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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 DEMONSTION SYSTEM DISTRIBUTION REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9002130135 DOC.DATE: 90/02/05 NOTARIZED: NO DOCKET FACIL:50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 AUTH. NAME AUTHOR AFFILIATION RAY,M.J. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
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SUBJECT:
Forwards plans for resolving concerns re potential pullby damage to electrical cable at facility.
DISTRIBUTION CODE: D030D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: TVA Facilities Routine Correspondence 3
NOTES:1 Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw, 05000260 R.Pierson,B.Wilson /
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INTERNAL: ACRS 1 1 NUDOCS-ABSTRACT 1 1 QC/J 1 0 OGC/HDS2 1 0 EG FILE 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTES 5 5 D
A D
D NOTE TO ALL "RIDS" RECIPIENTS:
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place FEB 05 590 UPS. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 Gentlemen:
In the Matter of ) Docket No. 50-260 Tennessee Valley Authority )
BROHNS FERRY NUCLEAR PLANT (BFN) RESOLUTION OF CABLE INSTALLATION CONCERNS (TAC NO. 62260)
References:
- 1. Letter from R. L. Gridley to NRC dated July 18, 1988, "Browns Ferry Nuclear Plant Resolution of Cable Installation Issues"
- 2. Letter from R. L. Gridley to NRC dated September 29, 1988, "Browns ferry Nuclar Plant Resolution of Cable Installation Issues Cable Testing
- 3. Letter from M. J. Ray to NRC dated July 1.9,. 1989,. "Browns.
Ferry Nuclear Plant Electrical Cable Installation - Revised Halkdown and Summary Reports The purpose of this letter is to transmit a plan for resolving concerns related to potential pullby damage to electrical cable at BFN. The plan defined in Enclosure 1 supplements previous submittals on this issue.
Cable installation concerns at TVA initially stemmed from reviews performed at Hatts Bar Nuclear Plant (HBN) and included a variety of issues (sidewall bearing pressure, jamming, inadequate support of cables in long vertical runs, pulling through 90 degree condulets and mid-run flex conduits, bend radius, and pullbys). Though there was no evidence at that time to indicate that damage actually existed, each plant has undertaken programs of analysis, inspection, and testing to confirm the integrity of its cable systems.
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At BFN, this effort, included extensive walkdowns, calculation, analysis, review of existing plant documentation, and in-situ high-potential dielectric withstand testings These reviews, which considered the successful test program at Sequoyah Nuclear Plant, provided a comparative analysis to SQNs installations, materials, and procedures. The results of those reviews were documented in References 1, 2, and 3 and established a high degree of confidence in the installed cahle systems at BFN.
Subsequent to the completion of those reviews and to the submittal of the above documentation, damage to ca" les at HBN was discovered. Analysis of the damage indicated it was because o" c.ab1e pullbys.
9002130i35 900205 05000260 PDR ADDCK P PDC An Equal Opportunity EmpIoyer
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FEB 05 1990 U.S. Nuclear Regulatory Commission Even though no pullby damage was identified at BFN during recent inspections performed as a part of the cable issues review, additional engineering evaluations are being performed to ensure that such damage has not occurred.
This effort will include further analysis of installed conduits and cables at BFN and a program of high-potential testing of cables which may have experienced sidewall bearing pressures during the pullby process. Successful completion of the program as outlined in the enclosure will resolve this issue for BFN and validate the conclusions previously drawn in the referenced reports. contains the commitment contained in this submittal. If you have any questions, please telephone Patrick Carier, BFN, at 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY Manager, Nucl ar Licensing and Regulatory Affairs Enclosures 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. Hilson, 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
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ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT CABLE PULLBYS
1.0 BACKGROUND
1.1 Initial Review During the summer of 1986, the U.S. Nuclear Regulatory Commission (NRC) began a review of concerns related to the adequacy of construction practices at the Tennessee Valley Authority's (TVA) Watts Bar Nuclear Plant (WBN). The review identified concerns for potential damage to electrical cables due to alleged improper or inadequate installation practices. Since TVA's Sequoyah (SQN) and WBN plants are based on the same overall design, the NRC extended the evaluation of the cable installation concerns to the SQN plant.
As a result, TVA performed an extensive and comprehensive evaluation of the SQN issues identified in NRC's Technical Evaluation Report (TER-C5506-649) as requiring implementation prior to that plant's restart. That effort resulted in the successful resolution of'able installation issues at SQN and demonstrated that adequate cable installation practices were used.
As a part of the normal process of generic review of Condition Adverse to Quality Reports (CAQRs), TVA initiated an indepth review .to evaluate the applicability of these same concerns to Browns Ferry Nuclear Plant (BFN).
