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| | number = ML20080P522 | | | number = ML20080P522 |
| | issue date = 03/02/1995 | | | issue date = 03/02/1995 |
| | title = Responds to NRC 950203 Ltr Re Violations Noted in Insp Rept 50-321/94-31.Corrective actions:on-site Fabricating of Rigging Slings for Use on Refueling Floor Has Been Prohibited | | | title = Responds to NRC Re Violations Noted in Insp Rept 50-321/94-31.Corrective actions:on-site Fabricating of Rigging Slings for Use on Refueling Floor Has Been Prohibited |
| | author name = Beckham J | | | author name = Beckham J |
| | author affiliation = GEORGIA POWER CO. | | | author affiliation = GEORGIA POWER CO. |
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| | contact person = | | | contact person = |
| | document report number = NUDOCS 9503080023 | | | document report number = NUDOCS 9503080023 |
| | | title reference date = 02-03-1995 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
| | page count = 8 | | | page count = 8 |
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| * 40 inverness Centir Parkway Post Offics Box 1295 Bermingham. Alabama 35201 Telephone 205 877 7279 - ' | | * 40 inverness Centir Parkway Post Offics Box 1295 Bermingham. Alabama 35201 Telephone 205 877 7279 - ' |
| 6 J. T. aeckham, Jr. GeorgiaPower afch Pro c thes uttondoctxsystem March 2, 1995 Docket No. 50-321 HL-4792 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Edwin I. Hatch Nuclear Plant - Unit 1 Reolv to a Notice of Violation Gentlemen: | | 6 J. T. aeckham, Jr. GeorgiaPower afch Pro c thes uttondoctxsystem March 2, 1995 Docket No. 50-321 HL-4792 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Edwin I. Hatch Nuclear Plant - Unit 1 Reolv to a Notice of Violation Gentlemen: |
| In response to your letter dated February 3,1995, and according to the requirements of 10 CFR 2.201, Georgia Power Company (GPC) is providing the enclosed response to the Notice of Violation associated with Inspection Report 94-31. In the enclosure, a transcription of the NRC violation precedes GPC's response. | | In response to your {{letter dated|date=February 3, 1995|text=letter dated February 3,1995}}, and according to the requirements of 10 CFR 2.201, Georgia Power Company (GPC) is providing the enclosed response to the Notice of Violation associated with Inspection Report 94-31. In the enclosure, a transcription of the NRC violation precedes GPC's response. |
| Sincerely, | | Sincerely, |
| [ | | [ |
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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. 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[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216H3641999-09-20020 September 1999 Forwards NRC Form 536 in Response to AL 99-03, Preparation & Scheduling of Operator Licensing Exams HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-5731999-09-16016 September 1999 Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573 HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification1999-09-13013 September 1999 Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification HL-5832, Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC1999-09-0101 September 1999 Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations1999-08-20020 August 1999 Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)1999-08-19019 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d) HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 141999-08-19019 August 1999 Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14 HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.111999-08-18018 August 1999 Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11 HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999 Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528 05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999 Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999 Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. 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Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999 Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999 Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210 HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999 Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999 Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999 Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999 Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21 HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999 Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant ML20205H1491999-03-25025 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility ML20205H1411999-03-24024 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirement for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Oglethorpe Power Corp Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 30% of Facility HL-5754, Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO1999-03-22022 March 1999 Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO ML20205H1381999-03-22022 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Georgia Power Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 50.1% of Facility ML20205H1581999-03-16016 March 1999 Forwards Info for OLs DPR-5 & NPF-7 