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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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I Tenrem Vahey AoP% IV.t Cha hm MG Dewsr. Alaten ME 2E MAR 171993 O J W Zeongue' i Wre P:mmm; tw;mt f or'y %ciew hunt U.S. Nuclear Regulatory Commission '
ATTN: Document Control Desk Washington, D.C. 20555 :
Centlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PIANT (BFN) - MEDIUM VOLTAGE CABLE BEND RADIUS ISSUES -
References:
- 1. Letter from TVA to NRC dated October 4, 1990, Revision to the Cable Installation Issues-Supplemental Report - Cable Pullby
- 2. NUREG-1232, Volume 3, Supplement 2 -' Safety Evaluation Report on Tennessee Valley Authority: ,
Browns Ferry Nuclear Performance Plan, January . i 1991
- 3. Letter from TVA to NRC dated May 10, 1991, Action Plan to Disposition Concerns Related to Units 1 and 3 Cable Installation Issues Including Cable ;
Separations
- 4. Letter from NRC to TVA dated April 8, 1992, Safety Evaluation of TVA Plans to Resolve 't Electrical Cable Installation and Separation Issues for the-Browns Ferry Nuclear Plant Units 1
This letter provides additional information regarding the resolution of 1 medium voltage electrical cable bend radius issues. The basic issue is that electrical cables can experience premature degradation of the '
insulation system if they are bent to an excessively tight radius. TVA's bend radius corrective action program was developed to ensure that i improper bends in safety-related electrical cables do not affect safe plant operations. The corrective actions for Unit 2 for the bend radius program were described in Reference 1. The NRC reviewed these corrective ,
actions and issued a Safety Evaluation on them in Reference 2. The ,
corrective actions for Units 1 and 3 were described in Reference 3. A' Safety Evaluation of the Units 1 and 3 corrective actions was also issued ,
(Reference 4). TVA subsequently determined that some of the corrective actions should be nodified. Enclosure 1 describes the program changes and ;
the basis for making the changes. Enclosure 2 summarizes the commitments ,
associated' with the program efianges. l e
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, l 93o32202TClMo259' ppg ADO -
PDR w - 1-
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'U.S. Nuclear Regulatory Commission !
l ttAR 171993 !
Based on these changes in the corrective actions. TVA requests NRC issue a '
supplement to NUREC-1232 Supplement 2, Section 3.11.5. TVA also requests a change to the April 8, 1992, Safety Evalus. tion for Units 1 and 3 to-accept the revised Group 2 cable testing plan. ,
Please refer any questions to G. D. Pierce Interim Manager of Site I Licensing, at (205) 729-7566.
Sincerely, ,
lOsJ.'Zeringue
,f 'I I bb I
i Enclosures !
cc (Enclosures): l' NRC Resident Inspector '
Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 ,
Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike '
Rockville, Maryland 20852 !
Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II
.101 Marietta Street, NW, Suite 2900 Atlanta, Georgic 30323 i
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ENCLO3URE 1 'l BROWNS FERRY CABLE BEND RADIUS CORRECTIVE ACTION FIRI CIULNCES I. BACKCROUND
- 1. Original action plan ;
The Cable Issues Supplemental Report, Corrective Actions, ,
Revision 3 was provided as an enclosure to Reference 1. '
t In the report, TVA proposed an action plan to resolve the medium voltage bend radius issue for Unit 2. The NRC staff reviewed this plan and concluded that it was acceptable as documented in Reference 2. A similar plan ,
was issued for Units 1 and 3. Reference 3 contains the plan for Units 1 and 3 and Reference 4 contains a Safety Evaluation of the plan for Units 1 and 3. The action plans classified cables according to bend radius ratio (the ratio of bend radius to cable diameter). The cables were to be classified into Groups 1, 2 and_3; Croup 1 having the smallest bend radius ratio. ;
- 2. Original disposition of Group 1 cables required to support Unit 2.
The action plan for Unit 2 identified 58 cables subject to medium voltage cable bend radius review.
Of the original 58 cables, there were 869 cable bends. !
