IR 05000352/1999302
| ML20210P439 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/04/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20210P423 | List: |
| References | |
| 50-352-99-302, 50-353-99-302, NUDOCS 9908130004 | |
| Download: ML20210P439 (46) | |
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l-l l U. S. NUCLEAR REGULATORY COMMISSION REGION 1 i
Docket Nos: 50-352, 50-353 Report Nos: 50-352/99-302,50-353/99-302 Licensee: PECO Nuclear Facility: Limerick Units 1 and 2, Sanatoga, P Dates: July 2 to 14,1999 (Administration)
July 15 to 22,1999 (Grading) ,
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- Examiners: Steve Dennis, Operations Engineer, Chief Examiner Carl Sisco, Operations Engineer Approved By: Richard J. Conte, Chief Human Performance and Emergency Preparedness Branch Division of Reactor Safety l l l
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9908130004 990004
[ PDR ADOCK 050003 2 l
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- , I EXECUTIVE SUMMARY Limerick Generating Stations Examination Report No. 50-352,353/99-302
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Ooerations e Six Limited Senior Reactor Operator (LSRO) applicants were administered initial licensing exams. All applicants successfully passed all portions of the exa * A performance deficiency was identified during the performance of a JPM when an applicant, while operating the refueling bridge under the direction of a fuel handling director (FHD), allowed the mast to make contact with the sot.:th fuel prep machine handrail. The mast was in the normal up position with no fuel grappled. Although the contact was minor and no damage resulted, the event indicated a lack of oversight on the part of the FHD and inattentiveness on the part of the applican The licensee immediately addressed the issue and subsequently issued PEP #l000997 Corrective actions were incomplete at the titt i of this repor * An exam security problem was identified by PECO involving exam material previously copied by a PECO_ exam team member and later discovered in the same copy machine by another PECO exam team membe l The examiner determined based on the timeline developed by PECO, through interviews with those involved, and re-enactment of the event, that the event was minor and the exam was not compromised. Additionally, investigation of the event and subsequent corrective actions taken by the licensee were found to be acceptable. PECO PEP
- 10009971 describes the problem and corrective actions, o The submitted written exam required revision on five of 65 questions due to either the
- question lacking stem focus or being unrelated to the required subject area. No revision was required on the operating exams. Facility personnel subsequently incorporated
- changes in the final exam * The facility used an examination preparation team of experienced instructors who assisted the NRC examiners in an excellent manner, i
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Report Details Operations 05 Operator Training and Qualifications 05.1 Limited Senior Reactor Ooerator initial Exams Scope The NRC examiners reviewed the written and operating initial examinations submitted by i the~ facility staff to ensure that they were prepared and developed in accordance with the guidelines of the " Examination Standards for Power Reactors" (NUREG-1021, Interim Revision 8). The review was conducted both in the Region 1 office and at the Limerick
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training facility. The NRC examiners administered the operating portion of the exam to all candidates. The written exams were administered by the facility's training i organizatio Observations and Findinas Gradina and Results The results of the exams are summarized below:
Peach Bottom Limerick Pass Fail Pass Fail Written 6 0 6 0 Operating . 6 0 6 0 Overall 6 0 G 0 Examination Preparation and Quality The written exams, job performance measures (JPMs) and simulator scenarios were ,
developed by the facility using the guidelines of the examination standards. The exam development team was comprised of training and operations representatives. All individuals signed onto a security agreement once the development of the exam ,
commenced. The NRC subsequently reviewed and approved all portions of the '
proposed exam .
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The submitted written exam required revision on five of 65 questions due to either the question lacking stem focus or being unrelated to the required subject area. No changes were required on the operating exams. Facility personnel subsequently incorporated changes in the final exam The facility used an examination preparation team of experienced instructors who assisted the NRC examiners in an excellent manne Written Test Performan_ce The facility training department performed an analysis of questions missed on the written exam for generic weaknesses. The facility noted six examples where half of the applicants missed the same question. The training staff subsequently determined the questions met the guidance of NUREG 1021, Appendix B, and were technically ;
accurate. Facility staff stated they would review these questions with the applicant This action was determined to be acceptabl Operatina Test Administration and Performance i
A performance deficiency was identified during the performance of a JPM when an applicant, while operating the refueling bridge under the direction of a fuel handling director (FHD), allowed the mast to make contact with the south fuel prep machine handrail. The mast was in the normal up position with no fuel grappled. Although the contact was minor and no damage resulted, the event indicated a lack of oversight on the part of the FHD and a lack of attention to the directed task on the part of the applican The licensee immediately addressed the issue and subsequently issued PEP #1000997 Corrective actions were incomplete at the time of this repor All other applicant performance was considered acceptabl c. Conclusions Six LSRO applicants were administered initial licensing exams. All applicants successfully passed all portions of the exa A performance deficiency was identified during the performance of a JPM when an j applicant, while operating the refueling bridge under the direction of a fuel handling '
director (FHD), allowed the mast to make contact with the south fuel prep machine handrail. The mast was in the normal up position with no fuel grappled. Although the contact was minor and no damage resulted, the event indicated a lack of oversight on the part of the FHD and a lack of attention to the directed task on the part of the i applican '
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The submitted written exam required revision on five of 65 questions due to either the question lacking stem focus or being unrelated to the required subject area. No changes were required on the operating exams. Facility personnel subsequently incorporated changes in the final exams, j
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The facility used an examination preparation team of experienced instructors who J
assisted the NRC examiners in an excellent manne i l
08 Miscellaneous Operations issues )
08.1 Exam Security
PECO identified a security problem involving exam material previously copied by an exam team member and later discovered in the copy machine by a PECO exam team member, Both exam team members were already on the security agreement. The J
material unknowingly remained in the copy machine intemal storage tray for '
approximately 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> and was discovered when the machine was reset. The material involved encompassed one JPM and two JPM question '
The examiner determined based on the timeline developed by PECO, through interviews with those involved, and re-enactment of the event, that the event was minor and the )
exam was not compromised. The examiner agreed that the material involved was limited !
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to one JPM and two JPM questions. The material was subsequently replaced by the facility prior to exam administration. Additionally, the investigation of the event and ,
subsequent corrective actions taken by the licensee were found to be acceptable. The problem is described in PEP # 1000997 All other aspects of exam security were found to be acceptable 08.2 Eliaibility Reauirements During a review of the candidates' applications, the examiners determined that: 1) the candidates met eligibility guidelines of NUREG 1021 and Reg. Guide 1.8 as applicable; and 2) the licensing basis documents for eligibility requirements (i.e., the Quality Assurance Plan, Technical Specifications, the Final Safety Analysis Report, and the licensed operator program requirements as accredited) were consisten X1 Exit Meeting Summary On July 19,1999, exam-related observations were discussed with the manager of Operations Training. The NRC expressed appreciation for the cooperation and assistance that was provided during both the preparation and exam week by the licensee's examination tea Attachment 1: LSRO Written Exam w/ Answer Key
I9 Attachment 1 LSRO WRITTEN EXAM W/ ANSWER KEY r
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CONFIDENTIAL I
LGS 1 & 2, PBAPS 2 & 3 1999 LSRO INITIAL LICENSE EXAM ANSWER KEY a 2 b 45. b d 2 c 46. a a 2 a 47. c d 2 a 48. a d' 2 d 49. b b 2 a 50. c c 2 a 51. b a 3 d 52. a a 3 a 53. b 10. b 3 a 54. c 11. c 3 b 55. b 12. d 3 c 56. d 13. b 3 a 57. b 14. b 3 c 58. b 15. b 3 c 59. d !