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Dalton Utilities Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 2.2% of Facility HL-5753, Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative1999-03-16016 March 1999 Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative HL-5757, Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 9901271999-03-15015 March 1999 Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 990127 HL-5756, Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 21999-03-12012 March 1999 Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5751, Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities1999-03-0505 March 1999 Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities HL-5735, Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC1999-03-0202 March 1999 Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC HL-5737, Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C1999-02-0505 February 1999 Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C HL-5733, Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions1999-01-29029 January 1999 Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions HL-5729, Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program1999-01-27027 January 1999 Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program HL-5728, Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures1999-01-19019 January 1999 Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures HL-5712, Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review1999-01-0707 January 1999 Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review HL-5725, Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied1999-01-0707 January 1999 Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied 05000366/LER-1998-004, Forwards LER 98-004-01 Re Personnel Error Which Resulted in Condition Prohibited by Ts.Rev Is Necessary Because Original LER Reported Inadvertent Criticality Could Have Occurred1999-01-0404 January 1999 Forwards LER 98-004-01 Re Personnel Error Which Resulted in Condition Prohibited by Ts.Rev Is Necessary Because Original LER Reported Inadvertent Criticality Could Have Occurred HL-5710, Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds1998-12-0202 December 1998 Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds HL-5708, Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers1998-11-20020 November 1998 Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers HL-5573, Withdraws Requesting Exemption from Requirements of GDC 56 with Respect to Ei Hatch,Unit 2 Reactor bldg-to- Suppression Chamber Vacuum Relief Sys Design Due to Listed Reasons1998-10-19019 October 1998 Withdraws Requesting Exemption from Requirements of GDC 56 with Respect to Ei Hatch,Unit 2 Reactor bldg-to- Suppression Chamber Vacuum Relief Sys Design Due to Listed Reasons HL-5687, Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment1998-10-19019 October 1998 Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment HL-5686, Informs That Corrective Actions Relative to Thermo-Lag 330-1 Issues Are Complete1998-10-16016 October 1998 Informs That Corrective Actions Relative to Thermo-Lag 330-1 Issues Are Complete HL-5697, Requests Delay of Insp of RPV Circumferential Shell Welds for Two Operating Cycles as Outlined in NRC Info Notice 97-63,Suppl 1 & That Proposed Alternative Be Authorized Per 10CFR50.55a(a)(3)(i),per1998-10-16016 October 1998 Requests Delay of Insp of RPV Circumferential Shell Welds for Two Operating Cycles as Outlined in NRC Info Notice 97-63,Suppl 1 & That Proposed Alternative Be Authorized Per 10CFR50.55a(a)(3)(i),per HL-5689, Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients1998-09-30030 September 1998 Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients HL-5673, Informs NRC That Util Intends to Load Four Lead Use Assemblies Into Unit 2 Core as Part of Reload 14/Cycle 15 During Fall 1998 Refueling Outage.Proprietary Info Encl. Proprietary Info Withheld,Per 10CFR2.7901998-09-18018 September 1998 Informs NRC That Util Intends to Load Four Lead Use Assemblies Into Unit 2 Core as Part of Reload 14/Cycle 15 During Fall 1998 Refueling Outage.Proprietary Info Encl. Proprietary Info Withheld,Per 10CFR2.790 HL-5680, Informs NRC of Util Plans & Schedule for Exam of Unit 1 RPV Shell Welds.Util Anticipates Having Final Relief Request Submitted to NRC for Review by 9907011998-09-18018 September 1998 Informs NRC of Util Plans & Schedule for Exam of Unit 1 RPV Shell Welds.Util Anticipates Having Final Relief Request Submitted to NRC for Review by 990701 1999-09-20
[Table view] |
Text
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- Georgia Power Company
- 40 inverness Centir Parkway Post Offics Box 1295 Bermingham. Alabama 35201 Telephone 205 877 7279 - '
6 J. T. aeckham, Jr. GeorgiaPower afch Pro c thes uttondoctxsystem March 2, 1995 Docket No. 50-321 HL-4792 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Edwin I. Hatch Nuclear Plant - Unit 1 Reolv to a Notice of Violation Gentlemen:
In response to your letter dated February 3,1995, and according to the requirements of 10 CFR 2.201, Georgia Power Company (GPC) is providing the enclosed response to the Notice of Violation associated with Inspection Report 94-31. In the enclosure, a transcription of the NRC violation precedes GPC's response.
