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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5741990-09-19019 September 1990 Forwards Rev 2 to Browns Ferry Nuclear Plant Cable Issues Supplemental Rept Corrective Actions,Sept 1990. Rept Revised to Clarify Cable Bend Radius & Support of Vertical Cable & Document Resolution of Jamming Issues ML20064A6871990-09-18018 September 1990 Requests Closure of Confirmatory Order EA-84-054 Re Regulatory Performance Improvement Program ML20059L4931990-09-17017 September 1990 Provides Addl Info Re 900713 Tech Spec Change 290 Concerning Hpci/Rcic Steam Line Space Temp Isolations,Per Request ML18033B5171990-09-17017 September 1990 Forwards Addl Info Re 900524 Tech Spec Change 287 on Reactor Pressure Instrument Channel.Schematic Diagrams Provided in Encl 2 ML20064A6851990-09-17017 September 1990 Responds to NRC Recommendations Re Primary Containment Isolation at Facility.Background Info & Responses to Each Recommendation Listed in Encl 1 ML20059K2971990-09-14014 September 1990 Responds to NRC 900208 SER Re Conformance to Reg Guide 1.97, Rev 3, Neutron Flux Monitoring Instrumentation. TVA Endorses BWR Owners Group Appealing NRC Position Directing Installation of Upgraded Neutron Flux Sys ML20059H3861990-09-10010 September 1990 Forwards Corrective Actions Re Radiological Emergency Plan, Per Insp Repts 50-259/89-41,50-260/89-41 & 50-296/89-41. Corrective Action:Plant Manager Instruction 12.12,Section 4.11.3.1 Revised ML18033B5031990-08-31031 August 1990 Forwards Financial Info Required to Assure Retrospective Premiums,Per 10CFR140 & 771209 Ltr ML20059E1741990-08-31031 August 1990 Informs That Plant Restart Review Board & Related Functions Will Be Phased Out on Date Fuel Load Commences ML20059D7061990-08-28028 August 1990 Requests That Sims Be Updated to Reflect Implementation of Program to Satisfy Requirements of 10CFR50,App J.Changes & Improvements Will Continue to Be Made to Reflect Plant Mods, Tech Spec Amends & Recommendations from NRC ML18033B4931990-08-20020 August 1990 Suppls Response to Violations Noted in Insp Repts 50-259/90-14,50-260/90-14 & 50-296/90-14.Corrective Actions: TVA Developed Corporate Level std,STD-10.1.15 Re Independent Verification ML20063Q2431990-08-20020 August 1990 Responds to 900807 Telcon Re Rev to Commitment Due Date Per Insp Rept 50-260/89-59 Re Electrical Issues Program ML20063Q2451990-08-17017 August 1990 Provides Revised Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants & Notification of Commitment Completion ML20063Q2441990-08-17017 August 1990 Advises That IE Bulletin 80-11 Re Masonry Wall Design Implemented at Facilities.Design Finalized,Mods Completed, Procedures Issued & Necessary Training Completed.Sims Data Base Should Be Updated to Show Item Being Implemented ML20059A4861990-08-16016 August 1990 Responds to Verbal Commitment Made During 900801 Meeting W/Nrc Re Control Room Habitability.Calculations Performed to Support Util 900531 Submittal Listed in Encls 1 & 2 ML20059A5141990-08-16016 August 1990 Provides Response to NRC Bulletin 88-008,Suppl 3 Re Thermal Stresses in Piping Connected to Rcs.Util Does Not Anticipate Thermal Cyclic Fatique Induced Piping,Per Suppl 3 to Occur in Plant.Ltr Contains No Commitment ML18033B4821990-08-14014 August 1990 Submits Revised Response to Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Extends Completion Dates for Commitments to 901203 ML18033B4831990-08-13013 August 1990 Responds to NRC 900713 Ltr Re Violations & Deviations Noted in Insp Repts 50-259/90-18,50-260/90-18 & 50-296/90-18. Corrective Actions:Craft Foreman Suspended for Three Days & Relieved of Duties as Foreman ML18033B4811990-08-10010 August 1990 Responds to NRC 900710 Ltr Re Power Ascension Testing Program.Four Hold Points Selected by NRC Added to Unit 2 Restart Schedule ML18033B4801990-08-0808 August 1990 Forwards Response to SALP Repts 50-259/90-07,50-260/90-07 & 