|
|
Line 13: |
Line 13: |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC |
| | page count = 23 | | | page count = 23 |
| | | project = TAC:59304 |
| | | stage = Other |
| }} | | }} |
|
| |
|
Line 19: |
Line 21: |
| t Georgia Pmer Cortpany 333 Poinut Amnue AtWla. Georgw LOWt T&r;h(e.e 404 'af.; C/26 M.enq AiMu-Post Of f te Ib 4M5 Atianta. GNrg a WW Georgia Power L T. Gacws tt ,e,m, ,, n ,+ | | t Georgia Pmer Cortpany 333 Poinut Amnue AtWla. Georgw LOWt T&r;h(e.e 404 'af.; C/26 M.enq AiMu-Post Of f te Ib 4M5 Atianta. GNrg a WW Georgia Power L T. Gacws tt ,e,m, ,, n ,+ |
| Msuger fbJ.-ar I nr;meer ng wwJ Groef tex tear tr ger ED-85-508 1866N July 18, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nucicar Regulatory Comission Washington, D.C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 INSERVICE INSPECTION RELIEF REQUESTS Centlemen: | | Msuger fbJ.-ar I nr;meer ng wwJ Groef tex tear tr ger ED-85-508 1866N July 18, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nucicar Regulatory Comission Washington, D.C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 INSERVICE INSPECTION RELIEF REQUESTS Centlemen: |
| By letter dated August 12, 1983, Georgio Power Corpany (GPC) submitted to WC on updated inservice inspection / inservice testing (ISI/IST) program for Hatch Units 1 and 2 based on NRC verbal recommendations. That submittal updated the ISI/IST programs from the 1974 Edition of the ASME Section XI Code with Addenda through Summer 1975 to the 1980 Edition with Addenda through Winter 1980. After the submittal was made, the examination procedures and plans were updated to the extent practical to meet the later edition of the Code. Since that time, NRC has approved the IST portion of the program with conditions as discussed in the WC letter dated June 4, 1985. MC, however, declined to act on the ISI portion of the program for | | By {{letter dated|date=August 12, 1983|text=letter dated August 12, 1983}}, Georgio Power Corpany (GPC) submitted to WC on updated inservice inspection / inservice testing (ISI/IST) program for Hatch Units 1 and 2 based on NRC verbal recommendations. That submittal updated the ISI/IST programs from the 1974 Edition of the ASME Section XI Code with Addenda through Summer 1975 to the 1980 Edition with Addenda through Winter 1980. After the submittal was made, the examination procedures and plans were updated to the extent practical to meet the later edition of the Code. Since that time, NRC has approved the IST portion of the program with conditions as discussed in the WC {{letter dated|date=June 4, 1985|text=letter dated June 4, 1985}}. MC, however, declined to act on the ISI portion of the program for |
| [gz reasons discussed in GPC's letter NED-85-483 dated June 25, 1985. | | [gz reasons discussed in GPC's letter NED-85-483 dated June 25, 1985. |
| b 8 The aforementioned CPC Ictter provided a new ten-year ISI/IST program mo for Hatch thits 1 and 2 since the Hatch Unit I first ten-year inspection W interval will conclude on December 31, 1985. It is the intention of CPC to complete the examinations for the Hatch Unit I first ten-year inspection Q | | b 8 The aforementioned CPC Ictter provided a new ten-year ISI/IST program mo for Hatch thits 1 and 2 since the Hatch Unit I first ten-year inspection W interval will conclude on December 31, 1985. It is the intention of CPC to complete the examinations for the Hatch Unit I first ten-year inspection Q |
Line 30: |
Line 32: |
| o' , | | o' , |
| Georgial'ower d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 July 18, 1985 Page Two recuests reouired by GPC for NRC review and approval. Please note that the reller reouest nunbers in Attachment 1 correspond with those in the June 25, 1985 submittal, where applicable. Nineteen (19) copies of this letter and its attachment are provided for your convenience. | | Georgial'ower d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 July 18, 1985 Page Two recuests reouired by GPC for NRC review and approval. Please note that the reller reouest nunbers in Attachment 1 correspond with those in the June 25, 1985 submittal, where applicable. Nineteen (19) copies of this letter and its attachment are provided for your convenience. |
| The relief reauests in Attachment I were based on a review of unresolved items in the safety evaluation report issued by NRC letter dated July 29, 1983 for the ISI program written to the 1974 Code, impractical 1980 Code reouirements, and other relief as identified. GPC reouests that WC grant the relief reouests included in Attachment 1 in accordance with 10 CFR 50.55a (g)(6). The relief reouested does not affect public health and safety. | | The relief reauests in Attachment I were based on a review of unresolved items in the safety evaluation report issued by NRC {{letter dated|date=July 29, 1983|text=letter dated July 29, 1983}} for the ISI program written to the 1974 Code, impractical 1980 Code reouirements, and other relief as identified. GPC reouests that WC grant the relief reouests included in Attachment 1 in accordance with 10 CFR 50.55a (g)(6). The relief reouested does not affect public health and safety. |
| The Hatch thit 1 maintenance / refueling outage is scheduled to begin November 30, 1985. Because of the extensive pre-outage planning associated with this effort, we respectfully reouest that ouestions concerning the enclosed inservice inspection relief reouests be brought to our prompt attention. To support our major planning ef fort, we are seeking your approval within 30 days of the date of this letter. Should you have any cuestions in this regard, please contact this office at anytime. We will give top priority to responding to your cuestions. | | The Hatch thit 1 maintenance / refueling outage is scheduled to begin November 30, 1985. Because of the extensive pre-outage planning associated with this effort, we respectfully reouest that ouestions concerning the enclosed inservice inspection relief reouests be brought to our prompt attention. To support our major planning ef fort, we are seeking your approval within 30 days of the date of this letter. Should you have any cuestions in this regard, please contact this office at anytime. We will give top priority to responding to your cuestions. |
| Pursuant to the recuirements of 10 CFR 170, enclosed herein as payment of the application fee for review of the subject relief reouests is our check in the amount of $150.00. | | Pursuant to the recuirements of 10 CFR 170, enclosed herein as payment of the application fee for review of the subject relief reouests is our check in the amount of $150.00. |