Sixteen of the original cables were determined to have i cable bends that had a radius less than 6 times the cable ,
diameter. These 16 were classified as Group 1 cables. '
Five of these cables were slated for replacement during the Unit 2 cycle G outage. l
- 3. Original Croup 2 cables testing plan. -,
The corrective action plan for all units required that high potential testing be used to verify that the affected cables were capable of maintaining the interfacial integrity of the shielding system. The 15 ,
worst case cables were to be tested to ensure adequacy for restart of the affected units. All Croup 2 cables ;
would be tested and trended during subsequent outages to facilitate a trend analysis. Final dispositions of Group 2 cables were dependant-on the outcome of the trending information, Group 3 cables would be subject to normal maintenance testing.
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l Page 2 ENCLOSURE 1 (Continued)
II. ADDITIONAL INFORMATION
- 1. Another cable was added to the bend radius review list for Unit 2 due to a design change that reclassified a non '
safety cable to Class 1E status. The design change required that alternate board feeders to Class 1E applications meet Class IE requirements. The cable, PP434-1E, is to be replaced during the Unit 2 cycle 6' .
outage for reasons other than bend radius.
- 2. During constructability walkdowns in support of the replacement plans for Group 1 cables ES2550-II, ES75-1, ES88-I, and ES113-I, the observed bends were significantly i less severe th-in the values which had been recorded during the original walkdown program. These cables have been ,
i recategorized as appropriate.
- 3. Cable PP453-II, which is associated with the Group 1 Unit 2 action plan, has been reclassified as non safety related and no longer aubject to the bend radius program.
Cable PP453-II is an intertie cable which is used to parallel diesel generators D and 3D or to power Shutdown Board D during a Unit 2 Appendix R event. BFN does not -
take credit for this cable for shutdown of the. units from any design basis accident, therefore, it is classified as nonsafety related.
III. REVISED DISPOSITION.
- 1. Revised disposition of Group 1 cables.
The Group 1 cable, PP453-II, which has been reclassified as.
nonsafety related, will not require replacement. The other four Unit 2 Group 1 cables, ES2550-II, ES75-I, ES88-1, and ESil3-1, which were reclassified based on the constructability walkdown data have been redispositioned in accordance with the action plan requirements. These cables had been scheduled for i replacement during the Unit 2 cycle 6 outage, but will now be l 1 eft in service. l
- 2. Revision to the Group 2 cables testing plan.
BFN implemented a Group 2 Load Cycle and Corona Test :
Program to replace the original high potential testing i program. The Load Cycle and Corona Test Program !
demonstrated the capability to maintain interfacial 1 integrin of the shielding system. This approach-has been utilized by TVA in the disposition of similar issues ,
at Watts Bar (Reference 5). The procedure is a modified i Association of Edison Illuminating Companies j qualification test. The test, CSS-87, Specifications for Thermoplastic and Cross-linked Polyethylene Insulated Shielded Power Cables Rates 5 through 35 Kv, has been performed on a cable bent to the lower bound of Group 2 (i.e., bent to 6 times OD).
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Page 3 ENCIASURE 1 (Continued) i The testing confirmed that the Group 2 cables can meet their design ;
requirements for interfacial shield integrity with no reduction in i life and without the need for further special high potential testing at each outage. Based upon the satisfactory results, the cables are !
now subject to only routine maintenance tests as appropriate. The testing results are available, for NRC review, at our Rockville office (Reference 6). The Load Cycle and Corona Test' Program is superior to the hi-pot test program for 3 reasons:
(1) Cables are testod under accelerated voltage and ;
temperature (aged) conditions rather than under normal conditions, (2) The integrity of the shielding system is physically inspected rather than making a determination by inference from voltage breakdown data, and (3) There is no potential to damage the plant equipment or cables as there is in hi-pot testing.
IV. EFFECTS OF REVISED DISPOSITION. ,
- 1. The five Group 1 cables which were slated for replacement during the Unit 2 cycle 6 outage will no longer require replacement.
- 2. The high potential testing and trending of Group 2 cables will be discontinued (except for normal maintenance and i modification activities).
V. JUSTIFICATION
- 1. Justification for reclassifying the Group 1 cables and for not reclassifying any Group 2 or 3 cables to Group 1: It ;
is improbable that there are cables which should have had ;
a lower group classification. The determination that observed bends were less severe than previous data led TVA to investigate the validity of the earlier walkdowns.