i 16. c 3 c 60. c l 61. a I 17. a 3 d 18. c 4 c 62. c j 19. c 4 c 63. b l
20. a 4 d 64. a l
21. b 4 a 65. c
22. d 4 c CONFIDENTIAL
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ANSWER KEY PECO NUCLEAR PAGE: 1 EXAM: 99 NRC LSRO 1) *PV:1.0 Q#: 1 RT:0.0 DF:2 LP:1, GF-THEORY .02 CT:99, LSR, W
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WHICH ONE of the following describes how a positive core K-excess is i established at the beginning of a core operating cycle? l l
a. New fuel is loaded b. Once burned fuel is shuffled c. Control rod blades are replaced d. Fission product poisons are loaded CORRECT RESPONSE :A REFERENCE: l NONE l
2) *PV:1.0 Q#: 2 RT:0.0 DF:2 LP:2, GF-THEORY.02 CT:99, LSR, W WHICH ONE of the following describes values for Keff and reactivity that will prevent an inadvertent criticality?
Keff Reactivity (%- 6k/k) >1 >0 s1 >0 <0 <1 <0 CORRECT RESPONSE :D REFERENCE:
NONE
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ANSWER KEY PECO NUCLEAR
'PAGE: 2 EXAM: 99 NRC LSRO
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3) *PV:1.0 Q#: 3 RT:0.0 DF:2 LP:3, GF-THEORY .03 CT:99, LSR, W WHICH ONE of the following explains why refueling the Reactor Core results in a longer Reactor Period for a given amount of positive reactivity added? I l A larger percentage of all core neutrons will be born delayed { A smaller percentage of all core neutrons will be born delayed i A larger percentage of source neutrons will cause fission A smaller percentage of prompt neutrons will cause fission i CORRECT RESPONSE :A REFERENCE:
NONE 4) *PV:1.0 Q#: 4 RT:0.0 DF:2 LP:4, GF-THEORY .05 CT:99, LSR, W During One Rod Out Interlock testing the RO reports that a " Double Notch Withdraw" from position 00 has occurre WHICH ONE of the following is the total distance travelled by the rod? " 1 I " l i " "
CORRECT RESPONSE :D REFERENCE:
j NONE I
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ANSWER KEY PECO NUCLEAR PAGE: 3 EXAM: 99 NRC LSRO 5) *PV:1.0 Q#: S RT:0.0 DF:1 LP:5, GF-THEORY .05 CT:99, LSR, W, PB PBAPS Unit 2 plant conditions are as follows:
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A reactor shutdown to begin a refueling outage is complet Unit operating history was 100% for 260 day WHICH ONE of the following describes the LARGEST source of decay heat !
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after shutdown? alpha decay of U-235 fission by source neutrons spontaneous fission of Pu-239 beta and gamma decay of fission products l
CORRECT RESPONSE :D REFERENCE:
NONE 6) *PV:1.0 Q#: 6 RT:0.0 DF:2 LP:6, GF-THEORY .08 CT:99, LSR, W, LGS LGS Unit 2 plant conditions are as follows:
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OPCON 5
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Fuel Pool gates to Unit 2 Reactor Cavity are removed
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25% of original Core has been off-loaded
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Fuel Pool cooling is in service per S53.7.A, Alignment of Fuel Pool Cooling System for Natural Circulation
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Fuel Pools are not cross-connected WHICH ONE of the following actions will enhance decay heat removal in the Unit 2 Reactor Cavity? Reduce RWCU Regenerative Heat Exchanger bypass flow Start an additional Fual Pool Service Water Booster Pump Lower Cavity level to Radwaste until weir overflow to SST stops Align FPCC system return water to both Cavity and Spent Fuel Pool CORRECT RESPONSE :B REFERENCE:
NONE
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l ANSWER KEY PECO NUCLEAR PAGE: 4 EXAM: 99 NRC LSRO 7), *PV:1.0 Q#: 7 RT:0.0 DF:1 LP:7, NLSROOO10.5B CT:99, LSR, W l
During Core Shuffle Phase I, a fuel bundle has been seated in the core to encoder position +547" WHICH ONE of the following reflects this fuel bundle's performance during full power operation?
Bypass Flow Bundle Power Higher I:igher Lower Lower Higher Lower i Lower Higher CORRECT RESPONSE :C REFERENCE:
NONE 8) *PV:1.0 Q#: 8 RT:0.0 DF:2 LP:8, NLSROO766.09 CT:99, LSR, W WHICH ONE of the following devices will prevent Main Hoist Motor l overheating due to a small overcurrent condition over a long time '
interval?
a. thermal overload b. magnetic overload c. undervoltage relay d. phase differential relay CORRECT RESPONSE :A REFERENCE:
NONE l
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9 ANSWER KEY PECO NUCLEAR PAGE: 5 EXAM: 99 NRC LSRO 9) *PV:1.0 Q#: 9 RT:0.0 DF:1 LP:9, NLSROOO10.2F CT:99, LSR, W WHICH ONE of the following requires removal from above vessel to replace the failed detector?
! a. LPRM "16-09-A" b. Tip Tube c. SRM "1D" d. IRM "2H" CORRECT RESPONSE :A
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REFERENCE: .
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10) *PV:1 0 Q#: 10 RT:0.0 DF:2 LP:10, NLSROOO10.5A
. CT:99, LSR, W j WHICH ONE of the following ruptured areas would prevent establishing two-thirds (2 /3 ) core coverage in the event of a Design Bases Accident LOCA? j a. Jet pump inlet riser b. Jet pump diffuser section I
c. Shutdown Cooling suction line I
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d. Low pressure LPCI injection line CORRECT RESPONSE :B REFERENCE-NONE l
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ANSWER KEY PECO NUCLEAR PAGE: 6 EXAM: 99 NRC LSRO 11) *PV:1.0 Q#: 11 RT:0.0 DF:2 LP:ll, GF-THEORY-0 CT:99, LSR, W, LGS LGS Unit 2 plant conditions are as follows:
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OPCON 5
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Core Shuffle Part 1 is in progress
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175 of 395 moves are complete
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Shutdown Margin is calculated to be 0.68% 6k/k Upon completion of step 395, SDM is re-calculated and determined to be 0.45% 6k/k WHICH ONE of the following conditions explains the change in Shutdown Margin?
