IR 05000382/1996008
| ML20129A086 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/17/1996 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20129A079 | List: |
| References | |
| 50-382-96-08, 50-382-96-8, GL-95-06, GL-95-6, NUDOCS 9610220023 | |
| Download: ML20129A086 (161) | |
Text
ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.:
50-382 License No.:
NPF-38 Report No.:
50-382/96-08 Licensee:
Entergy Operations, Inc.
Facility:
Waterford Steam Electric Station, Unit 3 Location:
Taft, Louisiana Dates:
September 9-20,1996 inspectors:
Ryan Lantz, Lead Inspector Tom Meadows, Chief Examiner Michael Murphy, Examiner David Graves, Senior Project Engineer Lee Keller, Senior Resident Inspector Approved By:
Tom McKernon, Acting Chief, Operations Branch Division of Reactor Safety ATTACHMENTS:
Attachment 1:
Partial List of Persons Contacted Attachment 2:
Procedures Reviewed Attachment 3:
Simulation Facility Report Attachment 4:
Final Written Examination and Answer Key 9610220023 961017 POR ADOCK 050003G2 G
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1 EXECUTIVE SUMMARY l
Waterford Unit 3
NRC Inspection Report 50-382/96-08 This inspection evaluated the competency of eight reactor operator license applicants to be issued operating licenses at your facility and also reviewed the licensed operator
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requalification program. The initial license examinations were developed by your facility
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using the pilot process program guidance and approved and administered by NRC examiners. Guidance for conduct of the pilot examinations was contained in Generic Letter 95-06 and Attachment 1 to Regional Office interaction Memorandum 9525. The licensed l
operator requalification program was assessed to determine whether the program
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incorporated appropriate requirements for both evaluating operators' mastery of training i
objectives and revising the program in accordance with 10 CFR Part 55.59(c). The licensed operator requalification program assessment included an evaluation of the program's controls to assure a systems approach to training, and evaluation of operating crew performance during annual requalification examinations. This included review of the facility documents, observation of operating and staff crews during dynamic simulator j
scenarios and plant walkthroughs, and an assessment of the examination evaluators'
i effectiveness in conducting examinations.
l-The initial written examination was administered to eight reactor operator applicants on l
September 6,1996. The operating tests were administered September 9 through l
12,1996. In general, all applicants displayed the requisite knowledge and skills to satisfy i
the requirements of 10 CFR 55 and were issued the appropriate licenses. No significant generic performance weaknesses were identified during the examinations. The facility's
annual operating test for licensed operator requalification was administered September 16 i
and 17. The biennial comprehensive requalification written examination was not i
administered this cycle. All operators participating in the annual operating test for requalification passed their evaluated examinations. Although no examination compromise
was indicated nor suspected, a potential vulnerability to the continued validity of the
requalification examinations was identified in that the requalification program allows a j -
substantial repetition of examination questions. Moreover, the requalification program l
allows the repetition of entire examinations during any given training cycle and during the comprehensive biennial written examination.
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- The inspection also included an evaluation of the plant referenced dynamic simulator used f
to conduct the examinations and the reference documentation used to produce the examinations.
Ooerations
I All applicants passed all portions of the initiallicense examinations and satisfied
the requirements of 10 CFR 55.33(a)(2) and were issued the appropriate
licenses in accordance with 10 CFR 55.51 (Sections 04.1,04.2).
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-3-Initial written examination scores ranged from 87 to 97 percent, with an average
of 91.8. No generic knowledge or training deficiencies were identified (Section 04.1).
All applicants displayed good communication skills, teamwork, plant system
l knowledge, and ownership of plant equiprnent (Sections 04.2, F8.1).
l Overall, the licensed operator requalification training program effectively
implemented a systems approach to training (Section 05.4).
Requalification annual examinations were comprehensive and discriminated at
the appropriate level, with some observations of potential vulnerabilities noted (Sections 0 1 2,05.3).
The licensed operator requalification facility evaluators administered the
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examinations professionally and in accordance with accepted industry practices (Section 05.1).
The requalification program was effective in tracking and maintaining operator
license requirements (Section 05.4).
The licensee's training bank of written questions, sirnulator scenarios, and job
performance measures was diverse and satisfied the requirements of 10 CFR 55.59 (Section 05.5).
The licensee's process for reviewing procedure changes and design modification
for inclusion or changes in the training program was satiaf actory (Section 05.6).
Licensed operator requalification facility audits were comprehensive, self-critical,
and identified areas for potential improvement (Section 07.1).
Plant Sucoort Plant housekeeping was very good (Section F8.1).
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-4 Report Details 1. Operations
Conduct of Operations 01.1 General Observations a.
inspection Scope i
During the in-plant main control room section of the initial examination walkthroughs, the examiners observed the on-shift operators during routine operations of the facility. The facility was at 100% power for the duration of the inspection, and all observations were conducted during the day shift, ccincident with conduct of the walkthrough examinations.
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Observations and Findinas Crew communication was clear, unambiguous, consistently three legged, and consistent with communication observed in the simulatcr during conduct of both the initial and requalification simulator examinations. The on-shift crews exhibited professional demeanor and the senior operators maintained a position of oversight and command and control. Shift operators were professional, in control of plant activities, and aware of on going shift work. Operators were aware of current plant evolutions and work in progress.
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Conclusions The control room staff exhibited professionalism and good cammunications and enmmand and control.
O4 Operator Knowledge and Performance 04.1 Initial Written Examination a.
Insoection Scope The initial written examination was developed by the facility and submitted to the chief examiner for review and approval for use as an NRC license examination. The chief examiner reviewed and approved the draft as submitted, with only minor editorial and construction type revisions. The examination was administered onsite on September 6,1996.
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Observations and Findinas The reference material provided by the facility was adequate to support final i
review of the examination. The facility was responsive and provided additional material, as requested, during final review of the examination.
The facility presented a draft written examination that was technically valid and discriminating. Only minor non-technical editing was required prior to examination administration. The post administration review did not identify any additional modifications, with the exception of an answer key error which was corrected.
The chief examiner graded the examinations with scores ranging from 87 to 97 percent, and an average score of 91.8 percent. Only one question was
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missed by 50 percent or more of the applicants.
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Conclusions I
All eight applicants passed the written examination portion of the license examination. The licensed operator training program was effective in adequately preparing license applicants for the examinations and subsequent licensed duties. Evaluation of the graded examinations did not identify any generic knowledge or training weaknesses.
04.2 Initial Operatina Test a.
Inspection Scope The operating test was developed by the facility, then reviewed and approved by the chief examiner. NRC examiners administered the operating test from September 9 through 12,1996. The examiners evaluated the applicants in three areas to assess their ability to safely operate the facility. The first area, integrated plant operations, evaluated the applicants functioning in shift crews and responding to component and instrument failures, and a major plant transient er accident, and utilized the dynamic plant referenced simulator in two or more scenarios. The second area, control room and plant systems, required each applicant to respond to simulated tasks or plant conditions, using the appropriate facility procedures as a guide to complete the tasks. The third area,
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administrative topics, consisted of an oral examination of the applicants'
administrative knowledge of facility operations.
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Observations and Findinas Tne reference material provided by the f acility was adequate to support final revision of the examination. The facility was also responsive to the pilot examination process, providing appropriate staff and draft materials early in the
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examination development effort, working casely with the chief examiner. The licensee staff involved in development of the examinations signed an
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examination security agreement that was in effect during development and administration of the examinations.
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The facility draft operating exarnination was technically valid and discriminating i
as submitted for review by the chief examiner. The chief examiner made only j
minor changes to the examination prior to final approval and administration.
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During the integrated plant operations simulator examinations, the examiners observed that the applicants consistently used formal, three legged
communication. The applicants referenced and correctly implemented j
appropriate procedures when required, and exhibited good control board j
awareness and operating and diagnostic skills. During the job performance measure and administrative areas of the operating test, the applicants exhibited
j good plant ^,ystems and administrative knowledge of the facility. All of the applicants passed all sections of the operating test.
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Conclusions All applicants passed the operating test with no significant generic weaknesses observed. Communications, command and control, and system knowledge were noted strengths.
Operator Training and Qualification 05.1 Reaualification Examination Administration a.
insoection Scoce The inspectors observed the administration of all aspects of the requalification examination to determine the evaluators' ability to administer an exaniination and assess adequate performance through measurable criteria. The inspectors conducted interviews to determine the knowledge level of the managers, supervisors, and instructors with regard to the requalification program implementation. The inspectors also noted the fidelity of the plant simulator to support training and examination administration.
b.
Observations and Findinqs The inspectors observed two crews of four licensed operators each, during conduct of the dynamic simulator scenarios and job performance measure evaluations. Six training staff evaluators were observed administering the examinations, including preexamination briefings, observations of operator performance, individual and group evaluations of observations, techniques for job performance measure cuing, and final evaluation documentation. Although
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-7-differences were noted by the inspectors in feedback to the examinee regarding simulated actions by the examinee, evaluators provided appropriate responses as necessary. The evaluators conducted the examinations professionally, with no inadvertent cuir.g, and were thorough in their documentation of observed weaknesses and areas for improvement. The evaluators passed all of the operators on all portions of the examinations. Although the inspectors were not coevaluating the examinations, the inspectors concurred with the facility evaluations.
The inspectors conducted interviews with two licensed operators, two trainers who were also licensed operators, the licensed operator training supervisor and the training manager. The inspectors questioned the staff to determine their level of knowledge of the facility training program, and their perception of the adequacy of the program to maintain licensed operator skills. Each staff member interviewed, and others not formally interviewed, were very knowledgeable of program requirements and held a generally positive opinion of the effectiveness of the program. The training staff was familiar with all requalification program requirements, however, the two operators that were interviewed did not have a good understanding of the regulatory requirements for an annual operating test and comprehensive biennial written examination.
Each of the two operators gave different, incorrect answers when asked about the regulatory periodicity requirements for requalification examinations.
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Conclusions The f acility evaluators effectively implemented the examination of operators to identify deficiencies or weaknesses in the trainees and the training program.
The training staff was knowledgeable in the regulatory and facility requirements for re,ualification, however, in some instances, licensed operators relied on trab department to ensure the requirements to maintain their licenses were rr.
he f acility evaluators 6dministered the examinations professionally and in accu ance with industry standards.
05.2 Recualification Written Examinations a.
insoection Scope The inspectors reviewed the biennial comprehensive written examination that was administered August through September,1995, and the weekly written examination that was administered during the inspection on September 19, 1996. The examinations were reviewed to evaluate their validity as a licensing examination and for compliance with facility program requirement. _. _ -.
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Observations and Findinas The examinations were reviewed using guidance of NUREG-1021," Operator j
Licensing Examiner Standards," for construction, scope of coverage, and cognitive level. The biennial examination questions tested at the appropriate j
level of comprehension and were linked to important learning objectives. The questions were operationally oriented and realistic. The examinations were well
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structured and comprehensive.
The examinations that were administered to reactor operators and senior operators were identical, tested at a reasonably high cognitive level of knowledge, and sampled from topics as required by the facility training procedure NTC-108, " Licensed Operator Requalification," Revision 5, and the regulations in 10 CFR 55.41 and.43. The current revision of training department instruction NTI-OP-004, " Examination / Quiz Development," Revision 5, which implements NTC-108, requires that 5 of the 40 questions on the biennial examinations be identified as senior operator only. Revision 4 of NTI-OP-004 was in effect at the time the biennial exam was developed and administered, but was unavailable to reference. NTI level documents are not formally controlled by the f acility document control program and are not required to be maintained after revision. A copy of revision 3 to NTI-OP-004 was located, and indicated that between revision 3 and 5 the requirement was added which quantified the number of questions on a biennial examination that should be SRO only. Common to all of the revisions was Attachment 8.2, " Written Examination / Quiz Checklist," which required the examination drafter to identify SRO unique questions, but not quantitatively how to disposition them. Also, Attachment 8.8, " Written Examination Worksheet," required the examination drafter to identify which questions are SRO only, although it does not give quantitative requirements. The inspectors reviewed the biennial written examinations and estimated that on average, the exams contained 2 to 3 questions that would be considered as senior operator only level of knowledge, c.
Conclusions The biennial comprehensive written requalification examinations administered by the facility were valid licensing examinations, with appropriate scope, depth, and cognitive level. One potential vulnerability was noted in that testing reactor operators and senior operators at the same level may reduce the opportunity to evaluate the reactor operator on additional reactor operator level tasks, and conversely, may reduce the opportunity to test the senior operators in senior operator only type knowledges and abilities. The inspectors were unable to determine if the licensee failed to meet its expectation for examination development due to the unavailability of the applicable revision of the training instructio.
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05.3 Reaualification Annual Operatina Test i
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Insoection Scope
The inspectors reviewed the annual operating test that was administered on
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September 16 and 17,1996. The inspectors used the guidance in NUREG-1021
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to determine the validity of the examinations to provide a basis for evaluating the examinee's knowledge of abnormal and emergency operating procedures and operation of plant systems. The inspectors also reviewed the licensee's
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administrative procedures for developing, administering, grading, and evaluating the examinations and conducted interviews with training management, i
instructors, evaluators, and examinees.
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Observations and Findinas
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The licensee's training staff indicated that the guidelines of NUREG-1021 were
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substantially utilized for the development and administration of the licensed operator requalification examination, in addition to the facility requalification training procedures.
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NUREG-1021, contained performance standards that were clear and objective, j
and critical task acceptance criteria were well defined and measurable. The job
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performance measures adequately supported topic areas from the licensed operator requalification program 2-year training plan.
The scenarios were also developed using the guidance of NUREG-1021 and contained clearly stated objectives. The initial conditions of the scenarios were realistic and the scenarios consisted of related events. The scenarios had been
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previously validated by the training staff and allowed the evaluators to measure the examinees' competencies commensurate with the scenario objectives.
4 The simulator scenarios and job performance measures were reviewed to ensure that the task was current and that the procedures referenced in the examination instruments were current. All procedures referenced in the simulator scenarios
and the reviewed job performance measures were found to be current.
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Conclusions
The annual operating examinations were comprehensive and discriminated at the appropriate level.
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inspection Scoce This portion of the inspection was conducted to determine the effectiveness of the methodology used to develop and construct the requalification examinations and to assess the effectiveness of the examinations to identify retraining needs and measure the examinees' subject knowledge. The inspectors utilized the guidance of NUREG-1220, Rev 1, " Training Review Criteria and Procedures," to evaluate the requalification program's ability to meet elements 4 and 5 of a systems approach to training. The inspectors evaluated the ability of the program to ensure that conditions of the operator licenses are met and maintained. This evaluation included review of the feedback tracking system and remedial training program, b.
Observations and Findinas The inspectors reviewed the requalification program guidance and verified that it met and implemented the requirements of 10 CFR 55.59, "Requalification."
The inspectors reviewed two remedial training programs that had been established for operators that failed a training cycle examination. The remedial program was focused on the identified weak areas and adequately retested the operator prior to returning to licensed duties.
The inspectors noted that the requalification program guidance permitted a N percent duplication of examination questions when comparing the developed examinations for a given training cycle, and that during a seven week training cycle where five examinations would be given, only three examinations were required to be developed. This policy would allow an examination to be generated that had no new questions when compared to other examinations in the same cycle, and would also allow a repeat of a previously administered examination to two of the five crews being tested. The inspectors expressed concern that this practice of not requiring some percentage of new questions on subsequent examinations to be a decrease in the effectiveness of barriers to potential examination compromise, and therefore examination validity. The licensee stated that, although this policy did remove one barrier to potential examination compromise, they were confident that additional compensatory measures in place provided adequate assurance for examination integrity. Tt:e inspectors agreed that no apparent compromise had been suspected or evidenced, and lacking definitive regulatory guidance, this practice did meet the requirements of the licensee's systems approach to training INPO accredited requalification progra. - -.
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The inspector reviewed Operating Instruction 01-024-000," Maintaining Active SRO/RO Status," Revision 5. The procedure contained all of the requirements of l
10 CFR 55.33 regarding maintaining current SRO/RO active status and the steps j
necessary to upgrade an operator license from inactive to active status.
The licensee had a total of 12 licensed operators (10 senior reactor operators
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and 2 reactor operators) who were maintaining inactive licenses. All of the
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inactive licenses were in the training department with the exception of the operations manager. The inspector reviewed the documentation associated with-i reactivation of five licenses between March 1995 and June 1996. Control room
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operating logs were reviewed to verify that the individuals were logged into the log as part of the operating crew and in the appropriate position. All
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i requirements were found to be satisfied for each licensee.
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Conclusions
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The licensee met the requirements of their requalification program and the governing regulations in 10 CFR 55.59. The licensed operator requalification program effectively implemented a systems approach to training to identify
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l operator performance and training weaknesses and modify the training and
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evaluation program to correct the identified weaknesses. The requalification program accurately tracks, maintains, and controls the conditions of operator
licenses and reactivation of inactive licenses in accordance with
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10 CFR 55.53(e) and (f).
05.5 Examination Develoor mnt Materials
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Inspection Scope
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The inspectors reviewed items in the licensee's examination bank, including i
simulator scenarios, job performance measures, and written examination j
questions, i
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Observations and Findinas
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The inspectors determined that the licensee's examination bank contained
a 205 different scenarios at the time of the inspection. The operations training i
supervisor stated that the scenarios were reviewed immediately prior to use to
ensure that they were current with the effective procedure revision and were t
accurate with regard to expected and required actions. The scenarios utilized in
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the observed operating examination had been reviewed and approved by training department personnel several days prior to the examinations.
l The inspectors reviewed the licensee's Licensed Operator Requalification Sample
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Plan and Two Year Guide. The sample plan provided good coverage of the I
topics referenced in the regulations. The 13 simulator scenarios developed for i
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i use during the current requalification cycle were reviewed and compared to the
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plant transients and evolutions listed in 10 CFR Part 55.45(a). The simulator
scenarios, in the aggregate, contained an adequate number of events to satisfy the requirements of the regulations.
The licensee's bank of job performance measures contained 1,577 job performance items including tasks for non-licensed operators, reactor operators, and senior reactor operators. Of those tasks,78 had Knowledge and Ability ratings of 2.5 or higher, which is the minimum utilized for examination purposes.
The licensee's training bank of written examination questions contained 4,325
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items. Of that number,851 items had Knowledge and Ability ratings of 2.9 or greater.
New test items were generated regularly as new procedures were issued, as information changed, or as program requirements were revised. Additionally, the licensee was in the process of updating the Knowledge and Ability reference for allitems in the training bank to the August 1995 revision of NUREG 1122,"Knowledges and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors."
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Conclusions The licensee's training bank of written questions, simulator scenarios, and job performance measures was diverse and varied enough to satisfy the requirements of 10 CFR 55.59.
05.6 Review of Desian Chanae Trainina Feedback a.
Inspection Scoqe The inspectors reviewed the procedure change process, the design modification process, and-several design modification packages to determine whether training requirements were identified and implemented.
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Observations and Findinas Operations Instruction 01-019-000," Operations Procedure Administration Group," Revision 11, step 5.12.18, directed that the cover sheet from procedure changes, which identified the scope of the change, be sent to the training department for review. The training manager then assigned an individual to review the associated procedure change for inclusion, as necessary,into the training program and subsequent revision of training material as appropriate.
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-13-With regard to design changes, Site Procedure W4.102, " Design Changes,"
Revision 4, step 6.8.4, stated that, prior to operational acceptance of a design modification, required training, procedure changes, and surveillances that impact the equipment affected by the design change have been performed.
Ten design modification packages were reviewed to determine whether the changes were reviewed for training required or impact on existing training methods and materials, in all ten cases, the licensee provided the training requests, or similar documentation that verified that the modification had been reviewed for training requirement applicability. The training requests were sufficiently detailed to determine that the modification packages had been adequately reviewed and evaluated by the I.censee, and that the necessary changes to the training program had been implemented.
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Conclusions The licensee's process for reviewing procedure changes and design mod;fication for inclusion or changes in the training program was satisfactory.
Quality Assurance in Operator Training 07.1 Review of Operations Quality Assurance Audits a.
Insoection Scone The inspectors reviewed the results of Quality Assurance Audit SA-96-003.1,
" Performance, Training, and Qualification," conducted May 7 through June 18, 1996, which included an audit of the licensed operator requalification program.
The inspectors reviewed an additional audit of the licensed operator requalification program that was conducted June 3 through 6,1996.
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Observations and Findinas The quaNy assurance audit and the additional audit both utilized personnel from outside the Entergy organization. Both audits were comprehensive and critical
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with items for improvement noted in both reports. Training requests were initiated and tracked regarding the identified areas for improvement. Ne items were identified related to licensed operator training or requalificaticn that resulted in condition reports being initiated.
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Conclusion The audits performed in the area of licensed operator requalification were comprehensive, self-critical, and identified areas for potentialimprovement.
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Miscellaneous Operations issues 08.1 Review of the Uodated Final Safety Analysis Report Commitments
A recent discovery of ' licensee operating their facility in a manner contrary to l
the Updated Final Safety Analysis Report description highlighted the need for a specia! focused review that compares plant practices, procedures, and/or
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parameters to the Updated Final Safety Analysis Report descriptions. While
performing the inspection discussed in this report, the inspector reviewed the applicab!a portions of the Updated Final Safety Analysis Report that related to
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the areas inspected. The inspector verified that the Updated Final Safety
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Analysis Report section for licensed operator replacement and requalification j
training was consistent with the observed plant practices and procedures.
IV. Plant Support j
F8 Miscellaneous Fire Protection issues j
F8.1 General Comments i
l The inspectors observed general plant housekeeping incident to administration
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of the in plant job performance section of the operatir.g test. The facility was i
reasonably clean and welllighted and the floors were clear and free from debris.
l The applicants were conscientious to note discrepancies and inform the main j
control room.
li V. Manaaement Meetinas i
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X1 Exit Meeting Summary l
The inspectors presented the preliminary results to members of the licensee
management at the conclusion of the inspection on September 20,1996. The
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licensee acknowledged the findings presented. An interim exit meeting was i
held on September 13,1996, when the chief examiner presented observations i
following the conclusion of the initiallicense examinations.
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The licensee did not identify as proprietary any information or materials j
examined during the inspection.
