IR 05000331/1999302
| ML20217N566 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/25/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20217N518 | List: |
| References | |
| 50-331-99-302OL, NUDOCS 9910290072 | |
| Download: ML20217N566 (200) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION lil-I Docket No:
50-331 License Nos:
DPR-49 l
Report No:
50-331/99302(OL)
Licensee:
IES Utilities Inc.
Facility:
Duane Arnold Energy Center Location:
IES Utilities Inc.
l 200 First Street SE P.O. Box 351 Cedar Rapids, IA-52406-0351 l
l Dates:
September 20-24,1999 l
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l Examiners:
D. McNeil, Chief Examiner, Rlll l.
D. Roth, Resident inspector - Dresden Station
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M. Murphy, Examiner, RIV l
A. Stone, Examiner, Rlli (Certification Examination)
l Approved by:
D. Hills, Chief, Operations Branch Division of Reactor Safety l
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9910290072 99i'?35
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PDR ADOCK 05GW 331 V
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EXECUTIVE SUMMARY Duane Arnold Energy Center NRC Examination Report 50-331/99302(OL)
A Nuclear Regulatory Ccmmission developed initial operator licensing examination was administered to two Reactor Operator and four Senior Reactor Operator license applicants.
The examiners reviewed several station administrative and operating procedures while developing the examination.
Examination Results:
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All applicanis passed all portions of the examination and were issued operating licenses.
Ooerations:
With one exception, the piocedures reviewed by the examiners were well written. The station's operators were normally able to use the provided procedures correctly.
(Section O3.1)
l The facility training staff developed a written examination and operating test that could be used to evaluate an applicant with a minimum of revision by the NRC examiners.
(Section 05.2)
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The applicants were well prepared for the operating test and written examination. In l
general, they displayed good operating and communicaticns skills during the operating
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test. The facility training staff was well prepared to support the examination process.
(Sections,05.3, 05.4)
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Reoort Details
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I 1. Operations
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Operations Procedures and Documentation 03.1 General Comments i
a.
Scope (71707)
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The examiners reviewed portions of selected administrative and operating procedures
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n during the initial license examination development using Inspection Procedure 71707.
See page 9 for a partial list of procedures reviewed.
b.
Observations and Findinas i
The NRC exam developers found that most procedures were well organized and nomially used correctly by the station operators and by the licensed /previously licensed applicants during the operating test validation and administration.
Almost all of the applicants pme currently licensed or previously licensed) had difficulty
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executing one abnormal operating procedure (AOP 915) during their Job Performance l
Measures (JPMs) test. See section 05.3 for details.
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Conclusions With one exception, the procedures reviewed by the examiners were well written. The station's operators were normally able to use the provided procedures correctly.
Operator Knowledge and Performance 04.1 General Comments Operators were observed while validating the operating test. The operators validated seven administrative JPMs, ten operating JPMs and two dynamic simulator scenarios.
The operators performed their responsibilities in an acceptable manner.
(Closed) Insoection Followuo item (IFI) 50-331/98301-03: This followup item concerned
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the operational adequacy of the licensee's operators and training staff and was based l
on the poor performance of the three operators that validated the 1998 initial license
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operating test. The operators were given remedial training and re-evaluated by the training staff. They were determined to be satisfactory operators and retumed to their i
operating crews. The operators assigned to validate this operating test displayed only I
one minor weakness while validating the dynamic simulator scenarios; the weakness was addressed immediately following the second dynamic simulator scenario by the training department instructors present at the validation. This item is closed.
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' Operator Training and Qualification 05.1. Pre-Examination Activities a.
Scope The Duane Amold Energy Center (DAEC) training staff used the guidance prescribed in NUREG 1021, Operator Licensing Examination Standards for Power Reactors, Rev. 8, April 1999, to prepare the operating test and the written examination.
b.
Observations and Findinas -
Outline Submittal
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The licensee submitted the examination outline on schedule. The outline contained several errors that were immediately corrected by the training staff when identified by the NRC examiners. The submitted outline:
did not have the correct number of administrative JPM tasks.
- Incorrectly repeated one safety function group twice on the control room job
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performance measures.
was missing some required initials on.a review sheet.
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'was missing required signatures at the bottom of the ES-301-5 form.
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Examination Submittal The proposed examination was submitted on schedule and contained all the required JPMs and scenarios to adequately evaluate an applicant. During the validation week, the NRC examiners determined that one administrative JPM was not ar. effectivt evaluation tool, and one operating JPM was more representative'of an administrative
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JPM. The original administrative JPM was replaced by the proposed oj 'erating JPM and p
a new operating JPM was inserted into the operating test.
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The written examinations developed by the training staff met the guidelines of NUREG l
1021. Only one question was determined to be unsatisfactory and was replaced at the direction of the examiners. The examiners suggested minor editorial changes to several other questions to improve their readability.
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Conclusions The facility training staff developed a written examination and operating test that could be used to evaluate an applicant with a minimum of revision by the NRC examiners.
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O5.3 Examination Activities a.
Scope
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The NRC examiners administered the operating test (JPMs and dynamic scenarios)
during the week of September 20,1999. Training department instructors administered the written examination on September 24,1999. The tests were administered using the guidance prescribed in sections ES-302 and ES-402 of NUREG 1021.
b.
Observations and Findinas Operatina Test During the operating test, the applicants quickly found appropriate procedures when required and normally executed the procedures correctly. Applicants corvnunicated clearly and accurately with only occasional failures to complete repeaAbas; crew briefs during the dynamic scenarios were generally good. Applicant diagnostic skills were normally accurate. Control board switch manipulations were normally accurate with only a few isolated errors. Senior Reactor Operator command and control skills and knowledge of technical specifications were good.
Several applicants became confused while trying to execute a JPM that required operators to transfer equipment control functions from the control room to the remote shutdown panel (AOP 915). After the controls were transferred, the examiners cued the applicants that the indicating lights for the "B" feedwater pump were still deenergized.
The applicants correctly entered AOP 915, Attachment 3, and determined that they should go to panel 1C422F to replace four fuses. When the applicants arrived at the fuse panel, they realized that the specified fuses provided power to "A" and "B" feedpump indications. This caused confusion because the applicants did not want to remove fuses for a running pump. An action r6 quest was written by a training department representative to document and resolve the procedure or JPM weakness.
The training staff's support of the examination process was good. Turnover sheets, surveillances, procedures, and other paperwork required to support the administration of the operating test was always correct and detailed. Shift tumovers provided by the instructors during the dynamic scenarios were typical of those used during the training process and varied slightly from those used in the control room. The licensee training staff coordinated the arrival times of the applicants and provided escorts to maintain examination security during the operating test. The licensee's daily setup and execution of the operating test during the validation and examination weeks was timely and accurate.
Written Examination The written examination was administered in the training center's examination room.
The room provided ample space for the applicants, and was quiet and well ventilated.
An instructor read the examination requirements to the applicants prior to the examination and verified that all applicants had all the examination materials required for the examination. The examination was completed within the allowable 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
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Conclusions The applicants were well prepared for the operating test and written examination. In general, they displayed good operating and communicating skills during the operating test. The facility training staff was well prepared to support the examination process.
05.4 Post Examination Activities a.
Examination Scoce The NRC examiners evaluated individual applicant performance on the operating test and the written examination. The licensee did not submit any post examination comments. Examiners followed the guidelines contained in sections ES-303, ES-403, and ES-501, of NUREG 1021.
b.
Observations and Findinas Job Performance Measures No generic knowledge deficiencies were discovered while grading the candidates'
performance of the operating and administrative JPMs.
Dynamic Simulator Scenarios
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The NRC examiners did not identify any significant or generic weaknesses during the review of the cynamic simulator scenario test results.
Written Examination All of the applictnts passed the written examination with scores ranging from approximately 81% to 94%. There were five questions that were answered incorrectly by more than 50% of the applicants. These questions were considered generic knowledge deficiencies and were provided to the DAEC training staff as feedback for consideration and implementation into the Systematic Approach to Training-based program.
Question #
Knowledae Weakness
- 6(RO/SRO)
Recognition of change in reactor period and the reason for the change in reactor period.
- 11(RO/SRO)
Insertion of Intermediate Range Monitors (IRMs) during an Anticipated Transient Without Scram (ATWS) event and the technique involved in using the IRM instrumentation.
- 60(SRO)
Automatic Depressurization System initiation requirements.
- 76(RO/SRO)
The primary side power supply for T4.
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- 96(SRO)
Authority to authorize exceeding applicable dose limits during a site emergency.
c.
Conclusions The lack of generic operating weaknesses and the small number of questions missed by more than 50% of the applicants indicated a comprehensive training program that met the needs of the applicants.
l 05.5 Simulator Fidelity
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The simulator performed well during the validation week, during the operating JPM test l
and during tae dynamic simulator scenarios with no noted deficiencies. This was documented in Enclosure 2, Simulation Facility Report.
V. Manaaement Meetinas I
X1 Exit Meetina Summarv
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The chief examiner presented the examination team's observations and findings to members of
the licensee's management on September 24,1999. The licensee acknowledged the findings l
presented and indicated that no proprietary information had been identified during the examination or at the exit meeting.
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o PARTIAL LIST OF PERSONS CONTACTED Licensee
R. Anderson, Plant Manager
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R. Becker, Training, Ops Instructor D. Curtland, Operations Manager M. Davis, Training Supervisor, Operations M. Fisher, Training, Ops instructor R. Hunt, Lead Simulator / Ops instructor J. Karrick, Licensing R. Murrell, Reg Comm Sup K. Peveler, Manager, Regulatory Communications W. Render, Training, Ops Instructor G. VanMiddlesworth, Site Vice President J. Van Sickel, Operations Superintendent M. Walter, Training, Ops Instructor K. Young, Manager, Nuclear Training i
NRC M. Kurth, Resident inspector, DAEC P. Prescott, Senior Resident inspector, DAEC INSPECTION PROCEDURES USED
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IP 71707, " Plant Operations"
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ITEMS OPENED, CLOSED, AND DISCUSSED Ooened None Closed 50-331/98301-03 IFl Operational adequacy of licensee's operators and training staff.
Discussed None
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e LIST OF ACRONYMS USED CFR Code of Federal Regulations
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DRS Division of Reactor Safety IP inspection Procedure JPM Job Performance Measure NRC Nuclear Regulatory Commission OL Operator Licensing -
RO Reactor Operator SRO Senior Reactor Operator PARTIAL LIST OF PROCEDURES REVIEWED ACP 1410.5, Section 3.4.3, Equipment Tagout
' ACP 1410.2, Safety Function Determination Program ACP 1411.13, Entry into Locked High Rad Area AOP 915, Shutdown Outside the Control Room -
ARP 1C04A (C-5), A RECIRC MG SET SCOOP TUBE LOCK DAEC Fire Plan, Volume 2," Fire Brigade Organization" DAEC Emergency Plan implementing Procedure (EPIP) 3.3, Dose Assessment DAEC EPIP, Table 2, Protective Action Recommendations (PARS)
DAEC EPIP, Section 10, PARS 01573, Containment Atmosphere Control System Ol 170, Standby Gas Treatment System Ol 264, Reactor Recirculation System Ol 304.2,4160 V/480 V Essential Electrical Distribution 01-152, High Pressure Coolant Injection System Oi 879.2, Area Radiation Monitoring System O1730, Control Building HVAC System Ol 317.1,120 VAC Instrument Control Power System
' SEP 307, Rapid Depressurization with Bypass Valves STP 3.0.0-01, Instrument Checks STP 3.0.0-02, Control Room Panel Shiftly Checklist
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Enclosure 3
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SIMULATION FACILITY REPORT Facility Licensee: Duane Amold Energy Center Facility Licensee Docket No: 50-331
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- Operating Tests Administered: August 20-23,1999 The following documents observations made by the NRC examination team during the initial license examination. These observations do rot constitute audit or inspection findings and are Q
not, without further verification and review, inc'icative of non-compliance with.10 CFR 55.45(b).
These observations do not affect NRC certification or approval of the simulation facility other than to provide information which may be used in future evaluations. No licensee action is required in response to these observations.
During the conduct'of the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTION
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l U.S. Nuclear Regulatory Commission l
Site-Specific i
Written Examination
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Applicant Information I
Name: MASTER COPY Region:
111 Date: September 24,1999 Facility / Unit:: DAEC
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License Level:
Start Time: 7:58 Finish Time: 12:58
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l instructions j
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected five hours after the examination starts.
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l Applicant Certification All work done on this examination is my own. I have neither given nor received aid, i
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Applicant's Signature Results Examination Value 100.0 Points Applicant's Score Points Applicant's Grade Percent
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WRITTEN EXAMINATION GUIDELINES 1.
Cheating on any part of the examination will result in a denial of your application and/or action against your license.
2.
After you complete the examination, sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the examination.
3.
To pass the examination, you must achieve a grade of 80.00 percent or greater; grades
will not be rounded up to achieve a passing score. Every question is worth one point.
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The time limit for completing the examination is five hours.
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You may use the provided pencils, and calculators. Do not use pens b mark your j
answers on the scan-tron answer sheets.
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6.
Print your name in the blank provided on the examination cover sheet and on the answer sheet. You may be asked to provide the examiner with some form of positive identification.
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Mark your answers on the answer sheet provided. Use only the paper provided. Erase completely if you decide to change your original answer, then mark the new answer yoiu have chosen. If the NRC grading examiner is unable to determine which answer you have selected because of poor erasure, the examiner will mark the answer as incorrect.
8.
If you have any questions concerning the intent or the initial conditions of a question, do not hesitate asking them before answering the question. Ask questions of the NRC examiner or the designated facility instructor only. When answering a question, do not make assumptions regarding conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question. For l
example, you should not assume that any alarm has activated unless the question so states or the alarm is expected to activate as a result of the conditions that are stated in the question.
9.
Restroom trips are permitted, but only one applicant at a time will be allowed to go to the l
restroom. Use the restroom in the exam room.
10.
When you complete the examination, bring the answer sheet and cover sheet to the
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NRC examiner or proctor. Sign the statement on the examination cover sheet indicating that the work is your own and that you have neither given nor received assistance in completing the examination. The proctor will clean up your table and reference material after you leave the exam room.
11.
After you have turned in your examination, leave the examination area as defined by the proctor or NRC examiner. If you are found in this area while the examination is stillin progress, your license may be denied or revoked.
12.
Do you have any questions?
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I REACTOR OPERATOR Page 3 QUESTION: 001 (1.00)
During a reactor power ascension following startup, the plant was operating at 25% load when alarm 1C07A A-2, MAIN TURBINE TRIP, actuated. While verifying turbine status as directed by the Annunciator Response Procedure, the operator notes the following:
Generator output breakers are TRIPPED.
' All turbine CONTROL VALVES are CLOSED.
All turbine main STOP VALVES are CLOSED.
All CIV STOP valves are OPEN.
All CIV INTERCEPT valves are 95% OPE.N and CLOSING.
Turbine BYPASS valves are open to control reactor pressure.
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Evaluate the above indications and select the answer that CORRECTLY describes the status of the Main Turbine.
a.
The main turbine did not respond correctly to the turbine trip and !s in danger of I
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sustaining damage.
b.
The main turbine tripped normally and will be coasting down; all valve positions are as expected.
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The turbine trip was due to mechanical overspeed and the turbine is responding normally to this condition.
d.
Not all turbine valves responded as expected, but the backup overspeed trip will protect the turbine.
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REACTOR OPERATOR Page 4 QUESTION: 002 (1.00)
The plant has SCRAMMED from full power. While stabilizing the plant, an operator observes the following indications:
The running CRD pump current is above normal running amps.
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CRD Cooling Water flow is DOWNSCALE.
Select the answer that CORRECTLY explains these indications and identifies the appropriate operator response.
a.
The flow control station has failed; action must be taken as soon as possible to protect the CRDMs.
b.
The in service CRD suction filter is clogged; the standby filter must be placed in service as soon as possible.
c.
CRD pump flow is being diverted through the Scram Inlet valves to the CRDMs and the reactor; no further actions are necessary.
d.
The running CRD pump is air bound and must be tripped as soon as possible.
QUESTION: 003 (1.00)
An l&C tech performing an STP inadvertently initiated a Group I isolation while at full power.
The resultant transient lifted four Safety-Relief Valves, including the two low-low set valves, on high RPV pressure. After these valves close, as indicated by their associated amber lights extinguishing, the operators take no further action. At WHAT PRESSURE will the next Safety-Relief Valve open and WHY?
a.
1020 psig; to prevent reaching the high pressure scram setpoint.
b.
1020 psig; to protect the SRV tailpipes from damage.
c.
1110 psig; to protect the reactor from overpressurization.
d.
1110 psig; to minimize cycling of the other SRVs.
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REACTOR OPERATOR Page5
- QUESTION: 004 (1.00),-
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One of the running Reactor Feed Pumps was inadvertently TRIPPED while the plant was at 90% power.
1)
Does the resultant transient result in CARRYOVER or CARRYUNDER 7 2)
What is the primary concern associated with this condition?
a.
1)
CARRYOVER 2)
Excess moisture impinging the blades of the Main Turbine.
b.
1)
CARRYOVER 2)
Reduction in Recire Pump Net Positive Suction Head.
c.
1)
CARRYUNDER
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Excess moisture impinging the blades of the Main Turbine.
d.
1)
CARRYUNDER 2)
Reduction in Recirc Pump Net Positive Suction Head, i
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REACTOR OPERATOR Page 6 l
l QUESTION: 005 (1.00)
' A Loss of Coolant Accident has occurred. The following conditions exist:
l RPV level is 150" and stable.
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Operators are lining up additional injection systems.
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Drywell pressure is 5 psig and slowly lowering.
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There are no abnormal rad conditions.
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- All plant equipment functioned as designed.
- Operators have taken all appropriate actions.
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The Chemists have been directed to use the Post Accident Sampling System (PASS) to sample the Drywell atmosphere for hydrogen. The OSS has authorized Chemists to override open the PASS Sample Station Exhaust Isolation dampers at Panel 1C24.
Which of the following CORRECTLY describes the affect of containment isolations on the ability of PASS to sample the Drywell?
a.
PASS will be available because there is no isolation signal present which would have isolated it.
b.
PASS will be available because Defeat 16, " Drywell and Torus Atmosphere Monitoring Sample Line Containment Isolation Defeat" would be installed per
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EOP-2, PC/H leg.
c.
PASS will NOT be available until operators can raise RPV level to >170" and reset the complete Group 3 Isolation.
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PASS will NOT be available until operators place the GROUP 3 CHANNEL A and B ALL SIGNALS OVERRIDE keylock handswitches in OVERRIDE (on panels 1C15 and 1C17 respectively) and reset the complete Group 3 Isolation.
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' REACTOR OPERATOR Page 7
' QUESTION: 006 (1.00)'
' The plant had been in operation at full power for two months until a reactor scram occurred 30
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A reactor startup is now in progress.
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RPV level control is on the Startup Feed Reg Valve in automatic with a 50 gpm
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drain established through RWCU.-
Reactor water temperature is 175'F.
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When the reactor first went critical in the SRM range, operators calculated a stable period of 120 seconds. As power first comes into the IRM range (ranges 1-4),' operators again calculate reactor period. Assuming no instrument inaccuracies, will the new reactor period be longer or shorter? Also identify the correct reason for this answer.
a.'
Longer - At the higher power, fission product poison concentration will start to rise more rapidly adding negative reactivity.
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. Longer - At the higher power, nuclear heat will start to raise reactor water temperature adding negative reactivity.'
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Shorter '- At the higher power, fission product poison concentration will start to
. lower more rapidly adding positive reactivity.
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Shorter - At the higher power, more feedwater flow will start to lower Reactor water temperature adding negative reactivity.
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REACTOR OPERATOR Page 8 l
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QUESTION: 007 (1.00)
. An electrical ATWS has occurred with reactor power remaining at approximately 7%. The 1C05 operator is directed to manually drive control rods.
1)
Should the Rod Worth Minimizer be PLACED IN BYPAS6 or should it REM,JN l
lN OPERATE 7 AND 2)
What is the CORRECT reason for the answer to part 1 of this question?
a.
1)
PLACED IN BYPASS 2)
To disable possible Select Blocks.
b.
1)
PLACED IN BYPASS
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To disable possible Insert Blocks.
c.
1)
REMAIN IN OPERATE 2)
To transmit rod positions to the Plant Process Computer.-
d.
1)
REMAIN IN OPERATE 2)
To enforce insertion of the highest worth rods first.
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REACTOR OPERATOR Page 9 I
l-QUESTION: 008 (1.00)
' Following a severe accident the crew carries out the actions of EOP 1'and EOP 2 to restore
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.mactor level and control containment parameters. Plant conditions are as follows:
Reactorlevel:
95", stable.
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Reactor pressure:
400 psig, dropping
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Drywell temperature:
215'F, rising
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Drywell pressure:
12 psig, rising
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Torus pressure:
11 psig, rising
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Which one of the following is a CORRECT reason for spraying the drywell at this point?
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To cool the RPV reference legs to maintain level indication as the RPV depressurizes.
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b,.
To divert RHR flow, controlling flow into the RPV to prevent uncontrolled floodup, c.
To return non-condensable gases to the drywell to protect containment integrity.
d.
To protect the drywell-Torus vacuum breakers from excessive cycling.
[ QUESTION: 009_. (1.00)
Which of the following is the value of the Reactor Coolant System Pressure SAFETY LIMIT?
Reactor steam dome pressure shall be...
a.
s 1240 psig.
b.-
. s 1250 psig.
c.
s 1325 psig.
d. '
s 1335 psig.
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REACTOR OPERATOR Page 10 QUESTION: 010 (1.00).
, An accident has occurred which has caused entry into the RPV Flood EOP. All control rods are fully inserted. Operators are injecting into the RPV with RHR and one condensate pump. The third SRV has just opened. Besides SRV position, which parameter (s) must the Panel 1C03 operator monitor to maintain RPV Flood conditions?.
a.
RPV pressure only, b.
- RPV pressure and Torus pressure, c.
RPV pressure and Drywell pressure.
d.
RPV pressure and injection flow rate.
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QUESTION: 011 (1.00)
~Ar. ATWS transient is in progress. Because reactor power. remained above 5*A, reactor water level was lowered to'+87 inches. The OSS now directs that RPV injection be restored to mainta:n between +70 inches and +85 inches. An EOP Training Technique addresses the use of IRMs in this situation.
According to this Train:ng Technique, can the IRMs be inserted at this poin*? (YES or NO) If YES, identify the answer that CORRECTLY describes how they are utilized. If NO, identify the answer that CORRECTLY explains why not.
YES, select one recorder on each' side for IRM and leave the IRM on Range 10.
a.
b.
YES, select one recorder on each side for IRM and keep that recorder on scale
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c by ranging down the IRM.
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. NO, IRMs may provide exaggerated responses during injection.
d.
NO, IRMs may be damaged by high flux levels.
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REACTOR OPERATOR Page 11 QUESTION: 012 (1.00)
I Operators are attempting to stabilize the plant after a combined ATWS and Loss of Coolant Accidents. Current plant conditions are:
All rods have been fully inserted.
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The B Loop of RHR is being used for Drywell Spray and Torus Spray.
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The A Loop of RHR is being used for Torus Cooling only.
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Drywell and Torus hydrogen concentrations are increasing.
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The OSS directs the BOP operator to begin nitrogen injection into the containment using the Containment Atmosphere Dilution (CAD) system. Which CAD injection point, if any, would be available in this plant condition?
a.
Both "A" and "B" Drywell Spray and Torus Spray headers.
b.
"A" Drywell Spray and Torus Spray headers only.
c.
"A" Drywell Spray header only, d.
No injection point would be available.
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QUESTION: 013 (1.00)
An accident has occurred. Plant conditions are as follows:
Drywell pressure:
11 psig, dropping 1 psig/ minute
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Torus pressure:
9 psig, dropping 1 psig/ minute
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Core Spray injecting to maintain level
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RHR spraying the Drywell and Torus
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Assuming no further operator action, which of the following correctly describes the next expected AUTOMATIC action, and what is the setpoint for that action?
a.
Torus spray valves ONLY will close when Torus pressure drops to 2 pig.
b.
Drywell spray valves ONLY will close when Drywell pressure drops to 2 psig.
c.
Drywell AND Torus spray valves will close when Torus pressure drops to 2 psig.
d.
Drywell AND Torus spray valves will close when Drywell pressure drops to 2 psi F
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Page 12 o-QUESTION: 014 (1.00)
The plant 'was in power operation with both Recire Pumps running at 80% speed and RPV level stable at 190 inches on the GEMAC level indicators. At this point the A Recirc Pump trips.
- Operators stabilize the plant and restore RPV to 190 inches on the GEMAC level indicators.
Select the answer that CORRECTLY describes how this transient will affect the FUEL ZONE RPV levelindication on Panel 1C03.
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Both Fuel Zone indicators will read the SAME BUT LOWER.
b.
. Both Fuel Zone indicators will read the SAME BUT HIGHER.
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' The A Fuel Zone it.dicator will read LOWER than the B Fuel Zone indicator.
d.
The A Fuel Zone indicator will read HIGHER than the B Fuel Zone indicator.
l-L QUESTION: 015' (1.00)
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i Reactor pressure is 800 psig. A normal reactor shutdown and cooldown is in progress per p
l pol-4, " Shutdown", Section 4.0, " Plant Cooldown with the Condenser Available". The Turbine j-Bypass Valves (BPVs) are being used to lower RPV pressure. Assume that a balance of plant problem were to occur which caused Main Condenser Backpressure to start INCREASING. At which of the following condenser backpressure values will the BPVs cease to be effective in reducing RPV pressure? -
a.
7.5 inches Hg. Abs.
-
b.
19 inches Hg. Abs.
.
-
c.
22 inches Hg. Abs.
j d.'
- 29 inches Hg. Abs.
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QUESTION: 016 (1.00)
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The plant was operating at full power with the Startup Transformer out of service when a severe disturbance occurred on the Mid An. erica Power Pool grid. This causes a loss of offsite power
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and a reactor scram. Both Standby Diesel Generators also fait after a short while. The System Dispatcher now calls the Control Room and reports that grid has been restored and stabilized at l 3700 VAC. Is grid voltage ABOVE or BELOW the Degraded Voltage Trip setpoint for the
'
Essential busses?
_
If ABOVE, identify how this protective feature is reset.
If BELOW, identify the CORRECT statement about resetting the Degraded Voltage trip.
j a.'
ABOVE - The Degraded Voltage logic will automatically reset at this voltage.
b.
ABOVE - The Degraded Voltage logic must be manually reset at panel 1C08.
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c.
BELOW '- The Degraded Voltage logic cannot be reset at this voltage.
d.
BELOW The Degraded Voltage' logic can be tiypassed and reset per AOP
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'301.1, " Station Blackout".
QUESTION: 017 (1.00)
A fire has severely damaged 250 VDC Bus 1D40, which will not be available for at least a week.
Toxic fumes from the fire preclude entry to the power block by operations personnel. Under these conditions, which of the following groups of systems is available for a safe plant shutdown? -
a.
Core Spray, RHR LPCI Mode l
l b.
Core Spray, HPCI c.
HPCI, RHR Shutdown Cooling Mode l.
d.
' RCIC, RHR Shutdown Cooling Mode
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' QUESTION: 018 (1.00)
A plant transient has resulted in the following plant conditions:
Reactor level 205 inches, rising at 1 inch / minute
-
Torus level 10.2 ft, rising at 0.05 ft/ minute
-
Drywell pressure 1.0 psig, rising at 0.1 psig/ minute
-
Reactor pressure 300 psig, lowering at 10 psig/ minute
-
HPCI does not currently have an initiation signal.
-
RCIC is running in the CST to CST mode.
-
Assume that:
l The above rates of change remain constant.
-
l All automatic actions occur at design setpoints,
-
l l,
How much longer will RCIC continue to operate in the CST to CST mode?
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a.
6 minutes b.
8 minutes c.
10 minutes i
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d.
20 minutes i
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Page 15
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QUESTION: 01'9 (1.00)
A plant transient has occurred resulting in the following piant conditions.
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All control rods fully inserted during the initial transient.
-
RPV level 190 inches, rising slowly. Reached a low of 175 inches
-
during initial transient.
RPV pressure 950 psig, lowering slowly. Reached a peak of 1030 psig
-
during initial transient.
Drywell pressure 2.8 psig, rising slowly since the initial transient.
-
Which of the following CORRECTLY identifies the Emergency Operating ProcedureW. if any, that must be entered?
a.
No EOPS must be entered.
- b.
Only EOP-1, "RPV Control", must be entered.
c.
Only EOP-2," Primary Containment Control", must be entered.
d.
Both EOP-1, "RPV Control" and EOP-2, " Primary Containment Control", must be entered.
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REACTOR OPERATOR Page 16 QUESTION: 020 (1,00)
~ A HPCI operability Survoillance Test Procedure (STP) is in progress during power operations.
. Assume that the A'brage Torus Water Temperature rises above 95'F during testing. Which of the following state.1ents is CORRECT concerning entry into EOP-2, " Primary Containment Control"?
?.(
' a.-
EOP-2 is entered and CANNOT be exited until Average Torus t%ter.
^
Temperature is <95'F.
b.
EOP-2 is entered but can subsequently be exited when it is determined that an emergency does not exist.
c.
EOP-2 is NOT entered when operator actions are govemed by the STP.
,
d.
EOP-2 is NOT entered for preplanned evolutions.
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REACTOR OPERATOR Page 17 QUESTION: 021 (1.00)
The plant was operating at 100% power when a NON-FIRE event occurs that requires evacuation of the Control Room per AOP-915, Shutdown Outside the Control Room". As airected, the 1C05 operator manually scrams the reactor and places The Mode Switch in the SHUTDOWN position, then verifies that all rods have inserted by using The Mode Switch in the REFUEL position. He is then able to complete the "as time permits" actions of AOP-915 before he evacuates the Control Room. Which of the following will be the final position of The Mode
- Switch when the Control Room is evacuated?
The Mode Switch will be in a.
REFUEL.
b.
SHUTDOWN.
c.
START & HOT STBY.
d.
RUN.
OUESTION: 022 (1.00)
The plant is operating at full power with all equipment operable. Fuel leakage is causing increased coolant activity and offsite release through the Offgas System. At which one of the following points will this release path be automatically isolated?
This release path will automatically isolate when...
a.
a HI Rad condition is sensed at the Offgas Carbon Bed Vault monitor, b.
a Hi-HI Rad condition is sensed at the Offgas Pretreatment sample point.
c.
a Hi-HI Rad condition is sensed at the Offgas Vent Pira sample point.
d.
a HI-Hl-HI Rad condition is sensed at the Offgas T';.,streatment sample point.
...
.
.
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REACTOR OPERATOR Page 18 QUESTION: 023 (1.00)
The plant is operating 100% power in the middle of the summer. All plant systems are in normal lineups except for the D Well pump, which is out of service. Assume that the B Well pump trips and that operators take the necessary actions per AOP-408 to continue operation with reduced well water flow. Of the following systems, which one WILL NOT be immediately affected or require operator action to stabilize?
a.
The Instrument and Service Air System b.
The Offgas System c.
The Control Building HVAC System d.
The Reactor Building HVAC System QUESTION: 024 (1.00)
A complete loss of the service and instrumeat air systems occurs while at full power. Operators are trying to restart a compressor as air header pressure lowers, but they may be required to scram the reactor. Which one of the following is a potential effect on the Control Rod Drive (CRD) Hydraulic System?
a.