50-296/90-07 for Jul 1989 - Mar 1990 ML20044B2121990-07-13013 July 1990 Clarifies Util Position on Two Items from NRC 891221 Safety Evaluation Re TVA Supplemental Response to Generic Ltr 88-01 Concerning IGSCC in BWR Stainless Steel Piping.Insp Category for Nine Welds Will Be Changed from Category a to D ML18033B4371990-07-13013 July 1990 Forwards Corrected Tech Spec Page 3.2/4.2-45 to Util 900706 Application for Amend to License DPR-52 Re ADS ML18033B4331990-07-13013 July 1990 Requests Temporary Exemption from Simulator Certification Requirements of 10CFR55.45(b)(2)(iii) ML20055F6091990-07-12012 July 1990 Provides Response to NRC Bulletin 88-003 Re Insp Results. No Relays Found to Have Inadequate Latch Engagements. Therefore,No Corrective Repairs or Replacement of Relays Required ML18033B4251990-07-10010 July 1990 Forwards Cable Installation Supplemental Rept,In Response to NRC Request During 900506 Telcon.Rept Contains Results of Walkdowns & Testing Except Work on Ongoing Cable Pullby Issue ML18033B4241990-07-0606 July 1990 Advises That Util Expects to Complete Implementation of Rev 4 to Emergency Procedure Guidelines by Mar 1991.Response to NRC Comments on Draft Emergency Operating Instructions Encl ML18033B4201990-07-0505 July 1990 Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3. Util Has Concluded That Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issue,Subj to Listed Conditions ML18033B4091990-07-0202 July 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-259/89-53,50-260/89-53 & 50-296/89-53.Corrective Actions: Condition Adverse to Quality Rept Initiated & Issued to Track Disposition of Deficiency in Chilled Water Flow Rates ML20043G4901990-06-14014 June 1990 Forwards Tabs for Apps a & B to Be Inserted Into Util Consolidated Nuclear Power Radiological Emergency Plan ML20043H3511990-06-14014 June 1990 Forwards Corrected Pages to Rev 15 to Physical Security Contingency Plan,As Discussed During 900606 Telcon.Encl Withheld (Ref 10CFR73.21) ML20043F4951990-06-11011 June 1990 Advises That Facilities Ready for NRC Environ Qualification Audit.Only Remaining Required Binder in Review Process & Will Be Completed by 900615 ML18033B3651990-06-0808 June 1990 Forwards Revised Page 3.2/4.2-13 & Overleaf Page 3.2/4.2-12 to Tech Spec 289, RWCU Sys Temp Loops. ML18033B3391990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-259/90-08,50-260/90-08 & 50-296/90-08.Corrective Actions: Individual Involved Counseled on Importance of Complying W/Approved Plant Procedures When Performing Assigned Tasks ML20043D3251990-06-0101 June 1990 Responds to NRC 900502 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty.Corrective Actions:Snm Program Action Plan Being Developed & Implemented,Consisting of Improved Training for Control Personnel & Accountability ML18033B3551990-05-31031 May 1990 Forwards Response to 891219 Request for Addl Info on Hazardous Chemicals Re Control Room Habitability ML20043C1951990-05-30030 May 1990 Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues ML20043C0601990-05-29029 May 1990 Forwards Response to Violations Noted in Insp Repts 50-259/90-12,50-260/90-12 & 50-296/90-12.Util Admits Violation Re Access Control to Vital Areas,But Denies Violation Re Backup Ammunicition for Responders ML18033B3351990-05-25025 May 1990 Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability. Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issues Subj to Listed Conditions ML18033B3221990-05-21021 May 1990 Forwards Rev 1 to ED-Q2000-870135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation, as Followup to Electrical Insp Rept 50-260/90-13 Re Ampacity Program ML18033B3101990-05-18018 May 1990 Responds to NRC 900417 Ltr Re Violations Noted in Insp Repts 50-259/90-05,50-260/90-05 & 50-296/90-05.Corrective Action: Senior Reactor Operator Assigned to Fire Protection Staff for day-to-day Supervision of Fire Protection Program ML20043A6101990-05-15015 May 1990 Forwards Rev 16 to Security Personnel Training & Qualification Plan.Rev Withheld (Ref 10CFR2.790) ML20043A4091990-05-14014 May 1990 Forwards Rev 14 to Physical Security/Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20043A4081990-05-14014 May 1990 Forwards Rev 15 to Physical Security/Contingency Plan, Consisting of Changes for Provision of Positive Access Control During Major Maint & Refueling Operations to One of Two Boundaries.Rev Withheld (Ref 10CFR73.21) ML18033B2921990-05-0909 May 1990 Provides Info for NRC Consideration Re Plant Performance for Current SALP Rept Period of Jan 1989 - Mar 1990.Util Believes Corrective Actions Resulted in Positive Individual Changes & Programmatic Upgrades ML20042F7401990-05-0404 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' TVA Will Finalize Calculations for Switch Setpoints Prior to Units Restart ML20042F7701990-05-0404 May 1990 Provides Results of Review of Util 890418 Submittal Re Supplemental Implementation of NUMARC 87-00 on Station Blackout.Implementation of 10CFR50.63 Consistent W/Guidance Provided by NUMARC 87-00 ML20042F3721990-05-0202 May 1990 Forwards Corrected Monthly Operating Repts for Jan-June 1989 & Aug 1989 - Jan 1990.Discrepancies Involve Cumulative Unit Svc Factors & Unit Availability Capacity Factors ML18033B2631990-04-12012 April 1990 Forwards Response to NRC 900212 Request for Info Re Power Ascension & Restart Test Program at Unit 2.Util Has Refined Power Ascension Program to Be More Integrated & Comprehensive ML18033B2551990-04-0909 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Corrective Actions: Contractor Will Perform Another Check Function Review for Mechanical Calculations & Area Walkdowns Will Be Conducted ML18033B2431990-04-0202 April 1990 Responds to NRC 900302 Ltr Re Violations Noted in Insp Repts 50-259/89-43,50-260/89-43 & 50-296/89-43.Corrective Action: Surveillance Insp Revised to Prevent Removal of All Eight Emergency Equipment Cooling Water Pumps from Water 1990-09-19
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ACCELERATED DISTRIBUTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ESSION NBR:8911270107 DOC.DATE: 89/11/20 NOTARIZED: NO g FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station,,Unit 3, Tennessee 05000296 AUTH. NAME . AUTHOR AFFILIATION Desk)'OCKET MEDFORD,M.O. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document'ontrol
SUBJECT:
Responds to NRC 891021 ltr re violations noted in Insp Repts 50 259/89 47150 260/89 47 & 50 296/89 47 CODE: IEOlD COPIES RECEIVED:LTR ~ ENCL i SIZE:
'ISTRIBUTION TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:1 Copy each to: B.Wilson,D.M.Crutchfield,B.D.Liaw,S.Black 05000259 R. Pierson, 1 Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw, 05000260 R. Pierson,B.Wilson 1 Copy each to: S. Black,D.M.Crutchfield,B.D.Liaw, 05000296 R. Pierson,B.Wilson RECIPIENT RECIPIENT COPIES ID CODE/NAME LTTR ENCL 1 1 ID CODE/NAME GEARS,G LTTR ENCL 1 1 PD I ERNAL: ACRS 2 2 AEOD 1 1 AEOD/DE IIB 1 1 1
AEOD/TPAD NRR SHANKMAN,S 1
1 1
1 DEDRO 1 NRR/DEST DIR 1 1 NRR/DLPQ/PEB 1 1 NRR/DOEA DIR 11 1 1 NRR/DREP/EPB 10 1 1 NOTES'OPIES NRR/DREP/RPB 10 NRR/PMAS/I LRB12 L N,J
'E 2,
1 1
2
.1 1
NRR/DRIS/DIR NUDOCS-ABSTRACT OGC/HDS2 1
1 1
1 1
1 RE FILE 1 1 RES MORISSEAU i D 1 1 01 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 5 5 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
0'
'0 TENNESSEE VALLEY AUTHORlTY CHATTANOOGA. TENNESSEE 37401 6N 38A Lookout Place NOV 20 888 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Hatter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 NRC INSPECTION REPORT NOS. 50-259/89-47, 50-260/89-47, AND 50-296/89-47 RESPONSE TO NOTICE OF VIOLATION This letter is to provide TVA's response to your letter from Bruce Wilson to Oliver D. Kingsley, Jr. dated October 21, 1989, which transmitted the subject report. This report cited TVA with one Severity Level V Violation O.
