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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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ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)
ACCESSION NBR:9103270252 DOC.DATE: 91/03/22 NOTARIZED: NO DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tephessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION MEDFORD,M.O. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) 1 I
SUBJECT:
Responds to notice of violation for Insp Repts ~50=259/90-"40, 3 D 50-260/90-40 & 50-296/90-40,re installation of improper materials & inadequate designs. Ensuring that personnel
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is properly trained & complete walkdown of electrical cable.
DISTRIBUTION CODE: IE01D COPIES RECEIVED LTR ENCL SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response A
NOTES:1 Copy each to: B.Wilson,S. BLACK 05000259 1 Copy each to: S.Black,B.WILSON 05000260 1 Copy each to: S. Black,B.WILSON 05000296 L
RECIPIENT COPIES RECIPIENT COPIES ID HEBDON,F CODE/NAME LTTR ENCL' I D CODE/NAME LTTR ENCL 1 ROSS,T. 1 1 iZNTERNAL: ACRS 2 2 AEOD 1 1 AEOD/DEIIB 1 1 AEOD/TPAB 1 1 DEDRO 1 1 NRR MORISSEAU,D 1 1 NRR SHANKMAN,S 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PEPB9D 1 1 NRR/DRIS/DIR 1 1 NRR/DST/DIR 8E2 1 1 NRR/PMAS/ILRB12 1 1 NUDOCS-ABSTRACT 1 OE DI~
R G~~-LE 1 1 OGC/HDS3 FILE 1
1 1
1 1 RGN2 01 1 1 R
EXTERNAL: EG&G/BRYCE,J.H. 1 1 NRC PDR 1 1 NSIC 1 1 NOTES: 5 5 D D
D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 29
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Tennessee Valley Autrtonty. 110t Market Streek Cnattanooga. Tennessee 37402 Mark O. Medford ViCe P~eSident. fduClear ASSuranCe. LiCenSing and FuelS MAR H 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk washington, D.C. 20555 Gentlemen:
In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROGANS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORT 50-259, 260, 296/90-40 REPLY TO NOTICE OF VIOLATION (NOV)
This letter provides TVA's response to the NOV transmitted by letter from B, A. Wilson to 0. D. Kingsley, Jr. dated February 20, 1991. NRC cited TVA with a violation consisting, of two examples. The first example consists of three events in which improper materials were installed at BFN. The second example consists of three events in which inadequate designs were installed at BFN.
TVA agrees that the examples noted in the NOV violated regulatory requirements. Enclosure 1 to this letter is TVA's "Reply to the Notice of Violation" (10 CFR 2.201). Enclosure 2 provides a listing of commitments being made in this letter.
If you have any questions regarding this response, please telephone Patrick P. Carier at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY M. 0 ~ Medford Enc losures cc: See page 2 9lt.'t=;270- " 910-.22 FDr AxiCh: ~>5000=:-~
F'DR ggc/
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V.S. Nuclear Regulatory Commission MAR 22 $ 91 cc (Enclosures):
Ms. S. C. Black, Deputy Director Project Directorate 11-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike, Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Hr. 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 V.S. Nuclear Regulatory Commission Region II 101 Yiarietta Street, NW, Suite 2900 Atlanta, Georgia 30323
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Enclosure 1 Tennessee Valley Authority Browns Ferry Nuclear Plant (BFN)
Reply to Notice of Violation (NOV)
Inspection Report Number 50-259 260 296/90-40 I. INTRODUCTION In accordance with the Commission's Rules of Practice and Procedure, as described in the NRC staff's February 20, 1991 letter transmitting the subject NOV, TVA hereby replies to the NOV per the requirements of 10 CFR 2.201.
II. SlPPIARY OF POSITION The NOV identified as a concern the "failure to implement design control measures." TVA agrees that the examples noted violated regulatory requirements. More specifically, TVA concurs with the NRC staff assessment that the violations resulted from failure to follow the provisions of the BFN design control program.
