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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 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 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 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 ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted 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 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 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-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 ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 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 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-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 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 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 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 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-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-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-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 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-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-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 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 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-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 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 HL-5679, Submits Response to RAI Re Extended Power Uprate LAR1998-09-11011 September 1998 Submits Response to RAI Re Extended Power Uprate LAR ML20155A5701998-09-0808 September 1998 Forwards Final Exercise Rept for 980520 Post Plume Phase Exercise of Offsite Radiological Emergency Response Plans site-specific to Hatch Nuclear Power Plant.No Deficiencies or Areas Requiring C/A Identified During Exercise 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 HL-1183, Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 19901990-08-27027 August 1990 Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 1990 ML20028G8441990-08-27027 August 1990 Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 1990. 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 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 HL-1125, Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 13, Per Amend 168 to License DPR-571990-06-0707 June 1990 Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 13, Per Amend 168 to License DPR-57 HL-1019, Submits Certification That Operator Licensing Simulation Facility Located at Plant Meets NRC Requirements1990-05-31031 May 1990 Submits Certification That Operator Licensing Simulation Facility Located at Plant Meets NRC Requirements HL-1082, Forwards Response to NRC Re Violations Noted in Insp Repts 50-321/90-07 & 50-366/90-07.Encl Withheld (Ref 10CFR73.21)1990-05-0707 May 1990 Forwards Response to NRC 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 HL-1053, 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 Overfills1990-05-0101 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 HL-1056, Forwards Results of 900411,13 & 16 Telcons & Provides Addl Info & Justification Requested by NRC Re Insp of IGSCC Susceptible Welds,Per Generic Ltr 88-01 & Rev 2 to NUREG-0313.Proposed Weld Overlay Designs Also Encl1990-04-30030 April 1990 Forwards Results of 900411,13 & 16 Telcons & Provides Addl Info & Justification Requested by NRC Re Insp of IGSCC Susceptible Welds,Per Generic Ltr 88-01 & Rev 2 to NUREG-0313.Proposed Weld Overlay Designs Also Encl HL-1043, Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow.Procedure Rev Currently in Validation Process at Plant Placing Cautionary Note in Procedure for Channeling Bundles1990-04-17017 April 1990 Responds to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Channel Box Bow.Procedure Rev Currently in Validation Process at Plant Placing Cautionary Note in Procedure for Channeling Bundles HL-1003, 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 9005041990-03-14014 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 ML20033E2911990-02-26026 February 1990 Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 9, Per Amend 106 to License NPF-5,authorizing Relocation of fuel-related Limits Out of Tech Specs & Into Core Operating Limits Rept 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 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 ML20005E6491990-01-0202 January 1990 Responds to NRC 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 ELV-01131, 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 Critical1989-12-0707 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 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 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 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 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 1990-09-04
[Table view] |
Text
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W. c. Hairston, iii se'vot Vice Pret cem Nscies' Ope'ams HL-986 000292 i
March 1, 1990 l
U.S. Nuclear Regulatory Commission ATTN:: Document Control Desk 1
Washington, D.C.
20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 l
GENERIC LETTER 90-01 VOLUNTARY PARTICIPATION IN NRC REGULATORY IMPACT SURVEY Gentlemen:
{
On January 18,' 1990, the NRC issued Generic Letter 90-01, " Request for Voluntary Participation in NRC Regulatory Impact Survey".
The generic letter requested that-utilities, on a voluntary basis, complete the questionnaire provided in the enclosure to the letter.
The purpose of this j
information is to provide the NRC with insight on the time which key managers spend in responding to various inspections and audits.
The completed qtutionnaire is provided as an enclosure to this letter..
L 1
In agreement with the views presented by INP0 in their letter to the NRC dated February.7, 1990. Georgia Power Company (GPC) has not included the time spent by managers during INPO assistance visits.
GPC agrees that such visits should not be categorized as an imposition, but-rather a L
response to a utility's request for assistance in a particular area.
