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MONTHYEARML20151G7081988-07-20020 July 1988 Forwards Revised Emergency Operating Procedures Generation Package,Per Suppl 1 to NUREG-0737 Project stage: Other ML20206C6951988-11-0909 November 1988 Forwards Supplemental Summary Rept on Plant Dcrdr,Per NRC 880809 Safety Evaluation Request.No New Human Engineering Discrepancies Which Require Correction Before Restart of Unit 2 Exists Project stage: Supplement ML20236D4431989-03-17017 March 1989 Discusses NRC Concerns Re Supplemental Dcrdr Summary Rept, Dtd 881109.Determination of Restart Applicability of Human Engineering Discrepancies Per Suppl 1 to NUREG-0737 Seems Questionable.Meeting to Discuss Concerns Will Be Called Project stage: Meeting ML20245E0021989-04-21021 April 1989 Summary of 890406 Meeting W/Util at Plant Re Dcrdr Human Engineering Discrepancy Closure Status Project stage: Meeting ML20070K5361991-03-14014 March 1991 Advises That NUREG-0737,Item I.D.1 Re Dcrdr Implemented at Facility,Including Item II.K.3.27 Re Common Ref Level for Vessel Level Instrumentation.Sims Data Base Should Be Updated to Reflect Implementation Project stage: Other ML20082J1381991-08-22022 August 1991 Forwards Licensee Supplemental Summary Rept for Plant Dcrdr, Including Open Issues,As Requested in NRC SER Project stage: Supplement 1989-03-17
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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:NRC TO UTILITY
MONTHYEARML20062E6601990-11-13013 November 1990 Confirms Arrangements for 901119 Mgt Meeting at Plant Site to Discuss Unit 2 Restart & Project Plan & Separation of Units 1 & 3 from Unit 2.Proposed Meeting Agenda Encl ML20217A5361990-11-13013 November 1990 Confirms Arrangements for 901119 Mgt Meeting at Plant Site to Discuss Shutdown from Outside Control Room Test to Be Conducted in Startup Test Program ML20062D5421990-11-0707 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20062B2371990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20059M8281990-09-14014 September 1990 Confirms Conversation Between P Carier,Pj Kellogg on 900910 Re Management Meeting Scheduled for 900921 ML20058Q1901990-08-13013 August 1990 Ack Receipt of 900705 & 0802 Ltrs,Transmitting Objectives & Scenario Package,Respectively,For Exercise Scheduled for Wk of 900917 ML20058N8001990-08-13013 August 1990 Requests Provision of Listed Info Prior to Restart of Units 1 & 3.Performance of PRA for Unit 2 in Manner That Takes Into Account Dependencies to Equipment Located in Other Two Units Also Requested ML20058Q1191990-08-13013 August 1990 Forwards Insp Repts 50-259/90-20,50-260/90-20 & 50-296/90-20 on 900625-29 & 0709-13.No Violations or Deviations Noted ML20056A6101990-08-0202 August 1990 Advises of Closure of NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow, Per Util ML20055H8851990-07-25025 July 1990 Considers 900425 Request for Approval to Eliminate Site Local Recovery Ctrs Withdrawn.Review Terminated ML20059M8551990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C7691990-06-12012 June 1990 Advises That 900615 SALP Meeting Cancelled Until Later Date ML20248B2521989-09-27027 September 1989 Forwards Summary of 890914 Mgt Meeting in Region II Ofc to Discuss Problems Encountered When NRC Administered Exams During Wks of 890710 & 17,to Employees Currently Holding Licenses to Operate Plant ML20248D4701989-09-25025 September 1989 Confirms 890928 Meeting W/Util Re Adequacy of Station Procedures at Plant ML20248G9931989-09-22022 September 1989 Advises That 880413 Response to NRC Bulletin 80-001, Confirming No Use of Westinghouse Circuit Breakers in safety-related Applications at Plant,Acceptable ML20248E7131989-09-21021 September 1989 Forwards Insp Rept 50-260/89-36 on 890828-0901.No Violations Noted ML20248E6811989-09-20020 September 1989 Forwards Insp Rept 50-260/89-30 on 890313-24.No Violations Noted IR 05000260/19890291989-09-20020 September 1989 Forwards Insp Rept 50-260/89-29 on 890220-24.Open Items Identified.Closure of Remaining Open Items Required Prior to Facility Restart ML20247N9571989-09-15015 September 1989 Forwards Amend 15 to Indemnity Agreement B-52,reflecting Rev of 10CFR140, Financial Protection Requirements & Indemnity Agreements. Amend Reflects Increase from $160 to $200 Million in Primary Layer of Nuclear Energy Insurance