ML20211G700
| ML20211G700 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 08/25/1999 |
| From: | Hurley L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9909010006 | |
| Download: ML20211G700 (1) | |
Text
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pS" "'% UNITED STATES l g g NUCLEAR REGULATORY COMMISSION
$ E REGloN IV
- 611 RYAN PLAZA DRIVE, SUITE 400
, g ARLINGTON, TEXAS 76011-8064 l
August 25,1999 1
l NOTE TO: NRC Document Control Desk Mail Stop O-5-D-24 FROM: Laura Hurley, Licensing Assistant Operations Eranch, Region IV
SUBJECT:
OPERATOR LICENSING EXAMINATIONS ADMINISTERED ON JULY 6-15,1999, AT SOUTH TEXAS PROJECT UNITS 1 AND 2.
DOCKETS #50-498; 50-499 On July 6-15,1999, Operator Licensing Examinations were administered at the referenced facility. Attached you will find the following information for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR:
ltem #1 - a) Facility submitted outline and the initial exam submittal for distribution under RIDS Code A070.
b) As given operating examination, designated for distribution under RIDS Code A070.
Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42.
If you have any questions, please contact Laura Hurley, Licensing Assistant, Operations Branch, Region IV at (817) 860-8253.
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l }?, 8 p REGloN IV 611 RYAN PLAZA DRIVE, SUITE 400 l
ARLINGTON, TEXAS 76011-8064 l .,,,,
JUL 2 6 ?ra William T. Cottle, President and Chief Executive Officer l STP Nuclear Operating Company P.O. Box 289 Wadsworth, Texas 77483
SUBJECT:
NRC INSPECTION REPORT NO. 50-498/99-301; 50-499/99-301
Dear Mr. Cottic:
This refers to the inspectiot;onducted on July 6-15,1999, at the South Texas Project Electric Generating Station, Units and 2, facilities. The enclosed report presents the results of this inspection.
This inspection included an evaluation of nine applicants for senior operator licenses and eight applicants for reactor operator licenses. We determined that all applicants satisfied the requirements of 10 CFR Part 55, and the appropriate licenses have been issued.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in the NRC Public Document Room (PDR).
Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, John L. Pellet, Chief Operations Branch Division of Reactor Safety l Docket Nos.: 50-498;50-499 License Nos.: NPF-76; NPF-80
Enclosure:
NRC Inspection Report No.
50-498/99-301;50-499/99-301
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STP Nuclear Operating Company cc w/ enclosure (w/ Attachments 1 to 3):
Ken Coates, Manager, Nuclear Training STP Nuclear Operating Company P.O. Box 289 Wadsworth, Texas 77483 cc w/ enclosure (w/ Attachments 1 and 2 only):
T. H. Cloninger, Vice President Engineering & Technical Services STP Nuclear Operating Company l P.O. Box 289 Wadsworth, Texas 77483 )
A. Ramirez/C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, Texas 78704 Mr. M. T. Hardt/Mr. W. C. Gunst City Public Service Board P.O. Box 1771 San Antonio, Texas 78296 D. G. Tees /R. L. Balcom Houston Lighting & Power Company P.O. Box 1700 Houston, Texas 77251 l
Jon C. Wood Matthews & Branscomb One Alamo Center 106 S. St. Mary's Street, Suite 700 l San Antonio, Texas 78205-3692 l
Jack R. Newman, Esc.
Morgan, Lewis & Bockius 4 1800 M. Street, N.W.
Washington, D.C. 20036-5869 Mr. G. E. Vaughn/Mr. C. A. Johnson Central Power & Light Company P.O. Box 289 Mail Code: N5012 Wadsworth, Texas 77483 l
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l STP Nuclear Operating Company. INPO Records Center
- 700 Galleria Parkway -
Atlanta, Georgia 30339-5957 Bureau of Radiation Control State of Texas 1100 West 49th Street Austin, Texas 78756 Mr. Jim Calloway Texas Public Utility Commission William B. Travis Building 1701 North Congress Avenue P.O. Box 13326 Austin, Texas 78701-3326 John Howard, Director Environmental and Natural Resources Policy Office of the Governor P.O. Box 12428 Austin, Texas 78711 Judge, Matagorda County Matagorda County Courthouse 1 1700 Seventh Street Bay City, Texas . 77414 1
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n STP Nuclear Operating Company E-Mail report to T. Frye (TJF)
E Mail report to D. Lange (DJL)
E Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK) bec to DCD (IE01) bec distrib. by RIV w/ enclosure and Attachments 1 and 2:
Regional Administrator Resident inspector DRP Director DRS Director RITS System Branch Chief (DRP/A)
RIV File Project Engineer (DRP/A)
R. Bachmann, OGC (MS: 15-B-18)
Branch Chief (DRP/TSS) bec w/ enclosure and Attachments 1-3: l D. Trimble (HOHB/NRR)(MS:D4) l L. Hurley DOCUMENT NAME:
To receive copy of docurnent. Indicate in box: "C" = Copy ethout enclosures *E' = Copy mth enclosures *N' = No copy RIV:SRE:OB E SRE:OB l RE:OB l_ SRE:OB ; SRE:OB l HBundy/Imb d GJohnstonM RLantz 'V ' SMcCrory#' TMeadows 07/4/99 07/U/99 'l 07/21/99 ' 07/2/99 ' 07/ /99 C:OB l N C:PBA fl , C;OB d JLPellet M JITapia W]LPellet Q#
071Pfe9 W 07/!*s9 /T 0 07/ dis 9 DFFICIAL RECORD COPY
ENCLOSURE l
U.S. NUCLEAR REGULATORY COMMISSION
, REGION IV l
Docket Nos.: 50-498;50-499 i License Nos.: NPF-76; NPF-80 l
l Report No.: 50-498/99-301;50-499/99-301 Licensee: STP Nuclear Operating Company Facility: South Texas Project Electric Generating Station, Units 1 and 2 i Location: FM 521 - 8 miles west of Wadsworth Wadsworth, Texas Dates: July 6-15,1999 l
l Inspectors: H. Bundy, Chief Examiner, Senior Reactor Engineer, Operations Branch l G. Johnston, Senior Reactor Engineer, Operations Branch
! R. Lantz, Reactor Engineer, Operations Branch
! S. McCrory, Senior Reactor Engincer, Operations Branch j T. Meadows, Senior Reactor Engineer, Operations Branch l Accompanying T. Stetka, Examiner-in-Training, Senior Reactor Engineer, Operations Branch Personnel:
l Approved By: John L. Peliet, Chief, Operations Branch Division of Reactor Safety l
l l ATTACHMENTS:
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l Attachment 1: Supplemental Information l l
l Attachment 2: Simulation Facility Report !
Attachment 3: Final Written Examinations and Answer Key l
l l l 440-7Jo o/-2/~
EXECUTIVE
SUMMARY
South Texas Project Electric Generating Station, Units 1 and 2 NRC Inspection Report No. 50-498/99-301; 50-499/99-301 NRC examiners evaluated the competency of 9 senior operator and 8 reactor operator license applicants for issuance of operating licenses at the South Texas Project Electric Generating Station. The licensee developed the initial examinations using NUREG-1021, Revision 8. NRC examiners reviewed and approved the examinations. The initial written examinations were administered to all 17 applicants on July 2,1999, by facility proctors in accordance with the guidance in NUREG-1021, Revision 8. The NRC examiners administered the operating tests on July 6-15,1999.
Operations
- All 17 applicants passed the examinations and exhibited no broad knowledge or training weaknesses. The applicants performed well during the operating test while exhibiting good oversight and peer checking. Consistent with past observations, the applicants demonstrated strong communications skills throughout the operating test as did the plant control room personnel during special activities (Sections 04.1 and 04.2).
- The licensee submitted an examination of excellent quality in that it was technically accurate, responsive to the examination standards without significant changes from NRC review, and required no post examination changes to the grading keys. Detailed licensee process procedures contributed to excellent performance by the examination development and administration team (Section 05.1.2).
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Report Details Summarv of Plant Status Both units operated at power for the duration of this inspection.
- 1. Operations 04 Operator Knowledge and Performance 04.1 initial Written Examination
- a. Insoection Scope On July 2,1999, the facility licensee proctored the administration of the written examinations approved by the NRC to eight individuals who had applied for initial reactor operator (RO) licenses, four individuals who had applied for initial instant senior operator (SO) licenses, and five individuals who had applied for upgrading their RO operator licenses to SO licenses. The licensee proposed grades for the written examinations and evaluated the results for question validity and generic weaknesses.
The examiners reviewed the licensee's results.
- b. Observations and Findinas All applicants passed the written examination. The minimum score was 80 percent.
The overal! average score was 89.4 percent. Applicant scores ranged from 83 to 95 percent. The licensee's post-administration analysis identified that five questions were missed by 50 percent or more of the applicants for each examination. Two of these questions were common to both examinations. The questions missed were RO 3, RO 88, RO 90, SO 19, SO 20, SO 70, RO 87/SO 91, and RO 91/SO 93. The chief examiner determined that the erroneous answers were not interrelated and no broad training or knowledge weaknesses were identified. There were no post-examination comments or changes to the written examination.
- c. Conclusions All 17 applicants passed the written examinations. No broad knowledge or training weaknesses were identified as a result of evaluation of the graded examinations.
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~ 04.2 initial Operatina Test l
Inspection Scope
- a. )
The examination team administered the various portions of the operating examination to the 17 applicants on July 6-15,1999. Each applicant participated in the appropriate number of dynamic simulator scenarios. Each RO and instant SO applicant received a walkthrough test, which consisted of tasks in 10 system and 4 administrative areas. The upgrade SO applicants were tested in five system and four administrative areas.
- b. Observations and Findinas l
l All applicants passed all portions of the operating test. Overall, the applicants l performed well in the dynamic simulator scenarios with good oversight and peer checks.
l Consistent with past practices at this facility, the examiners observed strong l communications throughout the operating test. Good crew briefs and status updates I
were consistently practiced in a form meeting licensee expectations. Communications clearly identified expected actions with consistent acknowledgment by the operators.
During the examinations the examiners observed similar communication practices by Unit 2 control room personnel when several special activities were in progress.
l The applicants researched and applied technical specifications appropriately and l correctly applied abnormal and emergency procedure entry conditions during the l dynamic scenarios. The applicants demonstrated a high level of proficiency in operating plant equipment from the simulator control room and in correctly locating and simulating operating local plant components. The examiners observed one minor knowledge deficiency by several applicants who did not know that the startup feedwater pump should start with the control room hand switch in the " AUTO" position if one of the two operating main feedwater pumps tripped.
l c. Conclusions l
l All 17 applicants passed the operating tests. The applicants performed well during the l
operating test while exhibiting good oversight and peer checking. Consistent with past observations, the applicants demonstrated strong communications skills throughout the operating test as did the plant control room personnel during special activities.
05 Operator Training and Qualification 05.1 Initial Licensina Examination Development ,
l The facility licensee developed the initial licensing examination in accordance with l guidance provided in NUREG-1021," Operating Licensing Examination Standards," ;
Revision 8. l l
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l 05.1.1_ Examination Outline i'
- a. Inspection Scope The facility licensee submitted the initial examination outlines on January 25,1999. The chief examiner reviewed the submittal against the requirements of NUREG-1021, j Revision 8.
- b. Observations and Findinas Region IV approved the initial examination outlines with very minor comments and l advised the licensee to proceed with examination development. The licensee supported the outlines well with background information such as scenario overviews and probabilistic risk assessment relationships, which greatly facilitated the NRC reviews.
- c. Conclusions The licensee submitted well supported examination outlines wh.ch Region IV approved with minor comments.
05.1.2 Examination Packaae
- a. Insoection Scope The draft examinations were transmitted by the licensee to the NRC on April 21,1999.
The licensee submitted the completed final examination package on June 24,1999, following the chief examiner's onsite review. The chief examiner reviewed the examinations against the requirements of NUREG-1021, Revision 8.
- b. Observations and Findinas The licensee submitted a technically valid draft examination of excellent quality that was responsive to the outline submitted by the licensee on January 25,1999. Following two independent examiner reviews, the chief examiner provided editorial and enhancement suggestions for 10 questions. The comments generally related to distractor plausibility.
After discussion of the suggested enhancements, the licensee modified the examinations as agreed. The NRC reviewers observed that the submitted examination appeared to discriminate at a very high level. In response, the licensee performed a further validation of the examination and proposed modification of seven and replacement of four questions with substitutes, which discriminated at a lower level. The chief examiner concurred with the resolution of the comments, the proposed question modifications and replacements, and the final product.
The licensee submitted four scenarios including a backup that were of excellent quality.
The NRC reviewers had no comments following in-office reviews. The chief examiner
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l validated the four scenarios during the week of June 14,1999, and determined that Scenario 1 was unusually complex and lengthy for initial license applicants and discriminated at too high a level. The chief examiner further determined that Scenario 4 (backup scenario) discriminated at an appropriate level and it was modified to serve as a I primary scenario.
To support the systems walkthrough section of the operating test, the facility licensee l
provided 11 job performance measures (JPMs) of excellent quality to evaluate selected -
operator tasks. Ten of the JPMs were common to the RO and instant SO applicants.
The upgrade SO applicants were evaluated on four of the common JPMs plus one unique JPM. The examiners provided a few minor enhancement comments and the licensee made minor changes to several JPMs during the chief examiner's onsite i review. !
To support the administrative topics section of the operating test, the licensee submitted nine administrative JPMs. This provided a unique set of five administrative JPMs for each applicant license level with the exception that the same JPM was used to evaluate the radiation control topic for either license level. In addition to minor enhancement comments, the examiners viewed one JPM to be too complex and another JPM to be too simplistic to discriminate at the appropriate level and the licensee replaced them during the chief examiner's onsite review.
The licensee facilitated the examination development and administration process .
through detailed licensee written procedures, which contributed to excellent l performance by tlie examination development and administration team. No changes to the grading keys were required as a result of post examination review. Stated '
objectives for the examination validation process were particularly useful. The licensee compiled all operating test materials in a manner, which greatly facilitated administration.
- c. Conclusions The licensee submitted an examination of excellent quality in that it was technically accurate, responsive to the examination standards without significant post review changes from NRC review, and required no post examination changes to the grading keys. Detailed licensee process procedures contributed to excellent performance by the examination development and administration team.
05.2 Simulation Facility Performance l
- a. Inspection Scope
- The examiners observed simulator performance with regard to fidelity during the examination validation and administration.
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l b. Observations and Findinas The simulation facility supported the validation and administration of the operating test well. Proposed job pedormance measures and dynamic scenarios ran on the simulator as designed. No simulator issues arose during validation and the two simulator issues discussed in Attachment 2 had minor impact on examination administration.
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- c. Conclusions I
The simulator and simulator staff supported the examination well.
V. Manaaement Meetinas X1 Exit Meeting Summary The examiners presented the inspection results to members of the licensee management at the conclusion of the inspection on July 14,1999. The licensee l acknowledged the findings presented.
l The licensee did not identify as proprietary any information or materials examined during this inspection.
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p ATTACHMENT 1 SUPPLEMENTAL INFORMATION
! PARTIAL LIST OF PERSONS CONTACTED 1
Licensee P. Arrington, Licensing Administrator J. Calvert, Operations Training Manager K. Coates, Nuclear Training Department Manager M. DeFrees, Lead Instructor, Licensed Operator Training l W. Dowdy, Unit 2 Operations Manager l R. Lovell, Generations Support Manager B. Markham, Senior Operator Training Instructor B. Mookhoek, Licensing Administrator B. Neurohr, Senior Operator Training Instructor J. Sheppard, Vice President, Engineering and Technical Services l K. Struble, Senior Operator Training Instructor K. Turner, Senior Operator Training Instructor T. Werk, Project Lead for Examination Development 1
NRC G. Guerra, Resident Inspector W. Sifre, Resident inspector i
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ATTACHMENT 2 SIMULATION FACILITY REPORT
. Facility Licensee: STP Nuclear Operating Company Facility Docket: 50-498;50-499 Operating Examinations Administered at: STP Electric Generating Station, Units 1 and 2 Operating Examinations Administered on: July 6-15,1999 These observations do not constitute audit or inspection findings and are not, without further verification and review, indicative of noncompliance 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 license action is required in response to these observations.
Deficiencies identified Durina Examination Preparation None Deficiencies identified Durina Examination Administration
- During performance of Scenario 3, Drain Valves FV-7952, -7953, and -7954 did not open as expected upon trip of Steam Generator Feedwater Pump No.12.
- The non-safety grade plant computer (ERFDADS) did not initialize properly when establishing the initial conditions for Scenario 3. After some delay the simulator staff was able to force it to properly initialize, but they could not determine why the extra steps were necessary.
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I ATTACHMENT 3 FINAL WRi1 TEN EXAMINATION AND ANSWER KEYS l l
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ES-401 Site-Specific Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission N. .
j Site-Specific ,'N.
l Written Examination 'N l Applicant Information Name: Region: IV - >=*-
Date: 7/2/99 Facility / Unit: South Texas Project -
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License Level: SRO ~ Reactor Type: W.
l Start Time: Finish Time:
Instructions I
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.
I Examination papers will be collected five hours after the examination starts.
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Applicant Certification _
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! All work done on this examination is my own. I have neither given nor received aid. l l
l l Applicant's Signature l
l Results Examination Value . -
Points Applicant's Score Points Applicant's Grade Percent NUREG-1021, Revision 8
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- ne n i not USd any unaumorded 13 e A : rB: : C: :D' <E^ 63 -A7 'B: :C tD;tE: references. I understand that I am not to remove any 14 A B C D E 64 A B C D E- of the examination materials from this room.
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1 O- 16 A B C D E 66 A 8 C D E y 17 : A : 'B- C :D -E 67 :A' -B: :C: :D: rEr 55 - 18 A B C D E 68 A B C D E O- Student Signature Date 19 c A i B -- C D- -E 69 -A- -B" ~C-"Da rE-l M " 20 A' B C D E 70 A B C D -E-O !1 r Aa rB: :C: :D: :E: 71 cA :Ba :Cs eD2 tEs l O' 22 - A - B- C D' E 72 A B -C- D :E E- 23 r A s eB3 tC' cDs tE' 73 r As e B, t C, c D 3 rE' l
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I signify that I have had the opportunity to review 24 A B' C D E 74 A B- C D -E my graded exam and am satisfied that I understand 1 -
25 r A2 rB: rC: :D: cEa 75 :A7 rB; cc: :Dr tE: the correct answer for those questions I missed.
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STP Senior Reactor Operator Exam Question 1 Assuming the following:
- Reactor tripped from 100% power equilibrium conditions
- Boron concentration remains the same
. Tave is at the no-load value Which ONE of the following conditions will result in the HIGHEST critical rod height?
A reactor startup:
A. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following the trip B. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> following the trip C. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the trip D. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> following the trip l
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STP Senior Reactor Operator Exarn Question 2 Given the following:
- RCS Tavg is 567 "F and stable
- Pressurizer pressure is 1737 psig and decreasing
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- Pressurizer level is 28% and increasing {
- Containment pressure is 0.1 psig and stable
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1 Which ONE of the following events has occurred?
A. Steam generator tube leak B. Loop C sample line rupture i
C. Stuck open pressurizer PORY D. Small steam line break in containment i
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STP Senior Reactor Operator Exam Question 3 Unit 2 was operating at 75% reactor power with the turbine in IMP OUT when a single control rod dropped into the core. OPOP04-RS-0001, Control Rod Malfunction, directs the operator to maintain Tavg by adjusting turbine load and /or boron concentration.
Which ONE of these statements is true concerning reactor power if Tave is returned to the same temperature which existed prior to the event?
A. If ONLY turbine load is adjusted, reactor power will be 75%.
B. If ONLY turbine load is adjusted, reactor power will be >75%.
C. If ONLY boron concentration is adjusted, reactor power will be 75%.
D. If ONLY boron concentration is adjusted, reactor power will be <75%.
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S FP Senior Reactor Operator Exam Question 4 Annunciator window 9M01/E8, SEISMIC EVENT, alarms in the Unit 2 Control Room.
