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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] |
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ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ESSION NBR: 9101170231 DOC. DATE: 91/01/16 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 WALLACE,E.G. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to NRC 901217 ltr re violations noted in Insp Rept D 50-259/90-33';50-260/90-33 & 50=296/90-33.Corrective actions:
TVA has revised its reportability determination.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR TITLE: General (50 Dkt)-Insp Rept/Notice of Vio ENCL ation Msponse MR SIZE:
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 D D
RECIPIENT COPIES RECIPIENT COPIES ID LTTR ENCL ID LTTR ENCL t
CODE/NAME CODE/NAME HEBDON,F 1 1 ROSS,T. 1 1 INTERNAL ACRS 2 2 AEOD 1 1 AEOD/DEIIB 1 1 AEOD/TPAB 1 1 DEDRO 1 NRR MORISSEAUiD 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 SE2 1 1 NRR/PMAS/ILRB12 1 1. NUDOCS-ABSTRACT 1 1 OE DIR .1 1 OGC/HDS3 1 ' 1 RE E '1 1 RGN2 FILE 01 1 EXTERNAL: EG&G/BRYCE, J. H. 1 1 NRC PDR 1 1 NSIC 1 1 NOTES: 5 5 D
S
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NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT COiNTROL DESK, ROOiil PI-37 (EXT. 20079) TO ELlii1lNATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUiXIENTS YOU DON'T NEED!
OTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 29
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 87401 5B Lookout Place JAN I6 'l931 U.S: Nuclear Regulatory Commission ATTN: Document Control Desks Washington, D.C. 20555 Gentlemen:
In the Matter of Docket Nos. 50-259 Tennessee, Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT "(BFN) NRC INSPECTION REPORT 50-259, 260, 296/90-33 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 December 17, 1990. NRC cited TVA with a violation consisting of three examples. The first two examples are related to TVA's failure to provide four-hour notifications to the NRC Operations Center.. The last example relates to TVA's failure to submit a Licensee Event Report to NRC.
TVA fully recognizes the importance of its obligation to comply with both the 10 CFR 50.72 immediate reporting requirements and the 10 CFR 50.73 licensee event reporting system. TVA admits Example A and Example C of the violation, but denies Example B. TVA has reviewed its interpretation of the 10 CFR 50.72 immediate notification rule and believes that its reporting philosophy is consistent with both industry practice and NRC guidance on the reporting requirements.
Enclosure 1 provides TVA's response to this violation. Each example of the violation is addressed separately along with corrective actions taken.
Enclosure 2 provides a listing of commitments made in this response.
If you have any questions, please get in touch with Patrick P. Carier, Manager of Site Licensing, at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY E. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosures cc: See page 2 9$ 0117023l 050002~~
PDR PDOf'g PDR An Equal Opportunity Employer
0 JAN 15 891 U.S. Nuclear Regulatory Commission cc (Enclosures):
Ms. S. C. Black, Deputy Director Project Directorate II-4 U.S. Nuclear Regul'atory 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 e
e RESPONSE BROWNS FERRY NUCLEAR PLANT (BFN)
NRC INSPECTION REPORT 50-259$ 260$ 296/90-33 LETTER FROM B. A. WILSON TO 0. D. KINGSLEY$ JR.
DATED DECEMBER 17, 1990 During the Nuclear Regulatory Commission (NRC) inspection conducted on October 16 November 16, 1990, violations of NRC requirements were
~ identified. The first violation involved failures to notify the NRC of reportable events in accordance with 10 CFR 50.72 and 50.73. The second violation was for failure to take corrective action for a previous nonconformance. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1990)$ the violations are listed below:
VIOLATION 10 CFR 50 requires notification and reporting to NRC of various reactor events. 10 CFR 50.72 requires that licensee's notify the NRC within four" hours of any event or condition that results in manual or automatic actuation of any Engineered Safety Feature (ESF). 10 CFR 50.73 requires that a Licensee Event Report (LER) be submitted within 30 days after the discovery of any operation or condition prohibited by the plant's Technical Specifications (TS).
