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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20216H3641999-09-20020 September 1999 Forwards NRC Form 536 in Response to AL 99-03, Preparation & Scheduling of Operator Licensing Exams HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-5731999-09-16016 September 1999 Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573 ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification1999-09-13013 September 1999 Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification HL-5832, Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC1999-09-0101 September 1999 Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations1999-08-20020 August 1999 Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)1999-08-19019 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d) HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 141999-08-19019 August 1999 Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14 HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.111999-08-18018 August 1999 Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11 ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999 Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528 05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999 Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999 Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage1999-07-15015 July 1999 Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-14014 July 1999 Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999 Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210 HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999 Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively1999-07-0909 July 1999 Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999 Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999 Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999 Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999 Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21 HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999 Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant ML20205H1491999-03-25025 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 1999-09-24
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6171990-11-19019 November 1990 Forwards Insp Repts 50-321/90-22 & 50-366/90-22 on 901015- 19.No Violations or Deviations Noted ML20062F8171990-11-14014 November 1990 Forwards Insp Repts 50-321/90-20 & 50-366/90-20 on 900915- 1020 & Notice of Violation ML20058H8421990-11-13013 November 1990 Forwards Insp Repts 50-321/90-21 & 50-366/90-21 on 901001- 05.No Violations or Deviations Noted ML20217A2921990-11-13013 November 1990 Advises That Kn Jabbour Assigned as Project Manager for Plant ML20217A7441990-11-0707 November 1990 Forwards Insp Repts 50-321/90-16 & 50-366/90-16 on 901001-12.No Violations or Deviations Noted ML20058E8491990-10-23023 October 1990 Forwards Insp Repts 50-321/90-19 & 50-366/90-19 on 900925-28.No Violations or Deviations Noted ML20062B2461990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20059J9151990-09-0707 September 1990 Forwards Guidance for Reporting of Events Under Requirements of 10CFR50.73.W/o Encl ML20058M3561990-08-0808 August 1990 Discusses Util Response to Generic Ltr 89-10, Safety- Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Licensees Test MOVs in Situ Under Design Basis Conditions ML20058L5031990-08-0303 August 1990 Advises That 900727 Response to Generic Ltr 88-14 Re Instrument Air Supply Sys Problems Affecting safety-related Equipment,Acceptable ML20055H3581990-07-23023 July 1990 Advises That Util Provided Acceptable Resolution to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs ML20055H6451990-07-13013 July 1990 Forwards Insp Repts 50-321/90-14 & 50-366/90-14 on 900512-0622.No Violations or Deviations Noted ML20055E8841990-07-10010 July 1990 Advises That EAS-28-0589, Edwin I Hatch Nuclear Plant Basis for Use of Homogeneous Equilibrium Model for Environ Qualification & Radiological Release Evaluation, Withheld from Public Disclosure (Ref 10CFR2.790),per 900628 Request ML20055H3451990-06-21021 June 1990 Responds to Re Basis for Employment Action Involving Former Util Employee Reporting Safety Concerns. Concurs W/Request to Defer Further Discussion Until Completion of Dept of Labor Process ML20059M9561990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055D0021990-06-11011 June 1990 Discusses Util 900514 Application for Amend to License NPF-47,increasing Suppression Pool Temp from 95 F to 100 F. Requests That Util Demonstrate Applicability of Items