < 55% power for turbine testing. Nominal power limit is 85%
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Distracter 3: With loadline <95%, nominal power limit is 85%.
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Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 75 -
Exam Series A
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!
Objective: 57.02.01.01 (From 1998 LOR exam.)
1 Point 76.
See Generator Capability Curves on the next page.
l The plant was operating at 100% power when a generator hydrogen leak occurred. The l
- leak was isolated..The BOP reports 30 psig H: pressure.
For which one of the following sets of Main Generator parameters would sustained operation be allowed?
a.
420 MWE and 250 MVARs LEADING b.
500 MWE and 200 MVARs LFADING c.
'
d.
550 MWE and 190 MVARs LAGGING ANSWER: B'
REFERENCE: OI 698, rev. 23 K/A (rev. 2): 245000 K/A Number: KG.04 K/A Valt;e: 2.6*/2.7 Cognitive Level: 3 Distracter 1: Outaide capability curve.
Distracter 2: Outs.ide capability curve on the Lag side of the curve.
Distracter 3: Outside capability curve on the Lag side of the curve.
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L Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-76-Exam Series A L
p L
_ Objective: 45.01.01.01 (NEW for 1998 ILC Retest)
1 Point l
77.' The plant is operating at full power when a failure'in the Extraction Steam system
"
necessitates isolation of condensate to Feedwater Heaters 3A,4A, and 5A. The Outage
'
Planning group v* ants to remain on line for two more weeks until a scheduled maintenance j.
outage.
Which of the following is the MOST LIMITING, APPLICABLE thermal power limitation?
l a.
80%;.the Feedwater Heater Out-of-Service Load Limit for the Main Generator.
b.
60%; the limit for condensate flow through only one Feedwater Heater string, c.
50%; the limit for operation with only one Condensate pump and one Feed pump.
. d.
25%; the administrative limit for an'unanalyzed loss of feedwater hea. ting.
ANSWER: D REFERENCE: 01-644 K/A System: 256000 -
K/A Number: K6.03 K/A Value:2.9/2.9 Cognitive Level: 2 Note: This question is based on a recent revision to 01-644.
Distracter li Applicable but not most limiting.
Distracter 2: No such limit. Plausible but not most limiting.
.
. Distracter 3: Two C & F pump operation could continue Not most limiting.
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.Rev.O Reactor Operator, 50007 l
l
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' 01/20/99 Topic 1999 NRC Retest j-5799NRCA.
- 77 -
Exam Series A l-
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' Objective: 94.04.04.02 (NEW for 1998 ILC Retest)
1 Point 78. The plant has been in Station Blackout conditions for 30 minutes. The System Dispatcher calls to report that the grid has been restored at less than normal voltage. The operators at IC08 determine that incoming voltage is 2500 VAC. There are no bus or transformer lockouts.
' All 4KV Bus Transfer switches have been placed in MANUAL at Panel IC08.
Which of the following CORRECTLY describes the operation of the Degraded Voltage protection circuits and closing of breakers 1A301/302 and 1A401/402, the Standby /Startup Transformer Supplies to 1A3 and 1A4? -
)
a.
Bypassing and resetting Degraded Voltage relays is NOT procedurally allowed at this grid voltage.
This would prevent closure of 1A301/302 and 1A401/402.
b.
Bypassing of Degraded Voltage relays is procedurally allowed, but Degraded Voltage
_ protection would not reset at this grid voltage.
_
This would prevent closure of IA301/302 and 1A401/402.
c.
Bypassing and resetting Degraded Voltage relays is procedurally allowed and can be accomplished at this grid voltage.
Closure of 1A301/302 and 1A401/402 would be prevented by breaker undervoltage
protection.
i d.
Bypassing and resetting Degraded Voltage relays is procedurally allowed and can be j
- accomplished at this grid voltage.
With this protection bypatsed,1A301/302 and 1A401/402 can be closed to reenergize essential busses.
ANSWER:- C REFERENCE: AOP 301.1, Tab 3; SD-304 i
K!A System: 262001 i
K/A Number: A2.11 K/A Value:3.2/3.0 Cognitive Level: 3
Distracter 1: Per Tab 3, the OSS can direct that DV be bypassed.
,
Distracter 2: DV will reset after relays are bypaesed.
!
Distracter 3: Breakers will not close due to their undervoltage trips when <65%
Reactor Operator, 50007 Rev.0 >
1-
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01/20/99 Topic 1999 NRC Retest 5799NRCA -
78-Exam Series A l
L Objective: 47.01.01.13 (NEW for 1998 ILC Retest)
1 Point 79. Assume that Motive Steam to the Offgas Jet Compressor is completely lost while the plant in normal full power operation.
Which of the following WOULD NOT OCCUR as a result of this failure?
.
1 a.