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l ATTACHMENT 1 l
i PAP.TIAL LIST OF PERSONS CONTACTED
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Licensee
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T. Brown, Operations Training Supervisor
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C. Dugger, General Manager, Operations j
J. Fisicaro, Director, Nuclear Safety B. Fletcher, Licensed Operator Trainer
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C. Fugate, Shift Superintendent, Operations i
T. Gaudet, Licensing Manager i
i-S. Hymel, Licensed Operator Trainer i
J. Lenz, Emergency Planning Manager j
D. Matheny, Operations Manager i
J. O'Hern, Training Manager j
O. Pipkins, Licensing
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R. Pradus, Senior Engineer, Licensing l
M. Sellman, Vice President, Operations
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H. Shrum, Shift Superintendent, Operations
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l W. Smith, Simulator Supervisor, Training
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G. Wilsnn, Coordinator, Quality Assurance i
j A. Vest, Senior Instructor, Operations e
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NRC
T. Pruett, Rasident inspector L. Ricketson, inspector
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ATTACHMENT 2 l
PROCEDURES REVIEWED l
W4.102, Design Changes, Revision 4 01-019-000, Operations Procedure Administrative Group, Revision 11
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01-024-000, Maintaining Active SRO/RO Status, Revision 5 l
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Design Change Packages:
DCP 3076, Revision 2 DCP 3268, Revision 5 DCP 3311, Revision 2 DCP 3374, Revision 3 DCP 3383, Revision 4 DCP 3385, Revision 2 DCP 3390, Revision 0 DCP 3459, Revision 0 DCP 3460, Revision 2 DCP 3461, Revision 1 OA AuJit SA-96-003.1, Performance, Training, and Qualification i
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Westrain Inspection of Waterford 3 Training Licensed Operator Requalification Program
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NTP-101, " Operations Training Program," Revision 8
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NTP-006," Control and Administration of Examinations," Revision 7 l
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NTC-108, " Licensed Operator Requalification," Revision 5 l
l NTI-OP-003, " Control of Job Performance Measures," Revision 3 NTI-OP-004, " Examination / Ouiz Development," Revision 3 and 5 l
NTI-OP-005, " Examination / Quiz Administration," Revision 4 i
NTI-OP-007, " Control of Simulator Events and Scenarios," Revision 1 l
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I l-2-NTI-OP-008, " Licensed Operator Requalification," Revision 1 NTI-OP-009, " Conduct of Simulator Training," Revision 1 1995 Licensed Operator Requalification Annual Written Examination W-3-E X M-LO R-95501, 95502, 95503, 95504, 95505, 95506, 95507 1996 Licensed Operator Requalification Annual Operating Test
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I ATTACHMENT 3
SIMULATION FACILITY REPORT Facility Licensee: Waterford Unit 3 Facility Docket: 50-382 Operating Examinations Administered at: Waterford Training Center, Killona, La.
Operating Examinations Administered on: September 9-17,1996
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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 licensee action is -
required in response to these observations.
No simulator modeling or performance issues were identified during the preparation and administration of the examinations. The simulation facility displayed excellent fidelity, with only minor exceptions previously identified by the staff and specifically briefed to the applicants prior to each training scenario session.
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ATTACHMENT 4 i
FINAL WRITTEN EXAMINATION AND ANSWER KEY l
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U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC WRITTEN EXAMINATION REACTOR OPERATOR LICENSE REGION 4 APPLICANT'S NAME:
FACILITY:
WATERFORD 111 REACTOR TYPE:
PWR-CE80 DATE ADMINISTERED: 96/09/06
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INSTRUCTIONS TO APPLICANT:
Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. Each question is worth one (1) point unless otherwise indicated in parentheses after the question. The passing grade requires a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.
TEST VALUE APPLICANT'S
%
SCORE 100.00
%
TOTALS FINAL GRADE All work done on this examination is my own. I have neither given nor received aid.
Applicant's Signature l
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l 1.
Clearance tags are being removed from Control Room AHU cooling coil D. The outlet
isolation valve CHW 599D is required to be positioned 4 2/3 turns open. As independent verifier how would you check this position?
.
A. Visually observe the positioner throttling the valve to the correct position.
i B. Move the valve slightly in the closed direction and then return it to its original
position.
C. Inspect the last valve lineup sheet for verification signature and compare recorded valve position with the required position.
i
' D. Compare stem or indicator position with the remote indication position.
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l I
)
i 2.
You have to drain the Demin Water Storage Tank via the normally closed bottom drain valve
'
due to a maintenance requested outage. How will this drain valve be documented open and documented restored after the outage.
A.
Open the valve, check level in tank every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> until drained, then reclose l
valve. Document draining and closing in the Watch Station Log.
B.
Iack the drain valve open. Unlock and close the drain valve after the outage.
Document IAW OP-100-009, Control of Valves and Breakers.
,
C.
Open the drain valve. Reclose the drain valve after the outage. Document opening and closing the drain valve with a clearance using an asterisked item.
D.
Caution tag the drain valve open. Remove the caution tag and close the valve after the outage. Document manipulations with a deviation sheet.
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3.
What is a Radiation Worker's Total Effective Dose Equivalent (TEDE) if he/she received the following doses during a calendar year?
1.060 REM Shallow Dose Egivalent (SDE):
1.735 REM l
Lens Dose Equivalent (LDE):
1.514 REM Committed Effective Dose Equivalent (CEDE):
2.078 REM A.
2.795 REM B.
3.138 REM C.
4.309 RSM D.
5.327 REM 4.
A valve reads 300 mr/hr behind 2 inches of lead. What will it read when the lead is removed?
A.
600 MR/HR B.
6000 MR/HR C.
3000 MR/HR D.
30000 MR/HR
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5.
In accordance with 01-002-000, Annunciator and Alarm Status Control, what documentation must be completed in order to clear the Equipment Out of Service checklist for a safety related annunciator and return it to operable status when a Temporary Alteration is to remain installed?
A. No action is required to clear the Equipment Out of Service checklist.
B. The Temporary Alteration safety and engineering review must be completed with a satisfactory response.
C. A Condition Report must be generated stating the acceptability of operation with the Temporary Alterationinstalled.
D. An immediate work Condition Identification must be generated to ensure prompt repair of the condition causing the installation of the Temporary Alteration.
6.
Which of the following best describes the condition in which the working hour policy (UNT-005-
-
005) applies?
A. a person working in training performing simulator operations i
B. a person working on a procedure revision for a quality related system C. a person working on a non-safety related system or component D. a person working on safety-related system or component
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7.
Which of the following best describes how far back in the Station Log an oncoming operator must
,
review, prior to shift turnover, if that individual has not been on shift for 60 days?
A. since the last shift watch that was stood B. three days C. one week D. two weeks Page 3 of 38
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8.
Fuel is being reloaded into the reactor vessel when the Shift Supervisor informs you that one
,
startup channel neutron flux monitor has failed. Which of the following describes the required
,
action?
A. Fuel reload may continue provided backup boron samples are taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
,
.
)
B. Fuel reload may continue provided the inoperable channel is returned to operable
status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
C. Suspend core alterations until boron sampling has been initiated every twelve (12)
hours for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
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D. Suspend core alterations until the inoperable channel is returned to operable status.
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9.
i The limitation on secondary system specific activity ensures that the resultant off-site dose will
!
be acceptable. This dose projection includes a gpm primary to secondary leak on the affected S/G with a concurred
.
,
l A.
0.5,1 micro curie primary activity
?
]
B.
1.0, loss of offsite power j
i C.
'
l D.
1.0,1 micro curie primary activity
I j
10, i
Reverification of a field controlled copy of a procedure is required to be performed every i
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A.
Iday
3
1 j
B.
7 days l
C.
14 days j
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D.
30 days Page 4 of 38
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All of the following tasks are allowed to be performed as an Informational Use procedure except:
A. Inserting or Withdrawing CEAs I
- B. Adding hydrogen to the VCT 1.
C. Processing Waste Tanks to Waste Condensate Tanks l
f j
D. Shifting Instrument or Station Air Compressors i
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12.
{
Which of the following is the bases for tripping the RCPs with RCS pressure <l621 psia l
following a LOCA?
1.
A. To eliminate RCP heat input to the RCS B. To minimize core uncovery due to phase separation
j C. To prevent damage to the RCP impeller
l D. To prevent damage to the RCP seals
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13.
Which hand held fire extinguisher is available at Waterford-3 for use on flammable liquid
fires?
l
.
i.
A.
Pressurized water i
B.
Pressurized Aqueous Foam C.
Dry chemical D.
Carbon Dioxide
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14.
Which ONE of the following interlocks /permissives in CEDMCS is provided by the reed switch
position transmitters (RSPT)?
A. Lower Group Stop.
'
B. Upper Electrical Limit.
.
C. Upper Control Limit.
D. Upper Group Stop.
15.
The Primary Operator is withdrawing CEA's in the Manual Sequential mode during a Reactor Startup. Regulating Group 5 has just started outward motion from 0.0 inches. At what Reg.
Group 5 position should Reg. Group 6 start outward motion?
A.
50 inches B.
75 inches
'
C.
100 inches D.
125 inches
)
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1 16.
WHICH ONE (1) of the following describes the generation of a CEDMCS CEA Withdrawal
Prohibit (CWP)?
I
A. Initiated by the pulse counter CEA Position Indication System in response to a 2/4 PRETRIP condition on DNBR and prohibits ALL outward movement of regulating
,
CEAs.
j B. Initiated by the Plant Protection System (PPS) in response to a 2/4 PRETRIP
condition on DNBR and prohibits ALL outward group movement of CEAs.
)
C. Initiated by the pulse counter CEA Position Indication System of the Plant Computer in response to OUT OF SEQUENCE condition and prohibits ALL outward movement ofCEAs.
i
,
D. Initiated by the Plant Protection System (PPS) in response to OUT OF SEQUENCE
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condition and prohibits ALL outward group movement of CEAs.
.
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17.
,
While performing a reactor startup which of the following indicates the earliest time that you
'
should anticipate criticality?
A. When the shutdown banks are being withdrawn
>
,
l B. When the first regulating group is being withdrawn
)
C. When the 1/M plot indicates criticality within the next 100" i
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D. When inside the window of five to seven doublings
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Page 7 of 38
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l 18.
i A cooldown and depressurization is in progress. RCS pressure is currently at 1100 psia and seal pressures for RCP IB are:
Vapor:
40 psia
Upper:
40 psia Middle:
530 psia Which RCP seal has failed?
A. lower seal B. middle seal C. upper seal D. vapor seal l
19.
Which of the following is the reason for preventing the start of the fourth Reactor Coolant Pump
- until RCS temperature is greater than 500 F7 A. To prevent exceeding RCS heatup rate limits.
B. To prevent excessive RCP starting currents.
C. To limit Steam Generator tube stresses.
D. To limit core uplift.
l Page 8 of 38
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20.
'
.Which of the following equipment receive an SIAS signal?
i
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A. CVC 101, letdown stop valve; CVC 103, letdown inside contaimnent isolation valve; CVC 109, letdown outside containment isolation valve.
B. CVC 169, VCT inlet valve; BAM 133, emergency boration valve; CVC 507, RWSP to j
charging pumps suction.
i C. BAM 143, direct boration valve; CVC 209, charging header isolation valve; CVC 401 i
RCP controlled bleedoffisolation valve.
i D. B AM 1 n A(B), B AMT A(B) gravity feed valves; CVC 103, letdown inside
-
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containment isolation valve; BAM 126 A(B), BAMT Pump A(B) recirculation
!
isolation valve.
t i
e i
21.
!'
If CVC 115, the CVCS letdown 650 psig relief valve, inadvertently lins, which of the following i
indications is expected?
f l
A. Back pressure regulating valve closes down i
B. VCT level rises slowly l
l C. Letdown Flow rises i
D. Letdown Heat exchanger temperature rises
,
22.
The plant is in Mode 3 with PLCS and Letdown in automatic. The NPO notes letdown flow rising. Which of the following is a possible cause?
A. Loss ofInstrument Air to Letdown backpressure regulating valve B. The selected PZR level control channel has failed high C. VCT level has dropped to less than 6%
D. Steam line 1 Atmospheric Dump valve controller setpoint has failed low Page 9 of 38
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23.
The following conditions exist:
A feedline break has occurred inside containment.
- Containment pressure is 17.5 psia.
- Cont), ment radiation is normal
<
PZR pressure is 1825 psia.
.
RWSP levelis 90%.
j SJ pressures are (SGl) 925 psia, (SG2) 580 psia.
e
SG levels are (SGI) 50% WR, (SG2) 20% WR
.
i.
All of the following actuation signals should have occurred with the exception of:
J j
A. SIAS
$
B. MSIS l-C. EFAS 1 D. CSAS 24.
After a reactor trip a secondary safety lifts and an uncontrolled cooldown commences. Automatic Safety Injection Actuation and Main Steam Isolation Signals fail to actuate and are initiated manually by the PNPO. All of the following occur except:
A. The Containment Cooling system realigned B. Containment Isolation C. Letdown has isolated D. The Safeguards Pump Room coolers started 25.
If the Excore Nuclear Instnimentation (ENI) Safety Channel upper detector were to fail low at power, the associated (selected) startup channel would:
A.
not energize on a reactor trip B.
energize high voltage C.
not be effected D.
energize its 10-6% bistable Page 10 of 38
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26.
Which of the following describes an automatic function of the 1 E-4% bistable?
A. bypasses High log power trip B. bypasses High S/G level trips C. enables High log power trip D. enables High S/G level trips 27.
Which of the following could be an indication of core uncovery? (Assume instruments are accurate)
CET Temperature equal to:
'
A. 550 F with RCS pressure equal to 1100 psia B. 570 F with RCS pressure equal to 1300 psia C. 590 F with RCS pressure equal to 1350 psia D. 610 F with RCS pressure equal to 1700 psia 28.
With Hot and Cold leg injection in progress, which of the following temperature indications should be used to monitor RCS temperature?
A. Representative CET B. Hot leg Safety Channel C. Cold leg Safety Channel D. Subcooled Margin Page 11 of 38
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29.
Which of the following best describes the configuration of the Containment Fan Coolers following an SIAS signal.
l A. Three fans start or shift to fast speed. The CCW outlet flow control valves will go l
to the two fan flow setpoint (1400 gpm).
B. Three fans start or shift to slow speed. The CCW outlet flow control valves will go
'
to the two fan Gow setpoint (1400 gpm).
C. All fans start or shift to fast speed. The CCW outlet flow control valves will go
,
i full open for maximum flow (2700 gpm).
l D. All fans start or shift to slow speed. The CCW outlet flow control valves will go full open for maximum flow (2700 gpm).
l l
l y
j 30.
Which of the following provide electrical power to the Containment Cooling Fans.
,
A.
!
B.
31AS and 31BS D.
31.
l Assuming all condensate pumps are mnning, and both Main Feedwater Pumps are mnning with HP Governor valves open, what, if any, would be the result if the B and C condensate pump were to trip? (ignore suction pressure trips)
l A.
MFW pump 'A' would trip B.
MFW pump 'B' would trip l
l C.
Both MFW pumps would trip D.
Neither MFW pump would trip l
l Page 12 of 38
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32.
l An EFAS 1 signal will be present for which of the following? (consider each answer separately)
A.
S/G l@ 20% NR, S/G 2@ 26.5% NR, S/G 1& 2 @ 600 psia B.
S/G l@ 30% NR, S/G 2@ 25 % NR, S/G l@ 700 psia, S/G 2@ 680 psia C.
S/G l@ 15% NR, S/G 2@ 20% NR, S/G 1@200 psia, S/G 2 @ 400 psia D.
S/G l@ 5% NR, S/G 2@ 10% NR, S/G l@ 500 psia, S/G 2 @370 psia 33.
Given the following plant conditions:
S/G 1 820 psia (constant); WR level 57%
S/G 2 530 psia (dropping);
WR level 54%
EFAS 1&2 MANUALLY initiated SIAS CIAS & MSIS initiated.
All other EFW flow controls in automatic Which of the following statements describes the status of the Emergency Feedwater system?
l A.
S/G 1 EFW Flow Isolation valves can be closed.
B.
S/G 2 EFW Flow Isolation valves are closed due to the MSIS.
C.
S/G 1 EFW flow control valves will maintain 400 gpm until reaching level Y.
D.
S/G 2 EFW flow will continue until level reaches level X.
Page 13 of 38
34.
All of the following are possible causes of automatic termination of WCT discharge to Circulating Water except:
A. Loss of sample flow B. Loss of radiation monitor power supply C. High discharge conductivity D. Low Waste Condensate Tank Level i
35.
Select the most correct reason for restoring FHB Normal Ventilation Supply and Exhaust Fans as soon as possible following high airborne activity in the FHB.
A. High differential pressure prevents personnel from entering / exiting the FHB.
B. Minimize changes in Spent Fuel Pool and Refueling Cavity level if Fuel Transfer Tube Gate Valve is open.
C. Minimize evaporation of water in the Spent Fuel Pool.
D. Restore ventilation to the Spent Fuel Pool Cooling Pumps.
36.
Which of the following occurs when one of the train A radiation monitors CROAl A North (0200.1) or CROAI A South (0200.5) for the control room air intake reaches its high radiation alarm setpoint?
,
A. All air intake to the RAB is secured.
B. Control room Toilet Exhaust Fan A starts.
l C. Control Room Normal Air Handling Unit A stops D. Control room Emergency Filtration Unit A starts.
Page 14 of 38
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37.
When cooling down the plant per OP-010-001, General Plant Operations, when are the Low
!
Temperature Over pressure Protection Relief Valves (LTOP's) required to be aligned for
. service?
A.
Prior to closing the Safety Injection Tanks' Isolation Valves.
.
B.
Prior to entering Mode 4.
!
i C.
Prior to placing both Letdown Flow Control Valves in service.
i l
D.
Prior to reducing RCS temperature to 272*F.
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38.
i l
Prior to plugging 10 percent of the U-tube area in each steam generator, the plant operated at j
100% power with RCS Tave at 574 F and a steam pressure of 850 psia. To what value must Tave be changed in order to maintain the same Steam Generator pressure at 100% power?
Assume RCS flow rate was unaffected by the tube plugging.
,
!
j A. 577.4 F i
B. 579.4 F l
C. 581.4 F
)
~ D. 583.4 F i
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39.
.
l The Reactor Coolant System Vents are required to be operable in Modes 1,2, 3, and 4 to:
!
A.
Limit combustible mixtures, j
B.
Prevent steam or non condensables from interfering with natural circulation.
C.
Equalize pressure between the Pressurizer and the Reactor Vessel head.
D.
Ensure that hot leg injection reaches the core.
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Page 15 of 38
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' 40.
,
The motor overload relays for SI-602A & B (Safety Injection Sump outlets) are bypassed...
t A.
On RAS to ensure the valves can be opened.
"
B.
On RAS to ensure the valves can be closed.
- C.
On SIAS to ensure the valves can be opened.
D.
On SIAS to ensure the valves can be closed.
.
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41.
Select the reason HPSI Cold Ieg Injection Flow Control Valves go to a throttled position on i
an SIAS.
,
i A.
To reduce the HPSI Pump starting current if RCS pressure is below shutoff head.
B.
To minimize back flow from the RCS in the event a HPSI Pump fails to start.
C.
To prevent HPSI Pump runout and balance flow to each of the cold legs.
,
i D.
To limit HPSI flow such that RAS does not occur earlier than assumed in the
!
safety analysis.
i 42.
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The purpose of energizing the Pressurizer Backup Heaters when Pressurizer level rises above Programmed level during an in-surge is:
A.
To raise Pressurizer pressure to saturation.
B.
To raise Pressurizer steam space temperature.
C.
To retum Pressurizer pressure to setpoint.
D.
To return Pressurizer water temperature to saturated conditions.
Page 16 of 38
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43.
Following a single channel CPC trip, how can the operator quickly determine if the trip signal is due to an Auxiliary Trip?
A.
By obtaining the CPC Trip Buffer Report.
B.
By observing a Trip light without the associated Pretrip light.
i
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C.
By obtaining the trip Sequence of Events Report (SOE).
D.
By observing that Diverse Reactor Trip has actuated.
l l
44.
t
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RAS initiation is delayed for at least 20 minutes after a large break LOCA occurs so that:
A. The RCS will have completed blowdown.
B. The LPSI pumps will have adequate NPSH.
C. Core boiloff is less than the capacity of one HPSI train.
D. Containment pressure will be reduced by half.
l 45.
You are withdrawing Reg Group 6 CEAs, IE one CEA in the group stops moving while the rest continue to withdraw, Which of the following will prevent any further group withdrawal
'
l when reached (assume Group 6 is at 130 inches when misalignment occurs)
A.
4.95 inch misalignment detected by CPC target CEAs i
B.
4.95 inch misalignment detected by CEACs C.
5.5 inch misalignment detected by CPC target CEAs D.
5.5 inch misalignment detected by CEACs l
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46.
Select which system provides the heat sink for cooling the Safety Injection Sump POST-LOCA following a Recirculation Actuation Signal (RAS).
A.
Shutdown Cooling System B.
High Pressure Safety Injection system C.
Low Pressure Safety Injection system D.
Containment Spray system 47.
Which of the following would occur as a DIRECT result of LO-LO spent fuel pool level (41.6 ft)?
A. Spent Fuel Pool Cooling Pumps trip B. CMU to Spent Fuel Pool Makeup Valve opens C. SFHM Hoist Up movement is disabled D. Fuel Handling Building Isolation Actuation occurs i
l Page 18 of 38
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t 48.
A Cooldown to Mode 5 using the Steam Bypass Control System is in progress.
Plant conditions are as follows:
Steam Generator 1 & 2 pressums am 800 psia.
Reactor Coolant System temperature is 518 F.
Pressurizer pressure is 2100 psia and level is 33 %.
RCPs I A, IB, and 2B are opemting.
Charging Pumps A & B are operating with Letdown in automatic control.
Select the action which should be performed to prevent an inadvertent Engineemd Safety l
!
Features Actuation Signal (ESFAS).
t
. A.
Reset the Pressurizer low pressure trip setpoints.
B.
Raise Pressurizer level to 50%.
C.
Bypass the Pressurizer low pressum trips.
D.
Reset the Steam Generator low pressure trip setpoints.
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49.
l The mactor trips from 100% power. The contml room operators verify that the reactor is i
tripped and immediately note that the turbine has not tripped and the generator breakers remain closed. If left unresolved this malfunction will cause:
l A.
An uncontrolled cool down of the RCS, resulting in less shutdown margin.
B.
Main turbine blade heating, possibly resulting in damage to the main turbine rotor and shaft.
C.
A loss of condenser vacuum, resulting in the loss of condenser steam dump.
D.
An increase in RCS pressure, possibly resulting in the Pressurizer safety valves I
lifting.
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50.
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l Complete the following statement.
l An Emergency Diesel Generator is supplying its associated safety bus in the Emergency Mode j
and normal power is aligned to the 2 bus with the 2 to 3 bus tie breaker closed. When the operator takes the associated synchronizer switch to the BUS TIE position:
j A.
the governor will be returned to the droop mode of operation.
B.
the governor swaps to the backup hydraulic isochronous mode.
!
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C.
the Diesel swaps to the Test Mode of operation.
D.
the Bus Tie Breaker closes following a Synch Check.
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51.
The output of Safety SUPS SA is considered to be uninterruptible because:
A.
Auctioneered AC power supplies are provided to the rectifier section.
B.
Inverter input is auctioneered between the rectifier output and a DC Safety Bus supply.
C.
An internal battery is auctioneered with the rectifier output.
D.
The Static Transfer Switch automatically transfers to AC alternate source.
52.
Which of the following describes 4.16KV breaker operation if DC control power is lost?
A. Breakers will remain in their "as is" condition and operation would only be possible by local manual means.
B. Automatic breaker trips would remain operational but remote operation of breakers would not be possible.
C. Breakers would remain remotely operable but automatic trip functions would become inoperable.
D. Breakers would trip open and operation would not be possible by local manual means.
Page 20 of 38
53.
Which of the following is the correct expected response if an EDG is paralleled to the grid and i
the Governor and Voltage control hand switches are both taken to Raise / Increase?
A.
Kw increases and EDG speed increases.
B.
Reactive load increases and Kw increases.
C.
Indicated output voltage increases and Reactive load increases.
D.
EDG speed increases and Indicated output voltage increases.
54.
With an inoperable LWM radiation monitor all of the following are required to perfonn a discharge from the Waste Condensate Tanks except:
A.
Obtain and analyze independent samples from the Waste Condensate Tank.