Letter Sequence Other |
---|
|
|
MONTHYEARIR 05000321/20040261985-06-0404 June 1985 Notice of Violation from Insp on 850321-0426 Project stage: Request ML20128P5511985-07-18018 July 1985 Forwards Requests for Relief from Certain ASME Code Inservice Insp Requirements to Complete First 10-yr Insp Interval of Plant.Approval Requested within 30 Days Due to Preoutage Planning Required for Maint/Refueling Outage Project stage: Other ML20210A6081985-11-0505 November 1985 Responds to B Trouvlin Request for Addl Info Re 850718 Request for Relief from Asme,Section XI Code Requirements to Support Inservice Insp During Upcoming Maint/Refueling Outage.Crd,Rcic & Feedwater Sys Makeup Flow Rates Listed Project stage: Request ML20136H1161985-11-0707 November 1985 SER Supporting Request for Relief from Certain ASME Code Inservice Insp Requirements.Relief Granted & Alternate Methods Imposed Give Assurance of Piping & Component Pressure Boundary & Support Structural Integrity Project stage: Other ML20136H1081985-11-0707 November 1985 Forwards SER Re 850718 Requests for Relief from Inservice Insp Requirements.Change in Insp Program Acceptable Based on Listed Condition.Summary Tabulation Encl Project stage: Approval 1985-11-07
[Table View] |
Similar Documents at Hatch |
---|
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: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. 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-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively1999-07-0909 July 1999 Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999 Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999 Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210 HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999 Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999 Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999 Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999 Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21 HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999 Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant ML20205H1491999-03-25025 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility ML20205H1411999-03-24024 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirement for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Oglethorpe Power Corp Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 30% of Facility HL-5754, Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO1999-03-22022 March 1999 Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO ML20205H1381999-03-22022 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Georgia Power Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 50.1% of Facility 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] Category:UTILITY TO NRC
MONTHYEARHL-1278, Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined1990-09-12012 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined HL-1176, Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date1990-09-12012 September 1990 Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date HL-1237, Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.11990-09-0404 September 1990 Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.1 HL-1250, Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage1990-08-27027 August 1990 Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage ML20059C6551990-08-27027 August 1990 Informs of Intention to Transfer Right of Way for Road 451 to Appling County So Road Can Be Straightened & Paved. Transfer Will Have No Significant Impact on Use of Road & Site Emergency Plan ML20028G8441990-08-27027 August 1990 Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 1990. HL-1245, Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d1990-08-23023 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d ML20056B3011990-08-20020 August 1990 Forwards Revised Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval, for Review & Approval.Program Will Be Implemented While Awaiting SER HL-1215, Informs of Implementation of Amend 169 to Facility Tech Specs1990-07-26026 July 1990 Informs of Implementation of Amend 169 to Facility Tech Specs HL-1035, Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists HL-1158, Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses1990-06-29029 June 1990 Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses ML20043E6691990-06-0707 June 1990 Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 13, Per Amend 168 to License DPR-57 ML20043C8621990-05-31031 May 1990 Submits Certification That Operator Licensing Simulation Facility Located at Plant Meets NRC Requirements ML20043A8081990-05-0707 May 1990 Forwards Response to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-321/90-07 & 50-366/90-07.Encl Withheld (Ref 10CFR73.21) ML20042F3331990-05-0101 May 1990 Provides Response to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Procedures Address Possibility of Vessel Overfill Events & Training Alert Operators to Potential Overfills ML20012C6351990-03-14014 March 1990 Responds to Generic Ltr 89-19 Re Safety Implementation of Control Sys in LWR Nuclear Power Plants,Per 890920 Request & Understands That NRC Has Agreed to Extend Response Deadline Until 900504 ML20012B7291990-03-0707 March 1990 Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant,Unit 2 Sept-Dec 1989 & Metallurgical Evaluation of Four Inch Pipe to Elbow Weld from Plant Hatch, Unit 2. ML20012B1161990-03-0707 March 1990 Forwards Results of Circuit Breaker Testing,Per Bulletin 88-010,per Telcon W/Lp Crocker ML20012A1261990-03-0101 March 1990 Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20012A9051990-02-27027 February 1990 Forwards Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Plant ML20012B4101990-02-22022 February 1990 Discusses NRC 900221 Granting of Discretionary Enforcement to Continue Shutdown Cooling Operation Until Reactor Level Instrument 1B21-N080A Can Be Returned to Svc.Replacement Expected to Be Completed by 900222 ML20006F4561990-02-20020 February 1990 Responds to Request for Addl Info Re Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matl & Impact on Plant Operations. RTNDT Value for Unit 2 Closure Flange Region Addressed ML20006D7481990-02-0606 February 1990 Forwards Final Technical Rept, Edwin I Hatch Nuclear Plant Unit 2 Reactor Containment Bldg 1989 Integrated Leakage Rate Test for Fall 1989 Maint/Refueling Outage,Per IE Notice 85-071 ML20006C9481990-01-31031 January 