Closure of CV-4108, Discharge to Offgas Stack.
b.
Closure of CV-1379, (SJAE) Imp Seal Isolation.
i c.
. Closure of MO-4151, Jet Compressor Inlet.
d.
Isolation of the Hydrogen Water Chemistry system.
ANSWER: A j
.
,
REFERENCE: OI-672 K/A System: 271000 K/A Number: A2.02 K/A Value: 2.9/3.1 Cognitive Level: 1 Note: CV-4108 is the main system isolation valve but it does not close in this situation.
)
Distracter 1: Plausible; This is a relatively minor valve but it isolates to prevent a radioactive release through a loop seal when line pressure increases due to MO-4151 closure.
Distracter 2: Plausible; but this valve closes when motive steam is lost.
Distracter 3: Plausible; This seems unrelated but it isolates as a result of MO-4151 closing.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA 79-Exam Series A
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Oujective: 85.00.00.03 (NEW for 1998 ILC Retest)
1 Point 80. Base the answer to this Process Radiation Monitoring question on your knowledge of the
l fundamental principles of radiation detectors, the installation of given detectors in the plant l
and the radiation levels involved.
What type of radiation detector is used in each of the following plant applications?
1) Main Steam Line Radiation Monitors 2) RHRSW/ESW Effluent Radiation Monitors
)
{
a.
1) lon Chamber 2) Geiger-Mueller b.
1) Ion Chamber
.
2) Scintillation c.
1) Geiger-Mueller 2) Geiger-Mueller d.
1) Geiger-Mueller 2) Seintillation ANSWER: B REFERENCE: SD-879.1
IUA: 272000 K/A Number: K1.01,1.02, &1.04 IUA Value: 3.6/3.8, 3.2/3.5, & 2.9/2.9
)
- Cognitive Level: 2 Distracter 1: RHRSW/ESW are scintillation detectors.
Distracter 2: MSL Rad monitors are Ion Chambers. RHRSW/ESW are scintillation detectors.
Distracter 3: MSL Rad monitors are Ion Chambers.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 80 -
Exam Series A l
l t
Objective: 65.01.01.05 (NEW for 1998 ILC Retest)
1 Point 81. An offsite radioactive release is in progress after an accident and the operators wish to maintain Control Room habitability by manually initiating the B Standby Filter Unit with a Control Building isolation.
(RIM-C101B is the Control Building Intake Air Rad Monitor.)
Can this be performed? (NO or YES)
If YES, what is/are the correct method (s) for accomplishing this?
l a.
NO; there is no procedure for this operation.
b.
YES; depress the TEST pushbutton for the B Standby Filter Unit.
c.
YES; remove the power supply fuse from the back of RIM-6101B.
~
I d.
YES; take the function control switch to ZERO on the front of RIM-Gl01B.
I ANSWER: C
REFERENCE: OI-730 K/A System: 290003 j
K/A Number: A3.01 K/A Value: 3.3/0.G J
Cognitive Level: 1
)
l
'
Note: Fuse removal was the correct method for many years untilit was changed to going to Zero.
Then it was discovered that going to zero did not work in every instance and the procedure was f
revised back to fuse removal. There is still a common misconception about how this is performed.
]
Distrccter 1: RO may not know that manualisolation/ initiation is possible.
Distracter 2: This will start the SFU but it will not initiate an isolation.
Distracter 3: RO may think going to zero is still a correct method.
Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest
!
5799NRCA-81-Exam Series A
o
)
' Objective: NSPEO 10.04.01.01 (NEW for 1998 ILC Retest)
1 Point 82. Which one of the following CORRECTLY describes the normal power supply arrangement for Air Compressor 1K 1?
a.
Transfer Switch IN3312 in AUTO position.
Normal Power Supply breaker 1B3312 CLOSED.
'
Back-up Power Supply breaker 1B4501 CLOSED.
If the.1B3312 power supply is lost, power will automatically transfer to IB4501.
There would be no interruption of power availability (make before break).
b.
Transfer Switch IN3312 in AUTO position..
Normal Power Supply breaker 1B3312 CLOSED.
Back-up Power Supply breaker IB4501 OPEN.
If the IB3312 power supply is lost, power will automatically transfer to IB4501.
Power would be momentarily interrupted (break before make).
.
!
c.
. Transfer Switch 1N3312 in the 1B3312 position.
i Normal Power Supply breaker 1B3312 CLOSED Back up Power Supply breaker 1B4501 CLOSED If the 1B3312 power supply is lost, the Transfer Switch IN3312 can be placed in the
,.
1B4501 position to restore power.
d.
Transfer Switch 1N3312 in the IB3312 position.
