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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
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ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DXSTRIBUTION SYSTEM (RIDS)
CESSION NBR:9112020273 DOC.DATE: 91/11/27 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 MEDFORD,M.O. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Responds to 911029 ltr re violations noted in Insp Repts 50-259/91-33, 50-260/91-33 & 50-296/91-33 & Enforcement D Action 91-120.Corrective actions:credible baseline inventory of all SNM on site will be reported to NRC.
DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR TITLE: General (50 Dkt)-Insp Rept/Notice of Vio 4 ation ENCL 3 SIZE:
Response
A NOTES:
D RECIPIENT COPIES 'ECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL HEBDON,F 1 1 ROSS,T. 1 1 WILLIAMS,J. 1 t
1.
INTERNAL: ACRS 2 2 AEOD 1 1 AEOD/DEIIB 1 1 AEOD/DS P/TPAB 1 1 DEDRO 1 1 NRR HARBUCK,C. 1 1 NRR MORISSEAUiD 1 1 NRR/DLPQ/LHFBPT 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PEPB9H 1 1 NRR/DST/DIR SE2 1 1 NRR/PMAS/ILRB12 1 1 NUDOCS-ABSTRACT 1 1 05-D.- 1 1 OGC/HDS3 1 1 G~- 02 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G/BRYCE 1 J H ~ 1 1 NRC PDR 1 + 1 NSIC 1 1 D
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D NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! COiVA ACT THE DOCUMENT CONTROL DESK, ROOii'I Pl-37 (EXT. 20079) TO ELIIIINATEYOUR NAb, IE FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TAL NUMBER OF COPIES REQUXRED: LTTR 25 ENCL 25
0 Tennessee Valley Authority, 1101 Market Street, Chattanooga. Tennessee 37402 Mark O. Medford Vice President, Nuclear Assurance, Licensing and Fuels November 27, 1991 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mashington, D.C. 20555 Gentlemen:
In the Hatter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROGANS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORT 50-259, 260, 296/91-33 REPLY TO NOTICE OF VIOLATION (NOV) (ENFORCEMENT ACTION 91-120)
This letter provides TVA's reply to S. D. Ebneter's letter to D. A, Nauman dated October 29, 1991, which transmitted the subject NOV involving the inaccurate TVA special nuclear material (SNM) baseline inventory which was transmitted to NRC on April 17, 1991.
Pursuant to 10 CFR 2.201 and as described in the enclosed "Reply to the Notice of Violation," TVA admits this violation. provides TVA's reply to the NOV. Enclosure 2 provides TVA commitments to ensure an accurate and credible SNM inventory at BFN.
If you have any questions regarding this response, please telephone
- 0. J. Zeringue at (205) 729-3675, or me at (615) 751-4776.
Sincerely, Hark 0. Medford Enclosures cc: See page 2
U.S. Nuclear Regulatory Commission November 27, 1991 cc (Enclosures):
NRC Resident Inspector
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Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One Mhite 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 Tennessee Valley Authority Browns.Ferry Nuclear Plant (BFN)
Reply to Notice of Violation (NOV)
(Enforcement Action 91-120)
Inspection Report Number 50-259, 260, 296/91-33 NRC STATEMENT OF VIOLATION "During the Nuclear Regulatory Commission (NRC) inspection conducted on September 3 through 6, 1991, a violation of HRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for HRC Enforcement Actions," 10 CFR Part 2, Appendix C (1991), the violation is listed below:
10 CFR 70.51(d) requires, in part, that each licensee who is authorized to possess at any one time and location special nuclear material (SNH) in a quantity totaling more than 350 grams of contained uranium-'235 shall conduct a physical inventory of all SNH in his possession under license at intervals not to exceed twelve months.
Contrary to the above, the licensee failed to perform an adequate physical inventory in 1990. Specifically, the February and March 1990 physical inventory failed to include an item containing SNM, which was identified in the spent fuel pool on September 7, 1991."
This is a Severity Level III violation (Supplement III).
TVA'S REPLY TVA admits that the results of its physical inventory of SNM conducted in 1991 at BFN were in error.
- 1. Reason for the Violation As stated during the October 4, 1991 enforcement conference, the two inventory discrepancies which are the subject of this violation resulted from the use of engineering judgments during TVA's efforts to confirm the SNH baseline inventory at BFN.
0 BFN considers that the judgments utilized were reasonable. However, in hindsight certain of these judgments proved faulty and =resulted in the misidentification of two non-fuel SNM items. Consequently, TVA inaccurately cataloged these items in its current inventory records.