B.
Perform an independent verification of discharge valve lineup.
I C.
Perform an independent verification of release rate calculation.
'
D.
Perform an independent verification of proper Cire Water flow.
55.
Which of the following describes the locations sampled by the PAS system?
l A. Reactor coolant system cold leg #1, RAB penetration areas, and containment SIS sump.
B. Containment Atmosphere, Reactor Coolant System hot leg #1, and containment SIS sump.
)
l C. Shutdown cooling train A, component cooling water system, and containment j
atmosphere.
]
D. Reactor coolant system hot leg #2, SDC cooling train B and containment SIS sump.
)
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56.
Choose the answer that best describes the normal alignment of the Diesel Fire Pump Suction.
A.
Diesel Fire Pump #1 takes suction from Fire Water Storage Tank A i
i B.
Diesel Fire Pump #1 takes suction from the Motor Driven Fire Pump discharge header.
C.
Diesel Fire Pump #1 takes suction from both Fire Water Storage Tanks.
)
D.
Diesel Fire Pump #1 takes suction from Fire Water Storage Tank B.
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57.
The primary reason for initiation of hot and cold leg injection to the SDC train with a cavitating LPSI pump is to:
A.
Prevent Boron precipitation.
B.
Ensure all injection flow is not lost through cold leg openings.
C.
Prevent over pressurization of cold leg nozzle dams.
D.
Provide subcooled water to the suction of the cavitating LPSI pumps.
58.
Assuming a Pmssurizer Safety Valve lifts, which of the following statements is most cormct?
A.
The downstmam Safety Relief temperatum detector will indicate T, for the current Pressurizer pressure.
B.
Quench Tank temperature will equal T, for the current Pressurizer pressure.
C.
The downstream Safety Relief temperature detector will indicate T, for the current Quench Tank pressure.
D.
Quench Tank pressure will equal P, for the curmnt Pressurizer vapor space temperature.
Page 22 of 38
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59.
I CCW pumps B and AB are operating. Although CCW pump AB is replacing A the AB bus is
{
powered from the B-side. The "CCW pump A Unavailable" alarm is locked in. Which of the following describes the status of the CCW system in the event of a concurrent loss of offsite
,
l power and SIAS?
B, CCW pumps A & B running i
C. Only CCW pump B running
}
D. All CCW pumps running
'
i
a 60.
.
All of the following conditions will automatically start the Train B Auxiliary Component
Cooling Water Pump except:
'
.
l A.
Train B CCW Heat Exchanger outlet temperature 10 deg F above the setpoint of I
CCW Temperature Controller, CC-ITIC-7070B.
B.
Wet Cooling Tower basin temperature reaches 95 deg F.
i
'
i j
C.
CCW Heat Exchanger outlet temperature t aches 100 deg F.
!
D.
a Safety Injection Actuation Signal occurs.
!
i
{
61.
j Which of the following describes a condition that prevents the Refueling Machine (RFM) from entering the upender zone?
,
!
A. RFM fuel hoist box is latched.
B. RFM fuel hoist overload
C. Spreader is fully retracted.
,
D. Upender is completely horizontal.
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Page 23 of 38
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i l
t 62.
'
Steam Bypass Valve 6 is the only Steam Bypass valve that receives a quick open block for a:
A.
Reactor Power Cutback with a load rejection B.
Reactor Power Cutback with a Feed pump trip t
i C.
Reactor trip with Tave equal to 550 F l
D.
Reactor trip with Tave equal to 570 F i
l l
l
63.
[
Concerning the Station and Instrument Air Systems, Which of the following is true?
':'
A.
The Instrument Air compmssors cycle between 112 PSIG and 120 PSIG; the Instrument Air Dryer skids are auto bypassed at 95 PSIG.
i B.
Backup air compressor starts at 105 PSIG; Station Air to Instmment Air backup opens when air dryers are bypassed.
i l
C.
When air pressure reaches 125 PSIG in the Station Air (SA) receiver, the unloader valve opens causing pressum between the air compressor separator and the
i compressor to equalize.
}
D.
Station air provides a backup source for instmment air via an interface valve which opens to supply air to the dryer inlet downstream of IA Receiver.
i
.
i
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i 64.
!
Which of the following occurs when Shield Building Ventilation shifts to the EXHAUST j
mode.
!
l A.
The in-service Containment Atmosphere Release (CAR) Exhaust fans START.
B.
The in-service Containment Atmosphere Release (CAR) Exhaust fans STOP.
- i
C.
The in-service Containment Atmosphere Release (CAR) Exhaust fans go to i
RECIRCULATION mode.
I D.
The in-service Containment Atmosphere Release (CAR) Supply fans go to
}
RECIRCULATION mode.
,
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i Page 24 of 58
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.,
l 65.
l Following a CEA or CEDMCS malfunction in which the CEA was misaligned greater than 19 l
inches, the off-normal procedure directs you to hold reactor power constant for after CEA alignment for A. 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, xenon redistribution l
B.
I hour, radial peaking
C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, clad relaxation
<
l D. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, isotopic iodine analysis i
i e
I l
l 66.
'
A Loss of Offsite Power has occurred. Plant conditions are as follows:
,
The Reactor is in Mode 3 CET temperature is 598 F j
RCS pressure is 1900 psia and slowly S/G 1 & 2 levels are 55% WR and slowly j
rising rising Te is 550 F and constant Th is 585 F and slowly lowering
All of the following conditions meet the criteria for single phase natural circulation in accordance
with OP-902-005, Loss of Offsite Power / Station Blackout Recovery Procedure with the i
exception of:
i A. Tc temperature trend t-l B. Th temperature trend
C. Subcooled Margin l
D. Th-CET differential temperature
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t Page 25 of 38
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67.
Which of the following conditions requires emergency Toration per OP-901-103, " Emergency Boration"?
A. Reg Group 6 CEA positioned just below the Pre-Power Dependent insertion Limit.
B. During refueling Keffis equal to 0.95.
C. Shutdown margin is 2.1% delta k/k with Tavg at 195 degrees F.
D. A main steam line safety valve sticks full open and will NOT reclose with the reactor at 1% power.
68.
The plant is at normal operating temperature and pressure when the Component Cooling Water Surge Tank level starts increasing. Select which of the following components could be causing this levelincrease. (Assume normal equipment conditions)
A. Spent fuel pool heat exchanger B. RCP seal cooler heat exchanger C. Waste Oas compressor D. Essential Chiller A
Page 26 of 38
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69.
Given the following plant conditions:
Pressurizer Level Control Channel Selector is positioned to Channel "Y" Pressurizer low level Heater Cutout Channel Selector is positioned to BOTH.
All Pressurizer Heaters are on for Boron Equalization.
Which of the following describes the status of the Pressurizer Heaters if Pressurizer level Channel
"X" fails low?
A. All Pressurizer Heaters remain energized.
B. All Pressurizer Heaters will de-energize.
C. All Backup Heaters de-energize, all Proportional Heaters remain energized D. All Pressurizer Heaters de-energize except Train B powered Heaters.
70.
After a loss of feedwater event an EFW pump is placed in service with SGI level at 22% NR and
,
SG2 level at 20% NR. Why should feed flow be initiated slowly to the steam generators?
j A. To limit the possibility of feed ring damage when SG level is below the feed ring.
B. To minimize the differential temperature across the tube bundle wrapper.
C. To limit the RCS cool down resulting from restoration of feedwater from the CSP D. To minimize the thermal shock to the SG tubes when feedwater is restored.
71.
Which of the following reflects the primary concern of the operators after a major steam line break upstream of the MSIV in which the affected SG blows dry.
A. Ensure the RCS reheats back to normal operating temperature within Tech Spec
,
heatup limits B. Maintain subcooling margin between 28 F and 200 F C Energize all pressurizer heaters to re-establish saturated conditions in the pressurizer D. Re-establish all safety injection flow Page 27 of 38
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. ~ _ - _ =. -
. - -
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)
72.
!
During a loss of condenser vacuum event, the following annunciators are received: FWPT A j
VACUUM LO and FWPT B VACUUM LO. Prior to these alarms what other alarms should j
j have been received?
!
A.
VACUUM PUMP - TRIP / TROUBLE j
B.
STM BYPASS SYSTEM CNDSR VACUUM FAIL i
'
C.
TURBINE TRIP VACUUM LOST l
D.
FWPT - TRIP VACUUM LO
i i
i 73.
During a station blackout, the Loss of Ofr b Power / Station Blackout Recovery Procedure (OP-
.
902-005) directs the Operator to place the Containment Spray Pump control switches to OFF.
,
I Which of the following describes the reason for this step?
A.
To prevent overloading the Emergency Diesel Generators when restored.
,
l; To prevent initiating Containment Spray when electrical power is restored.
B.
!
C.
To prevent starting the Containment Spray Pumps with no seal cooling after
'
power is restored.
D.
To protect the Containment Spray Pumps from the effects ofloss of DC control power if battery chargers cannot be restored.
j Page 28 of 38
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a 74.
>
l Which of the following Reactor Trip Breakers would indicate open on a loss of vital instrument j
bus SUPS MD?
I A. Breakers 1,2,3,4 B. Breakers 5,6,7,8
,
C. Breakers 1,2,5,6
.
D. Breakers 3,4,7,8 i
i s
75.
'
immediately upon confirmation of a fire alarm the Nuclear Plant Operator is responsible for all of the following actions except:
j A. Making preliminary reportability verification
.
l B. Sounding the fire alarm and announcing the fire over plant page l
l C. Obtaining pertinent information from the person confirming the alarm
.
i
{'
D. Ensure the SS/CRS is notified i
!
!
!
76.
If a fire in the +35 Cable Spreading Room burns for 45 minutes before it is extinguished,
.
which of the following will still be a reliable indication for RCS pressure?
A.
Safety Channel B Wide Range Pressurizer Pressure
!
B.
Safety Channel D Narrow Range Pressurizer Pressum
i
C.
Hot Ixg 1 Pressum a
D.
Pressurizer Pressure Controller
i i
.
Page 29 of 38
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77.
Why is emergency boration required when the reactor is tripped from outside the control room following a Control Room Evacuation?
A. The MSR temperature control valve logic cannot be reset from outside the control
{
room.
B. The Main Turbine will not trip when the reactor is tripped outside the control room.
)
C The operator is unable to verify CEA positian following a trip from outside the control
]
room.
D. The Feedwater Control System will not shift to the RTO mode when the reactor is tripped from outside the control room 78.
During Irradiated fuel movement within containment, it is reported that the Equipment Hatch Door is held in place by three(3) bolts. Which of the following actions should be taken.
A.
Suspend Core Alterations or irradiated fuel movement in containment if LLRT test results are not satisfactory.
B.
Immediately suspend Core Alterations or irradiated fuel movement within containment.
C.
Within I hour restore the Equipment Door to operable status or suspend Core Alterations and irradiated fuel movement within containment.
D.
Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> restore the Equipment Door to Operable Status or suspend Core Alterations or irradiated fuel movement within containment.
79.
A heat addition to a fluid with a quality of o% results in a temperature increase with no phase change. What was the condition of the fluid prior to the heat addition? (assume pressure of the
.
'
fluid is held constant)
A. Subcooled liquid B. Saturated liquid C. Wet vapor D. Saturated vapor Page 30 of 38
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80.
All of the following items are sampled and analyzed by the W-3 Chemistry Department when OP-901-410, High Activity in Reactor Coolant System is implemented with the exception of:
l A. Cesium Concentration l
B. Dose Equivalent lodine Concentration l-C. Dose Equivalent Iodine isotopic analysis
!
D. Gross RCS activity I
i 81.
Regulating Group 6 CEAs are being withdrawn from 120" in an attempt to maintain ASI constant. When the shim switch is released Regulating Group 6 continues to move outward.
When the mode select switch is taken to "OFF" motion stops. What actions should be taken?
A. Trip the reactor and go to OP-902-000 B. Ifuncontrolled movement does not occur aner the mode switch is removed from
"OFF" borate CEAs to fully withdrawn position C. If continuous movement occurs aner the mode select switch is removed from "OFF" then trip the reactor D. Declare group 6 inoperable and commence a plant downpower using part length rods for ASI control
82.
While at 80% power, a shutdown bank CEA drops into the core. In accordance with the Tech Spec COLR, a downpower must be completed within minutes to a maximum power level of A. 15, 60%
B. 30,70%
l C. 45,60%
D. 60, 70%
l Page 31 of 38 l
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.-.
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83.
Which of the following best describes the Diversified Reactor Trip system (DRTS), assuming DRTS enabled.
A.
Must push both DRTS push buttons together, at the same time, to manually l
actuate.
,
B.
Auto actuation requires 2/2 pressurizer safety grade pressures at 2340 psig.
- !
C.
Can be manually initiated locally at the Reactor Trip Switchgear (+21 RAB)
'
D.
Could actuate with failure of one pressure transmitter high and pressing one
!
manual pushbutton.
l
.! -
t
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84.
I All of the following allow termination of Safety Injection after a small break LOCA except?
?
'
A. Subcooled margin 50 F i
'
D. Pzr Level 35% and dropping slowly C. RVLMS level 5 not voided
i
i
l 85.
Select the combination of Reactor Coolant System passure and Low Pressure Safety !njection
Train A flow that would be acceptable during the injection phase of a large LOCA.
}
A.
175 psia 500 gpm
j B.
125 psia 2500 gpm C.
100 psia 2800 gpm D.
50 psia 3600 gpm
a
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$
Page 32 of 38
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86.
!
Following a LOCA, Reactor Coolant Pumps were secured. Which of the following conditions
would indicate a problem with natural circulation flow after flow had been established?
I j
A.
Steam Generator pressures are rising i
B.
PRESSURIZER level is 18% and slowly lowering
I C.
RCS sub cooling is 30 F and constant D.
RCS loop delta temperature is 50 F and lowering 87.
While operating at power, significant current oscillations (100 amps) are observed on 480V bus 3B31-S. Annunciator " CHARGING PUMP HEADER FLOW LOW" actuates and shortly thereafter, Charging Pump B trips on overcurrent. Which of the following actions should be taken?
A.
Start an alternate charging pump after verifying its suction path.
B.
Restart Charging Pump B after resetting the overturrent trip.
C.
Secure letdown and initiate an investigation for the loss of Charging Pump B.
D.
Secure letdown, start an alternate charging pump, then restore letdown.
88.
Which of the following describes the reason for the requirement to have a Hot Leg vent path for a loss of shutdown cooling when SG nozzle dams are installed?
A.
To prevent steam formation in the Hot Leg from causing an erroneously high Reactor Vessellevelindication.
I B.
To prevent steam formation in the Reactor Vessel head from pressurizing the RCS, l
leading to core uncovery.
C.
To prevent steam formation in the Hot Leg which will ultimately collapse, causing severe water hammer.
D.
To prevent the loss of RCS inventory caused by lifting a Low Temperature Overpressure Protection (LTOP) relief valve.
)
l Page 33 of 38 i
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l 89.
{
The plant is shutdown and drained to mid-loop for replacing Reactor Cooling Pump seals. The time of shutdown was 8/31/96 0300. At 0300 on 9/10/96 LPSI Pump A is secured due to
'
cavitation of the pump. LPSI Pump B is started and trips. Estimate the time to reach 200 F if initial RCS temperature was 100 F.
A. 15 Minutes
!
B. 20 Minutes
,
i C. 25 Minutes
!
.
{
D. 30 Minutes
!
i 90.
OP-902-000, Step 1 Contingency Action directs the operator to open the feeder breakers to 480 VAC busses 3A32 and 3B32 for 5 seconds and then reclose them. The purpose of reciosing the feeder bmakers is to:
A.
Restore power to the CEDMCS in order to venfy that all CEAs have fully inserted.
B.
Re-energize the A32 and B32 busses before the under voltage relays strip the individual loads from the busses.
C.
Restore power to the Pressurizer proportional heaters only.
D.
Restore power to all the Pressurizer heaters.
J Page 34 of 38
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91.
In order to prevent an inadvenent release of radioactive material through the Condenser Air Evacuation System (AE), wide range gas monitor samples the AE exhaust. Upon receipt of a high rad alarm, the AE System:
A.
Isolates all flow from the Main Condenser B.
Initiates recirculation of the non-condensables from the separator unit to the condenser.
C.
Diverts the AE exhaust discharge to the Normal RAB HVAC exhaust filter units.
D.
Diverts the AE exhaust to the waste gas header.
92.
During a SGTR, the isolated SG level is maintained greater than 77% WR in order to:
A.
prevent spmy thinugh the rupture from depressurizing the SG B.
reduce flow impingement on other tubes C.
reduce the static head differential across the break D.
condense the steam issuing from the break i
93.
A Main Feedwater line break will depressurize the affected S/G and start an uncontrolled cooldown when:
A. The reactor trips on low S/G level B. The main feedwater isolation valve is closed on the affect S/G C. The feedwater line water level drops below the break location D. The S/G level drops below 50% WR level
.
Page 35 of 38
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94.
An Emergency Feedwater Actuation Signal (EFAS) has been initiated due to low level in both j
Steam Generators. Steam Generator 1 & 2 levels are below Critical Level.
Select the level band that the Emergency Feedwater System will automatically maintain?
,
-
A.
68 - 71% NR j
B.
68 - 71% WR
,
C.
55 - 71% NR
D.
55 - 71% WR
95.
A total loss of offsite power has occurred and both Emergency Diesel Generators have failed to start automatically or manually. Which of the following statements describes how long the operator has to shed specific DC Safety bus loads?
,
l A. Within 15 minutes B. Within 30 minutes C. Within 45 minutes D. Within 60 minutes 96.
All of the following are allowed by procedure except:
A.
Discharging one Boric Acid Condensate Tank while filling another.
B.
Discharging a Boric Acid Condensate Tank to the PWST.
C.
Recircing one Boric Acid Condensate Tank while discharging another.
.
D.
Recircing one Boric Acid Condensa*e Tank while filling another.
Page 36 of 38
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97.
After evaluation of the current activity readings how many of the following Containment Atmosphere Purge monitors high alarm setpoints should be set at 40 mr/hr?
ARM-IRE-5024S 1.17 E+2 mr/hr ARM-IRE-5025S 1.75 E+1 mr/hr ARM-IRE-5026S 2.25 E+1 mr/hr ARM-IRE-5027S 3.50 E0 mr/hr A. I B. 2 C. 3 D. 4 98.
Which of the following actions should be performed initially if the Thot input to the Reactor Regulating System (RRS) fails HIGH7 A. Place Pzr level controller to MANUAL B. Swap position of the Thot selector switch behind CP-2 C. Place Letdown Flow control valve to MANUAL D. Take backup heaters to OFF Page 37 of 38
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99.
Which of the following fuel handling events is addressed in OP-901-405, Fuel Handling Incident?
A.
A spent fuel assembly is damaged while being withdrawn from the core.
.
B.
A new fuel assembly cask is found with the motion sensors tripped during fuel receipt inspection.
C.
The Reactor goes critical while a fuel assembly is being insened into the core.
D.
A CEA is hanging from the upper guide structure during removal of the upper guide structure.
100.
A Reactor T_ip is required when Instrument Air Pressure drops to:
A.
60 PSIG B.
65 PSIG C.
70 PSIG D.
75 PSIG
.
Page 38 of 38
Required Power Reduction After Single CEA Deviation *
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15
45
Time After CEA Deviation (Minutes)
Figure 2 a When core power is reduced to 60% of rated power per this limit curve, funher reduction is not required by this specification.
I OP-902-ATT Revision 4 Attachment 6:
MINIMUM LPSI FLOW VERSUS PRESSURIZER PRESSURE
'
RCS PRESSURE, PSIA 300 275 250 225 200 N
A TABM R0W 175
,
T
\\
150
\\
125
,
100 UNACCEPTABLE
3
x
\\
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0 500 1000 1500 2000 2500 3000 3500 4000 4500 5000 TRAIN A OR TRAIN B FLOW RATE (GPM)
Page 1 of 1
Shutdown Cooling OP-901-131 Molfunction Revision
Page 1 of 1 Attachment 2: Heatuo Rate vs Time After Shutdown
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6
10
30
50 DAYS AFTER REACTOR SHUTDOWN
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i Wr.terf:rd 3 Examincti:n Questi:n
,
Examination Bank
,1
Esanination Question Number i
QUESTION ID:
3160 A
STATUS:
Approved LAST USED DESCRIrrION:
Proper method ror verifying the position of a throttled valve AUTIIOR:
avest REVISION
REv1SION DATE 6/27/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 i
{
REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/27/96
'
TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE
'
SPECIAL REFERENCES:
SIMULATOR SETUP
'
PLANT SYSTEM:
PPA CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CilANGE:
DATE:
OP-ICO-009
00 12/6/93 NRC KA NUMBER:
OBJEC.TIVE 2129 3.4 3.3 w 3-lp ops. ppa 00
,
QUESTION Clearance tags are being removed from Control Room AHU cooling coil D. The outlet isolation valve CHW
,
j 599D is required to be positioned 4 2/3 turns open. As independent verifier how would you check this position?
A. Visually observe the positioner throttling the valve to the correct position.
.
B. Move the valve slightly in the closed direction and then return it to its original position.
C. Inspect the last valve lineup sheet for verification aignature and compare recorded valve position with
l the required position.
.
D. Compare stem or indicator position with the remote indication position.
ANSWER q
A. Visually observe the positioner throttling the valve to the correct position.
COMMENTS
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.
Page 1 of 100
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Waterford 3 Examination Question
'
Examination Bank i
Examination Question Number 2
,
QUESTION ID:
1620-A STATUS:
Approved LAST USED
'
DE.SCRIITION:
A6tions to be performed when vents and drains must be left open unattended AUTIIOR:
avest REVISION I
REVISION DATE 11/19.94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/27/96
.
TYPE:
Mdtiple Choice TINIE:
POINTS:
I j
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE I
SPECIAL REFERENCES:
SINIULATOR SETUP PLANT SYSTEhl:
oOP CATEGORY:
Procedure PPA
,
REFERENCE:
REVISION:
CllANGE:
DATE:
UNT 003-003
1 972/93 NRC KA NUSIBER:
OBJECrIVE 2213 3.6 3.8 w-3-lp<9s-ppa 00
i
-
.OliESTION
.
You have to drain the Demin Water Storage Tank via the normally closed bottom drain valve due to a maintenance requested outage. How will this drain valve be documented open and documented restored after the outage.
A.
Open the valve, check level in tank every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> until drained, then reclose valve. Document draining and closing in the Watch Station Log.
B.
Lock the drain valve open. Unlock and close the drain valve aner the outage. Document IAW OP-100-009, Control of Valves and Breakers.
C.
Open the drain valve. Reclose the drain valve after the outage. Document opening and closing the drain valve with a clearance using an asterisked item.
D.
Caution tag the drain valve open. Remove the caution tag and close the valve after the outage.
Document manipulations with a deviation sheet.
ANSWER C.
Open the drain valve. Reclose the drain valve after the outage. Document opening and closing the drain valve with a clearance using an asterisked item.
COMMENTS Page 2 of 100
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Waterford 3 Examination Question
Examination Bank Esimination Question Number 3 QUESTION ID.