Normal Power Supply breaker 1B3312 CLOPRD -
Back-up Power Supply breaker 1B4501 OPEN If the 1B3312 power supply is lost, breaker 1B3312 can be opened, breaker 1B4501 can be closed and the Transfer Switch 1N3312 can be placed in the 1B4501 position to restore power.
' ANSWER:. D REFERENCE: 01518.1
.
K/A System: 300000
~ K/A Number: K2.02 K/A Value: 3.0/3.0 Cognitive Level: 1 Notei The potential exists to cross. tie essential busses through this switch, which is why it was
' designed as a break before make and why IB4501 is left open.
,
Distracter 1: No AUTO position or function.1B4501 is normally open.
Distracter 2: No AUTO position or function. IB4501 is normally open.
Distracter 3: IB4501 is normally open so this transfer cannot be accomplished from 1N3312.
'Rev.O Reactor Operator,50007
'
01/20/99 Topic 1999 NRC Retest 5799NRCA
- 82 -
Exam Series A
Objective: 28.01.01.05 (NEW for 1998 ILC Retest)
1 Point 83. A loss of Offsite power occurs while at power. The A and C General Service Water (GSW)
pumps were in operation.
When the Emergency Diesel Generators reenergize their respective busses, which General Service _ Water pump (s), if any, would be expected to be operating?
(Assume no further operator action.)
a.
'None b.
C GSW pump only c
A & B GSW pumps only d.
A, B, & C GSW pumps
,
ANSWER: A REFERENCE: SD-411 K/A System: 400000 K/A Number: K2.01 K/A Value:2.9/3.0
- Cognitive Level: 3 Note: A and B GSW pumps are from essential 4 KV busses; C GSW pump is from a non essential j
4 KV bus. If pump handswitches are not in PTL they spring to AUTO, providing a pump start on
)
low header pressure. However, these pumps load shed on a LOOP and will not auto restart if the
-
SBDGs are supplying bus power.
Distracter 1: No power to C. Selected if RO thinks C is from essential and A & B are not.
Distracter 2:. The essential busses for both A and B have power. Selected if RO does not know about load shed feature.
_
'
Distracter 3: The essential busses for both A and B have power but GSW pumps have load shed.
No power to C. Selected if RO thinks all pumps will restart on low pressure. This distracter
,
provides symmetry.
.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest
- 5799NRCA
- 83 -
Exam Series A
-
Objective: 83.01.01.02 (NEW for 1998 ILC Retest)
1 Point 84. The plant is operating at power. An LPRM calibration (OD 1) using the Transversing In-Core Probe (TIP) system has just been completed. All TIP detectors indicate IN-SHIELD and the TIP Ball valve indicates CLOSED.
The NSPEO in the Reactor Bldg. reports an acrid odor in the area of the TIP Room and recommends entering the TIP Room to investigate. The on-shift Health Physics Technician (HP) reviews survey history of the area and reports that there are general area dose rates of up to 2 Rem / Hour near the TIP Drive Mechanisms and dose rates of 5-8 Rem / Hour in the Chamber Shield (Pig) room.
Operators have tagged out the TIP System.
1) Will the NSPEO be performing an entry into a HIGH RAD AREA or a LOCKED HIGH RAD AREA?
And 2) Who must sign on the tagout?
.
a.
1) HIGH RAD AREA 2) Only OPERATIONS must sign on the tagout.
b.
1) HIGH RAD AREA 2) OPERATIONS and the responsible HEALTH PHYSICS Supervisor must sign on the tagout, c.
1) LOCKED HIGH RAD AREA.
2) Only OPERATIONS must sign on the tagout.
d. - 1) LOCKED HIGH RAD AREA 2) OPERATIONS and the responsible HEALTH PHYSICS Supervisor must sign on the tagout.
ANSWER: D
'
REFERENCE: ACP 1411.22;01-878.0 K/A System: 215001 K/A Number: Generic 2.3.10 K/A Value: 2.9/3.3 Cognitive Level: 1
,
. Distracter 1: >1R/ Hour is a LHRA. 01878.0 P&L 10 requires HPs on a TIP entry tagout.
Distracter 2: >1R/ Hour is a LHRA -
Distracter 3: 01878.6 P&L 16 requires HPs on a TIP entry tagout.
..Rev.O Reactor Operator, 50007 01/20/99-Topic 1999 NRC Retest 5799NRCA
- 84 -
Exam Series A
p
-
Objective: NSPEO 33.01.01.02 (NEW for 1998 ILC Retest)
1 Point 85. The plant is in a refueling outage with the refueling cavity filled and the Fuel Pool gates removed. The Fuel Pool Cooling system is in service with one pump, one heat exchanger und one domineralizer. Core Alterations are to begin in a few hours. The following system lineups are applicable:
The A loop of RHR is in the Shutdown Cooling mode and the B loop has been drained
.
for outage work.'
j
. Operators are' hanging the tagout in preparation for major maintenance on the Safety e
'
Relief Valves.