Addressed in Encl Hatch Safety Evaluation to Facility ML20055C5131990-05-17017 May 1990 Authorizes Restart of Facility When Identified Flaws in Welds Repaired W/Overlay Designs,Per Util & Generic Ltr 88-01.Full Rept of outage-related Insp Activities Should Be Submitted Following Restart ML20055C4771990-05-11011 May 1990 Forwards Insp Repts 50-321/90-13 & 50-366/90-13 on 900430-0504.No Violations or Deviations Noted ML20248D1821989-09-20020 September 1989 Forwards Insp Repts 50-321/89-16 & 50-366/89-16 on 890722- 0825.Violations Noted But Not Cited Since All Criteria of licensee-identified Violations Met ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247C9281989-09-0606 September 1989 Forwards Exam Rept 50-321/OL-89-01 Administered on 890612-16.Concerns Raised Re pre-exam Review Ineffective in Ensuring site-specific Exam Validity & Operator Generic Weaknesses ML20247B3931989-09-0505 September 1989 Forwards Insp Repts 50-321/89-17 & 50-366/89-17 on 890612-16 & 0731-0804.No Violations or Deviations Noted ML20247B5381989-09-0101 September 1989 Forwards Insp Repts 50-321/89-18 & 50-366/89-18 on 890807-11.Violation Noted But Not Cited,Based on Meeting Criteria of licensee-identified Violations ML20246E6861989-08-24024 August 1989 Advises That 890807 Rev to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20246M8791989-08-23023 August 1989 Forwards Insp Repts 50-321/89-13 & 50-366/89-13 on 890710-13.Violations Noted ML20246P4921989-08-22022 August 1989 Forwards Insp Repts 50-321/89-15 & 50-366/89-15 on 890724-28.No Violations or Deviations Noted ML20246N8001989-08-18018 August 1989 Forwards Insp Repts 50-321/89-08 & 50-366/89-08 on 890515-19,0605-09 & 19 & Notice of Violation.Concern Raised Re Implementation of Inservice Testing of Pumps & Valves on Emergency Diesel Generator Sys ML20246C9721989-08-16016 August 1989 Advises That Apr 1989 Rev 9 to Emergency Plan Meets Planning Stds of 10CFR50.47(b) & Requirements of 10CFR50,App E ML20246A6621989-08-0808 August 1989 Forwards Insp Repts 50-321/89-14 & 50-366/89-14 on 890717-20.No Violations or Deviations Noted ML20248C9041989-08-0202 August 1989 Forwards Insp Repts 50-321/89-12 & 50-366/89-12 on 890624-0721.Violations Noted.Violation Not Being Cited Due to Licensee Meeting All of Criteria for Categorization of licensee-identified Violations ML20248A2941989-08-0101 August 1989 Discusses Util Compliance W/Atws Rule (10CFR50.62).Design Change to Utilize Test Switches to Block Actuation Signal to Alternate Rod Injection Solenoid Valve During Testing Acceptable ML20247N7801989-07-27027 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/88-37 & 50-366/88-37.Violation Occurred as Stated in Notice of Violation.Assessment Withheld (Ref 10CFR73.21) ML20247E6181989-07-24024 July 1989 Informs of Agreement Reached During 890719 Telcon Re IGSCC Exam for Fall 1989 Refueling/Maint Outage & Matter of Calibr Blocks to Be Used for Ultrasonic Insp Activities During Outage ML20247E4251989-07-19019 July 1989 Requests Listed Items for Reactor Operator & Senior Operator Licensing Exams Scheduled for Wk of 891009.All Reactor Operator & Senior Reactor Operator License Application Info Should Be Submitted at Least 30 Days Before First Exam Date ML20247B0761989-07-19019 July 1989 Ack Receipt of Util Withdrawing 880711 Request for Relief from ASME Code Section XI Requirement for Testing Class 2 Portions of Main Steam Lines of Units at 1.25 Times Design Pressure.Code Case N-479 Acceptable for Use at Plant IR 05000321/19890021989-07-17017 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/89-02 & 50-366/89-02 ML20247E3651989-07-17017 July 1989 Requests Listed Items for Requalification Program Evaluation Scheduled for Wks of 890911 & 25.NRC to Administer Operating & Written Exams & Discuss W/Qualified Personnel & Operators Schedule for Processing Exams.Ref Matl Requirements Encl ML20246Q2511989-07-14014 July 1989 Forwards Insp Repts 50-321/89-11 & 50-366/89-11 on 890619-23.Noted Violations Not Being Cited Due to Criteria for Categorization of Licensee Identified Violations Being Met ML20247P5571989-07-13013 July 1989 Documents Info Received During Discussions Between Region II Personnel & Concerned Individual.Encl Withheld (Ref 10CFR2.790(a)) ML20246F6661989-07-0606 July 1989 Affirms Validity of Staff Reaction to Final Rept,Submitted in Util Re Bent Rockbolts Observed in Torus Anchorage.Bent Rockbolts Appear to Pose No Safety Impediment to Restart.Issue Closed ML20246K7441989-07-0505 July 1989 Forwards Insp Repts 50-321/89-10 & 50-366/89-10 on 890527- 0623.Details Re Licensee non-cited Violations Described in Rept ML20246B6351989-06-30030 