IR 05000334/1998301
| ML20153F352 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/21/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20153F311 | List: |
| References | |
| 50-334-98-301OL, 50-412-98-301, 50-412-98-301OL, NUDOCS 9809290081 | |
| Download: ML20153F352 (115) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION 1
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Dock'et Nos.': 50-334 50-412 l
Report No.: '98-301 l License' No.: NPF-73
Licensee: Duquesne Light Compeny -
Facility: Beaver Valley Unit 2 Nuclear Power Plant Location: Shippingport, Pennsylvania Dates: August 3-7,17-21,1998 !
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Chief Examiner: . T. Kenny, Senior Operations Engineer / Examiner Examiners: J. D' Antonio, Operations Engineer / Examiner
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P. Bissett, Senior Operations Engineer / Examiner Approved By: Richard J. Conte, Chief, Operator Licensing and Human Performance Branch '
Division of Reactor Safety
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EXECUTIVE SUMMARY Beaver Valley Unit 2 Nuclear Power Plant inspection Report No. 50-412/98-301 Operations t Four Unit 2 senior reactor operator instant (SROI) candidates passed all portions of the initial license examinatio 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 well informed. Crew briefings were routinely held when time permitted. The written examination was developed at the i appropriate SRO knowledge level, at were the job performance measwes 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 examinatio Current operator license training is being conducted in accordance with RG 1.8 Rev. Appropriate waivers were submitted by the facility licensee and were addressed by the NRC staf 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 complete 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 realize With respect to licensee restart items M-9 and P-16, during the shutdown, the facility eppeared 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 realize 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 evolution . .
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fleport Details l
l. Operations - '
05 Operator Training and Qualifications 05.1' Senior Reactor Ooerator Initial Examinations Sgga The examination was prepared by Beaver Valley Power Station (BVPS) personnel in accordance with the guidelines in interim Revision 8, of NUREG-1021," Examiner I Standards." The NRC examiners administered initial operating licensing portion of *
the examination to four Unit 2 senior reactor operator instant (SROI) candidate The written examination was administered by the facility's training organizatio Observations and Findinas The results of SRO examination for Unit 2 are summarized below:
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SRO Pass / Fail -
Written 4/O
- Operating 4/O Overall 4/O 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 revie 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 examinatio 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 demonstration 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 -
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The operating portion of the examination was conducted from August 17-21,1998, and consisted of four simulator scenarios and ten JPMs. All JPMs were followed up with two system-related questions. All candidates were also examined using JPMs and/or questions to evaluate the administrative requirement portion of the examinatio Simulator and JPM performance by the candidates was good. Communication was also good, including the use of repeat backs. The examiners noted that crew
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. briefings were routinely performed by the SROs. Good control board awareness by
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c.t : 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 facility thoroughly evaluated the knowledge and ability of each candidate in an effort to determine their readiness to sit for an initial NRC, SROI examinatio Crew communications, control board awareness, and crew briefings were good. As
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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 examination .2 Reaulatorv Guide (RG) 1.8 Rev. 2 Reauirements insoection Scope (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-l and NRC records to verify compliance with these requirement Observations and Findinas RG 1.8 requires that:
e Each candidate, for a senior license, have a high school diploma or equivalent. The inspectors verified that all candidates met or exceeded the requiremen e Each candidate, for a senior license, have four years of responsible power plant experience. The inspectors verified that all candidates met or exceeded the requiremen . .
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4 4 e 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 j granted a waiver on August 17,1998, to take the examination. This may result in l l a condition on the issued license.
i e Each candidate, for a hot license, should manipulate controls of the facility during a
- 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
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 me ;
1 The licensee agreed, via a letter dated July 13,1998, that the candidates will be j
placed in the requalification training program as if the licenses are issue ' Conclusions j Current operator license training is being conducted in accordance with RG 1.8
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Rev. 2. Appropriate waivers were submitted by the facility licensee in a timely manner and were addressed by the NRC staf Miscellaneous Operations issues 08.1 Condition Report 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 Condition 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 change .2 Procedures (IP 42700)
During the shutdown period, the operating procedures underwent major revision 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 easil The examiners concluded that the procedures used were complete in their technical content, were well written, and were clear and understandable for the us'er .. - . . - - - .. . . _ . . - -.
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il. Maintenance '
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M8.1 Technical Soecification (TS) Surveillance Schedulina and Trackin l Scoos (IP 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.
l 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 surveillance coordinator generates reports of potential
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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 M 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 facility generated a software matrix able to cross reference TS's and procedure 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 Quality Assurance was performed with minor discrepancies resolve During this inspection, the coordinator was in the process of verifying that these procedures were correctly referenced in the hard copy technical specification I matrix. As a result of this review, additional required changes had be a iden.tified which will be incorporated into a future review of the matri Conclusions
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( This restart item (P-14) was acceptably completed.
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l M8.2 Work Control l l Scone (IP 62700)
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The inspector evaluated the status of facility restart issues P-15 and P-19, which adoressed the implementation of a 12 week work management process and a i combined 12 week / forced outage schedul Observations and Findinas 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 l 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 schedule based on priority. The on-line j 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 performanc l
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This meeting also includes readiness of current planned work to proceed. The
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inspector observed a meeting and considered the interaction a benefi 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 l 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 schedula. 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 change 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.
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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
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effectiveness of this procedure remains to be realized.
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6 M8.3 ~ Post MaintenanceTestina
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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 opsrating shif Observations and Findinas item M-9 concerned verifying required post maintenance testing was complete 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 testing paperwork was in the control room or tracking it down if it was not. He was also coordinating with work control and the control room to ensure necessary 1 work was completed for restart and to schedule specific PMT activities as '
necessary. The inspector considered the assignment of a dudicated individual and
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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 wJs assigned to work control to evaluate work packages prior to scheduling and modify post maintenance testing requirements if necessary.
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The second measure was the development of a post maintenance testing procedure to aid shift personnel in determining appropriate post maintenance testin Development of this procedure had just started and the form of the end product was not determined. The inspector considered the SRO reviews at the planning and
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scheduling stage, coupled with the dedicated SRO post maintenance testing
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reviewer for mode change to be adequate for startu Conclusions With respect to licensee restart item M-9 and P-16, during the shutdown, the
> facility 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 realize .
. M8.4 ' Licensee " Culture" Enhancements
. Scone (lP 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
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technical specifications. 2) Developed a plan to upgrade General Employee Training
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(GET) and General Employee Refresher Training (GERT) programs ensuring increased i sensitivity to Technical Specification (TS) compliance. 3) Develop a "Just in Time"
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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,"
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from the outage, was not ready for inspection.
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The Training Administrative Manual had been changed to require a two hour session
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concerning technical specifications in each module for both programs. This training was in addition to TS training presented with each specific system. This training was scheduled to commence with the next module (module 5) for non licensed
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 appropriate quality.
The inspector reviewed Addendum 98.5 to GERT which described TS's including; i their development, ownership of the document, responsibility for implementation, i 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 I of GET in the futur The Operations Department in conjunction with the Training Department developed a "just in time" training program. The inspector reviewed documents and had i discussions with training department personnel regaraing training that was presented to operators during this extended outage as follows: All operators have
- received training regarding changes to procedures altered during this outag Operators also received training on design changes implemented during this outag To be completed is training for start up and heat up of the plant prior to the overall
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plant start up. Training management informed the inspector that this training will take place just prior to returning the unit to servic ' Conclusions The facility developed a plan for upgrading TS training in the requalification programs for licensed and nonlicensed operators, as stated in their restart pla 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 operating crews prior to important evolution E8 Review of the FSA While performing the preexamination activities discussed in this report, the inspectors reviewed applicable portions of the FSAR, that related to the selected
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examination questions ov' topic areas. No discrepancies were noted.
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1 V. Manaaement Meetinas
X1 Exit Meeting Summary l 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.
L The examiners also expressed their appreciation for the cooperation and assistance that i was provided during both the preparation and examination week by licensed operator training personnel and operations personnel. The following were present at the exit The results of an earlier inspection evaluation the restart items were also discusse l PARTIAL LIST OF PERSONS CONTACTED SfAVER VALLEY l J. Cross, President Generation Group i M. Johnson, Manager of Security (Acting VP)
l K. Beatty, General Manager, Nuclear Support R. Brooks, Sr. Nuclear Operations Instructor W. Lindsey, Director, Operator Training R. Hart, Senior Licensing Supervisor liBG l l
T. Kenny, Senior Operations Engineer, Chief Examiner I J. D' Antonio, Operations Engineer D. Kern, Senior Resident inspector
! INSPECTION PROCEDURES USED IP 41500: Training and Qualification Effectiveness i IP 62700: Maintenance Program implementation IP 42700: Plant Procedures
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- LIST OF ACRONYMS
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CFR Code of Federal Regulations i
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Condition Report GERT.- General Employee Refresher Training ,
GET General Employee Training - l JP Job Performance Measure i NRC- Nuclear Regulatory Commission PRA.- Probabilistic Risk' Assessment . 1
PTM - ' Post Maintenance Test ,
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- QA Quality Assurance 'I
.RG- Regulatory Guide '
RO Reactor Operator l SR Senior Reactor Operator )
SROI Senior Reactor Operator Instant-s TS Technical Specifications l
Attachments:
1. Beaver. Valley Unit 2 SRO Written Examination w/ Answer Key 2. Simulation Facility Report
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4 4 .J du e is e - se e Attachment 1 BV-2 SRO WRITTEN EXAMINATION W/ ANSWER KEY i
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RTL #A5,62 DUQUESNE LIGHT COMPANY
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l Nuclear Power Division Procedure 5-5 Training Administrative Manual Figure 5- Revision 12 Page 1 of 1 WRITTEN EXAMINATION COVER SHEET
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PROG' RAM: . Licensed Operator Training '
- CLASS NUMBER: 2 LOT 2A
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- SUBJECT: Initiral NRC SRO Exam
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By this signature, I state that all'of the work done on this examination is my own. I have neither givea nor-
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received ai ,
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SIGNATURE DATE '
NAME-
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ANSWER KEY DLC EMP. #
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COMPANY
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(if other than DLC)
' POSSIBLE POINTS 100 SCORE Instructor
, initials PREPARED BY Thomas Stanley TRAINING DIRECTOR /SUPERVidOR
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BVPS-2
, NRC Exam: 2 LOT 2, Rev Question 8-98-1 by .- The unit is at 100% with all systems NSA. The following annunciators are lit:
A4-3C "TAVG DEVIATION FROM TREF" AS-4F " ROD CONTROL BANK D LOW-LOW
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Trefis 5'F above Tavg
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A. Lower turbine load and add boron '
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B. Raise turbine load and add boron
C. Lower turbine load and dilute
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D. Raise turbine load and dilute l
ANSWER: A
.- K/A: 001 K3.01 Importance: 3.1/ Cognitive Level: Comprehension CLOSED BOOK Ref.: AOP 2.1.3 Step 21ssue I A Rev. 3 -
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Source: NEW l JTA:0000040401 i
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NRC Ex:m: 2 LOT 2, Rev 0 g
U . Question 8-98-2
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2.' The unit is operating at 100% with all systems NS A. Control Rod H-4 drops into the core. 9he
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h 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.
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Which of the following actions will be needed to' comply with the LCO:
- .Within I hour verify compliance with T.S. 3.1.3.6 " Control Rod Insertion Limits". .
J ? Within I hour verify shutdown margin per T.S. 3.1.1."Boration Control - Shutdown f
Margin". '
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- 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
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 Control Assemblies-Group Height".
ANSWER: B
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K/A: 003 Kl.0 Importance: 3.1/ '
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OPEN BOOK ;
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- 20MS3.C.2.1.8 " Rod Inoperability" Issue I A, Rev0 Step 4 i Beaver Valley Technical Specification 3.1.1 "Boration Control- Shutdown Margin
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_; NRC Exam: 2 LOT 2, Rev 0
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Question 8-98-3 During the performance of ES-0.1 " Reactor Trip Response" the NCO reports that control tod F-8 indicates 24 steps and control rod H-8 indicates 227 steps on the Rod Position Indication Pane Which of the following actions is needed to ensure adequate shutdown margin? ' Stop dumping steam to stabilize Reactor Coolant System temperature at 547 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 dro Emergency borate until the in service Boric Acid Storage tank shows an 18% level dro ANSWER: D 1 K/A: 003 A2.03 Importance: 3.3/ Cognitive Level: Analysis OPEN BOOK Re M-53A.I.ES-0.1" Reactor Trip Response" Issue IB Rev. 4 Step 6
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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 i
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History I Source: NEW JTA:301AAA0601 Student gets Copy of EOP ES-0.1 and CB-27 l
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NRC Exam: 2 LOT 2, Rhv 0 Question 8-98-4 ' .
