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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-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 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-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 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:NRC TO U.S. CONGRESS
MONTHYEARML20248F0321989-09-14014 September 1989 Forwards Rept of AOs at Licensed Facilities for First Calendar Quarter 1989.Plug Failure Resulted in Steam Generator Tube Leak at North Anna Unit 1 & Steam Generator Ruptured at McGuire Unit 1.W/o Encl ML20247L2401989-09-13013 September 1989 Responds to Re K Barnes Concerns Regarding Safety at Plants.Advises That to Date,Releases from Plants Remain Well within Accepted Stds ML20246K8571989-08-25025 August 1989 Discusses NRC Actions in Reponse to Constituent Concerns Re Excessive Overtime Worked by Employees of Plants ML20246B6591989-08-18018 August 1989 Forwards 40th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants from Apr-June 1989. Lilco Shareholders Voted to Accept Terms That Provide for Sale of Plant to State of Ny ML20247C0111989-05-12012 May 1989 Forwards NRC Quarterly Status Rept to Congress Covering First Quarter 1989.On 890303,NRC Dismissed Shoreham Intervenors from Licensing Proceeding for Misconduct During Proceeding.W/O Encl ML20246N8891989-03-22022 March 1989 Responds to to Zech Forwarding W Lewis Expressing Concern About Family Safety.Nrc Has Not Attempted to Keep Secret Findings in Reed Rept,Nor Ignore Potential Safety Significance of Findings ML20247C3541989-03-17017 March 1989 Forwards Detailed Info Re Status of Implementation of TMI Action Plan Items at Listed Plants.Small Number of Action Items Still Need Resolution ML20236D4761989-03-0909 March 1989 Forwards NRC 38th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1988 ML20195G8521988-11-10010 November 1988 Forwards Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Jul-Sept 1988.Inability of Commission to Forecast Licensing Schedule for Shoreham & Seabrook Noted ML20245D6531988-09-14014 September 1988 Responds to Re Requested Response to Concerns of H Nickerson Long Work Hrs for Personnel at Various Central Illinois Nuclear Generating Plants.Related Info Encl ML20245D5811988-08-22022 August 1988 Forwards 36th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants Covering Apr-June 1988.Licensing Schedule Cannot Be Realistically Forecast Due to Unresolved Emergency Preparedness Issues ML20207G2211988-08-15015 August 1988 Responds to Requesting Response to P Birnie Re Event at LaSalle Involving Recirculation Pump. NRC Response to P Birnie Identical to Ltr Addressed to Recipient ML20195G6681988-06-10010 June 1988 Provides Info in Response to Rl Spaulding Re Problems Associated W/Full Power Operation Authorization & Plant Shutdown.Plants Must Demonstrate Satisfactory Solutions to Issues Before Restart or Full Power Operation ML20151D3921988-04-0606 April 1988 Provides Listed Info Requested in Re Operating Nuclear Power Units Located at Twelve Sites Along Great Lakes ML20148E0961988-02-29029 February 1988 Forwards Quarterly Rept Covering Fourth Quarter of 1987,in Response to House Rept 97-850 ML20196G9691988-02-29029 February 1988 Forwards 34th Quarterly Status Rept on Emergency Preparedness for Nuclear Power Plants for Oct-Dec 1987. Commission Unable to Forecast Licensing Schedule for Shoreham & Seabrook Because of Unresolved Issues ML20195J6611988-01-20020 January 1988 Responds to Concerns Raised in Re Stainless Steel Matl Designated as E-Brite 26-1.Actions Taken to Address Allegation That E-Brite 26-1 Unsuitable for Use in Nuclear Power Plants Listed ML20236K8761987-11-0303 November 1987 Responds to Sztaba Expressing Concerns Re Safe Operation of State of CT Nuclear Power Plants.Plants in State Not Rated Among Most Troublesome in Nation.Licensee Performance Monitored in Publicly Available SALP Repts ML20236G1831987-10-27027 October 1987 Responds to Re Proposed Rule 10CFR50 & Congressional Ltrs Received on Morning