a. Core flow has increased b. Moderator temperature has increased c. The number of new fuel assemblies has increased d. The number of fully inserted control rods has increased CORRECT RESPONSE :C REFERENCE:
NONE l
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12) *PV:1.0 Q#: 12 RT:0.0 DF:2 LP:12, NLSROO761.5E CT:99, LSR, W, PB i PBAPS Unit 3 plant conditions are as follows:
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In-vessel maintenance is in progress
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CRB 18-15 is to be removed
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The Aux. Hoist with CRB grapple is positioned on the bail handle
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HCU/CRD coordinator has verified CRB uncoupled
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Hoist pendant ENGAGE pushbutton is actuated
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Hoist pendant "UP" pushbutton is actuated
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Hoist load indication is +0000 l WHICH ONE of the following explains the reason for these indications and the action required to grapple the CRB?
a. bail handle is cruciform, CRB uncoupling tool must be used b. bail handle is cruciform, CRB grapple must be rotated by 90 c. bail handle is single handle, CRB uncoupling tool must be used d. bail handle is single handle, CRB grapple must be rotated by 90
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ANSWER KEY PECO NUCLEAR PAGE: 7 EXAM: 99 NRC LSRO CORRECT RESPONSE :D REFERENCE:
NONE 13) *PV:1.0 Q#: 13 RT:0.0 DF:2 LP:13, NLSRO1840.3C, TS 3. CT:99, LSR, W, LGS Unit 2 plant conditions are as follows:
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Reactor is shutdown at 1200, July 2, to begin a refueling outag WHICH ONE of the following describes when in-core fuel moves can start I and why? ! July 3, ensures shutdown margin specification is met July 3, allows decay of short lived fission products , July 2, prevents assembling a critical array in the l storage racks ] , July 2, ensures SFP heat load is not exceeded before alternate decay heat removal systems become available
CORRECf RESPONSE :B i REFERENCE: !
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l ANSWER KEY PECO NUCLEAR PAGE: 8 EXAM: 99 NRC LSRO l
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14) *PV:1.0 Q#: 14 RT:0.0 DF:3 LP:14, NLSROOO30.08, 043-C-001-C, M-43 CT:99 l l
I LGS Unit 1 plant conditions are as follows: ,
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"1A" RHR pump is in shutdown cooling
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In Vessel Visual Inspection (IVVI) is scheduled this shift WHICH ONE of the following describes a set of core locations where BOTH can be inspected with minimal risk of camera damage?
Jet Pump Recirc Pump Hold-Down Beams Suction Nozzle N1B N1A N1A N1B CORRECT RESPONSE :B REFERENCE:
LGS 'A' RHR returns to Jp 11-20
'A' RHR suction is from Recirc 'B' suction
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{ ANSWER KEY PECO NUCLEAR PAGE: 9 EXAM: 99 NRC LSRO
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15) *PV:1.0 Q#: 15 RT:0.0 DF:2 LP:15, NLSROO370.12 CT:99, LSR, A, PB l
PBAPS Unit 2 plant conditions are as follows:
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MODE 5
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"2A" RHR pump is in Shutdown Cooling
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All other ECCS is lined-up for automatic operation i An inadvertent LOCA initiation signal (-160") is received on all four ECCS channels WHICH ONE of the following describes the response of the indicated RHR pumps?
a. Remain in S/D cooling Align and inject to RPV b. Isolate Align and inject to RPV c. Isolate Remain shutdown d. Remain in S/D cooling Remain shutdown CORRECT RESPONSE :B REFERENCE:
NONE
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ANSWER KEY PECO NUCLEAR PAGE: 10 EXAM: 99 NRC LSRO 16) *PV:1.0 Q#: 16 RT:0.0 DF:2 LP:16, NLSROO370.10, ON121 CT:99, LSR, W, LG LGS Unit 2 plant conditions are as follows:
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"2A" RHR subsystem is in Shutdown Cooling
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A loss of 2AY160 has caused a loss of power to all channels of S/D Cooling isolation logic Given the following Shutdown Cooling valves:
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HV-051-2F008 Outboard Suction
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HV-051-2F009 Inboard Suction
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HV-051-2F00?_5A "A" Loop Return
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HV-051-2F006A "A" Loop Suction WHICH ONE of the following describes the effect of the loss of 2AY160 on the valves final position?
HV-051-2F008 HV-051-2F009 HV-051-2F0015A HV-051-2F006A OPEN OPEN CLOSE OPEN OPEN CLOSE OPEN CLOSE CLOSE CLOSE CLOSE OPEN CLOSE OPEN OPEN CLOSE CORRECT RESPONSE :C REFERENCE:
NONE
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ANSWER KEY PECO NUCLEAR PAGE: 11 EXAM: 99 NRC LSRO 17) *PV:1.0 Q#: 17 RT:0.0 DF:2 LP:17, NLSROOO60.06, M-C-741-301 CT:99, LSR, PBAPS Unit 3 plant conditions are as follows:
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Control Rod Blades are being removed per M-C-741-301, Control Rod Blade, Fuel Support Piece and Control Rod Guide Tube Removal and Installation
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CRBs will be uncoupled and removed using CRB Latch tool WHICH ONE of the following actions will uncouple the control rod blade?
a. Lifting the coupling release handle (D-handle)
b. Rotating the spud lock plug counter-clockwise c. Landing the tool's weight on the CRB d. Lowering the CRD uncoupling rod CORRECT RESPONSE :A REFERENCE:
NONE 18) *PV:1.0 Q#: 18 RT:0.0 DF:2 LP:18, NLSROOO60.05, M-C-741-301 CT:99, LSR, LGS Unit 2 plant conditions are as follows:
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OPCON 5
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CRB 30-31 is being removed from above vessel with j the CRB Grapple WHICH ONE of of the following is an indication that the CRB has been uncoupled?
I a. Aux Hoist weight 400 lbs {
t b. Aux Hoist Interlock light li c. Overtravel alarm and "* *" indication on 4-rod display d. Full Core Display red light lit with CRD stall flow indicate CORRECT RESPONSE :C .
REFERENCE: l NONE l i
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ANSWER KEY PECO NUCLEAR PAGE: 12 EXAM: 99 NRC LSRO
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i 19) *PV:1.0 Q#: 19 RT:0.0 DF:2 LP:19, NLSROOO80.2B, M-C-741-301 CT:99, LSR, j
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PBAPS Unit 3 plant conditions are as follows:
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CRB removal using CRB latch tool is in progress 1
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CRB is coupled j
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CRB to be removed is verified at position 48
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CRB latch tool is engaged on CRB per CCTAS
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Rod position indication is not bypassed WHICH ONE of the following describes rod control system switch positions j required to be held in, by the RO, to complete CRB unlatching and CRD l isolation? i l
Rod Control Switch Notch Override Switch j
! In Emergency In i In Off j Notch out Notch override Notch out Off CORRECT RESPONSE :C REFERENCE:
Only c. provides the required continuous withdraw signal !
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LGS Unit 1 plant conditions are as follows:
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OPCON 5 !
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Shuffle Phase 2 is in progress
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All control rods are fully inserted and control rod 38-23 is selected
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Bridge conditions are given on ATTACHMENT Q20 WHICH ONE of the following Interlock Status Display lights sets will be lit? j a. " Rod Block Interlock #1" and " Rod Block Interlock #2" !
b. " Backup Hoist Limit" and " Fuel Hoist Interlock" ;
c. " Rod Block Interlock #1" and " Reverse Stop #1" ;
d. " Rod Block Interlock #2" and " Reverse Stop #2" !