3206-A STATUS:
Approved LAST USED DESCRIPTION:
New 10CFR20 done calculation question AUTilOR:
RJC REVISION
REVISION DATE 1/6.94 APPROVAL:
tbrown APPROVAL DATE:
7/3.96 REFERENCE VERIFIED:
VERIFICATION DATE:
1/6S4 TYPE:
Multiple Choice TIME:
POLNTS:
l QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPA CATEGORY:
PROCEDL1tE REFERENCE:
REVISION:
CIIANGE:
DATE:
NRC KA NUMBER:
OBJECrIVE 2-31 2.6
w-3-lp. ops-ppa 00
,
W 3-LP 'xWT-18
QUESTION What is a Radiation Worker's Total Effective Dose Equivalent (TEDE) if he/she received the following doses during a calendar year?
1.060 REM Shallow Dose Egivalent (SDE):
1.735 REM Lens Dose Equivalent (LDE):
1.514 REM Committed Effective Dose Equivalent (CEDE):
2.078 REM A.
2.795 REM B.
3.138 REM C.
4.309 REM D.
5.327 REM i
l ANSWER B.
3.138 REM COMMENTS Page 3 of 100
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Waterford 3 Examination Question Examination Bank
'
I Examination Question Number 4 QUESTION ID:
457-A SrATUS:
Approved LAST USED DESCRIFTION:
Dose rate / sheilding prohtem
.
j AUTIlOR:
whardm REVISION
REVISION DATE 7/2634
'
APPROVALt tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
whardin VERIFICATION DATE:
7/26/94 TYPE:
MULTIPLE CllOICE TIME:
$
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYSTEM:
RAD CATEGORY:
PROCEDURE i
REFERENCE:
REVISION:
CIIANGE:
DATE:
NRC KA NUMBER:
OBJECTIVE 2-3 10 2.9
W 3-LP-OPS-RAD 02
i QUESTION A valve reads 300 mr/hr behind 2 inches oflead. What will it read when the lead is removed?
A.
600 MR/HR B.
6000 MR/HR C.
3000 MR/HR D.
30000 MR/HR ANSWER c
COMMENTS Page 4 of 100
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Waterford 3 Examination Question Examination Bank
,
Eximination Question Number 5 Qt:ESTION ID:
1342-A STATt'S:
Approved LAST t! SED DESCRIPTION:
Retuming safety related annunciators to senice with a TAR installed AUTilOR:
avest REVISION I
REVISION DATE 6/22,94 APPROVAL:
tbrown APPROVAL DATE:
7,5.96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/22/94 TYPE:
Multiple Choice TIMER
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPA CATEGORY:
Procedure
)
REFERENCE:
REVISION:
CILANGE:
DATE:
OW02 000
00 2/3.95 i
NRC KA NUMBER:
OBJECTIVE 2431 3.3
w 3-fpwa00
194001.Al.03 QUESTION In accordance with Ot 002-000, Annunciator and Alarm Status Control, what documentation must be completed
-
in order to clear the Equipment Out of Service checklist for a safety related annunciator and return it to operable status when a Temporaly Alteration is to remain installed?
A. No action is required to clear the Equipment Out of Service checklist.
B. The Temporary Alteration safety and engineering review must be completed with a satisfactory
,
response.
C. A Condition Report must be generated stating the acceptability of operation with the Temporary Alteration installed.
D. An immediate work Condition Identification must be generated to ensure prompt repair of the condition causing the installation of the Temporary Alteration.
ANSWER l
B. The Temporary Alteration safety and engineering review must be completed with a satisfactory response.
COMMENTS
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Waterford 3 Examination Question Examination Bank Eremination Question Number 6 QUESTION ID-
.A STATUS:
Approved IAST USED DESCRIrrION:
Working hour policy apply?
AUTIIOR:
tmccool REVISION I
REVISION DATE 6/20,94
'
APPROVAL:
thrown APPROVAL DATE:
7/5,96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
6/20.94 TYPE:
Multiple Choice T151E:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE NPECIAL REFERENCES:
SIMU1ATOR SETUP PLANT SYSTEM:
PPA CATEGORY:
Procedure REFERENCE:
REVISION 1 CilANGE:
DATE:
UNT 005 005
01 9/8.92 NRC KA NUMBER:
OBJECrIVE 211 3.7 3.8 w-3-lpwa00
194001. Al 03
- QUESTION Which of the following best describes the condition in which the working hour policy (UNT-005-005) applies?
A. a person working in training performing simulator operations B. a person working on a procedure revision for a quality related system C. a person working on a non-safety related system or component D. a person working on safety-related system or component ANSWER D. a person working on safety-related system or component
'
COMMENTS
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Waterford 3 Examination Question
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Examination Bank Examination Question Number 7
_ QUESTION ID:
3303
.A STATUS:
Approved LAST USED
'
DESCRIPTION:
shiA tumover, log book review if not on shift for 60 days AUTilOR:
tmccool REVISION
REVISION DATE 7/13/94 APPODVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
mjesse VERIFICATION DATE:
12/29/95 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR $ETUP PLANT SYSTEM:
PPA CATEGORY:
Procedure
REFERENCE:
REVISION:
CIIANGE:
DATE:
.
OP lCH)07
00 3/13/96 l
NRC KA NUMBER:
OBJECTIVE 313
3.4 w.3.lp-ops. ppa 00
19CD01.Al.03 QUESTION i
Which of the following best describes how far back in the Station Log an oncoming operator must review, prior
to shin turnover, if that individual has not been on shia for 60 days?
A. since the last shift watch that was stood
'
B. three days
C. one week D two weeks ANSWER D two weeks COMMENTS i
Page 7 of 100
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Waterf:rd 3 Examirtti:3 Questi:2 Examination Bank Esamination Question Number 8 QUESTION ID:
3461
.A STATUS:
Approved LAST USED DF.SCRIFrION:
Requecment for Startup Channels during refuelsg ALTHOR:
bmather REVISION I
REVISION DATE 6/28.96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 i
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/28,96 TYPE:
Muttspie Chou:s TIME:
$
POINTS:
QUIZ ON LY:
CLOSED REFERENCE:
X OPEN REFERENCE
,
'
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
ENI CATEGORY:
SYSTEM
)
,
TS REFERENCE:
REVISION:
CHANGE:
DATE:
OBJECTIVE Ol5 GEN.II W.3 LP-OPS-EN!00
2 1-33
4
. QUESTION
,
Fuel is being reloaded into the reactor vessel when the Shift Supervisor informs you that one startup channel
neutron flux monitor has failed. Which of the following describes the required action?
A. Fuel reload may continue provided backup boron samples are taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
8. Fuel reload may continue provic'ed the inoperable channel is returned to operable status within 4
'
hours.
l C. Suspend core alteratir. s until boron sampling has been initiated every twelve (12) hours for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
D. Suspend core alterations until the inoperable channel is returned to operable status.
ANSWER D. Suspend core alterations until the inoperable channel is returned to operable status.
COMMENTS
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Waterford 3 Examination Question
"
Examination Bank Examination Question Number 9 QUESTION !D:
2922
.A STATUS:
Approved LAST USEO DESCRIPTION:
secorahry actinty bases AUTHOR:
ANv REVISION
REVISION DNIE 12/2962 APPROVAL:
thrown APPROVAL DATE:
7/5/96
- REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/28/96 TYPE:
Multiple Choice TIME:
$
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFER 8CE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPO CATEGORY:
TS kEFERENCE:
REVISION:
CilANGE:
DATE:
TS BASES NRC KA NUMBER:
OBJECTIVE 2-3-22 3.4 4i W-3-LP. OPS-PPO20
OC3337 GEN 04 039 GEN 06 QUESTION The limitation on secondary system specific activity ensures that the resultant off-site dose will be acceptable.
This dose projection includes a gpm primary to secondaly leak on the affected S/G with a concurrent.
'
.
A.
0.5, I micro carie primary activity B.
1.0, loss of offsite power C.
0.5, loss of offsite power D.
1.0, I micro curie primaly activity ANSWER B.
1.0, loss of offsite power i
i
%
COMMENTS
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Page 9 of 100
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Waterford 3 Examination Question Examination Bank l
i Excmination Question Number 10 QUESTION ID:
1630
.A STATUS:
Approved LAST USED DESCRil" TION:
Frequency for updating field control venfications AUTilOR:
avest REVISION I
REVISION DATE 11/19.94 APPROVAL:
tirown APPROVAL DATE:
7/$/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
!!/19/94 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
GOP CATITX)RYi Procedure PPA REFERENCE:
REVISION:
CHANCE:
DATE:
I OP-100 001
00 7/24,96 UNT 00449
00 3/21/96 NRC KA NUMBER:
OIMECTliT, 190301.Al.03 w 3-lp-ops-ppa 00
2-1 21 3.1 3.2
,
i QUESTION l
i
,
Reverification of a field controlled copy of a procedure is required to be performed every l
A.
I day B.
7 days C.
14 days D.
30 days -
)
i ANSWER C.
14 days COMMENTS Page 10 of 100
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Waterford 3 Examination Question Examination Bank ExCmination Question Number 11 QUESTION ID:
4105-A STATUS:
Approved LAST USED DESCRIPTION:
Procedure Usage AUTHOR:
bmather REVISION
REVISION DATE 6/25/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96
-
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/25.96 TYPE:
Multiple Choice TINIE:
$
POINTS:
I
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
ppa CATEGORY:
PROCEDURE
<
REFERENCE:
REVISION:
CilANGE:
DATE:
OP.100 001
00 7/24/96
NRC KA NUMBER:
OBJECrIVE 2120 4.3 4.2 w-3-lp ops-ppa 00
1 QUESTION i
i, l
All of the following tasks are allowed to be performed as an Informational Use procedure except:
s
A. Inserting or Withdrawing CEAs
,
!
.
C. Processing Waste Tanks to Waste Condensate Tanks
D. Shifting Instrument or Station Air Compressors
!
ANSWER t
j A. Inserting or Withdrawing CEAs i
l
COMMENTS i
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Waterford 3 Examination Question Examination Bank l
Exemination Question Number 12 QUESTION ID.
4131-A STATUS:
Approved LAST USED DESCRIPTION:
rrip two leave two entena AUTilOR:
bmather REVISION
REVISION DATE 7/3S6 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/3/96 i
TYPE:
Multiple Choice TIME:
POINTS:
I l
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE l
SPECIAL REFERENCES:
SIMULATOR SETUP
'
PLANT SYSTEM:
PPE CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CilANGE:
DATE:
OP 902 002
00 12/1/95 NRC KA NUMBER:
OBJECTIVE i
2-4 18 2.7 3.6 W-3-LP-OPS-PPE02
l QUESTION Which of the following is the bases for tripping the RCPs with RCS pressure <1621 psia following a LOCA?
A. To eliminate RCP heat input to the RCS B. To minimize core uncovery due to phase separation C. To prevent damage to the RCP impeller D. To prevent damage to the RCP seals ANSWER B. To minimize core uncovery due to phase separation COMMENTS
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Waterford 3 Examination Question Examination Bank
. Examination Question Number 13
' QUESTION !D:
2840
.A STATUS:
Approved LAST USED DESCRitrrION:
Use cihand held fire extinguisher
'
s AUTilOR:
abond REVISION I
REVISION DATE 8/12/94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 I
REFERENCE VERIFIED:
abond VERIFICATION DATE:
8/12.94
TYPE:
MULTIPLE CilOICE TIME:
POINTS:
I l
QUIZ ONLY:
CIDSED REFERENCE:
X OPEN REFERENCE J
SPECIAL REFERENCES:
SIMULATOR SETUP l
PLANT SYSTEM:
FPD CATEGORY:
SYSTEM REFERENCE:
REVISION:
CILANGE:
DATE:
'
NRC KA NUMBER:
OIMECrIVE 3-4-36 2.9 3.3 W 3-LP-FPFB-FBIA2
QUESTION
.
Which hand held fire extinguisher is available at Waterford-3 for use on flammable liquid fires?
'
A.
Pressurized water j
<
l B.
Pressurized Aqueous Foam l
C.
Dry chemical
.
D.
Carbon Dioxide
ANSWER
!
C.
Dry chemical
COMMENTS
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Page 13 of 100
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Waterford 3 Examination Question l
Examination Bank l
Excmination Question Number N QUESTION ID.
3203
.A STATUS:
Approved LAST USED DESCRIPTION:
CEDMCS RSIT Functions AUTHOR:
avest REVISION I
REVISION DATE 6/28,96 APPROVAL:
thrown APPROVAL DATE:
7/596 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/28,96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP l
PLANT SYSTEM:
CED CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
NRC KA NUMBER:
OBJECTIVE 3.1001.K4.03 3.5 3.8 W4-LP4PS-CED00
l l
QUESTION Whech ONE of the following interlocks /permissives in CEDMCS is provided by the reed switch position transmitters (RSPT)?
A. Lower Group Stop.
i B. Upper Electrical Limit.
C. Upper Control Limit.
D. Upper Group Stop.
ANSWER B. Upper Electrical Limit.
COMMENTS i
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Waterford 3 Examination Question Examination Bank Esanination Question Number - 15 QUESTION ID:
1033-A STATUS:
Approved IAST USED DESCRIPTION:
Manual / Auto Sequential CEA movement program AUTHOR:
avest REVISION
REVISION DATE 6/28/96
- APPIOVAL:
tbron APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/28/96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE i
SPECIAL REFERENCES:
SIMULATOR SETUP l
PLANT SYSTEM:
CED CATEGORY:
SYSTEM I
REFERENCE:
REVISION:
CHANGE:
DATE:
OP 010401
01 7/11/96 OP-004404
00 12/13/95 NRC KA NUMBER:
OBJECTIVE 3.1-001 K4.02
3.8 W-3-LP OPS-CED00
W 3-LP-OPS-PPN01
QUESTION i
The Primaly Operator is withdrawing CEA's in the Manual Sequential mode during a Reactor Startup.
Regulating Group 5 hasjust started outward motion from 0.0 inches. At what Reg. Group 5 position should i
Reg. Group 6 start outward motion?
A.
50 inches i
B.
75 inches
>
C.
100 inches i
D.
125 inches ANSWER C.
100 inches COMMENTS Page 15 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 16 QUESTION II):
3454
.A STATUS:
Approsed LAST USED DESCRIPT10N:
Generation of a CWP AUTilOR:
bmather REVISION
REVISION DATE 6/28/96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/2836 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CED CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
OP.5004)08
00 6/21/95 NRC KA NUMBER:
OBJECTIVE 3.t@l K4 23 3.4 3.8 W 3-LP-OPS-CPC00
W-3-LP-OPS-PPS00
$
QUESTION WHICH ONE (1) of the following describes the generation of a CEDMCS CEA Withdrawal Prohibit (CWP)?
A. Initiated by the pulse counter CEA Position Indication System in response to a 2/4 PRETRIP condition on DNBR and prohibits ALL outward movement ofregulating CEAs.
B. Initiated by the Plant Protection System (PPS)in response to a 2/4 PRETRIP condition on DNBR and prohibits ALL outward group movement ofCEAs.
C. Initiated by the pulse counter CEA Position Indication System of the Plant Computer in response to OUT OF SEQUENCE condition and prohibits ALL outward movement of CEAs.
D. Initiated by the Plant Protection System (PPS)in response to OUT OF SEQUENCE condition and prohibits ALL outward group movement of CEAs.
ANSWER B. Initiated by the Plant Protection System (PPS) in response to a 2/4 PRETRIP condition on DNBR and prohibits ALL outward group movement of CEAs.
COMMENTS l
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d Waterford 3 Examination Question Examination Bank Excmination Question Number 17 QUESTION ID:
4106
.A STATUS:
Approved LAST USED DE.sCRIPTION:
Anticipation ofCriticahty AUTilOR:
bmather REVISION I
REVISION DATE 6/25/96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/25/96 TYPE:
Multiple Choice TIME:
PolNTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP Pl. ANT SYSTEM:
ppn CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CIIANGE:
DATE:
,
OP410401
01 7/11/96 NRC KA NUMBER:
OBJECrIVE
'
31401.K5.18 4.2 4.3 W 3.LP OPS-PPN01
.
QUESTION While performing a reactor startup which of the following indicates the earliest time that you should anticipate criticality?
A. When the shutdown banks are being withdrawn B. When the first regulating group is being withdrawn
,
C. When the 1/M plot indicates criticality within the next 100" D. When inside the window of five to seven doublings ANSWER A. When the shutdown banks are being withdrawn COMMENTS Page 17 of 100
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Waterford 3 Examination Question Examination Bank l
Excmination Question Number 18 QUESTION ID:
4114-A STATUS:
Approved LAST USED DESCRIFTION:
Identify failed RCP seals at reduced pressure AUTIIOR:
bmather REVISION
REVISION DATE 6d&S6 APPROVAL:
thrown APPROVAL DATE:
7/5.96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6d&96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
RCP CATEGORY:
SYSTEM
,
REFERENCE:
REVISION:
CIIANGE:
DATE:
OP-901 130
00 2G&94 NRC iCA NUMBER:
OBJEcrIVE 3.4-C33-A2.01 3.5 3.9 W-3-LP-OPS RCP00
QUESTION A cooldown and depressurization is in progress. RCS pressure is currently at 1100 psia and seal pressures for RCP IB are:
Vapor:
40 psia
,
Upper:
40 psia i
Middle:
530 psia Which RCP seal has failed?
A. lower seal B. middle seal C. upper seal D. vapor seal ANSWER C. upper seal COMMENTS Page 18 of 100
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Waterford 3 Examination Question Examination Bank j
.
?
Examination Question Number 19
QUESTION ID-3456-A STATUS:
Approved IAST USED DESCRIPTION:
Reason for starting 4th RCP after 500 F.
AUTHOR:.
hmather REVISION
REVISION DATE 6/28196 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/28/96 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
,
SPECIAL REFERENCES:
SIMULATOR SETUP i
PLANT SYSTEM:
RCP CATECORY:
REFERENCE:
REVISION:
CIIANGE:
DATE:
OP-010 001
01 7/11/96 NRC KA NUMBER:
OBJECTIVE 003 GEN 01 W-3-LP-OPS-PPN01
34003-A1.07 3.4*
3.4 W-3-LP OPS-RCP00 1I QUESTION
,
j Which of the following is the reason for preventing the start of the fourth Reactor Coolant Pump until RCS
temperature is greater than 500 F7 i
A. To prevent exceeding RCS heatup rate limits.
i i
B. To prevent excessive RCP starting currents.
'
C. To limit Steam Generator tube stresses.
D. To limit core uplift.
i ANSWER
,
D. To limit core uplift.
.
COMMENTS
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Waterford 3 Examination Question i
Examination Bank Examination Question Number 20 i
QUESTION ID:
4115-A STATUS:
Approved LAST USED
'
DESCRIITION:
bmather REVISION
REVISION DATE C28/96
'
APPROVAL:
thrown APPROVAL DATE:
7/5/96
d
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/28/96 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE
.,
'
SPECIAL REFERENCES:
SIMULATOR SETUP
!
PLANT SYSTEM:
CVC CATECORY:
SYSTEM
'
f REFERENCE:
REVISION:
CllANGE:
DATE:
i OP-902-002
00 12/1/95
'
NRC KA NUMBER:
OBJELTIVE
3.2-004 A2.12 4.1 4.3 W-3-LP4PS-CVC00
QUESTION Which of the following equipment receive an SIAS signal?
A. CVC 101, letdown stop valve; CVC 103, letdown inside containment isolation valve; CVC 109, letdown outside containment isolation valve.
B. CVC 169, VCT inlet valve; BAM 133, emergency boration valve; CVC 507, RWSP to charging pumps suction.
C. BAM 143, direct boration valve; CVC 209, charging header isolation valve; CVC 401 RCP controlled bleedoffisolation valve.
D. BAM 113 A(B), BAMT A(B) gravity feed valves; CVC 103, letdown inside containment isolation valve; BAM 126 A(B), BAMT Pump A(B) recirculation isolation valve.
ANSWER D. B AM 113 A(B), B AMT A(B) gravity feed valves; CVC 103, letdown inside containment isolation valve; BAM 126 A(B), BAMT Pump A(B) recirculation isolation valve.
COMMENTS i
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Waterford 3 Examination Question Examination Bank Excmination Question Number 21 QUESTION ID:
4116
.A STATUS:
Approved LAST USED DESCRIPTION:
Indications of CVC 650 relief valve lifting AUTilOR:
bmather REVISION I
REVISION DATE 6/28S6 APPROVAL:
thrown APPROVAL DATE:
7/SS6 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/28/96 TYPE:
Multiple Choice TIME:
.
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYFTEM:
CVC CATEGORY:
SYSTEM RFFERENCE:
REVISION:
CIIANGE:
DATE:
'
NRC EA NUMBER:
OBJECrIVE 3.2 C3C-A4.05 3.6 3.1 W-3-LP-OPS-CVC00
i QUESTION
"
If CVC 115, the CVCS letdown 650 psig relief valva, inadvertently lifts, which of the following indications is expected?
A. Back pressure regulating valve closes down
i B. VCT level rises slowly
.
C. Letdown Flow rises
!
D. Letdown Heat exchanger temperature rises
ANSWER A. Back pressure regulating valve closes down COMMENTS
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Page 21 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 22 QUESTION ID:
4117
.A STATUS:
Approved LAST USED i
DESCRIPTION:
Operation of CVC at power AUTIIOR:
bmather REVISION I
REVISION DATE 6/28S 6
'
APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/2896 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP l
PLANT SYSTEM:
CVC CATEGORY:
SYSTEM l
REFERENCE:
REVISION:
CllANGE:
DATE:
'
NRC KA NUMHER:
OBJECr!VE 3.3 004-KI.01 3.6
'4 W-3 LP-OPS-CVC00
l QUESTION The plant is in Mode 3 with PLCS and Letdown in autt latic. The NPO notes letdown flow rising. Which of the following is a possible cause?
l A. Loss ofInstrument Air to Letdown backpressure regulating valve B. The selected PZR level control channel has failed high C. VCT level has dropped to less than 6%
D. Steam line 1 Atmospheric Dump valve controller setpoint has failed low ANSWER B. The selected PZR level control channel has failed high COMMENTS l
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Page 22 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 23 QUESTION ID:
4118-A STATUS:
Approved LAST USED DESCRllTION:
Diagnosis of ESFAS actuations AUTilOR:
hmather REVISION
REVISION DATE 6/29.96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
$
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SY5 TEM:
PPS CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
TS 33.2 NRC KA NUMBER:
OBJECTIVE 32-013-A4.03 4.5 4.7 W 3-LP4PS-PPS00
'
QUESTION The following conditions exist:
A feedline break has occurred inside containment.
e
',
Containment pressure is 17.5 psia.
e Containment radiation is normal
<
e PZR pressure is 1825 psia.
- RWSP levelis 90%.
e SG pressures are (SGI) 925 psia, (SG2) 580 psia.
All of the folk. wing actuation signals should have occurred with the exception of:
{
ANSWER I
D. CSAS i
I COMMENTS l
i f
Page 23 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 24 QUESTION ID:
4104
.A STATUS:
Approved LAST USED DESCRIFrION:
Effect of manuaHy initiating SIAS vs. Automatie initiation of SIAS AUTilOR:
avest.
