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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.~~SUBJECT: Forwards'1991
'final SNM accountability rept for eight in-core detectors in radwaste evaporation bldg re notice of violation 6 proposed imposition of civil penalty per Insp Repts 50-259/89-55.50-260/89-55
&50-296/89-55.
DISTRIBUTION
'CODE: IE14D'OPIES RECEIVED:LTR J ENCL/SIZE: TITLE: Enforcement.
Action Non-2.790-Licensee Response,.
A 05000259 05000260 D 05000296 D 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 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS).CESSION NBR:9104260087 DOC.DATE: 91/04/17 NOTARIZED:
NO DOCKET FACIL: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 ZERINGUE,O.J,.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)RECIPIENT ID CODE/NAME KREBS,M.ROSS,T.COPIES LTTR ENCL 1'1 1 1 RECIPIENT ID CODE/NAME HEBDON,F COPIES LTTR ENCL 1 1 ERNAL: AEOD/DOA DEDRO NRR/PMAS/ILRB12 OE DIR~RGN..RS~1 1 1 1 1" 1 1 1 1.1 1 1 AEOD/DSP/TPAB, 1 1 NRR/DOEA/OEAB11 1 1 NUDOCS-ABSTRACT 1 1 OE FILE'1 1 1 RGN2 FILE 03 1 1 EXTERNAL: NRC PDR NOTES: 5 5 NSIC 1'1 D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE lVASTE!CONTACT THE DOCUMENT CONTROL DESK, t ROOXI Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 21 D D
Tennessee vattey Autnority, post Othe Sos 2000 Deca:ut.A!abatna 35609 U.S.Nuclear Regulatory Commission ATTN: Document 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)-1991 FINAL SPECIAL NUCLEAR MATERIAL (SNM)ACCOUNTABILITY REPORT On November 8, 1989, TVA determined that eight incore detectors in the Radwaste Evaporator Building (REB)were not accounted for in the 1986 SNM baseline inventory.
A subsequent search in the REB revealed additional SNM inventory deficien'cies.
On May 2, 1990, NRC transmitted Enforcement Action (EA)89-239 entitled"Notice of Violation and Proposed Imposition of Civil Penalty" for NRC Inspection Report Nos.50-259, 260, 296/89-55 for lack of control of SNM.The Enclosure to this letter provides TVA's final 1991 SNM Accountability Report.This report documents the corrective actions taken to address the referenced NOV.Based on the completion of these corrective actions, TVA concludes that an accurate and manageable SNM program has been established at BFN, and that the corrective actions taken will preclude further violations of.this type.Furthermore, to provide an additional level of confidence the BFN Quality Assurance organization performed an independent review of the SNM inventory and program.In a telephone conversation, TVA and NRC personnel agreed to a new submittal date of April 18, 1991.I104~60087 9104i7 t.'DR t-"tDOCK 0 00025~PDR.((
U.S.Nuclear Regulatory Commission APR f.7 m If you have any questions concerning this SNM report, please telephone Patrick P.Carier't (205)729-3570.Very truly yours, TENNESSEE VALLEY AUTHORITY/pe/0.J.Zer'ue, Vic Pres dent Brp s-rry Operat ons 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 Brooms"Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000-
'David R.McGuire (enclosure)
Chief Safeguards Section U.S.Nuclear Regulatory Commission Region II 101 Marietta Street NW, Suite 2900 Atlanta, Georgia 30323 Mr.Thierry M.Ross, Project Manager U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Mary'land 20852 Mr.B.A.Wilson, Project Chief U.S.Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
ENCLOSURE'ennessee Valley Authority Browns Ferry Nuclear Plant (BFN)1991 Final Special Nuclear Material (SNM)4 I.BACKGROUND On November 8, 1989, TVA determined that eight incore detectors were not accounted for in the 1986 SNM baseline inventory.
Additional searches conducted November 26-29, 1989 of 21 SNM storage drums identified further SNM inventory deficiencies.
This'information was submitted to NRC in TVA's December 1, 1989 report on SNM accountability and in a December 8, 1989 voluntary licensee event report,(LER).
Subsequently, in Inspection Report 50-259, 260, 296/89-55 NRC issued a notice of violation (NOV)and proposed'imposition of civil penalty for lack of SNM control.On June 1, 1990, TVA submitted its reply to the NOV and, proposed imposition of civil penalty.In these submittals BFN acknowledged weaknesses in its 1986 SNM baseline inventory and committed to'significant corrective actions.II.CORRECTIVE ACTIONS TVA took a proactive role to ensure control of the SNM at BFN.An action plan defining TVA's interim recovery plan was developed and immediate corrective actions were taken to support the control of SNM accountability.
Specifically, areas where SNM might have been stored and which could present a significant radiological hazard to onsite personnel were searched for SNM items.This included the traversing incore probe (TIP)rooms and the drywell undervessel areas in all three units, the Radwaste Evaporator Building (REB), the Power-Stores warehouse SNM storage area, the Chemical Laboratory SNM.vault, the RADCON Instrument Lab SNM cabinet;and the local power'ange monitor (LPRM)box on the refuel floo Page 2 of 4 Additionally, SNM drums in the REB were segregated from non-SNM radwaste.The SNM drums were emptied and the SNM items (detectors)
were separated from other waste including the detector cables, canisters and shielding bricks.The SNM was labeled and placed in one drum which=is currently stored in an area separate from non-SNM waste.Discrepancies between the previous BFN inventory list and the drum contents were reported to NRC in LER 259/89016.