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ANSWER KEY PECO NUCLEAR PAGE: 13 EXAM: 99 NRC LSRO CORRECT RESPONSE :A REFERENCE:
NONE 21) *PV:1.0 Q#: 21 RT:0.0 DF:3 LP:21, NLSROO110.7B, S44.7.B, S13. CT:99, LGS Unit 1 plant conditions are as follows:
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OPCON 5
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Coolant temperature is 75 F and dropping
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RWCU is in use as an alternate decay heat removal method with DWCW lined up to RECW
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"1A" RWCU Non-Regenerative Heat Exchanger is in service I WHICH ONE of the following will REDUCE the heat removal rate?
a. Start an additional RWCU pump l
b. Reduce DWCW flow through "1A" NRHX I l
c. Open RWCU Regenerative Heat Exchanger Bypass Line d. Place the "1B" RWCU Non-Regenerative Heat Exchanger in service CORRECT RESPONSE :B REFERENCE:
NONE
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ANSWER KEY PECO NUCLEAR PAGE: 14 EXAM: 99 NRC LSRO l
l 22) *PV:1.0 Q#: 22 RT:0.0 DF:2 LP:22, NLSROO240.1B, TS 3.3. CT:99, LSR, '
PBAPS Unit 3 plant conditions are as follows:
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Shuffle Part 2 is complete with the exception of cell 50-35
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Two (2) fuel bundles of cell 50-35 are removed, DBG is installed and the CRB is fully withdrawn for stroke time testing l All RPS Manual Scram channels are inoperable Plant conditions prevent placing any channel or trip system in a trip condition Repair of the RPS Manual Scram function will take three (3) hours to complete WHICH ONE of the following describes the maximum required Completion Time to fully insert rod 50-35? Twelve (12) hours Six (6) hours One (1) hour Immediately I
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CORRECT RESPONSE :D REFERENCE:
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l ANSWEP KEY PECO NUCLEAR PAG'::: 15 EXAM: 99 NRC LSRO enum 23) *PV:1.0 Q#: 23 RT:0.0 DF:2 LP:23, NLSROO200.06 CT:99, LSR, W, LGS l
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LGS Unit 1 plant conditions are as follows:
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OPCON 4
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Refuel Floor Secondary Containment is established
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Unit 2 Refuel Floor HVAC is in service
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Unit 1 Refuel Floor HVAC is secured Unit 1 Reactor Enclosure HVAC receives an isolation signal l l
WHICH ONE of the following describes where Standby Gas Treatment system l will align? Refuel Floor only Unit 1 Rx Enclosure only Unit 1 Rx Enclosure and the Refuel Floor Unit 1 and 2 Rx Enclosure and the Refuel Floor CORRECT RESPONSE :B REFERENCE:
NONE
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- ANSWER KEY PECO NUCLEAR
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PAGE: 16 EKAM: 99 NRC LSRO 24) *PV:1.0 Q#: 24 RT:0.0 DF:2 LP:24, NLSROO240.2E, TS 3.9.2, FIG 3.3.6-1 C LGS Unit 1 plant conditions are as follows:
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OPCON 5
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Fuel moves in progress
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Core shuffle part 2 is 92% complete
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The following SRM data is obtained:
SRM Signal / Noise Count Rate 1A B C BYPASSED BYPASSED 1D Refer to ATTACHMENT Q24 to answer the following question WHICH ONE of the following CCTAS steps meets its SRM operability requirements? ,
l ' CORRECT RESPONSE :C REFERENCE 1
"C" SRM bypassed, B SRM is Inop (below signal / noise graph), D SRM is <3 counts but above S/N graph so it is usabl Move in "A" & "D" quad are allowe % complete indicates > 16 fuel assembJies l
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l ANSWER KEY PECO NUCLEAR
' PAGE: 17 EXAM: 99 NRC LSRO
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25) *PV:1.0 Q#: 25 RT:0.0 DF:2 LP:25, NLSROO350.03, S52.5.B 4.3.22 CT:99, L l
LGS Unit 2 plant conditions are as follows:
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GP 6.1 Reactor Vessel disassembly is in progress WHICH ONE of the following describes the system and preferred suction source for Reactor Well flood-up?
System Preferred Suction Source a. Core Spray CST I
b. RHR CST c. Core Spray SP l
CORRECT RESPONSE :A REFERENCE:
NONE 26) *PV:1.0 Q#: 26 RT:0.0 DF:3 LP:26, NLSROO370.04, S010.1.B-2 CT:99, LSR, PBAPS Unit 2 plant conditions are as follows: I
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Cavity is flooded
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Spent Fuel Pool gates are removed
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"2A" RHR pump is in shutdown cooling 1
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"2D" RHR LPCI Discharge Piping Flush from Cavity to Torus is in progress
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MO-2-10-034B, " Full Flow Test" is throttled to 2000 gpm for the flush
"2A" RHR Pump trips WHICH ONE of the following describes the effect on Reactor level with NR operator intervention?
a. Stabilize at approximately +1" b. Drop to -160" then be recovered by LPCI injection l
c. Stabilize at approximately +470" d. Drop to -129" then be recovered by LPCI injection CORRECT RESPONSE :A
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ANSWER KEY PECO NUCLEAR I PAGE: 18 EXAM: 99 NRC LSRO REFERENCE:
NONE f
27) *PV:1.0 Q#: 27 RT:0.0 DF:2 LP:27, NLSROO370.03, MOD-P00781-1 CT:99, LSR l LGS Unit 1 plant conditions are as follows:
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Core Alterations are in progress
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"1B" Loop of RHR is operating in the Alternate Decay Heat Removal mode
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RHR SDC suction PCIV HV-51-F009 LLRT is in progress
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Fuel Pool Cooling and Cleanup is secured WHICH ONE of the following describes suction and return flowpaths during Alternate Decay Heat Removal made of operation?
Suction Return "A" Recirc Loop Rx Cavity Sparger FPCC Pump Suction Spent Fuel Pool "B" Recirc Loop Jet Pumps 1-10 Skimmer Surge Tank "B" Recirc Loop CORRECT RESPONSE :D l REFERENCE: l NONE >
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P ANSWER KEY PECO NUCLEAR PAGE: 19 EXAM: 99 NRC LSRO l 28) *PV:1.0 Q#: 28 RT:0.0 DF:2 LP:28, NLSROO685.03, F-R-700 CT:99, LSR, W,
LGS Unit 2 plant conditions are as follows:
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New fuel receipt is in progress An electrical fault in a Refuel Floor lighting panel initiates a fire on the refuel floor. This results in a loss of all refuel floor communication WHICH ONE of the following will provide a fire alarm in the MCR?
a. Actuation of Fire Pull Box b. Refuel Floor automatic sprinkler initiation c. Refuel Floor automatic CO2 initiation d. Actuation of Refuel Floor Deluge Valve System J
CORRECT RESPONSE :A 3 REFERENCE:
NONE 29) *PV:1.0 Q#: 29 RT:0.0 DF:2 LP:29, NLSROO710.04, TS 3.3. CT:99, LSR, l
LGS Unit 1 plant conditions are as follows:
-
OPCON 5 l
-
fuel moves in progress '
-
The Plug Laydown Area ARM (North Wall) (RIS33-M1-1K600) was declared INOP last shift
-
I&C reports that the Spent Fuel Pool ARM (RIS31-M1-1K600) alarm l setpoint is 70 mR/h and cannot be adjusted I WHICH ONE of the following describes the status of the Refuel Floor !
