|
---|
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 DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT December 1, 1979-December 31, 1979 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By
- fi~c P ant S erintendent TABLE OF CONTENTS Operations Summary.Refueling Information Significant Operational Events Average Daily Unit Power Level lo Operating Data Reports 13 Unit Shutdowns and Power Reductions.
16 Plant Maintenance 19 Outage Summary~1~~~~~~26
0 erations Summar The following summary describes the significant operational activities during the reporting period.Tn support of this summary, a chronological log of significant events is included in this report.There were fourteen reportable occurrences reported to the NRC during the month of December.Unit 1 There were no scrams on the unit during the month.Unit 2 There were three scrams on the unit during the month.On December 2, the reactor scrammed due to abrupt movement of the turbine control valves apparently caused by EHC pressure control problems.The turbine control valves abruptly opened, then started closing, leading to a high neutron flux scram.The reactor was manually scrammed on December 13 to investigate vibration on the 2A recirculation motor, pump, and associated piping.On December 17, the reactor was manually scrammed for implementation of modifica-tions of certain PCIS valves and the installation of acoustic monitoring instrumentation on the MSRV's.Unit 3 0 erations Summa (Continued)
Unit 3 Unit startup (BOC-3)following a refuel outage began on December 6.The unit scrammed once during the month.On December 30, the reactor was manually scrammed to install overhead cables from the cooling tower switch gear to the bus tie boards.Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows: Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line Feedwater nozzle Closure studs 0.00421 0.20264 0.17644 0.00317 0.13592 0.11572 0.00283 0.10480 0.08561 Note: This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.
Common S stems Approximately 1.13E+06 gallons of waste liquid were discharged containing 2.75E+00 curies of activity.
Refuelin Information Unit 2 Unit 1 is scheduled for its third refueling beginning on or about January 3, 1980, with a restart date of February 19, 1980.This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel, LPCI modifications, installing acoustical monitors on KSRV's, and containment isolation modifications.
There are 764 fuel assemblies in the reactor vessel.The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies, two 8 x 8 R fuel assemblies, and 252 new fuel assemblies.
Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 720 assemblies.
With present capacity, Unit 1 does not have full core discharge capability in the pool.Unit 2'I Unit 2 is scheduled for its third refueling beginning on September 1, 1980, with a scheduled restart date of October 7, 1980.Resumption of operation on that date will require a change in technical specifications pertaining to the core thermal limits.Licensing information in support of these changes will be submitted to the NRC before the outage.This refueling involves replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.
There are 764 fuel assemblies in the reactor vessel.At the end of the month, there were 132 discharged cycle 1 fuel assemblies and 268 discharged cycle 2 fuel assemblies in the spent fuel storage pool.The present storage capacity of the spent fuel pool is 1080 assemblies.
With present capacity, the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
Refuelin Information (Continued)
Unit 3 Unit 3 resumed power operation December 8, 1979, after its second refuel outage which began August 24, 1979.Unit 3 is scheduled for its third refueling beginning on September 6, 1980, with a scheduled restart date of October ll, 1980.This EOC-3 refueli'ng involves loading additional 8 x 8 R (retrofit) assemblies into the core.There are 764 fuel assemblies presently in the reactor vessel.There are 144 discharged cycle 2 fuel assemblies and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool.The present storage capacity of the spent fuel pool is 1528 assemblies.
