Letter Sequence Other |
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Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: BSEP-96-0428, Provides Comments on Resolution of Spent Fuel Storage Pool Safety Issues, HL-5262, Forwards Comments to 960917 NRC Ltr Re Resolution of Spent Fuel Pool Safety Issues, ML20116E584, ML20116F061, ML20129D921, ML20129D965, ML20129F423, ML20132G883, ML20134C905, ML20134M234, ML20134M563
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MONTHYEARML20116F0611996-07-25025 July 1996 Responds to , Spent Fuel Survey Commitments for Byron Station,Units 1 & 2, Informing NRC That Clarification of Description of Refueling Activities Including Full Core Temporary Offload Will Be Provided by Dec 1996 Project stage: Other ML20116E5841996-08-0101 August 1996 Responds to Re Spent Fuel Survey Commitments for Waterford Steam Electric Station,Unit 3 Project stage: Other ML20129D2741996-09-20020 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Intends to Conduct plant-specific Regulatory Analyses to Evaluate Potential Safety Enhancement Backfits,Per 10CFR50.109(a)(3) Project stage: Approval ML20129D3051996-09-24024 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129D3351996-09-24024 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Intends to Conduct plant-specific Regulatory Analyses to Evaluate Potential Safety Enhancement Backfits,Per 10CFR50.109(a)(3) Project stage: Approval ML20129F6741996-09-24024 September 1996 Informs That Staff Has Completed Detailed Review of Sfsp Safety Issues & Forwards Results for Review Project stage: Approval ML20129F4231996-09-25025 September 1996 Forwards 960726 Memo to Commission from J Taylor Re Resolution of Spent Fuel Storage Pool Action Plan Issues. Concludes That Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Other ML20129D9761996-09-26026 September 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues.Staff Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129D9211996-09-26026 September 1996 Forwards NRC Rept on Resolution of Spent Fuel Storage Pool Safety Issues.Concludes That Exisiting Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Other ML20129D9651996-09-26026 September 1996 Forwards Rept Re Resolution of Spent Fuel Storage Pool Safety Issues.Concludes That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Other ML20129E1121996-09-26026 September 1996 Discusses Detailed Review of Spent Fuel Storage Pool Safety Issues.Results of Review Encl Project stage: Approval ML20129E5361996-09-27027 September 1996 Forwards Results of Detailed Review of Spent Fuel Storage Pool Safety Issues.Rept Should Be Reviewed for Applicability to Facility & Actions Considered Re Design of Spent Fuel Pool Decay Heat Removal Sys.No Response Required Project stage: Approval ML20128H4541996-10-0101 October 1996 Discusses Completion of Detailed Review of Sfsp Safety Issues.Staff Concludes That Existing Structures,Sys & Components Related to Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20128Q3811996-10-0303 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues Documented in Encl Rept to Commission. Structure,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20128N1961996-10-0404 October 1996 Requests Review of Resolution of Spent Fuel Storage Pool Safety Issues:Issuance of Final Rept,Vermont Yankee Power Station.Rept to Commission Encl Project stage: Approval ML20134C9051996-10-0808 October 1996 Forwards Final Rept Re Spent Fuel Storage Pool Safety Issues Project stage: Other ML20128M7171996-10-0909 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Pool Safety Issues Documented in Encl Rept to Commission. Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129C0531996-10-17017 October 1996 Discusses Review of Rept of Sfsp Safety Issues,Concluding That Existing Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection.Staff to Conduct plant-specific Safety Enchancement Backfit Analyses Project stage: Approval ML20129D1911996-10-22022 October 1996 Discusses Completion of Detailed Review of Sfsp Safety Issues.Staff Concludes That Existing Structures,Sys & Components Related to Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety Project stage: Approval ML20129H3761996-10-30030 October 1996 Forwards Results of Staff Review of Spent Fuel Storage Issues.Structures,Sys & Components Re Storage of Irradiated Fuel Provide Adequate Protection of Public Health & Safety. W/O Rept to Commission Project stage: Approval ML20134J7151996-11-13013 November 1996 Forwards Results of Staff Review of Resolution of Spent Fuel Storage Pool Safety Issues Project stage: Approval ML20134M2341996-11-13013 November 1996 Responds to NRC Re Resolution of Spent Fuel Pool Safety Issues & Issuance of Final Staff Rept & Notification of Plans to Perform plant-specific,safety-enhancement Backfit Analyses Project stage: Other HL-5262, Forwards Comments to 960917 NRC Ltr Re Resolution of Spent Fuel