'Please recognize that the hput provided for upper management involvement only reflects the time spent for Plant Hatch, even though the
" Chief Nuclear Officer," and one of the two " Corporate Vice Presidents"
-also have responsibilities for other plants within the Southern Company.
l i.
9003000342 900301
['
PDR ADOCK 05000321
P PNV f
[f
///
I l Georgia Power A U.S. Nuclear Regulatory Commission March 1, 1990 Page Two If you have any questions in this regard, please call this office at any time.
Sincerely, n/d /kV W._G. Hairston, III JKB/eb
Enclosure:
NRC Regulatory Impact Survey Questionnaire c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS 1'
U.S. Nuclear Reaulatory Commission. Washinoton. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion-II i
Mr. S. D. Ebneter, Regional Administrator Mr..J. E. Menning, Senior Resident Inspector - Hatch l
l l
I 000292 i
l h
i k
ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet j
1.
Type of inspection, audit or evaluation:
NRC Team Insoections i
2.
Based on actual experience over the past several years, about how often is i
this activity conducted? Normally twice a year 3.
Operations / Construction areas covered:
Emeroency Operatino Procedures.
Operational Performance Assessment. Maintenance Team Inspections Safety System Functional Insoections of EDG. Quality Verification. Balance of j
Plant 4.
Extent of the activity (how many people, for how long) _10 Insoectors a
for two weeks 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
[
a.
Plant Department Heads 640 (number involved) 12 b.
Plant Manager 35 c.
Corporate Department Heads 420 (number involved) 6 d.
Corporate Vice Presidents 70 (numberinvolved) 2 e.
Chief Nuclear Officer 8
f.
Other Supervision 1000 (numberinvolved) 42 NOTE: Times are given in total manhours.
000301 1
,-m
L ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
Other NRC Resident.
Reaional and Headouarters Insoections/ Audits.
2.
Based on actual experience over the past several years, about how often is this activity conducted? Resident insoections - Once Der month:
Reaional and Headauarters - Every Two Weeks 3.
Operations / Construction areas covered:
All areas of Plant Ooeration and Emeraency Preparedness 4.
Extent of the activity (how many people, for how long)
Resident -
Two Inspectors. 21 days per month. Reaional and Headouarters - One insoector for 5 days once every two weeks 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads _195_
(numberinvolved) 12 b.
Plant Manager 62 c.
Corporate Department Heads 770 (numberinvolved) 6 d.
Corporate Vice Presidents 250 (numberinvolved) 2 e.
Chief Nuclear Officer 24 f.
Other Supervision 1450 (numberinvolved) 42 NOTE: Times are given in total manhours.
000301 2
i ENCLOSURE a
e E. 1. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
INPO Evaluation 2.
Based on actual experience over the past several years, about how often is this activity conducted? Once per year 3.
Operations / Construction areas covered:
Plant Safety. Manaaement Systems.
Technical Support. Plant Operations Maintenance. Quality Proarams.
t Radioloaical Protection Practices 4.
Extent of the activity (how many people, for how long) 15 to 20 Evaluators for 10 days.
y which the following managers Approximate manhours (on an annual basis)during, and in response to the l
S.
must spend in direct involvement before, activity described in item #1.
a.
Plant Department Heads _192_
(numberinvolved) 12 b.
Plant Manager 60 c.
Corporate Department Heads _llD_ (numberinvolved) 6 d.
Corporate Vice Presidents 100 (numberinvolved) 2 e.
Chief Nuclear Officer 16 f.
Other Supervision 800 (numberinvolved) 42 NOTE: Times are given in total manhours.
l 00030) 3
^
l ENCLOSURE E. 1. HATCH WUCLEAR PLANT NRC Regulatory Impact Survey Ouestionnaire Sheet 1.
Type of inspection, audit or evaluation:
Insurers (ANI) Insoections.
[
Audits or Evaluations 2.
