Letter Sequence RAI |
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MONTHYEARML20204A2801982-08-18018 August 1982 Instructions for Calculation of Offsite Dose from Limiting Primary Sys Break Which Does Not Isolate Primary Containment Vent & Purge Valves Project stage: Other ML20076J5441983-08-31031 August 1983 Comments on 810629 Generic Evaluation of NUREG-0737,Item II.E.4.2 Containment Purge & Vent Valve High Radiation Isolation. Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Unnecessary Project stage: Other ML20084P5971984-04-10010 April 1984 Forwards Final Design Criteria for Resolution of NUREG-0737, Item II.E.4.2(7), Purge & Vent Valve Isolation, Requiring Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Project stage: Other ML20084L3701984-05-0707 May 1984 Forwards Figures 1 & 2,inadvertently Omitted from 840410 Submittal,Providing Description of Mods Planned to Satisfy Purge & Vent Valve Isolation Requirements of TMI Item II.E.4.2 Project stage: Other ML20097A7211984-09-0505 September 1984 Proposed Amend to Tech Specs,Reflecting Implementation of NUREG-0737,Item II.E.4.2(7) Re Automatic Closure of Containment Purge & Vent Valves on High Containment Radiation Signal Project stage: Other ML20097A7121984-09-0505 September 1984 Application to Amend License NPF-5,changing Tech Specs to Reflect Implementation of NUREG-0737,Item II.E.4.2(7) Re Containment Purge & Vent Valves.Change Adds Limiting Conditions for Operation & Surveillance Requirements Project stage: Request ML20128A0331985-06-25025 June 1985 Forwards Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981, Effective 860101. Interim Relief Requested in Event That Final Review/Approval Not Provided by Program Effective Date.Fee Paid Project stage: Request PNO-II-85-071, on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed1985-07-25025 July 1985 PNO-II-85-071:on 850724,unit Tripped as Result of High Steam Flow Signal.Caused by Malfunctioning Msiv.Unit out-of-svc for 3 to 5 Days While Valve Repaired & Maint Work Performed Project stage: Request ML20137F9931985-08-20020 August 1985 Proposed Revs to Tech Spec Tables 3.2-1 & 4.2-1 Re Purge/Vent Valve Isolation Project stage: Other ML20137F9761985-08-20020 August 1985 Application for Amend to License DPR-57,reflecting Addition of High Radiation Isolation Signal for Containment Purge & Vent Valves.Fee Paid Project stage: Request ML20138B2331985-10-0404 October 1985 Informs That Util on Purge & Vent Mods Contained Proposed Tech Spec Requirements More Restrictive than Those Reviewed by Plant Review Board.Board Will Review Requirements by 851010 Project stage: Other ML20136A7651985-12-23023 December 1985 Forwards Request for Addl Info Re Inservice Insp Program for Second 10-yr Interval.Response Requested within 30 Days of Ltr Receipt Project stage: RAI ML20244D7371986-03-11011 March 1986 Forwards Safety Evaluation Accepting BWR Owners Group 850620 Request for Review of Offsite Radiological Consequences for Accidental Releases Not Meeting NUREG-0737, Item II.E.4.2(7).Regulatory Analysis Also Encl Project stage: Approval ML20204A2781986-04-28028 April 1986 Forwards Request for Addl Info Re Request for Rev to Tech Specs to Reflect Addition of Closure of Containment Purge & Vent Valves on High Containment Radiation Signal.Response Requested within 60 Days Project stage: RAI ML20199K5171986-06-26026 June 1986 Forwards Response to 860428 Request for Info Re Automatic Isolation of Containment Purge & Vent Valves on High Containment Radiation Signal.Procedures for Venting Containment Have Separate Sections for Drywell & Torus Project stage: Request 1985-12-23
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Similar Documents at Hatch |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20216H3641999-09-20020 September 1999 Forwards NRC Form 536 in Response to AL 99-03, Preparation & Scheduling of Operator Licensing Exams HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-5731999-09-16016 September 1999 Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573 ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification1999-09-13013 September 1999 Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification HL-5832, Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC1999-09-0101 September 1999 Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations1999-08-20020 August 1999 Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)1999-08-19019 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d) HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 141999-08-19019 August 1999 Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14 HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.111999-08-18018 August 1999 Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11 ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999 Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528 05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999 Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999 Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage1999-07-15015 July 1999 Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-14014 July 1999 Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999 Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210 HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999 Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively1999-07-0909 July 1999 Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999 Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999 Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999 Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999 Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21 HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999 Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant ML20205H1491999-03-25025 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 1999-09-24
