Letter Sequence Supplement |
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TAC:M96431, Implement 10 CFR 50, Appendix J, Option B, TSTF-45, TSTF-46, TSTF-17 (Approved, Closed) TAC:M96432, Implement 10 CFR 50, Appendix J, Option B, TSTF-45, TSTF-46, TSTF-17 (Approved, Closed) TAC:M96433, Implement 10 CFR 50, Appendix J, Option B, TSTF-45, TSTF-46, TSTF-17 (Approved, Closed) |
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MONTHYEARML20149E7371997-07-14014 July 1997 Discusses Improved Standard TS for Browns Ferry Nuclear Plant,Unit 1.In Order to Issues Its,Nrc Will Require That Appropriate Controls Be Implemented in License to Ensure All Activities Comply W/Its Will Be Completed Prior to Restart Project stage: Other ML20217E2681997-09-17017 September 1997 Forwards Detailed Comments on Sections 3.5,3.9 & 3.10 of Brown Ferry Nuclear Improved TS Submittal.Tva Requested to Provide Addl Info to Address Comments to Facilitate Staff Review Project stage: Approval ML20211J8981997-09-29029 September 1997 Forwards Staff Detailed Comments Re Sections 1,2,3.0,3.1, 3.2,4 & 5 of BFN ITS Submittal.Requests Addl Info to Address Comments to Facilitate Review Project stage: Other ML20198Q4451997-11-0505 November 1997 Provides Suppl Info to TS-362 Amend Request Re Improved TS (ITS) Sections 1.0,2.0 & 3.2.Suppl Incorporates Its/Its Bases Revs & Changes to Supporting Documentation Resulting from Responding to NRC Questions Project stage: Other ML20199E1181997-11-14014 November 1997 Forwards Suppl Info Supporting TS-362 Amend Request Relating to Section 3.4, Reactor Coolant Sys. Suppl Makes Several Improved Ts/Improved TS Bases Revs & Changes to Supporting Documentation Associated W/Addressing NRC Questions Project stage: Other ML20199D5201997-11-14014 November 1997 Forwards Supplemental Info Which Supports TS-362 License Amend Request Re Improved TS Sections 3.0 & 4.0,in Response to RAI Project stage: Supplement ML20198F4301997-12-29029 December 1997 Forwards TS Section 3.6 Containing Several Proposed Improved TS Revs & Changes to Supporting Documentation Re Addressing NRC Comments,Per 970612 & 0714 Ltrs Project stage: Other ML20203B0781998-02-11011 February 1998 Requests Addl Info Re Conversion of Custom TS to Improved Std TS Format for Nuclear Measurement Analysis & Control Power Range Neutron Monitor Sys Project stage: Other ML20203L4261998-02-26026 February 1998 Forwards Request for Addl Info Re Conversion of Custom TS to Improved Std TS Project stage: RAI ML20216E8591998-04-14014 April 1998 Summary of 980326 & 27 Meeting W/Util to Discuss Technical & Working Level Nature Re Conversion of Custom TS to Improved Std Ts.List of Attendees Encl Project stage: Meeting ML20217D4741998-04-20020 April 1998 Summary of 980414 Meeting W/Participants to Discuss Licensee Amend Request for Conversion of Custom TS to Improved Std TS Project stage: Meeting 1997-09-17
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
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~ ' ll November 14, 1997 1
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U.S. Nuclear Regulatory Commission ATTN: Document Control Desk i Washingtcn, DC 20555 ,
- Gentlemen; .
l l i 2 In the Matter of ) Docket Nos. 50-259 h Tennessee Valley Authority ) 50-260 hj 2
50-296 / '
= I '
BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 TECHNICAL .- i l #
SPECIFICATIONS (TS)-362 - IMPROVED TECHNICAL SPECIFICATIONS (ITS) SUPPLEMENT 4 - RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION (RAI) - ITS SECTIONS 3.0 and 4.0 (TAC NOS. M96431, g 5
M96432, AND M96433) 1 -
l u
j The enclosures to this letter provide supplemental .nformation f.l in support of the TS-362 amendment request relating to .fL Section 3.v, Limiting Condition for Operation (LCO)
[
i Applicability, and Section 4.0, 've s i g n Features. NRC j questions on t: ese sections were included in an RAI dated , ;
-i September 29, 1997 TS-362 is TVA's conversion packaue from .
4 Current Techr.ical Specifications (CTS) to ITS and was "
- originally submitted to NRC on September 6, 1996. [
.nq This supplement makes several ITS/ITS BASES revisions and changes to supporting documentation associated with addresslag . --
the NRC questions. In addition, changes and corrections
^
associated with in-house TVA reviews are included. Also, applicable owners Group Technical Specification Task Force
('I J T F ) items have been jncorporated.
- ( h,: 1
\
A separate enclosure is provided for each individual ITS
^
section. The standard format for enclosures includes tne
^
9711200354 971114 mtimisp '
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E ADOCK 05000259 Ql;ldlirtu!Ill l ul1, nllulll211$11$u lllll PDR - * * ' ' ~
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U.S. Nuclear Regulatory Commission Page 2 November-14. 1997 information below. The enclosures will contain these subsections only if there are changes.