Criticality monitors and continued fuel movement?
No. of Operable Channels Fuel movement prohibited permitted prohibited permitted ;
CORRECT RESPONSE :A
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ANSWER KEY PECO NUCLEAR PAGE: 20 EXAM: 99 NRC LSRO REFERENCE:
l NONE 30) *PV:1.0 Q#: 30 RT:0.0 DF:2 LP:30, NLSROO655.02 CT:99, LSR, W, PB l PBAPS Unit 3 plant conditions are as follows:
-
Core shuffle Part 1 is in progress
-
A loss of off-site power occurs i
NHICH ONE of the following describes the effect on electrical power to the Refuel Bridge?
i remains available, bridge operations continue throughout event lost until Non-Safeguard power is restored from off-site lost until MCR manually resets the Div I load center lost for (10) seconds then bridge can be restarted locally
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CORRECT RESPONSE :D REFERENCE: I NONE 31) *PV:1.0 Q#: 31 RT:0,0 DF:2 LP:31, NLSROO685.02, PF-57 CT:99, LSR, W, PB
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PBAPS Unit 2 plant conditions are as follows:
-
New fuel receipt and inspection in progress A class "C" fire has started in a portable air sampler located in the new fuel container storage area, reactor building, 234' elevation i
WHICH ONE of the following describes the appropriate fire fighting agent i to suppress the fir l l
l CO2 Foam Water MET-L-X CORRECT RESPONSE :A
,
REFERENCE:
l NONE
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ANSWER KEY PECO NUCLEAR PAGE: 21 EXAM: 99 NRC LSRO l l
l 32) *PV:1.0 Q#: 32 RT:0.0 DF:2 LP:32, NLSROO750.03B, S53.3.G, M-53, M-62 CT
{
LGS Unit 2 plant conditions are as follows: I
-
OPCON 5
-
Reactor Cavity is flooded
-
Fuel Pool Gates are removed
-
CRD is in service
-
Fuel Pool Cooling and Cleanup pumps have just tripped WHICH ONE of the following describes the reason cavity letdown directly to the Equipment Drain Collection Tank for level control must be secured?
a. prevent direct siphoning of cavity / pool water b. prevent reverse flow through FPCC Filter /Demins c. protect FPCC Filter /Demins from high temperatures l d. protect Equipment Drain Filter from high temperatures CORRECT RESPONSE :A REFERENCE:
NONE 33) *PV:1.0 Q#: 33 RT:0.0 DF:3 LP:33, NLSROO750.3C, S51. CT:99, LSR, W, LGS Unit 1 plant conditions are as follows:
-
OPCON 5
-
Core Offload is complete RHR System backup to Puel Pool Cooling is required due to Spent Fuel Pool heat load
!!hICH ONE of the following actions prevents pumping the Skimmer Surge Tanks to the Suppression Pool from an RHR Loop operating in Fuel Pool Cooling Assist Mode?
a. Close and deenergize HV-51-1F007A, " Minimum Flow Bypass", (Min Flow A)
b. Close and deenergize HV-51-1F007B, " Minimum Flow Bypass", (Min Flow B)
c. Close HV-51-1F008, " Shutdown Cooling suction Isolation",
(Outboard)
d. Close 51-1F067A, "1C RHR Pump Shutdown Cooling suction Valve"
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l PAGE: 22 EXAM: 99 NRC LSRO !
l CORRECT RESPONSE :B REFERENCE:
l l
LGS Unit 1 - Only 'B' RHR Loop (B pump) available for FPC assist.
l 34) *PV:1.0 Q#: 34 RT:0.0 DF:0 LP:34, NLSROO761.05, M-C-741-301, FH-6C CT:9 PBAPS Unit 3 plant conditions are as follows:
-
Control Rod Blade (CRB) replacements for 3R12 are ready to commence using the CRB Grapple and Fuel Support Piece (FSP)
Grappl WHICH ONE of the following describes required fuel handling equipment setup to support CRB replacements?
a. Mono hoist tooled with a doubled swivel adapter to a Grid Guide and FSP Grapple b. Mono hoist tooled with a single swivel adapter to a Top Frame and CRB Grapple ;
c. Frame hoist tooled with a single swivel adapter to the CRB Grapple and Grid Guide d. Frame hoist tooled with a doubled swivel adapter to a Top Frame and FSP Grapple CORRECT RESE2NSE :C REFERENCE:
NONE
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ANSWER KEY
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PECO NUCLEAR
PAGE: 23 EXAM: 99 NRC LSRO l b
35) *PV:1.0 Q#: 35 RT:0.0 DF:2 LP:35, NLSROO762.03B, NLSROO762 PG27 CT:99, PBAPS Unit 2 plant conditions are as follows:
i
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Mode 5
-
The Main Hoist Grapple is engaged on fuel bundle P2 CORE 23-14 SW bail handle
-
" Slack Cable" light is lit
-
Hoist Grapple switch is in " ENGAGE"
-
Hoist Grapple switch " green" light is OUT (bulb is good)
WHICH ONE of the following describes the hoist response if hoist control is held in " RAISE" position?
a. raise until hoist loads to a550# then stop b. raise to " Normal Up" hoist position c. raise to encoder position +376" then stop d. no hoist movement CORRECT RESPONSE :A l REFERENCE: '
NONE 36) *PV:1.0 Q#: 36 RT:0.0 DF:3 LP:36, NLSROO766.13, S018.1.A-2 CT:99, LSR, PBAPS Unit 3 plant conditions are as follows:
-
3R12 Shuffle Phase 2 is in progress
-
MCR reports that Rod Select Power is turned OFF for performance of ST-0-018-130-3, "One Rod Out Interlock Function Test"
-
The Bridge will NOT move North in variable or jog speeds Bridge indications are provided on ATTACHMENT Q36 WHICH ONE of the following Interlock Status Display lights are lit?
a. Backup Hoist Limit b. Reverse Stop #1 c. Reverse Stop #2 d. Safety Travel Interlock CORRECT RESPONSE :C REFERENCE:
NONE
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ANSWER KEY PECO NUCLEAR l
PAGE: 24 EXAM: 99 NRC LSRO
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l 37) *PV:1.0 Q#: 37 RT:0.0 DF:2 LP:37, NLSROO761.05B, M-C-797-003 CT:99, LSR ,
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PEAPS Unit 3 plant conditions are as follows: l
)
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Vacuum operations are in progress in-vessel
-
"3A" RHR subsystem is in Shutdown Cooling WHICH ONE of the following describes the consequences of placing an underwater vacuum cleaner directly (no stand) on the Drywell Seal Plate? creates a vessel drain path interference with fuel movement potential Drywell radiological hazard possible entrainment in Jet Pump suction CORRECT RESPONSE :C REFERENCE:
i NONE
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38) *PV:1.0 Q#: 38 RT:0.0 DF:3 LP:38, NLSROO420.07, A035.1-2, SE-11 CT:99, PBAPS Unit 2 plant conditions are as follows:
-
MODE 4
-
"2A" and "2B" FPCC Heat Exchangers are in service
-
"2B" and "2C" FPCC Pumps are in service
-
SFP temperature is 86 F All offsite power is lost WHICH ONE of the following combinations describes the number of FPCC pumps with power available and the expected change in long term SFP temperature?
