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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC |
| | page count = 9 | | | page count = 9 |
| | | project = TAC:42603, TAC:42604, TAC:51984, TAC:51985, TAC:53476, TAC:53477, TAC:59543, TAC:59544 |
| | | stage = Other |
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| ) Gentlemen: | | ) Gentlemen: |
| The purpose of this letter is to provide additional 10 CFR 50.92 justification for the two amendments to the Technical Specifications proposed in our submittals of May 31, 1983 and June 15, 1983. | | The purpose of this letter is to provide additional 10 CFR 50.92 justification for the two amendments to the Technical Specifications proposed in our submittals of May 31, 1983 and June 15, 1983. |
| In the May 31, 1983 letter, we proposed a change to Dose Equivalent Iodine (CEI) for Unit 1. Unit 1 was licensed with a DEI limit of 10 microcuries per gram of coolant on a site specific basis. The submittal requested to change this basis to a worst-case non-site specific limit of 0.2 microcuries per gram. % is change is clearly in the conservative direction. The change also provided for minor administrative changes in the terminology in the specification and frequency of analyses. | | In the {{letter dated|date=May 31, 1983|text=May 31, 1983 letter}}, we proposed a change to Dose Equivalent Iodine (CEI) for Unit 1. Unit 1 was licensed with a DEI limit of 10 microcuries per gram of coolant on a site specific basis. The submittal requested to change this basis to a worst-case non-site specific limit of 0.2 microcuries per gram. % is change is clearly in the conservative direction. The change also provided for minor administrative changes in the terminology in the specification and frequency of analyses. |
| In the June 15, 1983 letter, we proposed a charge to purge valve operability specifications for both units. Unit 2 was licensed with a restriction inposed on the amount of time that the 18" purge and vent isolation valves | | In the {{letter dated|date=June 15, 1983|text=June 15, 1983 letter}}, we proposed a charge to purge valve operability specifications for both units. Unit 2 was licensed with a restriction inposed on the amount of time that the 18" purge and vent isolation valves |
| .could be open. In subsequent discussions with the NRC Staff it was determined that if: 1) a site specific dose analysis was submitted; 2) measures were taken to protect downstream structures; and 3) valve operability was demonstrated; then the restrictions on valve operability could be lifted. The dose analysis and the valve operability data, with the exception of ~ the seismic test results sumary, were submitted in our letter of May 31, 1983. %e sumary of the seismic test data was included as an attachment to our June 15, 1983 letter. A sumary of a proposed design modification to protect downstream structures was also attached to our letter of June 15, 1983. The proposed change cannot and will not be implemented until after the design modification has been made. A committment similar to the current Unit 2 Technical Specification for valve operability was made for Unit 1 in our letter of October 1, 1982. The i intent of the proposed change is to supplant the comittment in the October 1, 1982 letter with a Technical Specification on Unit 1 and remove the restrictions on Unit 2 upon implementation of the design modification on both units. ( | | .could be open. In subsequent discussions with the NRC Staff it was determined that if: 1) a site specific dose analysis was submitted; 2) measures were taken to protect downstream structures; and 3) valve operability was demonstrated; then the restrictions on valve operability could be lifted. The dose analysis and the valve operability data, with the exception of ~ the seismic test results sumary, were submitted in our letter of May 31, 1983. %e sumary of the seismic test data was included as an attachment to our {{letter dated|date=June 15, 1983|text=June 15, 1983 letter}}. A sumary of a proposed design modification to protect downstream structures was also attached to our letter of June 15, 1983. The proposed change cannot and will not be implemented until after the design modification has been made. A committment similar to the current Unit 2 Technical Specification for valve operability was made for Unit 1 in our letter of October 1, 1982. The i intent of the proposed change is to supplant the comittment in the {{letter dated|date=October 1, 1982|text=October 1, 1982 letter}} with a Technical Specification on Unit 1 and remove the restrictions on Unit 2 upon implementation of the design modification on both units. ( |
| 8309160053 830901 l' l PDR ADOCK 05000321 P pm | | 8309160053 830901 l' l PDR ADOCK 05000321 P pm |