ML20248C8371989-09-0808 September 1989 Revises Time for 890819 Mgt Meeting W/Util in Region II Ofc to Discuss Operator Requalification Program ML20247C9481989-09-0101 September 1989 Forwards Requalification Exam Rept 50-260/OL-89-01 Administered During Wks of 890710 & 17.Concerns Raised Re Operator Performance & Exam Administration ML20248B5981989-08-0101 August 1989 Advises That 890721 Revs to ASME Section XI Pump & Valve Testing Program SER Acceptable ML20247H5181989-07-17017 July 1989 Forwards Insp Rept 50-260/89-31 on 890426-0628.No Violations Noted.Open Issues Re Dynamic Model of Reactor Pressure Vessel,Including Internals & Supports,Which Incorrectly Assumed Existence of Seismic Restraints Noted in Rept ML20246G9251989-07-10010 July 1989 Provides Addl NRC Audit Insights Re Plant Risk Review for Info Helpful in Refinement of Response to Generic Ltr 88-19. NRC Recommends That Util re-examine Plant Emergency Operating Procedures Used in Recovery from Transient ML20246F0841989-07-0606 July 1989 Advises That 890601 Clarification to Granting Relief Request H-3 Re Changing Pressure Boundary for HPCI Sys from Valve 73-646 to Valve 73-645 Does Not Affect Request Acceptability ML20245K4401989-06-23023 June 1989 Forwards,For info,890605 Ltr Ack Receipt of Petition Filed by Ecology Ctr of Southern CA & States That Petition Is Being Treated Under 10CFR2.206 IR 05000259/19860351989-06-19019 June 1989 Addresses TVA Responses Submitted as Result of Notice of Violation & Insp Repts 50-259/86-35,50-260/86-35 & 50-296/86-35.Summary of Issues Identified & Resolution Based on Util Actions Also Encl.Nrc Considers Issues Resolved ML20246N2701989-06-15015 June 1989 Forwards Insp Rept 50-260/89-21 on 890123-24.Three Open Items Previously Identified in NRC Insp Rept 50-260/88-38 in Areas of Amplified Response Spectra Generation,Drywell Platforms & Electrical Conduit & Supports Reviewed ML20246N1721989-06-14014 June 1989 Forwards Insp Rept 50-260/88-39 on 881219-22.Six Addl Items Closed w/22 of Initial 32 Issues Identified in Insp Rept 50-260/88-38 Remaining Open.Remaining Open Items to Be Reviewed in Future Insps IR 05000259/19870371989-06-0909 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-259/87-37, 50-260/87-37 & 50-296/87-37 ML20244C6501989-06-0606 June 1989 Submits Findings Based on Review of NFPA Code Deviations Associated W/Preaction Water Sys in Plant Cable Spreading Room & Intake Structure IR 05000259/19890211989-06-0101 June 1989 Ack Receipt of 890505 Revised Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-259/89-21,50-260/88-21 & 50-296/88-21 IR 05000260/19880361989-06-0101 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 259/88-36, 50-260/88-36 & 50-296/88-36 ML20247M4681989-05-18018 May 1989 Forwards Insp Rept 50-260/89-15 on 890123-0203.Open Items Re IE Bulletin 79-14 & 79-02 Programs to Generate Calculations for safety-related Piping Noted ML20246M5751989-05-11011 May 1989 Informs That Plant Still Under Review by NRC & Should Be Considered as Table 1 Plant for Review of Generic Ltr 89-04 Re Guidance on Developing Acceptable Inservice Testing Program ML20247P2421989-05-11011 May 1989 Ack Receipt of Forwarding Detailed Scenario for Plant 890531 Radiological Emergency Plan Exercise IR 05000259/19880071989-05-10010 May 1989 Ack Receipt of 881103 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-259/88-07,50-260/88-07 & 50-296/88-07 ML20246M3771989-05-0909 May 1989 Forwards Safety Evaluation Accepting Util 890317 Proposed long-term Solution to Correct Rust Problems in Containment Spray Headers ML20246M4761989-05-0909 May 1989 Informs That Listed Schedular Commitments Fulfill Requirements in Responding to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment, Based on Review of Util ML20246M4971989-05-0808 May 1989 Advises That Util Response to NRC Bulletin 88-004 Re Potential safety-related Pump Loss Acceptable.Schedule for long-term Resolution Should Be Submitted 30 Days Prior to Restart IR 05000259/19880131989-05-0808 May 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-259/88-13, 50-260/88-13 & 50-296/88-13 ML20245H3031989-05-0101 May 1989 Forwards Safety Evaluation Accepting 831107 Response to Generic Ltr 83-28,Item 2.1 Re Vendor Interface Program ML20245H5511989-04-28028 April 1989 Advises That First Part of App R Insp Re post-fire Safe Shutdown Sys,Will Be Conducted