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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: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
[Table view] 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
[Table view] |
Text
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., 1e . g l' W. G. Heirston, Ill '
l W ro' W ePerutwa 1 Nuow o.m m, j HL-882 ,
000071 January 23: 1990 .,
Regional Administrator, Region II U.S. Nuclear Regulatory Comission .
101 Marietta Street,'N.W., Suite 2900 l Atlanta, Georgia - 30323 !
. ATIN: Mr. S. D. Ebneter !
t t,
PLANT HATCH - UNITS 1, 2 1 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 l GENERIC LETTER 89-13, SERVICE WATER -
SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT J l Gentlemen:
i Generic . Letter 89-13, " Service Water System Problems affecting Safety >
Related Equipment" was issued on July 18, 1989 to all holders of' operating
, licenses or construction permits. The generic letter requires licensees to ;
l take actions to ensure that the service water systems are in compliance and will be maintained in compliance with 10 CFR Part 50, Appendix A, General Design Criteria 44, 45, and 46 and Appendix B. Section XI. Licensees are -
required to provide a response indicating plans to implement i
recommendations I-V of the generic letter or advise- the NRC of an equally I ,
1 " effective alternate course of action. Generic Letter 89-13 further states that if an altera tive course of action is chosen, justification that the ;
heat _ removal requirements of the service water system are satisfied by use of the alternative program should be documented and retained in appropriate ,
l ,
plant records. Licensees are also required to provide confirmation to the :
l NRC indicating that all initial tests or activities have been completed and l' that -continuing programs have been established within 30 days after
" implementation.
L In response, Georgia Power Company (GPC) plans to augment existing l' programs or implement new programs to meet the intent of the generic letter with respect to safety-related portions of the service water systems. The attsched enclosure provides a discussion of each of the initial recommended actions along with GPC's response. GPC intends to ,
implement the program as described in the enclosure; however, i,hould more effective methods become available for implementing these actions in the .
future, the program may be revised accordingly. Implementation of the l recommended or equally effective actions and establishment of a continuing program will be complete for both units prior to plant startup following lj 000130044S 900123 FDR ADOCK 05000321 h p/ t as P Poc /
i L
00! hit Power -
l w <
U.S. Nuclear Regulatory Commission l- January 23, 1990 Page'Two ;
i the Unit 1 Fall 1991 refueling outage. A response indicating that all
! . initial tests or activities have been completed and that continuing ,
programs have been established will be submitted within 30 days of the !
- ' final implementation. l 1
Mr. W. G. Hairston, III states that he is a Senior Vice President of I
, Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company and that, to the best of his knowledge and belief, 6
the facts set forth in this letter are true.
GEORGIA POWER COMPANY ,
BY: Id .b. $1N &
W. G. Hairston, III -
Sworn to and subscribed before me this [ day of (}thumu 1990.
(4 . m f' % _$h u, Notaq)Public gygotlA1 510N C S RES M C 15' E 2
Enclosure:
Wvice Water System Problems Affecting Safety-Related Equipment c: Georaia Power Company Mr. H. C. Nix, General Manager - Nuclear Plant ,
Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch '
GO-NORMS U.S. Nuclear Reaulatory Commission. Washinoton. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion 11 Mr. S. D. Ebneter, Regional Administrator -
Mr. J. E. Menning, Senior Resident Inspector - Hatch
ENCLOSURE PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321. 50-366 OPERATING LICENSES DPR-57, NPF-5 GENERIC LETTER 89-13,' SERVICE WATER ,
SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT l RECOMMENDED ACTIONS I. GENERIC LETTER ISSVE I; NRC RECOMMENDED ACTION:
l For open-cycle service water systems, implement and maintain an oagoing program of surveillance and control techniques to- :'
significantly reduce the incidence of flow blockage problems as a result of biofouling. The following program, or an equally effective program, is -acceptable: ,
A. The intak$ structure should be visually inspected, once per l' refueling cycle, for macroscopic biological fouling organisms sediment and corrosion. Inspections should ,
(i.e.,
be Asiatic clams)by performed either scuba divers or by dewatering the intake '
structure or by other comparable methods. Any fouling accumulations should be removed.