NO. of FPCC numns SFP Temperature with nower available None 89 All 82o One 89*
! Two 820 l
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ANSWER KEY PECO NUCLEAR PAGE: 25 EXAM: 99 NRC LSRO REFERENCE:
2C is E-powered 39) *PV:1.0 Q#: 39 RT:0.0 DF:2 LP:39, NLSROOO11.1D, S97. CT:99, LSR, W, l
l Refer to ATTACHMENT Q39 to answer the following question WHICH ONE of the following represents the target core cell coordinates for the Main Hoist mast to complete step #1? l CORRECT RESPONSE :D REFERENCE:
Mast must be at target cell CRB location to insert a DBG.
40) *PV:1.0 Q#: 40 RT:0.0 DF:3 LP:40, NLSRO1530.2A, GP-6 CT:99, LSR, W, PB PBAPS Unit 3 plant conditions are as follows:
-
MODE 5
-
Reactor cavity floodup is complete
-
Fuel Pool gates are removed
-
Cavity level indication is being monitored on PR/FR3-06-097 via LT-70 Refer to ATTACHMENT Q40 to answer the following question WHICH ONE of the following set of conditions will cause water to overflow into the Fuel Pool exhaust ductwork?
Reactor Wtr Temo (*F) Indicated Level (Inches) r
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l l ANSWER KEY PECO NUCLEAR I PAGE: 26 EXAM: 99 NRC LSRO l
l CORRECT RESPONSE :C l REFERENCE:
GP-6 caution - RF level is not density compensated 475" indicated at 146 F = 482.6" actual - 7.6" increase
,41) *PV:1.0 Q#: 41 RT:0.0 DF:2 LP:41, NLSROO761.03A CT:99, LSR, W, PB PBAPS Unit 2 plant conditions are as follow I
-
A fuel bundle is being raised from the reactor vessel l
-
Bridge indications are provided on ATTACHMENT Q41 l WHICH ONE of the following actions is required? lower bundle until, " MAIN HOIST LOADED" light goes out lower bundle until, " SLACK CABLE" light goes on lower bundle until, " MAIN HOIST JAM" light goes out lower bundle until, " GRAPPLE FULL DOWN" light goes out CORRECT RESPONSE :C REFERENCE:
S018.1.A-1 42) *PV:1.0 Q#: 42 RT:0.0 DF:3 LP:42, NLSROO766.3B, S97.0.M, S97. CT:99, LGS Unit 1 plant conditions are as follows:
-
OPCON 5
-
Core Alterations in progress per FH-105 Refer to ATTACHMENT Q42 to answer the following question WHICH ONE of the following CCTAS steps requires an operable " Hoist override" pushbutton?
' l CORRECT RESPONSE :D
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ANSWER KEY PECO NUCLEAR PAGE: 27 EXAM: 99 NRC LSRO
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.
REFERENCE:
See Attachment Q42 - DBG through cattle chut Requires " Hoist Override" to -4.0" to prevent impact 43) *PV:1.0 Q#: 43 RT:0.0 DF:3 LP:43, NLSROO766.13, S97. CT:99, LSR, W, LGS Unit 2 plant conditions are as follows: !
-
Core Shuffle Part I is in progress
)
-
All control rods are fully inserted
-
Reactor Mode Switch is in REFUEL
-
Bridge indications are provided on ATTACHMENT Q43 l
Bridge Main Disconnect switch, 20-S380, is opened due to smoke coming from the hoist MG-set l
WHICH ONE of the following describes the status of the MCR " Rod Out Block" annunciator before and after 20-S380 is open?
20-S380 closed 20-S380 open OUT ON l OUT OUT l ON OUT l ON ON CORRECT RESPONSE :A REFERENCE: l No Hoist is fuel loaded S97.0.M Precaution, 3.15, De-energized Bridge w/ track switches actuated caused rod withdraw block.
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ANSWER KEY PECO NUCLEAR
! PAGE: 28 EXAM: 99 NRC LSRO ammmmmmmmmmmmumuur 44) *PV:1.0 Q#: 44 RT:0.0 DF:2 LP:44, NLSROO767.02, S97. CT:99, LSR, W LGS Unit 1 plant conditions are as follows:
-
Core shuffle part 2 is in progress
-
A bundle is being lowered into position L1 Core 59-24 SW The following indications are observed:
-
Hoist position +555"
-
" Slack Cable Light" lit
-
" Hoist Loaded" light out WHICH ONE of the following describes the current status of the bundle?
a. normally seated in fuel support piece b. suspended above the fuel support piece c. 1cwered past the fuel support piece d. hung-up on top guide CORRECT RESPONSE :C EEFERENCE:
NONE 45) *PV:1.0 Q#: 45 RT:0.0 DF:2 LP:45, NLSRO1550.01, ON-124 CT:99, LSR, W, P Refer to ATTACHMENT Q45 to answer the following question
-
CCTAS Step 93 is in progress
-
Bundle is grappled at hoist position 550"
-
RO reports WRNM readings from ATTACHMENT Q45 )
WHICH ONE of the following describes the required actions? {
a. Stop all fuel moves and evacuate fuel floor b. Raise bundle to clear top grid, determine WRNM count rate trend ;
c. Contact RE's for a change to CCTAS and continue fuel moves I d. Verify count rate stabilizes below 200 cps prior to continuing CORRECT RESPONSE :B !
