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MONTHYEARML20212M1001987-01-20020 January 1987 Forwards Listings of Operations Category Employee Concern Element Repts W/Examples of NRC Problems.Repts Should Be Reviewed & Appropriately Modified Project stage: Other ML20212L2551987-01-21021 January 1987 Forwards Summary of Staff Concerns Identified for Five Element Repts in Engineering Category of Employee Concerns. Repts Constitute Sample of Approx 10 Repts Received Prior to Jan 1987.Repts Should Be Reviewed & Modified Project stage: Other IR 05000327/19870341987-06-0909 June 1987 Insp Repts 50-327/87-34 & 50-328/87-34 on 870518-22.Major Areas Inspected:Radiological Effluents,Chemistry, Confirmatory Measurements,Environ Programs & Open Items for Closeout Project stage: Request ML20236K8301987-07-31031 July 1987 Advises That Nuclear safety-related Criteria of Employee Concern Special Program (Ecsp) Acceptable.Nrc Evaluations on Implementation of Criteria to Exclude Submittal of Element Repts Will Be Issued Soon Project stage: Other ML20237J9991987-08-24024 August 1987 Safety Evaluation Re Industrial Safety Category of Special Employee Concern Program for Plant Based on 870203 Audit of Case Files & Repts.Employee Concerns Adequately Addressed. Minor Changes Recommended in Case Files Project stage: Approval ML20237J9941987-08-24024 August 1987 Forwards Safety Evaluation for Industrial Safety Category of Special Employee Concern Program for Plant Based on 870203 Audit of Case Files & Repts.Employee Concerns for Category Adequately Addressed.Minor Changes in Files Recommended Project stage: Approval ML20237L3441987-08-27027 August 1987 Forwards Technical Evaluation Rept TER-C5506-623, Evaluation of Nuclear Safety Review Staff Concerns Requiring Resolution Before & After Restart. List of Nuclear Safety Review Staff Recommendations Acceptable Project stage: Other ML20235S9251987-10-0606 October 1987 Forwards Safety Evaluation for Util Employee Concern Special Program (Ecsp),Including 850715-870203 Insps.Ecsp Contains Acceptable Procedures & Guidelines to Evaluate & Provide Corrective Actions for Concerns Raised Prior to 860201 Project stage: Approval ML20206G0341988-11-0404 November 1988 Forwards SERs Re TVA Employee Concerns Element Repts as Part of Employee Concerns Special Program.Tva Sufficiently Resolved Restart Employee Concerns to Support Restart of Unit 1 Project stage: Approval ML20067A8591991-02-0505 February 1991 Forwards Documentation Re Deviation from Corrective Action Plan for Corrective Action Tracking Document Catd 20406-BFN-01 on Nuclear Performance Plan Project stage: Other 1987-07-31
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
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1emnuee Valey A#mts 1101 Market S9eM Chowog lemetsee 3702 FEB 051991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 t
Centlement In the Matter of ) Docket Nos. 50-259 !
Tennesree Valley Authority ) 50-260 50-296 /
p BROWNS FERRY (BFN) SAFETY EVALUATION REPORT (SER) - MAY 31, 1990, SAFETY EVALUATIONS ON THE TENNESSEE VALLEY AUTHORITY EMPLOYEE CONCERNS SUBCATEGORY REPORTS - BFN, UNITS 1, 2, AND 3 -- DOCUMENTATION RELATIVE TO CORRECTIVE ACTION PLAN (CAP) DEVIATION TO CORRECTIVE ACTION TRACKING DOCUMENT (CATD) 20406-BFN-OL The purpose of this letter is to provide NRC the ( aentation relative tc a deviation to the CAP for SFN CATD ;9406-BFN-01. This CATD is a part of the Employee Concerns Task Group (ECTG) report 20400, "Er;ineering Organization and Operating Procedures."
The May 31, 1990, BFN SER included evaluations against ECTG report 20400, and the evaluations were based on the originally-approved CAPS for BFN CATDs written under ECTG report 20400.
Enclosed is TVA's submittal correspondence relative to a Level II CAP deviation to CATD 20406-BFN-OL. The proposed Level II deviation to the CATD was approved in accordance with TVA Nuclear Power Standard 1.4.2. ,
" Resolution and Closure of Employee Concerns Special Program Cortective Action Tracking Documents," (NP-STD-1.4.2). The responsible BFN line organization was notified of approval of the CAP deviation to CATD 20406-BFN-01 on January 17, 1991.
