ML20154D448
| ML20154D448 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/05/1998 |
| From: | Curley V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9810070223 | |
| Download: ML20154D448 (1) | |
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o0 68 [ /7Y NOTE T0:
NRC DOCUMENT CONTROL DESK MAIL STOP 0-5-D-24 daIf bOR
, LICENSING ASSISTANT FROM:
OPERgINGLICEN3 BRANCH _ REGION I
SUBJECT:
OPERATOR LICENSING EXAMINATION ADMINISJERED ON AnsasY 17-2I IT ?f, AT benko Valle u L DOCKSTNO.So_h/A I
ON Nanusf17-21199 f/ OPERATOR LICENSING EXAMINATIONS WERE ADMIN ATTH[ REFERENCEbFACILITY. ATTACHED YOU WILL FIND THE FOLLOWING INFORMATION FOR PROCESSING THROUGH NUDOCS AND DISTRIBUTION TO THE NRC STAFF, INCLUDING THE NRC PDR.
Item #1 a)
FACILITY SUBMITTED OUTLINE AND INITIAL EXAM SUBMITTAL DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE A070.
b)
AS GIVEN OPERATING EXAMINATION, DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE A070.
Item #2 EXAMINATION REPORT WITH THE AS GIVEN WRITTEN EXAMINATION ATTACHED, DESIGNATED FOR DISTRIBUTION UNDER RIDS CODE IE42.
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NUCLEAR REGULATORY COMMISSION 5
'l REGloNl 47$ ALLENDALE ROAD
,o'f KING oF PRUSSIA, PENNSYLVANIA 19406 1415 September 18, 1998 Mr. J. E. Cross President Generation Group Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania 15077
SUBJECT:
BEAVER VALLEY UNIT 2 SENIOR REACTOR OPERATOR INITIAL EXAMINATION REPOF'T NO. 50-334/98-301 and 50-412/98 301(OL)
Dear Mr. Cross:
This report transmits the findings of the senior reactor operator (SRO) licensing operating examination, conducted by NRC examiners, during the week of August 17-21,1998 at the Beaver Valley Unit 2 Nuclear Power Plant. The report also transmits the results of inspections performed during the week of August 3-6,1998. Based on the results, all four SRO applicants passed all portions of the examination. At the conclusion, Mr. T. Kenny discussed the preliminary findings with members of your staff.
The examination addressed areas important to public health and safety and was developed and administered under interim Revision 8 to the Examiner Standards (NUREG-1021). All portions of the examination were developed by Beaver Valley Power Station (BVPS), while the NRC provided oversight and final approval prior to it's administration. BVPS training personnel administered the, NRC-approved, written portion of the examination, while the operating portion was administered by the NRC.
Several restart and enhancement items were inspected with no adverse findings.
In accordance with 10 CFR 2.790 of t.he NRC's " Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
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l Mr. J. E. Cross 2
No reply to this letter is required, however, if you have any questions, please contact me at 610 337-5183.
Sincerely, i
gi Richard J. Conte hief Operator Licensing and Human Performance Branch Division of Reactor Safety Docket No. 50-334;50-412
Enclosure:
Initial Examination Report No. 50 334/98 301 and 50-412/98 301(OL) w/ Attachments 1 and 2 cc w/ encl; w/o Attachments 1-2:
Sushil C. Jain, Senior Vice President, Nuclear Services Group R. Brandt, Vice President, Nuclear Operations Group and Plant Manager R. LeGrand, Vice President, Operations Support Group B. Tuite, General Manager, Nuclear Operations Unit W. Kline, Manager, Nuclear Engineering Department M. Pergar, Acting Manager, Quality Services Unit S. Hobbs, Director, Safety & Licensing Department J. Macdonald, Manager, System and Performance Engineering J. A. Hultz, Manager, Projects and Support Services, FirstEnergy M. Clancy, Mayor, Shippingport, PA Commonwealth of Pennsylvania State of Ohio State of West Virginia cc w/enci and Attachments 1-2:
K. Beatty, General Manager, Nuclear Support
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Mr. J. E. Cross 3
Distribution w/enci and Attachments 1-2:
DRS Master Examination File l
PUBLIC Nuclear Safety Information Center (NSIC)
V. Curley, DRS Distribution w/ encl: w/o Attachments 1-2:
Region i Docket Room (with concurrences) 1 J. Wiggins, DRS L. Nicholson, DRS R. Conte, DRS T. Kenny, Chief Examiner, DRS l
N. Perry, DRP D. Haverkamp, DRP W. Axelson, DRA NRC Resident inspector DRS OL Facility File DRS File Distribution w/ encl: w/o Attachmen'ts 1-2 (VIA E-MAIL):
D. Brinkman, NRR R. Correia, NRR S. Bajwa, NRR W. Dean, OEDO (WMD)
R. Frahm, Jr., NRR S. Richards, OLB/NRR J. Stolz, NR3 J. Harold, NRR D. Kerns - SRI - Beaver Valley G. Wunder, NRR F. Talbot, NRR DOCDESK Inspection Program Branch, NRR (IPAS) l
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1 U. S. NUCLEAR REGULATORY COMMISSION REGION 1 Docket Nos.:
50-334 50-412 Report No.:
98 301 License No.:
NPF 73 Licensee:
Duquesne Light Company i
Facility:
Beaver Valley Unit 2 Nuclear Power Plant Location:
Shippingport, Pennsylvania Dates:
August 3-7,17-21,199B Chief Examiner:
T. Kenny, Senior Operations Engineer / Examiner Examiners:
J. D' Antonio, Operations Engineer / Examiner P. Bissett, Senior Operations Engineer / Examiner Approved By:
Richard J. Conte, Chief, Operator Licensing and Human Performance Branch Division of Reactor Safety 8
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AEGyZiGOEI- //Cff-
EXECUTIVE
SUMMARY
Beaver Valley Unit 2 Nuclear Power Plant inspection Report No. 50-412/98-301 Coerations Four Unit 2 senior reactor operator instant (SROI) candidates passed all portions of the initial license examination.
Good performance was noted during the Unit 2 examination in the area of crew communications, control board awareness, and crew briefings during the simulator portion of the operating examination. The NRC examiners observed communications to be direct, succinct, and that all crew members were kept wellinformed. Crew briefings were routinely held when time permitted. The written examination was developed at the appropriate SRO knowledge level, as were the job performance measures and follow-up questions. Several JPMs, in lieu of questions, were appropriately developed to test the knowledge level of the applicants in the administrative area of the examination.
Current operator license training is being conducted in accordance with RG 1.8 Rev. 2.
Appropriate waivers were submitted by the facility licensee and were addressed by the NRC staff.
The examiners concluded that the procedures used were complete in their technical content, were well written, and were clear and understandable for the user.
With respect to licensee restart item P-14, technical specifications surveillance scheduling, was acceptably completed.
With respect to licensee restart items P 15 and P-19, plans and procedures for the new "on-line" scheduling process appear to be in place, but the effectiveness of this procedure remains to be realized.
With respect to licensee restart items M 9 and P-16, during the shutdown, the f acility appeared to have taken adequate steps to reduce the shift workload burden due to post maintenance testing; however, the effectiveness of this process remains to be realized.
The facility developed a plan for upgrading TS training in requalification programs for licensed and nonlicensed operators, as stated in their restart plan. GET and GERT now contain TS training for all non licensed personnel and is of appropriate quality. "Just in time " training was enhanced to include training of operating crews prior to important evolutions.
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Report Details
- 1. Operations 05 Operator Training and Qualifications 05.1 Senior Reactor Ooerator Initial Examinations i
a.
SE921 The examination was prepared by Beaver Valley Power Station (BVPS) personnel in accordance with the guidelines in interim Revision 8, of NUREG-1021," Examiner Standards." The NRC examiners administered initial operating licensing portion of the examination to four Unit 2 senior reactor operator instant (SROI) candidates.
The written exam: nation was administered by the facility's training organization, b.
Observations and Findir.as The results of SRO examination for Unit 2 are summarized below:
SRO Pass / Fail Written 4/0 Operating 4/0 Overall 4/0 Overall the entire examination was well written and validated by the licensee prior to the NRC reviewing it. This was evidenced by the few changes that were required by the NRC after their review.
The written portion, job performance measures (JPMs) and simulator scenarios were developed by BVPS and their contractor in accordance with NR-1021. All individuals involved signed a security agreement once the development of the examination commenced. BVPS personnel validated the operation portions of the examination prior to their submitting it to the NRC. The NRC subsequently reviewed and observed the validation of all portions of the proposed examination.
During the examination preparation week (August 3-7,1998)the NRC examiners noted that the facility staff had performed good validation of the new simulator scenarios and JPM's, because little or no changes were required after the demonstrations.
The written portion of the examination was administered on August 17,1998,and consisted of 100 multiple choice questions. Prior to administration there were minor editorial comments noted by the NRC, that were promptly corrected by the licensee.
2 17-21,1998, The operating portion of the examination was conducted from August All JPMs were followed and consisted of four simulator scenarios and ten JPMs.
up with two system related questions. All candidates were also examined using JPMs and/or questions to evaluate the administrative requirement portion of the examination.
Simulator and JPM performance by the candidates was good. Communication was also good, including the use of repeat backs. The exarniners noted that crew briefings were routinely performed by the SROs. Good control board awareness by all of the candidates was evident throughout each of the four scenarios.
c.
. Conclusions The candidates performed well on both the written and operating portions of the examination. The candidates were well prepared for the examination, indicating that the f acility thoroughly evaluated the knowledge and ability of each candidate in an effort to determine their readiness to sit for an initial NRC, SROI examination.
i Crew communications, control board awareness, and crew briefings were good. As noted in past BVPS NRC reports, the training department, did wellin adhering to the examiner standards and in developing the examination materials needed to administer the examinations.
05.2 Reaulatorv Guide (RG) 1.8 Rev. 2 Reauirements Insoection a.
Scoce (IP 41500)
RG 1.8 Rev. 2 requires certain requirements, and certain obligations be satisfied by a license candidate prior to taking the examination for a hot Senior Reactor Operators license. The inspectors reviewed the four candidates' training records and NRC records to verify compliance with these requirements.
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b.
Observations and Findinas RG 1.8 requires that:
Each candidate, for a senior license, have a high school diploma or equivalent. The inspectors verified that all candidates met or exceeded the requirement.
Each candidate, for a senior license, have four years of responsible power plant experience. The inspectors verified that all candidates met or exceeded the requiroment.
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3 Each candidate, for a senior license, serve three months as an extra person on shift in training for that position. Three months is the equivalent of 520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br /> for a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week. The candidates did not meet this requirement, however, the NRC granted a waiver on August 17,1998, to take the examination. This may result in a condition on the issued license.
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Each candidate, for a hot license, should manipulete controls of the facility during a j
minimum of five reactivity changes. The inspectors verified that all candidates met or exceeded the requirement [10 CFR 55.31(a)(5)). The candidates did not meet I
this requirement, however, the NRC granted a waiver on August 17,1998, to take the examination and the licenses will not be issued until this requirement is met.
The licensee agreed, via a letter dated July 13,1998, that the candidates will be placed in the requalification training program as if the licenses are issued.
c.
Conclusions Current operator license training is being conducted in accordance with RG 1.8 Rev. 2. Appropriate waivers were submitted by the facility licensee in a timely manner and were addressed by the NRC staff.
08 Miscellaneous Operations issues 08.1 Condition Reoort In NRC inspection report 50/334 97 300 the inspector documented inconsistencies within certain documents regarding training requirements. Although, the licensee was conducting the training of perspective operators in accordance with RG 1.8, Rev. 2 other documents listed different training requirements. The licensee issued Leadition Report (CR) 980734, on April 9,1998, that described the inconsistencies. During this inspection, the inspector reviewed the licensee's corrective actions to the CR, and found them satisfactory. Changes to documents reflecting proper training requirements for operators, maintenance personnel and other personnel were being tracked by the licensee's tracking system until licensing basis document are properly changed.
08.2 Procedures (IP 42700)
During the shutdowr, period, the operating procedures underwent major revisions.
The procedures used during the simulator and JPM exercises were reviewed to verify if technical adequacy of the procedures was consistent with desired actions and modes of operation and to verify the ability of procedure (content and format) to be used easily.
i The examiners concluded that the procedures used were complete in their technical content, were well v0ritten, and were clear and understandable for the us' rs.
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{l. Maintenance M8.1 Technical Soecification (TS) Surveillance Schedulina and Trackina, s.
Scone UP 62700)
The inspector evaluated the status of facility restart issue P-14, that addressed centralization of TS surveillance scheduling and tracking in one database, under one Surveillance Coordinator. This was accomplished by a review of the applicable procedure and interviews of the surveillance coordinator and schedulers, b.
Observations and Findinas NPDAP 8.12 Rev 3 " Control and Coordination of Technical Specification Surveillances" defines the responsibilities of the surveillance coordinator. This position tracks all surveillances with frequencies greater than or equal to weekly, including conditional surveillances which may, or may not, be required based on plant operating mode. This tracking is accomplished with a database in the facility's MP (maintenance planning system) software. Required periodic surveillances are incorporated into the baseline 12 week schedule, that is generated with a software called "Primavera." Conditional surveillances are scheduled for the applicable plant mode. The su.veillance coordinator generates reports of potential conditional surveillances and coordinates with schedule preparation personnel reports to ensure required surveillances are indicated. The coordinator is informed of completion of surveillances and any necessary changes such as increased frequency testing requirements both by E-mail and hard copy, then he enters this information into MP.
The inspector reviewed activities performed to verify the accuracy of the consolidated database. The facility had performed an extensive review to ensure that procedures existed to properly test all (TS) requirements. This review was discussed in integrated report 50 344&412/97-11. As a result of this review the f acility generated a software matrix able to cross reference TS's and procedures.
This software cross matrix is redundant to an existing hard copy matrix. The surveillance coordinator had verified that all procedures for which he was responsible for had been correctly entered into MP. A partial audit by Ouality Assurance was performed with minor discrepancies resolved.
During this inspection, the coordinator was in the process of verifying that these procedures were correctly referenced in the hard copy technical specification matrix. As a result of this review, additional required changes had been identified which will be incorporated into a future review of the matrix.
c.
Conclusions This restart item (P 14) was acceptably completed.
5 M8.2 Work 2ontrol a.
Scone UP 62700)
The inspector evaluated the status of facility restart issues P-15 and P-19, which addressed the implementation of a 12 week work management process and a combined 12 week / forced outage schedule.
b.
Observations and Findinos The week of this inspection was the second week of the facility's revised scheduling and work control process. Scheduling of work was divided into a 12 week "on-line" schedule and an outage schedule. With the plant in an extended forced outage, these schedules have been combined into one schedule. The on-line schedule is planned around a baseline schedule of work windows for systems and trains. Routine preventive maintenance and surveillance items are added to this schedule, along with corrective maintenance. Work is accommodated in the present schedule or the next 12 week scheoule based on priority. The on-line schedulers are current or former SROs for each unit. Once a week, meetings were held between the schedulers, work week management personnel, and supervisors to monitor preparation for future work weeks in advance of scheduled oerformance.
This meeting also includes readiness of current planned work to proceed. The inspector observed a meeting and considered the interaction a benefit.
Outage work was normally planned separately from on-line work. Due to the extended forced outage, the potential benefits of the 12 week schedule were not being realized. The 12 week schedule had been prepared by the on-line schedulers, but any outage related work that could be performed was given priority and fit into the schedule, sometimes with as little as one shift notice. As a result, the potential operational safety benefits of the new schedule and evaluation of equipment out of service were not being realized. These benefits would include ensuring safety related equipment was not removed from service during operations for longer than necessary due to lack of personnel, parts, or interdepartmental coordination, and timely PRA review of the proposed schedule. Since the schedule may have changes subsequent to PRA review, the inspector verified that the facility has an operations department shutdown risk assessment procedure to verify required equipment is operable despite late schedule changes.
Due to the present overlap between shutdown and on-line schedules, the facility did not intend to begin tracking performance indicators for the effectiveness of the revised process until the unit was back on line.
c.