of 871022 Meeting. Commission Stands Behind Declaring Process for Proposed Rule Open ML20235J5351987-09-28028 September 1987 Responds to Constituent Tf Gross Ltr Supporting Ucs 870210 10CFR2.206 Petition to Suspend OLs & CPs of Any Util Operating or Bldg Nuclear Power Reactors Designed by B&W,Per 870803 Request.Nrc Statements Re Plants Discussed ML20235J1171987-09-28028 September 1987 Responds to Requesting Info Re Ucs 870210 Petition Requesting Mods to B&W Facilities,Per E Gallizzi to Recipient Requesting Support of Petition. Gallizzi Statements Discussed.Petition Under Review ML20236L1811987-08-0404 August 1987 Responds to Addressed to Chairman Zech,Requesting That Commission Keep Recipient Fully Apprised of All Developments Re Both Petition Filed by Ucs & Ongoing Reassessment of B&W Reactors.Review of Petition Continuing ML20215K5981987-06-10010 June 1987 Responds to 870508 Request for Testimony at 870514 Hearing on External Influence on NRC Adjudicatory Procedures in Shoreham Proceeding.Index of Pertinent Documents Encl ML20215H9431987-06-0505 June 1987 Advises That Review of B&W Designed Nuclear Power Plants Will Not Satisfactorily Address Safety Issues Associated W/ B&W Design.Supports Efforts to Create Independent Safety Review Board ML20214P8401987-05-15015 May 1987 Responds to Rj Mrazek Re Util Request to Operate Facility at 25% Power.Commission Will Not Make Decision on Merits of Request Until All Parties Have Opportunity to Have Views Considered ML20214J5261987-05-15015 May 1987 Responds to Recipient Expressing Support for NRC Shut Down of Peach Bottom Atomic Power Station & Concern Re Emergency Planning Issues at Seabrook.Commission Unable to Comment on Issues Before Commission or Adjudicatory Boards ML20207A2061987-04-17017 April 1987 Responds to Request for Rept Re Legal & Institutional Aspects Under NRC Jurisdiction on Possible Conversion of Unit 1 to Defense Matls Production Reactor.Cp Still in Effect.Util Plans to Mothball Reactor by June 1988 ML20210N2161986-09-25025 September 1986 Discusses Governor Celeste Opposing Full Power Operations of Plants.Order Bars Commission from Voting Until Further Order by Us Court of Appeals.Served on 860930 NUREG-0396, Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs1986-09-10010 September 1986 Forwards Chronology of Meetings & Discussions W/Util & Other Groups,Internal Meetings & Lists of Public & Internal Documents,Per 860828 Request for Info Re Reducing Emergency Planning Zones for Seabrook & Calvert Cliffs NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls1986-08-26026 August 1986 Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls ML20209E6291986-08-26026 August 1986 Responds to 860731 Request to Be Kept Informed of Proceedings Re Facilities ML20206Q1321986-08-20020 August 1986 Submits Interim Response to Re Alleged Falsification of Welding Certificates for Welders at Plants Employed by Powerplant Specialists,Inc ML20204F9361986-07-30030 July 1986 Responds to from R Blank,Addressing Concerns Re Safety of Older Nuclear Plants,Per SO Conte 860701 Request ML20204F9311986-07-23023 July 1986 Responds to to Palladino,Recommending Establishment of Independent Review Group to Examine B&W Plant Design.Nrc Handling of Reassessment Program for B&W Design Defended.Formation of New Group Opposed ML20215L2051986-06-16016 June 1986 Responds to to NRC Requesting That FEMA Conduct Public Meeting Re FEMA Assessment of 861213 Emergency Planning Exercise.Commission Addressed Similar Response in 860606 Memorandum & Order NUREG-1195, Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco1986-04-23023 April 1986 Forwards Response to Re NRC Reexam of B&W Reactor Design.Review Efforts Intensified After TMI Accident.Nrr Reorganized Last Yr to Increase Attention to Major Vendor Product Lines.Action Plan Under Development for Rancho Seco NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress1986-04-23023 April 1986 Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress ML20137P5121986-01-24024 January 1986 Provides Info Concerning