With present capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
Si nificant Operational Events Unit 1 Date Time Event 12/01/79 0001 0020 0150 0700 Reactor thermal power at 92%, core limited Reduced thermal power from 92%to 80%for turbine C.V.tests and SI's Turbine C.V.tests and SI's completed, commenced power ascension Reactor thermal power at 91%, core limited 12/03/79 1500 12/05/79 0700 12/07/79 2115 2143 2310 Reactor thermal power at 90%, core limited Reactor thermal power at 89%, core limited Reduced thermal power from 89%to 75%for turbine C.V.tests and SI's a Turbine C.V.tests and SI's completed, commenced power ascension Commenced PCIOMR from 82%thermal power 12/08/79 1500 12/10/79 0700 1500 12/12/79 1500 12/14/79 2300 12/17/79 1500 12/21/79 1500 12/30/79 0930 1620 1730 Reactor thermal power at 89%, core limited Reactor thermal power at 88%, core limited Reactor thermal power at 88%, core limited Reactor thermal power at 87%, core limited Reactor thermal power at 86%, core limited Reactor thermal power at 85%, core limited Reactor thermal power at 84%, core limited Peduced thermal power from 84%to 73%for control rod scram testing Control rod scram testing completed, commenced power ascension Reactor thermal power at 84%, core limited 12/31/79 2400 Reactor thermal power at 84%, core limited Si nificant 0 erational Events'Unit 2 Date Time Event 12/Ol/79 0001 1200 12/02/79 0555 0755 1202 1417 1439 12/03/79 0020 0755 1500 Reactor thermal power at 65%, sequence"B" with power ascension in progress Commenced FCIOM from 80%thermal power Reactor scram no.89 from 100%thermal power (suspected (1)EHC pressure regulator printed circuit board problems caused the turb control valves to open excessively and then abruptly began closing)Commenced rod withdrawal Reactor critical no.100 Rolled T/G Synchronized generatory, commenced power ascension , Reduced thermal power from 70%to 65%for control rod pattern adjustment Control.rod pattern adjustment completed, commenced power ascension Reactor thermal power at 70%, holding for"A" reactor feedpump vibration checks 12/05/79 0040 0400 Commenced power ascension from 70%thermal power Reduced thermal power from 90%to 70%for removal of"A" reactor feedoump from service for maintenance 12/08/79 0030 0220 0730 Connnenced turbine C.V.tests and SI's Completed turbine C.V.tests and ST.'s, commenced power ascension from 70%thermal power Reactor thermal power at 75%, holding for"A"'reactor feedpump maintenance 12/09/79 2200"A" reactor feedpump maintenance completed, connnenced power ascension 12/10/79 0130 2348 Commenced PCXOHR frcm 80%thermal power Reactor thermal power at 96%, holding due to excessive vibration on"A" recirculation pump 12/10/79 0700 Reduced thermal power from 96%to 94%due to excessive vibration on"A" recirculation oump 12/13/79 2000 2204 Commenced reducing thermal power to shutdown for"A" recirculation pump maintenance Reactor scram no.90 manual from 40%thermal power to acconnnodate maintenance to"A" recirculation pump 12/14/79 2005 Maintenance completed on 2A recirculation pump, holding for maintenance on FCV-1-55 valve 1
Si nificant 0 erational Events Unit 2 Date Tfrae Event 12/15/79 1821 1930 2347 IMntenance completed on FCV-1-55 valve, commenced rod withdrawal for startup Reactor critical no.101 Rolled T/G-could not reach rated spped, EHC problems (electronic card)12/16/79 0118 0125 0330 2300 Turbine tripped Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOHR from 78%thermal power 12/17/79 0035 0245 2122 2220 Reactor thermal power at 85%, holding for turbine C.V.tests and SI's Turbine C.V.tests and SI's completed, commenced PCIONR from 85%thermal power Commenced reducing thermal power from 90%for shutdown for modifications Reactor scram no.91 manual from 