Based on actual experience over the past several years, about how often is this activity conducted? Normally twice per year 3.
Operations / Construction areas covered:
Radiation exoosure. containment Leakaae Testina. Records Retention. Effluent Monitorina. Comouter Software Control. Ooerations Turnover Practices. etc.
1 4.
Extent of the activity (how many people, for how long) 3 Inspectors for seven days i
(
5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads 80 (numberinvolved) 8 b.
Plant Manager 5
c..
Corporate Department Heads
__11_
(number involved) 4 d.
Corporate Vice Presidents 15 (number involved) 2 e.
Chief Nuclear Officer 0
f.
Other Supervision 50 (numberinvolved) 15 NOTE: Times are given in total manhours.
000301 4
i
?
1 ENCLOSURE E. I. HATCH NUCLEAR Pl. ANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
EPA 2.
Based on actual experience over the past several years, about how often is this activity conducted? No EPA Inspections in Recent History i
3.
Operations / Construction areas covered:
4.
Extent of the activity (how many people, for how long)
I 5.
Approximate manhours (on an annua'l basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads (numberinvolved) b.
Plant Manager c.
Corporate Department Heads (number involved) d.
Corporate Vice Presidents (numberinvolved) e.
Chief Nuclear Officer f.
Other Supervision (number involved)
NOTE: Times are given in total manhours.
000301 5
P ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Ouestionnaire Sheet 1.
Type of inspection, audit or evaluation:
OSHA Audits 2.
Based on actual experience over the past several years, about how often is this activity conducted? Last audit in 1986. none since then.
This activity is included in routine NRC insoection activity.
3.
Operations / Construction areas covered:
4.
Extent of the activity (how many people, for how long) 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in item #1.
a.
Plant Department Heads (numberinvolved) b.
Plant Manager c.
Corporate Department Heads (number involved) 1' l-d.
Corporate Vice Presidents (number involved) 1 i
e.
Chief Nuclear Officer 1
i f.
Other Supervision (number involved) l-1 l
NOTE: _ Times are given in total manhours, l
1 I
000301 6
l
I.'
j ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey l
Questionnaire Sheet i
1.
Type of inspection, audit or evaluation:
DOT 2.
Based on actual experience over the past several years, about how often is this activity conducted? No insoections in recent history.
3.
Operations / Construction areas covered:
4.
Extent of the activity (how many people, for how long) r 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item fl.
a.
Plant Department Heads (number involved) b.
Plant Manager c.
Corporate Department Heads (number involved) d.
Corporate Vice Presidents (numberinvolved) e.
Chief Nuclear Officer l --
f.
Other Supervision (number involved)
NOTE: 1) Times are given in total manhours.
000301 7
i e
l ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory impact Survey Duestionnaire Sheet 1.
Type of inspection, audit or evaluation:
State and local Authorities j
2.
Based on actual experience over the past several years, about how often is this activity conducted? Normally twice per year 3.
Operations / Construction areas covered:
State Environmental Protection i
Division (EPD) Solid Waste Landfill Insocction. National Pollutant Discharae Elimination System Permit Inspection. Elevator Insoection.
Fire Protection. etc.
4.
Extent of the activity (how many people, for how long) One Insoector for half a day 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
1 a.
Plant Department Heads 12 (numberinvolved) 3 b.
Plant Manager 1
c.
Corporate Department Heads 0
(numberinvolved) 0 d.
Corporate Vice Presidents 0
(number involved) 0 e.
Chief Nuclear Officer 0
f.
Other Plant Supervision 50 (numberinvolved) 9 l
t NOTE: Times art given in total manhours.
000301 8
ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
0A (Technical Soecifications)
Audits reauired by NRC 2.
Based on actual experience over the past several years, about how often'is this activity conducted? 53 Audits for 1989.
Averaaed anoroximately 57 audits /vr. for cast 5 years.
3.
Operations / Construction areas covered:
Trainina. Limitoraue Actuators.
