IR 05000361/1999301: Difference between revisions

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{{Adams
{{Adams
| number = ML20199E879
| number = ML20206H777
| issue date = 01/13/1999
| issue date = 05/06/1999
| title = Informs That During 990112 Telcon Between Mk Rauch & J Pellet,Arrangements Were Made for Administration of Written Retake License Exams 50-361/99-301 & 50-362/99-301 at San Onofre,During Wk of 990308
| title = NRC Operator Licensing Exam Repts 50-361/99-301 & 50-362/99-301 Administered on 990416.Exam Results:Two RO & Two SRO Applicants Passed Exam
| author name = Pellet J
| author name =  
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
| addressee name = Ray H
| addressee name =  
| addressee affiliation = SOUTHERN CALIFORNIA EDISON CO.
| addressee affiliation =  
| docket = 05000361, 05000362
| docket = 05000361, 05000362
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = 50-361-99-301, 50-362-99-301, NUDOCS 9901210109
| document report number = 50-361-99-301, 50-362-99-301, NUDOCS 9905120012
| document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE
| package number = ML20206H769
| page count = 4
| document type = EXAMINATION REPORT, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 134
}}
}}


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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION


==REGION IV==
o Docket Nos.: 50-361;362
. License Nos.: NPF-10; NPF-15 Report No.: 50-361; 362/99-301 Licensee: Southern California Edison C Facility: San Onofre Nuclear Generating Station Location: P.O. Box 128 San Clemente, California 92674-0128 Dates: April 16,1999
- Inspector: John L. Pellet, Chief, Operations Branch Approved By: Arthur T. Howell 111, Director Division of Reactor Safety ATTACHMENTS:
Attachment 1: Supplemental Information Attachment 2: Final Written Examination and Answer Key
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9905120012 990506 PDR ADOCK 05000361  l V  PDR ,
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EXECUTIVE SUMMARY San Onofre Nuclear Generating Station NRC Inspection Report 50-361; 362/99-301 -
NRC examiners evaluated the competency of four operator license applicants for issuance of operating licenses at the San Onofre Nuclear Generating Station. The licensee developed the retake written examination using NUREG-1021, Interim Revision 8, January 1997. NRC examiners reviewed, and approved the examination. The written examination was administered on April 16,1999, by facility proctors in accordance with the guidance in NUREG-1021, Interim Revision Operations
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The two reactor operator and two senior operator license applicants passed the examination (Section 04.1).
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The test material was adequate for administration as submitted, with no post-examination changes identified (Section 05.1).
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    . Report Details  ,
Summarv of Plant Status
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The plant operated at essentially 100 percen't power for the ' duration of this inspectio l. Operations  '
04- (Operator Knowledge and Performance 0 Initial Written' Examination    i Insoection Scope    l On April 16,1999, the' facility licensee proctored the administration of the written -
examination approved by the NRC to the two individuals who had reapplied for a reactor -
operator (RO) and two who had applied for senior operator (SRO) licenses.' The
  : licensee proposed grades for the written examinations and evaluated the results for question validity and generic weaknesses. The examiner reviewed the licensee's result Observations and Findinas The minimum passing score was 80 percent.- The candidates' scores for the written examination ranged from 88 to 94 percent. The average score was 90. The licensee's post-administration analysis identified that the administered examination was acceptable. There were no post-examination comments or changes to the written
  - examination recommended by the licensee or identified by examiner review of the results. Licensee review of the examination results indicated several questions ;
identified potential validity or training deficiencies for further internal review. The l specific questions identified were common RO/SRO questions 1,37,39,52, and 69; RO questions 82,95,~ 96, and 99; and SRO only questions 83,85,86,87,92,96,98, and 99 ,
  (shown in Attachment 2 as questions 108,110,111,112,118,123, and 124). The  l licensee found all questions appropriate and valid. The examiner reviewed this analysis j and the specific questions and determined that the issues were narrowly focused within j various systems, such as auxiliary feedwater, procedure immediate actions from memory, annunciators, and technical specifications, and did not represent generic weaknesse j ' Conclusions
  ' The four applicants passed the written' examination. No broad knowledge or training weaknesses were identified as a result of evaluation of the graded examinatio .
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        .s l-4-05 Operator Training and Qualification 0 Initial Licensina Examination Development The facility licensee developed the initial licensing examination in accordance with guidance provided in NUREG-1021," Operating Licensing Examination Standards,"
Interim Revision 8, dated January 199 .1.1 Examination Outline Insoection Scope The facility licensee submitted the initial examination outlines on January 14,1999. The chief examiner reviewed the subraittal against the requirements of NUREG-1021, Interim Revision . Observations and Findinas The chief examiner determined that the initial examination outlines satisfied NRC requirement Conclusions The licensee submitted an adequate examination outlin . Examination Packaae Insoection Scope The draft examination was transmitted by the licensee to the NRC on March 29,199 The licensee submitted the completed final examination package on April 5,1999. The chief examiner reviewed the examination against the requirements of NUREG-1021, Interim Revision Observations and Findinas The draft written examinations each contained 100 questions. The draft examinations were technically valid, discriminated at the proper 'evel, and responsive to the outline ,
submitted by the licensee. The written examination was considered adequate for administration, as submitted. The examiner developed clarificat, ion or enhancement comments on about one fourth of the questions. The licensee staff incorporated these comments and all proposed enhancements were accepted by the examiner. In contrast to the prior examination (see NRC Inspection Report 50-361; -362/98-302), the submitted examination demonstrated improved question stem focus and distractor credibility. The quality of the submitted examination was reflected in the lack of post-administration changes, especially as compared to the prior examination, for which the license requested changes to a significant number of the questions.
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l-5-c. Conclusions
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The test material was adequate for administration as submitted by the licensee. No j changes to examination materials were required as a result of administration, q V. Manaaement Meetinas X1 Exit Meeting Summary I
The chief examiner telephonically presented the inspection results to the licensee staff 4 at the condusion of the inspection on May 3,1999. The licensee acknowledged the findings presente The licensee did not identify as proprietary any information or materials examined during this inspectio l
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ATTACHMENT 1  {
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SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee K. Rauch, Operations Training Supervisor NRC None INSPECTION PROCEDURES USED  j NUREG-1021, NUREG-1021, " Operating Licensing Examination Standards," Interim Revision 8, January 1997 l
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ATTACHMENT 2 FINAL WRITTEN EXAMINATION AND ANSWER KEY
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i ATTACHMENT 2  '
I FINAL WRITTEN EXAMINATION AND ANSWER KEY )
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#' "'44 9  UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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$ f  REGloN IV 611 RYAN PLAZA drive, SUITE 400
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y g  ARLINGTON, texas 76011-8064 January 13,1999 l Harold B. Ray, Executive Vice President Southern California Edison Co.
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San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, California 92674-0128 SUBJECT: NRC INSPECTION REPORT 50-361/99-301; 50-362/99-301
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==Dear Mr. Ray:==
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In a telephone conversation on January 12,1999, between Messrs. K. Rauch and J. Pellet,  j arrangements were made for the administration of written retake licensing examinations at San
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, Onofre, during the week of March 8,1999.


As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in Revision 8, of NUREG-1021," Operator Licensing Examination Standards for Power Reactors." The NRC regional office will discuss with your staff any changes that might be necessary before the examinations are administered.
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COMPOSITE
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NRC EXAM KEY .
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Question #1 Given the following plant conditions:
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Unit 2 is operating at 100% power
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All CEAS are fully withdrawn to the Upper Electrical Limit
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RSPT#1 for CEA 46 to CEAC #1 reads 140" Which CPC/CEAC annunciator display light should be illuminated? CEAC FAIL CEA DE .
1 CEAC INO CEAC SENS FAIL Answer B Exam Level B Cognitive Level . Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 001 ak2.05 Rod motion lights  RO Group: 2 SRO Group: 1 RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Core Protection /CEAC SO23-3-2,13  Att.10 107 10 Refererte Title Operation Material Required for Examination Question Source: New
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. Question #2 The following plant conditions exist:
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The plant has tripped
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All systems actuated as expected with the exception of the following:
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CEAs 40 and 41 are stuck fully withdrawn
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The operating charging pump has tripped on a loss of suction pressure
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Operators are unable to start any charging pumps Which of the following operator actions is procedurally required under these conditions? Lower RCS pressure and borate via HPS Borate via gravity feed suction pat , .- Initiate RCS cooldown and initiate SLA Stabilize RCS temperature and pressure until boration is initiate '
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 001 k4.05 Boration and Dilution RO Group: 1  SRO Group: 1 RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Emergency Boration SO2313-11  5 4 6552 Material Required for Examination Question Source: New r
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Question #3 Which one of the following is the reason for not starting the fourth Reactor Coolant Pump until RCS temperature is greater than 500 degrees Fahrenheit? To prevent exceeding RCS heatup rate limit To prevent excessive RCP starting current To prevent Steam Generator tube stresse To prevent core uplif Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 002 K8.02 RCP  RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Plant S/U from CSD to HSB SO23-5- Att.16 118 19 664g Material Required for Examination Question Source: New l
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Question #4 The following conditions exist:
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Unit 2 at 85% powe Recovery of a dropped CEA (#20) is in progres Group 6 is at 149 inches withdraw CEA #20 (a Group 6 CEA) is at 100 inches withdraw CEA #1 (a Group 2 CEA) drops fully into the cor Which of the following is/are the correct required action (s)? Continue realigning CEA # 20, then align CEA # Realign CEA # 1, then continue aligning CEA # 2 ' Manually trip the reacto l
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"' Reduce turbine load to maintain Tc within the operating ban '
l Answer C Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 003 ak1.03 Rotatenship of reactivity and reactor power to RO Group: 2 SRO Group: I rod motio RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning O l Misaligned CEA SO23-13-13  4 4 6565 Material Required for Examination Question Source: New l
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Reactor tripped from 100% power
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Pressurizer pressure - 1870 psia
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Containment pressure - 3.8 psig To where is RCP bleedoff flow being directed? The VC l l
I The Quench Tan The Containment Sum I HeRCD Answer B Exam Level B CognitiveLevel Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 003 k6.04 Containment isolation valves af fecting RO Group: 1 SRO Group: 1 operatio RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob CVCS  PalD 40124A    23 9210 l l
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Given the following plant conditions on Unit 3:    l l
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Plant is in a normal full power alignment -    .
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Pressurizer levelis 43%    I
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Pressurizer level setpoint is 48%
Which of the following is the expected automatic response of the CVCS system?
l Three charging pumps in service and letdown flow at maximu l One charging pump in service and letdown flow at minimu One charging pump in service and letdown flow at maximu Three charging pumps in service and letdown flow at minimu .
Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 004 A1.04 Pzr pressure and level  RO Group: 1 SRO Group: 1 RO K/A RO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Pressurizer Pressure SO2341.10 '  Att. 2 18 8 6706 and Level Control Material Required for Examination Question Source: Bank
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Question #7
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The plant is at 75% power when a new Purification Demineralizer is placed in service. Which of the following will occur if the boron saturation of this demineralizer is incomplete? T-ave will increas Reactor power will decreas Lithium concentration will go u Demineralizer resin channelin Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 004 k5.15 Boron and control reactivity effects as they RO Group: 1 SRO Group: 1 relate to MT ,
l RO K/A SRO K/A i Reference Title Facility Reference Number Section Page Revision Learning Ob RCS Purification and SO23-3- Att. 6 36 10 g7g7 Deborating lon Exchanger Operation      !
Material Required for Examination Question Source: New l
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j Given the following plant conditions:
  -= ; Plant is at 100% power, all' rods out
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Subsequently, CEA'3 (SD Bank A) drops into the core
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Which of the following is the reason for reactor power to be reduced below 90%7
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To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by January 21,1999. The written examinations and the supporting reference
  ~A. - To minimize radial power peakin To prevent adverse' Axial Shape inde To prevent a CPC generated Reactor Tri To ensure Transient Insertion Limits are not exceede Answer 'A Exam Level B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 005 ak106. Bases for power limit, for rod misalignmen RO Group: 1 SRO Group: 1 l
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob i l
Technical  Reactivity Control Systems LCS 3-1 3-1.10 '
Specifications  105 6565
 
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Question #9 A hot leg vent is required whenever the Steam Generator Nozzle Dams are installed. Which of the following states a reason for this if a loss of Shutdown Cooling (SDC) were to occur? To prevent steam buildup in the hot leg which could cause a loss of natural circulatio To prevent steam buildup in the hot leg which will ultimately collapse, causing ;
severe water hamme l To prevent RCS pressurization leading to a failure of the cold leg nozzle dam and potential core uncover To prevent RCS pressurization from causing an erroneous Draindown 12 vel Monitoring System (DLMS) indicatio l Answer C Exam Level 8 Cognitive Level Memory Facility San Onofre 2 & 3 - Exam Date 4/16/99 Tier: (2) 005 k3.01 RCS  RO Group: 3  SRO Group: 3 ,
l RO K/A SRO K/A i Reference Title Facihty Reference Number Section Page Revision Learning Ob Draining tile RCS SO23-3- Att. 21 159 13 3366 Material Required for Examination Question Source: New
 
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l I Question #10 An RCS HOT LEG break has just occurred on Unit 2.
 
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l What would be the result if the EOI steps to initiate simultaneous hot / cold leg injection were performed immediately following the LOCA diagnosis? Inadequate Core Cooling due to the loss of Safety injection flow out of the break.
 
l The HPSI pumps would reach runout conditions.
 
; Boration flow would be inadequate to maintain Shutdown Margin requireme.r t
l Injection flow through the core would be stoppe l Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 006 K.3.01 RCS  RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Ob LOCA Bases SO23-14-3  At gg3 Material Required for Examination Question Source: Bank l
 
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Question #11 Given the following plant conditions:
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Plant tripped 30 minutes ago    l
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Pressurizer Safety Valve is lifting
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Pressurizer pressure is 1900 psia
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RCS Tu is 545 F      ,
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Quench Tank rupture disk has ruptured    '
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Containment Pressure is I psig What is the expected temperature in the tailpipe downstream of the affected Pressurizer Safety Valve? degrees degrees degrees ' degrees Answer A {xam level B Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) Ow a2.01 Siuck open safet RO Group: 3 SRO Group:'3 RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Steam Tables Mollier Diagram 4068 l
Material Require <1 for Examination Steam Tables Question Source: New l
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l Question #12 i
Given the following:
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Component Cooling Water (CCW) Pumps P-024 and P-026 are operating
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P-025 is aligned to Train A and is in standby    ,
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A Safety injection Actuation Signal (SIAS) and a Loss of Voltage Signal (LOVS) i
 
occurred on both safety related buse Both safety related buses have been reenergized from their respective Emergency Diesel Generators (EDGs).
 
Which of the following correctjy describes how the CCW pumps automatically respond to the  ]
conditions described?      1 All CCW pumps star P-024 and P-026 start; /-025 does not star P-024 and P-025 start; P-026 does not star P-025 and P-026 start; P-024 does not star Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: '?) 008 a2.01 Loss of CCW Pump  RO Group: 3 SRO Group: 3 PO K/A SRO K/A !
Reference Title Facility Reference Number Section Page Revision Learning Ob Loss of CCW/SWC SO23-13-7 Material Required for Examination Question Source: NRC 6/98
 
Question #13 Which of the following Design Basis Accidents would generate the GREATEST amount of hydrogen and the reason why? SMALL BREAK LOCA, due to increased heat input from the mnning RCP LARGE BREAK LOCA, due to greater steam voiding in the cor SMALL BREAK LOCA, due to less steam voiding in the cor LARGE BREAK LOCA, due to hydrogen coming out of solutio Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/1699 Tier: (1) 009 2.4.21 Small Break LOCA  RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob UFSAR    6.2. .2.77 13 65II Material Required for Examination Question Source: New i
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Plant tripped 10 minutes ago l
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Pressurizer pressure is 2l00 psia and slowly increasing l -
Pressurizer level lowered to 28% and is now slowly increasing
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Both Steam Generator levels are 18% and slowly increasing l
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Both Steam Generator pressures are 1000 psia and steady    l l
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All systems are in Automatic and have actuated as required Which of the following is the co'rrect conditiori for the Pressurizer heaters at this time?
(ASSUME NO OPERATOR ACTION) E heaters are off and all other heaters a_e on. - All Pressurizer heaters are o E and proportional heaters are off, non 1E backup heaters are o lE and non IE backup heaters are on, proportional heaters are of Answer A Exam Level B Cognitive Level Application Facdity San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) PPCS 010 A4.02 Pressurizer heaters  RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob PZR Pressure and SO23-3-1.10  6 8 10729 Level Control Material Required for Examination Question Source: Bank I
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Given the following plant conditions:
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materials identified in Attachment 2 of ES-201 will be due by March 1,1999. Any delay in j
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Unit 2 is in MODE 3
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Pressurizer Ixvel Control System is in automatic    i Which of the following would cause letdown flow to increase?
 
- Irss ofinstrument air to the inservice letdown flow control valv The pressurizer level transmitter equalizing valve has vibrated'ope Volume Contml Tank level has increased to 85%. SBCS controller setpoint has failed low with 2 valves in manual permissiv Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier. ( 2) 011 A3.03 Charging and letdow RO Group: 2 SRO Group: 2 j RO K/A SRO K/A ;
Reference Title Facility Reference Number Section Page Revision Learning Ob PZR Pressure and SO23-3-1.10  Att. 2 18 8 Level Control 10596 Material Required for Examination Question Source: New
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Question #16 A LOCA occurred 90 minutes ago and SO23-12-3 is being implemented. You are monitoring the Floating Step for "Two-phase heat removal established."
 
i Which of the following temperature sensors are required to be monitored during implementation  ;
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of this floating step?
i l Hot leg RTD ' Cold leg RTD l Core exit thermocouple l Heated junction thermocouple Answer C Exam Level B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99
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Tier: (1) 011 ek1.01 Natural circulation and cooling, including reflux RO Group: 2 SRO Group: 1 .
boilin RO K/A l SRO K/A . Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA  SO23-12-3  FS-4 37 15 2537 Material Required for Examination      .
I Question Source: NRC 6/98
 
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Question #17 Given the following conditions:
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A large loss of coolant accident is in progress
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SIAS, CIAS, MSIS, CSAS, and RAS have actuated
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RWSTlevelis 16%
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Emergency sump levelis 20'
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ECCS valves are in the following positions:
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RWST Suction valves HV9300/HV9301 OPEN
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Containment sump isolation valves HV9302/HV9303 OPEN
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Containment sump isolation valves HV9304/HV9305 OPEN
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SI pumps combined recirc valves HV9306/HV9307 OPEN Which of the following valve (s) has failed to automatically reposition to its Recirculation Actuation Signal position? HV9300/HV930 j HV9302/HV930 HV9304/HV930 HV9306/HV930 Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16FJ9 Tier: (2) 013 a2.01 LOCA  RO Group: 1 SRO Group: 1
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RO K/A SRO K/A l Reference Title Facility Reference Number Section Page Revision Learning Ob ESFAS Operation SO23-3-2.22  Att.15 102 12 6221 Material Required for Examination Question Source: Bank
 
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Question #18 He plant is in normal operation at 100% power, when one CEA drops fully into the cor Which of the following statements correctly describes the plant response to this event, assuming no operator action? Reactor power decreases and RCS temperature decreases below progra Turbine MWs lower and RCS temperature stays on progra Reactor power decreases and RCS temperature stays on progra Turbine MWs constant and RCS temperature decreases below progra Answer A  Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 014  A2.03 Dropped Ro RO Group: 2  SRO Group: 1
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RO K/A SRO K/A Reference Title  Facility Reference Number Section Page  Revision Learning Ob Misaligned CEA  SO23-1313  2  4 4362 Material Required for Examination Question Source: Bank l
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. Question #19 A reactor startup is in progress and the reactor is approaching criticalit Which set of parameters correctly describes the indications used to declare criticality? Neutron count rate increasing, SUR positive, rods being withdraw Neutron count rate decreasing, SUR negative, rods being inserte Neutron count rate increasing, SUR positive, rod motion stoppe Neutron count rate decreasing, SUR zero, rod motion stoppe Answer C Exam Level O  Cognitive Level Mernory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier; (2) 015 k5.05  Criticality and its indication RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number  Section Page Revision Learning Ob Reactor Startup SO23-3- Att. 2 31 19 4392 Material Required for Examination Question Source: Bank
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l Question #20 l
i The plant has just tripped from 100% power. What effect will a rise in containment temperature (i.e. from 80 F to 250*F) have on the Steam Generator Narrow Range level instruments? Actual level will be higher than indicated level due to voiding in the variable le Actual level will be higher than indicated level due to reference leg temperature increas Indicated level will be higher than actual level due to voiding in the variable le ! Indicated level will be higher than actual level due to reference leg temperature increas Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 016 2.4.48 Non-Nuclear Instrumentation RO Group: 2 SRO Group: 2 System RO K/A l SAO K/A )
Reference Title Facility Reference Number Section Page Revision Learning Ob Instrumentation Generic Fundamentais
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Question #21 Which of the following could be an indication of core uncovery?
    (Assume instmments are accurate)
CET Temperature equal to: degrees Fahrenheit with RCS Pressure equal to 1200 psi degrees Fahrenheit with RCS Pressure equal to 1350 psi degrees Fahrenheit with RCS Pressure equal to 1500 psi degrees Fahrenheit with RCS Pressure equal to 1650 psi Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 017 k5.03 Indication of Superheatin RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3  At Material Required for Examination Question Source: New
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Question #22
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Unit 2 was operating at full power when a plant trip occurred. The operators have initiated SO23-12-1, Standard Post Trip Action Plant conditions are as follows:
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One CEA is not fully inserted
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Pressurizer levelis 20% and rising    ,
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Pressurizer pressure is 1950 psia and rising
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S/G narrow range water levels are at 29% with MFW RTO actuated
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Containment average temperature is 125 F
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Containment average pressure is 1.0 psig
        !
What is the correct operator action to be taken at this time, per the SPTAs?
a Ensure normal containment cooling is functioning properl Emergency borate the RC ' Reenergize Pzr heaters to raise pressurizer pressur l Override AFW system to feed both S/Gs at greater than 200 gp Answer A Exctn Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 022 Generic 2.4.21 Knowledge of the parameters used to RO Group: 1 SRO Group: 1 asses the status of safety function RO K/A SRO K/A Reference Title Facility Reference Number Sect Page Revision Learning Ob SPTA  SO23-12-1  11 15 5359 Material Required for Examination Question Source: Bank
 
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Question #23      ;
 
Plc.nt is operating in a normal full power alignmen Which of the following will result in a loss of letdown flow? Temperature of 150 F leaving the letdown heat exchange J Volume Control Tank outlet valve LV-0~227B fails close Loss of instrument air to FV203 Boronometer/ Rad Monitor control valv gpm letdown flow with only one charging pump runnin Answer B Exam Level 0 Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 022 AK3.04 Isolating letdown  RO Group: 2 SRO Group: 2
  . RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob CVCS  DBD-SO23-390  Fig. D-1 160 5 8992 I
Material Required for Examination Question Source: New l
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Question #24
 
Which of the following is a condition requiring emergency boration? Part length CEAs inserted to 138 inches withdrawn with Unit at 90% powe loss of all CEA Reed Switch Position indication during a reactor startu Regulating Group 6 CEAs inserted to 100 inches withdrawn with the Unit at 100% powe !
l Loss of Pulse Counter CEA Position indicatio Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 ak3.01 When emergency boration is require RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob j Emergency Boration of SO23-13-11  2 4 the RCS 6552 l
Material Required for Examination Question Source: New
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i Question #25        l i
i Given the following plant conditions.
 