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MONTHYEARML20062E5901978-11-29029 November 1978 Discusses Possible Dangers of LOCA in Containment Purging During Normal Plant Oper.Requests Either Commitment to Limit Purging or Justification for Continuing.W/Encl ANO: 7812080207 Project stage: Other ML20055A4361980-02-28028 February 1980 Electrical,Instrumentation & Control Sys Support, Interim Rept Project stage: Other ML20070E4031982-12-13013 December 1982 Advises That Specific Containment & Purge Valves Identified in NRC Are Not Applicable to Facilities.Meeting Requested to Determine Status of Remaining Issue Re Purging & Venting Project stage: Meeting ML20071P1221983-05-31031 May 1983 Proposed Changes to Dose Equivalent Iodine Tech Specs & Preliminary Proposed Tech Specs for Drywell & Suppression Chamber Purge Sys Project stage: Request ML20071P0991983-05-31031 May 1983 Application for Amend to Licenses DPR-57 & NPF-5,revising Dose Equivalent Iodine Tech Specs to Reflect Current Requirements.Info Resolving Outstanding Purge & Vent Valve Operability Issues Encl Project stage: Request ML20024A6451983-06-15015 June 1983 Application for Amend to Licenses DPR-57 & NPF-5 Changing Tech Specs 3/4.6-2,B 3/4 6-6 & Adding 3/4.6-46 for Unit 2 & 3.7-10a,3.7-34,3.7-34a & Adding 3.7-10b & 3.7-34b for Unit 1 Re Purge & Vent Valve Operability Project stage: Request ML20077Q2661983-09-0101 September 1983 Provides Addl 10CFR50.92 Justification for 830531 & 0615 Applications for Amends to Tech Specs Re Change in Dose Equivalent Iodine & Change in Purge Valve Operability Specs Project stage: Other ML20082H5041983-11-22022 November 1983 Proposed Tech Spec Changes Re Dose Equivalent Iodine in Reactor Coolant Sys Project stage: Other ML20082H4861983-11-22022 November 1983 Application for Amend to Licenses DPR-57 & NPF-5,changing Tech Specs Re Dose Equivalent Iodine in Reactor Coolant Sys. Original Amend Submitted on 830531.Class III License Amend Fee Encl Project stage: Request ML20134G8521985-08-20020 August 1985 Proposed Tech Specs,Adding Surveillance Requirements for fast-acting Dampers in Standby Gas Treatment Sys Installed During Recent Refueling Outage Project stage: Other ML20134G8381985-08-20020 August 1985 Application for Amends to Licenses DPR-57 & NPF-5,adding Surveillance Requirements for fast-acting Dampers in Standby Gas Treatment Sys Installed During Recent Refueling Outage Project stage: Request 1983-11-22
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Category:CORRESPONDENCE-LETTERS
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[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216H3641999-09-20020 September 1999 Forwards NRC Form 536 in Response to AL 99-03, Preparation & Scheduling of Operator Licensing Exams HL-5839, Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-5731999-09-16016 September 1999 Forwards Three New & One Revised Relief Requests for Third 10-year Interval ISI Program for Plant,Developed to Clarify Documentation Requirements,To Propose Alternate Exam Requirements IAW ASME Code Cases N-598 & N-573 HL-5837, Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification1999-09-13013 September 1999 Informs That Recent Evaluation of Inservice Testing Program Activities Has Resulted in Requirement for Snoc to Revise Two Existing Requests for Relief,Withdraw One Request for Relief & Revise One Existing Cold SD Justification HL-5832, Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC1999-09-0101 September 1999 Submits Comments Concerning Reactor Vessel Integrity Database (Rvid),Version 2 for Plant Hatch,Per NRC HL-5825, Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations1999-08-20020 August 1999 Forwards Response to Informal NRC RAI Re Proposed Emergency Actions Levels Associated with Independent Spent Fuel Storage Operations HL-5827, Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d)1999-08-19019 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting period,Jan-June 1999,as Required by 10CFR26.71(d) HL-5788, Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 141999-08-19019 August 1999 Forwards Owner Activity Repts,Form OAR-1 for Ei Hatch Nuclear Plant for First Period of Third 10-yr Interval ISI Program.Repts Are for Unit 2 Refueling Outages 13 & 14 HL-5824, Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.111999-08-18018 August 1999 Requests Exemption from Expedited Implementation Requirements of Paragraph 10CFR50.55a(g)(6)(ii)(B) as Applicable to Containment General Visual Exams of Subsection Iwe,Table IWE-2500-1,Category E-A,Item E1.11 HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999 Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528 05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999 Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999 Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. 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Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-14014 July 1999 Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210J1091999-07-10010 July 1999 Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively1999-07-0909 July 1999 Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999 Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999 Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210 HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999 Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999 Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999 Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999 Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999 Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21 HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999 Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant ML20205H1491999-03-25025 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility ML20205H1411999-03-24024 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirement for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Oglethorpe Power Corp Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 30% of Facility HL-5754, Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO1999-03-22022 March 1999 Forwards Ei Hatch Nuclear Plant Unit 2 Extended Power Uprate Startup Test Rept for Cycle 15, IAW