I f/ The reactor has tripped and a Safety Injection was actuated on low RCS pressure. The crevris -
transitioning from E-0" Reactor Trip and Safety Injection" to E-1 " Loss of Primary or Secondary
' Coolant", Step 1. The following conditions exist:
RCS Pressure 980 psig - stable
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' Steam Generator Pressure - 950 psig -' stable
~ Containment Pressure : 8 psig - stable
' RWST level 500 inches -slowly dropping HHSI flow 520 gpm -stable -
i During the crew briefing at transition, which of the following sets of pumps should be operating?
- Low Head SI pumps Reactor Coolant pumps Quench Spray pumps ,
. Component Cooling pumps
.A - All listed pumps
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, _LHSI and Reactor Coolant Pumps only LHS1 and Component Cooling Pumps only
. LHSI and Quench Spray Pumps only *
ANSWER: D
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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 l 20M-53;1.E-1 " Loss of Primary or Secondary Coolant" Issue 1B, Rev. 5 LP#: - 2LP-SQS-53.3 - OBJ: 3 -
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' f ..; NRC Exam: 2 LOT 2, Rev 0 ,
Question 8-98-5 - '
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%M 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
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the following criteria 1-
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J . Maximize core cooling following a cold leg break with flow into vessel and out of cold leg l
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, Dilute boron concentration in the reactor vessel to prevent precipitation of boron on clad
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! Minimize differential pressure from cold leg to allow maximum flow into reactor vesse i
, Limit void in' upper vessel to prevent blockage of natural circulation flow into hot legs,
ANSWER B1 i l K/A: 011 K3.12 :- Importance: 3.8/ I
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Ref.: 20M53B.3.E-1" Loss of Primary or Secondarv Coolant" Issue IB Rev. 5 Note before step 31
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- 2 LOT 2, Rev 0 1
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, - Question 8-98-6 - !
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'Ihe crew is performing ES-12 " Post LOCA Cooldown and Depressurization" At step 2&indhe
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. procedure the ANSS instructs the Reactor Operator to : .-
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"Deoressurize the RCS to minimize break flow until PRZR level is GREATER THAN 76% or = '
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- Subcooline is less than subcooline listed on A***hment A-5.2" -
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Which oIthe folloAing actions will result in the lowest RCS pressure and limit the rise in l
- Pressurizer level? ,
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' Using a PORV to' reduce RCS pressur ,
i Using normal PRZR spray while reducing charging flo .:_ :
!
- Lock out the PRZR heaters while spraying the PRZ '
D. . Aligning auxiliary spray for maxunum temperature differentia g ANSWER: B-
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K/A: W/E02 EK1.2 - In.portance:3.5/ ' '
F Cognitiv Level: Analysis CLOSED BOOK
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Ref.: - 20M53.A.ES-1.2 " Post LOCA Cooldown and Depressurization" issue IB, Rev. 5 Step 24
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2OM53.B.ES-1.2 " Post LOCA Cooldown and Depressurization" Background" Issue IB, Rev. 5 -
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.: NRC Exim: 2 LOT 2, Rev 0
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l.,_- Question 8-98-7 l
- +^ - At step 28 in E-0 " Reactor Trip or Safety injection", the following parameters are noted: . ~
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RCS Subcooling 55 degrees and rising , J Total AFW Flow - 400 gpm - stable RCS Pressure 2100 psig - rising -
I PRZR level 19%-rising Based on these parameters, which of the following is a correct statement? , RCS pressure is sufficient to make RCS subcooling an indication of RCS inventory l l AFW flow is sufficient to make RCS pressum an indication of RCS inventory .. l RCS subcooling is sufficient to make PRZR level an indication of RCS inventory -
. RCS pressure is sufficient to make PRZR level an indication of RCS inventory i
i ANSWER: C
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K/A: W/E02 EA Importance: 3.8/ ;
= 1
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Cognitive Level: Comprehension CLOSED. BOOK .
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Ref.: 20M-53A-E-0" Reactor Trip and Safety Injection", Issue IB, Rev. 4
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20M-53B.5.GI-l1 "Si Ternunation Criteria" Issue IB, Rev.1 Page 7 w . !
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t- NRC Enm: 2 LOT 2, Rev 0
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- Question 8-98-8 SN 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
- A 4KV Bus Frequency = <57.5 Hz -
'C
-
2A 4KV Bus Voltage = 75% of rated voltage - RCP 21 A Motor Electrical Protection Overcurrent
'
. ANSWER: A i
K/A: 0015/17 K1.02 - Importance: 3.7/ ,
Cognitive Level: Comprehension CLOSED BOOK ,
Ref.: 20M-6 " Reactor Coolant System" issue 4, Rev. O Section IOM-6.1.D, Page 1 of 19 20M-6 " Reactor Coolant e st m" Figure 06-22 " 10080-LSK-25-1 A LP#: 2SQS- OBJ: 8 -
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. NRC Exam: 2 LOT 2, Rev 0 ,
- Question 8-98-9 A Reactor Trip with loss of offsite power has occurred. ~Ihe following conditions exist: . -
Core Exit Thermocouple Temperatures = 582*F and stabl All Hot leg Temperatures = 580 F and stabl All Cold Leg Temperatures = 550 F and stabl ,
Pressurizer Pressure = 2085 psig and stabl Containment Pressure = 10 psia and stable
- It is desired to reduce RCS pressure but maintain 50 F subcooling. The minimum pressure that can be achieved to maintain 50 F subcooling as indicated on PSMS is: .
A. 1930 psi B. 1942 psi '
C. 1947 psi D. 1962 psi ANSWER C (Psat for 632*F =1947 psia)
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K/A: E09EK Importance: 3.5/3.6
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Cognitive Level: Analysis OPEN BOOK Ref.: Steam Tables
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.y NRC Exam: 2 LOT 2, Rev 0
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L, .. Question 8-98-10
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1 Which of the following would comply with the requirements for emergency boration? - Open 2CHS*MOV350, verify 30 gpm on 2CHS*Fil 10 Emergency Boration Flow and verify greater than 30 gpm charging flow to the RC . Open 2CHS*SOV206 and 2CHS*FCVI 13A, verify 30 gpm on 2CHS*FH 10 Emergency Boration Flow and 40 gpm charging flow to the RCS.
l .Open 2CHS*MOV350 and verify greater than 40 gpm boration flow on 2CHS*FR113 - ,
Boric Acid to Blender Flow Recorde Open 2CHS*SOV206 and 2CHS*FCVI13A, verify greater than 40 gpm boration flew on 2CHS*FRil3 Boric Acid to Blendef Flow Recorde _ ANSWER D _
-
K/A: 024 A2.02 Importance: 3.9/ Cognitive Level: Analysis OPEN BOOK
-
Ref.: 2 )M-7.4.Q " Emergency Boration" Issue 4 Rev.1 Pages 1 and 2 LP#: 2LP-SQS- OBJ: 8 History Source: NEW *
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BVPS-2 f 'NRC Exam: 2 LOT 2, Rev 0 ,
Question 8-98-11
-> 1 ' Unit 2 is in Mode 5 on RHS cooling with 2RHS P21 A running. The following conditionsexist:
2CCP*P21 A is running 2CCP*E21 A and 2CCP'E21B heat exchangers are in sen> ice 2CCP*DCV101 A and B CCP Hx Diff. Press. Control Valves are operating in manual 2CCP*TCV100A end B CCP Hx Temp. Control Valves are operating in auto Which of the following would be the effect on the plant from loss ofinstrument air? CCP*DCV101 A and B fail closed,2CCP*TCV100A and B fail open and RHS temperature drop ... CCP'DCV101 A and B fail open,2CCP*TCV100A and B fait closed and RHS temperature drop CCP*DCV101 A and B fail closed,2CCP*TCV100A and B fail open and RHS temperature rise ~ CCP*DCV101 A and B fail open,2CCP*TCV100A and B fail closed and RHS
.7
' '
temperature rise .
ANSWER B K/A: 026 K3.03 Importance: 3.5/ ' Cognitive Level: Comprehension CLOSED BOOK -
Re M-15.5 "CCP System", Issue 4 Rev. O Figure 15-1 10080-RM-415-1 Rev. 9 LP#: 2LP-SQS-1 OBJ: 3 History Source: NEW JTA: 0050080101
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- BVPS-2 77 NRC Exam: 2 LOT 2, Rev 0 *
Question 8-98-12
ksh 1 The crew has initiated emergency boration in response to an ATWS. RCS pressure is 23M psi ,
i Which of the following actions would maximize negative reactivity and minimize the addition of -
positive reactivity being added to the RCS?
'
- A.- Raise AFW flow to 700 gpm and fill all steam generators to 5% narrow range level: Lower charging flows to 40 gpm and raise letdown flow to 120 gpm by placing two letdown orifices in servic ' . Verify Pressurizer PORV motor isolation valve open and verify /open a Pressurizer PORV, Place Steam Dump Controller to Manual and open the steam dump .1 ANSWER: C . 1 K/A: 029 K1.03 Importance: 3.6/ .
>
Cognitive Level: Comprehension ' CLOSED BOOK
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Ref.: 20M-53.4.FR.S-1" Response to Nuclear Power. Generation-ATWS", Step Description for Step,8, l
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. NRC Exam: 2 LOT 2, Rev 0 Question 8-98-13 U.,
1 The Reactor Coolant system parameters are 1700 psig and 490 degrees., All actions required by 20M-51.4.C " Station Shutdown-Cooldown from Mode 3 to Mode 4" procedure are in effec Which of the following actions would automatically terminate the cooldown via the steam dumps?
_ A and 21B Steam Generator pressures drop to 450 psig in each generator B Steam Generator pressure drops from 690 to 490 psig in 45 seconds
A Steam Generator level rises from 55% to 85 % in 45 seconds ! A and 21C Steam Generator levels drop to less than 5% narro'w ra6ge
.
ANSWER B K/A: 040 K3.04 Importance: 4.2/ gtive Level: Comprehension CLOSED BOOK Ref.: 20M21 " Main Steam", Iss. 4, Rev. O, Section 20M-21.1.D Page 20f 11, 20M-21.B Page 2
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. Question 8-98-14 s ,,
,, .1 , In step 13 of ECA'- 2.1" Uncontrolled Depressurizaten of All Steam Generators" the operator
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. confirms that Si accumulators will be isolated when 2 of 3 Hot Leg temperatures are less than 390
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( degrees.) Isolation of the accumulators below this temperature is required to prevent:
I _ Injection of nitrogen gas in to the Reactor Coolant Syste '
- Bc Violation of Technical Specification temperature pressure limit '
L' - Entry into Pressurized 1hermal Shock conditions in the vesse / . .
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' High pressure differential across the steam generator tubes.
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ANSWER A K/Ai 040 Al.04 Importance: 4.3/ l
Cognitive Level: Knowledge : CLOSED BOOK j Ref.: 2OM-53.A.4.ECA-2.1 " Uncontrolled Depressurization of All Steam Generators" Iss. IB Rev . .
..l-- helewound Description for Step 13 -
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NRC Exam: 2 LOT 2, Rev 0 .
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Question 8-98-15 I
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1 Following a steam break tha: occurred 20 minutes ago, the crew has completed isolating the steam i
i generator using E-2 " Faulted Steam Generator Isolation" with the following status:
l
-
Reactor Coolant Temperature at 258 degrees and stable -
-
Reactor Coolant Pressure at 1400 psig and stable 21 A Steam Generator Pressure 25 psig and stable 21B and 21C Steam Generator Pressures at 420 psig and stable l
l Based on the'given information, select the appropriate procedure for the transition from E-2" Faulted Steam Generator Isolatio ,
._ Go to E-1 " Loss of Primary or Secondary Coolant" Step Go to ECA - 2.1 " Uncontrolled Depressuna' ion of Al; dteam Generators" Step ' Verify no higher " RED" path present and go to FR-P.1 " Response to Imminent
- Pressurized Thermal Shock" Step 1.
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< Verify no higher " ORANGE" path or any " RED PATH present and go to FR-P.2
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U " Response to Anticipated Pressurized'Ihermal Shock".
.
ANSWER D K/A: W/E08 A2.01 Importance 3.4/ Cognitive Level: Analysis OPEN BOOK l Ref.: 20M-53.1.F-0.4 " Vessel Integrity" Issue 1B, Rev. I 20M-53A. I.A-4.4 " PTS-Operation Limits Curve" Issue IB, Rev. 2 i LP#: 2LP-SQS-5 OBJ: 12 *
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,' , --NRC Exam: 2 LOT 2, Rev 0
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l Question 8-98-16 -
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1 As pressure rises in the' Main Condenser to normal atmospheric pressure, in what sequence will the :
,
following protective functions actuate?