June 1989 Forwards NRR Ack Receipt of Petition Filed by Ecology Ctr of Southern California,For Info.Ltr States That Petition Being Treated Under 10CFR2.206 of Commission Regulation ML20245K9301989-06-23023 June 1989 Advises That Apr 1989 Rev to Physical Security Plan Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20245J9641989-06-22022 June 1989 Advises That Util 880224 Rev 2 to Inservice Insp Program for Second 10-yr Interval Acceptable Except as Noted in Encls ML20245H7291989-06-19019 June 1989 Forwards Insp Repts 50-321/89-07 & 50-366/89-07 on 890422-0526.Licensee Identified Violations Not Cited ML20245D4541989-06-15015 June 1989 Forwards Insp Repts 50-321/89-02 & 50-366/89-02 on 890227-0317 & Notice of Violation ML20245A9991989-06-14014 June 1989 Forwards Insp Repts 50-321/89-09 & 50-366/89-09 on 890522-26.No Violations or Deviations Noted ML20248C1331989-06-0606 June 1989 Forwards Director'S Decision 89-03,transmittal Ltr & Fr Notice Denying Ocre Petition Filed Under 10CFR2.206 for Commission Take Action Applicable to All Bwrs,Per 890309 Power Oscillation Event at LaSalle Unit 2 ML20244D1581989-06-0505 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/89-06 & 50-366/89-06 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 ML20205A2991999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Hatch PPR on 990202.PPR Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Feb 1997 - Jan 1999.Insp Plan for Future Encl ML20207M1771999-03-11011 March 1999 Forwards SE Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Welds ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207D3131999-02-24024 February 1999 Forwards Insp Repts 50-321/98-09 & 50-366/98-09 on 981213- 990123.No Violations Noted.Conduct of Activities at Hatch Facility Generally Characterized by safety-conscious Operation,Sound Engineering & Maintenance ML20203G4161999-02-17017 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs ML20203G3481999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20199H8941999-01-21021 January 1999 Discusses Responses to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Controls, for Plant,Units 1 & 2 ML20199H8761999-01-21021 January 1999 Informs That Proposed GL 88-01 Examinations of Spring 1999 Refueling Outage of Plant,Unit 1 Acceptable ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20199F1331998-12-29029 December 1998 Forwards Insp Repts 50-321/98-07 & 50-366/98-07 on 981101- 1212.No Violations Identified.Activities at Hatch Facility Generally Characterized by safety-conscious Operations, Sound Engineering & Maintenance Practices ML20199E7411998-12-23023 December 1998 Refers to 981105 Training Managers Conference Conducted at RB Russell Bldg with Representatives from All Utils.Agenda Used for Conference & List of Attendees Encl.Goal of Providing Open Forum of Operator Licensing Issues Was Met ML20196J4771998-12-0707 December 1998 Refers to 980311 Submittal of Four New Relief Requests & One Revised Relief Request for IST Program for Pumps & Valves Ei Hatch Npp.Se Accepting Proposed Alternatives Encl ML20196J2581998-12-0101 December 1998 Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities ML20196J2851998-12-0101 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Details of Insp Plan for Next 4 Months & Historial Listing of Plant Issues Called Plant Issues Matrix, Encl ML20196F1661998-11-24024 November 1998 Forwards Insp Repts 50-321/98-06 & 50-366/98-06 on 980920-1031.Insp Rept Identifes Activities That Violate NRC Requirements But Not Subject to Enforcement Actions ML20195D7961998-11-16016 November 1998 Informs That Licensee 980114 Request for Exemption from Requirements of General Design Criterion 56 for Edwin I Hatch Nuclear Plant,Unit 2 Found Acceptable & No Exemption from GDC-56 Required ML20196C8001998-11-12012 November 1998 Forwards Copy of Forms a & B,Individual Answer Sheets & Exam Results Summary of GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl ML20195B7891998-11-0909 November 1998 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Hrps, for Plant,Unit 1 ML20155H4181998-11-0303 November 1998 Advises That Info Contained in 980918 Application & 980813 Affidavit, GE14 Lua Fuel Bundle Description Rept, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20155B6061998-10-28028 October 1998 Forwards Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Tp ML20155A5461998-10-21021 October 1998 Forwards FEMA Final Rept on Exercise of Offsite Radiological Emergency Response Plans for Hatch Plant,Conducted on 980520.No Deficiencies or Areas Requiring Corrective Actions Identified During Exercise ML20155B2461998-10-15015 October 1998 Forwards Insp Repts 50-321/98-05 & 50-366/98-05.No Violations Noted ML20155A6261998-10-15015 October 1998 Informs That NRC Recently Obtained Info Re Industrial Safety Issues at Hatch Facility.Info Indicated That Personnel Unnecessarily Working on Energized Electrical Equipment Without Appropriate Clothing ML20154L4491998-10-14014 October 1998 Informs That NRC Reconsidered Relocation of PCP to PCP Manual Against Guidance in Regulatory Guide 1.143 & Believe That Locating of PCP in PCP Manual,Acceptable ML20155B0371998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators 1999-09-24