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6171990-11-19019 November 1990 Forwards Insp Repts 50-321/90-22 & 50-366/90-22 on 901015- 19.No Violations or Deviations Noted ML20062F8171990-11-14014 November 1990 Forwards Insp Repts 50-321/90-20 & 50-366/90-20 on 900915- 1020 & Notice of Violation ML20058H8421990-11-13013 November 1990 Forwards Insp Repts 50-321/90-21 & 50-366/90-21 on 901001- 05.No Violations or Deviations Noted ML20217A2921990-11-13013 November 1990 Advises That Kn Jabbour Assigned as Project Manager for Plant ML20217A7441990-11-0707 November 1990 Forwards Insp Repts 50-321/90-16 & 50-366/90-16 on 901001-12.No Violations or Deviations Noted ML20058E8491990-10-23023 October 1990 Forwards Insp Repts 50-321/90-19 & 50-366/90-19 on 900925-28.No Violations or Deviations Noted ML20062B2461990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20059J9151990-09-0707 September 1990 Forwards Guidance for Reporting of Events Under Requirements of 10CFR50.73.W/o Encl ML20058M3561990-08-0808 August 1990 Discusses Util Response to Generic Ltr 89-10, Safety- Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Licensees Test MOVs in Situ Under Design Basis Conditions ML20058L5031990-08-0303 August 1990 Advises That 900727 Response to Generic Ltr 88-14 Re Instrument Air Supply Sys Problems Affecting safety-related Equipment,Acceptable ML20055H3581990-07-23023 July 1990 Advises That Util Provided Acceptable Resolution to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs ML20055H6451990-07-13013 July 1990 Forwards Insp Repts 50-321/90-14 & 50-366/90-14 on 900512-0622.No Violations or Deviations Noted ML20055E8841990-07-10010 July 1990 Advises That EAS-28-0589, Edwin I Hatch Nuclear Plant Basis for Use of Homogeneous Equilibrium Model for Environ Qualification & Radiological Release Evaluation, Withheld from Public Disclosure (Ref 10CFR2.790),per 900628 Request ML20055H3451990-06-21021 June 1990 Responds to Re Basis for Employment Action Involving Former Util Employee Reporting Safety Concerns. Concurs W/Request to Defer Further Discussion Until Completion of Dept of Labor Process ML20059M9561990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055D0021990-06-11011 June 1990 Discusses Util 900514 Application for Amend to License NPF-47,increasing Suppression Pool Temp from 95 F to 100 F. Requests That Util Demonstrate Applicability of Items Addressed in Encl Hatch Safety Evaluation to Facility ML20055C5131990-05-17017 May 1990 Authorizes Restart of Facility When Identified Flaws in Welds Repaired W/Overlay Designs,Per Util & Generic Ltr 88-01.Full Rept of outage-related Insp Activities Should Be Submitted Following Restart ML20055C4771990-05-11011 May 1990 Forwards Insp Repts 50-321/90-13 & 50-366/90-13 on 900430-0504.No Violations or Deviations Noted ML20248D1821989-09-20020 September 1989 Forwards Insp Repts 50-321/89-16 & 50-366/89-16 on 890722- 0825.Violations Noted But Not Cited Since All Criteria of licensee-identified Violations Met ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247C9281989-09-0606 September 1989 Forwards Exam Rept 50-321/OL-89-01 Administered on 890612-16.Concerns Raised Re pre-exam Review Ineffective in Ensuring site-specific Exam Validity & Operator Generic Weaknesses ML20247B3931989-09-0505 September 1989 Forwards Insp Repts 50-321/89-17 & 50-366/89-17 on 890612-16 & 0731-0804.No Violations or Deviations Noted ML20247B5381989-09-0101 September 1989 Forwards Insp Repts 50-321/89-18 & 50-366/89-18 on 890807-11.Violation Noted But Not Cited,Based on Meeting Criteria of licensee-identified Violations ML20246E6861989-08-24024 August 1989 Advises That 890807 Rev to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20246M8791989-08-23023 August 1989 Forwards Insp Repts 50-321/89-13 & 50-366/89-13 on 890710-13.Violations Noted ML20246P4921989-08-22022 August 1989 Forwards Insp Repts 50-321/89-15 & 50-366/89-15 on 890724-28.No Violations or Deviations Noted ML20246N8001989-08-18018 August 1989 Forwards Insp Repts 50-321/89-08 & 50-366/89-08 on 890515-19,0605-09 & 19 & Notice of Violation.Concern Raised Re Implementation of Inservice Testing of Pumps & Valves on Emergency Diesel Generator Sys ML20246C9721989-08-16016 August 1989 Advises That Apr 1989 Rev 9 to Emergency Plan Meets Planning Stds of 10CFR50.47(b) & Requirements of 10CFR50,App E ML20246A6621989-08-0808 August 1989 Forwards Insp Repts 50-321/89-14 & 50-366/89-14 on 890717-20.No Violations or Deviations Noted ML20248C9041989-08-0202 August 1989 Forwards Insp Repts 50-321/89-12 & 50-366/89-12 on 890624-0721.Violations Noted.Violation Not Being Cited Due to Licensee Meeting All