A discussion of the two events resulting in the inventory discrepancies is set forth below:
A. Event 1 On August 21, 1991, a local-power range monitor (LPRM) without a "hot end" (detector assemblies) was discovered. The LPRM was previously identified in the SNM baseline inventory as containing a "hot end."
Mhen the SNM baseline inventory of the Unit 2 spent fuel storage pool (SFSP) was conducted, 18 full length LPRMs stored in the SFSP wore found severely entangled. The engineer performing the inventory in the SFSP concluded that these 18 LPRMs could not be individually separated without violating the instructions provided in the maintenance request (MR) which was specifically initiated to perform the inventory.
These instructions required the LPRMs to be maintained at least five feet under the surface of the SFSP at all times, to ensure prop'er shielding and for maintaining radiation exposures as low as reasonably achievable (ALARA). Accordingly, a decision was made to rely on a visual inspection of the LPRMs, obtaining the serial number at the cold end where practical. This was considered a reasonable approach under the circumstances.
The LPRM discovered on August 21, 1991, without a "hot end" was one of these 18 LPRMs from the Unit 2 SFSP.
B. 'Event 2 On September 7, 1991, while conducting a cleanup of the Unit 1 SFSP a LPRM "hot end" was discovered lying on the SFSP floor.
The LPRM "hot en'd" found during the pool cleanup was positioned under a length of Fuel Pool Cooling system piping in the pool and was partially obscured from view by this pipe. This area of the SFSP had been used to store other "cold end" pieces. During the SNM baseline inventory of the Unit 1 SFSP, a visual inspection was performed of the LPRMs stored in the Unit 1 SFSP. However, this LPRM "hot end" was not observed at this location in the SFSP.
0 TVA's analysis of the two events reflects that the inventory discrepancies can be directly attributed to the prior inventory problems which were addressed in a comprehensive plan developed in 1990. (This perspective is especially important in view of the fact that TVA has experienced no discrepancies in its new SNM tracking program at BFN.)
This comprehensive plan was instituted as a result of the previous enforcement action (EA 89-239). It was in Phase II of this plan that, the inventory discrepancies were identiEied.
- 2. Corrective Actions Taken and Planned As discussed in the enforcement conference of October 4, 1991, to address previous SHM inventory issues raised in EA 89-239, TVA developed a comprehensive three-phase plan in 1990 to complete non-fuel SNM storage activities.
Phase I of the plan consisted oE performing extensive plant searches and detailed piece counts. High level radwaste barrels and lead bricks were opened, and searches were made in the SFSPs. The searches of the SFSPs involved the use oE robots and video equipment to provide a detailed piece count. In addition, TVA reinventoried previously packaged shipping liners and defined specific SHM storage areas within the SFSPs.
Phases II and III consists oE a cleanup of the SFSPs and disposal of non-fuel SHM stored in the SFSPs. The cleanup efEorts provided TVA with a validation of the SFSP inventory and facilitated maintenance of the inventory. The ef Eor ts include processing approximately 300 non-SNM.items stored in tho SFSPs. These items include: boxes, brushes, cold end material, and miscellaneous fuel assembly parts.
In the cover letter to the NOV the Staff requested that BFN "reconfirm" seven speciEic commitments (including schedule) that it states were made during the October 4, 1991 enforcement conference.
TVA'ddresses below each oE these matters.
"The Plant Manager will be responsible Eor site activities associated with the SFSPs."
BFH has enhanced management oversight by reiterating the Plant Manager's responsibility for material stored in the SFSPs. This was communicated to the Plant Operations Manager on November 1, 1991, and subsequently included in Operations'ight orders.
The applicable reEueling operations procedure will be revised to clarify the Plant Manager's responsibility for the SFSPs. This revision will be completed by December 23, 1991.
e "Mhen cleanup is complete, the SFSPs will serve only as storage for spent LPRMs, and the LPRMs will be stored
'emporary in a manner that assures proper identification and accountability."
The applicable refueling operations procedure will be revised to identify the SFSPs as a temporary storage location for spent LPRMs and non-essential components. This proceduxe will also be revised to provide for recommendations from Operations to the plant manager for disposal of unusable non-fuel SHM and non-essential components in the SFSPs. This xevision will be completed by Decembex 23, 1991. In addition, the applicable maintenance instruction is being revised to address proper storage of LPRMS which will assist in assuring proper identification and accountability. This revision will be completed by December 16, 1991.
"Cutting and packaging operations of spent LPRMs for disposal will be performed only at a time just prior to offsite shipment to an offsite burial facility."
The applicable radwasto spent fuel pool clean-out procedure is being revised to direct the cutting and packaging requirements.
Specifically, LPRMs will be stored in the SFSPs in a full-length condition until just prior to the time of shipment to an offsite disposal facility.