Regulatory Commitments.Testing Identified No Major Problems.Startup Testing for Unit 1 Is Scheduled for Spring 1999 RFO ML20205H1381999-03-22022 March 1999 Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Georgia Power Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 50.1% of Facility ML20205H1581999-03-16016 March 1999 Forwards Info for OLs DPR-5 & NPF-7 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Dalton Utilities Is One of Licensed Owners of Ei Hatch,Units 1 & 2,owning 2.2% of Facility HL-5753, Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative1999-03-16016 March 1999 Submits Response to Five Criteria Described in NUREG/CR-6396 Section 3.3.2.Attachment Contains Relief Request RR-P-14, Which Has Been Revised & Enhanced to Include Addl Info to Justify Proposed Alternative HL-5757, Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 9901271999-03-15015 March 1999 Informs That SNC Withdraws SNC Proposed Rev to Plant Hatch QA Program Submitted 990127 HL-5756, Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 21999-03-12012 March 1999 Submits Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5751, Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities1999-03-0505 March 1999 Forwards Change to Hatch EP for Review & Approval,Per Requirements of 10CFR50,App E,Section Iv.B.Bases for Proposed EALs & Statements of Agreement from State & Local Governmental Authorities HL-5735, Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC1999-03-0202 March 1999 Provides NRC with Update Status of Progress Util Is Making Toward Development of Product That Was Originally Identified in to NRC HL-5737, Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C1999-02-0505 February 1999 Forwards Part of Table (Table 1) Util Provided in 980728 Response to RAI for GL 92-01,Rev 1,Suppl 1,reflecting Lower Shell Axial Welds Identified as C-4-A Through C-4-C & Lower Intermediate Axial Welds Identified as C-3-A Through C-3-C HL-5733, Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions1999-01-29029 January 1999 Forwards Rev 17A to Ei Hatch FSAR & Rev 14A to Fire Hazards Analysis & Fire Protection Program, for Plant.Encl Reflects Changes Made Since Previous Submittal.With Instructions HL-5729, Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program1999-01-27027 January 1999 Submits Proposed Rev to Plant QA Program as Described in Chapter 17 of Unit 2 Fsar,Per 10CFR50.54(a)(3).Rev Would Relocate to Controlled Document Other than Fsar,Units 1 & 2 Lists of SR SSC Comprising Items Covered Under QA Program HL-5728, Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures1999-01-19019 January 1999 Requests That RPV Shell Weld Ultrasonic Exams Be Performed Using Techniques & Procedures,Iaw ASME Section Xi,App Viii, 1992 Edition,1993 Addendum,In Lieu of ASME Section XI,1989 Edition Exam Techniques & Procedures HL-5712, Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review1999-01-0707 January 1999 Forwards Ehnp Intake Structure License Rept, to Provide Example of Technical Content & Level of Detail Planned for Application for License Renewal,For NRC Review HL-5725, Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied1999-01-0707 January 1999 Informs That SNC Intends to Examine Approx Dozen Weld Overlays During Unit 1 Spring 1999 Outage That to Date Have Not Been Examined Three Times Since Weld Overlay Was Supplied 05000366/LER-1998-004, Forwards LER 98-004-01 Re Personnel Error Which Resulted in Condition Prohibited by Ts.Rev Is Necessary Because Original LER Reported Inadvertent Criticality Could Have Occurred1999-01-0404 January 1999 Forwards LER 98-004-01 Re Personnel Error Which Resulted in Condition Prohibited by Ts.Rev Is Necessary Because Original LER Reported Inadvertent Criticality Could Have Occurred HL-5710, Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds1998-12-0202 December 1998 Requests Approval of Alternative Reactor Vessel Weld Exam for Ehnp,Unit 1,per 10CFR50.55a(g)(6)(ii)(A)(5) for Permanently Excluding Exam of RPV Circumferential Shell Welds HL-5708, Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers1998-11-20020 November 1998 Provides Updated Response to RAI for GL 96-06, Waterhammer in Containment Coolers HL-5573, Withdraws Requesting Exemption from Requirements of GDC 56 with Respect to Ei Hatch,Unit 2 Reactor bldg-to- Suppression Chamber Vacuum Relief Sys Design Due to Listed Reasons1998-10-19019 October 1998 Withdraws Requesting Exemption from Requirements of GDC 56 with Respect to Ei Hatch,Unit 2 Reactor bldg-to- Suppression Chamber Vacuum Relief Sys Design Due to Listed Reasons HL-5687, Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment1998-10-19019 October 1998 Forwards Required 120-day Response to GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment HL-5686, Informs That Corrective Actions Relative to Thermo-Lag 330-1 Issues Are Complete1998-10-16016 October 1998 Informs That Corrective Actions Relative to Thermo-Lag 330-1 Issues Are Complete HL-5697, Requests Delay of Insp of RPV Circumferential Shell Welds for Two Operating Cycles as Outlined in NRC Info Notice 97-63,Suppl 1 & That Proposed Alternative Be Authorized Per 10CFR50.55a(a)(3)(i),per1998-10-16016 October 1998 Requests Delay of Insp of RPV Circumferential Shell Welds for Two Operating Cycles as Outlined in NRC Info Notice 97-63,Suppl 1 & That Proposed Alternative Be Authorized Per 10CFR50.55a(a)(3)(i),per HL-5689, Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients1998-09-30030 September 1998 Forwards Request for NRC