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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5741990-09-19019 September 1990 Forwards Rev 2 to Browns Ferry Nuclear Plant Cable Issues Supplemental Rept Corrective Actions,Sept 1990. Rept Revised to Clarify Cable Bend Radius & Support of Vertical Cable & Document Resolution of Jamming Issues ML20064A6871990-09-18018 September 1990 Requests Closure of Confirmatory Order EA-84-054 Re Regulatory Performance Improvement Program ML20059L4931990-09-17017 September 1990 Provides Addl Info Re 900713 Tech Spec Change 290 Concerning Hpci/Rcic Steam Line Space Temp Isolations,Per Request ML18033B5171990-09-17017 September 1990 Forwards Addl Info Re 900524 Tech Spec Change 287 on Reactor Pressure Instrument Channel.Schematic Diagrams Provided in Encl 2 ML20064A6851990-09-17017 September 1990 Responds to NRC Recommendations Re Primary Containment Isolation at Facility.Background Info & Responses to Each Recommendation Listed in Encl 1 ML20059K2971990-09-14014 September 1990 Responds to NRC 900208 SER Re Conformance to Reg Guide 1.97, Rev 3, Neutron Flux Monitoring Instrumentation. TVA Endorses BWR Owners Group Appealing NRC Position Directing Installation of Upgraded Neutron Flux Sys ML20059H3861990-09-10010 September 1990 Forwards Corrective Actions Re Radiological Emergency Plan, Per Insp Repts 50-259/89-41,50-260/89-41 & 50-296/89-41. Corrective Action:Plant Manager Instruction 12.12,Section 4.11.3.1 Revised ML18033B5031990-08-31031 August 1990 Forwards Financial Info Required to Assure Retrospective Premiums,Per 10CFR140 & 771209 Ltr ML20059E1741990-08-31031 August 1990 Informs That Plant Restart Review Board & Related Functions Will Be Phased Out on Date Fuel Load Commences ML20059D7061990-08-28028 August 1990 Requests That Sims Be Updated to Reflect Implementation of Program to Satisfy Requirements of 10CFR50,App J.Changes & Improvements Will Continue to Be Made to Reflect Plant Mods, Tech Spec Amends & Recommendations from NRC ML18033B4931990-08-20020 August 1990 Suppls Response to Violations Noted in Insp Repts 50-259/90-14,50-260/90-14 & 50-296/90-14.Corrective Actions: TVA Developed Corporate Level std,STD-10.1.15 Re Independent Verification ML20063Q2431990-08-20020 August 1990 Responds to 900807 Telcon Re Rev to Commitment Due Date Per Insp Rept 50-260/89-59 Re Electrical Issues Program ML20063Q2451990-08-17017 August 1990 Provides Revised Response to Generic Ltr 89-19 Re Request for Action Concerning Resolution of USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants & Notification of Commitment Completion ML20063Q2441990-08-17017 August 1990 Advises That IE Bulletin 80-11 Re Masonry Wall Design Implemented at Facilities.Design Finalized,Mods Completed, Procedures Issued & Necessary Training Completed.Sims Data Base Should Be Updated to Show Item Being Implemented ML20059A4861990-08-16016 August 1990 Responds to Verbal Commitment Made During 900801 Meeting W/Nrc Re Control Room Habitability.Calculations Performed to Support Util 900531 Submittal Listed in Encls 1 & 2 ML20059A5141990-08-16016 August 1990 Provides Response to NRC Bulletin 88-008,Suppl 3 Re Thermal Stresses in Piping Connected to Rcs.Util Does Not Anticipate Thermal Cyclic Fatique Induced Piping,Per Suppl 3 to Occur in Plant.Ltr Contains No Commitment ML18033B4821990-08-14014 August 1990 Submits Revised Response to Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Extends Completion Dates for Commitments to 901203 ML18033B4831990-08-13013 August 1990 Responds to NRC 900713 