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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
Georg a F%er Company 333 Pedmont Avenue Atlanta, Georga 30308 Telepticre 4LM 5Tr6526 t Off 4545 Atlanta. Georg:a 30302 h Georgia Power L r. cuewa w m'-w k w m uanager naciear Eno.neereg at Chief NucMar Engmer g,g,g 2017N September 9, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 RESPONSE TO REQUEST FOR INFORMATION REGARDING IMPLEMENTATION OF NEW EMERGENCY OPERATING PROCEDURES Gentlemen:
Georgia Power Company (GPC) hereby submits our response to comments contained in your letter and Safety Evaluation Report (SER) dated June 5,1985 regarding implementation of new Emergency Operating Procedures (EOPs). Also attached is Revision 1 to the Procedures Generation Package (PGP), which has been issued to address recent plant design changes and comments provided in the subject SER. The Plant-Specific Technical Guideline (P-STG) is currently being revised. However, none of the P-STG revisions being made specifically relate to the SER comments.
Please contact this office if you have any further questions or comments.
Very truly yours,
~b QO h L. T. Gucwa PLS/mb Attachment A C((3 4 00'. TE/odet]EFS xc: Mr. J. T. Beckham, Jr. 18//>M/IltB 8CY Mr. H. C. Nix, Jr.
Dr. J. N. Grace (NRC-Region II) #CV Senior Resident Inspector MtE/Dir/AES h
F
i ATTACHMENT 1 TO LETTER NED-85-579 RESPONSES TO SER ITEMS REGARDING PLANT HATCH EMERGENCY OPERATING PROCEDURE IMPLEMENTATION GEORGIA POWER COMPANY SEPTEMBER 9, 1985 L
A. PLANT SPECIFIC TECHNICAL GUIDELINES (P-STGs)
SER ITEM A.1:
Deviations from and additions to the generic guidelines that are of safety significance must be identified in the P-STG. In addition, analyses or other technical justification supporting these deviations and additions must be provided for both Units 1 and 2.
GPC RESPONSE:
The Plant-Specific Technical Guideline (P-STG) does not include any significant additions to the generic guidelines. The only deviations from the generic guidelines are deletion of plant features referenced in the Emergency Procedure Guidelines (EPGs) that do not exist in the plant
, (e.g., Mark II and Mark III containment, isolation condenser and high pressure core spray), and substitution of Hatch-specific parameters calculated in accordance with instructions provided with the BWR Owners Group EPGs. All of the deletions are in accordance with the instructions of the NRC-approved EPGs, and none of the deletions are considered to be of safety significance. Accordingly, no supplemental analysis or technical justification supporting the deviations is appropriate. ;
SER ITEM A.2:
The PGP should discuss how the additions and deviations are to be verified / validated.
GPC RESPONSE:
l Subsection 2.12 of the E0P implementation plan states that the i verification process will verify that the "EOPs are technically correct and accurately reflect the technical guidelines." Verification was performed independently by the plant STA staff. The plant QA department also reviewed the P-STG and determined that the P-STGs have been prepared by a program that is in accordance with the requirements of
- NUREG-0899.
I As stated in the response to SER Item A.1, we have made no deviations of i
safety significance or that are counter to the instructions of the 1
generic guidelines or the guidance of NUREG-0899. A documented review has been performed to verify that conversion from EPG to P-STG was technically correct, and that controls and instrumentation called for in the E0Ps exist, and that verbatim nomenclature has been used.
The intent of validation of the E0Ps is to ensure that they are usable, i
understandable, compatible with expected crew composition, and that 4
appropriate guidance is provided to mitigate the effects of transients
-n --. <-, - , -, ,,n . _ . - - , , , , , , , - ~ _ , - . , , - _ , . , , , - , - - - . . . , ,,-n,-w,, ,.--n-., -
and accidents. Based on this definition, which is widely accepted in the industry, validation is appropriate only for the finished procedure derived from the P-STG, but not directly applicable to a technical bases document such as the P-STG. Notwithstanding the preceding, deficiencies identified by the validation program may require changes to the P-STG for correction.
The ~ verification and validation (V&V) sections (3.6 and 3.7, respectively) of the implementation plan have been expanded to clarify the definition and intent of the V&V program as described above. Also see the responses to the SER Section C on verification and validation.
SER ITEM A.3: .,
- a. GPC should explicitly identify the plant-specific information and control needs, which are necessary for preparing E0Ps and determining the adequacy of existing instrumentation and controls.
- b. GPC must describe the process used to identify plant-specific parameters and other plant-specific information and control capability needs and must describe how the characteristics of needed instruments and controls will be determined.
