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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: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
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November 29, 1990 l l 1
)
1 Georgia Power Company ATTN: Mr.'W. G. Hairston, III Senior Vice Prt.sident i i Nuclear Operations l P. O. Box 1295 Birmingham, AL 35001 i Gentlemen: ]
j
SUBJECT:
REACTOR OPERATOR'AND SENIOR REACTOR OPERATOR LICENSING l EXAMINATIONS l
In a telephone conversation between1Mr. M. Crosby, Operat' ions !
Training Classroom Specialist and Mr. G. Hopper, License Examiner, NRC Region II Operator Licensing Section,. arrangements were made i for the administration of licensing examinations at the E. I. Hatch Facility.
The written examinations are scheduled for February 25, 1991.
The operating examinations-are scheduled'for February 26.thru March-01, 1991.
To meet the above schedule, it will'be necessary for you to I furnish the reference materinl-listed-in Enclosure;1,
" Reference Material ~ Requireinents for Reactor / Senior Reactor i Operator Licensing Examinations," by January 2, 1991. Any: delay "
in' receiving approved, properly bound and indexed reference-material, or the submittal of inadequate or. incomplete reference material may result in the examination being-rescheduled.
Mr. Crosby'has been advised of our' reference material requirements and the address where each set is to be mailed.
You are responsible for providing adequate' space and accom-modations for administration of 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.
l Enclosure 3 contains the Rules;and Guidelines that will~be in effect during the administratica of the written examination. The facility management is responsible for ~er suring that' all
' applicants are aware of.these rules.-
The facility staff review of the_ written examination will be conducted in accordance with requirements specified in Enclosure l 4, " Requirements for Pacility Review of Written Examinations."
lf i Mr. Crosby has been informed of these requirements.
9012170033 901129 F 7
PDR ADOCK 05000321 Mc- - 1-V PDR
A u .
Georgia Power Company 2 November 29, 1990 To better document simulator examinations, the Chief Examiner will have the simulator operator record predetermined plant conditions (1. e., plant pressure, temperature, pressurizer level, etc.), for i each simulator scenario. The applicants will be responsible for providing this informstion, with any appeal of a simulator operating examination. Therefore, your training staff should retain the original simulator examination scenario information ,
until all applicants who took examinations have either passed the ,
4 operating examination, accepted the denial of their license, or filed an appeal.
Preliminary reactor operator and senior reactor operator license applications 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 certifi-cations, and prepare final examiner assignments after applicant eligibility has been determined. If the applications are not received Et 1 bast 30 days before the examination dates, it is likely that a postponement will be necessary. Final signed applications certifying that all training has been completed shall be submitted at least 14 days before the first examination date.
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 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 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 Information and Records Management Branch, Division of Information, Support Services, Office of Information Resources Management, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555; and to the Paperwork Reduction Project I (3150-0101), Office of Information and Regulatory Affairs, NE OB-l 3019, Office of Management and Budget, Washington, D. C. 20503.
Thank you for your consideration in this matter. If you have any questions regarding the examination procedures and requirements, please contact Mr. L. Lawyer, Chief, Operator Licensing Section 1 at (404) 331-4700, or myself et (404) 331-5541.-
Sincerely, i
l (0RIGINAL SIGNED BY T. A. PEEBLES)
Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety l
Enclosures:
(See Page 3) l
l
. l Georgia Power Company 3 Novemiber 29, 1990 Enclosures
- 1. Reference Material Requirements for Reactor / Senior Reactor operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rul s and Guidelines for Written Examinations
- 4. Requirements for Facility Review of Written Examinations cc w/encls:
C. L. Coggin, Training Supervisor H L. Sumner, Plant Manager 6 ste of Georgia bec w/encls: ,
K. Jabbour, NRR Project Manager A. F. Gibson, DRS X. Brockman, DRP Section Chief G. Hopper, DRS Chief Examiner Sepior Resident Inspector spcumentControlDesk i
i l
i
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ENCLOSURE 1 REFERENCE MATERIAL REOUIREMENTS FOR REACTOR / SENIOR REACTOR ;
OPERATOR LICENSING EXAMINATIONS
- 1. Existing learning objectives, Job Performance Measures, student handouts 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 j 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 i 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.