Ltr Re Violations & Deviations Noted in Insp Repts 50-259/90-18,50-260/90-18 & 50-296/90-18. Corrective Actions:Craft Foreman Suspended for Three Days & Relieved of Duties as Foreman ML18033B4811990-08-10010 August 1990 Responds to NRC 900710 Ltr Re Power Ascension Testing Program.Four Hold Points Selected by NRC Added to Unit 2 Restart Schedule ML18033B4801990-08-0808 August 1990 Forwards Response to SALP Repts 50-259/90-07,50-260/90-07 & 50-296/90-07 for Jul 1989 - Mar 1990 ML20044B2121990-07-13013 July 1990 Clarifies Util Position on Two Items from NRC 891221 Safety Evaluation Re TVA Supplemental Response to Generic Ltr 88-01 Concerning IGSCC in BWR Stainless Steel Piping.Insp Category for Nine Welds Will Be Changed from Category a to D ML18033B4371990-07-13013 July 1990 Forwards Corrected Tech Spec Page 3.2/4.2-45 to Util 900706 Application for Amend to License DPR-52 Re ADS ML18033B4331990-07-13013 July 1990 Requests Temporary Exemption from Simulator Certification Requirements of 10CFR55.45(b)(2)(iii) ML20055F6091990-07-12012 July 1990 Provides Response to NRC Bulletin 88-003 Re Insp Results. No Relays Found to Have Inadequate Latch Engagements. Therefore,No Corrective Repairs or Replacement of Relays Required ML18033B4251990-07-10010 July 1990 Forwards Cable Installation Supplemental Rept,In Response to NRC Request During 900506 Telcon.Rept Contains Results of Walkdowns & Testing Except Work on Ongoing Cable Pullby Issue ML18033B4241990-07-0606 July 1990 Advises That Util Expects to Complete Implementation of Rev 4 to Emergency Procedure Guidelines by Mar 1991.Response to NRC Comments on Draft Emergency Operating Instructions Encl ML18033B4201990-07-0505 July 1990 Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3. Util Has Concluded That Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issue,Subj to Listed Conditions ML18033B4091990-07-0202 July 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-259/89-53,50-260/89-53 & 50-296/89-53.Corrective Actions: Condition Adverse to Quality Rept Initiated & Issued to Track Disposition of Deficiency in Chilled Water Flow Rates ML20043G4901990-06-14014 June 1990 Forwards Tabs for Apps a & B to Be Inserted Into Util Consolidated Nuclear Power Radiological Emergency Plan ML20043H3511990-06-14014 June 1990 Forwards Corrected Pages to Rev 15 to Physical Security Contingency Plan,As Discussed During 900606 Telcon.Encl Withheld (Ref 10CFR73.21) ML20043F4951990-06-11011 June 1990 Advises That Facilities Ready for NRC Environ Qualification Audit.Only Remaining Required Binder in Review Process & Will Be Completed by 900615 ML18033B3651990-06-0808 June 1990 Forwards Revised Page 3.2/4.2-13 & Overleaf Page 3.2/4.2-12 to Tech Spec 289, RWCU Sys Temp Loops. ML18033B3391990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-259/90-08,50-260/90-08 & 50-296/90-08.Corrective Actions: Individual Involved Counseled on Importance of Complying W/Approved Plant Procedures When Performing Assigned Tasks ML20043D3251990-06-0101 June 1990 Responds to NRC 900502 Ltr Re Notice of Violation & Proposed Imposition of Civil Penalty.Corrective Actions:Snm Program Action Plan Being Developed & Implemented,Consisting of Improved Training for Control Personnel & Accountability ML18033B3551990-05-31031 May 1990 Forwards Response to 891219 Request for Addl Info on Hazardous Chemicals Re Control Room Habitability ML20043C1951990-05-30030 May 1990 Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues ML20043C0601990-05-29029 May 1990 Forwards Response to Violations Noted in Insp Repts 