[Table view] |
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July 19,i1989 b
,m Georgia Power Company'
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$ ' ATTN: Mr. W.-G. Hairston, III SeniorLVice President Nuclear. Operations-40 Invsrness Center Parkway c
P.'O.' Box 1295 Birmingham, AL 35201 Gentlemen:
SUBJECT:
REACTOR OPERATOR'AND SENIOR 0PERATOR LICENSING EXAMINATIONS ;
In . a < telephone conversation : between Mr. M. Crosby, ' Operations Training Classroom Specialist, and Mr. George Hopper,.NRC-Region II Operator Licensing
- Section,' arrangements were made for administration of the replacement examin-ations at the~ E. I. Hatch facility.
The written' examinations are scheduled for the week of October 9,1989. The simulator / operating. examinations are scheduled for October 10 - 13, 1989,. at the Hatch simulation. facility. The plant oral examinations are scheduled for October 10.-.13, 1989.
In order-.for us ;to meet the above schedule, it will be necessary for the facility to furnish ~ the approved reference material listed in Enclosure 1
" Reference Material Requirements for -Reactor / Senior Reactor Operator Licensing Examination,"'by August 10, 1989. 'Any delay in receiving approved, properly bound and' indexed: reference material, or -the . submittal of inadequate .or
-incomplete reference. material will result:in the examinations being rescheduled. -
Mr. Crosby. has been advised of our reference material requirements- and the examiners' names and addresses where each set is to be mailed.-
The facility- management is responsible for providing adequate space and accommodations in ' order .to properly ~ conduct the . written examinations.
Enclosure 2, " Requirements for Administration of Written Examinations,"
describes' our requirements for conducting these examinations. Mr. Crosby
'has also'been informed of these requirements.
In addition, to better document simulator examinations, the Chief Examiner will have the facility simulator operator record prespecified plant conditions (i.e., plant pressure, temperature, pressurizer level, etc.), for each simulator scenario. The candidate will be responsible for providing this information, along with any appeal of his simulator operating examination.
Therefore, the facility training staff should retain the simulator examination i scenario-information until all candidates taking- the examination have passed the operating examination, accepted the denial of their license, or had their appeals completed.
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, ' Georgia Power-Company. 2 July 19, 1989 Enclosure 3- contains the Rules and Guidelines that will be in effect during the administration of the written examination. The facility management .is responsible for ensuring that all. candidates are aware of these Rules.
All completed reac' tor operator and senior reactor. operator license application informatic': should be submitted at least 30 days before the first examination'
. dates so that we will be able to review the training and experience- of the candidates, process the medical certifications, and prepare final examiner assignments after candidate eligibility has been determined.
This request is covered by Office of Management and Budget Clearance Number 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7-hours per response, including gathering, xeroxing, and mailing the required material. Send comments.regarding-this burden estimate or any other aspect of
' this ' collection 'of information, including suggestions for reducing this burden, to the' Records' and Reports Management Branch, Division of Information Support Services, Office .of. Information Resources Management, U. S. Nuclear Regulatory Commission,'Washingtonm'D. C. 20555; and to the Paperwork Reduction-Project ' (3150-0101) , Office of Management and Budget, Washington, D. C.
20503.
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for Facility Review of Written Examination." Mr. Crosby has been informed of
- these requirements.