REFERENCE: l 96 LSRO Exam Generic weakness j
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ANSWER KEY PECO NUCLEAR i PAGE: 29 EXAM: 99 NRC LSRO 46) *PV:1.0 Q#: 46 RT:0.0 DF:2 LP:46, NLSROO763.07, S53. CT:99, LSR, W, LGS Unit 2 plant conditions are as follows:
-
OPCON 5
-
"2A" & "2C" CS & RHR systems are out of service (blocked)
-
Hotwell and Cooling Tower are drained to support maintenance activities
-
Fuel pool level is decreasing rapidly
-
Makeup has been initiated from the following systems:
-
-
CRD WHICH ONE of the following systems can be used for additional makeup to the Fuel Pool?
d. Service Water CORRECT RESPONSE :A REFERENCE:
NONE 47) *PV:1.0 Q#: 47 RT:0.0 DF:1 LP:47, NLSRO1570.3B, FH-GE-77 CT:99, LSR, W, PBAPS Unit 2 plant conditions are as follows:
-
The DA assisting the fuel sipping crew with equipment installation reports procedure FH-GE-7, " General Electric Fuel Bundle Vacuum Sipping" must be revised due to field conditions j WHICH ONE of the following individuals must review the procedure ;
revision for impact on station operation? l a. Ops Training Manager l b. Fuel Floor Coordinator c. Reactor Engineering Manager d. Engineering Response Manager CORRECT RESPONSE :C
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ANSWE;! KEY PECO NUCLEAR l PAGE: 30 EXAM: 99 NRC LSRO REFERENCE:
NONE 48) *PV:1.0 Q#: 48 RT:0.0 DF:3 LP:48, NLSROO190.02, TS 3.6.5.3, FH-106, TBL1 LGS Unit 2 plant conditions are as follows: ,
-
Reactor was shutdown to begin 2R05 February 24, 1999
-
Last discharge of irradiated fuel to Unit 2 Spent Fuel Pool March 20, 1999
-
Today's date is April 1, 1999 WHICH ONE of the following set of conditions is required to start dummy bundle moves in the Unit 2 Spent Fuel Pool today? )
l Zone III SGD-76-206-3 Both SBGT Trains Operable l
l Open Yes Open No Closed Yes Closed No CORRECT RESPONSE :A REFERENCE
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c54 days since S/D prior to discharge of fuel to 2 SFP 7 day TS LCO in Opcon 1
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I ANSWER KEY PECO NUCLEAR PAGE: 31 EXAM: 99 NRC LSRO 49) *PV:1.0 Q#: 49 RT:0.0 DF:3 LP:49, NLSRO1550.01, ON-124 CT:99, LSR, W, P PBAPS Unit 3 plant conditions are as follows:
-
A fuel bundle removed from the core is entering the cattle chute
-
The RO reports that cavity level is decreasing at 3" per minute
-
HP reports rad levels are increasing slowly A loss of field to the trolley motor occurs with the Bridge currently at the position given on ATTACHMENT Q49 WHICH ONE of the following describes Hoist Operating Mode and an appropriate location to place the fuel assembly?
Hoist Operation Bundle Location Manual Core Manual SFP Motorized Cask Pit Motorized Core CORRECT RESPONSE :B REFERENCE: l NONE l l
50) *PV:1.0 Q#: 50 RT:0.0 DF:2 LP:50, NLSROO762.8, FH-6C, M-C-741-301 CT:99 PBAPS Unit 3 plant conditions are as follows:
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CRB moves are in progress per FH-6C and M-C-741-301 WHICH ONE of the following describes the minimum water coverage to be maintained over the CRB and how this limit is enforced?
a. 4', Main Hoist Jam b. 4', Fuel Hoist Interlock c. 6' 6", Jamming Buttons d. 6' 6", Boundary Zone Computer CORRECT RESPONSE :C REFERENCE:
NONE
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ANSWER KEY PECO NUCLEAR l PAGE: 32 EXAM: 99 NRC LSRO 51) *PV:1.0 Q#: 51 RT:0.0 DF:2 LP:51, NLSROO767.05, FH-105 STP CT:99, L LGS Unit 2 plant conditions are as follows:
-
An irradiated fuel bundle is in the Fuel Prep Machine
-
The Fuel Prep Machine is full up
WHICH ONE of the following actions are required if work must be l suspended for nine (9) hours? l l lower FPM, place lock on operating mechanism lower FPM, return bundle to fuel storage rack note bundle location on FHD Log and turnover sheet notify RO bundle will be up in the FPM for nine hours CORRECT RESPONSE :B REFERENCE:
NONE 52) *PV:1.0 Q#: 52 RT:0.0 DF:3 LP:52, NLSROO766.2F, S97. CT:99, LSR, W, LGS Unit 1 plant conditions are as follows:
-
The Main Holst is being used to move fuel into the North Fuel Preparation machine for re-channeling
-
Hoist position agrees with that for fuel fully seated in FPM
-
" Grapple Release" and " Grapple Lockout Bypass" are depressed
-
Spotter reports grapple is closed WHICH ONE of the following is the reason the main grapple will not attempt to release? " Slack Cable" light not lit " Main Hoist Loaded" light not lit " Grapple Full Down" light not lit " Backup Hoist Limit" light not lit CORRECT RESPONSE :A REFERENCE:
Must have slack cable <50# or normal up w/<485# to ope .
ANSWER KEY PECO NUCLEAR PAGE: 33 EXAM: 99 NRC LSRO 53) *PV:1.0 Q#: 53 RT:0.0 DF:2 LP:53, NLSROO370.07, FH-6C CT:99, LSR, W, PB PBAPS Unit 2 plant conditions are as follows:
)
-
Mode 5 for 2R13
-
Moderator temperature is 78*F
-
"2B" RHR subsystem is in Shutdown Cooling at 12,000 gpm
-
Core Shuffle Part 1 is about to begin l Refer to ATTACHMENT Q53 to answer the following question l WHICH ONE of the following actions is required prior to performing CCTAS, step 1? Reduce "2B" RHR flow to 6000 gpm Swap RHR SDC to "2D" Loop at 6500 gpm Swap RHR SDC to "2C" Loop at 6000 gpm Start "2A" Recirc Pump and shutdown "2B" RHR pump CORRECT RESPONSE _B
REFERENCE: i i
PB prefered Loops A or D, cannot throttle B, C Loops l
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ANSWER KEY PECO NUCLEAR PAGE: 34 EXAM: 99 NRC LSRO 54) *PV:1.0 Q#: 54 RT:0.0 DF:2 LP:54, NLSROO200.05, GP-9 CT:99, LSR, W LGS Unit 1 plant conditions are as follows:
-
Unit is shutdown for refueling
-
OPCON 3
-
Zones 1 and 3 are tied in an extended boundary with HS-76-151A(B) and HS-76-152A(B) in " Interlock"
-
Reactor Cavity Shield plug removal is in progress RPV water level drops to -42 inches for 100 seconds and is then restored to +17 inche WHICH ONE of the following identifies the status of Unit 1 Reactor j Enclosure and Refuel Area HVAC? !
i RE HVAC RF HVAC Isolated Operating Operating Isolated .
I Isolated Isolated Operating Operating )
CORRECT RESPONSE :C REFERENCE:
-38" with zones tied causes isol of both zone .
ANSWER KEY PECO NUCLEAR PAGE: 35 EXAM: 99 NRC LSRO 55) *PV:1.0 Q#: 55 RT:0.0 DF:2 LP:55, NLSROO767.07, FH-105, ERP-101 CT:99, LGS Unit 2 plant conditions are as follows:
-
FH-105, Core Components to final core configuration is in progress
-
A fuel bundle is dropped in the cattle chute during movement ,
from vessel to Spent Fuel Pool l MCR refueling floor area ventilat'.on exhaust monitor alarm has
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annunciated
-
Refuel floor area ventilation exhaust monitors have increased to 0.88 mR/hr Refer to ATTACHMENT Q55 to answer the following question WHICH ONE of the following describes the minimum required Emergency Classification for this event?
a. Unusual Event b. Alert c. Site Area Emergency d. General Emergency CORRECT RESPONSE :B REFERENCE:
NONE l
56) *PV:1.0 Q#: 56 RT:0.0 DF:2 LP:56, NLSROO763.02, FH-6C, ATTACHMENT Q56 C '
PBAPS Unit 2 plant conditions are as follows:
-
Core offload is in progress Refer to ATTACHMENT Q56 to answer the following question WHICH ONE of the following identifies the required entries to complete Table 1, (Box I and II), at the end of X-shift on 07-01-99?