50-259/90-12,50-260/90-12 & 50-296/90-12.Util Admits Violation Re Access Control to Vital Areas,But Denies Violation Re Backup Ammunicition for Responders ML18033B3351990-05-25025 May 1990 Provides Basis for Closure of Generic Ltr 83-28,Item 4.5.3, Reactor Trip Sys Reliability. Analyses Presented in BWR Owners Group Repts Acceptable for Resolving Issues Subj to Listed Conditions ML18033B3221990-05-21021 May 1990 Forwards Rev 1 to ED-Q2000-870135, Cable Ampacity Calculation - V4 & V5 Safety-Related Trays for Unit 2 Operation, as Followup to Electrical Insp Rept 50-260/90-13 Re Ampacity Program ML18033B3101990-05-18018 May 1990 Responds to NRC 900417 Ltr Re Violations Noted in Insp Repts 50-259/90-05,50-260/90-05 & 50-296/90-05.Corrective Action: Senior Reactor Operator Assigned to Fire Protection Staff for day-to-day Supervision of Fire Protection Program ML20043A6101990-05-15015 May 1990 Forwards Rev 16 to Security Personnel Training & Qualification Plan.Rev Withheld (Ref 10CFR2.790) ML20043A4091990-05-14014 May 1990 Forwards Rev 14 to Physical Security/Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20043A4081990-05-14014 May 1990 Forwards Rev 15 to Physical Security/Contingency Plan, Consisting of Changes for Provision of Positive Access Control During Major Maint & Refueling Operations to One of Two Boundaries.Rev Withheld (Ref 10CFR73.21) ML18033B2921990-05-0909 May 1990 Provides Info for NRC Consideration Re Plant Performance for Current SALP Rept Period of Jan 1989 - Mar 1990.Util Believes Corrective Actions Resulted in Positive Individual Changes & Programmatic Upgrades ML20042F7401990-05-0404 May 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants.' TVA Will Finalize Calculations for Switch Setpoints Prior to Units Restart ML20042F7701990-05-0404 May 1990 Provides Results of Review of Util 890418 Submittal Re Supplemental Implementation of NUMARC 87-00 on Station Blackout.Implementation of 10CFR50.63 Consistent W/Guidance Provided by NUMARC 87-00 ML20042F3721990-05-0202 May 1990 Forwards Corrected Monthly Operating Repts for Jan-June 1989 & Aug 1989 - Jan 1990.Discrepancies Involve Cumulative Unit Svc Factors & Unit Availability Capacity Factors ML18033B2631990-04-12012 April 1990 Forwards Response to NRC 900212 Request for Info Re Power Ascension & Restart Test Program at Unit 2.Util Has Refined Power Ascension Program to Be More Integrated & Comprehensive ML18033B2551990-04-0909 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Repts 50-259/89-16,50-260/89-16 & 50-296/89-16.Corrective Actions: Contractor Will Perform Another Check Function Review for Mechanical Calculations & Area Walkdowns Will Be Conducted ML18033B2431990-04-0202 April 1990 Responds to NRC 900302 Ltr Re Violations Noted in Insp Repts 50-259/89-43,50-260/89-43 & 50-296/89-43.Corrective Action: Surveillance Insp Revised to Prevent Removal of All Eight Emergency Equipment Cooling Water Pumps from Water 1990-09-19
[Table view] |
Text
__ _,
. TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II October 19, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 By my letter to you dated September 22, 1983 we submitted a request to change the technical specifications of the Browns Ferry Nuclear Plant (TVA BFNP TS 191). The requested specifications enclosed with-the letter revise the pressure-temperature limit curves for hydrostatic pressure test, reactor vessel heatup and cool down, and nuclear core operation.
The enclosure to this letter provides additional information in support of TS 191 requested by your staff.