- Thank you for your consideration in this matter.- If you have any questions regarding. . the . examination procedures' and requirements, please contact Mr. Charles A. Casto, Chief, Operator Licensing Section 1, at 404/331-5544.
Sincerely, (Original signed by'C. A. Casto for )
Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety
Enclosures:
- 1. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines for Written Examinations
- 4. Requirements for Facility Review of Written Examinations cc w/encis:
C. Coggins, Manager of Training H. C. Nix, Plant Manager State or Georgia
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Georgia Power Company 3 July 19, 1989 bec w/encls:
L. Crocker, NRR L. Trocine, DRP G. Hopper, DRS J. Menning, Hatch Senior Resident. Inspector Document Control Desk i
RII RII RII RII hau BMichael:btm GHopper CCasto TPeebles 7//8/89 7/ /89 7/ /89 7/ /89 l
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4 ENCLOSURE 1 l
REFERENCE MATERIAL REQUIREMENTS FOR REACTOR / SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing learning objectives, Job Performance Measures and lesson plans (including training manuals, plant orientation manual, system descriptions, reactor theory, thermodynamics, etc.).
A copy of the facility Job and Task Analysis (JTA), specifying the knowledges and abilities required of an operator at the facility. Each particular knowledge and/or ability will include an importance rating correlating it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122 (1123) will be used to establish content validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and, as identified in the facility JTAs, outside of the control room, i.e., local operations.
l Training materials shall include all substantive written material used for preparing applicants for initial R0 and SR0 licensing. The written material shall include learning objectives and the details presented during lectures, rather than outlines. Training materials shall be identified by plant and unit, bound, and indexed. FAILURE TO PROVIDE COMPLETE, PROPERLY B0UND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL 0F CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E.G., VICE PRESIDENT OF NUCLEAR OPERATIONS). ACCOMPANYING THE MATERIAL WILL BE A COVER LETTER EXPLAINING THE DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials which include the following shall be provided:
l System descriptions including descriptions of all operationally relevant flow paths, components, controls and instrumentation.
System training material should draw parallels to the actual i procedures used for operating the applicable system.
l l -
Complete and operationally useful descriptions of all safety-system interactions and, where available, BOP system interactions under l emergencv and abnormal conditions, including consequences of anticipated operator error, maintenance error, and equipment failure.
Training material used to clarify and strengthen understanding of emergency operating procedures.
l l
l
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[ Enclosure'l- 2 1-
-- Comprehensive theory material that includes fundamentals in the area of . theory of reactor operation, thermodynamics, heat transfer and fluid flow, as well as specific application to actual in-plant components. ' For example, mechanical theory material on- pumps shall include pump theory as well as descriptions of how these principles actually, apply to major. plant pumps and the systems in which they.
are installed - (i .e. , Reactor Coolant Pumps, all .ECCS pumps, Recirculation pumps, Feedwater pumps and : Emergency Feedwater pumps).. Reactor Theory material shall include descriptions that draw explicit ties between the. fundamentals and the actual operating limits ' followed in the plant (i.e., reactor theory material shall-contain explanations how principles relate to the actual curves used by operators to verify shutdown margin or calculate an ECP).
- 2. Complete Procedure Index (alphabetical'by subject).
- 3. All administrative. procedures (as applicable to reactor operation or safety).
- 4. All integrated plant procedures (normal or general operating procedures).
'5. Emergency . procedures (emergency instructions, abnormal or special procedures).
~6. Standing orders (important orders that are safety-related and may supersede the regular procedures).
- 7. . Fuel-handling and core-loading procedures.
- 8. Annunciator procedures (alarm procedures, including set points).-
- 9. . Radiation protection manual (radiation control manual or' procedures). j
- 10. Emergency plan implementing procedures.
- 11. Technical Specifications. J
'12. System operating procedures.
- 13. . Piping and instrumentation diagrams, electrical single-line diagrams, or flow diagrams.
14 Technical Data Book, and/or plant curve information as used b and facility precautions, limitations, and set points (PLS)y operatorsfor the facility.
- 15. Questions and answers that the facility licensee has prepared and which may be used .in the written or operating examinations.
- 16. The following on the plant reference simulation facility:
- a. List of all readily available initialization points.
