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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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m TENNESSEE VALLEY AUTHORITY' R P. O. Box 2?00 Decatur,: Alabama SEP 181990 ,
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U.S. Nuclear Regulatory Commission ATTN L Document Control Desk l i Washington, D.C. 20555 Gentlemen:' U In the Matter'of ) Docket Nos. 50-259-Tennessee Valley Authority ) 50-260 i 50-296 I
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BROWNS FERRY NUCLEAR PLANT (BFN)'- REGULATORY PERFORMANCE IMPROVEMENT PROGRAM -
The purpose of this letter is to to request the closure of Confirmatory Order EA 84-54. . This Order was issued on July 13, 1984 and required the implementation of the Reg 1latory Performance Improvement Program (RPIP) for
.BFN. ,
i li LTheovers111objectiveoft.teRPIPwasto-provideaplanforensuringsafe ~!
- operation of the Browns Feiry Nuclear Plant.by achieving the improvements
- considered necessary to mee: NRC regulatory requirements. By-. letter dated .
, l March.18, 1986, TVA providel a status update of the RPIP action items and j L; ' requeated'~that the action it ems which remained open af ter NRC's review be L . incorporated-in TVA's Nuclesr Performance Plant (NPP) forjBFN. The NPP-provided a1 comprehensive. pit.n for correcting the overall problems-with the TVA-nuclear program.and was much broader in scope than the RPIP. NRC last'
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Linspected open RPIP action items in 1988 (Inspection Report 88-31, dated ,
p October-24, 1988) and in that report, indicated that the remaining'RPIP action-K . items =were covered in various sections of the NPP for BFN. Consequently, TVA ,
. considers'the=open action items contained-in the.RPIP to be. resolved by '
incorporation-into the NPP. The enclosure to this submittal provides the basis for the closure of each of the remaining open RPIP items tracked.by the b 4 NRC staff, t-1 l
There'are no commitments-contained in this letter. If you have any questions, .-
please contact Patrick P. Carier, Manager of Site Licensing, at (205) 729-3570. "}
p Very truly yours, }
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SEE VALLEY AUTHORITY
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E. G. Wal ace, Manager l' 9009270058 900918 Nuclear Licensing and DR- ADOCK 0500 9 A Regulatory Affairs !
Enclosure cc: See page 2 u
An Equal Opportunity Employer ll00l f
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U.S. Nuclear Regulatory Commission b
SEP 181990 cc-(Enclosure):
.Ms. S.'C. Black, Deputy Director l Project Directorate II-4 U.S.- Nuclear Regulatory Commission
'One White Flint, North 11555 Rockville Pike,
- Rockville, Maryland 20852 NRC Resident Inspector ;
Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Thierry M. Ross, Project Manager ,
U. S. Nuclear Regulatory Commission One W11te Flint, North- t 11555 Rockville Pike '
Rockville, Maryland 208-Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission i Region II 101 Marietta Street, NW,. Suite 2900 i Atlanta, Georgia 30323 .
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t ENCLOSURE BROWNS FERRY NUCLEAR PLANT-CLOSURE:0F REGULATORY PERFORMANCE IMPROVEMENT PROGRAM :
Background:
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TVA submitted the Regulatory Performance Improvement Plan (RPIP), by letter
- darsi 'ebruary 24, 1984, which described both short-range and long-range :
objvN ives for achieving the improvements considered necessary to meet regulatory requirements at Browns. Ferry. On July 13, 1984, the NRC Region II office' issued Confirmatory Order EA 84-54. .The Order stated that the completion of those initiatives which were described in the RPIP were necessary and appropriate to the continued safe operation of the Browns Ferry
. Plant.
Subsequently, in March 1985, Browns Ferry was shut down.- On September 17,
'1985, the NRC staff requested, pursuant to 10 CFR 50.54(f), that TVA submit.
information about its plans for, among other things, correcting the Browns Ferry problems. 'In response, the Browns Ferry Nuclear Performance Plan (NPP)- '
was submitted on August 28, 1986 and revised.by letters dated July 16, 1987
.and October 24, 1968. r As discussed in Appendix _A of the NPP, many of the long-term RPIP action items !