1990 Responds to NRC 900102 Ltr Re Violations Noted in Insp Repts 50-321/89-28 & 50-366/89-28.Corrective Actions:Deficiency Card Documenting Event Initiated as Required by Plant Procedures ML20006A8911990-01-23023 January 1990 Responds to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Plans to Augment Existing Programs or Implement New Programs to Meet Intent of Generic Ltr ML20005F9341990-01-10010 January 1990 Offers No Comments Re SALP Repts 50-321/89-22 & 50-366/89-22 Dtd 891205 ML20005E6491990-01-0202 January 1990 Responds to NRC 891208 Ltr Re Violations Noted in Insp Repts 50-321/89-30 & 50-366/89-30.Corrective Actions:Util Personnel Documented Engineering Judgment Used as Basis for Use of Agastat Relays in Question ML20005E5621989-12-28028 December 1989 Certifies That fitness-for-duty Program Meets 10CFR26 Requirements.Util Screens for Two Addl Substances Not Required by Rule,Benzodiazepine & Barbiturates.List Re Panel & Cutoff Levels Encl ML20005E1411989-12-28028 December 1989 Responds to Generic Ltr 89-10, Motor-Operated Valve Testing & Surveillance. Thermal Overloads on Most safety-related motor-operated Valves Are Jumpered During Operation.Epri Developing Program to Calculate Valve Thrust Requirements ML20005D9611989-12-22022 December 1989 Forwards Rev to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20011D8721989-12-21021 December 1989 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor-Darling S350W.... Review of Sys Drawings Determined That No Subj Valves Installed at Facilities ML19332G0371989-12-13013 December 1989 Summarizes Util Plans to Recaulk & Seal Plant Refueling Floor Precast Concrete Panel Walls,Per 891129 Telcon. Special Purpose Procedure Developed to Ensure That Containment Integrity Maintained During Recaulking ML19332G0201989-12-12012 December 1989 Forwards Addl Info Re Use of Code Case N-161 for Upgrading Ultrasonic Insp & Testing Instrument Calibr Blocks ML19332F3571989-12-0707 December 1989 Provides Feedback on NRC Pilot Project Involving Electronic Distribution of NRC Generic Communications.Sys Found to Be Most Useful Re Generic Ltrs & Bulletins Where Timely Receipt Critical ML19332E1521989-11-29029 November 1989 Responds to NRC 891101 Ltr Re Violations Noted in Insp Repts 50-321/89-19 & 50-366/89-19.Corrective Actions:Procedure 31GO-INS-001-OS Revised to Include Requirements to Record & Compare Valve Stroke Times Following Valve Maint ML19332D0921989-11-22022 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Closure Plan for USI A-10 Will Be Submitted in 1990.Response to USI A-47 Re Safety Implications of Control Sys Will Be Submitted in Mar 1990 ML19332E4451989-11-21021 November 1989 Certifies That Initial & Requalification License Operator Training Programs at Plant Accredited & Based on Sys Approach to Training,Per Generic Ltr 87-07 ML19327C2451989-11-13013 November 1989 Forwards Amend 13 to Indemnity Agreement B-69 ML19332B9461989-11-10010 November 1989 Forwards Updated Chronological Tabulated List of Outstanding Licensing Requests for Plant.List Identifies Priority Items for Early NRC Approval ML19327C0321989-11-0606 November 1989 Advises That No Corrections Necessary Re 890331 Response to NRC Bulletin 88-010,Suppl 1.Documentation Available at Plant Site for Review ML19325E8821989-11-0101 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Contingency Plan Developed Which Has Been Added to Security Plan to Include short-term Actions Against Attempted Sabotage ML19324B8741989-10-27027 October 1989 Transmits Proposed Program for Completing Individual Plant Exam Process,Per Generic Ltr 88-20 & NUREG-1335.Program Should Identify Method & Approach Selected for Performing Exam ML19325E5491989-10-27027 October 1989 Submits Update on Lighting Observed During NRC Insp on 891002-06.All Temporary Lighting Reinstalled.Mfg of Four Cluster Lights,Holophane,Has Been Onsite & Will Give Recommendations for Permanent Lighting ML19327B6151989-10-24024 October 1989 Responds to Generic Ltr 89-16, Hardened Vent, by Encouraging Licensees to Voluntarily Install Hardened Vent Under 10CFR50.59 ML19327B3001989-10-23023 October 1989 Documents NRC Agreement W/Util Justification for Use of Pathway Corp as Replacement Bellows Vendor,Based on 891004 Telcon.Util Proceeding W/Procurement of Replacement Bellows ML19327B1551989-10-17017 October 1989 Forwards Revs 0 to Corporate Emergency Implementing Procedures,Including HNEL-EIP-01,HNEL-EIP-02,HNEL-EIP-03, HNEL-EIP-04,HNEL-EIP-05,HNEL-EIP-06,HNEL-EIP-07,HNEL-EIP-08, HNEL-EIP-10 & HNEL-EIP-11 ML19325C7451989-10-11011 October 1989 Advises That Effective 890913 Th Hunt No Longer Employed by Util.Operator License Terminated ML20248H3061989-10-0404 October 1989 Forwards Revised Tech Specs to Util 890622 Application for Amends to Licenses DPR-57 & NPF-5,per NRC Request,Re cycle- Specific Parameter Limits ML20247G4631989-09-14014 September 1989 Responds to NRC Re Violations Noted in Insp Repts 50-321/89-08 & 50-366/89-08.Corrective Actions:Procedure Revised to Include Periodic Analysis of Fuel Oil Parameters & Change Sampling Methodology ML20246D4541989-08-22022 August 1989 Forwards Corrected Tech Spec Changes Re Reactor Protection Sys Instrumentation Surveillance Requirements,Per NRC Request 1990-09-04
[Table view] |
Text
_ _ _ _ _ _ - - _ _ _ _
t Georgia Pmer Cortpany 333 Poinut Amnue AtWla. Georgw LOWt T&r;h(e.e 404 'af.; C/26 M.enq AiMu-Post Of f te Ib 4M5 Atianta. GNrg a WW Georgia Power L T. Gacws tt ,e,m, ,, n ,+
Msuger fbJ.-ar I nr;meer ng wwJ Groef tex tear tr ger ED-85-508 1866N July 18, 1985 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nucicar Regulatory Comission Washington, D.C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 INSERVICE INSPECTION RELIEF REQUESTS Centlemen:
By letter dated August 12, 1983, Georgio Power Corpany (GPC) submitted to WC on updated inservice inspection / inservice testing (ISI/IST) program for Hatch Units 1 and 2 based on NRC verbal recommendations. That submittal updated the ISI/IST programs from the 1974 Edition of the ASME Section XI Code with Addenda through Summer 1975 to the 1980 Edition with Addenda through Winter 1980. After the submittal was made, the examination procedures and plans were updated to the extent practical to meet the later edition of the Code. Since that time, NRC has approved the IST portion of the program with conditions as discussed in the WC letter dated June 4, 1985. MC, however, declined to act on the ISI portion of the program for
[gz reasons discussed in GPC's letter NED-85-483 dated June 25, 1985.