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. Enclosure 1 3
- b. List of all preset malfunctions with a clear identification number.
The list should include cause and effect information.. Specifically, for, each malfunction, a concise description of the expected result, or range of results, that will occur upon implementation should be provided. Additionally, an indication of which annunciators are to be initially expected should be given.
- c. A description of simulator capabilities for valves, breakers, i
indicators, and alarms,
- d. Where the capability exists, an explanation of the ability to vary the severity of a particular malfunction should be provided, i.e.,
ability to vary the size of a given LOCA or steam leak, or the ability to cause a slow failure of a component such as a feed pump, turbine generator or major valve (e.g., drifting shut of a main feedwater control valve).
- e. An identification of modeling conditions / problems that may impact the examination.
- f. Identification of any known Performance Test Failures not yet completed.
- g. Identification of significant differences between the simulator and the reference plant's control room.
- h. Copies of facility generated scenarios that expose the candidates to situations of degraded pressure control (PWR), degraded heat removal capability (PWR and BWR), and containment challenges (BWR) shall be provided.
- i. Simulator instructors manual,
- j. Description of the scenarios used for the training class (voluntary bylicensee).
- 17. Surveillance procedures (procedures that are frequently run, i.e., weekly ordaily).
- 18. Additional material required by the examiners to develop examinations that meet the requirements of these standards and the regulations.
The above reference material should be approved, final issues and should be so marked. If a plant has not finalized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is
. available and that agreement has been reached with the licensee for limiting changes before the administration of the examination. All procedures and reTerence mateMal should be bound with appropriate indexes or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material will result in the material being returned and could result in cancellation or rescheduling of the examinations.
ENCLOSURE 2 REQUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for completing the written examination.
The location of this room and supporting restroom facilities shall be such as to prevent contact with all other facility and/or contractor ,
personnel during the duration of the written examination. If necessary, !
the facility should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of the licensee.
- 2. Minimum spacing is required to ensure examination integrity as determined by the Chief Examiner. Minimum spacing should be one candidate per table, with a 3-foot space between tables. No wall charts, models, and/or other training materials shall be present in the examination j roem.
- 3. Suitable arrangements shall be made by the facility if the candidates are to have lunch, coffee, or other refreshments. These arrangements shall comply with Item 1 above. These arrangements shall be reviewed by the examiner and/or proctor.
- 4. The facility staff shall be provided a copy of the written examination ;
and answer key after the last candidate has completed and handed in his written examination. The facility staff shall then have five working days to provide formal written comments with supporting documentation on ,
the examination and answer key to the Chief Examiner or to the Regional Office Section Chief.
- 5. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each candidate's use in completing the examination. The examiner shall distribute these pads to the candidates. All reference material needed to complete the examination l shall be furnished by the examiner. Candidates can bring pens, pencils, calculators, or slide rules into the examination room, and no other equipment or reference material shall be allowed. l
- 6. Only blank ink or dark pencils should be used for writing answers to questions.
- 7. The licensee shall provide one set of steam tables for each applicant The examiner shall distribute the steam tables to the applicants. No wall charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
I l
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ENCLOSURE 3 PROCEDURES FOR THE ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until instructed to do so.
READ THE FOLLOWING INSTRUCTIONS VERBATIM:
During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your , application and could result in more severe penalties.
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own and you have not received or given assistence in completing the examination. This mest be done after you complete the examination.
READ THE FOLLOWING INSTRUCTIONS
- 1. Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
- 2. Use black ink or dark pencil only to facilitate legible reproductions.
- 3. Print your name in the blank provided in the upper right-hand corner of the examination cover sheet.
- 4. Fill in the date on the cover sheet of the examination (if necessary).
- 5. You may write your answers on the examination question page or on a separate sheet of paper. USE ONLY THE PAPER PROVIDED AND 00 NOT WRITE ON '
THE BACK SIDE OF THE PAGE.
- 6. If you write your answers on the examination question page and you need more sphce to answer a specific question, use a separate sheet of the paper provided and insert it directly after the specific question. DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION PAGE.
- 7. Print your name in the upper right hand corner of the first page of each section of your answer sheets whether you use the examination question pages or separate sheets of paper. Initial each page.
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Enclosure 3 2
- 8. Before you turn in your examination, consequently number each answer sheet, including any additional pages inserted when writing your answers on the examination question page.