Pool Safety Issues1996-11-14014 November 1996 Forwards Comments to 960917 NRC Ltr Re Resolution of Spent Fuel Pool Safety Issues Project stage: Other ML20134M5631996-11-14014 November 1996 Provides Comments on Rept on Spent Fuel Storage Pool Issues & Accompanying NRC Project stage: Other BSEP-96-0428, Provides Comments on Resolution of Spent Fuel Storage Pool Safety Issues1996-11-15015 November 1996 Provides Comments on Resolution of Spent Fuel Storage Pool Safety Issues Project stage: Other ML20132G8831996-12-20020 December 1996 Submits Comments on NRC Rept Re Resolution of Spent Fuel Storage Pool Safety Issues:Issuance of Final Staff Rept & Notification of Staff Plans to Perform Plant-Specific,Safety Enhancement Backfit Analyses,Dbnps Project stage: Other 1996-11-14
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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: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] |
Text
,~.. _ ___._. .. - - _ . . - _ _ . - , - . _ _..- ._ .-__. . _ . . . . _
, J Gcor0ia Power Company i" .40 inverness Center Parkway
. Post Office Box 1295 i
' Birrmngham. Alabama 35201 ;
Telephone (205) 877-7279 Vic siden - N clear GeorgiaPbwer l Hatch Project l a guygig;ary of l November 14, 1996 w souttiorn ccrnparty L
l i
f Docket Nos. 50-321 HL-5262 l 50-366 1 l TAC No. M88094 f
I~ .t U. S. Nuclear Regulatory Commission i ATTN: Document Control Desk i Washington, D. C. 20555 l i
Edwin I. Hatch Nuclear Plant s I j
l Resolution ofSpent Fuel Pool Safety Issues ?
[ Comments to NRC Letter Dated September 17.1996 l
i' !
L Gentlemen: ~!
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l ' On S'eptember 17,'1996, the Nuclear Regulatory Commission (NRC) Project Manager for l Plant Edwin. I. Hatch issued a letter, " Resolution of Spent Fuel Storage Pool Safety . l Issues: Issuance of Final Staff Report and Notification of Staff Plans to Perform Plant - !
Specific, Safety Enhancement Backfit Analyses - Edwin I. Hatch Nuclear Plant, Units 1 - !
l
- and 2 (TAC No. M88094)". . The letter references internal NRC correspondence, " Memo l; to the Commission, from J. Taylor, ' Resolution of Spent Fuel Storage Pool Action Plan ;
l Issues,' dated July 26,1996" as its basis. The letter states that the staff has identified i
[ certain design features that may reduce the reliability of the spent fuel pool decay heat l l . removal, increase the potential for loss of spent fuel coolant inventory, or increase the !
potential for consequential loss of essential safety functions at an operating reactor. The NRC staff stated their intent to conduct plant-specific regulatory analyses to evaluate potential safety enhancement backfits pursuant to 10CFR.50.109(a)(3) at a number of l
operating plants that possess one or more of these design features. .
The September 17 letter invites Georgia Power Company (GPC) to provide comments \
{- l l relative to the NRC staff understanding of the plant design, safety significance of concerns j identified, cost of potential modifications, protection provided by the existing design, and administrative controls currently in place. GPC offers the comments to the specific concerns identified for Plant Hatch in the enclosure to this letter. Cost estimates for
/%[ ] ;
L modifications are not provided because GPC believes that adequate protection exists with l
- the existing design and administrative controls. ;
l i- l l !
i 9611190092 961114 .
PDR ADOCK 05000321 !
p PDR l
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._--J
.. . . . - . . - _ - - - . _. .- _. =.- _ _ . - . - ~ . . . - -
a Georgi 5 power U. S. Nuclear Regulatory Commission Page 2
~ November 14, 1996
( Should you have questions or comments, please contact this office.
Sincerely,
.,. h $
J. T. Beckham, Jr.
JAW /eb i
Enclosure:
Resolution of Spent Fuel Pool Safety Issues Comments to NRC Letter Dated September 17,1996 cc: Georgia Power Company I Mr. H. L. Sumner, Nuclear Plant General Manager
{
NORMS. .
l-i U. S. Nuclear Regulatory Commission. Washington. D. C. I Mr. K. Jabbour, Licensing Project Manager - Hatch i
U. S. Nuclear Reeulatory Commission. Region 11 Mr. S. D. Ebneter, Regional Administrator Mr. B. L. Holbrook, Senior Resident Inspector - Hatch State ofGeorgia
- Mr. J. D. Tanner, Commissioner - Department of Natural Resources i
l h
HL-5262
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Enclosure Edwin I. Hatch Nuclear Plant Resolution of Spent Fuel Pool Safety Issues Comments to NRC Letter Dated September 17.1996 In a letter to Georgia Power Company (GPC) from the NRC dated September 17,1996, the NRC staff addresses concerns identified in an internal NRC memo, dated July 26, 1996, from James Taylor to the Cormnissioners. The NRC memo identifies concerns for specific sites, and categorizes them. Thus, the GPC comments reference the category numbers and title of each concern applicable to Plant Hatch as listed in the July 26 memo.