Financial Qualifications of Utils Re Safety of Plants.Nrc Regulation of Commercial Nuclear Power Based on Responsibility of Licensees for Safe Operation.Addl Views of Asselstine Encl ML20132G6251985-09-19019 September 1985 Forwards Responses to Gao Rept, NRC Should Rept on Progress in Implementing Lessons Learned from TMI Accident ML20140H5551985-08-13013 August 1985 Forwards Press Release 85-108 Re Proposed Fine Concerning Util Alleged Violation of NRC Requirements Which Prohibit Discrimination Against Employee for Identifying Safety Concerns to Mgt ML20140H5741985-08-12012 August 1985 Forwards Press Release 85-106 Re Proposed Fine for Util Alleged Violation of NRC Requirements Concerning Employee Discrimination in Cleanup Program ML20140H5911985-07-23023 July 1985 Forwards Press Release 85-99 Re NRC Proposed Civil Penalty in Amount of $150,000 Against Util for Violation of Requirements Concerning Reactor Vessel Water Level Instruments ML20132B8341985-07-18018 July 1985 Forwards Quarterly Status Rept for Second Quarter CY85. Licensing Delay for Limerick 1 Projected to Be 5 Months. Delay Cannot Be Quantified for Shoreham Due to Litigation. Full Power OL Issued for Palo Verde 1 on 850601 IR 05000409/20050311985-07-16016 July 1985 Forwards Notice of Violation Issued to Util Based on 850409-0531 Insp ML20140H6231985-07-15015 July 1985 Forwards Press Release 85-95 Re NRC Proposed Fine Against Util for Alleged Violations of Safety Requirements During Apr 1985 ML20141H1081985-07-0909 July 1985 Forwards Responses to 850610 Questions Re Diablo Canyon OL Proceeding.Responses Delayed Due to Press of Other Business ML20140H6461985-06-0404 June 1985 Forwards Press Release 85-80 Re NRC Proposed Civil Penalty in Amount of $500,000 Aginst Util for Alleged Matl False Statements Made to NRC Concerning Operator Qualifications & Training ML20140H6701985-06-0303 June 1985 Forwards Press Release 85-78 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Unplanned Occupational Radiation Exposures & Failure to Control Contractor Work Forces ML20140H7211985-05-24024 May 1985 Forwards Press Release 85-75 Re NRC Proposed Fine Against Util for Alleged Violations of Requirements Concerning Failure to Take Corrective Action When Warranted Concerning QA Program ML20140H7451985-05-17017 May 1985 Forwards Press Release 85-70 Re NRC Proposed Civil Penalty in Amount of $50,000 Against TVA for Alleged Violation of Security Requirements 1989-09-14
[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 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 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 ML20199H8761999-01-21021 January 1999 Informs That Proposed GL 88-01 Examinations of Spring 1999 Refueling Outage of Plant,Unit 1 Acceptable 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 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 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 ML20155B2461998-10-15015 October 1998 Forwards Insp Repts 50-321/98-05 & 50-366/98-05.No Violations Noted 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
[Table view] |
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(v The Honorable Lindsay Thomas United States House of Representatives Washington, DC 20515
Dear Congressman Thomas:
1 am pleased to respond to the questions raised by your constituent Mr. J. Richard Bass. Mr. Bass's January 2, 1984 letter asked several questions concerning the $100,000 civil penalty issued by the NRC on December 27, 1983 to the Georgia Power Company. Enclosure 1 contains the answers to Mr. Bass's questions. _
The Georgia Power Company paid the proposed civil penalty and responded to the ,
violations by letter dated January 25, 1984. Copies of (1) NRC's December 27, 1983 proposed civil penalty and the January 6,1984 correction letter, (2) Georgia Power's January 25, 1984 response, (3) the NRC's February 14, 1984 acknowledgement, and (4) a computer printout containing a brief description of the violations identified at Hatch Units 1 and 2 during the past two years are enclosed.