35%'hermal power to accommodate PCIS post modification 12/18/79 0910 Reactor at cold shutdown 12/22/79 2300 2345 PCIS'post modification tests completed, commenced rod withdrawal Reactor critical no.102 12/23/79 1535 Rolled T/G 1611 Synchronized generator, commenced power ascension 12/24/79 0135 12/25/79 1500 12/28/79 2325 Commenced PCIOMR from 50%thermal power Reactor thermal power at 85%, flow limited Reduced thermal power from 85%to 50%for control rod scram testing 12/29/79 0200 0500 Control rod scram testing completed, commenced power ascension Commenced PCIOHR from 65%thermal power 12/30/79 1500 12/31/79 2400 Reactor thermal power at 98%, flow limited Reactor thermal power at 98%, flow limited Si nificant 0 erational Events Unit 3 Date TMe Event 12/01/79 0001 1245 1325 1450 2045 Reactor shutdown for EOC 2, with BOC 3 fuel loaded in vessel Commenced pressurizing reactor vessel for hydrostatic test Reactor vessel pressure at 1005 PSI, holding for hydro-static test Commenced reducing reactor pressure to 570 PSI, holding for drywell leak checks Reduced reactor pressure to zero 12/06/79 0400 0645 Commenced rod withdrawal for startup Reactor critical no.88 12/08/79 1441 1615 Rolled T/G Synchronized generator, commenced power ascension as conditions allow 12/15/79 2330 Reduced thermal power from 80%to 66%for RTI's 23A, 22 and 32A 12/17/79 2000 12/18/79 1145 12/20/79 0830 2005 RTI's completed, commenced power ascension Reactor thermal power at 79%, flow limited Reduced thermal power from 79%to 60%for control rod pattern adjustment Commenced power ascension 12/21/79 0300 12/23/79 0706 0745 1100 2200 Commenced PCIOMR from 64%thermal power Reduced thermal power from 98%to 70%due to"A" and"B" string high pressure heaters isolation High pressure heaters"A" and"B" returned to service, commenced power ascension Commenced PCIONR from 88%thermal power Reactor thermal power at 97%, flow limited 12/24/79 1926 2114 2300 Reduced thermal power from 97%to 57%for control rod sequence exchange from"A" to"B" Control rod sequence exchange completed, commenced power ascension Commenced PCIOtlR from 67%thermal power Si nificant 0 erational Events Unit 3 Date Tame Event 12/26/79 0850 1145 Reduced thermal power from 92%to 86%for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced PCIONR from 86%thermal power 12/27/79 0600 1800 1930 2245 Reactor thermal power at 98%, flow limited Reduced thermal power from 98%to 80%for condensate demineralizers"A" and"3" backwash and precoat"A" and"B" condensate demineralizer placed in service, holding for"C" and"H" condensate demineralizer backwash and precoat"C" and"H" condensate demineralizer placed in service, commenced po~er ascension 12/28/79 0300 0700 1257 Commenced PCIOMR from 90%thermal power Reactor thermal power at 98%, flow limited Reduced thermal power from 98%to 85%for condensate demineralizer maintenance 12/29/79 2002 Condensate demineralizer maintenance completed, commenced power ascension 12/30/79 0700 2000 2230 Reactor thermal power at 98%, flow limited Commenced reducing thermal power for shutdown to install overhead cables from cooling tower switchgear to bus tie boards Reactor scram no.79 manual from 35%thermal power to accommodate maintenance 12/31/79 2400 Unit at cold shutdown (1)Equipment malfunction 10 AVERAGE DAILY UNIT POWER LEVEL DOCKET>NO.UNIT DATE MONTH December 197.9 DAY.AVERAGE DAlLY POWER LEVEL (MWe Net)964 DAY AVERAGE DAILY POWER LEVEL (M We.Net)915 l7 3 IO l2 I3 14 IS l6 953 953 933 934 952 938 943 929 926 926 915 920 IS 19 20 2,1 22 23'>5 26 27 2S'>9 30 3l 910 908 905 895-910 895 897 890 892 870.916 844 838 877 INSTRUCTIONS On this format.!ist the average daily unit power level in MWe.Net for each day>n the rep<>rtine
>n>>nti>.Ci>mpute tu the nearest whole megawat t.