b 8 The aforementioned CPC Ictter provided a new ten-year ISI/IST program mo for Hatch thits 1 and 2 since the Hatch Unit I first ten-year inspection W interval will conclude on December 31, 1985. It is the intention of CPC to complete the examinations for the Hatch Unit I first ten-year inspection Q
.o c interval based on the revised Long-Term Examination Plan which implements the ISI Program and was written to the 1980 Edition of ASE Section XI with p
Addenda through Winter 1980 where practical.
gg ma.o In order to complete the first ten-year inspection interval at Hatch Unit 1, relief from certain of the Code recuirements relative to inservice inspection is necessary. Enclosed herein as Attachment I are the relief
o' ,
Georgial'ower d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 July 18, 1985 Page Two recuests reouired by GPC for NRC review and approval. Please note that the reller reouest nunbers in Attachment 1 correspond with those in the June 25, 1985 submittal, where applicable. Nineteen (19) copies of this letter and its attachment are provided for your convenience.
The relief reauests in Attachment I were based on a review of unresolved items in the safety evaluation report issued by NRC letter dated July 29, 1983 for the ISI program written to the 1974 Code, impractical 1980 Code reouirements, and other relief as identified. GPC reouests that WC grant the relief reouests included in Attachment 1 in accordance with 10 CFR 50.55a (g)(6). The relief reouested does not affect public health and safety.
The Hatch thit 1 maintenance / refueling outage is scheduled to begin November 30, 1985. Because of the extensive pre-outage planning associated with this effort, we respectfully reouest that ouestions concerning the enclosed inservice inspection relief reouests be brought to our prompt attention. To support our major planning ef fort, we are seeking your approval within 30 days of the date of this letter. Should you have any cuestions in this regard, please contact this office at anytime. We will give top priority to responding to your cuestions.
Pursuant to the recuirements of 10 CFR 170, enclosed herein as payment of the application fee for review of the subject relief reouests is our check in the amount of $150.00.
Very truly yours,
/X@=
L. T. Cucwa JAE/olm
Enclosures:
- 1. Attachment 1 - Hatch Unit 1 Inservice Inspection Relief Recuests
- 2. Application Fee Check xc J. T. Beckham, Jr.
H. C. Nix, Jr.
J. N. Grace (NRC-Region II)
Senior Resident Inspector
ATTACHENT 1 HATCH UNIT 1 - INSERVICE INSPECTION RELIEF REQUESTS 1
l l
l 07/18/85
l ,
2.1.1 Volumetric Examination of Reactor Pressure Vessel and Closure Head Welds 2.1.1.1 Recuirement From Which Relief is Recuested Item Nos. B1.11, Bl.12, B1.21, and 81.22 of Table IWB-2500-1 for the 1980 Edition of ASME Section XI recuire the volumetric examination of Reactor Pressure Vessel (RPV) and Closure Head circumferential, longitudinal, and meridional welds. At Hatch, these examinations will be performed using ultrasonic technicues. The applicable examination volumes are shown in Figures IWB-2500-1, -2, and -3. The Code also recuires that welds selected for examination are to be examined for essentially 100% of their length.
Relief from this'recuirement'is reouested.
2.1.1.2 Justification At Hatch, physical limitations prevent the examination of the entire length of these welds. The 1974 Edition with Addenda through Summer 1975 and earlier editions of the ASME Section XI Code recuired that the examination cover at least 10% of the length of each longitudinal weld and 5% of the length of each circumferential weld. For Hatch 1, the minimum lengths described above were met for those welds examined previously. For Hatch 1 RPV circumferential and longitudinal welds, approximately 5 to 15% of the total length of the welds are to be examined.
Limitations also exist for the ultrasonic examination of RPV bottom head circumferential and meridional welds. To complete the ekaminations for the first ten-year interval, the examination coverage for the following welds will still be per the 1974 Edition of the ASME Section XI Code with the following limitations:
Weld No./ Description Coverage / Limitations C-7 5% of weld to be examined; (Bottom Head Torus to examination will be performed Bottom Head Dome Circ. Weld) from one side only (bottom head torus side) due to the RPV support skirt BHT-A,-B,-C,-D,-E,-F,-G, and -H 10% of weld to be examined (Bottom Head Torus Meridional Welds)
The examination of the following welds is not possible due to inaccessibility. The RPV support skirt surrounds these welds and prohibits any examination.
Weld No./ Description Coverage / Limitations C-8 No examination (Bottom Head Dollar Plate Circumferential Weld)
BHD-A,-8,-C,-D,-E, and -F Na examination (Bottom Head Dome Meridional Welds) 07/18/85 - - _ .
l I
No known limitations exist for the ultrasonic examination of RPV Closure Head
,. circumferential and meridional welds.
L.
I 2.1.1.3 Testing in Lieu of ASE Section XI Recuirements For future examinations of RPV circumferential, longitudinal, and meridional welds, the examinations will be performed to the extent possible as described in the previous paragraphs.
07/18/85 - _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _
2.1.2 Straight Beam Examination of Reactor Pressure Vessel and Closure Head Welds Including Nozzle-to-Vessel Welds 2.1.2.1 Recuirement From Which Relief is Recuested Subparagraph T-441.4.3 of Article 4 for the 1980 Edition of ASME Section V recuires that prior to the angle beam examination, the base material through which the angle beam will travel shall be scanned with a straight beam transducer to detect laminar reflectors which might affect the angle beam results.