.were carried forward <into the-NPP as a superseding plan for tracking !
programmatic-improvement efforts at BFN. The status of the RPIP items carried-as open by the NRC staff was listed in Appendix A of the NPP and discussed in Inspection Report 88-31, dated October 24, 1988. These items, the associated cactions, and a basis for the closure of each item is provide as follows:
a Open-Iterns and Basis for Closure: s Shod TerrN RPIP Action items:
' Item I-3.8,' Regulatory Compliance Training
- Actions- Ensure that each classification of employees understands his or her responsibilities and authority regarding quality and j ,
-compliance. Rigidly require the craftsman to certify all work for quality and completeness. The craftsman must understand that quality is.his responsibility and that quality control inspectors only verify the quality.
1 JClosuret- This RPIP item was closed in Inspection Report 88-31, dated October 24,.1988. The Inspection Report concluded that BFN l developed and implemented a-formal training program on QA/QC, plant procedures, and regulatory compliance for all personnel.
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ENCLOSURE (CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLOSURE OF, REGULATORY: PERFORMANCE. IMPROVEMENT: PROGRAM. 1 Short-Term RPIP. Action items (Continued):
Item I-4.5, organization 7
Action Review and revise appropriate documents to define and describe the new-organization.
Closures This' RPIP item was closed in Inspection Report 88-31, dated October 24, 1988. The Inspection Report concluded that the BFN Final Safety Analysis Report (FSAR) and TVA's Topical Report,
-TVA-TR 75-1A, dated.May 6, 1988, addressed the relationship of
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various organization positions.
Item I-4.ll, Independent Safety Engineering-Group
? ' Action: Implement an Independent Safety Engineering Group closure ~ This RPIP item was closed in Inspection Report 88-31, dated October. 24, 1988. 'The Inspection Report concluded that a long -I term stef fing plan was established and the NRC's review and -
determination of BFN ISEG acceptability would be addressed in a Safety Evaluation Report on the NPP. Supplement 1 to the Safety Evaluation Report on the Browns Ferry Nuclear Performanos Plan - NUREG 1232,_ Volume 3, was' issued on October 24, 198V.
Section 4.2.2, Independent Safety Engineering Group, concluded that the ISEG program for Browns Ferry was adequately constituted ,
and chartered to enhance the safety. posture of the-plant in_the_ s manner outlined by NUREG-0737 and SECY 80-242.- 0 l
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, ENCLOSURE (CONTINUED)~
r BROWNS FERRY NUCLEAR PLANT ,
j CLOSURE OF REGULATORY PERFORMANCE: IMPROVEMENT PROGRAM 1
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.'Long Terni FU)lP )(ction Iterns: !
Item II-1.1, Vendor Manual Upgrade Program Actions Review and resolve an audit finding on the vendor manual-control program.
Closure TVA's revised Vendor Manual Control Program was discussed in NPP !
Sections II.2.4 and II.5.1. The Vendor Manual control Program at i Browns Ferry was reviewed and found acceptable as documented in -1 Inspection Report 89-56, dated March 26, 1990. Since that time, >
the Staff issued Generic Letter 90-03, dated March 20, 1990, which j relaxed the guidance previously provided in Generic' Letter 83-28, Item 2.2, Part 2, Vendor Interface for Safety-Related components. ,
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TVA11etter dated August 24, 1990 certified that TVA's corporate standard met the requirements of Generic-Letter 90-04. This ,!
standard is scheduled for implementation on September 28, 1990.
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. Item 11-1.2, Close out of QA Audit Findings *
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Actions- Close out QA findings for which corrective action is complete.
Closure: This RPIP item was closed in Inspection Report 88-31, dated October :24,'1988. The Inspection Report stated that there were two remaining QA audit findings which required ~ closure. The first a was for TVA to implement a technical training program for the-Modification and Plant Engineering sections in preparation of work plans. The second was the improvement.of inadequate corporate < M pcocedures.
The technical training program audit finding was resolved in 1987.
Training was performed on work plans for the modifications group and similar training was-provided to the. plant engineering staff'.
The audit-finding regarding the improvement of corporate procedures was closed since TVA had committed in the Corporate Nuclear Performance Plan-(CNPP), which'was originally submitted to NRC on November 1, 1985, to correct identified weaknesses in.
programs and procedures. The NRC reviewed the CNPP and concluded in the July 28, 1987 Safety Evaluation Report that TVA's effort to upgrade procedures and to establish uniform controls and.
centralized direction.was an acceptable program for procedure development.
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ENCLOSURE-(CONTINUED)- '
BROWNS FERRY NUCLEAR PLANT CLOSURE OF REGULATORY PERFORMANCE IMPROVEMENT PROGRAM ;
Long Term RPIP Action items (Continued): ;
item II-2.1,-Close-out of ECN D'cumentation :
Action: Assign management priority to the BFN As-Constructed Drawing Task ,
Force for resolution of open/ incomplete ECNs, workplans, as-constructed drawings, and resolve the disapproved but implemented FCR backlog issue.