I l -
HPSI Pump 2P-018 is aligned to TR AIN B l -
Large Break LOCA inside Containment has occurred on Unit 2  I l
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Pressurizer pressure is'900 psia
-
Containment pressure is 13 psig    i Which of the following TRAIN B pumps should be running due to ESFAS actuations?  j l LPSI Pump P-016, HPSI Pump P-019, HPSI Pump P-01 CS Pump P-013, HPSI Pump P-019, HPSI Pump P-018.
 
l
, CS Pump P-013, LPSI Pump P-016, HPSI Pump P-019.
 
l' CS Pump P-013, LPSI Pump P-016, HPSI Pump P-01 Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier: ( 2) 026 K2.01 Containment Spray Pumps RO Group: 2 SRO Group: 1 RO K/A SR O K/A l Reference Title Facility Reference Number Section Page  Revision Learning Ob )
Safety injection, DBD-SO23-740  1.1. ,41.43  2
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Containment Spray and 7328 I
1.1.1.2 l Shutdown Cooling Systems l
l Material Required for Examination Question Source: New l
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Question #26 l
Which of the following Pressurizer Pressure / Level carameters would require entry into a Technical Specification action statement with Unit 3 at 100% power? Levelof 28%. levelof 56%. Pressure of 2030 psi ,
        . Pressure of 2280 psi Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 027 AA2.04 Technical Spocification limits for RCS pressur RO Group: 1 SRO Group: 2
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RO K/A SRO K/A Reference Title Facility Reference Nr:nber Section Page Revision Learning Ob !
Technical Reactor Coolant System 3. .4- 1  67lg i
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Specifications Material Required for Examination Question Source: New
 
Question #27 What is the purpose of the Trisodium Phosphate (TSP) Dodecahydrate baskets in Containment?  l l Minimize the evolution of Hydrogen from containment sump wate Minimize the evolution of Oxygen from containment sump wate Lower pH of containment sump wate j Raise pH of containment sump wate ;
Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/09 ;
Tier: (2) 027 k1.01 CSS  RO Group: 3 SRO Group: 2 l
RO K/A SRO K/A l Reference Title  Facility Raference Section Page Revision Learning Ob Number Safety injection, Containment Spray DBD-SO.3-740 1.1.12 43 2 and Shutdown Cooling Systems 3285 Material Required for Examination Question Souice: New l
 
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y-Question #28 Given the following plant conditions:
-- Reactor Trip has just occurred '
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Pressurizer levelis 19% and rising
--
Pressurizer pressure is 1950 psia and lowering Which of the following actions is required per SO23-12-1, Standard Post Trip Actions, for these conditions? Verify all available charging and HPSI Pumps are runnin Ensure all available charging pumps are runnin Verify all pressurizer heaters are O Ensure Pressurizer normal and auxiliary spray valves close Answer D Exam Level D Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 028 ak305 Actions contained in EOP for Pzr level RO Group: 3 SRO Group: 3 malfunction, RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA  SO23-12-1  5 15 622 Material Required for Examination Question Source: Bank i
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w Question #29 Given the following plant conditions:
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An inadvertent MSIS has occurred
-
The Reactor trip circuit breakers have RQI opened
-
The Anticipated Transient Without SCRAM / Diverse SCRAM System (ATWS/ DSS) has caused a reactor trip Which of the following has automatically occurred to mitigate the event? SIAS is initiate l l
I CEDMCS MG set output BREAKERS ope CEDMCS MG set output CONTACTORS ope V Buses BIS and B16 deenergize Answer C Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (1) 029 ek3.01 Verifying a reactor trip; methods RO Group: 2 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob *
Plant Protection DBD-SO23-710  2. g System Material Required for Examination Question Source: New
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- Question #30 Given the following plant conditions:'      ,
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Unit 2 tripped 25 minutes ago    ~l
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A Stearn Generator Tube Rupture has been diagnosed and RCS cooldown has been initiated
-
Hot leg temperature is 529 F    l
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RCPs 2P001 and 2P004 have been secured
-
S/G levels are 27% in E089 and 31% in E088 and slowly rising'~
-
Pressurizer level is 20% and slowly rising
-
Pressurizer pressure is 1480 psia    ;
Which of the following actions should be performed at this time? Perform HPSI throttle sto ' Override and feed both steam generator . Secure 2 charging pump . Isolate the affected steam generato Answer D Exam Level B Cognitive Level Application Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier:( 2) 035 A2.01 Faulted or ruptured S/Gs RO Group: 2 SRO Group: 2 RO K/A SRO K/A i Reference TiUe Facility Reference Number Section Page Revision Leaming Ob SGTR  SO2312-4  11 16 6g74
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Material Required for Examination Question Source: New
 
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~ Question #31 Given the following plant conditions:
- Unit 2 tripped 18 minutes ago
-
Steam Generator Tube Rupture has been diagnosed and SO23-12-4 has been  l implemented      j
 
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All Reactor Coolant Pumps were secumd 12 minutes ago
-
Natural Circulation Criteria has been verified
-
HPSI throttle /stop has been completed; all HPSI and charging pumps are secured
--
Pressurizer pressure is 1150 psia AND slowly lowering
-
Pressurizer level is 66% AND slowly rising    !
Which of the following conditions would explain the pressurizer level response? Pressurizer level instrument variable leg has broke Voiding is occurring in the RCS head regio l l S/G back leakage into the RC RCS heatup is occurrin I Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 038 ekt.03 Natural Circulation  RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title - Facility Reference Number Section Page Revision Learning Ob ,
I SGTR Bases  SO23-14-4  At l Material Required for Examination Question Source: New l
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Question #32 '
        -
l Unit 3 is at 17% power and the operator has just applied Block Imad when a generator trip occurs. Describe the expected response of the Main Steam Safety Valves (MSF Vs) and the Steam l Bypass Control System (SBCS) to this event.
 
, MSSVs will initially open, then reseat; SBCS valves will open as required to control main steam pressur MSSVs will not open; SBCS valves will open as required to control main steam pressur MSSVs will initially open, then reseat; SBCS valves receive a " quick-open" block signal due to low Tav MSSVs and SBCS valves will be unaffecte .
Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 041 k4.17 Reactor Trip  RO Group: 3 SRO Group: 3 RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob S/G and Secondary DBD-SO23-365 6. Side 6455 Material Required for Examination Question Source: New I
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{ Question #33 l While performing a heat treat on Unit 3, the condenser low vacuum alarm is received. You note that main condenser backpressure is 5.8" Hg ab ;
l What effect should this have on Steam Bypass Control System (SBCS) operation? SBCS is disabled due to low condenser vacuum.
 
,        , The SBCS " Emergency Off" push button should be pushed to prevent system operation during the low vacuum conditio Vacuum is not degraded enough to have an effect or require any action D.- SBCS " quick-open" actuation is blocked but modulate operation is still enable Answer C Exam Level Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 051 ak3.01 Loss of steam dump capabihty upon loss of RO Group: 1 SRO Group: 1 condenser vacuu RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Steam Bypass System SO23-3-2.18 Operation 6455 Material Required for Examination Question Source: New
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Question #34 Given the following plant conditions:
-
Unit 2 tripped 45 minutes ago
-
An Excess Steam Demand Event is in progress    l
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E089 is about to reach dryout    i Which of the following conditions could occur if steaming is not commenced on the unaffected S/G7 l Loss of natural circulation in the affected RCS loop resulting in stabilization of I RCS temperature Loss of RCS subcooling resulting in a loss of natural circulation in both RCS loop less of inventory in the affected S/G resulting in a loss of natural circulation in that loo Loss of natural circulation in both RCS loops resulting in RCS repressurizatio Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 054 ak3.04 Actions contained in EOP's for loss of MFW, RO Group- 2 SRO Group: 2 RO K/A SRO K/A ' Reference Tit!e Facility Reference Number Section Page Revision Learning Oo ESDE Bases SO2314-5  At Material Required for Examination Question Source: New
 
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Question #35 Plant conditions are as follows:
-
A Imss of Offsite Power caused a reactor trip 30 minutes ago
-
MSIVs have been manually closed
-
Main Steam pressure is being maintained at 1000 psia following the reactor trip Which of the following conditions would be expected for the above conditions? Hot leg temperature of 550 F and risin Cold leg temperature of 530 F and lowerin Hot leg temperature of 570 F and lowerin Cold leg temperature stable at 545 Hot leg temperature of 587 F and risin Cold leg temperature stable at 545 Hot leg temperature of 570 F and lowerin Cold leg temperature of 540 F and lowerin Answer B Exam Level B Cognitive Level Comprehension  Facility San Onoire 2 & 3 Exam Date 4/16/99 Tier: (1) 055 aki.02 Natural Circulatioin Cooling  RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number  Section Page Revision Learning Ob Loss of Offsite Power SO23-12-7    8 15 6469 Material Required for Examination Question Source: New
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Question #36 he plant was initially operating at 100% powe ;
I A complete less of Offsite Power occurred 5 minutes ago.- HQ operator actions have been taken  I and all systems functioned as designe l How are the S/Gs maintaining RCS heat removal?    l 1 AFW supplying S/Gs; steaming out Main Steam Safety Valve ]
        . AFW supplying S/Gs; steaming using the' Atmospheric Dump Valve MFW supplying S/Gs; no steaming require : '
MFW supplying S/Gs; steaming using the SBC Answet .A Exam Level B CognitivoLevel Comprofiension Facility San Onofre 2 & 3 Exam Date 4/18/99 Tier:(1) 050 AA2.56 RCS T-av RO Group: 3 SRO Group: 3 '
RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Ob SPTA  SO23-12-1  8 15 63l6 Material Required for Examination Question Source: Bank
 
I Question #37
        !
Given the following plant conditions:      !
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Channel"A" RCS hot leg temperature Tr-0122-1 has failed and the affected functional units have been bypassed ~
-
Channel"C" RCS hot leg temperature TF-0122-3 has also failed and the affected functional units have been placed in trip    1
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A loss of vital bus inverter 2Y004 occurs and the Reactor does NOT trip
-
All other plant conditions are normal    l
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Which of the following action is required? Vital bus 2YO4 must be placed on its attemate source within 24 hour Manually trip the reacto Initiate a Rapid Downpower per SO23-5-1.7, Power Operation Initiate a normal plant shutdown per SO23-5-1.7, Power Operation Answer C Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 057 aa2.03 RPS panel alarm annunciators and RO Group: 1 SRO Group: 1 trip indicators RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob RPS/ Loss of Vital Bus GO23-1318  Att 2 12 2 6593 inverter Material Required for Examination Question Source: New
 
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. Question #38 Given the following plant conditions:
-
Unit 2 tripped 40 minutes ago
-
Both Main Steam Isolation Valves (MSIVs) have failed closed
- - All Auxiliary Feedwater has been lost and could not be restored Which of the following methods should be used to recover the RCS Heat Removal Safety Function? Establish HPSI flow to the cold legs for once-through core coolin Reestablish Main Feedwater flow to the S/G Establish LPSI flow to the cold legs for once-through core coolin Establish low pressure allemate feedwater flow using condensate pump Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/1&'99 Tier: (2) 059 k304 RCS  RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Functional Recovery SO23-12-9  Att. 8 330 18 ggl6 Material Required for Examination
- Question Source: Bank i
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Question #39 l
Given the following plant conditions:
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Unit 2 is at 355' A cooldown is in progress using the S/G's Which of the following is required to be OPERABLE per Technical Specification 3.7.5, Auxiliary i Feedwater System?
1 All three AFW Pump l Two motor driven AFW Pump l One motor driven and one steam driven AFW Pum One motor driven AFW Pum Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 ;
Tier: (2) 061 Generic 2.1.12 Ability to apply Technical Specifications to a RO Group: 1 SRO Group: 1 system RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj, Technical  Auxiliary Feedwater System 3. .7-11 Specifications 6643 Material Required for Examination Question Source: New I
 
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Question #40 Given the following information:
-
The unit tripped from 100% power 20 minutes ago
-
Both Steam Generator levels lowered to 17% NR and recovered to 26% NR  I
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The operator has depressed the " Override" pushbuttons for the AFW valves and is feeding each steam generator at 450 gprn l
Subsequently:      4
 
-
Steam Generator E088 pressure decxases to 700 psia with level at 25% N Steam Generator E089 pressure decreases to 850 psia with level at 27% NR Which of the following describes the status of the AFW system (assume no other operator actions have occurred)? Both steam generator E088 and E089 are being fed,
        ' E088 is being fed and E089 is isolate Neither steam generator E088 nor E089 is being fe i E089 is being fed and E088 is isolate _
Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 I Tier: (2) 061 a3.04 Automatic AFW lsolation  RO Group: 1 SRO Group: 1 RO K/A SRO K/A 42 Reference Title Facility Reference Number Section Pagc Revision Learning Ob}.
Plant Protection DBD-SO23-710  2.1. System 4726 Material Required for Examination Question Source: Bank l        1
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receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled.  ;
l in order to conduct the requested written examinations, it will be necessary for your staff to l provide adequate space and accommodations in accordance with ES-402.


Appendix E of NUREG-1021 contains a number of NRC policies and guidelines that will be in effect while the written examinations are being administered.
,        ,
Question #41 Given the following:
        !
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Both Units 2 and 3 are at full powe Unit 2 is preparing to shift Train A SWC pumps
-
The operator assigned to perform 4KV breaker manipulations goes to the wrong unit and tums off DC control power to 3Pi l2, which was running at the time What effect does this have on the Unit 3 SWC system?    j SWC pump 3P112 breaker opens, SWC pump low flow alarms are receive ,
1 SWC pump 3P112 breaker opens, no alarms are received due to the loss of  l control powe SWC pump 3P112 breaker stays closed, no remote operation or automatic tripping is availabl I SWC pump 3P112 breaker stays closed, no remote operation is possible but automatic trips are functiona Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 063 K3.02 Components using DC control RO Group: 2 SRO Group: 1 Power RO K/A SRO K/A l Reference Title Facility Reference Number Section Page Revision Learning Ob Elementary Diagram 30795    18 5220 l
l Material Required for Examination Question Source: New i
 
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- Question #42 Plant conditions are as follows:
-
Unit 2 tripped 10 minutes ago on low pressurizer pressure  ,
 
-
A loss of offsite power occurred 6 minutes ago
-
Pressurizer pressure is now 1430 psia    ,
-
Bus 2A04 is energized
-
20003 has just tripped and bus 2A06 is deenergized    j l
Which of the following diesel generator trips could have caused the loss of 2G003? -   l l High crankcase pressur High jacket water cooling temperatur )
1 Loss of excitatio Generator differentiel, Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier: (2) 064 k4.02  Trips for ED/G while RO Group: 2' SRO Group: 2 operating (normal or emergency) RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Elementary Diagram 30330    22 5346
- Material Required for Examination Question Source: New I
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Question #43 Given the following plant conditions:
-
Plant is operating at 100% power
  -
Alarm 61 A15 (Fire Detected) is received in the Control Room
-
The Fire Computer indicates the fire is in the Unit 2 computer room Which of the following explains the expected conditions for a fire in the computer room? Supply and exhaust dampers open, for 'once through' air flo I Supply and exhaust dampers close, isolating the computer roo I Supply damper closes, exhaust damper opens to exhaust smoke, i Supply damper opens, exhaust damper closes to allow fresh air i Answer B- Exam Level . 8 Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 067 aa1.05 Plant and Control Room Ventilation System RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Halon Fire Protection SO23-7-4  6. System Operation      8356 Material Required for Examination Question Source: New
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Question #44 A release of one of the Radwaste Secondary Tanks is in progress. Liquid Rad Waste Monitor (RE-7813) fails lo Which of the following will allow the release to recommence? Die Plant Superintendent must approve the release permi Two independent samples, release rate calculations, and valve lineup verifications must be performe The sample flowrate must be estimated at least once every 4 hour The liquid release cannot recommence until RE-7813 is detemiined to be OPERABL Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam oate 4/16/99 Tier: (2) 068 k6.10 Radiation monitors  RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Ob Liquid Radioactive SO23-8-7  Att. 6 95 10 g()6g Waste Release      )
Operations      ;
Material Required for Examination Question Source: New
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Question #45 Given the following:
-
Wide Range Gas Monitor (WRGM),3RE-7865, is aligned to the Plant Vent Stack
        )
-
A Waste Gas Decay Tank release is in progress
-
Alarm 61 A27," Plant Vent Stack Radiation Hi", is received due to high radiation on 3RE-7865 Which of the following best describes the automatic action (s) caused by the WRGM for the above set of conditions? The monitor realigns to containment purge to sample that flow pat I 1 Sample flow control shifts from Isokinetic flow control to manual flow contro The waste gas discharge flow control valve FV-7202 close , The outside containmerit mini-purge isolation valve HV9825 close Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 071 k4.04 Isolation of waste gas release tanks RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Radwaste Gas SO2M-15 Discharge 9413 Material Required for Examination Question Source: NRC 6/98 I
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Question #46
        !
Unit 2 is in MODE 6. During fuel inspection activities, the fuel inspection device was raised out of the Spent Fuel Poo Airbome radiation levels as sensed by the Fuel Handling Building Vent Airbome Monitors RE-  i
        '
7822 & RE-7823 have exceeded the alarm / trip setpoin l
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RE-7822 is in bypass      j
-
RE-7823 is in normal operation    j Based on these conditions, which of the following statements represents correct system response?        i l FHIS actuation, Train 'A'. FHIS actuation, Train 'B'. FHIS actuation, Trains 'A' and 'B'. No FHIS actuation occur l Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 072 kl.03 Fuel Building Isolation  RO Group: 1  SRO Group: 1 RO K/A SRO K/A Reference Title  Facility Reference Section Page Revision Learning Ob Number
        -
Fuel Handling Area Vent airborne Process SO23-3-2.2 . Radiation Monitoring System Operation 6302 Material Required for Examination Question Source: Bank
 
Question #47-Given the following plant conditions:
-
A Waste Gas Decay Tank release using 2/3 RT-7808, Plant Vent Stack Airbome Radiation Monits,is in progres Rad monitor 3RT-7865, Containment / Plant Vent Stack Radiation Monitor, becomes INOPERABL What additional action must be performed to allow the release to continue? Process flow rate must be estimated at least once every 12 hour Two independent samples must be drawn at least once every 4 hour Reverify valve alignment, sample and recalculate release rate calculation Verify composite samplers are operational for the gaseous radwaste syste Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/1049 Tier: (2) 073 Generic 2.1.20 Ability to execute procedure step RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Radwaste Gas so23-8-15  4.11 4 11 Discharge 10103 Material Required for Examination      ,
Question Source: New      I I
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l Question #48 The plant has just tripped from 100% power operation, the SPTAs are being carried out and plant conditions are as follows:
-
All CEAs are fully inserted
-
PZR level is 20%
-
RCS Subcooling is 88 F
-
Pressurizer pressure is 1410 psia
-
RCS cold leg temperature is 490 F
-
CNTMT pressure is 0.5 psig
-
All ESFAS Systems have actuated as required Which of the following is required per the SPTAs for Reactor Coolant Pump operation? Trip four RCP Trip two RCP Leave all four RCPs runnin Trip one RC Answer B Exam Level B Cognitive Level Comprehenson Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 074 ek304 Tripping RCPs  RO Group: 1 SRO Group: 1 R O K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA  SO23-12-1  5 15 622 Material Required for Examination Question Source: New l
 
Question #49 Which of the following electrical buses supply power to the 4 Saltwater Cooling Pumps located in the Unit 2 Saltwater Cooling Pump Room? One (I) pump from each of 2B04,3B04,2B06, and 380 Two (2) pumps from each of 2B04 and 2B0 One (1) pump from each of 2A04,3A04,2A06, and 3A0 Two (2) pumps from each of 2A04 and 2A0 Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 075 K2.03 Cire Water System Emergency RO Group: 2  SRO Group: 2 Essential SWS pumps RO K/A l SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Saltwater Cooling P3D-SO23-410  Table C-1 98 2 System 6727 Material Required for E.iamination Question Source: New s
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To permit timely NRC review and evaluation, your staff should submit preliminary reactor  l
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operator and senior reactor operator license applications (Office of Management and Budget (OMB) approval number 3150-0090), medical certifications (OMB approval number 3150-0024),
[ Question #50
and waiver requests (if any) (OMB approval number 3150-0090) at least 30 days before the first examination date. If the applications are not received at least 30 days before the examination l
.        l
i date, a postponement may be necessary. Signed applications certifying that all training has been completed should be submitted at least 14 days before the first examination date.
        ,
l l A fire has been detected in Containment. As the Fire Brigade Technical Advisor working with the  l Fire Depetment, you are asked what type of automatic water suppression system is used in the  l immediate vicinity of RCP P00 l l
l Which of the following is the correct response? A deluge water spray sprinkle ! A wet pipe sprinkle Automatic pre-action sprinkle No suppression system is located in the are Answer. A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 1/16/99 Tier: (2) 086 K5.03 Effect of H,0 spray on electrical components RO Group: 2  SRO Group: 2 RO K/A SRO K/A .
Reference Title  Fac!hty Reference Section Page Revision Learning Ob Number Fire Suppression Water System SO23-71  Att. 7 53 18 93g6 Operation Material Required for Examination Question Source: Bank
 
Question #51 With Unit 2 in MODE 1, an inadvertent CIAS occur Which of the following describes the FIRST actions required to be performed per the AOI? Initiate SO23-13-7, Loss of CCW/SW Trip the Reactor Coolant pump Trip the Reactor and Turbin Override /Open CCW NCL Isoltt. valves'.
Answer C Exam Level B Cognitive Level . Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 103 a3.01 Containment isolation  RO Group 3  SRO Group: 2 RO K/A ' SRO K/A l Reference Title  Facility F'aference Section Page Revision Learning Ob Number
 
Recovery From inadvertent Safety SO23-13-17 3. I Injection / containment isolation 6584 Material Required for Examination Question Source: Bank      ;
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f Question #52 l
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The unit is operating at 100% power. The following conditions exist on Reactor Coolant Pump i P002:
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Vapor Seal Cavity Pressure  78 psig    ;
-
Upper Seal Cavity Pressure 2240 psig    {
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Middle Seal Cavity Pressure 2250 psig Which of the following actions are required for the stated conditions? Full power operations may continue, trend P002 parameter Initiate a normal plant shutdow Initiate a Rapid Downpowe j Immediately trip the reactor and 5 seconds after the CEAs are inserted, trip RCP P00 Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 015/17 aa2.01 Cause of RCP failure RO Group: 1 SRO Group: 1 RO K/A SRO K/A Referonce Title Facility Reference Number Section Page Revision Learning Ob RCP Seal Failure SO23-134 Material Required for Examination Question Source: Bank I
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Question #53 During normal plant operations, while performing actions outside of the Control Room, what is the relationship between the Control Room Operators and the PEO? The PEO will take direction from the CRS, but is responsible to the C The ACO will direct the PEO's activities, but will inform the CRS before action is  I take I The CO will direct the PEO's activities, but only with SM concurrenc The CO will direct the PEO's activities under the supervision of the CR l Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exarn Date 4/16/99 l Tier: 2. Knowledge of conduct of operations requirements RO Group: SRO Group:
RO K/A SRO K/A 3.8 i Reference Title Facility Reference Number Section Page Revision Learning Ob l Conduct of Operations SO23-(M6  6.1 )g4l7 l
l Material Required for Examination Question Source: NRC L1/98 l
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i Question #54
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Given the following plant conditions on Unit 2:    1 i
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RCS average temperature is 295 Maintenance is being conducted in the switchyar At 9:00 am the switchyard foreman reports a crane operator lost control and tripped open the Unit 2 switchyard Reserve Auxiliary Transformer breaker Substation personnel on the scene have conducted a visual inspection and report -
that the breakers will be OPERABLE at 10:30 a '
What actions are required by Technical Specifications?
i No further action is required since the LCO will be met within the Required Action Completion Tim Within I hour, perform surveillance test on both DG Take action to suspend any positive n' activity additions entil the second offsite  ,
circuit is energize Within I hour, verify correct breaker and power availability for the offsite circuit I that was not deenergize Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.11 Knowledge of <1 hr Tech Spec action statement RO Group:  SRO Group:
RO K/A SRO K/A 18 Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Electric Power Systems 3. .8-1 Specifications 9964 Material Required for Examination
_ Question Source: NRC 6/98 l
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Question #55        4 i
l Which of the following sets of conditidns will allow a start (breaker closure) of Circulating Water  j Pump P115 (Assume 2A0308 breaker racked in with DC on)?    j
 
-
211V5288 - CW P115 Discharge Valve
-
211V5100 - TPCW supply valve from Pl15 to TPCW IlX    -
l V5288 open,2iiV5100 close VS288 open,211V5100 open.
 
, HV5288 closed,2iiV5100 ope V5288 closed,2iiV5100 close Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 i l
Tier: 2.1.24 Ability to obtain and interpret electrical and mechanical RO Group:  SRO Group:
drawing RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Ob l l
Elementary Diagrams 31001,31005,31000,  17,9,4,8 48(>2 31061 Material Required for Examination prints: 31001,31005,31009,31061    j
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Question Source: Bank
 
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Question #56 When observing a Motor Operated Valve (MOV) during stroke testing, it is important to stand cl car of the handwheel plan This is because the handwheel will rotate at high speed and could disintegrate if: The limit switch fails to actuat The clutch does not disengag The motor phase rotation is incorrec The torque switch fails to actuat Answer B Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2.2.12 Knowledge of Surveillance Procedure RO Group:  SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Valve Operation SO23-O-2 .13 5 5 6363 j Material Required for Examination Question Source: Bank
 
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l l' Question #57 Which of the following Reactor Protection System (RPS) Trips is HQI required by Technical Specifications? Pressurizer Pressure-Lo Pressurizer Pressure-Hig Steam Generator Level-Lo I 1 Steam Generator levci-Hig I i
Ansi.cr D Exam Level B Cognitive Level Memory  Facnity San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.222 Knowledge of limiting conditions for operations and safety RO Group:  SRO Group:
Jimit j RO K/A SRO K/A ]
Reference Title Facility Reference Number Section Pago Revision Learning Ob Technical  RPS Instrumentation 3. Table 3.3.1-1 Specifications 7270 j
 
Material Required for Examination      l Question Source: Bank i
 
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r Question #58 Why must a MODE 6 EDMR be issued if the Spent Fuel Pool boron concentration drops below 2600 ppm? The SFP water could dilute the refueling cavity when the fuel transfer tube is opene The addition of spent fuel assemblies to the spent fuel pool could cause spent fuel pool criticalit The RCS water could dilute the Spent Fuel Pool when the fuel transfer tube is opene The movement of a fuel assembly out of a high density fuel rack could cause spent fuel pool criticalit ,.
Answer - A Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2.2.27 Knowledge of the refueling proces RO Group:  SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCAR and EDMR SO123-0-13  6. Material Required for Examination Question Source: Bank i
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[ Question #59 l- A worker has been assigned the task of unbolting incore detector flanges.
 
l The following is the year to date dose for this worker, j -
Deep Dose Equivalent - 0.5 REM l -
Committed Effective Dose Equivalent - 0.2 REM l
Dose Rate for this task is 0.9 R/HR gamma radiation l
Which of the following is the maximum stay time for this worker per SONG's Administrative Limits?
i minute minutes.