Which ONE of the following describes how the Unit 2 Control Room staff can verify the alarm validity?
A. Check the Seismic Monitoring System Panel (CP013) located at the rear of the Unit 2 control room.
B. Check the Seismic Monitoring page on the QDPS Computer.
C. Check the Seismic Monitoring inputs to the Plant Computer.
D. Contact the Unit 1 Control Room.
Page 4 of 100
STP Senior Reactor Operator Exam Question 5 Given the following conditions:
. Unit 1 is operating at 75% power
. Condensate pump 13 is out of service for maintenance
. Power is being increased at 10% per hour Condensate Pump 11 trips from UNKNOWN causes.
Which ONE of the following is the appropriate action per the COND PMP TRIP annunciator response?
A. Stop the power increase and stabilize Deaerator level at the present power level.
B. Attempt to restart Condensate Pump 11, then continue the power increase once it is running.
C. Commence a power decrease to less than 50% at 5% per minute.
D. Trip the turbine and stabilize Deaerator level at no load conditions.
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I STP Senior Reactor Operator Exam l Question 6 l
1 l A Plant Operator is required to perform an extensive valve lineup in an area where the radiation level is 200 mrem / hour. The Plant Operator's current annual Total Effective Dose Equivalent (TEDE) is 1600 mrem.
liow long can the Plant Operator work in this area and not exceed STP's Administrative Action l Level (AAL) for annual TEDE?
A. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l
B. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> C. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l
D. 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> 1
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I STP Senior Reactor Operator Exam Question 7 l
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- Preparations are being made to enter a radiologically controlled area with a general area dose rate of 75 mrem /hr.
Which ONE of the following would be the FIRST to exceed his/her 10CFR20 Dose Limits?
A. Plant worker with a year-to-date exposure of 1350 mrem (TEDE) l B. Working Visitor with a year-to-date exposure of 0 mrem (TEDE)
C. Declared pregnant worker with a to date exposure of 425 mrem (DDE) during the pregnancy l D. Contract employee with a year-to-date exposure at all sites of 1875 mrem (TEDE) l l
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( STP Senior Reactor Operator Exam l Question 8 OPGP03-ZG-0050, Radiation Protection Program, provides for an extension ofindividual occupational dose. A request to extend an individuals annual dose limit to 3000 mrem /yr has been submitted.
Which ONE of the following signature combinations is necessary to approve the extension request?
A. Responsible Depanment Manager & Radiation Protection Manager.
j B. Responsible Department Manager & Plant Manager.
l l C. Radiation Protection Manager & a Senior Management Team member.
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! D. Plant Manager & a Senior Management Team member.
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STP Senior Reactor Operator Exam Question 9 A high radiation alarm is received in the Control Room on RT-8066, Control Room Area Monitor.
Which ONE of the following is an action that would be implemented in accordance with OPOP04-RA-0001, Radiation Monitoring System Alarm Response?
A. Verify all three trains of Control Room HVAC have automatically started and are running in the emergency mode.
B. Prepare the Unit for a Technical Specification required shutdown if the monitor does not j return to nonnal within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. j C. Dispatch an operator to Health Physics to obtain ALNORs for the Control Room Staff.
D. Contact Health Physics to determine the validity of the alarm.
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STP Senior Reactor Operator Exam Question 10 A rupture has occurred in a Reactor Head Degassing System Storage Tank.
Which ONE of the following Area Radiation Monitors would be the first to reach alarm conditions as a result of this event? (assume all setpoints are the same)
A. RE-8097, PASS Lab B. RE-8060, MAB Floor Drain Area C. RE-8061, CCW Coolers D. RE-8068, Rad Waste Control Room l
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I STP Senior Reactor Operator Exam Question 11 While operating at 15% power, a steam generator tube leak of approximately 85 gallons per day occurs.
l Which ONE of the following is the LEAST reliable method of tube leakage detection at this l power level?
l l A. N-16 Primary to Secondary Leak Monitor l
l B. SG Blowdown Radiation Monitor l C. SG Main Steam Line Radiation Monitor
- D. CARS Radiation Monitor 1
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STP Semor Reactor Operator Exam Question 12 Which ONE of the following Area Radiation Monitors would require that the unit be shut down if the monitor were out of service for greater than 7 days?
l A. RT-8050, RCB High Range Area Monitor B. RT-8090, SFP Area Monitor C. RT-8059, Waste Gas Area Monitor D. RT-8096, Emergency Operations Facility Area Monitor l
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l STP Senior Reactor Operator Exam Question 13 l
A Waste Monitor Tank release is in progress when a high alarm is received on RT-8038, LWPS l Monitor.
l l Which ONE of the following describes how the Reactor Operator can verify the release has been terminated?
The position of WL-FV-4077, LWPS Discharge Valve, can be verified by:
A. checking the valve position indicating lights on CP-018 in the Control Room. ,
I l B. dispatching an operator to check the valve position indicating lights on the Radwaste l l Control Room panel.
C. checking the LWPS system screen on the ERFDADS computer.
D. dispatching an operator to check the valve position indicating lights on the TGB local j control panel.
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STP Senior Reactor Operator Exam j Question 14 Per OPGP03-ZF-0018, Fire Protection Operability Requirements, which ONE of the following identifies the minimum operability requirements for the Fire Protection Water Supply System?
i Storage Tank Volume Number of Pump Capacity callons per tank Pumps in com A. 200,000 2 2500 B. 250,000 1 2000 C. 300,000 2 2500 D. 350,000 1 2000 I
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! STP Senior Reactor Operator Exam l Question 15 i
l Which ONE of the following is the LOWEST Emergency Plan Classification at which the Emergency Response Data System (ERDS) must be activated?
A. Unusual Event B. Alert C. Site Area Emergency D. General Emergency I
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STP Senior Reactor Operator Exam Question 16 h
Unit 1 is in Mode 1 at 100% power when the following occurs:
. 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> - Fire reported in the Unit 1 Relay Room and fire brigade dispatched
. 1308 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.97694e-4 months <br /> - OPOP04-ZO-0001, Control Room Evacuation procedure is entered
. 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> - Control Room actions of OPOP04-ZO-0001 are complete
. 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br /> - Communications established between ASP and Remote Stations
. 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> - Control of SG 1D PORV and #14 AFW Pump are transferred to ASP Based on the above timeline, which ONE of the following Emergency Classifications is appropriate for this event?
A. Unusual Event B. Alert C. Site Area Emergency D. General Emergency 1
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i STP Senior Reactor Operator Exam Question 17 i Which ONE of the following contains only instruments listed in LCO 3.3.3.6 Accident i
Monitoring Instrumentation Table 3.3-10.
Containment Intermediate Th (WR) SG Level Water Level Range NIs (WR)
(NR) i A. X X X l
B. X X X I J
- c. x x x D. X X X l
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STP Senior Reactor Operator Exam Question 18 l Given the following:
. Unit 1 is in Mode 6
. 18 fuel assemblies have been reloaded afler a complete core off-load
. RHR Train l A is in service maintaining RCS temperature at 97 oF
. RHR Train 1 A loop boron concentration was 2870 ppm on the last sample
. Source Range N-31 indicates 2 cps
. Source Range N-32 indicates 3 cps and is selected for audible count rate indication
. Both Extended Range channels N-45 and N-46 are INOPERABLE I
in accordance with OPOP08-FH-0009, Core Refueling, which ONE of the following conditions i requires suspension of Core Alterations?
A. Both Source Range channel indications unexpectedly increase to 7 cps.
B. RHR Train l A inlet temperature is 103cF on the next successive reading.
C. RHR Train I A boron concentration is 2860 ppm on the next successive sample.
D. Direct communications is lost between the RCB and the FHB Fuel Handling personnel.
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STP Senior Reactor Operator Exam Question 19 While operating the Refueling Machine, which ONE of the following will prevent the operator from disengaging the fuel gripper and dropping an assembly?
The fuel gripper will not disengage unless the:
A. SLACK CABLE light is lit.
B. GRIPPER UP ENGAGED light is extinguished.
C. GRIPPER MAST DOWN light is lit.
D. TRANSFER PERMISSIVE light is lit.
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STP Senior Reactor Operator Exam Question 20
?
Unit 2 is in Mode 6 with the following conditions:
. A fuel assembly was dropped in the reactor cavity.
. OPOP04-FH-0001, Fuel liandling Accident, was entered.
. The containment building has been evacuated.
. Health Physics has verified that dose rates and airborne radioactivity levels on the refueiing deck are acceptable.
. The refueling crew has requested entry into the containment building to begin recovery ,
I actions.
Per OPOP04-Fli-0001, which ONE of the following individuals must give permission to allow the refueling crew to enter containment?
A. Shift Supervisor B. Operations Manager C. Technical Services Department Manager D. Plant Manager l l
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STP Semor Reactor Operator Exam Question 21 Unit 2 is conducting a reactor startup with the following conditions:
- Plant is at no-load temperature and pressure e Control Banks A and B are fully withdrawn from the core
. Control Bank C is being withdrawn from the core Source Range Detector N-31 output fails low.
Which ONE of the following indicates the actions required by Technical Specifications?
A. Irnmediately stop the withdrawal of Control Bank C.
B. Insen Control Banks A, B and C fully into ;he core within I hour.
C. Immediately initiate and continue emergency boration at greater than or equal to 30 gpm until Cold Shutdown xenon free boron concentration is achieved.
D. Reactor startup may continue provided an operable Extended Range Monitor is available to be substituted for N-31.
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STP Senior Reactor Operator Exam Question 22 The following conditions exist on Unit 1:
- Plant startup is in progress per OPGP03-ZG-0005, Plant Stanup to 100%
- Reactor Power is 4%
- Tavg is currently 569 "F
= Annunciator window 5M02/E6, T REF / AUCT T AVG DEV is received Which ONE of the following identifies actions that must be taken in accordance with the annunciator response procedure?
A. If Tavg is high, insert control rods to lower Tavg B. If Tavg is low, withdraw control rods to increase Tavg to 2 571 F C. Record Tavg at least once per hour to ensure it is within il.5 F of Tref D. Verify Tavg is greater 2 561 F at least once every 30 minutes 1
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STP Senior Reactor Operator Exam Question 23 Which ONE of the following is a requirement found in the Conduct of Operations Manual?
A. The required minimum Shift Compliment for Unit 1 and Unit 2 Combined is 4 SROs, 5 ROs, and 10 Plant Operators.
B. As a minimum, the Energy Management and Control System (EM ACS) should be updated once per week.
C. Thermal overload devices may be reset once with the permission of the Unit Supervisor.
D. The Reactor Operator may decide to allow a nuisance alarm to continue flashing if he has determined there is no operational impact.
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STP Senior Reactor Operator Exam
, Question 24 L
l You have been directed to perform Lineup 1, Electrical Lineup, of 0 POP 02-DB-0003, Balance of l Plant Diesel Generator.
l Which ONE of the following correctly describes the procedure usage requirements in effect for l this task? (Cover page of 0 POP 02-DB-0003 is attached) l The lineup can be performed provided:
1
! A. there is a current working copy of the procedure in the Turbine Building Basement Operators Station.
l B. you review a current working copy of the procedure first.
! C, you have a current working copy of the lineup with you during performance of the lineup.
D. you are in radio contact with a Reactor Operator in the Control Room.
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f(>6M13e 95'?o /69'?
SOUTil TEXAS PROJECT ELECTRIC GENERATING STATION D0527
=="l=;~"* " " " "
_ , nm. ,,, u . . . -. 0 POP 02-DB-0003 Rev.15 l'are i d 19 Balance of Plant Diesel Generator Non Quality Non Safety-Related Usage: IN IIAND Effective Date: 05/19/98 M P mit PJ Bengel Crew IE Operauons PREPARER TECHNICAL USER COGNIZANT DEPT.
Usage Table of Contents Pace 4 1.0 Purpose . . . . . . . . . . . . . . . . . . .. . . .2 4 2.0 References . . . . . . .. . . . .. .. . .2 3 3.0 Prerequisites.. . . ... ... . . .. . .3 3 4.0 Notes and Precautions . . .. . ..
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1 5.0 Aligning Balance of Plant (BOP) Diesel Generator (DG) for Automatic Response. .6 1 6.0 Manual Starting of BOP DG . .. . . . .. .. . .. . .9 1
7.0 Unloading and Securing BOP DG. . . . . .. . .11 4 8.0 Support Documents . . . . ..
.I2 l Lineup 1, Electrical Lineup . . . . ... . . . . . . . . .13 i Lineup 2, Valve Lineup. ... . .. . . . . . . . . , .. .15 1
Logsheet 1, BOP DG Logsheet.. . . . .. . . .. I 8 Usace I
l - IN ii AND 1 2 - IN HAND CONTROLLING STATION 3 - REFERENCED 4- AVAILABLE l
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STP Senior Reactor Operator Exam Question 25 The Unit 1 EAB Watch while doing rounds finds the following conditions locally at the Diesel Generator 11:
- Starting Air Receiver #11 pressure indicates 95 psig
- Starting Air Receiver #12 pressure indicates 225 psig Which ONE of the following states the condition of DG 11and why? l l
A. OPERABLE; because Starting Air Receiver #12 is > 175 psig.
B. INOPERABLE; because both Starting Air Receivers are required to be > 175 psig.
C. INOPERABLE; as long as Starting Air Receiver #11 is < 100 psig.
D. OPERABLE; as long as Starting Air Receiver #11 remains > 90 psig.
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STP Semor Reactor Operator Exam Question 26 A License Compliance Review (LCR) is being performed in accordance with OPAP01-ZA-0103, License Compliance Review, for a proposed change to the SG Blowdown System operating alignment. The individual preparing the LCR has answered Question #2 "Does the subject of this review involve a change to the procedures as described in the S AR" as YES.
Which ONE of the following describes how the proposed change will be processed?
The LCR will:
A. not be completed, an Unreviewed Safety Question Evaluation (USQE) will be performed per OPGP05-ZA-0002,10CFR50.59 Evaluations.
B. not be completed, a change to the UFSAR will be prepared per OPGP05-ZN-0004, Changes to Licensing Basis Documents.
l C. be completed, then a change to the UFSAR will be prepared per OPGP05-ZN-0004, Changes to Licensing Basis Documents.
D. be completed, then an Unreviewed Safety Question Evaluation (USQE) will be performed per OPGP05-ZA-0002,10CFR50 Evaluations.
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STP Senior Reactor Operator Exam Question 27 Given the following conditions:
. Troubleshooting under a work package is in progress on Circulating Water Pump 11 to determine why the pump will not stan.
. Several leads in the start pennissive circuitry for Circulating Water Pump 11 have been litied and pump start verified during troubleshooting.
. Due to increasing bearing temperature on Circulating Water Pump 14, Plant Management has decided to operate Circulating Water Pump 11 with the lifted leads and secure Circulating Water Pump 14 in order to keep the unit in operation.
Which ONE of the following indicates how Circulating Water Pump 11 would be restored to operation?
A. Retum the pump to operation maintaining the work package open. Continue troubleshooting when the pump can be secured.
B. Close the existing work package and retum the pump to operation. Then write a new work package to continue troubleshooting when the pump can be secured.
C. Install a temporary modification for the lifled leads, then retum the pump to operation.
D. Retum the pump to operation, then approve a design change to incorporate the lifted leads.
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i STP Senior Reactor Operator Exam Question 28 Which ONE of the following is the BASIS for the Auxiliary Feedwater Storage Tank minimum level of 485,000 gallons?
Contains sufficient inventory, without makeup, to maintain the plant in liot Standby for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followed by a cooldown to:
)
A. 200 *F at 25 *F/hr.
B. 200 *F at 100 *F/hr.
1 C. 350 *F at 25 *F/hr.
D. 350 *F at 100 *F/hr.
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STP Senior Reactor Operator Exam Question 29 OPOP05-EO-EC00, Loss of All AC Power, step 4 contains the action to " VERIFY AFW Flow -
GREATER TliAN 576 GPM."
l Which ONE of the following statements describes the BASIS for this step?
A. Ensure minimum flow is provided for the running AFW pumps.
B. Ensure NONE of the steam generators reach dry out conditions.
C. Ensure an adequa'e heat sink is maintained for heat removal.
D. Ensure a RCS cooldown is commenced.
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I STP Senior Reactor Operator Exam Question 30 Given the following:
. Unit 2 experienced RCS leakage into containment
. The crew entered OPOP04-RC-0003, Excessive RCS Leakage
. The unit was ramped down to 43% power where it was tripped and Safety Injection initiated
. Currently the crew is at step 5 of 0 POP 05-EO-ES12, Post LOCA Cooldown and ;
Depressurization preparing to initiate a RCS cooldown using the steam dumps {
I Current plant conditions are:
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+ Containment Pressure: 2.3 psig '
+ RCS Pressure: 1600 psig
+ Przr Level: 6%
+ Tave: 567 *F
+ RCPs: 4 running
+ SG Pressures: 1183 psig
+ SG NR Levels: 22-30%
Which ONE of the following statements describes the relationship of SG heat removal to break flow heat removal at this time?
A. SGs remove all the decay heat; break flow removes no decay heat. ,
i B. SGs remove almost all the decay heat; break flow removes very little decay heat.
C. SGs remove very little decay heat; break flow removes almost all the decay heat.
D. SGs remove no decay heat; break flow removes all the decay heat.
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STP Senior Reactor Operator Exam Question 31 Given the following conditions:
. Operators are performing the actions of OPOP05-EO-FRH1, Response to Loss of Secondary Heat Sink
. AFW pump 1I was just re-started
. SG A, B, C, and D WR Levels are 30%,45%,47%, and 42% respectively Which ONE of the following indicates the action to be performed by the operators?
A. Increase total AFW flow to greater than 576 gpm.
B. Commence filling each SG at a rate not to exceed 100 gpm.
C. Commence filling SGs B, C, and D at a rate not to exceed 100 gpm each.
D. Actuate Safety Injection and open both Pressurizer PORVs.
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STP Senior Reactor Operator Exam Question 32 Unit 2 is recovering from a Loss of Offsite Power with the following conditions:
. Reactor is tripped
. All Reactor Coolant Pumps (RCP) are off and cannot be started
. The Primary Reactor Operator is directed to verify natural circulation cooling exists in which ONE of the following sets of conditions can natural circulation cooling be verified to exist?
Time Core Exit RCS Tu ( F) Tc ("F) S/G Press.
T/Cs ("F) Subcooling (psig)
("F) 0400 560 36 557 536 916 A.
0430 555 32 552 532 886 1
0400 560 40 558 540 940 B.
0430 560 36 557 528 830 0400 560 42 557 536 916 C.
0430 555 41 552 532 886 0400 560 40 558 540 948 D.
0430 564 43 560 544 980 eaye n or no
i STP Senior Reactor Operator Exam Question 33 The following conditions exist on Unit 1:
. Small break LOCA has occurred
. All equipment is operating as designed
. Tavg is 569 *F and increasing
. Pressurizer pressure is 1490 psig and decreasing l
. AFWST level is 490,000 gallons and decreasing
. Operators are performing steps in OPOP05-EO-EOOO, Reactor Trip or Safety injection Which ONE of the following explains why the operators must trip the RCPs under these l
conditions?
A. Conserve AFWSTinventory B. Protect the RCP #1 seals i
C. Stop the RCS heatup D. Conserve RCS inventory i
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STP Senior Reactor Operator Exam Question 34 The following conditions exist on Unit 1:
. CETs indicate 1225 F
. RVWL indicates 0% Plenum Level j
. RCS pressure is 2280 psig l . SG A, B, C, D WR Levels are 7%,10%,8%,20% respectively i
. Operators are performing the actions of 0 POP 05-EO-FRCl, Response to Inadequate Core Cooling Which ONE of the following describes the operator actions for this condition as required by OPOP05-EO-FRCl?