Emeraency Prepareness. Desian Modifications. Refuelina Outaae Activities Health Physics. ISI Proaram. etc.
4.
Extent of the activity (how many people, for how long)
Averaae aooroximately 2 peoole for 8 days per audit.
I 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
{
a.
Plant Department Heads 1320 (number involved) 12 b.
Plant Manager
__15 c.
Corporate Department Heads _i2Q_ (numberinvolved) 6 l
l d.
Corporate Vice Presidents 180 (numberinvolved) 2 e.
Chief Nuclear Officer 8
f.
Other Supervision 2000 (number involved) 42 NOTE:
Times are given in total manhours.
000301 9
I ENCLOSURE l
E. I. HATCH NUCLEAR PLANT NRC Regulatory impact Survey Ouestionnaire Sheet 1.
Type of inspection, audit or evaluation:
Self-As sessment s Resultina from External Commitnents i
2.
Based on actual experience over the past several years, about how often is this activity conducted? Assessments associated with Confiauration Manaaement Proaram and Trainino 3.
Operations / Construction areas covered:
Maintenance. Operations.
Enaineerina. Nuclear Safety & Comoliance. Health Physics. Chemistry.
General Suocort. Trainina. Outaae Manaaement. Security. Desian Enaineerino 4.
Extent of the activity (how many people, for how long) Averaae of 5 peoo19 for 3 months for each assessment I
5.
Approximate manhours (on Lan annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads 325 (number involved) 12 b.
Plant Manager 75 c.
Corporate Department Heads _192_ (number involved) 6 d.
Corporate Vice Presidents 15 (number involved) 2 e.
Chief Nuclear Officer 0
f.
Other Supervision 2500 (number involved) 30 NOTE: Times are given in total manhours.
000301 10
i l
ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet E'
1.
Type of inspection, audit or evaluation:
Other:
Plant visits by NRC Uoner Manacement.
2.
Based on actual experience over the past several years, about how often is
.this activity conducted? Acoroximately two to three Der year 3.
Operations / Construction areas covered:
Plant Manaaement 4
Extent of the activity (how many people, for how long) 2 oeoole for 1 day P
5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Itein #1.
a.
Plant Department Heads 36 (number involved) 9 b.
Plant Manager 5
c.
Corporate Department Heads
__1Q_
(number involved) 6 d.
Corporate Vice Presidents 16 (numberinvolved) 2 i
e.
Chief Nuclear Officer 8
f.
Other Supervision 25 (numberinvolved) 2 l
NOTE: Times are given in total manhours.
1 000301 11 L
g
Georg a Pwer Comnan,
{
333 Pocmom A<ense AtaNa ceo pa 30306 h>eD50ne 404 526 3195 i
1 M akng M c'ess
.)
4D irvemess Ceme' Pa4 6ar Pec CP'ce Bo.1295 B.em ap* am Aabama 35001 It'rD % nt 205 008 550*
t w..; e...
u.
l W. G. Hairston, lli l
Senof Vce Fren otN Nsnea* 0nera, ens l
HL-986 000292 March 1, 1990 f
I U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 i
PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-32), 50-366 OPERATING LICENSES DPR-57, NPF-5 GENERIC LETTER 90-01 VOLUNTARY PARTICIPATION IN i
NRC REGULATORY IMPACT SURVEY l
Gentlemen:
On January 18, 1990, the NRC issued Generic Letter 90-01, ' Request for i
Voluntary Participation in NRC Regulatory impact Survey".
The generic letter-requested that utilities, on a voluntary basis, complete the questionnaire provided in.the enclosure to the letter. The purpose of this information 'is to provide the NRC with insight on the time which key managers spend in responding to various inspections and audits.
The completed questionnaire is provided as an enclosure to this letter.