Assume that all equipment operates as designed. Will the following valve manipulations
,
(
LOWER or have NO AFFECT on the Skimmer Surge Tank level?
,
'
!
- (Evaluate separately.)
1) Open MO 1937, INBD RHR DRAIN TO RW ISOL and throttle open MO-1936, OUTBD RHR DRAIN TO RW THRTL ISOL.
- 2) Open MO-4423 and MO 4424, INBD and OUTBD MAIN STEAM LINE DRAIN ISOL valves.
a.
1) LOWER 2) LOWER
'
b.
1) LOWER
2) NO AFFECT 1) Nd AFFECT c.
2) LOWER
'd.
1) NO AFFECT-2) NO AFFECT
,
-ANSWER: B REFERENCE: 01-149; RFP 107 K/A System: 233000 K/A Number: A1.01
-
K/A Value: 2.6/2.9 -
Cognitive Level: 3 Distracter 1: 2) There is no affect because the steam line plugs would be installed.
Distracter 2: 1) It willlower because RHR crossover line is realigned to keep the drain valves in service for SDC. : 2) There is no affect because the steam line plugs would be installed.
Distracter 3: 1) It will lower because RHR crossover line is realigned to keep the drain valves in l'
service for SDC.
l Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-
- 85 -
Exam Series A l
Objective: 98.02.01.02 (NEW for 1998 ILC Retest)
1 Point 86. The upper-travel stops on the fuel prep machines have been adjusted upsard for new fuel receipt and inspection. The prescribed warning signs have been posted.
May an irradiated fuel assembly be placed in these prep machines? If YES, CORRECTLY identify the operation (s) for which this io permitted.
a.. NO b.
YES; Channel removal / replacement only i
c.
YES; Channel removal / replacement and testing for leaking fuel (Sipping).
d.
YES: Channel removal / replacement and fuel rod removal / replacement ANSWER: A
)
'
REFERENCE: RFP 404 K/A System: 234000 K/A Number: K4.03 i
K/A Value: 3.4/4.2 Cognitive Level: 1 Distracter 1: Not allowed under any circumstance.
Distracter 2: Not allowed under any circumstance.
Distracter 3: Not allowed under any circumstance.
Rev.0-Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-
-80-Exam Series A
rt l
Objective: 67.01.01.05a (NEW for 1998 ILC Retest)
1 Point l
87. Secondary Containment integrity has been established for refueling operations. Reactor Building
'
,
Ventilation is in a normallineup with Main Plant Exhaust Fans EF 1 and EF 2 running.
If the following postulated Reactor Building Ventilation failures were to occur, would Secondary Containment integrity be MAINTAINED or LOST? (Evaluate separately.)
l 1) Operators remove ventilation access panels in the vent duct from the Reactor Building to l
the Steam Tunnel (above the CRD Repair Room and in the Steam Tunnel) in order to route j
hoses for localleak rate tests. There is air flow out of the access panel above the CRD Repair
'
Room.
'
2) A System Engineer performing walkdowns in the Main Plant Exhaust Fan Room discovers a 1 inch x 3 ft, crack in a wall adjacent to the Reactor Building Vent Shaft. There is air flaw l
from the Vent Shaft into the Exhaust Fan Room through the crack
~
a.
1) MAINTAINED 2) MAINTAINED b.- 1) MAINTAINED 2) LOST
'
l c.
1) LOST
,
2) MAINTAINED i
d.
1) LOST ~
2) LOST ANSWER: B REFERENCE: P&ID M176<2> & M 153 K/A System: 288000 l
K/A Number: K1.02
- K/A Value:3.4/3.4 Cognitive Level: 3
- Note: 1) is routinely performed during outages; 2) was a plant event; Distracter 1: 2) The leak described essentially bypasses isolation dampers IV-AD 13A&B.
Distracter 2: 2) The leak described essentially bypasses isolation dampers IV AD-13A&B.
1) The Steam Tunnelis part of the Reactor Bldg. It has its own airlock from the Turbine Bldg.
Therefore Secondary Containment is not affected.
l Distracter 3: 1) the Steam Tunnel is part of the Reactor Bldg. It has its own airlock from the
'
Turbine Bldg. Therefore Secondary Containment is not affected.
Rev.O Reactor Operator, 50007
,
i'
.01/20/99 Topic 1999 NRC Retest 5799NRCA
- 87 -
Exam Series A
i Objective: 93.25.01.19 (From 1998 LOR exam.)
1 Point l
88. Which form of component verification, DUAL or INDEPENDENT, is required of the personnel involved in the following activities? (Evaluate separately.)
,
l 1) Two 345 KV breakers in the switchyard are opened and tagged for system distribution work.