Sincerely, islgned)T. A.Rohd illiam J. Dircks Executive Director for Operations
Enclosures:
As stated 8510230048 851004 l PDR FOIA PDR JACOBS85-478
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pitauq jo,, UNITED STATES y g NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D. C. 20555 j
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FEB 2 8 1984 s
The Honorable Lindsay Thomas United States House of Representatives Washington, DC 20515
Dear Congressman Thomas:
I am pleased to respond to the questions raised by your constituent Mr. J. Richard Bass. Mr. Bass's January 2,1984 letter asked several questions concerning the $100,000 civil p,enalty issued by the NRC on December 27, 1983 to the Georgia Power Company. Enclosure 1 contains the answers to Mr. Bass's questions. _
The Georgia Power Company paid the proposed civil penalty and responded to the ,
violations by letter dated January 25, 1984. Copies of (1) NRC's December 27, 1983 proposed civil penalty and the January 6, 1984 correction letter, (2) Georgia Power's January 25, 1984 response, (3) the NRC's February 14, 1984 acknowledgement, and (4) a computer printout containing a brief description of the violations identified at Hatch Units 1 and 2 during the past two years are enclosed.
Sincerely, 751gned)T. A Rehm illiam J. Dircks Executive Director for Operations
Enclosures:
As stated l
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, s Enclosure 1
. Answers to the questions contained in Mr. Bass's January 2,1984 letter.
Question s According to the source of information the plant was fined $100,000 for not reporting something that could have developed into a very critical matter.
Answer The civil penalty was not based upon a failure to report information to the NRC. The civil penalty was based upon three violations. These violations 4 concerned the failure of .the operators at Hatch Unit 2 to follow procedures during a reactor shutdown on July 14, 1983. The NRC resident inspector entered the control room when the improper reactor shutdown was in progress. He asked several questions concerning the method being used to shut down the reactor.
The improper reactor shutdown was stopped and the reactor was then properly i shut down. Since the NRC resident was aware of the violation as it was -
l occurring, there was no failure to report information to the NRC in this instance. .
Question If the plant officials at Plant Hatch violated this regulation and were fined
$100,000, how do you or I know that they are not violating a number of other regulations?
Answer Companies such as Georgia Power which receive a license from the Nuclear i Regulatory Commission (NRC) to operate a nuclear power plant have the primary responsibility for safe operation of the facility. While no program can guarantee that every requirement is properly satisfied, the NRC has a program of site inspections to ensure that nuclear power plants are operated safely
- and in compliance with regulatory requirements.
The NRC conducts daily inspections at the Hatch facility. These inspections are performed by two NRC resident inspectors who are assigned to the Hatch
- facility. Additionally, inspectors from the NRC's Region II office in Atlanta also perform regular inspections at the Hatch facility. These inspections are supplemented by periodic special NRC inspections. This inspection program is typical of the inspections which are conducted at all operating commercial nuclear power plants.
Additionally, companies operating nuclear power plants, such as the Georgia Power Company, are required to make reports to the NRC. The Georgia Power Company has a good record of identifying and reporting violations as required j by NRC regulations.
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, , i Enclosure 1 ,
l Question I woul'd appreciate it very much if you could send me a list of the violations of the Hatch Plant which'are recorded by the Nuclear Regulatory Agency in Washington.
Answer The enclosed computer printouts. contain a brief description of the violations which have been identified at Hatch Units 1 ano 2 during the past two years. ,
These violations are more fully described in NRC inspection reports. These reports are available to the public in the Public Document Room located in the Appling County Public Library, 301 City Hall Drive, Baxley, Georgia 31563.
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Georgia Power Comoany ATTN: Mr. R. J. Kelly Executive Vice President P.O. Box 4545 Atlanta, GA 30302 Gentlemen:
SUBJECT:
PROPOSED IMPOSITION .0F CIVIL PENALTIES: EA 83-86 l IMPROPER SHUIDCWN (
REFERENCE:
INSPECTION REPORT NO. 50-366/83-23)
The enclosed Notice of Violation and Proposed Imoosition of Civil Denalties '
is. based upon the fincings of an NRC special inspection. The inspection examined the circumstances associated with the improper snutcown of Hatch, -
Unit 2, on July la, 1983.