The enclosure includes information regarding chemical composition of reactor vessel material, end-of-life neutron fluence, and Charpy impact testing results. Please get in touch with us through the Browns Ferry Project Manager if additional information is needed.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Ma ager Nuclear Licensing Subscribed a sworn to beror me this. '/ dayof[O68[g, 1983 h0Atl/$ Y $ N Notary Public
,My Commission Expires _
Enclosure e oc: See page 2 8310280148 831019 PDet ADOCK 05000259 00l p PDR An Equal Opportunity Employer 8(3 a
a
,T Mr. Harold R. Denton October 19, 1983
.cc (Enclosure):
Mr. Charles R.. Christopher-Chairman, Limestone County Commission P.O. Box 188
-Athens, Alabama ~ 35611 Dr. Ira L. Myers State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 Mr. R. J. Clark U.S. Nuclear Regulatory Commission Browns Ferry Project Manager 7920 Norfolk' Avenue Bethesda, Maryland, 20814 _
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ENCLOSURE ADDITIONAL INFORMATION REGARDING REACTOR-VESSEL MATERIAL TOUGHNESS AND NEUTRON FLUENCE IN SUPPORT ~OF AMENDMENT REQUEST TVA BFNP TS-191 BROWNS FERRY NUCLEAR PLANT (DOCKET NOS.. 50-259, -260,_-296)
Attachment 1 - Reactor Vessel Beltline Material Toughness Data
~
Attachment'2 - GE letter dated February 9, 1971 - Information Regarding Neutron Fluence Attachment 3 - Browns Ferry unit 1.-' Analysis of Vessel Wall Neutron Dosimeter'- (report by Southwest Research Institute)
Attachment 4 - Browns Ferry units 2 and 3 - Analysis of Vessel Wall Neutron Dosimeter (two reports by Southwest Research Institute)
Attachment 5 - Fabrication and Testing of Reactor Vessel Material (report by TVA's Singleton Materials Engineering Laboratory).
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Table 1.. ,
Keactor Vessel.Deltline Material Toughness D.its ,
Browns Ferry Nuclear. Plant Units 1, 2, and 3 Shift in Finill RTNDT for RTNDT for-Minimum Initial' 40.F.FPY:
40EgPY.
-Heat Material Cu ' - NDTTs 50 ft }b/35 mil temp ( F) , RTNDT I 1/4T - .at:1/4T:
Component Unit No. Crade (5)1 (oF) ,PMWD 4 ,o. NMWDS,o (or) '(oF) (oF).
Dase Hetal 1 C-2884 SA 302 GRB 0.12 **
02 +34 - +543 0' 32 32 -
HAZ 1 .- Weld. - -03! +60 +803' +20 32 ~ .52 0.10 WELD 1- - Weld . +133 -
+38 +13 26 39-Pase Metal 2 A-0981 SA 302 CRB 0.14 -102 - -14 '+143 -10 39 ' 29
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Weld - 03 -40 -283 0 39 39.
WELD 2 -- Weld 0.20 03 - +18 0. ~ 58 - 58 ,
Base Metal 3 B-7267' SA 302 cRB 0.10 - 202. -36 .-183 ,
-20 ' 26 '6 IIAZ 3 - ' Weld - 03 +20 +473- 0' ,26' 26' WELD 3 - Weld 0.11 03 - ,-22 0 z 29 29 10ee letter fron T. F. Henry, Combustion Engineering, Inc., to' John Fox dated April 6,1993 20eneril Electric Company' letter from R. B.' Beers to H.'M. Bankus, " Reactor Vessel Surveillance Program",-dated February 9, 1971 (ecpy attached).
3 Estimated based on Branch Technical Position HTEB 5-2 (copy attached) and minimum valves from Charpy impact data prov'ded i by~
Singleton Laboratory (see attached memorandum from F. Van Meter to T. F. Ziegler dated August 11, 1983--L21 830812 112) kP arallel to rijor working direction Snormal to major workinc direction
- 6Determined by using minimum values from Charpy impact data provided by Singleton t.aboratory.
7The greater of NDTT or yC (50 ft Ib/35 mils) - 60 for NMWD 8Estimated using 1 above, Regulatory Guide 199 Curves (copy attached) and neutron fluence determined from flux wire testing (see,_
C16 790223 019 and L26 800318 883--copy attached).
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Interoffice Correspondence
.- POWER SYSTEMS
. April 6, 1983 Mr. John Fox Tennessee Valley Authority
Subject:
_ Materials Analyses .