Finding of Exigent Circumstance Re License Amend for Extended Power Update Operation.Changes Would Be Made While Plant Is Operating,Which as Stated,Has Potential to Create Unnecessary Plant Transients HL-5673, Informs NRC That Util Intends to Load Four Lead Use Assemblies Into Unit 2 Core as Part of Reload 14/Cycle 15 During Fall 1998 Refueling Outage.Proprietary Info Encl. Proprietary Info Withheld,Per 10CFR2.7901998-09-18018 September 1998 Informs NRC That Util Intends to Load Four Lead Use Assemblies Into Unit 2 Core as Part of Reload 14/Cycle 15 During Fall 1998 Refueling Outage.Proprietary Info Encl. Proprietary Info Withheld,Per 10CFR2.790 HL-5680, Informs NRC of Util Plans & Schedule for Exam of Unit 1 RPV Shell Welds.Util Anticipates Having Final Relief Request Submitted to NRC for Review by 9907011998-09-18018 September 1998 Informs NRC of Util Plans & Schedule for Exam of Unit 1 RPV Shell Welds.Util Anticipates Having Final Relief Request Submitted to NRC for Review by 990701 1999-09-20
[Table view] Category:UTILITY TO NRC
MONTHYEARHL-1278, Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined1990-09-12012 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-321/90-15 & 50-366/90-15.Corrective Actions: Mispositioned Valves 1E21-F025B & 1E21-F027B Placed in Correct Positions & Technicians Disciplined HL-1176, Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date1990-09-12012 September 1990 Forwards Updated Listing of Outstanding Licensing Requests for Plant,Tabulated Chronologically by Util Submittal Date HL-1237, Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.11990-09-0404 September 1990 Requests Permission to Use Facility Reactor Bldg Crane to Move Large Shipping Casks,Per Tech Spec 3.10.F.1 & 4.10.F.1 HL-1250, Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage1990-08-27027 August 1990 Forwards Post-Refueling Outage Startup Test Rept,Unit 1 Cycle 13, Per Tech Spec 6.9.1.1.Rept Presents Static & Dynamic Functional Core Tests Performed During Startup from Spring 1990 Maint/Refueling Outage ML20059C6551990-08-27027 August 1990 Informs of Intention to Transfer Right of Way for Road 451 to Appling County So Road Can Be Straightened & Paved. Transfer Will Have No Significant Impact on Use of Road & Site Emergency Plan ML20028G8441990-08-27027 August 1990 Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant Unit 1 Feb-June 1990. HL-1245, Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d1990-08-23023 August 1990 Forwards Fitness for Duty Performance Data for First Six Month Reporting Period,Per 10CFR26.71d ML20056B3011990-08-20020 August 1990 Forwards Revised Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval, for Review & Approval.Program Will Be Implemented While Awaiting SER HL-1215, Informs of Implementation of Amend 169 to Facility Tech Specs1990-07-26026 July 1990 Informs of Implementation of Amend 169 to Facility Tech Specs HL-1035, Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists1990-07-25025 July 1990 Forwards Nuclear Decommissioning Funding Plan for Plant,Per 10CFR50.75(b) & 33(k).Reasonable Assurance That NRC Prescribed Min Funding Will Be Available to Decommission Each Unit on Current Expiration Date Exists HL-1158, Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses1990-06-29029 June 1990 Forwards Rev 0 to SIR-90-039, Flaw Evaluation & Weld Overlay Designs for Ei Hatch Unit 1 Spring 1990 Refueling Outage. Rept Details IGSCC Exam Results,Weld Overlay Design & Evaluation of Weld Shrinkage Stresses ML20043E6691990-06-0707 June 1990 Forwards Rev 0 to Core Operating Limits Rept for Operating Cycle 13, Per Amend 168 to License DPR-57 ML20043C8621990-05-31031 May 1990 Submits Certification That Operator Licensing Simulation Facility Located at Plant Meets NRC Requirements ML20043A8081990-05-0707 May 1990 Forwards Response to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-321/90-07 & 50-366/90-07.Encl Withheld (Ref 10CFR73.21) ML20042F3331990-05-0101 May 1990 Provides Response to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Procedures Address Possibility of Vessel Overfill Events & Training Alert Operators to Potential Overfills ML20012C6351990-03-14014 March 1990 Responds to Generic Ltr 89-19 Re Safety Implementation of Control Sys in LWR Nuclear Power Plants,Per 890920 Request & Understands That NRC Has Agreed to Extend Response Deadline Until 900504 ML20012B7291990-03-0707 March 1990 Forwards Owners Data Rept for Inservice Insp Ei Hatch Nuclear Plant,Unit 2 Sept-Dec 1989 & Metallurgical Evaluation of Four Inch Pipe to Elbow Weld from Plant Hatch, Unit 2. ML20012B1161990-03-0707 March 1990 Forwards Results of Circuit Breaker Testing,Per Bulletin 88-010,per Telcon W/Lp Crocker ML20012A1261990-03-0101 March 1990 Forwards Completed Questionnaire in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20012A9051990-02-27027 February 1990 Forwards Summary Rept of Present Level & Source of Onsite Property Damage Insurance Coverage for Plant ML20012B4101990-02-22022 February 1990 Discusses NRC 900221 Granting of Discretionary Enforcement to Continue Shutdown Cooling Operation Until Reactor Level Instrument 1B21-N080A Can Be Returned to Svc.Replacement Expected to Be Completed by 900222 ML20006F4561990-02-20020 February 1990 Responds to Request for Addl Info Re Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matl & Impact on Plant Operations. RTNDT Value for Unit 2 Closure Flange Region Addressed ML20006D7481990-02-0606 February 1990 Forwards Final Technical Rept, Edwin I