This inspection was conducted by the NRC Resident and Region-based inspectors I on July 14 and 15, 1983 to review the circumstances of the improper shutcown of your Haten Unit 2 reactor on July 14, 1983 (the findings are set forth in Insoection Report No. 50-366/83-23). The detailed findings of this inspection were ciscussed at the site with facility management at the conclusion of the inspection. In addition, NRC safety concerns were discussed curing enforcement conferences held in the Region II office in Atlanta, Georgia, on July 21, 1983, at Plant Hatch on Novemoer 2, 1983, anc in the NRC offices in Wasnington, D.C. on Novemcer 14, 1983.
The findings of the inspection revealed that on July 14, 1983, while Unit 2 was Deing returned to service, a problem was experienced with main concenser vacuum. This problem required a recuction in reactor power to avoic a reactor shutcown. The on-shift coerators anc :neir supervisors recognized that tne normal method of reducing power would not achieve a sufficiently timely power reduction to avoid a scram. These incividuals, accarently strongly influenced by advice from two snif t tecnnical advisers, mace a " consensus cecision" to acnieve tne necessary -acic power recuction by cycassing both the Rod Worth Minimi:er and.the Roc Secuence Controller and oy selectively scramming incividual control "Ods, witnout an accroved procecure, from the Scram Time Test Panel wnicn is out of signt of, anc out of normal voice communications witn, tne reactor control console. The " consensus cecision" and tne resulting actions resulted in a control rod configuration tnat nad not been analyzed fMm a reactor safety viewooint.
CERTIFIED MAIL RETURN RECEIcT REGUESTED
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.g DEC 37 333 Georgia Power Company b To emphasi:e the level of unacceptability of the manner in wnicn tne reactor was controlled on July'14, 1983, and after consultation with the Director of the Office of Inspection and Enforcement, I have been autnorized to issue tne enclosed Notice of Violation and Proposed Imposition of Civil Penalties in :ne amount of One Huncred Thousand Dollars based uoan the findings of the first inspection. Three separate violations were identifiec and a separate civil
. penalty could have been assessed for each. However, since all three violations stemmed from the same fundamental proolem, the violations have been classified together as a Severity Level II problem (Supplement I) pursuant to the NRC Enfo'rcement Policy, 10 CFR Part 2 iocendix C. and a single civil penalty is proposed. 'The base penalty of $64,000 has ceen escalatec to $100,000 because of the' seriousness of tnis event, the number of Tecnnical Specifications that were violated, and the number of licensed ocerators and supervisors involvec.'
You are required to respond to the Notice and should follow the instructions-scecifiec tnerein when preparing your response. The secuence of events that ,
occurred on July 14, 1983 gives rise to a numcer of questions which the NRC believes must be address'ed by the Georgia Power Comoany. First, has the-Georgia Power Company's colicy of " safety first" been compromised by improper consideration by indivicual. members of the Plant Hatch staff of " keeping the plant running" without proper consideration of overall plant safety? Second,
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has the Georgia Power Company's policy of strict acherence to approved operating procedures ceen compromised at Plant Hatch by individual supervisors and managers and has an effective system of audits been implemented to assure compliance with tre policy? Third, is each operations supervisor fully aware'of nis/her indivicual responsibilities for making decisions? Fourtn, is the role and the autnority of the snift technical adviser clear to them and to each operations i supervisor? And finally, is each licensec operator aware of the importance of adherence to Technical Specifications and knowledgeable of aoproved intercretations of those Technical Soecifications? Your resconse to the attacned Notice of Vfclation and Proposed Imposition of Civil penalties snould accress, in detail, each of these cuestions witn carticular emonasis on assuring gooc vertical communications between Plant Haten in Eaxley, Georgia, and tne corporat'e offices in Atlanta, Georgia. It is further requestec tnat you crovice sufficient information On :nese scecific matters so snat we may conclude that your corrective actions will ce effective over tne long run.
Your reply to this letter, and the results of future insoectiors, will ce consicered in determining wnetner furtner action is accrocriati.
In accorcance with 10 CFR 2.790 of the NRC's " Rules of Practice", Part 2, Title 10, Code of Feceral Regulations, a cooy of tnis letter and tne Notice :#
V1olation will be placed in tne NRC's Duolic Jocument R00m. To orotect tne privacy of tne individuals involvec, tre Letters of Reorimanc will not ce ,
olaced in tne Puolic Occument Room at tnis time.