The scram discharge volume may fail to isolate when the scram occurs.
l b.
The Backup scram valves could fail to vent the Scram Air Header when the l
scram occurs.
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- The running CRD pump could be operating in a runout condition before the scram occurs.
d.
Cooling flow could be lost to the control rod drive mechanisms before the scram t
occurs.
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QUESTION: 025 (1.00)
j The plant was operating normally at 90% power. l&C technicians performing a surveillance test on the Main Condenser Backpressure Primary Containment isolation Instrumentation.
'
Inadvertently cause a Group 1 isolation. Which one of the following signals will initiate the resulting reactor scram?
a.
APRM High Flux (Flow Biased)
b.
RPV High Pressure c.
MSIVs Not Full Open
' d.
. Turbine Trip l
QUESTION: 026 (1.00)
A reactor startup is in progress with RPV premure at 600 psig. Operators are precharging the accumulator with nitrogen on control rod.22-23, which is fully withdrawn. The Charging Water to
-
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this' HCU is valved out. ' At this point the running CRD pump trips and the alternate CRD pump cannot be started.
<
1).
What is the approximate scram time for control rod 22-23 in this condition?
'
2)
is there a problem with continued operation in this condition?
a.
.1).-
- 2.5 seconds 2)
There is no problem because scram time of this rod is still less than 7 seconds.
b.-
1)
2.5 seconds 2)-
The scram function of this rod could be degraded during a depressurization event.
! c.
1)
4.5 seconds 2)-'
There is no problem because scram time is still less than 7 seconds.
' d.'
1)
4.5 seconds 2)-
The scram function of this rod could be degraded during a -
depressurization event.
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REACTOR OPERATOR Page 20 QUESTION: 027 (1.00)
During an accident, with RPV pressure at 800 psig, the Average Torus water temperature reaches the Heat Capacity Limit (HCL) and is still increasing. At this point the EOPs direct
.
operators to Emergency Depressurize. An ED at this point will prevent exceeding CERTAIN CONTAINMENT LIMITS. Which of the following is the MOST LIMITING containment limit for the DAEC in this situation?
.
a.
The Torus Pressure Suppression Pressure Limit.
b.
The Primary Containment Pressure Limit.
c.
The Drywell design temperature limit.
i d.-
The Torus design temperature limit.
i QUESTION: 028 (1.00)-
,
Sprinkler system #12 covers the HVAC area above the Control Room. If a fire were to occur in this area, would this sprinkler automatically actuate (i.e. spray water on the fire)? (YES or NO) If NO, identify the operator action necessary to actuate this sprinkler.
'
a.
YES, - Sprinkler 12 is charged and ready to actuate if a fire is sensed.
' b.
NO, - A manual isolation valve must also be opened, located in the Turbine Bldg., North 757ft. level, East of the Feed Reg Valves.
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- c.
NO, - A manual isolation valve must also be opened, located in the Control Bldg.
Battery Room Corridor, on the south wall.
s d.
NO, - A manualisolation valve must also be opened, located in the Reactor Bldg.', North-East 7866 level, by the MG Room door.
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REACTOR OPERATOR Page 21 QUESTION: 029 (1.00)
EOP-2, " Primary Containment Control", Step T/L-10, directs the operator to maintain Torus water level below 1.3.5 ft. Which of the following CORRECTLY identifies the basis for this limit?
Above this level -
a.
the Torus to Drywell vacuum breakers become covered.
- b.'
the SRV tanpipe limit is exceeded.
I'nsufficient air space remains in the Torus to receive a LOCA blowdown without c.
exceeding the containment design pressure.
d.
primary containment failure could occur during an Emergency Depressurization of the RPV.
- QUESTION: 030 (1.00) -
The plant was operating at full power when a transient occirred which caused EOP-2 entry on LOW TORUS LEVEL. Plant conditions are as follows:
RPV level:
190", stable
-
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RPV pressure:
- 1000 psig, stable
-
Drywell pressure:
0.5 psig
-
Torus pressure:
O psig
-
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Torus level:
7 feet
-
Torus temperature:
105'F
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,
What adverse consequences could result if a large line break LOCA occurred during these cor~'itions?
a.
. inadequate volume of water is available for low pressure ECCS to leflood the vesselin the event of a LOCA.
~ b.
RCIC is not available for injection into the RPV due to inadequate heat sink for the turbine exhaust.
LOCA Downcomer flow will bypass the normal flowpath, directly pressurizing the
- c.
torus air space with steam.
-
d.
Relief valves cannot be used for pressure control or emergency depressurization due to inadequate heat sink.
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REACTOR OPERATOR Page 22 QUESTION: 031 (1.00)
A Loss of Coolant accident has occurred which requires operators to perform SEP 301.1, " Torus Vent irrespective of Rad Release". One train of Standby Gas Treatment (SBGT) is in operation.
Drywell pressure is 50 psig and still rising slowly with two Torus vent valves open; CV-4301, OUTBD TORUS VENT ISOL, and CV-4309, INBD TORUS VENT BYPASS ISOL.
SEP 301.1 now directs that the third Torus vent valve be opened; CV-4300, INBD TORUS VENT ISOL. Which of the following will be the primary personnel exposure concem when
,
CV-4300 is opened?
a.
Radiation levels near the NE Corner Room Torus vent ducting.
b.
Radiation levels near SBGT charcoal adsorbers.
c.
Airbome activity levels on the Reactor Building Second Floor (El. 786ft.).
d.
Airborne activity levels in the NE Comer Room.
QUESTION: 032 (1.00)
The plant was operating with a suspected fuel leak when an accident occurred. The operating crew has stabilized RPV level and pressure. At this point, the crew receives a report that a radioactive release in progress above the Alert level. The release rate is rising slowly.
The crew will be required to emergency depressurize the reactor if the source of the leak cannot be isolated and is from which one of the following systems?
a.
spent fuel pool b.
main steam piping c.
radwaste sump system d.
liquid radwaste system
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l-QUESTION: 033 (1.00)
l The on shift crew is cooling down the reactor in preparation for a refueling outage. Immediately after initiating shutdown cooling, the RHR and Recirc pumps are lost due to a short in LPCI loop select logic. AOP-149, " Loss of Shutdown Cooling", directs operators to raise RPV water level in this situation. Which of the following is the CORRECT reason for this action, per AOP-149?
The higher RPV water level...
a.
increases NPSH on the RWCU pumps, allowing them to pump more water and therefore remove more heat.
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b.
forces cold water from the bottom of the vessel into the core area, temporarily dropping fuel temperatures.
c.
increases water flow through the core by allowing water to overflow the moisture separator.
d.
' maximizes the amount of water available'to absorb decay heat.-
QUESTION: 034' (1.00)
.The plant was in a normal ventilation lineup when a refueling accident results in a complete Group 3 bolation. Which of the following CORRECTLY describes how Refuel Floor ventilation'
{
, is affected?
I
.q a.
The Refueling Pool Exhaust Fan,1V-EF-10, automatically starts.
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b.-
The' inlet ' dampers to the Reactor Building Exhaust Fan, EF-11 A &B, shift to take
{
suction on the Refuel Floor.
'
c.
- The Refuel Pool to Vent Shaft Inlet Valve, AV-7604V, automatically opens.
]
]
d.
The Refuel Floor Damper Control automatically shifts the associated dampers to High Bay Exhaust.
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REACTOR OPERATOR Page 24
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~ QUESTION: 035 (1.00)
The MAX SAFE values for Reactor Building Temperatures used in EOP-3, " Secondary
.
Containment Control" are based on which of the following criteria?
Max Safe temperatures are based on an engineering evaluation of the highest value a. -
expected to be seen during normal operations.
b.
expected to be seen during an accident.
c.
at which NO equipment will fail.
d.
at which equipment needed for safe shutdown of the plant will not fail.
QUESTION: 036 (1.00)
The plant has experienced a seismic event while operating at power. This resulted in a large HPCI steam line break in the Reactor Building. HPCI failed to automatically isolate as required.
An operator reports reactor building ventilation isolated on high radiation, but SBGT will not start.
'
Reactor building pressure is now positive and continues to rise. What is a potential consequence if this situation continues?
a.
Damage to reactor building ventilation isolation dampers.
-
b.
An uncontrolled, unmonitored release through SBGT due to forced air flow, c.
Damage to the reactor building Kaman radiation monitors.
. d.
An uncontrolled, unmonitored release from the reactor building.
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REA' TOR OPERATOR Page 25 C
, - QUESTION: 037- (1.00)
'
What are the power supplies to the Alternate Rod Insertion (ARI) solenoids?
-
a.
RPS, Channels A and B b.'
Instrument AC, Divisions 1 and 2
,
c.
24 VDC, Divisions 1 and 2 d.
125 VDC, Divisions 1 and 2 QUESTlON: 038 (1.00)
Which one of the follow'ng correctly describes the condition (s) which will result in alarm 1CO' A D-6, ROD DRIFT, actuating for:
1)
The Selected Rod?
l and 2)
A Non-Selected Rod?
a.
1)
No even-numbered reed switch detected.
2)
Not at an even-numbered position OR at an odd-numbered position.
-)
Odd-numbered notch ' position with no motion demanded.
b.
2)
' Not at an even-numbered position OR at an odd-numbered position, c.
1)
No even-numbered reed switch detected.
2).
No rod is driving AND an odd-numbered rsed switch detected.
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d.
1)
Odd-numbered notch position with no motion d3manded.
2).
No rod is driving AND an odd-numbered reed r, witch detected.
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REACTOR OPERATOR Page 26 QUESTION: 039 (1.00)
The plant was operating at power with both Recirc Pumps at 60% speed when a feedwater problems results in both pumps running back to 45% Pump Speed (P). Operators stabilize the plant at a lower power and take no further action with the Recirc MG Set Speed Controls.
1)
Which of the following CORRECTLY describes the response of the Recirc MG
' Speed Control Speed Demand (S) signals?
'
and 2)
What is the consequence of depressing the 45% RUNBACK SPEED LIMITER RESET pushbutton in this situation?
a.
1)
Both controllers will automatically go to 45% Speed Demand (S).
2)
The Runback will reset and Recire Pump speet ;<ill remain stable, l
b.
1)
Both controllers will automatically go to 45% Speed Demand (S).
2)
The Runback will NOT reset due to an interlock which requires the Scoop
l Tube to be locke(.irst.
j c.
1)
Both controllers will remain at 60% Speed Demand (S).
2)
The Runback will reset and Recirc Pump speed will ramp up to 60%.
'
d.
1)
Both controllers will remain at 60% Speed Demand (S).
2)
The Runback will NOT reset due to an interlock which requires the Speed Demand (S) to be adjusted to less than 45% first.
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' REACTOR OPERATOR-Page 27 QUESTION: 040 _(1.00)
~ The plant has just' entered Mode 4. All safety related equipment is operable. The RHR System is aligned as follows:
The B Loop of RHR is in the Shutdown Cooling Mode.
-
The A RHR pump is running in the Torus Cooling Mode.
-
At this point a Loss of Coolant accident results in a LPCl initiation on low RPV level. The amber light is ON above the B LOOP SELECTED RHR mimic label. ~ Assuming NO OPERATOR
_
ACTION, which RHR pumps will automatically begin injecting into the RPV7 a.
None b.
A and C RHR pumps
- c.
B and D RHR pumps
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' d.
A, B, C, and D RHR Pumps l
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- QUESTION: 041 (1.00)
.
..
Which Torus level corresponds to the HPCI Turbine exhaust elevation?
a.
. 7.1 ft.
b.
6.0 ft.-
. c.
5.8 ft.
..
d.
4.5 ft.
.
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QUESTION: 042 (1.00)
.
The plant was operating normally with the "A" Core Spray pump running for periodic test when a
,
L small break LOCA occurred inside the drywell, raising drywell pressure above the Core Spray L
initiatica setpoint. Which one of the following CORRECTLY describes the response of the i
follomng "A" Core Spray valves to this event?
i Test Bypass valve, MO-2112 (which is' OPEN at the start of the accident.)
-
Min Flow Bypass valve, MO-2104 (which is CLOSED at the start of the accident.)
-
Inboard Inject valve MO-2117
-
a.
The TEST BYPASS will CLOSE.
The MIN FLOW BYPASS will OPEN.
When RPV pressure drops to <450 psig, the INBOARD INJECT will AUTOMATICALLY OPEN. When injection to the RPV begins, the MIN FLOW BYPASS will CLOSE.
J b.
-The TEST BYPASS will CLOSE.
The MIN FLOW BYPASS will OPEN.
x l
When RPV pressure drops to <450 psig, the INBOARD INJECT must be MANUALLY OPENED. When injection to the RPV begins, the MIN FLOW BYPASS will CLOSE.
,
t c.
The TEST BYPASS REMAINS OPEN.
The MIN FLOW BYPASS REMAINS CLOSED.
When RPV pressure drops to <450 psig, the l EST BYPASS will CLOSE and the
' INBOARD INJECT will AUTOMATICALLY 'OPEN.
l d.
-The TEST BYPASS will CLOSE.
The MIN FLOW BYPASS REMAINS CLOSED.
The INBOARD INJECT valve will AUTOMATICALLY OPEN on the initiation i
signal and injection to the RPV begins when RPV pressure drops to <450 psig.
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REACTOR OPERATOR Page 29 l
l QUESTION: 043 (1.00)-
An AW/S transient occurs and boron must be injected with the Standby Liquid Control System (SBLC). Which ONE of the following describes the effect of a SUCCESSFUL INITIATION of SBLC on these indications:
1)
Squib Valve Ready (Continuity) lights 2)
Alarm 1C05A F-3, SBLC SQUlB VALVE CONTINUITY LOSS 3)
Pump discharge pressure a.
1)
liluminate.
2)
Actuates.
3)
<1350 psig.
b.
1)
Extinguish.
- -
2)
Actuates.
3)
<1350 psig.
c.
1)
lliuminate.
2)
Does NOT actuate.
3)
>1350 psig.
d.
1)
Extinguish.
2)_
Does NOT actuate.
3)
>1350 psig.
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REACTOR OPERATOR Page 30 QUESTION:044 (1.00)
A reactor scram cannot be reset for 10 seconds after a scram. Which of the following is the reason for this delay?
To allow time...
a.
for all of th'e control rods to fully insert.
b.
to initiate the Alternate Rod Insertion system, c.
for the reactor water level to stabilize above the scram setpo'.:1t.
d.
for the Scram Discharge Volume vent and drain valves to fully close before reopening.
QUESTION: 045 (1.00)
,
A normal plant startuf is in progress with The Mode Switch in the START & HOT STBY position.
-
IRM Channel A is failed downscale.
l
.
IRM Channel A is bypassed on Panel 1C05.
-
l IRM Channel A Mode switch is in STANDBY.
.
All of the'IRM range switches, including IRM Ohannel A, are on range 2.
Which of the following CORRECTLY describes the automatic actions that would occur if IRM Channel A were to be taken out of bypass?
a.
% scram only b.
Control rod block only c.
IRM Downscale alarm only d.
. % scram and control rod block
i REACTOR OPERATOR Page 31 QUESTION: 046 (1.00)
A reactor startup is in progress. The Mode Switch is in the START & HOT STCY position. No SRMs are bypassed. The SRM detectors are PARTIALLY WITHDRAWN. Which one of the following sets of conditions will then result in a rod withdrawal block?
a.
IRMs on range 1. All SRMs reading approximately 120 cps, b.
IRMs on range 2. SRM "A" reads approximately 90 cps, all othe. SRMs reading approximately 150 cps.
c.
IRMs on range 3. All SRMs reading approximately 90 cps, d.
IRMs on range 4. SRM "A" reads approximately 90 cps, all other SRMs reading
,
approximately 120 cps, i
QUESTION: 047 (1.00)
'
Following startup, power is at 55% and rising as the crew brings the plant to full load. Just as the operator is about to withdraw the selected control rod, APRM "A" fails, indicating a constant i
10% power. Which one of the following describes the effect on RBM "A"?
- a.
RBM "A" will NOT enforce rod blocks until APRM "A"is bypassed, at which time RBM "A" will use APRM "E" as it's reference.
,
b.
RBM "A" will enforce rod blocks until APRM "A"is bypassed, at which time RBM
"A" will use APRM "F" as it's reference.
c.
RBM "A" will NOT enforce rod blocks until APRM "A" Mode Switch is moved out of OPERATE, at which time RBM "A" will use APRM "E" as it's reference.
d.
RBM "A" will enforce rod blocks uritil APRM "A" Mode Switch is moved out of OPERATE, at which time RBM "A" will use APRM."F" as it's referenc REACTOR OPERATOR Page 32 QUESTION: 048 (1.00)
The Reference Leg Backfill system has been out of service for an extended period of time when a plant transient results in a reactor scram and rapid depressurization of the RPV. Assume that non-condensable gasses will be released in the reference leg of the B GEMAC level instrumentation. How will B GEMAC level INDICATION be affected?
a.
Indicated level will read HIGHER than actual due to a decrease in the sensed differential pressure between the reference and variable legs, b.
Indicated level will read HIGHER than actual due to an increase in the sensed differential pressure between the reference and variable legs.
c.
Indicated level will read LOWER than actual due to a decrease in the sensed differential pressure between the reference and variable legs.
d.
Indicated level will read LOWER than actual due to an increase in the sensed differential pressure between the reference and variable legs.
QUESTION: 049 (1.00)
What is the power supply to the RCIC Inboard Steam Line Isolation valve, MO-24007
a.
480 VAC, Bus 1842 b.
480 VAC, Bus 1814 c.
250 VDC, Bus 1D41 d.
125 VDC, Bus 1D14
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- QUESTIONi 050 (1.00)
,
The plant was at full power when a leak developed inside the drywell. All isolations and i
automatic actions occurreo so expected, but the operators fail to re-open CV-4371 A, DW AND l
TORUS DISCHARGE ISOLATION, as directed by procedure. As plant conditions continue to
)
degrade, how could future mitigating actions be impacted by this mistake?
i The SRVs...
a.
may not open in response to a manual signal, but they should still respond to an-ADS initiation.
!
b.
should still open in response to an RPV high pressure condition or a manual l-signal, but may not an open for an ADS initiation.
c.
may fail to open as needed for manual.RPV pressure control or for initiation of ADS.
d.
should still open in response to manual signal, but may not open for initiation of j
,
ADS and or for an RPV high pressure condition.
QUESTION: 051 (1.00)
. Operators are preparing for a plant startup after a forced outage.' The Drywell remained inerted because there was no need to enter Primary containment. Given the following readings on the
'
Liquid Nitrogen Storage Tank level and the Containment Atmosphere Dilution (CAD) nitrogen
' inventory, which action, if any, will be necessary for startup?
"
l Liquid Nitrogen Storage Tank level 180 inches
-
CAD Bottle Pressure 1500 psig -
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l
-
CAD Bottle Temperature 80*F a.-
Inventories are satisfactory; no further action is necessary for startup; b. -
Order more liquid Nitrogen.
l'
c.
Vent the Liquid Nitrogen Storage Tank.
d.
Charge the CAD Nitrogen supply tanks.
,
,
n REACTOR OPERATOR Page 34
{
I QUESTION: 052 (1.00)
The following plant conditions exist:
A plant startup is in progress.
-
Condenser high backpressure bypass switches are in the BYPASS position.
-
Condenser backpressure is 20 inches Hg Abs.
-
MSIVs are open.
-
-
Reactor pressure is 875 psig.
The Mode Switch is in the START & HOT STBY position.
-
If the following actions were to occur, which one would cause a Group 1 Isolation?
.....
a.
Lowering EHC Pressure Set to 840 psig.
b.
Jacking open a Turbine Bypass Valve, c.
Placing the Mode Switch in RUN.
d.
Opening the Main Condenser Vacuum Breakers.
QUESTION: 053 (1.00)
A Safety Relief Valve (SRV) tailpipe vacuum breaker has failed in the OPEN position during SRV operation. Which of the following will result?
a.
- Steam will discharge from the tailpipe into the Drywell each time the SRV is opened.
b.
Steam will discharge from the tailpipe into the Torus air space each time the SRV is opened.
c..
Water from the Torus will be drawn up into the SRV tailpipe when the SRV closes.
d.
Steam will bypass the T-quencher and discharge directly from the tailpipe into the water.
i:
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REACTOR OPERATOR Page 35
- QUESTION: 054 (1.00)
'
The plant was operating at 90% power when the Stator Cooling Water TCV failed, bypassing the
,
heat exchanger. Using the attached EHC Electronics schematic, identify the CORRECT point at
'
which this failurts initiates action by the Turbine Control System.
This failure initiates action at...
a.
Point A.
i b.
Point B.
c.
Point C.
d.
Point D.
QUESTION: 055 (1.00)
The plant is operating a 55% power during power ascension. The second Condensate and Feed pumps have been started. At this point the A Condensate pump trips. Which of the following is the expected response of the Feedwater System?
a.
Only the A Feed pump will trip. This is due to an interlock with A Condensate 7 ump.
b.
Only the A Feed pump will trip. This is due to a shorter time delay on the A Feed pump low suction pressure trip.
c.
Both Feed pumps will trip. They will trip on low suction pressure due to the inability of one Condensate pump to supply both Feed pumps.
d.
Both Feed pumps will continbe to operate. One Condensate pump can adequately supply both Feed pumps at this power level.
_
h REACTOR OPERATOR Page 36 i
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l.
l-QUESTION: 056 (1.00)
l i
!
- The plant is in normal operation at 60% power after a startup. The 1C05 operator reports the j
i j
. following:
The B Feed pump flow is higher than A Feed pump flow
--
The B Feed pump motor is also drawing 50 more amps than A Feed pump.
-:
l
Which of the following is the reason for these indications?
!
. a.
The voltages of the 4KV Non-Essential busses are not properly matched.
i b.
. The bias settings of the A and B Feed Reg Valve Controllers are not properly matched.
c.
The Setpoint (S) values of the A and B Feed Reg Valve Controllers are not properly matched.
d.
There was too much deviatic,n between Controller Output (P) values of the A and B Feed Reg Valve Controllars when the Master Feed Reg Valve Controller was
placed in auto.
l l
QUESTION: 057 (1.00)
Which one of.the following CORRECTLY describes the relationship between HPCI and SBGT7 a,
' The HPCI barometric condenser vacuum pump exhausts directly to the stack,
~ where any release is monitored. ~ At least one OG STACK EXH FAN, 1V-EF-18A(B], must be on when HPCI is running.
I-b.
The HPCI barometric condenser vacuum pump exhausts directly to the stack,
. where any release is monitored. The OG STACK EXH FAN,1V-EF-18A[B], can be off when HPCI is running.
c.
The HPCI barometric condenser vacuum pump exhausts through the SBGT '
trains, where gases are treated before leaving the plant via the stack. At least one SBGT EXHAUST FAN,1V-EF-15A[B], must be on when HPCI is running.
d.
The HPCI barometric condenser vacuum pump exhausts through the SBGT trains, where gases are treated before leaving the plant via the stack. The SBGT EXHAUST FAN,1V-EF-15A[B], can be off when HPCI is running.
!.
1:
REACTOR OPERATOR Page 37 QUESTION: 058 (1.00)
"A" SBDG was operating in parallel with the Startup transformer for surveillance testing, carrying a load of 2500 KW. A lightning strike occurred that tripped OPEN the Etartup and Standby transformer incoming breakers (J, K, and M). Bus 1 A3 does not have a Lockout. Which of the following CORRECTLY describes the response of the "A" SBDG and its output breaker?
a.
The Output Breaker will trip open due to a signal from the Degraded Voltage logic. Then, if the SBDG exceeds 1044.19 RPM, the SBDG will trip.
b.
The Output Breaker will trip open due to a 1 A3 Bus Undervoltage signal. Then, if the SBDG exceeds 104419 RPM, the SBDG will trip.
c.
If the SBDG exceeds 104419 RPM, the SBDG will trip. Then the Output Breaker will open due to a signal from the Shutdown Relay.
d.
If the SBDG exceeds 104419 RPM, the SBDG will trip. Then the Output Breaker will open due to a 1A3 Bus Underfrequency signal.
QUESTION: 059 (1.00)
A large break LOCA has occurred, and Core Spray has initiated and injected into the reactor vessel. Which one of the following describes the use of the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03 to shutdown the system when no longer needed for injection?
.
a.
After all initiation signals have cleared, the initiation signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03.
Then the valves may be repositioned and the pump secured.
b.
After all initiation signals have cleared, the initiation signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03.
Then the pump will stop and the valves automatically reposition.
c.
At any time restoring the Core Spray system is desired, the initiation signalis reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset
,
pushbutton on panel 1C03. Then the valves may be repositioned and the pump secured.
d.
At any time restoring the Core Spray system is desired, the initiation signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03. Then the pump will stop and the valves automatically reposition.
l-
REACTOR OPERATOR Page 38 QUESTION: 060 (1.00)
The plant was operating at full power with HPCI tagged out for corrective maintenance A transient occurred which resulted in a totalloss of feedwater and an unisolable RWCU leak OUTSIDE the Drywell. Assuming no operator action, which one of the following describes the response of the ADS system to depressurize the reactor and allow injection?
a.
As soon as any low pressure ECCS pump reaches normal discharge pressure, AND reactor level reaches low-low-low, the ADS valves will open.
b.
With any low pressure ECCS pump at normal discharge pressure, AND two minutes after reactor level reaches low-low-low level, the ADS valves will open.
c.
As soon as any low pressure ECCS pump breaker is CLOSED, AND reactor level reaches low-low-low, the ADS valves will open, d.
With any ECCS pump breaker CLOSED, AND two minutes after reactor level reaches low-low-low level, the ADS valves will open.
OUESTION: 061 (1.00)
The plant experienced a transient some time ago and a 1/2 Group 3 Isolation occurred on the
"A" side logic. All expected system responses and operator actions occurred for this event.
Which one of the below is a CORRECT statement concerning the signal (s) needed for an AUTO start of the "B" SBGT Fan?
The "B" SBGT Fan will AUTO start when..
a.
the flow in the "A" train drops below 3300 SCFM.
b.
Group 3B Isolation signal is received or the flow in the "A" train drops below 3300 SCFM.
c.
a Group 3B lsolation signal is received AND the flow in the "A" train drops below 3300 SCFM.
d.
a Group 3B isolation signal is receive n I
~ REACTOR OPERATOR -
Page 39 i
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' QUESTION: 062 (1.00)
]
- The BOP operator is performing a slow manual start of the 1G31 diesel generator from the
control room, for post maintenance testing, in accordance with the Operating Instruction (01).
He has set the prelube pump timer for one (1) minute and depressed the prelube pump start
!
pushbutton.- Just as the operator is about to start the Diesel, a problem develops on another -
. system and the OSS suspends the SBDG testing. The problem is resolved in 5 minutes and the OSS authorizes the BOP operator to resume his job on the SBDG. The next step is to start the SBDG. May the operator proceed with the next step of the Ol? (YES or NO) If NO, identify the CORRECT reason.
'
.
a._
YES b. '
NO, the operator must back up a few steps and re-perform the prelube steps.
Then the SBDG can be started.
c.
NO, the pre-lube pump operation described will activate an annunciator on local Panel 1C91 which must be reset before the SBDG will start.
l d.
NO, the operator must direct the in-plant operator to trip the SBDG and roll the engine over with air before resuming the slow manual start procedure.
s r 1
REACTOR OPERATOR Page 40
'
i, QUESTION: 063 (1.00)
While the plant was at power, a Group 1 Isolation occurred due to high Turbine Bldg.
temperatures. The plant responded as designed. Applicable plant conditions are as follows:
The steam leak that initiated the event has been locally isolated.
-
All Turbine Bldg. and Steam Tunnel area temperatures have returned to normal.
-
RPV level is being controlled in the green band.
--
- The Condenser High Backpressure Bypass switches are all in BYPASS.
-
The MSIV handswitches remain in the OPEN position.
-
The Mode Switch is in SHUTDOWN.
-
- 1 Turbine Control Valve is stuck 50% open.
-
If the DIV 1 aiid DIV 2 RESET pushbuttons are momentarily depressed in this plant condition, will the Group 1 Isolation reset?
a.
. Yes; a!! parameters are below their Group 1 initiating device setpoints or are bypassed.
b.
No; the MSIV handswitches must be taken to CLOSE before the Group 1 will reset.
j c.
No; the Mode Switch must be taken out of SHUTDOWN before the Group 1 will reset.
d.
No; #1 Turbine Control Valve must be <10% open before the Group 1 will reset.
I
.
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l REACTOR OPERATOR Page 41 i
f QUESTION: 064 (1.00)
,
l See simplified schematic on the next page. Assume that the contacts shown on the logic
arrangement provided come from nuclear boiler instrumentation, j
1)
is this type of arrangement used for a Reactor Protection System (RPS) TRIP
,
LOGIC or an Emergency Core Cooling System (ECCS) INITIATION LOGIC? -
)
i-AND
2)
Does this type of arrangement use AC power or DC power?
a.
1)
RPS TRIP LOGIC l
2)
AC power
!
b.
~1)
RPS TRIP LOGIC '
W 2)
DC power c.
1)
ECCS INITIATION LOGIC l
.2)
AC power i
d.
1)
ECCS INITIATION LOGIC 2)
DC power f
I i
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REACTOR OPERATOR Page 42 l
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!
QUESTION: 065 (1.00)
The plant is at 100% power near the end of cycle with all contro! rods fully withdrawn At this point the SCRAM INLET VALVE fails OPEN for control rod 18-27. Which of the following t
,
' CORRECTLY explains the response of the plant over the next five (5) minutes?
1)
Affect on reactor power.
2)
Affect on rod position (s).
3)
Affect on Scram Discharge Volume (SDV).
a.
-1)
Reactor power will be DOWNSCALE on the APRMs.
2)
~ This is because ALL RODS WILL INSERT when the reactor scrams.
3)
There will be flow into the SDV that exceeds the capacity of the SDV drain and that causes the scram.
,
b.
1)
Reactor power will be LOWER, but the plant will continue to operate at power.
2)
This is because ROD 18-27 WILL INSERT.
3)
There will be flow into the SDV but it will be within the capacity of the SDV
<
drain, c.
1)
Reactor power will be LOWEP., but the plant will continue to operate at power.
-
<
2)
This is because ROD 18-27 WILL INSERT.
3)
There will be NO flow into SDV.
d.
1)
Reactor power will remain at 100% power.
2)
This is because there will be NO ROD MOTION.
3)-
There will be NO flow into the SDV.
l l
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g y
REACTOR OPERATOR Page 43 QUESTION: 066 (1.00)
The Rod Worth Minimizer is designed to prevent reaching what level of fuel enthalpy under what conditions?
a.
280 calories / gram If Reactor Manual Control System (RMCS) failures caused the strongest operable rod to continuously withdraw from the core at the maximum permissible rod speed.
b. -
~ 280 calories / gram if Control Rod Drive Mechanism (CRDM) failures caused the -
strongest operabic rod to free fall from the core at the maximum possible speed.
c.
- 425 calories / gram If Reactor Manual Control System (RMCS) failures caused the
.
strongest operable rod to continuously withdraw from the core at the maximum permissible rod speed.
d.
425 calories / gram If Control Rod Drive Mechanism (CRDM) failures caused the strongest operable rod to free fall from the core at the maximum possible speed.
QUESTlON: 067- (1.00)
Which of the following signals is used to develop the Total Core Flow indication on panel 1C057 i
l ai Calibrated Jet Pump #1 Flow (from transmitter FT-4518)
b.