2.1.2.2 Justification During the preservice examination at Hatch 1, the adjacent base material for the RPV and Closure Head welds, including the Nozzle-to-Vessel welds, were examined with a straight beam transducer and any laminar reflectors which would interfere with the angle beam scans were recorded. Since the size of these reflectors will not change, it is unnecessary to perform the straight beam scans again. Also, these scans would only result in additional radiation exposure without a corresponding benefit in reliability.
2.1.2.3 Testing in Lieu of ASME Section XI Recuirements Other examinations designed to detect service-induced flaws are recuired by ASME Section XI on these welds.
07/18/85 - - _. .
2.1.3 Volumetric Examination of Reactor Pressure Vessel and Closure Head Nozzle-to-Vessel Welds and Nozzle Inside Radius Sections 2.1.3.1 Recuirement From Which Relief is Recuested Item Nos. 83.90 and B3.100 of Table IWB-2500-1 for the 1980 Edition of ASME Section XI reouire the volumetric examination of RPV and Closure Head Nozzle-to-Vessel welds and Nozzle Inside Radius Sections. The applicable examination volumes are shown in Figures IWB-2500-7(a) through (d). At Hatch, these examinations will be performed using ultrasonic technioues.
2.1.3.2 Justification At Hatch, physical limitations prevent the ultrasonic sound beam from passing through the entire examinat!;n volume as shown by Figure IWB-2500-7(a) through (d). At a minimum, eight-five percent (85%) of the examination volume has ultrasonic sound beams passing through it. Showing the Nozzle-to-Vessel weld as N to V and the Nozzle Inside Radius Section as IRS, the following Hatch 1 nozzles cannot receive a full-Code examination:
Nozzle Identification Limited Examinations N2A (Recirc. Inlet) N to V N2B (Recirc. Inlet) N to V N2C (Recirc. Inlet) N to V N2D (Recirc. Inlet) N to V N2E (Recirc. Inlet) N to V N2F (Recirc. Inlet) N to V N2G (Recirc. Inlet) N to V N2H (Recirc. Inlet) N to V N2J (Recirc. Inlet) N to V N2K (Recirc. Inlet) N to V N48 (Feedwater) N to V; IRS N4D (Feedwater) N to V; IRS The nozzles listed above are the only ones with known limitations. Any other welds where limitations are encountered will have such limitations reviewed and documented.
2.1.3.3 Testing in Lieu of ASME Section XI Recuirements Not applicable to this relief reouest.
07/18/85 . -. -
2.1.4 Volumetric Examination of Austenitic and Dissimilar Metal Piping Welds 2.1.4.1 Reouirement From Which Relief is Recuested Item Nos. B5.10, B5.50, B9.ll, and B9.12 of Table IWB-2500-1 for the 1980 Edition of ASME Section XI recuire a volumetric and surface examination of austenitic and dissimilar metal piping welds. In addition, Item No. B14.10 of Table IWB-2500-1 reouires either a volumetric or a surface examination of the pressure retaining welds in Control Rod. Drive (CRD) housings. These volumetric examinations are to be performed using ultrasonic technioues in accordance with Paragraph IWA-2232 of Section XI. This paragraph specifies that austenitic and dissimilar metal piping welds are to be examined in accordance with Article 5 of ASME Section V.
2.1.4.2 Justification Article 5 of ASME Section V does not provide the detailed guidance necessary to examine austenitic and dissimilar metal piping welds with the exception of austenitic piping welds which have been repaired by weld overlay. These clad overlaid piping welds will be examined in accordance with Article 5 of ASME Section V and Appendix III of ASME Section XI.
2.1.4.3 Testing in Lieu of ASME Section XI Recuirements Since ferritic piping welds will be examined per Appendix III of ASME Section XI and to provide consistency, austenitic and dissimilar metal piping welds will also be examined in accordance with Appendix III.
f l
l i
! 07/18/85 l
- - - ,- -- , y
2.1.6 - Reactor Pressure Vessel Nozzle to Safe-End Welds (Nominal Pipe Size
<4 Inches) 2.1.6.1 Recuirement From Which Relief is Recuested Item No. B5.11 of Table IWB-2500-1 for the 1980 Edition of ASME Section XI recuires a surface examination of the RPV nozzle-to-safe-end welds with nominal pipe size <4 inches. Relief from this reouirement is reouested.
2.1.6.2 Justification The nozzle-to-safe-end welds for the instrumentation nozzles listed below are physically inaccessible for surface examination. The affected Hatch 1 nozzles are:
a N10 N11A N118 N12A N128 N16A N168 In addition, the 2-inch RPV bottom head drain nozzle-to-safe-end weld cannot be examined due to inaccessibility. This drain line is surrounded by instrumentation lines and CRD housings which prevent the examiner from
- performing this examination.
2.1.6.3 Testing in Lieu of ASME Section XI Recuirements The nozzle-to-safe-end welds listed above will receive a remote visual examination with the exception of the 2-inch drain nozzle weld. In addition, these nozzles will be pressure tested per IWB-5000 of ASME Section XI since they are located within the hydrostatic test boundary of the Nuclear Steam Supply System.
07/18/85 _,. - - , - - - - -
2.1.7 Volumetric and Surface Examinations of Pressure Retaining Welds in Piping with Nominal Pipe Size 2 4 Inches 2.1.7.1 Recuirement From Which Relief is Recuested Item No. B9.11 of Table IWB-2500-1 for the 1980 Edition of ASME Section XI recuires the examination of pressure retaining welds in piping that are located within flued head containment penetration assemblies. These welds and diqir penetration assenbly number for Hatch 1 are listed below.
Weld Identification No. Penetration No.