.
.
9901210109 990113 l PDR ADOCK 05000361 y PDR l
        ' minute minutes.
 
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Answer A Exam Level B Cognitive Level Applicahon Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2. Knowledge of 10 CFR:20 and related facility radiation RO Group: SRO Group:
control requirement RO K/A SRO K/A Reference Title Facility Reference Number ! ection S  Page Revision Learning Ob Health Physics SO123-Vil-20  6.4. gggj Program
- Material Required for Examination
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Question Source: New I        1
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i Question #60 Which of the following statements describes the relationship between dose rate and distance for a point source?      l The dose rate varies inversely to the square of the distanc ) The dose rate varies inversely to distanc i l The dose rate does not drop off appreciably with distanc ) The dose rate is insignificant at a distance of three fee Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2. Knowledge of facility ALARA progra RO Group: SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals    96gl Material Required for Examination Question Source: Bank m


l San Onofre Nuclear Generating Station  -4-    l E-Mail report to T. Frye (TJF)
r Question #61        j
E-Mail report to D. Lange (DJL)
        !
E-Mail report to NRR Event Tracking System (IPAS)
Given the following:       !
E-Mail report to Document Control Desk (DOCDESK)
  /
bec to DCD (IE01) - DRS, DRP, and Decommissioning d
bec distrib. by RIV:
Regional Administrator DRS Director    -
Resident inspector DRP Director DRS-PSB DRS Director MIS System
  '
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Branch Chief (DRP/E)
 
RIV File Senior Project inspector (DRP/E)
t
Branch Chief (DRP/TSS)
'
DOCUMENT NAME: R:\_SO23\SO930111.]lp To receive copy of document, Indicate in box: "C' = Copy without enclosures *E' = Copy with enclosures "N* = No copy l ' C:OB l@- D:DRP l  l  l  l JLPellet/imb6 " '
l
KEBrockmanW 01/fV99 01/tV99 OFFICIAL RECORD COPY    ,
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        ,
The unit is in MODE 1      '
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  -
2RT-7865 is aligned to the Plant Vent Stack
  -
Containment Mini-Purge is in progress    I
 
l Which of the following would require immediate securing of the Containment Mini-Purge?  j
        : RT-7865, Containment / Plant Vent Stack Radiation Monitor becomes INOPERABL RT-7804, Containment Airborne Radiation Monitor becomes INOPERABL RT-7828, Containment Purge Stack Radiation Monitor becomes  i INOPERABL . FR-7826, Containment Purge Stack Process Flow Recorder becomes INOPERABL Answer C Eram Level Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2. . Knowledge of the process for performing a containment RO Group: SRO Group:
purg RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Containment Purge and SO23-1- Att.13 70 22 Recirculation Filtration System 7576 Material Required for Examination Question Source: Bank
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-        i Question #62 A major earthquake occurred ten minutes ago. The Reactor has tripped and the following conditions exist on Unit 2:
-
A loss of the switchyard has occurred
-
Both S/Gs are at 17% NR level and no AFW flow can be established to either S/G
-
Pressurizer Level is 12% and decreasing
-
Main Steam Line Radiation Monitors are trending upscale t
Which of the following is the appropriate Emergency Operating Instruction to mitigate the Unit 2 event? SO23-12-4, Steam Generator Tube Ruptur SO23-12-6,- Loss of Feedwate SO23-12-7, Loss of Forced Circulation / Loss of Offsite Powe I SO23-12-9, Functional Recover Answer D' Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2. Knowledge of EOP entry conditions and immediate action RO Group:  SRO Group:
step j RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA  SO2312-1  Att. 2 19 15 4845 Material Required for Examination
- Question Source: Bank l
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l Question #63 i
A Reactor Trip has occurred. The crew is ready to report Standard Post Trip Actions.
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Reactivity Control and Vital Auxiliaries have been reporte l
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l Which of the following states the correct sequence for the next four (4) safety functions to be  l reported?        l RCS Inventory Control RCS Pressure Control RCS Heat Removal Core Heat Removal RCS Inventory Control RCS Pressure Control Core Heat Removal RCS Heat Removal RCS Pressure Control RCS Inventory Control Core Heat Removal RCS Heat Removal RCS Pressure Control RCS Inventory Control RCS Heat Removal Core Ileat Removal Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.14 Knowledge of general guidelines for EOP flowchart use. RO Group:  SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA  SO23-12-1  At Material Required for Examination Question Source: Bank i
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- Question #64 Quench Tank level has been rising slowly,
        !
Which of the following annunciators would assist the operator in determining why this is  j occurring? -
j i A32, PZR Spray Valve Bellows Seal Failur I l A35, Reactor Vessel Seal Irakag i l B59, RCP Bleedoff Relief Valve leakin C46, RCP Intergasket Leakag l l
Answer C Exam Level B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99
        )
Tier: 2.4.46 Ability to verify that the alarms are consistent with plant RO Group:  SRO Group: I condition RO K/A SRO K/A j
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Reference Title Facility Reference Number Section Page Revisio Learning Ob l Annunciator Panol SOA SO23-15-50.A2  50A31 9 5 6569 Material Required for Examination Question Source: New        ,
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Question #65 -
Which of the following conditions will result in starting the LP Turbine Exhaust Hood Emergency Spray Water Pump following a Turbine Trip from 100% power? Condensate supply press to the LP Spray system <100 psig and the LP Spray valve is ope Depressing the " START" handswitch with a SIAS presen LP Exhaust Temperature >l60 Fon one or more exhaust hood Depressing the " OVERRIDE" handswitch with a MSIS presen Answer A Exam Level B Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) BW/A04 aa Adherence to appropriate procedures and RO Group: 2 SRO Group: 2 I operation within the limitations in the facility's  l license and amendmein RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learnity Ob Turbine Protective SO23-10-4 Device Testing 5377 Material Required for Examination Question Source: Bank
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m Question #66 Given the following:
-
  ' An unisolable ESDE has occurred outside Containment
-
The affected S/G has blown dry
-
RCS temperature is 350 F
-
Pressurizer pressure ic 1290 psia The crew should: Secure all running RCP Stabilize RCS temperature and depressurize the RC Reduce RCS temperature to establish 20 F subcoolin Stabilize RCS pressure and temperature at current value Answer B Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BW/E03 ea2.2 Adherence to appropriate procedures and  RO Group: 1 SRO Group: 1 q operation within the hmitations in the facility's license and amendment RO K/A SRO K/A I Reference Title Facility D:lerence Nurnber Section Page Revision Learning Ob ESDE  SO23-12-5  12 15 6906
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Material Required for Examination  Steam Tables Question Source: New      I l
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Question #67 -
Given the following plant conditions:
      -
A small break LOCA is in progress and SIAS has actuated
      -
All systems are operating as expected Per the stated conditions, which of the following is the basis for maintaining a secondary heat sink?
      ' To minimize boron stratification of the RCS, RCS pressure may remain so high that cooling from the injection flow alone is inadequate to remove decay hea Reflux boiling is the primary means of heat removal prior to voiding in the hot leg To provide an attemative method of RCS pressure contro Answer B Exam Level B Cognitive Level Memory  Facihty San Onofre 2 & 3  Exam Date 4/16/99 Tier: (1) BW/E04 ea Facihty conditions and selecten of RO Group: 2  SRO Group: 2 appropriate procedures during abnormal and emergency operation RO K/A ' SRO K/A Reference Title Facility Reference Number Section Page Revision  Learning Ob LOCA Bases  SO23143  At Material Required for Examination Question Source: New l
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Question #68 Given the following:
        ~
  -
The unit tripped 30 minutes ago due to a LOCA
  -
RCS temperature is 525 degrees F
  -
Pressurizer pressure is 1600 psia
  -
Power has been lost to the switchyard
  -
IE power is being supplied by the diesel generators    {
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Voids have formed in the head    j For the given con'd itions, which of the following actions will be required x promote greater cooling in the reactor vessel head? Start a CEDM Cooling Uni Vent the head to the quench tan '
        ' Start a Reactor Coolant Pum Altemately raise, then lower, RCS pressur ;
Ii Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BW/E08 ek Manipulation of controls required to obtain RO Group: 2 SRO Group: 2 desired operating results during abnormal and emorgency situation RO K/A SRO K/A a Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3  At ,
l Material Required for Examination Question Source: NRC 6/98
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Question #69 Unit 3 is at 100% steady state power. 'Ihe following data has been gathered conceming RCS leakage:
-
3.9 gpm leakage into the Quench Tank from RCGVS
-
3.1 gpm leakage into the Reactor Drain Tank from 3PV0100A
-
_ l.8 gpm leakage past all check valves from RCS to SI system
-
700 gpd E088 S/G primary to secondary leakage
-
10 gpd E089 S/G primary to secondary leakage
-
0.8 gpm leakage into Containment Sump Which of the following is true conceming the above RCS leakage per Technical Specifications? No Technical Specification entry require Identified Irakage has exceeded the limi Unidentified Leakage has exceeded the limi Primary to Secondary Leakage has exceeded the limi Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/A16 Generic 2.1.12 Ability to apply Technical Specifications RO Group:3  SRO Group:3 for a syste RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  RCS Operational Leakage 3.4 13 3.4-37 Specificatons      6574 Material Required for Examination Question Source: New l
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        } Question #70 The following conditions exist on Unit 2:
, . -.
  -
A LOCA has occurred
'
  -- SIAS, CIAS, and CCAS have actuated
  -
The STA reports that the Safety Function Status Check has failed on Inventory Control Which of the following Containment Isolation Valve (s) FAILURE IQ CLOSE would cause a flowpath to outside of containment? IIV-5388 Instniment Air to Containment Isolation Valv I HV-6223 Train A CCW Supply Isolation Valv , HV-9217 and HV-9218 RCP Bleed-off to VCT Isolation Valve .
        " HV-5434 Nitrogen Supply to SIT Isolation Valve Answer C Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) CE/E09 generic 2.4.21 Knowledge of the parameters and RO Group: 2 SRO Group: 2 logic used to assess the status of safety function RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3  AtL1 17 4 Functonal Recovery SO23-14-9  At ;
Bases        j
- - Material Required for Examination Question Source: New l
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Question #71 A Shutdown From Outside the Control Room is being performed per SO23-13-2. Plant conditions are as follows:
-
Pressurizer pressure is 2050 psia and slowly lowering
-
T-hot is 575 F and slowly lowering
-
T-cold is 555 F and stable
-
Pressurizer level (actual) is 21% and slowly lowering
-
Charging is NQIestablished
-
S/G E089 level (actual) is 58% narrow range
Which of the following statements is correct conceming Natural Circulation for the current plant  l conditions?
! Natural Circulation is not established because the plant parameters are outside the guideline Natural Circulation is established but cannot be verified until Pressurizer lxvel is greater than 40% Natural Circulation cannot be verified until manual control of the ADV's is established and T-cold is lowerin Natural Circulation is established and may be verifie Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier; (1) CE/A13 aa Facihty conditions and selection of appropriate RO Group: 1 SRO Group: 1 procedures during abnormal and emergency operation RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob shutdown From Outside SO23-13-2  Att.15 103 5 6774 the Control Room Material P.equired for Examination: Steam Tables Question Source: NRC 6/98
        .
p Question #72 i
Unit 2 has experienced a loss of Offsite Power. Following the subsequent Reactor Trip both S/G pressures are noted to be 760 psia and lowerin What action should be taken? Override and stop the turbine driven AFW pum Declare a cooldown in progress and reset the MSIS setpoint Shut the MSIV Ensure MSR isolation valves close Answer C Exam Level B Cognitive Level - Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/A11 ak Components and functions of control and RO Group: 1 SRO Group: 1 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual features,    q J
RO K/A SRO K!A Reference Title Facility Referer,ce Number Section Page Revision Learning Ob SPTA  SO23-12-1  8 15 473[
Material Required for Examination Question Source: New
r Question #73 The following conditions exist:
-
A small break Loss of Coolant Accident has occurred
-
HPSI Pumps P018 and P019 have been stopped upon meeting IIPSI Throttle /Stop Criteria
-
All three charging pumps are running
-
Pressurizer pressure is 1400 psia and steady
-
Core exit subcooled margin is 25 F
-
RCS cooldown is in progress
-
Pressurizer level is 28% and slowly lowering Which of the following is an appropriate action for these conditions? Start HPSI Pump P019, and throttle open HPSI Injection valves to restore  ,
Pressurizer leve {
        !
Start HPSI Pump P018 and P019 in preparation for reinitiating injection if
        ' Pressurizer level continues to decrease, Reduce the RCS cooldown rate to allow Pressurizer level to recove Start HPSI Pumps P018 and P019, and fully open all HPSI Injection valves until subcooled margin is restore Answer A Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) W/E02 ek Facility's heat removal systems, incl; ding RO Group: 2 SRO Group: 1 primary coolant, emergency coolant, the decay heat removal systems and relatens between    j the proper operation of these systems to the    '
operation of the facility, RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA  SO23-12-3  Att. 2 45 15 6511 Material Required for Examination Question Source: New
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Question #74 Given the following plant conditions:
-
The plant is at 100% power
-
2F1-0212, charging flow indication is reading 15 GPM
-
Radwaste Operator reports a leak in the charging header between Charging Header Isolation valve, S21208MUO91, and Containment Isolation valve
  ~ 2HV.9200 Which of the following flow paths could provide flow using a charging pump to the Reactor Coolant System? LPSI heade HPSI heade Auxiliary Spray Flow heade Charging Header Spring leaded Check Valve 2XCV921 Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) W/E04 EK Components and functions of control and RO Group: 2 SRO Group: 1 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual feature RO K/A SRO K/A Reference Title Facility Reisence Number Section Page Revision Learning Ob RCS Leak SO23-13-14  3. Material Required for Examination Question Source: New
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. Question #75 l
Given the following plant conditions:      I
  -
E088 S/G pressure is 725 psia
  -
E089 S/G pressure is 1000 psia
  -
Pressurizer pressure is 1600 psia
  -
Containment pressure is 12 psig
  -
Containment Ili Range Radiation monitors read 13 R/hr and increasing
  -
Nn operator actions has been performed i
Given these conditions, which of the following ESFAS Actuations should HQI have  l automatically initiated?      !
l l CRI SIA MSIS,      ' CSA Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) W/E 16 Eld.1 Components and functions of control and RO Group: 2 SRO Group: 2 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual feature RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Ob Annunciator Panel 57A SO23-15-57A  57A03 13 4 5375
- Material Required for Examination Question Source: New Question #76 A plant startup is in progress and the following conditions exist:
  -
The reactor is critical at 5E-5% power -
  -
  .Tave is at 545 degrees F
  -
RO inadvertently withdraws Group 5 CEAs from 35" to 55"
  -
No reactor trip occurs Which of the following describes the effect that this event will have on reactor parameters over the NEXT MINUTE? Reactor Power will rise, the response of Tave will depend upon core lif Reactor Power and Tave will both ris Reactor Power will be unaffected, Tave will ris ' Reactor Power will rise, Tave will be unaffecte Answer D Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 001 a1.06 Reactor Power  RO Group: 1 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 793l Material Required for Examination
~ Question Source: 'New I
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Question #77 Given the following:
-
  - A Loss of Coolant Accident has occurred at Unit 2  )
-
SO23-12-3 is being implemented    j
-
The ACO has been directed to STOP all Reactor Coolant Pumps (RCPs)  1
-
RCP 2P001 fails to stop when the STOP pushbutton is depressed Which of the following is the appropriate action for stopping 2P00l?    I i Dispatch an operator to open the breaker to 2P001 locally, at the bu Dispatch an operator to verify locally that DC power is aligned to 2P001 breake Deenergize 2A01 by opening the supply breaker from the Reserve Auxiliary Transforme Deenergize Reserve Auxiliary Transformer 2XR3 by opening the breakers from the switchyar Answer C Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 003 k2.01 RCPS  RO Group: 1  SRO Group:
RO K/A SRO K/A Reference Title  Facility Reference Number Sectio Page Revision Learning Ob n Conducts of Operations SO23-046  6.1 gg Transferring 6.9 KV Buses SO23-6-1 Material Required for Examination Question Source: NRC 6/98
        . . . .
Question #78 The following conditions are present:
-
Channel A Irw DNBR trip is bypassed
-
RCP P001 flow input to CPC Channel B has failed low Which of the following conditions will result in a reactor trip? loop I hot leg temperature input to Channel B CPC fails hig Imop i hot leg temperature input to Channel A CPC fails lo Pressurizer pressure input to Channel B CPC fails hig Pressurizer pressure input to Channel C CPC fails lo l Answer D Exam Level R Cognitive Level Comprehonsion Facility San Onofre 2 & 3 Exam Date 4/16/99 3/13/99 Tier:(2) 012 RPS K4.02 Automatic Reactor Trip when RPS RO Group: 2 SRO Group:
setpoints are exceeded for each RPS function; basis for each RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Obj. -
Plant Protection D8D-SO23-710  2, System 4936 Material Required for Examination Question Source: New
Question #79 The following sequence of events occurs:
-
A LOCA has occur ed
-
  . A Safety injection Actuation Signal (SIAS) has started all required ECCS pumps
-
he diesels are running unloaded
-
  : 5 minutes after the SIAS, offsite power is lost Which of the following describes the expected response of the ECCS pumps subsequent to the less of Offsite Power?-
I All required ECCS pumps restart immediately after their train's EDG output breaker close The SIAS will need to be manually actuated to allow all the required ECCS pumps to automatically star '
All required ECCS pumps will restart in time delayed sequenc ,
I The SIAS will have to be reset and the required ECCS pumps started by operator  I actio i Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 013 kl.01 -
Initiation si0nals for ESF circuit logic RO Group: 1 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Elementary Diagram 30643    7 10397 Material Required for Examination Question Source: New
Question #80 Which of the following statements accurately describes the Power Trip Test Interlock (PTTI) in the Excore Safety Channel System? Simulates a 200% linear power ou.put causing a PPS high linear power trip in the affected channe ' Actuates the LO DNBR and HI LPD CPC trips for the affected channe I Prevents more than one channel of log power being simulated greater than 1.0E-4% power during testin Gives permissive to manually bypass the LO DNBR and HI LPD CPC trips when reactor power lowers to less than 1.0E-4%.
Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 015 k3.01 RPS  RO Group: 1 SRO Group:
RO K/A SRO K/A Explanationof Answer Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Protective SO23-3-2.12  0. System Operation 7175 Material Required for Examination
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Question #81 Which of the following is an indication that Natural Circulation flow may be lost during EOI implementation? RCS pressure greater than Saturation pressure of the Steam Generato T-hot rising with constant T-col Delta T (Core Exit Thermocouple minus T-hot) equal to 10 Delta-T (T-hot minus T-cold) of 28 Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 017 a3.01 Indications of normal, natural, and interrupted RO Group: 1 SRO Group:
circulationof RC RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA  SO23-12-1  6 15 2536 Material Required for Examination Question Source: Bank i
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Question #82 Given the following plant conditions:
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Unit 2 is at 100% power when an inadvertent SIAS occurs
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Reserve Auxiliary Transformer 2XR1 relays on sudden pressure
  -
Diesel Generator 20002 started and is loaded on bus 2A04
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Diesel Generator 2G003 started and tripped 15 seconds later Which of the following is performing the containment cooling function? Containment Normal and Emergency Cooler Containment Normal and Train "A" Emergency Cooler Both Train "A" and "B" Containment Emergency Cooler t- Only Train "A" Containment Emergency Cooler Answer D Exam Level R  Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 022 K2.01 containment cooling system cooling fans  RO Group: 1 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number  Section Page Revision Learnity Ob Elementary Diagrams 31248,31249,31250,    14,15,14,15,7 31251,31269      7367 Material Required for Examination Question Source: New l
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Question #83 Given the following plant conditions:
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Unit 2 operating at 100% power
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CCW pump 2P-025 in service and aligned to Train B for single train operation
- A ground fault causes a loss of 4KV Bus 2A06 What operator actions are required to restore CCW to the RCPs? Ensure start of CCW pump 2P-024 and SWC pump 2P-30 Ensure start of CCW pump 2P-026 and SWC pump 2P-11 Ensure start of CCW pump 2P-024 and transfer Non-critical Loo Ensure start of CCW pump 2P-026 and transfer Non-critical loo Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/18/99 Tier: (1) 026 aa2.02 The cause of possible CCW loss RO Group: 1 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Loss of CCW/SWC SO23-13-7 Material Required for Examination Question Source: New
Question #84'
Given the following:
- Unit 2 is in MODE The core is being off loaded to the SF The OPERABLE Containment Purge valve, ilV-9949, is determined to be stuck in the open positio What action is required per Technical Specifications LCO 3.9.3, Containment Penetrations? Immediately place containment mini-purge in operatio Isolate the affected purge flowpath within 4 hour Decnergize the affected valve within I hou I
D. Immediately suspend core alterations and movement of irradiated fue Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16,99 Tier:(2) 028 Generic 2.1.12 Ability to apply Technical Specifications RO Group: 3 SRO Group:
to a system RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  Containment Penetrations LCO 3. .9-4 Specifications 7375 Material Required for Examination Question' Source: New
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Question #85 Which of the following will cause an actuation that closes the containment main purge isolation valves? High Containment Pressur High Containment Temperatur High Containment Radiatio Low Pressurizer Pressur Answer C Exam Level R Cognitive Level Memory  Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (2) 029 K103 Engineered Safeguards  RO Group: 2 SRO Group:
RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Containment Airborne Radiation SO23-3-2.24.11 Monitor System Operation
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Question #86 Which of the following is the I F AST preferred source of makeup to the Spent Fuel Pool? Primary Makeup Water (PMW).
i Boric Acid Makeup Tanks (BAMU). i
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        ! Refueling Water Storage Tanks (RWST).    {
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        ; Nuclear Service Water (NSW). l Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier: ( 2) 033 SFPCS A2.01 Inadequate SDM RO Group: 2 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Spent Fuel Purification SO23-3-2.1 .1 3 6 Cross-tie Operation 4582 Material Required for Examination Question Source: New l
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Question #87 Given the following plant conditions on Unit 3:
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SG Generator E-088 has a known Primary to Secondary leak of 0.3 gpm
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SG Generator E-089 has a known Primary to Secondary leak of 0.4 gpm Which of the following actions is required by Technical Specifications? No action require Commence a controlled plant shutdow ' Commence a rapid plant shutdow Manually trip the reactor and perform SPTA ;
l Answer A Exam Level R CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 037 aa220 Tech Spec limits for RCS leakag RO Group: 2 SRO Group:
RO K/A 32  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical RCS Operational Leakage 3.4.13 3.4-37  g3g Specifications Material Required for Examination Question Source: New
- Question #88 Given the following:
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Unit 3 is at 5% power
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Temperature is being maintained by the Steam Bypass Control System
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The Isothermal Temperature Coefficient (ITC) is POSITIVE  .
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A total loss of condenser vacuum occurs    j
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All systems are in' automatic    j
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Which statement correctly describes Reactor response? Positive reactivity will be added, reactor will eventually trip on VOP J Negative reactivity will be added, reactor power will stabilize above the point of adding hea ~ Negative reactivity will be added, reactor power will stabilize below the ' point of
  - adding hea ' Positive reactivity will be added, reactor power will increase until the Main Steam Safety Valves lif j Answer D Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 039 k5.08 Eflect of steam removal on reactivit RO Group: 2 SRO Group:
RO K/A SRO KIA Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 4354 Material Required for Examination Question Source: Bank
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- Question #S9 he reactor trips from 100% power. He operators verify that the reactor is tripped and immediately note that the turbine has not tripped and the g:nerator breakers remain close Which of the following statements describes potential consequences of this event? A loss of subcooling, resulting in the need to trip all RCP An uncontrolled cooldown of the RCS, resulting in less shutdown margi ;
I A decrease in RCS inventory, resulting in core uncover ;
1 An increase in RCS pressure, possibly resulting in the Pressurizer safety valves liftin Answer B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 045 a1.05 Expected response of primary plant . RO Group: 3 SRO Group:
parameters (temperature and pressure)
following T/G tri l l
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Reference Title Facility Reference Number Secton Page Revision Learning Ob i SPTA Bases SO23-14-1  At Material Required for Examination Question Source: New
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l Question #90 I
l Given the following:
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2RT-7870 Condenser Air Ejector Radiation Monitor setpoint is 1.05E-0
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Secondary Radiation HI alarm actuates
:- 5 minutes later 2RT-7870 indicates 2.20E-0 Which of the following actions is required for the above conditions? Manually trip the reactor and carry out the SPTAs.
l Commence a controlled plant shutdown and insert rods below 5% reactor power.
1 Commence a rapid tjant shutdown and trip the unit at 35% reactor powe Remain at power, sample all SG's and perform a leakrate calculation.
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Answer C Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 055 K1.06 FRM system  RO Group: 2 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Coolant Leak SO23-13-14  3.4. Material Required for Examination Question Source: NRC 6/98 l
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_ Question #91        ,
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Given the following plant conditions-
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Unit is initially operating at 100% power
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Condensate Pumps P050, P051 and P052 are initially running
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Condensate Pump P050 trips Which of the following automatic actions should occur?
        -1 ' Heater Drain Pumps will trip on low flDT level l
l Condensate Pump P053 will auto star Recirculation valve for Condensate Pump P050 will auto clos . Main Feedwater Pumps will trip on low suction pressur Answer - B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 056 a2.04 Loss of condensate pumps RO Group: 1 SRO Group:
RO K/A SRO K/A Referonce Title Facility Reference Number Section Page Revision Learning Ob Condensate Pump SO23-2-2  Att. 2 23 9 Operation 5364
: Material Required for Examination
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I Question #92 Given the following plant conditions:      )
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Unit 2 is operating at 100%. j
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Vital Bus Inverter 2Y002 has just failed, deenergizing vital bus 2YO2 Which of the following is correct concerning Auxiliary Feedwater Flow to the steam generators?  : Only one S/G is being fed.
i- No AFW components change stat Both S/Gs are being fe , P-140 running, neither S/G is being fe Answer . A Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 4/16/99 Tier: (1) 058 aa2.03 DC loads lost; impact on abihty to operate and ROGroup: 2  SRO Group:
monitor plant system RO K/A SRO K/A ReferenceTitle -  Facihty Reference Number Section Page Revision Learning Ob RPS FAILURE / LOSS OF VITAL SO12-1318  ATT 2 17 of 24 2 BUS INVERTER 13644 Material Required for Examination Question Source: New
I Question #93 A loss of all Feedwater has occurred. Upon restoring Feedwater, the operator opens the MFW Regulator Bypass Valves to 20% for 5 minutes.
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Why are these actions necessary?
' Prevents rapid cooldown of the RC Allows equalizing temperature across the S/ Minimize the possibility of a water hammer event to the tubeshee Ensures S/G feedring is slowly refille Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 059 a2.04 Feeding a dry S/G  RO Group: 1 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Lossof Feedwatcr SO23-14-6  Att. I 14 4 4734 Bases Material Required for Examination Question Source: Bank
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Question #94 An Emergency Diesel Generator (D/G) monthly surveillance test is being performed. D/G load is indicating 4.7 MW Which of the following is correct? D/G load is be!aw the allowable range of the acceptance criteria, and above the minimum limit for dieselloadin D/G load is within the allowable range of the acceptance criteri D/G load is above the allowable range of the acceptance criteria, and below the maximum limit for dieselloadin D/G load is above the maximum limit for diesel loadin Answer B Exam Level R  Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 062 A1.01  Significanceof D/Gloadlimits RO Group: 2 SRO Group:
RO K/A SRO K/A Reference Title  Facihty Reference Number Section Page Revision Leaming Ob Diesel Generator  SO23-3-323  At Monthly Test -      6697 s Material Required for Examination Question Source: New
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Question #95 The Control Room was evacuated 15 minutes ago due to dense smoke. A shutdown from outside the cc u. I room is in progres Which of the following lists the PREFERRED components to be used to establish auxiliary feedwater to steam generator E089?      1 (Assume all AFW components are available)    l )IIV-4763 P141 discharge bypass valve 2) HV-4731 AFW isolation valve    ;
3) P141 motor driven AFW pump ) HV-4706 Pl40 discharge to E089 2) HV-4731 AFW isolation valve 3) Pl40 steam driven AFW pump ) HV-4713 P141 discharge valve 2) HV 4731 AFW isolation valve    l I
3) Pl41 motor driven AFW pump ) HV-4706 P140 discharge to E089 2) HV-4715 AFW isolation valve 3) Pl40 steam driven AFW pump Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 068 aa1.03 S/G level  RO Group: 1 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Shutdown from Outside SO23-13-2  Att. 6 47 5  9444 the Control Room Material Required for Examination Question Source: New
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l Question #96        )
i Which of the following would be the PREFERRED discharge path per SO23-8-7, Liquid  i Radioactive Waste Release Operations, when performing a radioactive liquid effluent release?
. Unit 2 with Circulating Water pumps P115 and P117, and Saltwater Cooling pump 2P307 mnnin Unit 2 with Circulating Water pumps P115, P116 and Pl 18 runnin Unit 3 with Circulating Water pumps P115, Pl 16, and Pl 17 runnin j Unit 3 with Circulating Water pumps P116 and Pl 18, and Saltwater Cooling  ,
        '
pump 3P112 runnin Answer C Exam Level R Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date.4/16,99 Tier: (2) 088 Generic 2.1.32 Ability to explain and apply all system RO Group: 1  SRO Group:
limits and precautions RO K/A SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Liquid Radioactive Waste Release SO23-8-7  Att. 9 127 10 Operations 9066 Material Required for Examination Question Source: New        k
l Question #97 Which of the following conditions represents a violation of Containment Systems as described in Technical Specifications? While at 100% power, a mechanic blocks open the outer containment airlock door for 2 hours to perform maintenance activities on the INOPERABLE inner containment doo While performing OPERABILITY tests on the redundant containment imp i Hot leg Sample valves (HV-0508 and HV-0509) at 100% power, one of the two valves (HV-0508) fails to completely clos While at 100% power, the nitrogen supply isolation valve to the Safety Injection
  . Tanks isolation valve (HV-5434) fails its required stroke tim While at 1(X)% power, the outer containment airlock door fails its leak rate test  (
and has to be opened to facilitate repairs that will take 2 hour I Answer A Exam Level R Co0nitivo Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 069 aat.01 Isolation valves, dampers and RO Group: 1 SRO Group:
electropneumatic device RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  Containment Air Locks 3. .6-3 Specifications 6235 Material Required for Examination Question Source: New I
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Question #98 What is the Instrument Air header pressure at which the Respiratory and Service Air System (RSAS) backup supply will automatically begin to supply the instrument air header? psi psi psi ! - 100 psi Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 079 A4.01 Cross-tie valves with IA RO Group: 2 SRO Group:
RO K/A SRO K/A Reference Title Facility Reference Numb Section Page Revision Learning Ob Instrument Air Gystem SO23-1-1  6.12 14 12 Operation 6531 Material Required for Examination Question Source: New
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i I-Question #99 The FIRST action that the Operations Izader performs after an Alert has been declared is: Station someone on the Ivory Phone.
I Evacuate personnel from Hazardous area Activate the Emergency Response Data Syste Perform siren and PA coordinatio Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 j      4/16/99 Tier: 2.4.29 Knowledgeof theemergencypla RO Group:  SRO Group:
RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Operations Leader SO23-Vill-30  6.1.1.1 4 3 Duties 857 Material Required for Examination Question Source: Bank l
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Question #100 A Main Steam Line Break inside Containment has occurre Assuming pmper operation of ESFAS Systems and equipment, what is the maximum expected Containment pressure by design? Approximately 3'7 psi Approximately 47 psi Approximately 57 psi Approximately 67 psi Answer C Exam Level R Cognitive Level Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 l I
Tier: (1) CE/E05 ek Normal, abnormal and emergency RO Group: 1 SRO Group: 1 d
operating procedures associated
        '
with Excess Steam Deman RO K/A SRO K/A
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Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Containment  B3. B3. Specificatens      7530 Material Required for Examination Question Source: NRC 6/98
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Question #101 After securing a Reactor Coolant Pump, what positive indication is available in the Control Room of the RCP being completely stopped? RCS flow low alan Green stop light o Zero (0) amps indicate . Zero speed light o Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 I
Tier: (1) 011 EA1.03 Securing of RCPs  RO Group:  SRO Group: 1
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RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Coolant Pump SO23-3- . Operation 5389 Material Required for Examination      )
Question Source: Bank      l i
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i Question #102 Plant conditions are as follows:
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Unit 2 at 100% power
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Channel A 2PI-0101-1 Narrow Range Pressure has failed high  j
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Channel B 2PI-0102-2 Wide Range Pressure has failed low
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All actions of SO23-13-18, Reactor Protection System Failure, have been completed      )
Which of the following correctly states the existing coincidence logic to trip the reactor on high Pressurizer Pressure?      l l
        , I out of out of I out of l 1 out of '
l Answer C Exam Level -S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99
        '
Tier: (2) 012 K4.02 Automatic reactor trip wt'en RPS setpoints are RO Group:  SRO Cioup: 2 exceeded for each RPS function; basis for eac RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  RPS Instrumentation 83. B3.3-3 Specifications 7297 Material Required for Examination Question Source: New i
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E Question #103 Given the following information on Unit 3:
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Reactor power - 100%
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92 day ESFAS logic matrix relay testing is in progress
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Control Room airbome radiation monitor RE-7824 is in BYPASS for maintenance
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During the performance of the logic matrix test, the trip matrix being tested was  -
prematurely de-energized, resulting in Trains "A" & "B" SIAS and CCAS  ;
actuation      I Which of the following is'the expected systems response to the above conditions?
1 CRIS actuation is blocke l
l CRIS occurs on Train "A" onl l CRIS occurs on Train "B" onl CRIS occurs on both Train Answer D Exam Level S Cognitive Level - Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 013 kl.01 initiation signals for ESF circuit logi RO Group:  SRO Group: 1 RO K/A  SRO K/A Reference Title  Facility Reference Number Section Page Revision Learning Ob Control Room Airborne Process SO23-3-2-2 .6 4 5 Radiation Monitoring System Operation 6999 Material Required for Examination Question Source: NRC 11/98
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Question #104 What is the basis for the Shutdown Margin requirement of 3% Delta K/K with T-ave less than 200 F?
i Removal of the CEAs during refuelin i l Reactivity effect from further cooldown to Mode A potential dih' tion c cen Allow for ern rs in e. .:cisment of the new fuel loa Answer C Exam Level S CognitiveLevel Memory  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 Generic 2.1.12 Ability to apply Technical RO Group:  SRO Group: 1 Specifications for a system RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Shutdown Margin  B3. B3.1-7  i Specifications 6957-
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I Material Required for Examination      j Question Source: Bank i
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Question #105 l
Which of the following valves would be throttled open by the operator to increase the RCS cooldown rate with Shutdown Cooling in service?
l Shutdown Cooling Heat Exchanger inlet valv Shutdown Cooling Heat Exchanger outlet valv )
l l Shutdown Cooling Heat Exchanger CCW outlet valv Shutdown Cooling Heat Exchanger CCW inlet vah I Answer B Exam Level S Cognitive Level Memory Facility San Onoire 2 & 3 Exam Date 4/10/99 Tier: (1) 025 AA1.01 RCS/RHRS cooklown rat RO Group:  SRO Group: 2 RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SDC System Operation SO23-3- .2.8.2 8 15 8036 Material Required for Examination Question Source: Bank L
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; Question #106
    .
The plant has just tripped from 50% power operation, the SPTAs are being carried out and plant conditions are as follows:
  -
Pressurizer pressure is 650 psia
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Containment average temperature is 251 F
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Both S/G levels 40% NR
  -
  . Both S/G pressures 800 psia Which ESFAS signal combinations should have automatically actuated?    ;
        ;
, EFAS, RAS, SIA CSAS, SIAS, CIA SIAS, CIAS, EFA SIAS, MSIS, CSA '
Answer B Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier:(2) 026 A1.01 Containment pressure  RO Group:  SRO Group: 1 -l A
RO K/A  SRO K/A 42 Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  ESFAS Instrumentation 3. .3-26 Specifications 7303 Material Required for Examination Question Source: New
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I Question #107-Both trains of CCW/SWC are in operatio What is the reason for aligning the Ixtdown Heat Exchanger to the Critical loop that is supplying the Non-Critical Loop? Reduces the potential for RCP seal deterioration by minimizing the temperature differential in the Non-Critical 12)o Maintains heat load requirements distributed evenly between the loop I Sets loop flows to match operating pressures of the loops to minimize cross train leakag Ensures that CCW process radiation monitor is aligned to detect any Letdown Heat Exchanger tube leakag Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 026 AA2.02 The cause of possible CCW los RO Group:  SRO Group: 1 RO K/A  SRO K/A l I
Reference Title Facility Reference Number Section Page Revision Learning Ob I CCW System SO23-2-17  Att. 7 56 12 Operation 6257 l
Material Required for Examination Question Source: NRC 11/98 I


