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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] |
See also: IR 05000259/1990029
Text
ACCELERATED
DISTRIBUTION
DEMONSTRATION
SYSTEM REGULATORY
INFORMATION
DISTRIBUTION
SYSTEM (RIDS)ESSION NBR:9101090152
DOC.DATE: 90/12/28 NOTARIZED:
NO DOCKET ACIL:50-259
Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 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)SUBJECT: Responds to NRC 901108 ltr re violations
noted in Insp Rept 50-259/90-29,50-260/90-29
&50-296/90-29.Corective
actions: mod forMan reprimanded
&retrained&event reviewed w/sys evaluators
&tagging&support coordinators.'ISTRIBUTION
CODE: IE01D COPIES RECEIVED:LTR
ENCL L SIZE: TITLE: General (50 Dkt)-Insp Rept/Notice
of Vio ation Response NOTES:1 Copy each to: B.Wilson,S.
BLACK 1 Copy each to: S.Black,B.WILSON
1 Copy each to: S.Black,B.WILSON
D A 05000259 05000260 05000296 D RECIPIENT ID CODE/NAME HEBDON,F I TERNAL: ACRS AEOD/DEIIB
DEDRO NRR SHANKMAN,S
NRR/DOEA/OEAB
NRR/DRIS/DIR
NRR/PMAS/I
LRB12 OE G FTrh 02 EXTERNAL EG&G/BRYCE i J~H~NSIC NOTES: COPIES LTTR ENCL 1 1 2 2 1 1'1 1 1 1 1 1 1 1 1 1 1.1 1 1 1 1 1 5 5 RECIPIENT ID CODE/NAME ROSS,T.AEOD AEOD/TPAB NRR MORISSEAU,D
NRR/DLPQ/LPEB10
NRR/DREP/PEPB9D
NRR/DST/DIR
8E2 NUDOCS-ABSTRACT
OGC/HDS3 RGN2 FILE 01 NRC PDR COPIES LTTR.ENCL 1 1 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!COiNTACT THE DOCUMENT CONTROL DESK, ROOli'I PI-37 (EYT.20079)TO ELliill NATE YOUR NAME FROID DISTRIBUTION
I.ISTS I OR DOCU)ilEiNTS
YOU DON'T NEED!TAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 29 D D
TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place GEc 38 1990 U.S.Nuclear Regulatory
Commission
ATTN:'ocument
Control Desk Washington, D.C.20555 Gentlemen:
In the Matter of Tennessee Valley Authority Docket Nos.50-259 50-260 50-296 BROWS FERRY NUCLEAR PLANT (BFN)-NRC INSPECTION
REPORT 50-259, 260, 296/90-29-RESPONSE TO NOTICE OF VIOLATION This letter provides TVA's response to the Notice of Violation transmitted
by letter from B.A.Wilson to 0.D.Kingsley, Jr.dated November 8, 1990.NRC cited TVA with a violation with two examples for failure to follow procedures.
The first example involved personnel working within an equipment clearance boundary without proper authorization
on a hold order.The-second, example involved an improperly
completed impact evaluation
of work activities
0 t which resulted an an unplanned engineered
safety features actuate.on.
Enclosure 1 provides TVA's response to this violation.
Each example is addressed separately
along with the corrective
actions taken.On December 17, 1990, NRC issued Inspection
Report 90-33 which cited two new.self-identified
examples of the problem identified
in this violation.
TVA will address both of these examples in a supplement
to this letter.The supplement
will be submitted by January 31, 1991.J As agreed with members of the NRC Region II staff, the due date for this'esponse was extended, to December 31, 19+.Enclosure 2 is a listing of the commitment
made in this response.If you have any questions regarding this response, please telephone Patrick P.Carier at (205)729-3570.Very truly yours, TENNESSEE VALLEY AUTHORITY gg gi 4<M.0.Medford, Vice President Nuclear Assurance, Licensing and Fuels Enclosure cc: See page 2 9101090152
901228 PDF'DGCI." 050002'=9 f,i PDR An Equal Opportunity
Employer g Eo/I/
l, l
U.S.Nuclear Regulatory
Commission
cc (Enclosure):
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
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, Georgia 30323
ENCLOSURE 1 RESPONSE-BROWNS FERRY NUCLEAR PLANT NRC'INSPECTION
REPORT 50 259'60~296/90 29 LETTER FROM B.A.WILSON TO 0.D.KINGSLEY, JR.DATED NOVEMBER 8, 1990 During the NRC inspection
conducted between September 16 and October 15, 1990 a violation of NRC requirements
for failing to follow procedures
was identified.
The first example of this violation involved personnel working inside an equipment clearance without proper authorization
on a hold order.The second example involved an improperly
completed impact evaluation
of work activities
which resulted in an unplanned engineered
safety features (ESF)actuation.
Technical Specifications, Section 6.8.1, Procedures, requires that written procedures
shall be established, implemented
and maintained
covering those recommended
in Appendix A of Regulatory
Guide 1.33, Revision 2, February 1978.Appendix A of Regulatory
Guide 1.33 includes administrative
procedures
and procedures
for controlling
repair activities
of safety-related
equipment.
Site Directors Standard Practice (SDSP)-7.9, Integrated
Schedule and Work Control, Section 6.4.1, requires that an impact evaluation
be performed on all activities
that have potential for affecting equipment operations
which may affect the safe and reliable operation of the unit except as specifically
exempted.Attachment
C to SDSP-7.9 is used to document that evaluation.