1821-lFW-18A-7A X-9A 1821-lFW-188-6A X-98 IE51-lRCIC-4-D-20A X-10 lE41-lHPCI-10-D-15A X-ll 1E11-1RHR-208-D-13A X-12
, .lEll-lRHR-24A-R-3A X-13A lEll-1RHR-248-R-38 X-138 1G31-1RWCU-6-D-15B X-14 1G31-lRWCU-6-D-15C X-14 lE21-lCS-10A-3A X-16A lE21-lCS-10B-4A X-168 1 Ell-lRHR-4-HS-6A X-17 2.1.7.2 Justification These' welds are inaccessible for examination due to the design of the flued head. All twelve circumferential butt welds, except the two located in the Reactor Water Cleanup (RWCU) penetration, are carbon steel.
The two stainless steel welds that are located in the RWCU penetration were made to replace a Type 304 SS pipe that had undergone IGSCC. The welds involved are a flued head with a Type 308L corrosion resistant clad on the inside surface to a Type 304L solution annealed pipe (<.035% carbon), and a Type 304L pipe-to-pipe weld. These welds were made in accordance with the guidelines of NUREG-0313 to minimize susceptibility to ICSCC.
2.1.7.3 Testing in Lieu of ASME Section XI Recuirements A UT baseline was performed on the two new welds in the RWCU system while they were accessible during repair to ensure a high ouality weld.
In accordance with IWB-5221 of ASME Section XI, a system leakage test is to be performed on all 12 welds prior to startup following each reactor refueling outage.
All pipe-to-penetration (flued head) welds outside containment will be examined volumetrically. In addition, a surface examination will be performed on the accessible weld (s) of the flued head penetration assembly.
07/18/85
-_ m. _ _ . . . . . . . _ _ . . _ ._ _ _ ___ _ _ - .
.l ..
2.1.8 ASE Class 1 (fouivalent) Valves Exceeding 4-Inches Nominal Pipe Size and ASE Class-1 (Ecuivalent) Pump Casings
- 2.13.1 Recuirement From Which Relief is Recuested Table IWS-2500-1, Item No. B12.40 for the 1980 Edition of ASE Section XI
reouires a visual examination of the internal pressure boundary surfaces of one valve in each group of valves that are of the same constructional design,
- such as globe, gate, or check valve, and manufacturing method and that are performing similar functions in the system.
Table IWB-2500-1, Item No. 812.20 of ASE Section XI reouires a visual I
- examination of the internal pressure boundary surface of one of the two
- Reactor Recirculation system pumps.
2.1.8.2 Justification 4
Disassembly of these valves and pumps for the visual examination during the '
inspection interval, in the absence of other recuired maintenance, represents an unnecessary exposure to radiation and contamination. Valves on the Reactor i Recirculation (RC) system and the Residual Heat Removal (RIR) system suction t lines would reouire off-loading the fuel elements and draining the RPV prior to disassembly. Work on the RC system pump discharge valves and the RHR system injection valves would recuire the installation of plugs in the jet pump risers. Preparatory work of this scope is considered impractical for the sole purpose of conducting a visual examination. Contamination levels in the valves and pumps associated with the RC system loops are particularly high due to the physical location at the bottom of the system. During routine t maintenance, the valve body and the pump _ casing internal surfaces are visually examined. Many of the valves, particularly the containment isolation valves are disassembled for maintenance of leak-tightness. Disassembly of other
- Class 1 valves and the pumps solely for internal examination is counter to the "ALARA" guidelines to keep the occupational dose rates as low as reasonably achievable. In view of the cost in man-rem and in view of the minimal benefits obtained, we conclude that this Code reouirement does not provide '
sufficient benefits to justify the exposure.
2.1.8.3 Testing in Lieu of ASE Section XI Reauirements Class 1 pumps and Class 1 valves exceeding four inches nominal pipe size are
- subject to visual examination of the internal surfaces when disassembled for maintenance. The coverage provided by examinations during routine maintenance coupled with periodic leak tests and hydrostatic tests will provide adeouate assurance of the structural integrity of the Class 1 pumps and valves, while keeping exposure to radiation and contamination as low as reasonably
- achievable.
4 f.
4
! 07/18/85 :
2.1.9 Pressure Retaining Welds in Control Rod Drive Housings 2.1.9.1 Recuirement From Which Relief is Recuested Table IWB-2500-1, Item No. B14.10 for the 1980 Edition of ASME Section XI recuires. a volumetric or surface examination of the pressure retaining welds in 10% of the peripheral Control Rod Drive housings. Each housing has a pipe-to-pipe weld located near the RPV and a pipe-to-flange weld.
2.1.9.2 Justification The examination of the pipe-to-pipe welds is not possible due to inaccessibility. The RPV support skirt surrounds the CRDs and prohibits any examination. (See relief reauest 2.1.1).
The examination of the pipe-to-flange welds is limited because of the location and design of the housings. Physical accessibility by an examiner is extremely limited by the close proximity of the housings to each other and by the support arrangement. Also, the insert and withdraw lines to the Control Rod Drive system are connected at the top of the housing flange and limit access to much of the lower weld. The combination of these factors limit the examination of these welds.
2.1.9.3 Testing in Lieu of ASME Section XI Recuirements These welds will be pressure tested per IWB-5000 of ASME Section XI since they :
are located within the hydrostatic test boundary of the Nuclear Steam Supply i system.
I l
07/18/85 .
3.1.1 Volumetric Examination of Pressure Retaining Welds in Class 2 Vessels 3.1.1.1 Recuirement From Which Relief is Rect'ested Item Nos. C1.10, Cl.20, and C1.30 of Table IWC-2500-1 for the 1980 Edition of ASME Section XI recuire the volumetric examination of Class 2 vessel shell circumferential, head circumferential, and tubesheet-to-shell circumferential welds, respectively. The volumetric examination of the Residual Heat Removal (RHR) system heat exchanger circumferential welds will be performed using ,
ultrasonic technioues. The recuired examination volumes are shown in ASME I Section XI Figures IWC-2500-1 and -2. Relief from this recuirement is recuested.