B. The service water system should be continuously (for example, during spawning) chlorinated (or equally effectively treated with another biocide) whenever the potential for a macroscopic biological fouling species exists (for example, Asiatic clams at freshwater plants). Precautions should be taken to obey Federal,
- State and local environmental regulations regarding the use of biocides.
C. Redundant and infrequently used cooling loops should be flushed and flow tested periodically at the maximum design flow to ensure that they are not fouled or clogged. Other components in the service water system should be tested on a regular schedule to ensure that they are not fouled or clogged. Service water cooling loops should be filled with chlorinated or equivalently ,
treated water before lay-up. Systems that use raw service water as a source, such as some fire protection systems, should also be chlorinated - or equally effectively treated before lay-up to help prevent microbiological 1y influenced corrosion (MIC).
Precautions should be taken to obey Federal, State and local '
environmental regulations regarding the use of biocides.
l 000071 HL-882 E-1
ENCLOSURE (Continued) !
GENERIC LETTER 89-13, SERVICE WATER l SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT )
RECOMMENDED ACTIONS i
D. Samples of water and substrate should be collected annually to I determine if Asiatic clams have populated the water source. .j Water and substrate sampling is only necessary at freshwater '
plants .that have not previously~ detected the presence of j freshwater clams in their source water bodies. If Asiatic clams ;
are detected, this sampling activity may be discontinued if !
desired and the chlorination treatment program should be modified ,
to be in agreement with paragraph B, above. ]
GPC RESPONSE:
A. GPC has previously performed visual inspections and cleaning of !
the Plant Hatch service water intake structure through implementation of procedure 52PM-MME-006-0, " Intake Pit Suction i Inspection". The existing program will be reviewed and revised '
as necessary with regard to the visual inspection and cleaning of the intake structure by means cf scuba divers to remove accumulations of macroscopic biological fouling organisms and t sedimentation to the extent practical. The intake structure.at Plant Hatch is common for both Units 1 and 2. Corrosion of the intake structure is not a problem since the intake structure is constructed of concrete. The next inspection is currently i planned for the summer of 1991. Future inspections will +
initially be established on a once per refueling cycle frequency.
The inspection frequency will be revised, if necessary, based on the results of inspections.
B. GPC currently has a program in place to chlorinate the service water system during periods when needed. This chlorination process is in accordance with the existing plant effluent discharge permit. A review of the existing chemical treatment programs associated with the service water systems with regard to biofouling, corrosion, and silting will be performed. The program will be augmented, if appropriate, to meet the intent of the recommendations provided in the Generic letter. Future biocidal treatments will continue to comply with environmental regulations regarding the use of biocides.
C. The service water system at Plant Hatch is basically a once through system. The appropriate maintenance and operations programs will be reviewed and revised, as appropriate, to periodically flush, or operate low flow or infrequently used portions of the service water system.
000071 HL-882 E-2
a - . - . -
F g, jA
- i ENCLOSURE (Continued)
GENERIC LETTER 89-13 SERVICE WATER I SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT RECOMMENDED ACTIONS i i
Inspection or testing for fouling may be used in lieu of flushing l or operation. The program will be developed for both units prior j to startup from the Unit 1, Fall 1991 refueling outage. The schedule for flushing, operation, inspecting, or testing will be l determined as part of the overall program, i
Actions necessary to restore deficient conditions identified will !
be addressed by the inspection and maintenance programs and 1 procedures corresponding to the actions for Generic letter i Issue III. 1 The Plant Hatch program for testing safety-related heat j exchangers is addressed in the response for Generic Letter ;
Issue II. Other service water system components (i.e., vents, '
drains, instrument lines) are not included in this program.
The fire protection system would normally receive water from deep draft wells rather than from the Altamaha River. Consequently, chlorinating or equivalently treating the fire protection water suppression system is not required. Connections between the '
service water system and the fire protection water system exist but are intended only as a backup water sources for the systems.