Section 7.0 specifies the Tagging and Support Coordinator's
duties in reviewing, correcting, and issuing hold order boundaries.
SDSP-14.9, Equipment Clearance Procedure, Section 6.1 provides both general and special requirements
for removing equipment from service to allow work to safely proceed.Contrary to the above, these requirements
were not met for the following two examples: l.On August 25, 1990 the requirements
were not met in that Workplan 0252-90 was determined
to be in progress without appropriate
supervision
having signed onto an existing hold order.2.On September 16, 1990 the requirements
were not met in that an inadequate
impact evaluation
resulted in licensee personnel cutting energized electrical
leads that were part of the D Diesel Generator initiation
logic circuits.This activity resulted in an unplanned engineered
safety feature actuation.
This is a Severity Level IV Violation (Supplement
I)applicable
to all three A units~
t x TVA admits the violation.
This violation occurred due to personnel error.The lead Modifications
foreman responsible
for signing on to the hold order failed to sign on to the hold order prior to the work being performed.
On August 16, 1990 while preparing to implement a workplan, modifications
personnel contacted the lead modifications
foreman and requested that he sign the workplan on to an existing hold order.After receiving the" request, the lead foreman noted in the Modifications
organization's
log book, which lists hold orders and denotes specific workplans covered by each hold order, that he had signed on to a hold order.Modifications
personnel responsible
for performing
the work reviewed the log book, confirmed that'the lead foreman had signed the workplan on the existing hold order, and proceeded to implement the workplan.However, although the lead foreman had noted in the log book that he had signed on to a hold order he never contacted appropriate
plant personnel to have the workplan signed on to the hold order.Signing on to hold orders prior to implementing
workplans is required by Site Director Standard Practice (SDSP)14.9, Equipment Clearance Procedure, if equipment must be removed from service to perform work.t v t v.n k v The Modifications
foreman associated
with this event received a reprimand from his supervisor.
This foreman was also retrained in the requirements
of SDSP 14.9.This training was conducted by a Shift Operations
Supervisor
and specifically
emphasized
the correct preparation
of tagout requests, the purpose of equipment clearances (to protect personnel and equipment), responsibilities
of the Operations
organization
for establishing
clearance boundaries, and responsibilities
of the Modifications
organization
for walking down and verifying established
boundaries
before beginning work.Prior to completing
this training the foreman was restricted
from signing on to hold orders.Rhd~t'a t v th r To prevent further recurrence
of this type of event, Modifications
management, general foremen and foremen were retrained in the requirements
of SDSP 14.9.The specifics of this training are discussed above.This training has been completed.
5.v TVA considers that it has achieved full compliance
with the specifics of this example of the violation.
1.m'h TVA admits the violation.
2.This violation occurred due to personnel error on the part of the individuals
responsible
for preparing and reviewing the impact evaluation
sheet.SDSP 7.9, Integrated
Schedule and Work Control, requires that scheduled work activities
be evaluated for impact on plant equipment.
This evaluation
is documented
on, Attachment
C, Plant Operation Impact Evaluation
Sheet (POIES).Individuals
responsible
for preparation
and review of the POIES are responsible
for identifying
significant
component and system responses such as ESF actuations, in addition to determining
whether work will be within a hold order boundary.Specifically, the Work Control System Evaluator (or system evaluator)
is responsible
for developing
a"...suggested Hold Order that encompasses
all the work that can be logically done under a given set of boundaries." The Tagging and Support Coordinator
is responsible
for"...review[ing]
and correct[ing]
the suggested Hold Order boundaries." In this event, the system evaluator was assessing the impact of two work orders directing replacement
of Raychem splices on the leads to two reactor vessel level transmitters.
These work orders were among approximately
15 other work orders directing replacement
of Raychem splices.Because several of the other work orders involved reactor protection
system (RPS)components, the system evaluator incorrectly
assumed that the work would affect RPS components
instead of emergency core cooling system components.
Based on this, he concluded that the work could be performed under an existing hold order for RPS components.
The system evaluator then provided this assessment
to the Tagging and Support Coordinator.
During his review of the assessment, the Tagging and Support Coordinator
questioned
personnel performing
the work, and their supervisor, regarding the appropriateness
of the suggested hold order boundary.Based on this information
and the assessment
provided by the system evaluator, the Tagging and Support Coordinator
incorrectly
determined
that the work could be performed under the existing hold order.
(~o
3.t'v t t'The Plant Operations
Manager reviewed this event with the Work Control Manager and the Operations
Superintendent.
These managers have in turn taken appropriate
corrective
actions with the system evaluator and the Tagging and Support Coordinator
associated
with this event.4, t'In order to prevent further recurrence
of this type of event, TVA reviewed this event with the system evaluators
and the Tagging and Support Coordinators
to stress the importance
of properly and thoroughly
completing
the impact.evaluation
sheet for each work activity to be performed.
In, addition, the importance
of Operations
personnel performing
a thorough review prior to work approval was stressed.5.t h n A v TVA considers that it has achieved full compliance
with the specifics of this example of the violation.
ENCLOSURE 2 COMMITMENT
RESPONSE-BROWNS FERRY NUCLEAR PLANT NRC INSPECTION
REPORT 50-259, 260, 296/90-29 LETTER FROM B.A.WILSON TO 0.D.KINGSLEY, JR.DATED NOVEMBER 8, 1990 On December 17, 1990, NRC issued Inspection
Report 90-33 which cited two new self-identified
examples of the problem identified
in this violation.
TVA will address both of these examples in a supplement
to this letter.The supplement
will be submitted by January 31, 1991.