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San Onofre Nuclear Generating Station -2-    !
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This letter contains information collections that are subject to t' e oapenvork Reduction Act of 1995(44 U.S.C. 3501 et seq.). These information collections v ro approved by the Office of Management and Budget, approval number 3150-0101, which apires on April 30,2000. l The public reporting burden for this collection of information iu a stiraated 'o average 500 hours per response, including the time for reviewing instructions, gttherilj ar.d maintaining the data needed, writing the examinations, and completing and reviewinl1 ti e collection of in'ormation.
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Send comments on any aspect of this collection of information, oc i hg suggestions for reducing the burden, to the information and Records Managemen' Branch E-6 F33), U.S.
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Question #108      l


Nuclear Regulatory Commission, Washington, DC 20555-0001, or isy !nte'ne; ?lectronic mail at BJS1 @NRC. GOV; and to the Desk Officer, Office of Information and Regulatory Affairs,  !
        )
NEOB-10202, (3150-0101), Office of Management and Budget, Washington, DC 20503.
, The following conditions exist:
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A large break LOCA occurred on Unit 216 hours ago
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SO23-12-3, "Ioss of Coolant Accident"is being implemente Hydrogen Monitors initially indicated 0.7%.
-
Following calibration Hydrogen concentration indicates 2.6%.
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All ESFAS equipment is available and functioning normall Which of the following actions is required to satisfy the Containment Combustible Gas Control safety function of SO23-12-37 Ensure both Hydrogen Recombiners energized and Containment Spray in servic I Ensure the Hydrogen Purge System in service and all Containment Dome Air Circulating Fans operatin Ensure both Hydrogen Recombiners energized and all Containment Dome ' Air Circulating Fans operatin Ensure both Hydrogen Rec'ombiners energized and Hydrogen Purge System in service.-
Answer C Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Eram Date 4/16/99 Tier:(2) 028 Generic 2.1.20 Ability to execute procedure fys RO Group:  SRO Group: 2 RO K/A  SRO K/A Reference Title Facuity Reference Number Section Page Revision Learning Ob LOCA  SO2312-3  At Material Required for Examination Question Source: New
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The NRC may not conduct or sponsor, and a person is not required to respond to, a collection I of information unless it displays a currently valid OMB control number.
Question #109 Which of the following radiation monitors will cause the initiation of the Containment Purge Isolation Signal (CPIS)? RE-7828 Containment Purge Stack Radiation Monito RE-7820 Containment High Range Radiation Monito RE-7808 Plant Vent Stack Radiation Monito RE-7804 Containment Airborne Radiation Monito Answer D Exam Level S Cognitive Lovel Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 4 i Tier: (2) 029 K1.03 Engineered safeguards RO Group:  SRO Group: 2 RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Containment Purge and SO23-142  Att.13 73 22 Recirculation Filtration 7550 System Material Required for Examination Question Source: Bank
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l Thank you for your cooperation in this matter. Mr. Rauch has been advised of the policies and guidelines referenced in this letter. If you have any questions regarding the i 1C's examination
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, procedures and guidelines, please contact me.
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Question #110 i
Given the following:
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The plant is in MODE 3
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A reactor startup is in progress
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Reactor power is at 2E-7%
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CEAs are being withdrawn      I
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Subsequently BOTH startup channels fail to zero    l Which of the following describes the action (s) to be taken?    l l Continue approach to criticality using safety channel power indicatio I i Immediately trip the Reacto Immediately stop all positive reactivity additions.


Sincerely, cLM*
1 Commence a reactor shutdow I Answer C Exam Level S CognitiveLevel Comprehension  Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier;(1) 032 Generic 2.1.12 Ability to apply Technical Specifications to RO Group:  SRO Group: 2 l a syste l l        l
John L. Pellet, Chief
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RO K/A  SRO K/A ]
Operations Branch   l Division of Reactor Safety Docket Nos.: 50-361;50-362
Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  Boron Dilution Alarm 3.3.111 3.3-111 1 Specifications
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        '3182 i
License Nos.: NPF-10; NPF-15 cc:
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l Material Required for Examination Question Source: New
Chairman, Board of Supervisors County of San Diego
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Question #111 The following conditions exist on Unit 3:
   -
Reactor power is 100%
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  -
At 1200 a known tube leak of 0.05 gpm exists in E089    j
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  -
At 1300 the leak increases to 0.075 gpm
  -
At 1400 the leak increases to 0.090 gpm
  -
At 1500 the leak increases to 0.12 gpm
  -
Secondary radiation monitor response confirms increases What action, if any, is required as a result of the increasing S/G tube leak as directed by SO23-13-14 " Reactor Coolant Leak"? Operation of the unit can continu ]
I The reactor should be tripped immediatel A rapid shutdown must be initiate A controlled shutdown must be completed within 6 hour Answer D Exam Level S Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4/16FJ9 4 i
Tier: (1) 037 AA2.05 Past history of leakage with current problem RO Group:  SRO Group: 2 RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob )
Raactor Coolant Leak SO23-13-14  3.4. Material Required for Examination Question Source: NRC 11/98 L
 
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i Question #112 l
During coastdown prior to a refueling ontage, system frequency increases to 60.5 hertz. How  l will the RCS respond? Temperature increases, pressure increase l Temperature increases, pressure decmase Temperature decreases, pressure decrease Temperature decreases, pressure increase Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/93 Tier (2) 039 K5.08 Effect of steam removal on reactivity RO Group:  SRO Group: 2 RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 4354
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Material Required for Examination      ;
1600 Pacific Highway, Room 335    l San Diego, California 92101 l
- Questica Source: New I
  % s R. Watts, Esq.
 
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Question #113 Unit 2 is operating at full power when a loss of 125VDC Bus 2D5 occur What effect does this have on the Unit 2 Turbine / Generator?
        )) A main generator automatic trip will occu The turbine will trip on overspee The turbine emergency oil pump motors will lose powe The Turbine Stop and Govemor valves will go close Answer D Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 058 AA2.03 DC loads lost; impact on abihty to operate and RO Group:  SRO Group: 2 monitor plant system RO K/A  SRO K/A .
Reference Title Facihty Reference Number Section Page Revision Learning Ob Operation of 125 VDC SO23-6-15  Att.13 71 13 glgg Systems Material Required for Examination Question Source: NRC i 1/98
        '
 
y Question #114      j
 
l Which of the following is the correct response if an Emergency Diesel Generator (EDG) is paralleled to the grid and both the governor and voltage control pushbuttons are taken to  i
" Raise"? EDG KW incieases and EDG speed increase l l EDG reactive load increases and EDG KW increase I EDG frequency increases and EDG reactive load increase l EDG speed increases and EDG frequency increase Answer B Exam Level B Cognitive Level Comprehension racility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 062 A1.01 Significsnce of D/G load timits RO Group: 2 SRO Group: 2 RO K/A SRO K/A ReferenceTitle . Facility deference Number Section Page Revision Learning Ob Diesel Generator SO23-3-3.23  At Monthly Test 7152 Material Required for Examination Question Source. New -
 
rr-Question #115 The Control Room has been evacuated due to a toxic chemical hazard inside the Control Room envelope. Shutdown fmm outside of the Control Room, SO23-13-2 is in progress:
At the EPPM L-411:
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SG E-088 Wide Range level, LI-l 1% indicates 55%
- RCS Tcold, indicates 530 F
- RCS Thot, indicates 548 F
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S/G pressure indicates 900 psia Determine the actual water level in steam generator E-08 %. %.      l %.
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Answer C Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 068 1.03 S/G level  RO Group:  SRO Group: 1 RO K/A  SRO K/A Reference Title Facliity Reference Number Section Page Revision Learning Ob Shutdown from Outside SO23-13-2  Att. 4 35 5 the Control Room 63025 Material Required for Examination SO23-13-2, Attachment 4 Question Source: Bank
 
~ Question #116
'Ihe following conditions exist during a Unit 2 refueling:
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  - Core offload is in progress
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Steam Generator E089 is being sludge lanced
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An operator reports that Main Steam Relief Header Drain Valve, S21301MU394, on S/G E089 is removed      j Which of the following actions is required? Restore Containment Integrity within one hou Suspend Core Alteration !
i i Initiate Manual Containment Purge Isolation Signa Verify containment leakage is within specification .
Answer B Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 069 aa1.01 Isolation valves, dampers and RO Group:  SRO Group: 1 electropneumatic devices RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical  Containment Penetrations 3. .9-4  777g Specifications Material Required for Examination Question Source: Bank
 
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Question #117 Given the following plant conditions:
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Unit 2 is at 20% power
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Tc is currently at 534 F Which of the following does the Technical Specifications require?    . Perform SR 3.4. Enter LCO 3.4.1 Condition Enter LCO 3.4.2 Condition Perform SR 3.4. I Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.33 Ability to recognize indications for system operating parameters RO Group:  SRO Group:
which are entry level conditions for Technical Specification RO K/A  SRO K/A Reference Title Facility Reference Number Section lPage Revision Learning Ob l Technical  RCS Minimum Temperature 3.4.2 ' 3.4-4  g3g  '
Specifications for Criticality i
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Material Required for Examination: T.S.s 3.4.1,3.4.2,3,4.3 (Bases not required)
Question Sourec Bank        !
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<etodruff, Spradlin & Smart 7T S. Parker St. Suite 7000 Ora ige, Califomia 92868-4720    /
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I l-Question #118 Given the following plant conditions:
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The' Unit is in MODE The Spent Fuel Pool Boron Concentration is 1825 pp Actions are being taken to restore boron concentratio Which of the following states an additional required action for this condition? . Direct HP to perform a radiation surve Install a local Criticality Accident Radiation Monito Initiate a manual Fuel Handling Isolation Signa Suspend movement of fuel in the Spent Fuel Pcc Answer D Exam Level S Cognitive Level Memory    Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.2.31 Knc uledge of SRO fuel handling responsibilities    RO Group:  SRO Group:
RO K/A  SRO K/A Reference Title Facility Reference Number Section  Page  Revision Learning Ob Technical  Fuel Storage Pool Boron 3.7.17  3.7 30 Specifications Concentration      7949 Material Required for Examination        l Question Source: Bank
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. Question #119 A Gaseous Effluent Release Permit requires a Weather Evaluation prior to the release. The following meteorological conditions exist:
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Wind direction is 210 degrees    l
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Temperature difference between 10 and 40 meters is minus 0.26 C  i
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X/Q value is <4.8E-6      i Determine the MINIMUM wind speed which would allow the release to be commence j mp mp .
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Answer B Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16FJ9 i
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Tier: 2.3.11 Ability to control radiathn releases  RO Group-  SRO Group:
        )
RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob l i
Radwaste Gas SO23-8-15  Att. 4 35 11 Discharge 6268 Material Required for Examination: SO23-8-15 Attachment 4 Question Source: NRC 6/98 I
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. Question #120 Unit 2 is in MODE 5 on Shutdown Coolin While maintenance was being performed on LTOP isolation valve 2HV9339, the valve packing faile Pressurizer level is lowering with the only available charging pump runnin The Loss of SDC AOI has been entered and a HPSI pump has been started to restore leve HPSI pump flow required to maintain Pressurizer levelis 150 gp Which of the following is the correct Emergency Event Classification? None appl B3- G I-l . B2- .;
l Answer C Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier: 2.4.29 Knowledge of the emergency plan  RO Group:  SRO Group:
RO K/A  SRO K/A ReferenceTitto Facility Reference Number Section Page Revison Learning Ob EPIP  SO123-VilM  Att. 2 50 11
      }7479 Material Required for Examination: SO123 Vill-1 Attachment 2 Question Source: flew .
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Question #121
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Unit 2 reactor has tripped. The Control Room is being evacuated due to dense smok Which of the following correctly identifies the order in which the "IMMEDIATE ACTIONS" for Shutdown From Outside the Control Room AOI, SO23-13-2 are to be completed?    j l.) Manually initiate MSIS 2.) Stop all RCPs 3.) Select manual and stop all Charging Pumps .) Select manual and stop all Charging Pumps l  2.) Manually initiate MSIS      .
l  3.) Stop all RCPs      l l.) Manually initiate MSIS 2.) Select manual and stop all Charging Pumps
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3.) Stop all RCPs l l.) Stop all RCPs      1 2.) Manually initiate MSIS      !
3.) Select manual and stop all Charging Pumps Answer C f Exam Level SCognitive Lovel Memory  Facility San Onofre 2 & 3 Exam Date'4/16/P9 Tier: 2.4.49 Ability to perform without reference to procedures those . RO Group:  SRO Group:
actions that require immediate operahon of system
  . components and controls RO K/A  SRO K/A _
Reference Title Facl6ty Roterence Number Section Page Revision Leaming Ob Shutdown from Outskie SO23-13-2 the Control Room Material Required for Examination Question Source: Bank -
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s Sherwin Harris, Resource Project Manager Public Utilities Department      l City of Riverside 3900 Main Street Riverside, California 92522
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l Question #122          ,