The connection point between the service water and fire protection systems will be considered in the scope of this program.
D. Samples of water and substrate will be collected annually to .
determine the extent to which Asiatic clams may have populated the water source. Historically, Asiatic clams have not been a
~
problem at Plant Hatch. We will continue the sampling program and take appropriate actions based on the results of water and substrate sample analyses, i
h l
000071 HL-882 E-3
i ENCLOSURE (Continued)
GENERIC LETTER 89-13, SERVICE WATER l SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT l RECOMMENDED ACTIONS II. GENERIC LETTER ISSUE II; NRC RECOMMENDED ACTION:
Conduct a test 3rogram to verify the heat transfer capability of all I safety-related leat exchangers cooled by service water. The total I test program should consist of an initial test program and a periodic l retest program, and should include heat exchangers connected to or i cooled by one or more open-cycle systems. The initial frequency for i the periodic retesting should be at least once ser fuel cycle, but j after three tests, licensees and applicants s1ould determine the '
best frequency for testing to provide assurance that the equipment ;
will perform the intended safety functions during the intervals )
between tests and meet the requirements of GDC 44, 45, 46. The 1 minimum final testing frequency should be once every five years. A summary of the program should be documented, including the schedule for tests, and all relevant documentation should be retained in appropriate plant records.
The need for testing of closed-cycle system heat exchangers has not been considered necessary because of the assumed high quality of existing chemistry control programs. If the adequacy of these chemistry control programs cannot be confirmed over the total operating history of the plant or if during the conduct of the total l testing program any unexplained downward trend in heat exchanger performance is identified that cannot be remedied by maintenance of an open-cycle system, it may be necessary to selectively extend the test program and the routine inspection and maintenance program addressed in Action III below to the attached closed-cycle systems.
J Testing should be done with necessary and sufficient instrumentation, though the instrumentation need not be permanently installed. The relevant temperatures should be verified to be within design limits.
If similar or equivalent tests have not been performed during the ,
past year, the initial tests should be completed before plant startup !
following -the first refueling outage beginning nine months or more .l after the date of this letter. I l
As a part of the initial test program, it may be decided to take l corrective action before testing. Tests should be performed for the l heat exchangers after the corrective actions are taken to establish i baseline data for future monitoring of heat exchanger performance.
In the periodic retest program, the best frequency for testing to i provide assurance that the equipment will perform the intended safety functions during the intervals between tests should be determined j l
l 000071 HL-882 E-4
l I
ENCLOSURE (Continued) )
GENERIC LETTER 89-13, SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT ;
1 RECOMMENDED ACTIONS after the completion of three tests. Therefore, in the periodic retest program, testing should be performed for the heat exchangers 4 before any corrective actions are taken. As in the initial test program, tests should be repeated after any corrective actions are ;
taken to establish baseline data for future monitoring of heat 1 exchanger performance. l An example of an alternative action that would be acceptable to the NRC is frequent regular maintenance of a heat exchanger in lieu of testing for degraded performance of the heat exchanger. This ,
alternative might apply to small heat exchangers, such as lube oil coolers, pump bearing coolers or readily serviceable heat exchangers !
located in low radiation areas of the facility. i The following program, or an equally effective program to ensure satisfaction of the heat removal requirements of the service water i system, is acceptable:
)'
A. All Heat Exchangers Monitor and record cooling water flow and inlet and outlet 4 temperatures for all affected heat exchangers during the modes of i operation in which cooling water is flowing through the heat l p exchanger. For each measurement, verify that the cooling water t
temperatures and flows are within design limits for the l conditions of the measurement. The test results from periodic l testing should be trended to ensure that flow blockage or -l L
excessive fouling accumulation does not exist. j l
B. Water-to-Water Heat Exchangers (In Addition to item A above) 1 1
- 1. Perform functional testing with the heat exchanger operating, if practical, at its design heat removal rate to verify its I capabilities. Temperature and flow compensation should be l made to adjust the results to the design conditions. Trend l the results, as explained above, to monitor degradation. '
- 2. If it is not practical to test the heat exchanger at the design heat removal rate, then trend test results for the I heat exchanger efficiency or overall heat transfer l coefficient. Verify that heat remnval would be adequate for the system operating with the most limiting combination of I flow and temperature.