3.1.1.2 Justification The shell and head circumferential weld examinations are limited by vessel j supports adjacent to these welds. In addition, the ultrasonic examination of l the head circumferential weld from the head side cannot be performed due to configuration. The examination volume as recuired by Figure IWC-2500-2 for the tubesheet-to-shell weld cannot fully be met due to configuration also.
3.1.1.3 Testing in Lieu of ASME Section XI Recuirements The ultrasonic examination of the shell and head circumferential welds will be supplemented by a surface examination. The tubesheet to shell weld cannot be properly prepared for surface examination nor can the examination be performed due to the tubesheet studs and nuts adjacent to the weld. In addition to the examinations described above, system pressure tests per Article IWC-5000 of ASME Section XI will be performed on these welds.
1 07/18/85 l
3.1.2 Surface Examination of Welded Attachments on RHR, Core Spray, HPCI, and RCIC Suction Lines from Torus 3.1.2.1 Recuirement From Which Relief is Recuested Item No. C3.40 of Table IWC-2500-1 for the 1980 Edition of ASME Section XI recuires 100% surface examination of integrally welded attachments on piping.
Figure IWC-2500-5 determines the surface area of this examination. a.
Suction lines for RHR, Core Spray, HPCI, and RCIC systems penetrating the torus are seal welded to the outside surface of the torus wall. Relief is reouested from the surface examination of these welded attachments.
3.1.2.2 Justification At both Hatch units, these integrally welded attachments on lines penetrating the torus are obstructed by reinforcement plates added after plant construction. One hundred percent (100%) of the seal weld is inaccessible for a meaningful surface examination.
r 3.1.2.3 Testing in Lieu of ASME Section XI Recuirements Visual examination (VT-1) in accordance with IWA-2211 will be performed to insure the integrity of these attachments.
07/18/85 . - . _.
3.1.3 Surface Examination of Pressure Retaining Welds in Class 2 Pumps 3.1.3.1 Recuirement From Which Relief is Recuested Item No. C6.10 of Table IWC-2500-1 for the 1980 Edition of ASME Section XI reouires a surface examination of the pump casing welds from one Class 2 pump in each group of pumps that are of similar design, size, function, and service in a system. Relief from this recuirement is reouested.
3.1.3.2 Justi71 cation Disassembly of these pumps for the surface examination during the inspection interval, in the absence of other recuired maintenance, represents an unnecessary exposure to radiation and contamination. During routine maintenance, the pump casing welds receive a surface examination. In view of the cost in man-rem and in view of the minimal benefits obtained, we conclude that this Code recuirement does not provide a corresponding benefit in reliability.
3.1.3.3 Testing in Lieu of ASME Section XI Recuirements Class 2 pump casing welds are subject to surface examination when disassembled for maintenance. The coverage provided by examinations during routine maintenance coupled with hydrostatic tests will provide adeouate assurance of the structural integrity of these pumps, while keeping exposure to radiation and contamination as low as reasonably achievable.
I 07/18/85 1
4.1.1 System Pressure Tests on Class 3 Small Diameter Piping 4.1.1.1 Reouirement From Which Relief is Recuested Table IWD-2500-1 for the 1980 Edition of ASME Section XI recuires a system pressure test for Class 3 lines regardless of size.
4.1.1.2 Justification The system pressure test recuirements for Class 3 will not be performed on lines two inches and smaller unless:
- a. They are connected to larger lines which will be pressure tested.
- b. Isolation valves are not provided so that these smaller lines may be isolated in case of leakage.
These smaller lines have wall thicknesses in excess of what ASME Section III recuires for retaining internal pressure. Using heavier walled piping in these small lines essentially means they are over-designed for the pressure they are retaining and are not susceptible to the type leakages found during hydrostatic testing.
4.1.1.3 Testing in Lieu of ASME Section XI Recuirements Accessible piping two inches and smaller will be visually examined under normal operating pressure.
07/18/85 l l
4.1.2 System Pressure Tests on Class 3 Buried Piping 4.1.2.1 Recuirement From Which Relief is Recuested Table IWD-2500-1 of the 1980 Edition of ASME Section XI recuires a system pressure test for Class 3 components including buried piping.
4.1.2.2 Justification The service water systems were designed without including provisions for testing buried piping as recuired by Paragraph IWA-5244. In addition, the visual examination for leakage at the ground level is not feasible since a majority of the piping is buried under asphalt.
4.1.2.3 Testing in Lieu of ASME Section XI Recuirements Normal system functional testing demonstrates leaktight integrity of all buried piping.
07/18/85 4.1.3 Pressure Test on Plant Service Water System 4.1.3.1 Recuirement From Which Relief is Recuested IWD-5223 of the 1980 Edition of ASME Section XI recuires that the Plant Service Water System be tested at a pressure of 1.10 times the design pressure. Relief is reouested from testing those portions where it is necessary-to use a butterfly valve ten inches in diameter or greater as a hydrostatic test boundary valve.
4.1.3.2 Justification Butterfly valves are basically flow control valves and are not intended to be block valves. The normal leakage through these large valves makes it impractical to attain and maintain the hydrostatic test pressure.
4.1.3.3 Testing in Lieu of ASME Section XI Recuirements A hydrostatic test will be performed on those portions of the Plant Service Water System which have a butterfly valve ten inches in diameter or greater at the normal operating pressure.
07/18/85 .l
5.1.1 Recuirement to Verify Hot or Cold Settings on Spring Cans and Snubbers 5.1.1.1 Reouirement From Which Relief is Recuested .
Subparagraph IWF-3410(a)(5) of the 1980 Edition of ASME Section XI states that a component support condition which is unacceptable for continued service is improper hot or cold positions for spring supports or snubbers. Relief from this reouirement is reouested.