of Criteria for Categorization of licensee-identified Violations ML20248A2941989-08-0101 August 1989 Discusses Util Compliance W/Atws Rule (10CFR50.62).Design Change to Utilize Test Switches to Block Actuation Signal to Alternate Rod Injection Solenoid Valve During Testing Acceptable ML20247N7801989-07-27027 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/88-37 & 50-366/88-37.Violation Occurred as Stated in Notice of Violation.Assessment Withheld (Ref 10CFR73.21) ML20247E6181989-07-24024 July 1989 Informs of Agreement Reached During 890719 Telcon Re IGSCC Exam for Fall 1989 Refueling/Maint Outage & Matter of Calibr Blocks to Be Used for Ultrasonic Insp Activities During Outage ML20247E4251989-07-19019 July 1989 Requests Listed Items for Reactor Operator & Senior Operator Licensing Exams Scheduled for Wk of 891009.All Reactor Operator & Senior Reactor Operator License Application Info Should Be Submitted at Least 30 Days Before First Exam Date ML20247B0761989-07-19019 July 1989 Ack Receipt of Util Withdrawing 880711 Request for Relief from ASME Code Section XI Requirement for Testing Class 2 Portions of Main Steam Lines of Units at 1.25 Times Design Pressure.Code Case N-479 Acceptable for Use at Plant IR 05000321/19890021989-07-17017 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/89-02 & 50-366/89-02 ML20247E3651989-07-17017 July 1989 Requests Listed Items for Requalification Program Evaluation Scheduled for Wks of 890911 & 25.NRC to Administer Operating & Written Exams & Discuss W/Qualified Personnel & Operators Schedule for Processing Exams.Ref Matl Requirements Encl ML20246Q2511989-07-14014 July 1989 Forwards Insp Repts 50-321/89-11 & 50-366/89-11 on 890619-23.Noted Violations Not Being Cited Due to Criteria for Categorization of Licensee Identified Violations Being Met ML20247P5571989-07-13013 July 1989 Documents Info Received During Discussions Between Region II Personnel & Concerned Individual.Encl Withheld (Ref 10CFR2.790(a)) ML20246F6661989-07-0606 July 1989 Affirms Validity of Staff Reaction to Final Rept,Submitted in Util Re Bent Rockbolts Observed in Torus Anchorage.Bent Rockbolts Appear to Pose No Safety Impediment to Restart.Issue Closed ML20246K7441989-07-0505 July 1989 Forwards Insp Repts 50-321/89-10 & 50-366/89-10 on 890527- 0623.Details Re Licensee non-cited Violations Described in Rept ML20246B6351989-06-30030 June 1989 Forwards NRR Ack Receipt of Petition Filed by Ecology Ctr of Southern California,For Info.Ltr States That Petition Being Treated Under 10CFR2.206 of Commission Regulation ML20245K9301989-06-23023 June 1989 Advises That Apr 1989 Rev to Physical Security Plan Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20245J9641989-06-22022 June 1989 Advises That Util 880224 Rev 2 to Inservice Insp Program for Second 10-yr Interval Acceptable Except as Noted in Encls ML20245H7291989-06-19019 June 1989 Forwards Insp Repts 50-321/89-07 & 50-366/89-07 on 890422-0526.Licensee Identified Violations Not Cited ML20245D4541989-06-15015 June 1989 Forwards Insp Repts 50-321/89-02 & 50-366/89-02 on 890227-0317 & Notice of Violation ML20245A9991989-06-14014 June 1989 Forwards Insp Repts 50-321/89-09 & 50-366/89-09 on 890522-26.No Violations or Deviations Noted ML20248C1331989-06-0606 June 1989 Forwards Director'S Decision 89-03,transmittal Ltr & Fr Notice Denying Ocre Petition Filed Under 10CFR2.206 for Commission Take Action Applicable to All Bwrs,Per 890309 Power Oscillation Event at LaSalle Unit 2 ML20244D1581989-06-0505 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/89-06 & 50-366/89-06 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D2901999-10-13013 October 1999 Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217G0401999-10-0707 October 1999 Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV ML20217G2631999-10-0707 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted ML20216G0251999-09-24024 September 1999 Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant ML20217B5271999-09-16016 September 1999 Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted ML20212A6411999-09-13013 September 1999 Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20210T6421999-08-17017 August 1999 Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2 ML20210V3311999-08-13013 August 1999 Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC ML20210Q4821999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date ML20210L7581999-08-0404 August 1999 Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20210J9021999-08-0202 August 1999 Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9501999-08-0202 August 1999 Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210E1601999-07-20020 July 1999 Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems ML20209E4801999-06-30030 June 1999 Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101 ML20196H8811999-06-25025 June 1999 Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207E7561999-06-0303 June 1999 Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable ML20206Q0751999-05-0606 May 1999 Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted ML20206G1611999-05-0404 May 1999 Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii) ML20206P6921999-04-27027 April 1999 Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl ML20205T1831999-04-0909 April 1999 Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne ML20205M3181999-04-0707 April 1999 Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999 ML20205M3011999-04-0202 April 1999 Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified ML20205D3211999-03-24024 March 1999 Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25 ML20205A2991999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Hatch PPR on 990202.PPR Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Feb 1997 - Jan 1999.Insp Plan for Future Encl ML20207M1771999-03-11011 March 1999 Forwards SE Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Welds ML20204E6601999-03-11011 March 1999 Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned ML20207D3131999-02-24024 February 1999 Forwards Insp Repts 50-321/98-09 & 50-366/98-09 on 981213- 990123.No Violations Noted.Conduct of Activities at Hatch Facility Generally Characterized by safety-conscious Operation,Sound Engineering & Maintenance ML20203G4161999-02-17017 February 1999 Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs ML20203G3481999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam ML20199H8941999-01-21021 January 1999 Discusses Responses to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Controls, for Plant,Units 1 & 2 ML20199H8761999-01-21021 January 1999 Informs That Proposed GL 88-01 Examinations of Spring 1999 Refueling Outage of Plant,Unit 1 Acceptable ML20199K1381999-01-12012 January 1999 Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl ML20199F1331998-12-29029 December 1998 Forwards Insp Repts 50-321/98-07 & 50-366/98-07 on 981101- 1212.No Violations Identified.Activities at Hatch Facility Generally Characterized by safety-conscious Operations, Sound Engineering & Maintenance Practices ML20199E7411998-12-23023 December 1998 Refers to 981105 Training Managers Conference Conducted at RB Russell Bldg with Representatives from All Utils.Agenda Used for Conference & List of Attendees Encl.Goal of Providing Open Forum of Operator Licensing Issues Was Met ML20196J4771998-12-0707 December 1998 Refers to 980311 Submittal of Four New Relief Requests & One Revised Relief Request for IST Program for Pumps & Valves Ei Hatch Npp.Se Accepting Proposed Alternatives Encl ML20196J2581998-12-0101 December 1998 Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities ML20196J2851998-12-0101 December 1998 Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Details of Insp Plan for Next 4 Months & Historial Listing of Plant Issues Called Plant Issues Matrix, Encl ML20196F1661998-11-24024 November 1998 Forwards Insp Repts 50-321/98-06 & 50-366/98-06 on 980920-1031.Insp Rept Identifes Activities That Violate NRC Requirements But Not Subject to Enforcement Actions ML20195D7961998-11-16016 November 1998 Informs That Licensee 980114 Request for Exemption from Requirements of General Design Criterion 56 for Edwin I Hatch Nuclear Plant,Unit 2 Found Acceptable & No Exemption from GDC-56 Required ML20196C8001998-11-12012 November 1998 Forwards Copy of Forms a & B,Individual Answer Sheets & Exam Results Summary of GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl ML20195B7891998-11-0909 November 1998 Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Hrps, for Plant,Unit 1 ML20155H4181998-11-0303 November 1998 Advises That Info Contained in 980918 Application & 980813 Affidavit, GE14 Lua Fuel Bundle Description Rept, Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20155B6061998-10-28028 October 1998 Forwards Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Tp ML20155A5461998-10-21021 October 1998 Forwards FEMA Final Rept on Exercise of Offsite Radiological Emergency Response Plans for Hatch Plant,Conducted on 980520.No Deficiencies or Areas Requiring Corrective Actions Identified During Exercise ML20155B2461998-10-15015 October 1998 Forwards Insp Repts 50-321/98-05 & 50-366/98-05.No Violations Noted ML20155A6261998-10-15015 October 1998 Informs That NRC Recently Obtained Info Re Industrial Safety Issues at Hatch Facility.Info Indicated That Personnel Unnecessarily Working on Energized Electrical Equipment Without Appropriate Clothing ML20154L4491998-10-14014 October 1998 Informs That NRC Reconsidered Relocation of PCP to PCP Manual Against Guidance in Regulatory Guide 1.143 & Believe That Locating of PCP in PCP Manual,Acceptable ML20155B0371998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators 1999-09-24
[Table view] |
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,k Docket No.: 50-321 366 Mr. J. T. Beckham, Jr. DEC 2 31985 Vice President, Nuclear Generation Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302
Dear Mr. Beckham:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION INSERVICE-INSPECTION PROGRAM Re: Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 We are reviewing the Inservice Inspection Program for the second ten year interval of operation of Hatch Units 1 and 2 that was submitted by your letter dated July 25, 1985. In order to complete this review, we need the additional information described in the enclosure. You are requested to provide a written response, submitting the requested information, within 30 days of receipt of this letter.