During Wk of 890501-05 & Second Part Tentatively Scheduled for 890717-21 ML20245D8511989-04-19019 April 1989 Requests Schedule to Implement Alternate Rod Injection/ Reactor Trip Sys Design in Full Compliance W/Atws Rule, within 60 Days ML20245C8221989-04-14014 April 1989 Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facilities. Printout of TMI Items Annotated Where Tracking Sys Indicates That Implementation Incomplete,Encl ML20244C4051989-04-10010 April 1989 Forwards Insp Repts 50-259/88-36,50-260/88-36 & 50-296/88-36 on 881208-31 & Notice of Violation.Response to First Violation Should Include Util Actions to Correct Deficiencies in Configuration Control Program ML20244D0321989-04-0606 April 1989 Requests Revised Response to Violations Noted in Insp Repts 50-259/88-21,50-260/88-21 & 50-296/88-21 within 30 Days. Corrective Actions Do Not Adequately Address Condition Adverse to Quality Repts IR 05000259/19880281989-04-0404 April 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-259/88-28, 50-260/88-28 & 50-296/88-28 IR 05000259/19880321989-04-0404 April 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-259/88-32, 50-260/88-32 & 50-296/88-32 ML20248J9361989-04-0404 April 1989 Ack Receipt of 890120 Response to 881222 Notice of Violation from Insp Repts 50-259/88-24,50-260/88-24 & 50-296/88-24. Response Acceptable Per 10CFR2.201 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217E0711999-10-14014 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 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 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 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 ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program 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 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 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 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 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 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 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 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML20205T3771999-04-0909 April 1999 Informs That on 990317,R Champion & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Are Wks of 000612 & 26 for Approx 16 Candidates ML20205J2521999-04-0505 April 1999 Informs That Effective 990328,A De Agazio Assigned as Project Manager for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20205F9231999-04-0101 April 1999 Forwards SE Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST, Valve Program for Plant,Units 1,2 & 3 ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20205A1821999-03-19019 March 1999 Discusses Plant Performance Review of Browns Ferry NPP Completed on 990208.Determined Overall Performance to Be Acceptable.Security,Fire Protection,Radiation Protection & Plant Chemistry Continued to Be Effective ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20203G4971999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20199B0811999-01-12012 January 1999 Forwards Request for Addl Info Re GL 96-05, Periodic Verification Design-Basis Capability of Safety-Related Motor-Operated Valves, to Request That NPP Licensees Establish Program Effectiveness of Current Program ML20199E3791998-12-23023 December 1998 Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl ML20198N8111998-12-18018 December 1998 Discusses Open Mgt Meeting Conducted on 981217 in Region II Ofc to Present self-assessment of Util Performance.List of Attendees & Copy of Presentation Handout Encl ML20198N7481998-12-14014 December 1998 Discusses DOL Case 98-ERA-34,DC Smith Vs Tva.Forwards Synopsis of OI Rept 2-1998-011,completed on 981030 ML20197H4421998-12-0202 December 1998 First Final Response to FOIA Request for Documents.Records Listed in App a Already Available in Pdr.App B Records Placed in Pdr.Portions of App C Records Withheld & App D Records Being Withheld in Entirety (FOIA Exemption 5) ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20196D1031998-11-16016 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plans Through March 1999 & Historical Listing of Plant Issues,Called Plant Issues Matrix Encl ML20196C9651998-11-13013 November 1998 Forwards Copy of Answer Key & Master Bwr/Pwr GFE Sections of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl ML20195B9211998-11-12012 November 1998 Forwards Staff Assessment of Fatigue Evaluation,Accepting Licensee 980919 Response to NRC 980916 Request for Certain Plant Specific Design & Installation Details Re Insp & Repair of Plant,Unit 3 Core Spray Sys Piping Internal to Rv ML20195B9291998-11-10010 November 1998 Forwards Transcript of 981026,informal Hearing on 2.206 Petition Filed by Union of Concerned Scientists ML20195H4501998-11-0909 November 1998 Summarizes 981105 Open Mgt Meeting in Atlanta,Ga Re Site Engineering Performance.List of Attendees & License Presentation Handouts Encl ML20195C4631998-11-0909 November 1998 Informs That Effective 981105,L Raghavan Was Assigned Project Manager for Plant,Units 1,2 & 3 ML20155H4131998-11-0404 November 1998 Informs That on 981013,TVA Informed Staff That Amend Proposed by TVA Application No Longer Needed. Commission Has Filed Encl Notice of Withdrawal of Application for Amend to FOL with Ofc of Fr ML20155H4481998-11-0404 November 1998 Informs That on 981005 TVA Informed Staff That Amend Proposed by TVA Application & Revised on 970306 No Longer Needed.Notice of Withdrawal of Application for Amend to FOL Filed with Ofc of Fr ML20155A5031998-10-23023 October 1998 Informs of Withdrawal of TS Change 356,submitted on 951222. Federal Register Notice Re Withdrawal Will Not Be Published, Due to Staff Failure to Issue Notice,Per 10CFR50.91(a)(2) (I) ML20155H1211998-10-21021 October 1998 Confirms 981021 Telcon Between T Abney & T Morrissey Re Mgt Meeting Scheduled for 981105 in Atlanta,Ga to Discuss Recent Browns Ferry Nuclear Plant Engineering Performance & on-going Site Activities ML20155B6861998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators ML20154J6231998-10-0808 October 1998 Forwards Notice of Withdrawal of 971230 Application for Amend to Browns Ferry Nuclear Plant,Units 1,2 & 3 Custom TSs to Remove Identified non-conservatism Re Number of RHRSW Pumps Required for multi-unit Operation ML20154J8181998-10-0707 October 1998 Discusses Closure of TAC Numbers M92757,M92758 & M92759. Notice of Withdrawal of Application for Amend to Licenses DPR-33,DPR-52 & DPR-69 Encl ML20155A6561998-10-0202 October 1998 Confirms 980929 Telcon Between T Abney & H Christensen Re Mgt Meeting at Licensee Request Scheduled for 981217 in Atlanta,Ga to Discuss Recent Plant Performance & on-going Site Activities ML20154A4991998-09-30030 September 1998 Ltr Contract:Task Order 25, Browns Ferry Safety Sys Engineering Insp (Ssei), Under Contract NRC-03-98-021 ML20153H3041998-09-28028 September 1998 Forwards SE Accepting Util Proposed Alternatives Contained in Requests for Relief 3-SPT-3 & 3-SPT-4 for Second Interval Per 10CFR50.55(a)(3)(i) & Code Case N-546.INEEL TER in Support of Relief Requests Also Encl ML20155B4421998-09-22022 September 1998 Announces Plans to Conduct Ssei at Bfnp on 981116-20 & 981130-1204.Insp Objective Will Be to Evaluate Capability of High Pressure Coolant Injection Sys to Perform Safety Functions Required by Design Basis 1999-09-28
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Text
. ,
i UNITED STATES a-
)/"# t o NUCLEAR REGULATORY COMMISSION d <
., i WASHINGTON, D. C. 20555 I '
March 17, 1989
' Docket Nos. 50-259/260/296 Mr. Oliver D. Kingsley, Jr. l Senior Vice President, Nuclear Power Tennessee Valley Authority l 6N 38A Lookout Place !
1101 Market Street I Chattano'oga, TN 37402-2801
Dear Mr. Kingsley:
SUBJECT:
BROWNS FERRY NUCLEAR PLANT (BFN) DETAILED CONTROL ROOM DESIGN REVIEW (TACS56104,56105,56106)
We have completed our initial review of your supplemental Detailed Control Room l Design Review (DCRDR) sumary report of November 9,1988. While the task ,
l analysis and control room inventory documented in this . supplemental report l appear to adequately meet the NUREG-0737 criteria pertaining to these activities, your determination of the restart applicability of Human Engineering Discrepancies (HEDs) seems questionable. Our staff's concerns ,
arise from a comparison'of the HEDs with the Restart Criteria provided in l Table IV-1 of the Browns Ferry Nuclear Performance Plan (BFNPP). Specifically, Criterion 1 of this Table states: i l
The item identifies a specific deficiency which has significant probability of leading to the inoperability of a system required for ;
startup or operation by the BFN Technical Specifications.