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. 1) AS-5B " CONDENSER VACUUM LOW TURBINE TRIP" 2) Al2-4C " CONDENSER UNAVAILABLE (C-9)"
3) A6-5G " CONDENSER VACUUM LOW / LOW-LOW"
4) LP Turbine Rupture Disk ruptures ,1,2 ,3,2 ' - 0 ,3,2 ,
' ,2,4 i
ANSWER A K/A: K/A'0051 K2.06 Importance: 1.6/ Cognitive Level: Knowledge CLOSED BOOK -
Ref.: 20M 26 " Main Turbine and Condenser", Section 21.1.C, Issue 4 Rev. 4 Page 5 ,,
2OM-26.4.AAB " Condenser Vacuum Low Turbine Trip" iss. 4 Re ,
~ 20M-26.AAK " Condenser Vacuum Low / LOW-LOW", Iss. 4 Rev. 4 20M-26 ABM " Condenser Unavailable"(C-9)" Iss; 4 Rev. O LP#: 2LP-SQS 3 OBJ: 5 History
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. NRC Exam: 2 LOT 2, Rev 0 '
Question 8-98-17 i 1 In step 25 of ECA-0.0 " Loss of All AC Power" all intact steam generators are depressurizp(pntil l the steam generator pressures are 300 psig. What is the basis for stopping at 300 psig? . To linut head voiding and ensure continued natural circulatio Minimize loss of RCS through the damaged Reactor Coolant Pump seal ~ Prevent the retum to criticality of the reactor core during cooldow D.- Prevent challenging the reactor vessel integrity limi .
ANSWER: D
K/A': 055 K3.02 Importance: 4.3/4.6 - .
.
Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M.53.B.4.ECA-0.0 " Loss of All AC Power" Background Issue 1B Rev 4 Page 114 l
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. NRC Exam: 2 LOT 2, Rev 0 :
L . Question 8-98-18 l l ;
1 Bus'2AE de energized when the normal feeder breaker opened Which out of position switch L .
' would prevent an emergency start of the 2-1 Emergency Diesel Generator?
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! Mode Selector Switch in NORMAL j
,
' D/G Auto / Local Key Switch in AUTO I
' . Generator Synchronous Check Switch in OFF ' ;
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~ Auto / Exerciser switch in EXERCISE - '
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' ANSWER: D l
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K/A: 055 Al.02 l Importance: 4.3/ l j l Cognitive Level: Comprehension - CLOSED BOOK
'
Ref.: 2OM-36.5 "4KV Station Service System Figures and Tables", Issue 4, Rev. O, l- Figures36-24A and 24B
- *
2OM-36.3.C.8 " Power Supply and Control Switch List Diesel Generator 2-1"
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- 2OM-53.A.4.ECA-0.0 " Loss of All AC Power", Issue IB, Rev. 4, Sten 8 -
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.,
' NRC Exam: 2 LOT 2, Rev 0 ;
Question 8-98-19 ' .
'
,o 1 A'short has damaged Vital Bus 2-3 and the panel will be unavailable from normal and alternate t
. su,noly. Which of the following actions will be required? j Pressurizer level 11 and til must be selected for service l
B.- Steam Generator Pressure Channel 111 must be selected for service Make-up to the VCT must be controlled in manual 1 Swapover to the RWST must be manually performed at 5% -
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- ANSWER: D j i
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K/A: 0057 A1.04 Importance: 3.5/ Cognitive Level:- Analysis OPEN BOOK i
Ref.: 20M-38.4.W " Extended Loss of Vital Bus 2-3" Issue 1, Rev. 4, Page 1
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NRC Exam: 2 LOT 2, Rev 0
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, Question 8-98-20 i
, . . . , .
- fi 2 Service Water Pump C is cunently in service and connected to the 4KV Emergency Bus 2bf
.
During an attempt to start Service Water Pump A, the discharge valve jamtaed partially open. If
. power were lost to the AE bus, what would be the status of the Service Water system at tlu:
'
!
' completion of the sequencing ofloads 'on the bus? '
~
' '.SWS pumps A and B would be runmng
- SWS pump B would be runmng only ..
-
, SWS pump C would be running only 3 -
-*
1 D.' SWS pumps A and C would be running ANSWER D K/Ai 062 A2.02' Importance: 2.9/ .
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#i 2LP-SQS-3 OBJ: 5 -
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,. - NRC Exam: 2 LOT 2, Rev 0
-
Question 8-98-21
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2 . A fire has caused the evacuation of the Control Room and the plant is being controlled from the Altemate Shutdown Panel (ASP) in accordance with 20M-56C, Alternate Safe Shutdown. Prior to j beginning a cooldown, the RCS is borated to the Xenon free cold shutdown Boron concentratio 'this is accomplished by: .
TA. Using 22A Boric Acid Transfer Pump [2CHS*P22A] and Alternate Emergency Boration Valve
!
,
- [2CHS*SOV206] to pump either Boric Acid Storage Tank to the suction of the Charging Pum l l 1 B. Gravity feed of 21B Boric Acid Tank [2CHS*TK21B] via Emergency Boration Isolation Valve l
[2CHS*MOV350] to the suction of the Charging Pump.
j_ C. Setting the Boric Acid Blender control to 2000 ppm and initiating a feed and bleed of the RC D. Aligning the suction of the Charging Pump (2CHS*P21B) to the RWS *-
ANSWER: A 3 K/A: 068AA1.II Importance: 3.9/ Cognitive Level: Knowledge CLOSED BOOK l .
l-Ref.: 20M56C.4.F.9" Operation of Alternate Emergency Boration Valve [2CHS*SOV206] and Remote .
Operation of Boric Acid injection Valve (2CHS*FCVI13A) Issue 1 Rev. 5 i.
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- NRC Exam: 2 LOT 2, Rev 0 .
- '
Question 8-98-22 O 22
.
A channel 11 Containment liigh-1 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 l containment isolation?
.
. . All inside and outside contaimnent penetrations will go to their Phase A configuratio All inside and outside containment penetrations will remain in their current configuratio ~
- Only the outside containment penetrations will go to their Phase A configuratio Only the inside containment penetrations will go to their Phase A configuratio a ANSWER: A K/A: 069( W/E 14) A1.01 Importance: 3.5/3.7 J
'
Cognitive Level: Comprehension CLOSED BOOK .-
Ref.: 20M-1.1.D " Reactor Control and Protection" Issue 4, Rev. O
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NRC Exam: 2 LOT 2, Rev 0
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Question 8-98-23 W ._
-
2 The crew has completed the actions of ES-l.3 " Transfer to Cold Leg Recirculation". SI, CIA and 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?
l . Restart A and B High Head Safety Injection Pumps j
- Restart C and D Recirc Spray pumps
" Restart A and B Quench Spray pumps Restart A and B Service Water Pumps .
a l ANSWER: B K/A: 074 E06/E07 EK Importance: 3.6/ !
Cognitive Level: Comprehension CLOSED BOOK l i
Ref.: 20M13.5 " Containment Depressurization System Tables and Figures" Figure 13-12, .
~
_
12241-LSK-27-1 A, Issue 4, Rev1 20MS3A.I.ES-1.3 " Transfer to Cold Leg Recirculation" Issue IB, Re "
20M-36.1.C "4KV Station Electrical Major Components", Iss. 4 Rev. C, pages 15 and 16 1 l
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- '
' NRC Exam: 2 LOT 2, Rev *
Question 8-98-24
- as
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1The chemist reports that reactor coolant system activity has reached 1.1 pCi/gm in lodine due to l
l failed fuel Atler 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:- limit thermal stresses on the failed fuel and reduce I-131 releases to the RC '
l
~ limit the Auxiliary Building dose rates to less than the requirements of 10CFR2 = limit the post LOCA containment dose limits to the requirements of 10CFR2 , limit the secondary side pressure in case of a steam generator tube ruptur '
, ,
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ANSWER: D i
K/A: 076 (General 2.2.25) Importance: 2.5/3.7
..
Cognitive Level: Knowledge CLOSED BOOK Ref.: BVPS Unit 2 Technical Speci6 cation 3/4.4.8 Basis
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l1 BVPS-2 l ., - NRC Exam: 2 LOT 2, Rev 0
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Question 8-98-25 ,
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2 Unit 2 has been stabilized after completing the actions of ES-0.1 " Reactor Trip Response". The l >
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crew is monitoring Mode 3 conditions. Which of the following would LOWER the Shutdown
Margin for the Core?- .
t . . .
L . Three Shutdown bank rods that remained 25 steps out of the core, drift down into cor .,
'
- The NCO opens 2CHS*MOV350 and starts the inservice Boric Acid pump.
l - - .
- n C. - 'Ihe Plant Operator lowers steam dump setpoint pressure from 1000 psig to 950 psi l
- The Plant Operator lowers Auxiliary Feedwater flow from 600 gpm to 400 gpm.
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ANSWER: C~ !
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K/A: 007 Kl.02 Importance: 3.4/ g Cognitive Level: Comprehension CLOSED BOOK Ref.: Generic Fundamentals Reactor'Iheory Fundamentals, Topic 1 Kl.10, Page 9. ,
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y l NRC Exam: 2 LOT 2, R:,v 0 '. ,
Question 8-98-26 '
'. . Unit 2 is in Mode 4 with the following indications: ,.
'
- RCS Wide Range Temperature = 325 degrees 2RCS-PI402 Wide Range Pressure = 460 psig 2RCS-PI403 Wide Range Pressure = 465 psig .
The RCS loop B Wide Range Cold Leg temperature indication (2RCS*TI423) input to B OPPS Train has failed low. Which of the following would be the potential consequence of this failure?
' RCS*PCV455C Pressurizer PORV opens .
- RCS*PCV456 Pressurizer PORV opens Pressurizer Code Safety Valve lifts RHS Suction Relief Valve lifts ANSWER
- B- .
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K/A: 008 A2.06 Importance ' 3.3/ .. ,
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Cognitive Level: Comprehension OPEN BOOK g.
,;.. - .
Ref.: - 2OM-6.4 ABC " Reactor Coolant Wide Range Pressure Deviation High" issue 4, Rev. O, Page 5 i
l BVPS Curve Book CB-25, Issue 7, Rev. 0 l l, LP#: 2LP-SQS-6.4 - OBJ: 5
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,. 9 NRC Exam: 2 LOT 2, Rev 0 .
. Question 8-98-27..
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kW 2 During the performance of ES-1.2 " Post LOCA Cooldown and Depressurization" the operators have commenced a cooldown. At the completion of step 18 the following conditions exist:
"C" RCP is running , ,
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RCS Subcooling 85*F and 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
- '
2CHS*P21 A running .
2CHS*P21B hasjust been secured What action must the ANSS take? Stop all operating Reactor Coolant Pump Restart the 2B HHS1 pump 2CHS*P21 ' Allow RCS pressure and PRZR level to stabiliz ['. . . . ' Establish normal charging flow.'
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ANSWER C- ,
K/A: 009 A1.01 Importance: 4.4/ Cognitive Level: Analysis OPEN BOOK
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Ref.: ~ 20MS3 A1.ES-1.2 " Post LOCA Cooldown and Depressurization" Background Caution before step 19 l -:
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LP#: ' 2LP-SQS-53.3 ' OBJ: 3 History Source: NEW ' ,
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Student gets ES-1.2
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BVPS-2 NRL Ex m: 2LDT2, Rev 0 t
Questien 8-98-28 kt:
2 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 the following indiente the potential failure of natural circulation?
- RCS Subcooling is 85 F and stable , ,, Steam Generator Pressures are 585 psig and stable
. Core Exit Thermocouples are 525 'F and stable RCS Cold Leg Temperatures are 500*F degrees and stable
,
ANSWER: D K/A: W/E03 EK Importance: 3.7/ !
Cognitive Level: Analysis OPEN BOOK
~
, Ref.: 20M-53 A-1.7 " Natural Circulation Verification" Issue IB, Rev. 2 !
LP#: 2LP-SQS-5 OBJ: 3 History i
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Source: NEW
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JTA: 301 AAA0601 Student gets attachment and steam tables
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. BVPS-2 .
- , . NRC Exam: 2 LOT 2, Rev 0 -
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' Question 8-98-29 -
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2 ' Following a LOCA, both trains of recirculation have become unavailable. The crew has responded using ECA-1.1 " Loss of Emergency Coolant Recirculation". The'ANSS has deternuned that minimum SI flow to maintain core cooling is 100 gpm. This will allow he performance of which of the fo0owing actions?
A; Normal charging may be' established from the VCT to the reactor coolant system to
,
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provide borated makeu ,
' RCS cooldown ra:es may be increased to maximum achievable to reduce time to reaghing
. RHS system startup condition . The SI accumulators may be isolated to preserve the inventory for use when the RWST is emptie Containment Recirc Spray pumps may be stopped to preserve inventory in the RWS ., .
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ANSWER A j
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K/A: W/ElI K Importance: 3.3/ . '- .