Non-Calibrated Jet Pump #10 Flow (from transmitter FT-4503)
i c.
. B Recirc Pump Discharge Flow (from transmitter FT-4632A)
d.
.T; Recirc Pump Differential Pressure (from transmitter PDT-4624)
i
I
' REACTOR OPERATOR '
Page 44 QUESTION: 638 (1.00)-
Is heat removed from the bearing oil of a RWCU Pump IN ANY OTHER WAY than losses to ambient from the bearing housing? (YES or NO) If YES, CORRECTLY identify how heat is removed.
a.
NO.
b.
YES. heat is removed by an extemal, air-cooled radiator, c.
YES, heat is removed by an oil cooler that shares RBCCW with the seal water cooler.
d.
YES, heat is removed by a newly installed cooler using RBCCW in the auxiliary.
Lube Oil system.
QUESTION: 069 (1.00)
The B Loop of the RHR system is operating normally in the Shutdown Cooling mode. Which of
. the following CORRECTLY describes how the B Loop valve positions are adjusted to control flowrate and cooldown rate?
MO-1904 is the B OUTBD INJECT ISOL valve
-
'
,
MO-1939 is the B HEAT EXCH INLET THROTTLE valve
--
-
MO-1940 is tne B HEAT EXCH BYPASS valve.
a..
MO-1904 ie adjusted to control BOTH flowrate and cooldown rate.
b.
MO-1904 is adjusted to control flowrate.
MO-1939 and MO-1940 are adjusted to control cooldown rate, c.
. MO-1904 is adjusted to control cooldown rate.
MO-1939 and MO-1940 are adjusted to control flowrate.
d.
MO-1939 and MO-1940 are adjusted to control BOTH flowrate and cooldown rate.
.
...
..
..
..
...
.. _
.
.
.
_-
_ _ _ _ - - _ _ _ _ _ _ _ _ _
REACTOR OPERATOR Page 45 QUESTION: 070 (1,00)
A non-selected control rod at position 36 is uncoupled. The RO will be withdrawing this rod fully.
Which of the following COP"ECTLY describes when the uncoupled control rod can be identified using RPIS?
a.
As soon as the control rod is selected.
b.
' When the selected control rod is withdrawn from position 36 to position 38.
c.
When the RMCS Timer times out with the selected control rod at position 48.
,
d.
When the selected control rod is withdrawn past position 48 independent of the RMCS Timer.
QUESTION: 071 (1.00)
The plant was operating at 50% power with a non-edge rod selected when the B Recirc Pump controller failed, raising the speed of the B Recirc Pump. Operators respond by locking the B Recirc MG scoop tube, but not before reactor power rises to 75%. Which of the following L
CORRECTLY describes the impact of this transient on the amplification applied to the average LPRM inputs in the Rod Block Monitor (RBM) system? (Assume no other operator actions on the RBM and APRM systems.)
a.
The amount of amplification to RBM "A" average LPRM input signal remains unchanged. The amount of amplification to RBM "B" average LPRM input signal is automatically adjusted to correspond to the speed of the B Recire pump.
b.
The amount of amplification to BOTH RBM "A" and "B'" average LPRM input signals is automatically adjusted to correspond to the reference APRM readings.
c.
The amount of amplification to BOTH RBM "A" and "B"' average LPRM input (
signa's is automatically adjusted to correspond to the new core flow.
d.
The amount of amplification to BOTH RBM "A" and "B" average LPRM input signal remains unchanged, s
-
.
-
--
_
REACTOR OPERATOR Page 46 QUESTION: 072 (1.00)
The plant was operating at full power when an operator mistakenly placed the Hydrogen Water Chemistry (HWC) System Enable Switch, HS-8900, in the SHUTDOWN position. Assume that the operator recognized his mistake and,' 4 minutes later, placed the System Enable Switch back in the AUTO position without taking any other operator actions. Which of the following describes the expected result?
The Hydrogen Flow Control Valves will...
i a.
ramp back to original positions with no adverse consequences, j
b.
open rapidly resulting in low Recirc dissolved Oxygen levels.
,
c.
' open rapidly resulting in high Main Steam Line radiation levels.
,
l d.
open rapidly resulting in a HWC System Hydrogen High Flow Trip.
QUESTION': 073' (1.00)
Which of the following CORRECTLY lists the power supplies to the AC and DC MSIV actuator solenoids?
a.
- AC Instrument AC Divisions 1 and 2 DC 24 VDC Divisions 1 and 2 b.
AC Instrument AC Divisions 1 and 2 DC 125 VDC Divisions 1 and 2 i
c. '
AC RPS Channels A and B DC 24 VDC Divisions 1 and 2 d.
AC RPS Channels A and B DC 125 VDC Divisions 1 and 2
..
.,
a
LREACTOR OPERATOR Page 47 QUESTION: 074. (1.00)
,
' The plant is at 100% power but is experiencing problems with Main Generator auxiliary systems:
'
Generator Megawatts:
560 MWE.
-
.
Genetator Megavars:
-
Generator Hydrogen pressure:
30 psig, stable
-
Generator Hydrogen purity 90%, lowering
'
Which of the following is CORRECT conceming continued operation of the Main Generator?
Operators must '
j
!
a.
lower generator voltage.
b.
raise generator voltage.
'
<
c.
reduce generator load to less than 8000 amps.
>
d.
secure the main generator.
i
'
QUESTION: 075 (1.00)-
~ A complete loss of Uninterruptible AC power occurred with the plant at 100% power. "A" GEMAC Ll-455g was controlling RPV level in automatic on the master controllar.. Assuming NO OPERATOR ACTION, which one of the following describes the INITIAL EFFECT on RPV water level and correctly explains WHY this response occurs?
a.
RPV level LOWERS due to shrink caused by the LOSS of EHC pressure control.
b.'
RPV level LOWERS due to both Feed Pump Recire valves falling OPEN.
. c.-
RPV level RISES due to the master feedwater controller responding to "A" LGEMAC failing DOWNSCALE.
d.'
RPV level RISES due to both Recirc pumps running back with the Feedwater i
Reg valves' LOCKED.
,y i
_
l-REACTOR OPERATOR Page 48 l
l QUESTION: 076 (1.00)
Construction Transformer T4 supplies power to most of the DAEC outbuildings, including the Badging Center, Data Acquisition Center and the Training Center. Which of the following CORRECTLY describes how the primary side of T4 normally receives power from offsite?
The primary s!de of T4 is normally supplied by
a.
the 36KV bus from the Shellsburg and 6th Street line.
b.
the 36KV bus from transformer T3 (161/36KV).
c.
The 4 KV bus from LLRPSF transformer 1XR1 (36/4KV).
d.
The 4 KV bus from the Substation Power Transformer (161/4KV).
QUESTION: 077 (1.00)
l Per IPOI-2, "Startup", which of the following RPV pressures is the minimum necessary to provide sufficient steam flow to reset the Offgas isolation on low steam flow to the Jet Compressor?
a.
300 psig b.
400 psig L
c.
500 psig d.
600 psig
-
REACTOR OPERATOR l Page 49
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QUESTION:078 (1.00)
The plant was in Mode 3 with no inoperable equipment.. Breaker 183401 was closed and
,
supplying busses 1834A and 1844A. An operator error resulted in the TOTAL LOSS of Division
'
1 125 VDC. This DC bus and all associated loads were restored 5 minutes later when operators
,
took corrective action. Which of the following CORRECTLY describes the affect of this transient on 1834017 a.
183401 will re,.nain energized and closed throughout this transient, b.-
1B3401 w;!! remain energized and closed when 125 VDC power is LOST but will automatically trip when 125 VDC power is RESTORED.
c.
1B3401 will remain closed but will appear deenergized on Panel 1C08 until 125 VDC power is RESTORED.
d.
1834d1 will automatically trip when 125 VDC power is LOST and' remain tripped
.
until subsequent operator action is taken to close it.
-QUESTION: 079 -(1.00)
A fire begins in the Main Generator Exciter while at power. An operator AT THE SCENE reports open flames inside the Exciter housing. Identify whether each of the following Exciter CO2 Fire Suppression System actions REQUIRES OPERATOR ACTION or OCCURS AUTOMATICALLY?
1)
Start of CO2 injection
'
2)-
Exciter ventilation shutdown a.
1)
. REQUIRES OPERATOR ACTION
,
'
2)
REQUIRES OPERATOR ACTION b.
1)
REQUIRES OPERATOR ACTION 2)'
OCCURS AUTOMATICALLY c.
1)-
i OCCURS AUTOMATICALLY 2)
REQUIRES OPERATOR ACTION
'
d.
1)
OCCURS AUTOMATICALLY 2)
OCCURS AUTOMATICALLY a
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r2; LREACTOR OPERATOR T Page 50
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.'
QUESTION! 080 (1.00)
~A large break Loss of Coolant Accident has occurred during power operations. The following l'
plant conditions exist; l-RPV level is 180", being maintained with Core Spray.
-
RPV pressure is 20 psig, slowly lowering.
!.
-
All electrical busses have remained energized.
-
Drywell temperature and pressure are elevated enough to require Containment
-
, sprays.
,
The RHR Suction strainers are completely blocked.
--
Operators have been unable to open RHRSW TO RHR CROSSTIE valve,
-
MO-1942.
All other equipment is operating as designed.
-
I
'Is any other system available to spray the containment? If YES, CORRECTLY identify that f
system.
'
'
l a.
.YES; the Condensate Service Water system.
.
. b.
YES; the Well Water system.
ll
. c.
YES; the Fire System.
' d.,
There are NO systems available to spray the containment.
l l
,
' QUESTION: 081 (1.00)
Due to a combination of severe cold weather and Auxiliary Boiler malfunctions, operators are having difficulty maintaining the temperature of the Control Building. General area temperatures in the Control Building are 65'F and lowering. Which of the following equipment must be verified.
for operability if the Control Building temperature continues to lower?
a.
Station Batteries l
. b.
Control' Room Chillers Standby Filter' Units
~c.'
d.
Fire System
.
o
'
REACTOR OPERATOR Page 51 QUESTION: 082' (1.00)
,,
Entering the control room, you note the following regarding the instrument air system:
!.
Instrument Air Header Pressure: 95 psig
-
l Air Compressor Lights on 1C07:
-
Based on these indications, which one of the following CORRECTLY describes the status of
.1K90A, B and C7 a.~
.1K90A is the Lag-lag compressor;'it has not received a start signal.1K90B &
- 1K90C are the Lead & Lag compressors; they are running to restore instrument air pressure.
' b.
1K90A is the Lead compressor; running to restore instrument air pressure.
1K90B & 1K90C are the Lag & Lag-Lag compressors; neither one has started yet.
!
c.
1K90A is the Lag-lag compressor; running to restore instrument air pressure.
1K90B & 1K90C are the Lead & Lag compressors; neither one has started yet.
!
.,
d.'
.1K90A is the Lead compressor; is not running.1K908 & 1K90C are the Lag &
.
Lag-Lag compressors; they are running to restore instrument air pressure.
i
. QUESTION: 083 (1.00) '
,
i Which of the following CORRECTLY describes a difference between ESW and RHRSW
.
operation when these systems are being used for an alternate RPV injection source?
a.
ESW injects through the "B" side of RHR and RHRSW injects through the "A" side of RHR.
j b.
The Main Condenser outlet valves, MO4208 and MO4209, must be closed ESW injection, but not for RHRSW injection.
,
c.
The RHRSW Heat Exchanger Discharge valves, MO2046 and MO1947, must be
- .
,
'
. open for ESW injection, but closed for full RHRSW injection.
,
' d.
- ESW injection flow is controlled by the RHRSW Heat Exchanger discharge valve and RHRSW injection flow is controlled by the LPCI Inject Valves.
i i REACTOR OPERATOR Page 52 QUESTION: 084 (1.00)
The plant is operating at full power with a TIP trace in progress. The system is being operated in the Automatic mode. Status of the TIPS is as follows:
. Channel A:
Inserting to position 2 (Coordinate 16-25)
-
Channel C:
Withdrawing (tracing) from position 2 (Coordinate 16-17)
-
At this point a transient occurs that results in an automatic reactor scram on low water level.
Which one of the following correctly describes the response of the TIP drives to this event?
a.
Channel "A" continues insertion to the top of core, than withdraws to the in shield position without tracing. Channel "C" continues withdrawing to the in shield j
position. The ball valves automatically close when associated detectors are at the in shield position.
b.
Both drives switch to manual reverse and withdraw from the core. The ball valves automatically close when associated detectors are at the in shield position.
c.
Channel "A" continues insertion to the top of core, then withdraws to the in shield position without tracing. Channel "C" continues withdrawing to the in shield position. The operator then closes both ball valves by placing the MAN VALVE CONTROL to CLOSE.
d.
Neither drive is affected until level drops to 119.5"; at that time both will switch to manual reverse and withdraw from the core. The operator then closes both bail valves by placing the MAN VALVE CONTROL to CLOSE.
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' REACTOR OPERATOR Page 53
,
QUESTION: 085 (1.00) -
I
"
The plant is operating at full power. If a leak were to begin past the inboard Fuel Pool gate, wou!d there be a LEAK DETECTION ALARM or must the Control Room identify the problem through an INDIRECT METHOD? If LEAK DETECTION ALARM, identify how the Control Room is informed. If INDIRECT METHOD, identify how the Control Room would know of this problem.
' a. '
LEAK DETECTION ALARM --This condition alarms on the Fuel Pool Cooling Panel 1C65/1C66 and there is an associated panel trouble alarm on Control Room Panel 1C04, b.
. LEAK DETECTION ALARM - This condition alarms on the Fuel Pool Filter /Demin Control Panel 1C136 and there is an associated panel trouble alarm on Radwaste Panel 1C84. The Radwaste Operator must call the Control Room.
c.
INDIRECT METHOD - A low Fuel Pool level condition is alarmed in the Control Room on Panel 1C04 and operators must investigate further.
<
. d.
INDIRECT METHOD - A Reactor Building Equipment Drain Sump high leakage condition is alarmed on Radwaste Panel 1C84. The Radwaste Operator must call the Control Room and operators must investigate further.
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REACTOR OPERATOR Page 54 i
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i QUESTION: 086 (1.00)
At which point in the following Core Alteration scenario would activation of the ROD OUT BLOCK annunciator first occur? (1C05B, A-6)
Scenario:
. The Mode Switch is in REFUEL.
-
All control rods are fully inserted.
-
One control Rod 'is selected.
-
There are no other Rod Blocks in effect.
-
The only hoist in use is the Main Grapple Holst.
-
A fuel assembly is grappled and raised to Full-Up in the Fuel Pool.
-
The Refuel Platform is driven over the core
-
The fuel assembly is lowered into its assigned location.
-
The 1C05 operator attempts to withdraw the selected control rod.
-
Rod Block first occurs when...
a.
the loaded Main Grapple Hoist reaches Full-Up in the Fuel Pool.
b.
the Refuel Platform is driven over the core.
c.
the Main Grapple Holst starts to lower the fuel assembly.
d.
the 1C05 operator attempts to withdraw the selected control rod.
QUESTION: 087 (1.00)
Operators are starting up the Turbine Building HVAC System. The LEAD Turbine Building Exhaust Fan,1V-EF-21 A, has been selected. Now the handswitches for all three Exhaust Fans must be placed in position for the desired speed of operation. At what plant location is this performed?
a.
In the Turbine Building, on the Northwest corner of the Operating Deck.
b.
In the Turbine Building, on the Southwest comer of the Operating Deck.
c.
In the Reactor Building, on the 3rd Floor (812 ele.) in the Southeast hallway.
I d.
In the Control Room at panel 1C23.
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- QUESTION: 088 (1.00)
The plant is in COLD SHUTDOWN for a refueling outage. As normal, approximately 200 of the 1000 annunciators in the Cont;oi Room are illuminated. Which of the following techniques is
. used to help operators more easily identify the true abnormal situations?
a.
Install Normal Outage Annunciator lenses over long-term alarms on any out-of-service equipment. No recording is necessary, b.-
Install Degraded Control Room Instrumentation CAUTION stickers over alarms on any out-of-service equipment. Record installation in the Degraded Instrument Log.
c.
Remove the light bulbs for alarms on disabled equipment that is not safety related. Record removalin the Outage Annunciator Log.
d.
Remove the annunciator panel cards for alarms on disabled equipment that is not safety related. Record removalin the Outage Temporary Modification Log.
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REACTOR OPERATOR Page 56
)
QUESTION: 089 (1.00)
- You are a licensed Reactor Operator working as the Assistant Nuclear Station Operating Engineer (ANSOE) while at power. You have just been informed that you must attend make-up training at the Training Center and that you will be relieved shortly. This training is expacted to take two hours.
1)
Are you required to fill out an ANSOE Turnover form? (YES or NO)
and 2)
is it required to have another Shift Crew Briefing for your relief? (YES or NO)
a.
1)
YES 2)
_YES -
b.-
1)
YES_
2)
NO c.
1)
NO 2)
YES d.
1)
NO_
l 2)
_NO
.
p
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REACTOR OPERATOR Page 57 l
OUESTION: 090 (1.00)
'
l A plant startup and heatup is in progress at 600 psig RPV pressure. The Main Turbine is in Chest Warming. IDT computer terminals are set up as follows:
The terminal next to 1C14 is being used to monitor KAMAN parameters.
-
-l The Chemist is collecting data from the MIDAS terminal.
-
The terminal to the left of the ANSOE desk is being used as the alarm monitor as
-
usual.
The other three IDT terminals around the Control Room operators' desks are set up as described below. Which set of Plant Process Computer displays is NOT ACCEPTABLE for this plant condition?
a.
HEATUP Group Display 32 (Startup parameters)
POWER (Turbine parameter display)
b.
SPMET 1 -
Group Display 15 (APRM and other date)
STATUS (Plant status overview display)
c.
SPTOP DR (Rod position display)
A Trend / Plot display of Main Turbine parameters d.
SPREAC PPC Menu Group Display 33 (Turbine Startup parameters)
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REACTOR OPERATOR ~
Page 58
L-.
L QUESTION: 091 (1.00)
l
.Which of the following is a design basis of HPCl? -
a.
Must be able to functiore adependent of on-site power sources, b.
Assures that the reactor core is adequately cooled to limit fuel clad tempers' rr in the event of a large break in the reactor coolant system.
c.
Assures that the reactor core is adequately cooled to limit primary containment 1
,
pressure in the event of a small break in the reactor coolant system.
J L
d.
Make up water to the reactor vessel in the everi of a loss of coolant situation that does not result in rapid RPV depressurization.
~
QUESTION: 092 (1'.00).
. A normal plant startup and heatup is in progress with the MSIVs open. Reactor pressure has ll
' been adjusted to 180 psig. -The STA reports that the Heatup Rate is 75'F/Hr and rising, so
.
operators suspend control rod withdrawal. Which one of the following methods should be used to lower the Heatup Rate?
a.
Lower the EHC Pressure Set setpoint.
b.
Raise the EHC Pressure Set setpoint.
'
c.-
Open Main Steam Line Drains.
d.
Close Main Steam Line Drains.
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REACTOR OPERATOR Page 59
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QUESTION: 093 (1.00)
Core alterations are in progress with operators preparing to lift a fuel assembly from the core.
. Which of the following conditions will automatically stop the upward movement of the Main Grapple Hoist Mast) if it were to occur while lifting a fuel assembly?
,
!
a.
Activation of the " Slack Cable" light.
b.
Activation of the " Grapple Full Down" light.
l-l c.
Loss of the " Grapple Closed" light.
d.
Loss of the "Holst Loaded" light.
,
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- QUESTION: 094 (1.00)
j
- During which one of the following postulated scenarios.is a Technical Specification SAFETY LIMIT violated?
l a.
At 100% power HPCI spuriously injects into the reactor vessel; the Reactor i
Engineer determines MCPR in the highest powered bundle was as low as 1.15.
1'
bl While at full power, EHC fails and causes the reactor to depressurize; the MSIVs
>
l remain open and before the operator manually scrams the reactor, he notes pressure is 750 psig.
!
l l
c.
While at power, a small break occurs in one of the Recirc pump suction lines.
The crew cannot restore injection and turn level until it drops to +18 inches.
'
, d.
' Immediately before the Mode Switch is to be placed in RUN during a startup, a l
Rod Drop accident causes power to peak at 20% before the APRM high flux a
scram occurs.
4 f REACTOR OPERATOR.
Page 60
.
QUESTION: 095 (1.00)
An area of the Radweste Building 'is set aside to store some highly radioactive material. It is
<
determined that the entrance into this area could result in personnel receiving 7 Rem in one hour 30 centimeters from the radiation source. Which of the following is the correct posting for
' this area? :
a.'
b.
,
c.
' Double Locked High Radiation Area
- d.
. Very High Radiation Area
QUESTION: 096 (1.00)
- During off normal working hours, a plant transient'results in fuel damage and declaration of a Site Area Emergency. Emergency' Response Organization callout has been initiated but the :
+
Technical Support Center (TSC) and Operational Support Center (OSC) are not yet manned. It.
is necessary for an operator to reenter the Reactor Building to terminate the offsite radioactive release that is in progress and you have been assigned this task. The Shift Manager, acting as
~ the Emergency Coordinator, performs the required briefing with~you. During the briefing he states that the expected exposure for this task is 7 Rem and authorizes you to exceed the occupational dose limit of 5 Rem / year.~ Does the Shift Manager have the authority to extend your occupational dose limit in this situation? (YES or NO)
'
If NO, identify the CORRECT reason why he cannot authorize this extension.
a.
YES:
b.
. NO; Emergency Plan Implementing Procedures limit exposures to 5 Rem.
c.
NO; Only the Site Radiation Protection Coordinator can authorize this extension.
NO; On!' after the TSC is manned can the Emergency Coordinator authorize this d.'
y extension.
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REACTOR OPERATOR Page 61
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QUESTION: 097 (1.00)
During recovery from a severe A1WS transient, the crew hears a muffled explosion and the 1C03 operator notices his wide range Drywell Pressure meters coming off their upper stops.
The Containment remains intact. Assume that actual Drywell pressure peaked at 120 psig.
Can the peak Drywell pressure be determined from the Control Room? If so, which control room instrument (s) can be used to identify that pressure?
From the Control Room, the peak Drywell pressure...
a.
CANNOT be determined.
b.
CAN be determined. Use SPDS Containment Conditions screen which plots Drywell pressure.
c.
CAN be determined. Use'1C09 Drywell Pressure recorders, PR-4398A and/or B.
d.
CAN be determined. Use 1C29 Drywell Pressure recorders, PR-4384A and/or PR-4385A.
QUESTION: 098 (1.00)
A large break Loss of Coolant Accider.t is in progress. The OSS has directed you, the Panel 1C03 operator, to open four ADS SRVs and maximize injection. Four ADS SRVs have opened but, even with the RPV depressurized and all available ECCS pumps injecting, RPV level cannot be raised above +15 inches. At this point the OSS directs you to open the Inboard Main Steam Line Drain Valve, MO-4423.
Which of the following is the reason for opening MO-4423 in this situation?
The OSS is anticipating the need a.
. to drain the steam lines.
b.
to establish a c< olant flowpath for RPV Flooding.
c.
to vent the RPV during containment flooding per the Severe Accident Guidelines (SAGS).
d.
to keep the RPV depressurized so low pressure systems can inject for Alternate Level Contro [.
L REACTOR OPERATOR Page 62 l
QUESTION: 099 (1.00)
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(Necessary attachments from AOP 302.2 " Loss of Alarm Panel Power" are provided as an exam handout.) During Panel Checks, it is discovered that Annunciator Panel 1C07A does not respond and appears deenergized. Annunciator checks on all other annunciator panels are satisfactory. Which power supply or fuses is/are the MOST LIKELY cause of this problem?.
a.
Tripped breaker 1D23, Ckt.10 b.
Blown fuse (s) Fu10A+ and/or Fui0A-c.
Blown fuse (s) FuA and/or F27A
, d.
Blown fuse (s) F2-6ASB and/or F1-6ASB QUESTION: 100 (1.00)
. You are a licensed Reactor Operator on dayshift, working on outage tagouts in the Work Control Center. You do not have assigned responsibilities in the Emergency Response Organization (ERO). A transient occurs that results in the declaration cf an ALERT Emergency and activation of the Evacuation Alarm. To which of the following locations do you report?
a.
. The Control Room.'
b..
The Warehouse assembly area.
,
c.
The Technical Support Center (TSC).
d.
The Offsite Relocation and Assembly Location (ORAL).
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(**"***"* END OF EXAMINATION *""*"")
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REACTOR OPERATOR Page 63 ANSWER: 001 (1.00)
ANSWER. 004 (1.00)
a.
d.
REFERENCE:
REFERENCE:
SD-693.1, revision 2, section F -
SD-880, rev 7, System Operation. Section Distracter 1: The CIV STOPS should close on C.4.
. a trip to protect the turbine from overspeed, Distracter 1: The transient will make level go the source of steam is the low-pressure low, not high.
heaters backing up into the turbine.
Distracter 2: Recirc pump NPSH is not Distracter 2: Mechanical overspeed trip looks affected by carryover.
like any other trip.
Distracter 3: Moisture content of the steam is Distracter 3: The backup overspeed trip not adversely affected by carryunder.
cannot help in this situation; the turbine stop valves are already closed.
295009K102
..(KA's)
' ANSWER: 002 (1.00)
. ANSWER: 005 (1.00)
c.
b.
REFERENCE:
REFERENCE:
SD 255, revision 4, System Operation, section 01-877; Defeat 16
- Distracter 1: Failure of the flow control station.
295009K102
..(KA's)
will also result in LOW current.
Distracter 2: A clogged drive filter will result in -
LOW amps on the motor.
ANSWER: 006 (1.00)
Distracter 3: An air bound pump will have c.
'
LOW current.
REFERENCE:
RT-29 295006K203
..(KA's)
Distracter 1: Would be shorter because Xenon would already be decaying and now l
start to bum out.
ANSWER: 003 (1.00)
Distracter 2: Would be shorter. The point of b.-
adding heat is on range 6.
REFERENCE:
Distracter 3: Shorter is correct, but feedwater SD-183.1, revision 3, Major Components, flow does not change until steaming rate Section B and Control and Instrumentation, changes.
section H Distracter 1: Purpose of LLS is to protect the _
295014A202
..(KA's)
SRV tailpipe, not prevent reaching 1055.
i
- Distracter 2:' LLS will lift the valve at'1020 to protect the SRV tailpipes.
Distracter 3: LLS lifts the valves at 1020 and 1025.
'
295007K304'..(KA's)
I i
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l REACTOR OPERATOh Page 64 L
ANSWER: ' 007 (1.00)-
ANSWER: 010 (1.00)
l b.
b.
REFERENCE:
REFERENCE:
EOP Bases, ATWS page 71; SD 878.8 RPV/F Note: RPV/F EOP is not provided. For Distracter 1: Select blocks come from RSCS.
RPV/F conditions, RPV must be 50 psig above Distracter 2: Placed in Bypass per RIP 103.3, torus pressure but as low as possible.
Distracter 1: Also need torus pressure.
Distracter 3: Placed in Bypass per RIP 103.3.
Distracter 2: Torus pressure not Drywell.
RWM enforcement is not desirable.
Distracter 3: Injection rate is pertinent but not necessary.
- 295015K301'
...(KA's)
295031G2.4
..(KA's)
ANSWER: 008 (1.00)
c.
ANSWER: 011 (1.00)
.
REFERENCE:
.
a.
EOP Bases Document, EOP-2, Primary REFERENCE:
Containment Control, revision 4, page 59.
ATWS EOP Bases Note: Inserting IRMs is an Distracter 1: We do not spray to cool the immediate operator action for the scram REFERENCE legs.
..
procedure.
Distracter 2: We do not spray to control RPV Distracter 1: Yes is correct, but the training
.
injection from RHR.
technique wams against ranging down i
Distracter 3: Sprays will cause (not prevent)
because it will result in exaggerated IRM
{
vacuum breaker cycling.
response.
'
Distracter 2: IRMs can be inserted.
295024K301
..(KA's)
Exaggerated response is true only if operator incorrectly ranges down.
Distracter 3: IRMs can be inserted. Damage ANSWER: 009 (1.00)
from high flux is not a stated concern.
. d.
REFERENCE:
295037A201
..(KA's)
T.S. 2.1.2 Distracter 1: Nominal setpoint of Safety Valves.
Distracter 2: RPV design pressure.
Distracter 3: RPV discharge piping design pressure.
295025K105
...(KA's)
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REACTOR OPERATOR Page 65 ANSWER: ' 012 (1.00)
ANSWER: 014 (1.00)
- c. -
c.
REFERENCE:
REFERENCE:
.
SEP 303.3 Note: Although thisANSWER is Instructor Guide 88.0; plant response. Note:
taken from procedure steps, an RO should Fuel Zone indicators read higher than the recognize that CAD cannot be injected when GEMACs at power because the lower taps are
- containment sprays are in service on that line.
share a sensing line with the calibrated jet
- Additionally, the RO should know that the pumps and see additional pressure.
torus spray header is ring header common to Distracter 1: They may both read lower but both loops of RHR.
they will not read the same because of Recire Distracter 1: Selected if RO does not.
flow in the B Loop which makes B Fuel Zone understand the relationship between RHR and read higher.
CAD.
Distracter 2: They will not read the same Distracter 2: Selected if RO does not because of Recirc flow in the B Loop which
_
understand about the torus ring header, makes B Fuel Zone read higher.
. Distracter 3: Selected if RO believes that any Distracter 3: A Fuel Zone will read lower.
form of containment spray disallows CAD injection.
295001A206
..(KA's)
5000A103
..(KA's)
ANSWER: 015 (1.00)
c.
' ANSWER: 013'(1.00)
REFERENCE:
'd.
ARP 1C07B, B-1 & C-1
' REFERENCE:
Distracter 1: This is the value for a Turbine SD-149, revision 6, page 22; EOP-2 Bases trip, but the Turbine would already be tripped.
Distracter 1: Both sets of spray valves receive Distracter 2: This is the value for a Group 1 the close signal from drywell pressure.
Isolation, but this feature would be bypassed Distracter 2: Both sets of spray valves receive during a plant cooldown.
- the close signal from drywell pressure.
Distracter 3: The maximum value for Distracter 3: Both sets of spray valves receive condenser backpressure (i.e. no vacuum).
the close signal from drywell pressure.
Homogeneous distracter.
~
L295024K211
..(KA's)
295002A106
..(KA's)
- .
A*'
' REACTOR OPERATOR Page 66
' ANSWER: 016 (1.00)
ANSWER: 019 (1.00)
de d.
REFERENCE:
REFERENCE:
AP 301.1, SD-304 Note: Nominal grid EOP-1 and 2 Entry Conditions voltage is 4160 VAC 3700 VAC=88%.
Distracter 1: Selected if RO does not Degraded Voltage trips at <92.5% for >8 recognize Drywell pressure >2 psig.
seconds Distracter 2: Selected if RO recognizes Distracter 1: Below 92.5% and logic does not Drywell pressure >2 psig as only an EOP 1 auto reset..
entry condition.
Distracter 2:. Below 92.5%
Distracter 3: Selected if RO recognizes Distracter 3: Below is correct, but AOP 301.1 Drywell pressure >2 psig as only an EOP 2 provides direction for resetting at this voltage.
entry condition.~ >2 psig is the only EOP-1 entry condition.