Conclusions With respect to licensee restart items P-15 and P-19, plans and procedures for the new "on-line" maintenance scheduling process appear to be in place, but the j
effectiveness of this procedure remains to be realized.
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M8.3 Post Maintenance Testina a.
Scone flP 62700)
The inspector reviewed the status of restart items M-9 and P 16. These items addressed review of outstanding post maintenance testing items for restart, and revision of the post maintenance testing process to reduce a work load burden on the operating shift.
b.
Observations and Findinas item M-9 concerned verifying required post maintenance testing was completed.
The inspector obtained a printout of work orders that had been statused as complete but awaiting post maintenance testing (PMT) and interviewed the PMT SRO. This individual was using the same printout, verifying that post maintenance He testing paperwork was in the centrol room or tracking it down if it was not.
was also coordinating with work control and the control room to ensure necessary work was completed for restart and to schedule specific PMT activities as necessary. The inspector considered the assignment of a dedicated individual and his evaluation to be appropriate.
Item P-16 concerned revision of the post maintenance testing process to better ensure appropriate post maintenance testing requirements were determined and performed prior to declaring equipment operable. This was being addressed in two parts. An SRO per unit was assigned to work control to evaluate work packages prior to scheduling and modify post maintenance testing requirements if necessary.
The second measure was the development of a post maintenance testing procedure to aid shift personnelin determining appropriate post maintenance testing.
Development of this procedure had just started and the form of the end product was not deterrnined. The inspector considered the SRO reviews at the planning and scheduling stage, coupled with the dedicated SRO post maintenance testing reviewer for mode change to be adequate for startup.
c.
Conclusions With respect to licensee restart item M 9 and P-16, during the shutdown, the f acility appeared to have taken adequate steps to reduce the shift work load burden due to post maintenance testing, however the effectiveness of this process remains to be realized.
M8.4 Licensee " Culture" Enhancements a.
Scooe (IP 62700)
The inspector reviewed the status of the following items listed as " culture" enhancements in the licensee's restart plan: 1) Develop a plan to upgrade licensed and nonlicensed requalification training programs for increased emphasis on technical specifications. 2) Developed a plan to upgrade General Employee Training l
7 (GET) and General Empbyee Refresher Training (GERT) programs ensuring increased sensitivity to Technical Specification (TS) compliance. 3) Develop a "Just in Time" training plan to train all operating crews involved in an activity prior to the performance of the identified activity. A fourth item concerning " lessons learned,"
from the outage, was not ready for inspection.
b.
Observations and Findmos The Training Administrative Manual had been changed to require a two hour session concerning technical specifications in each module for both programs. This training was in additio'n to TS training presented with each specific system. This training was scheduled to commence with the next module (module 5) for non licensed l
operator training and had already commenced for licensed operator training. The inspector reviewed the lesson plan for the session taught and considered it to be of 1
appropriate quality.
The inspector reviewed Addenduin 98.5 to GERT which described TS's including; their development, ownership of the document, responsibility for implementation, and purpose for the document. The inspector verified that the addendum was presented to all employees, and that the training will be presented at each session of GET in the future.
The Operations Department in conjunctbn with the Training Department developed a "just in time" training program. The inspector reviewed documents and had discussions with training department personnel regarding training that was presented to operators during this extended outage as follows: All operators have received training regarding changes to procedures altered during this outage.
Operators also received training on design changes implemented during this outage.
2 To be completed is training for start up and heat up of the plant prior to the overall plant start up. Training management informed the inspector that this training will
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take place just prior to returning the unit to service.
c.
Conclusions 1
The facility developed a plan for upgrading TS training in the requalification programs for licensed and nonlicensed operators, as stated in their restart plan, GET and GERT now contains TS training for all non licensed personnel and is of appropriate quality. "Just in time " training was enhanced to include training of i
operating crews prior to important evolutions.
E8 Review of the FSAR.
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While performing the preexamination activities discussed in this report, the inspectors reviewed applicable portions of the FSAR, that related to the selected examination questions or' topic areas. No discrepancies were noted.
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8 V. Mannaement Meetinas i
X1 Exh Meeting Summary On August 21,1998 the NRC examiners discussed their observations regarding the examination with Beaver Valley Unit 2 operations and training management representatives. The examiners discussed candidate performance, including communications and briefings among themselves, both were good.
The examiners also expressed their appreciation for the cooperation and assistance that was provided during both the preparation and examination week by licensed operator training personnel and operations personnel. The following were present at the exits.
The results of an earlier inspection evaluation the restart items were also discussed.
PARTIAL LIST OF PERSONS CONTACTED BEAVER VALLEY J. Cross, President Generation Group M. Johnson, Manager of Security (Acting VP)
K. Beatty, General Manager, Nuclear Support R. Brooks, Sr. Nuclear Operations instructor W. Lindsey, Director, Operator Training R. Hart, Senior Licensing Supervisor BB.C T. Kenny, Senior Operations Engineer, Chief Examiner J. D' Antonio, Operations Engineer D. Kern, Senior Resident inspector INSPECTION PROCEDURES USED IP 41500: Training and Qualification Effectiveness IP 62700: Maintenance Program implementation IP 42700: Plant Procedures
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9 LIST OF ACRONYMS CFR Code of Federal Regulations CR Condition Report 4
GERT General Employee Refresher Training GET General Employee Training Job Performance Measure i
JPM i
NRC Nuclear Regulatory Commission PRA Probabilistic Risk Assessment PTM Post Maintenance Test QA Quality Assurance i
RG Regulatory Guide RO Reactor Operator SRO Senior Reactor Operator SROI Senior Reactor Operator Instant TS Technical Specifications Attachments:
4-
- 1. Beaver Valley Unit 2 SRO Written Examination w/ Answer Key
- 2. Simulation Facility Report 8
S
e BV-2 SRO WRITTEN EXAMINATION W/ ANSWER KEY l
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RTL #A5.620.H DUQUESNE LIGHT COMPANY Volums 3 Nuclear Pownr Division Procedure 5 5 Training Administrative Manual Figure 5-5.1 Revision 12 1,
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Page 1 of 1 WRITTEN EXAMINATION COVER SHEET PROGRAM: Licensed Operator Training CLASS NUMBER: 2 LOT 2A
SUBJECT:
Initial NRC SRO Exam i
By this signature, I state that all of the work done on this examination is my own. I have neither given nor received aid.
(fi SIGNATURE DATE NAME ANSWER KEY DLC EMP. #
(Please Print)
COMPANY (if other than DLC)
POSSIBLE POINTS 100 SCORE Instructor Initials PREPARED BY Thomas Stan_ley TRAINING DIRECTOR /SUPERVidOR SIGN ATURE <
4h APPROVAL
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-1 The unit is at 100% with all systems NSA. 'Ihe following annunciators are lit:
1, A4 3C "TAVG DEVIATION FROM TREF" AS-4F " ROD CONTROL BANK D LOW-LOW Trefis 5'F above Tavg Which of the following actions is required to restore Tavg-Tref to within limits and clear the Rod Insertion Low-Low Limit?
A. Lower turbine load and add boron B. Raise turbine load and add boron C. Lower turbine load and dilute D. Raise turbine load and dilute ANSWER: A K/A: 001 K3.01 Importance: 3.1/3.5
(;cg Cognitive Level: ComprehensionCLOSED BOOK
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Ref.:
AOP 2.1.3 Step 2 Issue I A Rev. 3 LP#:
2LP-SQS-53C.1 OBJ:
Obj. 8 l
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Historv Source: NEW JTA:0000040401 r
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-2
'+f 2.
The unit is operating at 100% with all systems NSA. Control Rod H-4 drops into the core. -The ANSS is informed that a blown fuse on the stationary gripper coil will require 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to replace.
Which of the following actions will be needed to comply with the LCO:
A.
Within I hour verify compliance with T.S. 3.1.3.6 " Control Rod Insertson Limits".
[
B.
Within I hour verify shutdown margin per T.S. 3.1.1 "Boration Control - Shutdown Margin".
C.
Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> place the unit in Hot Standby per T.S. 3.1.3.1 " Movable Control i
l Assemblies-Group Height" Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> align the bank to within 12 steps of H-4 per T. S. 3.1.3.1 " Movable D.
r i
Control Assemblies-Group Height" i
L ANSWER: B j
K/A: 003 K1.07 Importance: 3.1/3.9
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Cognitive Level: Analysis OPEN BOOK Ref.:
20M53.C.2.1.8 " Rod Inoperability" Issue 1 A, Rev0 Step 4
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l Beaver Valley Technical Specification 3.1.1 "Boration Control Shutdown Margin LP#:
2LP-SQS 53C-1 OBJ:
8 History Source NEW 1
JTA:0000070401 Note: Student has copy of Tech Specs
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-3
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During the performance of ES-0.1 " Reactor Trip Response" the NCO reports that control tod F-8 3.
indicates 24 steps and control rod H 8 indicates 227 steps on the Rod Position Indication Panel.
Which of the following actions is needed to ensure adequate shutdown margm? ~
A.
Stop dumping steam to stabilize Reactor Coolant System 6.pEure at 547'E B.
Borate the RCS to Cold Shutdown Concentration at 200'F from Curve CB-27.
Emergency borate until the in service Boric Acid Storage tank shows a 36% level drop.
C.
D.
Emergency borate until the in service Boric Acid Storage tank shows an 18% level drop.
ANSWER: D K/A: 003 A2.03 Importance: 3.3/3.4 Cognitive Level: Analysis OPEN BOOK Ref.
20M-53 A.I.ES-0.1" Reactor Trip Response" Issue IB Rev. 4 Step 6 20M-53A.I.ES-0.1 " Reactor Trip Response" Background Issue IB, Rev. 4
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Beaver Valley Curve Book Curve CB 27 Issue 7 Rev. O LP#:
2LP-SQS 53.3 OBJ: 6 Historv Source: NEW JTA:301 AAA0601 Student gets Copy of EOP ES-0.1 and CB 27 I
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-4 4;
The reactor has tripped and a Safety injection was actuated on low RCS pressure. The crew is transitioning from E-0" Reactor Trip and Safety injection" to E-1 "less of Primary or Secondary Coolant", Step l. The following conditions exist:
RCS Pressure 980 psig - stable Steam Generator Pressure 950 psig - stable Contamment Pressure 8 psig - stable RWST level 500 inches - slowly dropping HHS1 flow 520 gpm - stable During the crew briefing at transition, which of the following sets of pumps should be operating?
1.
Low Head SI pumps 2.
Reactor Coolant pumps 3.
Quench Spray pumps 4.
Component Cooling pumps A
Alllisted pumps B,
LHSI and Reactor Coolant Pumps only C.
LHS1 and Component Cooling Pumps only D.
LHSI and Quench Spray Pumps only ANSWER: D K/A: 011 K3.14 Importance4.1/4.2:
Cognitive Level: Analysis CLOSED BOOK Ref.:
20M 53.1.E-0 " Reactor Trip and Safety injection" issue 1B, Rev. 4 20M-53.1 E-1 " Loss of Primarv or Secondary Coolant" issue IB, Rev. 5 LP#:
2LP-SQS-53.3 OBJ: 3 Historv I
Source: NEW JTA 3010010601 a
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NRC Exam: 2 LOT 2, Rev 0 I
Question 8 98-5 Transfer to Hot leg Recirculation,14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> following a LOCA, is designed to meet which.one of 5.
j the following criteria?
Maximize core cooling following a cold leg break with flow into vessel and out of cold leg A.
break.
Dilute boron concentration in the reactor vessel to prevent precipitation of boron on clad B.
surfaces.
Minimize differential pressure from cold leg to allow maxunum flow into reactor vessel.
C.
Limit void in upper vessel to prevent blockage of natural circulation flow into hot legt D.
ANSWER: B Importance: 3.8/4.2 K/A: 011 K312 Cognitive Level: Knowledge CLOSED BOOK 20M538.3.E-1" Loss of Primary or Secondary Coolant" issue IB Rev. 5 Note before step 31 Ref.:
p219 OBJ-3 LP#:
2LP SOS-53.3 History Source: NEW JTA: 3010010601 1
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s
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-6
/
6.
The crew is performing ES-1.2 " Post LOCA Cooldown and Depressurization". At step 24 irrthe procedure the ANSS instructs the Reactor Operator to :
"Deoressurize the RCS to minimize break flow until PRZR level is GREATER THAN 76% or Subcoolina is less than subcooline listed on Attachment A-5.2" Which of the following actions will result in the lowest RCS pressure and limit the rise in Pressurizer level?
A.
Using a PORV to reduce RCS pressure.
B.
Using normal PRZR spray while reducing charging flow.
C.
Lock out the PRZR heaters while spraying the PRZR.
D.
Aligning auxiliary spray for maximum temperature differential.
ANSWER: B K/A: W/E02 EK1.2 Importance:3.5/3.8
(*.::)
Cognitive Ixvel: Analysis CLOSED BOOK Ref.:
20M53.A.ES-1.2 " Post LOCA Cooldown and Depressurization" issue 1B. Rev. 5 Step 24 2OM53.B.ES-1.2 " Post LOCA Cooldown and Depressurization" Background" Issue iB, Rev. 5 LP#:
2LP SOS 53.3 OBJ: 3 Historv Source: NEW i
JTA: 301 AAA0601 l
r t,i
NRC Exam: 2 LOT 2, Rev 0 Question 8 98-7 At step 28 in E-0 " Reactor Trip or Safety Injection", the following parameters are noted.. -
d 7.
RCS Subcooling 55 degrees and rising Total AFW Flow - 400 gpm - stable RCS Pressure 2l00 psig-rising PRZR level 19%-rising Based on these parameters, which of the fcilowing is a correct statement?
RCS pressure is sufficient to make RCS subcooling an indication of RCS inventoo-A.
AFW flow is suflicient to make RCS pressure an indication of RCS inventory B.
RCS subcooling is sufficient to make PRZR level an indication of RCS inventory C.
RCS pressure is sufficient to make PRZR level an indication of RCS inventon' D
ANSWER: C K/A: W/E02 EA1.3 Importance: 3 8/4.0 Cognitive Level: Comprehension CLOSED BOOK
[.
Ref.:
20M-53A-E-0" Reactor Trip and Safety injection", Issue IB, Rev. 4 20M-53B.5.GI-l1 "Si Ternunation Criteria" Issue IB, Rev.1 Page 7 w
OBJ:
3 LP#:
2SQS 53 2 Historv:
Source: NEW JTA: 301 AAA0601 r
G
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Qutstion 8 98-8 8.
The unit is at 100% power with all systems NSA. Which of following will NOT automatically trip the 21 A Reactor Coolant Pump?
A.
RCP 21 A Bearing Low Lube Oil Level = 1.25 in. below Normal i
B.
2A 4KV Bus Frequency = <57.5 Hz C.
2A 4KV Bus Voltage = 75% of rated voltage D.
RCP 21 A Motor Electrical Protection Overcurrent ANSWER: A K/A: 0015/17 K1.02 Importance: 3.7/4.1 Cognitive Level: Comprehension CLOSED BOOK i
Ref.:
20M 6 " Reactor Coolant System" Issue 4, Rev. O Section IOM 6.1.D, Page 1 of 19 20M-6 " Reactor Coolant System" Figure 06-22 " 10080-LSK-25-1 A LP#:
2SQS-6.3 OBJ:
8 I
History Source: NEW l
JTA: 003 AAA04011 i
s
DVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-9 A Reactor Trip with loss of offsite power has occurred. The following conditions exist:
(._./
9.
Core Exit Thermocouple Temperatures = 582*F and stable.
All Hot leg Temperatures = 580 F and stable.
All Cold Leg Temperatures = 550*F and stable.
Pressurizer Pressure = 2085 psig and stable.
Containment Pressure = 10 psia and stable it is desired to reduce RCS pressure but maintain 50*F subcooling. The muumum pressure that can be achieved to maintain 50 F subcooling as indicated on PSMS is:
A. 1930 psia.
B. 1942 psia.
C. 1947 psia-D. 1962 psia.
ANSWER: C (Psat for 632 F =1947 psia)
(
)
K/A: E09EK3.3 Importance: 3.5/3.6 Cognitive Level: Analysis OPEN BOOK Ref.: Steam Tables OBJ:
14 LP#:
2SQS 3.1 History Source: New JTA: 0170020101 Student given Steam Tables s
0
. BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-10 10.