- 2) A Lifted Lead is performed as part of an approved Temporary Modification to the Feedwater Heater level controllers.
i l
a.
1) DUAL l
2) DUAL b.
1) INDEPENDENT 2) DUAL
.
c.
' 1) DUAL l
2) INDEPENDENT d.
1) INDEPENDENT 2) INDEPENDENT
L ANSWER: A
.
l REFERENCE: IPOI 7, Rev. 53, Section 8.1(2)
K/A System: Generic; Conduct of Ops K/A: 2.1.29 K/A Value: 3.4/3.3 Cognitive Level: 2 Distracter 1: Switchyard repositioning requires Dual.
Distracter 2 : Temp Mods in any system require Dual.
Distracter 3: Switchyard repositioning requires Dual. Temp Mods in any system require Dual.
I i
.Rev.O Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest
- 5799NRCA -
- 88 -
Exam Series A
c Objective: 93.16.01.10 (Revised, from a 1996 LOR weekly exam. )
1 Point 89. A normal reactor shutdown is in progress. The reactor is in Mode 2 at 9% power. A second
.
licensed operator has been assigned to assist in reactivity monitoring.
I l
At this point, the Ik0 Supervisor informs ihc Control Room that, due to a non qualified part, f
l the Rod Worth Minimizer (RWM) may not enforce Insert Blocks for out-of-sequence control rods. The OSS declares the RWM inoperable.
l
Which of the following is CORRECT?
I l
The RWM is not required to be operable at 9% power. No further action is required and a.
the shutdown may continue, b.
The RWM is not required to enforce Insert Blocks during a reactor shutdown. No further action is required and the shutdown may continue.
.
STP 3.3.2.1-04 "RWM Inoperative Test" should be performed and then the shutdown may c.
continue.
d.. A reactor scram is the only way to insert control rods with the RWM inoperable.
I ANSWER: C REFERENCE: IPOI-4 K/A System: Generic; Operator Responsibilities in All Modes.
K/A Number: 2.1.2 K/A Value: 3.0/4.0 Cognitive Level: 1 Distracter 1: T.S. Requires RWM operability < 10% power and IPOI-4 requires it at all times.
Distracter 2: T.S. Requires RWM operability < 10% power and IPOI-4 requires it at all times.
l Distracter 3: Not true if the STP is performed.
l l
Rev.O Reactor Operator,50007 01/20/09 Topic 1999 NRC Retest 5799NRCA
- 89 -
Exam Series A
,
~ Objective: 93.24.01.01 (NEW for 1998 ILC Retest)
1 Point 90. The plant is operating at full power during very cold winter weather. The Circulating Water System is operating as follows:
8 Cooling tower fans are either STOPPED or operating in REVERSE in order to
.
de-ice the Cooling Tower cells.
The Auxiliary Operator reports that Cooling Tower de-icing has been effective.
j
.
Cire Water Blowdown, MO-4253, is open with 50% of this flow supplying de-icing
.
flow to the intake Structure.
Cooling Tower outlet temperature is 99.5*F and rising slowly.
.
Which of the following is CORRECT concerning operation of the Cire Water System?
a.
No operator action is necessary because the warmer Cire Water is desired for de-icing Cooling Tower cells.
.
b.
Operators must start more Cooling Tower Fans in FORWARD.
c.
Operators must close V 42-9 & 10 to secure flow to the Intake Structure de-icing and
'
verify that the Blowdown is open.
d.-
Operators must throttle the Cooling Tower Sparger Bypass valves further open.
ANSWER: B REFERENCE: IPOI 6;01-410; 01-442 K/A System: Generic; Perform Ols and IPOIs -
K/A Number: 2.1.23
- K/A Value: 3.9/4.0 Cognitive Level: 2 Note: Tower Discharge must be maintained <100 F in this mode. Correct answer option is not explicitly stated, but it is the only viable action.
Distracter 1: Warmer water is better, but the Tower outlet limit is 100 F which requires action.
Distracter 2: Plausible action to stop discharge, but blowdown flow also goes to the river so this action does not solve the problem. Also, RWS could be lost ifintake screens freeze over.
Distracter 3: Adjusting spargers is a plausible action to control Cooling Tower Temperatures, but throttling these valves open causes Tower discharge temp to increase.
Rev.O Reactor Operator, 50007-01/20/99'
Topic 1999 NRC Retest 5799NRCA
- 90 -
Exam Series A
7_
Objective: 93.11.01.13 (Revised, from 11996 LOR weekly exam.)
1 Point 91. What is the MAXIMUM loadline allowed by IPOI 3," Power Operations"?
a 105 %
.
b.'
100%
c.
107 %
d. '108%-
- ANSWER: D~
REFERENCE: IPOI 3, P&L 7 K/A System: Generic; Explain / Apply system limits and precautions.
