|
---|
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] |
Text
_ _ - _
a
'{T En Tennessee V@ey Aaney 1101 Md4 het C%Uanmga Tewssee 3N02 APR 291991 U.S. Nuclear Regulatory Commission
- ATTN: Document Control Desk >
-Washington, D.C. 20555
' Gentlemen:
In the Matter-of ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-296 >
- BROWNS FERRY NUCLEAR PLANT (BFN) - PROGRAM FOR RESOLVING LONG-TERM. TORUS INTEGRITY ISSUE PRIOR TO THE RESTART OF UNITS 1 AND 3 Reference -TVA letter, dated-January 9, 1991, plans for the Return to Service of BFN Units 1 and 3 As part-of the referenced letter, TVA committed to provide-the NRC Staff with the' action plan for dispositioning the long-term torus integrity t issue at, BFN Units 1 and 3. Enclosure 1 to'this letter provides a summary-of this. issue, a review of the. Unit 2 resolution, a discussion of lessens. learned, and a description of how this issue will be resolved on Units- 1' and 3. - This submittal is provided for informational purposes
- only. No NRC action is specifically requested.
A summary list of commitments contained in this letter is provided in Enclosure 2.- If-you have any questions,1please contact Joseph E. t McCarthy, Unit 3 Licensing Manager, at (205) 729-3604.
Very truly'yours, TENNESSEE VALLEY AUTHORITY
/
E. G. Wallace, Manager.
Nuclear Licensing-and' Regulatory Affairs Enclosures cci -Soo page-2
~
%\
( l \k
- 9105030077 910429-ADOCK 05000259 lPDR p, PDR
_ _ - .. -- . .~.
l
. 8 U.S. Nuclear Regulatory Commission /kfg gg ec (Enclosures):
Ms. S. C. Black, Deputy Director Project Directorate 11-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike, Rockville, Maryland 20852 l NRC Resident Inspector '
Browns Ferry Nuclear Plant j Route 12. Box 637 )
Athens, Alabama 35609-2000 l 1
-Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission j One White Flint, North 11555 Rockville Pike l Rockville, Maryland 20852 l
Mr. B. A. Wilson, Project Chief !
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
e immisep_i mumimu ai ..
ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT - UNITS 1 AND 3 LONG-TERM TORUS INTEGRITY PROGRAM CORRECTIVE ACTION PLAN ISSUE SUL9AARY The Browns Ferry Units 1, 2, and 3 containment systems are one of the first generation General Electric (GE) Boiling Water Reactor (BWR) nuclear steam supply systems housed in a containment structure designated as the Mark I containment system. The original design of the Mark I containment system included pressure and temperature loads associated with a Loss of Coolant Accident (LOCA), seismic loads, dead loads, jet impingement loads, hydrostatic loads due to water in the suppression chamber, overload pressure test loads, and construction loads.
During the conduct of a large scale testing program for the advanced design pressure suppression containment system (Mark III), new suppression pool hydrodynamic loads associated with a postulated LOCA were identified which had not been included in the original design of the Mark I containment system. In addition, experience at operating plants indicated that the dynamic effects of safety relief valve discharges to the suppression pool could be substantial and needed reconsideration.
Interim operation of GE BWRs with a Mark I containment was found to be acceptable as documented in NUREG-0408, Mark I containment Short-Term Program Safety Evaluation Report, dated December 1977. A generic letter was issued to all Mark I BWRs on March 12, 1979, which established the schedule for the resolution and implementation of the plant unique aspects of the Mark I containment Long-Term Program.
The long-term issues were considered to be resolved in July 1980, when NRC issued NUREG-0661, Safety Evaluation Report - Mark I Containment Long-Term Program. This report specified NRC generic acceptance criteria which were required to- 1) Establish design basis loads that were appropriate for the anticipated life of each Mark I BWR facility, and 2) Restore the originally intended design safety margins for each Mark I containment system.
Supplement 1 was issued in August 1982.