REVISION
REVISION DATE 6/25/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/25/96 TYPE:
Multiple Choice Tl?tE:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPS CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
45700028
12/16/91 NRC KA NUMDER:
OBJEL71VE 3.2413.A3.01 3.7*
3.9 W 3-LP-OPS-PPS00
QUESTION After a reactor trip a secondary safety lifts and an uncontrolled cooldown commences. Automatic Safety Injection Actuation and Main Steam Isolation Signals fail to actuate and are initiated manually by the PNPO. All of the following occur except:
A. The Containment Cooling system realigned B. Containment Isolation C. Letdown has isolated
,
,
D. The Safeguards Pump Room coolers started ANSWER B. Containment Isolation COMMENTS Page 24 of 100
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i Waterford 3 Exarnination Question
'
Examination Bank Excmination Question Number 25 QUESTION ID:
1385-A STATUS:
Approved LAST USED DESCRII"rION:
Failure of an Upper Detedor
)
AUTilOR:
TPM REVIslON O
REVISION DATE 4/15/91 l
APPROVAL:
tbrown A' PROVAL DATE:
7/5/96 j
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29S 6 i
TYPE:
MULTIPLE CllOICE TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE l
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
ENI CATEGORY:
SYSTEM REFERENCE:
REVISION:
CHANCE:
DATE:
OP 004-008
00 9/27/92 NRC KA NUMBER:
OBJECrIVE 015CC3.K6.04 W.3-LP-OPS-ENICO
3.7413 K4.01 3.1 3.3 0150C3.K4.01 OUESTION If the Excore Nuclear Instlumentation (ENI) Safety Channel upper detector were to fait low at power, the associaed (selected) startup channel would:
'
A.
not energize on a reactor trip B.
energize high voltage
'
C.
not be effected D.
energize its 10 6% bistable ANSWER C.
not be effected COMMENTS Page 25 of 100
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Waterford 3 Examination Question i
Examination Bank
!
Eramination Question Number 26 QUESTION ID.
4119-A STATUS:
Approved LAST USED DESCR! PRION:
le-4% B! STABLE ACTIONS AttrilOR:
bmather REVISION
REVISION DATE 6/29/96
'
APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Afultiple Choice TISfE:
$
POINTS:
QUIZ ONLY:
CLOSED PEFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
PIANT SYSTEM:
EN!
CATEGORY:
SYSTEM
PPS l
REFERENCE:
REVISION:
CllANGE:
DATE:
'
NRC KA NUMBER:
OBJECTIVE
'
3.7 0l $-K4.06 3.9 4.2 W-3 LP-OPS-EN100 OS
'
QUESTION
~
Which of the following describes an automatic function of the 1 E-4% bistable?
i A. bypasses High log power trip B. bypasses High S/G level trips C. enables High log power trip
D. enables High S/G level trips
!
ANSWER C. enables High log power trip
.
COMMENTS i
i
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Page 26 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 27 QUESTION ID:
4133-A STATUS:
Approved IAST USED DESCRIPTION:
Indications of Core Uncovery
)
AUTilOR:
bmather REVISION I
REVISION DATE 7/5/96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 i
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/5/96 TYPE:
hiuttiple Choice TINIE:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
Sl%IULATOR SETUP PIANT SYSTESI:
med CATEGORY:
REFERENCE:
REVISION:
CILLNCE:
DATE:
OP-902402
00 12/1/95 NRC KA NUafBER:
OBJECTIVE 3 7-017 K5.03 3.7 4.1 W-3-LP4Ps-hiCD03
QUESTION Which of the following could be an indication of core uncovery? (Assume instluments are accurate)
CET Temperature equal to:
A. 550 F with RCS pressure equal to 1100 psia B. 570 F with RCS pressure equal to 1300 psia C. 590 F with RCS pressure equal to 1350 psia D. 610 F with RCS pressure equal to 1700 psia ANSWER C. 590 F with RCS pressure equal to 1350 psia COMMENTS Page 27 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 28 j
j QUESTION ID:
4137-A STATUS:
Approved LAST USED
DESClurTION:
Use of CET: when 51in progress i
AUTIIOR:
bmather REVISION I
REVISION DATE 7/5S6
)
,
APPROVAL:
thrown APPROVAL DATE:
7/5/96
l REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/5/96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAl, REFERENCES:
SIMULATOR SETUP PIANT SYSTEM:
PPE CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CllANGE:
DATE:
.i op-903-C32
00 12/1/95 NRC KA NUMBER:
OBJECTIVE 3.7417-Kl.02 3.3 3.5
QUESTION
_
With Hot and Cold leg injection in progress, which of the following temperature indications should be used to monitor RCS temperature?
,
A. Representative CET B. Hot leg Safety Channel C. Cold leg Safety Channel
,
D. Subcooled Margin a
ANSWER
'
A. Representative CET
,
i COMMENTS
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Page 28 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 29 QUESTION ID.
2364-A STATUS:
Approved LAST USED DESCRWIION:
TPM REVISION O
REVISION DATE 11/731 APPROVAL:
thrown APPROVAL DATE:
7/5S6 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/2996 TYPE:
MULTIPLE CHOICE TIME:
POINTS:
QU1Z ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CCS CATEGORY:
SYSTEM REFERENCE:
REVISION:
C11ANGE:
DATE:
OP-008403
00 2/6S1 NRC KA NUMBER:
OBJFI.TIVE 3.5-032 A3.01 4.1 4.3 W.3-LP OPS-CCS00
022000.A3.01 QUESTION Which of the following best describes the configuration of the Containment Fan Coolers following an SIAS signal.
A. Three fans start or shift to fast speed. The CCW outlet flow control valves will go to the two fan flow setpoint (1400 gpm).
B. Three fans start or shift to slow speed. The CCW outlet flow control valves will go to the two fan flow setpoint (1400 gpm).
C. All fans start or shift to fast speed. The CCW outlet flow control valves will go full open for maximum flow (2700 gpm).
.
D. All fans start or shift to slow speed. The CCW outlet flow control valves will go full open for maximum flow (2700 gpm).
ANSWER D. All fans start or shift to slow speed. The CCW outlet flow control valves will go full open for
.
maximum flow (2700 gpm).
,
COMMENTS Page 29 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 30 QUESTION ID.
2.363
.A STATUS:
Approved LAST USED
'
DESCRIPTION:
Power Supplies to CFC's AUTiiOR:
TPM REVISION O
REVISION DATE 110.91
.
APPROVAL:
tbrown APPROVAL DATE:
7/5,96 REFERENCE VERIFIED:
shymel VERIFICATION DATE:
7/24.95 TYPE:
MULTIPLE CHOICE TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
,
a SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CCS CATEGORY:
SYSTEM i
REFERENCE:
REVISION:
CHANGE:
DATE:
OP-CD8403
00 2/6/91 J
'
NRC KA NUMBER:
OBJECTIVE 022000.K2.01 W-3-LP4PS-CCS00
'
3.5422 K2 01 3.0*
3.1 QUESTION
Which of the following provide electrical power to the Containment Cooling Fans.
,
A.
31 AS and 31BS
D.
,
ANSWER
'
A.
COMMENTS
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a
i Page 30 of 100
,
i Waterford 3 Examination Question Examination Bank f
Examination Question Number 31 QUESTION ID:
1870-A STATUS:
Approved IAST USED DESCRIITION:
Feedwater Pump Trips due to corulensate pumps i
ALTilOR:
PJO REVislON O
REVISION DATE 7/24.91
'
APPROVAL:
tbrown APPROVAL DATE:
7/5/96 j
REFERENCE VERIFIED:
avest VERIFICATION DATE:
3/8/95
)
TYPE:
MULTIPLE CliO!CE TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
)
PLANT SYSTEM:
CD CATEGORY:
SYSTEM FWP FW REFERENCE:
REVISION:
CHANGE:
DATE:
OP-003403
01
$/2/96 NRC KA NUMBER:
OBJECTIVE 056010.K4.12 W-3-LP-OPS-FWP00
3.4 056-A2.04 2.6 2.8*
QUESTION
_
Assuming all condensate pumps are running, and both Main Feedwater Pumps are running with HP Governor valves open, what, if any, would be the result if the B and C condensate pump were to trip? (ignore suction pressure trips)
A.
MFW pump 'A' would trip B.
MFW pump 'B' would trip C.
Both MFW pumps would trip D.
Neither MFW pump would trip j
ANSWER B.~
MFW pump 'B' would trip COMMENTS Page 31 of 100
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Waterford 3 Examination Question
,
Examination Bank Escmination Question Number 32 j
QUESTION ID:
2335-A STATUS:
Approved LAST USED
'
,
DESCRIPTION:
Deternune EFnS status from given condnions i
AUTHOR:
whardm REVISION
REVISION DATE 2/1035 j
APPROVAL:
thrown APPROVAL DATE:
7/5/96
)
REFERENCE VERIFIED:
whardm VERIFICATION DATE:
2/10/95 TYPE:
Multiple Choice TIME:
POINTS:
I i
Qt:1Z ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
EFW CATEGORY:
SYSTEM PPS
REFERENCE:
REVISION:
CllANCE:
DATE:
NRC KA NUMBER:
OBJECTIVE 061000 K4.02 W-3 LP-OPS-EFWOO
'
3.4461 K4.02 4. 5 4.6 W-3-LP-OPS-PPs00
i QUESTION
'
- .
'
An EFAS 1 signal will be present for which of the following? (consider each answer separately)
A.
S/G l@ 20% NR, S/G 2@ 26.5% NR, S/G l& 2 @ 600 psia
B.
S/G l@ 30% NR, S/G 2@ 25% NR, S/G l@ 700 psia, S/G 2@ 680 psia C.
S/G l@ 15% NR, S/G 2@ 20% NR, S/G l@200 psia, S/G 2 @ 400 psia D.
S/G l@ 5% NR, S/G 2@ 10% NR, S/G l@ 500 psia, S/G 2 @370 psia
,
ANSWER
"
'
D.
S/G l@ 5% NR, S/G 2@ 10% NR, S/G l@ 500 psia, S/G 2 @370 psia
'
COMMENTS
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Page 32 of 100
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j Waterford 3 Examination Question Examination Bank
- Exemination Question Number 33
'
QUESTION ID.
2680-A STATUS:
Approved LAST USED DESCRIPTION:
EFAs ANALYSIS QUESTION AUTilOR:
BL REVISION
REVISION DATE 3/19/92 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96
TYPE:
Muttiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE
"
SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYhTEM:
EFW CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
'
OP409 003
00 5/2/96 NRC KA NUMBER:
OBJECTIVE i
3.4461.A3.03 3.9 3.9 W-3-LP-ops-EFWOO
!
061000. Al.01 QUESTION
,
'
. Given the following plant conditions:
!
S/G 1 820 psia (constant);
WR level 57%
i S/G 2 530 psia (dropping); WR level 54%
EFAS1&2 MANUALLY initiated SIAS CIAS & MSIS initiated.
All other EFW flow controls in automatic Which of the following statements describes the status of the Emergency Feedwater system?
A.
S/G 1 EFW Flow Isolation valves can be closed.
B.. S/G 2 EFW Flow Isolation valves are closed due to the MSIS.
C.
S/G 1 EFW flow control valves will maintain 400 gpm until reaching level Y.
D.
S/G 2 EFW flow will continue until level reaches level X.
ANSWER D.
S/G 2 EFW flow will continue until level reaches level X.
COMMENTS Page 33 of 100
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Waterford 3 Examination Question i
Examination Bank Excinination Question Number 34 QUESTION ID:
4107 A
STATUS:
Approved LAST USED j
DESCRil" TION:
Auto isolation of WCT discharge AUTIIOR:
bmather REVISION I
REVISION DATE 6/25/96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIF1ED:
hmather VERIFICATION DATE:
6/25/96 TYPE:
Multiple Choice TIME:
$
POINTS:
I i
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE
- '
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
LWM CATEGORY:
SYSTEM RMS REFERENCE:
REVIslON:
CllANGE:
DATE:
'
NRC KA NUMBER:
OBJECTIVE 3.948-A4.04
3.7 W-3-LP-OPS-RM500
W-3-LP-RO LWM00 04,05 r
QUESTION All of the following are possible causes of automatic termination of WCT discharge to Circulating Water except:
A. Loss of sample flow i
B. Loss of radiation monitor power supply
C. High discharge conductivity
,
D. Low Waste Condensate Tank Level
f l
ANSWER C. High discharge conductivity
,
COMMENTS l
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Page 34 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 35 QUESTION ID:
2540
.A STATUS:
Approved LAST USED DESCRIPTION:
Why restore FilB normal ventilation ASAP 7 AUTilOR:
tmccool REVISION
REVISION DATE 9/2/94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
9/2/94 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
!!VF CATEGORY:
Procedrn PPO System REFERENCE:
REVISION:
CilANGE:
DATE:
OP-901404
00 1/29/93 NRC KA NUMBER:
OBJECrIVE
'
3.7472-K3.02 3.1 3.5 w-3-Ip ops-hvf00
072000.Kl.01 W.3-LP-OPS-PPO40
QUESTION Select the most correct reason for restoring FHB Normal Ventilation Supply and Exhaust Fans as soon as possible following high airborne activity in the FHB.
l A. High differential pressure prevents personnel from entering / exiting the FHB.
B. Minimize changes in Spent Fuel Pool and Refueling Cavity level if Fuel Transfer Tube Gate Valve is open.
C, Minimize evaporation of water in the Spent Fuel Pool.
i D. Restore ventilation to the Spent Fuel Pool Cooling Pumps.
ANSWER D. Restore ventilation to the Spent Fuel Pool Cooling Pumps.
COMMENTS
Page 35 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 36 QUESTION ID:
3504-A STATUS:
Approved LAST USED DESCRIITION:
Actuation of CR emergency venulation AUTilOR:
bmather REVIslON
REVISION DATE 6/29,96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29.96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLLNT SYSTEM:
IIVC CATEGORY:
SYSTEM PPO REFERENCE:
REVISION:
CIIANGE:
DATE:
OP-901401
00 4/2/93 NRC KA NUMBER:
OBJECTIVE C2060 EK2.02 W-3-LPOPS-1(VC00
3.7 072 K2.04 3.3*
3.5'
QUESTION l
Which of the following occurs when one of the train A radiation monitors CROAI A North (0200.1) or CROAI A South (0200.5) for the control room air intake reaches its high radiation alarm setpoint?
A. All air intake to the RAB is secured.
B. Control room Toilet Exhaust Fan A starts.
C. Control Room Normal Air Handling Unit A stops D. Control room Emergency Filtration Unit A starts.
ANSWER D. Control room Emergency Filtration Unit A starts.
COMMENTS Page 36 of 100
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Waterford 3 Examination Question Examination Bank Eximination Question Number 37 QUEhTION ID 1036-A STATUS:
Approved LAST USED DESCRIFTION:
T.S. temperature requirement for having LTOPS in service AUTilOR:
atest REVISION I
REVISION DATE 6/2996 APPROVAL:
tbrown APPROVAL DATE:
7/$/96 I
REFERENCE VERIFIED:
avest VERIFICATION DA(Er 6/29.96 TYPE:
Multiple Choice TIME:
P'
I QUIZ ONLY:
CLOSED REFERENCE:
X
.FERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
RCS CATEGORY:
PROCEDURE TS REFERENCE:
REVISION:
CHANGE:
DATE:
TS 3 4.8 05-010-001
01 7/11/96 NRC KA NUMBER:
OBJECr!VE 3.4-002-K4.10 4.2 4.4 W.3.LP-OPS-PPN02
W.3.LP-OPS.5100
W 3-LP. OPS-S100
QUESTION When cooling down the plant per OP-010-001, General Plant Operations, when are the Low Temperature Over pressure Protection Relief Valves (LTOP's) required to be aligned for service?
A.
Prior to closing the Safety Injection Tanks' Isolation Valves.
B.
Prior to entering Mode 4.
C.
Prior to placing both Letdown Flow Control Valves in se!vice.
D.
Prior to reducing RCS temperature to 272 F.
<
ANSWER l
D.
Prior to reducing RCS temperature to 272 F.
{
COMMENTS
<
Page 37 of 100
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Waterford 3 Examination Question i
,
Examination Bank
!
Examination Question Number 38 QUESTION ID:
1216-A STATU3:
Approved LAST USED DESCRIPTION:
Change necessary in Tavg to maintain SO pressure constar.t with 10% plugged tubes AUTIIOR:
whardin REVISION
REVISs0N DATE 8/2/94 i
APPROVAL:
thrown APPROVAL DATE:
7/5/96
REFERENCE VERIFIED:
whardm VERIFICATION DATE:
8 @ 94
'
TYPE:
Multiple Choice TIME:
POINTS:
1 QUIZ ONLY CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
,
'
PLANT SYSTEM:
RCS CATEGORY:
Fundamentals TYli l
REFERENCE:
REVISION:
CilANGE:
DATE:
NRC KA NUMBER:
OBJECTIVE J
3.4-002-K5.01 3.1 3.4 W.3-LP-OPS-TYlI07
QUESTION
!
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Prior to plugging 10 percent of the U-tube area in each steam generator, the plant operated at 100% power with
RCS Tave at 574 F and a steam pressure of 850 psia. To what value must Tave be changed in order to maintain the same Steam Generator pressure at 100% power? Assume RCS flow rate was unaffected by S tube plugging.
d A. 577.4 F l
'
i
1 B. 579.4 F
,
C. 581.4 F J
i i
D. 583.4 F
.
ANSWER i
l B. 579.4 F i
!
COMMENTS
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Page 38 of 100
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Waterford 3 Examination Question Examination Bank i
Excmination Question Number 39 QUESTION ID:
1276
.A STATt'S:
Approved IAST USED DESCRIPTION:
RC S vents T.S. requirements
,
)
AUTl!OR:
WJV REVISION O
REVISION DATE 4/5/91
.
'
]
APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CIDSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYSTEM:
RCS CATEGORY:
SYSTEM
+
REFERENCE:
REVISION:
CIIANGE:
DATE:
RO FRO TRAINING MATERIAL:
OIMECTIVE 3.2402.A2.03 4.1 4.3 W-3-LPOPS-RCS00
QUESTION '
The Reactor Coolant System Vents are required to be operable in Modes 1,2,3, and 4 to:
i A.
Limit combustible mixtures.
B.
Prevent steam or non condensables from interfering with natural circulation.
i C.
Equalize pressure between the Pressurizer and th; Peactor Vessel head.
D.
Ensure that hot leg injection reaches the core.
l
.
ANSWER B.
Prevent steam or non condensables from interfering with natural circulation.
COMMENTS Page 39 of 100
.
b Waterford 3 Examination Question Examination Bank
,
Excmination Question Number 40 QUESTION ID:
1532-A STATI?S:
Approved LAST USED
,
DESCRIPTION:
Signal that bypasses the motor overloads for SI 602A(B) and reason AUTiiOR:
avest REVISION I
REVISION DATE 6/29 S 6 APPROVAL:
thrown APPROVAL DATE:
7/5/96
'
REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/29 96 TYPE:
Nfultiple Choice TIME:
POINTS:
s
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE MPECIAL REFERENCES:
51MULATOR SETUP PLANT SYSTEM:
CS CATEGORY:
System r
Si REFERENCE:
REVISION:
CIIANGE:
DATE:
OP.0094)08
00 2/7/96
'
NHC KA NUMBER:
OBJEC1 kVE
3.34)o6-Kl.02 4.3
W-3.LP-OPS 4S00
'
W-3-LP-OPS-S100
OUESTION
!
The motor overload relays for SI-602A & B (Safety Injection Sump outlets) are bypassed.
i A.
On RAS to ensure the valves can be opened.
.
B.
On RAS to ensure the valves can be closed.
C.
On SIAS to ensure the valves can be opened.
D.
On SIAS to ensure the valves can be closed.
J
ANSWER
,
'
D.
On SIAS to ensure the valves can be closed.
COMMENTS
4 d
<
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Page 40 of 100
l Waterford 3 Examination Question Examination Bank Enmination Question Number 41 QUESTION ID-1563-A STATUS:
Approved IAST USED DESCRIFTION:
reason IIPSI FCVs are throuted on SIAS AUTIIOR:
avest REVISION
REVISION DATE 6/29'96
APPROVAL:
tbrown APPROVAL DATE:
7/5S6 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/29S6 j
TYPE:
Multiple Choice TIME:
POINTS:
4 QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
'
PIANT SYSTEM:
SI CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
NRC KA NU4fitER:
OBJECTIVE 12-006-K4.09 3.8 4.2 W.3-LP-OPS-S100
QUESTION Select the reason HPSI Cold Leg Injection Flow Control Valves go to a throttled position on an SIAS.
A.
To reduce the HPSI Pump starting current if RCS pressure is below shutoff head.
B.
To minimize back flow from the RCS in the event a HPSI Pump fails to start.
'
C.
To prevent HPSI Pump runout and balance flow to each of the cold legs.
D.
To limit HPSI flow such that RAS does not occur earlier than assumed in the safety analysis.
,
.
ANSWER
,
C.
To prevent HPSI Pump runout and balance flow to each of the cold legs.
,
COMMENTS
,
Page 41 of 100
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l Waterford 3 Examination Question Examination Bank Examination Question Number 42 QUENTION ID:
1398-A STATUS:
Approved LAST USED DESCRIITION:
Pzr backup heater action on an insurge AUTiiOR:
TPM REVISION O
REVISION DAT E 4/15.91 i
APPROVAL:
thrown APPROVAL DATE:
7/596 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29.96 TYPE:
MULTIPLE CliolCE TIME:
POINTS:
QUlz ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPC CATEGORY:
SYSTEM i
,
P'FERENCE:
REVISION:
CllANCE:
DATE:
.
A NUMBER:
OBJECrIVE-K l.08 3.2 3.5 W-3-LP-OPS-PLC00
4.
Osw J.K6.02 QUESTION t
i The purpose of energizing the Pressurizer Backup Heaters when Pressurizer level rises above Programmed Level j
during an in-surge is:
A.
To raise Pressurizer pressure to saturation.
B.
To raise Pressurizer steam space temperature.
\\
C.
To returr.
'surizer pressure to setpoint.
,
i i
!
D.
To return Pressurizer water temperature to saturated conditions.
- i
'
ANSWER
.
,
i D.
To return Pressurizer water temperature to saturated conditions.
'
COMMENTS i
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Page 42 of 100
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Waterford 3 Examination Question
Examination Bank Enmination Question Number 43 QUESTION ID:
1797-A STATlfS:
Approved LAST USED D2.ScklPTION:
Aux, tnp, tnp without pretnp light AUrl!OR:
Wall REVISION
REVISION DATE I/6/94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmeaol VERIFICATION DATE:
9'21/94 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CPC CATEGORY:
SYSTEM REFERENCE:
REVISION:
CllANGE:
DATE:
NRC KA NUMBER:
OBJECTIVE 3.7-012 K6.07 2.9 *
3.2 W 3.LP-OPS {PCol
i QUESTION Following a single channel CPC trip, how can the operator quickly determine if the trip signal is due to an Auxiliary Trip?
A.
By obtaining the CPC Trip Buffer Report.
B.
By observing a Trip light without the associated Pretrip light.
C.
By obtaining the trip Sequence of Events Report (SOE).
D.
By observing that Diverse Reactor Trip has actuated.
j ANSWER B.
By observing a Trip light without the associated Pretrip light.