Which of the following would comply with the requirements for emergency boration?
A.
Open 2CHS*MOV350, verify 30 gpm on 2CHS*F1110 Emergency Boration Flow and verify greater than 30 gpm charging flow to the RCS.
B.
Open 2CHS*SOV206 and 2CHS*FCVil3A, verify 30 spm on 2CHS*FH 10 Emergency Boration Flow and 40 gpm charging flow to the RCS.
C.
Open 2CHS*MOV350 and verify greater than 40 gpm boration flow on 2CHS*FRI 13 Boric Acid to Blender Flow Recorder.
D.
Open 2CHS*SOV206 and 2CHS*FCVI 13A, verify greater than 40 gpm boration flew on 2CHS*FRil3 Boric Acid to Blender Flow Recorder.
ANSWER: D K/A: 024 A2.02 Imponance: 3.9/4.4 Cognitive Level: Analysis OPEN BOOK
(?,
Ref.: 2OM-7.4.Q "Emereency Boration" Issue 4 Rev.1 Pages 1 and 2 LP#:
2LP SQS-7.1 OBJ:
8 History Source: NEW JTA: 004EEE0101 Student has copy of procedure I
l' 10
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Qurstion 8-98-11 I 1.
~ Unit 2 is in Mode 5 on RHS cooling with 2RHS P21 A running. He following conditionsexnt:
2CCP'P21 A is running l
2CCP'E21 A and 2CCP'E21B heat exchangers are in senice 2CCP'DCV101 A and B CCP Hx Diff. Press. Control Valves are operating in manual 2CCP*TCV100A and B CCP Hx Temp. Control Valves are operating in auto Which of the following would be the eff:ct on the plant from loss ofinstrument air?
2CCP*DCV101 A and B fait closed,2CCP*TCV100A and B fail open and RHS A.
temperature drops.
2CCP'DCV101 A and B fail open,2CCP'TCV100A and B fait closed and RHS B.
temperature drops.
2CCP'DCV101 A and B fail closed,2CCP'TCV100A and B fail open and RHS C.
temperature rises.
2CCP'DCV101 A and B fail open,2CCP'TCV100A and B fail closed and RHS
~
D.
..3
~
temperature n'ses.
ANSWER: B K/A: 026 K3.03 Importance: 3.5/3.7 Cognitive Level: Comprehension CLOSED BOOK Ref.
20M-15.5 CCP System" lssue 4 Rev. 0 Figure 15-1 10080-RM-415-1 Res. 9 l
LP#:
2LP-SQS-15.1 OBJ:
3 L
l History l
Source: NEW JTA: 0050080101 2
v=
11
BVPS-2 NRC Exam 2 LOT 2, Rev 0 Question 8-98-12 12.
The crew has initiated emergency boration in response to an ATWS. RCS pressure is 23}$ psig.
Which of the following actions would maximize negative reactivity and minimize the addition of positive reactivity being added to the RCS7 A.
Raise AFW flow to 700 gpm and fill all steam generators to 5% narrow range level:
)
B.
Lower charging flows to 40 gpm and raise letdown flow to 120 gpm by placing two letdown orifices in service.
j C.
Verify Pressurizer PORY motor isolation valve open and verify /open a Pressurizer PORV.
l D.
Place Steam Dump Controller to Manual and open the steam dumps.
l ANSWER: C K/A: 029 K1.03 Importance: 3.6/3.8 Cognitive Level Comprehension CLOSED BOOK Ref,: 20M-53.4.FR.S 1" Response to Nuclear Power Generation-ATWS", Step Description for Step 8,
3 1ssue IB, Rev. 5 LP#:
2LP SOS 53.3 OBJ:
3 History Source NEW I
JTA: 3110010601 l
1:
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-13
%)
The Reactor Coolant system parameters are 1700 psig and 490 degrees., All actions required by 13.
20M 51.4.C " Station Shatdown-Cooldown from Mode 3 to Mode 4" procedure are in effect.
Which of the following actions would automatically tenninate the cooldown via the steam dumps?
21 A and 21B Steam Generator pressures drop to 450 psig in each generator
_ A.
21B Steam Generator pressure drops from 690 to 490 psig in 45 seconds B.
C.
21 A Steam Generator level rises from 55% to 85 % in 45 seconds D.
21 A and 21C Steam Generator levels drop to less than 5% narrow range 1
ANSWER: B K/A: 040 K3.04 Importance: 4.2/4.5 Cognitive Level: Comprehension CLOSED BOOK Ref.:
20M21 " Main Steam", Iss. 4, Rev. O. Section 20M-21.1.D Page 2of 11, 20M-21.B Page 2 LP#:
2LP-SQS-21.1 OBJ:
3
~
History Source: NEW JTA: 0390090101 9
1.1
BVPS-2 NRC Exam: 2 LOT 2, Rev 0
. uestion 8-98-14 Q
i,..)
14.
In step 13 of ECA-2.1" Uncontrolled Depassurization of All Steam Generators" the operator confirms that Si accumulators will be isolated when 2 of 3 Hot Leg temperatures are less than 390 degrees. Isolation of the accumulators below this temperature is required to prevent:
A.
_ injecta of nitrogen gas in to the Reactor Coolant System B.
Violation of Technical Specification temperature pressure limits.
i C.
Entry into Pressurized Thermal Shock conditions in the vessel.
D.
High pressure differential across the steam generator tubes.
.L ANSWER: A K/A: 040 A1.04 Importance: 4.3/4.3 Cognitive 1.evel: Knowledge CLOSED BOOK Ref.: 20M 53.A.4.ECA-2.1 " Uncontrolled Depressurization of All Steam Generators" Iss. IB Rev 6.
. Background Description for Step 13 LP#:
2LP-SQS-53.3 OBJ:
3 History Source: NEW JTA: 301003d601 3
e 4
9 14
l BVPS-2 NRC Exam: 2 LOT 2; Rev 0 Question 8-98-15 Following a steam break that occurred 20 minutes ago, the crew has completed isolating the ste 1
15.
i j
generator using E-2 " Faulted Steam Generator Isolatxm" with the following status:
Reactor Coolant Temperature at 258 degrees and stable -
j Reactor Coolant Pressure at 1400 psig and stable i
1 21 A Steam Generator Pressure 25 psig and stable J
l 21B and 21C Steam Generator Pressures at 420 psig and stable
?'
i Based on the given information, select the appropriate procedure for the transition from I'
E-2" Faulted Steam Generator Isolation.
4 i
A.
Go to E-1 "less of Primary or Secondary Coolant" Step 1.
i Go to ECA - 2.1 " Uncontrolled Depressurization of All Steam Generators" Step 1.
f B.
Verify no higher " RED" path present and go to FR-P.I " Response to Imminent C.
Pressurized Thermal Shock" Step 1.
Verify no higher " ORANGE" path or any " RED PATH present and go to FR-P.2 D.
" Response to Anticipated Pressurized Hermal Shock" ANSWER: D K/A: W/E08 A2.01 Importance: 3.4/4.2 Cognitive Level: Analysis OPEN BOOK Ref.: ' 20M 531.F-0.4 " Vessel Integrity" issue iB, Rev. I 20M-53 A. I. A-4.4 " PTS-Operation Limits Curve" Issue I B. Rev. 2 LP#:
2LP-SQS-53.3 -
OBJ:
12 History
.o Source: NEW JTA: 3110140601 Student gets F-0.4 and A-4.4 15
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-16 16.
As pressure rises in the Main Cond scr to normal atmospheric pressure, in what sequence will the following protective functions actuate?
1 I) AS-5B " CONDENSER VACUUM LOW TURBINE TRIP"
,2) A12-4C " CONDENSER UNAVAILABLE (C-9)"
- 3) A6 50 " CONDENSER VACUUM LOW / LOW-LOW"
- 4) LP Turbine Rupture Disk ruptures
- l A.
3,1,2 B.
1,3,2 C.
4,3,2 D.
3,2,4 ANSWER: A
(]ex K/A: K/A 005i K2.06 Importance: 1.6/1.5 Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M 26 " Main Turbine and Condenser", Section 21.1.C, Issue 4 Rev. 4 Page 5 20M-26.4.AAB " Condenser Vacuum Low Turbine Trip" Iss. 4 Rev. I 20M-26.AAK Condenser Vacuum Low / LOW-LOW", Iss. 4 Rev. 4 2OM-26 ABM " Condenser Unavailable"(C-9)"Iss. 4 Rev. O LP#:
2LP SQS 31.1 OBJ:
5 Histon-l Source: NEW l
JTA: 0750030101 e
16
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-17 In step 25 of ECA-0.0 " Loss of All AC Power" all intact steam generators are de 17.
the steam generator pressures are 300 psig. What is the basis for stopping at 300 psig?
To hnut head voiding and ensure continued natural circulation.
A.
Minimize loss of RCS through the damaged Reactor Coolant Pump seals..
B.
C.
~ Prevent the retum to criticality of the reactor core during cooldown.
Prevent challenging the reactor w=1 integrity limit.
D.
ANSWER: D Importance: 4.3/4.6 K/A: 055 K3.02 CLOSED BOOK Cognitive Level: Knowledge 20M.53.B.4.ECA-0.0 " Loss of All AC Power" Background Issue IB Rev 4 Page 114 Ref.:
OBJ:
3 LP#:
2LP-SQS-53.3 Historv i
Source: NEW JTA: 3010060601 4
F A
l l
l 17
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-18 U
~
18.
Bus 2AE de-energized when the normal feeder breaker opened Which out of position switch l
l would prevent an emergency start of the 2-1 Emergency Diesel Generator?
A.
Mode Selector Switch in NORMAL B.
.D/G Auto / Local Key Switch in AITTO C.
Generator Synchronous Check Switch in OFF D.
Auto / Exerciser switch in EXERCISE ANSWER: D K/A: 055 A1.02 Importance: 4.3/4.4 Cognitive Level: Comprehension CLOSED BOOK Ref.:
20M-36.5 "4KV Station Service System Figures and Tables", Issue 4, Rev. O, Figures36-24A and 24B 20M-36.3.C.8 " Power Supply and Control Switch List Diesel Generator 2-1"
(
't Issue 4, Rev. 8, Page 19 20M-53.A.4.ECA-0.0 " Loss of All AC Power". Issue IB. Rev. 4, Step 8 LP#:
2LP-SOS-53.3 OBJ:
3 History Source: NEW JTA: 3010060601 2
18
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-19 A short has damaged Vital Bus 2-3 and the panel will be unavailable from n l
19.
supply. Which of the following actions will be required?
Pressurizer level 11 and ill must be selected for service A.
Steam Generator Pressure Channel III must be selected for service B.
C.
Make-up to the VCT must be controlled in manual Swapover to the RWST must be manually performed at 5%
D.
ANSWER: D Importance: 3.5/3.6 K/A: 0057 A1.04 OPEN BOOK Cognitive Level: Analysis 20M-38.4.W " Extended Loss of Vital Bus 2-3" issue 1, Rev. 4. Page I Ref.:
OBJ: 7 LP#:
2LP-SQS-39.1 History -
Source: NEW l
9 Student gets copy of 38.4.W JTA: 0630040101 4
A 19
. \\
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-20 20.
Service Water Pump C is currently in service and connected to the 4KV Emergency Bus 2bf
'I During an attempt to start Service Water Pump A, the discharge valve jammed partially open. If power were lost to the AE bus, what would be the status of the Service Water system at the completion of the sequencmg ofloads on the bus?
A.
SWS pumps A and B would be runmng B.
SWS pump B would be running only C.
SWS pump C would be running only l
i D.
SWS pumps A and C would be running
_ ANSWER: D K/A: 062 A2.02 Importance: 2.9/3.6 Cognitive level: Comprehension OPEN BOOK Ref.:
20M 30.5 " Service Water Figures and Tables" Issue 4, Rev. 2 Figure 30-612241 LSK-17-A LP#:
2LP-SQS-30.1 OBJ:
5 History Source: NEW-JTA: 076-C0121 Student gets LSK S
l
.9 20
BVPS-2 NRC Exain: 2 LOT 2, Rev 0 Question 8-98-21
(,/
A fire has caused the evacuation of the Control Room and the plant is being controlled 21.
Alternate Shutdon Panel (ASP) in ash with 20M 56C, Alternate Safe Shutdown. Prio beginning a cooldown, the RCS is borated to the Xenon free cold shutdown Boro This is accomplished by:
A. Using 22A Boric Acid Transfer Pump [2CHS*P22A] and Alternate Emergency Borati
[2CHS*SOV206) to pump either Boric Acid Storage Tank to the suction of the Charg B. Gravity feed of 21B Boric Acid Tank [2CHS*1K21B] via Emergency Boration isolation V
[2CHS*MOV350] to the suction of the Charging Pump.
C. Setting the Boric Acid Blender control to 2000 ppm and initiating a feed and bleed of D. Aligning the suction of the Charging Pump (2CHS*P21B) to the RWST.
ANSWER: A importance: 3.9/4.1 K/A: 068AA1.ll Cognitivelevel: Knowledge CLOSED BOOK 20M56C.4.F.9" Operation of Alternate Emergency Boration Valve [2CHS*SOV206) and Remote Ref.:
Operation of Boric Acid injection Valve (2CHS*FCVI13A) Issue i Rev. 5 OBJ:
8 LP#:
2LP.SQS 53C.1 History Source: New JTA: 0000020-101
.f I
21
I BVPS-2 NRC Exam-2 LOT 2. Rev 0 Question 8-98-22 C.,, )
22 A channel 11 Containment High-l pressure signal is in test with a trip signal when a second channel Containment High I is generated by electrical noise. Which of the following will be the status of containment isolation?
A.
. All inside and outside contamment pendrations will go to their Phase A configuration.
B.
All inside and outside contamment penetrations will remain in their current configuration.
C.
Only the outside containment penetrations will go to their Phase A configuration.
D.
Only the inside containment penetrations will go to their Phase A configuration.
a.
ANSWER: A K/A: 069( W/E 14) A1.01 Importance: 3.5/3.7 Cognitive Level: Comprehension CLOSED BOOK Ref.:
20M 1.1.D " Reactor Control and Protection" Issue 4, Rev. O
~
FS AR Table 6.2-60
(%
J LP#:
2LP-SQS 1.2 OBJ: 9 Historv Source: NEW JTA: 0060150101
+
4 22
= -.. ~
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-23 He crew has completed the actions of ES-l.3 ' Transfer to Cold Ug Recirculation". S!, CIA and 23.
CIB have been reset. Off site power is lost and both EDG's start and load busses AE and DF. To ensure core cooling, which of the following actions will be required?
A.
. Restart A and B High Head Safety Injecuan Pumps B.
Restart C and D Recire Spray pumps C.
Restart A and B Quench Spray pumps D.
Restart A and B Servil:e Water Pumps ANSWER: B K/A: 074 E06/E07 EK 2.1 Importance: 3.6/3.8 Cagnitive Level: Comprehension CLOSED BOOK 20M13.5 " Containment Depressurization System Tables and Figures" Figure 13-12, Ref.:
_~
12241-LSK 27-1 A, Issue 4, Revi
.fG 20MS3 A.I.ES-1.3 " Transfer to Cold Leg Recirculation" Issue IB, Rev.
'/
20M-36.1.C "4KV Station Electrical Maior Components". Iss. 4 Rev. C pages 15 and 16 LP#:
2LP-53.3 OBJ:
8 History Source: NEW JTA: 301 AAA0601 o
23
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-24
~
24.
The chemist reports that reactor coolant system activity has reached 1.1 pCi/gm in lodine due to 4
failed fuel. After 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> at this level of activity the unit must be brought to less than 500 *F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to:
A.
limit thermal stresses on the failed fuel and reduce 1-131 releases to the RCS.
B.
limit the Auxiliary Building dose rates to less than the requirements of 10CFR20.
C.
limit the post LOCA containment dose limits to the requirements of 10CFR20.