TVA submitted the required torus integrity long-term program plant unique analysis report by letters dated January 3, 1984, September 11, 1984, and January 25, 1985. TVA then performed the committed modifications for all three units. NRC performed a post-implementation audit and documented their review in a safety Evaluation, dated May 6, 1985. This Safety Evaluation completed NRC action for all three BFN units.
l 1
- - - - - - - ~ _ - - . _ - _ - - __
I
' Page 2 of 6 ENCLOSURE 1 (CONTINUED)
BROWNS FERRY NUCLEAR PLANT - UNITS 1 AND 3 LONG-TERM TORUS INTEGRITY PROGRAM CORRECTIVE ACTION PLAN Discrepancies between the designed modifications and the as-constructed torus attached piping supports were identitied in Unita 1 and 3 by NRC in Inspection Report 85-26, dated May 14, 1985. Deficiencies in weldments and qualification of wolders were identified in Inspection Report 86-34, dated December 5, 1986.
These discrepancies were the impetus for the Unit 2 long-term torus integrity corrective action program. TVA's long-term torus integrity corrective action program was initially focussed on Unita 2 and 3, but soon shifted exclusively to Unit 2 when Unit 2 was made the restart priority.
The following is a summary of the more significant TVA/NRC correspondence which documents the resolution of these discrepancies. This summary is provided in order to assist the NRC Staff if additional detailed historical information is required. TVA responded to the violation cited in Inspection Report 85-26 by letters dated June 14, 1985, July 3, 1985, and July 31, 1986.
The violation was closed in Inspection Report 86-30, dated October 10, 1986.
TVA responded to the violation cited in Inspection Report 86-34 by letter, dated December 30, 1986. This violation was closed in Inspection Report 87-11, dated September 16, 1987.
Monitoring and evaluation of TVA's corrective actions is also documented in:
Inspection Report 85-30, dated June 24, 1985, Inspection Report 8',-07, dated March 9, 1987, Inspection Report 88-12, dated July 5, 1988, Inspection Report 88-19, dated August 29, 1988, Inspection Report 88-28, dated December 9, 1988, Inspection Report 88-35, dated March 17, 1989, Inspection Report 89-15, dated May 18, 1989, Section 2.2.4.4 of NUREG-1232, Volume 3, Supplement 1, dated October 24, 1989, and Inspection Report 89-44, dated December 11, 1989.
TVA responded to the final inspection open item by letter dated March 16, 1990. By letter dated October 2, 1990, TVA provided notification that BFN had implemented the requirements of the long-term torus integrity program for Unit 2. The acceptability of TVA's program to re-evaluate the adequacy of the torus integrity for Unit 2 was documented in Section . 2.4.4 of NUREG-1232, Volume 3, supplement 2, dated January 23, 1991.
]
Page 3 of F \
ENCLOSURE 1 (CONTINUED)
BROWNS FERRY NUCLEAR PLANT - UNITS 1 AND 3 i LONG-TERM TORUS INTEGRITY PROGRAM CORRECTIVE ACTION PLAN 1 1
l A review of the Unit 2 resolution, a discussion of lessons learnod, and a description of:how this, issue will be resolved on Units 1 and 3 is presented below.
REVIEW OF THE UNIT 2 RESOLUTION OF TORUS ATTACHED PIPING SUPPORTS. TORUS. AND TORUS RELATED QTRUCTURES
'TVA's long-term torus integrity corrective action program initially consisted
- of the development of procedures and instructions for the re-inspection of those configurational attributes-associated with the torus attached piping support modifications required by the long-term torus integrity program (LTTIP). Examples of the inspection attributes included verification of support location, member sizes, welds (size and configuration), and bolting.' The scope of=these inspections was subsequently expanded to includo additional commodities. This revised correctiva action program included the following commodities:
'1) Torus attached pipirg supports, including portions not modified as part of the'LTTIP upgrades, 2F Torus structural modifications which were part of the LTTIP upgrades (e.g.,-torus tie-downs, cradle and ring girder reinforcements, and torus shell reinforcements), and
- 3) Torus related structures which were modified as part of.the.long-term torus upgrades (e.g., vont system, safety relief valve-system,, catwalk,-
and valve access platforms)..
The safety-related portions of these commodities were inspected.
Discrepancies between the as-designed and as-constructed configuration were analyzed and modified, as necessary, to correct the. discrepancies.
l l-l l
L r
- - , , , . . . ~ - n
v .