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Given the following:
    ,_ _ i San Onofre Nuclear Generating Station -3-R. W. Krieger, Vice President Southem California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, California 92674-0128
  -
  . Stephen A. Woods, Senior Health Physicist Division of Drinking Water and Environmental Management Nuclear Emergency Response Program Califomia Department of Health Services P.O. Box 942732, M/S 396 Sacramento, California 94334-7320 Mr. Michael R. Olson Sr. Energy Administrator-
A reactor trip has occurred from 100% power
. San Diego Gas & Electric Company P. O. Box 1831
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All systems have responded normally
San Diego, Califomia 92112-4150 Mr. Steve Hsu Radiological Health Branch State Department of Health Services P.O. Box 942732 Sacramento, California 94234
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No operator actions have occurred
Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672
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The following conditions are observed:
Mr. Truman Burns \Mr Robert Kinosian Califomia Public Utilities Commission 505 Van Ness, Rm. 4102 San Francisco, California 94102
  -- RCS temperature is 545 F and stable
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  -
Both S/G !cvels are 35% NR and rising
  -
Both S/G pressures are 1000 psia and stable Given these conditions, which of the following statements correctly describes the feedwater configuration to the S/Gs?
  . MFW only is supplying feedwater to both S/G AFW only is supplying feedwater to both S/G MFW and AFW are both supplying feedwater to both S/Gs, No feedwater is being supplied to the S/Gs, AFW will have to be manually aligned to supply feedwate Answer A . Exam Level S ' CogndiveLevel Application    Facihty San Onofre 2 a 3 Exam Date 4/16/99 Tier:(1) CE/E02 ek22 Facility's heat tornoval systems, including  RO Group:  SRO Group: 2 primary coolant, omergency coolant, the decay heat removal systems and retarons between
  .,   the proper operation of these systems to the
{ ,'g  operation of the tacility
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, ,       RO K/A  SRO K/A 4.0
 
Reference Title Facility Reference Number Section  Page  Revision Leaming Obi,
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;. Reactor Trip Recovery SO2:k12-2    5  13 6509
[4v Material Required for Examination Question Source: Bank
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r Question #123
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An Excess Steam Demand Event is in progress. The affected Steam Generator has just boiled dr Which of the following actions must be taken to ensure RCS pressure control is satisfied? Ensure Emergency Feedwater Actuation Signal is actuate Establish maximum Safety Injection Flo Initiate Safety Injection HPSI Throttle /Sto Ensure letdown system in servic I Answer C Exam Level S CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 I Tier:(1) CE/EOS ok12 Normal, abnormal and emergency operating RO Group:  SRO Group: 1 procedures associated with Excess Steam
        '
Deman RO K/A  SRO K/A eference Title Facility Reference Number Section Page Revision Learning Ob ESDE Bases  SO23-14-5 At Material Required for Examination Question Source: New
 
{        l Question #124 Which of the following is HQI a direct advantage of forced circulation during recovery from an Excess Steam Demand Event (ESDE)? Instrument response to operator action Reactor vessel head coolin Pressurizer pressure contro Pressurizer level contro Answer D Exam Level Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/E05 ek Normal, abnormal and emergency operating RO Group:  SRO Group: 1 procedures associated with Excess Steam Deman RO K/A  SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob ESDE Bases SO23-14-5  At Material Required for Examination Question Source: Bank i
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Question #125 Given the following plant conditions:
- Per SO23-12-1, SPTAs, a LOCA has been identified
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Pressurizer pressure is 1250 psia
  -
Pressurizer levelis 100%
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HPSIinjection valves are fully open
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RCS is 17 F subcooled
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RVLMS indicates 100% in plenum and 48% in upper head
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No RCP's are mnning
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Containment temperature and pressure are 195'F and 11 psig, respectively
- SIAS, CIAS, MSIS and CSAS have actuated
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A cooldown is in progress using steam generators Which of the following actions should be directed by the CRS? Throttle HPSI flow to allow depressurization of the primary syste . Throttle HPSI flow to restore pressurizer level to progra Continue maximum injection flow until subcooling is restore Continue maximum injection flow until the RVLMS indicates the upper head is ful Answer C Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) W/E11 ek22 Facility's heat removal systems, including RO Group:  SRO Group: 2 primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facilit RO K/A  SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3  At Material Required for Examination:
Question Source: Bank
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Latest revision as of 03:13, 29 December 2020

NRC Operator Licensing Exam Repts 50-361/99-301 & 50-362/99-301 Administered on 990416.Exam Results:Two RO & Two SRO Applicants Passed Exam
ML20206H777
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 05/06/1999
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20206H769 List:
References
50-361-99-301, 50-362-99-301, NUDOCS 9905120012
Download: ML20206H777 (134)
v • d • e


Text

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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

o Docket Nos.: 50-361;362

. License Nos.: NPF-10; NPF-15 Report No.: 50-361; 362/99-301 Licensee: Southern California Edison C Facility: San Onofre Nuclear Generating Station Location: P.O. Box 128 San Clemente, California 92674-0128 Dates: April 16,1999

- Inspector: John L. Pellet, Chief, Operations Branch Approved By: Arthur T. Howell 111, Director Division of Reactor Safety ATTACHMENTS:

Attachment 1: Supplemental Information Attachment 2: Final Written Examination and Answer Key

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9905120012 990506 PDR ADOCK 05000361 l V PDR ,

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EXECUTIVE SUMMARY San Onofre Nuclear Generating Station NRC Inspection Report 50-361; 362/99-301 -

NRC examiners evaluated the competency of four operator license applicants for issuance of operating licenses at the San Onofre Nuclear Generating Station. The licensee developed the retake written examination using NUREG-1021, Interim Revision 8, January 1997. NRC examiners reviewed, and approved the examination. The written examination was administered on April 16,1999, by facility proctors in accordance with the guidance in NUREG-1021, Interim Revision Operations

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The two reactor operator and two senior operator license applicants passed the examination (Section 04.1).

The test material was adequate for administration as submitted, with no post-examination changes identified (Section 05.1).

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. Report Details ,

Summarv of Plant Status

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The plant operated at essentially 100 percen't power for the ' duration of this inspectio l. Operations '

04- (Operator Knowledge and Performance 0 Initial Written' Examination i Insoection Scope l On April 16,1999, the' facility licensee proctored the administration of the written -

examination approved by the NRC to the two individuals who had reapplied for a reactor -

operator (RO) and two who had applied for senior operator (SRO) licenses.' The

licensee proposed grades for the written examinations and evaluated the results for question validity and generic weaknesses. The examiner reviewed the licensee's result Observations and Findinas The minimum passing score was 80 percent.- The candidates' scores for the written examination ranged from 88 to 94 percent. The average score was 90. The licensee's post-administration analysis identified that the administered examination was acceptable. There were no post-examination comments or changes to the written

- examination recommended by the licensee or identified by examiner review of the results. Licensee review of the examination results indicated several questions ;

identified potential validity or training deficiencies for further internal review. The l specific questions identified were common RO/SRO questions 1,37,39,52, and 69; RO questions 82,95,~ 96, and 99; and SRO only questions 83,85,86,87,92,96,98, and 99 ,

(shown in Attachment 2 as questions 108,110,111,112,118,123, and 124). The l licensee found all questions appropriate and valid. The examiner reviewed this analysis j and the specific questions and determined that the issues were narrowly focused within j various systems, such as auxiliary feedwater, procedure immediate actions from memory, annunciators, and technical specifications, and did not represent generic weaknesse j ' Conclusions

' The four applicants passed the written' examination. No broad knowledge or training weaknesses were identified as a result of evaluation of the graded examinatio .

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.s l-4-05 Operator Training and Qualification 0 Initial Licensina Examination Development The facility licensee developed the initial licensing examination in accordance with guidance provided in NUREG-1021," Operating Licensing Examination Standards,"

Interim Revision 8, dated January 199 .1.1 Examination Outline Insoection Scope The facility licensee submitted the initial examination outlines on January 14,1999. The chief examiner reviewed the subraittal against the requirements of NUREG-1021, Interim Revision . Observations and Findinas The chief examiner determined that the initial examination outlines satisfied NRC requirement Conclusions The licensee submitted an adequate examination outlin . Examination Packaae Insoection Scope The draft examination was transmitted by the licensee to the NRC on March 29,199 The licensee submitted the completed final examination package on April 5,1999. The chief examiner reviewed the examination against the requirements of NUREG-1021, Interim Revision Observations and Findinas The draft written examinations each contained 100 questions. The draft examinations were technically valid, discriminated at the proper 'evel, and responsive to the outline ,

submitted by the licensee. The written examination was considered adequate for administration, as submitted. The examiner developed clarificat, ion or enhancement comments on about one fourth of the questions. The licensee staff incorporated these comments and all proposed enhancements were accepted by the examiner. In contrast to the prior examination (see NRC Inspection Report 50-361; -362/98-302), the submitted examination demonstrated improved question stem focus and distractor credibility. The quality of the submitted examination was reflected in the lack of post-administration changes, especially as compared to the prior examination, for which the license requested changes to a significant number of the questions.

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l-5-c. Conclusions

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The test material was adequate for administration as submitted by the licensee. No j changes to examination materials were required as a result of administration, q V. Manaaement Meetinas X1 Exit Meeting Summary I

The chief examiner telephonically presented the inspection results to the licensee staff 4 at the condusion of the inspection on May 3,1999. The licensee acknowledged the findings presente The licensee did not identify as proprietary any information or materials examined during this inspectio l

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ATTACHMENT 1 {

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SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee K. Rauch, Operations Training Supervisor NRC None INSPECTION PROCEDURES USED j NUREG-1021, NUREG-1021, " Operating Licensing Examination Standards," Interim Revision 8, January 1997 l

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ATTACHMENT 2 FINAL WRITTEN EXAMINATION AND ANSWER KEY

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i ATTACHMENT 2 '

I FINAL WRITTEN EXAMINATION AND ANSWER KEY )

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COMPOSITE

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NRC EXAM KEY .

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Question #1 Given the following plant conditions:

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Unit 2 is operating at 100% power

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All CEAS are fully withdrawn to the Upper Electrical Limit

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RSPT#1 for CEA 46 to CEAC #1 reads 140" Which CPC/CEAC annunciator display light should be illuminated? CEAC FAIL CEA DE .

1 CEAC INO CEAC SENS FAIL Answer B Exam Level B Cognitive Level . Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 001 ak2.05 Rod motion lights RO Group: 2 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Core Protection /CEAC SO23-3-2,13 Att.10 107 10 Refererte Title Operation Material Required for Examination Question Source: New

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. Question #2 The following plant conditions exist:

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The plant has tripped

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All systems actuated as expected with the exception of the following:

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CEAs 40 and 41 are stuck fully withdrawn

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The operating charging pump has tripped on a loss of suction pressure

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Operators are unable to start any charging pumps Which of the following operator actions is procedurally required under these conditions? Lower RCS pressure and borate via HPS Borate via gravity feed suction pat , .- Initiate RCS cooldown and initiate SLA Stabilize RCS temperature and pressure until boration is initiate '

Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 001 k4.05 Boration and Dilution RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Emergency Boration SO2313-11 5 4 6552 Material Required for Examination Question Source: New r

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Question #3 Which one of the following is the reason for not starting the fourth Reactor Coolant Pump until RCS temperature is greater than 500 degrees Fahrenheit? To prevent exceeding RCS heatup rate limit To prevent excessive RCP starting current To prevent Steam Generator tube stresse To prevent core uplif Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 002 K8.02 RCP RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Plant S/U from CSD to HSB SO23-5- Att.16 118 19 664g Material Required for Examination Question Source: New l

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Question #4 The following conditions exist:

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Unit 2 at 85% powe Recovery of a dropped CEA (#20) is in progres Group 6 is at 149 inches withdraw CEA #20 (a Group 6 CEA) is at 100 inches withdraw CEA #1 (a Group 2 CEA) drops fully into the cor Which of the following is/are the correct required action (s)? Continue realigning CEA # 20, then align CEA # Realign CEA # 1, then continue aligning CEA # 2 ' Manually trip the reacto l

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"' Reduce turbine load to maintain Tc within the operating ban '

l Answer C Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 003 ak1.03 Rotatenship of reactivity and reactor power to RO Group: 2 SRO Group: I rod motio RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning O l Misaligned CEA SO23-13-13 4 4 6565 Material Required for Examination Question Source: New l

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l Question #5 Given the following Unit 2 conditions:

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Reactor tripped from 100% power

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Pressurizer pressure - 1870 psia

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Containment pressure - 3.8 psig To where is RCP bleedoff flow being directed? The VC l l

I The Quench Tan The Containment Sum I HeRCD Answer B Exam Level B CognitiveLevel Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 003 k6.04 Containment isolation valves af fecting RO Group: 1 SRO Group: 1 operatio RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob CVCS PalD 40124A 23 9210 l l

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- Question #6 l

Given the following plant conditions on Unit 3: l l

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Plant is in a normal full power alignment - .

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Pressurizer levelis 43% I

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Pressurizer level setpoint is 48%

Which of the following is the expected automatic response of the CVCS system?

l Three charging pumps in service and letdown flow at maximu l One charging pump in service and letdown flow at minimu One charging pump in service and letdown flow at maximu Three charging pumps in service and letdown flow at minimu .

Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 004 A1.04 Pzr pressure and level RO Group: 1 SRO Group: 1 RO K/A RO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Pressurizer Pressure SO2341.10 ' Att. 2 18 8 6706 and Level Control Material Required for Examination Question Source: Bank

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Question #7

The plant is at 75% power when a new Purification Demineralizer is placed in service. Which of the following will occur if the boron saturation of this demineralizer is incomplete? T-ave will increas Reactor power will decreas Lithium concentration will go u Demineralizer resin channelin Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 004 k5.15 Boron and control reactivity effects as they RO Group: 1 SRO Group: 1 relate to MT ,

l RO K/A SRO K/A i Reference Title Facility Reference Number Section Page Revision Learning Ob RCS Purification and SO23-3- Att. 6 36 10 g7g7 Deborating lon Exchanger Operation  !

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. Question #8 o

j Given the following plant conditions:

-= ; Plant is at 100% power, all' rods out

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Subsequently, CEA'3 (SD Bank A) drops into the core

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Which of the following is the reason for reactor power to be reduced below 90%7

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~A. - To minimize radial power peakin To prevent adverse' Axial Shape inde To prevent a CPC generated Reactor Tri To ensure Transient Insertion Limits are not exceede Answer 'A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 005 ak106. Bases for power limit, for rod misalignmen RO Group: 1 SRO Group: 1 l

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob i l

Technical Reactivity Control Systems LCS 3-1 3-1.10 '

Specifications 105 6565

.. Material Required for Examination -- 1 Question Source: New

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Question #9 A hot leg vent is required whenever the Steam Generator Nozzle Dams are installed. Which of the following states a reason for this if a loss of Shutdown Cooling (SDC) were to occur? To prevent steam buildup in the hot leg which could cause a loss of natural circulatio To prevent steam buildup in the hot leg which will ultimately collapse, causing ;

severe water hamme l To prevent RCS pressurization leading to a failure of the cold leg nozzle dam and potential core uncover To prevent RCS pressurization from causing an erroneous Draindown 12 vel Monitoring System (DLMS) indicatio l Answer C Exam Level 8 Cognitive Level Memory Facility San Onofre 2 & 3 - Exam Date 4/16/99 Tier: (2) 005 k3.01 RCS RO Group: 3 SRO Group: 3 ,

l RO K/A SRO K/A i Reference Title Facihty Reference Number Section Page Revision Learning Ob Draining tile RCS SO23-3- Att. 21 159 13 3366 Material Required for Examination Question Source: New

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l I Question #10 An RCS HOT LEG break has just occurred on Unit 2.

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l What would be the result if the EOI steps to initiate simultaneous hot / cold leg injection were performed immediately following the LOCA diagnosis? Inadequate Core Cooling due to the loss of Safety injection flow out of the break.

l The HPSI pumps would reach runout conditions.

Boration flow would be inadequate to maintain Shutdown Margin requireme.r t

l Injection flow through the core would be stoppe l Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 006 K.3.01 RCS RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Ob LOCA Bases SO23-14-3 At gg3 Material Required for Examination Question Source: Bank l

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Question #11 Given the following plant conditions:

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Plant tripped 30 minutes ago l

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Pressurizer Safety Valve is lifting

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Pressurizer pressure is 1900 psia

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RCS Tu is 545 F ,

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Quench Tank rupture disk has ruptured '

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Containment Pressure is I psig What is the expected temperature in the tailpipe downstream of the affected Pressurizer Safety Valve? degrees degrees degrees ' degrees Answer A {xam level B Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) Ow a2.01 Siuck open safet RO Group: 3 SRO Group:'3 RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Steam Tables Mollier Diagram 4068 l

Material Require <1 for Examination Steam Tables Question Source: New l

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l Question #12 i

Given the following:

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Component Cooling Water (CCW) Pumps P-024 and P-026 are operating

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P-025 is aligned to Train A and is in standby ,

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A Safety injection Actuation Signal (SIAS) and a Loss of Voltage Signal (LOVS) i

occurred on both safety related buse Both safety related buses have been reenergized from their respective Emergency Diesel Generators (EDGs).

Which of the following correctjy describes how the CCW pumps automatically respond to the ]

conditions described? 1 All CCW pumps star P-024 and P-026 start; /-025 does not star P-024 and P-025 start; P-026 does not star P-025 and P-026 start; P-024 does not star Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: '?) 008 a2.01 Loss of CCW Pump RO Group: 3 SRO Group: 3 PO K/A SRO K/A !

Reference Title Facility Reference Number Section Page Revision Learning Ob Loss of CCW/SWC SO23-13-7 Material Required for Examination Question Source: NRC 6/98

Question #13 Which of the following Design Basis Accidents would generate the GREATEST amount of hydrogen and the reason why? SMALL BREAK LOCA, due to increased heat input from the mnning RCP LARGE BREAK LOCA, due to greater steam voiding in the cor SMALL BREAK LOCA, due to less steam voiding in the cor LARGE BREAK LOCA, due to hydrogen coming out of solutio Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/1699 Tier: (1) 009 2.4.21 Small Break LOCA RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob UFSAR 6.2. .2.77 13 65II Material Required for Examination Question Source: New i

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l Question #14 l

l Given the following conditions:

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Plant tripped 10 minutes ago l

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Pressurizer pressure is 2l00 psia and slowly increasing l -

Pressurizer level lowered to 28% and is now slowly increasing

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Both Steam Generator levels are 18% and slowly increasing l

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Both Steam Generator pressures are 1000 psia and steady l l

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All systems are in Automatic and have actuated as required Which of the following is the co'rrect conditiori for the Pressurizer heaters at this time?

(ASSUME NO OPERATOR ACTION) E heaters are off and all other heaters a_e on. - All Pressurizer heaters are o E and proportional heaters are off, non 1E backup heaters are o lE and non IE backup heaters are on, proportional heaters are of Answer A Exam Level B Cognitive Level Application Facdity San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) PPCS 010 A4.02 Pressurizer heaters RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob PZR Pressure and SO23-3-1.10 6 8 10729 Level Control Material Required for Examination Question Source: Bank I

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i Question #15 j

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Given the following plant conditions:

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Unit 2 is in MODE 3

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Pressurizer Ixvel Control System is in automatic i Which of the following would cause letdown flow to increase?

- Irss ofinstrument air to the inservice letdown flow control valv The pressurizer level transmitter equalizing valve has vibrated'ope Volume Contml Tank level has increased to 85%. SBCS controller setpoint has failed low with 2 valves in manual permissiv Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier. ( 2) 011 A3.03 Charging and letdow RO Group: 2 SRO Group: 2 j RO K/A SRO K/A ;

Reference Title Facility Reference Number Section Page Revision Learning Ob PZR Pressure and SO23-3-1.10 Att. 2 18 8 Level Control 10596 Material Required for Examination Question Source: New

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Question #16 A LOCA occurred 90 minutes ago and SO23-12-3 is being implemented. You are monitoring the Floating Step for "Two-phase heat removal established."

i Which of the following temperature sensors are required to be monitored during implementation  ;

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of this floating step?

i l Hot leg RTD ' Cold leg RTD l Core exit thermocouple l Heated junction thermocouple Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99

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Tier: (1) 011 ek1.01 Natural circulation and cooling, including reflux RO Group: 2 SRO Group: 1 .

boilin RO K/A l SRO K/A . Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA SO23-12-3 FS-4 37 15 2537 Material Required for Examination .

I Question Source: NRC 6/98

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Question #17 Given the following conditions:

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A large loss of coolant accident is in progress

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SIAS, CIAS, MSIS, CSAS, and RAS have actuated

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RWSTlevelis 16%

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Emergency sump levelis 20'

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ECCS valves are in the following positions:

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RWST Suction valves HV9300/HV9301 OPEN

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Containment sump isolation valves HV9302/HV9303 OPEN

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Containment sump isolation valves HV9304/HV9305 OPEN

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SI pumps combined recirc valves HV9306/HV9307 OPEN Which of the following valve (s) has failed to automatically reposition to its Recirculation Actuation Signal position? HV9300/HV930 j HV9302/HV930 HV9304/HV930 HV9306/HV930 Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16FJ9 Tier: (2) 013 a2.01 LOCA RO Group: 1 SRO Group: 1

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RO K/A SRO K/A l Reference Title Facility Reference Number Section Page Revision Learning Ob ESFAS Operation SO23-3-2.22 Att.15 102 12 6221 Material Required for Examination Question Source: Bank

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Question #18 He plant is in normal operation at 100% power, when one CEA drops fully into the cor Which of the following statements correctly describes the plant response to this event, assuming no operator action? Reactor power decreases and RCS temperature decreases below progra Turbine MWs lower and RCS temperature stays on progra Reactor power decreases and RCS temperature stays on progra Turbine MWs constant and RCS temperature decreases below progra Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 014 A2.03 Dropped Ro RO Group: 2 SRO Group: 1

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RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Misaligned CEA SO23-1313 2 4 4362 Material Required for Examination Question Source: Bank l

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. Question #19 A reactor startup is in progress and the reactor is approaching criticalit Which set of parameters correctly describes the indications used to declare criticality? Neutron count rate increasing, SUR positive, rods being withdraw Neutron count rate decreasing, SUR negative, rods being inserte Neutron count rate increasing, SUR positive, rod motion stoppe Neutron count rate decreasing, SUR zero, rod motion stoppe Answer C Exam Level O Cognitive Level Mernory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier; (2) 015 k5.05 Criticality and its indication RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Startup SO23-3- Att. 2 31 19 4392 Material Required for Examination Question Source: Bank

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l Question #20 l

i The plant has just tripped from 100% power. What effect will a rise in containment temperature (i.e. from 80 F to 250*F) have on the Steam Generator Narrow Range level instruments? Actual level will be higher than indicated level due to voiding in the variable le Actual level will be higher than indicated level due to reference leg temperature increas Indicated level will be higher than actual level due to voiding in the variable le ! Indicated level will be higher than actual level due to reference leg temperature increas Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 016 2.4.48 Non-Nuclear Instrumentation RO Group: 2 SRO Group: 2 System RO K/A l SAO K/A )

Reference Title Facility Reference Number Section Page Revision Learning Ob Instrumentation Generic Fundamentais

'1915 Material Required for Examination Question Source: Bank I I

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Question #21 Which of the following could be an indication of core uncovery?

(Assume instmments are accurate)

CET Temperature equal to: degrees Fahrenheit with RCS Pressure equal to 1200 psi degrees Fahrenheit with RCS Pressure equal to 1350 psi degrees Fahrenheit with RCS Pressure equal to 1500 psi degrees Fahrenheit with RCS Pressure equal to 1650 psi Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 017 k5.03 Indication of Superheatin RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3 At Material Required for Examination Question Source: New

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Question #22

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Unit 2 was operating at full power when a plant trip occurred. The operators have initiated SO23-12-1, Standard Post Trip Action Plant conditions are as follows:

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One CEA is not fully inserted

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Pressurizer levelis 20% and rising ,

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Pressurizer pressure is 1950 psia and rising

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S/G narrow range water levels are at 29% with MFW RTO actuated

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Containment average temperature is 125 F

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Containment average pressure is 1.0 psig

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What is the correct operator action to be taken at this time, per the SPTAs?

a Ensure normal containment cooling is functioning properl Emergency borate the RC ' Reenergize Pzr heaters to raise pressurizer pressur l Override AFW system to feed both S/Gs at greater than 200 gp Answer A Exctn Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 022 Generic 2.4.21 Knowledge of the parameters used to RO Group: 1 SRO Group: 1 asses the status of safety function RO K/A SRO K/A Reference Title Facility Reference Number Sect Page Revision Learning Ob SPTA SO23-12-1 11 15 5359 Material Required for Examination Question Source: Bank

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Question #23  ;

Plc.nt is operating in a normal full power alignmen Which of the following will result in a loss of letdown flow? Temperature of 150 F leaving the letdown heat exchange J Volume Control Tank outlet valve LV-0~227B fails close Loss of instrument air to FV203 Boronometer/ Rad Monitor control valv gpm letdown flow with only one charging pump runnin Answer B Exam Level 0 Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 022 AK3.04 Isolating letdown RO Group: 2 SRO Group: 2

. RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob CVCS DBD-SO23-390 Fig. D-1 160 5 8992 I

Material Required for Examination Question Source: New l

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Question #24

Which of the following is a condition requiring emergency boration? Part length CEAs inserted to 138 inches withdrawn with Unit at 90% powe loss of all CEA Reed Switch Position indication during a reactor startu Regulating Group 6 CEAs inserted to 100 inches withdrawn with the Unit at 100% powe !

l Loss of Pulse Counter CEA Position indicatio Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 ak3.01 When emergency boration is require RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob j Emergency Boration of SO23-13-11 2 4 the RCS 6552 l

Material Required for Examination Question Source: New

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i Question #25 l i

i Given the following plant conditions.