- K/A Number: 2.1.32 K/A Value: 3.4/3.8 Cognitive Level: 1 Distracter 1: Plausible and homogeneous; but too low.
Distracter 2: Plausible and homogeneous; but too low.
Distracter 3: Plausible and homogeneous; but too low.
)
Rev.O Reactor Operator, 50007
. 01/20/99 Topic 1999 NRC Retest 5799NRCA
- 91 -
Exam Series A
.-
Objective: 90.05.02.15 (NEW for 1998 ILC Retest)
1 Point 92. A plant shutdown is being planned.
The Chemistry Supervisor wants to keep the Hydrogen Water Chemistry (HWC) system in service as long as possible. He requests that HWC be secured at 10% power rather than 20% power as directed by IPOI-4, " Shutdown".
Assume that the Operations Manager decides that there would be no operational problem involved.
- Which of the following is CORRECT concerning the use of an Operating Order and/or a Shift Order to implement this change?
- a.
NEITHER an Operating Order nor a Shift Order would be appropriate.
b.
An Operating Order would be appropriate.
- A Shift Order would NOT be appropriate.
c.
A Shift Order would be appropriate.
An Operating Order would NOT be appropriate.
d.
EITHER an Operating Order or a Shift Order would be appropriate.
ANSWER: A REFERENCE: ACP1410.1, Sect. 3.10 K/A System: Generic; Conduct of Operations K/A Number: 2.1.1 K/A Value: 3.7/3.8 Cognitive Level: 2 Distracter 1,2, &3: NEITHER would be appropriate. Operating Orders and Shift Orders cannot conflict with approved procedures.
,
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-92-Exam Series A
Objective 90.05,02.21 (NEW for 1998 ILC Retest)
1 Point 93.: The plant is in normal full power operation with no LCOs.
At panel 1C05, the Reactor Operator notices that the Standby Liquid Control Tank level has lowered slightly and asks the NSPEO to investigate. The NSPEO reports that there are no
. leaks but that the levelindicator bubbler air flow is low. The RO airects the NSPEO to rod out the bubbler tube.
!
l After a short while, the NSPEO calls the Control Room and states, "The SBLC procedure is l
missing and it has been a long time since I have done this. Do I rod it out from the top or L
from the bottom?". The RO provides the answer and verifies that NSPEO understands the l
remaining steps.' The NSPEO successfully completes the task. The SBLC tank level returns to normal.
Have the operators in the above postulated scenaric ;omplied with ACP 101.01, " Procedure Use and Adherence" and with ACP 1410.1, " Conduct of Operations"?
.
a.
COMPLIED; This is an "Immediate Operator Action" procedure per ACP 1410.1 which allows referencing a procedure after completion of the task, b.
COMPLIED; The "Information Use" level of procedure adherence is applicable to this situation. The operator retains responsibility for proper performance.
J c.
DID NOT COMPLY; The " Reference Use" level of procedure adherence is applicable to this situation and there was no procedure present at the SBLC tank.
d.
DID NOT COMPLY; ACP 1410.1 specifies Operating Instructions (OIs) as " Continuous Use" procedures and there was no procedure present at the SBLC tank.
ANSWER: C REFERENCE: ACP 101.01; ACP 1410.1 K/A System: Generic; Ability to execute procedure steps K/A Number: 2.1.20 K/A Value: 4.3/4.2 Cognitive Level: 3 Note: Step 3.3(4) states that if there is any doubt as to procedural action, the procedure shall be present j
l
' (Reference use) and ACP 1410.1 explicitly lists Ols as " Reference Use".
Distracter 1: Plausible, but task is not listed in ACP 1410.1(mainly emergency operations).
Distracter 2: A common misconception. ACP 1410.1 explicitly lists Ols as " Reference Use".
Distracter 3: Plausible if the definition of" Continuous Use"is not understood. ACP 1410.1 specifies OIs as " Reference Use" and STPs as " Continuous Use".
!
Rev.O Reactor Operator, 50007 l
01/20/09 Topic 1999 NRC Retest l
5799NRCA.
- 93 -
Exam Series A
[I I
l
' Objective: 1.06.01.01 (NEW for 1998 ILC Retest)
1 Point 94. Which of the following situations WOULD require implementation of ACP 1410.6,
" Temporary Modification Control"?
a.
Temporary hose connections are made between a system and the Local Leak Rate Test l
(LLRT) equipment.
' b.
Jumpers are installed in an RPS panel as part of a Special Test Procedure that includes sign-offs for jumper installation, verification and removal.
c.
An RHRSW pump motor is determinated per CMAR for removal to a repair shop during an outage, l
d.
A high speed recorder is installed per a CMAR and left in place for several days to monitor an intermittent main generator ground problem.