Project No. 900051 -
Job No. 98120216 ~
MML-83-72 -
h3e L3e 3aa Wed
-Unit 1, Unit 1, Unit 2, Unit 3, Sampic: 2868 2884 E6B Unit 2, Unit 3 Unit 1, 65E EBM 67J-(P23079) (P23080) (P23031) Weld Plate (P23082) (D39368) (D39369) (D39370) ~
C .22 .27 .20 .18 .15 .16 .17 Mn 1.39 1.33 1.35 1.27 1.49 P .007 .008 1.50 1.45
.007 .007 .010 .011 S .009 .015 .011 .012
.007 .011 .012 .013 Si .23 .21 .19 .22 Ni .52 .09 .10 .09
.52 .55 .51 .33 Cr .07 .09 .28 .30
.11 .08 .08 .08 Mo .48 .46 .49 .06
.47 .49 .49 .48 V .002 .003 .002 .002 .003 .003 .003 Co. .009 .010 .012 .010 .011
.09 .010 .010 Cu .12 .14 .10 -
.20 Al .032 .11 .10
.035 .025 .015 .007 B <.001 <.001
.006 .010' e.001 s.001 <.001 <.001 W <.01 < 01 .01 <.001- "
<.01 <.01 c.01 <.01 As .006 .009 .015 .010 .013 .008 .009 Sn .006 .008 .013 .008 .009 .005 .006 Zr <. 001 <.001 s.001 <.001 <.001 <.001 <.001
'N .006 .007 .007 2 .005 .007 .006 .006 .
We certify that the information recorded above is an accurate copy of the data obtained from tests performed at the Metallur-gical and Materials Laboratory.
COMBUSTI N ENGINEERING, INC.
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\ ATOMIC POWEn cc TENT GENERAL' CLcCTnlO . COMPANY. 175 CUnTNCn AVE , - SAN JOSc. CAL.lf. 95125 Phone (108) 297 3000. TWX. NO. 910 336-011G ~ ~ ~ " '" M EW ;- - - - . ,
ncuvro FEB 1 2 1971
. tttr. R.11.1Dunham Letter No. BP 3'G93 etsien utenianc.6 .
~C hicC !!cchar.ical Engineer February 11, 1971 n 6 twe i t.m ser,s -
Tennessco Valley Authority *
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Tebruary 9, 1971 ,c.iy '# "' " g ,
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Mr. it. M. Banhus O'.1{-p/v> -;""' [-~ Z$ '
General Electric Company t iunai_ _, um i .
1301 llannah Avenue H. W.
Knoxville, Tennessee 37921
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Subject:
" Reactor Vessel Surve.illance Program .__.i i ._.J.'^ '
Reference:
TVA to GE Letter 6599 and 3-3336 T 6,
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'A
. We have attached numbered. Our answers a marked-up refer to the copy above of TVA Letter 6599 with the questions '( #
nuir.bers: e JF
- 1) shell
- 2) - According to our QC records, the following is the data on the f4K !!58 f,c,'. -
plate material:
6) lleat fio. Plate'No. NDTT ( F) I TVA I C-2884 6-139-19 0 C-2868 C-2753 6-139-20 6-139-21 0
-20 h-.'te.W-
/ /
TVA II o A-0981 6-127-6 -10 c'/,
D g to C-2467 6-127-10 -10 C-2849 6-127-20 -10 7 c./ /) /M TVA III C-3201 C-3188 6-145-1 6-145-2
-30
-30
/UM Ab. -
B-7267 6-145-6 -20
- 3) B!JI cites the second sentence of Par. 3.3.1 ("The Buyer can furnish a plan which the Seller may use as a guide.") as permission to use Appendix B and Drawings 11781549 and ll7B1500.in lieu of preparing the required document. G&W stated that they followed these documents in preparing the surveillance specimen. 8t.U states that the surveillance samples will be taken from either MK !!57 or 14K #58 plate mat ^-i.4 w.- - . . . . . .