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Cognitive level: Knowledge CLOSED BOOK Ref.:^ 20M53h3.4.ECA-1.1." Loss of Emergency Coolant recirculation " Background, Issue IB, Rev. 5
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' Step 16 l
LP#: 2LP-SQS-5 OBJ: 5 -
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- NRC Exam: 2 LOT 2, Rev 0 ,
y.! [~ :LQuestion 8-98-30.; ,
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.s 30, Annunciator A2-3F." Letdown Flow Path Trouble"is lit. Computer point." REGEN HX LTDN
' TEMP CHS-TE140 HIGH" is in alarm. The following conditions exist:.
, Charging Flow 45 gpm -
i Seal Injection Flow- ' 22 gpm l
!
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 Exchanger?
-
!
~ A.- Lower Charging Flow by closing Charging Pump Flow Control Valve 2CHS*FCV122
]
. B. - Place another. orifice in service by opening 2CHS*AOV200C '
.!
- Remove 60 gpm orifice from service by closing 2CHS*AOV200B -
,
' Raise letdown flow by opening Non-Regen Hx Discharge Pressure Con' trol Valve j
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2CHS*PCV145
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ANSWER: C
K/A: 022 K3.02 lii W m : 3.5/ Cognitive Level: Analysis CLOSED BOOK Ref.: 20M7.4.AAF" Letdown Flow Path Trouble" Issue I, Rev.10 Page 3 Of 6 LP#:' 2LP-SQS- OBJ:' 7 History -
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. NRC Extm:-2 LOT 2, Re,v 0 '
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q L. Question 8-98-31-
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3 ' Unit 2 has been shutdown for 5 days. The following conditions exist: '
- j Reactor coolant temperature is 125 degrees 'F L< Pressurizerlevelis 22% -
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l . RCS pressure is 95 ~psig using nitrug ihe PRZR i; ,
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= He operating RHS pump has become gas bound and is shutdown by the crew. How long would the crew have to vent the pump before reaching saturation in the RCS?.
, . 'A .- J 270 minutes' .
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I' ' 175 minutes b> .166 minutes
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' ANSWER: B l .
! s K/A: . . .025 K1.01 Importance: 3.9/4.3 '-
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Cognitive Leveli Analysis ' OPEN BOOK
. Ref.:: 2OM53.C.4.2.10.1 " Residual Heat Removal Loss", Issue IA; Rev. 4, Attachments 1,2,3 and 4 k I
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LP#: 2LP-SQS-10.'l OBJ: 10
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History -
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Source: NEW
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JTAs 0000'180401 Assumptions:
i Saturation for 110 psia is 335 degrees
, . i- 1
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Current RCS Temp is 125 degre'c .
'
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*Fdr
. . i Student gets Attachments and steam tables i
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.,.- ' NRC Ex:.m: 2 LOT 2, Rev 0
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Question 8-98-32
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3 De 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 h the next control action that would automatically occur?(Assume no operator actions) -
- ~5 1 ressurizer Heater Banks A,B,D, and E are deargized from PT445 on high RCS ,
pressur . Pressurizer Variable Heater bank C is de-energized from loss of PT444 signa PORY 2RCS-PCV455C opens on a high pressure signal for PT44 PORV 2RCS*PCV455D and 2RCS*PCV456 open on high pressure signal from PT445.
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ANSWER D K/A: 027 K2.03 Importance: 2.6/ .s
'
Cognitive Level: Analysis OPEN BOOK .
.
Ref.: 2OM-6.4.IF " Instrument Failure", Issue 4, Rev. 4, Page 16 .
2OM-6.5 " Reactor Coolant System Figures and Tables" , Issue 4, Kev. 6, Figures 6-35 and 6-36 l LPM: 2LP-SQS- OBJ: 10-i History
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JTA: 002009010 t Copy of section of references ;
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.. NRC Exam: 2 LOT 2, Rev 0 *
,
^** j Question 8-98-33 '
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3 A unit startup is in progress with the reactor critical at 2200 cps in the source range when N-31 i
l
~ Source Range Detector High Voltage is lost. Choose the correct respons , Raise power to the P-6 setpoint and continue the startu .
.
. Verify overlap of I decade with the Intermediate Range and continue startu i
. , j Place the unit in Hot Standby with the Reactor Trip Breakers ope Suspend positive reactivity additions and restore N-31 to operable statu *
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ANSWER: D K/A: 032 K3.01 Importance: 3.2/3.6 -
'
.D Cognitive Level: Analysis - CLOSED BOOK !
Ref.: 20M-53C.4.2.2 " Source Range Channel Malfuretion" Issue 1 A, Rev. 4, Step 2 and 3
~ .
(Jnit 2 Technical Specification 3.3.1 Table 3.3-1 '
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.r lNRC Exim: 2 LOT 2, Rev 0 -
,
- Question 8-98-34 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?
. ' During startup, the P-6 permissive will not de-energize the Source Range High voltag ' During shutdown, the P-6 permissive to re-energize the Source Rarrge High voltage will be
'
delaye .
. . . During startup, the P-10 permissive to manually de-energize the Source Range High voltage will be delaye .
' During shutdown, the P-10 permissive to manually unblock the Source Range High .,
. voltage will not functio ANSWER * B
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K/A: "033 A2.ll importance: 3.1/3.4 -
Cognitive 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
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NRC Exam: 2 LOT 2, Rev 0; ;
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- Question 8-98-35
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35. - ' Unit 2 is operating in Mode I with all systems NSA. He most recent samples indicate the
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' following leakages in all three steam generator A= 0.5 spm . B= 0.1 gpm C=0.15 gpm . *
'
Which o[the followmg would be the required Technical Specification actions? , 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 houis and in
'
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Cold Shutdown withm the next 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> i
- 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 -
hours and in Cold Shutdown within the next 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> , 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 />.
7 . 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
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is in Cold Shutdow #
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ANSWER: A '
K/A: 037 2.1.22 Importance: 3.4/ :
o
" l Cognitive Level: Analysis - OPEN BOOK ' -
!
Ref.: BVPS Unit 2 Technical Specification 3.4. LP#: 2LP-SQS-53 OBJ: 2 History:
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- Modified from LOT #852
- l l JTA:'0000110401 Student gets copy ofTech Spec 1
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BVPS-2 .
fL NRC Exam: 2 LOT 2, Rev 0
.- Question 8-98-36
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. ;
36. -. . A cooldown is being conducted in accordance with ES-3.1 "RCS Cooldown Using Backfill." The
'depressurization of the RCS may be halted just before going to less than 360 psi Which of the following is the reason for stopping depressurization at this pressure?. The vessel must be soaked for I hour to remove thermal stresses from the cooldow <
,
\ The ruptured steam generator must be soaked above Nil Ductility Transition Temperatur To allow the differential pressure across RCP 21C to be maintained,above 215 psi i
. To stop backfill from the ruptured steam generator prior to establishing RHS coolin !
i ANSWER: C i
,
K/A: 038 K3.08 Importance: ,
Cel ive t Levil:' KnowW CLOSED BOOK Ref.: 20M-53B.4.ES-3.1 " Post-SGTR Cooldown Using Backfill" Issu#c IB, Rev. 4 Background for Note
. ..; .7
[ prior to Step 8 .
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1,. NRC Exam: 2 LOT 2, Rev 0
, Question 8-98-37 Y
L 3 Which of the following will complete arming of the C-20 signal for AMSAC7 Main Feedwater total flow has been greater than 25% for 180 second Two of three Narrow Range Steam Oenerator levels on one steam generator greater than
. . .
25%. T
' wo of four Power Range NI's are greater than 40% powe Two of two First Stage Impulse pressure transmitters are greater than 40% powe .. ,
--
I ANSWER: D K/A: 054 A2.03 Importance Cognitive Level: Comprehension CLOSED BOOK
,
Ref.: 2OM-1.1.B " Reactor Control and Protection Summary Description" Issue 4 Rev.1, Page 22 i
LP#: 2LP-SQS- OBJ: 4 Estory .
Source: LRT Exam Unit 1, ILP-LRT-III-49,- 2 LOT 2A Exam 11,12/18/97
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- ,. - NRC Extm
- 2 LOT 2, Rev 0
- . Que'stion 8-98-38 -
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L 3 Unit 2 is at.100% with all systems NSA. - Aruiunciator A8-9E "125V DC BUS 2-5 TROUBLE" is l:
l, ' lit. The following conditions exist: .
. .:
l Al-I A" DC DISTRIBUTION PANEL LOSS OF CONTROL DC" is lit . !
'
! Battery Charger Volts Meter on Battery charger 2-5 reads "0" volts p Which of the following would result from a loss of voltage on DC Bus 2-57 L.
! -. . A. - . 2 t A and 21B Main Feedwater pumps trip on loss of control power to 4KV bus 2A and2D ;
!: ,
.
j Main Generator Exciter Field Breaker ACB 41 opens on loss of control power 2
~^
l 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 l OPen l:
i- .
ANSWEk: C e.;
i
, K/A: 058 A2.03 ' Importance 3.5/3.6 l . .
[
Cognitive Level: Analysis OPEN BOOK ,
.
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LP#: 2LP-SQS-3 OBJ: 7 l
l History NEW
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JTA: 063004010i Student gets copy of reference s
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-
. NRC Exam: 2 LOT 2, Rev 0
'
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_ Question 8-98-39 l :?
u .
l . Unit I and Unit 2 are both at 100% power when a HIGH alarm is received on Control Room
Radiation Monitor [2RMC*RQ201J. Control Room Radiation Monitor [2RMC*RQ202] is in ALERT. Select from the list below the expected response from these alarm A. [2HVCMOD201 A & C] CR ACU Air intake and Exhaust Dampers close; [2HVC* MOD 201B &
D] CR ACU Air intake and Exhaust Dampers remain ope .
B. The Control Room Emergency Bottled Air Pressurin.-ion System will actuat C, 'ne Unit I and Unit 2 Emergency Ventilation fans start after a 60-minute time dela .
D. The standby Unit 2 Air Handling Unit, [2HVC*ACU201 A/B] receives an auto start signa ANSWER B K/A: 061 AA1.01 Importance: 3.6/ '
Cognitive Level: Knowledge CLOSED BOOK O3 Ref.: 2OM-43.4 "ADB Local Control Room Area (2RMC*RQ20l) High Alarm Level", Issue 1, Rev. 4
.
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LPS: 2LP-SQS-4 OBJ: 5 -
History:
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Source: LOT bank #0509 modified JTA: 013001010I l
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BVPS-2
- NRC Enm: 2 LOT 2, Rev 0 '
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- - Question 8-98-40
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40; The Unit is at 100% with all systems NSA. 21AC-P1106A "CNMT Instrument Air Header j
Pressure" reads O psig. If air pressure is not restored to containment, which of the following will cause a reactor trip?
'
- A .. Low SG level when SG Main Feed Reg. valves 2FWS-FCV478,488 and 498 clos '~
B . Low Pressurizer pressure when PORV's 2RCS*PCV455A and 455B ope l High pressuria.r level when Letdown Orifice Inlet valves 2CHS'*AOV200A, B and C
'
clos j High RCS pressure when Main Steam Isolation Valves 2 MSS-AOV101 A, B and C Sos l ANSWER: C ,
'
K/A: 065 K3.03 Importance: 2.9/ . Cognitive Level: Comprehension - CLOSED BOOK
-
Ref.: 2OM-53.4.3.34.2 " Loss of Containment Instrument Air", Anne t 1. Issue I A, Rev. 2 LP#: 2LP-SQS-3 OBJ: -5 *
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Source: NEW -
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, ' BVPS-2 t
, - NRC Exam: 2 LOT 2, Rev 0 -
Question'8-98-41
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4 The Reactor Coolant Tavg signal from loop 21 A is lost due to wire breakage. The u' nit is at 100%
c with all systems NSA; Which of the foll6 wing describes the impact on pressurizer level?
F A. - Pressurizer level will control at program level for 100% reactor powes:- ; _ Charging Flow Control valve 2CHS*FCV122 opens on indicated low level, actual
~
pressurizer level rise ^ Letdown Orifice Inlet valves close on indicated low level, actual pressurizer level rises.
- TA4-lC " PRESSURIZER CONTROL LEVEL DEVIATION HIGH/ LOW" is lit with all I heaters on. >
, ANSWER A
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K/A: ' 028 A2.02 Importance: 3.4/3.8 t .
-
Cognitive Level: Comprehension CLOSED BOOK >
Ref.: ' 2OM-6.5 Reactor Coolant System Figures and Table", Figure 6-62, Issue 4, Rev.' 6
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20M-7 " Chemical and Volume System Figures and Tables" Figure 7-15,
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.*. - NRC Exam: 2 LOT 2, Rev 0
- Quesdon 8-98-42
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4 Which of the following conditions will directly initiate stripping of the motor loads from the 4KV l Emergency Bus 2DF? .
. Bus 2P voltage drops to 90% of rated voltage for 90 second KV Station Dus 2D drops to 75% of rated voltage for 0.33 seconds
. Overcurrent on 480 VAC 2P Feeder Bkr 2F11 to 480 VAC Emergency Bus 2 . Emergency Bus 2DF Supply Leads Differential to from 2D to 2DF 4KV Emergency Bu .:.
