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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:NRC TO PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA
MONTHYEARML20247Q4601989-09-19019 September 1989 Responds to to Chairman Carr Re RWCU Sys Sample Panel Being Installed at Plant.Potential of Glass Rotameter to Rupture Due to Mechanical Failure of Veriflow Pressure Regulating Valve Assessed ML20245F4671989-08-0303 August 1989 Responds to to Chairman Carr Re Concerns.Concerns Have Technical Merits But Do Not Constitute Nuclear Safety Issues ML20246J9791989-07-0303 July 1989 Responds to Re Potential Industrial Safety Hazard Resulting from Inclusion of Glass Rotameter in RWCU Sample Line at Plant.Nrc Will Continue Monitoring Util Implementation of Corrective Action ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20245B4051989-04-14014 April 1989 Responds to 881004 & 890119,23 & 0310 Ltrs Re Status of Investigation of Concerns About Corrosion Inhibitors & Design of Sampling Sys.Low Velocity of Liquid in Hotwell Sampling Considered Satisfactory ML20207D1121988-07-0505 July 1988 Partial Response to FOIA Request for Documents.Forwards App M Documents.App L Documents Maintained in Pdr.Apps N & O Documents Partially & Totally Withheld,Respectively (Ref FOIA Exemption 5) ML20196A7521988-06-21021 June 1988 Responds to Re Effect of Proposed Landfill on Emergency Evacuation at Plant.Proposed Landfill Would Be Taken Into Account in Emergency Plan Review to Reflect Increased Traffic ML20151M6061988-04-19019 April 1988 Responds to FOIA Request for Info Re Scores of Reactor Operators & Senior Reactor Operators.Forwards Requalification Exam Summary Source Sheets Listed in Encl App W/Personal Privacy Info Deleted ML20211A0661986-10-0303 October 1986 Partial Response to FOIA Request.Forwards Document Listed in App.Document Also Available in PDR ML20204G0891986-07-29029 July 1986 Ack Receipt of to Lw Zech.Responsibility for Action on Concern Assigned to Region Ii.Ofc Will Respond in Near Future ML20136H8461985-07-19019 July 1985 Further Response to FOIA Request Re Fuel Loading & Low Power Tests at Diablo Canyon,Gpu Damage Claim Against NRC & AEOD Rept on Water Discharge Detection at Browns Ferry.Documents Listed in App B Available in PDR IA-85-240, Further Response to FOIA Request Re Fuel Loading & Low Power Tests at Diablo Canyon,Gpu Damage Claim Against NRC & AEOD Rept on Water Discharge Detection at Browns Ferry.Documents Listed in App B Available in PDR1985-07-19019 July 1985 Further Response to FOIA Request Re Fuel Loading & Low Power Tests at Diablo Canyon,Gpu Damage Claim Against NRC & AEOD Rept on Water Discharge Detection at Browns Ferry.Documents Listed in App B Available in PDR 1989-09-19
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML20205T3771999-04-0909 April 1999 Informs That on 990317,R Champion & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Are Wks of 000612 & 26 for Approx 16 Candidates ML20205J2521999-04-0505 April 1999 Informs That Effective 990328,A De Agazio Assigned as Project Manager for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20205F9231999-04-0101 April 1999 Forwards SE Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST, Valve Program for Plant,Units 1,2 & 3 ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20205A1821999-03-19019 March 1999 Discusses Plant Performance Review of Browns Ferry NPP Completed on 990208.Determined Overall Performance to Be Acceptable.Security,Fire Protection,Radiation Protection & Plant Chemistry Continued to Be Effective ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20203G4971999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20199B0811999-01-12012 January 1999 Forwards Request for Addl Info Re GL 96-05, Periodic Verification Design-Basis Capability of Safety-Related Motor-Operated Valves, to Request That NPP Licensees Establish Program Effectiveness of Current Program ML20199E3791998-12-23023 December 1998 Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl ML20198N8111998-12-18018 December 1998 Discusses Open Mgt Meeting Conducted on 981217 in Region II Ofc to Present self-assessment of Util Performance.List of Attendees & Copy of Presentation Handout Encl ML20198N7481998-12-14014 December 1998 Discusses DOL Case 98-ERA-34,DC Smith Vs Tva.Forwards Synopsis of OI Rept 2-1998-011,completed on 981030 ML20197H4421998-12-0202 December 1998 First Final Response to FOIA Request for Documents.Records Listed in App a Already Available in Pdr.App B Records Placed in Pdr.Portions of App C Records