000071 HL-882 E-5
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! l ENCLOSURE (Continued) l
' r GENERIC LETTER 89-13, SERVICE WATER .'
f SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EOUIPMENI I RECOMMENDED ACTIONS
- C. Air-to-Water Heat Exchangers (In addition to Item A above) l
- 1. Perform efficiency testing (for example, in conjunction with surveillance the maximumtesting)d heat loa thatwithcan thebe heat obtainedexchanger practically operating andunder correct the results for off-design conditions. Verify design heat removal capacity and trend results to identify any degraded equipment. .
- 2. If it is not possible to test the heat exchanger to provide statistically significant results (for example, if error in i the measurement exceeds the value of the parameter being measured), then trend test results for both the air and water ,
flow rates in the heat exchangers and perform visual inspections, where possible, of both the air and water sides of the heat exchanger to ensure cleanliness of the heat exchanger. !
D. Heat Exchangers Other than Water-to-Water and Air-to-Water (In Addition to Item A above) t
- 1. If plant conditions allow testing at design heat removal l- conditions, verify that the heat exchanger performs its intended functions and trend the test results to monitor degradation. -
- 2. If testing at design conditions is not possible, then provide for extrapolation of test data to design conditions. The heat exchanger efficiency or the overall heat transfer coefficient of the heat exchanger should be determined whenever possible. Where possible, provide for visual -
inspection of the heat exchanger.
GPC RESPONSE:
GPC will develop and implement a test program for both units prior to startup from the Unit 1 Fall 1991 refueling outage to verify the acceptable performance of safety-related heat exchangers cooled by the service water system. The test program will consist of an initial test with periodic retest. The initial test and periodic l
retesting program will consider the EPRI Guidance published in their l
interim report titled, " Heat Exchanger Performance Monitoring l Guidelines for Service Water Systems" as much as practical, u
l l 000071 HL-882 E-6
9 I
I ENCLOSURE (Continued) [
GENERIC LETTER 89-13. SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENI RECOMMENDED ACTIONS The results of the initial test, operating history, and performance criteria will be used to determine the appropriate frequency for .
future testing to provide assurance that the equipment will perform the intended safety functions during the intervals between tests. '
Based on the results of initial tests, a given heat exchanger may not i be tested initially for three consecutive cycles and a retest interval greater than five years may be established. In cases where the testing frequency is greater than the recommended frequency, sufficient justification to provide assurance that the equipment will t' perform the intended safety function during the intervals between tests will be developed. All relevant documentation will be retained in appropriate plant records. j Testing of the safety-related heat exchangers cooled by service water :
will be performed with sufficient instrumentation, using both permanently installed and temporary instrumentation. The test '
program will address the evaluation of the heat exchanger performance i with respect to design limits. A summary of the test program <
including test schedules and bases will be documented. .
Actions necessary to restore deficient conditions identified during the initial testing and periodic retests will be addressed by the inspection and maintenance program and procedures corresponding to the actions for Generic Letter Issue III. The program will ensure !
that tests are conducted before and after any corrective actions that could impact the performance of heat transfer capabilities (e.g.,
cleaning or plugging tubes).
In some cases regular maintenance of a heat exchanger may be implemented in lieu of testing.
000071 HL-882 E-7 p
E
1 ENCLOSURE (Continued) l GENERIC LETTER 89-13, SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EOUIPMINI ;
RECOMMENDED ACTIONS j
III. GENERIC LETTER ISSVE III; NRC Recomended Action Ensure by establishing a routine inspection and maintenance program for open-cycle service water system piping and components that corrosion, erosion, proter.tive coating failure, silting and biofouling cannot degrade the performance of the safety-related ;
systems supplied by service water. The maintenance program should have at least the following purposes: ;
- 1. To remove excessive accumulations of biofouling agents, corrosion 1 1:
products, and silt; ;
- 2. To repair defective protective coatings and corroded service -
water system piping and components that could adversely affect performance of their intended safety functions.
