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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20216H3641999-09-20020 September 1999 Forwards NRC Form 536 in Response to AL 99-03, Preparation & Scheduling of Operator Licensing Exams HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-5731999-09-16016 September 1999 Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573 ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification1999-09-13013 September 1999 Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification HL-5832, Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC1999-09-0101 September 1999 Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations1999-08-20020 August 1999 Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)1999-08-19019 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d) HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 141999-08-19019 August 1999 Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14 HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.111999-08-18018 August 1999 Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11 ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999 Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528 05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999 Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999 Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage1999-07-15015 July 1999 Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-14014 July 1999 Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999 Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210 HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999 Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively1999-07-0909 July 1999 Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999 Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999 Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999 Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999 Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21 HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999 Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant ML20205H1491999-03-25025 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 1999-09-24
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 ML20205A2991999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Hatch PPR on 990202.PPR Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Feb 1997 - Jan 1999.Insp Plan for Future Encl ML20207M1771999-03-11011 March 1999 Forwards SE Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Welds ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207D3131999-02-24024 February 1999 Forwards Insp Repts 50-321/98-09 & 50-366/98-09 on 981213- 990123.No Violations Noted.Conduct of Activities at Hatch Facility Generally Characterized by safety-conscious Operation,Sound Engineering & Maintenance ML20203G4161999-02-17017 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs ML20203G3481999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20199H8941999-01-21021 January 1999 Discusses Responses to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Controls, for Plant,Units 1 & 2 ML20199H8761999-01-21021 January 1999 Informs That Proposed GL 88-01 Examinations of Spring 1999 Refueling Outage of Plant,Unit 1 Acceptable ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20199F1331998-12-29029 December 1998 Forwards Insp Repts 50-321/98-07 & 50-366/98-07 on 981101- 1212.No Violations Identified.Activities at Hatch Facility Generally Characterized by safety-conscious Operations, Sound Engineering & Maintenance Practices ML20199E7411998-12-23023 December 1998 Refers to 981105 Training Managers Conference Conducted at RB Russell Bldg with Representatives from All Utils.Agenda Used for Conference & List of Attendees Encl.Goal of Providing Open Forum of Operator Licensing Issues Was Met ML20196J4771998-12-0707 December 1998 Refers to 980311 Submittal of Four New Relief Requests & One Revised Relief Request for IST Program for Pumps & Valves Ei Hatch Npp.Se Accepting Proposed Alternatives Encl ML20196J2581998-12-0101 December 1998 Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities ML20196J2851998-12-0101 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Details of Insp Plan for Next 4 Months & Historial Listing of Plant Issues Called Plant Issues Matrix, Encl ML20196F1661998-11-24024 November 1998 Forwards Insp Repts 50-321/98-06 & 50-366/98-06 on 980920-1031.Insp Rept Identifes Activities That Violate NRC Requirements But Not Subject to Enforcement Actions ML20195D7961998-11-16016 November 1998 Informs That Licensee 980114 Request for Exemption from Requirements of General Design Criterion 56 for Edwin I Hatch Nuclear Plant,Unit 2 Found Acceptable & No Exemption from GDC-56 Required ML20196C8001998-11-12012 November 1998 Forwards Copy of Forms a & B,Individual Answer Sheets & Exam Results Summary of GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl ML20195B7891998-11-0909 November 1998 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Hrps, for Plant,Unit 1 ML20155H4181998-11-0303 November 1998 Advises That Info Contained in 980918 Application & 980813 Affidavit, GE14 Lua Fuel Bundle Description Rept, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20155B6061998-10-28028 October 1998 Forwards Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Tp ML20155A5461998-10-21021 October 1998 Forwards FEMA Final Rept on Exercise of Offsite Radiological Emergency Response Plans for Hatch Plant,Conducted on 980520.No Deficiencies or Areas Requiring Corrective Actions Identified During Exercise ML20155B2461998-10-15015 October 1998 Forwards Insp Repts 50-321/98-05 & 50-366/98-05.No Violations Noted ML20155A6261998-10-15015 October 1998 Informs That NRC Recently Obtained Info Re Industrial Safety Issues at Hatch Facility.Info Indicated That Personnel Unnecessarily Working on Energized Electrical Equipment Without Appropriate Clothing ML20154L4491998-10-14014 October 1998 Informs That NRC Reconsidered Relocation of PCP to PCP Manual Against Guidance in Regulatory Guide 1.143 & Believe That Locating of PCP in PCP Manual,Acceptable ML20155B0371998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators 1999-09-24
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L .f !
March 12, 1997 i
l l
l l
Georgia Power Company i ATTN: Mr. H. L. Sumner..Jr. ;
Vice President. Plant Hatch ,
Nuclear Operations i P.O. Box 1295 !