The Category 1 HEDs enumerated in the supplemental summary report (HEDs 300 and 311) document deficiencies which may cause operator error and, therefore, result in challenges to critical safety functions. These conditions appear to meet the BFNPP restart criteria. As well, the staff feels that several otner HEDs of less severe categories (HEDs 299, 302, 305, 306, and 308) may also meet the restart criteria.
Following a sampling of HEDs identified during the original BFN DCRDR, we have also developed concerns regarding the restart applicability-of the following HEDs:
Category 1 12, 72, 189, 190, 273, 283, and 284 Category 2 157 and 280 ;
We desire to meet with your staff regarding the restart applicability of all l HEDs discussed in the preceding paragraphs. During this meeting, we would like to review your restart criteria against these HEDs and any documentation resulting from the restart evaluations performed on these'HEDs. TVA's l commitment to evaluate all HEDs versus the restart criteria was made during the DCRDR pre-implementation audit, and is documented on Page 13 of the Technical
^
8903230106 890317 '
.PDR ADOCK 05000259 [0(\
\ P PDC h 1 ?
Mr. Oliver, D. Kingsley, Jr. ..
Evaluation Report attached to our Safety Evaluation of the BFN DCROR' dated August 9, 1988. During this meeting, we would also like to discuss the restart evaluations and dispositions of all Category 1 and 2 HEDs documented in both the original and supplemental DCRDR summary reports. l If you have any questions regarding the above, please contact Gerald E. Gears at (301) 492-0767.
Sincerely, Suzann lack, Assistant Director
.for Projec+s TVA Projet ' Divisien Office of Nuclear Reactor Regulation cc: See next page l
l l
l
(
a
-- .---.____.___m._______ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _
i i
Mr. Oliver D. Kingsley, Jr. l 1
Evaluation Report attached to our Safety Evaluaticn of the BFN DCRDR dated i August 9, 1988. During this meeting, we would also like to discuss the restart l evaluations and dispositions of all Category 1 and 2 HEDs documented in both !
the original and supplemental DCRDR summary reports. j If you have any questions regarding the above, please contact Gerald E. Gears at (301) 492-0767.
Sincerely, )
Original signed by j Suzanne Black, Assistant Director j for Projects TVA Projects Division Office of Nuclear Reactor Regulation !
(
1 cc: See next page Distribution j Docket File NRC PDR Local POR j Projects Reading ADSP Reading D. Crutchfield B. D. Liaw (
i S. Black R. Pierson {
L. Watson W. S. Little M. Simms P. Castleman G. Gears D. Moran J. Rutberg S. Varga B. Grimes E. Jordan ACRS(10)
GPA/CA GPA/PA BFN Rdg. File
~
)
0FC :NRR:TVA/PM*:NRR:TVA/PM* :TVA:AD/TP* :TVA:AD/ :TV . /:
_____:____......__:_____________: .... ___...: ..___j >___:___ s y __.___________:___________
NAME :PCastleman :GGears :RPierson :SBlackl :BDL M': :
DATE :3/17/89 :3/17/89 :3/17/89 : 3 / 67/ 8 9 :3/d/89 : :
0FICIAL RECORD COPY 'f .
i
.- . .; . ,. 1 Mr. Oliver D. Kingsley, Jr. 1 Evaluation Report attached to our Safety Evaluation.of the BFN DCRDR dated-August 9,1988. During-this meeting, we would also like to discuss the restart
. evaluations and dispositions of. all Category 1 and 2 HED's documented in both the original and. supplemental DCRDR summary reports.
If you have any questions regarding the above, please' contact Gerald E. Gears at(301)492-0767.
Sincerely, i
Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation cc: See next page Distribution Docket File i
NRC PDR Local PDR !
Projects Reading ADSP Reading D. Crutchfield i B. D. Liaw ,
S. Black R. Pierson L. Watson W. S. Little M. Simms )
P. Castleman i G. Gears D. Moran J. Rutberg S. Varga B. Grimes E. Jordan
'ACRS (10)
GPA/CA GPA/PA BFN Rdg. File 1
~OFC ::NRR:TVA/FM :NRR:TVA/PM :TVA AD :TVA:AD L :TVA:D :
.....:...._____ ....________..:#, j /TP.typ:____:____
p.__.____..._____:___________.....______
NAME :PCastlema :
.GGe AF# :RP erson :SBlac :BDLiaw : :
.DATE:3//7/89 :3/\ /89 : 3/"7 /89 - :3/l' /89 :3/ /89' : :
0FFICIAL RECORD COPY 1