~~AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.v UNIT DATE 1-0-80 CO~IPLETED BY TELEPHONE iE(ON TH December 1979 DAY AVERAGE DAILY POWER LEVEL (M We-Net)DAY AVERAGE DAILY POWER LEVEL (MWe-iVet) 17 3 7t 10 12 13 l4 IS 16 676 819 805 810 800 807 965 1031 1013 916-13 541 18 19 20 21 23 25 26 27 28 29 30 3I-12-10-10 136 680 865 897 887 801 1045 1062 INSTRUCTIONS On this format.list the average daily unit pi>wer levei'n l>I'tVe.Net for each day in the repi>rtinu lnontll.Ci>ltlpute to the nearest whole tnega.vat t.[9l77 s 12 AVERAGE DAlLY UNIT POWER LEVEL'DOCKET NO.50 296 T Browns Ferry 3 DATE~E!COMPLETED BY Ted Tham MONTH~'December 1979~r DAY AVERAGE DAlLY P01UER I.EVEL (!tI We-Net)I-10-10 DAY AVERAGE DAILY POWER LEVEL (hI1Ve.Net)
~689 839 3 IO l2 l3 l4 IS-10 38 163 223 353 477 515 68 812 724 l9 20 21 23 24 TS 26 27 28 29 30 31 837 633 747 959 1008 983 808 974 1002 1049 871 963-12 INSTRUCTIONS On this format.!ist the average daily unir power level in Mac Nct for each day in thc reportin!t ntonth.Compute to tNe rtearcst whole megawatt;I')t77) 13 OPERATING DATA REPORT DOCKET NO.1~5-80 COMpi,ETED BY~Do Green TELEPHONE~o U29-6846 OPERATING STATUS Notes 1.Unit Name 2.Reporting Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross<II We): S.Design Electrical Rating (Net M1Ve): e e cit e'OWe: 0 8.4 1065 7.Maxuntum Dep ndabl Capa y(N ti)8.If Changes Occur in Capacity Ratings (Items Numoer 3 Through 7)Since Last Report, Give Reasons: N A 9.Povver Level To Which Restricted, If Any (Net MWe): 10.Reasons For Restrictions, lf Any: N/A This M on t h Yr.-to.Date 744 12.Number Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On-Line 744 IS.Unit Reserve Shutdown Hours 0 0'.16.Gross Thermal Energy Generated (MWH)17.Gross Electrical Energy Generated (MWH)7,700,460 Ih.Net Electrical Energy Generated (M}VH)7,495,748 19.Unit Service Factor, 100 90.4 20;Unit Availability Factor-~100 90.4 21.Unit Capacity Factor (Using ilIDC Net)80.3 22.Unit Capacity Factor (Using DER Net)23.Uiiit Forced Outage Rate 0 4.4 24.Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duratinn of Each}: Refuel January 1980 Cumulative 47',498 28,277.28 0 74 136 493 24,518,460 23,801,968 58'58.1 47.1 47.1 33.0 25.If Shut Dnwn At End Of Rcport Period.Estimated Date of Startup: '26.Uiiits in Test Status iPri<<r to Coinmercial Operation}:
Forecast Achieved INITIAL CRlTICALITY INITIAL ELECTRlCITY COi'it'll ERCIA L OPERATION io/77) a~I OPERATING STATUS OPERATING DATA REPORT DOCKET NO 5 1-260 BETE 1~5-BO C05tPLETED BY~&Green TELEPHONE~~o-6846 Notes 1.Unit Name: 2.Reportfng Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Cross MWe): 5.Design Electrical Rating (Net MWe): 6.Maximum Dependable Capacity (Gross hIIVe): 1098.4 7.Maximum De endable Ca acit Net hllVe: 1065 p p y()8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: N/A ,5 9.Power Level To lVhich Restricted, If Any (Net MWe): 10.Reasons For Restrictions, If Any: I I.Hours In Reporting Period 12.Number Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On.Line 15.Unit Reserve Shutdown Hours.16.Gross Thermal Energy Generated (MWH)17.Gross Electrical Energy Generated (MWH).18.Net Electrical Energy Generated (MWH)19 Unit Service Factor 20., Unit Availability Factor 21.Unit Capacity Factor (Using hlDC Net)2'2.Unit Capacity Factor (Using DER Net), 23.Unit Forced Outage Rate 24.Shutdowns Scheduled Over Next 6 Months This Month Yr:to.Date 744'760 73.1 73e1 58.3 86.7 86.7 79.8 10.3 2.7 (Type.Date.and Duration uf Each):~571.03 7,766.19 172.97 298.23 543.98~7,596.45 0 1,458,581 22,703,212 475,610 7,636,280 461.952 7,441.305 Cumulative 42 409 24,484.48-.11,774.94.