Categorv 4: Limited Instrumentation for Loss of Coolant Events The letter states that Plant Hatch has only indirect indication and alarm for low Spent Fuel Pool (SFP) level, and that the SFP low level alarm is available only from the SFP surge tank level instrumentation. Also, the letter states that there are low discharge pressure alarms on the SFP cooling system pumps. Per the letter, absence of a direct SFP low level alarm could delay operator identification of a significant loss of SFP coolant inventory. '
Ihe staffplans toperform regulatory analyses to determine ifenhancements to level monitoring capability arejustified.
GPC Comments:
Contrary to the staff findings in the letter, Plant Hatch does have level switches installed directly in the SFP on Units 1 and 2, in addition to the surge tank level switches, pump -
discharge pressure switches, and associated alarms. The switches are identified in the Unit 1 FSAR, figure 10.4-1 and Unit 2 FSAR figure 9.1-6, as G41-LS-N372. These switches provide a low level and high level alarm in the main control room for each unit, providing direct indication ofloss of coolant. In addition to direct SFP level measurement, Plant Hatch has leakage detection instrumentation and alarms for the various channels attaching to the pool, including the Unit I to Unit 2 transfer canal, SFP to reactor cavity, drywell to reactor cavity seals, refueling bellows, and for reactor cavity level. This instrumentation provides early detection of any leakage that might decrease the i pool inventory.
In addition to installed instrumentation, licensed operators are always present on the refueling floor during outages when fuel is being transferred between the SFP and the reactor pressure vessel (RPV). To facilitate fuel movement and other refueling operations, gates between the SFP and reactor vessel cavity are removed. In this configuration, procedures require continuous water level monitoring, providing additional l assurance that water level is etTectively monitored.
1 i
l HL-5262 E-1
I
~
. Enclosure
, Resolution of Spent Fuel Pool Safety Issues Comments to NRC letter dated September 17,1996 Catenorv 6: Shared Systems and Structures at Multi-Unit Sites i
The letter states that, at multi-unit sites with shared systems and structures, with one unit operating, and one unit in refueling with a full-core or near full-core ofiload in the pool, loss of pool cooling may cause systems required for operation or safe-shutdown of the operating unit to fail or degrade. T!ae staffplans to conduct detailedreviews to identify enhancements to refuelingprocedures or to cooling system reliability that arejustified, based on the reducedpotentialfor SFP conditions to impact safey systems supporting an operating unit.
GPC Comments:
At Plant Hatch, this statement would be applicable with one unit in an outage, with the core ofiloaded to the pool, and with the other unit operating. Plant Hatch uses a defense-in-depth approach to ensure adequate pool cooling is available. Loss of cooling would require multiple failures of systems and administrative controls. GPC procedures and system design are in place to preclude sustained loss of cooling.
GPC performs an outage safety assessment every outage, controlled by procedure, which includes a review of decay heat removal capability during and after fuel ofiload, and during fuel reload. As input to the review, specific evaluations of the decay heat of the fuel in the vessel and in the pool are performed, including a day-by-day review of expected heat loads and system configurations. This review determines the primary means to provide decay heat removal and the backup methods available. The review determines the minimum time to the onset of boiling, the time to boiloff to the top of active fuel, and ,
performs a time dependent decay heat model for the outage duration. With all fuel in the l SFP, the minimum time to the onset of boiling is typically > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, with the gates between the pool and the reactor vessel cavity installed. With removal of the gates, the time increases to > 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
GPC uses diverse and reliable systems to perform SFP cooling. These systems are described in detail in the Plant Hatch FSAR's (Unit 1, sections 10.3 and 10.4; Unit 2 sections 9.1.2 and 9.1.3). A brief description of these systems is provided below.
- 1. The normal fuel pool cooling (FPC) system has three trains of cooling for both units SFP's. (Two installed in Unit l's reactor building and one installed in Unit 2's reactor building) The outage unit has the capability of two trains being aligned for cooling its l SFP, with a single train aligned to the operating unit's SFP. One train is adequately l sized for the heat load from the spent fuel in the operating unit.
