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:INCOMING CORRESPONDENCE
MONTHYEARML20216H3641999-09-20020 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
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
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
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
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-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
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-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-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
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
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
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
ML20205H1411999-03-24024 March 1999
Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirement for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Oglethorpe Power Corp Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 30% of Facility
HL-5754, Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO1999-03-22022 March 1999
Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO
ML20205H1381999-03-22022 March 1999
Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Georgia Power Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 50.1% of Facility
ML20205H1581999-03-16016 March 1999
Forwards Info for OLs DPR-5 & NPF-7 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Dalton Utilities Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 2.2% of Facility
HL-5753, Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative1999-03-16016 March 1999
Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative
HL-5757, Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 9901271999-03-15015 March 1999
Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 990127
HL-5756, Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 21999-03-12012 March 1999
Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 2
HL-5751, Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities1999-03-0505 March 1999
Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities
HL-5735, Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC1999-03-0202 March 1999
Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC
HL-5737, Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C1999-02-0505 February 1999
Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C
HL-5733, Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions1999-01-29029 January 1999
Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions
HL-5729, Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program1999-01-27027 January 1999
Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program
HL-5728, Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures1999-01-19019 January 1999
Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures
HL-5712, Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review1999-01-0707 January 1999
Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review
HL-5725, Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied1999-01-0707 January 1999
Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied
05000366/LER-1998-004, Forwards LER 98-004-01 Re Personnel Error Which Resulted in Condition Prohibited by Ts.Rev Is Necessary Because Original LER Reported Inadvertent Criticality Could Have Occurred1999-01-0404 January 1999
Forwards LER 98-004-01 Re Personnel Error Which Resulted in Condition Prohibited by Ts.Rev Is Necessary Because Original LER Reported Inadvertent Criticality Could Have Occurred
HL-5710, Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds1998-12-0202 December 1998
Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds
HL-5708, Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers1998-11-20020 November 1998
Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers
HL-5573, Withdraws Requesting Exemption from Requirements of GDC 56 with Respect to Ei Hatch,Unit 2 Reactor bldg-to- Suppression Chamber Vacuum Relief Sys Design Due to Listed Reasons1998-10-19019 October 1998
Withdraws Requesting Exemption from Requirements of GDC 56 with Respect to Ei Hatch,Unit 2 Reactor bldg-to- Suppression Chamber Vacuum Relief Sys Design Due to Listed Reasons
HL-5687, Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment1998-10-19019 October 1998
Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment
HL-5686, Informs That Corrective Actions Relative to Thermo-Lag 330-1 Issues Are Complete1998-10-16016 October 1998
Informs That Corrective Actions Relative to Thermo-Lag 330-1 Issues Are Complete
HL-5697, Requests Delay of Insp of RPV Circumferential Shell Welds for Two Operating Cycles as Outlined in NRC Info Notice 97-63,Suppl 1 & That Proposed Alternative Be Authorized Per 10CFR50.55a(a)(3)(i),per1998-10-16016 October 1998
Requests Delay of Insp of RPV Circumferential Shell Welds for Two Operating Cycles as Outlined in NRC Info Notice 97-63,Suppl 1 & That Proposed Alternative Be Authorized Per 10CFR50.55a(a)(3)(i),per
HL-5689, Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients1998-09-30030 September 1998
Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients
HL-5673, Informs NRC That Util Intends to Load Four Lead Use Assemblies Into Unit 2 Core as Part of Reload 14/Cycle 15 During Fall 1998 Refueling Outage.Proprietary Info Encl. Proprietary Info Withheld,Per 10CFR2.7901998-09-18018 September 1998
Informs NRC That Util Intends to Load Four Lead Use Assemblies Into Unit 2 Core as Part of Reload 14/Cycle 15 During Fall 1998 Refueling Outage.Proprietary Info Encl. Proprietary Info Withheld,Per 10CFR2.790
HL-5680, Informs NRC of Util Plans & Schedule for Exam of Unit 1 RPV Shell Welds.Util Anticipates Having Final Relief Request Submitted to NRC for Review by 9907011998-09-18018 September 1998
Informs NRC of Util Plans & Schedule for Exam of Unit 1 RPV Shell Welds.Util Anticipates Having Final Relief Request Submitted to NRC for Review by 990701
1999-09-20
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Category:UTILITY TO NRC
MONTHYEARHL-1278, Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined1990-09-12012 September 1990
Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined
HL-1176, Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date1990-09-12012 September 1990
Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date
HL-1237, Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.11990-09-0404 September 1990
Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.1
HL-1250, Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage1990-08-27027 August 1990
Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage
ML20059C6551990-08-27027 August 1990
Informs of Intention to Transfer Right of Way for Road 451 to Appling County So Road Can Be Straightened & Paved. Transfer Will Have No Significant Impact on Use of Road & Site Emergency Plan
ML20028G8441990-08-27027 August 1990
Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 1990.