The reporting and recordkeeping requirements of this letter affect fewer than ten respondents; therefore, OMB clearance is not required under.P.L.96-511.
Sincerely, o
. OriginnI signeny George Rivenbark, Project Manager BWR Project Directorate #2 Division of BWR Licensing
Enclosure:
Request for Additional Information cc: See next page DISTRIBUTION:
(Docket-file &
NRC PDR Local PDR PD#2 R/F DMuller OELD EJordan BGrimes JPartlow GRivenbark SNorris 0FFICIAL RECORD COPY ACRS (10)
PD Plant-specife (Hatch 1 & 2)
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DB1LPD#2j DBL 2 SNOW is GRis nbark:nc 12/.70/85 12/9/85 0601020268 851223 !
PDR ADOCK 05000321 l G PDR 1
._. _ , . _ -_ - _ _ _ _ -.m.--
Mr. J. T. Beckham, Jr. ~
Edwin I. Hatch Nuclear Plant,
, . Georgia Power Company -
Units Nos. I and 2 cc:
G. F. Trowbridge, Esq.
Shaw, Pittman, Potts and Trowbridge
, 1800 M Street, N.W.
, Washington, D.C. 20036 Mr. L. T.~ Gucwa
-Engineering Department Georgia Power Company P. O. Box 4545 Atlanta, Georgia 30302 Mr. H. C. Nix, Jr. , General Manager Edwin I. Hatch Nuclear Plant Georgia Power Company P. O. Box 442 i Baxley, Georgia 31513 Mr. Louis B. Long li Southern Company Services, Inc.
P. O. Box 2625 Birmingham, Alabama 35202 4
Resident Inspector U.S. Nuclear Regulatory Commission Route 1.- P. O. Box 279 Baxley, Georgia 31513
- Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, Suite 3100 Atlanta, Georiga 30303 Mr. Charles H. Badger Office of Planning and Budget Room 610 c 270 Washington Street, S.W.
Atlanta, Georgia 30334 Mr. J. Leonard Ledbetter, Commissioner Department of Natural Resources 270 Washington Street, N.W.
Atlanta, Georgia 30334 Chairman Appling County Commissioners County Courthouse Baxley, Georgia 31513 i:
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM i
EDWIN I. HATCH NUCLEAR PLANT UNITS 1 AND 2 By letter dated June 25,1985,(1) from L. T. Gucwt (Georgia Power) to J. F.
Stolz (NRC), you submitted your latest proposed insarvice inspection (ISI) program for Edwin I. Hatch Nuclear Plant Units 1 r.nd 2 second 10 year inspection interval. We will be evaluating your relief requests accompanying your ISI program and using documents referenced in it and other documents (see attached document review list). If there are any additional relief requests i
or supporting information you wish to be considered, please provide us with copies. If they have been previously furnished to the NRC, please document
.by reference.
Fourteen of the following 15 questions address tha second 10 year interval relief requests for Edwin I. Hatch Nuclear Plant Units 1 and 2. The fifteenth question requests information regarding fulfillment of the first 10 year interval examination requirements.
- 1. You have requested relief (ISI Plan Section 2.1.1) from the requirements of performing a 100% volumetric examination of reactor pressure vessel and closure head welds, item numbers Bl.11, Bl.12, B1,.21, and 81.22 of Table IWB-2500-1. The contents of your relief request indicate that you may be attempting to examine the accessible portions of all vessel and head welds.
The 1980 Edition with Addenda through Winter 1981 requires that only one weld from each of the Code Item Numbers listed above be volumetrically i
examined during the second inspection interval.
i a
Please prov.ide the following information:
(a) Identify one weld for each code item number to be examined; also specify the percentage of the weld accessible for examination.
Give a complete description of the reason why 100% of the weld length cannot be examined (i.e. , describe physical limitations).
(b) For welds listed in (a) above that will not receive a 100% exam-ination, define additional welds of the same code item number (B1.11 and 81.12 must be beltline welds) that can be examined as an alternative to the code requirement. Choose enough welds such that the total weld length examined, to the extent of available welds, equals the length of the weld defined in (a) above.
(c) If enough welds are not available for a given Code item, identify additional similar welds (i.e., shell welds outside of bel'tline region, or closure head welds in place of bottom head welds) that can be examined to the extent that (1) either the length of examined welds equals the length of the weld requiring examination or (2) there are no more accessible portions of similar welds available.
- 2. You have requested relief (ISI Plan Section 2.1.2) from the requirement of performing an ultrasonic examination using a straight-beam transducer on the reactor pressure vessel and closure head welds'. Subparagraph
, T-441.4.3 of Article 4 of ASME Section V requires 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. Yourjustification that the size of the laminar reflectors will not change from preservice
examination and that the scans will result in additional radiation exposure requires clarification. Please supply the following information:
(a) Provide analyses or studies of the laminar indications, which justify your statement that the laminar reflectors will not change.