- 2. GPC has installed a Decay Heat Removal (DHR) system for SFP cooling. The outage unit will have the system piping installed in its SFP The DHR system is a 100%
HL-5262 E-2 l
4
' ~
. ' Enclosure :
. , Resolution of Spent Fuel Pool Safety Issues j Comments to NRC letter dated September 17,1996 l t
l ?
t capacity system, which is powered from an otTsite power source separate from the ,
normal plant offsite power. When required during outages, GPC has a dedicated ,
diesel generator available onsite to provide backup power to the DHR system. l i 3. The RHR system can be aligned for SFP cooling in the FPC Assist mode. To use this l L system, a blank " spectacle" flange must be removed between RHR and the FPC system, and the gates between the SFP and reactor vessel cavity removed. When used ,
in this configuration, FPC Assist and RHR shutdown cooling are operated in parallel, I with an RHR pump taking suction from the SFP and one loop of the Reactor .
I Recirculation system, and discharging to the SFP and to the reactor vessel. The RHR .
system has backup power from the emergency diesel generators. Normally, the spectacle flange takes 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to remove. In an emergency, the flange can likely be removed in 2 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. !
l
- 4. In an emergency, GPC has procedures in place to respond to a failure of the normal . (
j systems used for SFP cooling. Ifinstalled, the gates between the SFP and reactor l L vessel cavity can be removed, providing more time before the onset of boiling (One of L the two overhead cranes can be powered by the emergency diesel generators). The ;
safety related plant service water system can be used to supply water for cooling by i opening manual valves. Water level is controlled using a feed and bleed approach. l Additional systems can be used as well, such as fire water and demineralized water. l The use of each is described in the plant procedures. i During an outage in which a full core offload is performed, the following schedule is l typical (based on a review of the last Unit I and Unit 2 outages): ,
l Duration ,
Day 1 (14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />) Begin Vessel disassembly Place Decay Heat Removal System in service Day 3 (62 hours7.175926e-4 days <br />0.0172 hours <br />1.025132e-4 weeks <br />2.3591e-5 months <br />) Complete Vessel disassembly Perform fuel movement prerequisites L
Day 4 - (0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />) Begin Fuel Unload p Day 8 (96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />) Complete Fuel Unload Total: (172 hours0.00199 days <br />0.0478 hours <br />2.843915e-4 weeks <br />6.5446e-5 months <br />)
I The DHR system has 100% cooling capability for spent fuel already in the SFP and a full j core offload at 24 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown. The FPC Assist mode of RHR has 100%
- cooling capability for a full core ofiload at 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> after shutdown, with the maximum i
HL-5262 E-3
. Enclosure ;
. Resolution of Spent Fuel Pool Safety Issues Comments to NRC letter dated September 17,1996 ;
i
. quantity of spent fuel previously in the pool, by design. The normal schedule from reactor l I
shutdown to full core ofiload is greater than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> as demonstrated during the last two refuelmg outages.
During outages, at least two independent and separate systems are available for decay heat j removal, with diverse power supplies. In addition, procedures are in place and adequate !
time is available for the plant personnel to manually align additional sources, i.e., plant !
service water, for cooling and level control in the incredible event that all of the normal !
and backup systems fail.
In the future, plans are to perform fuel shuffles, without a full core ofiload to the SFP. l Although the total decay heat load of the spent fuel will not change, the outage safety :
assessments will consider the various scenarios of decay heat load and availability of cooling systems, as they do now.
Catemorv 10: Limited Instrumentation for Loss of Cooline Events l
The letter states that Plant Hatch lacks a direct reading of high SFP temperature or an I alarm to identify a sustained loss of SFP cooling. The letter recognizes that other alarms j may be available, such as SFP cooling system low-flow and low-pressure, which would i indicate inadequate pool cooling. The staffplans to determine ifadditiomd ;
- instrumentation or operator controls are warranted. . l GPC Comments:
The FPC system consists of pumps, piping, and heat exchangers to provide continuous ,
pool cooling. There is temperature indication and alarm in the main control room for each '
pump suction and for each heat exchanger outlet. Both of these provide an indication of l loss of the heat removal capability. The FPC pumps trip on low suction pressure, which would indicate draining of the pool and pump down of the skimmer surge tank. There are pressure switches which alarm in the main control room for low pump discharge pressure
. and high pump discharge pressure. The low pressure alarm would be indicative of a i potential pump trip and a high pressure alarm would be indicative of a flow restriction downstream of the pump. In either case, the alarms would provide immediate indication
- to the operator of a potential loss of cooling.