- c. For each instrument and control used to implement the E0Ps, there should be an auditable record of how the needed characteristics of the instrument and controls were determined. These needed characteristics should be derived from the information and control needs identified in NRC-approved EPGs and from analysis of plant-specific information.
GPC RESPONSES:
- a. Information and control needs will be evaluated as part of the Detailed Control Room Design Review (DCRDR) described in the DCRDR program plan transmitted to the NRC by letter NED-84-556, dated October 23, 1984. Information and control needs will be derived from the generic EPGs. The control room equipment will then be reviewed to identify any discrepancies. The discrepancies will then be evaluated and resolved as described in the DCRDR program plan.
- b. Plant specific parameters and plant specific information and control needs for emergency operations will be derived from the EPGs as part of the DCRDR program. Per the instructions of the NRC-approved EPGs, existing plant instrumentation and controls (I&C) with verbatim nomenclature are used in the E0Ps. The E0P implementation plan does not include a program to evaluate instrumentation and control needs and characteristics. Rather, it is the DCRDR program that evalurf.es plant capability in accordance with NUREG 0737, Supplement 1 (Generic Letter 82-33). This is intended to be an integrated process per the requirements of the generic letter. The E0P implementation plan, therefore, should not be reviewed in isolation, but rather as part of an integrated process to upgrade plant emergency response capability as described in the GPC response to the referenced generic letter. The PGP
, implementation plan (pages 17 of 36 through 21 of 36) has been revised to clarify this point and to reference the DCRDR program plan.
- c. Item A.3.c is also addressed as part of the DCRDR program per the instruction of the NRC. There will be an auditable record of how the needed characteristics of the instrument and controls were determined. Details of how this . is accomplished are provided in the DCRDR program plan. The E0P implementation plan has been revised to reference the appropriate sections of the DCRDR program plan.
B. PLANT SPECIFIC WRITER'S GUIDE SER ITEM B.1:
The writer's guide should be revised to include all the necessary information and guidance for translating the P-STGs into E0Ps (e.g.,
what actions steps identified in the P-STG will be included in the flow charts and which ones will be included in the end-path-manual).
GPC RESPONSE:
Actions needed to bring the plant to a known stable condition, and near-term actions needed to protect plant equipment are included in the flow charts. Instructions for long-term plant recovery are in the end-path-manual. Subsections 8.1.6.2 and 8.1.6.3 of the writer's guide have been expanded to provide criteria for placement of action steps in
, the flow charts and end-path-manuals. Detailed instructions for translating the P-STG into an E0P have been added to the writer's guide
, as Section 9.
SER ITEM B.2:
The following items of concern related to flow charts were identified:
- a. The writer's guide should be revised to clarify how the information in the cover procedures can be available to the operator early in an emergency.
- b. Section 8.2, which is the section that addresses flow charts, should be expanded to include the following:
A
- 1. If written material is to be in capital letters, as shown in the example on page 63, then instructions to this effect should be provided in Section 8.2.
- 2. If cautions are to be highlighted with asterisks, as shown in the example on page 63, then instructions to this effect should be provided in Section 8.2.
- c. To ensure that the E0Ps are easily accessible in an emergency, the accessibility and availability of the flow charts should be addressed in the writer's guide, i
- d. To ensure the legibility of reduced copies of the flow charts, the minimum size for symbols, lines, and type should be specified in the writer's guide.
- e. Several reproduction methods for flow charts are discusseu *n Subsection 8.2.19, on page 22 of 70. This subsection shoul u revised to specify that any flow charts intended for use by the operators in an emergency must be of the same quality as a legible original. The same color coding, as specified in Subsection 8.2.21 on page 22 of 70, must be preserved.
GPC RESPONSES:
- a. Information contained in the cover procedures is background information which is not referenced during the initial stages of an emergency. Cautions and notes needed while the flow charts are in use are placed on the flow chart. The cover procedures are reviewed during training and may be referenced following an event once the plant condition is stabilized and the operators have exited the flow chart. Subsection 8.1.6.1 has been expanded to clarify the intended use for the cover procedure, b.l. Written material on the flow charts is all capital letters to enhance legibility of the reduced size print. The writer's guide, 4
Section 8.2.5, has been revised to clarify this point.
b.2. Asterisks will not be used for highlighting in the Hatch E0Ps. The writer's guide has been revised to delete the referenced example.
- c. The implementation plan, Section 3.14, has been revised to specify the intended location for storage of the flow charts and end-path-manuals. Accessibility and availability of the E0Ps will be evaluated as part of the DCRDR, and any feedback will be incorporated into the E0P implementation plan.