I l A. Start an RCP to provide temporary cooling for the core.
l l B. Open accumulator outlet valves to inject additional water into the RCS.
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C. Start a HHSI pump to supply water to the RCS.
D. Start a CCP to supply additional water to the RCS.
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f STP Senior Reactor Operator Exam
! Question 35 l
Given the following Unit 2 conditions:
l
. A Small Break LOCA has occurred
. Si has been reset
. Operators havejust completed step 1 of OPOP05-EO-E010, Loss of Reactor or Secondary Coolant The Shift Technical Advisor repons the following:
+ RCS pressure - 1830 psig and stable
+ RCS subcooling - 60 "F
+ Pressurizer level - 15%
+ SG A, B, C and D NR Levels are 8%,10%,17% and 19% respectively
+ Total AFW flow - 400 gpm
+ Adverse containment conditions do NOT exist l l
Which CNE of the following actions will the operators perform?
A. Manually actuate SI and transition to OPOP05-EO-E000, Reactor Trip or Safety Injection B. Transition to OPOP05-EO-FRH1, Response to Loss of Secondary Heat Sink C. Transition to OPOP05-EO-FRP2, Response to Anticipated Pressurized Themial Shock Condition D. Transition to OPOP05-EO-ES11, St Termination l
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S1 P Semor Reactor Operator Exam Question 36 I
The following have occurred:
l . LOCA outside containment
. Transfer to Cold Leg Recirculation
. Transition to OPOP05-EO-EC11, Loss of Emergency Coolant Recirculation OPOP05-EO-EC11 provides instructions to stop backDow from the RWST to the containment sump to conserve RWST inventory.
Per OPOP05-EO-EC1I which ONE of the following is the correct sequence to stop the backDow?
A. 1. Stop the LHSI, HHSI and CS Pumps
- 2. Close the Containment Sump Suction Valves
- 4. Open the SI Pump Mini Flow Valves
B. 1. Stop the LHSI, HHSI and CS Pumps
- 3. Open the SI Pump Mini Flow Valves
- 4. Close the Containment Sump Suction Valves
- 3. Close the Containment Sump Suction Valves
- 4. Open the SI Pump Mini Flow Valves
- 2. Open the S1 Pump Mini Flow Valves
- 3. Close the Containment Sump Suction Valves
- 5. Start the LHSI, HHS1 and CS Pumps as necessary l
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l STP Senior Reactor Operator Exam Question 37 Given the following conditions:
. Unit 2 is operating at 100%
. Chemistry reports a 200 gpd tube leak in SG C
. OPOP04-RC-0004, Steam Generator Tube Leakage is in progress
. A power reduction is about to commence Per OPOP04-RC-0004, which ONE of the following indicates when stearn flow from SG C should be isolated?
A. Right afler the power decrease has commenced B. When power has decreased to less than 50%
C. Right after the main turbine is tripped D. When it is determined that SG C level cannot be maintained greater than 33%
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STP Senior Reactor Operator Exam Question 38 OPOP05-EO-EC31, SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired, directs the operator to monitor RWST level vs. Containment level per Addendum 6.
Which ONE of the statements below is correct?
If the decrease in RWST level:
A. disagrees with the increase in Containment level, a subcooled recovery is desired since a RCP can be started to reduce the cooldown time.
B. disagrees with the increase in Containment level, a saturated recovery is desired to increase the Si flowrate, which will allow a faster transition to cold leg recire.
C. agrecs with the increase in Containment level, a subcooled recovery is desired since long term cooling is assured.
D. agrees with the increase in Containment level, a saturated recovery is desired to lower the leak rate and delay RWST depletion. :
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r STP Senior Reactor Operator Exam Question 39 Given the following:
. An ATWS has occurred
. Operators are performing the steps of 0 POP 05-EO-FRS1, Response to Nuclear Power Generation - ATWS
. Emergency Boration is in service
. MSIVs and MSIBs were closed by the operators
. RCS pressure is 1950 psig and slowly decreasing
. CETs are slowly decreasing
. SG A, C and D pressures are stable
. SG B pressure is decreasing Under these conditions, OPOP05-EO-FRS1 will direct the operators to perform which ONE of the following?
A. Initiate Safety Injection to inject additional borated water from the RWST into the RCS.
B. Isolate AFW to SG B to minimize RCS cooldown.
C. Align the RWST to the charging pump suction to inject borated water from the RWST into the RCS.
l D. Increase AFW flow to SG B to maintain ALL SG levels greater than 14% for adequate heat sink during the ATWS.
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STP Senior Reactor Operator Exam Question 40 While performing a plant heatup in Unit 1 per OPOP03-ZG-0001, Plant Heatup, an unisolable break occurred on the SG D steam line. Cunently, the crew is proceeding through OPOP05-EO-FRP1, Response to Imminent Pressurized Thermal Sheck Condition, due to excessive cooldown. ( FIm' = c a EeA 2 A o d* N Which ONE of the following statements is correct regarding steps that will be taken?
A. The .RCS will be depressurized allowing Si flow to relieve thermal stresses. J B. The charging pump suction will be realigned from the RWST to the VCT to minimize boron precipitation in the core.
C. RCS temperature will be kept stable for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to relieve thermal stresses across the reactor vessel wall.
D. RCP(s) will NOT be restarted because the pressure transient may cause propagation of a flaw in the reactor vessel.
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c STP Senior Reactor Operator Exam Question 41 l
Assuming all plant systems function as designed, which ONE of the following Critical Safety l Functions would degrade to a Red Path condition during a postulated Uncontrolled Depressurization of ALL Steam Generators?
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A. Core Cooling (C)
B. Heat Sink (H)
C. Integrity (P) )
D. Inventory (1) l l
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l STP Senior Reactor Operator Exam Question 42 OPOP05-EO-EC21, Uncontrolled Depressurization of ALL Steam Generators, directs the operator to minimize AFW flow.
Which ONE of the following statements contains the bases for reducing AFW flow to a
! minimum value?
A. Limit RCS cooldown, Prevent SG tube dryout, and Minimize mass release out the fault.
B. Extend the use of the AFWST, Prevent SG tube dryout, and Minimize the RCS-to-SG differential pressure.
C. Limit RCS cooldown, Reduce the number of running AFW pumps, and Minimize the RCS-to-SG differential pressure.
D. Reduce the number of running AFW pumps, Minimize mass release out the fault, and Extend the use of the AFWST. ,
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STP Senior Reactor Operator Exam Question 43 In accordance with OPOP05-EO-EC21, Uncontrolled Depressurization of All Steam Generators, which ONE of the conditions below requires AFW flow to be controlled at 100 gpm to a SG?
A. AFWST Level is < 138,000 gallons (26%)
- 8. NR Level in the SG is < 14%[34%)
i C. NR Level in the SG is > 50%
D. Przr Level cannot be maintained > 8%[44%) '
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l STP Senior Reactor Operator Exam Question 44 l
OPOP05-EO-E020, Faulted Steam Generator Isolation, was entered due to indications of a steam line break in containment and the Operators are performing step 3.
The STA announces the following to the control room:
. An ORANGE condition exists in the Containment Critical Safety Function Status Tree e A RED condition exists in the Integrity Critical Safety Function Status Tree Which ONE of the following describes the actions that should be taken by the control room crew?
A. Immediately stop perfomiance of OPOP05-EO-E020 (do not complete step 3) and transition to OPOP05-EO-FRP1, Response to imminent Pressurized Thermal Shock Condition.
B. Immediately stop performance of OPOP05-EO- EO20 (do not complete step 3) and transition to OPOP05-EO-FRZl, Response to liigh Containment Pressure.
- C. Suspend the performance of OPOP05-EO- EO20 (complete step 3) and transition to l
OPOP05-EO- FRZl, Response to liigh Containment Pressure.
D. Suspend the performance of OPOP05-EO- E020 (complete step 3) and transition to OPOP05-EO-FRP1, Response to Imminent Pressurized Thermal Shock Condition.
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STP Senior Reactor Operator Exam Question 45 While responding to an inadequate Core Cooling situation the operators are directed to reestablish some form of core cooling.
Which ONE of the following statements describes the INITIAL response of the CETs, and the reason for this response, if the operators restarted the safety injection pumps?
l A. Increase due to saturated steam being forced out of the core.
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B. Decrease due to saturated steam forming a frothy two phase mixture.
l C. Increase due to superheated steam being forced out of the core.
D. Decrease due to superheated steam causing injected water to boil forming a frothy two phase mixture.
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I STP Senior Reactor Operator Exam Question 46 Following a reactor trip in Unit 1, a SG Lo-Lo Level signal was generated. The operator notes that AFWP#14 failed to start because the Trip and Throttle Valve (AF-MOV-0514)is closed l with power removed.
Where should the Reactor Operator direct the Plant Operator go to close the MOV breaker?
l A. Non-Class 1E 480VAC LC (1J1)
B. Non-Class 1E 125 VDC SWBD (1 A)
C. Class lE 480 VAC MCC (EIC4)
D. Class 1E 125 VDC SWBD (eld 11) i l
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STP Senior Reactor Operator Exam Question 47 During 100% steady state operation, while the operator is walking down the control boards, several BYP/INOP indicators are received. The operator looks down and notices:
. Containment Spray Pump B Red and Green indicating lights are extinguished.
Which ONE of the following explains the observed indications?
A. Loss of Class 1E 4160V Bus ElB B. Trip of a Class lE 125 VDC SWBD ElBil breaker 5t s ytw at a lo"l C. Trip of a 120 VAC Class Vital Distribution Panel DP1203 breaker Ss/plyM/ a Io'd D. Trip of a 120 VAC Non-Class Vital Distribution Panel DP006 breaker uppNcE g a. locJ i
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I STP Senior Reactor Operator Exam Question 48 l Which ONE of the following indicates the correct sequence for transferring DP-1201 from
- Normal to Emergency power?
A. 1) Verify the Channel i Voltage Regulator Transformer ERV001 A is energized.
- 2) Open the MAIN C.B. NORMAL SOURCE breaker on DP-1201.
! 3) Close the MAIN C.B. EMERG SOURCE breaker on DP-1201.
B. 1) Verify the Channel i Voltage Regulator Transformer ERV001 A is energized.
- 2) Close the MAIN C.B. EMERG SOURCE breaker on DP-1201.
- 3) Open the MAIN C.B. NORMAL SOURCE breaker on DP-1201.
l l C. 1) Open the MAIN C.B. NORMAL SOURCE breaker on DP-1201.
- 2) Close the MAIN C.B. EMERG SOURCE breaker on DP-1201.
- 3) Energize the Channel I Voltage Regulator Transformer ERV001 A.
l D. 1) Close the MAIN C.B. EMERG SOURCE breaker on DP-1201.
- 2) Energize the Channel i Voltage Regulator Transformer ERV001 A.
- 3) Open the MAIN C.B. NORMAL SOURCE breaker on DP-1201.
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l STP Senior Reactor Operator Exam Question 49 1
l Which ONE of the following is the correct sequence for paralleling the main generator to the grid?
A. 1) Place the GEN BKR SYNC SW in the ON position
- 2) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 3) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 4) Close the Main Generator Exciter Field Breaker
- 5) Close the Main Generator Breaker B. 1) Close the Main Generator Exciter Field Breaker
- 2) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 3) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 4) Place the GEN BKR SYNC SW in the ON position
- 5) Close the Main Generator Breaker l
C. 1) Close the Main Generator Exciter Field Breaker J
- 2) Place the GEN BKR SYNC SW in the ON position 1
- 3) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 4) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 5) Close the Main Generator Breaker D. 1) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 2) Place the GEN BKR SYNC SW in the ON position l
- 3) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 4) Close the Main Generator Exciter Field Breaker
- 5) Close the Main Generator Breaker 1
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STP Senior Reactor Operator Exam Question 50 A lockout has occurred on 4.16 KV ESF Bus EI A and OPOP04-AE-0001, Loss of Any 13.8 KV or 4.16 KV Bus has been entered.
Which ONE of the following correctly describes the MOST LIMITING action required by this condition?
If the bus is not restored within:
A. 15 minutes, batteries EI Al1 AND eld 11 must be declared inoperable and the Unit must be placed in Hot Standby within the next 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
B. I hour, OPSP03-EA-0002, ESF Power Availability must be performed every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> due j to DG 11 being inoperable.
C. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the Unit must be placed in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to El AlI battery having both chargers de-energized.
D. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the Unit must be placed in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> due to 4160v bus EI A being de-energized.
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STP Senior Reactor Operator Exam Question 51 The following plant conditions exist:
. Reactor Power is 55%
. Main condenser vacuum is 26 inches Hg and decreasing Which ONE of the following describes the appropriate operator action per OPOPO4-CR-0001, Loss of Condenser Vacuum?
A. Ensure the reactor and main turbine are tripped at 22 inches Hg.
B. Ensure the reactor and main turbine are tripped at 25 inches Hg.
C. Ensure the main turbine is tripped at 22 inches Hg.
D. Ensure the main turbine is tripped at 25 inches Hg.
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F STP Senior Reactor Operator Exam Question 52 l
l Given the following conditions on Unit 1:
. Reactor power is being maintained at 30%
. SGFPs 11 and 12 are in service
. All controls are in automatic SGFP 12 trips due to a loss oflube oil and OPOP04-FW-0002, Steam Generator Feedpump Trip l is entered.
Which ONE of the following describes the immediate operator actions that should be taken?
A. 1) Check the SGFP Master Speed Controller operating correctly.
- 2) Ensure Feed Flow is greater than or equal to Steam Flow.
l B. 1) Start a standby FW Booster Pump. '
- 2) Reduce turbine load.
C. 1) Check the SGFP Master Speed Ccntroller operating correctly.
- 2) Reduce turbine load.
D. 1) Start a standby FW Booster Pump.
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STP Senior Reactor Operator Exam Question 53 Given the following conditions:
. Unit 1 is operating at 100% power
. SGFPs 11,12 and 13 are in service and in AUTO
. Operator notices the speed is increasing on all three SGFPs Which one of the following explains why the speed is increasing on the SGFPs?
A. SG C FWIV failed closed B. SG B controlling steam flow channel failed low C. Steam Header Pressure PT-557 failed low D. SG Feedwater Inlet Pressure PT-558 failed low Page 53 of 100
STP Senior Reactor Operator Exam Question 54 Given the following:
. Unit 1 is performing a Mode 3 cooldown
. RCS is at 520 oF and 1800 psig
. A loss of power occurs on 120 VAC vital distribution panel DP-001
. The crew enters OPOP04-VA-0001, Loss of 120 VAC Class Vital Distribution
. A Plant Operator is directed to locally open the 1 A SG PORV for temperature control OPOP04-VA-0001, cautions the Plant Operator to NOT open the SG PORV more than 50%.
Which ONE of the following is the reason for this caution?
A. Prevent excessive cooldown with limited RCS instrumentation available.
B. Minimize the mass loss out of the l A SG with limited AFW capability.
C. Ensure the ability to reclose the l A SG PORV following opening.
D. Avoid an inadvertent safety injection actuation on low steam line pressure.
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STP Senior Reactor Operator Exam Question 55 )
Unit 1 is operating at 77% power performing a power ascension when the operator notices the following conditions:
- C-20 AMSAC BLOCKED lampbox is illuminated e C-7 TURB IMP PRESS STM DUMP PERMISSIVE lampbox is illuminated ~
e TURBINE POWER P-13 CH I bistable light is illuminated
. TURBINE POWER P-13 CH 2 bistable light is extinguished e Tave is 583.88 F e Trefis 583.93 F e STM DUMP UNBLOCK AVAILABLE light is illuminated ;
Which ONE of the following is responsible for these indications?
A. Turbine Impulse Pressure Transmitter PT-505 has failed low.
B. Turbine Impulse Pressure Transmitter PT-505 has failed high.
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C. Turbine Impulse Pressure Transmitter PT-506 has failed low.
D. Turbine Impulse Pressure Transmitter PT-506 has failed high.
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l STP Senior Reactor Operator Exam l Question 56 Unit 1 is operating at 90% power when the following annunciator and Bistable Monitoring Panel (BSMP) indications are received:
- 5M2/F2 UV RX PRETRIP e BSMP - RCPIB U/V RX TRIP NO other alarms or changes in indications or equipment status are observed.
Which ONE of the following statements is correct?
A. Control of RCP 1 B from the Control Room has been lost.
B. The Auxiliary Bus 1G UV device should have tripped RCP IB.
C. The Reactor Protection System failed to actuate and initiate a reactor trip.
D. The RCP IB UV device has failed.
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STP Senior Reactor Operator Exam Question 57 1
Unit 1 is operating at 100% power when a leak develops in the Component Cooling Water System. OPOPO4-CC-0001, Loss of Component Cooling Water, is entered.
. Level in the CCW surge tank is 63% and decreasing slowly.
Which ONE of the following components is a potential source of the leak?
A. Letdown Heat Exchanger (Hx)
B. Reactor Coolant Pump IC motor air cooler I
C. Reactor Coolant Drain Tank lix D. Excess Letdown Hx Page 57 of 1(F) l
STP Senior Reactor Operator Exam l Question 58 l
l The plant has experienced a Large Break LOCA. The crew is performing the actions of 0 POP 05-EO-E000, Reactor Trip or Safety Injection, to mitigate the event.
At Step 15 of 0 POP 05-EO-EOO0:
i l . The Unit Supervisor directs the Primary RO to " Check if Containment Spray is required".
l . The Primary RO reports that Containment Pressure is 13 psig and that Containment Spray has initiated.
l In accordance with OPOP05-EO-E000, Step 15, which Component Cooling Water (CCW) ,
valve (s) must be verified closed at this time?
CCW valve (s) to and/or from the:
A. Spent Fuel Pool Heat Exchangers B. Excess Letdown Heat Exchanger l
C. CCW Common Header D. Reactor Coolant Pumps l
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STP Sernor Reactor Operator Exam Question 59 Unit 1 is operating at 100% power with the following conditions:
. Annunciator 04M7/A7, RCP 1D SEAL WTR INJ FLOW LO, is illuminated
. Seal injection flow indicates 4.5 gpm for Reactor Coolant Pump (RCP) 1D
. CCW Hx outlet temperature is 90 F
. RCP 1 D lower seal water bearing temperature is 210 "F
. RCP 1 A,1B and IC seal injection flows indicate 8.8 gpm
. Efforts to raise RCP ID seal injection flow by throttling open 1-CV-0032D, RCP 1D SEAL WATER THROTTLE VALVE, have not been successful Per OPOPO4-RC-0002, Reactor Coolant Pump Off Normal, which ONE of the following l conditions must be satisfied in order to maintain RCP 1D in operation?
A. Component Cooling Water flow to RCP 1D thermal barrier is verified >30 gpm.
B. RCP 1 D lower seal water bearing temperature is verified <240 F.
C. RCP 1D number one seal leakoffisolation valve is verified closed. ;
D. RCP 1D number one seal inlet temperature is verified <250 F.
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STP Senior Reactor Operator Exam Question 60 Given the following conditions:
. Unit 1 is in Mode 5
. CCW Trains A and C are in senice
. CCW Train B is selected to STANDBY
. ALL ECW Trains are in service CCW Pump A trips causing common header pressure to decrease to 70 psig. Which ONE of the following is true conceming this event?
CCW Pump B will:
A. start ONLY if the mode selector switch is placed in run.
B. not start because ECW Trains A and C are still in service.
C. start because the common header pressure is less than the low-pressure setpoint.
D. no_1 start because the common header pressure did not decrease to the low-pressure setpoint.
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l STP Semor Reactor Operator Exam Question 61 Unit I was operating at 100% power when a reactor trip and safety injection occurred. Which ONE of the following combinations states the expected valve position for each valve listed?