TVA considers that the BFN design control program has been and continues to be sound. The deficiencies identified by TVA (and cited in the NOV) do not, in TVA's view, indicate a breakdown in design control. To the contrary, the process through which TVA identified these issues proves that the existing program does work. The checks and balances in the program allowe'd TVA to detect and correct deficiencies which had resulted from personnel error.
Enclosure 1 Page 2 III. REPLY TO THE NOTICE OF VIOLATION A. The NOV states:
"10 CFR 50 Appendix B, Criterion III, Design Control, requires that measures shall be established to assure the design basis are correctly translated into specifications, drawings, procedures, and instructions, and that measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the structure, systems, and components.
Contrary to the above, activities involving design control were not being correctly implemented in accordance with requirements for the following two examples:
- l. After problem reporting document BFP 900189P, that concerned the specification of cable design criteria, was issued on June 6, 1990, and the establishment of a qualified cable list per quality design change notice Q13819A on August 28, 1990, incorrect cables were installed in three applications. Approximately 3,470 feet of type PX unjacketed cable, instead of type PXJ jacketed cable, was installed for four design change notices. Design criteria BFN-50-758 did not allow use of Anaconda or THHN cables in other applications but these cables were installed or specified in design change notices.
- 2. During the performance of three post modification tests (PMTs) equipment failed to operate as designed because the drawings used in the design had not been updated with the latest design change or were incorrect.
During performance of PMT-BF-86-006, the RHR Inboard Injection Valve indicated both open and closed. at the local control stations because of a wiring error due to an incorrect drawing used in the modification workplan. A problem occurred with circuit breaker ope'ration after the slow bus transfer modification under DCN W14030 because the drawings used in the design change did not incorporate design information following an Appendix R modification. During PMT-BF-57.038 onl'y two of four logic relays operated because an incorrect drawing was used in the modification workplan.
This is a Severity Level IV Violation (Supplement I) applicable to all three units."
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Enclosure 1 Page 3 .
B. TVA's Res onse
- l. Admission of Violation TVA agrees that the deficiencies violate regulatory requirements.
This example involved incorrect installation of three types of cables: Brand Rex, Anaconda, and THHN.
Brand Rex Cable: This event was the result of a personnel error. Unjacketed cable (PX) was issued and installed instead of the jacketed cable (PXJ) indicated in the design documentation. This event was self-identified by TVA during install'ation of the cable.
On November 9, 1990, a Condition Adverse to Quality Report (CAQR) was issued when a Quality Assurance inspector noted that a splice was being installed on unjacketed cable. The inspector was aware of the design criteria for splicing cable and this was not the installation he expected to see. investigation of the CAQR showed unjacketed cable was not qualified for installation and that the cable had been issued contrary to provisions in the BFN design control program.
Prior to this event, TVA had discovered that unqualified cable had been procured for installation at BFN. On June 6, 1990 a Problem Reporting Document (PRD) was issued to address this concern. Investigation of the event showed unjacketed cables had been procured which did not meet BFN design criteria. The resolution of this PRD was the issuance of a Quality Design Change Notice (QDCN). The QDCN provided a list of cables, by contract "
and work number, qualified for, installatiqn at BFN and was issued to maintenance, modifications, and procurement personnel. In addition, the QDCN was distributed by memorandum to ensure appropriate organizations were informed.
Contrary to the QDCN, TVA personnel issued unjacketed cable. The stores issue clerk, who 'is responsible for issuing materials from stores, was aware of the QDCN and the requirement to ensure cable issuance was -'n compliance. The individual did not review the'QDCN prior to issuing the cable; instead he operated from memory.
This was a personnel error for failure to follow provisions in the design control program when issuing cable. A contributing factor to this event was a weakness in the corrective action in response to the initial PRD issued June 6, 1990. TVA did not segregate or remove the unqualified cable from the warehouse.