Sincerely,
[
[J. T. Beckham, Jr.-
OCV/eb
Enclosures:
- 1. Violation 94-31-01 and GPC Response
- 2. Violation 94-31-02 and GPC Response cc: Georgia Power Company Mr. H. L. Sumner, Jr., Nuclear Plant General Manager NORMS U. S. Nuclear Regulatorv Commission. Washington. D. C, Mr. K. Jabbour, Licensing Project Manager - Hatch U. S. Nuclear Rerulatorv Commission. Region 11 Mr. S. D. Ebneter, Regional Administrator Mr. B. L. Holbrook, Senior Resident Inspector - Hatch
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95030B0023 950302 PDR ADOCK 05000321 / i G PDR / l' I
i Enclosure Edwin I. Hatch Nuclear Plant j Violation 94-31-01 and GPC Resoonse VIOLATION 94-31-01 Criterion V, Appendix B of 10 CFR 50, Instructions, Procedures and Drawing, requires j that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in ;
accordance with these instructions, procedures or drawings. Instructions, procedures or drawings shall include appropriate qualitative ac2 >ptance criteria for determining that important activities have been satisfactorily ace amplished. j Contrary to the above, on D-==har 21,1994, activities affecting quality were not y adequately prescribed in that contract personnel assigned tc refuel floor activities l fabricated seven rigging slings without documented licensee instructions, procedures, or 'i drawings. A vendor instruction was referenced but was insufficient to ensure that the i appropriate construction, testing, reviews, approvals, or training were completed. As a j result of this inadequacy, the slings were not fabricated in accordance with the vendor 1 instruction. I This is a Severity Level IV violation (Supplement 1).
RESPONSE TO VIOLATION 94-31-01 Reason for the violation:
The seven rigging slings used on the Unit I shroud head bolts were not fabricated in accordance with the vendor instruction because of personnel error. The vendor instmetion was sufficient to properly constmet the rigging slings. Also, plant procedures 52IT-MLH-005-0S, "R.igging Inspection Procedure", and 52IT-MLH-004-0S " Inspection and Load Testing Equipment Prior.to Fuel Handling," prescribe activities to ensure -
rigging slings are capable oflifting the intended load. However, personnel making the slings, a presumed " skill-of-the-craft" activity, failed to properly orient the sleeves in the ,
crimping tool used to make the slings. The same personnel also failed to crimp the sleeves !
the number of times required by a table contained in the vendor instructions.
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HL-4792 El-1 i l
E n . E Enclosure 1 Violation 94-31-01 and GPC Response j
. Corrective =*= wwh have W taken and the m*= mhved:
As a result of this event, the plant General Manager, in a letter dated 1/24/95, prohibited .
the on-site fib.-iceing ofrigging slings for use on the refueling floor. In addition, the General Manager directed that refueling floor slings that were fabricated on site and the ,
tools used to fabricate slings be tagged to prohibit their future use in rigging activities.
The existing slings and tools will be removed from the refueling floor when practical Personnel who incorrectly fabricated the rigging slings are no longer employed at Plant f Hatch; therefore, they could not be disciplined for their errors.
l Corrective stens which will be taken to avoid further violations:
Tagging tie existing slings and the associated tools will prevent their future use in rigging ;
activities. Ten slings currently in use to suspend items in the Unit 2 Spent Fuel Pool will - '!
be removed when practical.
Should a need to fabricate slings arise in the future, they veill be fabricated on site only after the permission of the General Manager has been obtained and the -asey procedures, training, and personnel qualification requirements have been implemented. !
Date when full compliance will be achieved:
Full compliance was achieved on 1/24/95 when senior site management prohibited refueling floor rigging slings from being fabricated on site and the tools used to fabricate slings were tagged to prohibit their use for rigging.
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HL-4792 El-2
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. ' Farla=n 2 ;
Edwin I. Hatch Nuclear Plant . j Vial =*ian 94-31-02 arwi GPC P=-== !
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- VIOLATION 94-31-02 i Hatch Unit 1 Technical SWe=* ion 6.8.1.a, requires that written procedures be. j established, implemented and maintained as recommended in App-wiir A of Regulatory )
Guide 1.33, Revision 2, February 1978. l Regulatory Guide 1.33, Revision 2, February 1978, Appaadiv A, lists preparation for !
refueling and refueling aiuipment operation and ra8=hg and core alterations as general l plant operating procedures.
l Procedure FP-OP-022-41604: Volume Reduction and Packaging ofIrradiated Hardware f and Mi=c# uws Components in the Spent Fuel Pool at E. I. Hatch Nuclear Station l using the CNSI 3-55 CASK and CNSI Equipment, Step 6.4.4, states in part, "to place all !
bearings in the storage container." Procedure FP-OPel1: Operating Procedure for the j CNSI Stellite Bearing Punch, Section 6.3: Transfer of Cut Stellite Bearings to Storage ;
Container, Step 6.3.1 also states in part, " transfer the stellite bearings to the designated !
storage container." J Procedure 52IT-MLH-005-0S: Rigging Inspection Procedure, Section 7.1 requires that all rigging shall be tested prior to acceptance for use at Plant Hatch and a certification of each test result should be kept on file; unmarked rigging devices shall not be used for l tigging purposes; and all special lifting devices used on the refuel floor shall be marked to j identify the intended use. Step 7.1.2 requires that all rigging devices should be marked with a legible serial number, safe working load and an annual inspection coded color.