NNS LOADS SFP HX INL CCW liX 1 A CCW HX 1 A INL ISOL ISOL OUTL TEMP FLOW CONT CONT (MOV-235/236) (MOV-447/032) (MOV-642)
(MOV-643) yx @yptoss A. Closed Open Open Open B. Closed Closed Open Closed C. Closed Closed Closed Closed l
D. Open Closed Closed Open l
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I STP Senior Reactor Operator Exam Question 62 Given the following conditions in Unit 2:
. Plant is in Mode 4 preparing to heat up to Mode 3
. During a surveillance test, CC-MOV-0050, RiiR liX 2A RET OCIV stroked partially closed and then its breaker tripped Which ONE of the following describes the action that must be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the reason for the action?
A. Manually open and de-energize the valve to maintain RIiR Train A operable.
B. Manually open and de-energize the valve to maintain minimum flow requirements for CCW Pump A.
C. Close and de-energize CC-MOV-0049, RliR 11X 2A RET ICIV to maintain CCW Train A operable.
D. C!ose and de-energize CC-MOV-0049, RHR liX 2A RET ICIV to maintain containment integrity.
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STP Senior Reactor Operator Exam Question 63 During the performance of 0 POP 05-EO-ES12, Post LOCA Cooldown and Depressurization, the operator is directed to STOP the LliSI Pumps and place them in AUTO if RCS pressure is greater than 415 psig and stable or increasing.
During subsequent recovery actions, which ONE of the following applies regarding operation of the LliSI Pumps?
A. LHSI Pumps will no longer be required, even if RCS pressure drops uncontrollably, since the RIIR System will be available to be placed in service.
B. LHSI Pumps will no longer be required, even if RCS pressure drops uncontrollably, since HilSI Pumps will be capable of providing sufficient flow to remove decay heat.
C. If RCS pressure drops in an uncontrolled manner to less than 400 psig, the ESF Load Sequencer will restart the pumps.
D. If RCS pressure drops in an uncontrolled manner to less than 400 psig, the operator will be required to manually restart the pumps.
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f l STP Senior Reactor Operator Exam Question 64 Unit I conditions:
. Reactor trip and Safety Injection due to SBLOCA
. RCS pressure stable at 1155 psig
. MODE I LOGIC is reset Subsequently, an unden oltage condition occurs on the ESF buses.
Which ONE of the following describes the effect on Core Cooling?
Upon Emergency Diesel Generator output breaker closure, Core Cooling will be:
A. immediately re-established.
B. automatically re-established within one minute.
l l C. lost until the operator restarts the LHSI Pumps.
l D. lost until the operator restarts the HHSI Pumps.
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STP Senior Reactor Operator Exam Question 65 A MODE Ill actuation of the sequencers has occurred.
In addition to resetting the Safety Injection, which ONE of the following MUST ALSO be performed in order to return the LilSi pumps to a standby condition in AUTO?
A. Reset the sequencer Mode I Logic (locally)
B. Reset SI AUTO RECIRC C. Reset P-4 by closing the Reactor Trip Breakers D. Reset the sequencers (CP-003)
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STP Senior Reactor Operator Exam Question 66 During a reactor startup, the P-6 pennissive is verified at approximately 1.0E-10 amps on the Intermediate Range Nis. At this power level, how much margin exists until the reactor trips due to Source Range Hi-flux 7 Ytw tu r{cdtt %vtet A .k( >
Approximately:
A. one-halfdecade B. one decade C. one and one-half decades D. two decades I
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STP Senior Reactor Operator Exam Question 67 Which ONE of the following describes the effect that a loss of compensating voltage to NI-35 will have on the Reactor Protec ion System (RPS)?
A. On a plant shutdown, when P-10 resets an IR Ifigh Level Trip will occur.
B. At high power, it will cause an IR/PR Rod Withdrawal Block.
C. On a reactor shutdown, P-6 will clear early and a SR liigh Flux Trip will occur.
D. On a reactor shutdown, P-6 will NOT clear and rar.cig zc the Source Range Detectorsy bl,o na uh.d.cM3 to g se e.
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STP Senior Reactor Operator Exam Question 68 Given the following:
. Unit 1 is in Mode 1 at 75% power
. Rod controlis in AUTO
. Control Bank D at 235 steps
. Main turbine control in IMP OUT
. Control rods continuously withdraw for no apparent reason
. Operators place rod control in MANUAL and rod motion stops
. Operators determine that Control Bank "D" rods have withdrawn a total of 10 steps Which ONE of the following conditions would exist?
A. Axial Flux Difference ( AFD) would become more positive (less negative).
B. Overpower Delta Temperature trip (OPDT) setpoint would increase.
C. Nuclear Enthalpy Rise Hot Channel Factor (HCF) would decrease.
D. Quadrant Power Tilt Ratio (QPTR) would increase. ;
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r STP Senior Reactor Operator Exam Question 69 Unit 1 is in Mode 3 preparing to start up the reactor when the following occurs:
- Turbine impulse Pressure channel PT-506 fails high.
Which ONE of the following Reactor Trip signals is ENABLED under these conditions?
I Reactor Trip from:
A. Low Pressurizer Pressure.
B. Loss of Reactor Coolant Flow in 1 Loop.
C. Pressurizer Low Water Level.
D. Turbine Trip.
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STP Senior Reactor Operator Exam Question 70 The following has occurred in Unit 1:
. At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, indicated Axial Flux Difference went outside the target band due to a perturbation with the plant at 100% power.
. At 0220 hours0.00255 days <br />0.0611 hours <br />3.637566e-4 weeks <br />8.371e-5 months <br />, power was reduced to less than 90%.
Which ONE of the following indicates a required action for this condition?
A. Power must be reduced to less than 50% within the next 30 minutes.
B. A notification must be made to the NRC Operations Center within the next 60 minutes.
C. The unit must be placed in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. A notification must be made to the NRC Operations Center within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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STP Senior Reactor Operator Exam Question 71 Unit 1 is operating at 100% power with the following initial conditions:
. CCW Train A operating
. ECW Trains A & B operating
. MCC ElB3 de-energized; crew investigating A Reactor Trip occurs followed by a Safety Injection due to low pressurizer pressure. The crew has completedphe immediate actions of OPOP05-EO-EOOD, Reactor Trip or Safety injection, and Just is proceeding through the procedure.
The following conditions exist:
+ Rx Power: 2.0E-7 amps
+ Containment Pressure: +0.2 psig
+ Tave: 557 F
+ Przr Pressure: 1850 psig
+ Przr Level: 12% l
+ Control Rod E5: 240 steps
+ MCC ElB3: de-energized
+ CV-FI-0205: 150 gpm j Which ONE of the following is the correct action to implement?
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A. Commence Emergency Boration. i B. Manually actuate Phase A.
C. Place SDG 12 in Emergency Stop.
D. Increase charging to maximum.
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m STP Senior Reactor Operator Exam Question 72 Unit 1 is operating at 100% power when a Large Break LOCA occurs. Five minutes later, the Primary Operator notices the following:
. ECW Pump 1B is running
. ECW Train 1B Blowdown isolation Valve is closed
. ECW Train 1 B Screen Wash Booster Pump is running
. ECW Pump 1B Discharge Valve indicates intermediate position (red AND green lights lit) l
. ECW Trains A and C are operating normally
. The yard watch reports the ECW Pump 1B Discharge Valve is 50% open Which ONE of the following is true concerning ECW Train 1B?
A. Safety injection actuation has blocked the trip of the pump to allow the train to operate.
The pump will continue to run even if deadheaded by a closed discharge valve.
B. Safety injection Train B was reset prior to the discharge valve reaching full open. The discharge valve will open fully when the control switch is taken to OPEN.
C. Safety Injection Train B did not actuate. Manually actuating Safety Injection will open the discharge valve fully.
D. ECW Pump IB did not receive a start signal from the sequencer. The pump was running prior to the Large Break LOCA.
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STP Senior Reactor Operator Exam Question 73 l
l Unit 2 experienced a LOCA and the crew hasjust transitioned to OPOP05-EO-ES13, Transfer To Cold Leg Recirculation. The Reactor Operator notes and reports that Train A DID NOT l automatically swap suction to the containment sump.
Which ONE of the following indications wouldjustify the failure? (consider each condition separately) l A. STATUS MONITORING PANEL IM25: BYP/INOP RWST OUTL MOV-0001 A - ON i B. STATUS LAMPBOX 5M2-3: AUTO RECIRC NOT RESET TRAIN A - OFF C. RWST LVL LI-931 = 70,000 gallons; LI-932 = 73,000 gallons D. HHSI Pump 1 A MIN FLOW ISOL MOV-0011 A - OPEN; MOV-0012A - CLOSED l
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! STP Senior Reactor Operator Exam Question 74 The Unit is in Mode 3 when the CNTMT PRESS HI/LO alarm comes in due to a high pressure condition in containment.
Which ONE of the following is TRUE conceming the containment pressure relief that must take place under these conditions?
A. The containment pressure relief CAN be performed under an expired Containment Purge Release Permit with Chemistry concurrence.
B. Opening the Supplementary Containment Purge valves without starting a fan does NOT constitute a containment purge.
C. With RT-8011, Containment Atmosphere Monitor out of service, the containment pressure relief may NOT be perfonned. i l
D. With RT-8012, RCB Purge Monitor out of service, the containment pressure relief CAN be performed with Chemistry concurrence.
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F I STP Senior Reactor Operator Exam Question 75 The following plant conditions exist:
. Large break LOCA has occurred
. Containment pressure is 10.2 psig
. Containment temperature is 240 oF
. OPOP05-EO-FRZ3 Response to High Containment Radiation Level,is entered
' Which ONE of the following actions is required in accordance with OPOP05-EO-FRZ3?
l A. Sample containment atmosphere activity using the PASS.
B. Ensure all Reactor Containment Fan Coolers are running.
C. Verify Containment Ventilation isolation has occurred.
D. Place the Containment Carbon Filter Units in service.
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STP Senior Reactor Operator Exam Question 76 OPOP05-EO-EC01, Loss of All AC Power Recovery Without SI Required, directs the Operator l to start the INST AIR EMERGENCY COOLING WATER PUMP if the Closed Loop Auxiliary Cooling Water System is not in service.
Which ONE of the following describes the suction supply to the INST AIR EMERGENCY COOLING WATER PUMP?
A. Open Loop Cooling Water System supply header B. Turbine Generator Building Fire Water main header C. Circulating Water System discharge header D. Closed Loop Auxiliary Cooling Water System supply header 1
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i STP Senior Reactor Operator Exam Question 77 Which ONE of the following describes the EMERGENCY power supply to Instrument Air l Compressor #12?
l A. TSC diesel generator which energizes LC 1U B. TSC diesel generator which energizes MCC IG5 C. BOP diesel generator which energizes LC IU D. BOP diesel generator which energizes MCC lG5 l
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STP Semor Reactor Operator Exam Question 78 The plant is operating at 100% power when Instrument Air pressure begins to decrease. The l BOP operator reports that Instrument Air pressure is 95 psig and slowly lowering.
1 Which ONE of the following actions should have already occurred?
A. 1(2)-IA-PV-8561, Instrument Air Dryer Bypass Valve is OPEN B. 1(2)-CV-FV-0011, Letdown Orifice Header Isolation Valve is CLOSED C. 1(2)-I A-PV-8568, Instrument Air to Yard Isolation Valve is CLOSED D. 1(2)-IA-PV-8559, Service and Instrument Air Crossover Valve is OPEN 1
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r S'lP Senior Reactor Operator Eum Question 79 Unit 1 is in Mode 4, coming out of a refueling outage, when a loss ofinstrument air occurs.
Given the following:
. Narrow Range SG levels; 1 A = 40%,1B = 35%,1C = 55%, 1D = 20%
. All motor driven AFW Pumps are operable
. RHR Train 1 B is in service and supplying Low Pressure Letdown
. RHR Train l A and IC are available
. SI Pumps are in the normal Mode 4 alignment
. Both Pressurizer PORVs are operable
. Vacuum has been established in the Main Condenser j
. Three Circulating Water pumps are running Which ONE of the following RHR valve alignment methods are Control Room operators directed to use for RCS temperature control in accordance with OPOP04-IA-0001, Loss of Instrument Air, Addendum 6, RCS Temperature Control on RHR?
A. LOOP B TC INJ MOV-0031B - open, Cycle RHR B Heat Exchanger OUTL TEMP CONT HCV-0865 as needed for temperature control.
B. MINI FLOW MOV-0067B - open, Cycle RHR B Heat Exchanger BYP FLOW CONT FCV-0852 as needed for temperature control.
C. MINI FLOW MOV-00678 - open, Cycle LOOP B TC INJ MOV-0031B as needed for temperature control.
D. LOOP B TC INJ MOV-0031B - open, Cycle RHR B Heat Exchanger CCW OUTL FV-4548 as needed for temperature control.
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STP Sernor Reactor Operator Exam Question 80 Operators are at the Auxiliary Shutdown Panel (ASP) following evacuation of the Control Room.
RCS temperature was being controlled using the Residual Heat Removal (RHR) system.
Which ONE of the following should the operators be aware of when transferring RHR Heat Exchanger (HX) controls to the ASP?
A. . There is no control of the RHR HX Bypass Flow Control Valves on the ASP.
. The operators have manual control of the RHR HX Outlet Temperature Control Valves.
. Total RHR flow is controlled automatically at 3500 gpm.
B. . Automatic control of the RHR HX Bypass Flow Control Valves is defeated.
. The operators have manual control of the RHR HX Outlet Temperature Control Valves.
. The operators must manually control total RHR flow. I C. . Automatic control of the RHR HX Bypass Flow Control Valves is still available.
. Automatic control of the RHR HX Outlet Temperature Control Valves is defeated.
. The operators have manual control of the RHR HX Outlet Temperature Control Valves.
D. . Automatic control of the RHR HX Bypass Flow Control Valves and RHR HX Outlet Temperature Control Valves is still available.
. There is no indication of RHR flow or temperature at the ASP.
. Total flow and outlet temperature must be monitored locally at the RHR HX.
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l STP Senior Reactor Operator Exam Question 81 i
Unit 1 is in Mode 5 with the following conditions:
. RCS level is -1 inches and decreasing on the narrow range hot leg level indicators
. RHR Train A is in sen' ice
. RHR Trains B and C are in standby
. The operator notices erratic current and discharge flow indications on RHR pump A
. OPOPO4-RH-000), Loss of Residual Heat Removal, is entered Per OPOP04-RH-0001, which ONE of the following actions should be taken by the operator?
A. Stop RHR pump A, THEN start RHR pump B or C.
B. Start RHR pump B or C, THEN stop RHR pump A.
C. Stop RHR pump A, THEN isolate letdown.
D. Stop RHR pump A, THEN start at least one available HHSI pump.
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STP Senior Reactor Operator Exam l
I Question 82 Assuming all equipment is operable unless indicated otherwise, which ONE of the following sets of conditions would place the Unit in a Technical Specification IJrnitirg Coiidition fm Opuotioii p? A e.M n s bh.med A. The Unit is in Mode 3 and 2 RCPs are in operation; RiiR Pump A is removed from service for maintenance.
B. The Unit is in Mode 5 with SGs in wet layup and 1 RCP and RIiR Train A in operation; RIiR Pumps B and C are removed from service for modifications.
C. During fuel movement in the reactor vessel, all RIiR pumps are stopped for 35 minutes to place an assembly near a hot leg opening.
D. During fuel movement in the reactor vessel with 2 RiiR Trains in service, I RHR Pump trips.
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STP Senior Reactor Operator Exam Question 83 Unit I was operating at 100% power with Boric Acid Pump 1 A OOS for motor replacement. A feedwater control failure results in the crew manually tripping the unit. The crew has transitioned to OPOP05-EO-ES01, Reactor Trip Response.
The following conditions exist:
. 2 Control Rods indicate 12 steps
. 1 Control Rod indicates 18 steps The Reactor Operator attempts to Emergency Borate, but Boric Acid Pump 1B fails to start. The following indications are observed:
+ Both pump status lights (Green & Red) are extinguished
+ Bypass /Inop 4M05/C2 BA XFER PUMP 1B is illuminated Which ONE of the following PAIRS of Emergency Boration flowpaths are available to be used?
A. 1-CV-0221 Manual Altemate immediate Borate &
Emergency Boration Via Gravity Feed.
B. Emergency Boration from RWST &
Emergency Boration Via Gravity Feed.
C. Emergency Boration Through Normal Boration Flowpath &
Emergency Boration from RWST D. Emergency Boration Through Normal Boration Flowpath &
1-CV-0221 Manual Alternate Immediate Borate l
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STP Semor Reactor Operator Exam Question 84 Unit 1 is operating at 100% power. OPSP03-R.S-0001, Monthly Control Rod Operability, is being performed.
Test Performer notes that two (2) rods in Control Bank A did not move
- Investigation reveals the rods are untrippable Which ONE of the following is required by Technical Specifications?
Within I hour:
A. ensure the remainder of the group is aligned within i 12 steps and restore the rods to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B. declare the rods inoperable and ensure the remainder of the group is aligned within 12 steps.
C. verify Shutdown Margin is satisfied and be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. trip the reactor and initiate Emergency Boration.
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STP Senior Reactor Operator Exam Question 85 Unit 1 is operating at 100% power with all systems in their normal lineup. A small RCS leak develops in the Chemical and Volume Control System (CVCS) with the following Control Room indications:
. Pressurizer level indicates 50% and is decreasing
. RCS pressure indicates 2220 psig and is stable
. Containment oressure is normal
. LETDN HX OUTLET PRESSURE PI-0135 indicates O psig
. PRT PRESS 111 alann is illuminated
. LETDN HX OUTL FLOW 111/LO alann is illuminated
. ERFDADS Points (2) CVCS LTDN AREA TEMP TRN lil are in alarm Considering these indications, which ONE of the following AUTOMATIC actions has taken place? ( w&c. 4 7,s-~~ > m ' - a m 8% 'c n v o.4 cou.O A. TCV-0143, Letdown Temperature Divert Valve, positioned to the VCT.
B. MOV-0023/0024, Letdown Line Containment Isolation Valves closed.
C. FV-0011, Letdown Header Orifice Isolation Valve closed.
D. PCV-0135, Letdown Pressure Control Valve opened.
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STP Senior Reactor Operator Exam Question 86 Given the following:
- Unit 1 is operating at 90% power, steady-state, following a power increase e Chemical Analysis reports that RCS samples indicate increasing RCS activity
. RT-8039, CVCS Letdown Failed Fuel Monitor is NOT in alarm
. Decontamination Factor (DF) across the inservice mixed bed demineralizer is adequate e CVCS letdown flow is 140 gpm Which ONE of the following actions, as directed by Chemical Analysis, is in accordance with OPOP04-RC-0001, High Reactor Coolant System Activity?
A. Maintain present letdown flow and place the alternate mixed bed demineralizer in sen ice.
B. Maintain present letdown now and place the cation demineralizers in service.
C. Maximize letdown now and place the alternate mixed bed demineralizer in service.
D. Maximize letdown Dow and place the cation demineralizers in service.
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j, STP Senior Reactor Operator Exam l
Question 87 l
l Charging flow has automatically DECREASED from 115 gpm to 50 gpm.
Which ONE of the following indicates the failure that would cause the change in flow?
l A. PT-505 Turbine Impulse Pressure, failed low B. Controlling Pressurizer Level channel failed high C. Loop 2 Tc failed high D. Loop 4 Tu failed low 1
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l 1 STP Senior Reactor Operator Exam i Question 88 l
The Reactor Operator is making a blended addition to the Volume Control Tank and sets up the controls as follows:
l . TOT M/U BATCH integrator set for 400 gallons l
- BA BATCH integrator set for 70 gallons e RC M/U CONT selector switch set to MAN
- All blender valves in AUTO l
- RC M/U CONT is taken to START and the blending operation begins l
Due to a malfunction, the TOT M/U BATCH integrator stops counting the gallons added part way through the operation.