- d. Subsection 8.2.20 of the writer's guide has been revised to address requirements for copies of the flow charts. A specification for symbol size, line width, and type has been added to the writer's guide. See pages 76 of 84 through 78 of 84.
- e. Only originals of the flow charts will be provided for use by the operators in an emergency. Consistent quality, including color, line width, size, shape of symbols, etc., is assured by a detailed specification, and by the quality assurance program of the vendor providing computer aided drafting services for the flow charts.
The writer's guide has been revised to clarify requirements for originals and copies of the flow charts. See Subsections 8.2.19 through 8.2.21.
SER ITEM B.3:
The writer's guide should address the formatting for the following types of action steps for both the flow charts and end-path-manuals:
- a. Steps used to verify whether the objective of a task or sequence of actions has been achieved.
- b. Steps which are repeatedly performed.
, c. Steps for which a number of alternative actions are equally acceptable.
- d. Steps performed concurrently with other steps.
GPC RESPONSE:
Subsections 8.2.7 and 8.2.8 (flow charts) and Subsection 8.3.7 (end-path-manuals) were written to specify formatting of action steps. These subsections have been revised as needed to address SER Items B.3.a through B.3.d, using the guidance of NUREG-0899, Section 5.7.
i SER ITEM B.4:
The manner in which the text is organized and divided should be evident through the use of headings and a numbering system. Several sections of the end-path-manuals are described in Subsection 8.1.6.3, on page 13 of 4
- 70. However, the following additional information should be provided:
- a. The intended sequencing of the sections listed in Subsection 8.1.6.3 should be stated and should include a description of the r content and format of headings and an example. l
- b. A method to permit rapid access to the various sections should be I specified. ,
r GPC RESPONSE: '
l
- a. The requested revision has been made to the writer's guide. See Subsection 8.1.6.3.6.
t
. - - , ,m.
- b. A grid system, described in Subsection 8.2.18, is used to permit rapid reference to sections of the flow charts. A system of tabs and section titles, described in Subsection 8.1.6.3.7, is incorporated into the end-path-manuals. The applicable sections of the writer's guide have been revised to provide additional detail on methods employed to provide convenient and rapid access to sections of the E0Ps.
SER ITEM B.5:
Subsection 8.3.10.8, on page 56 of 70, states that reverse page printing may be used to keep certain curves associated with the procedural text in the same area of view. This subsection should be revised to include guidance on the location of curves and tables that will not be placed on ,
the reverse page.
GPC RESPONSE:
The referenced subsection has been revised to specify that curves and tables not tied to a specific section in the body of the procedure will be placed at the end of that procedure as an attachment.
SER ITEM B.6:
Since copies of the end-path-manuals should be complete (contain all of the information from the original) and legible, the criteria regarding completeness and legibility of the reproduced copies should be addressed in the writer's guide.
GPC RESPONSE:
Subsection 8.3.10.9 has been added to the writer's guide to specify requirements for copies of the end-path-manual.
SER ITEM B.7:
The following errors or inconsistencies were identified:
- a. The verification step number 3.0, in Attachment 7, directs the operators to verify that all control rods are fully inserted, whereas the contingency step specifies an action only if two or more roas are not fully inserted. No guidance is given for the situation in which only one control rod is not fully inserted.
This discrepancy should be corrected.
- b. The place-keeping aids that are specified in Subsection 8.3.6.3, on page 30 of 70, are not included in the example in Attachment 7.
This discrepancy should be corrected.
- c. The logic terms that are used in the flow chart example in Attachment 4 and the example in Subsection 8.2.12, on page 20 of 70, are not underlined for emphasis as specified in Subsection 8.3.7.4.1, on page 45 of 70. The examples should be corrected.
- d. The guidance on when to list conditions or objects of action words differs between Subsection 8.3.6.9.4, on page 35 of 70, and e
8.3.7.4.4, on page 45 of 70. This difference should be corrected.
- e. The "G0 TO PATH 3" action step at the bottom right of path 1 (Attachment 4) should be a PATH TO PATH arrow.
- f. The entry point, "ANY SCRAM," into the Flow Path 1 ( Attachment 4) at the bottom right appears to be in error and should be removed.
- g. The example Caution in Attachment 7 is not consistent with the guidance provided for Cautions in Subsection 8.3.6.5.2, and the information in the example should be a Note not a Caution. These errors should be corrected.
GPC RESPONSE:
a&b. Attachment 7, which contained the errors noted, has been deleted from the writer's guide. Attachment 7 provided guidance for optional dual-column procedure format, which will not be used.
- c. It was intended that logic terms be underlined only in the end-path-manuals. For improved legibility with the smaller print,
, underlining is not used in the flow charts. The writer's guide has been revised to clarify requirements for underlining. See Subsection 8.3.7.4.1.