(b) Confirm that the laminar reflectors were scanned and recorded during preservice inspectiot: 'n accordance with the procedure consistent with that required by the 1980 Edition with Addenda through Winter 1981.
(c) Provide an estimate of the personnel radiation exposure for the straight beam scan. Also provide an estimate of the radiation ex-posure for the 45- and 60-degree scans.
- 3. You have requested relief (ISI Plan Section 2.1.3) from the requirement of performing a 100% volumetric examination of certain nozzle-to-vessel welds and nozzle inside radius sections. Please provide the following informa-tion:
(a) For each nozzle weld or inside radius section requiring relief, give the estimated percentage of the volume that will be examined.
(b) Provide sketches of the nozzles for which relief is requested, with enough dimensional detail, including ultrasonic transducer dimensions, to enable verification of the interference causing the examination difficulty.
(c) Address scan heads and alternative scan angles to enable a more complete examination.
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- 4. You have requested relief (ISI Plan Section 2.1.5) from performing a surface examination on the inside surface of the reactor vessel support skirt weld. Your relief justification, physical access restricted by high radiation and.CRD housing obstructions, requires clarification.
(a) Provide an estimate of the total radiation exposure for the exam-ination for which relief is requested.
(b) Provide sketches that show the physical obstructions preventing the surface examination of the weld. Include enough dimensional detail to enable a complete evaluation of the interference.
- 5. You have requested relief (ISI Plan Section 2.1.6) from performing the required surface examination of certain reactor pressure vessel (RPV) nozzle-to-safe end welds. In order for us to evaluate the relief request, please provide a description, sketches where applicable, of the inter-ference affecting their examination. This information is not needed for the 2-in. RPV bottom head drain nozzle-to-safe end weld since it is exempted from examination.
- 6. You have requested relief (ISI Plan Section 2.1.8) from performing visual examination of the internal pressure boundary of Class 1 pumps and valves. Your basis for relief states that "during routine maintenance, the valve body and the pump casing internal surfaces hre usually examined.
Many of the valves, particularly the containment isolation valves are dis-assembled for maintenance of leak-tightness." Please provide the fol-lowing information:
(a) Identify the Class 1 pumps and valves that do not have routine maintenance.
t_-______________-_---__-____-____--_____-_-___________-_-
(b) Of.the other pumps and valves, identify which do have routine maintenance and at what frequency.
(c) Does the routine maintenance of any of the above valves require off-loading the core and draining the RPV prior to disassembly?
Enumerate these.
(d) Provide an estimate of the number of man-rems required to perform routine maintenance or required inspections on various types of pumps and valves.
- 7. You have requested relief (ISI Plan Section 2.1.9) from performing the required volumetric or surface examination of the pressure retaining welds in 10% of the peripheral control rod drive housings. For us to evaluate the possibility of these welds meeting the Code exemption criteria of IWB-1220(a), please provide the following information for both Hatch units:
(a) The maximum leakage rate under normal plant operating conditions resulting from a CRD housing failure.
(b) The total capacity of makeup systems which are operable from on-site emergency power.
- 8. You have requested relief (ISI Plan Section 3.1.1) from the requirements of performing a 100% volumetric examination of the residual heat removal (RHR) heat exchanger Class 2 vessel shell, head, and tubesheet-to-shell circumferential welds. Please provide the following information:
(a) Define the percentage of the volumetric examination for each weld that will receive a partial volumetric examination.
~.
(b) Of,the other pumps and valves, identify which do have routine maintenance and at what frequency.
(c) Does the routine maintenance of any of the above valves require off-loading the core and draining the RPV prior to disassembly?
Enumerate these.
(d) Provide an estimate of the number of man-rems required to perform routine maintenance or required inspections on various types of pumps and valves
- 7. You have requested relief (ISI Plan Section 2.1.9) from performing the required volumetric or surface examination of the pressure-retaining welds in 10% of the peripheral control rod drive housings. For us to evaluate the possibility of these welds meeting the Code exemption criteria of IWB-1220(a), please provide the following information for both Hatch units:
(a) The maximum leakage rate ~ under normal plant operating conditions resulting from a CR0 housing failure.
(b) The total capacity of makeup systems which are operable from on-site emergency power.
i
- 8. You have requested relief (ISI Plan Section 3.1.1) from the requirements of performing a 100% volumetric examination of the residual heat removal (RHR) heat exchanger Class 2 vessel shell, head, and tubesheet-to-shell circumferential welds. Please provide the following information:
(a) Define the percentage of the-volumetric examination for each weld that will receive a partial volumetric examination.
l l
(a) The Code allows surface examinations of Class 2 pump casing welds to be performed from the inside or outside surface of the pump.
Is there a reason why the examination can not be performed from the outside surface?