In agreement with the views presented by INPO in their letter to the NRC dated February 7, 1990. Georgia Power Company (GPC) has not included the time spent by managers during INPO assistance visits. GPC agrees that such visits should not be categorized as an imposition, but rather a response to a utility's request for assistance in a particular area.
Please recognize that the input provided for upper management involvement only reflects the time spent for Plant Hatch, even though the i
' Chief. Nuclear Officer," and one of the two " Corporate Vice Presidents" also have responsibilities for other plants within the Southern Company.
t i
s
._.. <. _ ~,
v_
)
i Georgia Poiver A l
. U.S. Nuclear Regulatory Commission March 1,-1990 i
Page Two j
If you have any questions in this regard, please call this office at i
any time.
Sincerely, n/d //V W. G. Hairston, III l
JKB/eb
Enclosure:
NRC Regulatory Impact Survey Questionnaire c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Nuclear Plant Mr. J. D. Heidt. Manager Engineering and Licensing - Hatch GO-NORMS U.S. Nuclear Reaulatory Commission. Washinaton. D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion II Hr. S. D. Ebneter, Regional Administrator i
Mr; J. E. Menning, Senior Resident Inspector - Hatch 1
1 o
l l
1-l' l
l t
f i:
000292
.u m
s.-m
..-- m--mm-u.
i ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey
[
Ouestionnaire Sheet 1.
Type of inspection, audit or evaluation:
NRC Team Insnections 2.
Based on actual experience over the past several years, about how often is this activity conducted? Normally twice a year 3.
Operations / Construction areas covered:
Emeroency Doeratina Procedures.
Ooerational Performance Assessment. Maintenance Team Insoections. Safety System Functional Inspections of EDG. Quality Verification. Balance of Plant 4.
Extent of the activity (how many people, for how long) 10 Insoectors for two weeks 5.
Approximate manhours (on an anntial basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads 640 (numberinvolved) 12 b.
Plant Manager 35 c.
Corporate Department Heads 12p_ (numberinvolved) 6 d.
Corporate Vice Presidents 70 (number involved) 2 e.
Chief Nuclear Officer 8
f.
Other Supervision 1000 (number involved) 42 NOTE: Times are given in total manhours.
1 000301 1
l L
ENCLOSURE E. 1. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 3.
Type of inspection, audit or evaluation:
Other NRC Resident.
Reaional and Headauarters Insoections/ Audits.
2.
Based on actual experience over the past several years, about how often is this activity conducted? Resident Insoections - Once ner month:
Reaional and Headauarters - Every Two Weeks
]
3.
Operations / Construction areas covered:
All areas of Plant Ooeration and Eme sency Preparedness 4.
Extent of the activity (how many people, for how long)
Resident -
Two Insoectors. 21 days Der month. Reaional and Headauarters - One Insoector for 5 days once every two weeks S.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item fl.
a.
Plant Department Heads E5_.
(number involved) 12 b.
Plant Manager 62 L
.c.
Corporate Department Heads 770 (numberinvolved) 6 d.
Corporate Vice Presidents 250 (numberinvolved) 2 l
e.
Chief Nuclear Officer 24 f.
Other Supervision 1450 (number involved) 42 l
L L
NOTE: Times are given in total manhours.
l 000301 2
i 1
i l
t ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet i
1.
Type of inspection, audit or evaluation:
INPO Evaluation l
2.
Based on actual experience over the past several years, about how often is l
this activity conducted? Once ner year 3.
Operations / Construction areas covered:
Plant Safety. Manaoement Systems.
Technical Suonort. Plant Ooerations Maintenance. Quality Procrams.
Radiolooical Protection Practices 4.
Extent of the activity (how many people, for how long) 15 to 20 Evaluators for 10 days.
5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in resPase to the activity described in Item #1.
[
a.
Plant Department Heads.lQD_
(numberinvolved) 12 b.
Plant Manager 60
[
l c.
Corporate Department Heads.llp_ (numberinvolved) 6 d.
Corporate Vice Presidents 100 (numberinvolved) 2 e.