Assuming the malfunction goes unnoticed by the operator, which ONE of the following describes the effect of the malfunction:
A. Reactor Makeup Water will continue to inject until stopped by the operator, causing a dilution of the RCS.
B. Boric Acid will continue to inject until stopped by the operator, causing a boration of the RCS.
C. Boric Acid and Reactor Makeup Water will both continue to inject at their present i flowrates until stopped by the operator causing the Volume Control Tank to fill with properly blended flow.
l D. Boric Acid and Reactor Makeup Water will both stop injecting immediately and operator I action will be required to continue blending.
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1 STP Senior Reactor Operator Exam Question 89 1
In accordance with Technical Specifications, which ONE of the following describes the TYPE and LIMIT for RCS leakage into the Pressurizer Relief Tank (PRT)?
RCS leakage into the PRT is considered:
A. UNIDENTIFIED LEAKAGE with a limit of I gpm.
B. UNIDENTIFIED LEAKAGE with a limit of 10 gpm.
C. IDENTIFIED LEAKAGE with a limit of I gpm.
D. IDENTIFIED LEAKAGE with a limit of 10 gpm.
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I STP Senior Pm sr Operator Exam Question 90 Given the following:
. Unit 2 is in Mode 4
. VCT is aligned to the GWPS
. GWPS Inlet Header valve (FV-4657) and Discharge Flow valve (FV-4671) handswitches are in their NORM AL positions on the Rad. Waste Control Panel
. A high alami condition occurs on RT-8032, GWPS Outlet radiation monitor Which ONE of the following correctly describes the final position of the GWPS Inlet Header (FV-4657) and Discharge Flow (FV-4671) valves?
j A. Inlet Header valve (FV-4657) CLOSED and Discharge Flow valve (FV-4671) CLOSED. I
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i B. Inlet Header valve (FV-4657) CLOSED and Discharge Flow valve (FV-4671) OPEN.
C. Inlet Header valve (FV-4657) OPEN and Discharge Flow valve (FV-4671) CLOSED.
D. Inlet Header va;ve (FV-4657) OPEN and Discharge Flow valve (FV-4671) OPEN.
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STP Senior Reactor Operator Exam Question 91
! Unit 2 is operating at 100% nearing end of cycle and a fuel defect has been identified.
Which ONE of the following would be responsible for an increase in plant vent Noble gas activity?
A. Pressurizer Relief Tank (PRT)
B. Reactor Coolant Drain Tank (RCDT)
C. Recycle Holdup Tank (RHT)
D. Waste Monitor Tank 2D (WMT 2D) l l
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STP Senior Reactor Operator Exam Question 92 1
Digital Rod Position Indication (DRPI) input to the Plant Computer has failed.
Which ONE of the following describes the effect of the failure on the Plant Computer?
l The Plant Computer is unable to.
A. monitor rod insertion limits making the BANK INSRT LO-LO alarm inoperable.
B. calculate Axial Flux Difference (AFD) making the AXIAL FLUX DIFFERENCE HI alarm inoperable.
C. calculate Quadrant Power Tilt Ratio (QPTR) making the PR UPPER DET FLUX DEV Hl/ AUTO DEF and the PR LOWER DET FLUX DEV Hl/ AUTO DEF alarms inoperable.
D. monitor control rod deviation making the ROD SUPV MNTR ROD POSITION TRBL alarm inoperable.
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STP Senior Reactor Operator Exam l
- Question 93 l
When performing RWST recirculation and purification, OPOP02-FC-0001 Spent Fuel Pool Cooling and Cleanup System, states that it is preferred to use SFP Demineralizer "A".
1 Which ONE of the following conectly states the reason for this preference?
l A. SFP Demineralizer "B" may only be equalized to 2500 ppm Boron.
B. To minimize silica contamination of the RWST.
C. SFP cooling has to be secured to use SFP Demineralizer"B".
D. To prevent transferring RWST water to the SFP.
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STP Senior Reactor Operator Exam l
Question 94 l
l The following conditions exist on Unit 1:
. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, a fire in the Central Alarm Station was reported to the control room
. Fire brigade has been dispatched
. Control Room staffis performing OPOP04-ZO-0008, Fire / Explosion
. At 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />, the Fire Brigade Leader reports that the fire is not yet extinguished Under these conditions, which ONE of the following actions should be taken?
A. Place EAB HVAC in the Smoke Purge mode ofoperation.
B. Close at least one of the Control Room Envelope HVAC Train C Inlet Isolation Dampers, INL DMPR FV-9664 or FV-9665.
C. Isolate EAB HVAC Train C using the train actuation handswitch in the stairwell.
D. Actuate the deluge valves for the Control Room Envelope Train C filters.
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i STP Senior Reactor Operator Exam Question 95 Which ONE of the following will PREVENT a Circulating Water (CW) Pump from starting?
(Blue PERM SATISFIED light NOT lit)
A. Piping downstream of the discharge valve is full.
B. Seal water pressure is 45 psig.
C. Discharge valve is fully closed.
D. A CW Pump was started 3 minutes ago.
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STP Senior Reactor Operator Exam l
l Question 96 Unit 2 is at 100% power perfomiing a release of Waste Monitor Tank (WMT) 2C with 4 Circulating Water (CW) Pumps in service. CW Pump 24 is to be secured for maintenance.
If the release is secured at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, in accordance with OPOP02-CW-0001, Circulating Water System Pump Operation, when is the earliest CW Pump 24 can be removed from service?
I A. 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> j
B. 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> C. I830 hours D. 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> l
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I STP Senior Reactor Operator Exam Question 97 Following a Loss of Offsite Power, which ONE of the following statements describes the pressurizer heater groups that will be available to maintain pressurizer pressure?
A. Control heater group C only B. Backup heater groups A and B only C. Backup heater groups C and D only D. All backup heater groups Page 97 of IN
F STP Senior Reactor Operator Exam Question 98 l
l During operation at 95% power with pressurizer level at 53%, the Tave input ( Auctioneered
! High) to the pressurizer level controller fails low.
l Which ONE of the following is an indication that this failure has occurred?
A. Backup heaters energize, Charging flow control valve opens, PRZR LEVEL DEV LO alann actuates.
B. Backup heaters energize, Charging How control valve closes, PRZR LEVEL DEV HI B/U HTRS ON alarm actuates.
C. Backup heaters de-energize, Charging flow control valve closes, PRZR LEVEL DEV HI B/U HTRS ON alarm actuates.
D. Backup heaters de-energize, Charging flow control valve opens, PRZR LEVEL DEV LO alarm actuates.
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STP Senior Reactor Operator Exam Question 99 Unit 1 is operating at 100% power with Pressurizer Pressure Control selected to P455/456 when power to PT-455 is lost.
Which ONE of the following will occur with NO operator intervention?
A. Reactor trip on high pressure B. Reactor trip on OTAT C. PCV-655A will control pressure D. PCV-656A will control pressure
I' STP Senior Reactor Operator Exam Question 100 i
Which ONE of the following sets of conditions would require the filGilEST hydrogen recornbiner power setting? (Addendum 1 of 0 POP 02-CG-0001, Electric Hydrogen Recombiners
[ is attached) i l
Pre-LOCA Post-LOCA RCB Temp RCB Press
( F) (psig)
A. 60 6
! B. 90 7 1
C. 60 8 D. 120 9 l
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OPOP02-CG-0001 Rev.2 Page 12 or is Electric Hydrogen Recombiners l
Addendum i Dry Containment Recombiner Power Correction Factor Pageiori Versus Containment Pressure 17
. k PRE LOCA CONTMNMENT TEMPf r TURE GO%%DF g
v iS / 9A%DF 120%%D F I
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4 10 0 2 4 6 8 to 12 14 FOST LOCn CONTAwf NT P84f $$J84E (PS'Gi TABLE 3
SRO EXAM SHORT ANSWER KEY Question # Answer Question # Answer Question # Answer Question # Answer IB 31 A 61 B 91 D 2C 32 C 62 D 92 D 3C 33 D 63 D 93 B 4D 34 A 64 D 94 C 5C 35 D 65 D 95 D 6A 36 A 66 A 96 A 7C 37 C 67 D 97 B 8A 38 C 68 A 98 B 9D 39 B 69 A 99 D 10 B 40 C 70 D 100 C ll A 41 C 71 B 12 A 42 A 72 A 13 B 43 B 73 B 14 C 44 A 74 A 15 B 45 C 75 C 16 C 46 D 76 D 17 A 47 B 77 D 1S A 48 A 78 D 19 A 49 C 79 C 20 A 50 A 80 B 21 A 51 A 81 C 22 D 52 A 82 A 23 C 53 D 83 B 4 24 C 54 C 84 C 25 A 55 C 85 B 26 D 56 D 86 D 27 C 57 B 87 B 28 C 58 D 88 A 29 C 59 A 89 D 30 B 60 C 90 A luc %!.a. July % l'Ni Pa'eI g ofI
ES-401 Site-Specific Written Examination Form ES-401-8 Cover Sheet U.S. Nuclear Regulatory Commission Site-Specific Written Examination-4 Applicant information Name: Region: IV -
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Date: 7/2/99. Facility / Unit: South Texas Project : l l
License Level: RO- Reactor Type: W I Start Time: Finish Time:
Instructions Use the answer sheets provided to document your answers. - Staple this cover. sheet on top -
of the answer sheets. The passing grade requires a final grade of at least 80.00 percent..
Examination pap'ers will be collected five hours after the examination starts.'
Applicant Certification All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature j i
Results .
Examination Value - Points l Applicant's Score Points Applicant's Grade Percent i
NUREG-1021, Revision 8
0 1 2 3 1 5 6 7 6 3 f f 40,L.Ll 0
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6 A B C D E 56 A B C D E 7 :A7 ~B' C D -E- 57 - A ; - B C :D :E-8 A B C D E 58 A B C D -E-9 cA: :B :C: :D. .E- 59 :A B: :C :D tE3 10 A B C D E 60 A B C- 'D E-11 t A s eB3 :C3 :Dr rE: 61 r A: tB: -C3 rDa rEs I signify that all answers in this examination are my 12 A 8' C D E 62 A B C D E own. I have not given or received any unauthorized
- a s ance and I han not use any unadoM 13 r A 3 cB: 'C: -D :E- 63 :A: :B: cC: :D: cE, references. I understand that I am not to remove any 14 A - B C D E 64 A B C D E' of the examination materials from this room.
15 - A ' 'B- -C- -D' 'E 65 A~ 'B- -C~'D: -Ei 16 A B C D E 66 A B C D E
- B: -C: D. :E- 67 - A - 0 :C: -D: rE-g '""" 17 r A :
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- 19 r A : rB -C: :D- :E 69 : A: tB,'C -D: cE' 20 A' B C D E 70 A B- C D E'
- 1 :A3 tB: :C :D tE: 71 cAa cB, cC: rDa ten 22 A- -B' C D -E 72 A- B C- D E.
23 c A2 rB1 :C: :D3 tE7 73 :A,cB.rC3 rD'cE' I signify that I have had the opportunity to review 24 A B C D E 74 A B- C- D- E my graded exam and am satisfied that I understand 25 t A3 cB3 tC :D cE: 75 c A: rB: rC: cD: rE: the correct answer for those questions I missed.
26 A B C D E 76 A B C D E' 27 :A: :B: C :D :E- 77 -A- -B: C- -D- rE-28 A B C D E 78 A B C D' E' 29 A: :B: C D -E 79 'A'- :
B' C:D 'E-3D A B C D E 80 A B C D E j- 31 :A rB: :C: D- :E- 81 :A"'B' :C: tD: tE:
!- 32 A B C D E- 82 A 'B C D E j- 33 c A eB: C: -D: -E: 83 c A eB: cC: :D E E 34 - A - -B- C D. E 84 A' 'B' C D- E j- 35 c A2 eB2 rC' cD, rE: 85 rAn rB: rCa rD: rEs f- 36 A- B- C D E 86 A B C D E' 37 cAs tB2 cC2 cDs tE: 87 cAa tBa ( Cs cD3 cE3 38 - A B' C~ D E 88 A B C -D -E 39 :A: rB 'C- :D: E- 89 A: -B: :C--D: rE:
40 ' A B C D E 90 A B C D E 41 - A : B' 'C' D E 91 A B- -C- D: E:
42 A B C D E 92 A C C D E 43 A B r D E 93 A B C D E 44 A 2 u , : . 3 i 15 A B C D E 35 A B C D E
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STP Reactor Operator Exam Question 1 Given the following:
. Small Break LOCA has occurred
. RVWL - HEAD level is 64%
. CET temperatures are 542 oF
. RCS wide range pressure is 1050 psig
. ECCS is functioning as expected
. All RCPs have been secured Which ONE of the following describes the condition of the fluid at the core exit?
A. Superheated Steam B. Saturated Steam C. Saturated Liquid D. Subcooled Liquid i
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l STP Reactor Operator Exam Question 2 l l
Given the following: l l . RCS Tavg is 567 F and stable
. Pressurizer pressure is 1737 psig and decreasing )
. Pressurizer level is 28% and increasing
. Containment pressure is 0.1 psig and stable l
Which ONE of the following events has occurred?
A. Steam generator tube leak i
B. Loop C sample line rupture C. Stuck open pressurizer PORV j D. Small steam line break in containment i
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STP Reactor Operator Exam Question 3 1
Unit 2 was opera 6ing at 75% reactor power with the turbine in IMP OUT when a single control l
rod dropped into the core. OPOPO4-RS-0001, Control Rod Malfunction, directs the operator to maintain Tavg by adjusting turbine load and /or boron concentration.
Which ONE of these statements is true concerning reactor power if Tave is returned to the same temperature which existed prior to the event?
A. If ONLY turbine load is adjusted, reactor power will be 75%.
B. If ONLY turbine load is adjusted, reactor power will be >75%.
C. If ONLY boron concentration is adjusted, reactor power will be 75%.
D. If ONLY boron concentration is adjusted, reactor power will be <75%.
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l STP Reactor Operator Exam Question 4 l
l Annunciator window 9M01/E8, SEISMIC EVENT, alarms in the Unit 2 Control Room.
l-Which ONE of the following describes how the Unit 2 Control Room staff can verify the alarm l
validity?
A. Check the Seismic Monitoring System Panel (CP013) located at the rear of the Unit 2 I
control room.
l B. Check the Seismic Monitoring page on the QDPS Computer.
C. Check the Seismic Monitoring inputs to the Plant Computer.
D. Contact the Unit 1 Control Room.
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I STP Reactor Operator Exam Question 5 Given the following conditions:
. Unit 1 is operating at 75% power
. Condensate pump 13 is out of service for maintenance
. Power is being increased at 10% per hour Condensate Pump 11 trips from UNKNOWN causes.
Which ONE of the following is the appropriate action per the COND PMP TRIP annunciator response?
A. Stop the power increase and stabilize Deaerator level at the present power level.
B. Attempt to restart Condensate Pump 11, then continue the power increase once it is running.
C. Commence a power decrease to less than 50% at 5% per minute.
D. Trip the turbine and stabilize Deaerator level at no load conditions.
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I STP Reactor Operator Exam Question 6 l
A Plant Operator is required to perform an extensive valve lineup in an area where the radiation level is 200 mrem / hour. The Plant Operator's current annual Total Effective Dose Equivalent (TEDE) is 1600 mrem.
How long can the Plant Operator work in this area and not exceed STP's Administrative Action Level (AAL) for annual TEDE?
A. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> C. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> 4
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STP Reactor Operator Exam Question 7 Preparations are being made to enter a radiologically controlled area with a general area dose rate of 75 mrem /hr.
Which ONE of the following would be the FIRST to exceed his/her 10CFR20 Dose Limits?
A. Plant worker with a year-to-date exposure of 1350 mrem (TEDE)
B. Working Visitor with a year-to-date exposure of 0 mrem (TEDE)
C. Declared pregnant worker with a to date exposure of 425 mrem (DDE) during the pregnancy D. Contract employee with a year-to-date exposure at all sites of 1875 mrem (TEDE) l I
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STP Reactor Operator Exam Question 8 OPGP03-ZG-0050, Radiation Protection Program, provides for an extension ofindividual occupational dose. A request to extend an indivi Juals annual dose limit to 3000 mremlyr has been submitted.
Which ONE of the following signature combinations is necessary to approve the extension request?
A. Responsible Depanment Manager & Radiation Protection Manager.
B. Responsible Depanment Manager & Plant Manager.
C. Radiation Protection Manager & a Senior Management Team member.
D. Plant Manager & a Senior Management Team member.
I STP Reactor Operator Exam Question 9 A rupture has occurred in a Reactor Head Degassing System Storage Tank.
Which ONE of the following Area Radiation Monitors would be the first to reach alarm l
conditions as a result of this event? (assume all setpoints are the same)
A. RE-8097, PASS Lab B. RE-8060, MAB Floor Drain Area C. RE-8061, CCW Coolers D. RE-8068, Rad Waste Control Room l
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STP Reactor Operator Exam Question 10 l
While operating at 15% power, a steam generator tube leak of approximately 85 gallons per day occurs.
Which ONE of the following is the LEAST reliable method of tube leakage detection at this power level?
A. N-16 Primary to Secondary Leak Monitor B. SG Blowdown Radiation Monitor C. SG Main Steam Line Radiation Monitor D. CARS Radiation Monitor l
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STP Reactor Operator Exam Question 11 Each of the Process and Effluent radiation monitors below are to automatically secure radioactive releases to the environment.
Per OPOP04-RA-0001, Radiation Monitoring System Alarms Response, which ONE of the following correctly matches a radiation monitor with its automatic action?
Monitor Automatic Action A. RT-8038 LWPS Monitor Waste Monitor Tank Pump stops.
B. RT-8041 TGB Drain TGB Sump Number 1 Sump Pumps stop.
Monitor C. RT-8042 Condensate 1(2)-FV-5804 TDS Waste Discharge to Neutralization Polisher System Basin Valve shifts to RECIRC.
D. RT-8043 SG Blowdown 1(2)-SB-FV-5019 SG Blowdown Isolation. n System Monitor Neutralization Basin Valve shifts to RECIRC.
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STP Reactor Operator Exam Question 12 Which ONE of the following Area Radiation Monitors would require that the unit be shut down if the monitor were out ofservice for greater than 7 days?
A. RT-8050, RCB High Range Area Monitor B. RT-8090, SFP Area Monitor C. RT-8059, Waste Gas Area Monitor D. RT-8096, Emergency Operations Facility Area Monitor enei:i,rion
STP Reactor Operator Exam Question 13 l
l Which ONE of the following is the LOWEST Emergency Plan Classification at which the l
Emergency Response Data System (ERDS) must be activated?
l 1 A. Unusual Event l
B. Alert l
C. Site Area Emergency D. General Emergency l
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r-STP Reactor Operator Exam Question 14 Which ONE of the following contains only instruments listed in LCO 3.3.3.6 Accident j Monitoring Instrumentation Table 3.3-10.
Containment Intermediate Th (WR) SG Level
- Water Level Range Nis (WR)
(NR)
A. X X X B. X X X C. X X X i D. X X ; X l
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STP Reactor Operator Exam 1
Question 15 Unit 2 is preparing for a reactor startup following a trip 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago with the following conditions:
. ECP critical boron (for an estimated startup time 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from now) is 860 ppm
. Primary Operator is withdrawing Shutdown Bank A The extra Reactor Operator requests permission to dilute the RCS to the critical boron concentration.
Which ONE of the following describes why the Reactor Operator should or should not be allowed to perform the dilution?
The dilution:
A. should be perfomled because the Primary Operator is already closely monitoring criticality and anticipcting criticality at any time.
B. should be perfomaed t.ecause this will allow the reactor startup to commence sooner such i that less positive reactivity will be added by the decaying Xenon. l C. should NOT be perfomied because Xenon is decaying, adding positive reactivity.