Closure: This was a broad based effort to establish a design baseline consistent with the as-built condition and to maintain control of future plant configuration changes. Actions to implement the effort were described in Section III.2 of the NPP. Major progress has been.made in the updating of drawings cnd the resolution of outstanding design and work documents.
Item II-3.1, Corporate Procedure Upgrade
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Action: Rework and upgrade upper-tier procedures. '
Closuro: As discussed in Item II-1.2 above, TVA committed in the Corporate Nuclear Performance Plan (CNPP) to correct identified weaknesses mi i-in programs and procedures. ' Procedures are being upgraded-through-short- and long-term programs. The NRC reviewed the CNPP and concluded in the July 28,.1987 Safety Evaluation Report that.TVA's
., . effort to upgrade procedures and to establish uniform controls'and
' centralized direction was an-acceptable' program for procedure development.
Item II-3.2, Management Observation and Craftsman or Operator Involvement in
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Procedures Action: Verify procedures during management observation in the field.
Assign senior craftsmen in each section to work with section q,; engineering personnel to ensure that. procedure revisions resulting from-field observations are written for the man performing the-work and not the reviewer.
Closure This RPIP item was closed in Inspection Report 88-31, dated October 24, 1988. The inspector noted that a majority of maintenance procedures were upgraded in the electrical, I&C, and Mechanical areas.
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a Page 5 of 11 ENCLOSURE (CONTINUED) a -BROWNS FERRY NUCLEAR PLANT CLOSURE OF REGULATORY PERFORMANCE IMPROVEMENT PROGRAM Long Term RPIP Action items (Continued):
Item 11-3.4, Intent /Non-Intent Revisions to Procedure
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Action: Define clearly the method and limitation imposed to revise !
. procedures on the spot and also ensure proper review-of the change. j Closure: TLis RPIP iten was closed in Inspection Report 88-31, dated i October 24, 1988. The Inspection Report stated that a Site Director Standard Practice described how to make .mmediate l Temporary changes which are.also known as non-intent changes.
They are normally used for completing a procedure in progress. !
requiring an immediate revision in which the change does not alter ;
the intent of the original procedure.
I Item II-3.5, Hodification Control Process '
Actions. Revise modification control procedures to ensure completion of work,. post-modification testing, configuration control, and .,1 training documents before'a modification is placed in service. i Closure This item covered a broad scope of activities and improvement for-the modification control process which were discussed in det... in Sections III.2.3 and III.2.4 of_the NPP. The performance of the 3 plant in the area of. modifications control was documented-in'the' 1 latest Systematic Assessment =of Licensee Performance, Inspection.
Report 90-07, dated June 14, 1990. There was increased management '
involvetrent and control of the modification control process. The Browns Ferry onsite engineering and modification groups were ~j reorganized. Improvements were made in accountability, responsiveness and effectiveness of these groups.
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ENCLOSURE (CONTINUED)
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" BROWNS FERRY NUCLEAR PLANT-L LCLOSURE OF REGULATORY PERFORMANCE IMPROVEMENT PROGRAM
~ Long Term RPIP Action items (Continued):
Item 11-3.6, Programmatic Improvements Action: Implement programmatic improvement plans in the areas of l radiological control, security, quality assurance, chemistry, and i fire protection.
l-closures Programmatic improvements have been made in the areas of g radiological control, security, quality assurance, chemistry, and l fire protection as documented be2ow j Programmatic improvements is the area of radiological control were j described in Section II.6.1 of the NPP. Reductions were achieved l in collective annual'aite dose, personnel contamination evento and )'
in the size of the area of the plant considered contaminated.
l- Training for Health Physics technicians was increased. The=NRC Staff evaluated improvements to radiological control in Section 4.10 of NUREG-1232, Volume 3, dated April 14, 1989.. The.
NRC Staff concluded in that document that-the: improvements were acceptable to support restart of BFN Unit 2.. The performance'of.
the plant-in the area of Radiological controls was documented in the latest Systematic Assessment of Licensee Performance, Inspection Report 90-07, dated June 14, 1990. ,.