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GEN ER Al @ ELECTRIC Mr.'H._M. Bankus February 9, 1971
'4) Further correspondence with BT,W has failed to obtain any further docu-
- 5) mentation or information beyond that described above. We are continuing to pursue this matter.
- 7) No special handling tools are provided for removal of the surveillance
- 8) specimen holders from the reactor vessel. The normal pool tool accessori.2 (J-hook, L-hook, . actuating pole, etc.), plus. the in-core detector cutter
_ are sufficient to remove, handle and prepare for shipment. Shipment is necessary because testing of the' individual specimen requires the services of a radiation-laboratory. It is left up to each customer to select the laboratory and contract for the particular services they desire.
Shipment is most easily accomplished by separating the specimen basket (intact with capsules containing-the individual specimen) from the sur-veillance holder pole. This is done with use of the in-core detector cutter. The basket is deposited in a small lead shipping cask and sent -
to the laboratory for processing. The remaining pole and handle assembly may be cut up and discarded as rad-waste.
- 9) GE would be willing to provide testing and evaluation service on irradiate
- 10) surveillance samples. Actual contract conditions will have to be negotiated through our Chattanooga office.
- 11) The maximum calculated integrated neutron dose (1 mov) on the vessel wal'.
12 is 3.80 x 1017 NVT. This exposure is expected to occur at an elevation 13 'three feet above the bottom of the active core at azimuthal positions 14 opposite the corner elements. The azimuthal positions are approximately 25*, 65*, 115 , 155 . 205*, 245*, 295 and 335 .
The calculated dose on the surveillance baskets at azimuthal locations c
. 30 , 120*, and 200 are equal and equivalent to
or 3.9 x 1017.NVT cm - sec at. rated power for 40 years. These values are based on the same calculati type as the maximum fluence base. The axial variation is assumed to be proportional to Figure 1.
The above data applies to all three units.
- 15) As stated in NED0-10ll5, Para. 5.7: "Because the boiling water reactor is a constant-temperature device, no special temperature monitoring devices are required." This has been confirmed by temperature monitot ing devices which had been installed in earlier plants.
./ o
. l'- _ G E N ERkt (h E LE CTRIC Mr. H. M. Banlius - -
.3- February 9,1971
_16 ) Two copics of NED0-10115 are enclosed.
This' completes ~our response to TVA 1.ctter 6599 and 3-3336.
t.l R.
B. B ,eers/l .h if -
_ Project Manager TVA Project JRO:kn Enclosure -
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General Electric ,,q CUSTONER ORDER.HO:- 205-55577- D A TE: _
10 8 ' N O :-- 5-2.5_.70 :
6.1.0.- 017 7- 51 Uni t # 1 TYPE OF MATEEIAL: Mn-Mo-Ni Cod - Case 1374 13 HO: 58A SPEclTICATION: u in?, <o - -A '
_ COMPON EN T S ER I A L nun'3ER:__.6-139-19 II'NN lie A T NO. i?. lC KH ESS: 6 1/8 Min .
- C l 1.in P l S Si Lukens C2884-2 .22- 1.33 .015 .016 Cr Ni no
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Sn l Fe
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l I EC H T O R O P if E I G H T - ASTM E206
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- F. T E EP.__i DEG. F FT. - LB- LATERAL 3-139-19T NF,NF 'F EXPASSION 5 SHEAR' F 0 F. i +10 33, 55, 34 .020, .038, 15, 20, 15 C2884-2 .026 6-139-193 NF,NF
+10 50, 44, 50' .036, .028, 35, 20, 25 Height - 3' .027 l Weight 100; Lbs. 240 Ft.-Lb. Energy. Load S PE C il!EN CODE HEAT HO. TENSILE Sil:EliCTH YlELD P0lHi ELOHCATION P.S.I. REDUCTION OF P.S.I. -- lH 2 INCHES AREA 5 BEN EST "3 - GRA'IN Silf' G-139-19T 88,250 69,500 26.6 68.2 Good' Ho:nogeneity 6 and C2884-2 J. - 13 9- 19B 92,250 69,750 OK Finer 24.2 69.3 f
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1600-1650 F. forfor 6:S lirs./ Brine Quench l l-6'; Mrs . /nrine Ouenci- .