D.
limit the secor.dary side pressure in case of a steam generator tube rupture.
ANSWER: D K/A: 076 (General 2 2.25)
Importance: 2.5/3.7 Cognitive Level: Knowledge CLOSED BOOK l
Ref.: BVPS Unit 2 Technical Specification 3/4.4.8 Basis LP#:
2LP SQS TS.2 OBJ:
9 History Source: NEW JTA: 3410180302 1
i l
24 L
BVPS-2 NRC Exam: 2 LOT 2, Rev 0
- Question 8-98-25
(.)
25.
Unit 2 has been stabilized aAct completing the actions of ES-0.1 " Reactor Trip Response" The crew is monitoring Mode 3 conditions. Which of the following would LOWER the Shutdown Margin for the Core?
A.
Droe Shutdown bank rods that remamed 25 steps out of the core, driR down into core.
B.
The NCO opens 2CHS*MOV350 and starts the inservice Boric Acid pump.
C.
De Plant Operator lowers steam dump setpoint pressure from 1000 psig to 950 psig.
D.
The Plant Operator lowers Auxiliary Feedwater flow from 600 gpm to 400 gpm.
ANSWER: C K/A: 007 K1.02 Importance: 3.4/3.8 Cognitive Level: Comprehension CLOSED BOOK Ref.: Generic Fundamentals Reactor Theory Fundamentals, Topic 1 Kl.10, Page 9..
LP#:
2LP_SQS-6.5 OBJ: 3 (4.1,)
Historv Source: NEW JTA: 002009010I 25
BVPS-2 NRC Exam 2 LOT 2. Rev 0 l
Question 8-98-26 l'
1 D'
26.
Urnt 2 is in Mode 4 with the following indications:
l RCS Wide Range Temperature = 325 degrees 2RCS P1402 Wide Range Pressure = 460 psig 2RCS-P1403 Wide Range Pressure = 465 psig The RCS loop B Wide Range Cold Leg temperature indication (2RCS*T1423) input to B OPPS Train has failed low. Which of the following would be the potential consequence of this failure?
A.
2RCS'PCV455C Pressurizer PORV opens B.
2RCS*PCV456 Pressurizer PORV opens C.
Pressurizer Code Safety Valve lifts D.
RHS Suction Relief Valve lifts ANSWER: B K/A: 008 A2.06 Importance: 3.3/3.6
-'T Cognitive Level: Comprehension OPEN BOOK Ref.:
20M 6.4 ABC " Reactor Coolant Wide Range Pressure Deviation High" Issue 4, Rev. O, Page 5 BVPS Curve Book CB-25, Issue 7, Rev. O LP#:
2LP-SQS-6 4 OBJ:
5 History Source: NEW JTA: 0020090101 Student gets references listed above f
26
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-27 u-During the performance of ES-1.2 " Post LOCA Couldown and Depressurization" th 27.
have com nenced a cooldown. At the completion of step 18 the following conditions er "C" RCP is running RCS Subcochng 85'F at a dropping RCS Pressure 1150 psig and slowly dropping SG Pressure 950 psig and stable HHS1 Flow 350 gpm on 2 SIS *943 Pressurizer 38% and slowly dropping i
2CHS*P21 A running 2CHS*P21B has just been secured What action must the ANSS take?
A.
Stop all operating Reactor Coolant Pumps.
B.
Restart the 2B HHS1 pump 2CHS*P21B.
C.
Allow RCS pressure and PRZR level to stabilize.
D.
Establish normal charging flow, b
-w ANSWER: C l Importance: 4.4/4.3 K/A: 009 A1.01 OPEN BOOK Cognitive Level: Analysis 20M53.A.I.ES 1.2 " Post LOCA Cooldown and Depressurization" Background Caution before Ref.:
step 19 OBJ:
3 LP#:
2LP-SQS-53.3 History Source: NEW St :nt gets ES-1.2 JTA: 301 AAA0601 4
e 27
- - -.. - = -..
BVPS-2 NRC Exam: 2LDT2, Rev 0 Question 8 98 28 i
- \\.
28.
The unit is cooling down in ES l.2 " Post LOCA Cooldown and Depressurization" with all Reactor Coolant Pumps off. Reactor Coolant System pressure is 1500 psig. Which of th: fo!!owing indicate the potential failure of natural circulation?
A.
RCS Subcooling is 85'F and stable B.
Str.un Generator Pressures are 585 psig and stable C.
Core Exit Thermocouples are 525 'F and stable D.
ICS Cold Leg Temperatures are 500'F degres and stable ANSWER: D K/A: W/EO3 EK2.2 Importance: 3.7/4.0 Cognitive Level: Analysis OPEN BOOK
~
Ref.: 20M 53 A 1.7 " Natural Circulation Verification" Issue IB, Rev. 2
-)
~'
LP#:
2LP-SQS-53.3 OBJ: 3 I
History Source: NEW JTA: 301 AAA0601 Student gets attachment and steam tables 28
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-29 k.]
Following a LOCA, both trains of recirculation have become unavailable. The cr 29 using ECA-l.1 " Loss of Emergency Cootant Recirculation" The ANSS has determm minimum Si flow to maintain con: cooling is 100 gpm. This will allow the performance of the following actions?
Normal charging may be established from the VCT to the reactor coolant system to A.
provide borated makeup.
RCS cooldown rates may be increased to maximum achievable to reduce time to reaghi B.
RHS system startup conditions.
The Si accumulators may be isolated to preserve the inventory for use when the RWS C.
emptied.
Containment Recirc Spray pumps may be stopped to preserve inventory in the RWST.
D.
(~%
ANSWER: A importance: 3.3/3.9 K/A: W/EI J K2.2 Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M53B.4.ECA-1.1 " Loss of Emergency Coolant recirculation " Background, Issue IB, Rev Step 16 OBJ 5
LPs:
2LP-SQS-53.3 Historv Source: NEW 1
JTA: 3010020601 s
4 20
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-30 30.
Annunciator A2 3F " Letdown Flow Path Trouble"is lit. Computer point " REGEN HX LTDN TEMP CHS TEl40 HIGH" is in alarm. De following conditions exist:
Charging Flow 45 gpm Sealinjection Flow 22 gpm Letdown Orifice Isolation Valves 2CHS*AOV200A and 2008 = OPEN Pressurizer level 2% above program Which of the following actions would LOWER the heat load on the Regenerative Heat Exchyger?
A.
Lower Charging Flow by closing Charging Pump Flow Control Valve 2CHS*FCV122 B.
Place another orifice in service by opening 2CHS*AOV200C C.
Remove 60 gpm orifice from service by closing 2CHS*AOV200B D.
Raise letdown flow by opening Nn.n-Regen Hx Discharge Pressure Control Valve 2CHS*PCV145
(. :-
ANSWER: C l
K/A: 022 K3.02 Importance: 3.5/3.8 Cognitive Level: Analysis CLOSED BOOK Ref: 20M7.4.AAF" Letdown Flow Path Trouble" issue 1, Rev.10 Page 3 Of 6 LPd:
2LP-SOS 71 OBJ:
7 History Source: NEW JTA: 0040150101 30 l
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-31 l
31.
Unit 2 has been shutdown for 5 days. The following conditions exist:
Reactor coolant temperature is 125 degrees 'F Pressurizerlevelis 22%
I RCS pressure is 95 psig using nitrogen in the PRZR The operating RHS pump has become gas bound and is shutdown by the crew. How long would the crew have to vent the pump before reachmg saturation in the RCS?
A.'
270 minutes B.
175 minutes C.
166 minutes D.
125 minutes I
l ANSWER: B l p.-
K/A: 025 K1.01 Importance: 3.9/4.3 Cognitive Level: Analysis OPEN BOOK Ref.: 2OM53.C.4.2.Q.1 " Residual Heat Removal Loss", issue I A, Rev. 4 Attachments 1,2,3 and 4 LP#:
2LP SQS-10.1 OBJ:
10 o
Historv Source: NEW JTA: 0000180401 Assumptions:
Saturation for 110 psia is 335 degrees Current RCS Temp is 125 degre'e o
Heat rate at 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> after shutdown is 1.2*F/hr Student gets Attachments and steam tables 31 f'
L s
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-32 O
32.
The unit is in Mode 3 with the Reactor Trip Breakers open when the NCO identifies pressurizer pressure transmitter PT444 as failed low. Which one of the following would b the next cont action that would automatically occur?(Assume no operator actions)
~
A.
Pressurizer Heater Banks A,B,D, and E are de energized from PT445 on high RCS pressure.
B.
Pressurizer Variable Heater bank C is de energimd from loss of PT444 signal.
C.
PORV 2RCS-PCV455C opens on a high pressure signal for PT445.
D.
PORV 2RCS'PCV455D and 2RCS*PCV456 open on high pressure signal from PT445.
ANSWER: D K/A: 027 K2.03 Importance: 2.6/2.8 Cognitive Level: Analysis OPEN BOOK Ref.:
20M-6.4.IF " Instrument Failure", Issue 4, Rev 4, Page 16 20M-6.5 " Reactor Coolant System Figures and Tables", Issue 4, Rev. 6, Figures 6-35 and 6-36 LP#:
2LP-SQS 6.4 OBJ:
10 l
History Source: NEW JTA: 0020090101 Copy of section of references J
32
BVPS-2 NRC Exara. 2 LOT 2, Rev 0 Question 8-98 33 g
33.
A unit startup is in progress with the reactor critical at 2200 cps in the source range when N-31 Suume Range Detector High Voltage is lost. Choose the correct response.
A.
Raise power to the P 6 setpoint and continue the startup.
B.
- Verify overlap of I decade with the Intermediate Range and continue startup.
C.
Place the unit in Hot Standby with the Reactor Trip Breakers open.
D.
Suspend positive reactivity additions and restore N-31 to operable status.
ANSWER: D K/A: 032 K3.01 Importance: 3.2/3.6 Cognitive Level: Analysis CLOSED BOOK Ref.:
20M-53C.4.2.2 " Source Range Channel Malfunction" Issue 1 A, Rev. 4, Step 2 and 3 Unit 2 Technical Specification 3.3.1 Table 3.3-1 LP#:
2-LP-TS.2 OBJ:
9 History Source: NEW JTA: 3410180302 d
O 33
.. ~.
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-34 O
34.
The ANSS notes that N-35 " LOSS OF COMP VOLT" light is lit on the N1 cabinet. Which of the following operations will be impacted by the loss of voltage?
A.
During startup, the P4 permissive will not de<mergune the Source Range High voltage.
~
B.
During shutdown, the P4 pernussive to re energize the Source Range High voltage will be delayed.
C.
During startup, the P-10 permissive to manually de-energize the Source Range High t
voltage will be delayed.
D.
During shutdown, the P-10 pennissive to manually unblock the Source Range High voltage will not function.
ANSWER: B K/A: 033 A2.I1 Importance: 3.1/3.4 Cngaitive Level: Comprehension CLOSED BOOK Ref.:
20M-2.4.AAC " NIS DETECTOR / COMPENSATOR TROUBLE", Issue 1, Rev. 3 Page 3 20M-53C.4.2.2.18 " Intermediate Range Channel Malfunction" issue I A, Rev.1, Step 4 LP#:
2LP-SQS 2.1 OBJ:
18 History Source: NEW
. JTA: 0000100401 e
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34 l
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BVPS-2
)
NRC Exam: 2 LOT 2, Rev 0 Question 8-98-35 Q) 35.
. Unit 2 is operating in Mode I with all systems NSA. De most recent samples indicate the following leakages in all three steam generators.
A= 0.5 spm B= 0.1 spm C=0.15 gpm Which $f the followmg would be the required Technical Specification actens?
A.
Reduce leakage to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
D.
Place the unit in Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Hot Shutdown within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C.
Place the unit in Hot Standby in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown within an additional 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
D.
Perform a reactor inventory balance within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and then every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until the unit
~
is in Cold Shutdown.
ANSWER: A 3
K/A: 037 2.1.22 Importance: 3.4/4.0 Cognitive Levei Analysis OPEN BOOK Ref.: BVPS Unit 2 Technical Specification 3.4.6.2 LP#:
2LP-SQS-53C. i OBJ:
2 Historv:
I Source: Modified from LOT #852 k
JTA: 000011040I Student gets copy of Tech Spec d
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4 35 C
.,. ~
3 BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-36 o0 A cooldown is being conducted in accordance with ES-3.1 "RCS Cooldown Using Backfill." The 36.
depressurization of the RCS may be halted just before going to less than 360 psig.
Which of the following is the reason for stopping depressurization at this pressure?
A.
The vessel must be soaked for I hour to remove thermal stresses from the cooldown.
B.
The niptured steam generator must be soaked above Nil Ductility Transition Temperature.
C.
To allow the differential pressure across RCP 21C to be maintained above 215 psid.
To stop backfill from the ruptured steam generator prior to establishing RHS cooling.
D.
ANSWER: C I
K/A: 038 K3.08 Importance:
Cognitive Level:' Kncwledge CLOSED BOOK 2OM-53B.4.ES-3.1 " Post-SGTR Coo!down Using Backfill" Issue IB, Rev. 4 Background for Note Ref.:
~
prior to Step 8 OBJ:
3 LP#:
2LP-SQS-53.1 Historv Source: NEW JTA: 3010040601 4
36
BVPS-2 NRC Exarn: 2 LOT 2, Rev 0 Question 8-98-37
.h Which of the follow' g will complete arming of the C-20 signal for AMSAC7 m
37.
Main Feedwater total flow has been greater than 25% for 180 seconds.
A.
Two of three Narrow Range Steam Generator levels on one steam generator greater tha B.
25%.
Two of four Power Range NI's are greater than 40% power.
C.
Two of two First Stage impulse pressure transmitters are greater than 40% power.
D.
2 ANSWER: D Importance:
K/A: 054 A2.03 CLOSED BOOK Cognitivelevel: Comprehension 20M-1.1.B " Reactor Control and Protection Summary Description" Issue 4, Rev.1, Page 22_ _
Ref.:
OBJ:
4 LP#:
2LP-SQS-1.5 History Source: LRT Exam Unit i, ILP-LRT III-49,- 2 LOT 2A Exam i1,12/18/97 JTA: 1500030101 d
9
, se j
37
l BVPS-2 I
NRC Exam: 2 LOT 2, Rev 0 Question 8-98-38 l
.g.<
l 38.
Unit 2 is at 100% with all systems NSA. Annunciator A8 9E "125V DC BUS 2-5 TROUBLE" is l
l tit. The following conditions exist:
Al-I A" DC DISTRIBUTION PANEL LOSS OF CONTROL DC" is lit Battery Charger Volts Meter on Battery charger 2-5 reads "0" volts l
Which of the following would result from a loss of voltage on DC Bus 2-57 A.
21 A and 21B Main Feedwater pumps trip on loss of control power to 4KV bus 2A and2D B.
Main Generator Exciter Field Breaker ACB 41 opens on loss of control power l
C.
Reactor trip is generated on 2/3 RCP bus Underfrequency above P-7 D.
Reactor trip is generated when Main Generator Output Breakers PCB-352 and 362 trip open l
ANSWER: C K/A: 058 A2.03 Importance: 3.5/3.6 Cognitive Level: Analysis OPEN BOOK Ref 20M 39.4. AAN "125V DC 2-5 Trouble". Issue 4, Rev. 2, Page 3 LP#:
2LP-SQS-39.1 OBJ: 7 Historv NEW Source:
JTA 0630040101 Student gets copy of reference 4
a L
1 r
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-39 Unit I and Unit 2 are both at 100% power when a HIGH alarm is received on Control Room 39.
Radiation Monitor [2RMC*RQ201]. Control Room Radiation Monitor [2RMC'RQ20 ALERT. Select from the list below the expected response from these alarms A. [2HVC MOD 201 A & C] CR ACU Air Intake and Exhaust Dampers close; [2HVC* MOD 20 i
- DJ CR ACU Air intake and Exhaust Dampers remam cpen.