Withheld & App D Records Being Withheld in Entirety (FOIA Exemption 5) ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20196D1031998-11-16016 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Details of Insp Plans Through March 1999 & Historical Listing of Plant Issues,Called Plant Issues Matrix Encl ML20196C9651998-11-13013 November 1998 Forwards Copy of Answer Key & Master Bwr/Pwr GFE Sections of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl ML20195B9211998-11-12012 November 1998 Forwards Staff Assessment of Fatigue Evaluation,Accepting Licensee 980919 Response to NRC 980916 Request for Certain Plant Specific Design & Installation Details Re Insp & Repair of Plant,Unit 3 Core Spray Sys Piping Internal to Rv ML20195B9291998-11-10010 November 1998 Forwards Transcript of 981026,informal Hearing on 2.206 Petition Filed by Union of Concerned Scientists ML20195H4501998-11-0909 November 1998 Summarizes 981105 Open Mgt Meeting in Atlanta,Ga Re Site Engineering Performance.List of Attendees & License Presentation Handouts Encl ML20195C4631998-11-0909 November 1998 Informs That Effective 981105,L Raghavan Was Assigned Project Manager for Plant,Units 1,2 & 3 ML20155H4131998-11-0404 November 1998 Informs That on 981013,TVA Informed Staff That Amend Proposed by TVA Application No Longer Needed. Commission Has Filed Encl Notice of Withdrawal of Application for Amend to FOL with Ofc of Fr ML20155H4481998-11-0404 November 1998 Informs That on 981005 TVA Informed Staff That Amend Proposed by TVA Application & Revised on 970306 No Longer Needed.Notice of Withdrawal of Application for Amend to FOL Filed with Ofc of Fr ML20155A5031998-10-23023 October 1998 Informs of Withdrawal of TS Change 356,submitted on 951222. Federal Register Notice Re Withdrawal Will Not Be Published, Due to Staff Failure to Issue Notice,Per 10CFR50.91(a)(2) (I) ML20155H1211998-10-21021 October 1998 Confirms 981021 Telcon Between T Abney & T Morrissey Re Mgt Meeting Scheduled for 981105 in Atlanta,Ga to Discuss Recent Browns Ferry Nuclear Plant Engineering Performance & on-going Site Activities ML20155B6861998-10-0909 October 1998 Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators ML20154J6231998-10-0808 October 1998 Forwards Notice of Withdrawal of 971230 Application for Amend to Browns Ferry Nuclear Plant,Units 1,2 & 3 Custom TSs to Remove Identified non-conservatism Re Number of RHRSW Pumps Required for multi-unit Operation ML20154J8181998-10-0707 October 1998 Discusses Closure of TAC Numbers M92757,M92758 & M92759. Notice of Withdrawal of Application for Amend to Licenses DPR-33,DPR-52 & DPR-69 Encl ML20155A6561998-10-0202 October 1998 Confirms 980929 Telcon Between T Abney & H Christensen Re Mgt Meeting at Licensee Request Scheduled for 981217 in Atlanta,Ga to Discuss Recent Plant Performance & on-going Site Activities ML20154A4991998-09-30030 September 1998 Ltr Contract:Task Order 25, Browns Ferry Safety Sys Engineering Insp (Ssei), Under Contract NRC-03-98-021 ML20153H3041998-09-28028 September 1998 Forwards SE Accepting Util Proposed Alternatives Contained in Requests for Relief 3-SPT-3 & 3-SPT-4 for Second Interval Per 10CFR50.55(a)(3)(i) & Code Case N-546.INEEL TER in Support of Relief Requests Also Encl ML20155B4421998-09-22022 September 1998 Announces Plans to Conduct Ssei at Bfnp on 981116-20 & 981130-1204.Insp Objective Will Be to Evaluate Capability of High Pressure Coolant Injection Sys to Perform Safety Functions Required by Design Basis 1999-09-28
[Table view] |
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. . , . 7 AUG 0 31989 Mr. Eugene D. Buggs 4D9 Cameron Circle, #2402 Chattanooga, Tennessee 37402
Dear Mr. Buggs:
This letter is in reply to your July 9,1989 lettar to Chairman Carr of the U.S. Nuclear Regulatory Commission -(NRC).
As discussed in our letters of April 14,.1989 June 15, 1989, and July 3, 1989, the concerns you identified have some technical merits. However, these concerns do not constitute nuclear safety issues. Nevertheless, as described in our previous letters, the NRC has reviewed TVA's efforts related to these concerns.
These efforts include system tests to determine whether or not modifications are warranted. TVA's final resolution of these issues will be reviewed by the NRC staff.
With respect to your access to TVA documents TVA's decision is wholly within their purview. Absent additional information, the NRC staff finds that TVA's actions to address these issues are acceptable. If you have additional information or questions, please contact Paul Cortland (301) 492-0754.