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MC 3 7 - 1983 l Georgia Power Company ..
The responses directed.by tnis letter and the enclosure are not subject to the clearance procedures ofsthe Office of Management and Budget as required by tne Paperwork Reduction Act of 1930 PL 96-511.
Sincerely, b G James P. O'Reilly Regional Acministrator
Enclosure:
Notice of Violation and Procosed Imoosition of Civil Penalties cc w/ encl: '
J. T. Becknam, Vice President and .
General Manager-Nuclear Generation H. C. Nix, Site General Manager C. E. Selflower, Site QA Supervisor s
o^
0 NOTICE OF VIOLATION
. AND
' PROPOSED IMPOSITICN OF CIVIL DENALTIES Georgia power Company Docket No. 50-366 Ha:cn Unit 2 License No. NPF-2 EA 83-86 A special inspection conducted at Hatch Unit 2 on July 14 and 15, 1983 disclosed that wnile Unit 2 was being returned to service, a problem was experienced with main condenser vacuum. This problem required a reduction in reactor power to avoid a reactor snutdown. The on-shift operators and tneir supervisors recogni:ed snat the normal method of reducing cower would not
~
acnieve a sufficiently timely power reduction to avoid a scram. These incivicuals, apoarently strongly influenced by advice from two shift tecnnical advisers, made a " consensus decision" to achieve tne necessary rapid power recuction cy bypassing both the Roc Worth Minimi:er and the Rod Secuence -
Controller and by selectively scramming indivicual control rods, without an approvec crocedure, from tne Scram Time Test Panel which is out of sight of, .
and out of normal voice communications with, the reactor control console. The
" consensus cecision" and the resulting actions resulted in a control rod configuration that had not been analyzed from a reactor safety viewpoint.
To emchasi:e the need to adhere to facility operations' and administrative procecures and to upgrade plant management control systems relating to licensed personnel shift tecnnical advisers, and suoervisor's decision-making resconsibilities, NRC procoses to impose a civil penalty in the amount of
$100.000 for tne matter of the improper reactor shutdown event' on July 14, 1982.
In accordance witn the General Policy and Procedure for NRC Enforcement Actions, 10 CFR Part 2 Apcendix C, and pursuant to Section 234 of the Atomic Energy Act of 1954, as amended, the violations and tne associated civil cenalties are set fortn below:
A. Tecnnical Specification 6.3.1 states that procedures snall be written, approvec and implementec for reactor coerations.
Contrary to the above, on July 14, 1983, control rod manipulations were conducted in violation of written and apor0ved crocecures, resulting in control rod patterns outsice those analy:ec for the Rod Drop Accioent described in FSAR cnacter 15.1.38. These maniculations were imorcoerly accomplished by scramming control rocs from tne scram time test canel (2H11-P610) and inserting cont-ol rocs using the Emergency In switen instead of the approved procecural .metnoc of inserting control rocs in notch control from tne main control panel (2H11-0603).
Examples of procecures wnich were not followed include:
- 1) Procedure, HNP-2-34, Rules for Performing Procedures, requires that veroatim comoliance is mancatory (?aragraoh 13.2) anc :nat, 'f an acoroved procedure cannot be performed as written, stop and cnange the crocecure. On July 14, 1983, Procedures HNP-2-9402 and HNP-2-9207 were not being followed vereatim nor was the event stopoec, and tne crocedures were not cnanged.
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, . .s-Notice of Violation 2) Procedure',' HNP-2-9402, Control Rod Scram Testing, requires, in step E.17, return.of tne scrammed rod to its initial position prior to scramming the next rod.s On July 14, 1983, the rods scrammed from tne time test panel (2H11-P610) were not being returned to their initial position prior to scramming the next rod.
- 3) Procedure, HNP-2-9207, Control Rod Movement, Paragraph 0.4 and Data Sheet i requires notch control for rods identified witn an asterisk.