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HPSI Pump 2P-018 is aligned to TR AIN B l -

Large Break LOCA inside Containment has occurred on Unit 2 I l

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Pressurizer pressure is'900 psia

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Containment pressure is 13 psig i Which of the following TRAIN B pumps should be running due to ESFAS actuations? j l LPSI Pump P-016, HPSI Pump P-019, HPSI Pump P-01 CS Pump P-013, HPSI Pump P-019, HPSI Pump P-018.

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, CS Pump P-013, LPSI Pump P-016, HPSI Pump P-019.

l' CS Pump P-013, LPSI Pump P-016, HPSI Pump P-01 Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier: ( 2) 026 K2.01 Containment Spray Pumps RO Group: 2 SRO Group: 1 RO K/A SR O K/A l Reference Title Facility Reference Number Section Page Revision Learning Ob )

Safety injection, DBD-SO23-740 1.1. ,41.43 2

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Containment Spray and 7328 I

1.1.1.2 l Shutdown Cooling Systems l

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Question #26 l

Which of the following Pressurizer Pressure / Level carameters would require entry into a Technical Specification action statement with Unit 3 at 100% power? Levelof 28%. levelof 56%. Pressure of 2030 psi ,

. Pressure of 2280 psi Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 027 AA2.04 Technical Spocification limits for RCS pressur RO Group: 1 SRO Group: 2

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RO K/A SRO K/A Reference Title Facility Reference Nr:nber Section Page Revision Learning Ob !

Technical Reactor Coolant System 3. .4- 1 67lg i

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Specifications Material Required for Examination Question Source: New

Question #27 What is the purpose of the Trisodium Phosphate (TSP) Dodecahydrate baskets in Containment? l l Minimize the evolution of Hydrogen from containment sump wate Minimize the evolution of Oxygen from containment sump wate Lower pH of containment sump wate j Raise pH of containment sump wate ;

Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/09 ;

Tier: (2) 027 k1.01 CSS RO Group: 3 SRO Group: 2 l

RO K/A SRO K/A l Reference Title Facility Raference Section Page Revision Learning Ob Number Safety injection, Containment Spray DBD-SO.3-740 1.1.12 43 2 and Shutdown Cooling Systems 3285 Material Required for Examination Question Souice: New l

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y-Question #28 Given the following plant conditions:

-- Reactor Trip has just occurred '

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Pressurizer levelis 19% and rising

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Pressurizer pressure is 1950 psia and lowering Which of the following actions is required per SO23-12-1, Standard Post Trip Actions, for these conditions? Verify all available charging and HPSI Pumps are runnin Ensure all available charging pumps are runnin Verify all pressurizer heaters are O Ensure Pressurizer normal and auxiliary spray valves close Answer D Exam Level D Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 028 ak305 Actions contained in EOP for Pzr level RO Group: 3 SRO Group: 3 malfunction, RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA SO23-12-1 5 15 622 Material Required for Examination Question Source: Bank i

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w Question #29 Given the following plant conditions:

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An inadvertent MSIS has occurred

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The Reactor trip circuit breakers have RQI opened

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The Anticipated Transient Without SCRAM / Diverse SCRAM System (ATWS/ DSS) has caused a reactor trip Which of the following has automatically occurred to mitigate the event? SIAS is initiate l l

I CEDMCS MG set output BREAKERS ope CEDMCS MG set output CONTACTORS ope V Buses BIS and B16 deenergize Answer C Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (1) 029 ek3.01 Verifying a reactor trip; methods RO Group: 2 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob *

Plant Protection DBD-SO23-710 2. g System Material Required for Examination Question Source: New

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- Question #30 Given the following plant conditions:' ,

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Unit 2 tripped 25 minutes ago ~l

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A Stearn Generator Tube Rupture has been diagnosed and RCS cooldown has been initiated

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Hot leg temperature is 529 F l

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RCPs 2P001 and 2P004 have been secured

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S/G levels are 27% in E089 and 31% in E088 and slowly rising'~

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Pressurizer level is 20% and slowly rising

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Pressurizer pressure is 1480 psia  ;

Which of the following actions should be performed at this time? Perform HPSI throttle sto ' Override and feed both steam generator . Secure 2 charging pump . Isolate the affected steam generato Answer D Exam Level B Cognitive Level Application Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier:( 2) 035 A2.01 Faulted or ruptured S/Gs RO Group: 2 SRO Group: 2 RO K/A SRO K/A i Reference TiUe Facility Reference Number Section Page Revision Leaming Ob SGTR SO2312-4 11 16 6g74

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Material Required for Examination Question Source: New

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~ Question #31 Given the following plant conditions:

- Unit 2 tripped 18 minutes ago

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Steam Generator Tube Rupture has been diagnosed and SO23-12-4 has been l implemented j

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All Reactor Coolant Pumps were secumd 12 minutes ago

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Natural Circulation Criteria has been verified

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HPSI throttle /stop has been completed; all HPSI and charging pumps are secured

--

Pressurizer pressure is 1150 psia AND slowly lowering

-

Pressurizer level is 66% AND slowly rising  !

Which of the following conditions would explain the pressurizer level response? Pressurizer level instrument variable leg has broke Voiding is occurring in the RCS head regio l l S/G back leakage into the RC RCS heatup is occurrin I Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 038 ekt.03 Natural Circulation RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title - Facility Reference Number Section Page Revision Learning Ob ,

I SGTR Bases SO23-14-4 At l Material Required for Examination Question Source: New l

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Question #32 '

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l Unit 3 is at 17% power and the operator has just applied Block Imad when a generator trip occurs. Describe the expected response of the Main Steam Safety Valves (MSF Vs) and the Steam l Bypass Control System (SBCS) to this event.

, MSSVs will initially open, then reseat; SBCS valves will open as required to control main steam pressur MSSVs will not open; SBCS valves will open as required to control main steam pressur MSSVs will initially open, then reseat; SBCS valves receive a " quick-open" block signal due to low Tav MSSVs and SBCS valves will be unaffecte .

Answer B Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 041 k4.17 Reactor Trip RO Group: 3 SRO Group: 3 RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob S/G and Secondary DBD-SO23-365 6. Side 6455 Material Required for Examination Question Source: New I

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{ Question #33 l While performing a heat treat on Unit 3, the condenser low vacuum alarm is received. You note that main condenser backpressure is 5.8" Hg ab ;

l What effect should this have on Steam Bypass Control System (SBCS) operation? SBCS is disabled due to low condenser vacuum.

, , The SBCS " Emergency Off" push button should be pushed to prevent system operation during the low vacuum conditio Vacuum is not degraded enough to have an effect or require any action D.- SBCS " quick-open" actuation is blocked but modulate operation is still enable Answer C Exam Level Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 051 ak3.01 Loss of steam dump capabihty upon loss of RO Group: 1 SRO Group: 1 condenser vacuu RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Steam Bypass System SO23-3-2.18 Operation 6455 Material Required for Examination Question Source: New

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Question #34 Given the following plant conditions:

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Unit 2 tripped 45 minutes ago

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An Excess Steam Demand Event is in progress l

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E089 is about to reach dryout i Which of the following conditions could occur if steaming is not commenced on the unaffected S/G7 l Loss of natural circulation in the affected RCS loop resulting in stabilization of I RCS temperature Loss of RCS subcooling resulting in a loss of natural circulation in both RCS loop less of inventory in the affected S/G resulting in a loss of natural circulation in that loo Loss of natural circulation in both RCS loops resulting in RCS repressurizatio Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 054 ak3.04 Actions contained in EOP's for loss of MFW, RO Group- 2 SRO Group: 2 RO K/A SRO K/A ' Reference Tit!e Facility Reference Number Section Page Revision Learning Oo ESDE Bases SO2314-5 At Material Required for Examination Question Source: New

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Question #35 Plant conditions are as follows:

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A Imss of Offsite Power caused a reactor trip 30 minutes ago

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MSIVs have been manually closed

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Main Steam pressure is being maintained at 1000 psia following the reactor trip Which of the following conditions would be expected for the above conditions? Hot leg temperature of 550 F and risin Cold leg temperature of 530 F and lowerin Hot leg temperature of 570 F and lowerin Cold leg temperature stable at 545 Hot leg temperature of 587 F and risin Cold leg temperature stable at 545 Hot leg temperature of 570 F and lowerin Cold leg temperature of 540 F and lowerin Answer B Exam Level B Cognitive Level Comprehension Facility San Onoire 2 & 3 Exam Date 4/16/99 Tier: (1) 055 aki.02 Natural Circulatioin Cooling RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Loss of Offsite Power SO23-12-7 8 15 6469 Material Required for Examination Question Source: New

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Question #36 he plant was initially operating at 100% powe ;

I A complete less of Offsite Power occurred 5 minutes ago.- HQ operator actions have been taken I and all systems functioned as designe l How are the S/Gs maintaining RCS heat removal? l 1 AFW supplying S/Gs; steaming out Main Steam Safety Valve ]

. AFW supplying S/Gs; steaming using the' Atmospheric Dump Valve MFW supplying S/Gs; no steaming require : '

MFW supplying S/Gs; steaming using the SBC Answet .A Exam Level B CognitivoLevel Comprofiension Facility San Onofre 2 & 3 Exam Date 4/18/99 Tier:(1) 050 AA2.56 RCS T-av RO Group: 3 SRO Group: 3 '

RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Ob SPTA SO23-12-1 8 15 63l6 Material Required for Examination Question Source: Bank

I Question #37

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Given the following plant conditions:  !

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Channel"A" RCS hot leg temperature Tr-0122-1 has failed and the affected functional units have been bypassed ~

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Channel"C" RCS hot leg temperature TF-0122-3 has also failed and the affected functional units have been placed in trip 1

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A loss of vital bus inverter 2Y004 occurs and the Reactor does NOT trip

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All other plant conditions are normal l

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Which of the following action is required? Vital bus 2YO4 must be placed on its attemate source within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Manually trip the reacto Initiate a Rapid Downpower per SO23-5-1.7, Power Operation Initiate a normal plant shutdown per SO23-5-1.7, Power Operation Answer C Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 057 aa2.03 RPS panel alarm annunciators and RO Group: 1 SRO Group: 1 trip indicators RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob RPS/ Loss of Vital Bus GO23-1318 Att 2 12 2 6593 inverter Material Required for Examination Question Source: New

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. Question #38 Given the following plant conditions:

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Unit 2 tripped 40 minutes ago

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Both Main Steam Isolation Valves (MSIVs) have failed closed

- - All Auxiliary Feedwater has been lost and could not be restored Which of the following methods should be used to recover the RCS Heat Removal Safety Function? Establish HPSI flow to the cold legs for once-through core coolin Reestablish Main Feedwater flow to the S/G Establish LPSI flow to the cold legs for once-through core coolin Establish low pressure allemate feedwater flow using condensate pump Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/1&'99 Tier: (2) 059 k304 RCS RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Functional Recovery SO23-12-9 Att. 8 330 18 ggl6 Material Required for Examination

- Question Source: Bank i

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Question #39 l

Given the following plant conditions:

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Unit 2 is at 355' A cooldown is in progress using the S/G's Which of the following is required to be OPERABLE per Technical Specification 3.7.5, Auxiliary i Feedwater System?

1 All three AFW Pump l Two motor driven AFW Pump l One motor driven and one steam driven AFW Pum One motor driven AFW Pum Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 ;

Tier: (2) 061 Generic 2.1.12 Ability to apply Technical Specifications to a RO Group: 1 SRO Group: 1 system RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Obj, Technical Auxiliary Feedwater System 3. .7-11 Specifications 6643 Material Required for Examination Question Source: New I

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Question #40 Given the following information:

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The unit tripped from 100% power 20 minutes ago

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Both Steam Generator levels lowered to 17% NR and recovered to 26% NR I

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The operator has depressed the " Override" pushbuttons for the AFW valves and is feeding each steam generator at 450 gprn l

Subsequently: 4

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Steam Generator E088 pressure decxases to 700 psia with level at 25% N Steam Generator E089 pressure decreases to 850 psia with level at 27% NR Which of the following describes the status of the AFW system (assume no other operator actions have occurred)? Both steam generator E088 and E089 are being fed,

' E088 is being fed and E089 is isolate Neither steam generator E088 nor E089 is being fe i E089 is being fed and E088 is isolate _

Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 I Tier: (2) 061 a3.04 Automatic AFW lsolation RO Group: 1 SRO Group: 1 RO K/A SRO K/A 42 Reference Title Facility Reference Number Section Pagc Revision Learning Ob}.

Plant Protection DBD-SO23-710 2.1. System 4726 Material Required for Examination Question Source: Bank l 1

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Question #41 Given the following:

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Both Units 2 and 3 are at full powe Unit 2 is preparing to shift Train A SWC pumps

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The operator assigned to perform 4KV breaker manipulations goes to the wrong unit and tums off DC control power to 3Pi l2, which was running at the time What effect does this have on the Unit 3 SWC system? j SWC pump 3P112 breaker opens, SWC pump low flow alarms are receive ,

1 SWC pump 3P112 breaker opens, no alarms are received due to the loss of l control powe SWC pump 3P112 breaker stays closed, no remote operation or automatic tripping is availabl I SWC pump 3P112 breaker stays closed, no remote operation is possible but automatic trips are functiona Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: ( 2) 063 K3.02 Components using DC control RO Group: 2 SRO Group: 1 Power RO K/A SRO K/A l Reference Title Facility Reference Number Section Page Revision Learning Ob Elementary Diagram 30795 18 5220 l

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- Question #42 Plant conditions are as follows:

-

Unit 2 tripped 10 minutes ago on low pressurizer pressure ,

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A loss of offsite power occurred 6 minutes ago

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Pressurizer pressure is now 1430 psia ,

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Bus 2A04 is energized

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20003 has just tripped and bus 2A06 is deenergized j l

Which of the following diesel generator trips could have caused the loss of 2G003? - l l High crankcase pressur High jacket water cooling temperatur )

1 Loss of excitatio Generator differentiel, Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier: (2) 064 k4.02 Trips for ED/G while RO Group: 2' SRO Group: 2 operating (normal or emergency) RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Elementary Diagram 30330 22 5346

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Question #43 Given the following plant conditions:

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Plant is operating at 100% power

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Alarm 61 A15 (Fire Detected) is received in the Control Room

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The Fire Computer indicates the fire is in the Unit 2 computer room Which of the following explains the expected conditions for a fire in the computer room? Supply and exhaust dampers open, for 'once through' air flo I Supply and exhaust dampers close, isolating the computer roo I Supply damper closes, exhaust damper opens to exhaust smoke, i Supply damper opens, exhaust damper closes to allow fresh air i Answer B- Exam Level . 8 Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 067 aa1.05 Plant and Control Room Ventilation System RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Halon Fire Protection SO23-7-4 6. System Operation 8356 Material Required for Examination Question Source: New

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Question #44 A release of one of the Radwaste Secondary Tanks is in progress. Liquid Rad Waste Monitor (RE-7813) fails lo Which of the following will allow the release to recommence? Die Plant Superintendent must approve the release permi Two independent samples, release rate calculations, and valve lineup verifications must be performe The sample flowrate must be estimated at least once every 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> The liquid release cannot recommence until RE-7813 is detemiined to be OPERABL Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam oate 4/16/99 Tier: (2) 068 k6.10 Radiation monitors RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Ob Liquid Radioactive SO23-8-7 Att. 6 95 10 g()6g Waste Release )

Operations  ;

Material Required for Examination Question Source: New

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Question #45 Given the following:

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Wide Range Gas Monitor (WRGM),3RE-7865, is aligned to the Plant Vent Stack

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A Waste Gas Decay Tank release is in progress

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Alarm 61 A27," Plant Vent Stack Radiation Hi", is received due to high radiation on 3RE-7865 Which of the following best describes the automatic action (s) caused by the WRGM for the above set of conditions? The monitor realigns to containment purge to sample that flow pat I 1 Sample flow control shifts from Isokinetic flow control to manual flow contro The waste gas discharge flow control valve FV-7202 close , The outside containmerit mini-purge isolation valve HV9825 close Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 071 k4.04 Isolation of waste gas release tanks RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Radwaste Gas SO2M-15 Discharge 9413 Material Required for Examination Question Source: NRC 6/98 I

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Question #46

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Unit 2 is in MODE 6. During fuel inspection activities, the fuel inspection device was raised out of the Spent Fuel Poo Airbome radiation levels as sensed by the Fuel Handling Building Vent Airbome Monitors RE- i

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7822 & RE-7823 have exceeded the alarm / trip setpoin l

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RE-7822 is in bypass j

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RE-7823 is in normal operation j Based on these conditions, which of the following statements represents correct system response? i l FHIS actuation, Train 'A'. FHIS actuation, Train 'B'. FHIS actuation, Trains 'A' and 'B'. No FHIS actuation occur l Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 072 kl.03 Fuel Building Isolation RO Group: 1 SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Section Page Revision Learning Ob Number

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Fuel Handling Area Vent airborne Process SO23-3-2.2 . Radiation Monitoring System Operation 6302 Material Required for Examination Question Source: Bank

Question #47-Given the following plant conditions:

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A Waste Gas Decay Tank release using 2/3 RT-7808, Plant Vent Stack Airbome Radiation Monits,is in progres Rad monitor 3RT-7865, Containment / Plant Vent Stack Radiation Monitor, becomes INOPERABL What additional action must be performed to allow the release to continue? Process flow rate must be estimated at least once every 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Two independent samples must be drawn at least once every 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Reverify valve alignment, sample and recalculate release rate calculation Verify composite samplers are operational for the gaseous radwaste syste Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/1049 Tier: (2) 073 Generic 2.1.20 Ability to execute procedure step RO Group: 2 SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Radwaste Gas so23-8-15 4.11 4 11 Discharge 10103 Material Required for Examination ,

Question Source: New I I

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l Question #48 The plant has just tripped from 100% power operation, the SPTAs are being carried out and plant conditions are as follows:

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All CEAs are fully inserted

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PZR level is 20%

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RCS Subcooling is 88 F

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Pressurizer pressure is 1410 psia

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RCS cold leg temperature is 490 F

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CNTMT pressure is 0.5 psig

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All ESFAS Systems have actuated as required Which of the following is required per the SPTAs for Reactor Coolant Pump operation? Trip four RCP Trip two RCP Leave all four RCPs runnin Trip one RC Answer B Exam Level B Cognitive Level Comprehenson Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 074 ek304 Tripping RCPs RO Group: 1 SRO Group: 1 R O K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA SO23-12-1 5 15 622 Material Required for Examination Question Source: New l

Question #49 Which of the following electrical buses supply power to the 4 Saltwater Cooling Pumps located in the Unit 2 Saltwater Cooling Pump Room? One (I) pump from each of 2B04,3B04,2B06, and 380 Two (2) pumps from each of 2B04 and 2B0 One (1) pump from each of 2A04,3A04,2A06, and 3A0 Two (2) pumps from each of 2A04 and 2A0 Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 075 K2.03 Cire Water System Emergency RO Group: 2 SRO Group: 2 Essential SWS pumps RO K/A l SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Saltwater Cooling P3D-SO23-410 Table C-1 98 2 System 6727 Material Required for E.iamination Question Source: New s

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[ Question #50

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l l A fire has been detected in Containment. As the Fire Brigade Technical Advisor working with the l Fire Depetment, you are asked what type of automatic water suppression system is used in the l immediate vicinity of RCP P00 l l

l Which of the following is the correct response? A deluge water spray sprinkle ! A wet pipe sprinkle Automatic pre-action sprinkle No suppression system is located in the are Answer. A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 1/16/99 Tier: (2) 086 K5.03 Effect of H,0 spray on electrical components RO Group: 2 SRO Group: 2 RO K/A SRO K/A .

Reference Title Fac!hty Reference Section Page Revision Learning Ob Number Fire Suppression Water System SO23-71 Att. 7 53 18 93g6 Operation Material Required for Examination Question Source: Bank

Question #51 With Unit 2 in MODE 1, an inadvertent CIAS occur Which of the following describes the FIRST actions required to be performed per the AOI? Initiate SO23-13-7, Loss of CCW/SW Trip the Reactor Coolant pump Trip the Reactor and Turbin Override /Open CCW NCL Isoltt. valves'.

Answer C Exam Level B Cognitive Level . Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 103 a3.01 Containment isolation RO Group 3 SRO Group: 2 RO K/A ' SRO K/A l Reference Title Facility F'aference Section Page Revision Learning Ob Number

Recovery From inadvertent Safety SO23-13-17 3. I Injection / containment isolation 6584 Material Required for Examination Question Source: Bank  ;

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f Question #52 l

The unit is operating at 100% power. The following conditions exist on Reactor Coolant Pump i P002:

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Vapor Seal Cavity Pressure 78 psig  ;

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Upper Seal Cavity Pressure 2240 psig {

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Middle Seal Cavity Pressure 2250 psig Which of the following actions are required for the stated conditions? Full power operations may continue, trend P002 parameter Initiate a normal plant shutdow Initiate a Rapid Downpowe j Immediately trip the reactor and 5 seconds after the CEAs are inserted, trip RCP P00 Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 015/17 aa2.01 Cause of RCP failure RO Group: 1 SRO Group: 1 RO K/A SRO K/A Referonce Title Facility Reference Number Section Page Revision Learning Ob RCP Seal Failure SO23-134 Material Required for Examination Question Source: Bank I

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Question #53 During normal plant operations, while performing actions outside of the Control Room, what is the relationship between the Control Room Operators and the PEO? The PEO will take direction from the CRS, but is responsible to the C The ACO will direct the PEO's activities, but will inform the CRS before action is I take I The CO will direct the PEO's activities, but only with SM concurrenc The CO will direct the PEO's activities under the supervision of the CR l Answer D Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exarn Date 4/16/99 l Tier: 2. Knowledge of conduct of operations requirements RO Group: SRO Group:

RO K/A SRO K/A 3.8 i Reference Title Facility Reference Number Section Page Revision Learning Ob l Conduct of Operations SO23-(M6 6.1 )g4l7 l

l Material Required for Examination Question Source: NRC L1/98 l

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i Question #54

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Given the following plant conditions on Unit 2: 1 i

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RCS average temperature is 295 Maintenance is being conducted in the switchyar At 9:00 am the switchyard foreman reports a crane operator lost control and tripped open the Unit 2 switchyard Reserve Auxiliary Transformer breaker Substation personnel on the scene have conducted a visual inspection and report -

that the breakers will be OPERABLE at 10:30 a '

What actions are required by Technical Specifications?

i No further action is required since the LCO will be met within the Required Action Completion Tim Within I hour, perform surveillance test on both DG Take action to suspend any positive n' activity additions entil the second offsite ,

circuit is energize Within I hour, verify correct breaker and power availability for the offsite circuit I that was not deenergize Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.11 Knowledge of <1 hr Tech Spec action statement RO Group: SRO Group:

RO K/A SRO K/A 18 Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Electric Power Systems 3. .8-1 Specifications 9964 Material Required for Examination

_ Question Source: NRC 6/98 l

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Question #55 4 i

l Which of the following sets of conditidns will allow a start (breaker closure) of Circulating Water j Pump P115 (Assume 2A0308 breaker racked in with DC on)? j

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211V5288 - CW P115 Discharge Valve

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211V5100 - TPCW supply valve from Pl15 to TPCW IlX -

l V5288 open,2iiV5100 close VS288 open,211V5100 open.

, HV5288 closed,2iiV5100 ope V5288 closed,2iiV5100 close Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 i l

Tier: 2.1.24 Ability to obtain and interpret electrical and mechanical RO Group: SRO Group:

drawing RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Learning Ob l l

Elementary Diagrams 31001,31005,31000, 17,9,4,8 48(>2 31061 Material Required for Examination prints: 31001,31005,31009,31061 j

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Question Source: Bank

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Question #56 When observing a Motor Operated Valve (MOV) during stroke testing, it is important to stand cl car of the handwheel plan This is because the handwheel will rotate at high speed and could disintegrate if: The limit switch fails to actuat The clutch does not disengag The motor phase rotation is incorrec The torque switch fails to actuat Answer B Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2.2.12 Knowledge of Surveillance Procedure RO Group: SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Valve Operation SO23-O-2 .13 5 5 6363 j Material Required for Examination Question Source: Bank

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l l' Question #57 Which of the following Reactor Protection System (RPS) Trips is HQI required by Technical Specifications? Pressurizer Pressure-Lo Pressurizer Pressure-Hig Steam Generator Level-Lo I 1 Steam Generator levci-Hig I i

Ansi.cr D Exam Level B Cognitive Level Memory Facnity San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.222 Knowledge of limiting conditions for operations and safety RO Group: SRO Group:

Jimit j RO K/A SRO K/A ]

Reference Title Facility Reference Number Section Pago Revision Learning Ob Technical RPS Instrumentation 3. Table 3.3.1-1 Specifications 7270 j

Material Required for Examination l Question Source: Bank i

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r Question #58 Why must a MODE 6 EDMR be issued if the Spent Fuel Pool boron concentration drops below 2600 ppm? The SFP water could dilute the refueling cavity when the fuel transfer tube is opene The addition of spent fuel assemblies to the spent fuel pool could cause spent fuel pool criticalit The RCS water could dilute the Spent Fuel Pool when the fuel transfer tube is opene The movement of a fuel assembly out of a high density fuel rack could cause spent fuel pool criticalit ,.