Birmingham. AL 35201
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-321/96-10, 50-366/96-10
Dear Mr. Sumner:
Thank you for your response of September 23. 1996, to our Notice of Violation (Notice) issued on August 30, 1996, concerning activities conducted at your Plant Hatch facility. We stated in our letter of October 2,1996, that we would evaluate your denial to the violation and notify you of the results of this evaluation at a later date.
~
We have reviewed your response to Violations B and C of NRC Integrated Inspection Report 50-321/96-10, 50-366/96-10. Violation B (96-10-05) specifically identified a condition where a deficient alarm for the 10 600 volt AC safety related bus was not promptly corrected. The deficiency was ident'ified on April 18, 1995, and was not corrected as of August 3. 1996.
As a result, control room personnel received an erroneous alarm on the safety-related 600V AC Bus 10. on July 25. 1996.
In your response to Violation B. you denied that a violation occurred as stated. You stated that the fact that-a deficient condition reoccurs before -
corrective actions can be implemented is not a violation of regulatory l requirements. You further stated that the problem was not operationally or l safety significant and correct 1ve action was assigned a low priority relative i .to other work activities.
i
! Violation C (96-10-02) specifically identified a condition where a four-hour L reporting requirement was not met on June 29. 1996, in that a maintenance deficiency was discovered that made the High Pressure Coolant Injection system -
(HPCI) inoperable. A report was not made to the NRC in accordance with 10 CFR
- 50.72.(b)(2)(iii)(D) until July 3. 1996.
In your response to Violation-C. -you denied that a violation occurred as 4
! stated. You stated that the event which made the Unit 1 HPCI system
- . inoperable on June 29. 1996. was reported within four hours of the event being ;
- determined to be reportable. Your conclusion was based upon guidance provided-1 in NUREG-1022. Supplement No.1. Licensee Event Report System. February 1984. !
1 You stated per the guidance given in the NUREG. the "reportability date" is
- "when someone decides or " discovers' that the event is reportable". Using I l this guidance referencing "reportability date", you additionally stated that j the applicable reporting requirements were met and no violation occurred. ;
9704010149 970312 PDR ADOCK 05000321 ,
G PDR l$,E g gggg
_ . -_ ##)
GPC 2 ,
After careful consideration of the bases for your denial of the aforementioned !
violations and an additional review conducted by the Region II staff, we are :
withdrawing Violation B. However, we have concluded, for reasons presented in the enclosure to this letter, that Violation C occurred as stated in the .
Notice of Violation. Therefore, in accordance with 10 CFR 2.201(a).. please i submit to this office within 30 days of the date of this letter a written statement describing steps which have been taken to correct Violation C and :
the results achieved. corrective steps which will be taken to avoid further !
violations, and the date when full compliance will be achieved. i We will examine the implementation of your actions to correct this violation i during future inspections. j The response directed by this letter and its enclosure are not subject to the clearance 3rocedures of the Office of Management and Budget as required by the Paperwork leduction Act of 1980. Pub. L No.96-511. l In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice." a copy of this letter, its enclosure, and your response will be placed in the NRC Public Document Room (PDR).
We appreciate your cooperation in this matter.
Sincerely.
(Original signed by Jon R. Johnson)
Jon R. Johnson. Director Division of Reactor Projects Docket Nos.: 50-321 and 50-366 License Nos.- DPR-57 and NPF
Enclosure:
Evaluation and Conclusion (Violation 96-10-02) cc w/ encl: P. Wells General Manager. Plant Hatch Georgia Power Company P. O. Box 439 Baxley. GA 31513 l- i l
D. M. Crowe l f Manager Licensing - Hatch Georgia Power Company P. O. Box 1295 !
Birmingham. AL 35201 l
! cc w/ encl cont'd: (See Page 3)' !
1
l .-'
GPC 3 i
cc w/ encl: Continued !
Ernest L. Blake Esq. l
-Shaw, Pittman, Potts and- !
Trowbridge. !
2300-N Street, NW i i Washington. D. C. 20037 l
l Charles H. Badger .
Office of Planning and Budget. :
Room 610 270 Washington Street. SW' :
. Atlanta. GA 30334 i l Harold Reheis. Director ;
Department of Natural Resources -
205 Butler Street, SE. Suite 1252 l Atlanta GA 30334 -
s l Thomas Hill, Manager l Radioactive Materials. Program
- Department of Natural Resources 4244 International Parkway Suite 114 1 Atlanta, GA 30354 Chairman Appling County Commissioners County Courthouse l Baxley, GA 31513 l
l Thomas P. Mozingo Manager of Nuclear Operations j Oglethor)e Power Corporation :
2100 E. Exchange Place Tucker, GA 30085-1349
! Charles A. Patrizia. Esq.
- l. Paul. Hastings, Janofsky & Walker
- 10th Floor l- 1299 Pennsylvania Avenue Washington, D. C.