Sincerely.
Odg'i.11
% sip 0d N B. D. Liaw, Director TVA Projects Division Office of Nuclear Reactor Regulation DISTRIBUTION:
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DATE :7/26/89 :7/26/89 :7/26/89 :8/M89 :7/27/89 : :
OFFICIAL RECORD COPY l
Mr. Eugene'D. Buggs 409 Cameron Circle, #2402 Chattanooga, Tennessee .37402-
Dear Mr. Buggs:
This : letter is ir. reply to your July 9,1989 letter to Chairman Carr of the U. S. Nuclear Regulatory Commission.(NRC).
As discussed in our letters of April 14, 1989, June 15, 1989, and July 3, 1989 the concerns you identified have some technical merits. However, these concerns do not constitute nuclear safety issues, Nevertheless, as des ~cribed in our previous letters, the NRC has reviewed TVA's efforts related to these concerns.
These efforts include system tests to determine whether or not modifications are warranted. TVA's final resolution of these issues Will be reviewed by the NRC staff.
With respect to your access to TVA documents TVA's decision is wholly within their purview. Absent additional information.fthe NRC staff finds that TVA's actions to address these issues are acceptab . If you have additional infor-mation or questions please contact Paul Cor,t and (301) 492-0754.
Sincerely, B. D. Liaw, Director TVA Projects Division Office of Nuclear Reactor Regulation DISTRIBUTION DCB (50-259/260/296) FMiraglia GHubbard NRC PDR w/ incoming FGillespie PCastlerain LPDR w/ incoming JPartlow MSimms ADSP R/F SECY (CRC-89-0649) OGC TVA R/F DCrutchfield TQuay TVA TP R/F BDLiaw GGears RCPierson DMoran DPotter (EDO #0 4610)
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DATE :7/26/89 :7/26/89 :7/26/89 : kiC\ 7/27/89 4 0FFICIAL RECORD COPY L.-- _ - - _ - - _ - . _ - _ . - - - - . . - - 1
.I' Mr. Eugene D. Buggs 409 Cameron Circle, #2402 Chattanooga, Tennessee 37402 >
Dear Mr. Buggs:
This letter is in reply to your July 9,1989 letter to Chaiman Carr of the U. S. Nuclear Regulatory Commission (NRC). i
- As discussed in our letters of April 14, 1989, June 15, 1989, and July 3, 1989 the concerns you identified have some technical merit. However, these concerns do not constitute nuclear safety issues. Nevertheless, as described in our previous letters, the NRC has reviewed TVA's efforts related to these concerns.
These efforts include system tests to determine whether or not modifications are warranted. TVA's final resolution of these issues will be reviewed by the NRC i
staff.
With respect to your access to TVA documents TVA's decision is wholly within their purview. Absent additional information, the NRC staff finds that TVA's actions to address these issues are acceptable. If you have additional infor-mation or questions please contact Paul Cortland (301) 492-0754.
Sincerely, Thomas E. Murley, Director Office of Nuclear Reactor. Regulation .
DISTRIBUTION DCB(50-259/260/296) FMiraglia GHubbard NRC PDR w/ incoming FGillespie PCastleman LPDR w/ incoming JPartlow MSimms-ADSP R/F SECY(CRC-89-0649) OGC TVA R/F.. . DCrutchfield ,
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- See Previous Sheet for Concurrence OFC : TVA:PSB : TVA:PSB/BC : TVA:AD/IP : NRR:D : Tech. Editor: :ADSP : NRR:D
.....:___........_:.............:...____.....: ...........:_____......_: : MMejac*
field: TMurley NAME :PCastleman* : GHubbard* : RPierson* : BDLiaw* :D
.....:............:..____.......:______.. __ :_ ........._:.........___:______ : 7/2.ff89 DATE : 7/26/89 : 7/26/89 : 7/26/89 : 7/26/89 : 7/27/89 : 7/ /89 0FFICIAL RECORD COPY
Mr. Eugene D. Buggs 409 Cameron Circle, #2402 Chattanooga, Tennessee 37402
Dear Mr. Buggs:
This letter is in reply to your July 9,1989 letter to Chairman Carr of the U. S. Nuclear Regulatory Commission.
You stated that you are skeptical of the corrective actions being implemented at the Browns Ferry Nuclear Plant in response to the concerns you raised while still an employee of the Tennessee Valley Authority (TVA). Further, you stated that TVA wil,1 not allow you to examine these corrective actions, and you requested that the NRC examine the Condition Adverse to Quality Reports which documented your concerns, as well as the associated proposed corrective actions, to determine i TVA has resolved the concerns.
i As andwe Julyhave descr\,
3, 1989 bed completed we have to you, in our detail, revfin ewour letters efforts dated April associated with 14, yourJune 15, concerns. Absent % dditional information, the NRC staff finds that TVA's plan to correct the problems you noted is acceptable and we are satisfied with the progress of corrective action implementation.