This program should be established before alant startup following the first refueling outage beginning 9 montis after the date of this -
letter. A description of the program and the results of these i maintenance inspections should be documented. All relevant j documentation should be retained in appropriate plant records.
?
GPC RESPONSE:
GPC has previously inspected portions of the service water system :
piping utilizing ultrasonic testing to identify pipe thinning and pipe blockage. Where appropriate, corrective actions have been '
implemented. The corrective actions include replacement of some portions of the safety-related carbon steel lines with stainless steel. GPC also plans to begin adding a chemical dispersant to the service water system in 1991 to remove suspended solids from the service water. The current inspection and maintenance programs in place at Plant Hatch will be reviewed and, if required, augmented to ensure that corrosion, erosion, silting and biofouling of piping and components of the service water systems will not adversely affect the l performance of the safety-related heat exchangers in the systems.
l: The program will be largely based on plant historical data to identify system inspections and nondestructive testing required to establish baseline conditions.
000071 HL-882 E-8
ENCLOSURE (Continued)
GENERIC LETTER 89-13, SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED E0VIPMENT RECOMMENDED ACTIONS A description of the inspection and maintenance program will be documented as well as inspection results.
IV. GENERIC LETTER ISSUE IV; NRC RECOMMENDED ACTION:-
Confirm that the service water systems will perform its intended function in accordance with the licensing basis for the pl ant.
Rectmstitution of the design basis of the system is not intended.
This confirmation should include a review of the ability to perform required safety functions in the event of failure of a single active component. To ensure that the as-built systems is in accordance with the appropriate licensing basis documentation, this confirmation .
should include recent (within the past 2 years) system walkdown inspections. This confirmation should be completed before 31 ant startup following the first refueling outage beginning 9 montis or more after the date of this letter. Results should be documented and retained in appropriate plant records.
GLC_RE.SP_QMSI:
GPC will confirm the ability of the systems to perform in accordance with the licensing basis of the plant. A review model of the plant service water system will assure the current as-built configuration of the system, based on plant walkdown and design information. A document will be developed which provides system piping data and an equipment thermal and hydraulic data base which includes design pressure drop, flow, and heat loads as well as physical heat exchanger Heat data (e.g.,
exchanger type, materials,tubearrangementandnumbergF performance will be based on the design maximum 95 service water temperature. The analysis of LOCA mode will consider the effect of single failure predictions on the capability to remove accident heat loads.
000071 HL-882 E-9 1
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o
- ~ i ENCLOSVRE (Continued)
GENERIC LETTER 89-13, SERVICE WATER SYSTEM PROBLEMS AFFECT.jr SAFETY-RELATED EQUIPMENT RECOMMENDED ACTIONS e 'V. GENERIC LETTER ISSVE V; NRC RECOMMENDED ACTION:
r Confirm that maintenance practices, operating and emergency procedures, and training that involves the service water system, are adequate to ensure that safety-related equipment cooled by the 1 service water system will function as intended and that operators of '
this equipment will perform effectively. This confirmation should include. recent (within the past 2 years) reviews of practices, ,
procedures and training modules. The intent of this action is to '
reduce human errors in the operation, repair and maintenance of the service water system. This confirmation should be completed ,
before plant startup following the first refueling outage beginning ,
9 months or more after the date of this letter. Results should be documented and retained in appropriate plant records.
GPC RESPONSE:
GPC has recently completed the Procedure Upgrade Program (PUP) that reviewed and, as necessary, revised safety-related plant procedures for both units. The PUP charter was to verify the technical adequacy and usability of the plant procedures. GPC intends to confirm the adequacy of maintenance practices, operating procedures, and E0Ps by utilizing the information, evaluations, and procedures developed in response to Generic Letter Issue I through IV. The training program will be made consistent with the importance of the operation of the safety-related equipment cooled by the Service Water Systems. These actions will be documented in the appropriate plant records.
000071 HL-882 E-10 t
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