TVA also identified long-term corrective actions to prevent similar events from recurring in the future.The corrective actions included: (1)providing SNM training for personnel involved in the search and inventory of SNM, (2)reviewing previous corrective actions for adequacy;.
(3)monitoring the SNM inventory and program by Quality Assurance (QA)to ensure a high confidence level, (4)developing an action plan for disposal of unusable SNM items, (5)establishing a temporary storage area for'SNM, and (6)performing a new baseline inventory of SNM.These actions have been completed, and are discussed in more detail below.Reactor Engineering personnel were trained to identify SNM and byproduct source material (BSM)such as TIPs, LPRMs, source range monitors (SRMs),,intermediate range monitors (IRMs), and fuel ,loading chambers (FLCs).Upon completion of this training a quiz was given to assess each persons knowledge.
The results of the quiz determined if they were qualified to search for SNM and BSM.All Reactor Engineering personnel involved in the inventory of SNM have been qualified.
Also, personnel from other site organizations were trained for the purpose of conducting a'site search.The training and testing of these personnel were the same as mentioned'bove.
2.Review of Previous Corrective Actions Corrective actions for previous violations involving control of SNM were reviewed for bad assumptions, weak or missing information, and inadequate or incomplete program fixes.Basic lessons learned from these events were incorporated in the'ngoing SNM inventory.
These general lessons were: inventories should entail a search of the entire area in question;when inventorying or searching for an item the personnel involved should have first-hand experience in recognizing the item and any packaging that it might be inside;and items should be removed from containers for countin Page 3 of 4 3.gA Review The BFN QA organization performed an independent assessment of the overall SNM program, the methodology for conducting the 1991 SNM baseline inventory, and initial portions of.the physical inventory to ensure that the control and accountability of SNM were-adequate at BFN.QA performed this assessment using three major objectives:
Procedural review to determine adequacy and proper implementation of upper tier requirements and regulatory commitments;
~~Accountability/inventory review to determine, if fuel and non fuel requirements were met, and Programmatic review to determine root cause and further weaknesses, if any.'lthough this independent QA assessment identified areas where further activities were needed, the methodology for completion of the 1991 SNM Baseline Inventory was found acceptable.
The identified areas for improvement were subsequently resolved during performance of the inventory.'
4.SNM Dis osal Plan An action plan was developed to dispose'f unusable SNM which is located in the REB and the spent fuel storage pools.SNM located in the REB has been identified, consolidated and stored for off-site disposal.In addition, a schedule for cleaning out BFN's spent fuel storage pools has been developed.
5.Tem orar Stora e Area A temporary storage area for SNM was established in the REB.This area is controlled as a locked, high radiation area in accordance with BFN's Technical Specifications.
In addition, the temporary storage area is controlled as an item control area in accordance with the SNM program.These actions provide adequate control to ensure that only authorized plant personnel access the SNM storage area.R 1 1 SNM Baseline Inventor The 1991 SNM Baseline Inventory involved physical searches to identify the location of SNM, labeling of SNM and verification of SNM serial numbers where practica Page 4 of 4 The physical searches were conducted by several site organizations.
However, the main search of the Reactor Building, Turbine Building, Radwaste Buildings, refueling floor, and Power Stores Warehouse was,conducted by teams composed of Reactor Engineering and Radcon representatives.
These searches involved a daily planning session and generation of detailed maps'of each area searched.The maps depicted boxes, drums and other containers which were found in each area.Following completion of the searches, SNM was labeled and verified.'pecifically, the serial numbers of each of the installed TIPs, IRMs, and SRMs in Units 1, 2, and 3 were visually verified.The serial numbers of LPRMs in Unit 2 which can be seen by underwater, camera were also verified..
However, the serial numbers of Westinghouse LPRMs can not be read while the detector is installed because verifying the serial numbers would , involve removing the assemblies which is a destructive process.Therefore, these serial numbers were not verified.TVA instead assigned a unique serial number to these LPRMs to ensure accountability upon removal.Additionally, the LPRMs were quantit'atively verified by undervessel observation of the electrical connector ends.Spent fuel and used LPRMs in the spent fuel storage pools were verified by serial number and/or a positive piece count process.SNM items in the REB were consolidated into one drum which only contained lead shielding and'the individually bagged and labeled detectors.
Finally, SNM such as new detectors, sources, and FLCs was inventoried by physical observation and serial number.As a result of the-1991 SNM Baseline Inventory, BFN considers that it has positively identified each item of SNM on site.TVA is maintaining a record of SNM location, serial number, type, and last inventory date.III.SIHKARY TVA has completed the aforementioned immediate and long-term corrective actions.TVA considers these corrective actions will preclude further SNM accountability deficiencies.
Additionally, no SNM discrepancies were identified since the initial deficiencies were reported in LER 259/89016 dated December 8, 1989.Therefore, TVA concludes that it has established an accurate and maintainable SNM baseline inventory, and is in full compliance with provisions of 10 CFR 70.51(c).