~
20004-9500 Distribution w/ encl:
K. N. Jabbour, NRR P. H. Skinner. RII R. P. Carrion, RII W. P. Kleinsorge. RII
, M. E. Ernstes, RII l PUBLIC
- Distribution w/ encl' cont *d
- (See Page 4) i
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Distribution w/ encl: Continued NRC Senior Resident Inspector !
U.S. Nuclear Regulatory Comission i 11030 Hatch Parkway North '
Baxley, GA 31513 i i
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GPC 4 Ristribution w/ encl Continued '
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EVALUATION AND CONCLUSION (Violation 96-10-02) !
On August 30. 1996. A Notice of Violation (Notice) was issued for a violation !
identified during a routine NRC inspection. Georgia Power Company (GPC) !
responded to the Notice on September 23. 1996. In the response. GPC denied !
the violation occurred as stated in the Notice. The NRC's evaluation and ;
conclusion regarding the licensee's response are as follows: !
Restatement of Violation ;
10 CFR 50.72 (b)(2)(iii)(D). four-hour reports, states in part that, tha !
licensee shall notify the NRC as soon as practical and in all cases, within l four hours of...any event or conditi^n that alone could have prevented the i fulfillment of the safety function of structures, or systems that are.needed i to mitigate the consequences of an accident.
l Contrary to the above a four-hour reporting requirement was not met on June 29. 1996. During system surveillance activities to verify operability of :
the Unit 1 high 3ressure coolant injection system, a maintenance deficiency r was discovered tlat made the system inoperable and a report was not made until '
11:14 a.m. on July 3. 1996. '
Summary of Licensee's Violation Resoonse l
The licensee denied that the violation occurred as stated in the Notice. The i licensee stated that the event which made the Unit 1 High Pressure Coolant i Injection (HPCI) system inoperable on June 29, 1996. was reported within four !
hours of the event being determined to be reportable as required by 10 CFR 50.72 (b)(2)(iii)lD). Per the guidance given in NUREG-1022. Supplement No.1.
" Licensee Event Report System." February 1984, the "reportability date" is when someone decides or discovers that the event is reportable [Page 22, Item 3 of the answer to question 14.5]. The subject event was reported within four hours of GPC personnel determining it was reportable per the requirements of 10 CFR 50.72 (b)(2)(iii)(D). The licensee concluded that the applicable reporting requirements were met and no violation occurred.
The Unit 1 HPCI system was inoperable for planned maintenance on the oil system. a condition not reportable per 10 CFR 50.72(b)(2)(iii)(D). On June 29. 1996, prior to restoring system operability following completion of the oil system maintenance, a valve failed. This failure, which was unrelated to the oil system maintenance, would have rendered the system inoperable:
however, personnel did not immediately re) ort this event because the system l was already considered inoperable. The C R does not clearly state this event l was reportable regardless of the status of the system upon discovery of the '
l valve failure. Only after GPC engineers reviewed additional guidance, j
! provided in NUREG-1022. Sup)lement No. 1 [Section II " Questions and Answers -
from the LER Workshops." Su)section 7.0, cuestions and answers 7.9 and 7.10.
page 11] as part of a routine review of ceficiency cards, was it determined l- this event was reportable. i t
I.
i Enclosure
,/ ,C 3
- 3. The "Reportability" Date when someone decides or
" discovers" that the event is reportable.
~ 4. The Report Date when the LER is submitted (entered in Item 7).
If there is a significant length of time (>30 days) between event date and either the discovery or "reportability" date.
the reason for the delay should be discussed in the LER text.
The review indicated that operations supervision had the responsibility to review this issue in a timely manner but failed to do so. It was stated in
.NRC Integrated Inspection Report 50-321/96-10, 50-366/96-10, section 03.1, subsection b, that the Superintendent on Shift (SOS) is one of the individuals identified as being responsible for making the report. This responsibility is described in procedure 00AC-REG-001-05 Federal and State Reporting Requirements, Revision 4. This section of the report further stated that a member of the Nuclear Safety and Compliance (NSAC) staff was always on call to assist personnel in making detailed analyses for reportability. In this case.
operations )ersonnel did not solicit NSAC assistance. Hence, the NRC staff concludes tlat Operations: supervision failed to take prompt reportability actions for the event until the reporting deficiency was discovered by NSAC several days later.
The review of NUREG/BR-0195. Rev. 1. Chapter 7, Section 7.10. Violations of Reporting Requirements, indicated "A licensee normally will not be cited for failing to report an issue if the licensee was not aware of the information that was reportable. However, a licensee should be cited for failure to report an issue if the licensee knew of the information to be reported, but did not recognize that a report was required. (Ignorance of the reporting requirement is not an excuse)."
NRC Conclusion For the above stated reasons, the NRC staff concludes that Violation C (96-10-02) occurred as stated.
Enclosure