- d. The noted discrepancy has been corrected. See the referenced sections in the revised writer's guide.
e&f. The examples noted are considered correct as written. The writer's guide, Attachment 5, has been revised to define the " Scram Entry" symbol.
- g. The offending section has been deleted from the writer's guide for the reason noted in the response to SER Item B.7.a&b.
SER ITEM B.8:
For consistency and clarity:
- a. The sample list of acceptable verbs and definitions (Attachment 8) should be finalized to include all acceptable terms,
- b. The list, from (a) above, should be expanded to include words to avoid (e.g., frequently, quickly, slowly).
- c. Abbreviations, symbols, and acronyms are discussed in Subsection 8.3.6.12, on page 38 and 39 of 70. To ensure that abbreviations, symbols, and acronyms are recognizable by the operators, an acceptable list of these items should be included in the writer's guide.
- d. Two types of page format, for the end-path-manual, are discussed in Subsection 8.3.6.2, on page 29 of 70. However, a single format '
should be specified so multiple writers will produce consistent procedures.
- e. Encouraging variations in the writer's guide can lead to procedures that are inconsistent and may be confusing to the operators, therefore Section 3.6, on page 57 of 70, should be deleted,
- f. Unit identification is specified for the flow charts in Section 8.2.3, on page 17 of 70. Similar guidance should be specified for the end-path-manuals.
GPC RESPONSE:
, a. The sample list of verbs is intended to include only frequently used verbs. A list of all acceptable verbs would be large and would be. overly restrictive if certain verbs were omitted due to oversight. Acceptable word usage and style is appropriately handled by Subsection 8.3.6.9 of the writer's guide.
- b. A guide on style and word usage, Subsection 8.3.6.9, is included in the writer's guide. Subsection 8.3.6.9.7 has been expanded to provide more detail on words to avoid in the E0Ps.
- c. A list of abbreviations, symbols, and acronyms is contained in the P-STG. The writer's guide, Subsection 8.3.6.12.1, has been revised to include a reference to that list.
- d. As noted previously, optional use of the dual-column format has been discontinued. Attachment 7, which provided criteria for dual-column formats, has been deleted from the writer's guide.
- e. We agree with the recommendation; the offending statement has been revised,
- f. Consistent with a recently implemented system for numbering Hatch procedures, the unit number is designated in the last digit of the procedure number. Numeral zero (0) is used to designate that the procedure applies to both units. A reference to the unit designation in the numbering system has been added to the writer's guide in Attachment 3.
SER ITEM B.9:
The numbering of instructional steps is discussed in Subsection 8.3.6.3, on page 30 of 70. This subsection should be revised to address the following items:
- a. Substep numbering down to the level of 1.1.1.1.1 may be greater than can adequately handled (sic) in the dual column format.
Consideration should be given to limiting the substeps to the 1.1.1 level.
- b. The step numbering in Attachment 7 uses the format 1.a, for substeps, rather than 1.1 format specified in Subsection 8.3.6.3.
The example should be changed to be consistent with system specified.
- c. Guidance should be provided, in the text, on the numbering of the '
contingency steps.
GPC RESPONSE:
- a. Optional use of dual column format specified in Attachment 7 has been deleted from the writer's guide. Substep numbering to the
, level of 1.1.1.1.1 will be retained in the single column format now specified exclusively.
- b. The error noted in SER Item B.9.b was eliminated when Attachment 7
- (dual column format) was deleted from the writer's guide.
- c. Subsection 8.3.6.3 provides requirements for substep numbering, including those in the contingency procedures. Subsection 8.3.2.3.2 describes the numbering system for all end-path-manual procedures, including the contingency procedures.
C. E0P VERIFICATION / VALIDATION SER ITEM C.1 The Implementation Plan should be revised to describe the specific methods that will be useo to verify and validate the E0Ps.
GPC RESPONSE:
E0P verification (confirmation that the E0Ps are technically correct, correctly implement the generic guidelines, and use verbatim nomenclature), was performed by the Plant Hatch Shift Technical Advisor (STA) staff in accordance with instructions which-have now been issued as Plant Procedure 30AC-0PS-006-0S. The procedure implements the
applicable INP0 and NRC guidance for E0P verification. The E0P implementation plan has been revised to expand the verification section, and to reference the specific procedure used for verification.
E0P validation (confirmation that the E0Ps are usable, understandable, compatible with expected crew composition, and provide appropriate guidance to mitigate the effects. of accidents and transients) will be performed in conjunction with the DCRDR program in accordance with the requirements of NUREG-0737, Supplement 1 (Generic Letter 82-33). The E0P implementation plan has been revised to expand the description of the validation program and to reference applicable sections of the DCRDR program plan.