TVA has not committed in NP STD-1.4.2 to routinely notify the NRC
- concerning the approval of Level II CAP deviations to CATDs except through the issuance of an annual report. However, since the subject BFN SER addressed ECTG 20400, the CAP deviation to CATD 20406-BFN-01 is being forwarded for your information in response to a telephone request by Paul Cc-tland of NRC.
9102080002 910205 PDR ADOCK 05000259
', h00! {
b- P PDR
- /[f c . .. .
,2 FEB 051991 U.S. Nuclear Regulatory Comission If you have any questions, please telephone T. L. Pitts of niy staf f at (615) 751-8087.
Very truly yours,-
TENNESSEE VALLEY AUTHORITY (bd .
TM %
E. G. I'y1 ace , nagj Nuclear Licensing an Regulatory Affairs Enclosure cc (Enclosure):~
Ms. S. C. Black, Deputy Director Project Directorate II - U.S. : Nuclear Regulatory Comission One White Flint, North 11555 Rockville Pike
-Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-200.)
-Mr. Paul Cortland NRC Special Projects One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
. Mr.'Fredrick J. Hebdon NRC Special Projects One White Flint North 11555 Rockville Pike Rockville, Maryland.20852 Mr. Thierry M. Ross, Project Manager U.S. Nuclear.Regalatory Commission One-Write Flint, North 11555 Rockville Pike Rockville,. Maryland 20852 Mr. B. A. Wilson, Project dialef U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Ceorgia 30323
C \
.- , _,m m e,~
QA Record B22 '90120 6 006 UNITCD STATES GOVERNMENT
. Memorandum TENNESSEE VALLEY AUTHORITY L. C. Ellis, Manager, Employee Concerns Special Program /Closcout TO :
Team, esf1TX;U FROM : J. R. Rupert, Project Engineer, Browns Ferry Engineering Project.
Nuclear Engineering, EDB 1A-BFN DATE :
DEC 0 61990
SUBJECT:
BROWNS FERRY NUCLEAR PIANT (BFN) - CORRECTIVE ACTION TRACKING DOCUMENT (CATD) 20406-BFN-01
References:
- 1. Memorandum f rom J. D. Hutson to S. H. Rudge dated May 14, 1990 (B22 900514 001)
- 2. Your memorandum to S. H. Rudge dated July 23, 1990 (W35 900720 800)
The purpose of this memorandum is to provide an amended corrective action plan (CAP) for the subject CATD. Reference 1 submitted a deviation to the originni CAP for review and approval by the Senior Management Review Group (SMRG). The deviation read as follows:
20406-B A 1 - Design Control Improvements ,
Inc CAP states that the requirements of Nuclear Engineering 7 Procedure (NEP) 6.3 and 6.4, which generally implement the Plant Modification Package (PMP) concept, will be implemented by Browns Ferry Engineecing Project (BFEP) Project Instruction (FI) 86-03.
The change con, trol procedure which was actually developed and is cutrently in use is described in BFEP PI 89-06. This procedure does not utilize the PMP~ concept given in NEP 6.3 and 6.4 but when combined with Site Director Standard Practices 8.10 and 8.11 accomplishes the overall controls in a m .a casily implemented manner.
The PMP concept was implemented at SQN and through that experience it was determined to be to cumbersome to allow timely accomplishment of plant modifications. The process described in BFEP PI 89-06 incorporates experience gained from the SQN restart effort and BFN site review and closure processes and is equivalent to the process of NEP 6.3 and NEP 6.4 in the degree of design and configuration control that is imposed.
At the request of the Nuclear Quality Assurance, as stated in reference 2, we are adding the f ollowing statement to the CAP deviation.
The Nuclear Performance Plan has been revised to read "TVA's permanent design control system will further develop the plant modification package concept."
l This statement added after the last rer. ten e in paragraph one of the deviation above provides the basis fo. implementing the design change control process described in BFEP PI 89-06 which enhanced the PMP concept.
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L. C. Ellis DEC 0 61990 BROWNS FERRY NUCLEAR PLANT (BFN) - CORRECTIVE ACTION TRACKING DOCUMENT ,
(CATD) 20406-BFN-01 To preclude the processing of this minor change to the CAP deviation from Boing through the complete SMRG review process again, I am requesting you provide this addition to NQA to provide evidence that -
the comment has been incorporated. This should expedite the process to allow BFN to submit the.CATD package for closure review.