4 In the event the normal FPC system is not available, Plant Hatch procedures require that .
temperature instrumentation be installed in the SFP and that it be monitored at least once. l
< per hour. Procedural controls are in place to ensure restoration of the FPC system and for
. providing alternate means of cooling.
I HL-5262 E-4 g
i l l
l , Enclosure l _
Resolution of Spent Fuel Pool Safety Issues l Comments to NRC letter dated September 17,1996 l In the FPC assist mode of RHR, flow indication to the SFP exists in the main control l room. Also, the RHR system has numerous alarms and indications in the main control l l room to indicate loss of the cooling function.
l Area Radiation Monitors are installed on the refueling floor which alarm in the main control room. In addition to direct instrumentation and alarm, these monitors provide a seccadary indication ofloss ofinventory or loss of cooling. High radiation due to loss of level from evaporation or boiling would cause the alarm, alerting the operators to a potential problem on the refueling floor, and hence, the SFP. In this event, the monitors ;
i also provide an isolation signal to the secondary containment, tripping the normal ;
ventilation systems, and starting the standby gas treatment (SBGT) system. The SBGT I system, which is designed for 100% relative humidity, will assist in removing any heat and humidity created by loss of coohng. j l
Cateeory 9: Infrequently Used Backun SFP Cooline Systems The letter states that Plant Hatch appears to rely on infrequently used backup SFP cooling systems to address long term loss of power events and mechanical failures. The staffwill 1 examine administrative controlsfor the availability and use of these systems during i refueling, and will review technical analyses demonstrating the capability of these l i
backup systems to determine the needforfurther regulatory analysis. i GPC Comments:
Systems and administrative controls available during refueling outages are discussed in the GPC comments to Category 6.
During normal operation when the decay beat load is low, sufficient time is available for operator action to restore pool cooling and level control per procedures and controls l which are currently in place. The normal means for water makeup is provided by the
- condensate transfer system. Backup sources include fire water (with its own diesel generator) and demineralized water hose stations. The safety related plant service water system can be aligned to provide cooling and level control. Each of these methods is procedurally controlled. As defense-in-depth, the decay heat removal system can be used for cooling, and is procedurally controlled. The FSAR (Unit I section 10.4.3.1, Unit 2 section 9.1.3.4) calculates time to boiling for the worst case of normal operation, bounded by one unit in operation and one unit in refueling assuming the equivalent heat load of l 1/3 core ofiload from each unit 21 days apart. In this case, the onset of boiling occurs in l Unit 1 in 14.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and in Unit 2 in 22.8 houri (For the analysis, Unit 2 was considered to be shutdown first, thus the time to boiling is ionger).
HL-5262 E-5 l
1
..a f
- Enclosure i
- . . Resolution of Spent Fuel Pool Safety Issues Comments to NRC letter dated September 17,1996 During refueling outages and during normal operation, loss of power alarms are available l to the operator for loss of power to the FPC pumps, and for the FPC alarms themselves.
l I
During outages, the FPC Assist mode of RHR or the DHR system will be available, and l
during normal operation, the PSW system or the DHR system is available to provide l
backup cooling and level control. ;
l Summarv I i
GPC believes that the existing SFP cooling systems are adequate as designed. This belief is based on the following facts: ;
i
- 1. Personnel are continuously present on the refueling floor during refueling operations. )
Any decrease in water level or substantial increase in pool temperature would not go j unnoticed.
I
- 2. Plant Hatch, in addition to the normal SFP cooling systems (FPC system and FPC j assist mode of RHR), has an independent decay heat removal system which is utilized l
during outages, which can also be used as an alternate source of SFP cooling during ;
normal operation.
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- 3. Plant Hatch has instrumentation available to detect loss ofinventory in the SFP. In j addition to the instmmentation in the skimmer surge tanks, as identified in the NRC .j letter, these level switches are installed directly in the pool.
- 4. In addition to personnel observation, temperature indication (FPC suction temperature and heat exchanger outlet temperature) is available in the main control room. If the FPC system is not available, temperature instrumentation is installed in the SFP and the temperature is recorded on an hourly basis. Procedural controls are in place to ensure restoration of the FPC system and for providing alternate means of cooling.
- 5. Emergency procedures are in place to assure makeup capability exists in the unlikely event that all SFP cooling is lost. Additionally, an assessment is made each outage to determine the decay heat removal capability needed for that outage.
- HL-5262 E-6 -
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