Answer - A Exam Level B Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2.2.27 Knowledge of the refueling proces RO Group: SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCAR and EDMR SO123-0-13 6. Material Required for Examination Question Source: Bank i

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[ Question #59 l- A worker has been assigned the task of unbolting incore detector flanges.

l The following is the year to date dose for this worker, j -

Deep Dose Equivalent - 0.5 REM l -

Committed Effective Dose Equivalent - 0.2 REM l

Dose Rate for this task is 0.9 R/HR gamma radiation l

Which of the following is the maximum stay time for this worker per SONG's Administrative Limits?

i minute minutes.

.

' minute minutes.

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Answer A Exam Level B Cognitive Level Applicahon Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: 2. Knowledge of 10 CFR:20 and related facility radiation RO Group: SRO Group:

control requirement RO K/A SRO K/A Reference Title Facility Reference Number ! ection S Page Revision Learning Ob Health Physics SO123-Vil-20 6.4. gggj Program

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Question Source: New I 1

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i Question #60 Which of the following statements describes the relationship between dose rate and distance for a point source? l The dose rate varies inversely to the square of the distanc ) The dose rate varies inversely to distanc i l The dose rate does not drop off appreciably with distanc ) The dose rate is insignificant at a distance of three fee Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2. Knowledge of facility ALARA progra RO Group: SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 96gl Material Required for Examination Question Source: Bank m

r Question #61 j

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Given the following:  !

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The unit is in MODE 1 '

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2RT-7865 is aligned to the Plant Vent Stack

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Containment Mini-Purge is in progress I

l Which of the following would require immediate securing of the Containment Mini-Purge? j

RT-7865, Containment / Plant Vent Stack Radiation Monitor becomes INOPERABL RT-7804, Containment Airborne Radiation Monitor becomes INOPERABL RT-7828, Containment Purge Stack Radiation Monitor becomes i INOPERABL . FR-7826, Containment Purge Stack Process Flow Recorder becomes INOPERABL Answer C Eram Level Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2. . Knowledge of the process for performing a containment RO Group: SRO Group:

purg RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Containment Purge and SO23-1- Att.13 70 22 Recirculation Filtration System 7576 Material Required for Examination Question Source: Bank

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- i Question #62 A major earthquake occurred ten minutes ago. The Reactor has tripped and the following conditions exist on Unit 2:

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A loss of the switchyard has occurred

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Both S/Gs are at 17% NR level and no AFW flow can be established to either S/G

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Pressurizer Level is 12% and decreasing

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Main Steam Line Radiation Monitors are trending upscale t

Which of the following is the appropriate Emergency Operating Instruction to mitigate the Unit 2 event? SO23-12-4, Steam Generator Tube Ruptur SO23-12-6,- Loss of Feedwate SO23-12-7, Loss of Forced Circulation / Loss of Offsite Powe I SO23-12-9, Functional Recover Answer D' Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2. Knowledge of EOP entry conditions and immediate action RO Group: SRO Group:

step j RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA SO2312-1 Att. 2 19 15 4845 Material Required for Examination

- Question Source: Bank l

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l Question #63 i

A Reactor Trip has occurred. The crew is ready to report Standard Post Trip Actions.

!

Reactivity Control and Vital Auxiliaries have been reporte l

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l Which of the following states the correct sequence for the next four (4) safety functions to be l reported? l RCS Inventory Control RCS Pressure Control RCS Heat Removal Core Heat Removal RCS Inventory Control RCS Pressure Control Core Heat Removal RCS Heat Removal RCS Pressure Control RCS Inventory Control Core Heat Removal RCS Heat Removal RCS Pressure Control RCS Inventory Control RCS Heat Removal Core Ileat Removal Answer B Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.4.14 Knowledge of general guidelines for EOP flowchart use. RO Group: SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA SO23-12-1 At Material Required for Examination Question Source: Bank i

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- Question #64 Quench Tank level has been rising slowly,

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Which of the following annunciators would assist the operator in determining why this is j occurring? -

j i A32, PZR Spray Valve Bellows Seal Failur I l A35, Reactor Vessel Seal Irakag i l B59, RCP Bleedoff Relief Valve leakin C46, RCP Intergasket Leakag l l

Answer C Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99

)

Tier: 2.4.46 Ability to verify that the alarms are consistent with plant RO Group: SRO Group: I condition RO K/A SRO K/A j

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Reference Title Facility Reference Number Section Page Revisio Learning Ob l Annunciator Panol SOA SO23-15-50.A2 50A31 9 5 6569 Material Required for Examination Question Source: New ,

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Question #65 -

Which of the following conditions will result in starting the LP Turbine Exhaust Hood Emergency Spray Water Pump following a Turbine Trip from 100% power? Condensate supply press to the LP Spray system <100 psig and the LP Spray valve is ope Depressing the " START" handswitch with a SIAS presen LP Exhaust Temperature >l60 Fon one or more exhaust hood Depressing the " OVERRIDE" handswitch with a MSIS presen Answer A Exam Level B Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) BW/A04 aa Adherence to appropriate procedures and RO Group: 2 SRO Group: 2 I operation within the limitations in the facility's l license and amendmein RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learnity Ob Turbine Protective SO23-10-4 Device Testing 5377 Material Required for Examination Question Source: Bank

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m Question #66 Given the following:

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' An unisolable ESDE has occurred outside Containment

-

The affected S/G has blown dry

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RCS temperature is 350 F

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Pressurizer pressure ic 1290 psia The crew should: Secure all running RCP Stabilize RCS temperature and depressurize the RC Reduce RCS temperature to establish 20 F subcoolin Stabilize RCS pressure and temperature at current value Answer B Exam Level B Cognitive Level Comprehension Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BW/E03 ea2.2 Adherence to appropriate procedures and RO Group: 1 SRO Group: 1 q operation within the hmitations in the facility's license and amendment RO K/A SRO K/A I Reference Title Facility D:lerence Nurnber Section Page Revision Learning Ob ESDE SO23-12-5 12 15 6906

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Material Required for Examination Steam Tables Question Source: New I l

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Question #67 -

Given the following plant conditions:

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A small break LOCA is in progress and SIAS has actuated

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All systems are operating as expected Per the stated conditions, which of the following is the basis for maintaining a secondary heat sink?

' To minimize boron stratification of the RCS, RCS pressure may remain so high that cooling from the injection flow alone is inadequate to remove decay hea Reflux boiling is the primary means of heat removal prior to voiding in the hot leg To provide an attemative method of RCS pressure contro Answer B Exam Level B Cognitive Level Memory Facihty San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BW/E04 ea Facihty conditions and selecten of RO Group: 2 SRO Group: 2 appropriate procedures during abnormal and emergency operation RO K/A ' SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23143 At Material Required for Examination Question Source: New l

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Question #68 Given the following:

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The unit tripped 30 minutes ago due to a LOCA

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RCS temperature is 525 degrees F

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Pressurizer pressure is 1600 psia

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Power has been lost to the switchyard

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IE power is being supplied by the diesel generators {

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Voids have formed in the head j For the given con'd itions, which of the following actions will be required x promote greater cooling in the reactor vessel head? Start a CEDM Cooling Uni Vent the head to the quench tan '

' Start a Reactor Coolant Pum Altemately raise, then lower, RCS pressur ;

Ii Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) BW/E08 ek Manipulation of controls required to obtain RO Group: 2 SRO Group: 2 desired operating results during abnormal and emorgency situation RO K/A SRO K/A a Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3 At ,

l Material Required for Examination Question Source: NRC 6/98

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Question #69 Unit 3 is at 100% steady state power. 'Ihe following data has been gathered conceming RCS leakage:

-

3.9 gpm leakage into the Quench Tank from RCGVS

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3.1 gpm leakage into the Reactor Drain Tank from 3PV0100A

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_ l.8 gpm leakage past all check valves from RCS to SI system

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700 gpd E088 S/G primary to secondary leakage

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10 gpd E089 S/G primary to secondary leakage

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0.8 gpm leakage into Containment Sump Which of the following is true conceming the above RCS leakage per Technical Specifications? No Technical Specification entry require Identified Irakage has exceeded the limi Unidentified Leakage has exceeded the limi Primary to Secondary Leakage has exceeded the limi Answer A Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/A16 Generic 2.1.12 Ability to apply Technical Specifications RO Group:3 SRO Group:3 for a syste RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical RCS Operational Leakage 3.4 13 3.4-37 Specificatons 6574 Material Required for Examination Question Source: New l

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} Question #70 The following conditions exist on Unit 2:

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A LOCA has occurred

'

-- SIAS, CIAS, and CCAS have actuated

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The STA reports that the Safety Function Status Check has failed on Inventory Control Which of the following Containment Isolation Valve (s) FAILURE IQ CLOSE would cause a flowpath to outside of containment? IIV-5388 Instniment Air to Containment Isolation Valv I HV-6223 Train A CCW Supply Isolation Valv , HV-9217 and HV-9218 RCP Bleed-off to VCT Isolation Valve .

" HV-5434 Nitrogen Supply to SIT Isolation Valve Answer C Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) CE/E09 generic 2.4.21 Knowledge of the parameters and RO Group: 2 SRO Group: 2 logic used to assess the status of safety function RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3 AtL1 17 4 Functonal Recovery SO23-14-9 At ;

Bases j

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Question #71 A Shutdown From Outside the Control Room is being performed per SO23-13-2. Plant conditions are as follows:

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Pressurizer pressure is 2050 psia and slowly lowering

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T-hot is 575 F and slowly lowering

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T-cold is 555 F and stable

-

Pressurizer level (actual) is 21% and slowly lowering

-

Charging is NQIestablished

-

S/G E089 level (actual) is 58% narrow range

Which of the following statements is correct conceming Natural Circulation for the current plant l conditions?

! Natural Circulation is not established because the plant parameters are outside the guideline Natural Circulation is established but cannot be verified until Pressurizer lxvel is greater than 40% Natural Circulation cannot be verified until manual control of the ADV's is established and T-cold is lowerin Natural Circulation is established and may be verifie Answer D Exam Level B Cognitive Level Application Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier; (1) CE/A13 aa Facihty conditions and selection of appropriate RO Group: 1 SRO Group: 1 procedures during abnormal and emergency operation RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob shutdown From Outside SO23-13-2 Att.15 103 5 6774 the Control Room Material P.equired for Examination: Steam Tables Question Source: NRC 6/98

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p Question #72 i

Unit 2 has experienced a loss of Offsite Power. Following the subsequent Reactor Trip both S/G pressures are noted to be 760 psia and lowerin What action should be taken? Override and stop the turbine driven AFW pum Declare a cooldown in progress and reset the MSIS setpoint Shut the MSIV Ensure MSR isolation valves close Answer C Exam Level B Cognitive Level - Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/A11 ak Components and functions of control and RO Group: 1 SRO Group: 1 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual features, q J

RO K/A SRO K!A Reference Title Facility Referer,ce Number Section Page Revision Learning Ob SPTA SO23-12-1 8 15 473[

Material Required for Examination Question Source: New

r Question #73 The following conditions exist:

-

A small break Loss of Coolant Accident has occurred

-

HPSI Pumps P018 and P019 have been stopped upon meeting IIPSI Throttle /Stop Criteria

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All three charging pumps are running

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Pressurizer pressure is 1400 psia and steady

-

Core exit subcooled margin is 25 F

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RCS cooldown is in progress

-

Pressurizer level is 28% and slowly lowering Which of the following is an appropriate action for these conditions? Start HPSI Pump P019, and throttle open HPSI Injection valves to restore ,

Pressurizer leve {

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Start HPSI Pump P018 and P019 in preparation for reinitiating injection if

' Pressurizer level continues to decrease, Reduce the RCS cooldown rate to allow Pressurizer level to recove Start HPSI Pumps P018 and P019, and fully open all HPSI Injection valves until subcooled margin is restore Answer A Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) W/E02 ek Facility's heat removal systems, incl; ding RO Group: 2 SRO Group: 1 primary coolant, emergency coolant, the decay heat removal systems and relatens between j the proper operation of these systems to the '

operation of the facility, RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA SO23-12-3 Att. 2 45 15 6511 Material Required for Examination Question Source: New

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Question #74 Given the following plant conditions:

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The plant is at 100% power

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2F1-0212, charging flow indication is reading 15 GPM

-

Radwaste Operator reports a leak in the charging header between Charging Header Isolation valve, S21208MUO91, and Containment Isolation valve

~ 2HV.9200 Which of the following flow paths could provide flow using a charging pump to the Reactor Coolant System? LPSI heade HPSI heade Auxiliary Spray Flow heade Charging Header Spring leaded Check Valve 2XCV921 Answer B Exam Level B Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) W/E04 EK Components and functions of control and RO Group: 2 SRO Group: 1 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual feature RO K/A SRO K/A Reference Title Facility Reisence Number Section Page Revision Learning Ob RCS Leak SO23-13-14 3. Material Required for Examination Question Source: New

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. Question #75 l

Given the following plant conditions: I

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E088 S/G pressure is 725 psia

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E089 S/G pressure is 1000 psia

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Pressurizer pressure is 1600 psia

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Containment pressure is 12 psig

-

Containment Ili Range Radiation monitors read 13 R/hr and increasing

-

Nn operator actions has been performed i

Given these conditions, which of the following ESFAS Actuations should HQI have l automatically initiated?  !

l l CRI SIA MSIS, ' CSA Answer D Exam Level B Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) W/E 16 Eld.1 Components and functions of control and RO Group: 2 SRO Group: 2 safety systems, including instrumentation, signals, interlocks, failure modes, automatic and manual feature RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Ob Annunciator Panel 57A SO23-15-57A 57A03 13 4 5375

- Material Required for Examination Question Source: New Question #76 A plant startup is in progress and the following conditions exist:

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The reactor is critical at 5E-5% power -

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.Tave is at 545 degrees F

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RO inadvertently withdraws Group 5 CEAs from 35" to 55"

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No reactor trip occurs Which of the following describes the effect that this event will have on reactor parameters over the NEXT MINUTE? Reactor Power will rise, the response of Tave will depend upon core lif Reactor Power and Tave will both ris Reactor Power will be unaffected, Tave will ris ' Reactor Power will rise, Tave will be unaffecte Answer D Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 001 a1.06 Reactor Power RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 793l Material Required for Examination

~ Question Source: 'New I

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Question #77 Given the following:

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- A Loss of Coolant Accident has occurred at Unit 2 )

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SO23-12-3 is being implemented j

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The ACO has been directed to STOP all Reactor Coolant Pumps (RCPs) 1

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RCP 2P001 fails to stop when the STOP pushbutton is depressed Which of the following is the appropriate action for stopping 2P00l? I i Dispatch an operator to open the breaker to 2P001 locally, at the bu Dispatch an operator to verify locally that DC power is aligned to 2P001 breake Deenergize 2A01 by opening the supply breaker from the Reserve Auxiliary Transforme Deenergize Reserve Auxiliary Transformer 2XR3 by opening the breakers from the switchyar Answer C Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 003 k2.01 RCPS RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Sectio Page Revision Learning Ob n Conducts of Operations SO23-046 6.1 gg Transferring 6.9 KV Buses SO23-6-1 Material Required for Examination Question Source: NRC 6/98

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Question #78 The following conditions are present:

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Channel A Irw DNBR trip is bypassed

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RCP P001 flow input to CPC Channel B has failed low Which of the following conditions will result in a reactor trip? loop I hot leg temperature input to Channel B CPC fails hig Imop i hot leg temperature input to Channel A CPC fails lo Pressurizer pressure input to Channel B CPC fails hig Pressurizer pressure input to Channel C CPC fails lo l Answer D Exam Level R Cognitive Level Comprehonsion Facility San Onofre 2 & 3 Exam Date 4/16/99 3/13/99 Tier:(2) 012 RPS K4.02 Automatic Reactor Trip when RPS RO Group: 2 SRO Group:

setpoints are exceeded for each RPS function; basis for each RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Leaming Obj. -

Plant Protection D8D-SO23-710 2, System 4936 Material Required for Examination Question Source: New

Question #79 The following sequence of events occurs:

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A LOCA has occur ed

-

. A Safety injection Actuation Signal (SIAS) has started all required ECCS pumps

-

he diesels are running unloaded

-

5 minutes after the SIAS, offsite power is lost Which of the following describes the expected response of the ECCS pumps subsequent to the less of Offsite Power?-

I All required ECCS pumps restart immediately after their train's EDG output breaker close The SIAS will need to be manually actuated to allow all the required ECCS pumps to automatically star '

All required ECCS pumps will restart in time delayed sequenc ,

I The SIAS will have to be reset and the required ECCS pumps started by operator I actio i Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 013 kl.01 -

Initiation si0nals for ESF circuit logic RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Elementary Diagram 30643 7 10397 Material Required for Examination Question Source: New

Question #80 Which of the following statements accurately describes the Power Trip Test Interlock (PTTI) in the Excore Safety Channel System? Simulates a 200% linear power ou.put causing a PPS high linear power trip in the affected channe ' Actuates the LO DNBR and HI LPD CPC trips for the affected channe I Prevents more than one channel of log power being simulated greater than 1.0E-4% power during testin Gives permissive to manually bypass the LO DNBR and HI LPD CPC trips when reactor power lowers to less than 1.0E-4%.

Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 015 k3.01 RPS RO Group: 1 SRO Group:

RO K/A SRO K/A Explanationof Answer Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Protective SO23-3-2.12 0. System Operation 7175 Material Required for Examination

- Question Source: New l

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Question #81 Which of the following is an indication that Natural Circulation flow may be lost during EOI implementation? RCS pressure greater than Saturation pressure of the Steam Generato T-hot rising with constant T-col Delta T (Core Exit Thermocouple minus T-hot) equal to 10 Delta-T (T-hot minus T-cold) of 28 Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 017 a3.01 Indications of normal, natural, and interrupted RO Group: 1 SRO Group:

circulationof RC RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SPTA SO23-12-1 6 15 2536 Material Required for Examination Question Source: Bank i

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Question #82 Given the following plant conditions:

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Unit 2 is at 100% power when an inadvertent SIAS occurs

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Reserve Auxiliary Transformer 2XR1 relays on sudden pressure

-

Diesel Generator 20002 started and is loaded on bus 2A04

-

Diesel Generator 2G003 started and tripped 15 seconds later Which of the following is performing the containment cooling function? Containment Normal and Emergency Cooler Containment Normal and Train "A" Emergency Cooler Both Train "A" and "B" Containment Emergency Cooler t- Only Train "A" Containment Emergency Cooler Answer D Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 022 K2.01 containment cooling system cooling fans RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learnity Ob Elementary Diagrams 31248,31249,31250, 14,15,14,15,7 31251,31269 7367 Material Required for Examination Question Source: New l

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Question #83 Given the following plant conditions:

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Unit 2 operating at 100% power

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CCW pump 2P-025 in service and aligned to Train B for single train operation

- A ground fault causes a loss of 4KV Bus 2A06 What operator actions are required to restore CCW to the RCPs? Ensure start of CCW pump 2P-024 and SWC pump 2P-30 Ensure start of CCW pump 2P-026 and SWC pump 2P-11 Ensure start of CCW pump 2P-024 and transfer Non-critical Loo Ensure start of CCW pump 2P-026 and transfer Non-critical loo Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/18/99 Tier: (1) 026 aa2.02 The cause of possible CCW loss RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Loss of CCW/SWC SO23-13-7 Material Required for Examination Question Source: New

Question #84'

Given the following:

- Unit 2 is in MODE The core is being off loaded to the SF The OPERABLE Containment Purge valve, ilV-9949, is determined to be stuck in the open positio What action is required per Technical Specifications LCO 3.9.3, Containment Penetrations? Immediately place containment mini-purge in operatio Isolate the affected purge flowpath within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Decnergize the affected valve within I hou I

D. Immediately suspend core alterations and movement of irradiated fue Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16,99 Tier:(2) 028 Generic 2.1.12 Ability to apply Technical Specifications RO Group: 3 SRO Group:

to a system RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Containment Penetrations LCO 3. .9-4 Specifications 7375 Material Required for Examination Question' Source: New

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Question #85 Which of the following will cause an actuation that closes the containment main purge isolation valves? High Containment Pressur High Containment Temperatur High Containment Radiatio Low Pressurizer Pressur Answer C Exam Level R Cognitive Level Memory Facility San Onotre 2 & 3 Exam Date 4/16/99 Tier: (2) 029 K103 Engineered Safeguards RO Group: 2 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Containment Airborne Radiation SO23-3-2.24.11 Monitor System Operation

~/303 Material Required for Examination Question Source: New l

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Question #86 Which of the following is the I F AST preferred source of makeup to the Spent Fuel Pool? Primary Makeup Water (PMW).

i Boric Acid Makeup Tanks (BAMU). i

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! Refueling Water Storage Tanks (RWST). {

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Nuclear Service Water (NSW). l Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 a 3 Exam Date 4/16/99 Tier
( 2) 033 SFPCS A2.01 Inadequate SDM RO Group: 2 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Spent Fuel Purification SO23-3-2.1 .1 3 6 Cross-tie Operation 4582 Material Required for Examination Question Source: New l

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Question #87 Given the following plant conditions on Unit 3:

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SG Generator E-088 has a known Primary to Secondary leak of 0.3 gpm

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SG Generator E-089 has a known Primary to Secondary leak of 0.4 gpm Which of the following actions is required by Technical Specifications? No action require Commence a controlled plant shutdow ' Commence a rapid plant shutdow Manually trip the reactor and perform SPTA ;

l Answer A Exam Level R CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 037 aa220 Tech Spec limits for RCS leakag RO Group: 2 SRO Group:

RO K/A 32 SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical RCS Operational Leakage 3.4.13 3.4-37 g3g Specifications Material Required for Examination Question Source: New

- Question #88 Given the following:

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Unit 3 is at 5% power

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Temperature is being maintained by the Steam Bypass Control System

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The Isothermal Temperature Coefficient (ITC) is POSITIVE .

-

A total loss of condenser vacuum occurs j

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All systems are in' automatic j

!

Which statement correctly describes Reactor response? Positive reactivity will be added, reactor will eventually trip on VOP J Negative reactivity will be added, reactor power will stabilize above the point of adding hea ~ Negative reactivity will be added, reactor power will stabilize below the ' point of

- adding hea ' Positive reactivity will be added, reactor power will increase until the Main Steam Safety Valves lif j Answer D Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 039 k5.08 Eflect of steam removal on reactivit RO Group: 2 SRO Group:

RO K/A SRO KIA Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 4354 Material Required for Examination Question Source: Bank

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- Question #S9 he reactor trips from 100% power. He operators verify that the reactor is tripped and immediately note that the turbine has not tripped and the g:nerator breakers remain close Which of the following statements describes potential consequences of this event? A loss of subcooling, resulting in the need to trip all RCP An uncontrolled cooldown of the RCS, resulting in less shutdown margi ;

I A decrease in RCS inventory, resulting in core uncover ;

1 An increase in RCS pressure, possibly resulting in the Pressurizer safety valves liftin Answer B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 045 a1.05 Expected response of primary plant . RO Group: 3 SRO Group:

parameters (temperature and pressure)

following T/G tri l l

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Reference Title Facility Reference Number Secton Page Revision Learning Ob i SPTA Bases SO23-14-1 At Material Required for Examination Question Source: New

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l Question #90 I

l Given the following:

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2RT-7870 Condenser Air Ejector Radiation Monitor setpoint is 1.05E-0

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Secondary Radiation HI alarm actuates

- 5 minutes later 2RT-7870 indicates 2.20E-0 Which of the following actions is required for the above conditions? Manually trip the reactor and carry out the SPTAs.

l Commence a controlled plant shutdown and insert rods below 5% reactor power.

1 Commence a rapid tjant shutdown and trip the unit at 35% reactor powe Remain at power, sample all SG's and perform a leakrate calculation.

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Answer C Exam Level R Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 055 K1.06 FRM system RO Group: 2 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Coolant Leak SO23-13-14 3.4. Material Required for Examination Question Source: NRC 6/98 l

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_ Question #91 ,

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Given the following plant conditions-

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Unit is initially operating at 100% power

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Condensate Pumps P050, P051 and P052 are initially running

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Condensate Pump P050 trips Which of the following automatic actions should occur?