B. 'Ihe Control Room Emergency Bottled Air Pressurization System will actuate.
C. The Unit I and Unit 2 Emergency Ventilation fans start after a 60-minute time delay.
D. The standby Unit 2 Air Handling Unit, [2HVC*ACU201 A/B] receives an auto start signal.
ANSWER: B K/A: 061 AA1.01 Importance: 3.6/3.6 Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M-43.4 "ADB Local Control Room Area (2RMC*RQ201) High Alarm Level", Issue 1, Rev. 4 LP#:
2LP-SQS-43.1 OBJ: 5 History:
Source: LOT bank #0509 modified TTA: 0130010101 1
d i
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-40
~
'~
40.
The Unit is at 100% with all systems NSA. 21AC-P1106A "CNMT Instrument Air Header Pressure" reads O psig. If air pressure is not restored to containment, which of the following will j
cause a reactor trip?
1 A
1.ow SG level when SG Main Feed Reg. valves 2FWS-FCV478,488 and 498 close.
l B.
Low Pressurizer pressure when PORVs 2RCS*PCV455A and 455B open.
C.
High pressurizer level when I.etdown Orifice inlet valves 2CHS'*AOV200A, B and C close.
D.
High RCS pressure when Main Steam Isolation Valves 2 MSS AOV101 A, B and C Sose.
l ANSWER: C K/A: 065 K3.03 Importance: 2.9/3.4 l
Cognitive Level: Comprehension CLOSED BOOK
(
Ref.:
20M-53.4.3.34.7_" Loss of Contamment Instrument Air", Attachment 1, Issue I A, Rev. 2 LP#:
2LP SOS-34.1 OBJ:
5 History Source: NEW -
l JTA: 0780030101 i
1 I
4 i
40 t
i
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-41
.e..
)
The Reactor Coolant Tavg signal from loop 21 A is lost due to wire breakage. The unit is at 100 41.
with all systems NSA. Which of the following describes the impact on pressurizer level?
A.
Pressurizer level will control at program level for 100% reactor power.
_ Charging Flow Control valve 2CHS*FCV122 opens on indicated low level, actual B.
pressurizer level rises.
\\
Letdown Orifice inlet valves close on M~~i low level, actual pressurizer level rises.
C.
A4-IC " PRESSURIZER CONTROL LEVEL DEVIATION HIGH/ LOW" is lit wit D.
.L heaters on.
ANSWER: A Importance: 3.4/3.8 K/A: 028 A2.02 CLOSED BOOK Cagnitive Level: Comprehension 20M-6.5 Reactor Coolant System Figures and Table", Figure 6-62, Issue 4, Rev. 6 Ref.:
20M-7 " Chemical and Volume System Figures and Tables" Figure 7-15, LP#:
2LP-SQS 6.4 OBJ:
11 History Source: NEW JTA: 002MMM040i 41
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-42
.g;;/
42.
Which of the following conditions will directly initiate stripping of the motor loads from the 4KV Emergency Bus 2DF?
A.
480 Bus 2P voltage drops to 90% of rated voltage for 90 seconds.
f l
B.
4KV Station Bus 2D drops to 75% of rated voltage for 0.33 seconds.
C, Overcurrent on 480 VAC 2P Feeder Bkr 2FII to 480 VAC Emergency Bus 2P.
D.
Emergency Bus 2DF Supply Leads Differential to from 2D to 2DF 4KV Emergency Bus.
ANSWER: A K/A: 056 K3.01 Importance: 3.5/3.9 Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M-36.1.C "4KV Station Service System Major Components", Issue 4, Rev. 3, Page3 of 23 20M 36.5 "4KV Station Service System Fipres and Tables" Issue 4, Rev. O Figure 36-7A LP#:
2LP-SQS-36.1 OBJ: 6 History Source: NEW JTA: 0620040'101 a
se 42
~. _ _... _. _ _ _
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Qu:stion 8-98-43 Control of the Atmospheric Steam Dumps 2SVS*PCVl01 A and 2SVS*PCV1018 has been 43.
transferred to the Attemate Shutdown Panel. If the valves are closed, rising steam pressure will cause which of the following automatae actions to occur first?
A.
Jdain Steam Safety Valves 2SYS'SV101 A, B and C will open.
B.
Atmospheric Dump Valves 2SVS*PCV101 A, B and C will open.
C.
Residual Heat Release Valve 2SVS*HCV104 will open.
D.
Only atmospheric Dump Valve 2SVS*PCV 101C will open.
ANSWER B:
K/A: W/E 13 K2.1 Importance: 3.0/3.1 Cagnitive Level: Comprehension CLOSED BOOK Ref.:
20M 21.1.C " Main Steam System " Major Components", I:: sue 4, Rev. 0 -
20M-21.1.C " Main Steam System Prec,autions, Limitations, Setpoints" Issue 4, Rev. 2 Page 3 and 4
20M 21.5 " Main Steam Figures and Tables" Figure 21-9A and 9-K LP#:
2LP-SOS-21.1 OBJ: 3 History Source: NEW JTA: 0390080101 2
33
i BVPS-2 j
NRC Exam: 2 LOT 2, Rev 0 l
Question 8-98-44
- f I
i %)
A fault occurs on the 4160 VAC Supply Breaker to the 480 VAC Bus 2A, causing it to okThis 44.
will result in:
l A. A Reactor Trip due to the loss of power to a Reactor Trip Breaker Rod Drive M/O set.
i B. A Reactor Trip due to the loss of power to all Gmup 'A' Shutdown Bank rods.
j-C. No Reactor Trip. No power for Rod Drive M/G sets or Control rod power comes from Bus 2A.
l D. No Reactor Trip. All loads on Bus 2A will be automatically tied to Bus 2B via a Tie-breaker.
I i
ANSWER: D i.
j K/A: 001K2.05 Importance: 3.1/3.5 i
Cognitive Level: Knowledge CLOSED BOOK i
l Ref.: 2OM36.4.ACJ" 4160 to 480v Substa Feeder ACB Auto-Trip" issue 1, Rev. 3, Page 1 LP#:
-2LP-SQS-36.1 OBJ: 6
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i Historv Source: New i
i JTA: 0620040101 I
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BVPS-2 J
NRC Exam: 2 LOT 2, Rev 0 Question 8-98-45
\\..
/.
When approaching criticality by rod withdrawal in 20M-50.4 " React
~
45.
Mode 2," which of the following methods will ensure a smooth addition of equal increments reactivity to the core?
l
_ Verification at 128 steps on Control Bank A that Control Bank B begins withdrawa A.
Halting rod withdrawal at every 100 steps on Control Banks A and B to level count rate.
B.
]
Verification of Shutdown Banks fully withdrawn prior to movement.of Control Bank A.
C.
Verification of Reactor Coolant System Tavg above 541*F every 15 minutes until cri+.ical.
D.
l ANSWER: A K/A: 001 KS.59 Importance: 2.7/3.4 CLOSED BOOK Cognitive Level: Comprehension 20M50.4.D " Reactor Startup From Mode 3 to 2", Issue I, Rev. 29, Page 19 Ref.:
Generic Fundamentals Reactor 'Iheorv Fundair.catals, Topic 3, Section B. K1.09, Page 18 OBJ:
4.d LP#:
2LP SQS-1.3 History Source: NEW-JTA: 0010090101 9
i e
E 45
-w-.
~
m
BVPS-2 NRC Exam: 2 LOT 2, Rev 0
, Question 8-98-46
- t.
46..
Given the following:
~*
There is a small break LOCA insule containment.
+
All systems respond as designed.
All S/O pressures are ~_1000 psig RCS Pressure is 1480 psig and dropping slowly.
Contamment Pressure is 12 psig.
~
e Which of the following describes the reason the RCP's must be tripped?
~
A.
To prevent excessive depletion of RCS inventory which could lead to severe core 4
uncovery.
}
B.
To prevent RCP motor bearing damage due to the loss of cooling.
C.
To prevent an RCP seal failure due to the loss of the seal water return flowpath.
D.-
To prevent RCP motor damage due to the high temperature, high humidity operating 3-environment of the containment.
ANSWER: B K/A: 003 K6.04 Importance: 2.8/3.1 Cognitive Level: Comprehension CLOSED BOOK Ref.:
20M-53A. I.E-0 " Reactor Trip and Safety injection" Left Hand Page LP#:
2LP-SQS-53A. I OBJ: -3 Historv 2 LOT 1 NRC Exam - March 1997 Source: NRC Exam Bank-Braidwood 52 JTA: 0030020101 s
v i.
i 4
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-47
- i. )
w 47.
Given the following:
Reactor Power at 50%
Tavg is at 562*F
~
Pressurizer Pressureis at 2235 psig Pressurizer Level is below program at 36%
All control systems are in automatic except Rod Control which is in Manual The Operator notes that Pressurizer level is dropping.
Which instrument failure would cat.,e the drop in Pressurizer level assuming there were no Operator actions taken?
A. Impulse Pressure channel PT446 failed high.
B.
'A' loop hot leg RTD failed high.
~
C. NI-44 Nuclear Instrumentation failed high.
h D. Charging flow transmitter FT122 fails high.
L ANSWER: D K/A: 004K3.02 Importance: 3.7/4. I Cognitive Level: Comprehension CLOSED BOOK Ref.:
20M 7.1.B " Chemical and Volume Control Figures and Tables" Issue 4. Rev. O Figure 07-15
' P#:
2LP SQS-6.4 OBP 13 history Source: NEW s
JTA: 0020090101 l
l l
l-47 l
l BVPS-2 NRC Exam: 3 LOT 2, Rev 0 Question 8-98-48
( )
l 48.
The unit is at 100% with all systems NS A. A Safety injection signal is generated High Head l
Safety injection Pumps Suction Valve [ 2CHS*LCVI15B] opened BUT [2CHS*LCVIISD) failed to open. What is the impact of this action on the Chargmg Pump suction flow?
A.
Both operating charging pumps will receive suction flow from the VCT.
j 1
t i
B.
One charging pump will continue to take suction from the VCT and one charging pump will take suction from the RWST.
.L C.
One charging pump will take suction from the RWST. The other charging pump will have I
no suction until operator action is tuen.
1 L
I D.
Both operating charging pumps would take suction from the RWST via
[2CHS*LCVI15B).
(
ANSWER: D K/A: 004 K1.23 Importance: 3.4/3.7 Cognitive Level: Comprehension CLOSED BOOK Ref.: 20M-7.5" Chemical Volume Control System Tables and Figures" Issue 4, Rev. O, Figure 7-1 I
LP#:
2LP-SQS 7.1 OBJ:
7 Historg I
Source: Taken from NRC 2, Question 266. ID. 519Q
-~
JTA: 0040150101 l
l J
O e
4S I
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98 49 49.
Unit 2 is in Mode 3 with the following conditions:
Tavg is at 400*F and stable
_ RCS Pressure is at 1000 psig and stable Steam Generator Pressures are at 230 psig and stable
'Ihe Control Room Operator turns on Pressurizer Heater Banks A and B. With'no further operator actions, the first actuation will be:
A.
Safety injection Signal on low steam generator pressure B.
Safety injection Signal on low RCS pressure C.
AMSAC actuation on low steam generator pressure D.
Reactor Trip signal generated on love RCS pressure
()
ANSWER: A K/A: 013 Kl.01 Irnportance: 4.2/4.4 Cognitive Level: Analysis CLOSED BOOK Ref.: 2OM-1.2.B " Reactor Protection Setpoints", Issue 4, Rev. 3, pages 4 and 5 LP#:
2LP 5QS-1.2 OBJ:
10 c
Historv LRT 1997 Module IV Written exam Source:
JTA: 0120050101 A
49
BVPS 2 NRC Exam: 2 LOT 2, Rev 0
~
Question 8-98-50 l'
i
- 50. '
During 100% power nr tration, the lowett (bottom) Data 'A' coil for a Shotdown Rank ' A' rod j
fails (open circuit.), What is the effect of this failed coil on the Digital Rod Position Indication (DRTI) system?
4 A. No effect. The rod will indicate normally until it is fully inserted.
B. No effect. The Data 'B' coils will compensate and provide normal indication for all rod elevations.
l C. All indication for the rod will be lost until the failed Data 'A' coil is removed from the circuitry by taking the Accuracy Mode Selector switch to the Data 'B' position.
t D. DRPI will automatically switch into the half-accuracy mode. A Rod Bottom and General Waming Status light will be flashing for the affected rod.
4 i
l ANSWER: D K/a: Ol4A2.06 Importance: 2.6/3.0 Cognitive Level: Comprehension CLOSED BOOK Ref.: 20M-1.1.B " Reactor Control and Protection" Page 18 of 22 issue 4 Rev.1 l
LP#:
2LP-SQS-1.4 I OBJ:
4 E
History:
1 Source: New i
i I
JTA: 0010090101 l
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BVPS 2 q
NRC Exam: 2 LOT 2, Rev 0 Question 8-98-51 4
t 1)
Following the perforr.ance of the Daily Heat Balance Calculation, reactor power is determined to 51.
be at 99.45%. Power Range nuclear instruments (Nis) read as follows:
N-41 = 99.5 %
N-42 = 99.3 %
N-43 = 99.6 */.
N-44 = 99.I %
Which, it any; Ni channels require adjustment?
A. All channels need to be adjusted to 99.4 %.
B. N-41 and N-43 need to be adjusted to < 99.45 %.
C. N-42 and N-44 need to be adjusted to >99.45 %.
D. No channels require adjustment.
ANSWER: C K/A: 015A1.01 Importance: 3.5/3.8 Cognitive Level: Analysis CLOSED BOOK Ref.: Daily Heat Balance 20M-54.4.Cl Issue i Rev.11 Page 2 of 5 LP#:
2LP-SQS-2.1 OBJ:
14 History:
Source: LOT Bank #0752 modified JTA: 0150070201 d
4 d
51
BVPS-2 NRC Exam: 2 LOT 2, Rev 0
.g Question 8-98-52 52 The B Train Inecre Thermocouple Reference Junction Box has lost input from the instalini RTD's that monitor temperature of the box and transmit the temperature to the Plant Safety Monitor
[
System display.
i If the Reference Junction box temperature rises from 160*F to 180'r, then thermocouple EMF would and indicated temperature would A.
drop, drop B.
drop, rise C.
rise, drop 4
D.
rise, rise l
h_.
_ ANSWER: A 2-K/A: K6.01 Importance: 2.7/3.0 Cognitive Level. Comprehension CLOSED BOOK 1
Ref.: Generic Fundamentals l
LP#.
2LP SQS-3.1 OBJ:
9 Historv Source NEW
~I JTA: 0170020101
.v 4
9 k
52
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-53 Containment Annunciator Al-lE" CONTAINMENT AIR PARTIAL PRESS HIGH/l.OW"is fit 53.
Air Partial pressure is rising. Which of the following is the maximum pressure that could be
' allowed?.
A.
8.9 psia with a Service Water temperature of 60 degrees B.
10.2 psia with a Service Water temperature of 60 degrees C.
10.4 psia with a Service Water temperature of 60 degrees D.
10.5 psia with a Service Water temperature of 90 degrees ANSWER: B K/A: 022 A1.01 Importance: 3.6/3.7
. Cognitive Level: Analysis OPEN BOOK
(. :-
20M-12.4.AAA "Contsinment Air Partial Press High/ Low", Issue 4, Rev.1, Page 3 s-Ref.:
BVPS 2 Curve Book CB-19A, Issue 7, Rev. 0 l
LP#:
2LP-SQS-12.1 OBJ:
10 History Source: NEW JTA: 0260060101 Student gets Curve 2
h
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l BVPS 2 NRC Exam: 2 LOT 2, Rev 0 l
Question 8-98-54 l
l 54 Due to an engineering conwrn. 2RSS P21 A and 7RSS P2lC Recire Spray Pumps were declared inoperable. Based on this situation, which of the following is the time limit allowed by Technical Specifications for restoration prior to starting a unit shutdown?
A.
2RSS-P21 A must be operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and 2RSS-P21C in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B.
2RSS P21 A must be operable within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 2RSS P21C in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
C.
2RSS-P21 A and 2RSS-P21C must be operable in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
D.
2RSS-P21 A and 2RSS-P2lC must be operable in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l l
ANSWER: C K/A: 026 2.2.22 Importance: 3.414.1 l
Cognitivelevel: Analysis OPEN BOOK (w '.