Training materials shall include all suustantive written material used for preparing applicants for initial RO and SRO 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 BOUND AND INDEXED PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL OF CORPORATE MANAGEMENT WHO IS RESPONSIBLE FOR PLANT OPERATIONS (E. G., VICE PRESIDENT OF NUCLEAR.
l 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:
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System descriptions including descriptions of all operationally relevant flow paths, components, controls, I
l and instrumentation. System training material should draw '
parallels to the actual procedures used for operating the applicable system.
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Complete and operationally useful descriptions of all safety-system interactions and, where available, BOP system interactions under emergency and abnormal
( conditions, including consequences of anticipated operator l error, maintenance error, and equipment failure.
I Training material used to clarify and strengthen l understanding of emergency operating procedures.
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- 2. Complete Procedure Index (including surveillance procedures, etc.). ,
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- 3. All administrative procedures (as applicable to reactor ;
operation or safety).
- 4. All integrated plant procedures (normal or general operating 1
procedures).
- 5. All emergency procedures (emergency instructions, abnormal or special procedures).
- 6. Standing orders (important orders that are safety-related and may supersede the regular procedures).
- 7. Surveillance procedures (procedures that are run frequently,
- i. e., weekly or that can be run on the simulator). ;
- 8. Fuel-handling and core-loading procedures, (initial core-loading procedures, when appropriate).
- 9. All annunciator / alarm procedures.
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- 10. Radiation protection manual (radiation control manual or procedures). -
- 11. Emergency plan implementing procedures.
- 12. Technical Specifications (and interpretations, if available) for all units for which licenses are sought.
- 13. System operating procedures.
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l 14. Piping and instrumentation diagrams, electrical single-line
- diagrams, or flow diagrams.
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- 15. Technical Data Book and/or plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility, l.
l 16.-Questions and answers specific to the facility training program which may be used in the written or operating examinations (voluntary by facility licensee).
- 17. The following on the plant reference simulation facility,
- a. List of all preprogrammed initial conditions.
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- b. List of all preset malfunctions with a clear identifi-cation number. The list shall include cause and effect information. Specifically, for each malfunction a concise description of the expected result, or range of resultc, that will occur upon implementation shall be provided.
Additionally, an indication of which annunciators are to ,
be initially expected shall be given.
- c. A description of simulator failure capabilities for valves, breakers, indicators, and alarms.
- d. Where the capability exists, an explanation of the Obility to vary the severity of a particular malfunction shall be provided, i. e., ability to vary the s'.ze 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 discrepancies not yet corrected,
- g. Identification of differences between the simulator and the reference plant's control room.
- h. Copies of facility generated scenarios that expose the applicants to situations of degraded pressure control i
(PWR), degraded heat removal capability (PHR and BWR) and containment challenges (PWR and BWR) may ce provided (voluntary by licensee),
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- 1. Simulator instructors manual (voluntary by licensee).
- j. Description of the scenarios used for the tre.ining class (voluntary by licensee).
- 18. Additional material required by the examiners to develop examinations thst meet the requirements of these Standards and the regulation'a.
The above reference material shall be approved, final issues and shall be so marked. If a plant has not finalized some of the material, the Chief ExaminerLshall 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 l
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before the administration of the examination. All procedures and reference material shall be bound with appropriate indices or tables of contents so that they can be used efficiently. Failure to provide complete, properly bound and' indexed plant reference material could result in cancellation or rescheduling of the examinations.
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- t ENCLOSURE 2 REOUIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINAT.IQHE l t
- 1. A single room shall be provided for administration of 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 >
written examination. If necessary, the facility should make ,
arrangements for the use of a suitable room at a local school, i 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 applicant per table, with a 3-foot space between tables.'
- 3. Suitable arrangements shall be made by the facility if the applicants are to have lunch, coffee, or other. refreshments.
These arrangements shall comply with Item 1 above and shall be reviewed by the proctor.
- 4. The facility licensee shall provide pads of 8-1/2 by 11 inch '
lined peper in unopened packages for ecuh applicant's use in completing the examination. The proctor shall distribute these pads to the applicants as needed. !