We note that you rais d no new concerns in your July 9,1989 letter.
\
\ Sincerely, N
\ Thomas E. Murley, Director x'
Office of Nuclear Reactor Regulation DISTRIBUTION \
DCB (50-259/260/296) FMiraglia's GHubbard NRC PDR w/ incoming FGillespie\ PCastleman ;
LPDR w/ incoming JPartlow MSimms ADSP R/F SECY (CRC-89-0649) OGC TVA R/F DCrutchfield TQuay TVA TP R/F BDLiaw GGears DPotter(EDO#004610) RCPierson DMoran VStello SBlack NMarkhisohn Murley/Sniezek BWilson TDaniels DMossburg (ED0 #004610) w/ incoming i
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- See Previous Sheet for Concurrence I 0FC : TVA:P5B* : TVA:P5B/BC* : TVA:AD/TP* : NRR:TVA/D* : Tech. Editor: NRR:ADSP : NRR:D NAME :PCastleman : GHubbard : RPierson : BDLiaw : . hw :DCrutchfield: TMurle
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i DATE : 7/26/89 : 7/26/89 : 7/26/89 : 7/26/89 : 7/26/89 : 7/ /89 : 7/ /89 OFFICIAL RECORD COPY
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a .
Mr. Eugene D. Buggs 409 Cameron Circle, #2402 Chattanooga, Tennessee 37402
Dear Mr. Buggs:
This . letter is in reply to your July 9,1989 letter to Chairman Carr of the U. S. Nuclear Regulatory Commission.
-You stated that you.are skeptical of.the correctivo actions being implemented at the Browns Ferry Nuclear Plant in response to the concerns you raised while still an emol'oyee of the Tennessee Valley Authority (TVA). Further, you stated that TVA will not allow you to examine these corrective actions, and you.
requested that the NRC examine the Condition Adverse to Quality Reports which documented your concerns, as well as the associated proposed corrective actions, to determine if TVA has resolved the concerns.
\
As we have described to you in detail in our letters dated April 14, June 15 s
and July 3,1989, we have completed our review efforts associated with your concerns. Absent additional information, the NRC staff finds that TVA's plan to correct the problems \you noted is acceptable, and we are satisfied with the progress of corrective action implementation.
We note that you raised nhnew concerns in your July 9,1989 letter.
N Sincerely,
\
Thomas E. Murley, Director Off ce of Nuclear Reactor Regulation 1
Ci 0FC : TVA:PSB TV B/BC : TVA:AD/TP : NR$ D,/ : NRR:ADSP : NRR:D :
NAME :PCastlema G ard : RPi n : BBC :DCrutchfield: TMurley :
e.....:.._______...:__..........:______....:__________:_________..:-_..______.:...........
DATE : 7/f4/89 : 7/26/89 : 7/%/89 : 7/nl/89 : 7/ /89 : 7/ /89 :
OFFICIAL RECORD COPY
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- %g.,... [ EDO; Principal-Correspondence Control-
, :1ROMal. 'DUE: 07/28/89 EDO-CONTROL: 0004610 1
DOC DT:-07/09/89-FINAL REPLY:
EUGENE D. BUGGS
- C H A T T A N O O G A , .- T N lTO:
CHAIRMAN CARR
.FOR SIGNATURE'0F:- ** GRN ** ' CRC NO: 89-0649 s
MURLEY DESC: ROUTING:
FOLLOW-UP LETTER'RE CONDITION ADVERSE TO QUALITY REPORTS (CAGRS)
.DATE: 07/14/89 ASSIGNED TO:L CONTACT:
- gR _ MURLEY SPECIAL INSTRUCTIONS OR REMARKS:'
NRR RECEIVED: JULY 17, 1989 ACTION: A SP:CRUTCHFIELDf
^ - NRR ROUTING:. MURLIY/SNIEZEK MIRAGLIA-Pt.RTLCW GILLESPIE
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, . ; PAPER? NUMBER:' 0649: ' LOGGING.-DATE: Jul'14 89-
' ACTION OFFICE .EDO ,
1ANTHOR$ E.D.'Buggs
? AFFILIATION:; TN '- (TENNESSEE) r .
.. LETTER.DATE:
1 Jul- 9 89l . FILE CODE:-
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- - . Follow-up letter re Condition. Adverse to Quality.
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