-)
Ref.:' BVPS Unit 2 Technical Speci6 cation 3.6.2.2 and 3.5.2 LP#:
2LP SQS 11.1 OBJ:
9 Historv 1
Source: NEW i
JTA: 3410180302 Student get Tech Spec l
1 l
l t
2 f.
i 54
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 i
Question 8-98 55 i
,)
With the unit operating at 100% power and all systems NS A, which of the following listed features 55.
will act to provide Net Positive Suction Head for the Main Feedwater Pumps?
-2CNM-AOV100 Coch Feedwater Heater Bypass Valve will open on low Feedwater A.
Pump Suction header pressure.
Condensate Spill valve 2CNS-MOV105 will open to divert condensate from Turbine Plant B.
Demineralized Water Storage Tank on low condensate header discharge pressure.
1 Standby Condensate Pump will start on low suction pressure to the Main Feedwater C.
Pumps.
Standby Condensate Pump will start on low condensate header discharge pressure.
D.
ANSWER: D c
Importance: 2.2/2.6 k....;./
K/A: 056 K4.14 CLOSED BOOK Cognitive Level: Knowledge 2OM 22 A.I.D " Condensate System Instrumentation and Control", Issue 4 Rev. 2, Pages 1-9 Ref.:
OBJ: 5 LP#:
2LP SQS-22A.!
Historv NEW Source:
JTA 0590030101 2
9 55
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-56 56 To minimi7e the time that a Main Feedwater Pump Motor [2FWS P21 Al} takes to reach rated speed, the start circuit of the Main Feedwater pump will:
A.
. Block start of the Main Feedwater pump if the Feed Pump Discharge valve [2FWS-MOV150A] is closed.
B.
Delay the start of the Main Feedwater Pump motor [2FWS-P21 A2).
C.
Block starting of the Main Feedwater pump until recirculation valve [2FWS-FCV150A] is e_
open.
D.
Delay starting of the Main Feedwater Pump motor [2FWS-P21 A2] until discharge valve
[2FWS-MOV150A] is open.
ANSWER: B l._.
K/A: 059 K4.14 Importance: 3.1/3.2 Cognitive Level: Analysis CLOSED BOOK Ref.:
20M-24.5 " Steam Generator Feedwater System Figures and Tables" Figure 24-06A, issue 4, Rev.
1 I
l LPit:
2LP SOS-24.1 OBJ:
6 l
Histors Source: NEW I
JTA: 0590030101 e
56
i BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-57 w-
- 57. Annunciator A2-3H " SAFETY SYSTEM TRAIN A INOPERABLE"is lit. Annunciator A2-4H
" SAFE 1Y SYSTEM TRAIN B INOPERABLE" is off. Which of the following would explain this condition? -
A.
Turbine Driven Auxiliary Foodwater pump overspeed latch not reset.
B.
Control of 2 MSS *SOV 105A and 2 MSS *SOV105D is selected to the Emergency Shutdown Panel.
e-C.
Control transfer switches for 2 MSS *SOV105 A and 2 MSS *SOV105D are NOT reser D.
Any Main Steam Supply Valve to Turbine Driven Auxiliary Feedwater Pump 2 MSS *AOV105A through F closed.
ANSWER: A l_
K/A: 061 K4.06 Importance: 4.0/4.2 Cognitive Level: Knowledge CLOSED BOOK Ref.:
2OM 24.1.D " Steam Generator Feedwater System" !ssue. 4 Rev. 2 Page 23 2OM24.5 " Steam Generator Feedwater System" issue. 4 Rev i Figure 24-11 LP#:
2LP hQS 24.1 OBJ:
10 History Source: NEW t
ITA: 0130010101 NOTE Change to Outline NEW K/A l
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i 57 L
l i
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-58 SR The imit is at 100% pnwer with all systems NSA 2 l A Steam Generator Aux. Feedwater Throttle Valve (2FWE-FCV100E) was closed for an approved BVT test and will not re-open. Which of the following actions must be taken?
A.
Restore the 2FWE-FCV100E and the 2A AFW train to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B.
Place the unit in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and HOT SHUTDOWN within an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c C.
Align the Turbine Driven Auxiliary Feed Pump to the B Auxiliary Feed Header within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
D.
Restore 2FWE-FCV100E to OPERABLE status within I hour or be in HOT STANDDY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ANSWER: B K/A: 061 2.1.12 Importance: 2.9/4.0 Cognitive Level: Analysis OPEN BOOK Ref.:
BVPS 2 Technical Specification 3.7.1.2" LP#:
2LP SOS-24.1 OBJ:
13 Historv Source NEW l
JTA: 3410180302 Student gets Tech Spec
_l 4
l l
58 I
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-59
~
i The Spare Battery Charger 7-7 will be removed from replacing Battery Charger /-l and will 50 replace charger 2 3. Which one of the follomag limits applies?
. Baeery 2-1 must be disconnected from DC Bus 2-1 while the Spare Charger is removed.
A.
B.'
Battery Charger 2-1 must be paralleled with the Spare Charger befo're the Spare Charge is removed.
C.
Uninteruptible Power Supply UPS*VITBS2-3 must be on altemate AC power sourcec when the Spare Charger is in service on BAT 2-3.
The Spare Charger FLOAT / EQUALIZER switch must be operated in " FLOAT" while in D.
senrice.
ANSWER: C qv.
K/A: 063 K1.01 Importance: 2.7/3.2 Cognitive Level Knowledge CLOSED BOOK Ref.: 20M-39.4.D " Placing Spare Battery Charger in Service", Issue 4, Rev. 5, Precaution and Limitation II. C, page i Of 5 LP#:
2LP-SQS 39.1 OBJ:
9
,Rstory Source: NEW JTAi 0620040101 e
59
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-60 60 Liquid Waste E&ent Monitor 2SGC-RQ100 is nut of service. He Steam Generator Blowdown Holding Tank 2SGC-TK21 A is to be released. What action will enable the release of the tank with j
the monitor out of service?
A.
2SGC TK21 A must be recirculated for sufficient time to turn volume over twice.
B.
Two independent samples for 2SGC-TK21 A must be analyzed.
C.
A Senior Licensed Operator must confirm release rate calculations and valve alignment.
D.
Emergency Outfall Flow must be adjusted to exceed 1000 gpm prior to and during release.
1 ANSWER: B I
K/A: 068 2.3.6 Importance: 2.1/3.I l
Cognitive Level: Knowledge CLOSED BOOK
~
I Ref.: ODCM Appendix C Page C-12 j
LP#:
2LP SQS-43.1 OBJ:
7 History Source: NEW JTA: 3410120302 i
.i 1
60
BVPS-2 NRC Exam: 2 LOT 2, Rev 0
- Question 8 98-61 Due to high activity being vented from the Boron Recovery System Degasifiers it has been d 61 to place the Waste Gas Charcoal Delay Beds {2GWS-TK22A(BXCXD)] in se'rvice in Gas System. Which of the followmg functions will be served by this action?
A.
Krypton isotopes will be delayed for up to 30 days for decay B.
lodine 131 will be delayed for up to 30 days for decay C.
Xenon isotopes will be delayed for a minimum of 30 days for decay e
Krypton 85 will be delayed until decayed below nummum detectable levels D.
ANSWER: C K/A: 071 2.1.28 Importance: 3.2/3.3 Cagnitive Level: Knowledge CLOSED BOOK
~
((q Ref.: 20M-19.1.C " Gaseous Waste Disposal System" Page 2 of 13 issue. 4 Rev.0 OBJ: 3 LP#:
2LP-SQS-19.1 Estory Source: NEW JTA: 0710080104 e
61
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98 62 62.
When using the RM. I I Console, the Key Lock function must be used to perfonn which of the following functions?
A.
-Acknowledge system alarms with the SYSTEM ACK function key B.
Request a filter advance using the FILTER function C.
Clear the RM 1 I screen with the CLEAR SCREEN entry function key D.
Reset RM-80 setpo'mts in SUPERVISORY mode i
ANSWER: D K/A: 072 A4.01 Impc.tance: 3.0/3.3 Cognitive Level: Knowledge CLOSED BOOK
~
Ref.: 20'
~3.1.D " Radiation Monitoring System" Page 4 of I8. Issue. 4 Rev. 0
(. _q LP#:
OBJ:
History Source: NEW JTA: 072BBB0221 Warning l'JA change to outline e
4
+
D2
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98 63
\\_.-
The unit it in Mode 3 in preparation for startup. The root stop isolation valve for the high-63 pressure side of RCS LOOP "A" flow transmitters,2RCS-414,415 and 416 has been isolated and the high pressure side depressurizes. Which of the following would be an expected response?
A.
Annunciator A2-SE " Reactor Coolant Loop Flow Low" is lit.
B.
A reactor trip signal is generated on low reactor coolant system flow.
C.
Annunciator A2-4G " Reactor Coolant Loop By-Pass Flow Low" is lit.
a D.
An Overpower / Delta T reactor trip signal is generated on low reactor coolant system flow.
ANSWER: A K/A: 002 A1.05 Importance: 3.1/3.7 Cognitive Level: Comprehension CLOSED BOOK Ref.:
2OM1.2.B " Reactor Control and Protection Precautions, Limits and Setpoints", Issue 4. Rev. 3 LP#.
2LP-SOS l.2 OBJ:
4 Historv Source: NEW JTA: 0020090101 i
63 m
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. BVPS-2 NRC Exam: 2 LOT 2, Rev 0
)
Question 8-98 64 j
i l
j' 64.
Following a Loss of Gehnt Accident (I.OCA), RCS pressure is 300 psig and slowly dropping.
l Which of the following statements describes what should be the normal status of the Emergency l
Core Cooling Flow at this point in time?
A. Constant HHSI flow exists with no LHSI flow.
l B; increasing HHS1 flow exists with no LHSI flow.
C. Constant HHSI and LHS1 flow exists.
a D. Increasing HHSI and LHSI flow exists.
ANSWER: B K/A: 006K5.06 Importance: 3.5/3.9 Cognitive Level Knowledge CLOSED BOOK C
Ref.: 2OM 53.A.I.ES 1.2 " Post LOCA Cooldown and Depressurization" Issue IB, Rev. 5, LP#:
2 Historv:
Source: LOT Bank #0490 JTA: 3010020601 I
I 64
- ~ - -.-.. -. -. -
. BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-65
- s The unit is heating up with the Reactor Coola 4 Pressure at 885 psig. Pressurizer Pressure Relief 65 Tank pressureis at 40 psia and PRT temperature is rising. What would be the mammum temperature that would appear on the Pressurizer Safety Relief Valve Tail Pipe Teimperature Indicator if one of the Pressurizer Safety valves were leaking?
A.
320 degrees B.
420 degrees C.
520 degrees D.
647 degrees ANSWER: A K/A: 010 Al.09 Importance: 3.4/3.7 Ceitivelevel: Cuinper=cion OPEN BOOK Ref.:
Steam Tables LP#:
2LP.SQS-6.4 OBJ:
3 History Source: NEW JTA. 0070030101 Student gets steam tables
. o 4
e 4
4 9
65
... -. ~..
i BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-66 66.
The unit is at 100% powcr with n!! systems NSA. Seal injection flow is the minimum allowed per operating procedure to each Reactor Coolant Pump. The flow controller for 2CHS*FCV122 has manuallywpositioned to demand What is the charging flow and seal injedian flows after 2CHS*FCV122 reaches its new demanded position?
A.
No charging flow and seal injection flow to each RCP beidw Aunimum.
B.
Maximum charging flow and seal injection flow to each Reactor Coolant Pump below minimum.
C.
Maximum charging flow and seal injection flow to each Reactor Coolant Pump i.
above minimum.
D Vo charging flow and seat injection flow to each Reactor Coolant Pump above nummum.
ANSWER: D K/A: 011 K1.02 Importance: 3.3/3.5 Cognitive Level: Comprehension CLOSED BOOK Ref.: 20M-7.1.C " Chemical and Volume Control System", Issue 4, Rev. 3 Page 23 LP#:
2LP SQS-7.1 OBJ: 5 Historv Source: NEW JTA: 0040150101 Assumptions: RCP seal injection at minimum of 6 Epm A
O e
e f
66
1 BVPS-2 NRC Exam: 2 LOT 2, Rev 0
'y Question 8-98-67
^
The plant is operating at 100% power when a loss of 4160 VAC Bus 2A occ 67.
reactor trip. The following signals were generated:
- 1. Low Reactor Coolant Flow Trip.
-2.SG21 A (21B) (21C) Iow level Reactor Trip.
- 3. RCP Breaker Trip.
- 4. Generator Trip Due to Turbine Trip.
Which one of the following choices depicts the order in ivhich the signals were generated?
A. 2, 3, 1, 4 B. 3, 1, 2, 4 C. 3, 4, 1, 2 D.1,3,4,2 O
ANSWER: B Importance: 3.9/4.3 K/A: 012K4.02 Cognitive Level: Comprehension CLCSED BOOK Ref.: 20M-1:2.B
- Reactor Control and Protection" Precautions, Limitations and Setpoint r
OBJ:
7 LP#:
2LP-SQS-1.1 History Souice. LOT Darl #0220 sTA: 0120050101 s
e O
P u.
9 67
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-68
%v 68.
Given the following-I The Unit is operating at 100% power with all systems NS RCS Tavg control channels are indicatmg as follows:
"A" loop - 580 *F e
"B" loop - 582 'F e
"C" loop - 581 'F
=
"B" loop Tcold instrument begins to slowly fail LOW.
e Which of the following describes the response of the Tavg control system to this failure?
As the "B" loop Tavg drops, the selected Tavg will swap from "C" loop to..
A.
"A" loop, then to "B", then finally back to "C"
,B.
"B" loop, then to "A", then fmally back to "C".
-(j, C.
"B" loop, then to "A", and remains there.
D.
"A" loop and remair.s there.
ANSWER: C K/A: 016 A3'.01 Importance: 2.9/2.9 Cognitive Lesel: Comprehension CLOSED BOOK Ref.: 20M 6.1.D Reacer Coolant System, Issue 4., Rev. O page 18 LPN-2LP-SQS 6.5 OBJ:
5.a History NRC 2 LOT 1-March 1997 Source: M-North Anna - 44 JTA: 3440210'3b2
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6S
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-69 t
Contaitunent Ilydrogen concentration has reached 1.5% when B Train Recomb 69.
the H2 concentration in Containment be affected?
Hydrogen concentraten will peak above the 4% design basis with only the A.
service.
Hydrogen concentration will remain below the 4% design basis using only th B.
Containment venting must be conducted to ensure Hydrogen concentration remains C,
than 4%.
Hydrogen concentration will remain less than 4% if Train B suction is aligned to D.
suction of the A Train Recombiner.
ANSWER B Importance: 3.3/4.0 K/A: 028 K3.01 CLOSED BOOK Cognitive Level: Comprehension 20M-46.1.A " Post DBA Hydrogen Control System", Issue 1, Rev. 5 page i Ref.:
l UFSAR Figure 6.2.136 OBJ:
1 LP#:
2LP-SQS-46.1 History 2 LOT 2,9/26/97, Exam (6.I3.8.1,I5.1,20.1,46.1.47.1)
Source: Modified from SQS Question 1422 JTA: 3010020601 4
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+
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-70 70.
The suction piping of the fuel pool coolmg pumps,2FNC'P21 A and 21B, has ruptured and cannot be isolated. Choose the lowest resulting fuel pool level by design that will result?
_A.
Approxunately 10 feet above spent fuel assemblies.
B.
' Approximately 23 feet above spent fuel assemblics, C.
Appmximately a level equal to the top of the fuel assemblies.
D.
The spent fuel pool will completely drain.