,
ANSWER: D
. REFERENCE: ACP 1410.6 K/A System: Generic; Knowledge of Temp Mods K/A Number: 2.2.11 K/A Value: 2.5/3.4 Cognitive Level: 2 Note: Specifically required by Section 1.0 (3 & 4) when installed under a CMAR for >8 hours.
Distracter 1: Specifically exempted by Section 2.0, Mechanical Jumpers.
Distracter 2: Specifically exempted by Section 1.0 (1).
Distracter 3: Specifically exempted by Section 1.0 (2).
<
Rev.O Reactor Operator, 50007
_
.01/20/99 Topic 1999 NRC Retest 5799NRCA
- 94 -
Exam Series A
Objective: 90.03.01.04 (From 1998 LOR exam.)
1 Point 95. The "Tagout Procedure", ACP 1410.5, describes a Temporary Tag Removal process.
Identify if the situation described in the following postulated scenario is an allowable tagging practice? (ALLOWABLE or NOT ALLOWABLE)
If ALLOWABLE, identify the correct additional considerations.
!
If NOT ALLOWABLE, identify the correct reason.
The Auxiliary Boiler is in operation for plant heating during a forced outage. Operators tagged out the Steam Drum sight glass due to a leak and Mechanics have completed repairs. The Operators and Mechanics agree to perform a Temporary Tag Removal to verify that the leak has been fixed before signing the release of the Hold Tags.
~
a.
ALLOWABLE, if tags removed by the Temporary Tag Removal process are replaced within four (4) hours, b.
ALLOWABLE, if the OSS or OSM also signs for approval of the Temporary Tag Removal.
c.
NOT ALLOWABLE, because the Temporary Tag Removal process cannot be us3d on the Auxiliary Boiler, d. -- NOT ALLOWABLE, because the Temporary Tag Removal process can only be used during refueling outages.
j ANSWER: C REFERENCE: ACP 1410.5; K/A System: 2.0 K/A Numbcr: 2.2.13 K/A Value: 3.6/3.8 Cognitive Level: 2 Note: The Temporary Tag Removal process can only be used to support maintenance on deenergized electrical busses.
Distracter 1: Plausible, but not allowed on Aux Boiler and no time limit is applicable Distracter 2: Plausible, OSS/OSM approvalis required, but not allowed on Aux Boiler
- Distracter 3: Plausible; such electrical maint is usually performed during refuel outages but there is no such restriction, the process could be used during a maintenance outage.
I
!
i l
Rev.O Reactor Operator, 50007 l
01/20/99 Topic 1999 NRC Retest l
5799NRCA 95 -
Exam Series A j
...
.
.
.
.
.
.
____
Objective: 1.03.03.03 (Revised from 1996 Audit Exam.)
1 Point 96. The Main Turbine Control Valve Fast Closure RPS Trip function is designed, in combination with other LCOs, to prevent any anticipated combination of transient conditions that would result ni ceaching which of the following limits?
i a.
The RPV high pressure scram setpoint.
b.
The RPV pressure SAFETY LIMIT.
c.
The Average Planar Linear Heat Generation Rate (APLHGR) Power Distribution Limit, d.
The fuel cladding integrity Minimum Critical Power Ratio (MCPR) SAFETY LIMIT.
'
- ANSWER:- D REFERENCE: T.S. Bases B2.1.1
K/A System: 2.0 K/A Number: 2.2.22 K/A Value: 3.-1/4.1 Cognitive Level: 1 Distracter 1&2: TCV Fast Closure Scram does lessen the RPV pressure transient, but its purpose is to avoid the MCPR SL.
Distracter 3: This is not the thermal limit of concern during TCV Fast Closure,
,
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA
Exam Series A
,
.
.
.
.
._
_
Objective: 1.03.02.01 (NEW for 1998 ILC Retest)
1 Point
' 97.' Assume that chart paper is replaced (uneventfully) on a Tech-Spec-required, Post Accident Monitoring (PAM) recorder in the control Room while at power.
Which of the following is CORRECT concerning the need to complete Safety Function Determination (SFDP) paperwork and a log entry for thie activity?
The activity described would require...
a.
neither SFDP paperwork nor a log entry.
b.
SFDP paperwork but not a log entry.
c.
a log entry but not SFDP paperwork.
- d.
both SFDP paperwork and a log entry.
ANSWER: A REFERENCE: ACP 1410.2 K/A System: Generic; Ability to track LCOs X/A Number: 2.2.23 K/A Value:2.6/3.8 Cognitive Level: 2 Note: This question arose after ITS implementation in 1998 and resulted in the first revision to the Safety Function Determination Program procedure, ACP1410.2. Per this ACP, LCOs are entered but need not be logged or further documented if the activity is uneventful.