(b) If the examination cannot be performed from the outside, you should provide an estimate of the total radiation exposure received in performing the required examination from the inside surface of the pump.
- 11. You have requested relief (ISI Plan Section 4.1.2) from the requirements of performing pressure testing on Class 3 buried piping. You justified 4 ,
this relief request because the service water systems were designed with-out including provisions for testing buried piping as required by Para-graph IWA-5244 of the Code. Please provide the following information:
(a) Define which service water systems require relief, including their Table IWD-2500-1 examination category.
(b) Provide a system description of each system from (a) above, with enough detail (include P& ids) to evaluate your relief request.
(c) Paragraph IWA-5244 allows testing methods for three different con-figurations of buried piping,.i.e., (a) non-redundant-isolable, (b) redundant-nonisolable, and (c) non redundant non-isolable.
State the configuration for each system for which relief is requested.
(d) Address any alternatives other than system functional testing that would enable testing of buried components.
- m. . 1
- 12. You have requested relief (ISI Plan Section 4.1.3) from the requirement of performing a hydrostatic test of portions of the plant service water system that require isolation using 10 in. or larger butterfly valves.
Please provide the following information:
(a) Provide a marked P&ID of the plant service water system showing the portions of the system for which relief is requested.
(b) Address any alternate test that would allow testing of the service water system at greater than normal operating pressure.
- 13. You have requested relief (ISI Plan Section 5.1.1) from the requirement of subparagraph IWF-3410(a)(5), that spring supports and snubbers operate only with proper hot or cold positions. Your relief justification, that there are no exact design positions on the scales of the spring and snubber supports, needs further clarification. It is recognized that component standard spring and snubber supports will not have exact hot or cold design positions marked for your particular application. However, these design positions should be available from the piping stress analysis reports. Where the hot or cold positions are not available, please pro-vide the reason why they are not.
- 14. You have requested relief (ISI Plan Section 8.1.2) to move up the start date of the second 10 year interval for Hatch 2 to January 1,1986. Your relief request states that the Hatch 2 second inspection period (80 months) ends January 5, 1986. You stated that this will nearly coincide with the start date of the second 10 year interval for Hatch 1. Please address the following concerning Hatch 1 and 2 interval dates:
- _ - ______ _ _______=__- ___,_-____- -___ _ __ __-_ _ - __ - _ ___ __ _ _ ___ _ -____ -_--__ ______________- __
(a) By. letter dated November 10, 1981,2 you requested an extension for the inservice inspection interval for Unit 1. Approval of this request was given by the NRC on November 23, 1981,3 resulting in the Unit 1 interval extending to May 5, 1986. If there has been subsequent NRC-GP correspondence concerning the Hatch-1 interval re-verting back to January 1, 1986, please provide references.
(b) Your letter dated June 25, 1985,1 transmitting Hatch Units 1 and 2 second interval ISI plans, states that the first 10 year interval for Hatch 2 will end in September 1989. This interval end date would result in a second inservice inspection period (80 months end date of May 1986, rather than January 1986, as stated in the plan relief request. Please address the difference in interval dates for Hatch Unit 2 as given in the Reference 1 letter and the plan relief request.
- 15. Under the terms of subparagraph 10 CFR 50.55a(g)(5)(iv), where an exam-ination or test is determined to be impractical by the licensee but has not been previously included in the ISI program, the basis for such determinations shall be demonstrated to the satisfaction of the NRC not later than 12 months after the expiration of the interval. Please review your first-interval submittals (ir -luding Reference 4) with this require-ment in mind and submit relief requests as necessary.
References ,
- 1. L. T. Gucwa (GPC) to J. F. Stolz (NRC); Submittal of Second ISI Interval for Hatch Units 1 and 2, June 25, 1985.
- 2. J. T. Beckham (GPC) to Director NRR (NRC); ISI Period Extension Request, Hatch Nuclear Station, Unit 1, November 10, 1981.
- 3. J. F. Stolz (NRC) to J. T. Beckham (GPC); Approval of ISI Extension Request, Hatch Nuclear Station, Unit 1, November 23, 1981.
- 4. L. T. Gucwa (GPC) to J. F. Stolz (NRC), Hatch Unit 1 Inservice Inspection Relief Requests, NED-85-508, July 18, 1985.
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i
"*Qym ____ , - , - - - - - , - - # - - -**
- g REVIEW DOCUMENT RECORD .
Unit (s) Hatch 1 and 2 (Page1) .
~~-- . ,
_. 10 Msmber and Date Author - Recipient Type ,
Subject Matter Mi s'c.