Programmatic improvements is the area of security were_ described-in Section II.7 of the NPP. The NRC Staff evaluated plant security in Section 4.8-of NUREG-1232, Volume 3, dated ,
U April.14, 1989. The Staff concluded that the physical security program was acceptable with the implementation of the following ;
- i. security related actions -
- 1) Test security emergency power,
- 2) Reduce the size of the protected area,
- 3) Improve alarm assessment capabilities, and ,
- 4) Reduce the number of compensatory measures.
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Page 7 of 11 ENCLOSURE-(CONTINUED)
BROWNS FERRY NUCLEAR PLANT CLOSURE OF REGULATORY PERFORMANCE IMPROVEMENT PROGRAM Long Term RPIP Action Items (Continued):
Item II-3.6, Programmatic Improvements (Continued) l i
closure: The security emergency power system was successfully tested (cont.). and the remaining security related actions are being finalized at the time of this submittal. The performance of the plant in the area of security was documented in the latest Systematic Assessment of Licensee Performance, Inspection Report 90-07, dated ;
June 14, 1990.
Programmatic improvements is the area of quality assurance.were discussed in Sections II.1.2.9 and II.2.2.6 of the NPP. The NRC Staff evaluated the conditions Adverse to Quality (CAQ) program and the quality assurance program in Sections 4.3.1.and 4.3.2 of d NUREG-1232, Volume 3, dated April. 14, 1989. The Safety Evaluation concluded that no issues involving the CAQ program needed to be resolved before restart of Unit 2 and the quality assurance . l~
program for the Browns Ferry Nuclear Plant was acceptable. The '
Crder'(EA 85-49)'regarding the CAQ-program was lifted by NRC !
Safety Evaluation, dated October 3, 1989. Involvement in the corrective action program was reviewed and documented in Inspect.on Report 90-20, dated August 13, 1990. _The Inspection- .i Report concluded that the CAQR program was. effective in the
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identification and resolution of problems in the previous one year! l period. j q
-Programmatic improvements is the area of. chemistry were discussed in Section II.6.2 of the NPP. The NRC Staff evaluated improvements to chemistry in Section 4.10 of NUREG-1232, Volume 3, dated April 14,1989. The NRC Staff concluded that the improvement measures were acceptable to support restart of BFN Unit 2. The performance of the plant in the area of chemistry was documented
( in.the latest Systematic Assessment of Licensee Performance, .
Inspection. Report-90-07, dated June 14, 1990.
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..' I Page 8 of 11 ENCLOSURE'(CONTINUED).
BROWNS: FERRY NUCLEAR ~ PLANT Cl.0SURE OF REGULATORY PERFORMANCE IMPROVEMENT PROGRAM i
l Long. Term RPIP Action items (Continued):
F Item II-3.6, Programmatic Improvements (Continued)-
- closure: Programmatic improvements is the area of fire protection were <
-(Cont.)- discussed in Section III.5 of the NPP. It was-concluded in Inspection Report 90-06, dated April 3, 1990, that Browns Ferry met the NRC's fire protection requirements.
P Programmatic improvements were made in the areas of radiological control, security, quality assurance, chemistry, and fire protection. . Justification for the closure of th3 RPIP action for each individual program has been provided.
Item,II-3.7, Plant Procedures Upgrade Action: Rework and~ upgrade plant procedures.= '
, closure The procedures upgrade activities were discussed in Section II.2.4 of the NPP. The NRC Scaff reviewed TVA's-programmatic approach
-and concluded in SECY-90-148, dated April 23, 1990, that the procedures upgrade program resulted in overall significant .
improvement'in procedures.
Item II-6.2, Streamline the Procurement Process Action Create a joint task force to study and recommend corrective I actions for the procurement process. ,
' Closures. A broad scope of activities have been taken to improve the procurement _ process. This RPIP action item was tracked by Inspector Follow-up Item 86-04-02, Implementation of. Corrective "
Actions to Resolve Procurement Problems. Corrective actions were reviewed, found to be satisfactory, and the item was closed in i Inspection Report 87-04, May 12, 1987. In addition, TVA har j undertaken an extensive program to review and evaluate pa ad present procurements of replacement items. The NRC Staff viewed TVA's programmatic approach and concluded in SECY-90-148, dated L- April 23, 1990, that the approach was acceptable.
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ENCLOSURE-(CONTINUED) .
BROWNS FERRY NUCLEAR: PLANT :
CLOSUllE OF REGULATORY PERFORMANCE IMPROVEMENT PROGRAM j Long Term RPIP Action items (Continued):
- Item.II-9.1, Review of Control Room Activities Actions. Assign a trained individual to conduct daily reviews of control room and other.operationcl activities.