The BFN evaluation consisted of the following;
'Com arisen to ~industr Dractices: Determine if the BFN cable installation practices and procedures were consistent with those used in the industry during the time period of BFN's construction.
- Plant walkdowns: Perform plant walkdowns to review specific practices and assess the overall quality of the cable installation.
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BFN 1ti: 'I were enveloped H
i by the th SQN tt cable hih issue resolution program.
- Review of test data: Evaluate BFN test documentation to confirm the adequacy of the cables and to assess BFN's failure rate as a measure of the quality of the installation process.
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Enclosure 1 Page 2 The review team noted the existence of various physical evidence and plant documentation which established increased confidence in the acceptability of the BFN cable installation process. The findings, which were described in detail in the Cable Installation Issues Reports (References 1, 2 and 3), are briefly summarized, as follows;
- No evidence was found to indicate that braided ~ull ro es had been used at BFN. In lieu of ropes, which had been noted at HBN during the review for the TER, only insulated pull wires were observed.
Subsequent to the task group review under discussion, interviews were conducted with several electricians who have worked at BFN for
't over a decade. These personnel were aware of the dangers of using abrasive cord during a pullby and indicated that such materials were not used at BFN. The insulated pull wires (typically PVC jacketed) have a much lower coefficient of friction and present a much lower
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Since pull forces vary exponentially with the degrees of bends between pull points, this factor was judged to reflect good workmanship as well as greatly increasing the potential for 1 t d.
successful pullbys.
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~ullb s had been made versus where no ~ullb occurred. This is 1
indicative of good craft practice. Current industry recommendations for performing pulibys have identified liberal lubrication as one of the most important factors in achieving a successful installation (ref; Committee Report Recommended Practice on Specific Aspects of Cable Installation in Power Generating Stations, IEEE / Insulated Conductors Committee, Task Force 14-1).
- Due to the ~h sical ~la out of the plant conduit runs are ~relativel short. In particular, the compact nature of the Hark I containment structure and the fact that the various board rooms are in- set into the reactor building minimizes the footage required to reach load devices. Since SNBP is directly proportional to length, pullbys in shorter conduits present less of a risk to the cables.
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of documentation indicated that the installation process was stems.
~it Documentation of both post- installation t'nstalled and maintenance high-potential testing of medium voltage cables indicated the presence of quality craftsmanship during initial installation. This was further borne out by BFN's low cable failure rate compared to industry norms (reference 2).
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Enclosure 1 Page 3
- ~Flnall the 10CFR50.49 cables located in the three worst case environmental areas of the Riant ~are bein ~re laced this o~uta e for environmental considerations. As a result, that group, which has the highest risk of failure should any damage have occurred, will be known to have been installed according to the latest criteria and constructed with state of the art materials.
The review team identified two areas in which cable integrity required further verification prior to plant restart. These consisted of excess unsupported vertical drop and inadequate bend radius, both as applied to medium voltage (5000 vac) cable'. As a result, a program of testing was undertaken to identify any existing degradation and provide a measure of confidence for further operation of those circuits. All 20 cables were successfully high-potential tested during 1989 at IEEE 400 maintenance levels.
In summary, a review team of engineers and consultants with a broad base of industry experience concluded that BFN compared favorably both with SQN and with other (non-TVA) plants of its vintage in both design and construction for each of the issues identified in the SQN TER.
Subsequent reviews have shown that certain practices, believed to be contributors to the potential for pullby damage were not present at BFN.
In particular, BFN conduit systems are not subject to frequent overfill conditions. When allowable fills are exceeded, the difficulty of obtaining a clear path is greater, thereby increasing the risk during the pullby. In addition, a review of BFN records indicates that bulk, rather than system pulling (which results in frequent pullbys), was the general practice. This is consistent with current industry good practice.
1.2 WBN Findings and BFN Response In July 1989, work was performed to resolve an employee concern related to potential heat damage to cables as the result of alleged improper welding activities on conduits at WBN. Installation damage was discovered to a total of five cables in three segments comprising a single run of conduit. Subsequent visual and laboratory evaluation confirmed the damage was caused by a pullby. An additional 33,500 feet of cable were removed to assess the scope of that damage. One additional instance of damage was noted. Analysis of the raceway systems showed a correlation between the calculated installation forces and the occurrence of damage.
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Enclosure 1 Page 4 Though the issue of pullbys had been extensively reviewed at BFN during the process described above, these findings were deemed to be of sufficient magnitude to warrant reanalysis. As a result of the above mentioned correlation of high forces to installation damage, TVA decided to invoke a screening process and perform pulling force calculations to more rigorously identify i'ts worst case pullbys. That ranking process is described in section 2.0. Once the worst case pullbys are identified, high-potential withstand testing will be conducted as outlined in section 3.0. During TVA presentations to the Staff in both December 1989 and in January of 1990, TVA indicated that three condui ts had already been identified for testing. Since TVA cannot be certain at this point in time that these conduits will be in the final worst case group, the expense and difficulty of testing these 50 cables / 210 conductors (approximate) is not warranted. Therefore, no further special action will be taken .on these three condui ts. Only those condui ts which are part of the final group described in section 2.0 will be tested.