5.1.1.2 -Justification There are no exact design positions on the scales for spring supports or snubbers but an operational range where the indicator should be located.
5.1.1.3 Testing in Lieu of ASME Section XI Recuirements The visual examination will verify that the indicator falls within the operational limits.
l l l l
I l
i 07/18/85 _ _- ____ _. - _ _ - __ . - - - - _ _ _. , - _ _ _ _ _
.._ _ . _,1
5.1.3 Visual Examination of ASME Class 1, 2, and 3 Component Supports 5.1.3.1 Recuirement From Which Relief is Recuested IWF-2410 of the 1980 Edition of ASME Section XI recuires that visual examinations of component supports be completed in accordance with the applicable section of IWB, IWC, or IWD; however, IWB does not specify a minimum line size for which component supports may be exempted. Relief is recuested from examining supports on ASME Class I lines, 2-inch nominal pipe diameter and less, during the completion of the Hatch Unit No. 1 first 10-year interval. Also, supports on ASME Class 2 and 3 lines 4-inch nominal pipe diameter and less will not be examined.
5.1.3.2 Justification The hanger surveillance program for the first 10-year interval wLs originally based on the 1974 Edition of ASME Section XI with Addenda through Summer 1975. In this edition of the Code, IWB-1220(b)(1) allowed the exemption of all components where under the postulated condition of loss of coolant from the component during normal reactor operation, the reactor can be shut down using only a normal makeup system. For Plant Hatch, 2-inch nominal pipe diameter lines and smaller with associated supports may be exempted using IWB-1220(b)(1). Also, IWC-1220(d) and IWD-2600(c) allowed the exemption of supports on lines 4-inch nominal pipe diameter and less.
Since all supporting documentation, examination plans, and procedures incorporate this exemption, the scope of examinations to complete the first 10-year interval will continue to be determined from the 1974 Edition of the Code. Examination technioues will be determined from the 1980 Edition of ASME Section XI with Addenda through Winter 1980.
5.1.3.3 Testing in Lieu of ASME Section XI Recuirements All supports on ASME Class 1 lines greater than 2-inch nominal pipe diameter will be visually examined. All supports on ASME Class 2 and 3 lines greater than 4-inch nominal pipe diameter will be visually examined.
l 07/18/85 o .
8.1.1 Basic Calibration Blocks for Pipe Weld Examinations 8.1.1.1 Recuirement From Which Relief is Recuested Appendix III of the 1980 Edition of ASME Section XI delineates the recuirements for the design and fabrication of basic calibration blocks for pipe weld examinations. It specifies that the basic calibration block shall be fabricated with notches and that the basic calibration block nominal diameter and thickness be ecuivalent to the component to be examined. Relief is recuested so that existing basic calibration blocks may be used for pipe weld examinations.
8.1.1.2 Justification The majority of existing Hatch basic calibration blocks used for pipe weld examinations were fabricated with diameters, thicknesses, and side-drilled holes in accordance with the 1974 Edition of ASME Section V. For the two primary reasons listed below, these same basic calibration blocks will be used to provide the most meaningful and thorough examinations possible:
- 1. Side-drilled holes as calibration reflectors result in a more sensitive ultrasonic examination than one using notches.
- 2. Correlation of ultrasonic data with previous examinations as recuired by Subarticle IWA-1400 of ASME Section XI makes it necessary that these basic calibration blocks be used so future examination results can be correlated with past results.
8.1.1.3 Testing in Lieu of ASME Section XI Recuirements The basic calibration blocks using side-drilled holes as calibration reflectors will be used for the majority of the pipe weld examinations.
l 07/18/85 i
8.1.3 Incorporation of Changes in Design, Testing, and Procedures without any Unreviewed Safety Questions into The Inservice Inspection Program / Plan 8.1.3.1 Recuirement From Which Relief is Recuested 10 CFR Part 50.59 allows changes to a nuclear facility and procedural changes in accordance with Plant Technical Specifications and the safety analysis report, without prior approval from the NRC, provided there are no unreviewed safety cuestions. The facility's Inservice Inspection Program / Plan should be revised to include these changes.
Changes such as valve operator, stroke time, pump performance, welds, etc.,
made in compliance with 10 CFR 50.59, which affects the ASME Section XI ,
> recuirements may not be shown on the existing revision of the ISI program plan !
document. A relief is reauested from this inconsistency.
8.1.3.2 Justification Records of these changes will be maintained and any changes in ASME Section XI recuirements pertaining to these changes will be complied with. However, a revision to the ISI Program Plan (s) for every minor change is unrealistic, costly and time consuming task. Any delay in revising the ISI program plan (s) will not endanger public health and safety.
8.1.3.3 Testing in Lieu of ASME Section XI Recuirements Records of all changes will be maintained. Changes affecting ASME Section XI recuirements shall be incorporated into the ISI Program Plan (s), whenever a need for their update is warranted.
1 07/18/85 1
8.1.5 Due Date for Owner's Data Report for Inservice Inspection, Form NIS-1 8.1.5.1 Recuirement From Which Rellef is Recuested l
Paragraph IWA-6230 of the 1980 Edition of ASME Section XI reouires that the Owner's Data Report for Inservice Inspection, Form NIS-1, shall be filed with the enforcement and re Regulatory Commission)gulatory authorities (in this case, the Nuclearwithin 90 day inspection. Relief from the ISI completion date relative to the reporting '
reouirement and the due date are reouested.
8.1.5.2 Justification The 90-day due date from the completion of the inservice inspection is unrealistic to prepare the NIS-1 Form and to have the multiple reviews reouired. The preparation of the NIS-1 Form itself reouires almost 90 days with at least another 30 days needed for the review by site personnel and the Inspector.
4 8.1.5.3 Reporting in Lieu of ASME Section XI Recuirements I form NIS-1 will be submitted to the NRC within 120 days after completion of l the outage in which the examinations were performed.
J, .
- i i
I i
i l l
07/18/85 ,
.