Enclosure 1 Page 4 Anaconda Cable: This event was the result of personnel error. Anaconda cable was installed even though design documentation indicates that Anaconda cable is not to be issued for installation. This event was self-identified by TVA during a review of material requests'he review of material requests was performed after TVA identified the inappropriate use of Brand Rex type PX cable, previously discussed.
Design Criteria BFN-50-758, "Power, Control and Signal Cables of Use in Class I Structures," does not =allow cable with chlorinated polyethylene jacket (e.g. Anaconda cable) in Class I structures. Contrary to the design criteria, two Design Change Notices (DCN) were issued specifying the installation of Anaconda cables. In addition, the contract referenced in the DCNs was not on the list provided in the QDCN previously discussed.
This event resulted from personnel errors. The first personnel error was the listing of an unapproved contract on the DCNs. The second personnel error was the issuance of unqualified cable from the warehouse. A contributing factor to these personnel errors was a deficient corrective action response to the PRD issued June 6, 1990, as described above.
THHN Cable: This event was the result of personnel error. THHN cable was installed even though design documentation indicates that THHN cable is not to be issued for installation in the reactor building. This event was self-identified by TVA during a review of material requests. The review of material requests was performed after TVA identified the inappropriate used of Brand Rex type PX cable, previously discussed.
Design Criteria BFN-50-758 does not allow THHN cable to be installed in the reactor building. Contrary to the design criteria, a work order was issued specifying the installation of THHN cable for a non-safety related cable application (drywell lighting). In addition, the contract referenced in the work order was not on the list provided in the QDCN previously discussed.
0 Enclosure 1 Page 5 This event resulted from personnel errors. The first personnel error was the listing of an unapproved contract on the work order. The second personnel error was the issuance of unqualified cable from the warehouse. A contributing factor to these personnel errors was a deficient corrective action in response to the PRD issued June 6, 1990, as described above.
This example involved the improper installation of three modifications: injection valves, shutdown boards, and diesel
'generator relays.
In 'ection Valves: This event was the result of a personnel error. The individual preparing the workplan for this 'modification did not include the latest revision of a design drawing. This event was self-identified by TVA during the performance of the PMT when an inboard injection valve indicated both open and 'closed at the local control station.
In this event, a design change was issued to replace an existing cable in the plant. Since the cable terminations were not being revised, the cable termination drawing was not required to be included in the design. However, Site Director Standard Practice (SDSP) 8.4, "Modification Workplans," states: "If the design change provided no Associated Drawing List, use the latest revision drawing available from Document Controls and Records Management." Contrary to SDSP 8.4, the workplan which implemented this design change did not incorporate the latest revision of cable termination the drawing due to a personnel error.
- 2. Shutdown Boards: This event was the result of a personnel error. The individual preparing a design change did not include the latest rev'sion of a design drawing. This event was self-identified by TVA during the performance of a 'PMT, when an alternate power feeder breaker tripped and would not close.
In this event a design change was issued which required the four alternate feeder breakers, associated with the Unit 1 and Unit 2 shutdown boards, to trip during the presence of an accident signal.
Enclosure 1 Page 6 BFN Project Instruction (PI) 89-06, "Design Output,"
states "Design documents used as a basis for development of a DCN shall be the latest issue of the Nuclear Engineering (NE) approved documents of record,..."
Contrary to PI 89-06 the approved design change did not include the latest revision of a required drawing due to a personnel error.
- 3. Diesel Generator Rela s. This event was the result of a personnel error. The individual that prepared a data sheet for landing leads failed to implement the approved design change. This event was self-identified by TVA during the performance of a PMT when only two-out of four diesel generator voltage available (DGVA) relays operated.
In this event a design change was issued to modify the DGVA relays. The design change provided a markup of a controlled drawing to illustrate the correct termination locations for a cable. During preparation of a workplan, the data sheet for landing leads failed to correctly implement the markup of the drawing due to a personnel error. This personnel error resulted in the electrical leads being terminated at the wrong location.
- 2. Corrective Ste s Taken and Results Achieved The common element of these events is personnel error.