2.0 SELECTION CRITERIA The population of conduits containing safety related circuits at BFN in which the potential exists for cable pullbys to have occurred is, being identified and screened using the criteria outlined below. Nithin 'this bounded population, a further screening will be performed of the top 30 to define and identify a group of 10 'worst'i.e. highest pullby damage potential) conduits. For the purposes of this evaluation that group is defined as those conduits meeting the following criteria; 2.1 Using non-QA databases taken from the Unit 1 and 2 cable and conduit schedules and the Unit 3 cable routing program, sorts were performed to identify those Vl-V4 safety related conduits containing more than one cable number. This population (approximately 1330 conduits) defines the group in which potential pullby operations have occurred.
2.2 This subpopulation was further reviewed to identify those conduits in voltage levels 1 through 3 which contain 8 or more cable numbers and those conduits in voltage level 4 which contain at least 4 cable numbers.,
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Enclosure 1 Page 5 2.3 Since conduits are field routed at BFN and the conduit and cable database does not include conduit lengths, these were estimated by scaling from design drawings. Conduits which were not at least 20 feet in length were eliminated from further consideration. This screening yielded a subgroup of approximately 120 conduits.
2.4 The remaining conduits will initially be ranked using the following formula:
(L*F)/R = ranking factor where:
L = conduit length as determined above F = conduit fill per the referenced database R = conduit bend radius per TVA standards This equation reflects the formulas for determining sidewall bearing
'pressure (SNBP) during pulling and includes several of the key parameters for consideration during a pullby.
Pull tension and SNBP increase directly with length. The potential for complex conduit geometry also increases with increasing conduit length.
For example, the likelihood of finding a high number of degrees of bends between pull points is greater for a 150 foot long conduit than for a 30 foot run.
By virtue of similar reasoning, the industry has recognized that the severity of a pullby goes up with fill due to the increasing difficulty of obtaining a clear path for the pullby cables (ref; IEEE/ICC Task Force 14-1 Report). For instance, a pullby into a conduit which results in a final fill of 10 to 15 percent may not have actually resulted in cable-to-cable interaction. This results from the pre-pullby conduit being relatively empty such that the new cables may have ridden directly on the conduit wall. In a conduit where the final fill is high, the reverse is true. Therefore, with a high degree of certainty it can be concluded that cable- to-cable interaction did occur. Additionally, since the severity of any given pullby is a function of its size, this factor will give preference to conduits with high fill and therefore, the potential for large pullbys. As an example, conduits which are lightly filled (i.e. or 2 cables) ca'nnot have exp'erienced large pullbys whereas 1
conduits which are highly filled (many cables) have a greater potential for having experienced large (5,6,7 . . . cables etc.) pullbys.
Finally, since SNBP is inversely proportional to the radius of bend of its conduit, the ranking will assume that each segment contains bends formed to the minimum radius allowed by TVA and industry standards.
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Enclosure 1 Page 6 The combination of these factors will permit quick and efficient determination of a family of conduit runs which contain the potential for significant pullbys to have occurred. As is described in section 2.6, that larger family will then be screened using a more rigorous methodology.
2.5 A review of this grouping will then be performed, to identify the top 30 conduits in which a pullby has occurred. This review will be performed using existing cable pullslip data and/or change package information.
2.6 The top 30 conduits identified in step 2.5 will then be walked down.
Sketches of each conduit will be prepared to identify all intermediate pull points, the length between bends and the degrees of each bend.
2.7 Detailed calculations will be performed to conservatively estimate the maximum SNBP -that would have been encountered during 'the largest pullby in each conduit. This analysis will be based on the configuration data taken in step 2.6 and utilize standard industry methodologies and formulas for the determination of expected pull tension and expected SNBP derived from the fundamental laws of physics. The calculations performed by TVA utilize variations of the following basic equations; T = L*N'K*EXP(K*A) and SNBP = T/R where:
T = pulling tension in pounds SNBP = sidewall bearing pressure in pounds per foot L = conduit length preceding a bend in feet N = weight per foot of the cables being pulled in pounds K = basic coefficient of friction A = angle of the bend in radians R = conduit bend radius in feet Such calculations by their very nature are approximations of the anticipated forces, yet represent best industry practice for their determination. Typical TVA and industry practice involves only the calculation of the maximum allowable forces and a determination that such allowables were not exceeded without a direct concern for degree of conservatism.