HL-1245, Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d1990-08-23023 August 1990
Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d
ML20056B3011990-08-20020 August 1990
Forwards Revised Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval, for Review & Approval.Program Will Be Implemented While Awaiting SER
HL-1215, Informs of Implementation of Amend 169 to Facility Tech Specs1990-07-26026 July 1990
Informs of Implementation of Amend 169 to Facility Tech Specs
HL-1035, Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists1990-07-25025 July 1990
Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists
HL-1158, Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses1990-06-29029 June 1990
Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses
ML20043E6691990-06-0707 June 1990
Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 13, Per Amend 168 to License DPR-57
ML20043C8621990-05-31031 May 1990
Submits Certification That Operator Licensing Simulation Facility Located at Plant Meets NRC Requirements
ML20043A8081990-05-0707 May 1990
Forwards Response to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-321/90-07 & 50-366/90-07.Encl Withheld (Ref 10CFR73.21)
ML20042F3331990-05-0101 May 1990
Provides Response to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Procedures Address Possibility of Vessel Overfill Events & Training Alert Operators to Potential Overfills
ML20012C6351990-03-14014 March 1990
Responds to Generic Ltr 89-19 Re Safety Implementation of Control Sys in LWR Nuclear Power Plants,Per 890920 Request & Understands That NRC Has Agreed to Extend Response Deadline Until 900504
ML20012B7291990-03-0707 March 1990
Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant,Unit 2 Sept-Dec 1989 & Metallurgical Evaluation of Four Inch Pipe to Elbow Weld from Plant Hatch, Unit 2.
ML20012B1161990-03-0707 March 1990
Forwards Results of Circuit Breaker Testing,Per Bulletin 88-010,per Telcon W/Lp Crocker
ML20012A1261990-03-0101 March 1990
Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey.
ML20012A9051990-02-27027 February 1990
Forwards Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Plant
ML20012B4101990-02-22022 February 1990
Discusses NRC 900221 Granting of Discretionary Enforcement to Continue Shutdown Cooling Operation Until Reactor Level Instrument 1B21-N080A Can Be Returned to Svc.Replacement Expected to Be Completed by 900222
ML20006F4561990-02-20020 February 1990
Responds to Request for Addl Info Re Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matl & Impact on Plant Operations. RTNDT Value for Unit 2 Closure Flange Region Addressed
ML20006D7481990-02-0606 February 1990
Forwards Final Technical Rept, Edwin I Hatch Nuclear Plant Unit 2 Reactor Containment Bldg 1989 Integrated Leakage Rate Test for Fall 1989 Maint/Refueling Outage,Per IE Notice 85-071
ML20006C9481990-01-31031 January 1990
Responds to NRC 900102 Ltr Re Violations Noted in Insp Repts 50-321/89-28 & 50-366/89-28.Corrective Actions:Deficiency Card Documenting Event Initiated as Required by Plant Procedures
ML20006A8911990-01-23023 January 1990
Responds to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Plans to Augment Existing Programs or Implement New Programs to Meet Intent of Generic Ltr
ML20005F9341990-01-10010 January 1990
Offers No Comments Re SALP Repts 50-321/89-22 & 50-366/89-22 Dtd 891205
ML20005E6491990-01-0202 January 1990
Responds to NRC 891208 Ltr Re Violations Noted in Insp Repts 50-321/89-30 & 50-366/89-30.Corrective Actions:Util Personnel Documented Engineering Judgment Used as Basis for Use of Agastat Relays in Question
ML20005E5621989-12-28028 December 1989
Certifies That fitness-for-duty Program Meets 10CFR26 Requirements.Util Screens for Two Addl Substances Not Required by Rule,Benzodiazepine & Barbiturates.List Re Panel & Cutoff Levels Encl
ML20005E1411989-12-28028 December 1989
Responds to Generic Ltr 89-10, Motor-Operated Valve Testing & Surveillance. Thermal Overloads on Most safety-related motor-operated Valves Are Jumpered During Operation.Epri Developing Program to Calculate Valve Thrust Requirements