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CATTOMER: Gene ral - Elec t ric , ,. s\'
CUST05ER ORDER Nc: 905-59577 CITE: 925-70 1.-
(Cf.XOf /510-019'h cil fini t //1 TTPE OF SATERIAL; Mn-Mo-Ni Code R^
Case 1 73 %
- C O ' '
SPECIFICATIONi ~3- O'>
M fc: 58A COMPONENT SERIAL NUIIBER: 6-139-20 6 1/8" Min. -
THICxnESS:
- 1) UNI}I HEAT NO. C Mn P S .Si Cr Ni Me
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f_ MOOF. 0 0F. +100F. TEMP. DEG. F EXPAHSION 0 INEA2 6-139-20T . F F NF,NF o F. +10 46, 55, 25 .035, .o4o, 35, 15, 35 .'
c2868- 2 .020 6-139-20B NF,NF +10 59, 56, 56 .c42, .041, 15, lo, 20 i-
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Height - 3' Weight - loo Lbs. 24o Ft.-Lb. Eriergy Load-SPECIMEN TENSILE STRENGTH TIELD P0lHT 5 ELONGATION HEAT HO. REDUCTION OF gEi C00- P.S.I. P.S.I. IN 2 !NCHES ARE) :
TEST I'~ID3 GRAIN. Sill i5-139-20T 86,500 68,000 27.3 69 9 Good Homogeneity 6 and.- .'
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D16 790223 U19 J. G. Dewease, Power Plant Superintendent, Browns Ferry ant Nuclear Pl H. J. Green, Chief, Nuclear Generation Branch, 727 EB-C FEB 2 81979 WALL NEUTADN DOS 4MTER FRett BR0 Attached are four copies of the completed report on s sthe analy i of the Browns Ferry unit I vessel wall dosimeter.
This analysis was performed to comply with the requirements of Browns Ferry Surveillance i (SI) 4.6.A.4. nstruction The results of the analysis do not meet the acceptance criteria of the above mentioned 51 Alch states that the experiment determined neutron-fluence. neutron fluence shall be less than ae the maximum The experimentally-determined neutron fluence for the end 10 I7 cn -2 of core cycle 1 at the inside diameter of the vessel was 5 64 x .
cm
-2
, while the calculated value of neutron fluence was 1.37 X II 10 Ve are therefore required to perform an analysis to determin e the ef fect of increased fluence on vessel-well embrlttlecunt HDT*
and RT Regulatory Guido 1.99 stipulates that the fluence value theatI/l.T (thickness) vessel wall location be used theshiftinRTbOT. Finure I e mas n ngthe basis for d f the same document presents a means to determine the shift in RT ET based on known fluence levels and material copper content.
In a letter from A. L. Vest, of General Electric Company, to me datud Decanbar 19, 1977, the curves of Figure I were extrapolated downward to allow determination of transitionperature tem shif ts at .the lower generating flux values for bolling eactors. water r A letter dated August 23, 1977, fmm J. E. Cllleland to A
. S chwence r, o f HRC, established an upper limit for plate and weld metal copper content of 0 30 weight percent.
Utillring this copper content, the projected 1/4T fluence value of 2.62 X 1016 c ,-1 per EFPY (derived frcro the '
product of 0.67 X 3 91 X 1016 c,-2
/EFPY taken frors the Swnl analysis),
and the extrapolated Figure 1 of Regulatory Culde , the 199 following chart l's generated. .
.s.
.. P.