SER ITEM C.2:
The verification / validation program should be expanded to include the criteria for selection of the team and to clearly identify their roles and responsibilities. As a minimum, the team should include technical writers and subject matter experts in addition to the operators and personnel specified.
GPC RESPONSE:
The verification process as defined for E0Ps ensures only that the procedures are technically correct and conform to existing plant instrumentation and control equipment. In view of this narrow purpose, a multidisciplinary team is not needed for this task. The STA staff possesses the requisite abilities to fulfill this purpose.
The validation process will be conducted by a multidisciplinary team as part of the DCRDR program described in the DCRDR program plan, dated October 23, 1984.
The E0P implementation plan has been revised to expand the description of the verification / validation process, and to provide appropriate references to the DCRDR program plan. See implementation plan Section 3.6 (verification), and Section 3.7 (validation).
1 SER ITEM C.3:
In Subsection 3.7, on page 16, GPC states that "multipla-event scenarios" will be used to exercise the E0Ps. This section snould be expanded to state -that multiple (simultaneous and sequential) failures shall be used to validate the E0Ps.
GPC RESPONSE:
It was intended that scenarios would be challenging, and would include single events and both simultaneous and sequential multiple events. The requested change has been made in the implementation plan.
SER ITEM C.4:
The validation program should include a description of the criteria that will be used to select the scenarios to be run during the validation process. For those parts of the E0Ps that cannot be validated on the simulator, the criteria for selecting additional validation that may be used, such as a control room walkthrough, should be described.
GPC RESPONSE:
Criteria used to develop scenarios are provided in the DCRDR program plan. As noted previously, the E0P implementation plan has been expanded to provide more detail on the V & V process and to provide appropriate references to the DCRDR program plan.
SER ITEM C.5:
The use of the verification / validation process for revisions should be discussed in the Implementation Plan. This should include the criteria to determine when verification / validation is required.
GPC RESPONSE:
Procedure 30AC-0PS-006-0S contains requirements for verification of the E0Ps. Procedure 30AC-0PS-007-0S contains the instructions for revising the E0P, including a checklist for determining which sections of the verification plan should be performed. The writer's guide, Subsection 8.2.21, has been revised to reference the requirements for revisions to the E0Ps.
SER ITEM C.6:
A description should be provided of the method by which multiple units will be handled in the verification / validation process to account for unit differences, if the differences are significant.
GPC RESPONSE:
Due to differences in equipment numbering and small design differences between the twin units, E0P verification will be performed separately
- for each Hatch Unit. E0P validation for both Hatch units will be performed primarily on the Hatch Simulator, which is based on the design of Unit 2. Differences between the two units and the simulator that affect the validation program will be evaluated either table-top or in the main control room as appropriate. Because of the close similarity ,
between the twin units, and because of the high degree of fidelity of the simulator, differences are not expected to be significant from the standpoint of E0P validation. See Section 3.7 of the implementation olan for additional det?il, 1
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D. E0P TRAINING PROGRAM SER ITEM D.1:
The training program description should indicate. that all E0Ps will be exercised by each operator.
GPC RESPONSE:
This was intended. The requested revision has been made (Subsection 3.8.1.2).
SER ITEM D.2:
The training program description should state that the objectives of Subsection 3.2 (Crew and Shift Policy Characteristics) of the Implementation Plan will be included in the training program. i GPC RESPONSE:
The E0Ps and the training program have been developed so that they are compatible with the minimum shift complement required by the Technical l Specifications. Section 3.2 has been revised to clarify this point.
1 SER ITEM D.3:
If major changes are made in the E0Ps as a result of the training
! feedback, the training program should include description of how GPC
! will ensure that the needed retraining will be controlled and performed.
, GPC RESPONSE:
4
) It is expected that changes to the E0Ps will be required as a result of
' training feedback. The implementation plan, Subsection 3.8.1.2, has been revised.to clarify how follow-up training will be conducted.
SER ITEM D.4:
GPC indicates, in Subsection 3.8.8 on page 26 of 29, that single and l multiple events will be used during simulator training. This should be revised to state that the multiple events will include simultaneous and i
sequential failures.
GPC RESPONSE:
This was intended. The requested revision to the training program i
description has been made.
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ATTACHMENT 2 TO LETTER NED-85-579 PLANT HATCH UNITS 1 & 2 E0P PROCEDURES GENERATION PACKAGE, REVISION 1 GEORGIA POWER COMPANY SEPTEMBER 9, 1985 l
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