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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
[Table view] |
Text
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.'s I July 20, 1998 i
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Ms. Pamela 81ockey-0brien D23. Golden Valley Road Douglasville, Georgia 30134
SUBJECT:
RESPONSE TO ITEMS DISCUSSED ON APRIL 15, 1998 )
Dear Ms. Blockey-0brien:
i During our telephone conversation on April 15. 1998, you asked several .
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questions and made a number of comments that I subsequently summarized into I i
six items. I have listed those six items and our responses in Enclosure 1 to ~{
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this letter. One of the items you mentioned was associated with the regulations in Title 40 of the Code of Federal Regulations. I have enclosed I some excerpts from that regulation as Enclosure 2. If you have any questions on the enclosures, you may contact me at 404-562-4653.
Sincerely, (Original signed by K. P. Barr) ;
I Kenneth P. Barr I)
Plant Support Branch Division of Reactor Safety y l l
Enclosures:
As stated a
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RESPONSE TO ITEMS DISCUSSED ON APRIL 15, 1998 Item 1 Be-7 found in the environment around Hatch could come from the plant as well as cosmic interactions.
Resnonse to item 1 In January 1998, you indicated you thought that the levels of Be-7 found around Hatch were higher than natural backgrourid levels. In our previous letter dated April 9,1998, we provided information indicating that international radiological protection organizatioris consider the source of Be-7 to be cosmic ray interactions with matter in the at'mosphere. In our April
- 15. 1998, telephone call, you indicated that Be-7 could also be produced in nuclear reactors.
You are correct in that pressurized water reactors (PWR) use various chemicals to control reactor coolant water conditions that, by interactions with subatomic particles, can result in the ]roduction low levels of Be-7.
Specifically, Be-7 can be produced by tie interactions of protons and lithium nuclei contained in PWR reactor coolant system chemical additives. However.
Hatch is a boiling water reactor (BWR) and does not add lithium to the reactor coolant water. Consequently, any Be-7 detected around the Hatch plant site would be expected to have been produced by cosmic interactions.
Item 2 You believed: (a) the State of Georgia should issue an alert because you believed that fish around Hatch were contaminated. (b) a State report associated with water quality of State waterways should list radioactivity levels in addition to the chemicals it lists, and (c) there were internal communications problems between several departments of the State.
Resoonse to Item 2 During our discussion, I believe you realized these items were primarily the jurisdiction of the State but you wanted to discuss them with me. I assume you agree that items (b) and (c) are not issues for NRC since they deal with a State report on non-radioactive chemicals and internal State communications matters, respectively. You may wish to contact the State directly on all of these matters.
With regard to the item (a) the 1996 State environmental rnort states on page 4. for the fish samples in the vicinity of Hatch. "All results were within the normal background range (less than 30 pCi/Kg fresh weight for Cs-137) and do not indicate any influence from Plant Hatch". Since there has been no statistically significant detectable influence on the fish population due to Hatch, the action you proposed appears not to be appropriate.
Enclosure 1
2 Item 3 Release of Co-60 and Cs-137 from a nuclear power plant is a violation of the Clean Water Act.
Resoonse to Item 3 During our conversation, you stated you believed that the release of Co-60 and Cs-137 from nuclear aower plants was in violation of the Clean Water Act. As you know, the Clean Water Act is the purview of the Environmental Protection Agency (EPA). Although NRC cannot interpret EPA regulations. I noted that EPA regulation. Title 40 CFR 122.2. Definitions, defines pollutants and specifically exempts radioactive materials regulated under the Atomic Energy Act of 1954, as amended. As I read that regulation, nuclear power )lant releases of radioactivity do not fall under the National Pollution )ischarge Elimination System established by EPA. For your information. Enclosure 2 provides some excerpts from 40 CFR 122.2. If you need additional information regarding the Clean Water Act and whether nuclear power plant liquid effluents violate the act, you may wish to contact the EPA directly.
Item 4 Contamination (Cs-137) found at Darien. GA came from Hatch.