ANSWER A I
K/A: 056 K3.01' , pportance: 3.5/ _ _
Cognitive Level: Knowledge C.OSED 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 Firpres and Tables" Issue 4, Rev. O Figure 36-7A '
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- NRC Exam: 2 LOT 2, Rev 0 l
- Question 8-98-43 -
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43) (Control of the Atmospheric Steam Dumps 2SVS*PCV101 A and 2SVS*PCV101B has been
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- transferred to the Altemate Shutdown Panel. If the valves are closed, rising steam pressure will l l: ;
'
l . cause which of the following automauc actions to occur first?
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h , Main Steam Safety Valves 2SYS*SV101 A, B and C will ope '
' Atmospheric Dump Valves 2SVS*PCV101 A, B and C will open.
b L ' Residual Heat Release Valve 2SYS*HCV104 will ope .
q Only atmospheric Dump Valve 2SVS*PCV 101C will ope l
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ANSWER B: ,
l K/Ai W/E 13 K Importance: 3.0/ i
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Cogaitive L.evel: Co.. yrd ;..eion
. CLOSED BOOK
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Re M-21.1.C " Main Steam System " Major Components", Issue 4, Rev. 0
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L 2OM-2 Ll.C " Main Steam System Precautions, Limitations, Setpoints" issue 4, Rev. 2 Page 3 and
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. NRC Exam: 2 LOT 2, Rev 0
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Question 8-98-44 i ,. .
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4 A fault occurs on the 4160 VAC Supply Breaker to the 480 VAC Bus 2A, causing it to open. This will result in:
A. A Reactor Trip due to the loss of power to a Reactor Trip Breaker Rod Drive M/G se B. A Reactor Trip due to the loss of power to all Group 'A' Shutdown Bank rod C. No Reactor Trip. No power for Rod Drive M/G sets or Control rod power comes from Bus 2 !
D. No Reactor Trip. All loads on Bus 2A will be automatically tied to Bus 2B via a Tie-breake ,
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ANSWER: D ]
K/A: 001K2.05 Importance: 3.1/ i Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M36.4.ACJ" 4160 to 480v Substa Feeder ACB Auto-Trip" Issue 1, Rev 3, Page 1 .
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_,. NRC Exam: 2 LOT 2, Rev 0 -
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- Question 8-98-45 4 When approaching criticality by rod ' withdrawal in 20M-50.4 " Reactor Startup From MoE to Mode 2," which of the following methods will ensure a smooth addition of equal increments of reactivity to the core?- Verification at 128 steps on Control Bank A that Control Bank B begins withdrawa Halting rod withdrawal at every 100 steps on Control Banks A and B to level count rat Verification of Shutdown Banks fully withdrawn prior to movenient.of. Control Bank . Verification of Reactor Coolant System Tavg above 541*F every 15' minutes until critica ..
ANSWER'A K/A: 001 K5.59 Importance 2.7/ .
'
Cognitive Level: Comprehension CLOSED BOOK .
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Ref.: 20M50.4.D " Reactor Startup From Mode 3 to 2", Issue 1, Rev. 29, Page 19 Generic Fundamentals Reactor Theory Fundamentals, Topic 3, tion B, Kl.09, Page 18
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- _ NRC Exami2 LOT 2, Rev Oi T Question 8-98-4 . . i
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.. There is a small break LOCA insule containmen .-
All systems respond as designe .
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. ' All S/G pressures are ~ 1000 psig
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RCS Pressure is 1480 psig and dropping slowl !
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.. Containment Pressure is 12 psi i Which of the following describes the reason the RCP's must be tripped?
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To prevent excessive depletion of RCS inventory which could lead to severe core ~ 1 1 ,
- uncover B.- . To prevent RCP motor bearing damage due to the loss of coolin : To prevent an RCP seal failure due to the loss of the seal water,retum flowpat . . .
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D. ' To prevent RCP motor damage due to the high temperature, high humidity operating
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environment of the conta'mmen .
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ANSWER: B -
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l~ K/A: 003 K6.04 i=e:-3=-r 2.8/ '
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Cognitive 1.evel: Comprehension CLOSED BOOK Ref.: 20M-53A.I.E-0 " Reactor Trip and Safety Injection" lea Hand Page '
f LP#: > 2LP-SQS-53 OBJ: 3 A
History 2 LOT 1 NRC Exam'- March 1997
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[ ' NRC Exam: 7 LOT 2, Rev 0 . "'
t ! Question 8-98-47:
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b' l Reactor Power at 50% I
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- Tavg is at 562*F 1 "
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-- Pressurizer Pressureis at 2235 psig -
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Pressurizer Level is below program at 36% !
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All control systems are in automatic except Rod Control which is in Manual '
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- The Operator notes that Pressurizer level is droppin i *
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l 1 Which instrument failure would cause the drop in Pressurizer level assuming there were no Operator )
I actions taken? ~
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'A; Impulse Pressure channel PT446 failed hig B. 'A'. loop hot leg RTD failed hig ~
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L C. NI-44 Nuclear Ir.0=._.;.Gon failed hig ,
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_ D. Chargmg flow transmitter FT122 fails high.
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ANSWER: D K/A: 004K3.02 - I=aartance: 3.7/ Coanitive level: Comprehension - CLOSED BOOK '
l Ref.: 20M-7.1.B " Chemical and Volume Control Figures and Tables" Issue 4, Rev. O, Figure 07-15
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. NRC Exam: 2 LOT 2, Rev 0 :
-f j i Question ~ 8-98-4 ;
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4 The unit is at 100% with all systems NSA. A Safety injection signal is generated High Head Safety Injection Pumps Suction Valve [ 2CHS*LCVI15B] opened BUT (2CH,S*LCV1ISD] failed '3 ,
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' to open, What is the impact of this action on the Chargmg Pump suction flow? - Both operating charging pumps will receive suction flow from the VCT. - '
B .' One charging pump will continue to take suction from the VCT and one charging pump . ;
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will take suction from the RWS , ,
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.l One charging pump will take suction from the RWST. The other charging pump will have j
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' no suction until operator action is take Both operating charging pumps would take suction from the RWST via -
' [2CHS*LCVil5B].
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ANSWER: D
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K/A: 004 K1.23 Importance: 3.4/ .
.
Cognitive Leveli Comprehension CLOSED BOOK
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! Ref.:- 2OM-7.5" Chemical Volume Control System Tables and Figures" Issue 4, Rev. O, Figure 7-1 !
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NRC Exam: 2 LOT 2, 'Rev 0 -
r . . ~ Question 8-98-49
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i 4 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 The Control Room Operator turns on Pressurizer Heater Banks A and B. Widino further operator
]
actions,: the first actuation will be:
.:. .
A.' Safety injection Signal on low steam generator pressure Safety injection Signal on low RCS pressure AMSAC actuation on low steam generator pressure - . Reactor Trip signal generated on low RCS pressure
.
!
h- ANSWER A K/A: 013 Kl.01 Importance: 4.2/ Cognitive Level: Analysis - CLOSED BOOK Ref.: 2OM-1.2.B " Reactor Protection Setpoints", Issue 4, Rev. 3, pages 4 and 5
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- BVPS-2 NRC Exam: 2 LOT 2, Rev 0 >
g.] - . Question 8-98-50 v:s .
l 5 During 100% power operation, the lowest (bottom) Data 'A' coil for a Shutdown Bank ' A' rod
_
fails (open circuit.), What is the effect of this failed coil on the Digital Rod Position Indication
- (DRPI) system? -
, . A.' No effect. The rod will indicate normally until it is fully inserted.
u B. No effect. The Data 'B' coils will compensate and provide normal indication for all rod elevation l
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C. All indication for the rod will .be lost until the failed Data 'A' coil is removed from the circuitry by
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taking the Accuracy Mode Selector switch to the Data 'B' positio )
i D. DRPI will automatically switch into the half-accuracy mode. A Rod Bottom and General Warning Status light will be flashing for the affected rod.
'
. ANSWER D K/A: 014A2.06 Importante: 2.6/ Cognitive Level: Co.rir,rdesion CLOSED BOOK
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Ref.: 2OM-1.1.B " Reactor Control and Protection" Page 18 of 22 Issue 4 Rev. I LP#: 2LP-SQS- OBJ: 4 l
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. NRC Exam: 2 LOT 2, Rev 0 Question 8-98-51
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5 Following the performance of the Daily Heat Balance Calculation, reactor power is determined to 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 anyl NI channels require adjustment? .t 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 adjustmen ~
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' ANSWER C K/A: 015A1.01 - Importance: 3.5/ Cognitive Level: Analysis- CLOSED BOOK ,
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Ref.: Daily Heat Balance 20M-54.4.C1 Issue 1 Rev.1I Page 2 of 5 LP#: 2LP-SQS- OBJ: 14 History:
Source: LOT Bank #0752 modified JTA: 0150070201
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- NRC Exam: 2 LOT 2, Rev 0
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..[- Question 8-98-52
, .
52 The B Train Incore Thermocouple Reference Junction Box has lost input from the installed RTD's
that monitor temperature of the box and transmit the temperature to the Plant Safety Monitor l l
System displa ;
I if the Reference Junction box temperature rises from 160'F to 180 F, then thermocouple EMF .
I would and indicated temperature would
.L drop, drop 1 drop, rise rise, drop rise, rise ANSWER A
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K/A: K6.01 Importance 2.7/ .
.
Cognitive Level: Comprehension CLOSED BOOK
, Ref.: Generic Fundamentals l- ,
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LNRC Exam: 2 LOT 2, Rev 0 ; -
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- Question 8-98-53 -
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5 Annunciator AI-lE " CONTAINMENT AIR PARTIAL PRESS HIGH/ LOW"is lit. Containment -
l Air Partial pressure is rising. Which of the following is the maximum pressure that could be
- - . allowed?_
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i i A.' 8.9 psia with a Service Water temperature of 60 degrees
- .2 psia with a Service Water temperature of 60 degrees _
. .4 psia with a Service Water temperature of 60 degrees
.- .5 psia with a Service Water temperature of 90 degrees
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l ANSWER.: B t
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l K/A:022 A1.01 Importance 3.6/3.7 -
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Cognitivo Level: Analysis OPEN' BOOK b r- '
[ Ref.: ( 2OM-12.4.AAA " Containment Air Partial Press High/ Low", Issue 4, Rev.1, Page 3 l
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- BVPS 2 Curve Bock CB-19A, Issue 7, Rev. 0 -
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'-Q1- : j ;. '-Question 8-98-54 ;
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- 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? - RSS-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 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> ! 2RSS-P21 A must be operabic 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 hour8.333333e-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 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> .:- RSS-P21 A and 2RSS-P21C must be operable in 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> .
ANSWER C l
[ K/A: 026 2.2.22 Importance: 3.41 "
Cognitive Level: Analysis
- '
' OPEN BOOK ,
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- NRC Exam: 2 LOT 2, Rev 0 !
O~_, } Question 8-98-55 --
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.. . . .
55. ' - With the unit operating at 100% power and all systems NSA, which of the following listed features a
will act to provide Net Positive Suction Head for the Main Feedwater Pumps?
A.- -2CNM-A0V100 Cc#=== Feedwater Heater Bypass Valve will open on low Feedwater !
' Pump Suction header pressur . Condensate Spill valve 2CNS-MOVl65 will open to divert condensate from Turbine Plant' .
Demineralized Water Storage Tank on low condensate header discharge pressur .L
.. . Standby Condensate Pump will start on low suction pressure to the Main Feedwater Pump ' Standby Condensate Pump'will start on low condensate header discharge pressur ' ANSWER D -
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K/A:. 056 K4.14 Iw.r,octi.r.ce: 2.2/ !
Cognitive Level: Knowledge CLOSED BOOK t
.
Ref.: 2OM-22A'l.D "Candam* System Instrumentation and Control", Issue 4 Rev. 2, Pages 1-9
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LP#: 2LP-SQS-22 OBJ: 5 *
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NRC Exam: 2 LOT 2, Rev 0
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Question 8-98-56'
,
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- . l 5 i To minimize the time that'a Main Feedwater Pump Motor [2FWS-P2i A1] takes to reach rated
.
.
speed, the start circuit of the Main Feedwater pump will:
~ Block start of the Main Feedwater pump if the Feed Pump Discharge valve [2FWS-MOV150A] is closed.
1; .
l . Delay the start of the Main Feedwater Pump motor [2FWS-P21 A2]. . . Block starting of the Main Feedwater pump until recirculation valve [2FWS-FCV150A] is
,
'
,L ope '
.
. Delay starting c.f the Main Feedwater Pump motor [2FWS-P21 A2] until discharge valve !
! [2FWS-MOV150Aj is open.
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- i ANSWER B
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K/Ai 059 K4.14 Importance 3.1/ .
Cognitive Level: Analysis - CLOSED BOOK
.