Chief Nuclear Officer 16 f.
Other Supervision 800 (number involved) 42 NOTE: Times are given in total manhours.
L 000301 3
-. =
-l ENCLOSURE E. I. HATCH NUCLEAR PLANT I
NRC Regulatory Impact Survey Duestionnaire Sheet 1.
Type of inspection, audit or evaluation: l surers (ANI) Insoections.
Audits or Evaluations 2.
Based on actual experience over the past several years, about how often is this activity conducted? Normally twice oer year j
3.
Operations / Construction areas covered:
Radiation exoosure. containment Leakaae Testino. Records Retention. Effluent Monitorina. Comnuter Software 1
Control. Operations Turnover Practices. etc.
4.
Extent of the activity (how many people, for how long) 3 Insoectors for seven days l
t 5.
Approximate manhours (on an annual basis which the following managers must spend in direct involvement before,)during, and in response to the activity described in Item #1.
a.
Plant Department Heads
__8L (number involved) 8 b.
Plant Hanager 5
c.
Corporate Department Heads
,_l l (number involved) 4 d.
Corporato Vice Presidents 15 (numberinvolved) 2 e.
Chief Nuclear Officer 0
f.
Other Supervision 50 (number involved) 15 l
NOTE: Times are given in total manhours.
000301 4
.[
ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
EPA 2.
Based on actual experience over the past several years, about how often is this activity conducted? No EPA Insnections in Recent History 3.
Operations / Construction areas covered:
o 4.
Extent of the activity (how many people, for how long) i 5.
Approximate manhours (on an annual basis) which the following managers l
must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads (numberinvolved) l b.
Plant Manager c.
Corporate Department Heads (numberinvolved) d.
Corporate Vice Presidents (number involved) e.
Chief Nuclear Officer f.
Other Supervision (numberinvolved)
NOTE: Times are given in total manhours.
000301 5
l i
ENCLOSURE t
E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Shts,1 t
1.
Type of inspection, audit or evaluation:
OSHA Audits 2.
Based on actual experience over the past several years, about how often is this activity conducted? Last audit in 1986 3one since then.
This activity is included in routine NRC insnection activity.
3.
Operations / Construction areas covered:
{
4.
Extent of the activity (how many people, for how long) l 5.
Approximate manhours (on an annual basis) which the following managers L
must spend in direct involvement before, during, and in response to the i
activity described in Item #I.
a.
Plant Department Heads (number involved) b.
Plant Manager c.
Corporate Department Heads (number involved) d.
Corporate Vice Presidents (numberinvolved) e.
Chief Nuclear Officer i
l-f.
Other Supervision (number involved)
NOTE: Times are given in total manhours.
000301 6
t l
i ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
DOT
[
2.
Based on actual experience over the past several years, about how often is 3
this activity conducted? No insoections in recent history.
9 3.
Operations / Construction areas covered:
4 4.
Extent of the activity (how many people, for how long) i 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item fl.
L a.
Plant Department Heads (number involved) b.
Plant Manager c.
Corporate Department Heads (numberinvolved) d.
Corporate Vice Presidents (number involved) e.
Chief Nuclear Officer l
f.
Other Supervision (number involved)
NOTE: 1) Times are given in total manhours.
000301 7
l
.,r...-.
l 4
ENCLOSURE E. I. HATCH NUCLE /.R PLANT NRC Regulatory Impact Survey Questionnaire Sheet
]
1.
Type of inspection, audit or evaluation:
State and Local Authorities
)
2.
Based on actual. experience over the past several years, about how often is this activity conducted? Normally twice per year
- 3.,0perations/ Construction areas covered:
State Environmental Protection Division (EPD) Solid Waste Landfill Insoection. National Pollutant i
Discharae E?imination System Permit Insoection. Elevator Inspection.
f_ ire Protection. etc.
4.
Extent of the activity (how many people, for how long) One Insoector for i
half a day l
l 5.