Resoonse to Item 4 In our conversation, you stated that you believe that the Cs-137 found at Darien. Georgia was from Hatch. As you know, sources of the Cs-137 could be residual fallout from world-wide fallout due to weapons testing and the Chernobyl accident and from Hatch. Darien is 100 miles downstream from Hatch and shows a level of Cs-137 four times higher than samples from locations i closer to Hatch. The environmental report from the State provided a reasonable discussion and plausible explanation for the level detected.
Item 5 The river around Vogtle should be posted because of the levels of tritium and Cesium-137 found.
Resoonse to Item 5 In our conversation. you stated you believed that the river around Vogtle had high levels of tritium and Cs-137 and should be posted to alert the public.
As you know, the highest resorted tritium level in 1996 in river water was 2000 pCi/l H-3. However, t1e 1996 report indicates that no Cs-137 was detected in the river samples.
We discussed in the Jast that Regulatory Guide (RG) 1.109. Calculation of Annual Doses To Man rom Routine Releases of Reactor Effluents For the Purpose ;
of Evaluating Compliance with 10 CFR 50. Appendix I. provides methods '
acceptable to NRC for the determination of radiation doses to man from nuclear powe'r plant releases. Using RG 1.109 parameters, the maximum dose to an individual in a year from tritium is well below NRC limits. Therefore, there l is no basis for NRC to' recommend posting of the river to the State. However.
l you may wish to contact the State on this matter.
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! Enclosure 1
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3 Item 6
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Several questions were asked regarding waste oil.
Response to Item 6
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During our conversation, you asked the following questions- . J
- a. Where is the waste oil from Hatch being incinerated?
- b. Were the areas around Hatch previously contaminated with oil cleaned up?
- c. Was the ground water tested for oil?
- d. Has the vendor incinerating the oil had their effluents tested for radioactit:ty?
With regard to item c. NRC has no regulations that require that ground water j be tested for oil so that-issue is outside NRC's purview. In an attempt to obtain information on questions', a, b and d, I conducted a review of Hatch inspection re3 orts for the last two years. I was unable to find any j information tlat would answer those questions. i I
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Enclosure 1 b
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I EXCERPTS FROM TITLE 40 - PROTECTION OF ENVIRONMENT l l
(Note: Underlining was added for emohasis.)
CHAPTER I--ENVIRONMENTAL PROTECTION AGENCY PART 122--EPA ADMINISTERED PERMIT PROGRAMS: THE NATIONAL POLLUTANT DISCHARGE ,
ELIMINATION SYSTEM i l
Subpart A Definitions and General Program Requirements {
Sec. 122.2 Definitions.
l The following definitions apply to parts 122, 123, and 124. Terms not defined in this section have the meaning given by CWA. When a defined ,
term appears in a definition, the defined term is sometimes placed in (
quotation marks as an aid to readers.
Pollutant means dredged spoil, solid waste, incinerator residue, filter I backwash, sewage, garbage. sewage sludge, munitions, chemical wastes, i biological materials, radioactive materials (exceot those reaulated under the Atomic Enerav Act of 1954. as amended (42 U.S.C. 2011 et sec . )), heat, wrecked or discarded equipment, rock, sand, cellar dirt anc industrial, municipal, and agricultural waste discharged into water.
It does not mean:
(a) Sewage from vessels; or (b) Water, gas, or other material which is injected into a well to facilitate production of oil or gas, or water derived in association with oil and gas production and disposed of in a well, if the well used either to facilitate production or for disposal purposes are approved by authority of the State in which the well is located, and if the State determines that the injection or disposal will not result in the degradation of ground or surface water resources.
Note: Radioactive materials covered by the Atomic Enerav Act are those encompassed in its definition of source. byoroduct. or soecial nuclear materials. Examoles of materials not covered include radium and accelerator-oroduced isotooes. See Train v. Colorado Public Interest Research Group. Inc. 426 U.S. 1 (1976).
L Enclosure 2
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