Hatch Nuclear Plant Unit 2 Reactor Containment Bldg 1989 Integrated Leakage Rate Test for Fall 1989 Maint/Refueling Outage,Per IE Notice 85-071 ML20006C9481990-01-31031 January 1990 Responds to NRC 900102 Ltr Re Violations Noted in Insp Repts 50-321/89-28 & 50-366/89-28.Corrective Actions:Deficiency Card Documenting Event Initiated as Required by Plant Procedures ML20006A8911990-01-23023 January 1990 Responds to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Plans to Augment Existing Programs or Implement New Programs to Meet Intent of Generic Ltr ML20005F9341990-01-10010 January 1990 Offers No Comments Re SALP Repts 50-321/89-22 & 50-366/89-22 Dtd 891205 ML20005E6491990-01-0202 January 1990 Responds to NRC 891208 Ltr Re Violations Noted in Insp Repts 50-321/89-30 & 50-366/89-30.Corrective Actions:Util Personnel Documented Engineering Judgment Used as Basis for Use of Agastat Relays in Question ML20005E5621989-12-28028 December 1989 Certifies That fitness-for-duty Program Meets 10CFR26 Requirements.Util Screens for Two Addl Substances Not Required by Rule,Benzodiazepine & Barbiturates.List Re Panel & Cutoff Levels Encl ML20005E1411989-12-28028 December 1989 Responds to Generic Ltr 89-10, Motor-Operated Valve Testing & Surveillance. Thermal Overloads on Most safety-related motor-operated Valves Are Jumpered During Operation.Epri Developing Program to Calculate Valve Thrust Requirements ML20005D9611989-12-22022 December 1989 Forwards Rev to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20011D8721989-12-21021 December 1989 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor-Darling S350W.... Review of Sys Drawings Determined That No Subj Valves Installed at Facilities ML19332G0371989-12-13013 December 1989 Summarizes Util Plans to Recaulk & Seal Plant Refueling Floor Precast Concrete Panel Walls,Per 891129 Telcon. Special Purpose Procedure Developed to Ensure That Containment Integrity Maintained During Recaulking ML19332G0201989-12-12012 December 1989 Forwards Addl Info Re Use of Code Case N-161 for Upgrading Ultrasonic Insp & Testing Instrument Calibr Blocks ML19332F3571989-12-0707 December 1989 Provides Feedback on NRC Pilot Project Involving Electronic Distribution of NRC Generic Communications.Sys Found to Be Most Useful Re Generic Ltrs & Bulletins Where Timely Receipt Critical ML19332E1521989-11-29029 November 1989 Responds to NRC 891101 Ltr Re Violations Noted in Insp Repts 50-321/89-19 & 50-366/89-19.Corrective Actions:Procedure 31GO-INS-001-OS Revised to Include Requirements to Record & Compare Valve Stroke Times Following Valve Maint ML19332D0921989-11-22022 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Closure Plan for USI A-10 Will Be Submitted in 1990.Response to USI A-47 Re Safety Implications of Control Sys Will Be Submitted in Mar 1990 ML19332E4451989-11-21021 November 1989 Certifies That Initial & Requalification License Operator Training Programs at Plant Accredited & Based on Sys Approach to Training,Per Generic Ltr 87-07 ML19327C2451989-11-13013 November 1989 Forwards Amend 13 to Indemnity Agreement B-69 ML19332B9461989-11-10010 November 1989 Forwards Updated Chronological Tabulated List of Outstanding Licensing Requests for Plant.List Identifies Priority Items for Early NRC Approval ML19327C0321989-11-0606 November 1989 Advises That No Corrections Necessary Re 890331 Response to NRC Bulletin 88-010,Suppl 1.Documentation Available at Plant Site for Review ML19325E8821989-11-0101 November 1989 Responds to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs. Contingency Plan Developed Which Has Been Added to Security Plan to Include short-term Actions Against Attempted Sabotage ML19324B8741989-10-27027 October 1989 Transmits Proposed Program for Completing Individual Plant Exam Process,Per Generic Ltr 88-20 & NUREG-1335.Program Should Identify Method & Approach Selected for Performing Exam ML19325E5491989-10-27027 October 1989 Submits Update on Lighting Observed During NRC Insp on 891002-06.All Temporary Lighting Reinstalled.Mfg of Four Cluster Lights,Holophane,Has Been Onsite & Will Give Recommendations for Permanent Lighting ML19327B6151989-10-24024 October 1989 Responds to Generic Ltr 89-16, Hardened Vent, by Encouraging Licensees to Voluntarily Install Hardened Vent Under 10CFR50.59 ML19327B3001989-10-23023 October 1989 Documents NRC Agreement W/Util Justification for Use of Pathway Corp as Replacement Bellows Vendor,Based on 891004 Telcon.Util Proceeding W/Procurement of Replacement Bellows ML19327B1551989-10-17017 October 1989 Forwards Revs 0 to Corporate Emergency Implementing Procedures,Including HNEL-EIP-01,HNEL-EIP-02,HNEL-EIP-03, HNEL-EIP-04,HNEL-EIP-05,HNEL-EIP-06,HNEL-EIP-07,HNEL-EIP-08, HNEL-EIP-10 & HNEL-EIP-11 ML19325C7451989-10-11011 October 1989 Advises That Effective 890913 Th Hunt No Longer Employed by Util.Operator License Terminated ML20248H3061989-10-0404 October 1989 Forwards Revised Tech Specs to Util 890622 Application for Amends to Licenses DPR-57 & NPF-5,per NRC Request,Re cycle- Specific Parameter Limits ML20247G4631989-09-14014 September 1989 Responds to NRC Re Violations Noted in Insp Repts 50-321/89-08 & 50-366/89-08.Corrective Actions:Procedure Revised to Include Periodic Analysis of Fuel Oil Parameters & Change Sampling Methodology ML20246D4541989-08-22022 August 1989 Forwards Corrected Tech Spec Changes Re Reactor Protection Sys Instrumentation Surveillance Requirements,Per NRC Request 1990-09-04
[Table view] |
Text
- . . _ _ . - _ - _ _ . . . .- - - - ~ -_ .