295003K103-..(KA's)
295012G2.4
..(KA's)
ANSWER: 017 (1.00)
a.
ANSWER: 020 (1.00)
REFERENCE:
b.
SD-375, Revision 4, Table C; AOP-149, REFERENCE:
revision 12, Section 3.2 ACP 1410.1 Distracter 1: HPCI will be unavailable due to Distracter 1: " Entered" is correct, but it can be loss of the bus.
.
_
exited when >95*F if no emergency exists.
Distracter 2; HPCI will be unavailable due to" Distracter 2: EOP-2 is entered. In some loss of the bus; RHR shutdown cooling suction situations STPs do govern operations. (E.g.
isolation (outboard) has no power.
Temp Mods)
Distracter 3: RCIC will only work until it Distracter 3: EOP-2 is entered. ACP states isolates; RHR shutdown cooling suction this explicitly for planned operations.
isolation (outboard) has no power.
295013G2.4
..(KA's)
295004A102
..(KA's)
ANSWER: 021 (1.00)
ANSWER: 018 (1.00)
d.
a.
REFERENCE:
ARP.1C04C, A-6 Note: RCIC trips on 211 _
AOP-915 Note: AOP-915 requires the Mode REFERENCE:
.
_
.
Switch be placed in RUN ifit was in RUN inches in 6 minutes.
originally.
Distracter 1: HPCI suction transfers to the Distracter 1: Last known position of Mode torus at 10.6 ft in 8 minutes. This also closes
- Switch.
the test valve shared by RCIC.
Distracter 2: Common misconception.
' Distracter 2: HPCl initiation' occurs at 2 psig in Distracter 3: Homogeneous distracter.
DW in 10 minutes. This also closes the test valve shared by RCIC.
295016G2.4
..(KA's)
Distracter 3: RCIC isolates on low steam supply pressure at 100 psig in 20 minutes.
295008K206
..(KA's)
i
REACTOR OPERATOR Page 67 ANSWER: 022 (1.00)
ANSWER: 025 (1.00)
d.
c.
REFERENCE:
REFERENCE:
AOP-672 ARP 1C05B, A-2, Step 2.2, Revision 2 Distracter 1: Plausible, but there is no control Distracter 1: Primary source signal is the function from this monitor.
MSIVs, High APRM Hi flux would be a backup Distracter 2: A common misconception.
signal.
Distracter 3: Plausible, but this condition Distracter 2: Primary source signal is the results in a Group 3 isolation.
MSIVs, High RPV pressure would be a backup signal.
295017A102
..(KA's)
Distracter 3: Testing PCIS instruments; Turbine shouldn't trip untillater ANSWER: 023 (1.00)
295020K301
..(KA's)
a.
REFERENCE:
50-518; AOP-408 Note: The main Inst and ANSWER: 026 (1.00)
Service air compressors have an independent d.
- cooling system. The backup compressor, REFERENCE:
which is idle in a normal lineup, is cooled by T.S. Bases 3.1.5, C.1& C.2; SD 255 Note:
well water.
.
The labels for the " vessel pressure only" and Distracter 1: Reduced cooling to the Offgas
" accumulator pressure only" lines on the recombiner closed cooling water heat graph have been deleted. Use of
,
exchanger and glycol refrigeration machines.
" approximate"in stem of question is justified I
Distracter 2: Loss of cooling to Control Bldg.
because there can be no confusion about
'
Chillers. AOP directs alternate use of ESW.
these values if the graph is interpreted Distracter 3: Loss of cooling to main intake correctly.
cooling coils, and low flow may auto bypass Distracter 1: Selected if RO uses the them. AOP directs bypassing these coils.
" accumulator pressure only" line. Per T.S.,
i scram function could be degraded which is
{
295018K101
.'.(KA's)
why the rod must be inserted.
I
'
Distracter 2: Selected if RO uses the
" accumulator pressure only" line.
ANSWER: 024 (1.00)
Distracter 3: Per T.S., scram function could be
,
d.
degraded which is why the rod must be REFERENCE:
inserted.
j AOP 518, revision 18 Distracter 1: SDV vents and drains fail 295022K101
..(KA's)
l CLOSED, not OPEN.
l Distracter 2: Backup scram valves are solenoid valves.
l Distracter 3: Flow control valve fait closed,
!
reducing CRD pump flow.
295019K201
..(KA's)
]
,
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I REACTOR OPERATOR Page 68 l
ANSWER: 027 (1.00)
ANSWER: 030 (1.00)
b.
c.
REFERENCE:
REFERENCE:
I.
EOP Bases, Curves and Limits, Page18 EOP-2 Bases, revision 4 Distracter 1: This limit is used to key the crew Distracter 1: Plenty of water to reflood is into the fact that the pressure suppression available.
function of the Torus is not working, requiring Distracter 2: RCIC exhaust is never a problem an ED. One of two " Torus" distracters, which because it is low flow and energy.
makes it attractive Distracter 3: Torus level is high enough to Distracter 2: This is not part of the bases HCL cover the downcomers.
but it is similar to Distracter 3 which is.
Distracter 3: This is part of the bases for HCL, 295030K101
..(KA's)
but not the most limiting.
i 295026K301
..(KA's)
ANSWER: 031 (1.00)
c.
REFERENCE.
.
ANSWER: 028 (1.00)01-170; SEP 301.1; SD-170 Note: 50 psig will b.
lift the SBGT overpressure relief damper on REFERENCE:
the RB second floor. The SBGT 01 directs that AOP-913 this area specifically be evacuated. Rad Distracter 1: Selected if RO does not know this levels will increase in other areas, but no other sprinkler is isolated.
area is specifically identified.
Distracter 2: This is the location of the Standby Distracter 1: Primary concern is the SBGT Filter Unit Deluge system isolation valve, Relief on RB Second Floor, which is also normally closed.
Distracter 2: Primary concem is the SBGT Distracter 3: This is the location of the Standby Relief on RB Second Floor.
Gas Treatment Deluge system isolation valve, Distracter 3: Primary concern is the SBGT which is also normally closed.
Relief on RB Second Floor.
600000A216
..(KA's)
295033G2.3
..(KA's)
ANSWER: 029 (1.00)
ANSWER: 032 a.
b.
REFERENCE:
REFERENCE:
EOP-2 Bases EOP Program Manual, EOP-4 section, Rev. 2 Distracter 1: SRV Tailpipe limit is 13.8 ft.
Distracter 1: ED will not reduce the leak rate Distracter 2: Not the basis. There is still 2.5 ft.
from this system.
of air space above 13.5.
Distracter 2: ED will not reduce the leak rate Distracter 3: Not the basis. This distracter from this system.
may relate again to the SRV tailpipe limit.
Distracter 3: ED will not reduce the leak rate from this system.
295029K205
..(KA's)
295038A204
..(KA's)
REACTOR OPERATOR Page 69 ANSWER: 033 (1.00)
ANSWER: 036 (1.00)
c.
d.
!
REFERENCE:
REFERENCE:
AOP 149, revision 10 SD-170.1, revision 3 Distracter 1: It is not necessary to increase Distracter 1: Isolation dampers are designed RWCU pump NPSH to increase flow, for more than 7" H20.
Distracter 2: This is true, but not the reason Distracter 2: If SBGT did not start there is no level is raised.
flowpath through the system, plus SBGT Distracter 3: This is true, but not the reason releases via the stack, which is monitored.
level is raised.
Distracter 3: High pressure will not affect the Kamans.
295021K301
..(KA's)
295035A101
..(KA's)
ANSWER: 034 (1.00)
>
c.
ANSWER: 037 (1.00)
REFERENCE:
d.
SD-733, ARP 1C058, C-8; P&lD M-176 Note:
REFERENCE:
During a Group 3, SBGT will align to the RB SD 358 Vent Shaft, thus drawing refuel floor air Distracter 1: Plausible, but incorrect, through AV-7604V.
Distracter 2: Plausible, but incorrect.
Distracter 1: EF-10 trips on a Group 3.
Distracter 3: Plausible, but incorrect.
Distracter 2: There are no such dampers and EF-11 A&B trip on a Group 3 isolation.
201001K205
..(KA's)
Distracter 3: Shifting to High Bay Exhaust is only done manually for refueling ops.
ANSWER: 038 (1.00)
295023K205
..(KA's)
b.
REFERENCE:
ARP 1C05A D-6, revision 5 ANSWER: 035 (1.00)
Distracter 1: Loss of the even numbered reed d.
switch (without detection of an odd switch)
REFERENCE:
does not give the DRIFT alarm.
EOP-3 Bases Distracter 2: Loss of the even numbered reed Distracter 1: Definition of Max Normal.
switch (without detection of an odd switch)
Distracter 2: Temperatures above Max Safe does not give the DRIFT alarm. Will actuate are an indication of an accident, but not the for a non-selected rod even if another rod is basis for the values.
driving.
Distracter 3: Some equipment may fail Distracter 3: Will actuate for a non-selected because max Safe is based on Safe rod even if another rod is driving.
Shutdown equipment failure.
201002K403
..(KA's)
295032K104
..(KA's)
I REACTOR OPERATOR Page 70 ANSWER: 039 (1.00)
ANSWER: 041 (1.00)
c.
c.
REFERENCE:
REFERENCE:
j ARP 1C04AD-8 Note: Speed Demand runs EOP-2 Bases Note: This value has recently back to 20% on a 20 % Runback but not to-been recalculated and changed from 6 ft. to 45% on a 45% runback. That is why the 5.8 ft.
procedures are different. The procedure for Distracter 1: Downcomers become uncovered.
resetting a 45% runback directs the operator Distracter 2: Former value.
to lock the scoop tube first. A DAEC RO Distracter 3: SRV tailpipes become should know this.
uncovered.
. Distracter 1: (S) Remains at 60% and pump speed would increase.
206000A104
..(KA's)
Distracter 2: (S) Remains at 60% and there is no such interlock.
Distracter 3: 60% is correct but there is no ANSWER: 042 (1.00)
such interlock, a.
REFERENCE:
202002A206
..(KA's)
01 151, Rev. 30, Sect. 4.0-209001A301
..(KA's)
ANSWER: 040-(1.00)
a. -
i REFERENCE:
ANSWER: 043 (1.00)
'01-149 b.
Distracter 1: The RHR Crosstie MO-2010 REFERENCE:
would be closed, preventing injection from 01153, revision 25, Section 4.0 A&C.
Distracter 1: Lights should go out, not come
.
Distracter 2: B loop does not automatically -
on.
realign itself for LPCI in;tiation. The Group 4 Distracter 2: Lights should go out, alarm isolation must also be reset before one B loop should go ON, pressure should be <1350 psig.
.
inject valve will open.
Distracter 3: Alarm should come on, pressure
'
Distracter.3: The RHR Crosstie MO-2010 should be <1350 psig.
would be closed, preventing injection from
,
A&C. B loop does not automatically realign 211000A408
..(KA's)
itself for LPCI initiation. The Group 4 isolation must also be reset before one B loop inject valve will open.
203000K401
..(KA's)
(
REACTOR OPERATOR Page 71 j
l ANSWER: 044 (1.00)
ANSWER: 047 (1.00)
a.
a.
REFERENCE:
REFERENCE:
J SD-358, Page 20 O! 878.5; SD 878.5
'
Distracter 1: This time woulo be used to Distracter 1: No rod blocks will be enforced; Initiate ARI if all rods do not insert, but this is the APRM is <30%. APRM "E"is the alternate not the correct basis.
for A RBM, APRM "F" for B RBM.
Distracter 2: RPV level needs time to stabilize Distracter 2: APRM f. lode Switch will not force but this is not the correct basis, the RBM to the alternate REFERENCE Distracter 3: SDV valves would be closing APRM.
during this period, but this is not the correct Distracter 3: No rod blocks will be enforced; basis.
the APRM is <30%. APRM Mode Switch will not force the RBM to the alternate 212000K502
..(KA's)
REFERENCE APRM. APRM "E"is the alternate for A RBM, APRM "F" for B RBM.
ANSWER: 045 (1.00)
215005K307
..(KA's)
d.
REFERENCE:
ARP _1C05A, B-3 and D-3; SD856.1 ANSWER: 048 (1.00)
~ Distracter 1: INOP causes a % scram yes, but a.
also a rod block.
REFERENCE:
Distracter 2: An IRM downscale is a rod block SD 880,Rev. Page 12. Note: Air bubbles above range 1, but not with that channel rising in theREFERENCE leg reduce the bypassed. Inop generates a % scram when pressure at the transmitter. (Notching) Lower IRM is unbypassed.
ref leg pressure translates to higher indicated Distracter 3: IRM Mode Switch must be in level.
OPERATE to get an IRM Downscale.
Distracter 1: Higher is correct but the sensed DP decreases.
T'5003A202
..(KA's)
Distracter 2: The sensed DP decreases but this causes indicated level to read higher.
Distracter 3: Lower is incorrect and the sensed ANSWER: 046 (1.00)
DP decreases.
b.
REFERENCE:
216000K506
..(KA's)
01878.1, Revision 11, Sect. 2.0
.
Distracter 1: Bypassed if SRM >100 cps.
Distracter 2: Rod block bypassed on Range 3 and above.
l-Distracter 3: Rod block bypassed on Range 3 and above.
215004A101
..(KA's)
.
..
.
-
-.
REACTOR OPERATOR Page 72 h
ANSWER: 049 (1.00)
ANSWER: 051 (1.00)
a.'
d.
REFERENCE:
REFERENCE:
01-573 Note: RO is required to know that DW O1-150 Note: RO is expected to know that inerted means <4% oxygen.
- MO-2400 wo 'Id be located in the Drywell and Distracter 1: Chosen if CAD low inventory not-therefore an AC valve. RO must also identified.
recognize that this valve would come from an Distracter 2 & 3: Chosen if CAD low inventory essential bus.
is not identified and operator is confused Distracter 1: This is an AC bus and it is about how to use Attachment 4.
located in nearby in the reactor bldg. but it is a non-essential bus. (1B14 comes from 1B1)
223001A410
..(KA's)
Distracter 2: Selected if RO thinks MO-2400 has a large DC motor.1D41 is the power supply to most HPCI DC equipment, including ANSWER: 052 (1.00)
the outboard steam line isolation valve.
c.
Distracter 3: Selected if RO thinks MO-2400 REFERENCE:
has a small DC motor.1D14 is the power ARP 1C05B, A-8 Note: Backpressure is supply to most RCIC DC equipment, including higb(>19 inches Hg Abs). The bypass which the outboard steam line isolation valve.
allows a startup with the MSIVs open is un-bypassed if the mode switch is placed in 217000K201
..(KA's)
run or a TSVis opened.
Distracter 1: Selected if confused with "<850 psig in RUN" Group 1.
ANSWER: 050 (1.00)
Distracter 2: Selected if confused with Turbine c.
Stop Valve opening which would result in a REFERENCE:
Group 1.
O1-573, Rev. 54, Sect 2.0; SD 183.1, Rev. 3, Distracter 3: Selected if confused about Cond System Interrelations High Backpressure Logic.
Distracter 1: ADS initiation will not work if there is no nitrogen.
223001A410
..(KA's)
Distracter 2: Manual signal will not workif there is no nitrogen..
Distracter 3: Manual signal will not work if.
ANSWER: 053 (1.00)
there is no 'litrogen., high pressure actuation a.
does not require nitrogen..
REFERENCE:
SD-183.1, revision 3, page 7 218000A203
..(KA's)
Distracter 1: Possible misconception. The Torus to DW Vacuum breakers are in the Torus air space.
Distracter 2: This occurs if the vacuum breaker has failed closed, not open.
Distracter 3: Selected if RO thinks the vacuum breakers are under water in the Torus.
239002K605
..(KA's)
a
_-
-____-_
_ - - _ - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l REACTOR OPERATOR Page 73
,
ANSWER: 054 (1.00)
ANSWER: 056 (1.00)
b.
b.
REFERENCE:
REFERENCE:
>
, ARP 1C08C D-4, Rev. 7; SD 693.2a; SD 697 01-644; SD-644 Distracter 1: Input from Turbine Trip. Runback Distracter 1: This could cause the given does not directly affect intercept valves, indications, but both Non-Essential busses are Distracter 2: Input from Power Load fed by the Auxiliary Transformer when the Unbalance. Runback does not input a "0" plant is in normal operation.
signal.
Distracter 2: Once the A&B controllers are in Distracter 3: Input from Low Vacuum to close Auto, their control is transferred to the Master BPVs. Runback does not input directly to controller. Adjusting the Setpoint knob does BPVs.
nothing.
Distracter 3: The A&B controllers and reg 241000A317
..(KA's)
valves themselves may have been in unequal positions when placed in auto, but it is the job of the Master Controller to provide them the ANSWER: 055 (1.00)
same signal now. The only difference will be a.
the bias setting of the individual controllers.
~
REFERENCE:
SD-644; SD-639 259002K501
..(KA's)
Distracter 1: A RFP does have a shorter low suction pressure trip time delay, but it trips on interlock.
ANSWER: 057 (1.00)
Distracter 2: Only A RFP trips. One d.
condensate pump can supply up to 68%
REFERENCE:
power.01-152; 01-170 Distracter 3: A RFP trips on interlock.
Distracter 1: Does NOT bypass SBGT, off gas fans are not relevant.
259001A310
..(KA's)
Distracter 2: Does NOT bypass SBGT, off gas fans are not relevant.
Distracter 3: Do not need a SBGT fan running for HPCI to work.
261000K106
..(KA's)
REACTOR OPERATOR Page 74
^NSWER: 058 (1.00)
ANSWER: 061 (1.00)
c.
d.
REFERENCE:
REFERENCE:
SD 324, revision 1 ARP 1C05B C-8, Rev.14; SD-170, Rev. 2, Distracter 1: This is opposite of the way page 10 Degraded Voltage protection works. With low Distracter 1: Low flow signal will not start the
{
bus voltage the Startup and STBY transformer
"B" train in this condition; it is not in standby..
treakers open. The SBDG gets a start sig~nal, Distracter 2: Low flow signal will not start the not a breaker trip signal.
"B" train in this condition; it is not in standby.
!
Distracter 2: Output breaker does not trip open Distracter 3: O:ny the Group 38 signalis on Bus undervoltage. The SBDG trips first on~
necessary; An auto start does not require a overspeed.
concurrent low flow condition on the A SBGT Distracter 3: It is true that the SBDG trips first train, on overspeed, but the Output breaker does not trip open on Bus underfrequency.
261000K401
..(KA's)
264000A207
..(KA's)
ANSVER: 062 (1.00)
d.
REFERENCE:
ANSWER: ' 059.(1.00)'
01324, Caution on page 10. Note: The a.
referenced caution requires the SBDG to be REFERENCE:
rolled with air before starting to prevent 01-151, revision 30, section 7.1 damage from oil which may have collected in Distracter 1: Pump and valves must be the upper piston area.
manually configured.
Distracter 1: Selected of RO is unaware of the Distracter 2: Cannot reset untilinitiation caution / operating characteristic.
signals are cleared.
Distracter 2: This step must also be performed Distracter 3: Cannot reset untilinitiation but the SBDG cannot be started until it has signals are cleared. Pump and valves must been rolled with air, be manually configured.
Distracter 3: Alarms on 1C91 activate the
shutdown relay and must be reset prior to a
. 209001G2.1
..(KA's)
SBDG start, but the prelube operation described does not activate such an alarm.
. ANSWER: 060 (1.00)
264000K603
..(KA's)
j b. '
REFERENCE:
ARP 1C03A A-6, revision 3 Distracter 1: ADS waits two minutes.
Distracter 2: Breaker closed is not the correct signal; triple low level must be in place two minutes.
Distracter 3: Breaker closed is not the correct signal.
218000K501
..(KA's)
l REACTOR OPERATOR Page 75 l
ANSWER: 063 (1.00)
ANSWER: 065 (1.00)
'
l b.
c.
REFERENCE:
REFERENCE:
!
SD959.1 Note: The ARP is somewhat SD-255, revision 3, page 22 Note:
misleading because the Oli/1&2 pushbuttons High-pressure water from the charging l
are momentarily depressed in the Operator header / accumulator under the drive piston
'
Actions, but the MSIV handswitches are taken nserts the rod (slower than normal). Exhaust to CLOSE in the Follow-up actions. Per the flow is to the reactor.
simplified diagram of the Group 1 logic, the Distracter 1: No flow to the SDV because MSIV HSs must be in CLOSE first. DAEC ROs CV-1850 remains closed.
are trained to always follow up a Group 1 Distracter 2: Parts 1 & 2 are correct but 3 is isolation at 1C03 by placing the MSIV incorrect because of No flow to the SDV.
handswitches in CLOSE.
Distracter 3: Part 3 is correct, but rod will Distracter 1: All parameters are sat, but the insert and lower power.
Group 1 will not reset because of the MSIV handswitches.
201003K404
..(KA's)
Distracter 2: The Group 1 will reset in any other mode than RUN.
Distracter 3: The Condenser high ANSWER: 066 (1.00)
backpressure bypass is disabled (preventing a b.
reset) if a Turbine Stop Valve is open, not a REFERENCE:
Turbine Control Valve.
SD 878.8 Distracter 1: Rod drop, not a CRWA..
223002A403
..(KA's)
Distracter 2: 280 calories per gram on a rod drop, not CRWA ANSWER: 064 (1.00)
Distracter 3: 280 calories per gram.
d.
REFERENCE:
201006K105
..(KA's)
SD-880 Distracter 1: Arrangement shown is typical of ECCS and would therefore be DC Powered.
ANSWER: 067 (1.00)
Distracter 2: Arrangement shown is typical of b.
ECCS.
REFERENCE:
Distracter 3: ECCS arrangements use DC SD264; P&lD 115& 116 Note: Total Core flow power and are energized to initiate.
is the sum of 16 non-calibrated Jet Pumps.
Distracter 1: Common misconception; 216000K405
..(KA's)
Provides indication only.
Distracter 2: Common misconception;
)
Distracter 3: Plausible and homogenous.
202001A103
..(KA's)
l l
p REACTOR OPERATOR Page 76 ANSWER: 068 (1.00)
ANSWER: 071 (1.00)
l c.
d.
l l
REFERENCE:
REFERENCE:
SD-261; P&lD M127 & M112; ARP 1C04D SD 878.5 Note: The amount of amplification l
C-8 Note: It is a common misconception that (gain)is established by the gain change unit
'
RBCCW supplies only the seal water cooler.
during a Null sequence. Nulling is initiated by:
Distracter 1: Common misconception.
Selecting a rod, unbypassing an RBM Distracter 2: Selected if basingANSWER on channel, shifting to an alternate reference common misconception and thinking that the APRM or depressing a Null pushbutton on the oil should have some means of heat removal.
RBM drawer.
Distracter 3: Auxiliary Lube Oil System is Distracter 1: Possible misconception. Gain relatively new. There is no cooler in the Aux does not change.
system.'
Distracter 2: Possible misconception. Gain does not change.
204000K601 '..(KA's)
Distracter 3: Possible misconception. Gain does not change.
' ANSWER: 069 (1.00)
215002A101
..(KA's)
d.
REFERENCE:
01-149 Note: DAEC no longer throttles with ANSWER: 072 (1.00)
l the inject valve to save wear and tear on the c.
larger, more expensive valve.
REFERENCE:
Distracter 1: Not used in this service. One O1-563 valve alone would be poor at controlling both Distracter 1: P&L #21 and several l
parameters.-
note / Cautions in 01 say not to do this because Distracter 2: Common misconception. HX inlet the FCVs open rapidly, and bypass control both.
Distracter 2: Rapidly is correct but result is Distracter 3: HX inlet and bypass control both.
Incorrect. Low Recirc dissolved O2 is a good thing but this parameter changes very slowly.
205000K502
..(KA's) _
lt would start increasing when H2 is Shutdown and merely retum to normal value when H2 is restored.
ANSWER: 070 (1.00)
Distracter 3: Rapidly is correct but result is d.
incorrect. High Flow trip set at 9.9 scfm. FCVs REFERENCE:
are set at 7 scfm maximum.
SD. 856.1 Distracter 1& 2: No way to detect this failure 272000K501
..(KA's)
until rod is at position 48 and a coupling check is performed.
Distracter 3: A Rod Drift alarm would be
. received when the RMCS timer timed out and the rod was not on an even numbered
_ position. RMCS timing out is not necessary to get the overtravel alarm.
205000K502
..(KA's).
_
.
i l
J
)
-REACTOR OPERATOR Page 77 ANSWER: 073 (1.00)
ANSWER: 076 (1.00)
d.
b.
REFERENCE:
REFERENCE:
SD-683, revision 0, page 28/29 SD 304 Note: T4 may not have high Distracter 1: Shou!d be RPS and 125 VDC.
operational validity, but this question also Distracter 2: Should be RPS.
challenges RO's knowledge of normal and Distracter 3: Should be 125VDC.
backup sources of power to the 36KV bus and
'
the role of the LLRPSF transformers.
239001K201 d a 's)
Distracter 1: This is the backup source of 36KV. There is an auto recloser on this line in case the normal supply voltage from T3 is lost.
ANSWER: 074 (1.00)
Distracter 2: The primary side of T4 is 36KV. A d.
common misconception. Substation REFERENCE:
schematic shows a tie in close to 1XR1.
O1-695.2 Note: Hydrogen purity which cannot Distracter 3: The primary side of T4 6 36KV.
be maintained >90% requires a generator A plausible / homogeneous Distractet.
j shutdown due to the possibility of an explosion at <74.2%.
262001K201
..(KA's)
Distracter 1: Selected if RO does not
,
'
recognize problem with purity. Voltage adjust
. would be correct otherwise.
ANSWER: 077 (1.00)
Distracter 2: Selected if RO does not d.
recognize problem with purity. Voltage adjust REFERENCE:
is also incorrect.
IPO-2
'
Distracter 3: Correct action for loss of bus duct Distracter 1: 300 psig is the normal operating cooling. Reducing load does not lessen the pressure for the Air Ejectors and Jet threat of an explosion.
Compressor after it is reduced from the Main Steam system 1950 psig.
-245000K604-..(KA's)
Distracter 2: > 300 psig but still too low per
,
IPOI-2.
Distracter 3: > 300 psig but still too low per ANSWER: 075 (1.00)
IPOl-2.
d.
REFERENCE:
271000A401
..(KA's)
,
l Turbine provides it's own power supply on.
kne.
Distracter 2: These valves fail open upon loss of inst AC,' not UPS. They are available for -
attemate level control.-
Distracter 3: Possible confusion with loss of
.
Div. 2125 VDC, which requires transfer to A Level. Feed regulating valves lock; the master controller is not affecting level.
262002K301
..(KA's)
l
I i
l REACTOR OPERATOR Page 78 l
ANSWER: 078'(1.00)
ANSWER: 081 (1.00)
d.
a.
'
I REFERENCE:
REFERENCE:
'AOP-302.1; ARP 1C08A, D-5 01-730, P&L 15;1 RM 3.8.2.3 Note: It seems Distracter 1: Selected if RO does not implausible but battery operability becomes a recognize Div 1 125 VDC as control power to concern <65'F. Until recently, an 01-730 P&L 183401 wamed about this. Now the P&L refers Distracte: 2: Selected if RO thinks that 125 '
operators to the TRM but operators should still VDC control power is necessary to trip the recognize the threat to the batteries.
breaker.
.
Distracter 2: Plausible because SFUs draw in Distracter 1: Plausible due to low load.
Distracter 3: 183401 will appear deenergized at 1C08, but it will be tripped. An ARP caution outside air during CB HVAC isolations.
wams about this.
Distracter 3: Plausible due to freezing in remote locations.
263000K302
..(KA's)
290003A202
..(KA's)
ANSWER: 079 (1.00)
a.
ANSWER: 082 (1.00)
REFERENCE:
d.01-513, Sect. 5.4 Note: Initiation and REFERENCE:
ventilation shutdown always requires operator SD 518, revision 3, page 12 action. - Auto shutdown of CO2 occurs in 2 minutes if initiated from the turbine op deck 300000G2.1
..(KA's)
(786' level). If CO2 is manually initiated from
.
the CO2 tank on the T8 ground floor (757'
level), it must also be manually isolated.
ANSWER: 083 (1.00)
Distracter 1: 2 requires operator action.
c.
' Distracter 2: 1 requires operator action.
REFERENCE:-
Distracter 3: 1&2 require operator action.
. AIP 401 and Als 402
_
Distracter 1: Both inject through A loop RHR.
286000K110
..(KA's)
Distracter 2: Not necessary for either ESW or RHRSW injection.
Distracter 3: Both are controlled by LPCI inject ANSWER: 080 (1.00)
valves. RHRSW HX Discharge valve is never a.
throttled during ESW injection. RHRSW HX j
REFERENCE:
. Discharge can be throttled open after LPCI AIP_403,404, & 405 Note: This question injects are closed during RHRSW injection.
<
requires knowledge of both the EOP-2 Table 9 systems and flowpath necessary to achieve 400000G2.4
..(KA's)
Cont Sprays.
Distracter 1: RO must recognize that this
.
system needs MO-1942 open for Cont Spray.
l Distracter 2: RO must recognize that this system needs MO-1942 open for Cont Spray.
l Distracter 3: Condensate Service is available.
226001K106
..(KA's)
REACTOR OPERATOR Page 79 ANSWER: 084 (1.00)
ANSWER: 086 (1.00)
>
b. -
b.
REFERENCE:
REFERENCE:
01-878.6, revision 20; SD 878.6, Rev. 2 SD 856.1, Table 2; ARP 1C05B, A4; STP Distracter 1: Both drives switch to manual and 3.9.1-01 withdraw.
Distracter 1: Bridge over the core with hoist
.
Distracter 2: Both drives switch to manual and loaded is a Rod Block. No Rod Block until withdraw; ball valve closure is automatic when then.
the detector reaches in shield position.
Distracter 2: Bridge over the are with hoist Distracter 3: Reactor scram is at the Group ll loaded is a Rod Block.
setpoint,170". ball valve closure is automatic Distracter 3: Bridge over the core with hoist when the detector reaches in shield position.
loaded is a Rod Block 215001K105
..(KA's)
234000K401
..(KA's)
ANSWER: 085 (1.00)
- ANSWER: 087 (1.00)
a.
c.
REFERENCE:
REFERENCE:
SD435 01-733 Distracter 1: Condition is alarmed but not on Distracter 1: Common misconception.
1C136 and Radwaste. Common Distracter 2: Common misconception.
Misconception.
Distracter 3: Common misconception.
Distracter 2: Fuel poollow level will alarm in the CR but the leakage condition is also 288000A401
..(KA's)
alarmed.
Distracter 3: RB EQ Drains are alarmed in the main CR, not Radwaste. ( A possibio -
ANSWER: 088 (1.00)
misconception and necessary to prevent a.
synonymous Distracters.) The leakage REFERENCE:
condition is alarmed.
ODI-14, ODI-12 2.1 Conduct of Op Note: An unfamiliar 233000A211
..(KA's) '
operator might think the correctANSWER is too good to be true.
Distracter 1: Not used. Instrumentation is not degraded. Also, each instance would require and associated work document. (CWO)
Distracter 2: This would resolve the problem, but there is no procedure for this action and there is no such thing as an " Outage Annunciator Log."
Distracter 3: Card removal could be used for nuisance alarms, but only on a small scale.
Each instance would require implementation of the Temporary Modification process. There i
is no such thing as an " Outage Temp Mod".