COMMENTS l
i Page 43 of 100
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Waterford 3 Examination Question Examination Bank Exarnination Question Number 44 QUESTION ID:
3139-A STATUS:
Approved 1AST USED DESCRIITION:
Reason for minimum time for RAS actuation after LOCA AUTi!OR:
avest REVISION
REVISION DATE 6/29S6 APPROVAL:
thrown APPROVAL DATE:
7/5S6 REFERENCE VERIFIED:
avest VERIFICATION DATE:
679/96 TYPE:
Multiple choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPS CATEGORY:
SYSTEM REFERENCE:
REVISION:
CllANGE:
DATE:
NRC KA NUMBER:
OBJECTIVE 3.3 006.K4 07 3.3 3.6 W-3-LP OPS-S!00
QUESTION RAS initiation is delayed for at least 20 minutes after a large break LOCA occurs so that:
A. The RCS will have completed blowdown.
B. The LPSI pumps will have adequate NPSH.
C. Core boiloffis less than the capacity of one HPSI train.
D. Containment pressure will be reduced by half.
ANSWER C. Core boiloffis less than the capacity of one HPSI train.
- COMMENTS Page 44 of 100
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l Waterford 3 Examination Question
'
Examination Bank
!
l Examination Question Number 45
!
QUESTION ID 3081
.A NTATUS:
Approved LAST USED DENCRIPTION:
CWP for Target CEA's vs. CEAC's AUTilOR:
tmccool REVISION
REVISION DATE 8/594 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
8/5/94 TYPE:
Niultiple Choice TINIE:
POINTS:
QUIZ ON LY:
CLOSED REFERENCE:
X OPEN REFERENCE X
NPECIAL uEFERENCES:
SINIULATOR SETUP PLANT SYSI m31:
CPC CATEGORY:
SYSTEA1 REFERENCE:
REVISION:
CllANGE:
DATE:
OP 004-006 to
4/1394 NRC KA NUNIBER:
OluECTIVE 314)l4.A2 04 3.4
W.3-LP-OPS-CPCol
3.1001 K4 08 3.2 '
3.4 QUESTION You are withdrawing Reg Group 6 CEAs, IE one CEA in the group stops moving while the rest continue to withdraw, Which of the following will prevent any further group withdrawal when reached (assume Group 6 is at 130 :nches when misalignment occurs)
A.
4.95 inch misalignment detected by CPC target CEAs B.
4.95 inch misalignment detected by CEACs C.
5.5 inch misalignment detected by CPC target CEAs D.
5.5 inch misalignment detected by CEACs ANSWER D.
5.5 inch misalignment detected by CEACs COMMENTS Page 45 of 100
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Waterford 3 Examination Question
,
Examination Bank
.
Examination Question Number 46 QUESTION ID:
2232 A
STATUS:
Approved LAST USED
,,
DESCRIPTION:
IIEAT SINK POST 4.OCA WIT 11 RAS AUTIIOR:
Wall REVISION O
REVISION DATE 9/5S1 APPROVAL:
thrown APPROVAL DATE:
7/550 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/29/96
'
TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
'
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CS CATEGORY:
PROCEDURE PPE SYSTEM REFERENCE:
REVISION:
CllANGE:
DATE:
'
00 12/1/95 NRC KA NUMBER:
OBJECrlVE 3.5426-K4.04 3.7 4.1 W.3-LP OPS-CS00
QUESTION Select which system provides the heat sink for cooling the Safety Injection Sump POST-LOCA following a Recirculation Actuation Signal (RAS).
A.
Shutdown Cooling System 5.
High Pressure Safety Injection system C.
Low Pressure Safety Injection system D.
Containment Spray system ANSWER D.
Containment Spray system i
'
COMMENTS Page 46 of 100
..
Waterford 3 Examination Question Examination Bank Excmination Question Number 47 QUESTION ID.
4127-A STATUS:
Approved LAST USED DESCRIPTION:
Actions that occur as a result of lo-lo level in the spent fuel pool AUTHOR:
avest REVISION
REVISION DATE 6/29 S 6 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6i.9S6
TYPE:
Multiple Choice TIME:
$
POINTS:
'
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMUIATOR SETUP PLANT SYSTEM:
FS CATEGORY:
SYSTEM REFERENCE:
REVISION:
CilANGE:
DATE:
OP-003406
00 8/1/94 i
NRC KA NUMHER:
OBJECrIVE 3.8433-A2.03 3.1 3.5 W.3 LP-OPS-FS00
0UESTION i
Which of the following would occur as a DIRECT result of LO-LO spent fuel pool level (41.6 ft)?
A. Spent Fuel Pool Cooling Pumps trip l
'
B. CMU to Spent Fuel Pool Makeup Valve opens C. SFIB1 Hoist Up movement is disabled D. Fuel Handling Building Isolation Actuation occurs ANSWER
/. Spent Fuel Pool Cooling Pumps trip COMMENTS Page 47 of 100
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i Waterford 3 EEamination Question Examination bank Examination Question Number 48 QUESTION ID:
-A STATUS:
Approved LAST USED DESCluPTION:
Conditions requinng resetting so tnp setpoints dunng RCS cooldown AUTIIOR:
RJC REVISION
REVISION DATE 2/2434 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/29 S 6 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPN CATEGORY:
PROCEDURE PPs SYSTEM l
REFERENCE:
REVISION:
CllANCE:
DATE:
'
OP-010-001
01 7/11/96 NRC KA NUMBER:
OBJECTI\\T, 3 4-035-KI.12 3.7 3.9 W 3-LP OPS-PPN02
W 3-LP-ops-PPs00
QUESTION A Cooldown to Mode 5 using the Steam Bypass Control System is in progress.
Plant conditions are as follows:
Steam Generator 1 & 2 pressures are 800 psia.
Reactor Coolant System temperature is 518 F.
l Pressurizer pressure is 2l00 psia and level is 33%.
RCPs l A, IB, and 2B are operating.
Charging Pumps A & B are operating with Letdown in automatic control.
Select the action which should be performed to prevent an inadvertent Engineered Safety Features Actuation l
Signal (ESFAS).
A.
Reset the Pressurizer low pressure trip setpoints.
B.
Raise Pressurizer level to 50%.
C, Bypass the Pressurizer low pressure trips.
i D.
Reset the Steam Generator low pressure trip setpoints.
l l
'
ANSWER D.
Reset the Steam Generator low pressure trip setpoints.
l COMMENTS
l Page 48 of 100
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--
Waterford 3 Examination Question Examination Bank Estmination Question Number 49 QUESTION ID:
-A STATUS:
Approved IAST USED
!
DESCRIPTION:
EfTest ofnot inpping the main turbine aAce a reactor trip AUTilOR:
avest REVISION
REVISION DATE 6/29,96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 i
REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/29.96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYSTEM:
PPE CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CilANGE:
DATE:
OP.902400
00 12/1/95 TO-OP-902400
00 2/13.96 l
NRC KA NUMBER:
OBJECTIVE l
3.4-039-K5.08
3.6 W.3-LP OPS-PPE01
4.1-E7-EK3.01
46 4.1 E7-EKl.03 3.7
l QUESTION
,
l The reactor trips from 100% power. The control room operators verify that the reactor is tripped and immediately note that the turbine has not tripped and the generator breakers remain closed. Ifleft unresolved this malfunction will cause:
A.
An uncontrolled cool down of the RCS, resulting in less shutdown margin.
B.
Main turbine blade heating, possibly resulting in damage to the main turbine rotor and shaft.
l C.
A loss of condenser vacuum, resulting in the loss of condenser steam dump.
D.
An increase in RCS pressure, possibly resulting in the Pressurizer safety valves lifting.
.
ANSWER l
l
A.
An uncontrolled cool down of the RCS, resulting in less shutdown margin.
I COMMENTS l
l l
!
Page 49 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 50 QUESTION ID:
1660-A STATUS:
Approved LAST USED DESCRIPTION:
Repowering the safety bus. taking the synch. Switch to bus tie places EDo in Droop but stays in Enwrgemy AUrHoR:
tmccool REVISION
REVISION DATE 8/15/94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
8/15/94 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SY!rrEM:
EDo CATEGORY:
SYSTEM REFERENCE:
REVISION:
CHANGE:
DATE:
OP-902 002
00 11/1/95 NRC KA NUMBER:
OBJECTIVE 3.6464 K4.03 2.5
W-3-LP-OPS-EDG00
QUESTION Complete the following statement.
An Emergency Diesel Generator is supplying its associated safety bus in the Emergency Mode and normal power is aligned to the 2 bus with the 2 to 3 bus tie breaker closed. When the operator takes the associated synchronizer switch to the BUS TIE position:
A.
the governor will be returned to the droop mode of operation.
B.
the governor swaps to the backup hydraulic isochronous mode.
C.
the Diesel swaps to the Test Mode of operation.
D.
the Bus Tie Breaker closes following a Synch Check.
ANSWER A.
the governor will be returned to the droop mode of operation.
COMMENTS Page 50 of 100
1 I
,
Waterford 3 Exanlination Question Examination Bank l
Examination Question Number $1 QUESTION ID:
2235
.A STATUS:
Approved LAST USED DESCRIPTION:
WilAT MAKES SUPS UNINTERRUFFIDLE
,
AUTHOR:
Wall REVISION
REVISION DATE 12/21/93
)
APPROVAL:
thrown APPROVAL DATE:
7/$/96
'
REFERENCE VERIFIED:
VERIFICATION DATE:
12/21/93 TYPE:
Multiple choice TIME:
POINTS:
QUIZ ONLYr CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
)
PLANT SYSTEM:
ID CATEGORY:
SYSTEM REFERENCE:
REVIslON:
CilANGE:
DATE:
NRC KA NUMBER:
OBJECilVE
'34-062.K4.10 3.1 3.5 W-3-LP-OPS-ID00
QUESTION The output of Safety SUPS SA is considered to be uninterruptible because:
A.
Auctioneered AC power supplies are provided to the rectifier section.
B.
Inverter input is auctioneered between the rectifier output and a DC Safety Bus supply.
C.
An internal battery is auctioneered with the rectifier output.
D.
The Static Transfer Switch automatically transfers to AC alternate source.
ANSWER B.
Inverter input is auctioneered between the rectifier output and a DC Safety Bus supply.
COMMENTS Page 51 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 52 QUESTION ID:
3410 A
STATUS:
Approved LAST USED DESCRlrrlON:
4.16 KV Iweaker operation on loss of DC power ALTTHOR:
shymel REVISION
REVISION DATE I1/5/94 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
shymel VERIFICATION DATE:
11/5/94 TYPE:
Multiple Choice TISIE:
$
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
ED CATEGORY:
Systan EPC REFERENCE:
REVISION:
CilANGE:
DATE:
NRC KA NUMBER:
OBJFX.' RIVE 34063-K3.02 3.5 3.7 W 3-LP. OPS-EPC00
QUESTION Which of the following describes 4.16KV breaker operation if DC control power is lost?
A. Breakers will remain in their "as is" condition and operation would only be pe;#.'e by local manual means.
B. Automatic breaker trips would remain operational but remote operation of breakers would not be possible.
C. Breakers would remain remotely operable but automatic trip functions would become inoperable.
D. Breakers would trip open and operation would not be possible by local manual means.
ANSWER
'
A. Breakers will remain in their "as is" condition and operation would only be possible by local manual means.
COMMENTS Page 52 of 100
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Waterford 3 Examination Question
'
Examination Bank
!
Examination Question Number 53 QUESTION ID.
3140 A
STATUS:
Approved LAST USED DESCRIPTION:
ElX) paralleled to gnd and voltage and governor switches taken to increase AUTilOR:
HC REVISION O
REVISION DATE IIllI/93
,
.i APPROVAL:
tbrown APPROVAL DATE:
7/5 96 J
REFERENCE VERIFIED:
VERIFICATION DATE:
11/11'93 TYPE:
Af ultiple Choice T1512:
POINTS:
QUIZ ONLY CLOSED REFERENCE:
X OPEN REFERENCE X
NPECIAL REFERENCES:
StatU1ATOR SETUP PLANT SYSTENt:
EDO CATEGORY:
FUNDAMENTALS SYSTEAf REFERENCE:
REVISION:
CllANGE:
DATE:
.,
'
OP 009-002
00 5/29/96 NRC KA NU5tBER:
OILIECTIVE 3 6-064-A2.03
3.1 W 3-LP-OPS-EDOOO
1
'
QUESTION Which of the following is the correct expected response if an EDG is paralleled to the grid and the Governor and Voltage control hand switches are both taken to Raise / Increase?
)
A.
Kw increases and EDG speed increases.
1
B.
Reactive load increases and Kw increases.
C.
Indicated output voltage increases and Reactive load increases.
D.
EDG speed increases and Indicated output voltage increases.
l ANSWER B.
Reactive load increases and Kw increases.
4 COMMENTS Page 53 of 100
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d Waterford 3 Examination Question Examination Bank Examination Question Number 54
'
QUEKrlON ID-2237 A
NTATUS:
Approsed LAST USED a
DESCRIPTION:
Requirernents for dtsharge with the LWht rad rnonitor OOS AUTIIOR:
avest REVISION
REVISION DATE 6/29/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/29S6 TYPE:
Afultiple Choice TIS!E:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIAIULATOR SETUP j
PLANT SYSTEAf:
LWh1 CATEGORY:
PROCEDURE PRAI REFERENCE:
REVISION:
CIIANGE:
DATE:
IIP 401-333
01 3/21/96 NRC KA NUhlBER:
OBJECTIVE
-
3.7473 K3.01 3.6 4.2 W 3-LP-RO-LWh100
QUESTION With an inoperable LWM radiation monitor all of the following are required to perform a discharge from the Waste Condensate Tanks except:
A.
Obtain and analyze independent samples from the Waste Condensate Tank.
'
B.
Perform an independent verification of discharge valve lineup.
'
C.
Perform an independent verification of release rate calculation.
D.
Perform an independent verification of proper Circ Water flow.
ANSWER D.
Perform an independent verification of proper Circ Water Gow.
COMMENTS Page 54 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 55 QUESTION ID-3519-A STATUS:
Approved LAST USED DESCRIPTION:
locations sampled by the pas syen AUTIIOR:
avest REVISION I
REVISION DATE 6/29/96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 g
REFERENCE VERIFIED:
avest VERIFICATION DATE:
W2996 TYPE:
Afultiple Choke TINIE:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECL4L REFERENCES:
SIMULATOR SETUP PLANT SYSTESI:
PAS CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANGE:
DATE:
'
NRC KA NUMBER:
OILIECrIVE 3.7 073 Kl.01
3.9 W 3-LP-OPS-PAS 00
W QUESTION Which of the following describes the locations sampled by the PAS system?
A. Reactor coolant system cold leg #1, RAB penetration areas, and containment SIS sump.
B. Containment Atmosphere, Reactor Coolant System hot leg #1, and containment SIS sump.
C. Shutdown cooling train A, component cooling water system, and containment atmosphere.
D. Reactor coolant system hot leg #2, SDC cooling train B and containment SIS sump.
ANSWER B. Containment Atmosphere, Reactor Coolant System hot leg #1, and containment SIS sump.
COMMENTS Page 55 of 100
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Waterford 3 Examination Question Examination Bank
'
i
Examination Question Number 56
-
,
QUESTION ID.
2280-A STATlis:
Approved LAST USED
.
j DESCRIPTION:
DFP WATER SUPPLY AUTilOR:
BCM REVISION
REVISION DATE 10/28/91 APPROVAL:
tbrown APPROVAL DATE:
7/5/96
REFERENCE VERIFIED:
VERIFICATION DATE:
10/28SI TYPE:
Muhiple Choice TIME:
$
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYNTEM:
FPD CATEGORY:
SYSTEM J
FPP REFERENCE:
REVISION:
Cl!ANCE:
DATE:
OP@9-004
O!
$/2/96 NRC KA NUMBER:
OBJECrWF.
,
3.0 086-K4 01 3. I 3.7 W 3-LP-OPS-FP00
'
3.0-086-AI.02 3.0 '
3.2 '
!
QUESTION
.
Choose the answer that best describes the normal alignment of the Diesel Fire Pump Suction.
T
A.
Diesel Fire Pump #1 takes suction from Fire Water Storage Tank A l
B.
Diesel Fire Pump #1 takes suction from the Motor Driven Fire Pump discharge header.
.
C.
Diesel Fire Pump #1 takes suction from both Fire Water Storage Tanks.
- D.
Diesel Fire Pump #1 takes suction from Fire Water Storage Tank B.
ANSWER
]
C.
Diesel Fire Pump #1 takes suction from both Fire Water Storage Tanks.
+
COMMENTS i'
!
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Waterford 3 Examination Question Examination Bank Examination Question Number 57 QUESTION ID-2024-A STATUS:
Approved IAST USED DESCRII" TION:
if at and Cold leg injection to cavitating LPSI i
AUTilOR:
WJV REVISION
REVISION DATE 7/16/91 APPROVAL:
ttwown APPROVAL DATE:
7/SS6 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29 S 6 TYPE:
MULTIPLE CliolCE TIME:
$
POINTS:
QUlz ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYSTEM:
SDC CATEGORY:
PRoCEDLTE REFERENCE:
REVISION:
CilANGE:
DATE:
OP-901 131
00 3/23 S 3 NRC KA NUMBER:
OIMECTIVE 000025 012 W.3-LP-OPS-REQ 21
3.4-005 4 3.05 3.7 '
3. 8'
OUESTION The primary reason for initiation of hot and cold leg injection to the SDC train with a cavitating LPSI pump is to:
A.
Prevent Boron precipitation.
l B.
Ensure all injection flow is not lost through cold leg openings.
J C.
Prevent over pressurization of cold leg nozzle dams.
D.
Provide subcooled water to the suction of the cavitating LPSI pumps.
ANSWER D.
Provide subcooled water to the suction of the cavitating LPSI pumps.
COMMENTS
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Waterford 3 Examination Question Examination Bank Excmination Question Number 58 QUESTION ID:
1310-A STATUS:
Approved LAST USED j
DEM'.Ril'rION:
Temperature change across a PZR safety
'
AUTIIOR:
WJV REVISION O
REVISION DATE 4/8/91 APPROVAlt thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
MULTIPLE Cl!OICE TIME:
$
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
^ SPECIAL REFERENCES:
SIMITLATOR SETUP PLANT SWrEM:
RCS CATEGORY:
)
TYli i
'
REFERENCE:
REVISION:
CllANGE:
DATE:
NRC KA NUMBER:
OELIECrIVE i
007000.A4.10 W.3-LP-OPS-MCD01
I 3,5-007.A4.10
3.8 W.3-LP-OPS-TYl104
W.3-LP-OPS-RCS00
QUESTION
)
Assuming a Pressurizer Safety Valve lifts, which of the following statements is most correct?
i A.
The downstream Safety Relief temperature detector will indicate T, for the current Pressurizer j
pressure.
l B.
Quench Tank temperature will equal T,,, for the current Pressurizer pressure.
C.
The downstream Safety Relief temperature detector will indicate T,,, for the current Quench Tank pressure.
D.
Quench Tank pressure will equal P,,, for the current Pressurizer vapor space temperature.
ANSWER C.
The downstream Safety Relief temperature detector will indicate T,,, for the current Quench Tank
]
pressure.
COMMENTS Page 58 of 100
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Waterford 3 Examination Question Examination Bank
Excmination Question Number 59
- QUESTION ID:
4120
.A STATUS:
Approved IAST USED
DESCRIPTION:
Response of CCW pump AB and spttsu with SIAS and LOOP AUTIIOR:
bmather REVISION
REVISION DATE 6/29/96 APPROVAL:
tbrown APPROVAL DATE:
7/5,96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
!
PIANT SYSTEM:
CC CATEGORY:
SYSTEM REFERENCE:
REVISION:
CllANGE:
DATE:
NRC KA NUMBER:
OBJECrIVE
~
3.8 C08 A3,08 3.6*
3.7*
W-3-LP-OPS 4C00 02,04 i
QUESTION CCW pumps B and AB are operating. Although CCW pump AB is replacing A the AB bus is powered from the B-side. The "CCW pump A Unavailable" alarm is locked in. Which of the following describes the status of the CCW system in the event of a concurrent loss of offsite power and SIAS?
A. CCW pumps B & AB running B. CCW pumps A & B running C. Only CCW pump B running D. All CCW pumps running ANSWER C. Only CCW pump B running COMMENTS Page 59 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 60
.,
QUESTION ID.
3136-A STATUS:
Approved IAST USED
]
DESCRIPTION:
ACCW pump starts AUTilOR:
kkirkpa REVISION
REVISION DATE 11/2,95
,
i APPROVAL:
tbrown APPROVAL DATE:
7/596 REFERENCE VERIF1ED:
kkirkpa VERIFICATION DATE:
1I/2.95 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CIDSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYSTF.M:
ACC CATEGORY:
REFERENCE:
REVISION:
CIIANGE:
DATE:
OP 002-001
02 6/18,96
NRC KA NUMBER:
OBJECrIVE 3 8 008-K4 01 3.1 3.3 W 3 LP-OPS-CC00
,
QUESTION
All of the following conditions will automatically start the Train B Auxiliary Component Cooling Water Pump
,
except:
,
A.
Train B CCW Heat Exchanger outlet temperature 10 deg F above the setpoint of CCW q
Temperature Controller, CC-ITIC-7070B.
a B.
Wet Cooling Tower basin temperature reaches 95 deg F.
!
C.
CCW Heat Exchanger outlet temperature reaches 100 deg F.
D.
a Safety Injection Actuation Signal occurs.
l ANSWER S
B.
Wet Cooling Tower basin temperature reaches 95 deg F.
.
COMMENTS
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i NEW K/A # 008.K4.01
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i Waterford 3 Examination Question Examination Bank
Esemination Question Number 61
QUF5rlON ID:
3486-A STATUS:
Approved LAST USED DESCR1PTION:
Refueling muhine interlocks AUTiiOR:
MMARLER REVISION
REVISION DATE 6/16/95 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
MMARLER VERIFICATION DATE:
6/16/95 l
TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
.
PLANT SYSTEM:
FilS CATEGORY:
SYSTEM i
REFERENCE:
REVISION:
CIIANGE:
DATE:
RF435-002
00 9/18/95 NRC KA NUMBER:
OBJECTIVE 3.8434 A3.01 2.5 '
3.1 W-3-LP OPS-FilS00
034003.K4.02
a QUESTION Which of the following describes a condition that prevents the Refueling Machine (RFM) from entering the upender zone?
.
.
A. RFM fuel hoist box is latched.
!
B. RFM fuel hoist overload i
'
j C. Spreader is fully retracted.
D. Upender is completely horizontal.
,
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ANSWER
,
i D. Upender is completely horizontal.
i T
COMMENTS
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Waterford 3 Examination Question i
i Examination Bank l
Exanination Question Number 62 QUESTION ID:
1261
.A STATUS:
Approved LA57 USED DESCRIPTION:
Quick Open Block (RX Trip)
AUTIIOR:
WJV REVISION O
REVISION DATE 4/5/91 l
APPROYAL:
thrown APPROVAL DATE:
7/5/96 (
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
t/12S5
'
TYPE:
MULTIPLE CHOICE TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP l
PLANT SYSTEM:
SBC CATEGORY:
SYSTEM REFERENCE:
REVISION:
CHANGE:
DATE:
NRC KA NUMHER:
OBJECIIVE 041030.K4.17 W.3-LP OPS-SBC00
3 4-041.A4.08
3. I '
QUESTION I
Steam Bypass Valve 6 is the only Steam Bypass valve that receives a quick open block for a:
A.
Reactor Power Cutback with a load rejection B.
Rearur Power Cutback with a Feed pump trip i
C.