If further assistance is' needed, contact J. L. Walton at extension 5063.
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I ECTG Corrective Action Trackinr, DocItment
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INITIATION fpplienblo ECTG Report No.: 204 0(o(cj
- 1. Immediato Corrective Action Required: O fos G No
- 2. Stop Vork Recommended: 0 Yo's fG No
- 3. CATD No.,_2_oM o G, "bFN ot 4. INITIATION..DATE 5- 8_ - 87
- 5. RESPONSIBLE-ORGANIZATION: 'DNE PEN
- 6. PROBLEN DESCRIPTION: C0 QR O NQR C m.co r u, a m moc e m co m m % m we WN PP A nt w,n W. ?-
_n mr evmW -
O 3TE- 52. Erwe w or ECNs Tsyed 'sme t ' OL (BFEp ~PI . 86 19 2o) 3 O ~Iff- VI REwEW or LOjs r5*,u'ib SWC E OL (PEEP *iT- Bfo
O IE. - 69 Imrumecer NEPI~(.'~f ( ft1f' fk csoontl O ATTACHMENTS -
- 7. PREPARED BY: -NAME .Sw bb f4W . 94c/ DATE: 5 8 -87 -
- 8. CONCURRENCE: CEG-H D~a k & &~
DATE: s-is k ? '
- 9. APPROVAL: ECIG PROGRAM MGM.Mre Trs oxV~--. _,DATE: 3 M .
ORRECTIVE ACTION jyjw(( 10. PROPOSED wkEELTIVE ACIION PLAR: _. __
Attachment A)
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/t - / ,/ E3 ATrACHMENTS
- 11. PROPOSED BY:
DIRECT Bn/4 L DATE: 1-2 D / 7_
__ D 0PgMGR:rv.[////iL W M M - ' '~'
- 12. CONCURRENCE: CEG-H: e DATE: 7 3c ibi __
. , :. . _ ECIG PROGPA KANAGER () /lk,v/4 /m DATE: 6///v/7
, VERIFICATION AND CLOSE00T .
IL Approved corrective actions have boon verified as satisf actorily implomonted.
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) SIGNATURE TITLE DATE.
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CAPP 1.0 REV. 1 ATTACIDiENT A CATD NO. 20406-BFli-01
- 10. PROPOSED CORRECTIVE ACTION PLAN:
The pin,n,1t modification packnne (PMP) proceso has been in pince nE PFN since the implementntion of BFEP PI 86-03 on 6-16-87. t(EP 6.3 and 17EP 6.4 will provide furthet* desinn channo control improvements by in,1 enentiny,,
t the PMP deco. loped Jn _ BPEP PI 86-03 vith improved methods of documentinn, nominircentinn, uno controllinn den 8.nn channen nnd implementinn these as corpornte vide procedure,1,,, ,
UEP 6.3 and '.TEP 6.4 will be issued by September 1987 and impicmented by December 31. 1987. BFEP PI 86-03 will then be revised to reference ITEP 6.3-and NEP 6.4. III-52 and III-57 nre Volume 3. IIPP commitments , and are trackco_.
as such by BFEP ONP. corporate DNE and the.NRC. Those items listed as unit I
restart items will be completed prior to unit restart. The review of ECNs issued since the nenntint of the OL nre beinn performed by the Desi'.n Baseline and Verification Progenm (DB&VP) in accordance with BFEP PI 86-14 R1, PI 86-20 RI. PI 86-21 RO. and PI 87-24 R1. The schedule for evnluntion of ECNs not required for, safe shutdown systems will be determined af ter restnet.
Does the corrective action plaa ecly on or take credit for currently identi.fied or previously completed work? Yes X No if yes, list parent documents (e.g. MCR, SCR, CAR, Audit, etc.)
BFFP PI 86-03. NEP 6.3 NEP 6.4 and the DB&VP ,
Does the problem described constitute a condition adverse to quality (CAQ)?
Yes No X No CA(s are known. Any identified by DB&VP will be documented at the time of discovery.
If Yes, CAQ No.
Schedule for completion of corrective action (schedulo date, if known, or milestone (e.g. BEL 1, etc.) See schedule above /
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ie-lkJ 87 Prepared bylDato Pr/
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