Ref.: 20M-24.5 " Steam Generator Feedwater System Figures and Tables" Figure 24-06A, issue 4, Re g
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BVPS- . NRC Exam: 2 LOT 2, Rev 0
. Question 8-98 57 .
. .
57.' Annunciator A2-3H " SAFETY SYSTEM TRAIN A INOPERABLE"is lit.- Annunciator A2-4H
,
" SAFETY SYSTEM TRAIN B INOPERABLE" is off. Which of the following would explain this condition? *
. Turbine Driven Auxiliary Feedwater pump overspeed latch not rese . Control'of 2 MSS *SOV 105A and 2 MSS *SOV105D is selected to the Emergency Shutdown Pane . e- Control transfer switches for 2 MSS *SOV105 A and 2 MSS *SOV105D are NOT reset
. > Any Main Steam Supply Valve to Turbine Driven Auxiliary Feedwater Pump 2 MSS *AOV105A through F close .
- ANSWER: A -
K/Ai 061 K4.06 bnportance 4.0/ Cognitive Level: Knowledge CLOSED BOOK
.
Ref.: 20M 24.1.D " Steam Generator Feedwater System" Issue. 4 Rev. 2 Page 23 2OM24.5 " Steam Generator Feedwater System" issue. 4 Rev I Figure 24-11 LP#: 2LP-SQS-2 OBJ: 10 History '
Source: NEW JTA: 0130010101 NOTE Change to Outline NEW K/A
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NRC Exam: 2 LOT 2, Rev 0 i
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[g ' Question 8-98-58 ;
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a .- :
SR The unit is at 100% power with all systems NSA. 21 A Steam Generator Aux. Feedwater Throttle Valve (2FWE-FCV100E) was closed for an approved BVT test and will not re-open. Which of l l
the following actions must be taken? - Restore the 2FWE-FCV100E and the 2A AFW train to OPERABLE status in 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> . C.- Align the Turbine Driven Auxiliary Feed Pump to the B Auxiliary Feed Header within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> l Restore 2FWE-FCV100E to OPERABLE status within I hour or be in HOT STANDBY l within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> l
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ANSWER B
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IUA: 061 2.1.12 Importance: 2.9/ .
Cognitive Level: Analysis OPEN BOOK
Ref.: BVPS 2 Technical Specification 3.7.1.2" '
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- Question 8-98-59 -
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59 !The Spare Battery Charger 2-7 will be removed from replacing Battery Charger 2-1 and will replace charger 2-3. Which one of the following limits applies?
l' : Battery 2-1 must be disconnected from DC Bus 2-1 while the Spare Charger is remove '
. .
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l ' B.' Battery Charger 2-1 must be paralleled with'the Spare Charger before the Spare Charger
. is remove Uninteruptible Power Supply UPS*VITBS2-3 must be on alternate AC power source I
.
,a when the Spare Charger it in service on BAT 2-3.'
' The Spare Charger FLOAT /EQUAll2ER switch must be operated in " FLOAT" while in -
servic J
,
.: ANSWER: C -
-
K/A: 063 Kl.01 Importance 2.7/ Cognitive Level: Knowledge CLOSED BOOK
.
Ref.: 20M-39.4.D " Placing Spare Battery Charg r in Service", Issue 4, Rev. 5, Precaution and
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NRC Exam: 2 LOT 2, Rev 0 ' ,
i .s t Question 8-98-60 -
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6 Liquid Waste Effluent Monitor 2SGC-RQ100 is out of service. The Steam Generator Blowdown Holding Tank 2SGC-TK21 A is to be released. What action will enable the release of the tank with
- the monitor out of service?
- .
' SGC-TK21 A must be recirculated for sufficient time to tum volume over twic s : Two indcpendent nmples for 2SGC-TK21 A must be analyze C. _ A Senior Licensed Operator must confirm release rate calculations and valve alignmen l
!- , s.' . Emergency Outfall Flow must be adjusted to exceed 1000 gpm prior to and during releas .
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ANSWER:: B K/A: 068 2.3.6- Importance 2.1/ l l !
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'$. Question 8-98-61
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61' Due to high activity being vented from the Boron Recovery System Degasifiers it has been decided to place the Waste Gas Charcoal Delay Beds [20WS-TK22A(B)(C)(D)] in se'rvice in the Waste E . .
Gas System. Which of the following functions will be served by this action? -
-
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- . Krypton isotopes will be delayed for up to 30 days for decay l . lodine 131 will be delayed for up to 30 days for decay - ,
. , : L Xenon isotopes will be delayed for a minimum of 30 days for decay -
.e . Krypton 85 will be delayed until decayed below minimum detectable levels - l
.
I ANSWER: C l K/A:- 071 2.1.28 Importance 3.2/ * Cognitive Level: Knowledge CLOSED BOOK
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6 When using the PJd !! Console, the Key Lock function must be used to perfonn which of the following functions? Acknowledge system alarms with the SYSTEM ACK function key
- Request a filter advance using the FILTER function . Clear the RM-1 I screen with the CLEAR SCREEN entry function key Reset RM-80 setpoints in SUPERVISORY mode c-ANSWER: D K/A: 072 A4.01 Importance: 3.0/ Cognitive Level: Knowledge CLOSED BOOK
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Ref.: 20M-43.1.D " Radiation Monitoring System" Page 4 of I8. Issue. 4 Rev. O
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NRC Exam: 2 LOT 2, Rev 0 .
L Question 8-98-63 ~
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l 63.' The unit is in Mode 3 in preparation for startup. The root stop isolation valve for the high- .
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l j.~ 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? -
l~ Annunciator'A2-5E " Reactor Coolant Loop Flow Low" is li _
l A reactor trip signal is generated on low reactor coolant system flow.
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.. C' . Annunciator A2-4G " Reactor Coolant Loop By-Pass Flow Low" is lit.
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- D.' : An Overpower / Delta T reactor trip signal is generated on low reactor coolant system flow,
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ANSWER: A
.
K/A: 002 A1.05 Importance: 3.1/3.7
' -
Cognitive Level: Comprehension CLOSED BOOK-
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- k.i.). Ref.: - 20M1.2.B " Reactor Control and Protection Precautions, Limits and Setpoints", Issue 4, Rev. 3 LP#: 2LP-SQS-1.2 - OBJ: 4 .
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6 Following a Loss of Coolant Accident (LOCA), RCS pressure is 300 psig and slowly droppin Which of the following statements describes what should be the nornul status of the Emergency Core Coding Flow at this point in time?
A. Constant HHSI flow exists with no LHSI flo , ,
B. Increasing HHSI flow exists with no LHS1 flo C. Constant HHSI and LHSI flow exist . D. Increasing HHSI and LHSI flow exist ANSWER B K/A: 006K5.06 Importance: 3.5/ '" Cognitive Level: Knowledge CLOSED BOOK (?)
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[w.p Question 8-98-65 ' .
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65 The unit is heating up with the Reactor Coolant Pressure at 885 psig. Pressurizer Pressure Relief -.
p : Tank pressureis at 40 psia and PRT temperature is rising. What would be the maximum . l
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temperature that would appear on the Pressurizer Safety Relief Valve Tail Pipe Teimperature !
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- .j Indicator if one of the Pressurizer Safety valves were leaking? . l t I ( degrees .
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ANSWERiA
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K/A: 010 A1.09 - Importance: 3.4/3.7, .
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i L .: Coanitive Level C6.recla.kwi OPEN BOOK l Ne Steam Tables .
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NRC Exam: 2 LOT 2, Rev 0 l '(hEi' Question 8-98-66
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6 The unit is at 100% power with all systems NSA. Seal injection flow is the minimum allowed per -
operating procedure to each Reactor C ' oolant Pump. De flow controller for 2CHS*FCV122 has
- manually repositioned to had What is the charging . flow and seat injecten flows after
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2CHS*FCV122 reaches its new demanded position? No charging flow and seal' injection flow to each RCP below f6inimu : Maximum charging flow and seal injection flow to each. Reactor Coolant Pump A
- below minimu '
4 Maximum charging flow and seal injection flow to each Reactor Coolant Pump above minimu . No charging flow and seal injection flow to each Reactor Coolant Pump above
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ANSWER: D
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K/A: 011 Kl.02 Importance 3.3/ ,
Cagnitive Level: Comprehension . CLOSED BOOK Ref.: 2OM-7.1.C "CWal and Volume Control System" , Issue 4, Rev. 3 Page 23
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L NRC Exam: 2 LOT 2, Rev 0
' Question 8-98-67~
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67. . . The plant is operating at 100* power when a loss of 4160 VAC Bus 2A occurs resulting in a
' reactor trip. The following signals were generated:
1. Low Reactor Coolant Flow Tri ,
._
2. SG21 A (21B) (21C) Low level Reactor Tri . RCP Breaker Tri ~
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4. Generator Trip Due to Turbine Tri Which one of the following choices depicts the order in ivhich the signals were generated? .
_ JA. 2, 3,11, 4 .
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- B. 3, 1, 2, 4 C. ~ 3, .4, .1, 2 D. ; 1, 3, 4,- 2 ,
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K/A: O12K4.02 Importance: 3.9/ Cagnitive Level: CompreWeio, CLOSED BOOK Ref.: 2'OM-1:2.B " Reactor Control and Protection" Precautions, Limitations and Setpoints, Issue 4, Rev. 3
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Which of the follawing describes the response of the Tavg control system to this failure? ?
l As the "B" loop Tavg drops, the selected Tavg will swap from "C" loop to...
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.' "A" loop, then to "B", then finally back to "C". .
., - , "B" loop, then to "A", then finally back to "C". ,
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K/A: 016 A3.01' Importance 2.9/ .
.
. . . .
. .
Cognitive Level: Comprehension CLOSED BOOK ,
l Ref.i 20M-6.1.D Reactor Coolant System', Issue 4 Rev. O page 18
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1 ' NRC Exam: 2 LOT 2, Rev 0 .
l f.' %.g;. ~ Question 8-98-69 y e Jba=
6 Contaitunent llydrogen concentration has reached 1.5% when B Train Recombiner fails. How will
~
the H2 concentration in Containment be affected? Hydrogen concentration will peak above the 4% design basis with only the A Train in
/
-service.
' Hydrogen concentration will remain below the 4% design basis using only the A Trai . Containment venting must be conducted to ensure Hydrogen concentration remains less .
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. than 4%.
- ~ Hydrogen concentration will remain less than 4% if Train B suction is aligned to Uie
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suction of the A Train Recombiner.
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ANSWER: B -
- K/A: 028 K3.01 Importance: 3 3/ .
Celtive Level: Comprehension CLOSED BOOK
.
I Ref.: : 2OM-46.1.A " Post DBA Hydrogen Control System", issue I, Rev. 5 page 1 i'~
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Question 8-98-70 .
7 The suction piping of the fuel pool cooling pumps,2FNC'P21 A and 21B, has ruptured and cannot
, be isolated. Choose the lowest resulting fuel pool level by design that will result? . Approximately 10 feet above spent fuel assemblie .
B. . ' Approximately 23 feet above spent fuel assembliese !
s Approxunately a level equal to the top of the fuel assembhe i
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K/A: 033 K3.03 Importance: 3.0/ Cognitive Level: Comprehension . CLOSED BOOK
. . .' " Ref.i 20M-21.1.B " Spent Fuel Pool Cooling and Purification System", Summary Description, Issue 4, l
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selected for control. . If the transmitter were isolated and vented, what would be the impact on the l
steam generator level control system?
f
. Ai Steam generator level would exceed program level causing feedwater flow to dro Steam generator level would drop to no-load level causing feedwater flow to ris Indicated steam flow would exceed feed flow causing feedwater flow to rise, i Indicated steam flow would be less than feed flow causing feedwater flow to dropf
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ANSWER: A ;
'
K/A: 035 A2.03 Importance: 3.4/ .. & I
~ '
C=nitive Level: Comprehansion CLOSED BOOK 1
6 '
Ref.: = 2OM-24.4.IF " Main Steam Instrument Failure" , Issue 4, Rev. 5, A*=rhment 5, page 38 of 43 ;
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NRC Exam: 2 LOT 2, Rev 0 -
- Q~ Question 8-98-72 ~
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7 ' The unit is on natural 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 and 21B Steam Generator Atmospheric Dump Valves only :
1 C Steam Generator Atmospherie Dump Valve only - l All steam generators via 2SVS*HCV104 Residual Heat Release Valve
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- - -
Cognitive Level: Comprehension , CLOSED BOOK Ref.: 20M21.3.C " Power Control and Switch List" Issue 4 Rev 7 Page 2 of 50 OBJ: 4
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/ Question 8-98-73 7 The unit is at 100% with all systems NS A. The following pump sets are runismg:
l Condensate 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 no fault detected. Which of the following will be the response of Service Water pumps and the Condensate pumps to the opening of the breaker?