. Geor@a Poer Company 333 hedmmt Awnue f ArWa Georqu 303G8 -
Tekphorm 404 526 6 % 6 Whng Address Post Ofie Box 454S Aranta Georg a 30302 b Georgia Power l #'"
- Power Generation Department NED-83-416 September 1, 1983 I Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 i Division of Licensing U. S. Nuclear Regulatory Ccanission Washirgton, D. C, 20555 NBC DOCKEIS 50-321, 50-366 i OPERATING LICENSES DPR-57, NPF-5 EININ I. HA'ICH NUCLEAR PLANT UNITS 1, 2
, CLARIFICATION OF PURGE AND VENT SUBMITTAIS i
) Gentlemen:
The purpose of this letter is to provide additional 10 CFR 50.92 justification for the two amendments to the Technical Specifications proposed in our submittals of May 31, 1983 and June 15, 1983.
In the May 31, 1983 letter, we proposed a change to Dose Equivalent Iodine (CEI) for Unit 1. Unit 1 was licensed with a DEI limit of 10 microcuries per gram of coolant on a site specific basis. The submittal requested to change this basis to a worst-case non-site specific limit of 0.2 microcuries per gram. % is change is clearly in the conservative direction. The change also provided for minor administrative changes in the terminology in the specification and frequency of analyses.
In the June 15, 1983 letter, we proposed a charge to purge valve operability specifications for both units. Unit 2 was licensed with a restriction inposed on the amount of time that the 18" purge and vent isolation valves
.could be open. In subsequent discussions with the NRC Staff it was determined that if: 1) a site specific dose analysis was submitted; 2) measures were taken to protect downstream structures; and 3) valve operability was demonstrated; then the restrictions on valve operability could be lifted. The dose analysis and the valve operability data, with the exception of ~ the seismic test results sumary, were submitted in our letter of May 31, 1983. %e sumary of the seismic test data was included as an attachment to our June 15, 1983 letter. A sumary of a proposed design modification to protect downstream structures was also attached to our letter of June 15, 1983. The proposed change cannot and will not be implemented until after the design modification has been made. A committment similar to the current Unit 2 Technical Specification for valve operability was made for Unit 1 in our letter of October 1, 1982. The i intent of the proposed change is to supplant the comittment in the October 1, 1982 letter with a Technical Specification on Unit 1 and remove the restrictions on Unit 2 upon implementation of the design modification on both units. (
8309160053 830901 l' l PDR ADOCK 05000321 P pm
_ _ _ _ , . _ _ _ _ . . _ , _ - . _ _ _- _ . ~ _ - - _ _ _ , - _ _ _ , _ . . . _
Georgia Power A Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comnissica Washington, D. C. 20555
. Septenber 1,1983 Page 'No In the attachments to this letter we are providing the requested 10 CFR 50.92 analysis for each proposed change to the Technical Specifications.
If you have further questions, please contact this office, Very Truly Yours, ee .r & n L. T. Gucwa Manager-Nuclear Engineering and Chief Nuclear Engineer MIB Attachnents
, xc: J. P. O'Reilley H. C. Nix, Jr.
Senior Resident Inspector i
700775
ATTACFNENT l NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EININ I. HA'ICH NUCLEAR PLAr7T UNIT 1 CLARIFICATION OF PURGE AND VENT SUBMITTALS DOSE EQUIVALENT IODINE (DEI)
Letter of May 31, 1983
- 1. Change from "10 microcuries per gram" to "0.2 microcuries per gram":
BASIS:
This change constitutes a more restrictive operational limitation to Unit 1. The resultant doses from a potential accident are less since the allowable initiating point for the transient is lower.
The change constitutes a major decrease in the effects of accidents previously analyzed, does not create any new accidents, and -
increases the margin of safety. % erefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 2. Change from operation at " equilibrium values by a factor of more than 10" to "less than or equal to 4.0 microcuries per gram":
BASIS:
This change constitutes a more restrictive operational limitation to Unit 1. The resultant doses from a potential accident are less since the allowable initiating point for the transient is lower.