Additional walkdowns were conducted using a sampling plan to establish a 95% confidence that 95% of the original ;
walkdown data would remain valid when remeasured (References 7, 3 and 9). To be considered valid, the original walkdown bend radius measurement would have to be smaller than, or equal to, the bend radius when remeasured l via the sampling plan. The sampling plan results are available for review at our Rochille Office, i
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ENCLOSURE 1 (Continued) l Of the 58 cables which were originally subject to bend radius review, 31 cables were available for reevaluation.
The 31 cables have 623 bends. The other 27 cables were not included in the sampling plan for the following !
reasons: ,
- a. Eleven were replaced by other programs f
- b. Five were ground cables, and therefore evaluated as f not subject to the voltage stresses which lead to premature ageing.
- c. Eleven are embedded cables. Embedded cables cannot be walked down. Since the conduit bend radius determines the cable bend radius, there is no -
concern for bend radius violations in embedded -
cables.
Of the 623 bends subject to the sampling plan, 54 randomly chosen bends were remeasured and reevaluated.
In all 54 cases, the original measurements were shown to be equal to or less than the remeasurements. This confirms the above 95/95 acceptance criteria to validate the original data.
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- 2. Justification for acceptin results of previous high potential testing: The hi potential testing which was ,
conducted to support Unit restart remains valid. It is possible that some bend radii were originally underestimated such that the related cables were included j in the 15 " worst case" test group, thereby eliminating l other cables with smaller bend radii from the " worst case" 3 group. Based upon the results of the sagling plan )
however, none of the displaced cables would meet Group 1 ,
criteria. Only Group 1 bends are expected to impact test ;
results.
VI. CONCLUSIONS .
l Five cables which were slated for replacement under the l original correctivo action plan will not be replaced due to j corrected dispositions. The test plan, which would have required testing and trending for subsequent outages, has been replaced by a load cycle and corona test program. Cable PP434-1E has been reclassified so that it now is subject to the bend radius evaluation. Cable PP434-1E is being replaced due to identified insulation damage.
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ENCLOSURE 1 (Continued) i
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c VII. REFERENCES.
- 1. TVA's letter to the NRC dated October 4,1990, Revision to the Cable Installation Issues Supplemental Report - Cable <
Pullby .l
- 2. NUREG-1232 Volume 3, Supplement 2 - Safety Evaluation l Report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan, January 1991
- 3. Letter from TVA to the NRC dated May 10, 1991, Action Plan.
to Disposition Concerns Related to Units 1 and 3 Cable Installation Issues Including Cable Separations
- 4. NRC letter to TVA dated April 8,1992, Safety Evaluation of TVA Plans to Resolve Electrical Cable Installation and Separation Issues for the Browns Ferry Nuclear Plant Units 1 and 3 (TAC Nos. M80681 and M80682) i
- 5. TVA letter to the NRC dated October 11, 1990, Watts Bar Nuclear Plant (WBN) - TVA Responses to NRC Comments Resulting From August 1-3, 1990 Meeting F
- 6. Group 2 Load Cycle and Corona Test Report
- 7. Samplin5 Plan; Cable Bend Radius Verification
- 8. Walkdown W41769 ,
- 9. Bend Radius Walkdown Data Sheets / Technical Review Data l Sheets (Calc ED-Q2999-920677 RO) ;
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ENCLOSURE 2 !
SUMMARY
OF COMMITMENTS .I i
I. NEW COMMITMENT: l TVA will replace cable PP434-IE during the Unit 2 cycle 6 outage. ,
II. SUPERSEDED COMMITMENTS: ;
- 1. TVA will replace cables ESil3-1, ES2550-II, PP-453-II, f ES75-I, and ES88-I during the next scheduled refueling outage. t
- 2. All cables in Group 2 will be tested to the requirements >
of SEMI-65 during the next scheduled outage and subsequent i outages to facilitate a trend analysis. BFN plans to !
evaluate the trend analysis at the end of the third -l refueling outage following restart to assess the need for continued trending of these cables.
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