'
A.' SWS pump 2SWS*P21 A powered from 2A SSST, all other pumps NS l l
I SWS pump 2SWS'P21 A powered from EDG 2-1, all other pumps NS SWS pump 2SWS*P21 A and CNM pump 2CNM*P21 A powered from 2A SSST.
, SWS pump 2SWS'P21 A powered from EDG 2-1, CNM pump 2CNM*P21 A off, CNM l
- ,
pump 2CNM'P21C o ;
L0 ANSWER: B
.
'
K/A: 062 K4 Importance: 2.8/ .
l Cognitive Level: Comprahension CLOSED BOOK l
Ref.: 2OM-36 .l.D" 4KV Station Service System Instrumentation and Controls" Issue 4, Rev. 3, pages 10
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to 20 LP#: 2LP-SQS-3 OBJ: 4 History (
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L. Question 8198-74 i
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7 Both'4KV Emergency Busses have been de-energized for over 30 minutes. Pressurizer level is off
'
L scale low with no cooldown in progress. All steam generators are less than 5% narrow range.
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When Diesel Generator 2-1 is loaded on the bus which of the following pumps will need ' =M=$a l
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. verification of starting per ECA-0.0 " Loss of All AC Power"? .
i y . HHS1 pump 2CHS*P21 A ' j
) Auxiliary Feedwater pump.2FWE*P23'A
- C.' Component Cooling Water pump 2CCP*P21 A , ;, ,
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' Service Water Pump 2SWS*P21 A
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~ANSWER: D
-
K/A: 064 K1.01- Importance: 3.1/ . . Celtive Level: C=preiwmion CLOSED BOOK
'
Ref.: 2OM53.4.ECA-0.0 "I~< of All AC Power" Issue IB, Rev. 4 Step 37
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Source: LOT exam bank 560 .
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- NRC Exam: 2 LOT 2, Rev 0 ;
.
Question 8-98-75
,_ j 7 Unit 2 is at 100% power with all systems NS.A. An " ALERT" alarm on 2CCP RQ100 occur '. Steam Generator 21B has high activity due to a small tube leak. Level is rising in the CCP surge tanks. Which of the below listed heat exchangers is likely to be leaking? - Boron Recovery Degasifier Vent Condenser 2BRS-E22A l B.- Reactor Coolant Pump Seal Water Return Heat Exchanger 2CHS*E21 !
'
. Steam Generator Blowdown Heat Exchanger 2BDG-E22 . . . ,
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i i- D. . . Letdown Non-Regenerative Heat Exchanger 2CHS*E22 ,
. .
,
.
ANSWER: D K/A: 073 K1.01 Importance 3.6/ Owaitive Level: Knowledge CLOSED BOOK -
- Ref.
- - 20M43.4.AAE Local C.- ==t Cooling Water (2CCP-RQ10d) Alert Alarm Level""
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LP#: 2LP-SQS - 4 OBJ: 9 ,
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I Source: Based on SQS 1203-JTA: 0000420401
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l .' NRC Exam: 2 LOT 2, Rev 0 Question 8-98-76 . . . ,
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L 7 A request has been submitted for a Temporary Operating Procedure to allow closing Main
,
! Condenser Outlet valves 2CWS*MOV100C and 100D to manually clean both waterboxes under i
one clearance. Which of the following must be resolved prior to approving the procedure change?
' Service water return from the CCS HX's to the cooling tower will be blocke ,
l Service water must be aligned to the Emergency Outfall to prevent overpressure of the condense , Service water return from the CDS Chillers must be aligned to Unit I Cooling Toweg Blowdow Service water pump seal injection water must be shifted from Filtered Water to the Service Water strainer .
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ANSWER:- A-l i K/A: 075 K4.01 Importance 2.5/ .
Chitive Level: Comprehension OPEN BOOK
.
Ref.: 20M-31.2.A " Circulating Water System Precautions and Limitations", Issue 4, Rev.0,
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Precautions 18 and 19" LP#: OBJ:
IIistory Source: Based on SQS question 60
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- .* NRC Exam: 2 LOT 2,'Rev 0 -
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-- Question 8-98-77 x ,
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7 ' The containment instrument air is currently being supplied by Station Instrument Air via r l
' 21AC*M'OV131. If a CIA signal were generated which of the following would be the impact on j
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the Containment Instrument Air system . ;
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A.- 21AC*MOV131 will close and the lead Containment Instrument Air compressor will star AC*MOV130 will close and the lead Containment Instrument Air compressor will star .t
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21AC*MOV131 will close and all containment air valves will go to fait position. D. ' 21AC*MOV130 will close and all containment air valves will go to fail position. , ,
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K/A: 079 A4.01 Importance 2.7. OPEN BOOK w. C== tive Level: Analysis
.
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Ref.: ' 20M-34.5"Camaressed Air Systems Figures and Table" , Issue 4l Rev. 3 Figures 34 3 and 34-7A
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- NRC Exam: 2 LOT 2, Rev 0
- -
Question 8-98-78 -
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t 7 ' A CO 2discharge is imminent in a protected zone. Which of the following actions are available to alert personnel in the protected zone?
- Predischarge waming horn sounds inside the protected zon , Blue rotating lights are initiated in all occupied areas for the protected zon The CO 2contains a Wintergreen oderizer to flood the zone prior to discharg All key card controlled entrance doors are locked closed for the affected zon "
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ANSWER: A K/A: 086 A4.04 Importance 3.1/
Cognitive Level: Knowledge CLOSED BOOK-i Ref.: 2OM 33.1.D " Fire Protection Systems Instrumentation and Control", Issue 4, Rev. 2, Page 4 of i 1
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LP#: 2LP-SQS-33 OBJ: 3 History 2 LOT 2,11/7/97, (Fire Protection, Alt. Safe Shutdown, Injury and Casualty Control) .
Source: BasM on SQS 1132 JTA: 086007010I i r
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NRC Exam: 2 LOT 2, Rev 0 Question 8-98-79
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7 When exiting the containment using the 18 inch Escape Manway,2PHS*PI f 0I" Altimeter" and 2PHS*F1101 " Speed Indicator" provide what function?
, Input to the Emergency Door "OPEN" alarm bell while opening the outside doo Provide an audible whistling sound until air pressure differential is less than 0.5 psi Guide the door operator to control depressurization rate while equalizing pressur . Input to the Personnel Hatch door interlock ring while equalizing pressur .
ANSWER: C K/A: 103 K4.04 Importance: 2.5/ Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M-47.4.C "18-inch Escape Manway Operations", Issue 4, Rev. 2, Not.e before step 2 on page 4
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NRC Exam: 2 LOT 2, Rev 0
- Question 8-98-80
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8 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
[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 2RHS*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 maintain flow at pre-event. Temperature will dro B. The valve fails open. The RHR pump will trip on overcurrent due to run-out. RCS temperature will initially drop and then rise aller the pump trip C. The valve fails closed. [2RHS*FCV605A] will automatically open to maintain flow. Temperature will ris D. He valve failing closed. [2RHS*FCV605A] will need to be manually opened to maintain flo Temperature will drop until FCV605A is opene ' -
ANSWER: A
'
K/A: 005A2.04 Importance: 2.9/ Cognitive Level: Comprehension CLOSED BOOK
_Ref.:
20M 10.5" Residual Heat Removal Systems Figures and Tables" Figure 1 LP#: 2LP-SQS-1 OBJ: 5 History:
Source: New TTA: 0050080101
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Question 8-98-81 8 ~ The reactor trips from 100% power. The following conditions exist:
- Steam Dump Mode Selector Switch is in Tavg position Reactor Trip Breaker "B" indicates close Which of the following plant responses will be the result of the above conditions? He C-20 Permissive 180 sec. time delay is blocked and AMSAC actuate . Tne Steam Dump Lo.ad Rejection controller maintains Tavg within 5'F of no-load Tav Feedwater Isolation Signal on Low Tavg is blocke The "B" Train Safety injection Automatic Actuation signal is blocked.
A ANSWER: B K/A: 041 K4.17 Importance: 3.7/ Cognitive Level: Comprehension CLOSED BOOK'
Ref.: 20M-21.5 " Main Steam System Figures and Tables" Issue 4, Rev. 2 Figures 21-9G to K .
LP#: 2LP-SQS- OBJ: 3 Hist '
Source: LOT Exam question 31 JTA: 0120080101
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' NRC Exam: 2 LOT 2, Rev 0
- Question 8-98 82 .
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8 During a turbine startup, the Valve Position Limiter is inadvertently left at 100% when the turbine latch pushbutton is pushed. Which of the following valve actuations occur?
1. -Throttle Valves Open
-
2. Govemor Valves Open 3. Reheat' Stop Valves Open i
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D. 2 onl ;
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C. l and 3
.
D. 2 and 3 i
ANSWER D j K/A: 045A4.% Importance: 2.8/ :
Cognitive Level: Comprehension CLOSED BOOK
.
Ref.: 20M-52.4.A " Increasing Power From 5% Reactor Power and Turbine on Turning Gear to Full Load Operation" Issue 1 Rev. 33, page 20 to 22 LP#: 2LP-SQS 5 OBJ: 9 History: i l
Source: LOT bank #0492 modified JTA: 0450020101
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.* Question 8-98-83
- . 8 . Pressurizer Relief Tank (2RCS-TK21) alarm A4 3H " PRESSURIZER RELIEF TANK
!
TROUBLE" is lit. Computer address LO494D is in alarm. Which of the following could be the i cause of this alarm?-
1 CHS*Pil45 Letdown pressure is 700 psig.
l l CHS*Pil22 Charging Pressure is 2275 psi ;
1 CHS*PIl38 Excess Letdown Pressure is 135 psi ..
' RCS*Pl402 Rx Coolant System pressure is 150 psi . .-
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ANSWER: A .
l K/A: 007 A3.01 Importance: 2.7/ Cognitive Level: Analysis OPEN BOOK .
Ref.: 20M-6.4.AAY " PRESSURE RELIEF TANK TROUBLE ", Issue 4, Rev. O, page 11 of 18 LP#: 2LP SQS- OBJ: 15
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' NRC Exam: 2 LOT 2, Rev 0
- .' - Question 8-98-84 8 Two separate channels, Pressurizer Pressure 2RCS*PT444 and PT445, are pr'ovided for Pressurizer Pressure Coutro ' 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 -
.
PT445 and cannot be selected between the tw .
B. A control switch is provided to determine which channel is used to accomplish various control function . 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 Controlle .
. .
ANSWER: A K/A: 2.1.28 Importance: 3.2/ Cognitive Level: Knowledge CLOSED BOOK
Ref.: 20M-6.6 " Reactor Coolant System Figures and Tables", Issue 4, Rev. 6, Figures 6-36 and 6-37 LP#: - 2LP-SQS- OBJ: 11 _
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- Question 8-98-85' ;
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85 - Given the following:
'I
' . Unit 2 is in Mode I
. Both Containment instrument Air Compressors have faile .
- [21AC-MOV131] Station Instrument Air to Containment Instrument Air Cross Connect has been opened to maintain containment instrument air pressur Which of the following represents the Technical Specification actions required for the above listed conditions? f A. The valve may be opened under Administrative control as long as an operator is 6xiicated to close the valve if the Standby Alarm is sounde B. . Commence immediate preparation for plant shutdow C. No Technical Specification actions require D. Restore containment instrument air pressure and close (21AC-MOV131] within one hour or be in Hot Standby within the next six hour .
ANSWER: C K/A: 2.1.10 ' Importance: 2.7/ :
Cognitive Level: Knowledge CLOSED BOOK i
j Ref.: .TS 3.6. ' '
LP#: 2LP-SQS-53 OBJ: 3 History I
Source: LOT Bank #0113 modified JTA: 1190150301
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BVPS-2 NRC Exem: 2 LOT 2, Rev 0
-
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8 Which of the following stateme.r.; is NOT correct regarding a confined space gntry?
A. An entry into the confined space shall consist of a minimum of two individual <
B. A method of communication shall be established to nuintain contact with personnel within the confined spac C. An SCBA for emergency use shall be located near the entrance of a confined space when certain .
tasks are being performed withi ' D. For conditions when an SCBA used by rescuers nuy be impractical, the ventilation flow can be ,
increased as an additional precautio ANSWER: A K/A: 2.1.26 Importanch: 2.2/ CLOSED BOOK
] Cognitive Level: Knowledge .
Ref.: NPDAP .
LP#: STOP Training ODJ:
History
-
Source: LOT Bank #0173 JTA: 3420200302
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[ < Question 8-98-87 L
87 Unit 1 is in Mode I and Unit 2 in Mode 4 with the normal shift complement. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, the Unit 2 ANSS is injured and is transported to a local Emergency Center for treatment. He will not r: turn this shif Which of the following statements is correct with regard to authorized shift staffing?