- 5. Applicants may Lring pens, pencils, calculators, or slide l
- rules into the examination room. Only black ink or dark i pencils should be used for writing answers to questions.
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- 6. The licensee shall provide one set of steam tables for eac'h applicant. The proctor shall distribute the steam tables to the applicants. No wall charts, models, end/or-other training materials shall be present in the examinat10n-room. No other equipment or reference material shall be allo,'ed unless provided by the proctor.
- 7. The facility staff shall be provided a copy of the written examination and answer key after the last candidate has handed in his written examination. The facility staff shall have five (5) working days to provide formal written comments with l supporting documentation regarding written examination l questions and answers to the Chief Examiner.
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I 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 assistance in completing the examination. This must be done after you complete the examination. 1 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 l
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 and each answer sheet.
- 4. Mark your answers on the answer sheet provided. USE ONLY THE PAPER PROVIDED, AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
- 5. Before you turn in your examination, consecutively number each answer sheet, including any additional pages inserted when writing your answers on. the examine'cion question page.
- 6. 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.
- 7. The point value for each question is indicated in parentheses after the question.
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- 8. Show all calculations, methods, or assumptions used to obtain an answer to any short answer questions.
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- 9. Partial credit may be given except on multiple choice I questions. Therefore, ANSWER ALL PARTS OF THE QUESTION, AND DO NOT LEAVE ANY ANSWER BLANK.
- 10. Proportional grading will be applied. Any additional wrong ,
l information that is provided may count against you. For '
example, if a question is worth one point end asks for four responses, each of which is worth 0.25 points, and you 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. ,
- 11. If the intent of a question is unclear, ask questions of the examiner only.
- 12. When turning in your examination, assemble the completed examination with examination questions, examination aids, and answer sheets. In addition, turn in all scrap paper.
- 13. Ensure all information you wish to have evaluated as part of your answer is on your answer sheet. Scrap paper will be disposed of immediately following the examination.
- 14. To pass the examination, you must achieve a grade of 80% or greater.
- 15. There is a time limit of-four (4) hours for completion of the examination.
- 16. 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.
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I ENCLO3URE 4 i
EEOUIREMENTS FOR FACILITY REVIEW OF WRITTEN EXAMINATIONS !
- 1. At the option of the Chief Examiner, the facility may review the written examination up to two weeks prior to its i administration. This review nay take place at the facility or )
in the Regional office. The review will be conducted using ;
the same material sent to the NRC for exam. generation I purposes. The Chief Examiner will coordinate the details of the review with the facility. An NRC examiner will always be available 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 nqt be retained by the facility.
- a. Pre-Examination Security Agreement-I, , acknowledge that I have acquired specialized knowledge concerning the examination scheduled for at as of the date of my signature below. I. agree that I will not knowingly divulge any information concerning'this examination to any unauthorized persons. I understand that I am not to participate in any instruction involving those applicants scheduled to be administered the above examination from this date until after the examination has <
been administered. I further understand that violation of the conditions of this agreement may result in the examination being canceled and/or enforcement action against myself or the facility licensee by whom I am l employed or represent.
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l Signature /Date In addition, the facility staff reviewers will sign the '
following statement after the written examination has been l administered.
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- b. post-Examination Security Agreement j I, , did not, to the best of my 3 knowledge, divulge any information concerning the i examinations administered during the week of j at to any unauthorized persons. I I
did not participate in providing any instruction to those.
applicants who were administered the examination from the j date I entered into this security agreement until the I completion of examination administration.
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- 2. Regardless of whether the above examination review option is exercised, immedir.tely following the administration of the written examination, the facility staff 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 the facility did not review the examination prior to its administration, they will have five (5) working days from the day of the written examination to submit formal comments. If ;
the facility 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 i Regional Office by the highest on-site level of corporate management for plant operations, e.g., Vice President for Nuclear Operations. A copy of the. submittal will be~ forwarded to tha Chief Examiner, as appropriate. Comments not submitted witnin the required time frame will be considered for inclusion in the grading process 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 the examinations may occur. 4 i
- 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).
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NOTES: (1) to change to the examination will be made without ;
submittal of a reference to= support the facility -
comment. Any supporting documentation that was not previously supplied, 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 !
diccretion 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 considered in the grading of the examination.
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