~
J.' G. Dewease VALL. NEUTRON DOS! HETER FROM BROW EFPY 1/4T Fluence (ca~ ) Sh!ft In RT NDT F) 1 2.62 x 10 I 0 2
5.24 x 10 16 20 3 16 7.86 x 10 25 4
1.05 x loI7 29 5
1 31 x 1o17 33 6
1.57 x loI7 36 7
1.83 x loI7 38 8
2.10 x 1017 gi 9
2 34 x 10I7 43 to
~
2.62 x 10 I7 45 11 2.88 x 10I7 48 12 3.1% X 10 7 50 13 3.41 x 1037 52 14 3.67 x 10I7 54 15 3 93 x 10I7 56 16 4.19 x 1037 58 17 4.46 x 1017 60 13 4.72 x 10I7 61 19 4.98 x 1017 63 20 5.24 x loI7 65
- 'l 5 50 x loI7 66 22 5 76 x 1037 68 l 23 -
6.o3 x loI7 69 24 6.29 x 10I7 71 25 6.55 x 10I7 73 26 6.81 x loI7 74 27 7.07 x loI7 75 28 7 34 x loI7 29 76 7.60 x loI7 78
- 30 7.86 x 1037 79 l
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J.'G. Dewease VALL NEUTRON DOSIMETER FROM SR EL SEL Effl.
1/47 Fluence (ca' )
Shlft in RTNDT ( F) 31 8.12 X 10'7 80 32 8.38 X 10'7 81 33 8.65 X 10II 82 34 8.91 X 10I7 OS 83 9.17 x 1037 36 85 9.43 x 1017 66 37' 9.69 x 1017 g7 38 9.96 x 1037 68
~
39 30 1.02 X 10 40 89 1.05 x 10 18 90 lho operator's curvos for unit I will not be af fo,cted by the above-roforenced bottline curve shift in RTMDT unti the alghth effective full tow r yea r o f ope ra t i on s i nce t he non be l t l i ne reg ion cu rve i s dcrainan t until the beltlino curve shifts by 40* F.
The predicted end of-core life adjusted reference temperatura e at th l/4T position determines the specimen capsule renovel schedule in accordance with 10 CFR 50, Appendix H.
l Page 22 of the attached report contains a table which depicts two different specimen capsule removal schedules based on the initial RT RT f r,the unit NOT tM M tline region plates. N HDT I reactor vessel beltline region is obtained as follows.
A letter dated February 9,1971, from R. 8. Seers , of GE. to H. M.
cankus, of GE, specifies that the highest NDTT value for unit I reactos vessel beltline region plates is O' F.
l This value la dartved frora drop-
- might tests performed by the vessel manufacturer. Copies of the test l certificates for the llaiting heats (C2868 and C2884) show the drop- L I
welght tost, as well as the singla-temperature Charpy notchVImpact O
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J. G. Do m se
. SOUTHWEST RESEARCH INSTITUTE - FINAL RE70RT ON VALL NEUTRON 00SIMETER FROM BROMIS FERRY UtilT 1 PRES test results (longi tudinally-orlanted specimens) .
Section 8.1.1. (4) of
' Branch Technical Pcsition HTES 5-2, " Fracture Toughness ements Requir for Older Plants," specifles how to determloe the RT WT c rresponding to the plate material if limited Charpy V notch tests were performed et a single-temperature on specimens oriented in the longitudinal direction It states that .
the RT if the minimum absorbed energy Is less than !+5 ft/lbs .,
t4DT is estimated as 20' F above the test temperature RT . Therefore, HDT - 1 F (test temperature) + 20' F = 30' F.
Since the above value of RT NDT Is greater than 12* F, the end-of-core life adjusted reference tersperatura at the 100* F.
1/4T position will exceed This dictates a specimen capsule withdrawal schedule conforming to Section ll.C.).b, 10 CFR 50, Appendix H.
RT SInce the 50* F shift In NT ccurs at approximately the !2 EFPY point, which exceeds thn one-fourth servico life value of 10 EFPY, the first specimen capsule removal should occur at the 10 EFPY point.
(Hota that the table on pego 22 of the attached report i s incorrect for this estirmte.) Note however that the results of the specimen tests are not utilized to prodlet in RT WT, but to vertfy, the shift If needed, Figure 3.6-2 of the Drowns Ferry unit I tc,chnical specifications.
Cnple , of applienble sections of all referenced docunents ached. are att H. J. Green BOD CAM:RWC:08 Attachments ces ARMS PP, 823 EB-C
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