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Enclosure 1 Page 7 2.8 The top 30 conduits from step 2.5 will be reranked according to SNBP.
Since cables of differing construction and SNBP limitations may be involved, the ranking will be based on the percentage of allowable SNBP rather than magnitude of the calculated SNBP.
NOTE: The screening process described in paragraph 2.4 does not include direct consideration for raceway configuration since this can only be known as the result of field walkdowns. Therefore, following completion of the detailed calculation and reranking process, the methodologies will be reviewed to confirm that the screening process has produced viable results. If acceptable correlation exists between the screening process and the detailed calculation, TVA will review the above comparison and results with the NRC prior to proceeding with step 2.9. If such correlation does not exist, the conduits (approximately 120) which remained fol.lowing step 2.3 will be reviewed to identify those in which pullbys have occurred. Those conduits will be walked down in accordance with step 2.6, calculations performed per step 2.7 and the total group will be reranked per step 2.8.
2.9 Cables in the top ten conduits identified by this process will be, subjected to high-potential testing as described in section 3.0. TVA anticipates the ten conduits will contain 100-200 cables comprising 400-700 conductors. Successful tests will confirm that the forces experienced during pullbys have not resulted in the systematic degradation of BFN's cable systems.
Implementation of the above screening and ranking process will be documented in a calculation.
3.0 CABLE TEST PROGRAM CRITERIA The predominant concerns during pullbys are for saw-through and mashing of the jacket and insulation. The postulated failure mechanism is the degradation of dielectric properties resulting from a reduction in insulation wall thickness and possible exposure of the copper conductors. The following test program is specifically designed to identify if such a condition exists.
3.1 Cables will be subjected to a high potential withstand test at 2',0 volts DC per mil (vpm) of insulation. The insulation thickness to be used in this determination shall be the minimum qualified thickness as established by a review of TVA and vendor documentation. Two additional criteria wi 11 be applied in assessing the appropriate voltage levels as a result of a review of specific cable constructions. First, the test voltage shall be limited to a maximum of 7200 volts DC. Of particular concern to TVA would be the application of as much as 15,000 volts to
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Enclosure 1 Page 8 certain coaxial cable constructions if the 240 vpm multiplier were directly applied. These cables are over-insulated to obtain the desired impedance characteristics and typically operate in the millivolt range.
Second, the test voltage shall not be allowed to exceed 801. of the industry standard values for factory testings Review of specific cable types (small gauge signal) has shown that 240 vpm would result in a field test above that required for new cable at the factory.
TVA will notify the NRC before testing any cables at levels other than those determined by the 240 vpm multiplier.
3.2 The test shall be 5 minutes in duration.
3.3 The voltage will be applied conductor-to-ground between the conductor under test and its conduit with the conduit, all other conductors, shields and drain wires tied together and tied to ground.
3.4 The tests will be performe~ after injecting ordinary tap water into the conduit segment in which the high SNBP occurred. Those segments to be tested will be reviewed on a case-by-case bas'is to determine the feasibility of introducing water, into, and removing it from, the conduit system without compromising equipment integrity or personnel safety.
TVA will notify the NRC of any instances where water cannot be introduced and the rationale for its exclusion will be documented.
The purpose of the introduction of water is to ensure, as a minimum, that moisture is present along the entire surface of the installed cables in that segment.
3.5 Leakage currents will be recorded at 1 minute intervals at the specified test voltage.
3.6 The cables must pass the in-conduit DC high-voltage test. The acceptance criteria (from ANSI/IEEE 141- 1986 section 11.11.4) is that a polarization index of 1.0 or greater must be demonstrated. The polarization index is the ratio of the current after minute to the 1
current after 5 minutes at the specified test magnitude. Any conductor with a polarization index of less than 1.0 wi 11 be considered a failure unless it can be demonstrated, by engineering evaluation or by retest, that the conductor is acceptable.
If the cables fail the high-voltage test, the NRC will be notified.
Enclosure 1 Page 9 The location of the failure shall be determined and the faulted section electrically isolated. The tests will be repeated. If the cause of the failure is subsequently determined to be non-pullby related and the cables successfully withstand the retest, then the test shall be considered successful in demonstrating adequate pullby practices. TVA will take the necessary actions to identify and bound any problems which are identified during the performance of the tests.
4.0 Conclusion No pullby damage has been identified at BFN. BFN is performing a study consisting of engineering analysis and high potential testing.
Successful testing of the cables in the 10 conduits identified by the selection criteria will ensure that BFN Unit 2 cables which have experienced a pullby are acceptable for service and further validate the conclusions previously drawn by the Cable Installation Issues Report.
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ENCLOSURE 2 COMMITMENT TVA will submit the results of BFN's study to validate that excessive sidewall bearing pressure was not incurred during cable installation involving pullby, which could result in cable damage.
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