Reactor trip with Tave equal to 550 F
D.
Reactor trip with Tave equal to 570 F ANSWER D.
Reactor trip with Tave equal to 570 F COMMENTS l
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Page 62 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 63 QUESTION ID:
1294
.A STATUS:
Approved IAST USED DESCRIFTION:
IA ar.L'POJTrs AND OPERAllON
' AUTIIOR:
JMO REVISION
REVISION DATE 8/16/91 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
VERIFICATION DATE:
8/16a1 TYPE:
MULTIPLE CilOICE TIME:
$
POINTS:
QUIZONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
IA CATEGORY:
SYSTEM REFERENCE:
REVISION:
CllANGE:
DATE:
OP403416
00 ll/20M5 NRC KA NUMBER:
OBJECrIVE 0780C3 A3.01 W 3.LP-OPS-IA00
3.8-078-A3.01 3.1 3.2 QUESTION Concerning the Station and Instrument Air Systems, Which of the following is true?
A.
The Instrument Air compressors cycle between 112 PSIG and 120 PSIG; the Instrument Air Dryer skids are auto bypassed at 95 PSIG.
B.
Backup air compressor starts at 105 PSIG; Station Air to Instrument Air backup opens when air dryers are bypassed.
'
C.
When air pressure reaches 125 PSIG in the Station Air (SA) receiver, the unloader valve opens causing pressure between the air compressor separator and the compressor to equalize.
D.
Station air provides a backup source for instmment air via an interface valve which opens to supply air to the dryer inlet downstream ofIA Receiver.
ANSWER A.
The Instrument Air compressors cycle between 112 PSIG and 120 PSIG; the Instlument Air Dryer skids are auto bypassed at 95 PSIG.
COMMENTS Page 63 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 64 QUESTION ID:
1795
.A STATUS:
Approved 1AST USED DESCRIPTION:
SUV EXilAUST MODE AUTilOR:
WA!!
REVISION O
REVISION DATE 7/18/91 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 i
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/2996 l
TYPE:
MULTIPLE Cl101CE TIME:
POINTS:
I QUIZ ONLY:
Closed REFERENCE:
OPEN REFERENCE
$PECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CAR CATEGORY:
SYSTEM SBV llRA REFERENCE:
REVislON:
CilANGE:
DATE:
NRC KA NUMBER:
OBJELTIVE 3.5-103.Kl.03 3. I '
3.S *
W 3 LP4PS-SBV00
QUESTION Which of the following occurs when Shield Building Ventilation shifts to the EXHAUST mode.
A.
The in-service Containment Atmosphere Release (CAR) Exhaust fans START.
B.
The in-selvice Containment Atmosphere Release (CAR) Exhaust fans STOP.
C.
The in-service Containment Atmosphere Release (CAR) Exhaust fans go to RECIRCULATION mode.
D.
The in-service Containment Atmosphere Release (CAR) Supply fans go to RECIRCULATION mode.
ANSWER B.
The in-service Containment Atmosphere Release (CAR) Exhaust fans STOP.
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COMMENTS l
Page 64 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 65 QUESTION ID.
3290-A STATUS:
Approved LAST USED DESCRIPTION:
following cea misalignment we wait for two hours for clad relaxation AUTIIOR:
tmccoal REVISION
REVISION DATE 6/30/94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
trnccool VERIFICATION DATE:
6/30,94 TYPE:
Multiple choice TIME:
POLNTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPO CATEGORY:
Procedure REFERENCE:
REVISION:
CllANCE:
DATE:
OP-901 102
O!
9/22,95 NRC KA NUMBER:
OBJECrIVE 4.2 AS AK3.05 3.4
W-3-LP-OPS-PPolo
QUESTION
-
Following a CEA or CEDMCS malfunction in which the CEA was misaligned greater than 19 inches, the off-normal procedure directs you to liold reactor power constant for after CEA alignment for A. 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, xenon redistribution B.
I hour, radial peaking C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, clad relaxation D. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, isotopic iodine analysis ANSWER C. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, clad relaxation COMMENTS Page 65 of 100
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Waterford 3 Examination Question
,
i Examination Bank Excmination Question Number 66 QUESTION ID:
4109-A STATUS:
Approved LAST USED
)
DESCRIPTION:
Abihty to determme irsingle phase natural circulation enteria is satisfied AUTHOR:
avest REVISION O
REVISION DATE 6/25/96 APPROVAL tbrown APPROVAL DATE:
7/556 REFERENCE VERIFIED:
avest VERIFICATION DATE:
6/25/96 TYPE:
Multiple Choice TIME:
$
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPII;IAL REFERENCES:
SIMULATOR SETUP PIAvr SYSTEM:
PPE CATEGORY:
PROCEDURE RCS REFERENCE:
REVISION:
CHANGE:
DATE:
OP-90M05
00 12/1/95 NRC KA NUMBER:
OBJECrIVE 4.2-A15/17-AAl.21 4.4 4.5 W-3-LP-OPS-PPE05
QUESTION A Loss of Offsite Power has occurred. Plant conditions are as follows:
The Reactor is in Mode 3 CET temperature is 598 F RCS pressure is 1900 psia and slowly S/G 1 & 2 levels are 55% WR and slowly rising rising
,
Tc is 550 F and constant Th is 585 F and slowly lowering All of the following conditions meet the criteria for single phase natural circulation in accordance with OP-902-005, Loss of Offsite Power / Station Blackout Recovery Procedure with the exception of:
A. Te temperature trend B. Th temperature trend C. Subcooled Margin D. Th-CET differential temperature ANSWER D. Th-CET differential temperature COMMENTS Page 66 of 100
l Waterford 3 Examination Question Examination Bank Excmination Question Number 67 QUESTION ID:
3312-A STATUS:
Approved LAST USED DESCRIPTION:
Emergency boration entry requirements AUTilOR:
tmccool REVISION
REVISION DATE 7/13 S 4 APPROVAL:
tbrowr.
APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
7/13S4 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPO CATEGORY:
Procedure REFERENCE:
REVISION:
CHANCE:
DATE:
OP-901 103
01 9/22/95 NRC KA NUMBER:
OBJECrIVE 4.2 A24-AK3.01 4.1 4.4 W-3-LP-OPS-PPO10
QUESTION Which of the following conditions requires emergency boration per OP-901-103, " Emergency Boration"?
A. Reg Group 6 CEA positioned just below the Pre-Power Dependent Insertion Limit.
B. During ' refueling Kefris equal to 0.95.
C. Shutdown margin is 2.1% delta k/k with Tavg at 195 degrees F.
D. A main steam line safety valve sticks full open and will NOT reclose with the reactor at 1% power.
ANSWER D. A main steam line safety valve sticks full open and will NOT reclose with the reactor at 1% power.
I COMMENTS
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Waterford 3 Examination Question Examination Bank Examination Question Number 68 QUESTION ID:
4121
.A STATUS:
Approved LAST USED DESCRIPTION:
Causes of CCW surge tank level rise AUTilOR:
bmather REVISION I
REVISION DATE 6/29 S6 APPROVAL:
thrown APPROVAL DATE:
7/5S6
'
REFERENCE VERIFIED:
hmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENLI SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CC CATEGORY:
SYSTEM REFERENCE:
REVISION:
CilANGE:
DATE:
OP-901510
00 9 @ 93 NRC KA NUMBER:
OBJECTIVE 4 2-A26-AA2.01 2.9 3.3 W 3-LP-OPS-CC00
W-3-LP-OPS PPO50
QUESTION
_
The plant is at normal opmting temperature and pressure when the Component Cooling Water Surge Tank level stalts increasing. Select s b ch of the following components could be causing this level increase. (Assume normal equipment conditions)
A. Spent fuel pool hea; exchanger i
B. RCP seal cooler heat exciegar C. Waste Gas compressor D. Essential Chiller A ANSWER B. RCP seal cooler heat exchanger
.
COMMENTS
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Page 68 of 100
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P Waterford 3 Examination Question Examination Bank
Enmination Question Number 69
'
QUESTION ID:
3190
.A STATUS:
Approved LAST USED DE5CRIPTION:
PPCS channel failure i
AUTilOR:
RJC REVISION
REVISION DATE 12S 9 3 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Muhiple Choice TIME:
POINTS:
,
}
QUlz ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PLC CATEGORY:
PROCEDURE
!
PPO SYSTEM
)
l PPC REFERENCE:
REVISION:
CIIANGE:
DATE:
,
OP-901 120
00 10/2193 NRC KA NUMBER:
')SJECrIVE 4 2 A27-AA2.16 3.6 3.9 W-3 LP-OPS-PPO10
l QUESTION i
i i
Given the following plant conditions.
Pressurizer Level Control Channel Selector is positioned to Channel "Y"
'
j Pressurizer low level Heater Cutout Channel Selector is positioned to BOTH.
,
i All Pressurizer Heaters are on for Boron Equalization.
Which of the following describes the status of the Pressurizer Heaters if Pressurizer level Channel "X" fails low?
,
A. All Pressurizer Heaters remain energized.
.
B. All Pressurizer Heaters will de-energize.
C. All Backup Heaters de-energize, all Proportional Heaters remain energized I
D. All Pressurizer Heaters de-energize except Train B powered Heaters.
!
ANSWER
B. All Pressurizer Heaters will de-energize.
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COMMENTS
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Waterford 3 Examination Question Examination Bank Examination Question Number 70 QUESTION ID 4122-A STATUS:
Approved LAST USED
'
DESCRIFrION:
thsis fw slow EFW flow initiation to SGs AUTIIOR:
bmather REVISION
REVISION DATE 6/29'96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POINTS:
1 QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
EFW CATEGORY:
PROCEDURE
.
REVISION:
CilANGE:
DATE:
OP-902 002
00 12/1/95 OP-902 008
00 12/1/95 OP-902407
00 12/1/95 OP-902 006
00 12/1/95 OP 902 005
00 12/195 OP 902404
00 12/1/95 NRC KA NUMBER:
OBJECTIVE 4.2-A40-AK3.04 4.5 4.7 W-3-LP-OPS-PPE06
QUESTION
,
After a loss of feedwater event an EFW pump is placed in service with SGI level at 22% NR and SG2 level at 20% NR. Why should feed flow be initiated slowly to the steam generators?
'
A. To limit the possibility of feed ring damage when SG level is below the feed ring.
B. To minimize the difTerential temperature across the tube bundle wrapper.
C. To limit the RCS cool down resulting from restoration of feedwater from the CSP.
'
D. To minimize the thermal shock to the SG tubes when feedwater is restored.
ANSWER A. To limit the possibility of feed ring damage when SG level is below the feed ring.
COMMENTS
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Page 70 of 100
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Waterford 3 Examination Question Examination Bank Exonination Question Number 71 QUESTION ID:
4123-A STATUS:
Approved LAST USED DESCRIPTION:
Operator concern on MSLil with SO dryout AUTi!OR:
brnather REVISION
REVISION DATE 6/29S6 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERf.NCE VERIFIED:
bmather VERIFICATION DATE:
6/2936 TYPE:
Multiple Choice TINIE:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIhlULATOR SETUP PLANT SYSTESt; PPE CATEGORY:
REFERENCE:
REVISION:
CilANGE:
DATE:
- OP-903-004
00 12/1/95 NRC KA NUMBER:
OILIECTIVE 4.3-A40-AKl.01 4.1 4.4 W-3-LP-OPS-PPE04
QUESTION
...
Which of the following reflects the primary concern of the operators after a major steam line break upstream of the MSIV in which the affected SG blows dry.
,
A. Ensure the RCS reheats back to normal operating temperature within Tech Spec heatup limits
,
,
B. Maintain subcooling margin between 28 F and 200 F C. Energize all pressurizer heaters to re-establish saturated conditions in the pressurizer D. Re-establish all safety injection flow ANSWER
B. Maintain subcooling margin between 28 F and 200 F
4 COMMENTS Page 71 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 72 QUESTION ID:
2348 A
STATUS:
Approved LAST f rSED DESCRIFrION:
System alarm setpoints AlfrHOR:
MJESSE REVISION I
REVISION DATE 8/3/94 APPROVAL:
thrown APPROVAL DATE:
7/5,96 REFERENCE VERIFIED:
MJESsE VERIFICATION DATE:
8/3S4 TYPE:
MULTIPLE CllOICE TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
.E CATEGORY:
Procedure
System REFERENCE:
REVISION:
CIIANCE:
DATE:
OP 500-005
01 4/16/94 NRC KA NUMBER:
OBJECrIVE 055C33 A2.04 W 3-LP-OPS-AE00
4.3-A51 AA2.02 3.9 4.1 W 3-LP-OPS-PPO20
QUESTION During a loss of condenser vacuum event, the following annunciators are received: FWPT A VACUUM LO and FWPT B VACUUM LO. Prior to these alarms what other alarms should have been received?
A.
VACUUM PUMP - TRIPfrROUBLE B.
STM BYPASS SYSTEM CNDSR VACUUM FAIL C.
TURBINE TRIP VACUUM LOST D.
FWPT - TRIP VACUUM LO ANSWER C.
TURBINE TRIP VACUUM LOST COMMENTS
Page 72 of 100
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d Waterford 3 Examination Question
Examination Bank Examination Question Number 73
'
QUESTION !D 2469
.A STATUS:
Approved LAST USED DESCRIPTION:
Why place CS switch to offin 005 case 11 AUTilOR:
RWF REVislON
REVISION DATE 12/21/93
.
APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
11/18S 4 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
,
SPECIAL REFERENCES:
SIMULATOR SETUP
,
PLANT SYSTEM:
PPE CATEGORY:
PROCEDURE'
REFERENCE:
REVISION:
CIIANGE:
DATE:
OP-9024X)5
00 12/1/95 NRC KA NUMBER:
OILIEcrIVE 4.1 E55-EK3.02
46 W 3-LP-OPS-PPE05
QUESTION During a station blackout, the Loss of Offsite Power / Station Blackout Recovery Procedure (OP-902-005) directs the Operator to place the Containment Spray Pump control switches to OFF.
Which of the following describes the reason for this step?
A.
To prevent overloading the Emergency Diesel Generators when restored.
B.
To prevent initiating Containment Spray when electrical power is restored.
C.
To prevent starting the Containment Spray Pumps with no seal cooling aller power is restored.
D.
To protect the Containment Spray Pumps from the effects ofloss of DC control power ifbattery chargers cannot be restored.
i ANSWER B.
To prevent initiating Containment Spray when electrical power is restored.
COMMENTS Page 73 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 74 QUESTION ID.
3316
.A STATUS:
Approved LAST USED DESCRIFr!ON:
which trip breakers open on loss of sups SMD (RO NRC EXAM 1994)
AUTIIOR:
tmccool REVISION I
REVISION DATE 7/13/94 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
tmccool VERIFICATION DATE:
7/13/94 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPO CATEGORY:
Procedure REFERENCE:
REVISION:
CIIANGE:
DATE:
OP 901312
00 4/30/93 NRC KA NUMBER:
OBJECTITE 4.2-A57 AA2.19
4.3 W-3-LP-OPS-CED00
W-3-LP4PS-PPO30
QUESTION l
Which of the following Reactor Trip Breakers would indicate open on a loss of vital instrument bus SUPS MD7 A. Breakers 1,2,3,4 B. Breakers 5,6,7,8 C. Breakers 1,2,5,6 D. Breakers 3,4,7,8 ANSWER D. Breakers 3,4,7,8 COMMENTS Page 74 of 100
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i Waterford 3 Examination Question Examination Bank Examination Question Number 75 i
QUESTION ID.
4108
.A STATUS:
Approved IAST USED
'
DESCRIPTION:
Fire Declaratmn AUTIIOR:
bmather REVISION l
REVISION DATE 6/25/96 APPROVAL:
thrown APPROVAL DATE:
7/$S6 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/25S 6 TYPE:
Muhiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
FPD CATEGORY:
SYSTEM FPP REFERENCE:
REVISION:
CilANGE:
DATE:
FP-001420 to
2/22/96 NRC KA NUMBER:
OBJECrIVE 4.2-AG7-AK3.02 2.5
W.3.LP-OPS PP00
QUESTION Immediately upon confirmation of a fire alarm the Nuclear Plant Operator is responsible for all of the following actions except:
A. Making preliminary reportability verification B. Sounding the fire alarm and announcing the fire over plant page C. Obtaining pertinent information from the person confirming the alarm D. Ensure the SS/CRS is notified ANSWER A. Making preliminary reportability verification COMMENTS Page 75 of 100
Waterford 3 Examination Question Examination Bank Esamination Question Number 76 QUESTION ID.
-A STATUS:
Approved LAST USED DESCRIPTION:
Evacuation of CR and Subsequent Plant Shutdown, reliable instrumentation AUTIIOR:
shymel REVISION
REVISION DATE 7/7<94 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
shymel VERIFICATION DATE:
7/7.94 TYPE:
Mll.TIPLE CliO!CE TISIE:
PolNTS:
QUIZ ONIN:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PIANT SYSTEM:
PPO CATEGORY:
Procedure REFERENCE:
REVISION:
CIIANGE:
DATE:
OP 901502
00 5/10S 5 NRC KA NUMBER:
OIUECTIVE 4.2 A6ll-AAl.12 4.4 4.4 W 3-LP-ops-PPO51
QUESTION If a fire in the +35 Cable Spreading Room burns for 45 minutes before it is extinguished, which of the following will still be a reliable indication for RCS pressure?
A.
Safety Channel B Wide Range Pressurizer Pressure B.
Safety Channel D Narrow Range Pressurizer Pressure C.
Hot Leg 1 Pressure D.
Pressurizer Pressure Controller ANSWER C.
Hot Leg 1 Pressure COMMENTS
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Waterford 3 Examination Question Examination Bank Examination Question Number 77 QUESTION ID:
4124-A STATUS:
Approved LAST USED DESCRIPTION:
Emergency Boration during CR evacuation AUTHOR:
bmather REVISION
REVISION DATE 6/29/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
brnather VERIFICATION DATE:
6/2956 TYPE:
Multiple Choice TIME:
POINTS:
1 QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPO CATEGORY:
REFERENCE:
REVISION:
CllANGE:
DATE:
OP-901502
00 5/1035 NBC KA NUMBER:
OBJECTIVE 4.2-A68-AK3.18 4.2 4.5 W-3-LP-OPS-PPO51
QUESTION Why is emergency boration required when the reactor is tripped from outside the control room following a Control Room Evacuation?
A. The MSR temperature control valve logic cannot be reset from outside the control room.
B. The Main Turbine will not trip when the reactor is tripped outside the control room.
C. The operator is unable to verify CEA position following a trip from outside the coritrol room.
D. The Feedwater Control System will not shift to the RTO mode when the reactor is tripped from outside the control room ANSWER C. The operator is unable to verify CEA position following a trip from outside the comrol room.
COMMENTS l
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Waterford 3 Examination Question Examination Bank Examination Question Number 78 QUESTION ID:
2299-A STATUS.
Approved LAST USED j
DESCRIPTION:
Action to ensure containment integrity AUTHOR:
bmather REVISION
REVISION DATE 6/29/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96
,
REFERENCE VERIFIED:
brnather VERIFICATION DATE:
6/29/96 TYPE:
MULTIPLE Cllo!CE TIME:
POINTS:
I QUIS ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CB CATEGORY:
TS REFERENCE:
REVISION:
CHANGE:
DATE:
OBJECTIVE 4.2.A69 AA2.02 3.9 4.4 W-3-LP-OPS-CB00 5,6 QUESTION During Irradiated fuel movement within containment, it is reported that the Equipment Hatch Door is held in place by three(3) bolts. Which of the following actions should be taken.
A.
Suspend Core Alterations or irradiated fuel movement in containment if LLRT test results are not satisfactory.
B.
Immediately suspend Core Alterations or irradiated fuel movement within containment.
C.
Within I hour restore the Equipment Door to operable status or suspend Core Alterations and irradiated fuel movement within containment.
D.
Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> restore the Equipment Door to Operable Status or suspend Core Alterations or irradiated fuel movement within containment.
ANSWER B.
Immediately suspend Core Alterations or irradiated fuel movement within containment.
COMMENTS Page 78 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 79 QUESTION ID:
4134-A STATUS:
Approved LAST USED DESCRIPTION:
Derinition of a subcooled liquid AUTIIOR:
bmather REVISION I
REVISION DATE 7/5/96 APPROVAL:
thrown APPROVAL DATE:
7/5S6 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/5S6 TYPE:
Muhiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
TYll CATEGORY:
REFERENCE:
REVISION:
CilANCE:
DATE:
NRC KA NUMBER:
OBJECTIVE 4.1-E74-EK l.08 2.8 3.1 W-3 LP-OPS-TYl103
QUESTION A heat addition to a fluid with a quality of 0% results in a temperature increase with no phase change. What was the condition of the fluid prior to the heat addition? (assume pressure of the fluid is held constant)
<
A. Subcooled liquid B. Saturated liquid C. Wet vapor D. Saturated vapor ANSWER A. Subcooledliquid COMMENTS I
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Waterford 3 Examination Question Examination Bank Examination Question Number 80 QUESTION ID:
4125
.A STATUS:
Approved LAST USED
=
DESCR!! TION:
Chemistry dept. responsibilities for high RCS activity ALTIIOR:
bmather REVISION I
REVISION DATE 6/29/96 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29 S 6 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPSN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PL ANT SYSTEM:
PPO CATEGORY:
PROCEDURE RCS REFERENCE:
REVISION:
CilANCE:
DATE:
OP.901410
00 4/16/93 NRC KA NUMBER:
OBJECTIVE 4.2-A76-AK3.06 3.2 3.8 W 3-LP-OPS-PPO40
QUESTION All of the following items are sampled and analyzed by the W-3 Chemistry Department when OP-901-410, High Activity in Reactor Coolant System is implemented with the exception of:
A. Cesium Concentration B. Dose Equivalent Iodine Concentration C. Dose Equivalent Iodine isotopic analysis D. Gross RCS activity ANSWER A. Cesium Concentration
{
COMMENTS Page 80 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 81 QUESTION ID.
4110-A STATUS:
Approved IAST USED DESCRIITION:
Continuous Rod Withdrawal actions
AUTilOR:
bmather REVISION I
REVISION DATE '
6/25.96 APPROVAL:
thrown APPROVAL DATE:
7/596 REFERENCE VERIFIED:
bmather VERIFICATION :DATE:
6/2596 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP l
'
PIANT SYSTEM:
ced CATEGORY:
PROCEDURE
)
SYSTEM
,
'
REFERENCE:
REVISION:
CIIANGE:
DATE:
i OP-901 IO2
01 9/22.95 NRC KA NUMBER:
OILIECTIVE 4.2 Al AAl.01 3.5 3.2 W 3-LP-OPS-PPolo
QUESTION
i Regulating Group 6 CEAs are being withdrawn from 120" in an attempt to maintain ASI constant. When the shim switch is released Regulating Group 6 continues to move outward. When the mode select switch is taken
i to "OFF" motion stops. What actions should be taken?
A. Trip the reactor and go to OP-902-000
,
B. If uncontrolled movement does not occur aller the mode switch is removed from "OFF" borate CEAs to fully withdrawn position C. If continuous movement occurs after the mode select switch is removed from "OFF" then trip the reactor D. Declare group 6 inoperable and commence a plant downpower using part length rods for ASI control ANSWER
C. If continuous movement occurs after the mode select switch is removed from off then trip the reactor
,
.