ANSWER: A' K/A: 033 K3.03 Importance: 3.0/3.3 Cognitive Level: Comprehension CLOSED BOOK Ref.: 2OM 21.1.B Spent Fuel Pool Cooling and Purification System" Summary Description, Issue 4,
~
Rev.1,page 3 of 4 LP#:
2LP - LRT Vill - 149 OBJ:
10 History 2 LOT 2,9/26/97, Exam (6.13,8.1,15.1,20.I,46.1,47.1)
Source LRT Question 1140:
JTA: 033-A0101 9
1 e
a e e c.
p 70 e
9 c
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1 1'
BVPS-2 i
NRC Exam: 2 LOT 2, Pav 0 Question 8-98-71
! (J 1
Unit 2 is at 35% with all systems NSA. First Stage impulse pressure transmitter 2 71.
selected for control. If the transmitter were isolated and vented, what would be the im i
j steam generater level control system?
Steam generator level would exceed program level causing feedwater flow to drop.
i A.
Steam generator level would drop to no-load level causing feedwater flow to rise.
B.
Indicated steam flow would exceed feed flow causing feedwater flow to rise.
C.
Indicated steam flow would be less than feed flow causing feedwater flow to drop.'
l D.
l i
i j
j ANSWER: A 1
Importance: 3.4/3.6 i
K/A: 035 A2.03 CLOSED BOOK j
Cogaitive Level: Comprehension
~
O
_Ref.:2OM-24.4.IF " Main Steam Instrument Failure", Issue 4, Rev. 5, A"achment 5, page 38 of 43 i
OBJ:
4 LP#:
2LP-SQS-24.1 i
Historv Source: NEW JTA: 0350060101 1
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l c
BVPS 2-NRC Exam: 2 LOT 2, Rev 0
-Question 8 98-72 uv.
72.
The unit is on natorni circulation, following a trip and loss of off site power. Emergency Diesel Generator 2-1 failed to start. Which of the following flow paths will be removing heat from the
. RCS? (Assume no operator actions)
A.
21 A and 21B Steam Generator Atmosphenc Dump Valves only B,
21C Steam Generator Atmospherie Dump Valve only.
C.
All steam generators via 2SVS*HCV104 Residual Heat Release Valve D.
All steam generators via Main Steam Safety Val /es i
ANSWER: D l
K/A: 039 K3.05 Ir.,portance: 3.6/3.7 l
L Cognitive Level: Comprehension CLOSED BOOK l
l -
Ref.: 2OM21.3.C " Power Control and Switch lim" issue 4 Rev 7 Page 2 of 50 l
I LP#: - 2LP-SQS 21.1 OBJ: 4 t
1 Historv Source: NEW l~
l JTA: 0390080101 l
i p
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't 4
I' ' '
'k
'i; I
g 72
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-73 w
1 73.
The unit is at 100% with all systems NSA. The followmg pump sets are runnmg:
h Cord u;atc Pumps 2CNM* P21 A and P21C
-Service Water Pumps 2SWS*P21 A and P21B The 4KV breaker Supply Bus 2AE to 2A, ACB [2A10], opens on a spurious trip with detected. Which of the following will be the response of Service Water pumps and th pumps to the opening of the breaker?
SWS pump 2SWS'P21 A powered from 2A SSST, all other pumps NS A.
A.
SWS pump 2SWS*P21 A powered from EDG 2-1, all other pumps NS A.
B, SWS pump 2SWS'P21 A and CNM p imp 2CNM*P21 A powered from 2A SSST C.
SWS pump 2SWS*P21 A powered from EDG 2 1, CNM pump 2CNM'P21 A o D.
pump 2CNM*P21C on.
O ANSWER: B Importance: 2.8/3.1 K/A: 062 K4.03 Cognitive Level: Comprehension CLOSED BOOK Ref.: 20M-36.l.D" 4KN Station Service System Instrumentation and Controls" Issue 4, Re c
to20 OBJ: 4 LP#:
2LP SOS-36.1 l
1 Estorv
' Source: LOT exam bank 647 JTA: 0620040101 D
73
... _ _ _.. _ _ _ _... ~. _. _. _. _ _. _. _ _ _ _ _ _.. _... _., _ _ _ _. _ _
+
BVPS-2 NRC Exam: 2 LOT 2, Rev 0
' Question 8-98-74
..\\,y
. Both 4KV Emergency Busses have been de-energized for over 30 minutes. Pressurizer level is off 74.
scale low with no cooldown in progress. All steam generators are less than 5% narrow range.
When Diesel Generator 2-1 is loaded on the bus wluch of the following pumps will need L+--- 4 **
verification of starting per ECA-0.0 " Loss of All AC Power"?
A.
HHSI pump 2CHS*P21 A B.
Auxiliary Feedwater pump 2FWE*P23A C.
Component Cooling Water pump 2CCP*P21 A D.
Service Water Pump 2SWS*P21 A 4-ANSWER D l
Importance: 3.1/3.6 K/A: 064 K1.01 e-Ceitive Level: Compiek=3 on CLOSED BOOK i
i Ref.: 20MS3.4.ECA-0.0 " Loss ofAll AC Power" issue IB, Rev. 4 Step 37 LP#:
2LP-SQS 53.3 OBJ:
3
_Historv Source: LOT exam bank 560 4
JTA: 3010060601 A
O e
O Ie p
e 74
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98 75 q,)
Unit 2 is at 100% power with all systems NSA. An " ALERT" alarm on 2CCP RQ100 o 75.
Steam Generator 21B has high activity due to a small tube leak. Level is rising in the C tanks. Wluch of the below listed heat exchangers is hkely to be leakmg?
Boron Recovery Degasifier Vent CWear 2BRS-E22A A.
Reactor Coolant Pump Seal Water Return Heat Exchanger 2CHS*E21 B.
Steam Generator Blowdown Heat Exchanger 2BDG-E22 C.
Letdown Non-Regenerative Heat Exchanger 2CHS'E22 D.
ANSWER: D Importance: 3.6/3.9 K/A: 073 Kl.01 Cognitivelevel: Knowledge CLQSED BOOK 2OM43.4.AAE tmIC,,T.r,c,nent Cooling Water (2CCP-RQ100) Alert Alarm Level""
-(('}
Ref.:
obi: 9 L
LP#:
2LP-SQS - 43.1 l-History Source,: Based on SQS 1203 I
JTA: 0000420401 l
i L
l.
!L' l
1 l
).5
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 j
Question 8-98-76 l
' Q)
A request has been submitted for a Temporary Operatmg Procedure to allow closing Main 76.
Condenser Outlet valves 2CWS* MOV100C and 100D to manually clean both waterboxes under l;
o one clearance. Which of the followmg must be resolved prior to approving the procedure change?
~
A.
Service water retum from the CCS HX's to the cmling tower will be blocked.
B.
Service water must be aligned to the Emergency Outfall to prevent overpressure of the condenser.
C.
Service water retum from the CDS Chillers must be aligned to Unit 1 Cooling Tower i
Blowdown.
D.
Service water pump seal injection water must be shifted from Filtered Water to the Service Water strainers.
ANSWER: A O>
K/A: 075 K4.01 Importance: 2.5/2.8 Cognitive Level: Comprehension OPEN BOOK Ref.:
20M 31.2.A " Circulating Water System Precautions and Limitations", Issue 4, Rev.0, Precautions 18 and 19" OBJ:
LP#:
i Historv l
Source: Based on SQS question 60 JTA: 0750140101
. Copy of system print OM Figure 30.1 O
0 4
i 76 l
I
1 BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-77
~ $
The containment instrument air is currently being supplied by Statisn Instrument A 77.
21AC*MOV131. If a CIA signal were generated which of the following would be the the Contamment instrument Air system 21AC'MOVl31 will close and the lead Containment instrument Air compressor w A.
21AC*MOV130 will close and the lead Containment Instrument Air compressor w B.
21AC* MOV 131 will close and all containment air valves will go to fail position.
.C.
21AC*MOV130 will close and all containment air valves will go to fail, position.
D.
i ANSWER: D Importance: 2.7.2.7 K/A: 079 A4.01 OPEN BOOK Cagnitive Level: Analysis 20M-34.5" Compressed Air Systems Figures and Table", Issue 4. Rev. 3 Figures 3 Ref.:
OBJ: 5 LP#:
2LP-SOS-34.1 j
Historv j
Source: Modified from LOT ltem 506 Students get Figures 34.3 and.7A JTA: 078AAA0101 d
S J
77
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-78 b
A CO discharge is imminent in a protected zone. Which of the following actions are available to 2
78.
alert personnel in the protteted zone?
A.
Predischarae waming hom sounds inside the protected zone.
B.
Blue rotating lights are initiated in all occupied areas for the protected zone.
C.
The CO connins a Wintergreen oderizer to flood the zone prior to discharge.
2 D.
All key card ccotrolled entrance doors are locked closed for the affected zone.
ANSWER: A K/A: 086 A4.04
- importance
- 3.1/3.4 Cmitive Level: Knowledge CLOSED BOOK 20M 33.1.D " Fire Protection Systems Instrumentation and Control", Issue 4. Rev. 2, Page 4 of i 1 Ref.:
(
LP#:
2LP-SQS-33 OBJ: 3 Historv 2 LOT 2. I1/7/97. (Fire Protection, Alt. Safe Shutdown. Injury and Casualty Control)
Source: Based on SQS 1132 JTA: 0860070101 1
a 78
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98-79 When exiting the containment using the 18 inch Escape Manway,2PHS*Pil0% " Altim 79, 2PHS* F1101 " Speed Indicator" provide what function?
Input to the Emergency Door "OPEN" alann bell while opening the outside door.
A.
Provide an audible whistling sound until air pressure differential is less than 0.5 psig.
B.
Guide the door operator to control depressurization rate while equa!izing pressure.
C.
. input to the Personnel Hatch door interlock rir:g while equalizing pressure.
D.
4 ANSWER: C Importance: 2.5/3.2 K/A: 103 K4.04 Cognitive Level: Knowledge CLOSED BOOK 20M-47.4.C "18 inch Escape Manway Operations", issue 4, ~.ev. 2, Not.e before step 2 on page 4 Ref.:
of6 OBJ:
4 LP#:
2LP.SQS047.1 Historv Source: Based on SQS Ii14 g JTA: 0210010101 l
l s
l 79
BVPS-2 l
NRC Exam: 2 LOT 2, Rev 0 Question 8 98 80 l
80.
The plant is in Mode 4 on RHR with a cooldown to Mode 5 in progress. The "A" Train of RHS is in service. During the construction of scaffolding on the RHR platfonn, the instrument air line to l
[2RHS*HCV758A) is broken, resulting in the loss of air to the valve. Which of the following describes the impact on RHS Heat Exchanger Outlet Flow Control Valve 2RMS*HCV758A and the status of the RHS system after the loss of air?
A. The valve fails open. [2RHS*FCV605A] will automatically close to control flow and naintain flow at pre-event. Temperature will drop.
I B. The valve fails open. The RHR pump will trip on overcurrent due to run-out. RCS temperature will initially drop and then rise after the pump trips.
C. The valve fails closed. [2RHS*FCV605A] will automatically open to maintain flow. Temperature will rise.
D. The valve failing closed. [2RHS*FCV605A] will need to be manually opened to maintain flow.
Temperature will drop until FCV605A is opened.
ANSWER: A l'
K/A: 005 A2.0h importance: 2 9/2.9 l
i Cognitive Level: Comprehension CLOSED BOOK l
' Ref.:
20M 10.5" Residual Heat Remosal Systems Ficures and Tables" Ficure101 j
LP#:
2LP SQS 10.1 OBJ:
5 l
Historv:
i Source: New JTA: 0050080101 i
l Sn
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 i
Question 8-98-81 The reactor trips from 100% power. The following conditions exist:
t 81.
Steam Dump Mode Selector Switch is in Tavg position Reactor Trip Breaker "B" indicates closed
)
Which of the following plant responses will be the result of the above conditions?
The C-20 Permissive 180 sec. time delay is blocked and AMS AC actuates.
A.
The Steam Dump Load Rejection controller maintains Tavg within 5 F of no-load Tavg.
B.
Feedwater Isolation Signal on Low Tavg is blocked.
C.
The "B" Train Safety injection Automatic Actuation signal is blocked.
D.
ANSWER: B Importance: 3.7/3.9 K/A: 041 K4.17 CLOSED BOOK Cognitive Level: Comprehension 20M-21.5 " Main Steam System Figures and Tables" Issue 4, Rev. 2 Figures 219G to K _
Ref.:
OBJ:
3 LP#.
2LP-SQS 1.2 Historv l
Source: LOT Exam question 31 JTA: 012008010l __
9 81
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i BVPS-2
}
NRC Exam: 2 LOT 2, Rev 0 Question 8-98-82 82.
During a turbine startup, the Valve Position Limiter is inadvertently left at 100% when the turbine l
latch pushbutton is pushed Which of the following valve actuations occur?
l
- 1. Throttle Valves Open
- 2. Govemor Valves Opea l
- 3. Reheat Stop Valves Open A. I and 2 B. 2 only C. I and 3 D. 2 and 3 l
ANSWER: D K/A: 045A4.06 Importance: 2.8/2.7 Cognitive Level: Comprehension CLOSED BOOK Ref.: 20M 52.4.A " Increasing Power From 5% Reactor Power and Turbine on Tumine Gear to Full Load l
)
Operation" Issue I, Rev. 33, pace 20 to 22 LP#:
2LP SQS 52.1
. OBJ:
9 Historv:
)
l Source: LOT bank 40492 modified 1
l JTA: 0450020101 l
l l
l 82
. _.. _ = _ _.
BVPS 2 NRC Exam:2 LOT 2, Rev 0 Question 8 98 83 Pressurizer ReliefTank (2RCS-TK21) alann A4-3H " PRESSURIZER RE 83.
TROUBLE" is lit. Computer address LO494D is in alarm. Which of the following could be cause of this alarm?
A.
2CHS*Pil45 Letdown pressure is 700 psig.
B.
2CES*Pil22 Charging Pressure is 2275 psig.
C.
2CHS*Pil38 Excess Letdown Pressure is 135 psig.
2RCS*PI402 Rx Coolant System pressure is 150 psig.
D.
ANSWER: A Impartance: 2.7/2.9 K/A: 007 A3.01 Cognitive Level: Analysis OPEN BOOK 20M-6.4. AAY " PRESSURE RELIEF TANK TROUBLE ", Issue 4, Rev. O, page i l of 18 Ref.:
LP#:
2LP SQS'-6.4 OBJ:
15 l
l History Source: NEW Student gets ARP JTA: 0070030101 l
83
. - - -. -. _... ~. - -.
BVPS-2
' NRC Exam: 2 LOT 2, Rev 0 Question 8 98-84 84.
Two separate charuiels, Pressurizer Pressure 2RCS'PT444 and PT445, are pr'ovided for Pressurizer Pressure Control.
Which of the following statements describes the interface between the two channels?
A. All indications, controls, and alarms in the control room are associated with either PT444 or t
PT445 and cannot be selected between the two.
B. A control switch is provided to determine which channel is used to accomplish various control functions.
C. The two channels (PT444 and PT445) use a conunon D/P cell with two transmitters connected to the one common D/P cell.
D. The signal from the two transmitters is auctioneered high and then compared to the pressure setpoint that is controlled by the Master Pressure Controller.
i ANSWER: A K/A: 2.1.28 Importance: 3.2/3.3 Cognitive Level: Knowledge CLOSED BOOK
+
Ref.: 20M 6.5 " Reactor Coolant System Figures and Tables", Issue 4. Rev. 6, Figures 6 36 and 6 37 LP#:- 2LP SOS-6 4 OBJ:
11 1
l liistory:
i Source: LOT Bank 40487 I
i JTA: 0100070101 l
84
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98 85 85 Given the following:
Unit 2 is in Mode I
)
Both Containment Instrument Air Compressors have failed.
[21AC-MOV131] Station Instrument Air to Contamment lastrument Connect has been opened to maintain contamment instrument air pressure.
Which of the following represents the Technical Specification actions required for the above lis conditions?
A. The valve may be opened under Administrative control as long as an operator js dedicated the valve if the Standby Alarm is sounded.
B. Commence immediate preparativn for plant shutdown.
C. No Technical Specification actions required.
D. Restore containment instrument air pressure and close (2f AC-MOV131] within one hour or b Hot Standby within the next six hours.