-1 ' Heater Drain Pumps will trip on low flDT level l

l Condensate Pump P053 will auto star Recirculation valve for Condensate Pump P050 will auto clos . Main Feedwater Pumps will trip on low suction pressur Answer - B Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 056 a2.04 Loss of condensate pumps RO Group: 1 SRO Group:

RO K/A SRO K/A Referonce Title Facility Reference Number Section Page Revision Learning Ob Condensate Pump SO23-2-2 Att. 2 23 9 Operation 5364

Material Required for Examination

. Question Source: New

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I Question #92 Given the following plant conditions: )

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Unit 2 is operating at 100%. j

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Vital Bus Inverter 2Y002 has just failed, deenergizing vital bus 2YO2 Which of the following is correct concerning Auxiliary Feedwater Flow to the steam generators?  : Only one S/G is being fed.

i- No AFW components change stat Both S/Gs are being fe , P-140 running, neither S/G is being fe Answer . A Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 4/16/99 Tier: (1) 058 aa2.03 DC loads lost; impact on abihty to operate and ROGroup: 2 SRO Group:

monitor plant system RO K/A SRO K/A ReferenceTitle - Facihty Reference Number Section Page Revision Learning Ob RPS FAILURE / LOSS OF VITAL SO12-1318 ATT 2 17 of 24 2 BUS INVERTER 13644 Material Required for Examination Question Source: New

I Question #93 A loss of all Feedwater has occurred. Upon restoring Feedwater, the operator opens the MFW Regulator Bypass Valves to 20% for 5 minutes.

l

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Why are these actions necessary?

' Prevents rapid cooldown of the RC Allows equalizing temperature across the S/ Minimize the possibility of a water hammer event to the tubeshee Ensures S/G feedring is slowly refille Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(2) 059 a2.04 Feeding a dry S/G RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Lossof Feedwatcr SO23-14-6 Att. I 14 4 4734 Bases Material Required for Examination Question Source: Bank

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Question #94 An Emergency Diesel Generator (D/G) monthly surveillance test is being performed. D/G load is indicating 4.7 MW Which of the following is correct? D/G load is be!aw the allowable range of the acceptance criteria, and above the minimum limit for dieselloadin D/G load is within the allowable range of the acceptance criteri D/G load is above the allowable range of the acceptance criteria, and below the maximum limit for dieselloadin D/G load is above the maximum limit for diesel loadin Answer B Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 062 A1.01 Significanceof D/Gloadlimits RO Group: 2 SRO Group:

RO K/A SRO K/A Reference Title Facihty Reference Number Section Page Revision Leaming Ob Diesel Generator SO23-3-323 At Monthly Test - 6697 s Material Required for Examination Question Source: New

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Question #95 The Control Room was evacuated 15 minutes ago due to dense smoke. A shutdown from outside the cc u. I room is in progres Which of the following lists the PREFERRED components to be used to establish auxiliary feedwater to steam generator E089? 1 (Assume all AFW components are available) l )IIV-4763 P141 discharge bypass valve 2) HV-4731 AFW isolation valve  ;

3) P141 motor driven AFW pump ) HV-4706 Pl40 discharge to E089 2) HV-4731 AFW isolation valve 3) Pl40 steam driven AFW pump ) HV-4713 P141 discharge valve 2) HV 4731 AFW isolation valve l I

3) Pl41 motor driven AFW pump ) HV-4706 P140 discharge to E089 2) HV-4715 AFW isolation valve 3) Pl40 steam driven AFW pump Answer C Exam Level R Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 068 aa1.03 S/G level RO Group: 1 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Shutdown from Outside SO23-13-2 Att. 6 47 5 9444 the Control Room Material Required for Examination Question Source: New

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l Question #96 )

i Which of the following would be the PREFERRED discharge path per SO23-8-7, Liquid i Radioactive Waste Release Operations, when performing a radioactive liquid effluent release?

. Unit 2 with Circulating Water pumps P115 and P117, and Saltwater Cooling pump 2P307 mnnin Unit 2 with Circulating Water pumps P115, P116 and Pl 18 runnin Unit 3 with Circulating Water pumps P115, Pl 16, and Pl 17 runnin j Unit 3 with Circulating Water pumps P116 and Pl 18, and Saltwater Cooling ,

'

pump 3P112 runnin Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date.4/16,99 Tier: (2) 088 Generic 2.1.32 Ability to explain and apply all system RO Group: 1 SRO Group:

limits and precautions RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Liquid Radioactive Waste Release SO23-8-7 Att. 9 127 10 Operations 9066 Material Required for Examination Question Source: New k

l Question #97 Which of the following conditions represents a violation of Containment Systems as described in Technical Specifications? While at 100% power, a mechanic blocks open the outer containment airlock door for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform maintenance activities on the INOPERABLE inner containment doo While performing OPERABILITY tests on the redundant containment imp i Hot leg Sample valves (HV-0508 and HV-0509) at 100% power, one of the two valves (HV-0508) fails to completely clos While at 100% power, the nitrogen supply isolation valve to the Safety Injection

. Tanks isolation valve (HV-5434) fails its required stroke tim While at 1(X)% power, the outer containment airlock door fails its leak rate test (

and has to be opened to facilitate repairs that will take 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> I Answer A Exam Level R Co0nitivo Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 069 aat.01 Isolation valves, dampers and RO Group: 1 SRO Group:

electropneumatic device RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Containment Air Locks 3. .6-3 Specifications 6235 Material Required for Examination Question Source: New I

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Question #98 What is the Instrument Air header pressure at which the Respiratory and Service Air System (RSAS) backup supply will automatically begin to supply the instrument air header? psi psi psi ! - 100 psi Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 079 A4.01 Cross-tie valves with IA RO Group: 2 SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Numb Section Page Revision Learning Ob Instrument Air Gystem SO23-1-1 6.12 14 12 Operation 6531 Material Required for Examination Question Source: New

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i I-Question #99 The FIRST action that the Operations Izader performs after an Alert has been declared is: Station someone on the Ivory Phone.

I Evacuate personnel from Hazardous area Activate the Emergency Response Data Syste Perform siren and PA coordinatio Answer D Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 j 4/16/99 Tier: 2.4.29 Knowledgeof theemergencypla RO Group: SRO Group:

RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Operations Leader SO23-Vill-30 6.1.1.1 4 3 Duties 857 Material Required for Examination Question Source: Bank l

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Question #100 A Main Steam Line Break inside Containment has occurre Assuming pmper operation of ESFAS Systems and equipment, what is the maximum expected Containment pressure by design? Approximately 3'7 psi Approximately 47 psi Approximately 57 psi Approximately 67 psi Answer C Exam Level R Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 l I

Tier: (1) CE/E05 ek Normal, abnormal and emergency RO Group: 1 SRO Group: 1 d

operating procedures associated

'

with Excess Steam Deman RO K/A SRO K/A

]

Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Containment B3. B3. Specificatens 7530 Material Required for Examination Question Source: NRC 6/98

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Question #101 After securing a Reactor Coolant Pump, what positive indication is available in the Control Room of the RCP being completely stopped? RCS flow low alan Green stop light o Zero (0) amps indicate . Zero speed light o Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 I

Tier: (1) 011 EA1.03 Securing of RCPs RO Group: SRO Group: 1

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RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Reactor Coolant Pump SO23-3- . Operation 5389 Material Required for Examination )

Question Source: Bank l i

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i Question #102 Plant conditions are as follows:

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Unit 2 at 100% power

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Channel A 2PI-0101-1 Narrow Range Pressure has failed high j

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Channel B 2PI-0102-2 Wide Range Pressure has failed low

-

All actions of SO23-13-18, Reactor Protection System Failure, have been completed )

Which of the following correctly states the existing coincidence logic to trip the reactor on high Pressurizer Pressure? l l

, I out of out of I out of l 1 out of '

l Answer C Exam Level -S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99

'

Tier: (2) 012 K4.02 Automatic reactor trip wt'en RPS setpoints are RO Group: SRO Cioup: 2 exceeded for each RPS function; basis for eac RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical RPS Instrumentation 83. B3.3-3 Specifications 7297 Material Required for Examination Question Source: New i

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E Question #103 Given the following information on Unit 3:

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Reactor power - 100%

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92 day ESFAS logic matrix relay testing is in progress

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Control Room airbome radiation monitor RE-7824 is in BYPASS for maintenance

-

During the performance of the logic matrix test, the trip matrix being tested was -

prematurely de-energized, resulting in Trains "A" & "B" SIAS and CCAS  ;

actuation I Which of the following is'the expected systems response to the above conditions?

1 CRIS actuation is blocke l

l CRIS occurs on Train "A" onl l CRIS occurs on Train "B" onl CRIS occurs on both Train Answer D Exam Level S Cognitive Level - Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 013 kl.01 initiation signals for ESF circuit logi RO Group: SRO Group: 1 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Control Room Airborne Process SO23-3-2-2 .6 4 5 Radiation Monitoring System Operation 6999 Material Required for Examination Question Source: NRC 11/98

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Question #104 What is the basis for the Shutdown Margin requirement of 3% Delta K/K with T-ave less than 200 F?

i Removal of the CEAs during refuelin i l Reactivity effect from further cooldown to Mode A potential dih' tion c cen Allow for ern rs in e. .:cisment of the new fuel loa Answer C Exam Level S CognitiveLevel Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 024 Generic 2.1.12 Ability to apply Technical RO Group: SRO Group: 1 Specifications for a system RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Shutdown Margin B3. B3.1-7 i Specifications 6957-

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I Material Required for Examination j Question Source: Bank i

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Question #105 l

Which of the following valves would be throttled open by the operator to increase the RCS cooldown rate with Shutdown Cooling in service?

l Shutdown Cooling Heat Exchanger inlet valv Shutdown Cooling Heat Exchanger outlet valv )

l l Shutdown Cooling Heat Exchanger CCW outlet valv Shutdown Cooling Heat Exchanger CCW inlet vah I Answer B Exam Level S Cognitive Level Memory Facility San Onoire 2 & 3 Exam Date 4/10/99 Tier: (1) 025 AA1.01 RCS/RHRS cooklown rat RO Group: SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob SDC System Operation SO23-3- .2.8.2 8 15 8036 Material Required for Examination Question Source: Bank L

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Question #106

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The plant has just tripped from 50% power operation, the SPTAs are being carried out and plant conditions are as follows:

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Pressurizer pressure is 650 psia

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Containment average temperature is 251 F

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Both S/G levels 40% NR

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. Both S/G pressures 800 psia Which ESFAS signal combinations should have automatically actuated?  ;

, EFAS, RAS, SIA CSAS, SIAS, CIA SIAS, CIAS, EFA SIAS, MSIS, CSA '

Answer B Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier:(2) 026 A1.01 Containment pressure RO Group: SRO Group: 1 -l A

RO K/A SRO K/A 42 Reference Title Facility Reference Number Section Page Revision Learning Ob Technical ESFAS Instrumentation 3. .3-26 Specifications 7303 Material Required for Examination Question Source: New

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I Question #107-Both trains of CCW/SWC are in operatio What is the reason for aligning the Ixtdown Heat Exchanger to the Critical loop that is supplying the Non-Critical Loop? Reduces the potential for RCP seal deterioration by minimizing the temperature differential in the Non-Critical 12)o Maintains heat load requirements distributed evenly between the loop I Sets loop flows to match operating pressures of the loops to minimize cross train leakag Ensures that CCW process radiation monitor is aligned to detect any Letdown Heat Exchanger tube leakag Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 026 AA2.02 The cause of possible CCW los RO Group: SRO Group: 1 RO K/A SRO K/A l I

Reference Title Facility Reference Number Section Page Revision Learning Ob I CCW System SO23-2-17 Att. 7 56 12 Operation 6257 l

Material Required for Examination Question Source: NRC 11/98 I

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Question #108 l

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, The following conditions exist:

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A large break LOCA occurred on Unit 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> ago

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SO23-12-3, "Ioss of Coolant Accident"is being implemente Hydrogen Monitors initially indicated 0.7%.

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Following calibration Hydrogen concentration indicates 2.6%.

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All ESFAS equipment is available and functioning normall Which of the following actions is required to satisfy the Containment Combustible Gas Control safety function of SO23-12-37 Ensure both Hydrogen Recombiners energized and Containment Spray in servic I Ensure the Hydrogen Purge System in service and all Containment Dome Air Circulating Fans operatin Ensure both Hydrogen Recombiners energized and all Containment Dome ' Air Circulating Fans operatin Ensure both Hydrogen Rec'ombiners energized and Hydrogen Purge System in service.-

Answer C Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Eram Date 4/16/99 Tier:(2) 028 Generic 2.1.20 Ability to execute procedure fys RO Group: SRO Group: 2 RO K/A SRO K/A Reference Title Facuity Reference Number Section Page Revision Learning Ob LOCA SO2312-3 At Material Required for Examination Question Source: New

Question #109 Which of the following radiation monitors will cause the initiation of the Containment Purge Isolation Signal (CPIS)? RE-7828 Containment Purge Stack Radiation Monito RE-7820 Containment High Range Radiation Monito RE-7808 Plant Vent Stack Radiation Monito RE-7804 Containment Airborne Radiation Monito Answer D Exam Level S Cognitive Lovel Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 4 i Tier: (2) 029 K1.03 Engineered safeguards RO Group: SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Containment Purge and SO23-142 Att.13 73 22 Recirculation Filtration 7550 System Material Required for Examination Question Source: Bank

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Question #110 i

Given the following:

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The plant is in MODE 3

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A reactor startup is in progress

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Reactor power is at 2E-7%

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CEAs are being withdrawn I

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Subsequently BOTH startup channels fail to zero l Which of the following describes the action (s) to be taken? l l Continue approach to criticality using safety channel power indicatio I i Immediately trip the Reacto Immediately stop all positive reactivity additions.

1 Commence a reactor shutdow I Answer C Exam Level S CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier;(1) 032 Generic 2.1.12 Ability to apply Technical Specifications to RO Group: SRO Group: 2 l a syste l l l

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RO K/A SRO K/A ]

Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Boron Dilution Alarm 3.3.111 3.3-111 1 Specifications

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Question #111 The following conditions exist on Unit 3:

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Reactor power is 100%

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At 1200 a known tube leak of 0.05 gpm exists in E089 j

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At 1300 the leak increases to 0.075 gpm

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At 1400 the leak increases to 0.090 gpm

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At 1500 the leak increases to 0.12 gpm

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Secondary radiation monitor response confirms increases What action, if any, is required as a result of the increasing S/G tube leak as directed by SO23-13-14 " Reactor Coolant Leak"? Operation of the unit can continu ]

I The reactor should be tripped immediatel A rapid shutdown must be initiate A controlled shutdown must be completed within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Answer D Exam Level S Cognitive Level Appleation Facility San Onofre 2 & 3 Exam Date 4/16FJ9 4 i

Tier: (1) 037 AA2.05 Past history of leakage with current problem RO Group: SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob )

Raactor Coolant Leak SO23-13-14 3.4. Material Required for Examination Question Source: NRC 11/98 L

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i Question #112 l

During coastdown prior to a refueling ontage, system frequency increases to 60.5 hertz. How l will the RCS respond? Temperature increases, pressure increase l Temperature increases, pressure decmase Temperature decreases, pressure decrease Temperature decreases, pressure increase Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/93 Tier (2) 039 K5.08 Effect of steam removal on reactivity RO Group: SRO Group: 2 RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Generic Fundamentals 4354

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Material Required for Examination  ;

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Question #113 Unit 2 is operating at full power when a loss of 125VDC Bus 2D5 occur What effect does this have on the Unit 2 Turbine / Generator?

)) A main generator automatic trip will occu The turbine will trip on overspee The turbine emergency oil pump motors will lose powe The Turbine Stop and Govemor valves will go close Answer D Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 058 AA2.03 DC loads lost; impact on abihty to operate and RO Group: SRO Group: 2 monitor plant system RO K/A SRO K/A .

Reference Title Facihty Reference Number Section Page Revision Learning Ob Operation of 125 VDC SO23-6-15 Att.13 71 13 glgg Systems Material Required for Examination Question Source: NRC i 1/98

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y Question #114 j

l Which of the following is the correct response if an Emergency Diesel Generator (EDG) is paralleled to the grid and both the governor and voltage control pushbuttons are taken to i

" Raise"? EDG KW incieases and EDG speed increase l l EDG reactive load increases and EDG KW increase I EDG frequency increases and EDG reactive load increase l EDG speed increases and EDG frequency increase Answer B Exam Level B Cognitive Level Comprehension racility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (2) 062 A1.01 Significsnce of D/G load timits RO Group: 2 SRO Group: 2 RO K/A SRO K/A ReferenceTitle . Facility deference Number Section Page Revision Learning Ob Diesel Generator SO23-3-3.23 At Monthly Test 7152 Material Required for Examination Question Source. New -

rr-Question #115 The Control Room has been evacuated due to a toxic chemical hazard inside the Control Room envelope. Shutdown fmm outside of the Control Room, SO23-13-2 is in progress:

At the EPPM L-411:

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SG E-088 Wide Range level, LI-l 1% indicates 55%

- RCS Tcold, indicates 530 F

- RCS Thot, indicates 548 F

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S/G pressure indicates 900 psia Determine the actual water level in steam generator E-08 %. %. l %.

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, %.

Answer C Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier:(1) 068 1.03 S/G level RO Group: SRO Group: 1 RO K/A SRO K/A Reference Title Facliity Reference Number Section Page Revision Learning Ob Shutdown from Outside SO23-13-2 Att. 4 35 5 the Control Room 63025 Material Required for Examination SO23-13-2, Attachment 4 Question Source: Bank

~ Question #116

'Ihe following conditions exist during a Unit 2 refueling:

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- Core offload is in progress

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Steam Generator E089 is being sludge lanced

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An operator reports that Main Steam Relief Header Drain Valve, S21301MU394, on S/G E089 is removed j Which of the following actions is required? Restore Containment Integrity within one hou Suspend Core Alteration !

i i Initiate Manual Containment Purge Isolation Signa Verify containment leakage is within specification .

Answer B Exam Level S Cognitive Level Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) 069 aa1.01 Isolation valves, dampers and RO Group: SRO Group: 1 electropneumatic devices RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Containment Penetrations 3. .9-4 777g Specifications Material Required for Examination Question Source: Bank

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Question #117 Given the following plant conditions:

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Unit 2 is at 20% power

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Tc is currently at 534 F Which of the following does the Technical Specifications require? . Perform SR 3.4. Enter LCO 3.4.1 Condition Enter LCO 3.4.2 Condition Perform SR 3.4. I Answer A Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.1.33 Ability to recognize indications for system operating parameters RO Group: SRO Group:

which are entry level conditions for Technical Specification RO K/A SRO K/A Reference Title Facility Reference Number Section lPage Revision Learning Ob l Technical RCS Minimum Temperature 3.4.2 ' 3.4-4 g3g '

Specifications for Criticality i

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Material Required for Examination: T.S.s 3.4.1,3.4.2,3,4.3 (Bases not required)

Question Sourec Bank  !

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I l-Question #118 Given the following plant conditions:

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The' Unit is in MODE The Spent Fuel Pool Boron Concentration is 1825 pp Actions are being taken to restore boron concentratio Which of the following states an additional required action for this condition? . Direct HP to perform a radiation surve Install a local Criticality Accident Radiation Monito Initiate a manual Fuel Handling Isolation Signa Suspend movement of fuel in the Spent Fuel Pcc Answer D Exam Level S Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: 2.2.31 Knc uledge of SRO fuel handling responsibilities RO Group: SRO Group:

RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob Technical Fuel Storage Pool Boron 3.7.17 3.7 30 Specifications Concentration 7949 Material Required for Examination l Question Source: Bank

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. Question #119 A Gaseous Effluent Release Permit requires a Weather Evaluation prior to the release. The following meteorological conditions exist:

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Wind direction is 210 degrees l

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Temperature difference between 10 and 40 meters is minus 0.26 C i

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X/Q value is <4.8E-6 i Determine the MINIMUM wind speed which would allow the release to be commence j mp mp .

I mp mp l

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Answer B Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16FJ9 i

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Tier: 2.3.11 Ability to control radiathn releases RO Group- SRO Group:

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RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob l i

Radwaste Gas SO23-8-15 Att. 4 35 11 Discharge 6268 Material Required for Examination: SO23-8-15 Attachment 4 Question Source: NRC 6/98 I

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. Question #120 Unit 2 is in MODE 5 on Shutdown Coolin While maintenance was being performed on LTOP isolation valve 2HV9339, the valve packing faile Pressurizer level is lowering with the only available charging pump runnin The Loss of SDC AOI has been entered and a HPSI pump has been started to restore leve HPSI pump flow required to maintain Pressurizer levelis 150 gp Which of the following is the correct Emergency Event Classification? None appl B3- G I-l . B2- .;

l Answer C Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/09 Tier: 2.4.29 Knowledge of the emergency plan RO Group: SRO Group:

RO K/A SRO K/A ReferenceTitto Facility Reference Number Section Page Revison Learning Ob EPIP SO123-VilM Att. 2 50 11

}7479 Material Required for Examination: SO123 Vill-1 Attachment 2 Question Source: flew .

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Question #121

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Unit 2 reactor has tripped. The Control Room is being evacuated due to dense smok Which of the following correctly identifies the order in which the "IMMEDIATE ACTIONS" for Shutdown From Outside the Control Room AOI, SO23-13-2 are to be completed? j l.) Manually initiate MSIS 2.) Stop all RCPs 3.) Select manual and stop all Charging Pumps .) Select manual and stop all Charging Pumps l 2.) Manually initiate MSIS .

l 3.) Stop all RCPs l l.) Manually initiate MSIS 2.) Select manual and stop all Charging Pumps

,

3.) Stop all RCPs l l.) Stop all RCPs 1 2.) Manually initiate MSIS  !

3.) Select manual and stop all Charging Pumps Answer C f Exam Level SCognitive Lovel Memory Facility San Onofre 2 & 3 Exam Date'4/16/P9 Tier: 2.4.49 Ability to perform without reference to procedures those . RO Group: SRO Group:

actions that require immediate operahon of system

. components and controls RO K/A SRO K/A _

Reference Title Facl6ty Roterence Number Section Page Revision Leaming Ob Shutdown from Outskie SO23-13-2 the Control Room Material Required for Examination Question Source: Bank -

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l Question #122 ,

Given the following:

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A reactor trip has occurred from 100% power

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All systems have responded normally

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No operator actions have occurred

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The following conditions are observed:

-- RCS temperature is 545 F and stable

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Both S/G !cvels are 35% NR and rising

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Both S/G pressures are 1000 psia and stable Given these conditions, which of the following statements correctly describes the feedwater configuration to the S/Gs?

. MFW only is supplying feedwater to both S/G AFW only is supplying feedwater to both S/G MFW and AFW are both supplying feedwater to both S/Gs, No feedwater is being supplied to the S/Gs, AFW will have to be manually aligned to supply feedwate Answer A . Exam Level S ' CogndiveLevel Application Facihty San Onofre 2 a 3 Exam Date 4/16/99 Tier:(1) CE/E02 ek22 Facility's heat tornoval systems, including RO Group: SRO Group: 2 primary coolant, omergency coolant, the decay heat removal systems and retarons between

., the proper operation of these systems to the

{ ,'g operation of the tacility

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Reference Title Facility Reference Number Section Page Revision Leaming Obi,

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k12-2 5 13 6509

[4v Material Required for Examination Question Source: Bank

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r Question #123

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An Excess Steam Demand Event is in progress. The affected Steam Generator has just boiled dr Which of the following actions must be taken to ensure RCS pressure control is satisfied? Ensure Emergency Feedwater Actuation Signal is actuate Establish maximum Safety Injection Flo Initiate Safety Injection HPSI Throttle /Sto Ensure letdown system in servic I Answer C Exam Level S CognitiveLevel Comprehension Facility San Onofre 2 & 3 Exam Date 4/16/99 I Tier:(1) CE/EOS ok12 Normal, abnormal and emergency operating RO Group: SRO Group: 1 procedures associated with Excess Steam

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Deman RO K/A SRO K/A eference Title Facility Reference Number Section Page Revision Learning Ob ESDE Bases SO23-14-5 At Material Required for Examination Question Source: New

{ l Question #124 Which of the following is HQI a direct advantage of forced circulation during recovery from an Excess Steam Demand Event (ESDE)? Instrument response to operator action Reactor vessel head coolin Pressurizer pressure contro Pressurizer level contro Answer D Exam Level Cognitive Level Memory Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) CE/E05 ek Normal, abnormal and emergency operating RO Group: SRO Group: 1 procedures associated with Excess Steam Deman RO K/A SRO K/A Reference Title Facility Reference Number Section Page Revision Learning Ob ESDE Bases SO23-14-5 At Material Required for Examination Question Source: Bank i

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Question #125 Given the following plant conditions:

- Per SO23-12-1, SPTAs, a LOCA has been identified

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Pressurizer pressure is 1250 psia

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Pressurizer levelis 100%

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HPSIinjection valves are fully open

-

RCS is 17 F subcooled

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RVLMS indicates 100% in plenum and 48% in upper head

-

No RCP's are mnning

-

Containment temperature and pressure are 195'F and 11 psig, respectively

- SIAS, CIAS, MSIS and CSAS have actuated

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A cooldown is in progress using steam generators Which of the following actions should be directed by the CRS? Throttle HPSI flow to allow depressurization of the primary syste . Throttle HPSI flow to restore pressurizer level to progra Continue maximum injection flow until subcooling is restore Continue maximum injection flow until the RVLMS indicates the upper head is ful Answer C Exam Level S Cognitive Level Application Facility San Onofre 2 & 3 Exam Date 4/16/99 Tier: (1) W/E11 ek22 Facility's heat removal systems, including RO Group: SRO Group: 2 primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facilit RO K/A SR O K/A Reference Title Facility Reference Number Section Page Revision Learning Ob LOCA Bases SO23-14-3 At Material Required for Examination:

Question Source: Bank

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