- Closure This RPIP item was closed in Inspection Report 88-31, dated E October 24, 1988. The Inspection Report stated that metsures to i monitor and improve control room activities (including logging practices) were implemented and performed on a routine basis.
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Item II-9.2, Valve. Status Alignment
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Action: Develop routine verification of the physical status of abnormal
-valves.
Closures This-PPIP ltem was closed in. Inspection Report 88-31, dated October 24, 1988. The Inspection Report stated that the commitment for issuance and implementation of a revised procedure' ,
dealing with valve alignment controls and valve position H verification was reviewed.
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Item II-9.3,LSecond Party-Verification Program -I I
Action: Develop procedures consistent with.INPO and NRC positions on- l second-party verification. I i Closure: This RPIP item was closed in Inspection Report 88-31, dated October 24, 1988.- The Inspection Report stated that the procedure .I on second party (or independent) verification incorporated the l INPO and NRC positions.
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ENCLOSURE (CONTINUED)
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BROWNS FERRY NUCLEAR PLANT 1 CLOSURE OF-REGULATORY-PERFORMANCE-IMPROVEMENT PROGRAM <
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Long Term RPIP Action items (Continued):.
Item II-9.6, Contractor Recommendation on NSSS l
Action: Utilize an outside contractor (General Electric) to evaluate NSSS -l operation. This includes normal operation, surveillance-procedures, and shift activities, t
Closure: The GenerEl Electric (GE) recommendations-were discussed in' )
Appendix B of the NPP. The TVA disposition of the GE recommendations was reviewed by th'e NRC staff as documented in Inspection Report 89-16, dated March 9, 1990. The report states-that in general, the team found that the commitment made in the NPP to disposition the contractor recommendations was satisfied.
Item II-9.7, Contractor Recommendations of Technical Specifications
-Action Utilize an'outside contractor (SAI Corporation) to perform an evaluation of Technical Specifications.
.1 LClosures This RPIP item was-closed in Intpection Report 88-31, dated !
October 24, 1988. The SAI Corporation recommendations and their disposition were discussed in Appendix B of the NPP. The Inspection Report stated.that. acceptability of TVA's work in this area was_ expected to be' addressed. separately.- Inspection ~ l Report 89-47, dated October 21,'1989 reviewed the. disposition of historical Technical Specifications problems. A final. pre-restart' Technical Specifications inspections is currently scheduled.
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-Item II-9.9, Contractor Recommendations on Administrative Management q Action: Reevaluate the 26 MAC recommendations on administrative' management.
Closure: This RPIP item;was closed in Inspection Report 88-31, dated-October 24, 1988. The MAC recommendations were reevaluated and incorporated into the NPP. The Inspection Report stated that the
-issue of administrative management would continued to be monitored separately as part of the overall monitoring of operation )
readiness for restart.
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BROWNS FERRY NUCLEAR PLANT-- e CLOSURE OF REGULATORY PERFORMANCE IMPROVEMENT-PROGRAM e . .
Other RPIP Acdion Itenis:
L In addition to the open items listed in Appendix A of.the NPP, discussions f with the Browns Ferry Resident Inspectors have indicated that two additional I ,
.long-term RPIP Items were being tracked by the NRC. These items and the basis for their closure is provided as follows:
a Item II-4.1, Interaction between Nuclear Engineering and the Plant Action: Provide for close and continuing interaction between EN DES'(now
/ titled Nuclear Engineering) and plant to resolve modification implementation questions and to establish priority and evaluation- '
D on nonconformance' items and failure evaluations.
Closure: .At this time, most Nuclear Engineering. activities are conducted ati >
the Browns Ferry site. The configuration management program '
involved a broad scope of activities and improvements for the l design and modification control process as discussed in. >
' Sections'III.2 of the NPP. The performance of the plant in the area of engineering and technical support is documented in the latest Systematic Assessment of Licensee Performance, Inspection ,
Report 90-07, dated June'14, 1990.- There was an increase in d management. involvement and: control of the onsite-engineering and modification groups. Improvements were made in accountability, responsiveness and' effectiveness of these groups. '
-: i Item II-7.0, Onsite Training Organization -
-t Action: Establish an onsite training organization under the supervision of the Training Branch ~with responsibility for all onsite training activities. Work toward INPO accreditation of BFN training programs.
i closures The onsite training organization was' established at the Browns
- Ferry Training and Visitors Center.- Browns Ferry's ten training programs-have been accredited by INPO. In addition, TVA is a memberlof-the National Academy for Nuclear Training.
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