ANSWER: C K/A: 2.1.10 "
Importance: 2.7/3.9 Cognitive Level: Knowledce CLOSED BOOK i
Ref.: TS 3.6.3.1 l
I i
OBJ:
3 LP#:
2LP-SQS 53C.I i
Histog l
l Source: LOT Bank #0113 modified JTA: 1190150301 l
85
. - -.. ~..
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-86 86.
Which of the following statements is NOT correct regarding a confined space entry?
A. An entry into the confined spece shall consist of a minimum of two individuals.
B. A method of conununication shall be established to maintain contact with personnel within the confined space.
C. An SCBA for emergency use shall be kated near the entrance of a confined space when certain tasks are being performed within.
D. For conditions when an SCBA used by rescuers may be impractical, the ventilation flow can be increased as an additional precaution.
ANSWER: A K/A: 2.1.26 Importance: 2.2/2.6 Cognitive Level: Knowledge CLOSED BOOK Ref.: NPDAP 3.7 LP#:
STOP Training
. OBJ:
Historv l
I Source: LOT Bank #0173 r--
JTA 3420200302 l.
86 l
l
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-87 Unit I is in Mode I and Unit 2 in Mode 4 with the normal shift complement. At 0400 87 Unit 2 ANSS is injured and is transported to a local Emergency Center for treatment.
return this shift.
Which of the following statements is correct with regard to authorized shift staffing?
A. Credit can be taken (or the Unit 1 ANSS provided the Unit 2 NSS does not leave the B. An additional supervisory qualified SRO must be added to the shift complement by 0 C. An additional supervisory qualified SRO must be added to the shift complement by 06 D. Since the next shift will be relieving witHn 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, shift manning is adequate provided shift has a full complement.
ANSWER: C Importance: 2.3/3.4 K/A: 2.1.4 I
Cognitive Level: Comprehension CLOSED BOOK l
1/20M-48.1.B " Operations Shift Complement and Functions" issue 3. Rev.17, pgs 3&4
-I Ref.:
OBJ:
2 LP#:
2LP SQS-48.1 Historv Source: LOT Bank #0312 modified l
l l
l JTA: 3430060302 l
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l 87
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-88 I
88.
Which of the following items on the ANSS ShiA Tumover Chxklist would ONLY be the responsibility of the OFF GOING ANSS?
A.
Review previous shiR narrative logs B.
List any Technical Speci6 cation itans in effect C.
Review the ESF Mimic Print for out of normal conditions D.
Log 5 qualified fire brigade members in the ANSS log ANSWER: B
^l K/A: 2.1.18 Importance: 2.9/3.0 l
l Cognitive level: Knowledge CLOSED BOOK Ref.: 1/20M-48.1.C Issue 4 Rev. 3 Figure 48.1.C-2 " Assistant Nuclear Shift Supervisors Turnover l
Checklist LP#:
2LP-SQS-48.1 OBJ:
3 l
i Historv l
Source: LOT Bank #0384 modified l
JTA: 1190030301 88 4
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98 89' O
The unit is at 375'F with pressiare at 900 psig. St Accumulator 2 SIS *TK21C is p 89.
$50 psig. Which of the following actions is allowed?
Heat up and RCS pressurization above 1000 psig may continue, with up to 6 A.
restore the accumulator to OPERABLE status.
Heat up and RCS pressurization above 1000 psig may continue, with up to I hou Bi restore the accumulator to OPERABLE status.
The unit must remain in HOT STANDBY below 1000 psig until the accumulator is C;
restored to operability.
The unit must be placed in HOT ShVfDOWN within I hour and COLD SHUTDO D.
within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ANSWER: C -
Importance: 3.4/4.0 K/A:- 2.1.33 Cognitive Level: Analysis OPEN BOOK Ref.: :. BVPS Unit 2 Technical Specifications 3.5.1 " Accumulators" Tech Spec 3.0.4 OBJ:
1 LP#:
2LP-SOS TS Historv Source: NEW Student gets copy of Tech Specs JTA: 3410180302
'T 4
e 89
BVPS-2 f
l NRC Exam: 2 LOT 2, Rev 0 Question 8-98 90 l
l 90.
The plant has just finished a refueling outage and is currently in Mode 3. Secondary SG pressures have reached 600 psig and testing of[2FWE*P22] is in progress. During the test run, the governor valve fails. Which of the following is the required action't A. Retum the plant to mode 4 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
B. Twenty four hours are available to repair [2FWE*P22] before any action heed to be taken.
C. Restore [2FWE*P22] within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
D. Restore [2FWE*P22] within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown within the following 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br />.
1 ANSWER: D K/A: 2.2.22 Importance: 3.4/4.I I
Cognitive Level: Comprehension OPEN BOOK Ref.: TS 3.7.1.2 LP#:
2LP-SQS-TS OBJ:
I Rstory:
Source: New JTA: 1190150301 Student gets copy of Tech Specs l
i I
90 l
l
BVPS 2 g
NRC Exem: 2 LOT 2, Rev 0 Question 8-98-91 91.
During Mode I operation. the following RWST parameters are noted:
Volume = 860,000 gallons Boron Concentration = 2110 ppm Temperature = 50'F Corrective action must be taken for which one of the following reasons?
A. De basis for determining the time for Transfer to Hot kg Recirculation following a LOCA may be invalid, resulting in precipitation of the soluble boron.
B. He reactor may not comply with Shutdown Margin Boron requirements to remain suberitical following an analyzed accident.
C. Contained volume in the RWST may be not sufficient for both ECCS and to restore containment pressure to sub-atmospheric pressures within the 1-hour design criteria.
D. During a Design Basis Accident the Recirculation Sump would overfill and flood safety related systems in the containment-I l
ANSWER: A K/A: 2.2.25 Importance: 2 5/3.7 Cognitive Level: Comprehension OPEN BOOK Ref.: TS,3.1.2.8 and Bases LP#:
2LP.SQS-TS OBJ:
I Historv l
Source: LOT Bank #0271 modified JTA: 1190150301 Copy of Tech Specs 91
BVPS 2 NRC Exam: 2 LOT 2, Rev 0 e
Question 8 98 92 1'
l 92.
When performing a station startup in accordance with OM Chapter $0,"Statio'n Startup," steps i
marked by a filled diamond sign ( + ) indicate the step:
A. may be skipped at the discretion of the NSS.
D. may be skipped provided the GMNO initials the omitted s'.ep.
C. cannot be omitted, but may be started out of sequence.
D. cannot be omitted and must be performed in the specified sequence.
ANSWER: C K/A: 2.2.1 importance: 3.7/3.6 Cognitive Level: Knowledge CLOSED BOOK Ref.: 1/20M-48.2.C " Adherence and Familiarization to Operating Procedures", Issue 4, Rev. O, Page 6 and 7 LP#:
2LP-SQS-48.1 OBJ:
10 Historv Source: LOT Bank #0386 l
l JTA: 119CCC0301 l
l l
92
l BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-93 6
The NSS and ANSS have decided that an On the Spot procedure change is need this shiR to 93.
l continue a process. The change is determined to remain within the intent of the procedure. The procedure change involves a system procedure, which has no impact on Technical Specific 1
Surveillance's. Which of the following may be OMITTED for the approval of the On the Spot change in order to use the procedure change this shiR?
A.
A review by an approved Operations Unit Non-Intent Reviewer.
B.
Approval by a Unit 2 Senior Reactor Operator.
C.
A review by a SPED engineer.
Approval by the GNMO or designated Technical Assistant within 14 days.
D.
ANSWER: C Importance: 2.3/3.3 K/A: 2.2.6 Cognitive Level: Knowledge CLOSED BOOK 1/20M-48.2.B Control of Operating Procedures issue. 4 Rev.15 Pages BIO and Bl1 Ref.:
LP#:
2LP-SOS-48.1 OBJ:
10 History Source: NEW
{~
j JTA: 3430200302 93
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Qu:stion 8-98-94 l
94.
Unit 2 is in the process of completing the initial conditions to release a Gaseous Waste Tank to the Unit i Atmospheric vent. Both Unit I and Unit 2 ANSS sign and date the PRE (discharge l
authorization block) of the RWDA-G. Which of the following is OUTSIDE the responsibility of l
the Unitt and Unit 2 ANSS signatures?
A.
The approval has been granted for the release of the specified tank under the RWD A-G.
B.
Only one gas tank from the station is being discharged at one time.
C.
Tritium sampling by the Chemistry department has been completed for the specified tank.
l D.
All RM 11 alarm setpoints have been properly adjusted in accordance with the RWDA-G.
ANSWER: C K/A: 2.3.9 Importance: 2.5/3.4 Cognitive Level: Knowledge CLOSED BOOK Ref.: 1/20M-19.4A.B " Unit 2 GW Storage Tk Disch to Unit i Atmos Vent" !!!. 9, page B3, issue. 3 Rev 6
LPh:
2LP SQS-19.1 OBJ: 9 History i
Source: NEW JTA: 3410120302 l
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94 l
l I
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 s
QuIstion 8-98 95 Unit 2 is in Mode 5 and containment purge is in progress under an RWDA-G. The ANSS is 95.
notified that a drain on the letdown line downstream from the Regenerative Heat Exchanger was opened and is draining to the floor. Which of the following actions should the ANSS take?
Stop the purge and close out the current RWDA-G for the containment purge.
A.
Stop the purge and notify the Health Physics departme-t to sample the Containment B.
atmosphere before re-initiation of the purge.
Stop the purge and verify the drainage is completed or stopped prior to restarting the 1
C.
contairunent purge.
Stop the purge and notify the Health Physics department to update the setpoints for the D.
RWDA-G before continuing the purge.
ANSWER: A Importance: 2.5/3.4 K/A: 2.3.9 i
Cocnitive Level: Knowledge CLOSED BOOK 20M44C.2. A " Precaution and Limitation", Issue 4, Rev.1. Item " General" 7. Pace 1 of 2 Ref.:
OBJ:
9 LP#:
2LP SQS-44C.l History Source NEW JTA: 3410120302 95
BVPS.2 NRC Exam: 2 LOT 2, Rev 0 Question 8 98 96 II 96.
Unit 2 is at 100% power with all systems NSA. What would be the result if the MSIV on 21 A
. Steam Generator were to go full closed?
A. Low Steam Line Pressure Safety injection.
B. Pressurizer Pressure High Reactor Trip.
C. High-High Steam Generator level Feedwater Isolation.
D. Pressurizer Pressure Low Safety Injr.ction.
ANSWER: A K/A: 2.4.4 Importance: 4.0/4.3 Cognitive Level: Comprehension CLOSED BOOK Ref.: Transient Analysis LP#:
2LP.SQS.21.1 OBJ:,. 7 Historv-1 Source: LOT Bank #0625 JTA: 3420250.302 4
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4 BVPS-2 NRC Exam: 2 LOT 2, Rev 0 I
Question 8 98-97 l
The DigitG Rod Position Indication system has just generated a Non-Urgent alarm. Which of the 97.
following could be the cause for this alarm?
l i
A Loss of Data A and Data B signal from a single rod.
l B. Disagreement between two central control rods.
C. A central control card calculates a rod's position as 236 steps withdrawn.
D. ' Accuracy mode selector switch placed in the A+B position.
l ANSWER: B i
i K/A: 2.4.31 Importance: 3.3/3.4 Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M1.1.B " Reactor Control and Protection Summary Description" Issue 4. 'Rei.1, Page 18 I
LP#:
2LP-SQS-1.4 OBJ:
8 l
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Source: LOT Bank #0690 modified JTA: 014003010 t l
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l BVPS 2 l
NRC Exam: 2 LOT 2, Rev 0 Question 8 98 98 98.
The Emergency Classification that requires the implementation of Site assembly / accountability is 1
. This assembly / accountability must be completed within 2 A. (1) Alert;(2) 30 minutes.
B. (1) Alert;(2) 60 minutes.
C. (1) Site Area Emergency;(2) 30 minutes.
D. (1) Site Area Emergency;(2) 60 minutes.
ANSWER:C K/A: 2.4.44 Importance: 2.1/4.0 Cognitive Level: Knowledge CLOSED BOOK j
Ref.: EPP/IP 3.2 " Site Assembly and Personnel Accountability" Page 5 and Page 1I LP#:
EPP57 OBJ:
Historv l
Source: LOT Bank #0723 l
JTA: 3440020302 98 l
i-
BVPS-2 NRC Exorn: 2 LOT 2, Rev 0 e
Question 8-98-99 Security has reported that there is smoke in the computer room for the Unit i Simulator Fac 99.
As ANSS what should your response be?
Authorize the Security Shift Supervisor to call the local fire departments for response.
A.
Dispatch the site fire brigade and notify the loc:.1 fire departments for support.
1 B.
Notify the local fire department and dispatch an operator to de-energize equipment as 4
C.
needed.
b otify the local fire department and dispatch security with the required support equipracrit D.
e ANSWERIC I
K/A: 2.4.27 Importance: 2.9/3.0 Cocnitive Level: Knowledge CLOSED BOOK 2OM-56B.4.1" Fire Brigade and Fire Fighting Procedures " issue 1. Rev. 9 page B9 of I8 Ref.:
OBJ:
5 LP#:
2LP-SQS-48.1 l
i Historv Source: NEW JTA 34400,70302 99
A BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Qurstion 8-98-100 i
l 100.
Unit 2 is operating at 100% with all systems NS A. A reactor trip is actuated. The ANSS observes the NCO's perfonning the following inunediate actions from E-0 " Reactor Trip and Safety injection":
1.
Manually stop both Turbine EH Fluid,.tmps.
2.
Manually open PCB 352,"No. 2 Main Tfmr No. 5 345 KV Bus Bkr".
3 Depress the Reheater Controller Reset pushbutton.
4.
Depress Emer Gen 2-1 " Start" pushbutton.
In what sequence should the ANSS observe the above actions?
A 1,3,4.2 B.
1.2,3,4 i
1 j
C.
1,2,4,3 D.
1,3,2,4 I'
ANSWER D K/A: 2.4.1 Importance: 4.3/4.6
__l l
Cognitive Level Knowledce CLOSED BOOK
}
l Ref.: 20M53.A 1.E-0 " Reactor Trip or Safety Iniection" issue 1B. Rev. 4 l OBJ l
l-3 l
LPp.
2LP-SOS-53.3 Historv Source: NEW JTA: 3010010601 '
i i
A i
100 1
BVPS-2 NRC Exam: 2 LOT 2, Rev 0 Question 8-98-101 1.
A 26.
B 51.
C 76 A
i 2.
B 27.
C 52.
A 77 D
3.
D 28.
D 53.
B 76.
A 4.
D 29.
A L_
C 79.
C 5.
B 30.
C 55.
D 80.
A f
6.
B 31.
B 56.
B 81.
B 7.
C 32.
D 57.
A 82.
D 8.
A 33.
D 58.
B 83.
A 9.
C 34.
B
$9.
C 84.
A 10.
D 35.
A 60.
B 85.
C 11.
B 36 C
61.
C 86 A
12.
C 37.
D 62.
D 87 C
13 B
38.
C 63.
A
'88 B
i 14.
A 39.
B 64.
B 89 C
l l
15 D
40.
C 65.
A 90.
D 16 A
41.
A 66.
D 91.
A 17.
D 42.
A 67.
B 92.
C 18.
D 43.
B 68.
C 93.
C 19 D
44 D
69.
B 94 C
20 D
45 A
70 A
95 A
21 A
46 B
71.
A 96 A
22 A
47 D
72.
D 97.
B 23.
B 48.
D 73.
B 98.
C 24.
D 49.
A 74.
D 99.
C 25 C
50 D
75 D
100 D
101
' 3 i
4 I
f SIMULATION FACfLITY REPORT Facility Licensee: Beaver Vallov Unit 2 Facility Docket No: 50-412 Operating Tests Administered from: Auoust 17-21.1998 This form is used only to report simulator observations. These observations do not
]
constitute audit or inspection findings and are not, without further verification and review, indicative of noncomp!!ance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that i
May be used in future evaluations. No licensee action is required in response to these f
observations.
i No simulator deficiencies, that affected the scenario examinations or JPMs, were identified
)
during the execution of the examination.
)
l l
i j
i l
4
.i 1
l t
t
_