D. should NOT be perfomied because the reactor is less than the Point of Adding Heat (POAH).
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STP Reactor Operator Exam Quesiion 16 I
Given the following:
. Unit 1 is in Mode 6
. 18 fuel assemblies have been reloaded after a complete core off-load
. RHR Train l A is in service maintaining RCS temperature at 97 F
. RHR Train l A loop boron concentration was 2870 ppm on the last sample l
. Source Range N-31 indicates 2 cps
. Source Range N-32 indicates 3 cps and is selected for audible count rate indication
. Both Extended Range channels N-45 and N-46 are INOPERABLE l
In accordance with OPOP08-FH-0009, Core Refueling, which ONE of the following conditions requires suspension of Core Alterations?
A. Both Source Range channel indications unexpectedly increase to 7 cps.
i B. RHR Train l A inlet temperature is 103of on the next successive reading.
C. RHR Train 1 A boron concentration is 2860 ppm on the next successive sample.
D. Direct communications is lost between the RCB and the FHB Fuel Handling personnel.
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STP Reactor Operator Exam Question 17 The following conditions exist on Unit 1:
- Plant startup is in progress per OPGP03-ZG-0005, Plant Startup to 100%
e Reactor Power is 4%
. Tavg is currently 569 "F e Annunciator window 5M02/E6, T REF / AUCT T AVG DEV is received Which ONE of the following identifies actions that must be taken in accordance with the annunciator response procedure?
A. If Tavg is high, insert control rods to lower Tavg B. If Tavg is low, withdraw control rods to increase Tavg to 2 571 F l l
C. Record Tavg at least once per hour to ensure it is within 1.5 "F of Tref D. Verify Tavg is greater 2 561 "F at least once every 30 minutes f
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STP Reactor Operator Exam Question 18 Which ONE of the following is a requirement found in the Conduct of Operations Manual?
A. The required minimum Shift Compliment for Unit I and Unit 2 Combined is 4 SROs, 5 ROs, and 10 Plant Operators.
B. As a minimum, the Energy Management and Control System (EMACS) should be updated once per week.
C. Thermal overload devices may be reset once with the permission of the Unit Supervisor.
D. The Reactor Operator may decide to allow a nuisance alarm to continue flashing if he has detemiined there is no operational impact.
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4 STP Reactor Operator Exam Question 19 l
You have been directed to perfomi Lineup 1, Electrical Lineup, of 0 POP 02-DB-0003, Balance of Plant Diesel Generator.
Which ONE of the following correctly describes the procedure usage requirements in effect for this task? (Cover page of OPOP02-DB-0003 is attached)
The lineup can be performed provided:
A. there is a current working copy of the procedure in the Turbine Building Basement ,
Operators Station. '
1 B. you review a current working copy of the procedure first.
C. you have a current working copy of the lineup with you during performance of the lineup.
D. you are in radio contact with a Reactor Operator in the Control Room.
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l y y yfSc 95'?s1997 SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION D0527
- ,=2??;rar"*"..'"*
~,1_.,-,,,u._. OPOP02-DB-0003 Rev.15 Pan i om Balance of Plant Diesel Generator Non Quality Non Safety-Related Usage: IN HAND Effective Date: 05/19/98 M P. Hill P.J Hengel Cre v IE Operanons i
PREPARER TECHNICAL USER COGN!ZANT DEPT.
Usage Table of Contents Page 4 1.0 Purpose . . . . . .
. . .2 4 2.0 References . . . . . . . . .. . . .2 3 3.0 Prerequisites.. . .... . . ...
.3 3 4.0 Notes and Precautions . . .. . .
.3 1
5.0 Aligning Balance of Plant (BOP) Diesel Generator (DG) for Automatic Response. .6 1
6.0 Manual Staning of BOP DG .. . . . .
.9 1
7.0 Ucloading and Securing BOP DG, .. .
. . . . . . . .11 4 8.0 Support Documents . ..
. .12 1
Lineup 1, Electrical Lineup . .. . . . . . . . . .13 1
Lineup 2, Valve Lineup. . . . . . .. . 15 1
Logsheet 1, BOP DG Logsheet.. . .. .. . . .18 Usace 1 - IN HAND 2 -IN HAND CONTROLLING STATION 3 - REFERENCED 4 - AVAILABLE
)
STP Reactor Operator Exam Question 20 The Unit 1 EAB Watch while doing rounds finds the following conditions locally at the Diesel Generator 11:
- Starting Air Receiver #11 pressure indicates 95 psig
. Starting Air Receiver #12 pressure indicates 225 psig Which ONE of the following states the condition of DG 1 land why?
A. OPERABLE; because Starting Air Receiver #12 is > 175 psig.
B. INOPERABLE; because both Starting Air Receivers are required to be > 175 psig.
C. INOPERABLE; as long as Starting Air Receiver #11 is < 100 psig.
D. OPERABLE; as long as Starting Air Receiver #11 remains > 90 psig.
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STP Reactor Operator Exam Question 21 Which ONE of the following is the BASIS for the Auxiliary Feedwater Storage Tank minimum level of 485,000 gallons?
Contains sufficient inventory, without makeup, to maintain the plant in Hot Standby for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followed by a cooldown to:
A. 200 oF at 25 oF/hr.
B. 200 oF at 100 *F/hr.
C. 350 oF at 25 oF/hr.
D. 350 'F at 100 F/hr.
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! STP Reactor Operator Exam Question -22 l
OPOP05-EO-EC00, Loss of All AC Power, step 4 contains the action to " VERIFY AFW Flow -
GREATER THAN 576 GPM."
Which ONE of the following statements describes the BASIS for this step?
A. Ensure minimum flow is provided for the running AFW pumps.
B. Ensure NONE of the steam generators reach dry out conditions.
C. Ensure an adequate heat sink is maintained for heat removal.
D. Ensure a RCS cooldown is commenced.
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r STP Reactor Operator Exam Quest;on 23 Given the following:
. Unit 2 experienced RCS leakage into containment
. The crew entered OPOPO4-RC-0003, Excessive RCS Leakage
. The unit was ramped down to 43% power where it was tripped and Safety injection initiated
. Currently the crew is at step 5 of 0 POP 05-EO-ES12, Post LOCA Cooldown and Depressurization preparing to initiate a RCS cooldown using the steam dumps Current plant conditions are:
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+ Containment Pressure: 2.3 psig '
+ RCS Pressure: 1600 psig
+ Przr Level: 6% )
+ Tave: 567 F !
+ RCPs: 4 running
+ SG Pressures: 1183 psig
+ SG NR Levels: 22-30%
Which ONE of the following statements describes the relationship of SG heat removal to break 1 How heat removal at this time?
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A. SGs remove all the decay heat; break Dow removes no decay heat.
B. SGs remove almost all the decay heat; break Dow removes very little decay heat.
C. SGs remove very little decay heat; break Dow removes almost all the decay heat.
D. SGs remove no decay heat; break How removes all the decay heat.
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' Question 24 During the performance of OPOP05-EO-ES12, Post LOCA Cooldown and Depressurization, the operator is directed to STOP the LHSI Pumps and place them in AUTO if RCS pressure is greater than 415 psig and stable or increasing.
During subsequent recovery actions, which ONE of the following applies regarding operation of the LiiSI Pumps?
A. LHSI Pumps will no longer be required, even if RCS pressure drops uncontrollably, since the RiiR System will be available to be placed in service.
B. LliS1 Pumps will no longer be required, even if RCS pressure drops uncontrollably, since HHSI Pumps will be capable of providing sufficient flow to remove decay heat.
C. If RCS pressure drops in an uncontrolled manner to less than 400 psig, the ESF Load Sequencer will restart the pumps. I D. If RCS pressure drops in an uncontrolled manner to less than 400 psig, the operator will be required to manually restart the pumps.
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F STP Reactor Operator Exam Question 25 Unit 2 was in a Train B Outage when a reactor trip occurred followed by a loss of offsite power (LOOP).
. The crew is in OPOP05-EO-FRH1, Response To Loss Of Secondary Heat Sink performing a feed and bleed.
. The plant operators have replaced the breaker for AFW Pump #21 with the one from AFW Pump #22.
. AFW flow has been re-established to SG 2A.
Current conditions are:
+ Containment Pressure: 2.1 psig
+ Containment Radiation: 10.1 R/hr
+ Containment Integrated Dose: 10.5 Rad
+ Core Exit Thermocouples: 584 oF
+ RCS Pressure: 1352 psig
Which ONE of the following conditions must be met to allow termination of the feed and bleed?
A. Total AFW Flow > 576 gpm B. At least 3 intact SG WR Levels > 41%
C. At least one SG NR Level > 34%
D. At least one SG NR Level > 14%
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I STP Reactor Operator Exam Question 26 l
Unit 2 is recovering from a Loss of Offsite Power with the following conditions:
. Reactor is tripped
. All Reactor Coolant Pumps (RCP) are off and cannot be started
. The Primary Reactor Operator is directed to verify natural circulation cooling exists In which ONE of the following sets of conditions can natural circulation cooling be verified to exist?
Time Core Exit RCS Tu ( F) Tc ("F) S/G Press.
T/Cs ("F) Subcooling (psig)
("F) l 0400 560 36 557 536 916 A. I 0430 555 32 552 532 886
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0400 560 40 558 540 940 B.
0430 560 36 557 528 830 0400 560 42 557 536 916 C.
0430 555 41 552 532 886 0400 560 40 558 540 948 l D.
0430 564 43 560 544 980 i
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STP Reactor Operator Exam Question 27 The following conditions exist on Unit 1:
. Small break LOCA has occurred
. All equipment is operating as designed
. Tavg is 569 F and increasing
. Pressurizer pressure is 1490 psig and decreasing
. AFWST level is 490,000 gallons and decreasing
. Operators are performing steps in OPOP05-EO-E000, Reactor Trip or Safety Injection Which ONE of the following explains why the operators must trip the RCPs under these conditions?
A. Conserve AFWSTinventory B. Protect the RCP #1 seals C. Stop the RCS heatup D. Conserve RCS inventory 1
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i STP Reactor Operator Exam l
Question 28 I
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Given the following conditions:
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. Unit 2 is operating at 100%
. Chemistry reports a 200 gpd tube leak in SG C 1
. OPOP04-RC-0004, Steam Generator Tube Leakage is in progress
. A power reduction is about to commence Per OPOPO4-RC-0004, which ONE of the following indicates when steam flow from SG C should be isolated?
A. Right aller the power decrease has commenced B. When power has decreased to less than 50%
C. Right after the main turbine is tripped D. When it is determined that SG C level cannot be maintained greater than 33%
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I STP Reactor Operator Exam Question 29
! The following have occurred: ,
l l . LOCA outside containment {
. Transfer to Cold Leg Recirculation
. Transition to OPOP05-EO-EC11, Loss of Emergency Coolant Recirculation l OPOP05-EO-EC11 provides instructions to stop backDow from the RWST to the containment ,
sump to conserve RWST inventory. I Per OPOP05-EO-ECl I which ONE of the following is the correct sequence to stop the backnow?
A. 1. Stop the LHSI, HHSI and CS Pumps
- 2. Close the Containment Sump Suction Valves
- 4. Open the SI Pump Mini Flow Valves
- 3. Open the SI Pump Mini Flow Valves
- 4. Close the Containment Sump Suction Valves
C. 1. Stop the LHSI, HHSI and CS Pumps
- 3. Close the Containment Sump Suction Valves
- 4. Open the S1 Pump Mini Flow Valves
- 2. Open the S1 Pump Mini Flow Valves l
- 3. Close the Containment Sump Suction Valves
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STP Reactor Operator Exam Question 30 OPOP05-EO-EC31, SGTR With Loss Of Reactor Coolant - Subcooled Recovery Desired, directs the operator to monitor RWST level vs. Containment level per Addendum 6.
Which ONE of the statements below is correct?
If the decrease in RWST level:
A. disagrees with the increase in Containment level, a subcooled recovery is desired since a RCP can be started to reduce the cooldown time.
B. disagrees with the increase in Containment level, a saturated recovery is desired to i increase the Si flowrate, which will allow a faster transition to cold leg recire.
C. agrees with the increase in Containment level, a subcooled recovery is desired since long term cooling is assured.
D. agrees with the increase in Containment level, a saturated recovery is desired to lower the leak rate and delay RWST depletion.
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STP Reactor Operator Exam Question 31 Given the following:
. An ATWS has occurred
. Operators are perfomling the steps of 0 POP 05-EO-FRS1, Response to Nuclear Power Generation - ATWS
. Emergency Boration is in service
. MSIVs and MSIBs were closed by the operators
. RCS pressure is 1950 psig and slowly decreasing
. CETs are slowly decreasing
. SG A C and D pressures are stable
. SG B pressure is decreasing Under these conditions, OPOP05-EO-FRS1 will direct the operators to perfonn which ONE of the following?
A. Initiate Safety injection to inject additional borated water from the RWST into the RCS.
B. Isolate AFW to SG B to minimize RCS cooldown.
l C. Align the RWST to the charging pump suction to inject borated water from the RWST l into the RCS.
D. Increase AFW flow to SG B to maintain ALL SG levels greater than 14% for adequate l heat sink during the ATWS.
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STP Reactor Operator Exam Question 32 OPOP05-EO-E020, Faulted Steam Generator Isolation, step 4 ensures isolation of Main and Auxiliary Feedwater to the affected SG(s).
Which ONE of the following is the BASIS for the actions of this step?
A. To maintain at least two loops available for cooldown.
B. To allow identification of the leak location.
C. Allows identification of the faulted SG(s).
D. Maximizes cooldown capability of the non-faulted SG(s).
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t j STP Reactor Operator Exam Question 33 While performing a plant heatup in Unit 1 per OPOP03-ZG-0001, Plant Heatup, an unisolable break occurred on the SG D steam line. Currently, the crew is proceeding through OPOP05-EO-FRP1, Response to Imminent Pressurized The al Shock Condition, due to l excessive cooldown. ( Rs eme " M M DM**
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Which ONE of the following statements is correct regarding steps that will be taken?
A. The RCS will be depressurized allowing Si flow to relieve thermal stresses.
B. The charging pump suction will be realigned from the RWST to the VCT to minimize boron precipitation in the core.
C. RCS temperature will be kept stable for > 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to relieve thermal stresses across the reactor vessel wall.
D. RCP(s) will NOT be restarted because the pressure transient may cause propagation of a flaw in the reactor vessel.
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( STP Reactor Operator Exam l
! Question 34 Assuming all plant systems function as designed, which ONE of the following Critical Safety Functions would degrade to a Red Path condition during a postulated Uncontrolled l
Depressurization of ALL Steam Generators?
i A. Core Cooling (C) l B. Ileat Sink (H) l C. Integrity (P)
D. Inventory (I) l l
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STP Reactor Operator Exam Question 35 i in accordance with OPOP05-EO-EC21, Uncontrolled Depressurization of All Steam Generators, which ONE of the conditions below requires AFW flow to be controlled at 100 gpm to a SG?
A. AFWST Level is < 138,000 gallons (26%)
B. NR Level in the SG is < 14%[34%)
C. NR Level in the SG is > 50%
D. Przr Level cannot be maintained > 8%[44%)
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STP Reactor Operator Exam Question 36 OPOP05-EO-EO20, Faulted Steam Generator isolation, was entered due to indications of a steam line break in containment and the Operators are performing step 3.
The STA announces the following to the control room:
. An ORANGE condition exists in the Containment Critical Safety Function Status Tree
- A RED condition exists in the Integrity Critical Safety Function Status Tree Which ONE of the following describes the actions that should be taken by the control room crew?
A. Immediately stop perfonnance of 0 POP 05-EO-EO20 (do not complete step 3) and transition to OPOP05-EO-FRP1, Response to Imminent Pressurized Thermal Shock Condition.
B. Immediately stop perfom1ance of 0 POP 05-EO- E020 (do not complete step 3) and transition to OPOP05-EO-FRZl, Response to High Containment Pressure.
C. Suspend the performance of OPOP05-EO- E020 (complete step 3) and transition to OPOP05-EO- FRZl, Response to High Containment Pressure.
D. Suspend the performance of OPOP05-EO- E020 (complete step 3) and transition to OPOP05-EO-FRP1, Response to Imminent Pressurized Thermal Shock Condition.
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STP Reactor Operator Exam Question 37 While responding to an inadequate Core Cooling situation the operators are directed to reestablish some fomi of core cooling.
Which ONE of the following statements describes the INITIAL response of the CETs, and the reason for this response, if the operators restarted the safety injection pumps?
A. Increase due to saturated steam being forced out of the core.
B. Decrease due to saturated steam forming a frothy two phase mixture.
C. Increase due to superheated steam being forced out of the core.
D. Decrease due to superheated steam causing injected water to boil forming a frothy two phase mixture.
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l STP Reactor Operator Exam Question 38 Following a reactor trip in Unit 1, a SG Lo-Lo Level signal was generated. The operator notes that AFWP#14 failed to start because the Trip and Throttle Valve (AF-MOV-0514) is closed with power removed.
Where should the Reactor Operator direct the Plant Operator go to close the MOV breaker?
A. Non-Class lE 480VAC LC (1J1)
B. Non-Class lE 125 VDC SWBD (I A)
C. Class lE 480 VAC MCC (EIC4)
D. Class IE 125 VDC SWBD (EIDil) l l
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STP Reactor Operator Exam Questior. 39 During 100% steady state operation, while the operator is walking down the control boards, several BYP/INOP indicators are received. The operator looks down and notices:
. Containment Spray Pump B Red and Green indicating lights are extinguished.
Which ONE of the following explains the observed indications?
A. Loss of Class 1E 4160V Bus ElB B. Trip of a Class lE 125 VDC SWBD ElB11 breaker $sgly mg al*A C. Trip of a 120 VAC Class Vital Distribution Panel DP1203 breaker 5 v,ysyMy n !=4 D. Trip of a 120 VAC Non-Class Vital Distribution Panel DP006 breaker s s,ylv ear dod i
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STP Reactor Operator Exam l
Question 40 Unit 1 Train A AND Train C 4.16 KV ESF Busses were de-energized and was expected to last for 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />. Train A 4.16 KV ESF Bus has been re-energized using the Train B ESF Diesel Generator per OPOPO4-AE-0001, Loss of Any 13.8 KV or 4.16 KV Bus. I Which ONE of the following describes the BASIS for this action?
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A. To enable the start of CCP A for RCS Inventory Control.
B. To enable the start of CCW Pump A for Spent Fuel Pool cooling. !
C. To extend the use of the Plant Computer System for accident monitoring.
D. To extend the use of the Train A Class lE batteries.
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STP Reactor Operator Exam Question 41 Which ONE of the following is the correct sequence for paralleling the main generator to the grid?
A. 1) Place the GEN BKR SYNC SW in the ON position
- 2) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 3) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 4) Close the Main Generator Exciter Field Breaker
- 5) Close the Main Generator Breaker B. 1) Close the Main Generator Exciter Field Breaker
- 2) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 3) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 4) Place the GEN BKR SYNC SW in the ON position
- 5) Close the Main Generator Breaker C. 1) Close the Main Generator Exciter Field Breaker
- 2) Place the GEN BKR SYNC SW in the ON position
- 3) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 4) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 5) Close the Main Generator Breaker D. 1) Adjust voltage until the INCOMING VOLTS is slightly higher than the RUNNING VOLTS
- 2) Place the GEN BKR SYNC SW in the ON position
- 3) Adjust Main Turbine speed so the SYNCHROSCOPE needle is rotating slowly in the clockwise direction
- 4) Close the Main Generator Exciter Field Breaker
- 5) Close the Main Generator Breaker Page 4l ot' 100
STP Reactor Operator Exam Question 42 During the immediate action performance of 0 POP 05-EO-E000. Reactor Trip or Safety injection, the operator notices the following on the EH Control Panel:
Green light Red light TV-1 ON OFF TV-2 OFF OFF TV-3 ON OFF TV-4 OFF OFF To verify the turbine throttle valves are closed, which ONE of the following pairs ofindications would be used?