%e change constitutes a major decrease in the effects of accidents previously analyzed, does not create any new accidents, and increases the margin of safety. %erefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the r a deral Register.
- 3. Change from "more than 5 percent of its yearly power operation" to "does not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in any consecutive 12 nonth period":
BASIS:
The change does not raise the probability or the consequences of an accident already evaluated. The charge by itself may increase the allowable time in excess of the DEI limit. However, the lower level of allowable DEI offsets any increase in time exposure. Were are no new modes of operation. There is no significant reduction in the margin of safety. %erefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (vi) of the " Examples of Amendments that are Considered N0t Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
This change is also administrative in that there is a change in nomenclature. The proposed change in nomenclature does not:
involve a significant increase in the probability or consequences of an accident previously evaluated; create the possibility of an accident of a type different from any evaluated previously; or involve a significant reduction in a margin of safety. Therefore, this change is consistant with Item (i) of the "Exanples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 4. Add to the Technical Specifications:
"Should the total operating time of a specific activity greater than 0.2 microcuries per gram dose equivalent I-131 exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6 month period, the licensee shall report the number of hours of operation above this limit to the NBC within 30 days":
BASIS:
This change constitutes a more restrictive operational limitation to Unit 1. %e resultant doses from a potential accident are less since the allowable initiating point for the transient is lower.
The change constitutes a major decrease in the effects of accidents previously analyzed, does not create any new accidents, and increases the margin of safety. Werefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.
- 5. Change from " steam line isolation valves shall be closed immediately" to
" steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />":
BASIS:
The change does not raise the probability or the consequences of an accident already evaluated. The charge by itself may increase the allowable time in excess of the DEI limit. However, the lower level of allowable DEI offsets any increase in time exposure. There are no new modes of operation. There is no significant reduction in the margin of safety. Werefore, the results of this change are clearly within acceptance criteria, and this charge is consistant with Item (vi) of the " Examples of Amendments that are Considered l Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 6. Charge " isotopic" to " iodine":
BASIS:
This change is administrative in that it is a charge in ncmenclature. The charge is a clarification of an existirg practice. Without this change the Technical Specification could be construed to mean that the total isotopic inventory must be converted to an equivalence of I-131. This is clearly not the intent of the specification. The intent is that all iodine
isotopes must be converted to an equivalence of I-131. The proposed change does not: involve a significant increase in the probability or consequences of an accident previously evaluated; create the possibility of an accident of a type different from any evaluated previously; or involve a significant reduction in a margin of safety. Therefore, this change is consistant with Item (i) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.
- 7. Add to the Technical Specifications: "(net change averaged for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />)":
BASIS:
This charge is administrative in thc.t it is a clarification in nomenclature. The proposed charge does not: involve a significant increase in the probability or consequences of an accident previously evaluated; create the possibility of an accident of a type different from any evaluated previously; or involve a significant reduction in a margin of safety. Therefore, this change is consistant with Item (i) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 8. Add to the Technical Specifications:
"3) ...at release rate less than 80,000 microcuries per second, or 4)
The off-gas levels at the SJAE, increases by more than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at release rate greater than 75,000 microcuries per second."
BASIS:
This change constitutes a more restrictive operational limitation to Unit 1. By a more restrictive limitation of when samples must be taken, the net effect is an improvement in the data base available to the plant staff. The resultant doses from a potential accident are less since the allowable initiating point for the transient is lower. The change constitutes a major decrease in the effects of accidents previously analyzed, does not create any new accidents, and increases the margin of safety. Therefore, the results of this change are clearly within acceptance criteria, and this charge is consistant with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 9. Charges to the bases reflect the above mentioned charges:
BASIS:
These changes overall constitute more restrictive operational limitations to Unit 1. The resultant doses from a potential accident are less since the allowable initiating point for the transient is lower. These charges constitute a major decrease in the effects of accidents previously analyzed, do not create any new accidents, and incre.ases the margin of safety. 'Iherefore, the results of these changes are clearly within acceptance criteria, and these charges are consistant with Items (i) , (ii) and (vi) of
the "Exanples of Amendments that are Considered Not Likely to
- .Invol ve Signi ficant Hazards Considerations" listed on page 14,870 j
of the April 6,1983, issue of the Federal Register, i
8 I
i f
I 1
l I
i 9
4 h
f 4
A 2
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ATTACINENr 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDNIN I. HA'ICH NUCLEAR PLANP UNITS 1, 2 CIARIFICATION OF PURGE AND VENP SUBMITTAIS PUHGE VALVE OPERABILITY Ietter of June 15, 1983
- 1. (Unit 1) Md to the Technical Specifications:
"3.7.A.8 Primary Containment Purge System a.) when primary containment is required, all drywell and suppression chamber 18 inch purge supply and exhaust isolation valves shall be operable and in the fully closed position except when required for inerting, deinerting, or pressure control. b.) Each drywell and suppression chamber 18 inch purge supply and exhaust -isolation valve shall have a leakage rate as specified in 4.7.A.2. If either of these requirements cannot be met, close the valve (s) or otherwise isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in
~at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shudown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.7.A.8 Primary Containment Purge System a.) Each drywell and suppression chamber 18. inch purge supply and exhaust isolation valve shall be verified to be closed at least monthly, b.) Each refueling outage ' each drywell and suppression chamber 18 inch purge supply and exhaust isolation valve with a resilient material seat shall be demonstrated operable by having its valve seat replaced and verifyirg that the leakage rate is within its limit."