2.1.2
..(KA's)
!
i
,
1 '
j.
. REACTOR OPERATOR Page 80 l
ANSWER: 089 (1.00).
ANSWER: 092 (1.00)
'
b.
a.
REFERENCE:
REFERENCE:
ACP 1410.10, Sect. 3.8 IPOI-2 Note: RO is not expected to know Distracter 1: Shift Crew Briefing is not procedure steps toANSWER this question.
required.
,
Candidate must recognize that lowering Distracter 2: The appropriate turnover form pressure set is the only viable method to
. shall be cornpleted any time a crew member is reduce heat up rate.
relieved. Shift Crew Briefing is not required.
Distracter 1: This will increase the heatup rate.
Distracter 3: The appropriate tumover form Distracter 2: MSL Drains should already be shall be completed any time a crew member is open. If they had been closed, this action relieved.
would merely close the turbine bypass valve.
RPV pressure and Heatup rate will remain the 2.1.3 -
..(KA's)
same.
Distracter 3: This will open the turbine bypass valve. RPV pressure and Heatup rate will
- ANSWER: 090 (1.00)
remain the same.
- a.
REFERENCE:
01-831.4 Note: All options are normal displays ANSWER: 093 (1.00)
used during a startup. An SPDS display must c.
be one of the screens. SPMET-1, SPTOP, and REFERENCE:
SPREAC are SPDS displays.
SD 281; RFP 301 Distracter 1: The onlyANSWER options Distracter 1: Stops downward movement, not without Turbine monitoring.
upward.
Distracter 2: The onlyANSWER options Distracter 2: Stops downward movement, not without a Group Display.
upward.
Distracter 3: The onlyANSWER options with a Distracter 3: It would not be good to continue,
,
' Menu being displayed.
but there is no interlock.
i L ANSWER: 091 (1.00)
~ ANSWER: 094 (1.00)
d. '
b.
REFERENCE:
REFERENCE:
SD 152 ITS 2.0 Distracter.1: Design Basis D states that HPCI Distracter 1: 1.07 is the limit.
.
uses plant DC power.
Distracter 2: t15"is the limit.
Distracter 2: Design Basis A states that HPCI Distracter 3: 15% scram is an LSSS but not a provides adequate core cooling, but not for safety limit. Failure to scram on a Primary Source signal is no longer a Safety Limit large breaks.
.
violation.
Distracter 3: It is designed for a small break LOCA but Containment protection is not one of its bases.
}
(
)
I REACTOR OPERATOR Page 81
?
' ANSWER: 095 (1.00)
ANSWER: 098 (1.00)
b.
c.
REFERENCE:
REFERENCE:
ACF 1411.13 and 22 Note: LHRA is EOP Bases, ED Note: ED flowchart is NOT
>1 Rem /Hr. Next highest p --ting is VHRA.
provided. DAEC operators are no lor.ger Distracter 1: HRA is >100 ivirem/Hr responsible for knowledge of SAGS, so they Distracter 2: Common misconception. This may dismiss the correct answer option.
term is no longer used.
MO-4423 is in the Drywell and may not open Distracter 3: VHRA is > 500 Rem /Hr when needed for PCF if DW water level is
>39ft.
Distracter 1: Obvious choice, but there is no ANSWER: 096 (1.00)
reason to drain MSLs.
,
a.
Distracter 2: RPV Flood coolant flowpath goes
'
REFERENCE:
through the SRVs to the Torus, not down the EPIP 4.3 Note: EPIPs allow Emergency MSLs.
Coordinator to extend dose limits. In this Distracter 3: RPV has a big leak the SRVs situation the SM is the EC.
opened, the P.PV will remain depe.ssurized for Distracter 1: Extension is allowed by EPIP 4.3.
injection.
Distracter 2: Extension is allowed by EPIP 4.3.
SRPC does not have the authority.
Distracter 3: Extension is allowed by EPIP 4.3.
ANSWER: 099 (1.00)
The EC in the TSC can also authorize this d.
extension, but that does not prohibit the SM REFERENCE:
from authorizing it when the TSC is not yet AOP 302.2, Rev. 8 activated.
Distracter 1: Would also deenergize 1C06A&B,1C078, and 1C08A
)
2.3.4
..(KA's)
Distracter 2: Would also deenergize 1C08A j
Distracter 3: Would also deenergize 1C07B l
ANSVER: 097 (1.00)
2.4.32
..(KA's)
c.
REFERENCE:
ITS Bases 3.3.3.1, Page 3.3-61 Note: This is a plant Operating Event (OE). Approx!mately one year ago the 1C09 instrument was
l removed without entering the LCO for inop
!
Post Accident instrumentation.
Distracter 1: Can be determined on 1C09
.
PAM/1.97 instruments,0-250 psig range.
Distracter 2: Not a PAM /1.97 instrument;
I range is only 0-100 psig.
i Distracter 3: Not PAM /1.97 instruments;
{
range is only -10-90 psig.
2.4.3
..(KA's)
REACTOR OPERATOR Page 82 ANSWER: 100 (1.00)
a.
REFERENCE:.
EPIP 2.5, Sect.3.3 Note: All Operations Dept.
personnel on-site report to the Control Room,
whether or not they are assigned on-shift duties.
Distracter 1: All other non-ERO Alliant employees report here.
Distracter 2: Work Control Center is located in the area converted into the TSC, and they could use operator assistance too.
Distracter 3: CorrectANSWER for all other non-ERO Alliant employees during a Site Area Emergency.
2.4.39
..(KA's)
.
(""""" END OF EXAMINATION "**"*"*)
l
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.s REACTOR OPERATOR Page 83 A N S W E R K E Y - MULTIPLE CHOICE 001
~ a
'021 d
041 c
061 d
081 a
002-c-
022 d
042 a'
062 d
082 d
003 b
023 a
043 b
063 b
083 c
004 d
024'
d 044 a
064 d
084 b
005 b
025-c 045 d
065-c 085 a
006 c-026 d
046 b
066 b
086 b
007 b
027 b
047 a
067 b
087 c
008 c
028 b
048 a
068 c
088 a
009 d
029 a
049 a
069 d
089 b
010
.b 030 c
050 c
070 d
090 a
011-a 031 c
051 d
071 d
091 d
,
012 c
032 b
052 c
072 c
092 a
013 d
033 c
053 a
073 d
093 c
014 c
034 c
'054 b
074 d
094 b
015 c
035
'd 055 a
075 d
095 b
'016 d
036
'd 056 b
076 b
096 a
017 a
037 d
057.
d 077 d
097 c
018 a..
038 b
058 c
078
.d 098 c
j 019'
d 039 c
059-a 079 a
099 d
020 b~
040 a
060 b
080 a
100 a
.
(**"""" END OF EXAMINATION """"")
i
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U.S. Nuclear Regulatory Commission i
Site-Specific l
Written Examination Applicant Information Name: MASTER COPY Region:
lli Date: September 24,1999 Facility / Unit:: DAEC License Level:
SRO Reactor Type: GE Start Time: 7:58 Finish Time: 12:58 i
Instructions l
Use the answer sheets provided to document your answers. Staple this cover sheet on top l
of the answer sheets. The passing grade requires a final grade of at least 80.00 percent.
Examination papers will be collected five hours after the examination starts.
l l
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature Results Examination Value 100.0 Points Applicant's Score Points Applicant's Grade Percent i
I
___
WRITTEN EXAMINATION GUIDELINES 1.
Cheating on any part of the examination will result in a denial of your application and/or
!
action against your license.
.
2.
' After you complete the examination, sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistance in completing the
- examination.
3.
To pass the examination, you must achieve a grade of 80.00 percent or greater; grades will not be rounded up to achieve a passing score. Every question is worth one point.
4.
' The time limit for completing the examination is five hours.
.
5.
You may use the provided pencils, and calculators. Do not use pens to mark your (
answers on the scan-tron answer sheets.
6.
Print your name in the blank provided on the examination cover sheet and on the answer sheet. You may be asked to provide the examiner with some form of positive identification.
l 7.
Mark your answers on the answer sheet provided. Use only the paper provided. Erase l'
. completely if you decide to change your original answer, then mark the new answer yoiu
[
have chosen. If the NRC grading examiner is unable to determine which answer you -
'
have selected because of poor erasure, the examiner will mark the answer as incorrect.
8.
If you have any questions conceming the intent or the initial conditions of a question, do
)
not hesitate asking them before answering the question. Ask questions of the NRC
!
examiner or the designated facility instructor only. When answering a question, do not make assumptions regarding conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question. For example, you should not assume thet any alarm has activated unless the question so states or the alarm is expected to activate as a result of the conditions that are stated in the question.
9.
Restroom trips are permitted, but only one applicant at a time will be allowed to go to the restroom. Use the restroom in the exam room.
10.
When you complete the examination, bring the answer sheet and cover sheet to the
NRC examiner or proctor. Sign the statement on the examination cover sheet indicating
- that the work is your own and that you have neither given not received assistance in completing the examination. The proctor will clean up your table and reference material
- after you leave the exam room.
11.
' After you have turned in your examination, leave the examination area as defined by the proctor or NRC examiner, if you are found in this area while the examination is still in progress, your license may be denied or revoked.
12.
Do you have any questions?
E I
l SENIOR REACTOR OPERATOR Page 3 l
l l
QUESTION: 001 (1.00)
L During a reactor power ascer.sion following startup, the plant was operating at 25% load when alarm 1C07A A-2, MAIN TURBINE TRIP, actuated. While verifying turbine status as directed by the Annunciator Response Procedure, the operator notes the following:
Generator output breakers are TRIPPED.
-
All turbine CONTROL VALVES are CLOSED.
-
All turbine main STOP VALVES are CLOSED.
-
All CIV STOP valves are OPEN.
-
All CIV INTERCEPT valves are 95% OPEN and CLOSING.
-
l Turbine BYPASS valves are open to control reactor pressure.
-
l Evaluate the above indications and select the answer that CORRECTLY describes the status of l
the Main Turbine.
[
a.
The main turbine did not respond correctly to the turbine trip and is in danger of sustaining damage.
j b.
The main turbine tripped normally and will be coasting down; all valve positions l
are as expected.
l
'
c.
The turbine trip was due to mechanical overspeed and the turbine is responding normally to this condition.
d.
Not all turbine vatves responded as expected, but the backup overspeed trip will protect the turbine.
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L SENIOR REACTOR OPERATOR '
Page 4
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i QUESTION: 002 (1.00)'
l l
The plant has SCRAMMED from full power. While stabilizing the plant, an operator observes the following indications:
The running CRD pump current is above normal running amps.
)
-
CRD Cooling Water flow is DOWNSCALE.
-
Select the answer that CORRECTLY explains these indications and identifies the appropriate operator response.
,a.
The flow control station has failed; action must be taken as soon as possible to protect the CRDMs.
b.'
The in service CRD suction filter is clogged; the standby filter must be placed in service as soon as possible.
c.
CRD pump flow is being diverted through the Scram inlet valves to the CRDMs and the reactor; no further actions are r.ecessary.-
d.
The running CRD pump is air bound and must be tripped as soon as possible.
. QUESTION: 003 (1.00)
An I&C tech performing an STP inadvertently initiated a Group i isolation while at full power, a
The resultant transient lifted four Safety-Relief Valves, including the two low-low set valves, on
' high RPV pressure. After these valves close, as indicated by their associated amberlights extinguishing, the operators take no further action. At WHAT PRESSURE will the next Safety-Relief Valve open and WHY?
a.
1020 psig; to prevent reaching the high pressure scram setpoint.
b.
1020 psig; to protect the SRV tajipipes from damage.
c.
1110 psig; to protect the reactor from overpressurization.
d. '
1110 psig; to minimize cycling of the other SRV c; SENlOR REACTOR OPERATOR Page 5
QUESTION: 004 (1.00)
One of the running Reactor Feed Pumps was inadvertently TRIPPED while the plant was at 90% power.
l 1)-
Does the resultant transient result in CARRYOVER or CARRYUNDER ?
2)
What is the primary concern associated with this condition?
a.
1)
CARRYOVER 2)
Excess moisture impinging the blades of the Main Turbine.
i b.
1)_
CARRYOVER 2)
Reduction in Recirc Pump Net Positive Suction Head.
i l
c.
1)
CARRYUNDER 2)
Excess moisture impinging the blades of the Main Turbine.
d.
1)
CARRYUNDER 2)
Reduction in Recirc Pump Net Positive Suction Head.
,.
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SENIOR REACTOR OPERATOR Page 6
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QUESTION: 005 (1.00)
A Loss of Coolant Accident has occurred. The following conditions exist:
RPV levelis 1502and stable.
-
Operators are lining up additional injection systems.
-
Drywell pressure is 5 psig and slowly lowering.
-
There are no abnormal rad conditions.
-
All plant equipment functioned as designed.
-
Operators have taken all appropriate actions.
-
The Chemists have been directed to use the Post Accident Sampling System (PASS) to sample the Drywell atmosphere for hydrogen. The OSS has authorized Chemists to override open the PASS Sample Station Exhaust Isolation dampers at Panel 1C24.
Which of the following CORRECTLY describes the affect of containment isolations on the ability of PASS to sample the Drywell?
a.
PASS wili be available because there is no isolation signal present which would have isolated it.
b.
PASS will be availablo because Defeat 16, " Drywell and Torus Atmosphere Monitoring Sample Line Containment Isolation Defeat" would be installed per EOP-2, PC/H leg.
c.
PASS will NOT be available until operators can raise RPV level to >170] and reset the complete Group 3 Isolation.
d.
PASS will NOT be available until operators place the GROUP 3 CHANNEL A and B ALL SIGNALS OVERRIDE keylock handswitches in OVERRIDE (on panels 1C15 and 1C17 respectively) and reset the complete Group 3 Isolatio !
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l SENIOR REACTOR OPERATOR Page 7-
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QUESTION: 006 (1.00)
The plant had been in operation at full power for two months until a reactor scram occurred 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> ago.
l A reactor startup is now in progress.
-
RPV level control is on the Startup Feed Reg Valve in automatic with a 50 gpm
-
drain established through RWCU.
Reactor water temperature is 175'F.
-
When the reactor first went critical in the SRM range, operators calculated a stable period of 120 seconds. As power first comes into the IRM range (ranges 1-4), operators again calculate reactor period. Assuming no instrument inaccuracies, will the new reactor period be longer or shorter? Also identify the correct reason for this answer, a.
Longer - At the higher power, fission product poison concentration will start to rise more rapidly adding negative reactivity, b.
Longer _- At the higher power, nuclear heat will start to raise reactor water temperature adding negative reactivity.
c.
Shorter - At the higher power, fission product poison concentration will start to lower more rapidly adding positive reactivity.
d.
Shorter - At the higher power, more feedwater flow will start to lower Reactor water temperature adding negative reactivity.
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l SENIOR REACTOR OPERATOR Page 8 QUESTION: 007 (1.00)
An electrical ATWS has occurred with reactor power remaining at approximately 7%. The 1C05 operator is directed to manually drive control rods.
1)
Should the Rod Worth Minimizer be PLACED IN BYPASS or should it REMAIN IN OPERATE 7 AND 2)
' What is the CORRECT reason for the answer to part 1 of this question?
a.
1)
PLACED IN BYPASS 2)
To disable possible Select Blocks.
b.
1)
PLACED IN BYPASS 2)
To disable possible Insert Blocks.
c.
1)
REMAIN IN OPERATE 2)
To transmit rod positions to the Plant Process Computer.
d.
1)
REMAIN IN OPERATE 2)
To enforce insertion of the highest worth rods first.
l QUESTION: 008 (1.00)
Which of the following is the value of the Reactor Coolant System Pressure SAFETY LIMIT?
Reactor steam dome pressure shall be...
a.
s 1240 psig.
b.
s 1250 psig.
c.
s 1325 psig.
d.
s 1335 psi c:_
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l SENIOR REACT R OPERATOR Page 9 l
QUESTION: 009 (1.00)
. An ATWS transient is in progress. Because reactor power remained above 5%, reactor water level was lowered to.+87 inches. The OSS now directs that RPV injection be restored to maintain between +70 inches and +85 inches. An EOP Training Technique addresses the use of IRMs in this situation.
According to this Training bchnique, can the IRMs be inserted at this point? (YES or NO) If YES, identify the answer that CORRECTLY describes how they are utilized. If NO, identify the answer that CORRECTLY explains why not.
a.
YES Select one recorder on each side for IRM and leave the IRM on Range 10.
b.
YES Select one recorder on each side for IRM and keep that recorder on scale by ranging down the IRM.
c.
NO IRMs may provide exaggerated responses during injection.
d.
NO l
lRMs may be damaged by high flux levels.
.
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SENIOR REACTOR OPERATOR Page 10 j
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QUESTION: 010 (1.00)
Operators are attempting to stabilize the plant after a combined ATWS and Loss of Coolant l
Accidents. Current plant conditions are:
All rods have been fully inserted.
-
The B Loop of RHR is being used for Drywell Spray and Torus Spray.
-
The A Loop'of RHR is being used for Torus Cooling only.
-
-
Drywell and Torus hydrogen concentrations are increasing.
The OSS directs the BOP operator to begin nitrogen injection into the containment using the Containment Atmosphere Dilution (CAD) system. Which CAD injection point, if any, would be available in this plant condition?
a.
Both "A" and "B" Drywell Spray and Torus Spray headers.
l b.
"A" Drywell Spray and Torus Spray headers only.
c.
"A" Drywell Spray header only.
d.
No injection point would be available.
QUESTION: 011 (1.00)
An accident has occurred. Plant conditions are as follows:
Drywell pressure:
11 psig, dropping 1 psig/ minute
-
Torus pressure:
9 psig, dropping 1 psig/ minute
-
- '
Core Spray injecting to maintain level
-
RHR spraying the Drywell and Torus Assuming no further operator action, which of the following correctly describes the next expected AUTOMATIC action, and what is the setpoint for that action?
a.
. Torus spray valves ONLY will close when Torus pressure drops to 2 psig.
b.
Drywell spray valves ONLY will close when Drywell pressure drops to 2 psig, c.
Drywell AND Torus spray valves will close when Torus pressure drops to 2 psig.
d.
Drywell AND Torus spray valves will close when Drywell pressure drops to 2
,
psi,
I.
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' SENIOR REACTOR OPERATOR Page 11
,
i QUESTION: 012 (1.00).
The plant was in power operation with both Recirc Pumps running at 80% speed and RPV level I
stable at 190 inches on the GEMAC levelindicators. At this point the A Recirc Pump trips.
l
. Operators stabilize the plant and restore RPV to 190 inches on the GEMAC level indicators.
Select the answer that CORRECTLY describes how this transient will affect the FUEL ZONE
!
RPV levelindication on Panel 1C03.
a.
Both Fuel Zone indicators will read the SAME BUT LOWER.
!
b.
. Both Fuel Zone indicators will read the SAME BUT HIGHER.
c.
The A Fuel Zone indicator will read LOWER than the B Fuel Zone indicator.
l d.
The A Fuel Zone indicator will read HIGHER than the B Fuel Zone indicator.
'
QUESTION: 013 (1.00)
l
'
Reactor pressure is 800 psig.' A normal reactor shutdown and cooldown is in progress per IPOI-4, " Shutdown", Section 4.0, " Plant Cooldown with the Condenser Available". The Turbine
'
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Bypass Valves (BPVs) are being used to lower RPV pressure. Assume that a balance of plant l
_ problem were to occur which caused Main Condenser Backpressure to start INCREASING. At which of the following condenser backpressure values will the BPVs cease to be effective in reducing RPV pressure?
a.
7.5 inches Hg. Abs.
b.
19 inches Hg. Abs.
c.
22 inches Hg. Abs.
d.
29 inches Hg. Abs.
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r SENIOR REACTOR OPERATOR'
Page 12 QUESTION: 014 (1.00)-
A fire has severelyNamaged 250 VDC Bus 1D40, which will not be available for at least a week.
Toxic fumes from the fire preclude entry to the power block by operations personnel. Under these conditions, which of the following groups of systems is available for a safe plant shutdown?.-
a.
Core Spray, RHR LPCI Mode b.
c, HPCI, RHR Shutdown Cooling Mode d.
RCIC, RHR Shutdown Cooling Mode QUESTION: 015 (1.00)
A plant transient has resulted in the following plant conditions:
-.
' Reactor level:
205 inches, rising at 1 inch / minute Torus level:
10.2 ft, rising at 0.05 ft/ minute
-
Drywell pressure:
1.0 psig, rising at 0.1 psig/ minute
-
Reactor pressure:
300 psig, lowering at 10 psig/ minute -
-
HPCI does not currently have an initiation signal.
-
RCIC is running in the CST to CST mode.
-
Assume that:
The above rates of change remain constantc All automatic actions occur at design setpoints.
How much longer will RCIC continue to operate in the CST to CST mode?
a.
6 ' minutes b.
8 minutes c.
10 minutes i
- d.
- 20 minutes
_-
SENIOR REACTOR OPERATOR Page 13 QUESTION: 016 (1.00)
Assume that the Average Torus Water Temperature rises above 95iF during testing. Which of-the following statements is CORRECT conceming entry into EOP-2, " Primary Containment
_
Control"?
a.
EOP-2 is entered and CANNOT be exited until Average Torus Water Temperature is <95'F.
b.
EOP-2 is entered but can subsequently be exited when it is determined that an emergency does not exist, c.
EOP-2 is NOT entered when operator actions are governed by the STP.
d.
EOP-2 is NOT entered for preplanned evolutions.
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' SENIOR REACTOR OPERATOR Page 14 QUESTION: 017 - (1.00)
The plant is operating at full power with all equipment operable. Fuel leakage is causing
. increased coolant activity and offsite release through the Offgas System. At which one of the following points will this release path be automatically isolated?
This release path will automatihally isolate when...
a.
a HI Rad condition is sensed at the Offgas Carbon Bed Vault monitor, b.
a Hi-HI Rad condition is sensed at the Offgas Pretreatment sample point.
c.
. a HI-HI Rad condition is sensed at the Offgas Vent Pipe sample point.
d.
a HI-HI-HI Rad condition is sensed at the Offgas Postreatment sample point.
QUESTION: 018 (1.00)
- The pl.3nt is operating 100% power in the middle of the summer. All plant systems are in normal lineups except for the D Well pump, which is out of service. Assume that the B Well pump trips and that operators take the necessary actions per AOP-408 to continue operation with reduced well water flow. Of the following systems, which one WILL NOT be immediately affected or require operator action to stabilize?
a.
The Instrument and Service Air System b.
The Offgas System-c.
The Control Building HVAC System
- d.
The Reactor Building HVAC System
.
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SENIOR REACTOR OPERATOR Page 15 l
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l QUESTION: 019 (1.00)
l A complete loss of the service and instrument air systems occurs while at full power. Operators j
l are trying to restart a compressor as air header pressure lowers, but they may be required to scram the reactor. Which one of the following is a potential effect on the Control Rod Drive (CRD) Hydraulic System?
a.
The scram discharge volume may fail to isolate when the scram occurs.
b.
The Backup scram valves could fail to vent the Scram Air Header when the scram occurs.
c.
The running CRD pump could be operating in a runout condition before the scram occurs.
j d.
Cooling flow could be lost to the control rod drive mechanisms before the scram occurs.
l QUESTlON: 020 (1.00)
The plant was operating normally at 90% power. I&C technicians performing a stwei" nce test on the Main Condenser Backpressure Primary Containment Isolation Instrumentath j
inadvertently cause a Group 1 isolation. Which one of the following signals willinitiate the resulting reactor scram?
a.
APRM High Flux (Flow Biased)
b.
RPV High Pressure c.
MSIVs Not Full Open d.
SENIOR REACTOR OPERATOR Page 16 QUESTION: 021 (1.00)
During an accident, with RPV pressure at 800 psig, the Average Torus water temperature reaches the Heat Capacity Limit (HCL) and is still increasing. At this point the EOPs direct operators to Emergency Depressurize. An ED at this point will prevent exceeding CERTAIN CONTAINMENT LIMITS. Which of the following is the MOST LIMITING containment limit for the DAEC in this situation?
a.
The Torus Pressure Suppression Pressure Limit.
j b.
The Primary Containment Pressure Limit.
j c.
The Drywell design temperature limit.
d.
The Torus design temperature limit.
j
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......
.
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SENIOR REACTOR OPERATOR Page 17 QUESTION: 022 (1.00)
Sprinkler system #12 covers the HVAC area above the Control Room. If a fire were to occur in this area, would this sprinkler automatically actuate (i.e. spray water on the fire)? (YES or NO) If NO, identify the operator action necessary to actuate this sprinkler, a.
YES, - Sprinkler 12 is charged and ready to actuate if a fire is sensed.
b.
NO, - A manual isolation valve must also be opened, located in the Turbine Bldg., North 757ft. level, East of the Feed Reg Valves, c.
NO, - A manualisolation valve must also be opened, located in the Control Bldg.
Battery Room Corridor, on the south wall.
d.
NO, - A manualisolation valve must also be opened, located in the Reactor Bldg.', North-East 7866 level, by the MG Room door.
>
. _ _. _ _ _. _ _.
SENIOR REACTOR OPERATOR Page 18 QUESTIONi 023 (1.00)
<
EOP-2, " Primary Containment Control", Step T/L-10, directs the operator to maintain Torus water level below 13.5 ft.~ Which of the following CORRECTLY identifies the basis for this limit?
Above this level a.
the Torus to Drywell vacuum breakers become covered.
b."
. the SRV tailpipe limit is exceeded.
c.
. insufficient air space remains in the Torus to receive a LOCA blowdown without
-
exceeding the containment design pressure.
d.
primary containment failure could occur during an Emergency Depressurization
.
of the RPV.
,
.
-...
....,
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SENIOR REACTOR OPERATOR Page 19
.
QUESTION: 024 (1.00)
i The plant was operating at full power when a transient c': curred which caused EOP-2 entry on LOW TORUS LEVEL. Plant conditions are as follows:
)
i RPV level:
190", stable
-
RPV pressure:
1000 psig, stable
-
Drywell pressure:
0.5 psig
-
Torus pressure:
O psig
-
Torus level:
7 feet
-
Torus temperature:
105'F
-
What adverse consequences could result if a large line break LOCA occurred during these -
conditions? '
a.
Inadequate volume of water is available for low pressure ECCS to reflood the vesselin the event of a LOCA.
b.
RCIC is not available for injection into the RPV due to inadequate heat sink for the turbine exhaust.
c.
LOCA Downcomer flow will bypass the normal flowpath, directly pressurizing the torus air space with steam.
d.
Relief valves cannot be used for pressure control or emergency depressurization due to inadequate heat sink.
a
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L SENIOR REACTOR OPERATOR Page 20
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QUESTION: 025 (1.00)
A Loss of Coolant accident has occurred which requires operators to perform SEP 301.1, ' Torus Vent irrespective of Rad Release". One train of Standby Gas Treatment (SBGT) is in operation.
Drywell pressure is 50 psig and still rising slowly with two Torus vent valves open; CV-4301, OUTBD TORUS VENT ISOL, and CV-4309, INBD TORUS VENT BYPASS ISOL.
'
' SEP 301.1 now directs that the third Torus vent valve be opened; CV-4300, INBD TORUS
' VENT ISOL. Which of the following will be the primary personnel exposure concern when CV-4300 is opened?
'
a.
Radiation levels near the NE Corner Room Torus vent ducting.
l b.
Radiation levels near SBGT charcoal adsorbers.
c.
Airborne activity levels on the Reactor Building Second Floor (El. 786ft.).
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d.
Airborne activity levels in the NE Corner Room.
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SENIOR REACTOR OPERATOR Page 21 QUESTION: 026 (1.00)
The ' lant was in a normal ventilation lineup when a refueling accident results in a complete p
Group 3 isolation. Which of the following CORRECTLY describes how Refuel Floor ventilation is affected?
a.
The Refueling Pool Exhaust Fan,1V-EF-10, automatically starts.
' b. '
The inlet dampers to the Reactor Building Exhaust Fan, EF-11 A &B, shift to take suction on the Refuel Floor.
- c.
The Refuel Pool to Vent Shaft Inlet Valve, AV-7604V, automatically opens.
d.
.The Refuel Floor Damper Control automatically shifts the associated dampers to High Bay Exhaust.
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I QUESTION: 027 (1.00)
The MAX SAFE values for Reactor Building Temperatures used in EOP-3, " Secondary
.
Containment Control" are based on which of the following criteria?
L Max Safe temperatures are based on an engineering evaluation of the highest value a.
. expected to be seen during normal operations.
l b.
expected to be seen during an accident.
c.
at which NO equipment will fail.
d. '
at which equipment needed for safe shutdown of the plant will not fail.
.
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Page 22 l
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QUESTION: 028 (1.00)'
. The plant has experienced a seismic event while operating at power. This resulted in a large
. HPCI steam line break in the Reactor Building.- HPCI failed to automatically isolate as required.
An. operator reports reactor building ventilation isolated on high radiation, but SBGT will not start.
Reactor building pressure is now positive and continues to rise. What is a potential consequence if this situation continues?
..
a.
Damage to reactor building ventilation isolation dampers, b.
An uncontrolled, unmonitored release through SBGT due to forced air flow.
c.
Damage to the reactor building Kaman radiation monitors.
d.
.' An uncontrolled, unmonitored release from the reactor building.
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QUESTION: 029 (1.00)
What are the power supplies to the Alternate Rod Insertion (ARI) solenoids?
a.
RPS, Channels A and B
'
b.
Instrument AC, Divis;ons 1 and 2 c.
24 VDC, Divisions 1 and 2
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d.
125 VDC, Divisions 1'and 2
.
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QUESTION: 030'-(1.00)
Which one of the following correctly describes the condition (s) which will result in alarm 1C05A D-6, ROD DRIFT, actuating for:
1)
The Selected Rod?
and 2)
A Non-Selected Rod?
a.
1)
No even-numbered reed switch 'letected.
l 2)
Not at an even-numbered position OR at an odd-numbered position.
b.
1)
Odd-numbered notch position with no motion demanded.
2)
Not at an even-numbered position OR at an odd-numbered position.
c.
1)
No even-numbered reed switch detected.
2)
No rod is driving AND an odd-numbered reed switch detected.
d.'
1)
Odd-numbered notch position with no motion demanded.
l.
2)
No rod is driving AND an odd-numbered reed switch detected, i
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- QUESTION: 031 (1.00)'
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The plant was operating at power with both Recire Pumps at 60% speed when a feedwater problems results in both pumps running back to 45% Pump Speed (P). Operators stabilize the
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plant at a lower power and take no further action with the Recirc MG Set Speed Controls.
1)-
Which of the following CORRECTLY describes the response of the Recirc MG
. Speed Control Speed Demand (S) signals?
and-i 2)
What is the consequence of depressing the 45% RUNBACK SPEED LIMITER RESET pushbutton in this situation?
,
a.
1)
Both controllers will automatically go to 45% Speed Demand (S).
'
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2)-
The Runback will reset and Recirc Pump speed will remain stable.
b.
1)
~ Both controllers will automatically go to 45% Speed Demand (S)..
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2).
The Runback will NOT reset due to an interlock which requires the Scoop j
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Tube to be locked first.
. c. -
1)
Both controllers will remain at 60% Speed Demand (S).
'
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The Runback will reset and Recirc Pump speed will ramp up to 60%.
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1)
Both controllers will remain at 60% Speed Demand (S).