BSMP BSMP THROT VLV 7M3/C3 TURB TURBINE TURBINE POSIT LVDT STM STOP STOP VLV EH FLUID VLV RX LO PRESS PRE-TRIP A. X X B. X X C. X X D. X X Page 42 of 100
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L STP Reactor Operator Exam Question 43 Unit 2 is operating at 100% power.
l l Upon a loss of all Condenser Air Removal Pumps, which ONE of the following will be the FIRST to occur (assuming NO operator action)?
A. Main Turbine trip B. Steam Generator Feed Pumps Trip C. Hotwell Dump Pump Trip D. Condensate Pumps trip i
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l STP Reactor Operator Exam Question 44 Unit 2 is operating at 90% power with the following conditions:
. Vacuum is at 28 inches Hg and decreasing
. Rod control is in automatic
. Turbine control is in IMP IN i
. Operators are perfonning the actions of OPOP04-CR-0001, Loss of Condenser Vacuum Which ONE of the following correctly describes the response of rod control to these conditions?
Control rods will step:
A. IN due to increasing reactor coolant system Tave.
B. IN due to increasing turbine load.
C. OUT due to decreasing reactor power.
D. OUT due to decreasing reactor coolant system Tave.
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STP Reactor Operator Exam Question 45 A nomial cooldown to Mode 5 is being performed in Unit I with the following conditions:
. RCS temperature is 555 "F and decreasing at 50 F/hr
. RCS pressure is 2000 psig and decreasing
. Cooldown is being performed using Steam Dumps in AUTO
. All RCPs are in operation A few minutes later, the Secondary Reactor Operator notices SG pressures increasing.
Which ONE of the following explains why SG pressures are increasing?
A. RCS temperature decreased below the Low-Low Tave setpoint B. Steam licader Pressure PT-557 failed low C. A Main Steamline Isolation occurred from liigh Steam Pressure Rate D. Turbine Impulse Pressure PT-505 failed high
STP Reactor Operator Exam Question 46 Given the following conditions:
. Unit 1 is operating at 100% power
. SGFPs 11,12 and 13 are in service and in AUTO
. Operator notices the speed is increasing on all three SGFPs Which one of the following explains why the speed is increasing on the SGFPs?
A. SG C FWIV failed closed B. SG B controlling steam flow channel failed low C. Steam Header Pressure PT-557 failed low D. SG Feedwater Inlet Pressure PT-558 failed low l
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f I STP Reactor Operator Exam Question 47 Given the following conditions:
. Plant is operating at 70% power
. SG 1 A STM/FW FLOW MSMTCH alarm is received
. SG A Feed Water Regulating Valve (FWRV) demand signal is increasing
. SG A level is increasing
. SG B, C and D levels are decreasing Which ONE of the following explains the reason for these indications?
A. Loss of Class 1E control power to SG A FWRV FCV-0551 B. Controlling level channel for SG A failed high C. Steam pressure for the controlling steam flow channel to SG A failed high D. Controlling feed water flow channel to SG A failed high l
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l STP Reactor Operator Exam Question 48 Given the following:
. Unit 1 is performing a Mode 3 cooldown
. RCS is at 520 oF and 1800 psig
. A loss of power occurs on 120 VAC vital distribution panel DP-001
. The crew enters OPOP04-VA-0001, Loss of 120 VAC Class Vital Distribution
. A Plant Operator is directed to locally open the l A SG PORV for temperature control OPOP04-VA-0001, cautions the Plant Operator to NOT open the SG PORV more than 50%.
Which ONE of the following is the reason for this caution?
A. Prevent excessive cooldown with limited RCS instrumentation available.
B. Minimize the mass loss out of the l A SG with limited AFW capability.
C. Ensure the ability to reclose the 1 A SG PORV following opening.
D. Avoid an inadvertent safety injection actuation on low steam line pressure.
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Question 49 l l 1
Unit 1 is operating at 77% power performing a power ascension when the operator notices the ;
following conditions:
- C-20 AMSAC BLOCKED lampbox is illuminated e C-7 TURB IMP PP.ESS STM DUMP PERMISSIVE lampbox is illuminated I
. TURBINE POWER P-13 CH 1 bistable light is illuminated !
- TURBINE POWER P-13 CH 2 bistable light is extinguished l
. Tave is 583.88 F e Trefis 583.93 F e STM DUMP UNBLOCK AVAILABLE light is illuminated 1
Which ONE of the following is responsible for these indications? !
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l A. Turbine Impulse Pressure Transmitter PT-505 has failed low.
B. Turbine Impulse Pressure Transmitter PT-505 has failed high.
C. Turbine Impulse Pressure Transmitter PT-506 has failed low. I D. Turbine impulse Pressure Transmitter PT-506 has failed high.
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- STP Reactor Operator Exam Question 50 Unit 1 is operating at 100% power when a leak develops in the Component Cooling Water System. OPOP04-CC-0001, Loss of Component Cooling Water, is entered.
. Level in the CCW surge tank is 63% and decreasing slowly.
Which ONE of the following components is a potential source of the leak?
A. Letdown Heat Exchanger (Hx)
B. Reactor Coolant Pump 1C motor air cooler C. Reactor Coolant Drain Tank Hx D. Excess Letdown Hx l
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STP Reactor Operator Exam Question 51 l
The plant has experienced a Large Break LOCA. The crew is performing the actions of 0 POP 05-EO-E000, Reactor Trip or Safety Injection, to mitigate the event.
I At Step 15 of 0 POP 05-EO-E000:
. The Unit Supervisor directs the Primary RO to " Check if Containment Spray is required".
. The Primary RO reports that Containment Pressure is 13 psig and that Containment Spray has initiated.
In accordance with OPOP05-EO-E000, Step 15, which Component Cooling Water (CCW) valve (s) must be verified closed at this time? 1 CCW valve (s) to and/or from the: i 1
A. Spent Fuel Pool licat Exchangers B. Excess Letdown lleat Exchanger C. CCW Common Header D. Reactor Coolant Pumps i
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F STP Reactor Operator Exam Question 52 Unit i is operating at 100% power with the following conditions:
. Annunciator 04M7/A7, RCP 1D SEAL WTR INJ FLOW LO, is illuminated
. Seal injection Dow indicates 4.5 gpm for Reactor Coolant Pump (RCP) 1D
. CCW lix outlet temperature is 90 "F
. RCP 1 D lower seal water bearing temperature is 210 "F
. RCP 1 A,1B and 1C seal injection Dows indicate 8.8 gpm
. Efforts to raise RCP 1D seal injection How by throttling open 1-CV-0032D, RCP ID SEAL WATER TliROTTLE VALVE, have not been successful Per OPOP04-RC-0002, Reactor Coolant Pump Off Normal, which ONE of the following conditions must be satisfied in order to maintain RCP ID in operation?
A. Component Cooling Water How to RCP 1D themaal barrier is verified >30 gpm.
B. RCP 1D lower seal water bearing temperature is verified <240 "F.
C. RCP 1D number one scal leakoffisolation valve is verified closed.
D. RCP 1D number one seal inlet temperature is verified <250 F.
Page 52 of 100
STP Reactor Operator Exam Question 53 Given the following:
. A Reactor Trip occurs due to a Loss of Offsite Power
. The ESF Diesel Generators have all started and restored power to their ESF buses
. The Control Room crew has just completed the immediate Actions of 0 POP 05-EO-EOOO, Reactor Trip or Safety injection Which ONE of the following correctly identifies the status of Containment Cooling?
l A. The RCFCs are running and CCW is flowing through the cooling coils.
1 B. The RCFCs are running and there is NO flow through the cooling coils. j I
C. The RCFCs are NOT running and CCW is flowing through the cooling coils. I D. The RCFCs are NOT running and there is NO flow through the cooling coils.
1 Page 53 oi io0
STP Reactor Operator Exam Question 54 I
Unit I was operating at 100% power when a reactor trip and safety injection occurred. Which j ONE of the following combinations states the expected valve position for each valve listed? l NNS LOADS SFP HX INL CCW HX 1 A CCW HX 1 A INL ISOL ISOL OUTL TEMP FLOW CONT CONT (MOV-235/236) (MOV-447/032) MOV-642)
(MOV-643) H < 83 psr A. Closed Open Open Open B. Closed Closed Open Closed C. Closed Closed Closed Closed D. Open Closed Closed Open j
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l STP Reactor Operator Exam l_ Question 55 l
l Unit 1 is operating at 100% power when annunciator 04M7/B1 RCP 1 A NO 1 SEAL LKF FLOW Hl/LO goes into alarm. Seal leakoff Gow for RCP 1 A indicates 0.9 gpm on FR-0156.
Which ONE of the following is the probable cause for the seal leakoff Gow being low?
A. High seal water injection temperature B. Loss of seal injection Dow j l
C. Excessive #2 sealleakage D. Low VCT Pressure Page 55 of 100
STP Reactor Operator Exam Question 56 Unit 1 is operating at 90% power when the following annunciator and Bistable Monitoring Panel j (BSMP) indications are received: l
- 5M2/F2 UV RX PRETRIP e BSMP - RCPIB U/V RX TRIP NO other alamis or changes in indications or equipment status are observed.
Which ONE of the following statements is correct?
A. Control of RCP 1B from the Control Room has been lost.
B. The Auxiliary Bus 1G UV device should have tripped RCP IB.
C. The Reactor Protection System failed to actuate and initiate a reactor trip. l D. The RCP 1B UV device has failed.
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l STP Reactor Operator Exam Question 57 A MODE 111 actuation of the sequencers has occurred.
In addition to resetting the Safety Injection, which ONE of the following MUST ALSO be l
performed in order to return the LHSI pumps to a standby condition in AUTO?
A. Reset the sequencer Mode I Logic (locally)
B. Reset SI AUTO RECIRC 1
C. Reset P-4 by closing the Reactor Trip Breakers D. Reset the sequencers (CP-003) l I
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STP Reactor Operator Exam Question 58 Given the following conditions:
. A steam line break occurred in containment
. Containment pressure reached the Containment Pressure Hi-3 setpoint 45 seconds after the Mode i Sequencer started A Loss of Offsite Power (LOOP) occurred 2 minutes after the Mode i Sequencer started When should the Containment Spray pumps have started following the LOOP?
A. As soon as the 4160 ESF Bus is re-energized by the Standby Diesel Generator.
B. 15 seconds afler the Mode 11I Sequencer started.
C. 30 seconds after the Mode 111 Sequencer started.
D. 40 seconds after the Mode III sequencer started.
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f STP Reactor Operator Exam Question 59 Which ONE of the following describes the effect that a loss of compensating voltage to NI-35 will have on the Reactor Protection System (RPS)?
A. On a plant shutdown, when P-10 resets an IR High Level Trip will occur.
B. At high power, it will cause an IR/PR Rod Withdrawal Block. !
C. On a reactor shutdown, P-6 will clear early and a SR liigh Flux Trip will occur.
D. On a reactor shutdown, P-6 will NOT clear and remergi7e se Source Range Detectors 4 m . n , s..o m, _,m, j i
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[ STP Reactor Operator Exam Question 60 I
Unit 1 is operating at 100% power when annunciator 5M03/A8 SSPS DC PWR LOSS TRN R l
goes into alarm. Per OPOP09-AN-05M3-A-8 an operator was dispatched to the Logic Train R cabinet and reported that a 48 VDC power supply light is NOT lit.
l Considering these conditions, the occurrence of which ONE of the following power supply l
failures would result in a reactor trip?
Failure of a:
1 A. +15 VDC Train R power supply. I 1
B. +48 VDC Train R power supply.
1 C. +15 VDC Train S power supply. 1 D. +48 VDC Train S power supply. j l
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f STP Reactor Operator Exam Question 61 Unit 1 is in Mode 3 preparing to start up the reactor when the following occurs:
. Turbine Impulse Pressure channel PT-506 fails high.
Which ONE of the following Reactor Trip signals is ENABLED under these conditions?
Reactor Trip from:
A. Low Pressurizer Pressure.
B. Loss of Reactor Coolant Flow in 1 Loop.
C. Pressurizer Low Water Level.
D. Turbine Trip.
Page 61 of 100
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l STP Reactor Operator Exam Question 62 1
Unit 1 is operating at 100% power when a Large Break LOCA occurs. Five minutes later, the Primary Operator notices the following:
. ECW Pump 1B is running
. ECW Train IB Blowdown Isolation Valve is closed
. ECW Train 1B Screen Wash Booster Pump is running ECW Pump 1B Discharge Valve indicates intermediate position (red AND green lights lit)
. ECW Trains A and C are operating nomially
. The yard watch reports the ECW Pump 1B Discharge Valve is 50% open Which ONE of the following is true conceming ECW Train 1B?
A. Safety Injection actuation has blocked the trip of the pump to allow the train to operate.
The pump will continue to run even if deadheaded by a closed discharge valve.
B. Safety injection Train B was reset prior to the discharge valve reaching full open. The discharge valve will open fully when the control switch is taken to OPEN.
C. Safety Injection Train B did not actuate. Manually actuating Safety injection will open the discharge valve fully.
D. ECW Pump 1B did not recei start signal from the sequencer. The pump was running prior to the Large Break LOC l
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STP Reactor Operator Exam Question 63 During a reactor startup, the P-6 permissive is verified at approximately 1.0E-10 amps on the Intermediate Range NIs. At this power level, how much margin exists until the reactor trips due to Source Range Hi-flux)t 'rew +k L 6< % t-Pfn..u'c' Approximately:
A. one-halfdecade B. one decade C. one and one-half decades D. two decades l
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STP Reactor Operator Exam Question 64 Unit 1 is operating at 100% power with the following initial conditions:
. CCW Train A operating
. ECW Trains A & B operating
. MCC ElB3 de-energized; crew investigating A Reactor Trip occurs followed by a Safety injection due to low pres.surizer pressure. The crew has completed the immediate actions of 0 POP 05-EO-E000, Reactor Trip or Safety injection, and 3M T 'Ts'p7ochedidg,through the procedure.
The following conditions exist:
+ Rx Power: 2.0E-7 amps
+ Containtiet Pressure: +0.2 psig
, Tave: 557 'F ,
- Przr Pressuc. .' 850 psig
+ Przr Level: 12%
+ Control Rod E5: 240 steps
+ MCC ElB3: de-energized
+ CV-FI-0205: 150 gpm l l
Which ONE of the following is the correct action to implement?
A. Commence Emergency Boration.
B. Manually actuate Phase A.
C. Place SDG 12 in Emergency Stop.
D. Increase charging to maximum.
ene w or no
STP Reactor Operator Exam Question 65 The Supplementary Containment Purge valves are open.
Which ONE of the following set of conditions would automatically close the Supplementary Containment Purge valves?
A. RT-8012, RCB Purge Exhaust Monitor failure OR a manual Safety Injection actuation.
B. RT-8012, RCB Purge Exhaust Monitor failure OR a manual CR Ventilation Emergency Recirculation actuation.
C. RT-8011, RCB Atmosphere Monitor failure OR a manual CR Ventilation Emergency Recirculation actuation.
D. RT-8011 RCB Atmosphere Monitor failure OR a manual Safety Injection actuation.
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m STP Reactor Operator Exam Question 66 Given the following conditions: I
\
. Plant is in Mode 6 )
- Fuel movement is in progress
. Supplementary purge is in ser/ ice RT-8013, RCB Purge Exhaust Monitor, spuriously goes in to high alarm.
Which ONE of the following describes the response of the Supplementary Purge System?
A. Continues to operate normally.
l B. All Supplementary Purge isolation valves close with subsequent trip of the running fans. !
l C. Only Train A powered Supplementary Purge isolation valves close D. Only Train B powered Supplementary Purge isolation valves close.
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STP Reactor Operator Exam Question 67 The Unit is in Mode 3 when the CNTMT PRESS Hl/LO alarm comes in due to a high pressure condition in containment.
Which ONE of the following is TRUE concerning the containment pressure relief that must take place under these conditions?
A. The containment pressure relief CAN be performed under an expired Containment Purge Release Pennit with Chemistry concurrence.
B. Opening the Supplementary Containment Purge valves without starting a fan does NOT constitute a containment purge.
C. With RT-80ll, Containment Atmosphere Monitor out of service, the containment pressure relief may NOT be perforrned.
D. With RT-8012, RCB Purge Monitor out of service, the containment pressure relief CAN be performed with Chemistry concurrence.
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STP Reactor Operator Exam I Question 68 The following plant conditions exist:
. Large break LOCA has occurred
. Containment pressure is 10.2 psig
. Containment temperature is 240 F
. OPOP05-EO-FRZ3, Response to liigh Containment Radiation Level, is entered Which ONE of the following actions is required in accordance with OPOP05-EO-FRZ3?
I A. Sample containment atmosphere activity using the PASS.
B. Ensure all Reactor Containment Fan Coolers are running.
C. Verify Containment Ventilation isolation has occurred.
D. Place the Containment Carbon Filter Units in service.
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STP Reactor Operator Exam Question 69 The plant is operating at 100% power when Instrument Air pressure begins to decrease. The BOP operator reports that instrument Air pressure is 95 psig and slowly lowering.
Which ONE of the following actions should have already occurred?
A. l(2)-IA-PV-8561, instrument Air Dryer Bypass Valve is OPEN B. 1(2)-CV-FV-0011, Letdown Orifice Header Isolation Valve is CLOSED C. 1(2)-IA-PV-8568, instrument Air to Yard Isolation Valve is CLOSED D. 1(2)-IA-PV-8559, Service and instrument Air Crossover Valve is OPEN b %) bh I
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STP Reactor Operator Exam Question 70 l
OPOP05-EO-EC01, Loss oi All AC Power Recovery Without SI Required, directs the Operator to start the INST AIR EMERGENCY COOLING WATER PUMP if the Closed Loop Auxiliary Cooling Water System is not in service.
Which ONE of the following describes the suction supply to the INST AIR EMERGENCY COOLING WATER PUMP?
A. Open Loop Cooling Water System supply header B. Turbine Generator Building Fire Water main header C. Circulating Water System discharge header D. Closed Loop Auxiliary Cooling Water System supply header i
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l STP Reactor Operator Exam Question 71 Which ONE of the following describes the EMERGENCY power supply to Instrument Air Compressor #12? .
A. TSC diesel generator which energizes LC IU B. TSC diesel generator which energizes MCC IG5 )
C. BOP diesel generator which energizes LC IU D. BOP diesel generator which energizes MCC IG5 1
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r STP Reactor Operator Exam Question 72 Unit 1 is in Mode 4, coming out of a refueling outage, when a loss ofinstrument air occurs.
Given the following:
. Narrow Range SG levels; 1 A = 40%,1B = 35%,1C = 55%, 1D = 20%
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. All motor driven AFW Pumps are operable
. RHR Train 1B is in service and supplying Low Pressure Letdown I
. RHR Train I A and IC are available
. S1 Pumps are in the normal Mode 4 alignment
. Both Pressurizer PORVs are operable
. Vacuum has been established in the Main Condenser
. Three Circulating Water pumps are running Which ONE of the following RHR valve alignment methods are Control Room operators directed to use for RCS temperature control in accordance with OPOP04-1A-0001, Loss of Instrument Air, Addendum 6, RCS Temperature Control on RHR?
A. LOOP B TC INJ MOV-0031B - open, Cycle RHR B Heat Exchanger OUTL TEMP CONT HCV-0865 as needed for temperature control. I B. MINI FLOW MOV-0067B - open, Cycle RHR B Heat Exchanger BYP FLOW CONT FCV-0852 as needed for temperature control.
C. MINI FLOW MOV-0067B - open, Cycle LOOP B TC INJ MOV-0031B as needed for temperature control. l l
D. LOOP B TC INJ MOV-0031B - open, Cycle RHR B Heat Exchanger CCW OUTL FV-4548 as needed for temperature control.
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( STP Reactor Operator Exam Question 73 Operators are at the Auxiliary Shutdown Panel (ASP) following evacuation of the Control Room.