Approximate manhours (on an annual basis) which the following managers 2
j must spend in direct involvement before, during, and in response to the activity described in Item #1.
i a.
Plant Department Heads
,__12_
(numberinvolved) 3 b.
Plant Manager 1
c.
Corporate Department Heads 0
(number involved) 0 d.
Corporate Vice Presidents 0
(number involved) 0 l
e.
Chief Nuclear Officer 0
f.
Other Plant Supervision 50 (numberinvolved) 9 NOTE: Times are given in total manh'ours.
000301 8
9 m
r
ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Duestionnaire Sheet t
1.
Type of inspection, audit or evaluation:
DA (Technical Specifications)
Audits reauired by NRC 2.
Based on actual experience over the past several years, about hou often is this activity conducted? 53 Audits for 1989. Averaaed aooroximatelv 57 l
audits /vr. for cast 5 years.
3.
Operations / Construction areas covered:
Trainino. Limitoraue Actuators.
Emeroency Prepareness. Desian Modifications. Refuelino Outaae Activities Health Physics. ISI Proaram. etc.
4.
Extent of the activity (how many people, for how long) s Averaae anoroximately 2 neoole for 8 days per audit.
5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
a.
Plant Department Heads.1320 (numberinvolved) 12 b.
Plant Manager 55 i
c.
Corporate Department Heads _420._ (number involved) 6 d.
Corporate Vice Presidents 180 (numberinvolved) 2 e.
Chief Nuclear Officer 8
f.
Other Supervision 2000 (numberinvolved) 42 NOTE: Times are given in total manhours.
000301 9
1
(; '
t ENCLOSURE L
E. 1. HATCH NUCLEAR PLANT l
NRC Regulatory Impact Survey Duestionnaire Sheet i
1.
Type of inspection, audit or evaluation:
Self-Assessment s Resultina from External Commitments 2.
Based on actual experience over the past several years, about how often is I
this activity conducted? Assessments associated with Confiauration Manaaement Proaram and Trainina 3.
Operations / Construction areas covered:
Maintenance. Ooerations.
[
Enaineerina. Nuclear Safety & Comoliance. Health Physics. Chemistry.
General Suncort. Trainina. Outane Manaaement. Security. Desian Enaineerina 4.
Exten,t of the activity (how many people, for how long) Averaae of 5 peoole for 3 months for ekch assessment 5.
Approximate manhours (on an annual basis) which the following managers i
must spend in direct involvement before, during, and in response to the activity described in item #1.
a.
Plant Department Heads.32L (numberinvolved) 12 b.
Plant Manager 75 c.
Corporate Department Heads _JDL (number involved) 6 d.
Corporate Vice Presidents 15 (number involved) 2 e.
Chief Nuclear Officer o
f.
Other Supervision 2500 (numberinvolved) 30 NOTE:
Times are given in total manhours.
000301 10
1
.~.
ENCLOSURE E. I. HATCH NUCLEAR PLANT NRC Regulatory Impact Survey Questionnaire Sheet 1.
Type of inspection, audit or evaluation:
Other:
Plant visits by NRC Unner Manacement.
2.
Based on actual experience over the past several years, about how often is this activity conducted't Anoroximately two to three ner year 3.
Operations / Construction areas covered:
Plant Manacement
[
4.
Extent of the activity (how many people, for how long) 2 neoole for 1 day 5.
Approximate manhours (on an annual basis) which the following managers must spend in direct involvement before, during, and in response to the activity described in Item #1.
5 a.
Plant Department Heads 36 (numberinvolved) 9 b.
Plant Manager 5
c.
Corporate Department Heads _ 1D_ (number involved) 6 d.
Corporate Vice Presidents 16 (number involved) 2 e.
Chief Nuclear Officer 8
l f.
Other Supervision 25 (number involved) 2 i
l NOTE: Times are given in total manhours.
l 000301-11 l
1
.