'nspection (Supplement I) in accordance with 10 CFR Part 2, Appen~ix C.
Enclosure 1 provides background information and TVA's response to the violation cited in the subject report.
A list of commitments is provided in Enclosure 2.
If you have any questions, please telephone Patrick P. Carier, BFN, at (205) 729-3570.
Very truly yours, goal TENNESSEE VALLEY AUTHORITY Mark O. Medford, Vice esident, Nuclear Technology and Licensing Enclosures cc: See page 2 85'11270 g 07 g.-.0
~E1OCr, <~.",iaoc>- ~-a i3 F'DC An Equal Opportunity Frnployer
U.S. Nuclear Regulatory Commission cc (Enclosures):
Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One Hhite Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Nilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NH, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route- 12, Box 637 Athens, Alabama 35609-2000
ENCLOSURE 1
RESPONSE
NRC INSPECTION REPORT NOS. 50-259/89-47, 50-260/89-47, AND 50-296/89-47 LETTER FROM B. A. HILSON TO O. D. KINGSLEY, JR.
DATED OCTOBER 21, 1989 Statement of Violation 10 CFR 50 Appendix B Criterion VI, Document Control, requires that measures shall be established to control the issuance of documents including changes thereto, which prescribe all activities affecting quality. These measures shall assure that documents, including changes, are reviewed for adequacy and are distributed to the location where the prescribed activity is performed.
Nuclear Quality Assurance Manual Part I, Section 2.6, Document Control, Paragraph 5.1.1, requires that programs and procedures shall be established for the control of documents for activities that affect safety-related functions.
Site Directors Standard Practice 2.12, Controlling Documents, establishes the requirements for the processing of controlled documents to ensure that the latest applicable controlled documents are available and distributed to identified recipients and to minimize the inadvertent use of voided or superseded documents.
Contrary to the above, these requirements were not met in that adequate document control was not maintained for a TS amendment and controlled copies of TS for the following three examples:
- l. Adequate document control was not maintained for TS Amendment 135, 131, 106, dated August 20, 1987, which revised TS definition 1.0.C.2 to.
clarify its applicability during Cold Shutdown or Refueling. On September 26, 1989, the inspector identified that page 1.0-2 located in controlled copies of the TS did not reflect the approved and issued change. The correct wording had been incorporated into controlled copies of the TS but not into the plant licensing's staff master copy. In February 1989, TS Amendment 158, 157, 129 revised different information contained on the same page in TS definition 1.0.C.2.
- 2. Unit 2 TS controlled copy 52 was not properly maintained with the latest amendment to TS. On September 27, 1989, the inspector identified that existing pages 1.1/2.1-2 through 1.1/2.1-4 of copy 52 reflected the original amendment dated March 19, 1987, instead of amendment 143 dated March 3, 1989.
- 3. Unit 2 TS Control Room copy 40 was not properly maintained. On September 27, 1989, the inspector identified that two copies of page 3.7/4.7-16 existed but only one of which was annotated with information pertaining to compensatory measures 88-64-2-007, in effect at the time.
The above instances are examples of a Severity Level V Violation (Supplement I) and is applicable to all three units.
Page 2 of 4 T VA Response
- l. Admission or Denial of the Alleged Violation TVA admits the violation occurred as stated. Due to the difference in the three examples, TVA will discuss the reasons for the violation, corrective steps which have been taken and results achieved, corrective steps which will be taken to avoid further violations, and date of full compliance separately for each example.
- 2. Reasons for the Violation A. TVA BFN uses a computer master TS file to store NRC approved TS's.
This file is updated by the BFN Licensing Speciali.st when the NRC approved TS change is received. The master file can only be accessed through a security code which is controlled by the Licensing Specialist. In investigating this specific example, it is apparent that the computer master file was not updated after the issuance of TS Amendment 135, 131, 106 dated August 20, 1987. As a result, when this specific page was revised (TS Amendment 158, 157, and 129), the original TS words were inadvertently incorporated. Therefore, when TS Amendment 158, 157, and 129 was issued, the previously approved changes in TS Amendment 135, 131, and 106 were not contained. This resulted in inadvertent use of the outdated wording in TS definition 1 ~ 0.C.2, however, use of the outdated wording did not decrease any margin of safety. The outdated words were minor in nature and were changed to only provide additional clarification.