23,664"31 66,155,000 21,950'b 21,3315469 55.8 55.8 47.2 47.2 36.8 5'25.If Shut Down At End Of Report Period, Estimated Date of Startup: 26.Units In Test Status (Prior tn Commercial Operation):
e INITIAL CRl'I'ICALITY INlTlA L ELECTRIC lTY COMht ERC I A L OPER ATlON Forecast Achieved (o/77) 15 OPERATING STATUS, OPERATING DATA REPORT Notes DOCKET NO SQ-296 DATE E-5 ED COMPLETED BY~~MD TELEPHONE~~-6846 1.Unit Name'.Reporting Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross hIWe): S.Design Electrical Rating (Net MIVe): 6.ihlaximum Dependable Capacity (Gross MWe): CI IWe 7.Maxtmum Dependable Capa ty (Net h).8.If Changes Occur in Capacity Ratings (Items Nxmber 3 Through 7)Since Last Report, Give Reasons: 9.Power Level To Which Restricted, lf Any (Net>IWe): 10.Reasons For Restrictions, lf Any: This Month Yr..to.Date Cumulative 11.Hours ln Reporting Period 12.iNumber Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On-Line IS.Unit Reserve Shutdown Hours'6.Gross Thermal Energy Generated (MWH)1.7.Gross Electrical Energy Generated (MWH)18.Net Electrical Energy Generated (MPH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (Using MDC Net)22.Unit Capacity Factor (Using DFR Net)23.Unit Forced Outage Rate 24.Situ(downs Scheduled Over Next 6 hlonths (T 591.75 131.50 534.25 5 816.35 552.9 5,708.30 1 231 495 403,790 390,613 16 956 484 5 635,080 5,482,585 71.8 4 65.2 8.8 49.3..--58.8 4.6 8.0 ipe.Date.and Duration of Each): 18 907.55 1,658.31.18438.28 53.107 866 17 402,580 16,887,773 74.2 74.2 63.8 9.0 S.If Shut Down At End Of Report Period.Estirrared Date of Startup: 6.Units ln Test Status (Prior to Commercial Op;mtion):
Forecast Achieved liVITIA L CRITICALITY INITIAL ELECTRICITY COhth(ERCIAL OPERATIC'E
.-UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT h(ONTII DOCKET NO.UNIT NAME DATE COhlPLETED IIV TELEPilONE rowns erry 1 o t:re en 205 29-68t'r6 Nii.nate~II fl I t4 cc Cl CA O Lieenscc Event Report 0'Cl 0 C E~Q Cause k.Corrective Action to Prevent Recurrence I F: Forced S: Scheduled (st/77)Reason: A.l'.quipmcot Failure (Explain)0-hiaiotcoaoce or Test C-lfefueling D Regulatory Restriction E"Operator Training k Liccnsc Examination I'.A J toinist rat ive C.Operational Error (Fxplain)ll Other (I:xplaht)
'(ethod: I hlaoual 2.hlanual Scram.3-Automatic Scram.4 Other (Explain)Exhibit C-Instructions for Preparation ot Data L'otry Sheets (or Licensee Eveot Report (LER>Flic (80REC-OI6I)Exlubtl I~Saroi Soon.e
--UNIT SIIUTDOWNS A4D POIVER REDUCTIONS REPORT hlOHTII DOCKET NO.50-260~UNIT NAME Browns Ferr 2 COhIPLETED IIY I<o l)ale C<r<Cl Q~r<C<~CJ c u~CA g Licensee Event Report¹<C<0 0'n cn G Cause 8'c Corrective Acttort to Prcvcnt Recurrence 109 791202 8.73 A.3 Suspected EliC pressure regulator printed circuit board problems, caused control valve closure and turbine trip.110 791213 53.44 Maintenance to"A" recirc pump and.FCV-1-5.'ll 791217 137.85 Pcs t modifications to the primary containment isolation system.112 791228 B Derated for control rod scram testin F: Forced S: Scl<eduletl
(<I/77)Reason: A-Equipment Failure (Explain)I}.hlaintenance or Test C Rcfuclittg D.Regulatory Restriction E Operator Training lc License Examination I'dllltntslrall"e G Op<'tattuttal Error (Fxplain}I I Otlt<'r (L<xplattt}
Method: I.hlanual 2rManual Scram.3-Aulomalic Scram.4.0tlter (Lxplain}Exltibit G-Instructions for Pret)aratiott of Data Entry Sheets I'or l.icensec Event Report (I.ER)Fii<s(NOREG-OI 6 I}Exhibit I~Sante Source
---VNIT SIIVTDOIVNS AND POlVER REDVCTIONS REPORT hIO")TII DOCKET NO.50 296 UNIT NAh!E DATE COhIPLETED BY Mn~tJ:a Ni I, Dull.'b I I Vl u V c u~-n tl AA Lice<<scc Event Rcport~Cause Ec Corrective Aetio<<tu Prcvcnt Rccurrcncc 109 110 791201.791220 791924 S 184.25 H Refueling Derated for control rod pattern adjustment.