Distracter 1: Neither is required for an uneventful paper replacement.
Distracter 2: Neither is required for an uneventful paper replacement.
Distracter 3: Neither is required for an uneventful paper replacement.
Rev.O Reactor Operator, 50007 01/20/99 Topic 1999 NRC Retest 5799NRCA-97-Exam Series A L
_
-
-;
n
" Objective: NSPEO 48 02 (NEW for 1998 ILC Retest)
1 Point
.
.
98J The following contamination levels were found during the survey of an area:
l
.
40 dpm /100 cm2 Alpha activity
e.
300 dpm /100 cm2 Beta Gamma activity Which of the following ' statements is CORRECT concerning the DAEC requirements for the radiological posting of this area?
a.
No posting is necessary.
Both Alpha'and Beta Gamma activity levels are BELOW the limit for a Contaminated Area.
b.
Area should be posted as a Contaminated Area.
Alpha activity levels are ABOVE the limit for a Contaminated Area.
Beta-Gamma activity levels are BELOW the limit for a Contaminated Area.
- c.
Area should be posted as a Contaminated Area.
Beta'-Gamma activity levels are ABOVE the limit for a Contaminated Area.
Alpha activity levels are BELOW the limit for a Contaminated Area, d.
Area should be posted as a Contaminated Area.
Both Alpha and Beta-Gnmma activity levels are ABOVE the limit for a Contaminated Area.
ANSWER: B EREFERENCE: ACP 1411.22 K/A System: Generic; Knowledge of Rad exposure and contamination limits.
K/A Number: 2.3.4
'
K/A Value: 3.5/3.1 Cognitive Level: 1
,
Note: Limits for a contaminated area are >20 dpm/100 cm2 Alpha or >1000 dpm/100 cm2 B-G.
< Numbers in stem are based on the possible misconception that Alpha limit is 50 and B-G limit is 200.
>
Distracter 1: Alpha > limit; B-G < limit.
,
Distracter 2: Alpha > limit; B-G < limit.
Distracter 3: Alpha >1imit; B-G < limit.
- .
!
I Rev,0:
Reactor Operator,50007 01/20/99 Topic 1999 NRC Retest j
5799NRCA ~
98-Exam Series A i
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l Objective: 94.25.01.01 (NEW for 1998 ILC Retest)
1 Point l
99. 'A major fire is in progress inside the Intake Structure and the Palo Fire Department has been called for assistance per AOP 913," Fire".
Which of the following is the AOP 913 identified source of water for Palo fire equipment?
a. ' Connection to the DAEC fire main.
b.
The Palo FD tanker truck, refilled at a Cooling Tower basin.
c.
Drafting from the Cedar River.
d.
Drafting from the Discharge Canal.
I ANSWEll: D
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REFERENCE: AOP 913 K/A System: Generic; Knowledge of the Fire AOP K/A Number: 2.4.27 K/A Value: 3.0/3.5 Cognitive Level: 1-Note: This question is based on a recent procedure revision. A concrete chamber was built in the discharge canal for the purpose of fire department drafting.
Distracter 1: Selected if RO does not know that the fire main does not go to the river.
Distracter 2: Plausible, but slow and not the identified source.
' Distracter 3: Plausible, but difficult to establish and not the identified source.
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l Rev.O Reactor Operator, 50007
'01/20/99 Topic 1999 NRC Retest 5799NRCA 99-Exam Series A
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Objective: None (NEW for 1998 ILC Retest)
1 Point
100.May the Evacuation Alarm be sounded from the Control Room in the following situations?
(YES or NO) -
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. (Evaluate separately.)
1) An event has occurred which requires evacuation of the Turbine Building. An Emergency
' Classification has not yet been declared but the crew wants to verify that everyone is out of the Turbine Building.
2) An Unusual Event has been declared and the situation warrants an evacuation.
a.
1) YES -
2) YES b.'
1)YES 2)NO
. c.
1)NO
'
2) YES d.
1)NO i
2)NO
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i ANSWER: A
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REFERENCE: EPIP 1.3 K/A System: Oeneric; Knowledge of EPIP communications K/A Number: 2.4.43 K/A Value: 2.8/3.5 Cognitive Level: 1 l
Note: At the DAEC, the STA usually performs this task but it is not uncommon for it to be delegated to an RO.
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Distracter 1: May be used for an UE per 3.1(1)(a).
Distracter 3: May be used for other occurrences per 3.1(1)(b) especially for accountability.
Distracter 3: May be used for other occurrences per 3.1(1)(b) especially for accountability. May be used for an UE per 3.1(1)(a).
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INITIAL SUBMITTAL OF THE OUTLINE FOR THE i
DUANE ARNOLD EXAMINATION - WEEK OF 05/24/99 l
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