Procedure 52IT-MLH-004-OS: Inspection and Load Testing Equipment Prior to Fuel !
Handling, Section 7.1, requires that personnel document the performance ofeach step l identified with an asterisk in applicable signature blocks on At*=chment 1. Section 7.4 and 7.5 delineated the applicable subsections to be documented on Attachment 1. Procedure SIGM-MLH-003-0S: Conduct of Crane Operators and Riggers, step 7.4.4.18 states in part, "if any doubt as to the safety of the rigging or load movement, stop the load l
movement and immediately notify the responsible supervisor. The load movement must I not be restarted until after the safety concern has been evaluated and is resolved."
Contrary to the above:
- 1. On November 11,1994, Procedure FP-OP-022-41604, Step 6.4.4 and Procedure FP-OP-011, step 6.3.1 were not implemented, in that the bearings were not placed in the designated storage container, but were placed in a designated open bucket, placed on the floor of the transfer canal, and transferred to a second open bucket during HL-4792 E2-1
, Enclosure 2 .
'i Violation 94-31-02 and GPC Response ;
which several balls were spilled onto the transfer canal floor. This resulted in an uncontrolled high radiation area occurring in the compartment adjacent to the bottom of the transfer canal. .
- 2. On December 28,1994, Procedure 521T-MLH-005-OS, Section 7.1 and Step 7.1.2
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~were not implemented, in that rigging slings used to move the shroud head bolts in the spent fuel pool were not marked with its (sic) intended use and did not contain a ,
legible serial number, safe working load, or an inspection color code. ,
I
- 3. On D-ami- 28,1994, Procedure 52IT-MLH-004-OS, Sections 7.1,7.4 and 7.5 were not implemented, in that documentation ofinspections and load testing of the slings prior to use wu not performed.
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- 4. On December 28,1994, Procedure 51GM-MLH-003-0S, Step 7.4.4.18 was not implemented, in that a contract foreman did not infonn the responsible supervisor aAer a shroud head bolt dropped into the spent fuel pool. Load moves were =di=W after the bolt dropped without evaluating and resolving the safety concernt This is a Severity Level IV violation (Supplement 1). ;
These violations are applicable to Unit 1 only.
RESPONSE TO VIOLATION 94-31-02 l t
Reason for the violation:
For Example 1, the uncontrolled high radiation area in the compartment adjacent to the bottom of the transfer canal was caused by an inadequate design feature of the transfer ,
canal. While the purpose of the transfer canal is to transport spent fuel assemblies and other highly radioactive material between the spent fuel pools and spent fuel shipping cask area, this event revealed that the transfer canalis not provided with sufficient shielding to prevent the occurrence of a high radiation area in the adjacent compartment in all cases The process of preparing the stellite bearings for removal required the bearings to be placed in a designated open bucket and transported through the transfer canal and ultimately to the storage / shipping watainer. Consequently, once the open bucket :
containing the stellite bearings was introduced into the transfer canal, a high radiation area !
in the adjacent compartment could result as standard practice is to perform the transport with the material as close to the floor of the transfer canal as possible.
I HL-4792 E2-2
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Racia==e 2 -
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Violation 94-31-02 and GPC Response - 4 s .!
y Personnel error on the part of the involved individuals did occur as manipulations involving the transfer of stellite balls from one open bucket to another open bucket were l performed since these manipulations were not contained in Procedures FP-OP-022-41604 and FP-OP-011. '
Prdcodures FP-OP-022-41604 and FP-OP-011 required the stellite bearings removed from l l
the control rod blades to be placed in a designated open bucket and then transported L through the transfer canal to the area where the storage / shipping container was located l l The storage container was not to be moved as part of this operation. The stellite balls -l E would then be placed into the storage container. This process would be r-H until all .l intended control rod blades were processed and all applicable material was placed into the j storage shipping container. On November 11,1994, the day the uncontrolled high j radiation area occurred, the involved personnel encountered difficulties with removing the l lid from the storage container. Consequently, a decision was made to proceed with the transfer of the stellite balls, using the designated open bucket, and temporarily storing the stellite balls in another open bucket located on the floor of the transfer canal Ultimately, the stellite balls in the temporary collection bucket would be placed in the stationary storage container. As stated in Example 1, the stellite balls were spilled onto the transfer canal floor during this operation.