Derated for control rod sequence exchange.112 791230 P 25.50 Ground in auxiliary power supply cables from cooling towers,to bus tie boards.Installation of over-head cables in progress.F: Forced S: Scheduled (It/77)Reasun: A.Equipmenl Failure (Explain)Il.hl;tintcnance or fest C-Rct'<<eliot, D.l<cttulatory Reslrictiun E-Ot>eratur Trainint', k Liccnsc Examination F-A Jlntrlist lative G Opclatil>>lal Lrrur (Explain)I I Other ((explain) 3 hlethod: I'hla<<ual 2-hlanual Sera<<i'.3 Auto<<latic Scram.4.Other (Explain)Exhibit G-Instructions for Preparatiun
<<I'Data Entry Sheets I'or l.ice<<see Event Report (LLR)Flh'WOREG-016I), Exhibit I-Salnc Source
CSSC E UIPMENT BROWNS FERRY NUCLEAR PIANT UNIT 1 MECIKHICAL MAINTENANCE SU%MARY ZR-DATE SYSTEM COi fPOHENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF Tl1E REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 12/9 HPCI FCV 73-16 Bad pinion gear With NPCI inop-able it could force unit shutdown Operation NPCI inoperable Replaced pinion gear in valve limitorque 12/13 Rx.Bldg.Uent.Computer Room Exhaust damper Damper closed None I Unknown Hone Opened damper and hooked linkage bac u 12/13 Fuel Pool Cooling"lA" FPC pump discharge check valve Disc pins broken None Operation None Replaced with r.ew valve 12/22 Fuel Pool Cooling"lA" FPC pump Internal part worn None Operation None Replaced all internal parts CSSC E UIPMENT BROWNS FERRY NUCLEAR FIANT UNIT 2 MECHANICAL MAINTENANCE SUl&fARY For the Month of DATE SYS TEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE
'QlE REACTOR CAUSE OF'ALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURREkacE 12/17 CRD"B" CRD discharge filter Dirty filter None Operation None Changed filter 12/17 Main Steam FCV-1-55 Pressure seal leak None OPeration None Disassembled, cleaned and installed new pressure seal rin~12/20 Radwaste FCV 2-77-2A Bad solenoid None Operation None Installed new solenoid valve BROWNS FERRY NUCLEAR PLANT UNIT 3?KQQQlICAL MAINTENANCE
SUMMARY
For the Month of December 19 79 SYS 621 COMPONENT NATURE OF HAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 12/1 Control Bay Vent"3A" Control Bay Chiller Nater Regu-lating Valve Bad Valve None Operation None Rebuilt valve 12/12 Auxiliary Boiler HCV 3-12-708 Bad packing glanQ leak None Operation None 12/19 Rx.fiater Cleanup FCV 69-60B Packing leak None Operation None Repacked valve CSSC E UIPENT BRO',FANS PERRY NUCLEAR PLANT UNIT 1 ELECTRICAL MAINTENANCE SENARY~For the Month of December 19 79 Date System Component Nature of Maintenance E ect on a e-Operation of The Reactor.Cause of Malfunction Results of Malfunction Action Taken To Preclude.Recurrence 12/9/79 HPCI FCV'73-16 HPCI turbine steam supply valve motor HPCI auxilia~oil pump will not start from control room HPCI inoperable at the time of failure Failed limit switch Auxiliary oil pump will not start Replaced limit switch.Auxiliary oil pump now starts as required.TR 146244 12/10/7 HPCI FCV-1-73-16 HPCI turbine steam supply valve motor Failed limit switch HPCI-inoperable at the time of failure Failed limit switch on FCV 73-16 t Valve inoperable Replaced torque switch, ran EMI 18.Checked OK.TR 161333 12/12/79 250V battery board 1A 250V bat-tery board HPCI gland seal conden-ser blower motor ground-'ed None Motor grounded Motor failed to operate Replaced motor.Checked OK.TR 149686 12/31/79 Common unit 90-51 neutron monitoring Motor that drives pumps is locked up, blowing fudes None