RCS temperature was being controlled using the Residual Heat Removal (RHR) system.
Which ONE of the following should the operators be aware of when transferring RHR Heat Exchanger (llX) controls to the ASP?
A. . There is no control of the RHR HX Bypass Flow Control Valves on the ASP.
. The operators have manual control of the RHR HX Outlet Temperature Control Valves.
. Total RHR How is controlled automatically at 3500 gpm.
B. . Automatic control of the RHR HX Bypass Flow Control Valves is defeated.
. The operators have manual control of the RHR HX Outlet Temperature Control Valves.
. The operators must manually control total RHR Dow.
C. . Automatic control of the RHR HX Bypass Flow Control Valves is still available.
. Automatic control of the RHR HX Outlet Temperature Control Valves is defeated.
. The operators have manual control of the RHR HX Outlet Temperature Control Valves.
D. . Automatic control of the RHR HX Bypass Flow Control Valves and RHR HX Outlet Temperature Control Vahes is still available. l
. There is no indication of RHR Gow or temperature at the ASP. l
. Total Dow and outlet temperature must be monitored locally at the RHR HX. l Page 73 of l00
STP Reactor Operator Exam Question 74 Unit 1 is in Mode 5 with the following conditions:
. RCS level is -1 inches and decreasing on the narrow range hot leg level indicators
. RilR Train A is in service
. Rif R Trains B and C are in standby
. The operator notices erratic current and discharge flow indications on RIIR pump A
. OPOPO4-Ril 0001, Loss of Residual 11 eat Pemoval, is entered Per OPOPO4-Ril-0001, which ONE of the following actions should be taken by the operator? I A. Stop RliR pump A, THEN start RHR pamp B or C.
B. Stan R11R pump B or C, T11EN stop RHR pump A.
C, Stop RilR pump A, THEN isolate letdown.
D. Stop RHR pump A, THEN start at least one available HHSI pump.
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I STP Reactor Operator Exam Question 75 Assuming all equipment is operable unless indioted otherwise, which ONE of the following sets I
of conditions would place the Unit in a Technical Specification % huruimg
~s%.hnn%Coud;ima fu Opaauun mi A. The Unit is in Mode 3 and 2 RCPs are in operation; RiiR Pump A is removed from service for maintenance.
B. The Unit is in Mode 5 with SGs in wet layup and 1 RCP and RHR Train A in operation; j RHR Pumps B and C are removed from service for modifications.
C. During fuel movement in the reactor vessel, all RHR pumps are stopped for 35 minutes to place an assembly near a hot leg opening.
D. During fuel movement in the reactor vessel with 2 RHR Trains in service,1 RHR Pump trips.
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1 STP Reactor Operator Exam l
l Question 76 l
l Unit 1 is operating at 100% power.
1 Given the following conditions: l l
. 4M08/E2 VCT LEVEL Hl/LO alarm
. VCT Level on CP-004: 34%
. VCT Pressure on CP-004: 20 psig
. Divert Valve, LCV-112A, indicates full divert to the RilT Which ONE of the following instrument failures is the cause for these plant conditions?
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A. VCT level Transmitter 112 has failed low l B. VCT Level Transmitter 112 has failed high 1
j C. VCT level Transmitter 113 has failed low D. VCT level Transmitter 113 has failed high l
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STP Reactor Operator Exam Question 77 Unit 1 is operating at 100% power with all systems in their normal lineup. A small RCS leak develops in the Chemical and Volume Control System (CVCS) with the following Control Room indications:
. Pressurizer level indicates 50% and is decreasing
. RCS pressure indicates 2220 psig and is stable l . - Containment pressure is normal l . LETDN HX OUTLET PRESSURE PI-0135 indicates O psig l . PRT PRESS HI alarm is illuminated
- . LETDN HX OUTL FLOW Hl/LO alarm is illuminated
. ERFDADS Points (2) CVCS LTDN AREA TEMP TRN H1 are in alarm j
Considering these indications, which ONE of the following* AUTOMATIC actions has taken place? ( Ab'*d'eu y
- x u s d m Fone +it airion ocwed
{
TCV-0143, Letdown Temperature Divert Valve, positioned to the VCT.
l A. 4 I B. MOV-0023/0024, Letdown Line Containment Isolation Valves closed.
! C. FV-0011, I.ctdown Header Orifice Isolation Valve closed.
D. PCV-0135, Letdown Pressure Control Valve opened.
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I STP Reactor Operator Exam i
i Question 78 l
Unit I was operating at 100% power with Boric Acid Pump 1 A OOS for motor replacement. A feedwater control failure results in the crew manually tripping the unit. The crew has transitioned to OPOP05-EO-ES01, Reactor Trip Response.
i The following conditions exist:
. 2 Control Rods indicate 12 steps
. 1 Control Rod indicates 18 steps I
The Reactor Operator attempts to Emergency Borate, but Boric Acid Pump IB fails to start. The following indications are observed:
- Both pump status lights (Green & Red) are extinguished
+ Bypass /Inop 4M05/C2 BA XFER PUMP IB is illuminated Which ONE of the following PAIRS of Emergency Boration flowpaths are available to be used?
l A. 1-CV-0221 Manual Altemate immediate Borate & l Emergency Boration Via Gravity Feed. ;
1 B. Emergency Boration from RWST & l Emergency Boration Via Gravity Feed.
C. Emergency Boration Through Nomial Boration Flowpath & l Emergency Boration from RWST D. Emergency Boration Through Normal Boration Flowpath &
1-CV-0221 Manual Altemate immediate Borate l
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S1 P Reactor Operator Exam Question 79 Unit I is operating at 100% power. OPSP03-RS-0001, Monthly Control Rod Operability,is being perfonned.
Test Performer notes that two (2) rods in Control Bank A did not move
- Investigation reveals the rods are untrippable Which ONE of the following is required by Technical Specifications?
Within I hour:
A. ensure the remainder of the group is aligned within 12 steps and restore the rods to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B. declare the rods inoperable and ensure the remainder of the group is aligned within 12 steps.
C. verify Shutdown Margin is satisfied and be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. trip the reactor and initiate Emergency Boration.
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STP Reactor Operator Exam Question 80 An inadvenent Safety injection hasjust occurred on Unit 1. During the perfonnance of OPOP05-EO-E000, Reactor Trip or Safety Injection, the operator checks the status of RCP Seal Injection and notes that the Seal Injection Containment Isolation Valves are closed.
Which ONE of the following would explain the reason for the valves being closed?
A. liigh differential pressure across the RCP #1 seal B. liigh seal return temperature C. liigh seal injection flow D. The running charging pump has tripped l
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i S FP Reactor Operator Eum Question 81 Given the following:
- Unit 1 is operating at 90% power, steady-state, following a power increase
. Chemical Analysis reports that RCS samples indicate increasing RCS activity e RT-8039, CVCS Letdown Failed Fuel Monitor is NOT in alarm
. Decontamination Factor (DF) across the inservice mixed bed demineralizer is adequate e CVCS letdown Dow is 140 gpm Which ONE of the following actions, as directed by Chemical Analysis, is in accordance with OPOP04-RC-0001, High Reactor Coolant System Activity?
A. Maintain present letdown flow and place the alternate mixed bed demineralizer in sen ice.
B. Maintain present letdown flow and place the cation demineralizers in service.
C. Maximize letdown Dow and place the alternate mixed bed demineralizer in service.
D. Maximize letdown flow and place the cation demineralizers in service.
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STP Reactor Operator Exam ;
Question 82 Charging flow has automatically DECREASED from 115 gpm to 50 gpm.
l Which ONE of the following indicates the failure that would cause the change in flow?
l A. PT-505, Turbine Impulse Pressure, failed low
! B. Controlling Pressurizer Level channel failed high C. Loop 2 Tc failed high D. Loop 4 Tu failed low l
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STP Reactor Operator Exam Question 83 The Reactor Operator is making a blended addition to the Volume Control Tank and sets up the controls as follows:
. TOT M/U BATCli integrator set for 400 gallons e BA BATC11 integrator set for 70 gallons e RC M/U CONT selector switch set to M AN e All blender valves in AUTO e RC M/U CONT is taken to START and the blending operation begins Due to a malfunction, the TOT M/U BATCH integrator stops counting the gallons added part way through the operation. l Assuming the malfunction goes unnoticed by the operator, which ONE of the following describes the effect of the malfunction: {
A. Reactor Makeup Water will continue to inject until stopped by the operator, causing a dilution of the RCS. j B. Boric Acid will continue to inject until stopped by the operator, causing a boration of the RCS.
C. Boric Acid and Reactor Makeup Water will both continue to inject at their present flowrates until stopped by the operator causing the Volume Control Tank to fill with properly blended flow.
D. Boric Acid and Reactor Makeup Water will both stop injecting immediately and operator action will be required to continue blending.
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I Sl P Reactor Operator Exam Question 84 In accordance with Technical Specifications, which ONE of the following describes the TYPE and LIMIT for RCS leakage into the Pressurizer Relief Tank (PRT)?
RCS leakage into the PRT is considered:
A. UNIDENTIFIED LEAKAGE with a limit of I gpm.
B. UNIDENTIFIED LEAKAGE with a limit of 10 gpm.
C. IDENTIFIED LEAKAGE with a limit of I gpm.
D. IDENTIFIED LEAKAGE with a limit of 10 gpm.
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1 STP Reactor Operator fixam Question 85 Which ONE of the following design features prevents the formation of explosive mixtures in the Gaseous Waste Processing System (GWPS)?
A. An 02 monitor is installed in the GWPS inlet header to shutdown the system if the 02 concentration reaches 1%.
13 . An 02 monitor is installed in the GWPS inlet header to shutdown the system if the 02 ,
concentration reaches 4%. l C. An 112 monitor is installed in the GWPS inlet header to shutdown the system if the H2 concentration reaches 1%.
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D. An 112 monitor is installed in the GWPS inlet header to shutdown the system if the H2 concentration reaches 4%.
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( STP Reactor Operator Exam Question 86 Given the following:
. Unit 2 is in Mode 4
. VCT is aligned to the GWPS
. GWPS Inlet lieader valve (FV-4657) and Discharge Flow valve (FV-4671) handswitches are in their NORM AL positions on the Rad. Waste Control Panel
. A high alarm condition occurs on RT-8032, GWPS Outlet radiation monitor which ONE of the following correctly describes the final position of the GWPS Inlet licader (FV-4657) and Discharge Flow (FV-4671) valves?
A. Inlet licader valve (FV-4657) CLOSED and Discharge Flow valve (FV-4571) CLOSED.
B. Inlet licader valve (FV-4657) CLOSED and Discharge Flow valve (FV-4671) OPEN.
C. Inlet licader valve (FV-4657) OPEN and Discharge Flow valve (FV-4671) CLOSED.
I D. Inlet IIcader valve (FV-4657) OPEN and Discharge Flow valve (FV-4671) OPEN.
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r-I STP Reactor Operator Exam Question 87 Unit 2 is operating at 100%, nearing end of cycle and a fuel defect has been identified.
Which ONE of the following would be responsible for an increase in plant vent Noble gas activity?
A. Pressurizer ReliefTank (PRT)
B. Reactor Coolant Drain Tank (RCDT)
C. Recycle Holdup Tank (RHT)
D. Waste Monitor Tank 2D (WMT 2D)
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I ST P Reactor Operator Exam Question 88 The following conditions exist on Unit 2:
. Mid Loop conditions have been established with all core exit thennocouples (CETs) operable.
. Preparations are being made to install SG nozzle dams.
Which ONE of the following describes the consequences of a CET developing an open circuit?
On Qualified Display Parameter System (QDPS), the CET temperature will:
A. indicate 4LO. The operator then needs to verify that at least 5 CETs remain operable on each train.
B. indicate 4LO. This makes the RC MID LOOP CORE EXIT TEMP lil alarm inoperable.
C. indicate 7111. This causes a high temperature alarm to be generated by " CORE EXIT TEMP TR-0001" D. indicate till. The operator needs to begin logging the fiflh highest QDPS core exit themloccuple reading at least every 10 minutes.
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STP Reactor Operator Exam Question 89 Digital Rod Position Indication (DRPI) input to the Plant Computer has failed.
Which ONE of the following describes the effect of the failure on the Plant Computer?
The Plant Computer is unable to:
A. monitor rod insertion limits making the BANK INSRT LO-LO alarm inoperable.
B. calculate Axial Flux Difference (AFD) making the AXIAL FLUX DIFFERENCE H1 alann inoperable.
C, calculate Quadrant Power Tilt Ratio (QPTR) making the PR UPPER DET FLUX DEV Hl/ AUTO DEF and the PR LOWER DET FLUX DEV HI/ AUTO DEF alarms inoperable.
D. monitor control rod deviation making the ROD SUPV MNTR ROD POSITION TRBL alamt inoperable.
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STP Reactor Operator Exam Question 90 Diesel Fire Pump #11 needs to be run for 20 minutes to perform an engineering test.
Which ONE of the following indicates the location that the engine MAY be started / stopped from?
The engine:
A. CAN be started from either unit Control Room and stopped from either unit Control Room.
B. MUST be started locally in the Fire Pump House, but CAN be stopped in either unit !
Control Room.
C. CAN be started from either unit Control Room, but MUST be stopped locally in the Fire Pump liouse.
D. MUST be started locally in the Fire Pump flouse and MUST be stopped locally in the Fire Pump 11ouse.
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STP Reactor Operator Exam Question 91 When perfomaing RWST recirculation and purification, OPOP02-FC-0001 Spent Fuel Pool Cooling and Cleanup System, states that it is preferred to use SFP Demineralizer "A".
Which ONE of the following correctly states the reason for this preference?
A. SFP Demineralizer "B" may only be equalized to 2500 ppm Boron.
.B . To minimize silica contamination of the RWST.
C. SFP cooling has to be secured to use SFP Demineralizer "B".
D. To prevent transferring RWST water to the SFP.
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STP Reactor Operator Exam Question 92 With the control switch in the START position, Containment Carbon Unit Fan 11 A will NOT start.
Which ONE of the following describes why the fan will NOT start?
A. The charcoal filter liigh Temperature alann is in.
B. Containment Carbon Unit Fan 12A is already running.
C. 11C-FV-9759, Containment Carbon Unit Fan 11 A inlet damper, did not open.
D. A high differential pressure exists across the filter unit.
Page 92 of 100
STP Reactor Operator Exam Question 93 The following conditions exist on Unit 1:
. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, a fire in the Central Alami Station was reported to the control room
. Fire brigade has been dispatched
. Control Room staffis performing OPOPO4-ZO-0008, Fire / Explosion
. At 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />, the Fire Brigade Leader reports that the fire is not yet extinguished Under these conditions, which ONE of the following actions should be taken?
A. Place EAB HVAC in the Smoke Purge mode of operation.
B. Close at least one of the Control Room Envelope HVAC Train C Inlet Isolation Dampers, INL DMPR FV-9664 or FV-9665.
C. Isolate EAB HVAC Train C using the train actuation handswitch in the stairwell.
D. Actuate the deluge valves for the Control Room Envelope Train C filters.
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STP Reactor Operator Exam )
Question 94 Which ONE of the following will PREVENT a Circulating Water (CW) Pump from starting?
(Blue PERM SATISFIED light NOT lit) l -
A. Piping downstream of the discharge valve is full.
B. Seal water pressure is 45 psig.
I C. Discharge valve is fully closed.
D. A CW Pump was started 3 minutes ago.
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l STP Reactor Operator Exam l
Question 95 l
Unit 2 is at 100% power performing a release of Waste Monitor Tank (WMT) 2C with 4 Circulating Water (CW) Pumps in service. CW Pump 24 is to be secured for maintenance.
If the release is secured at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, in accordance with OPOP02-CW-0001, Circulating Water System Pump Operation, when is the earliest CW Pump 24 can be removed from sersice?
A. 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> B. 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> C. 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> D. 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> l
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STP Reactor Operator Exam Quet. ion 96 Following a Loss of Offsite Power, which ONE of the following statements describes the pressurizer heater groups that will be available to maintain pressurizer pressure?
A. Control heater group C only B. Backup heater groups A and B only C. Backup heater groups C and D only D. All backup heater groups i
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l STP Reactor Operator Exam Question 97 During operation at 95% power with pressurizer level at 53%, the Tave input (Auctioneered liigh) to the pressurizer level controller fails low.
Which ONE of the following is an indication that this failure has occurred?
A. Backup heaters energize, I Charging flow control valve opens, PRZR LEVEL DEV LO alann actuates.
B. Backup heaters energize, Charging flow control valve closes, PRZR LEVEL DEV HI B/U HTRS ON alarm actuates.
C. Backup heaters de-energize, -
Charging flow control valve closes, PRZR LEVEL DEV HI B/U HTRS ON alarm actuates.
D. Backup heaters de-energize, Charging flow control valve opens, PRZR LEVEL DEV LO alarm actuates.
Page 97 of 100 L_
I' STP Reactor Operator Exam Question 98 Unit 1 is operating at 100% power with Pressurizer Pressure Contral selected to P455/456 when power to PT-455 is lost.
Which ONE of the following will occur with NO operator intervention?
A. Reactor trip on high pressure B. Reactor trip on OTAT C. PCV-655A will control pressure D. PCV-656A will control pressure l
Page 98 of 100
STP Reactor Operator Exam Question 99 Given the following:
. PRZR safety valve fails open
. PRT PRESS H1 alarm comes in
. Operator notices PRT pressure is 10 psig and increasing
. Later, the Operator notices PRT pressure is O psig Which ONE of the following explains why PRT pressure decreased?
A. Responding to the high-pressure condition, FV-3653, PRT to GWPS ICIV opened, venting the PRT to the GWPS.
B. Responding to the high-pressure condition, FV-3650, PRT SPRAY ISOL opened, l spraying Rh1W into the PRT vapor space to reduce pressure.
C. Responding to the subsequent high level, LV-4911, RCDT LEVEL CONT VLV opened, lowering PRT level and consequently PRT pressure. I D. Responding to the subsequent over pressure condition, the PRT rupture disc blew venting the PRT to the containment.
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STP Reactor Operator Exam Question 100
( Which ONE of the following describes the effect on Containment Hydrogen concentration with a single Hydrogen Recombiner operating during recovery from a Large Break LOCA?
Containment hydrogen concentration:
A. can be maintained less than 4% by the Hydrogen Recombiner.
B. would be greater than 4% but can be maintained less than the flammable limit of 10% by i the Hydrogen Recombiner.
C. can be maintained less than 4% with the Hydrogen Recombiner AND Supplemental Purge operating together.
l D. would be greater than 4% but can be maintained less than the flammable limit of 10% by the Hydrogen Recombiner AND Supplemental Purge operating together.
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l RO EXAM SHORT ANSWER KEY Question # Answer Question # Answer Question # Answer Question # Answer 1 D 31 B 61 A 91 B l 2 C 32 D 62 A 92 C 3 C 33 C 63 A 93 C D
4 34 C 64 B 94 D 5 C 35 B 65 A 95 A 6 A 36 A 66 B 96 B 7 C 37 C 67 A 97 B 8 A 38 D' 68 C 98 D 9 B 39 B 69 D 99 D
. 10 A 40 D 70 D 100 A 11 B 41 C 71 D 12 A 42 D 72 C 13 B 43 A 73 B 14 A 44 A 74 C f 15 D 45 B 75 A 16 A 46 D 76 D 17 D 47 C 77 B 18 C 48 C 78 B 19 C 49 C 79 C 20 A 50 B 80 D 21 C 51 D 81 D 22 C 52 A 82 B 23 B 53 B 83 A 24 D 54 B 84 D 25 D 55 C 85 A 26 C 56 D 86 A 27 D 57 D 87 D 28 C 58 B 88 A 29 A 59 D 89 D j 30 C 60 B 90 C t una.n. AA ori. t en Pagei ofI
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