Advises of intention to develop first interval ,
11/15/76 GPC to NRC Ltr ISI program ,
11/26/76 Lear (NRC) to Mit.chell (GPC) Ltr Guidance _
1/7/77 NBC to GPC Ltr Guidance _
5tatus of first interva) 151 program and 6/7/77 Whitmer (GPC) to Stolz (NRC) Ltr request for preservice inspection i Rejects request for " reduction in preservice 7/7/77 Stolz (NRC) to Whitmer (GPC) Ltr 1 r,spection" RAI Preservice and first interval inservice questior s 12/19/77 Stolz (NRC) to Whitmer (GPC)
- First interval 151 and IST program ..
8/3/78 Whitmer (GPC) to NRR (NRC) Subm. submitted (74575 Code) for Unit 1-First interval 151 program (submitted with
, 9/21/78 GPC to NRC Subn. FSAR) for Unit 2 t Lyon (PNL) to Cheng (NRC) RAI RAI Initial questions on 8/3/78 submittal j 10/12/78 .
1/24/79 Whitmer (GPC) to'NRR (NRC) Ltr Change Sprina'79 inspection 2nd 40-month oeriod Ippolito (NRC) to Whitmer (GPC) Ltr First interval IS! Mtg (2/22/79) summary ~
3/28/79 6/06/79 Whitmer (GPC) to NRR (NRC) - Subm. First interval ISI program Amendment #1 8/28/79 Lyon (PNL) to NRC SER Draft SER ,
~
Eisenhut to Schroeder (NRC) Hemo Recommends DOR Review Units 1 and 2 together 9/14/79 _
1/31/80 Taylor (PNL) to Johnson (NRC) SER 8f f8 e va Widner (GPC) to Director NRR (NRC) Subm. Additional information and relief requests 5/1/80
- First Interval Unit 1 ISI program Amendment #2 1/2'7/81 Widner (GPC) to NRR (NRC) Subm. (replaces 6/6/79) 74575 Code 2/3'/81 PNL to Kennedy (NRC) RAI Request for additional information 11/10/81 Beckham (GPC) to NRC Ltr Request to extend first interval ISI - Unit 1
? -
J.
REVIEW DOCUMENT RECORD ..
I Unit (s) Hatch I and 2 (Page 2) ,.
L _. ,.
ID Mimber and Misc.
Author - Recipient Type Subject Matter Date , _
5 d
Request f or extension of examination period 11/18/81 Beckham (GPC) to NRC Ltr for supports .
i, ..
Ltr Relief request
! 11/18/81 Beckham (GPC) to Director (NRC) 11/23/81 Stolz (NRC) to Beckham (GPC) Ltr Grants extension of First Interval ISI - Unit 1 f First interval 151 of Class 1,2,3 Supports for
! 3/2/82 Beckham (GPC) to NRC Ltr Unit 2 Ltr Request-for relief from hydrostatic test requirenents 3/11/82 Widner (GPC) to NRC
! 3/12/82 Stolz (NRC) to Beckham (GPC) RAI First Interval ISI - RAI on Unit 1 1
4/6/82 Stolz (NRC) to Beckham (GPC) RAI First. Interval ISI - RAI on Unit 2 Stolz (NRC) to Beckham (GPC) Ltr Hydrostatic test on procedure relief .
4/7/82 Widner (GPC) to NRC Ltr Response to RAI on First Interval ISI - Units 1 and 2 i
. 6/11/82 Technical Evaluation Report of Hatch Units 1 and 2; 9/2/82 SAIC to NRC TER First Interval ISI Gucwa (GPC) to Stolz (NRC) Ltr Delay of updating ISI program to 1980 Edii. ion 1/7/83
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Blake (NRC) to GPC Report I&E inspection report
- 6/24/83 Transmittal of SER on first interval ISI for l 7/29/83 Stolz (NRC) to Beckham (GPC) Ltr Hatch Units 1 and 2 Beckham (GPC) to Stolz (NRC) Ltr Second interval ISI for Hatch Units 1 and 2 8/12/83
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Gucwa (GPC) to Stolz (NRC) Ltr Notifying mid-January update to 1980 Edition j 1/9/84
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Blake (.RC) to GPC Report I&E inspection report 10/30/84 N ,
l Blake (NRC) to GPC Report I&E inspection report l 11/15/84 Ltr Submittal of Unit I report on IGSCC 12/10/84 Gucwa (GPC) to Stolz (NRC) j _._
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REVIEW DOCUMENT RECORD .
Unit (s) Hatch 1 and 2 (Page 3) l 10 kmber and Date Author - Recipient Type
i' 4/22/85 Blake (NRC) to GPC Report ISE Inspection Report 6/25/85 Gucwa (GPC) to Stolz (NRC) Ltr. Revised 2nd Interval ISI for Hatch Units 1 and 2 7/18/85 Gucwa (GPC) to Stolz (NRC) Ltr. Hatch Unit 1 ISI relief requests 8/5/85 Rivenbark (NRC) to Beckham (GPC) Ltr. License Amendments Re: Snubber TS i
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