"All currently known non-fuel SNM items and non-essential components will be removed from all spent fuel pools, and [TVA]
will refrain from using the spent fuel pools to store these items during future operations."
Known non-fuel SNM items have been removed from the SFSPs and shipped offsite for disposal. Known non-essential components are being readied for disposal. As stated above, procedures will be revised to ensure that SFSPs are used only for temporary storage.
Additionally, some non-essential components (e.g., control rod blades, filters,'tellite rollers from the control xod blades, small items xetrieved duxing the vacuuming px'ocess, Unit 3 vibration strings) must remain in temporary storage until equipment is available to process these items. These items will be processed and shipped for disposal duxing Phase III as required by our disposal action plan of 1990. However, the disposal of the stellite rollers is pending evaluation to
determine if the activity oE the rollers is low enough to allow disposal at an offsite burial facility. If the activity is not low enough, the rollers will have to remain in the SFSPs until such time as the activity has decreased sufficently to allow shipment. TVA expects the non-essential components, excluding the stellite rollers, to be removed from the SFSPs by June 1, 1992.
"[TVA] will vacuum clean sludges and other debris Erom all spent fuel pools and video-tape all items remaining in the pools after clean up is complete."
Accessible floor areas of the SFSPs are being vacuumed, and accessible floor areas and fuel storage areas are being videotaped to ensure thoroughness of the searches in the SFSPs for non-Euel SNM. If previously unaccounted for non-fuel SNM items are identified, they will be promptly included on BFH's inventory List and prepared for disposal in accordance with Phase III of BFN'omprehensive plans. Those discrepancie will be reported to NRC, as appropriate. Vacuuming will be completed by January 9, 1992. Final videotaping will be performed after the non-essential components, discussed above, are removed from the SFSPs. TVA expects the final videotaping to be completed by July 1, 1992.
"[TVA] will establish and report to HRC, an accurate and credible baseline inventory of all SNM on site ([TVA] indicated that this item would be completed by October 26, 1991)."
TVA believes it will have a credible vacuuming and videotaping of the baseline SNM inventory are completed.
when the SFSPs Vacuuming difEiculties (e.g., vacuum cleaner breakdowns, and vacuuming under 40 feet of water) have extended the October 26, 1991 completion date that was previously scheduled in the
.plan-of-the-day report provided during the enforcement conference. It should be noted that the fuel racks were not disassembled or moved due to the difficulty of moving the spent fuel stored in the SFSP.
"[TVA] will have an independent organization from outside the Tenne soe Valley Authority evaluate the entire SNM control and accounting program at the Browns Ferry Plant."
As a continuing corrective action and to provide further assurance of our programmatic control of SHM, TVA will provide for an independent evaluation oE SHM control and accounting by an outside organization. TVA expects thi evaluation to be completed by July 1, 1992. If a change occurs to this schedule, TVA will notify the StaEE.
- 3. Date When Full Co lienee will be Achieved TVA considers that full compliance will be achieved when procedure revisions are complete, SFSPs are vacuumed and videotaped, and the independent evaluation is .completed. TVA expects these actions to be completed by July 1, 1992. Should TVA discover any discrepancies as a result of the independent evaluation, TVA will report such discrepancies as appropriate.
PLLIC207/42
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ENCLOSURE 2 Tennessee Valley Authority Browns Ferry Nuclear Plant Commitments from Enclosure 1
- 1. Revise refueling operations procedure to address plant manager' responsibility for the spent fuel storage pools (SFSPs). This revision will be completed by December 23, 1991.
- 2. Revise refueling operations procedure to provide for recommendations from operations to the plant manager for the disposal of unusable non-fuel special nuclear material (SNM)/non-essential components in SFSP and a step which states the SFSP is only a temporary storage area for non-fuel SNM/non-essential components. This revision will be completed by December 23, 1991.
- 3. Complete vacuuming of SFSPs. Vacuuming will be completed by January 9, 1992.
- 4. Videotape SFSPs to ensure no non-fuel SNM is stored in SFSP.
Videotaping will be completed by July 1, 1992.
- 5. TVA will provide for an independent evaluation of SNM control and accounting by an outside organization. TVA expects this evaluation to be completed by July 1, 1992.
- 6. Maintenance Instruction i being revised to address proper torage of LPRM which will assure proper identification and accountability.
This revision will be completed by December 16, 1991.
- 7. Radwaste procedure is being revised to address cutting and packaging requirements for LPRM storage. This revision will be completed by December 16, 1991.
- 8. Dispose of non-essential components in SFSP. Disposal of non-essential components, excluding stellite rollers, will be completed by June 1, 1992.
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