BASIS:
This change constitutes a more restrictive operational limitation to Unit- 1. The probability of a potential accident is not changed. The effects of a postulated accident are not changed since ' assurance is provided that the downstream filters are protected from the IDCA induced pressure, spike by the proposed design change. The. Technical Specification change does not create any new accidents, and increases the margin of safety. Therefore, the results of this change are clearly within acceptance criteria, and . this change is consistant with Item (vi) of the " Examples of Amendments ;that are Considered Not Likely to Involve Significant l-Hazards Considerations" . listed on page 14,870 of 'the April 6,1983, issue of the Federal Register.
- 2. (Unit 1) Mditions to the bases to reflect the above mentio"A change:
BASIS:
This change constitutes a more restrictive operational limitation to Unit 1. %e probability of a potential accident is not changed. The effects of a postulated accident are not charged since assurance is provided that the downstream filters are protected from the IDCA induced pressure spike by the proposed
, design change. The Technical Specification change does not create any new accidents, and increases the margin of' safety. %erefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (ii) of the " Examples of
--,,,,----,,,,,,,,,-,,n,.,,
, u Amendments that are Considered Not Likely to Involve Significant t Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.
f 3. (Unit 2) Deletion of 4.6.1.1.b:
I BASIS:
This specification is being replaced by 3/4.6.6.5. This change does not change the effects or probability of accidents previously analyzed, does not create any new accidents, or decrease the margin of safety. %erefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (i) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 4. (Unit 2) Add to the Technical Specifications:
"CONTAIl@ENT SYSTENS PRIMARY CONTAINMENT PUICE SYSTEM LIMITING CObDITION FOR OPERATION 3.6.6.5 'Ihe drywell and suppression chamber 18 inch purge supply and exhaust isolation valves shall be OPERABLE with: a.) Each valve may be open for purge system operation for inerting, deinerting and pressure control; b.) A leakage rate such that the provisions of Specification 3.6.1.2 are met.
APPLICABILITY: OPERATIONAL CONDITIONS 1,2 and 3.
AcrION: a.) With an 18 inch drywell and suppression chamber purge stpply and/or exhaust isolation valve (s) inoperable or open for reasons other than inertina, deinerting or pressure control, close the open 18 inch valve (s) or otherwise isolate the peretration(s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOP SHU'IDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHU'IDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILIANCE REQUIRENENTS 4.6.6.5 The primary containment purge system shall be demonstrated OPERABLE: at least once per 31 days, when not purging and venting, by verifying that each 18 inch drywell and suppression chamber valve is closed; at least once per 18 months by replacing the valve seat of each 18 inch drywell and suppression chamber purge supply and exhaust isolation valve having a resilient seat and verifying that the leakage rate is within its limit."
BASIS:
This change is administrative in that it is a change in nomenclature by defining when the valves may be open rather than a set number cf hours per year. By so doing the proposed change does not: involve a significant increase in the probability or consequences of an accident previously evaluated; create the possibility of an accident of a type different from any evaluated previously; or involve a significant reduction in a margin of safety. Werefore, this change is consistant with Item (i) of the
" Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
This change also constitutes a more restrictive operational limitation to Unit 2 by mandating when the valve seats must be
replaced. The probability of a potential accident is not changed by the limitations on the lergth of time that a valve seal may be in service. %e change provides added assurance that the effects of the same postulated accident are as described in the FSAR. The change constitutes no change in the probability or effects of accidents previously analyzed, does not create any new accidents, and increases the margin of safety. Werefore, the results of this charge are clearly within acceptance criteria, and this change is consistant with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.
This change constitutes a more restrictive operational limitation to Unit 2. %e probability of a potential accident is not charged. %e effects of a postulated accident are not changed since assurance is provided that the downstream filters are protected from the ILCA induced pressure spike by the proposed design charge. The Technical Specification change does not create any new accidents, and increases the margin of safety. Therefore, the results of this change are clearly within acceptance criteria, and this change is consistant with Item (ii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
- 5. (Unit 2) Additions to the bases to reflect the above mentioned charges:
BASIS:
These changes overall constitute more restrictive operational limitations to Unit 2. %e probability of a potential accident is not charged. The effects of a postulated accident are not charged since assurance is provided that the downstream filters are protected from the IOCA induced pressure spike by the proposed design change. %e Technical Specification charges do not create any new accidents, and increase the margin of safety. %erefore, the results of these changes are clearly within acceptance criteria, and this charge is consistant with Items (i), (ii) and (vi) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the April 6, 1983, issue of the Federal Register.
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