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The Runback will NOT reset due to an interlock which requires the Speed Demand (S) to be adjusted to less than 45% first.
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x SENIOR REACTOR OPERATOR Page 25 QUESTION: 032 (1.00).
The plant has just entered Mode 4. All safety related equipment is operable. The RHR System
.
is aligned as follows:
The B Loop of RHR is in the Shutdown Cooling Mode.
-
. The'A RHR pump is running in the Torus Cooling Mode.
.
At this point a Loss of Coolant accident results in a LPCI initiation on low RPV level. The amber
' light is ON above the B LOOP SELECTED RHR mimic label. Assuming NO OPERATOR
,
ACTION, which RHR pumps will automatically begin injecting into the RPV7 a.
None b.
' A and C RHR pumps c.
B and D RHR pumps
. 4 d. -
A, B, C, and D RHR Pumps QUESTION: 033 (1.00)-
1Which Torus level corresponds to the HPCI Turbina exhaust elevation?
a.
' 7.1 ft.'
t
- b. '
6.0 ft. '
c.
5.8 ft..
d.
4.5 ft.
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i QUESTION: 034 (1.00)
The plant was operating normally with the "A" Core Spray pump running for periodic test when a small break LOCA occurred inside the drywell, raising drywell pressure above the Core Spray initiation setpoint. Which one of the following CORRECTLY describes the response of the following "A" Core Spray valves to this event?
)
Test Bypass valve, MO-2112 (which is OPEN at the start of the accident.)
-
Min Flow Bypass valve, MO-2104 (which is CLOSED at the start of the accident.)
-
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Inboard inject valve MO-2117 a.
The TEST BYPASS will CLOSE.
The MIN FLOW BYPASS will OPEN.
When RPV pressure drops to <450 psig, the INBOARD lNJECT will AUTOMATICALLY OPEN. When injection to the RPV begins, the MIN FLOW BYPASS will CLOSE.
b.
The TEST BYPASS will CLOSE.
The MIN FLOW BYPASS will OPEN.
When RPV pressure drops to <450 psig, the INBOARD INJECT must be MANUALLY OPENED. When injection to the RPV begins, the MIN FLOW BYPASS will CLOSE.
c.
The TEST BYPASS REMAINS OPEN.
The MIN FLOW BYPASS REMAINS CLOSED.
When RPV pressure drops to <450 psig, the TEST BYPASS will CLOSE and the INBOARD INJECT will AUT OMATICALLY OPEN.
d.
The TEST BYPASS will CLOSE.
The MIN FLOW BYPASS REMAINS CLOSED.
The INBOARD INJECT valve will AUTOMATICALLY OPEN on the initiation signal and injection to the RPV begins when RPV pressure drops to <450 psi [:.
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SENIOR REACTOR OPERATOR -
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. QUESTION: 035 ~ (100).
An ATWS transient occurs and boron must be injected with the Standby Liquid Control System (SBLC). Which ONE of the following describes the effect of a SUCCESSFUL INITIATION of SBLC on these indications:
1)
' Squib Valve Ret.dy (Continuity) lights l
2)
Alarm.1C05A F 3, SBLC SQUlB VALVE CONTINUITY LOSS 3)
Pump discharge pressure a.
1)
llluminate.
2)
Actuates.
3).
<1350 psig.
b.
1)
Extinguish.
2)
. Actuates.
3)
<1350 psig.-
c.
- 1).
Illuminate.
2)
Does NOT actuate.
,
3)
>1350 psig.-
d.
1)
' Extinguish.
2)
Does NOT actuate.
3)'
' >1350 psig.
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- SENIOR REACTOR OPERATOR Page 28 QUESTION: 036 (1.00)
A reactor scram cannot be reset for 10 seconds after a scram. Which of the following is the reason for this delay?
To allow time...
a.
for all of the centrol rods to fully insert.
b.
to initiate the Alternate Rod Insertion system.
c.
for the reactor water level to stabilize above the scram setpoint.
d.
for the Scram Discharge Volume vent and drain valves to fully close before reopening.
QUESTION: 037 (1.00)
A reactor startup is in progress. The Mode Switch is in the START & HOT STBY position. No SRMs are bypassed. The SRM detectors are PARTIALLY WITHDRAWN. Which one of the.
following sets of conditions will then result in a rod withdrawal block?
a.
IRMs on range 1. All SRMs reading approximately 120 cps, b.
IRMs on range 2. SRM "A" reads approximately 90 cps, all other SRMs reading approximately 150 cps.
c.
IRMs on range 3. All SRMs reading approximately 90 cps.
d.
IRMs on range 4. SRM "A" reads approximately 90 cps, all other SRMs reading approximately 120 cps.
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. QUESTION: 038 (1.00)
i-Following startup, power is at 55% and rising as the crew brings the plant to full load. Just as the operator is about to withdraw the selected control rod, APRM "A" fails, indicating a constant
{
10% power. Which one of the following describes the effect on RBM "A"?
a.
RBM "A" will NOT enforce rod blocks until APRM "A" is bypassed, at which time RBM "A" will use APRM "E" as it's reference.
'
b.
RBM "A" will enforce rod blocks until APRM "A"is bypassed, at which time REM
"A" will use APRM "F" as it's reference.
,
l c.
RBM "A" will NOT enforce rod blocks until APRM "A" Mode Switch is moved out l
of OPERATE, at which time RBM "A" will use APRM "E" as it's reference.
d.
RBM "A" will enforce rod blocks until APRM "A" Mode Switch is moved out of OPERATE, at which time RBM "A" will use APRM "F" as it's reference.
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QUESTION: 039 (1.00)
The Reference Leg Backfill system has been out of service for an extended period of time when a plant transient results in a reactor scram and rapid depressurization of the RPV. Assume that non-condensable gasses will be released in the reference leg of the B GEMAC level instrumentation. How will B GEMAC level INDICATION be affected?
a.
Indicated level will read HIGHER than actual due to a decrease in the sensed differential pressure between the reference and variable legs.
b.
Indicated level will read HIGHER than actual due to an increase in the sensed differential pressure between the reference and variable legs.
c.
Indicated level will read LOWER than actual due to a decrease in the sensed differential pressure between the reference and variable legs.
d.
Indicated level will read LOWER than actual due to an increase in the sensed differential pressure between the reference and variable legs.
QUESTION: 040 (1.00)
What is the power supply to the RCIC Inboard Steam Line Isolation valve, MO-2400?
a.
480 VAC, Bus 1842 b.
480 VAC, Bus 1814 c.
250 VDC, Bus 1D41 d.
125 VDC, Bus 1D14
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QUESTION: 041 (1.00)
l The plant was at full power when a leak developed inside the drywell. Allisolations and automatic actions occurred as expected, but the operators fail to re-open CV-4371 A, DW AND TORUS DISCHARGE ISOLATION, as directed by procedure. As plant conditions continue to degrade, how could future mitigating actions be imoacted by this mistake?
The SRVs...
a.
may not open in response to a manual signal, but they should still respond to an ADS initiation.
b.
should still open in response to an RPV high pressure condition or a manual signal, but may not an open for an ADS initiation.
c.
may fail to open as needed for manual RPV pressure control or for initiation of ADS.
d.
should still open in response to manual signal, but may not open for initiation of ADS and or for an RPV high pressure conditio E
SENIOR REACTOR OPERATOR Page 32
l QUESTION: 042 (1.00)
l Operators are preparing for a plant startup after a forced outage. The Drywell remained inerted l
because there was no need to enter Primary containment. Given the following readings on the Liquid Nitrogen Storage Tank level and the Containment Atmosphere Dilution (CAD) nitrogen inventory, which action, if any, will be necessary for startup?
Liquid Nitrogen Storage Tank level 180 inches
-
CAD Bottle Pressure 1500 psig
-
CAD Bottle Temperature 80*F
-
Inventories are satisfactory; no further action is necessary for startup.
a.
b.
Order more liquid Nitrogen.
c.
Vent the Liquid Nitrogen Storage Tank.
d.
Charge the CAD Nitrogen supply tanks.
.
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- QUESTION: 043. (1.00)
The following plant conditions exist:
J
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. A plant startup is in progress.
Condenser high backpressure bypass switches are in the BYPASS position.
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' Condenser backpressure is 20 inches Hg Abs.
.
MSIVs are open.~
-
Reactor pressure is 875 psig.
-
The Mode Switch is in the START & HOT STBY position.
-
If the following actions were to occur, which one would cause a Group 1 Isolation?
!
a.
Lowering EHC Pressure Set to 840 psig, b.
Jacking open a Turbine Bypass Valve.
c.
- Placing the Mode Switch in RUN.
d.
Opening the' Main Condenser Vacuum Breakers.
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l QUESTIONi 044 (1.00).
'A Safety R li f V la ve (SRV) tailpipe vacuum breaker has failed in the OPEN position during ee l
SRV operation. Which of the following will result?
Steam will' discharge from the tailpipe into the Drywell each time the SRV is a.
opened.
b.
Steam will discharge from the tailpipe into the Torus air space each time the SRV i
is opened.
c;
. Water from the Torus will be drawn up into the SRV tailpipe when the SRV i:
closes.
'd.
- Steam will bypass the T-quencher and discharge directly from the tailpipe into the
,
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Page 34 QUESTION: 045 (1.00)
The plant.was operating at 90% power when the Stator Cooling Water TCV failed, bypassing the heat exchanger. Using the attached EHC Electronics schematic, identify the CORRECT point at which this failure initiates action by the Turbine Control System.
-This failure initiates action at...
a.
Point A.
b.
Point B.
c.
Point C.
d.
Point D.'
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l SENIOR REACTOR OPERATOR Page 35 OUESTION: 046 (1.00)
The plant is in normal operation at 60% power after a startup. The 1C05 operator reports the following:
-
.The B Feed pump flow is higher than A Feed pump flow The B Feed pump motor is also drawing 50 more amps than A Feed pump.
-
I Which of the following is the reason for these indications?
a.
The voltages of the 4KV Non-Essential busses are not properly matched.
b.
_ The bias settings of the A and B Feed Reg Valve Controllers are not properly matched.
c.
.. The Setpoint (S) values of the A and B Feed Reg Valve Controllers are not properly matched, d.
There was too much deviation between Controller Output (P) values of the A and B Feed Reg Valve Controllers when the Master Feed Reg Valve Controller was l
placed in auto.
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i QUESTION: 047 (1.00)
Which one of the following CORRECTLY describes the relationship between HPCI and SBGT?
a.
The HPCI barometric condenser vacuum pump exhausts directly to the stack, where any release is monitored. At least one OG STACK EXH FAN, 1V-EF-18A[B), must be on when HPCI is running.
b.
The HPCI barometric condenser vacuum pump exhausts directly to the stack, i
~ where any release is monitored. The OG STACK EXH FAN,1V-EF-18A[B], can be off when HPCI is running.
c.
The HPCI barometric condenser vacuum pump exhausts through the SBGT l
trains, where gases are treated before leaving the plant via the stack. At least l
one SBGT EXHAUST FAN,1V EF-15A[B), must be on when HPCI is running.
d.
The HPCI barometric condenser vacuum pump exhausts through the SBGT trains, where gases are treated before leaving the plant via the stack. The SBGT
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EXHAUST FAN,1V-EF-15A[B], can be off when HPCI is running.
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p-i SENIOR REACTOR OPERATOR Page 37 QUESTION: 048 (1.00)
"A" SBDG was operating in parallel with the Startup transformer for surveillance testing, carrying a load of 2500 KW. A lightning strike occurred that tripped OPEN the Startup and Standby transformer incoming breakers (J, K, and M). Bus 1A3 does not have a Lockout. Which of the following CORRECTLY describes the response of the "A" SBDG and its output breaker?
a.
The Output Breaker will trip open due to a signal from the Degraded Voltage logic. Then, if the SBDG exceeds 1044.9 RPM, the SBDG will trip.
b.
The Output Breaker will trip open due to a 1 A3 Bus Undervoltage signal. Then, if the SBDG exceeds 1044.9 RPM, the SBDG will trip.
c.
If the SBDG exceeds 1044,9 RPM, the SBDG will trip. Then the Output Breaker will open due to a signal from the Shutdown Relay.
d.
If the SBDG exceeds 1044.9 RPM, the SBDG will trip. Then the Output Breaker will open due to a 1A3 Bus Underfrequency signal.
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Page 38 l
QUESTION: 049 (1.00)
l A large i reak LOCA has occurred, and Core Spray has initiated and injected into the reactor vessel. bnich one of the following describes the use of the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03 to shutdown the system when no longer needed for
'
injection?
- a.
After all initiation signals have cleared, the initiation signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03.
Then the valves may be repositioned and the pump secured.
. b.
. After all initiation signals have cleared, the initiation signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03.
i Then the pump will stop and the valves automatically reposition.
c.
At any time restoring the Core Spray system is desired, the initiaticn signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03. Then the valves may be repositioned and the pump secured.
d.
At any time restoring the Core Spray system is desired, the initiation signal is reset by depressing the A(B) CORE SPRAY INITIATION SEAL-IN reset pushbutton on panel 1C03. Then the pump will stop and the valves automatically reposition.
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QUESTION: 050 (1.00)
The BOP operator is performing a slow manual start of the 1G31 diesel generator from the control room, for post maintenance testing, in accordance with the Operating instruction (01).
He has set the prelube pump timer for one (1) minute and depressed the prelube pump start pushbutton. Just as the operator is about to start the Diesel, a problem develops on another system and the OSS suspends the SBDG testing. The problem is resolved in 5 minutes and the OSS authorizes the BOP operator to resume his job on the SBDG. The next step is to start the SBDG. May the operator proceed with the next step of the Ol? (YES or NO) If NO, identify the CORRECT reason.
a.
.YES b.
NO, the operator must back up a few steps and re-perform the prelube steps.
Then the SBDG can be started.
c.
NO, the pre-lube pump operation described will activate an annunciator on local Panel 1C91 which must be reset before the SBDG will start.
. d.
NO, the operator must direct the in-plant operator to trip the SBDG and roll the engine over with air before resuming the slow manual start procedure.
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i SENIOR REACTOR OPERATOR Page 40 QUESTION: 051 (1.00)
i Which of the following signals is used to develop the Total Core Flow indication on panel 1C057 a.
Calibrated Jet Pump #1 Flow (from transmitter FT-4518)
b.
Non-Calibrated Jet Pump #10 Flow (from transmitter FT-4503)
c.
B Recire Pump Discharge Flow (from transmitter FT-4632A)
d.
B Recirc Pump Differential Pressure (from transmitter PDT-4624)
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t QUESTION: 052 (1.00)
The B Loop of the RHR system is operating normally in the Shutdown Cooling mode. Which of the following CORRECTLY describes how the B Loop valve positions are adjusted to control
!!owrate and cooldown rate?
'
MO-1904 is the B OUTBD INJECT ISOL valve
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MO-1939 is the B HEAT EXCH INLET THROTTLE valve
-
MO-1940 is the B HEAT EXCH BYPASS valve.
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a.
MO-1904 is adjusted to control BOTH flowrate and cooldown rate.
b.
MO-1904 is adjusted to control flowrate.
MO-1939 and MO-1940 are adjusted to control cooldown rate.
c.
MO-1904 is adjusted to control cooldown rate.
MO-1939 and MO-1940 are adjusted to control flowrate.
d.
'MO-1939 and MO-1940 are adjusted to control BOTH flowrate and cooldown rate.
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SENIOR REACTOR OPERATOR Page 42 QUESTION: 053. (1.00)
A non-selected control rod at position 36 is uncoupled. The RO will be withdrawing this rod fully.
' Which of the following CORRECTLY describes when the uncoupled control rod can be identified using RPIS?
'a.
As soon as the control rod is selected.
' b.
.When the selected control rod is withdrawn from position 36 to position 38.
c.
When the RMCS Timer times out with the selected control rod at position 48.
d.
When the selected control rod is withdrawn past position 48 independent of the RMCS Timer.
QUESTION: 054 (1.00)
Which of the following CORRECTLY lists the power supplies to the AC and DC MSIV actuator solenoids?
a.
AC Instrument AC Divisions 1 and 2 DC 24 VDC Divisions 1 and 2 I
b.
AC Instrument AC Divisions 1 and 2 DC 125 VDC Divisions 1 and 2 c.
AC - RPS Channels A and B DC 24 VDC Divisions 1 and 2 d.
AC RPS Channels A and B DC 125 VDC Divisions 1 and 2 l
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- QUESTION: 055. (1.00)-
The plant is at 100% power but is experiencing problems with Main Generator auxiliary systems:
Generator Megawatts:
560 MWE j
-
Generator Megavars:
-
Generator Hydrogen pressure:
30 psig, si ible
-
-
Generator Hydrogen purityd:
90%, lowering Which of the following is CORRECT concerning continued operation of the Main Generator?
-Operators must a.
. lower generator voltage, b.
raise generator voltage.
c.
reduce generator load to less than 8000 amps.
d.
secure the main generator.
QUESTlON: 056 (1.00)
A complete loss of Uninterruptible AC power occurred with the plant at 100% power. "A" GEMAC LI-4559 was controlling'RPV level in automatic on the master controller. Assuming NO OPERATOR ACTION, which one of the following describes the INITIAL EFFECT on RPV water level and correctly explains WHY this response occurs?
,
a.
RPV level LOWERS due to shrink caused by the LOSS of EHC pressure control.
b.
RPV level LOWERS due to both Feed Pump Recirc valves failing OPEN.
c.
RPV level RISES due to the master feedwater controller responding to "A'
GEMAC failing DOWNSCALE..
d.
'RPV level RISES due to both Recirc pumps running back with the Feedwater
. Reg valves LOCKE SENIOR REACTOR OPERATOR Page 44
' QUESTION: 057 (1.00)
Construction Transformer T4 supplies power to most of the DAEC outbuildirgs, including the Badging Center, Data Acquisition Center and the Training Center. Which of the following CORRECTLY describes how the primary side of T4 normally receives power from offsite?
The primary side of T4 is normally supplied by
a.
the 36KV bus from the Shellsburg and 6th Street line, b.
the 36KV bus from transformer T3 (161/36KV).
c.
The 4 KV bus from LLRPSF transformer 1XR1 (36/4KV).
,
d.
The 4 KV bus from the Substation Power Transformer (161/4KV).
i QUESTION: 058 (1.00)
Per IPO!-2, "Startup", which of the following RPV pressures is the minimum necessary to provide sufficient steam flow to reset the Offgas isolation on low steam flow to the Jet Compressor?
a.
300 psig -
b.
400 psig c.
500 psig d.
600 psig
' SENIOR REACTOR OPERATOR Page 45 QUESTION: 059 (1.00)
A fire begins in the Main Generator Exciter while at power. An operator AT THE SCENE reports open flames inside the Exciter housing. Identify whether each of the following Exciter CO2 Fire Suppression System actions REQUIRES OPERATOR ACTION or OCCURS AUTOMATICALLY?
1)
Start of CO2 injection 2)
Exciter ventilation shutdown a.
1)
REQUIRES OPERATOR ACTION 2)
REQUIRES OPERATOR ACTION b.
- 1)
REQUIRES OPERATOR ACTION 2)
OCCURS AUTOMATICALLY c.
1).
OCCURS AUTOMATICALLY 2)
REQUIRES OPERATOR ACTION d.
-1)
OCCURS AUTOMATICALLY 2)
OCCURS AUTOMATICALLY
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QUESTION: 060 (1.00)
A large break Loss of Coolant Acciden' has occurred during power operations. The following t
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j-plant conditions exist:
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'. RPV level is 180lf, being maintained with' Core Spray.
-
RPV pressure is 20 psig, slowly lowering.
--
All electrical busses have remained energized.~
--
Drywell temperature and pressure are elevated enough to require Containment
-
sprays.
The RHR Suction strainers are completely blocked.
-
,--
Operators have been unable to open RHRSW TO RHR CROSSTIE valve, MO-1942.
All other equipment is operating as designed.
-
L is any other system available to spray the containment? If YES, CORRECTLY identify that
'
system.
a.
YES; the Condensate Service Water system.
I b. -
YES; the Well Water system.
c.
YES; the Fire System.
. d.
_There are NO systems available to spray the containment.
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- QUESTION: 061 (1.00)
l Due to a combination of severe cold weather and Auxiliary Boiler malfunctions, operators are L
having difficulty' maintaining the temperature of the Control Building. General area temperatures in the Control Building are 65'F and lowering. Which of the following equipment must be verified for operability if the Control Building temperature continues to lower?
a.
Station Batteries
. b.
Control Room Chillers.
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'c.
Standby Filter Units -
d.
Fire System
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l SENIOR REACTOR OPERATOR Page 47 l
QUESTION: 062. (1.00)
Entering the control room, you note the following regarding the instrument air system:
Instrument Air Header Pressure: 95 psig
-
Air Compressor Lights on 1C07:
-
,
Based on these indications, which one of the following CORRECTLY describes the status of 1K90A, B and C7 i
r a.
,1K90A is the Lag-lag compressor; it has not received a start signal.1K90B &
1K90C are the Lead & Lag compressors; they are running to restore instrument air pressure.
l b.
1K90A is the Lead compressor; running to restore instrument air pressure.
i 1K90B & 1K90C are the Lag & Lag-Lag compressors; neither one has started
,
yet.
c.
1K90A is the Lag-lag cornpressor; running to restore instrument air pressure.
1K908 & 1K90C are the Lead & Lag compressors; neither one has started yet.
'd.
1K90A is the Lead compressor; is not running.1K908 & 1K90C are the Lag &
,
Lag-Lag compressors; they are running to restore instrument air pressure.
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L SENIOR REACTOR OPERATOR Page 48 QUESTlONi 063 (1.00)
Which of the following CORRECTLY describes a di'ference between ESW and RHRSW operation when these systems are being used for an altemate RPV injection source?
' a.
ESW injects through the "B" side of RHR and RHRSW injects through the "A" -
side of RHR.
b.
The Main Condenser outlet valves, MO4208 and MO4209, must be closed for ESW injection, but not for RHRSW injection, c.
The RHRSW Heat Exchanger Discharge valves, MO2046 and MO1947, must be open for ESW injection, bijt closed for full RHRSW injection.
d.
ESW injection flow is controlled by the RHRSW Heat Exchanger discharge valve and RHRSW injection flow is controlled by the LPCI Inject Valves.
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QUESTION: 064 (1.00)
!-
The plant is operating at full power with a TIP trace in progress. The system is being operated j
m the Automatic mode.' Status of the TIPS is as follows:
l l
Channel A:
Inserting to position 2 (Coordinate 16-25)
--
l Channel C:
Withdrawing (tracilg) from position 2 (Coordinate 16-17)
-
l At this point a transient occurs that results in an automatic reactor scram on low water level.
Which one of the following correctly describes the response of the TIP drives to this event?
.,
!
' a.
Channel "A" continues insertion to the top of core, then withdraws to the in shield position without tracing. Channel "C" continues withdrawing to the in shield position. The ball valves automatically close when associated detectors are at the in shield position.
b.
Both drives switch to manual reverse and withdraw from the core. The ball l
valves automatically close when associated detectors are at the in shield L
position.
c.
Channel"A" continues insertion to the top of core, then withdraws to the in shield position without tracing. Channel"C" continues withdrawing to the in shield position. The operator then closes both ball valves by placing the MAN VALVE CONTROL to CLOSE.
l:
d.
Neither drive is affected until level drops to 119.5"; at that time both will switch to manual reverse and withdraw from the core. The operator then closes both ball valves by placing the MAN VALVE CONTROL to CLOSE.
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SENIOR REACTOR OPERATOR Page 50 l
QUESTION: 065 (1.00)
Tha plant is operating at full power. If a leak were to begin past the inboard Fuel Pool gate,
wculd there be a LEAK DETECTION ALARM or must the Control Room identify the problem through an INDIRECT METHOD? If LEAK DETECTION ALARM, identify how the Control Room is informed. If INDIRECT METHOD, identify how the Control Room would know of this problem.
'
a.
LEAK DETECTION ALARM - This condition alarms on the Fuel Pool Cooling Panel 1C65/1C66 and there is an associated panel trouble alarm on Control Room Panel 1C04.
b.
LEAK DETECTION ALARM - This condition alarms on the Fuel Pool Filter /Demin Control Panel 1C136 and there is an associated panel trouble alarm on Radwaste Panel 1C84. The Radwaste Operator must call the Control Room.
c.
INDIRECT METHOD - A low Fuel Pool level condition is alarmed in the Control Room on Panel 1C04 and operators must investigate further.
d.
INDIRECT METHOD - A Reactor Building Equipment Drain Sump high leakage condition is alarmed on Radwaste Panel 1C84. The Radwaste Operator must call the Control Room and operators must investigate further.
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' SENIOR REACTOR OPERATOR Page 51 QUESTION: 066 (1.00)
' At which point 'in the following Core Alteration scenario would activation of the ROD OUT BLOCK annunciator first occur? (1C05B, A-6)
Scenario:
The Mode Switch is in REFUEL.
-
All control rods are fully inserted.
-
One control Rod is selected.
-
.
There are no other Rod Blocks in effect.
-
The only hoist in use is the Main Grapple Hoist.
-
A fuel assembly is grappled and raised to Full-Up in the Fuel Pool.
-
The Refuel Platform is driven over the core.
-
The fuel assembly is lowered into its assigned location.
-
The 1C05 operator attempts to withdraw the selected control rod.
-
' Rod Block first occurs when...
a.
the loaded Main Grapple Hoist reaches Full-Up in the Fuel Pool.
b.
the Refuel Platform is driven over the core, i
c.
the Main Grapple Hoist starts to lower the fuel assembly, d.
the 1C05 operator attempts to withdraw the selected control rod.
QUESTIONi 067- (1.00).
Operators are starting up the Turbine Building HVAC System. The LEAD Turbine Building Exhaust Fan,1V-EF-21A, has been selected. Now the handswitches for all three Exhaust Fans must be placed in position for the desired speed of operation. At what plant location is this performed?
'
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a.
In the Turbine Building, on the Northwest corner of the Operating Deck.
b.
In the Turbine Building, on the Southwest corner of the Operating Deck.
,
c.
In the Reactor Building, on the 3rd Floor (812 ele.)in the Southeast hallway.
d.
in the Control Room at panel 1C23.
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SENIOR REACTOR OPERATOR Page 52
'
QUESTION: 068 (1.00)
The plant is in COLD SHUTDOWN for a refueling outage. As normal, approximately 200 of the-1000 annunciators in the Control Room are illuminated. Which of the following techniques is used to help operators more easily identify the true abnormal situations?
a.
Install Normal Outage Annunciator lenses over long-term alarms on any out-of-service equipment. No recording is necessary.
b.
Install Degraded Control Room Instrumentation CAUTION stickers over alarms on any out-of-service equipment. Record installation in the Degraded Instrument Log.
c.
Remove the light bulbs for alarms on disabled equipment that is not safety
)
related. Record removalin the Outage Annunciator Log.
d.
Remove the annunciator panel cards for alarms on disabled equipment that is not safety related. Record removalin the Outage Temporary Modification Log.
QUESTION: 069 (1.00)
,
'
i Which of the following is a design basis of HPCl?
I
a.
Must be able to function Independent of on-site power sources.
b.
Assures that the reactor core is adequately cooled to limit fuel clad temperature
!
in the event of a large break in the reactor coolant system.
c.
Assures that the reactor core is adequately cooled to limit primary containment pressure in the event of a small break in the reactor coolant system.
d.
Make up water to the reactor vessel in the event of a loss of coolant situation that does not result in rapid RPV depressurizatio SENIOR REACTOR OPERATOR -
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-QUESTION: 070 (1.00)
A normal plant startup and heatup is in progress with the MSIVs open. Reactor pressure has been adjusted to 180 psig. The STA reports that the Heatup Rate is 75'F/Hr and rising, so operators suspend control rod withdrawal. Which one of the following methods should be used to lower the Heatup Rate?
a.
Lower the EHC Pressure Set setpoint.
b.'
- Raise the EHC Pressure Set setpoint.
c.
Open Main Steam Line Drains.
d.
Close Main Steam Line Drains.
- QUESTION: 071 (1.00)-
,
Core alterations are in progress with operators preparing to lift a fuel assembly from the core.
Which of the following conditions will automatically stop the upward movement of the Main Grapple Hoist (Mast) if it were to occur while lifting a fuel assembly?
Activation of the " Slack Cable" light'.
a..
b.
Activation of the " Grapple Full Down" light.
c.
Loss of the " Grapple Closed" light.
. d.
Loss of the "Holst Loaded" light.
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SENIUR REACTOR OPERATOR Page 54
QUESTION: 072 (1.00)
An area of the Radwaste Building is set aside to store some highly radioactive material. It is determined that the entrance into this area could result in personnel receiving 7 Rem in one hour 30 centimeters from the radiation source. Which of the following is the correct posting for this area?.
a.
Double Locked High Radiation Area d.
Very High Radiation Area QUESTION: 073 (1.00)
During recovery from a severe ATWS transient, the crew hears a muffled explosion and the 1C03 operator notices his wide range Drywell Pressure meters coming off their upper stops.
The Containment remains intact. Assume that actual Drywell pressure peaked at 120 psig.
Can the peak Drywell pressure be determined from the Control Room? If so, which control room instrument (s) can be used to identify that pressure?
'
From the Control Room, the peak Drywell pressure..
a.
CANNOT be determined.
b.
CAN be determined. Use SPDS Containment Conditions screen which plots Drywell pressure.
c.
CAN be determined. Use 1C09 Drywell Pressure recorders, PR-4398A and/or B.
d.
CAN be determined. Use 1C29 Drywell Pressure recorders, PR-4384A and/or PR-4385 I SENIOR REACTOR OPERATOR Page 55 a
QUESTION: 074 (1.00)
,
A large break Loss of Coo l ant Accident is in progress. The OSS has directed you, the Panel 1C03 operator, to open four ADS SRVs and maximize injection. Four ADS SRVs have opened but, even with the RPV depressurized and all available ECCS pumps injecting, RPV level cannot I
be raised above +15 inches. At this point the OSS directs you to open the Inboard Main Steam l
Line Drain Valve, MO-4423.
'
]
Which of the following is the reason for opening MO-4423 in this situation?
]
The OSS is anticipating the need a.
to drain the steam lines.
b.
to establish a coolant flowpath for RPV Flooding.
c.
to vent the RPV during containment flooding per the Severe Accident Guidelines (SAGS).
d.
to keep the RPV depressurized so low pressure systems can inject for Alternate Level Control.
QUESTION: 075 (1.00)
(Necessary attachments from AOP 302.2 " Loss of Alarm Panel Power" are provided as an exam handout.) During Panel Checks, it is discovered that Annunciator Panel 1C07A does not
-
respond and appears deenergized. Annunciator checks on all other annunciator parats are satisfactory. Which power supply or fuses is/are the MOST LIKELY cause of this pr a:.;17.
a.
Tripped breaker 1D23, Ckt.10 b.
Blown fuse (s) Fu10A+ and/or Fu10A-c.
. Blown fuse (s) FuA and/or F27A d.
Blown fuse (s) F2-6ASB and/or F1-6ASB
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SENIOR REACTOR OPERATOR Page 56 QUESTION: 076 (1.00)
. A Loss of Coolant accident has occurred while operating at power. Drywell pressure is 4 psig and steadily rising. At Panel 1C03, the operatoris preparing to spray the Torus.
1)
in which situation would the Primary Containment be CLOSER TO " Chugging" conditions:
Spraying the Torus now AT 4 PSIG or later when APPROACHING 11 PSIG?