B., BFN Document Control uses two methods of updating controlled documents. The first method utilizes Document Control staff to physically insert the revised pages in the controlled document. In the second method, the revised pages are submitted to the document holder with instructions of how to update their controlled documents. Upon completion of either process, documentation of completion is returned to Document Control. The subject controlled document, TS copy 52, is updated by the BFN Document Control staff.
For the specific example cited in the subject inspection report, the pages were either inadvertently replaced with the original pages 1.1/2.1-2 through 1.1/2.1-4 or those revised pages were not inserted when the controlled document was being updated. Controlled copy 52 is the Site Residents copy of the BFN TS. This copy is not used to perform any safety analysis or operation of the plant, therefore, this specific issue did not decrease any margin of safety.
C. The Unit 2 Control Room TS copy 40 is updated by the Document Control staff. When this copy was updated, the existing, page 3.7/4.7-16 was measured'his to be replaced. When the revised page was placed in the document, the existing page was not removed. This resulted in two page 3.7/4.7-16's left in the document. The only difference in the two pages was the revised page had an annotation pertaining to a compensatory is an additional requirement implemented by BFN. The Limiting Condition of Operation (LCO) and the Surveillance Requirement (SR) were the same on both pages therefor e, there was no decrease in the margin of safety.
Page 3 of 4
- 3. Corrective Steps Which Have Been Taken and Results Achieved TVA reviewed these three examples to determine the reason for error.
Based on this review it was determined that these were isolated issues and there is not a programmatic problem. In all three cases personnel error was identified to be the reason for the error.
When TS Amendment 158, 157, and 129 was issued (February 1989), BFN typically reviewed only those parts of the LCOs or SRs that were being revised. In early spring 1989, BFN started to review not only those sections being revised but the entire page. This provided additional checks and balances to ensure that the entire page reflects not only those sections being revised but ensures the rest of the page reflects what has been approved by NRC in previous changes. Since'his practice was implemented, BFN has minimized such errors.
As a result of the subject inspection report, BFN Document Control Records Management (DCRM) conducted a 100% assessment (51 copies) of the controlled sets of TS's on site and 2 additional sets in Chattanooga. The scope of this assessment was to see if any other controlled copies of the BFN TS's contained the same page errors identified in controlled copy 52. The results of the assessment demonstrated that the page errors were unique to controlled copy 52.
This is considered an isolated case which resulted from personnel error.
In early 1989, DCRM implemented a self-assessment program, improved transmittal receipt acknowledgment tracking system, and a reduction in the number of controlled manuals in an effort to enhance the overall document control process at BFN. DCRM instruction DCRMI 302.2 was also updated to require that an audit of selected controlled documents (including the Technical Specifications) be performed on an annual basis. These steps, in addition to the actions discussed above, have enhanced the overall control process of these documents.
After NRC identified that two copies of the same page existed in Unit 2 TS Control Room copy 40, one of the pages was deleted to correct the problem. Upon correcting this problem, DCRM instructed their personnel of the importance of correctly updating controlled manuals. In addition, DCRM performed a 100% audit of controlled copies of the TSs on site to ensure that the same problem did not exist (two copies of the same page 3.7/4.7-16). This audit did not identify any other copies with the same problem, therefore, this is con'sidered an isolated case which resulted from personnel error.
Page 4 of 4
- 4. Corrective Steps Hhich Hill Be Taken to Avoid Further Violations A. To correct the specific problem, BFN will resubmit the correct page 1.0-2 in a subsequent TS submittal to NRC. This has been discussed and approved by the NRC/TVA Project Manager.
B. The continued implementation of the corrective steps discussed in section 3.B above are considered adequate to avoid further violations. No other steps are being considered at this time.
C. As stated above, DCRM procedure DCRM 302.2 was revised to require an annual audit be performed on specified controlled documents to minimize such errors. In addition, continued emphasis to the DCRM employees on the importance of correctly updating these documents is expected to avoid further violations of this nature.
- 5. Date Hhen Full Compliance Hill Be Achieved A. The correct page 1.0-2 wi 11 be submitted to NRC by January 5, 1990.
B. BFN is in full compliance with the steps stated abov'e.
C. BFN is in full compliance with the steps stated above.
ENCLOSURE 2 LIST OF COMMITMENTS
- 1. TVA will submit the correct page 1.0.2 to NRC by January 5, 1990.