Accordingly, TVA continues to emphasize to its employees at BFN the importance of strict procedural adherence. In addition to the specific corrective steps identified below for each example, TVA has stressed that each individual is responsible for ensuring accuracy and quality in the work they perform. Notwithstanding the messages that plant management has periodically delivered to site personnel regarding procedure adherence, in his March 15, 1991 Site Director's Message, the BFN Site Director reiterated the need to adhere strictly to procedures. Furthermore, he cautioned that hasty or inadequate reviews destroy the credibility of the work.
In addition to the Site Director's message, discussed above, TVA issued a memorandum to all NE personnel .on January 25, 1991.
This memorandum stressed the importance of ensuring quality work in addition to ensuring compliance with procedures. Furthermore, this memorandum stressed the importance of each individual's role in the restart of Unit 2 and in the production of high quality products by NE.
I Enclosure 1 Page 7 The following corrective steps apply to all three events described in this example: Brand Rex, Anaconda, and THHN cables. These steps take the actions necessary to ensure personnel are properly trained, unqualified cable has been evaluated and cables installed in the plant are acceptable.
First, SDSP-16.16, Material Issuance and Return, has been revised to address the concerns described in the violation.
Training of power stores personnel on this revision has been completed. Also, additional training was provided to personnel in the procurement engineering and electrical design groups on design criteria BFN-50-758.
Second, a complete walkdown of electrical cable stored on site has been performed. The results of this walkdown were evaluated to ensure the cables are in compliance with the requirements of BFN-50-758. Cable found not to be in compliance with the requirements of BFN-50-758 has been segregated and/or removed from site.
Finally, a review of all cables issued for installation in the plant after August 1, 1987, has been completed. This review ensured cable installations in the plant meet the requirements of BFN-50-758. Cables installed in the plant which do not meet the requirements of BFN-50-758 will be evaluated and/or replaced as necessary prior to the restart of each unit at BFN.
- b. ~Exam le 2:
- 1. In 'ection Valves: For this'vent, the workplan was revised to include the latest revision, of the required drawing. The affected cable associated with the Residual Heat Removal system inboard injection valve was reterminated and the PMT was completed successfully.
- 2. Shutdown Boards: For this event, the design change was reissued to include the latest revision of the required drawing. The plant modification was performed to implement the required revision for the alternate power feed breaker modifications and, the PMT was successfully completed. In addition, personnel corrective actions were taken in accordance with TVA policies and procedures.
- 3. Diesel Generator Rela s: For this event the landed lead data sheet was revised to accurately implement the design change. The cable was reterminated for the DGVA relays, based on the revised data sheet and the PMT was successfully completed.
Enclosure 1 Page 8
- 3. Corrective Ste s Which Will be Taken
- a. ~Exam le 1:
Cables installed in the plant after August 1, 1987, which do not meet the requirements of BFN-50-758, will be evaluated and/or replaced prior to the restart of each uni.t.
- b. ~Exam le 2:
No further corrective actions are required.
4.'ate When Full Com liance Will Be Achieved
'Programmatically, TVA is in full compliance with the requirements of 10 CFR 50, Appendix B, Criterion III, Design Control.
Regarding specific cable evaluations and/or replacements, TVA will be in full compliance prior to the restart of each unit at BFN.
IV. CONCLUSION In conclusion, TVA considers that the examples noted in the NOV resulted from personnel error. That is, individuals involved failed to follow the provisions of the design control program. Accordingly, TVA considers that these events are not indicative of a programmatic breakdown. TVA has taken steps to correct the specifics of each example and has provided additional training where necessary to minimize the probability of recurrence of these types of events. Furthermore, TVA continues to stress to personnel at BFN the need for strict procedural adherence.
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Enclosure 2 Listin of Commitments
- 1. Cables installed in the plant after August 1, 1987, which do not meet the requirements of TVA Design Criteria BFN-50-758, "Power, Control and Signal
, Cables of Use in Class I Structures," will be evaluated and/or replaced as necessary prior to the restart of each unit.
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