And 2)
What is the CORRECT reason for the answer to Part 1 of this question?
a.
1)
AT 4 PSIG
.2)
There would be fewer non-condensible gasses in the Drywell atmosphere AT 4 PSIG.
b.
1)
AT 4 PSIG 2)There would be fewer non-condensible gasses in the Torus air space AT 4 PSIG.
c.
1)
APPROACHING 11 PSIG 2)
There would be fewer non-condensible gasses in the Drywell atmosphere when approaching 11 psig.
d.
1)
APPROACHING 11 PSIG 2)-
There would be fewer non-condensible gasses in the Torus air space when approaching 11 psig.
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SENIOR REACTOR OPERATOR Page 57 (
QUESTION: 077 (1.00)-
An operating crew entered RPV/F and are injecting into the RPV with RHR and one condensate
'
pump. All control rods are fully inserted. The following indications exist at 1C03:
ADS handswitches are in the OPEN position.
-
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The amber tailpipe pressure indicating lights are ON for:
-
- PSV 4402
- PSV 4405 j
- PSV 4406 j
'
Reactor pressure:
75 psig
-
Torus pressure:
1 psig
-
Were RPV/F actions successful?
a.
Yes, because at least three SRVs are open and reactor pressure is at least 50 psig greater than torus pressure.
b.
Yes, because at least one SRV is opan and sactor pressure is less than the discharge pressure of the low pressure injection sources.
c.
No, because all four ADS SRVs are required to be open with reactor pressure at least 50 psig greater than Drywell pres-sure.
d.
- No, because all four ADS SRVs should be open with reactor pressure approximately equal to condensate pump discharge pressure.
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SENIOR REACTOR OPERATOR Page 58
' QUESTlONi 078 (1.00)
' The plant is operating at full power with the Startup Transformer out of service when a severe disturbance occurs on the Mid America Power Pool grid. This causes a loss of offsite power
. and a reactor scram. ' Both Standby Diesel Generators also fail after a short while. Operators have used HPCI and RCIC to perform a plant cooldown. The plant conditions are as follows:
RPV Level 190 inches.
-
RPV pressure 400 psig.
-
Drywell Average Air Temperature 265'F and rising very slowly.
-
Drywell pressure > 2 psig.
-
Torus Average Water Temperature 162*F.
-
The System Dispatcher now calls the Control Room and reports that grid has been restored and stabilized at less than normal voltage. Operators at 1C08 report incoming voltage at approximately 3700 VAC.
1)
Would low pressure ECCS pumps operate at this voltage? (YES or NO)
and 2)
Do plant operators have the capability of reenergizing an Essential bus at this
.l grid voltage? (YES or NO)
a.
1)
YES 2)
YES.'
,
b.
1)
NO 2)
YES c.
1)
YES 2).
NO
,
d.
1)
NO
. 2)
-NO.
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l QUESTION: 079 (1.00)
l The reactor was operating at 100% power for several weeks. A major rupture in the Well Water
[
system has resulted in rising containment pressures and temperatures. The Well Water Header Supply Pressure indicator on Panel 1C23 is reading 10 psig. The reactor was manually scrammed when Drywell temperature rose to 150*F. On the scram, RPV level dropped below 170 inches TAF. Current plant conditions are as follows:
All Control Rods are fully inserted.
-
RPV level +190 inches TAF and steady.
-
MSIVs remain open.
--
Drywell pressure 4.5 psig. and rising 0.1 psig per minute.
-
Drywell temperature 250*F and rising 3*F per minute.-
-
.
Which of the following actions must be taken to alleviate the current containment problem?
a$
Vent the Drywellin accordance with 01573 and commence an air purge.
'
b.
Initiate Containment Atmosphere Dilution (CAD) injection.
'
c.
Shutdown the Recire Pumps, verify that Torus level is below 13.5 feet, and Spray the Drywell.
d.
Anticipate Emergency Depressurize through the Turbine Bypass Valves.
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Page 60 l
QUESTION: 080 (1.00)'-
The plant is operating at full power when operators smell smoke and then see open flames L
under Panel 1C03. Operators scram the reactor, sound the Fire Alarm, and send the BOP operator to activate the Fire Brigade. One operator performs the "as time permits" actions of
<
AOP-915. Another operator uses an extinguisher to suppress the open flames. The damaged equipment continues to smolder, making breathing difficult. At this point the OSS directs activation of the Remote Shutdown Panel,1C388. The Shift Manager, Shift Technical Advisor, one Reactor Operator, and both in-plant operators take the necessary equipment'and evacuate to 1C388. The OSS and one remaining Reactor Operator are qualified to wear Self Contained
Breathing. Apparatus (SCBA), which they don and remain in the Control Room until 1C388 is i'
fully activated. The Fire Brigade has not yet responded..
Are the personnel activities described in this postulated scenario in compliance with plant procedures? (YES or NO) If NO, identify the CORRECT reason why they are not in compliance.
,
a.
YES b.
NO, AOP 915 directs ALL personnel to evacuate in this situation.
' c.
NO, AOP 915 directs ALL personnel EXCEPT THE OSS to evacuate in this j
. situation.
.
d.
NO, ACP 1410.1, " Conduct of Operations", prohibits' staying in an atmosphere where SCBAs are necessary to remain.
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, i SENIOR REACTOR OPERATOR Page 61 QUESTION: 081 (1.00)
A reactor startup is in progress with RPV pressure at 600 psig. A "CRD ACCUMULATOR LO PRESSURE OR HI LEVEL" alarm was received on control rod 22-23, which is fully withdrawn.
Operators are responding by precharging this accumulator with nitrogen. The Charging Water to this HCU is valved out. At this point the running CRD pump trips on overcurrent and appears damaged. The alternate CRD pump cannot be started. Which of the following identifies the REQUIRED ACTION (s) and COMPLETION TIME (s) for this condition?
'
a.
Declare control rod 22-23 scram time " slow" or declare it inoperable. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
Declare control rod 22-23 scram time " slow" or declare it inoperable.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, c.
Restore charging header pressure to >940 psig.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
d.
Scram the reactor / place Mode Switch in SHUTDOWN. Immediately. Declare control rod 22-23 inoperable.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
QUESTION: 082 (1.00)
A loss of feedwater heating and attendant reactivity addition has resulted in fuel failure.
Compounding the situation, HPCI cannot be isolated and there are high temperatures and radiation levels in the HPCI area. Other plant parameters are:
All rods are fullin
-
-
RPV pressure:
800 psig, dropping
-
RPV level:
175" stable
-
Coolant activity:
310 mci / gram dose equivalent 1131 RB Vent Shaft Radiation:
15 mr/hr
-
-
RB KAMAN 5x10~2 mci /cc for 20 minutes
-
All Turbine Building HVAC fans have stopped.
What actions are appropriate?
a.
Restart turbine building ventilation exhaust fans.
b.
Restart main plant supply and exhaust fans.
c.
Verify SBGT running, then re-establish reactor building HVAC to maximize heat removal from HPCI.
d.
Secure the offgas stack fans (1V-EF-18A/B) until normal HVAC lineups cari be establishe. SENIOR REACTOR OPERATOR Page 62 QUESTION: 083 (1.00)
The reactor has been shutdown for 12 days. RPV level.is 200" and steady when shutdown cooling is lost. Reactor coolant temperature is 104*F at the beginning of the transient. Using
- the attached graphs, determine the approximate time it will take to reach boiling in the reactor.
, a.
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> b.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> c.
15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> d.
31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> QUESTION: 084 (1.00)
A small break LOCA has occurred and the operators are taking actions to control plant parameters. All systems and instrumentation are functioning as expected. The STA reports Process Computer Point A1112, a local torus water temperature indication, is reading 175'F.
Other plant parameters are as follows:
All rods are in.
-
RPV pressure:
850 psig, dropping slowly
--
RPV level:
105", rising slowly
-
Torus level:
11 feet, stable
-
Torus pressure:
12 psig, rising slowly
-
-.
Drywell temperature:
- 235'F, rising slowly
. HPCI and RCIC injecting for level control
-
~
Both RHR loops in torus cooling mode
-
' Select the CORRECT operator actions for these indications.
a.
Verify torus temperature on the front panel indication and proceed based on that indication.
b'.
Verify torus temperature using another local torus temperature computer point and proceed based on that indication.-
c.
Minimize further heat input to the torus by entering EOP ED and depressurizing the RPV..
d.
Minimize further heat input to the torus by tripping HPCI and RCIC until they are neede _
I SENIOR REACTOR OPERATOR T'aos 63 QUESTION: 085-(1.00)
You are on watch as the Fuel Handling Supervisor during core alterations. Work is in progress in the Drywell and Torus areas.: An event occurs that causes the water level in the refueling cavity to drop below the weir plate and lower uncontrollably.
Where should a grappled fuel assembly be placed in the following situations?
1)
_ A fuel assembly that has just been withdrawn from an in-core location.
.2)'
A fuel assembly that is being transferred to the Spent Fuel Pool and has just gone through the cattle chute.
a.
1)
Insert the assembly into the closest available in-core location.
2)
Insert the assembly into the closest available location in the spent fuel racks.
. b.
1)
Insert the assembly into the closest available in-core location.
2)
Insert the assembly into the spent fuel racks per the fuel moving plan.
c.
1)
Re-insert the assembly into the in-core location from which it came.
2).
Insert the assembly into the closest available location in the spent fuel racks.
d.
1)
Re-insert the assembly into the in-core location from which it came.
2)
Insert the assembly into the spent fuel racks per the fuel moving plan.
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SENIOR REACTOR OPERATOR Page 64 x
QUESTION: 086 (1.00)_
~
The plant is in a refueling outage:
The reactor cavity is flooded with the Fuel Pool gates removed.
-
The Refueling Bridge is out of commission, awaiting parts for the DC300
-
controller.
The Reactor Building Crane is being used to bring replacement fuel bundles uo to
-
the Refuel Floor. These are to replace the four bundles that were found to have fretting damage, during receipt inspection.
. Maintenance is being performed to repair a leak on the B Reactor Recirculation
-
Pump casing.
The pump suction, discharge, and discharge bypass valves, MO4602, MO4628,
-
and MO4630, respectively, are locked closed.
' The pump casing is open to atmosphere.
-
That is the only drywell work scheduled for today.
--
The south Drywell airlock has been removed and the north drywell equipment
-
hatch is open.
-
- The Mechanics need to open the Reactor Building Railroad Airlock to bring in new fuel boxes to be taken to the Refuel Floor.
1):
Can both sets Railroad Airlock doors be opened at the same time (Yes or No)?
2)
Choose the answer that gives the correct reason behind your response to part 1,
,
above.
j a.
1)
No --
.
.
,
2)
OPDRVs are in progress and Secondary Containment is required.
b.
1)
No 2):
Fuel Movement is in progress inside Secondary Containment. - Therefore
. Secondary Containment is required.
1)'
Yes c..
2)-
Secondary Containment is not required.
- d.
1).
Yes 2)
As long as the outer door to the LLRPSF is closed, Secondary Containment integrity is met.
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SENIOR REACTOR OPERATOR Page 65 QUESTION: 087 (1.00)
i Standby Liquid Control (SBLC) is being injected during an ATWS transient. The SBLC tank level is lowering. At which of the following level.s can it FIRST be considered that the Hot Shutdown Boron Weight has been injected? Hot Shutdown Boron Weight has been injected when the SBLC tank level has lowered to I
a.
45%
b.
36%.
c.
28 %
)
I d.
14%
QUESTION: 088 (1.00)
.
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The plant has experienced a severe transient complicated by containment PRESSURE i
SUPPRESSION PROBLEMS and a sustained LOSS OF RPS POWER. The following plant conditions exist:
All control rods are fully inserted.
-
RPV level is being maintained 170 inches - 211 inches.
--
-
Torus pressure is 51 psig and rising steadily.
-
Torus levelis 10.5 feet and stable.
-
Containment venting has NOT been established.
-
One train of SBGT is running satisfactorily.
-
Should Torus venting be performed using the Hard Pipe Vent, CV-43577 (YES or NO) If YES, which answer correctly describes one action necessary to proceed, with venting. If NO, which answer correctly explains why not?.
a.
YES; The 125 VDC fuses from the Hard Pipe Vent package must be installed.
b.
YES; Defeat 10 "Drywell/ Torus Vent and Purge Isolation Defeat" must be installed.
c.-
NO; Torus venting through the SBGT Train is preferable in this situation and should be attempted first, d.
NO; Torus pressure is still less than the burst pressure for the Hard Pipe Vent Rupture Disc, PSE-4357.
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i SENIOR REACTOR OPERATOR Page 66
)
.
I QUESTION: 089 (1.00)
Which of the following is defined as the " Minimum Steam Cooling RPV Water Level" for the
.
DAEC7
'
a.
O inches b.
-30 inches c.
-39 inches.
d.
-40 inches
' QUESTION: 090 (1.00)
j Which one of the following describes the DIRECT affect that a reactor vessel pressure signal of 1200 psig will have on the Reactor Recirculation system pumps and alternate rod insertion (ARI)
system?
The Recirc Pump...
a.
drive motor breaker will trip and the ARI solenoid valves will energize.
b. '
drive motor breaker will trip and the ARI solenoid valves will deenergize.
c.
RPT breakers will trip and the ARI solenoid will energize, d.
RPT breakers will trip and the ARI solenoid valves will deenergize.
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SENIOR REACTOR OPERATOR Page 67
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QUESTION: 091 (1.00)
l A plant shutdown is in progress for scheduled maintenance. All control rods are fully inserted and the cooldown has progressed to the point that the RPV Head Vent valves have been opened. There are no extra operators on shift, so the Balance of Plant ANSOE has been dispatched to the North-East Corner Room to venfy a tagout. At this point, a fire occurs in an Essential Switchgear Room, which causes the loss of Shutdown Cooling.
1)
is one of the two remaining NSOEs allowed to leave the Control Room to serve as Fire Brigade Leader? (ALLOWED or NOT ALLOWED)
AND 2)
Should the Shift Manager GO TO THE SCENE or REMAIN IN THE CONTROL ROOM?
a.
1) ALLOWED,2) GO TO THE SCENE b.
1) ALLOWED,2) REMAIN IN THE CONTROL ROOM
!
c.
1) NOT ALLOWED,2) GO TO THE SCENE d.
1) NOT ALLOWED,2) REMAIN IN THE CONTROL ROOM
.
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SENIOR REACTOR OPERATOR Page 68
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QUESTION: 092 (100)
.
Theiollowing conditions exist:
Reactor waterlevel:
186"
-
Reactor building vent shaft radiation level: 12 mr/hr
--
--
Fuel pool exhaust RIS.4131A:
8 mr/hr
' RCIC room ambient temperature:
168'F
-
RCIC room area waterlevel:
4 inches
-
Steam is observed in the RCIC room.
-
All other plant systems are operating normally. Which one of the following outlines the appropriate actions based on the above conditions?
' a.
Enter EOP-3, commence a normal reactor shutdown, isolate RCIC l
b.
. Enter EOP-3, verify Reactor Building Vent isolation, isolate RCIC c.
Enter EOP-1, scram the reactor, establish level control with a motor driven system
'
d.
Enter EOP-1, verify Reactor Building Vent Isolation, commence a normal reactor
~ shutdown
.
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SENIOR REACTOR OPERATOR Page 69 i
QUESTION: 093 (1.00)
Operators have been responding to problems in the Offgas system. The following conditions have been observed:
High range Offgas flow peaked at 100 scfm and is now stable at 50 scfm.
-
The in-service Recombiner temperatures are at 600*F and have been rising
.
slowly throughout the transient..
Offgas pressure is at 20 in. HgA and steady.'
-
Both hydrogen analyzers are reading stable at 4.5%.
-
What, if any, actions must be taken, in response to the above listed situation?
a.
There are no actions to be taken at this time, b.
Increase steam pressure to the operating SJAE to about 300 psig.
c.
Place all of the loop seal drain valve handswitches in OPEN, within 5 minutes, to reduce system pressure to normal.
' d.
- Reduce the Offgas hydrogen concentration to <4% in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
,
,
SENIOR REACTOR OPERATOR Page 70 QUESTION: 094 (1.00)
Upon completion of troubleshooting of a logic circuit, the OSS authorizes removal of a Temp Mod, which consists of two Jumpers and a Relay Block. The l&C Technician returns the Temp Mod Permit and equipment to the OSS and then departs. While reviewing the Temp Mod Permit, the OSS identifies that the Technician initiated for the removal of the Jumpers and Relay Block but that no one initialed for the verification of the removal.
Is this Temporary Modification practice ALLOWABLE or NOT ALLOWABLE? If ALLOWABLE, identify the necessary additional considerations. If NOT ALLOWABLE, identify the CORRECT reason.
a.
ALLOWABLE; if the I&C Technician removing the Temp Mod was task qualified, b.
ALLOWABLE; if the OSS initials for the verification of the removal.
c.
NOT ALLOWABLE; Temp Mod removal requires Dual Verification.
d. -
NOT ALLOWABLE; Temp Mod removal requires Independent Verificatio.-
SENIOR REACTOR OPERATOR Page 71
. QUESTION: 095' (1.00)
The plant.was operating at full power with no inoperable equipment when an Armed Security-Threat in the Protected. Area was confirmed.' Operators have begun AOP 914," Security Emergency", immediate actions. Operators have manually scrammed the reactor and the plant responded as designed.' The Panel 1C05 Operator has secured one Feed Pump. RPV level is 200 inches and rising slowly. EHC is controlling RPV pressure at 940 psig.
1)
What is the required lineup for the Reactor Water Cleanup (RWCU) system for this emergency?.
2)
.What is the required lineup for the High Pressure Coolant injection (HPCI)
system for this emergency?
a.
_1)
Lined up to drain the RPV for post scram level control.
. 2)
Operating in the CST-to-CST mode, b.
1)
Lined up to drain the RPV for post scram level control.
2)
Steam line manually. isolated, c.
1)
RWCU Inlet and Outlet isolation valves manually closed.
2).
Operating in the CST-to-CST mode.
i d.
.1)
RWCU Inlet and Outlet isolation valves manually closed.
2)
Steam line manually isolated.
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SENIOR REACTOR OPERATOR Page 72 QUESTION: 096 ' (1.00)
A Refueling Outage has been in progress for two weeks. The Drywell is being continuously ventilated and both access points, the alrlock and the equipment hatch, are open. Is the Drywell considered a " Confined Work Space"in this situation? (YES or NO) If YES, identify the
]
CORRECT " Confined Work Space" classification. If NO, identify the CORRECT reason it is not a " Confined Work Space".
j a.
YES, classified as a " Permit-Required Confined Space".
' b.
YES, classified as a "Non-Permit Confined Space".'
i c.
NO, with ventilation established there is no " potential to contain a hazardous atmosphere".
- d.
NO, with both access points open there is no longer a " limited means of entry and exit".
QUESTION: 097 (1.00)
Which of the following is considered a valid ESF actuation?
a.
An instrument Tech. pulls the wrong relay block out of the HPCl initiation relay, during an STP, causing HPCI to initiate.
'b.
A Security Guard keys his radio in the Reactor Building, near 1C58, in the NECR, causing a reactor scram on APRM flow biased signals.
c.
A loss of Well Water causes Drywell pressure to raise to 2.1 psig, causing initiation of RHR, CS, SBDGs, and PCIS Groups 2 - 4.
' d.
A generic problem with the wide range Yarway level indicating switches, causes one to drift below the Low-Low-Low RPV setpoint, causing the initiation of RHR, CS, SBDG, portions of PCIS Groups 1 & SENIOR REACTOR OPERATOR-Page 73 QUESTION: 098 (1.00)
' The plant is in a refueling outage. Core alterations have been suspended for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for repair
-
of the refueling bridge. The repairs are now complete and the OSS authorizes re-commenaument of refueling activities. Do the Fuel Handling Supervisor, the senior on-duty Reactor E:,gitieer, or Principal Engineer-Refueling and Fuel Storage also have the authority to authorize re-commencement of refueling activities? (YES or NO) If YES, CORRECTLY identify which other position has this authority.
a.-
NO.
b.
YES, the onduty Fuel Handling Supervisor also has this authority, c.
YES, the senior on-duty Reactor Engineer also has this authority.
d.
YES, the on-duty Principal Engineer-Refueling and Fuel Storage also has this authority.
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i SENIOR REACTOR OPERATOR Page 74 i
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QUESTION: 099 (1.00)
A plant transient results in fuel damage and d6%rMou Site Emergency. The plant has been stabilized, the offsite release has been tcc xwe A er s scovery operations are in i
'
progress. The Main Turbine Tuming Gear will not Snags automatically and the TSC engineers are concerned about damage to this valuable property, The Emergency Coordinator has authorized entry into the Turbine Building to attempt to engage it manually at the middle standard. An operator and a HP have volunteered to perform this task. All Turbine Building ARMS are reading in greater than 5 Rem / Hour and exposures in excess of 5 Rem are projected, Per the Emergency Plan Implementing Procedures, are the members of the repair team allowed to enter even the, ugh their dose may exceed 5 Rem? (NO or YES) If YES, what will be the higher exposure limit?
a.
NO; Personnel are not allowed to exceed 5 Rem for repair work.
)
b.
YES; 10 Rem c.
YES; 25 Rem
- d.
YES; 50 Rem i
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SENIOR REACTOR OPERATOR-Page 75 QUESTION: 100 (1.00).
It is a normal working day when a Loss of Coolant Accident occurs that requires declaration of a Site Area Emergency. There is no radioactive release currently in progress. Do the non-essential personnel depart IMMEDIATELY for the Offsite Relocation and Assembly Area at Palo School? (YES or NO) If NO, identify the CORRECT point at which they will be directed to evacuate the site.
'
a.
YES-b.
NO; evacuate after the TSC is declared operational.
j i
c.
NO; evacuate after Security personnel complete Emergency Accountability.
d.
NO; evacuate only if there is a threat of radioactive release.
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("*"""* END OF EXAMINATION """"")
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' SENIOR REACTOR OPERATOR Page 76 REFERENCES
ANSWER: 001 (1.00)
ANSWER: 004 (1.00)
a.
d.
REFERENCE:
REFERENCE:
SD-693.1, revision 2, section F SD-880, revision 7, System Operation, Distracter 1: The CIV STOPS should close Section C.4.
on a trip to protect the turbine from Distracter 1: The transient will make level go overspeed, the source of steam is the low, not high.
Iow-pressure heaters backing up into the Distracter 2: Recirc pump NPSH is not turbine.
affected by carryover.
Distracter 2: Mechanical overspeed trip looks Distracter 3: Moisture content of the steam is like any other trip.
not adversely affected by carryunder.
Distracter 3: The backup overspeed trip cannot help in this situation; the turbine stop valves are already closed.
ANSWL "
005 (1.00)
,
)
b.
REFERENCE:
ANSWER: 002 (1.00)01-877; Defeat 16 c.
REFERENCE:
SD 255, revision 4, System Operation, ANSWER: 006 (1.00)
section 4 c.
Distracter 1: Failure of the flow control station REFERENCE:
will also result in LOW current.
RT-29 Distracter 2: A clogged drive filter will result Distracter 1: Would be shorter because
{
in LOW amps on the motor.
Xenon would already be decaying and now Distracter 3: An air bound pump will have start to burn out.
LOW current.
Distracter 2: Would be shorter. The point of adding heat is on range 6.
Distracter 3: Shorter is correct, but feedwater ANSWER: 003 (1.00)
flow does not change until steaming rate
<
b.
changes.
REFERENCE:
SD-183.1, revision 3, Major Components, Section B and Control and Instrumentation, ANSWER: 007 (1.00)
i section H b.
Distracter 1: Purpose of LLS is to protect the REFERENCE:
SRV tailpipe, not prevent reaching 1055.
EOP Bases, ATWS page 71; SD 878.8 Distracter 2: LLS willlift the valve at 1020 to Distracter 1: Select blocks come from RSCS.
protect the SRV tailpipes.
Distracter 2: Placed in Bypass per RIP 103.3.
Distracter 3: LLS lifts the valves at 1020 and RWM does not transmit to PPC.
,
1025.
Distracter 3: Placed in Bypass per RIP 103.3.
RWM enforcement is not desirable.
0
SENIOR REACTOR OPERATOR Page 77 ANSWER: 008 (1.00)
ANSWER: 011 (1.00)
d.
d.
REFERENCE:
REFERENCE:
T.S. 2.1.2 SD-149, revision 6, page 22; EOP-2 Bases Distracter 1: Nominal setpoint of Safety Distracter 1: Both sets of spray valves Valves.
receive the close signal from drywell Distracter 2: RPV design pressure.
pressure.
Distracter 3: RPV discharge piping design Distracter 2: Both sets of spray valves pressure.
receive the close signal from drywell pressure.
Distracter 3: Both sets of spray valves ANSWER: 009 (1.00)
receive the close signal from drywell a.
pressure.
REFERENCE:
ATWS EOP Bases Note: Inserting IRMs is an immediate ANSWER: 012 (1.00)
operator action for the scram procedure, c.
Distracter 1: Yes is correct, but the training REFERENCE:
technique wams against ranging down Instructor Guide 88.0; plant response.
because it will result in exaggerated IRM Note: Fuel Zone indicators read higher than response.
the GEMACs at power because the lower Distracter 2; 1RMs can be inserted.
taps are share a sensing line with the Exaggerated response is true only if operator calibrated jet pumps and see additional incorrectly ranges down.
pressure.
Distracter 3: IRMs can be inserted. Damage Distracter 1: They may both read lower but from high flux is not a stated concern.
they will not read the same because of Recirc flow in the B Loop which makes B Fuel Zone read higher.
ANSWER: 010 (1.00)
Distracter 2: They will not read the same c.
because of Recirc flow in the B Loop which REFERENCE:
makes B Fuel Zone read higher.
SEP 303.3 Distracter 3: A Fuel Zone will read lower.
Note: Although this answeris taken from procedure steps, an RO should recognize that CAD cannot be injected when ANSWER: 013 (1.00)
containment sprays are in service on that line.
c.
Additionally, the RO should know that the REFERENCE:
torus spray header is ring header common to ARP 1C078, B-1 & C-1
. both loops of RHR.
Distracter 1: This is the value for a Turbine Distracter 1: Selected if RO does not trip, but the Turbine would already be tripped.
understand the relationship between RHR Distracter 2: This is the value for a Group 1 and CAD.
Isolation, but this feature would be bypassed Distracter 2: Selected if RO does not during a plant cooldown, understand about the torus ring header.
Distracter 3: The maximum value for Distracter 3: Selected if RO believes that any condenser backpressure (i.e. no vacuum).
form of containment spray disallows CAD Homogeneous distracter.
injection.
-...
...
SENIOR REACTOR OPERATOR Page 78 ANSWER: ; 014 (1.00)
ANSWER: 017 (1.00)
a.'
d.
REFERENCE:
REFERENCE:
SD-375, Revision 4, Table C; AOP 149, AOP-672 revision 12, Section 3.2
.
Distracter 1: Plausible, but there is no control Distracter 1: HPCI will be unavailable due to function from this monitor.
loss of the bus.
Distracter 2: A common misconception.
Distracter 2: HPCI will be unavailable due to Distracter 3: Plausible, but this condition loss of the bus; RHR shutdown cooling
' results in a Group 3 isolation.
suction isolation (outboard) has no power Distracter 3: RCIC will only work until it isolates; RHR shutdown cooling suction ANSWER: 018 (1.00)
isolation (outboard) has no power, a.
REFERENCE:
SD-518; AOP-408 Note: The main Inst and ANSWER: 015 (1.00)
Service air compressors have an a.
independent cooling system. The backup REFERENCE:
compressor, which is idle in a normal lineup, ARP 1C04C, A-6 is cooled by well water.
Note: RCIC trips on 211 inches in 6 minutes.
Distracter 1: Reduced cooling to the Offgas Distracter 1: HPCI suction transfers to the recombiner closed cooling water heat torus at 10.6 ft in 8 minutes. This also closes exchanger and glycol refrigeration machines.
the test valve shared by RCIC.
Distracter 2: Loss of cooling to Control Bldg.
Distracter 2: HPCI initiation occurs at 2 psig in Chillers. AOP directs alternate use of ESW.
DWin 10 minutes.
Distracter 3: Loss of cooling to main intake This also closes the test valve shared by cooling coils, and low flow may auto bypass RCIC.
them. AOP directs bypassir.g these coils.
Distracter 3: RCIC isolates on low steam supply pressure at 100 psig in 20 minutes.
ANSWER: 019 (1.00)
d.
ANSWER:' 016 (1.00)
REFERENCE:
- b.'
AOP 518, revision 18 REFERENCE:
Distracter 1: SDV vents and drains fail ACP.1410.1 CLOSED, not OPEN.
Distracter 1: " Entered" is correct, but it can be Distracter 2: Backup scram valves are exited when >95*F if no emergency exists.
- Distracter 2: EOP-2 is entered. In some Distracter 3: Flow control valve fail closed, situations STPs do govern operations. (E.g.
reducing CRD pump flow.
Temp Mods) -
Distracter 3: EOP-2 is entered. ACP states this explicitly for planned operations.
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. SENIOR REACTOR OPERATOR Page 79
- ANSWER: 020 (1.00)
ANSWER: 023 (1.00)
c.
a.
REFERENCE:
REFERENCE:
ARP 1C05B,~ A-2, Step 2.2, Revision 2 EOP-2 Bases Distracter 1: Primary source signal is the Distracter 1: SRV Tailpipe limit is 13.8 ft.
MSIVs, High APRM Hi flux would be a Distracter 2: Not the basis. There is still 2.5 backup signal.
ft. of air space above 13.5.
Distracter 2: Primary source signal is the Distracter 3: Not the basis. This distracter MSIVs, High RPV pressure would be a may relate again to the SRV tailpipe limit.
backup signal.
Distracter 3: Testing PCIS instruments;-
Turbine shouldn't trip untillater ANSWER: 024 (1.00)
.
c.
REFERENCE:
ANSWER:' 021 (1.00)
EOP-2 Bases, revision 4 i
b.
Distracter 1: Plenty o! water to reflood is i
REFERENCE:
available.
EOP Bases, Curves and Limits, Page18 Distracter 2: RCIC exhaust is never a Distracter 1: This limit is used to key the crew problem because it is low flow and energy.
Into the fact that the pressure suppression Distracter 3: Torus levelis high enough to function of the Torus is not working, requiring cover the downcomers.
an ED.1One of two " Torus" distracters, which makes it attractive Distracter 2: This is not part of the bases HCL ANSWER: 025 (1.00)
but it is similar to Distracter 3 which is.
c.
Distracter 3: This is part of the bases for HCL, REFERENCE:
but not the most limiting.01-170; SEP 301.1; SD-170 Note: 50 psig will lift the SBGT overpressure
<
relief damper on the RB second floor. The ANSWER: 022 (1.00)
SBGT 01 directs that this area specifically be ~
b.
evacuated. Rad levels willincrease in other REFERENCE:
areas, but no other area is specifically AOP-913 identified.
Distracter 1: Selected if RO does not know Distracter 1: Primary concern is the SBGT this sprinkler is isolated.
Relief on RB Second Floor.
,
Distracter 2: This is the location of the.
Distracter 2: Primary concern is the SBGT l
Standby Filter Unit Deluge system isolation.
Relief on RB Second Floor.
valw, which is also normally closed.