Final Safety Analysis Report (FSAR) section 1.6.2, Nuclear Safety Systems and Engineered Safeguards, includes both the Primary Containment Isolation Control System (PCIS) and Secondary Containment. The PCIS automatically initiates closure of isolation valves to seal off all potential leakage paths for radioactive material to the environs.
TS section 3.11.A.l requires that the fire detection instrumentation listed in TS Table 3.11.A be operable whenever equipment protected by the fire instrument is required to be operable. TS section 3.11.A.l.a 'etection requires that the fire detection system's heat and smoke detectors for all protected zones be operable and TS section 3.11.A.l.b requires that a patrolling fire watch be established whenever TS section 3.11.1.a cannot be met.
e Contrary to the above, the licensee failed to notify-the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the ESF actuations in a and b, below, and failed to submit an LER within 30 days for item c below.
~Exam le a.
On October 20, 1990, Unit 3 Reactor Water Cleanup system valve 3-FCV-69-01, a PCIS valve, unexpectedly. isolated during a momentary power loss from an electrical board transfer. This valve is designed to isolate on a PCIS group 3 actuation signal. The licensee did not notify the NRC Operations Center of this unplanned ESF actuation via the Emergency Notification System until October 30, 1990.
ENCLOSURE 1 Page 2 of 5
~Exam le b.
On November 4, 1990, the Refuel Zone ventilation system isolated due to a failed relay in the circuit for the refueling floor static pre'ssure relays.
This ventilation system is designed to isolate upon receipt of a PCIS group 6 actuation signal. The licensee did not notify the NRC Operations Center of this unplanned ESF actuation.
~Exam le c.
On September 27, 1990, a patrolling fire watch missed the hourly check of the A 4160V shutdown board room due to the vital door being locked during a loss of the security card reading system. The fire watch was required because the duct detector in the room would not actuate the associated dampers as required by TS Table 3.11.A. The licensee did not submit an LER to the NRC on this event.
These examples are a Severity Level IV violation (Supplement I) which is applicable to all three Units.
TVA's Res onse to Exam le A
- l. . Admission or Denial of the Violation TVA admits the violation.
- 2. Reason for the Violation This violation was caused by TVA's interpretation of the guidance contained in NUREG 1022, Licensee Event Report System.
TVA's determination that the event was not reportable was based on the fact that closure of 3-FCV-69-1 did not constitute an ESF actuation since the system was isolated due to a planned evolution and the closure was not in response to an accident signal.
Nore specifically, the determination was influenced by the NRC response to question 6.9 in NUREG 1022, Supplement No. 1, which states that:
If the system is not required to be operable and it has been properly removed from service such that it can not perform its intended function (e.g., manual discharge valves are shut, breakers are open), then a spurious actuation of part of the system (e.g., the pump starts but the discharge valve remains shut) is not reportable.
0 ENCLOSURE 1 Page 3 of 5 In this event, the reactor water cleanup (RWCU) system had been properly removed from service and was not required to be operable. 3-FCV-69-1 is a primary containment inboard isolation valve for the RWCU system. TVA determined the closure of 3-FCV-69-1 was due to a failed fuse. Since the RWCU system had been properly removed from serv'ce and the valve closure was a result of fuse failure, TVA concluded this event showed sufficient similarity to the example provided in NUREG 1022 and therefore was reportable. not'onsidered However, upon further evaluation, the closure of 3-FCV-69-1 has been determined to be a result of the loss of initiation logic power and included a part of the ESF logic. Therefore, TVA has revised its reportability position for this example and has subsequently reported this event.
- 3. Corrective Ste s Which Have Been Taken and Results Achieved As noted above, TVA has revised its reportability determination for this example and has concluded that this event is reportable. A Licensee Event Report (LER) 296/90004 was submitted on November 19, 1990.
- 4. Corrective Ste s Which Have Been or Will Be Taken to Avoid Further Violations I
This violation and its response will be included as required reading for the shift operations supervisors by June 1, 1991.
- 5. Date When Full Com liance Will Be Achieved Full compliance has been achieved for the specifics of this examples TVA's Res onse to Exam le B
- 1. Admission or Denial of the Violation TVA denies the violation.