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COMMENTS i;
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Waterford 3 Examination Question
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Examination Bank Examination Question Number 82 QUEFrION ID; 4129-A STATUS:
Approved LAST USED DESCRIPTION:
Required time for downpower aAer a dropped CEA AUTilOR:
bmather REVISION I
REVISION DATE 7/2/96
.
APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/2/96
TYPE:
Multiple Choice TIME:
POINTS:
I j
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
X SIMULATOR SETUP PLANT SYSTEM:
CED CATEGORY:
PROCEDURE TS PPO
,
$
REFERENCE:
REVIS10N:
CilANGE:
DATE'
'
01 9/22/95 NRC KA NUMBER:
OBJECrIVE
-
42-A3 AK3.04 3.8'
4. I '
W-3-LPOPS-PPO10
QUESTION While at 80% power, a shutdown bank CEA drops into the core. In accordance with the Tech Spec COLR, a downpower must be completed within minutes to a maximum power level of
A. 15, 60%
.
f B. 30,70%
l
~
C. 45,60%
,
D. 60,70%
ANSWER
'
s l
C. 45,60%
i i
i COMMENTS
,
Provide COLR Fig 2 " Required Power Reduction After Single CEA Deviation"
,
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Page 82 of 100
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-...... -
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l Waterford 3 Examination Question Examination Bank i
Examination Question Number 83 QUESTION II)
1789-A STATUS:
Approved LAST USED DEM'RIPTION:
DRTS ActuationIegic AUTilOR:
bmather REVISION
REVISION DATE 7/23 S 5
APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/2195 TYPE:
MULTIPLE CllOICE TIN 1E:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SINIULATOR SETUP PIANT SYSTEM:
ATS CATEGORY:
REFFRENCE:
REVISION:
CilANGE:
DATE:
)
NRC KA NUMBER:
OIMECTIVE 4.1-E7 EA2.04
4.6 W-3-LP-OPS ATS00
i 000007.EA2.02 QUESTION Which of the following best describes the Diversified Reactor Trip system (DRTS), assuming DRTS enabled.
A.
Must push both DRTS push buttons together, at the same time, to manually actuate.
B.
Auto actuation requires 2/2 pressurizer safety grade pressures at 2340 psig.
i C.
Can be manually initiated locally at the Reactor Trip Switchgear (+21 RAB)
j i
D.
Could actuate with failure of one pressure transmitter high and pressing one manual pushbutton.
ANSWER D.
Could actuate with failure of one pressure transmitter high and pressing one manual pushbutton.
COMMENTS Page 83 of 100
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t Waterford 3 Examination Question Examination Bank l
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ExCmination Question Number 84 QUESTION !D:
4135
.A STATUS:
Approved LAST USED DESCRIITION:
Safety injection termination criteria AUTilOR:
bmather REVISION
REVISION DATE 7/5/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/5/96 TYPE:
Multiple Choice TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPE CATEGORY:
SYSTEM REFERENCE:
REVISION:
CIIANCE:
DATE:
OP-902 002
00 12/1/95
- NRC KA NUMBER:
OBJECTIVE 4.1 E9-EK3 21 4.2 4.5 W-3-LP OPS-PPE02
i QUESTION I
l All of the following allow termination of Safety Injection after a small break LOCA except?
l A. Subcooled margin 50 F B. Pzr Level 35% and dropping slowly C. RVLMS level 5 not voided l
!
ANSWER B. Pzr Level 35% and dropping slowly COMMENTS l
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Waterford 3 Examination Question
'
Examination Bank Examination Question Number 85
QUESTION ID:
A STATUS:
Approved LAST USED l
DESCRIPTION:
LPS! flow requirements following LB-LOCA i
AUTHOR:
RJC REVISION
REVISION DATE 2,1364 APPROVAL:
thrown APPROVAL DATE:
715/9 6 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/2936 TYPE:
MULTIPLE CHOICE TIME:
POINTS:
'
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPE CATEGORY:
,
'
REFERENCE:
REVISION:
CIIANGE:
DATE:
OP.903402
00 12/1/95
,
NRC KA NtJMBER:
OBJECTIVE
<
006000.K6.03 W.3.LP4PS-PPE02
4.1 Ell.EK3.05 4.0*
4.1
{
QUESTION Select the Combination of Reactor Coolant System pressure and Low Pressure Safety Injection Train A flow that
would be acceptable during the injection phase of a large LOCA.
A.
175 psia 500 gpm B.
125 psia 2500 gpm
,
i
C.
100 psia 2800 gpm D.
50 psia 3600 gpm ANSWER B.
125 psia 2500 gpm COMMENTS Provide attachment 6 of OP-902-ATT Page 85 of 100
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i Waterford 3 Examination Question
'
Examination Bank Examination Question Number 86 QUES ~ TION ID:
1988-A STATUS:
Approved LAST USED
DESCRIFTION:
Diagnose problem with Natural cire flow following LOCA
,
AUTIlOR:
AV REVISION O
REVISION DATE 8/2/91 APPROVAL:
throati APPROVAL DATE:
7/5S6 l
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96
TYPE:
MULTIPLE CllOICE TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
PPE CATEGORY:
PROCEDURE i
REFERENCE:
REVISION:
CllANGE:
DATE:
OP-903402
00 12/1/95
,
NRC KA NUMBER:
OBJECTIVE 000009.EA2.37 W-3.LP-OPS-PPE02
4.1 Ell EA2.09 4.2 4.3
,
QUESTION Following a LOCA, Reactor Coolant Pumps were secured. Which of the following conditions would indicate a problem with natural circulation flow after flow had been established?
A.
Steam Generator pressures are rising B.
PRESSURIZER level is 18% and slowly lowering C.
RCS sub cooling is 30 F and constant i
D.
FCS loop delta temperature is 50 F and lowering ANSWER A.
Steam Generator pressures are rising COMMENTS Page 86 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 87 QUESTION ID:
2911-
-A STATUS:
Approved IAST USED DESCRIFrION:
Actions ror charging purnp trips
'
AUTIIOR:
ANV REVISION
REVISION DATE 12/29/92 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
binather VERIFICATION DATE:
6/29/96 TYPE:
MULTIPLE CllOICE TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP
-
PIANT SYSTEM:
CVC CATEGORY:
PROCEDURE PPO REFERENCE:
REVISION:
CHANGE:
DATE:
OP 901-ll2
00 9/22/95
' NRC KA NUMBER:
OlWECr!VE 4.3-A33-AA2.02 3.2 3.7 W-3-LP-OPS-PPolo
4.3-A23-AA1.02
2.9 4.3-A22 AK3.02 3.5 3.8
QUESTION While operating at power, significant current oscillations (100 amps) are observed on 480V bus 3B31-S.
Annunciator " CHARGING PUMP HEADER FLOW LOW" actuates and shortly thereafter, Charging Pump B
.
trips on overcurrent. Which of the following actions should be taken?
A.
Start an alternate charging pump after verifying its suction path.
B.
Restart Charging Pump B after resetting the overcurrent trip.
C.
Secure letdown and initiate an investigation for the loss of Charging Pump B.
D.
Secure letdown, start an alternate charging pump, then restore letdown.
ANSWER A.
Start an alternate charging pump after verifying its suction path.
COMMENTS
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Page 87 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 88 QlIEKrION ID:
3199-A STATUS:
Approved LAST USED DESCRIPTION:
RCS reduced inventory AUTilOR:
RJC REVISION
REVISION DATE 12'30.93 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POINTS:
I QUlz ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMUIATOR SETUP PLANT SYSTEM:
PPo CATEGORY:
REVISION:
CilANCE:
DATE:
OP-001003
01 7/2396 oP-901 131
00 3/23,93 NRC KA NUMBER:
OBJECTIVE 4.2-A25-AA102 3.8 3.9 W-3-LP-OPS-REQ 22
. QUESTION Which of the following describes the reason for the requirement to have a Hot Leg vent path for a loss of shutdown cooling when SG nozzle dams are installed?
A.
To prevent steam formation in the Hot Leg from causing an erroneously high Reactor Vessel level indication.
B.
To prevent steam formation in the Reactor Vessel head from pressurizing the RCS, leading to core uncovery.
C.
To prevent steam formation in the Hot Leg which will ultimately collapse, causing severe water hammer.
D.
To prevent the loss of RCS inventory caused by lifting a Low Temperature Overpressure Protection (LTOP) relief valve.
ANSWER B.
To prevent steam formation in the Reactor Vessel head from pressurizing the RCS, leading to core uncovery.
COMMENTS Page 88 of 100
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Waterford 3 Examination Question Examination Bank Excmination Question Number 89 Qt'ESTION ID:
4130-A STATUS:
Approved LAST USED DESCRII" TION:
Time to reach 200 degrees after SDC Malfunction AUTilOR:
avest REVISION
REVISION DATE 7/2/96 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
avest VERIFICATION DATE:
7/2/96 TYPE:
Multiple Choice TIME:
POINTS:
I
' QUIZ ONLY:
CLOSED REFERENCE:
OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP i
PLANT SYSTEM:
PPO CATEGORY:
PROCEDURE
SDC REFERENCE:
REVISION:
CIIANGE:
DATE:
OP.901 131
00 3/23/93 NRC KA NUMBER:
OBJECTIVE 4.3-A25-AKI.01 3.9 4.3 W-3-LP-OPS-REQ 21
QUESTION The plant is shutdown and drained to mid-loop for replacing Reactor Cooling Pump seals. The time of shutdown
{
was 8/31/96 0300. At 0300 on 9/10/96 LPSI Pump A is secured due to cavitation of the pump. LPSI Pump B is started and trips. Estimate the time to reach 200 F ifinitial RCS temperature was 100 F.
A.15 Minutes B. 20 Minutes C. 25 Minutes D. 30 Minutes ANSWER -
C. ?? Minutes COMh. 5 N TS
-
Provide attachment 2 from OP-901-131
,
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l Waterford 3 Examination Question
Examination Bank Eximination Question Number 90 QUESTION ID-1704-A STATUS:
Approved LAST USED DESCRIPTION:
Resettmg 32 bus breakers AUTilOR:
RC REVISION O
REVISION DATE 7/15/91 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 a
TYPE:
MULTIPLE CIIO!CE TIME:
POINTS:
QUIZONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
CED CATEGORY:
SYSTEM REFr.RENCE:
REVISION:
CilANGE:
DATE:
OP-902-000
00 12/1/95 J
NRC KA NUMBER:
OILIECrIVE 4,1-E29-EK3.12 4.4 4.7 W 3-LP-OPS-PPE01
QUESTION OP-902-000, Step 1 Contingency Action directs the operator to open the feeder breakers to 480 VAC busses
-
3 A32 and 3B32 for 5 seconds and then reclose them. The purpose of reclosing the feeder breakers is to.
.
i A.
Restore power to the CEDMCS in order to verify that all CEAs have fully inserted.
B.
Re-energize the A32 and B32 busses before the under voltage relays strip the individualloads from the busses.
.
C Restore power to the Pressurizer proportional heaters only.
D.
Restore power to all the Pressurizer heaters.
ANSWER D.
Restore power to all the Pressurizer heaters.
COMMENTS
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Excmination Question Number 91 QUESTION ID:
1279-A STATUS:
Approved LAST USED
,
DESCRIPTION:
PRM automatic actions AUTilOR:
MJESSE REVISION I
REVISION DATE 8/3/94 i
APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
MJESSE VERIFICATION DATE:
8/3/94
$
TYPE:
Muhiple Choice TIME:
$
POINTS:
I l
QUIZ ONLY:
CLOSED REFERENCE:
-X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP I
PLANT SYSTEM:
AE CATEGORY:
System REFERENCE:
REVISION:
CHANGE:
DATE:
OP-003 001
02 6/14/94 OP-901202
00 4/24/95 l
,
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NRC KA NUMBER:
OBJECTIVE l
.,
. 4 2-A37 AK3.05 3.7
W-3-LP-OPS-AE00
'
4'
W 3-LP4PS-RMS00
.
QUESTION
i In order to prevent an inadvertent release of radioactive material through the Condenser Air Evacuation System
,
(AE), wide range gas monitor samples the AE exhaust. Upon receipt of a high rad alarm, the AE System:
i
{
A.
Isolates all flow from the Main Condenser
,
l B.
Initiates recirculation of the non-condensables from the separator unit to the condenser.
C.
Diverts the AE exhaust discharge to the Normal RAB HVAC exhaust filter units.
- L.
Diverts the AE exhaust to the waste gas header.
>
ANSWER
C.
Diverts the AE exhaust discharge to the Normal RAB HVAC exhaust filter units.
COMMENTS
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4 Page 91 of 100
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Waterford 3 Examination Question Examination Bank Examination Question Number 92 QUESTION ID.
1172
.- A STATUS:
Approved LAST USED DESCRIPTION:
Why greater than 779. level on SOTR events AUTIIOR:
.tmecool RFXISION I
REVISION DATE I1/18S4 APPROVAL:
tbrown APPROVAL DATE:
7/5S6 REFERENCE VERIFIED:
tmeccol VERIFICATION DATE:
11/1SS4 TYPE:
Muhiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SINIULATOR SETUP PLANT SYSTEM:
PPE CATEGORY:
REFERENCE:
REVISION:
CIIANGE:
DATE:
OP 902-007
00 12/195 NRC KA NUMBER:
OBJECTIVE 000030.EAl.44 W-3-LP-OPS PPE07
41 E38-EK3 06 4.2 4.5 QUESTION During a SGTR, the isolated SG level is maintained greater than 77% WR in order to:
A.
prevent spray through the rupture frorc depressurizing the SG B.
reduce flow impingement on other tubes C.
reduce the static head differential across the break D.
condense the steam issuing from the break ANSWER A.
prevent spray through the rupture from depressurizing the SG COMMENTS Page 92 of 100
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l Waterford 3 Examination Question j
Examination Bank Eximination Question Number 93 QUESTION ID.
4136-A STATUS:
Approved IAST USED
,
DESCRIPTION:
Depressunzation of the 50 dunng a MFLB j
AUTilOR:
bmather REVISION
REVISION DATE 7/5/96 j
A FPROVAL:
tbrown APPROVAL DATE:
7/5/96
'
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
7/5/96 TYPE'
MuMple Choice TIME:
POINTS:
I QUIZ ONLY CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP Pr (NT SYSTEM:
PPE CATEGORY:
PROCEDURE ii 'ERENCE:
REVISION:
Cl!ANGE:
DATE:
l 0.
1M06
00 12/1/95 I
NRC KA NUMBER:
OBJECTnT.
'
4 2 AS4-AKl.01 4.1 4.3 W-3-LPOPS-PPE06
!
l QUESTION l
I A Main Feedwater line break will depressurize the affected S/G and start an uncontrolled cooldown when:
A. The reactor trips on low S/G level B. The main feedwater isolation valve is closed on the affect S/G C. The feedwater line water level drops below the break location D. The S/G level drops below 50% WR level ANSWER C. The feedwater line water level drops below the break location COMMENTS
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l Page 93 of 100
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i Waterford 3 Examination Question l
Examination Bank Excmination Question Number 94 QUESTION ID:
-A STATUS:
Approved LAST USED DESCRIPTION:
EFW control setpoint
,
AUTilOR:
CAR REVISION
REVISION DATE 2/25/94
.
APPROVAL:
tbrown APPROVAL DATE:
7/536
'
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
5/235 TYPE:
MULTIPLE CllOICE TIME:
POINTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE X
SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
EFW CATEGORY:
SYSTEM REFERENCE:
REVISION:
CilANGE:
DATE:
OP 902&6
00 12!)/95 NRC KA NUMBER:
OBJECrlVE 061000 A3 0)
W.3-LP-OPS-EFWOO
4.2.A54-AA2.04 4.2 4.3
,
061 GEN.04 QUESTION
An Emergency Feedwater Actuation Signal (EFAS) has been initiated due to low level in both Steam Generators.
Steam Generator 1 & 2 levels are below Critical Level.
Select the level band that the Emergency Feedwater System will automatically maintain?
A.
68 - 71% NR
B.
68 - 71% WR
'
C.
55 - 71% NR D,
55 - 71% WR
ANSWER
i B.
68 - 71% WR COMMENTS Page 94 of 100
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Waterford 3 Examination Question l
Examination Bank Excznination Question Number 95 QUESTION ID:
4126-A STATUS:
Approved LAST USED DESCRIPTION:
Shed DC loads after a LOOP wnh failure of both EDGs to start AUTHOR:
bmather REVISION
REVISION DATE 6/29 S 6 APPROVAL:
tbrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POLNTS:
I QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
DC CATEGORY:
PROCEDURE l
l PPE REFERENCE:
REVISION:
CIIANGE:
DATE:
OP-902 005
00 12/1/95 NRC KA NUMBER:
OIMECTIVE 4 2 AS8 AA2 03 3.5 3.9 W-3-LP4Ps PPE05
QUESTION A total loss of offsite power has occurred and both Emergency Diesel Generators have failed to stan automatically or manually. Which of the following statements describes how long the operator has to shed specific DC Safety bus loads?
A. Within 15 minutes B. Within 30 minutes C. Within 45 minutes D. Within 60 minutes ANSWER B. Within 30 minutes COMMENTS Page 95 of 100
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i Waterford 3 Examination Question
Examination Bank Examination Question Number 96 QUESTION ID:
2361
.A b. ATUS:
Approved IAST USED DESCRIPTION:
Procedural requirements for ducharging a BAcT AUTIIOR:
DM REVISION O
REVISION DATE 11/7/91
,
APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
beoble VERIFICATION DATE:
7/31/95
i TYPE:
MULTIPLE CHOICE TIME:
POINTS:
j
- QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
BM CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CilANCE:
DATE:
OP C37 001
01 8/1/96 NRC KA NUMBER:
OBJECTIVE 4.2 A59-AK3.01 3.5 3.9 W-3-LP-ops-BM00
QUESTION
,
All of the following are allowed by procedure except:
A.
Discharging one Boric Acid Condensate Tank while filling another.
B.
Discharging a Boric Acid Condensate Tank to the PWST.
C.
Recircing one Boric Acid Condensate Tank while discharging another.
D.
Recircing one Boric Acid Condensate Tank while filling another.
ANSWER C.
Recircing one Boric Acid Condensate Tank while discharging another.
COMMENTS Page 96 of 100
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Waterford 3 Examination Question
,
Examination Bank Examination Question Number 97 QUESTION ID.
4112
.A hTATUS:
Approved LAST USED i
DEKRilTION:
Containment Purge Morutor setpoints
'
AUTIIOR:
bmather REVISION
REVISION DATE 6/26/96
. APPROVAL:
tbrown APPROVAL DATE:
7/5/96
,
REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/26/96 TYPE:
Multiple Choice TIME:
POINTS:
'
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP j
PLANT SYSTEM:
arm CATEGORY:
PROCEDURE l
REFERENCE:
REVISION:
CIIANCE:
DATE:
OP 903-001
06 7/29/96 TS 3.3.3 NRC KA NUMBER:
OBJEC. IVE T
4.2-AGI-AA2.03
3.3 W-3 LP-OPS-liVR00
QUESTION After evaluation of the current activity readings how many of the following Containment Atmosphere Purge monitors high alarm setpoints should be set at 40 mr/hr?
,
.
ARM-IRE-5024S 1.17 E+2 mr/hr ARM-IRE-5025S 1.75 E+1 mr/hr ARM-IRE-5026S 2.25 E+1 mr/hr ARM-IRE-5027S 3.50 E0 mr/hr
,
A. 1
.
B. 2
i C. 3
D. 4 ANSWER B. 2 i
COMMENTS
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Page 97 of 100
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Waterford 3 Examination Question Examination Bank i
Examination Question Number 98 QUESTION ID:
3453
.A STATUS:
Approved LAST USED
!
DESCRIPTION:
Thc4 fails high AUTilOR:
bms'br REVISION
REVISION DATE 6/2996 APPROVAL:
tbrov.n APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29,96 TYPE:
Muhiple Choice TIME:
POINTS:
QUIZ ONLY:
CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYhTEM:
RR CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CllANGE:
DATE:
OP-901-ilo
00 9/22/95 NRC KA NUMBER:
OBJECTIVE 4.2-A28 AK3.05 3.7 4.1 W.3-LP OPS-PPO10
015000.Kl.06 W 3-LP-OPS-RR00
,
QUESTION
.
-,. -
]
Which ef the following actions should be performed initially if the Thot input to the Reactor Regulating bystem (RRS) fails HIGH7 i
A. Place Pn level controller to MANUAL B. Swap position of the Thot selector switch behind CP-2 C. Place Letdown Flow control valve to MANUAL D. Take backup heaters to OFF ANSWER A. Place Pzr level controller to MANUAL i
COMMENTS Page 98 of 100
Waterford 3 Examination Question Examination Bank Examination Question Number 99 QUESTION ID.
2630 A
STATUS:
Arproved LAST USED DESCRIrrlON:
evenu addrened by fuel handling incident AUTIIOR:
W All REVISION
REVISION DATE 1/31/92 APPROVAL:
tbrown APPROVAL DATE:
7/5,96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
Multiple Choice TIME:
POINTS:
QUIZ ONLY:
CI OSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERF*TES:
SIMUIATOR SETUP i
PLANT SYSTEM:
PPO CATEGORY:
PROCEDURE J
REFERENCE:
REVISION:
CHANGE:
DATE:
OP-901-405
00 1/29.93 NRC KA NUMBER:
OBJECrIVE 4.2-A36-AK3.03 3.7 4.1 W.3 LP-ops-PPO40 I
QUESTION Which of the following fuel handling events is addressed in OP-901-405, Fuel Handling Incident?
A.
A spent fuel assembly is damaged while being withdrawn from the core.
B.
A new fuel assembly cask is found with the motion sensors tripped during fuel receipt inspection.
C.
The Reactor goes critical while a fuel assembly is being inserted into the core.
D.
A CEA is hanging from the upper guide structure during removal of the upper guide structure.
ANSWER A.
A spent fuel assembly is damaged while being withdrawn from the core, COMMENTS
1 Page 99 of 100
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Waterford 3 Examination Question
'
Examination Bank Excmination Question Number 100 QUESTION ID.
2475
.A STATUS:
Approved LAhT USED DESCRIPTION:
Reactor Trip setpomt ror IA
~
AUTIIOR:
RWF REVISION
REVISION DATE 12!!7/91 APPROVAL:
thrown APPROVAL DATE:
7/5/96 REFERENCE VERIFIED:
bmather VERIFICATION DATE:
6/29/96 TYPE:
MULTIPLE CilOICE TIME:
POINTS:
QUIZ ONLY CLOSED REFERENCE:
X OPEN REFERENCE SPECIAL REFERENCES:
SIMULATOR SETUP PLANT SYSTEM:
lA CATEGORY:
PROCEDURE REFERENCE:
REVISION:
CIIANGE:
DATE:
OP-901511
01 4/5/96 NRC KA NUMBER:
OBJECTIVE 4.3-A35 AA2.06 16'
4.2 W-3-LPOPS-IA00
W.3-LP-OPS-PPO50
QUESTION A Reactor Trip is required when Instrument Air Pressure drops to:
A.
60 PSIG B.
65 PSIG C.
70 PSIG
D.
75 PSIG ANSWER B.
65 PSIG i
l COMMENTS
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i Page 100 of 100