ML20005D9611989-12-22022 December 1989
Forwards Rev to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20011D8721989-12-21021 December 1989
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor-Darling S350W.... Review of Sys Drawings Determined That No Subj Valves Installed at Facilities
ML19332G0371989-12-13013 December 1989
Summarizes Util Plans to Recaulk & Seal Plant Refueling Floor Precast Concrete Panel Walls,Per 891129 Telcon. Special Purpose Procedure Developed to Ensure That Containment Integrity Maintained During Recaulking
ML19332G0201989-12-12012 December 1989
Forwards Addl Info Re Use of Code Case N-161 for Upgrading Ultrasonic Insp & Testing Instrument Calibr Blocks
ML19332F3571989-12-0707 December 1989
Provides Feedback on NRC Pilot Project Involving Electronic Distribution of NRC Generic Communications.Sys Found to Be Most Useful Re Generic Ltrs & Bulletins Where Timely Receipt Critical
ML19332E1521989-11-29029 November 1989
Responds to NRC 891101 Ltr Re Violations Noted in Insp Repts 50-321/89-19 & 50-366/89-19.Corrective Actions:Procedure 31GO-INS-001-OS Revised to Include Requirements to Record & Compare Valve Stroke Times Following Valve Maint
ML19332D0921989-11-22022 November 1989
Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Closure Plan for USI A-10 Will Be Submitted in 1990.Response to USI A-47 Re Safety Implications of Control Sys Will Be Submitted in Mar 1990
ML19332E4451989-11-21021 November 1989
Certifies That Initial & Requalification License Operator Training Programs at Plant Accredited & Based on Sys Approach to Training,Per Generic Ltr 87-07
ML19327C2451989-11-13013 November 1989
Forwards Amend 13 to Indemnity Agreement B-69
ML19332B9461989-11-10010 November 1989
Forwards Updated Chronological Tabulated List of Outstanding Licensing Requests for Plant.List Identifies Priority Items for Early NRC Approval
ML19327C0321989-11-0606 November 1989
Advises That No Corrections Necessary Re 890331 Response to NRC Bulletin 88-010,Suppl 1.Documentation Available at Plant Site for Review
ML19325E8821989-11-0101 November 1989
Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Contingency Plan Developed Which Has Been Added to Security Plan to Include short-term Actions Against Attempted Sabotage
ML19324B8741989-10-27027 October 1989
Transmits Proposed Program for Completing Individual Plant Exam Process,Per Generic Ltr 88-20 & NUREG-1335.Program Should Identify Method & Approach Selected for Performing Exam
ML19325E5491989-10-27027 October 1989
Submits Update on Lighting Observed During NRC Insp on 891002-06.All Temporary Lighting Reinstalled.Mfg of Four Cluster Lights,Holophane,Has Been Onsite & Will Give Recommendations for Permanent Lighting
ML19327B6151989-10-24024 October 1989
Responds to Generic Ltr 89-16, Hardened Vent, by Encouraging Licensees to Voluntarily Install Hardened Vent Under 10CFR50.59
ML19327B3001989-10-23023 October 1989
Documents NRC Agreement W/Util Justification for Use of Pathway Corp as Replacement Bellows Vendor,Based on 891004 Telcon.Util Proceeding W/Procurement of Replacement Bellows
ML19327B1551989-10-17017 October 1989
Forwards Revs 0 to Corporate Emergency Implementing Procedures,Including HNEL-EIP-01,HNEL-EIP-02,HNEL-EIP-03, HNEL-EIP-04,HNEL-EIP-05,HNEL-EIP-06,HNEL-EIP-07,HNEL-EIP-08, HNEL-EIP-10 & HNEL-EIP-11
ML19325C7451989-10-11011 October 1989
Advises That Effective 890913 Th Hunt No Longer Employed by Util.Operator License Terminated
ML20248H3061989-10-0404 October 1989
Forwards Revised Tech Specs to Util 890622 Application for Amends to Licenses DPR-57 & NPF-5,per NRC Request,Re cycle- Specific Parameter Limits
ML20247G4631989-09-14014 September 1989
Responds to NRC Re Violations Noted in Insp Repts 50-321/89-08 & 50-366/89-08.Corrective Actions:Procedure Revised to Include Periodic Analysis of Fuel Oil Parameters & Change Sampling Methodology
ML20246D4541989-08-22022 August 1989
Forwards Corrected Tech Spec Changes Re Reactor Protection Sys Instrumentation Surveillance Requirements,Per NRC Request
1990-09-04
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