- 2. Reasons for the Denial The event described in this example was not reported as an unplanned ESF actuation because no ESF logic was actuated during the event. The Refuel Zone Ventilation System fans and isolation dampers are dual function components. First, the refuel zone ventilat'ion fans are shutdown and the dampers closed to isolate secondary containment upon receipt of a PCIS" Group 6 isolation signal. Second, they are utilized for pressure control of the ventilation zones.
ENCLOSURE 1 Page 4 of 5 A PCIS Group 6 isolation signal is developed when any of the following conditions exist: low reactor vessel water level, high drywell pressure, or high radiation in the reactor zone. At the time of the event, none of the ESF logic (either spurious or valid) associated with any of these .
three conditions was actuated.
At the time the PCIS Group 6 signal was received, TVA investigated the event and determined that the refuel zone isolation was initiated by the spurious action of the, refuel zone static pressure switch 1-PDS-64-611B/D. This switch is not associated with the ESF, but is designed to protect the Reactor Building zones from excessive positive or negative pressures. Further, this switch is nonsafety-related and is not required to perform a safe shutdown function. The relationship of the zonal pressure switch logic to the PCIS logic is shown on Enclosure 3.
As depicted on the diagram, the static pressure switch logic is independent of the PCIS logic. The refuel zone isolation characterized by this event was an expected non-ESF response to a spurious actuation of a refuel zone zonal pressure switch.
Since the refuel zone isolation resulting from the static pressure switch failure was not a valid ESF signal, TVA determined this event to be not reportable per 10 CFR 50.72 or 10 CFR 50.73, and made this determination within four hours of receiving the isolation, signal.
TVA considers that this interpretation of what constitutes an is consistent with guidance provided by the NRC. During the ESF'ctuation NRC Region Event Reporting Workshop (Regions IV and V) held on November 8, 1990, this type of example was the subject of discussion (involving dual function components) when the following question was'sked:
[Is] the actuation of an ESF component from a non-ESF source, closure reactor water cleanup isolation valves in response to an ion change or high temperature? Is that viewed as a valid ESF actuation under 50.72~
Nr. Weiss, Chief, Operations Officer Section, AEOD, NRC, responded the following:
. where you had reactor water cleanup isolation and its closing due to a process parameter saying that the ionization beds needed to be protected from high temperatures, that's not an engineered safety feature actuation signal.
It would be my judgment that that would not be a reportable ESF item.
If you have a dual safety function in a reactor water cleanup isolation valve going closed, and it' for a nonsafety purpose, we'e not all that interested in it.
ENCLOSURE 1 Page 5 of 5 TVA's Res onse to Exam le C Admission or Denial of the Violation TVA admits the violation.
- 2. Reason for the Violation This violation has been attributed to a failure to maintain compliance with the TSs. BFN TSs show the function of the shutdown board room "A" fire detection system is to alarm in the main control room and to actuate the ventilation duct dampers. These dampers were out of service and a maintenance'work order had been issued.
However, the alarm function of the fire detection system was operable.
In addition, 10 CFR 50 Appendix R modifications previously installed fire-rated dampers in these ducts. Therefore, based on the operability of both the alarm function of the fire detection system and the Appendix R related dampers, TVA determined the intent of the TSs were met and the failure of the fire watch to physically enter'he room was not reportable per 10 CFR 50.73. Based on additional review by TVA, it was t
determined that compliance with the TSs had not been maintained and that this item is reportable per 10 CFR 50.73.
- 3. Corrective Ste s Which Have Been Taken or Will Be Taken and Results Achieved The LER associated with this event will be submitted to NRC by February 14, 1991. /
- 4. Corrective Ste s Which Will Be Taken or Have Been Taken to Avoid Further Violations This event has been reviewed with the appropriate operations, technical support, and fire protection personnel to ensure awareness of the importance of maintaining strict compliance with technical specifications.
- 5. Date When Full Com liance Will Be Achieved Full compliance will be achieved with the submittal of an LER. The LER will be submitted by February 14, 1991.
0 ENCLOSURE 2 COMNITMENT The Licensee Event Report which TVA committed to prepare in response to Example C of Notice of Violation 90-33-01 will be submitted to NRC by February 14, 1991. 4 This violation and its response will be included as required reading for the shift op'erations supervisors by June 1, 1991.
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