- 9. If you are using separate sheets, number each answer as to category and number (i.e., 1.04, 6.10) and skip at'least 3 lines between answers to allow space for grading.
- 10. Write "End of Category " at the end of your answers to a category.
- 11. Start each category on a new page.
- 12. Write "Last Page" on the last answer sheet.
- 13. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as _ or _ signs to avoid a simple transposition error resulting in an incorrect answer. Write it out.
- 14. The point value for each question is indicated in parentheses after the question. The amount of blank space on an examination question page is NOT an indication of the depth of answer required.
- 15. Show all calculations, methods, or assumptions used to obtain an answer.
- 16. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 17. Proportional grading will be applied. Any additional wrong information that is provided may count against you. For example, if a question is worth one poirt and asks for four responses, each of which is worth 0.25 points, and ycu give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for that question will be 0.80 instead of 1.00 even though you got the four correct answers.
- 18. If .the intent of a question is unclear, ask questions of the examiner only.
- 19. When turning in your examination, assemble the completed examination with exam nation questions, examination aids, and answer sheets. In addition, turn in all scrap paper.
- 20. To pass the examination, you must achieve an overall grade of 80 percent or greater and at least 70 percent in each category.
- 21. There is a time limit of (6) hours for completion of the examination (or some other time if less than the full examination is taken).
- 22. When you are done and have turned in your examination, leave the examination area (DEFINE THE AREA). If you are found in this area while the examination is still in progress, your license may be denied or revoked.
4 #
ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS
- 1. At the option of the Chief Examiner, the facility may review the written examination up to two weeks prior to its administration. This review may take place at the facility or in the Regional office. The Chief Examiner will coordinate the details of the review with the facility. An NRC examiner will always be present during the review.
Whenever this option of examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the examination. The examination or written notes will not by ratained by the facility,
- a. Pre-Examination Security Agreement I agree that ' will not knowingly divulge any information concerning the replacems at (or initial) examination scheduled for to any unauthorized persons. I ;
understand that I am not to participate in any instruction involving those reactor operator or senior reactor operator applicants scheduled to be administered the above replacement (or initial) examination from now until after the examination has been administered. I understand that violation of this security agreement could result in the examination being voided.
Signature /Date In addition, the facility staff reviewers will sign the following statement after the written examination has been administered,
- b. Post-Examination Security Agreement I __ did not, to the best of my knowledge, l divulge any information concerning the written examination administered on to any unauthorized persons. I did not participate in providing any instruction to those reactor ,
operator and senior reactor operator applicants who were !
l administered the examination from t' time that I was allowed access to the examination.
l Signature /Date L
.g+
Enclosure 4i ~2
- 2. Regardlep of whether the above ex' amination review option is exercised, immediately following the administration- of the written examination, the facility vcaff shall be provided a marked up copy of the examination and the answer key. The copy.of the written examination shall' include pen and-ink. changes made to questions during the examination administration.
! If _ thel facility did not review the examination prior to its administra-tion, they will have five (P working days from the day of the written examination to submit formal comments.- If theLfacility reviewed the examination prior to its administration, any additional comments must be.
given to an examiner prior to his/her leaving the site at the end of the week of ~ the written examination administration. In either case, the comments will be addressed to the ' responsible Regional Office by the highest level of' corporate management for plant operations, e.g., Vice President for Nuclear ' Operations. A_. copy ' of the submittal will be forwarded to.the Chief Examiner, as. appropriate. Comments not submitted within the required; time frame will. be considered for inclusion in the -
grading proce'is on a case-by-case basis by the Regional Office Section Chief. Should the comment submittal deadline not be met, a:long delay in grading tha examinations may occur.
- 3. The ~ following format should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and reference,
- b. . Facility comment / recommendation.
- c. Reference (to support facility comment).
NOTES: 1. No change to the examination will be made without submittal of a reference to support the facility comment. Any supporting documentation that was not previously s ulied, should be provided.
- 2. Comments made without a concise facility recommendation will not be addressed.
- 4. A two-hour post examination review may be held at the discretion of the Chief Examiner. If this review is held, the facility staff should be informed that only written comments that are properly supported will be j considered in the grading of the examination.
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