A. Credit can be taken for the Unit i ANSS provided the Unit 2 NSS does not leave the control roo f
'
B. An additional supervisory qualified SRO must be added to the shift complement by 0500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> '
l- C. An additional supervisory qualified SRO must be added to the shift complement by 0600 hour0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> D. Since the next shift will be relieving within 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 the next I
shift has a full complemen ANSWElt C K/A: 2. Importance: 2.3/ !
Cognitive Level: Comprehension CLOSED BOOK
.
Ref.: 1/20M-48.1.B " Operations Shift Complement and Functions" Issue 3, Rev.17, pgs. 3&4 LP#: 2LP-SQS-4 OBJ: 2 i
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History
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JTA: 3430060302 l
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- BVPS-2 NRC Ex:m: 2 LOT 2, Rev 0 e Question 8-98-88 L
8 . Which of the following items on the ANSS Shift Turnover Checklist would ONLY be the responsibility of the OFF-GOING ANSS7 . Review previous shift narrative logs - List any Technical Specification items in effect Review the ESF Mimic Print for out of normal conditions ,
Log 5 qualified fire brigade members in the ANSS log - .' ANSWER B K/A: 2.1.18 Importance: 2.9/ 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 Checklist LP#: 2LP-SQS-4 OBJ: 3 .
History Source: LOT Bank #0384 modified JTA: 1190030301
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DVPS-2 l NRC Ex:m: 2 LOT 2, Rev 0
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Question 8-98-89 . .
i 8 The unit is at 375'F with pressure at 900 psig. St Accumulator 2 SIS *TK21C is pressurized to i
550 psig. Which of the following actions is allowed?
l IIcat up and RCS pressurization above 1000 psig may continue, with up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to l
restore the accumulator to OPERABLE statu l l Heat up and RCS pressurization above 1000 psig may continue, with up to I hour to j l
l restore the accumulator to OPERABLE statu l The unit must remain in HOT STANDBY below 1000 psig until the accumulator is I
restored to operabilit ] The unit must be placed in HOT SHUTDOWN within I hour and COLD SHUTDOWN l within ti e following 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> . . ..
ANSWER: C K/A: 2.1.33 Importance: 3.4/ .
Cognitive Level: Analysis OPEN BOOK Ref.: BVPS Unit 2 Technical Specifications 3.5.1 " Accumulators" Tech Spec 3. LP#:- 2LP-SQS-TS OBJ: 1 History Source: NEW JTA: 3410180302 Student gets copy of Tech Specs
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NRC Exam: 2 LOT 2, Rev 0
< Question 8 98-90 9 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?
A. Return the plant to mode 4 within the next 6 hour6.944444e-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 take 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 hour6.944444e-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 hour0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> :
ANSWER: D K/A: 2.2.22 Importance: 3.4/ Cognitive Level: Comprehension OPEN BOOK Ref.: TS 3.7. LP#: 2LP-SQS-TS OBJ: 1 ,
I History:
Source: New .
JTA: 1190150301 Student gets copy of Tech Specs l
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 L .- Question 8-98-91
!
s, 9 During Mode 1 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. The basis for determining the time for Transfer to Hot Leg Recirculation following a LOCA may be invalid, resulting in precipitation of the soluble boro B. The reactor may not comply with Shutdown Margin Boron requirements to remain suberitical following an analyzed acciden 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 criteri D. During a Design Basis Accident the Recirculation Sump would overfill and flood safety related systems in the containmen .
ANSWER: A
K/A: 2.2.25 Importance: 2.5/ ' ' '
Cognitive Level: Comprehension OPEN BOOK Ref.: TS 3.1.2.8 and Bases LP#: 2LP-SQS-TS OBJ: 1 History Source: LOT Bank #0271 modified JTA: 1190150301 Copy of Tech Specs
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0
- .
- Question 8-98-92-92i: When performing a station startup in accordance with OM Chapter 50, " Station Startup," steps marked by a filled diamond sign (+) indicate the step:
A. may be skipped at the discretion of the NS B. may be' skipped provided the GMNO initials the omitted ste C. cannot be omitted, but may be started out of sequenc D. cannot be omitted and must be perfonned in the specified sequenc "
ANSWER: C -
i K/A: 2. '
Importance: 3.7/ .
Cognitive Level: Knowledge CLOSED BOOK Ref.: 1/20M-48.2.C " Adherence and Familiarization to Operating Procedures", Issue 4, Rev. O, Page 6
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and 7 LP#: 2LP-SQS-4 OBJ: 10 ,
History Source: LOT Bank #0386 l
JTA: 119CCC0301 l
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< r LQuestion 8-98-93 = )
9 'The NSS and ANSS have decided that an On the Spot procedure change is need this shift to- i
.J-1 e continue a process. The change is determined to remain within the intent of the procedure. ~Ihe .j
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l procedure change involves a system procedure, which has no impact on Technical Specification
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' 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 shift? ,
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. A review by an approved Operations Unit Non-intent Reviewe B. . Approval by a Unit 2 Senior Reactor Operato ' A review by a SPED enginee D.' ' Approval by the GNMO or designated Technical Assistant within 14 days.:
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ANSWER: C'
K/A: 2.2.6 - Importance: 2.3/ .
Cognitive Level:' Knowler, , ' CLOSED BOOK -
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Ref.: --'1/20M-48.2.B Control of Operating Procedures issue. 4 Rev.15 Pages B10 and Bi1 LP#:' ! 2LP-SQS-4 l OBJ: 10 History ~
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BVPS-2 : {
NRC Exam: 2 LOT 2, Rev 0 ]
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i 94.- Unit 2 is in the process of completing the initial conditions to release a Gaseous Waste Tank to the i
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' Unit 1 Atmospheric vent. Both Unit I and Unit 2 ANSS sign and date the PRE (discharge authorization block) of the RWDA-G. Which of the following is OUTSIDE the re's ponsibility of the Unitt and Unit 2 ANSS signatures?;
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A .- The approval has been granted for the release of the specified tank under the RWDA- .
. Only one gas tank from the station is being discharged at one tim Tritium sampling by the Chemistry department has been completed for the specified tan All RM-11 alarm setpoints have been properly adjusted in accordance with the RWDA- I ANSWER: C K/A: 2. Importance: 2.5/ Cognitive Level: Knowledge CLOSED BOOK Ref.: ' 1/20M-19.4A.B " Unit 2 GW Storage Tk Disch to Unit 1 Atmos Vent" III. 9, page B3, Issue. 3 Rev ,
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LP#: 2LP-SQS-1 OBJ: 9 - -
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JTA: 34l'0120302
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NRC Exam: 2 LOT 2, Rev 0 i
- - Questio'n 8-98-95
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95, Unit 2 is in Mode 5 and containment purge is in progress under an RWDA-G.' He ANSS is notified that a drain on the letdown line downstream from the Regenerative Heat Exchanger was
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opened and is draining to the floor. Which of the following actions should the ANSS take? j ' Stop the purge and close out the current RWDA-G for the containment purg j i Stop the purge and notify the Health Physics department to sample the Containment !
l atmosphere before re-initia. ion of the purg Stop the purge and verify the drainage is completed or stopped prior to restarting the conta'inment purg D .~ Stop the purge and notify the Health Physics department to update the setpoints for the RWDA-G before continuing the purg ANSWER: A K/A: 2. Importance: 2.5/ .
Sognitive Level: Knowledge CLOSED BOOK Ref.: - 20M44C.2.A " Precaution and Limitation", Issue 4, Rev.1, Item " General" 7, Page 1 of 2
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BVPS-2 NRC Exam: 2 LOT 2, Rev 0 l Question 8-98-96
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9 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?
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A. Low Steam Line Pressure Safety injectio ' B. Pressurizer Pressure High Reactor Tri '
C. High High Steam Generator Level Feedwater Isolatio . D. Pressurizer Pressure Low Safety injectio .
ANSWER: A ]
I K/A: 2. Importance: 4.0/ l Cognitive Level: Comprehension CLOSED BOOK Ref.: Transient Analysis ,
LP#: 2LP-SQS-2 OBJ: 7 History: .
Source: LOT Bank #0625 JTA: 342025Q302
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- BVPS-2 NRC Exam: 2 LOT 2, Rev 0 e . Question 8-98-97
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9 De Digital Rod Position Indication system has just generated a Non-Urgent alarm. Which of the following could be the cause for this alarm?
~ Loss of Data A and Data B signal from a single ro .
B. Disagreement between two central control rod C. A central control card calculates a rod's position as 236 steps withdraw D. Accuracy mode selector switch placed in the A+B positio ANSWER B K/A: 2.4.31 Importance: 3.3/ , , _
Cognitive Level: Knowledge CLOSED BOOK Ref.: 20M 1.1.B " Reactor Control and Protection Summary Description" Issue 4,' Reil; 1, Page 18 LP#: 2LP-SQS- OBJ: 8 History: .
Source: LOT Bank #0690 modified JTA: 0140030101
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' NRC Ex:m: 2 LOT 2, Rev 0 e Question 8-98-98 9 The Emergency Classification that requires the implementation of Site assembly / accountability is I . This assembly / accountability must be completed within 2
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A. (1) Alert;(2) 30 minute k-B. (1) Alert;(2)60 minute C. (!) Site Area Emergency;(2) 30 minutes.-
D. (1) Site Area EmerF.ency;(2) 60 minute ANSWER:C
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K/A: 2.4.44 Importance: 2.1/ Cognitive Level: Knowledge CLOSED BOOK
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Ref.: EPP/IP 3.2 " Site Assembly and Personnel Accountability" Page 5 and Page 11 LP#: -EPP57 OBJ:
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- BVPS-2 ,
L NRC Ex:m: 2 LOT 2, Rev 0 e Question 8-98-99 I
i 99. - Security has reported that there is smoke in the computer room for the Unit i Simulator Facility,
= As ANSS what should your response be? Authorize the Security Shift Supervisor to call the local fire departments for respons i Dispatch the site fire brigade and notify the local fire departments for suppor ! Notify the local fire department and dispatch an operator to de-energize equipment as neede Notify the local fire department and dispatch security with the required support equipmen ANSWER C l K/A: 2.4.27 Importance: 2.9/ Cognitive Level: Knowledge CLOSED BOOK l
Ref.: 20M-56B.4.1" Fire Brigade and Fire Fighting Procedures " issue 1, Rev. 9 page B9 of 18 LP#: 2LP-SQS 4 OBJ: 5
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- NRC Exam: 2 LOT 2, Rev 0 - !
!v- Qurstion 8-98-100
10 Unit 2 is operating at 100% with all systems NSA. A reactor trip is actuated. The ANSS observes the NCO's performing the following inunediate actions from E-0 " Reactor Trip and Safety injection": Manually stop both Turbine EH Fluid pumps, i Manually open PCB 352, "No/ 2 Main Tfmr No. 5 345 KV Bus Bkr"
! Depress the Reheater Controller Reset pushbutto l
, .< i Depress Emer Gen 2-1 " Start" pushbutto l
In what sequence should the ANSS observe the above actions? l ,3,4,2 l i ,2,3,4 l l ,2,4, )
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K/A: - 2. Importance: 4.3/ Cognitive Level: Knowledge CLOSED BOOK
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Ref.: 20M53.A.I.E-0 " Reactor Trip or Safety Injection" Issue IB, Rev. 4 - . .- 1 l- l l
LP#: 2LP-SQS-5 OBJ: 3 l History i'
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- NRC Exam: 2 LOT 2, Rev 0 ~
,. Question 8-98-101 I; A 2 D 5 C 7 A B 2 C 5 A 7 D D 2 D 5 B 7 A D 2 A' 5 C 7 C B 3 C 5 D 8 A l B 3 B 5 B 8 B J C 3 D $ A 8 D j A 3 D 5 B 8 A C 3 B 5 C 8 A ;
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1 D 3 A 6 B 8 C 1 B 3 C 6 C 8 A l l
1 C 3 D 6 D 8 C 1 B 3 C 6 A '8 B I i
1 A 3 B 6 B 8 C
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1 D 4 C 6 A 9 D j 1 A 4 A 6 D 9 A !
1 b 4 A 6 B 9 C .
1 D 4 B 6 C 9 C
1 D 4 D 6 B 9 C 2 D 4 A 7 A 9 A 21 A 4 B 7 A 9 A 22.- A 4 D 7 D 9 B ,
23.- B 4 D 7 B 9 C 2 D 4 A
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25 C 5 D 7 D 10 D
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l Attachment 2 j SIMULATION FACILITY REPORT Facility Licensee: Beaver Vallev Unit 2 l
Facility Docket No: 50-412 l
Operating Tests Administered from: Auoust 17-21,1998 l
This form is used only to report simulator observations. These observations do not i constitute audit or inspection findings and are not, without further verification and review, )
indicative of noncompliance with 10 CFR 55.45(b). These observations do not affect NRC certification or approval of the simulation facility other than to provide information that May be used in future evaluations. No licensee action is required in response to these observation No simulator deficiencies, that affected the scenario examinations or JPMs, we e identified i during the execution of the examinatio .
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