- Responses to NRC questions
- Summary Description of ITS/ITS BASES Changes
- Justification for 'nanges to CTS (DOCS) Revised Pages
- Justification for Changes to NUREG-1433 (JDs) Revised Pages
- No Significant Hazards Considerations Revised Pages
-Many of the NRC RAI questions request additional justification for More Restrictive, Less Restrictive, and Relocatec changes in *.he conversion from CTS to ITS. When possible, the additional justification will be provided in the RAI question response. The associated DOCS will be revised only if the scope of the original DOC is significantly changed. This same approach will also be applied to JDs.
Regarding TSTF items, ai previously agreed, TVA has reviewed and incorporated NRC approved TSTF items determined applicable to these sections. TVA has established September 1, 1997, as the cut-off date for incorporation of TSTFs. The Summary Description of ITS changes in the enclosures lists the TSTF items incorporated in this submittal.
The enclosed supplemental information does not alter the determination that there are no significant hszards considerations associated with the proposed changes and the determination that the changes qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR Sl .22 (c) (9) . Additionally, in accordance with 10 l' CFR 50. 91 (b) (1) , TVA is sending a copy of this letter and enclosures to the Alabama State Department of Public Health.
N U.S. . Nuclear Regulatory Commission Page 3:
November 14, 1997 There are no commitments contained'in this letter. If you have any questions, please contact-me at (205)-729-2636, S ncerely E4 -
T. E. Abney Manager of icensi g i .and Ind stry-Affcirs Subscribed and sworn to before me n this pth day of November 1997, Ytso] h. Om$tm My commission expires: ".* "
Enclosures cc: see page 4
'U.S.-Nuclear-Regulatory Commission Page 4 November 14. 1997 Enclosure cc (Enclosures)i.
Chairman-Limestone. County Commission 3J0 West. Washington Street hthens,-Alabama 35611' Mr. Mark S. Lesser, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.
Suite 23T85
' Atlanta,. Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. J. F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Dr. Donald E. Williamson State Health Officer Alabama State Department of Public Health 434-Monroe Street Montgomery, Alabama 36130-3017
Enclosure 1.0 ITS Section 3.0 LCO Applicability Enclosure Contents Enclosed?
- Response to NRC questions . . . . . . . . . . . . . . Yes
- Summary Description of ITS/ITS BASES Changes. . . . . Yes
- ITS Revised Pages . . . . . . . . . . . . . . . . . . Yes
- ITS BASES Revised Pages . . . . . . . . . . . . . . . Yes
- CTS Markup Revised Pages. . . . . . . . . . . . . . . N/A
- Justifications for Changes to CTS (DOCS)
Revised Pages . . . . . . . . . . . . . . . . . . . . Yes
- NUREG-1433 BWR/4 S"S Mark-up Revised Pages. . . . . . Yes
Revised Pages . . . . . . . . . . . . . . . . . . . . Yes
- No Significant Ha:ards Considerations Revised Pages . N/A
- Cross-Reference Matrix Correlating Changes Between the CTS, ITS, and NUREG-1433. . . . . . . . . N/A
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Response to NRC Questions '
ITS Section 3.0 L
3.0-1 NRC Description ofissue: ITS 3.0.5 changes are proposed to make it apply to variables as well as equipment, NRC Comment: The changes proposed here were reviewed and rejected as TSTF 001. ' Provide markup deleting these changes.
( Response: ITS 3.0.5 changes associated with Technical Specifications Task l
Force (TSTF) item 001 have been deleted in the attached revised ITS and ITS Bases.
3.0-2 NRC Description ofIssue: None l NRC Comment: These changes are generic and must be handled accordingly.
Generic changes go to the Technical Specifications Task Force (TSTF) to be reviewed by the OGs and submitted as a TSTF. Provide new pages deleting the changes.
Response: We consider that the BFN proposed changes to ITS Section 3.0.6 Bases referenced in the Staff s question are be'ow the significance threshold for processing as generic changes for Bases as defined in NEl 96-06, " Improved Technical Specifications Conversion Guidance." Rather, the changes are editorial in nature and serve to simplify text and facilitate use of the Bases using language that is more familiar to BFN personnel. Accordingly, we consider the
! revisions within the prerogative of the Licensee's scope for changes for improved usability at BFN.
3.0-2 NRC Description ofissue: None NRC Comment: Thejustifications for change provide excellent explanations of -
what the LCOs do. They do r.ot, however, providejustification ofwhy they are acceptable for Biowns Ferry, whether they impose any operational constraints, ,
impact any system design or the current licensing basis. Provide simple statement of applicability to your plant.
Response: BFN CTS DOCS M1, M2, and M3 have been revised to provide additionaljustification on these more restrictive changes.
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Summary Description of ITS/ITS Bases Changes ITS Section 3.0 LCO 3.0.5 and Associated BASES Deleted TSTF-001. The original TS-362 submittal incorporated text changes proposed in TSTF-001. This TSTF was subsequently not approved by the NRC. The ITS and corresponding bases show the deletion of the TSTF and a return to the standard NUREG-1433 provisions.
LCO 3.0.6 Incorporated TSTF-166 to explicitly require an evaluation in accordance with the Safety Function Determination Program to determine if a loss of safety function exists.
LCO 3.0.5 BASES Incorporated TSTF-165 to use the words " required testing" instead of "SR." This change provides consistency in nomenclature, i
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