Upon occurrence of the spill, personnel handling the stellite balls assumed that the design of the transfer canal would have adequate shielding to accomma4te the presence of the highly radioactive material, since they knew the transfer canal is used to transfer spent fuel assemblies and other highly radioactive materials. Further, they assumed that no immediate corrective actions were necessary. As a result of these incorrect assumptions, they failed to retrieve the stellite balls from the floor of the transfer canal in a timely.
manner and also failed to notify Health Physics personnel or the responsible GPC supervisor of the event.
Example 2 was the result of personnel error. Personnel who fabricated the seven rigging slings used on the Unit I shroud head bolts failed to tag all the slings with the information required by plant procedure 52IT-MLH-005-0S, " Rigging Inspection Procedure."
Example 3 was the result of personnel error. The slings were load tested prior to their use; however, the test load wu not as large as required by plant procedure 52IT-MLH-004-0S, " Inspection and Load Testing Equipment Prior to Fuel Handling,"
nor was the load test documented. The test load was smaller than required due to a miscommunication between the foreman and the workers who performed the test.
- Consequently, the safe working load for the slings was not adequately established.
Personnel incorrectly assumed that documentation of the load test was not required since the slings were to be used only once and then discarded with the Unit I shroud head bolts.
l HL-4792 E2-3
i? 2
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Violation 94-31-02 and GPC Response E== ale 4 was the result ofpersonnel error. . After the shroud head bolt was dropped, personnel on the refueling floor performed a cursory laa =*ian for evidence of damage (bubbles, drop in pool water level) to the spent fuel pool liner. However, they did not notify the responsible supervisor of the event nor apparently did they attempt to determine why the sling failed prior to lifting the next bolt.'
Corrective stens which have ha*n taken and the ra=*= achieved: .
i . . 1 Upon notification of the high dose rates on the 185-foot elevation of the Unit 1 Reactor Building in the area under the transfer canal, Health Physics personnel surveyed the area, -
determined it was a high radiation area, and posted a Health Physics technician outside the area to control access as required by plant procedures. After Health Physics personnel investigated and located the source of the radiation, refueling floor personnel removed the _
stellite bearings from the transfer canal and placed them in the spent fuel shipping cask . ,
area. Health Physics personnel re-surveyed the area under the transfer canal and found.
that dose rates had decreased significantly. Access to this area was restored.
Personnel involved in the movement of the stellite balls are no longer employed at Plant Hatch and thus could not be disciplined for their errors.
Plant procedure 52GM-T24-001-0S, " Fuel Transfer Canal Operation," has been revised to prevent the transfer canal from being placed into service until appropriate areas in the ;
Unit 1 Reactor Building have first been posted by Health Physics personnel as high +
radiation areas.
The personnel who failed to mark the rigging slings, to perform a proper load test, and to document that load test are no longer employed at Plant Hatch; therefore, they could not i be disciplined for their errors. As discussed in the response to Violation 321/94-31-01, .
however, the practice of manufacturing slings on site has been stopped at the direction of ,
the General Manager. Should a need to fabricate slings arise in the future, they will be t made on site only after the permission of the General Manager has been obtained and the necessary procedures, training, and personnel qualification requirements have been ,
implemented.
The foreman who failed to inform his supervisor of the dropped shroud head bolt was counseled regarding his inappropriate actions and was reminded of the requirement to inform supervisory personnel when unusual or unexpected events occur.
HL-4792 E2-4 e
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Violation 94-31-02 and GPC Response i
Corrective stens which will be taken to avoid funher violations: '
The need for locked barriers in the appropriate areas in the Unit 1 Reactor Building will be evaluated.
l Date when full comnhnce will be achieved: j I
For Example 1, full compliance was achieved on 11/12/94 when access to the high radiation area on the 185-foot elevation of the Unit 1 Reactor Building was controlled by
- Health Physics personnel as required by plant procedures.
For Examples 2 through 4, full compliance was achieved on 12/29/94 when the rigging _
slings used for the Unit I shroud head bolts were removed from service by disposing of .
them along with the shroud head bolts.
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J HL-4792 E2-5
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