Distracter 3: Primary concern is the SBGT
~ Distracter 3: This is the location of the Relief on RB Second Floor.
~ Standby Gas Treatment Deluge system
- isolation valve, which is also normally closed.
,
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i SENIOR REACTOR OPERATOR'
Page 80 i
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ANSWER: - 026 L(1.00)
ANSWER: 030 (1.00)
c.
b.
REFERENCE:
REFERENCE:
SD-733, ARP 1C05B, C-8; P&lD M-176 ARP 1C05A D-6, revision 5 i
Note: During a Group 3, SBGT will align to Distracter 1: Loss of the even numbered I
the RB Vent Shaft, thus drawing refuel floor
' reed switch (without detection of an odd air through AV-7604V.
switch) does not give the DRIFT alarm.
i l
Distracter 1: EF-10 trips on a Group 3.
Distracter 2: Loss of the even numbered Distracter 2: There are no such dampers and reed switch (without detection of an odd
. EF-11 A&B trip on a Group 3 isolation.
switch) does not give the DRIFT alarm. Will i
Distracter 3: Shifting to High Bay Exhaust is actuate for a non-selected rod even if another
'
only done manually for refueling ops.
rod is driving.
Distracter 3: Will actuate for a non-selected l
rod even if another rod is driving.
ANSWER: '027 (1.00)
l
. d.
l REFERENCE:
ANSWER: 031 (1.00).
EOP-3 Bases c.
I Distracter 1: Definition of Max Normal.
REFERENCE:
Distracter 2: Temperatures above Max Safe
. ARP 1C04AD-8 are an indication of an accident, but not the Note: Speed Demand runs back to 20% on a basis for the values.
20 % Runback but not to 45% on a 45%
Distracter 3: Some equipment may fail runback. That is why the procedures are beca'use max Safe is based on Safe different. The procedure for resetting a 45%
Shutdown equipment failure, runback directs the operator to lock the scoop tube first. A DAEC RO should know this.
Distracter 1: (S) Remains at 60% and pump ANSWER: 028 (1.00)
speed would increase.
i I
d.
Distracter 2: (S) Remains at 60% and there is REFERENCE:
no such interlock.
l SD-170.1, revision 3 Distracter 3: 60% is correct but there is no Distracter 1: Isolation dampers are designed such interlock.
i l
for more than 7" H20.
Distracter 2: If SBGT did not start there is no flowpath through the system, plus SBGT releases via the stack, which is monitored.
Distracter 3: High pressure will not affect the l
Kamans.
l l
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ANSWER:- 029 (1.00)
l d.
l-REFERENCE:
!
SD 358 Distracter 1: Plausible, but incorrect.
Distracter 2: Plausible, but incorrect.
Distracter 3: Plausible, but incorrect.-
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. SENIOR REACTOR OPERATOR Page 81 ANSWER:. 032 (1.00)
ANSWER: 035 (1.00)
, ~
a.
b.
REFERENCE:
REFERENCE:
01-149 01153, revision 25, Section 4.0 Distracter 1: The RHR Crosstie MO-2010 Distracter 1: Lights should go out, not come would be closed, preventing injection from on.
A&C.~
Distracter 2: Lights should go out, alarm Distracter 2: B loop does not automatically.
should go ON, pressure should be <1350 realign itself for LPCI initiation. The Group 4 psig.
isolation must also be reset before one B loop Distracter 3: Alarm should come on, inject valve will open..
pressure should be <1350 psig.
Distracter 3: The RHR Crosstie MO-2010 would be closed, preventing injection from A&C. B loop does not automatically realign ANSWER: 036 (1.00)
itself for LPCI initiation. The Group 4 isolation -
a.
must also be reset before one B loop inject REFERENCE:
valve will open.
SD-358, Page 20 :
Distracter 1: This time would be used to initiate' ARI if all rods do not insert, but this is j
ANSWER: 033 (1.00)
not the correct basis, j
c.
Distracter 2: RPV level needs time to stabilize I
. REFERENCE:
but this is not the correct basis.
EOP-2 Bases Distracter 3: SDV valves would be closing Note: This value has recently been during this period, but this is not the correct recalculated and changed from 6 ft to 5.8 ft.
basis.
' Distracter 1: Downcomers become uncovered.
Distracter 2: Former value.
ANSWER: 037 (1.00)
Distracter 3: SRV tailpipes become b.
. uncovered.
REFERENCE:
Ol 878.1, Revision 11, Sect. 2.0
..
..
Distracter 1: Bypasued if SRM >100 cps.
' ANSWER: 034 (1.00)
Distracter 2: Rod block bypassed on Range a. >
3 and above.
,
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REFERENCE:
Distracter 3: Rod block bypassed on Range 01-151, Rev. 30, Sect. 4.0 3 and above.
.
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l SENIOR REACTOR OPERATOR Page 82 ANSWER: 038 (1.00)
ANSWER: 040 (1.00)
a.
a.
REFERENCE:
REFERENCE:
01878.5; SD 878.5
_
01-150 Distracter 1: No rod blocks will be enforced; Note: RO is expected to know that MO-2400
the APRM is <30% APRM "E"is the would be located in the Drywell and therefore attemate for A RBM, APRM "F" for B RBM.
an AC valve. RO must also recognize that Distracter 2: APRM Mode Switch will not this valve would come from an essential bus.
force the RBM to the attemate reference Distracter 1: This is an AC bus and it is APRM.
located in nearby in the reactor bidg. but it is Distracter 3: No rod blocks will be enforced; a non-essential bus. (1814 comes from 1B1)
i the APRM is <30%. APRM Mode Switch will Distracter 2: Selected if RO thinks MO-2400 not force the RBM to the attemate reference has a large DC motor.
APRM. APRM "E"is the attemate for A RBM, 1D41 is the power supply to most HPCI DC APRM "F" for B RBM.
equipment, including the outboard steam line isolation valve.
Distracter 3: Seiected if RO thinks MO-2400 ANSWER: 039 (1.00)
has a small DC motor.1D14 is the power-a.
supply to most RCIC DC equipment, including REFERENCE:
the outboard steam line isolation valve.
SD 880,Rev. Page 12.
Note: Air bubbles rising in the reference leg
. reduce the pressure at the transmitter.
ANSWER: 041 (1.00)
(Notching) Lower refleg pressure translates c.
to higher indicated level.
REFERENCE:
Distracter 1: Higher is correct but the sensed 01-573, Rev. 54, Sect 2.0; SD 183.1, Rev. 3,
- DP decreases.
System Interrelations Distracter 2: The sensed DP decreases but Distracter 1: ADS initiation will not work if this causes indicated level to read higher.
there is no nitrogen.
Distracter 3: Lower is incorrect and the Distracter 2: Manual signal will not work if i
sensed DP decreases.-
there is no nitrogen.
'
Distracter 3: Manual signal will not work if there is no nitrogen.; high pressure actuation does not require nitrogen.
ANSWER: 042 (1.00)
d.
REFERENCE:
01-573 Note: RO is required to know that DW inerted
,
means <4% oxygen.
Distracter 1: Chosen if CAD low inventory not identified.
'
Distracter 2 & 3: Chosen if CAD low inventory is not identified and operator is confused
about how to use Attachment l SENIOR REACTOR OPERATOR Page 83 ANSWER: 043 (1.00).
ANSWER: 046 (1.00)
- c.
b.
REFERENCE:
REFERENCE:
ARP 1CO5B, A-8 01-644; SD-644 Note: Backpressure is higb(>19 inches Hg Distracter 1: This could cause the given Abs). The bypass which allows a startup with.
indications, but both Non-Essential busses the MSIVs open is un-bypassed if the mode are fed by the Auxiliary Transformer when the switch is placed in run or a TSV is opened, plant is in normal operation.
Distracter 1: Selected if confused with "<850 Distracter 2: Once the A&B controllers are in psig in RUN" Group 1.
Auto, their control is transferred to the Master
!
Distracter 2: Selected if confused with controller. Adjusting the Setpoint knob does Turbine Stop Valve opening which would nothing, result in a Group 1.
Distracter 3: The A&B controllers and reg Distracter 3: Selected if confused about Cond valves themselves may have been in unequal
- High Backpressure Logic.
positions when placed in auto, but it is the job of the Master Controller to provide them the same signal now. The only difference will be ANSWER: 044 (1.00)
the bias setting of the individual controllers.
a.
- REFERENCE:
i SD-183.1, revision 3, page 7 ANSWER: 047 (1.00)
Distracter 1: Possible misconception. The d.
Torus to DW Vacuum breakers are in the REFERENCE:
Torus air space.01-152; O1-170 Distracter 2: This occurs if the vacuum Distracter 1: Does NOT bypass SBGT, off breaker has failed closed, not open.
gas fans are not relevant.
Distracter 3: Selected if RO thinks the.
Distracter 2: Does NOT bypass SBGT, off vacuum breakers are under water in the gas fans are not relevant.
Torus.
Distracter 3:. Do not need a SBGT fan running for HPCI to work.
ANSWER: 045 (1.00)
b.
ANSWER: 048 (1.00)
REFERENCE-c.
ARP 1C08" i -4, Rev. 7; SD 693.2a; SD 697 REFERENCE:
f
<
Distracter 1: Input from Turbine Trip. Runback SD 324, revision 1 does not directly affect intercept valves.
Distracter 1: This is opposite of the way i
Distracter 2: Input from Power Load Degraded Voltage protection works. With low Unbalance. Runback does not input a "0" bus voltage the Startup and STBY signal, transformer breakers open. The SBDG gets Distracter 3: Input from Low Vacuum to close a start signal, not a breaker trip signal.
BPVs. Runback does not input directly to Distracter 2: Output breaker does not trip BPVs.
open on Bus undervoltage. The SBDG trips first on overspeed.
Distracter 3: It is true that the SBDG trips first on overspeed, but the Output breaker does j
not trip open on Bus underfrequency.
<
1
i SENIOR REACTOR OPERATOR Page 84 ANSWER: 049 (1.00)
ANSWER: 052 (1.00)
a.
d.
REFERENCE:
REFERENCE:
01-151, revision 30, section 7.1 01-149 Distracter 1: Pump and valves must be Note: DAEC no longer throttles with the inject manually configured.
valve to save wear and tear on the larger, Distracter 2: Cannot reset untilinitiation more expensive valve, signals are cleared.
Distracter 1: Not used in this service. One
!
Distracter 3: Cannot reset untilinitiation valve alone would be poor at controlling both
'
signals are cleared, parameters.
Pump and valves must be manually Distracter 2: Common misconception. HX configured.
inlet and bypass control both.
Distracter 3: HX inlet and bypass control both.
,
I ANSWER: 050 (1.00)
d.
ANSWER: 053 (1.00)
REFERENCE:
d.
01324, Caution on page 10. Note: The REFERENCE:
referenced caution requires the SBDG to be SD 856.1 rolled with air before starting to prevent Distracter 1& 2: No way to detect this failure damage from oil which may have collected in until rod is at position 48 and a coupling the upper piston area.
check is performed.
{
Distracter 1: Selected of RO is unaware of the Distracter 3: A Rod Drift alarm would be I
caution / operating characteristic.
received when the RMCS timer timed out and Distracter 2: This step must also be the rod was not on an even numbered performed but the SBDG cannot be started position. RMCS timing out is not necessary to untilit has been rolled with air.
get the overtravel alarm.
i Distracter 3: Alarms on 1C91 activate the shutdown relay and must be reset prior to a SBDG start, but the prelube operation ANSWER: 054 (1.00)
described does not activate such an alarm, d.
REFERENCE:
SD-683, revision 0, page 28/29 ANSWER: 051 (1.00)
Distracter 1: Should be RPS and 125 VDC.
b.
Distracter 2: Should be RPS.
REFERENCE:
Distracter 3: Should be 125VDC.
SD264; P&lD 115& 116 Note: Total Core flow is the sum of 16 non-calibrated Jet Pumps.
Distracter 1: Common misconception; Provides indication only.
Distracter 2: Common misconception; Distracter 3: Plausible and homogenou SENIOR REACTOR OPERATOR Page 85 ANSWER: 055 (1.00)
ANSWER: 057 (1.00)
d.
b.
REFERENCE:
REFERENCE:
01-695.2 SD 304 Note: Hydrogen purity which cannot be Note: T4 may not have high operational maintained >90% requires a generator validity, but this question also challenges shutdown due to the possibility of an RO's knowledge of normal and backup explosion at <74.2%.
sources of power to the 36KV bus and the Distracter 1: Selected if RO does not role of the LLRPSF transformers.
recognize problem with purity. Voltage adjust Distracter 1: This is the backup source of would be correct otherwise.
36KV. There is an auto recioser on this line in Distracter 2: Selected if RO does not case the normal supply voltage from T3 is recognize problem with purity. Voltage adjust iet.
is also incorrect.
Distracter 2: The primary side of T4 is 36KV.
.
Distracter 3: Correct action for loss of bus A common misconception. Substation duct cooling. Reducing load does not lessen schematic shows a tie in close to 1XR1.
the threat of an explosion.
Distracter 3: The primary side of T4 is 36KV.
A plausible / homogeneous distracter.
ANSWER: 056 (1.00)
d.
ANSWER: 058 (1.00)
REFERENCE:
d.
AOP 357, Rev. 23 REFERENCE:
Distracter 1: EHC pressure controlis not lost IPO-2 Turbine provides it's own power supply on Distracter 1: 300 psig is the normal operating line.
pressure for the Air Ejectors and Jet Distracter 2: These valves fail open upon Compressor after it is reduced from the Main loss of Inst AC, not UPS. They are available Steam system <950 psig, for alternate level control.
Distracter 2: > 300 psig but still too low per Distracter 3: Possible confusion with loss of IPOI-2.
Div. 2125 VDC, which requires transfer to A Distracter 3: > 300 psig but still too low per Level. Feed regulating valves lock; the master IPOI-2.
controller is not affecting leve SENIOR REACTOR OPERATOR Page 86 ANSWER: 059 (1.00)
ANSWER: 062 (1.00)
a.
d.
REFERENCE:
REFERENCE:
01-513, Sect. 5.4 SD 518, revision 3, page 12 Note: Initiation and ventilation shutdown always requires operator action. Auto shutdown of CO2 occurs in 2 minutes if ANSWER: 063 (1.00)
,
initiated from the turbine op deck (7866 level).
c.
If CO2 is manually initiated from the CO2 REFERENCE:
tank on the TB ground floor (7576 level), it AIP 401 and AIP 402 must also be manually isolated.
Distracter 1: Both inject through A loop RHR.
Distracter 1: 2 requires operator action.
Distracter 2: Not necessary for either ESW or Distracter 2: 1 requires operator action.
RHRSWinjection.
Distracter 3: 1&2 require operator action.
Distracter 3: Both are controlled by LPCl inject valves. RHRSW HX Discharge valve is never throttled during ESW injection. RHRSW ANSWER: 060 (1.00)
HX Discharge can be throttled open after a.
LPCI injects are closed during RHRSW REFERENCE:
Injection.
AIP 403,404, & 405 Note: This question requires knowledge of i
both the EOP-2 Table 9 systems and ANSWER: 064 (1.00)
flowpath necessary to achieve Cont Sprays.
b.
Distracter 1: RO must recognize that this REFERENCE:
system needs MO-1942 open for Cont Spray,01-373.6, revis:.sn 20; SD 878.6, Rev. 2 Distracter 2: RO must recognize that this Distracter 1: Both drives switch to manual system needs MO-1942 open for Cont Spray, and withdraw.
Distracter 3: Condensate Service is available.
Distracter 2: Both drives switch to manual and withdraw; ball valve closure is automatic when the detector reaches in shield position.
ANSWER: 061 (1.00)
Distracter 3: Reactor scram is at the Group ll a.
setpoint,170". ball valve closure is automatic REFERENCE:
when the detector reaches in shield position.01-730, P&L 15; TRM 3.8.2.3
' Note: It seems implausible but battery operability becomes a concern <65'F. Until recently, an 01-730 P&L wamed about this.
Now the P&L refers operators to the TRM but operaters should still recognize the threat to
,
!
the batteries.
Distracter 1: Plausible due to low load.
Distracter 2: Plausible because SFUs draw in
,.
'
outside air during CB HVAC isolations.
Distracter 3: Plausible due to freezing in remote locations. i i
SENIOR REACTOR OPERATOR Page 87 ANSWER: 065 (1.00)
ANSWER: 068 (1.00)
a.
a.
REFERENCE:
REFERENCE:
SD435 ODI-14, ODI-12 Distracter 1:- Condition is alarmed but not on 2.1 Conduct of Op Note: An unfamiliar 1C136 and Radwaste. Common operator might think the correct answer is too Misconception.
good to be true.
Distracter 2: Fuel poollow level will alarm in Distracter 1: Not used. Instrumentation is not the CR but the leakage condition is also degraded. Also, each instance would require alarmed... RB EQ Drains are alarmed in Distracter 2: This would resolve the problem, and associated work document. (CWO)
Distracter 3:
the main CR, not Radwaste. ( A possible but there is no procedure for this action and misconception and necessary to prevent there is no such thing as an " Outage synonymous distracters.) The leakage Annunciator Log."
)
condition is alarmed.
Distracter 3: Card removal could be used for nuisance alarms, but only on a small scale.
Each instance would require implementation ANSWER: 066 (1.00)
of the Temporary Modification process. There l
b.
is no such thing as an " Outage Temp Mod".
REFERENCE:
SD 856.1, Table 2; ARP 1C058, A-6; STP 3.9.1-01'
.
ANSWER: 069 (1.00)
.
Distracter 1: Bridge over the core with hoist d.
loaded is a Rod Block. No Rod Block until REFERENCE:
then.
SD 152 Distracter 2: Bridge over the core with hoist
- loaded is a Rod Block.
~ Distracter 1: Design Basis D states that HPCI uses plant DC power.
Distracter 3: Bridge over the core with hoist Distracter 2: Design Basis A states that HPCI loaded is a Rod Block provides adequate core cooling, but not for large breaks.
Distracter 3; it is designed for a small break ANSWe'1: 067.(1.00)
LOCA but Containment protection is not one c.
of its bases.
REFERENCE:
,-
!01-733 Distracter 1: Common misconception.
l
. Distracter 2: Common misconception.
j Distracter 3: Common misconception.
I
'
[:
.
SENIOR REACTOR OPERATOR Page 88 L
ANSWER: 070 (1.00)
ANSWER: 073 (1.00)
a.
c.
REFERENCE:
REFERENCE:
l l POI-2 ITS Bases 3.3.3.1, Page 3.3-61 Note: RO is not expected to know procedure Note: This is a plant Operating Event (OE).
steps to answer this question. Candidate Approximately one year ago the 1C09
,
!:
must recognize that lowering pressure set is instrument was removed without entering the the only viable method to reduce heat up rate.
LCO for inop Post Accident instrumentation.
Distracter 1: This will increase the heatup Distracter 1: Can be determined on 1C09 l
rate.
..
PAM /1.97 instruments,0-250 psig range.
Distracter 2: MSL Drains should already be Distracter 2: Not a PAM /1.97 instrument; open. If they had been closed, this action range is only 0-100 psig.
would merely close the turbine bypass valve.
Distracter 3: Not PAM /1.97 instruments; l
RPV pressure and Heatup rate will remain the range is only -10-90 psig.
same.
Distracter 3: This will open the turbine bypass
,
l
. valve. RPV pressure and Heatup rate will ANSWER: 074 (1.00)
remain the same, c.
REFERENCE:
EOP Bases, ED ANSWER: ' 071 (1.00)-
Note: ED flowchart is NOT provided. DAEC c.
operators are no longer responsible for REFERENCE:
knowledge of SAGS, so they may dismiss the SD 281; RFP 301
- correct answer option. MO-4423 is in the Distracter 1: Stops downward movement, not Drywell and may not open when needed for upward.
PCF if DW water level is >39ft.
Distracter 2: Stops downward movement, not Distracter 1: Obvious choice, but there is no upward.
reason to drain MSLs.
Distracter 3: It would not be good to continue, Distracter 2: RPV Flood coolant flowpath but there is no interlock.
goes through the SRVs to the Torus, not down the MSLs.
Distracter 3: RPV has a big leak, the SRVs ANSWER: 072 (1.00)
opened, the RPV will remain depressurized
,
b.
for injection.
REFERENCE:
. ACP 1411.13 and 22 ANSWER: 075 (1.00)
Note: LHRA is > 1 Rem /Hr. Next highest d.
posting is VHRA.
REFERENCE:
!
Distracter 1: HRA is >100 Mrem /Hr AOP 302.2, Rev.' 8 Distracter 2: Common misconception. This Distracter 1: Would also deenergize term is no longer used.
1C06A&B,1C078, and 1C08A Distracter 3: VHRA is > 500 Rem /Hr Distracter 2: Would also deenergize 1C08A Distracter 3: Would also deenergize 1C078
i-l
,
!
' SENIOR REACTOR OPERATOR Page 89 ANSWER: 076 (1.00)
ANSWER: 080 (1.00)
c.
a.
REFERENCE:
REFERENCE:
EOP-2 and Bases.
AOP-915, Rev.15
.
Note: AOP-915 requires the Mode Switch be L
placed in RUN if it was in RUN originally.
.
- ANSWER: 077- (1.00)
Distracter 1&2: In compliance. AOP directs a.
the OSS and one other operator to remain in REFERENCE:
this situation.
l RPV/F EOP & Bases Distracter 3: In compliance. There is no such Note: RPV/F EOP is not provided, restriction in ACP1410.1 SCBAs are staged l
RPV/F requires ~3 SRVs open and RPV in the Control Room forjust this contingency.
l pressure 50 psig above torus pressure.
AOP-915 directs use of SCBA to re-enter the Switchgear rooms if there is smoke.
ANSWER: 078 (1.00)
_
.
a.
ANSWER: 081 (1.00)
' REFERENCE:
d.
AOP 301.1. Tab 3 REFERENCE:
Distracter 1: 3700 VAC=88% which is high T.S. 3.1.5 and Bases.
enough to operate ECCS pumps.
Note: SRO would be expected to know that Distracter 2:. Degraded Grid voltage the scram function of this rod would be
- (<92.5%) can be bypassed in this seriously degraded in a depressurization emergency.
event. Immediate insertion of the control rod, Distracter 3: 3700 VAC=88% which is high'
Required Action C.1, is not an option because d
enough to operate ECCS pumps.
there are no CRD pumps running, Degraded Grid voltage (<92.5%) can be Distracter 1: Selected if SRO mistakenly bypassed in this emergency
- eferences Condition A.
Distracter 2: Selected if SRO mistakenly references Condition B and applies Required ANSWER: 079 (1.00)
Action B.2.1 and 82.2.
d.
'
Distracter 3: Selected if SRO mistakenly REFERENCE:
references Condition B and applies Required EOP 2, EOP Bases Document Action B.1.
~ Distracter #1: Cannot vent the containment l=
when thove 2 psig, except as directed by the l
SAGS.
ANSWER: 082 (1.00)
Distracter #2: CAD will inject but this action is a.
.
. not directed by EOP-1 or EOP-2.
REFERENCE:
E Distracter #3: Cannot spray the Drywell, due EOP-3 revision 13; EOP-4, revision 13 to not meeting the conditions for the DSIL-Distracter 1: Prohibited by reactor building curve.
vent radiation levels.
' Distracter 2: Prohibited by reactor building vent radiation levels.
l Distracter 3: Fans are needed to remain
running in this situation.
>
-
SENIOR REACTOR OPERATOR Page 90 ANSWER: 083 (1.00)
ANSWER: 086 (1.00)
b.'
c.
REFERENCE:
REFERENCE:
AOP 149, revision 12 Technical Specifications 3.6.4.1 and Bases Distracter 1: This is what you get if you read 3.6.4.1, IPOl 8 Definition of OPDRVs.
the right graph for immediately after Distracter #1: Definition of OPDRVs excludes shutdown, those systems that are isolated by at least Distracter 2: This is what you get if you read one locked closed valve on each side.
>
the wrong graph for immediately after Distracter #2: The applicability for Secondary shutdown.
Containment integrity is concemed with the Distracter 3: This is what you get if you use movement of irradiated fuel inside Secondary the wron curve but the right time since Containment.
.
w
shutdown.
Distracter #3: The LLRPSF and its doors do not make up the boundary for Secondary Containment at any time.
ANSWER: 084 (1.00).
a.
REFERENCE:
ANSWER: 087 (1.00)
EOP-1; EOP-2; ACP 1410.1, Section 3.9(3)
a.
,
Note: The K/A is for Ability to monitor torus REFERENCE:
'
temp. The EOP actions are incorrect and are EOP ATWS, Rev. 8 merely_distracters. The ACP referenced Distracter 1: Homogeneous distracter.
. prohibits actions taken based on computer Distracter 2: Correct answer for many years points alone, until the last revision of the ATWS EOP.
Distracter 1: The back panelindications are -
Distracter 3: Homogeneous distracter. Cold not preferred points.
.
'
Distracter 2: ED is not warranted based on computer data alone.
Distracter 3: This is not warranted, since they ANSWER: 088 (1,00)
are used for level control.-
a.
REFERENCE:
SEP 301,1 ANSWER: 085 (1.00)
Distracter 1: Defeat 10 needs RPS power to c.
function.
REFERENCE:
Distracter 2: Hard Pipe Venting is RFP 403 appropriate; Torus venting needs RPS power.
Distracter #1: Assembly is re-inserted into the Distracter 3: Hard Pipe Venting is slot from which it came.
appropriate; Burst pressure is 50 psig.
Distracter #2: Assembly is re-inserted into the slot from which it came. Assembly is placed in closest available rack.
Distracter #3: Assembly is placed in closest -
available rack.
i
!
l SENIOR REACTOR OPERATOR Page 91 ANSWER: 089 (1.00)
ANSWER: 092 (1.00)
b.
b.
REFERENCE:
REFERENCE:
EOP Bases Document, ALC EOP-3, revision 11 Distracter #1: Homogeneous distracter; top of Distracter 1: Normal reactor shutdown is not active fuel.
procedurally directed.
Distracter #2: 2/3 Core Coverage ALC Distracter 2: EOP d entry conditions are not breakpoint for transition to SAGS.
met.
Distracter #3: Minimum Zero injection RPV Distracter 3: EOP * entry conditions are not Water Level; ALC breakpoint for transition to met.
SAGS ANSWER: 093 (1.00)
ANSWER: 090 (1.00)
d.
c.
REFERENCE:
REFERENCE:
TRM 3.10.A SD 264, Ol 264 Distracter 1: TRM 3.10 applies.
Distracter #1: Drive Motor breaker trip is a Distracter 2: This action is for a premature result of the RPT breaker trip.
recombination event. There is no evidence, Distracter #2: Drive Motor breaker trip is a other than flow, of this event taking place, result of the RPT breaker trip.
Recombiner temperatures contraindicate the Distracter #3: ARI solenoids energize to vent presence of a premature recombination off the Scram Air Header.
event.
Distracter 3: In the case of a loss of Offgas ANSWER: 091 (1.00)
system, HIC 4151 is used to lower system b.
pressure, not the loop seal drain valves.
REFERENCE:
Opening the drain valves at this time would ACP 1410.1,3.3(5) and 3.11.1(9)
cause a release of airborne contamination Distracter 1: ACP 1410.13.11.1(9) requires into the Power Block and Retention Building.
the OSM to remain in the Control Room during transients.
Distracter 2: Only one RO is required in Cold ANSWER: 094 (1.00)
Shutdown. ACP 1410.1 3.11.1(9) requires b.
the OSM to remain in the Control Room REFERENCE:
during transients.
ACP 1410.6,3.2.4; IPOl-7 Distracter 3: Only one RO is required in Cold Distracter 1: Removal verification is still Shutdown.
necessary.
Distracter 2: Temp Mod installation requires Dual verification, not removal.
Distracter 3: Independent verification not used with Temp Mod !
!
( SENIOR REACTOR OPERATOR -
Page 92 ANSWER: 095 (1.00)
ANSWER: 098 (1.00)
c.
a.
REFERENCE:
REFERENCE:
i
"AOP-914~
RFP'402 Distracter #1: AOP directs that RWCU be Distracter #1,2, &3: Only the OSS/OSM can isolated.
authorize restart of fuel moving. All other Distracter #2: AOP directs that RWCU be answer options are the personnel most isolated and HPCI placed in CST-CST.
involved in fuel moving. None of them share Distracter #3: AOP directs that HPCI placed this authority.
{
L in CST-CST.
i L
l ANSWER: 099 (1.00)
ANSWER: 096 (1.00)
b.
b.-
REFERENCE:
REFERENCE:
EPIP 4.3 ACP 1411.11 Distracter 1: Entry is allowed and the 5 Rem l
Note: This revised procedure was recently limit can be exceeded to save valuable implemented (5/28/99).
property.
Training was performed by a Power Point Distracter 2: The higher limit is 10; 25 is for presentation'sent via E-Mail to all employees.
saving a life or protecting large populations.
The OSS has a large responsibility in the '
Distracter 3: The higher limit is 10;
implementation of this procedure.
homogenous distracter and the accepted Distracter 1: It is a Confined Space but is dose above which effects will be noticeable -
downgraded to non-permit after initial entry-j
. with ventilation established.
i L
Distracter 2: Hazardous atmosphere is part of ANSWER: 100 (1.00)
i
the definition for a Permit-Required Confined a.
i Space, but not for just a Confined Space.
REFERENCE-Distracter 3: It seems plausible that two EPIP 1.2 & Form NOTE-4
)
access points make it not a confined space.
Note: After many years of performing
'
However, the Drywellis a recognized DAEC accountability first, the EPIPs have recently Confined Space per Attachment 1. The only been revised to evacuate immediately upon variable is Permit or Non-Permit.
declaration of a Site Area Emergency.
Distracter 1: It would be good to get the TSC i
staffed first, but EPIPs direct immediate evac.
l ANSWER: 097 (1.00)-
Distracter 2: It would be good to get
-
c.
accountability done first, but EPIPs direct REFERENCE:
immediate evac.
i ACP 1402.3 definitions Distracter 3: Plausible, but incorrect.
Distracters 1,2, &3: All are examples of -
invalid ESF actuations due to human error, radio frequency interference, and instrument drift.
(""""" END OF EXAMINATION ***""*")
l l
,
l
)
SENIOR REACTOR OPERATOR Page 93 A N S W E R K E Y - MULTIPLE CHOICE
\\
001 a
021 b
041 c
061 a
081 d
002 c
022 b
042 d
062 d
082 a
003 b
023 a
043 c
063 c
083 b
l
.004 d
024 c
044 a
064 b
084 a
,
005 b
025 c
045 b
065 a
085 c
006 c
026 c
046 b
066 b
086 c
,
007 b
027 d
047 d
067 c
087 a
008 d
028 d
048 c
068 a
088 a
009 a
029 d
049 a
069 d
089 b
]
i 010 c
030 b
050 d
070 a
090 c
l 011 d
031 c
051 b
071 c
091 b
012 c
032 a
052 d
072 b
092 b
i 013 c
033 c
053 d
073 c
093 d
014 a
034-a 054 d
074 c
094 b
015 a
035 b
055 d
075 d
095 c
016 b
036 a
056 d
076 c
096 b
]
017 d-037 b
057 b
077 a
097 c
I
'018 a
038 a
058 d
078 a
098 a
019 d
039 a
059 a
079 d
099 b
020 c ~
040 a-060 a
080 a
100 a
(""**"" END OF EXAMINATION ""*"*")
l