Bad motor Cam inoperable Replaced bad motor, started unit.Checke OK.TR 161539 CSSC E UIPMENT PROSER PERRY NUCLEAR PLP3lT URYT 2.ELECTRICAL MAINTENANCE SALARY For the Month of December 19 79 Date System Component Nature of Maintenance ect on a e Operation of The Reactor.'ause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 12/14/79 I Hain steam FCV'2-1-55 steam line drain valve motor Green light Not applicable and open limit switch not working right Limit switch drive frozen False indication Replaced limit switch drive and gear key per EMI 16 and 18.Checked OK.TR 134713 12/20/79 Ventila-tion 8-3 drywell air blower motor Breaker trips out when try-ing to start None Motor grounde'd Motor failed to operate Replaced motor.Checked OK.TR 122352 EROUMR PERRX NUCLEAR PLY~VX tRlXX 3 ELECTRICAL MAINTENANCE Sl&QSRY Fore Month of December 19 79 Date System Component Nature of Maintenance ect on a e Operation of The Reactor.Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 12/4/79 Diesel generator D/G.3C failed to accept load on emergency load acceptance test Hi voltage supply None U-3C diesel generator frequency gen-erator was supplying too high voltage to SSPl and SSP2 Too high voltage Adjusted air gap.on frequency generator pickup to reduce supplied voltage to correct valve.Checked OK.TR 96702 BFRO 50 296/7923 12/5/79 Core spray FCV 75-50 (core spray II test valve)motor Motor failed to operate None SBM switch controls HIY were not ma!'ing Up Valve would not operate.Replaced SBM switch, functional.
Cheeked OK.TR 146429.
CSSC E UIPOKNT BROGANS 1ERRY NUCLEAR PLQ<T UNIT INSTRU?fENT MAINTENANCE SUGARY~FOR TI?E MONTH OF December 19 79 Init 1 2-10.2-31 SYSTHf Neutron Monitoring CO~fPOHENT FI-67-9A AERf-A NATURE OF?fAINTENANCE Calibr,ate Calibrate EFFECT ON SAFE OPERATION OF THE REACTOR None None CAUSE OF?fALFUNCTION Instrum nt Drift Instrument Drift RESULTS OF?fALFUNCTION Flow Indicator Pegged Upscs,le Rod Block came in with lg LPRM's in-stead of 13 ACTION TAKEN TO PRECLUDE RECURRENCE None None Init, 2?0?K Init 3 2-13 Standby Die el Generator 3D Air Com-pressor.Pres-sure Switches Calibrate None Setpoint Drift Air Compressor shut off 3 PSI low None 2-26 Standby Diesel Generator 3A Diesel Replace Generator Fue1 Pressure Gage None Leaking Gage Diesel Fuel in gage None 2-26 Radwa ste Lls 77 ll)B Clean None Static on Meter Face Static Charge Caused Indicator to Stick Hone 26 OUTAGE
SUMMARY
December 1979 The Unit 3, cycle 2 refuel outage was completed on Saturday, December 8, 1979, marking the completion of a 107 day modification, maintenance, and refuel outage.Unit 2 was shutdown on December 17 for modifications to the primary con-tainment isolation system and installation of an accoustic monitoring system for the main steam relief valves.During this outage, approximately 80 percent of the repair items on the Unit 2 short outage list were completed as well as the PCES and accou tic monitoring mods.Unit 2 was returned to service on December 23.Unit 3 was shutdown on December 30 for a modification to install an alternate power supply from the cooling tower transformers to the Unit 3 shutdown bus tie board.This modification should be completed and the unit returned to service by the middle of January.Preparations have been underway for the upcoming Unit 1, cycle 3 refueling outage and should be completed by January l.Unit 1 is scheduled for a 48 day refueling outage to begin January 3, 1980.