Box I Box II .
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ANSWER KEY PECO NUCLEAR PAGE: 36 EXAM: 99 NRC LSRO CORRECT RESPONSE :D l REFERENCE:
Box I: Total # of Bundles moved to pool in the LAST 24 hrs this shift: 12 last 16 hrs: 47 + 53 = 100 12 + 100 = 112 Box II: # Bundles allowed to be moved to pool in NEXT 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> previous 16 hrs: 12 + 53 = 65 FH-6C Limit = 150 (can be determined from Z shift 6-30) 107 + 43 = 150 150 - 65 = 85 57) *PV:1.0 Q#: 57 1.T:0.0 DF:2 LP:57, NLSROO190.3D, S15.3.C, ARC-BOP-10C222 LGS Unit 1 plant conditions are as follows:
-
OPCON 5
-
" Seal No.3 Reactor Well (Top Seal) " annunciator lit on 10C222 panel WHICH ONE of the following conditions will cause this alarm?
a. Seal drain flow greater than 1 gpm b. Low pressure in seal and 3-way valve NOT in full vent position c. Backup nitrogen bottle pressure to seal less than 500 psig d. Instrument Air supply pressure regulator to seal isolated CORRECT RESPONSE :B REFERENCE:
NONE
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i ANSWER KEY PECO NUCLEAR -
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l 58) *PV:1.0 O#: 58 RT:0.0 DF:1 LP:58, NLSRO1570.1E, A-C-130, OM-C-6.1:12 CT l
PBAPS Unit 2 plant conditions are as follows:
l
-
Jet pump disassembly is in progress
-
Work is scheduled to take 3 shifts WHICH ONE of the following describes the Foreign Material Exclusion (FME) controls required to be documented each shift by the oncoming FHD?
'
a. A review of the FME Drop Log b. A visual check of the reactor cavity / vessel c. A review of the FME area Material Control Log d. A visual check of the tops of fuel in the spent fuel pool CORRECT RESPONSE :B REFERENCE:
FHD checklist Part B, step 6 59) *PV:1.0 Q#: 59 RT:0.0 DF:2 LP:59, NLSRO1705.01, HP-300 CT:99, LSR, W WHICH ONE of the following combinations requires restricting personnel access in the Limerick, Unit 1, Drywell while transporting the component through the cattle chute?
l Comoonent prywell elevation and above l Irradiated fuel 277'
l Jet Pump Rams Head 286' Irradiated LPRM 296' Irradiated CRB 313'
CORRECT RESPONSE :D REFERENCE:
NONE l
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ANSWER KEY PECO NUCLEAR PAGE: 38 EXAM: 99 NRC LSRO 60) *PV:1.0 Q#: 60 RT:0.0 DF:0 LP:60, NLSRO1705.05 CT:99, LSR, W WHICH ONE of the following types of body cells has the highest radiosensitivity to an airborne alpha radiation source?
a. muscle b. nerve c. lung l d. bone CORRECT RESPONSE :C REFERENCE:
NONE
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61) *PV:1.0 Q#: 61 RT:0.0 DF:3 LP:61, NLSRO1760.08, M-C-774-010 CT:99, LSR, PBAPS Unit 2 plant conditions are as follows:
-
LPRM removal is in progress
-
LPRM 40-49 is clamped on the bending tool
-
elevator of bending tool is NOT full down, scribe marks on inner tube are NOT visible above the elevator WHICH ONE of the following adverse situations will occur as this LPRM is bent?
a. failure to bend the instrument in the middle with resulting adverse radiological conditions b. hot end of instrument will contact the vessel flange with l resulting adverse radiological conditions c. instrument handling tool will fail to disengage with resulting frame hoist damage d. air driven bending tool stalls with resulting instrument air i relief valve lifting on Fuel Floor CORRECT RESPONSE :A REFERENCE:
M-C-774-010 Procedure Caution
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ANSWER KEY PECO NUCLEAR PAGE: 39 EXAM: 99 NRC LSRO 62) *PV:1.0 Q#: 62 RT:0.0 DF:2 LP:62, NLSRO1760.04, HP-C-106 CT:99, LSR, W WHICH ONE of the following describes the annual Administrative Limit for a 38 year old radiation worker who provides a current year exposure statement and an NRC Form 4 Lifetime Exposure History showing 2 Rem TEDE? R/yr R/yr R/yr 1 R/yr CORRECT RESPONSE :C REFERENCE: l NONE 63) *PV:1.0 Q#: 63 RT:0.0 DF:2 LP:63, NLSOR1760.04, HP-C-106 CT:99, LSR, W, l
LGS Unit 2 plant conditions are as follows:
-
Reactor Cavity /SFP level is dropping slowly
-
Rad levels on the Refuel Bridge are 3.4 R/hr
-
'2C' Main Stram Line plug must be repositioned using the monorail hoist
-
The RPO's cuttrent year exposure is 1.5 REM
-
The work will take 30 minutes to complete WHICH ONE of the following signatures is needed to approve an Administrative Dose Extension Request to permit this RPO to stop the leak? HP Supervisor Plant Manager Immediate Supervisor HP Manager CORRECT RESPONSE :B REFERENCE:
30 min = 1.7R + 1.5R = 3.2R, >3R = Plant Manager
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ANSWER KEY PECO NUCLEAR PAGE: 40 EXAM: 99 NRC LSRO 64) *PV:1.0 Q#: 64 RT:0.0 DF:1 LP:64, NLSRO1760.06, HP-C-215 CT:99, LSR, W WHICH ONE of the following describes the radiological posting and maximum stay time for an individual, with no prior exposure, working in a 50 mR/hr field from exceeding Dose Control exposure levels?
Posting Stav Time Radiation Area 40 hrs High Radiation Area 40 hrs Radiation Area 80 hrs High Radiation Area 80 hrs CORRECT RESPONSE :A REFERENCE:
Limit is 2000 mR / 50 mR/hr = 40 hrs Rad area 5-100 mR/hr i
65) *PV:1.0 Q#: 65 RT:0.0 DF:2 LP:65, GET, HP-CG-400-4 CT:99, LSR, W
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l During performance of a whole body frisk with an RM-14, the HP-210 probe's mylar window is found to be broken WHICH ONE of the following actions is required to complete the frisk after replacing the probe? : Set detector range to x10 scale Raise alarm setpoint to top of scale Source check the RM-14 replacement detector Place response control switch to " FAST" position CORRECT RESPONSE :C REFERENCE:
NONE