This asterisk was on all rod groups moved during the shutdown of July 14, 1983, up to the point-wnere-the reactor manual scram was initiated, and tnese movements were not conducted by notch control.
1
- 4) Procedure, HNP-2-9207, Control Rod Movement, Paragrach E.5 requires that rod movement be stopped if proper operatio.1 of the Rod Sequence Control System (RSCS) is not confirmed. On July 14, 1983, rod move-ment was continued even though the RSCS was circumvented and -
tnerefore inoperative.
B. Technical Specification 3.1.4.1 requires the Rod Worth Minimizer (RWM) to be coerable or a second licensed operator or otner qualified member of the technical staff to be present at the reactor console to verify compliance with the prescribed control rod pattern. -
Contrary to the above on July 14, 1983, after bypassing the RWM, a second perso^ did not verify compliance with the prescribed rod pattern. As a consequence, the rod insertion sequence was violated as evidenced by Control Rod 42-39 at notch 12 versus the required notch 48.
C. Technical Saecification 3.1.4.2 requires that the Rod Secuence Control System (RSCS) be operable in Operation Condition 1 when :nermal power is below 20%.
Contrary to the above, on July 14, 1983, unfle in Cperation Condition 1, with thermal power below 20%, the RSCS was not operational in tnat it was not performing its intended function of notch control.
The required notch control was circumvented by use of :ne Emergency In switch and the scram switenes on the scram time test canel.
Collectively, the above violations nave ceen evaluated as a Severity Level : ~.
proolem. (Supplement I)
Cumulative Civil Penalty - 5100,000 assessed equally among tne violations.
, . >~
Notice of Violation '
Pursuant to tne provision of 10 CFR 2.201, Georgia Power Comoany is herecy recuired to suomit to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and a copy to the Regional Acministrator, U.S. Nucl' ear Regulatory Commission, Region II, witnin 30 cays of tne date of nis Notice a written statement or explanation, including for each allegec violation: (1) acmission or denial of the alleged violations; (2) :ne reasons for tne violation if acmitted; (3) tne corrective steps wnich have been taken anc the results achieved; (4) the corrective steps wnich will be taken to avoic further violations; and (5) the date when full compliance will be achieved.
Consideration may be given to extending the response time for good cause shown.
Under the authority of Section 182 of the Act, 42 U.S.C. 2232, the response snall be suomittec uncer catn or affirmation.
Within the same time as provided for the response required above under 10 CFR 2.201, Georgia Power Company may pay the civil penalties in the cumulative amount of
$100,000 or-may protest imposition of tne civil cenalties in whole or in part by a written answer. Should Georgia Power Company fail to answer within the time specified, the Director, Office of Inspection and Enforcement, will issue an I
order imposing the civil penalties in the amounts proposed above. Should -
) Georgia Power Company elect to file an answer in accordance with 10 CFR 2.205 protesting the civil penalties, such answer may: (1) deny the violations listed in this Notice in whole or in part; (2) demonstrate extenuating circumstances; (3) show error in this Notice; or (4) show other reasons why the penalties should not be imposed. In addition to protesting the civil penalties in whole or in part, such answer may request remission or mitigation of the penalties.
In recuesting mitigation of the proposed penalties, the five factors accressed in Section IV(B) of 10 CFR Part 2, Appendix C should be adcressed. Any written answer in accorcance with 10 CFR 2.205 should be set forth separately from tne statement or explanation in reply pursuant to 10 CFR 2.201, but may incorocrate oy specific reference (e.g., citing cage and paragrapn numoers) to avoic repetition. Georgia Power Company's attention is directed to the other provisions of 10 CFR 2.205, regarding the procecure for imoosing a civil cenalty.
Upon failure to pay tne cumulative penalties cue, which have been subsequently determinec in accordance with the applicable.crovisions of 10 CFR 2.205, tnis matter may be referred to the Attorney General, and the penalties, unless compromised, remitted, or mitigatec may be collected by civil action pursuant to Section 234c of tne Act, 42 U.S.C. 2282.
FOR THE NUCLEAR REGULATCRY COMMISSION U[ /J James P. O'Reilly Ylt8 Regional Acministrator Datec at Atlanta, Georgia
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