' Page 4 of 6 ENCLOSURE 1 (CONTINUED)
BROWNS FERRY NUCLEAR PLANT - UNITS 1 AND 3 LONG-TERM TORUS INTEGRITY PROGRAM CORRECTIVE ACTION PLAN Valve access platforms and the majority of the catwalk inside the torus are non-safety-related. The safety design basis for these non-safety-related torus internal structures requires their structural integrity not be compromised by design basis loadings.
TVA's corrective action program for the valve access platforms involved an inspection of two of the six platforms using the uttributes previously discussed. These inspection results were evaluated and no modifications were required to insure the structural integrity of the platforms. Therefore, inspections were not performed on the remainir.g four platforms.
TVA's corrective action program for the non-safety-related portion of the catwalk involved an inspection of a sample of the catwalk using the attributes previously discussed. These inspection results were evaluated. Modifications were required to welds and to bolted connections to ensure the structural integrity of the catwalk. The remainder of the non-safety-related catwalk was only inspected for these two attributes and the required modifications were performed.
TVA has developed a long-term torus integrity corrective action plan for Units 1 and 3 based upon the review of the Unit 2 precedent. This corrective action plan is composed of separate programs for
- 1) Torus attached piping supports, and
- 2) The torus and torus related structures.
The program for torus related structures is further divided into programs for safety-related and non-safety-related structures. A discussion of the specific lessons learned from the Unit 2 precedent and a detailed description of the Units 1 and 3 corrective action plan is presented below for each of these separate program areas. In summary, TVA will implement a program for Units 1 and 3 torus attached piping supports in accordance with the Unit 2 criteria and implementation precedent. TVA's will use the lessons learned from the Unit 2 precedent to refine the implementation of the program for Units 1 and 3 torus and torus related structures.
s
> e l
Page 5 of 6 ENCLOSURE-1 (CONTINUED)
BROWNS FERRY NUCLEAR PLANT - UNITS 1 AND 3 .!
LONG-TERM. TORUS INTEGRITY PROGRAM CORRECTIVE ACTION PLAN 1
DISCUSSION OF LESSONS LEARNED FROM UNIT 2 TORUS ATTACHED PIPING SUPPQRTS TVA's program for the resolution of torus attached piping support 1 discrepancies resulted in. modifications for each of the inspection attributes.
Therefore, TVA can not justify the elimination of any of these attributes from the inspection of Units.1 and 3 torus attached piping supports. l 1
RESCRIPTION OF THE UNITS 1 AND 3 PROGRAM FOR TORUS ATTACHED PIPING SUPPORTS TVA has determined that the resolution of torus attached piping support discrepancies will be implemented, in accordance with the Unit 2 criteria and J will use the configurational attributes from the Unit 2 implementation precedent. This work will be completed prior to the. restart of Unite 1 and 3.
l.
I DISCUSSION OF LESSONS LEARNED FROM UNIT 2 TORUS AND TORUS RELATED STRUCTURES TVA's' program for the resolution of Unit 2 structural discrepancies on
!. safety-related torus and torus related structures resulted in modificatione L associated with each of the applicable inspection attributes, except for l ,
1). Dimensions of standard structural shapes,
- 2) Correct materiale, p 3) Grout dimensions, and.
p 4) Location of commodities attached to concreto surface mounted baseplates.
l
[ TVA's program for the resolution of discrepancies associated with the
-non-safety-related valve access platforme did.not result in modifications.
Modifications to welds and to bolted connections were required to ensure the
-structural integrity 1of the catwalk.
l
Page 6 of 6 ENCLOSURE 1 (CONTINUED)
BROWNS FERRY NUCLEAR PLANT - UNITS 1 AND 3
.LONG-TERM TORUS-INTEGRITY PROGRAM. CORRECTIVE ACTION PLAN DESCRIPTION OF THE UNITS 1 AND 3 PROGRAM FOR TORUS AND TORUS RELATED STRUCTURES TVA's inspection of Units 1 and 3 eafety-related torue and torus related structures will exclude the four attributes which did not result in modifications on Unit 2. ~ With the exception of these four attributes, the resolution of discrepancies on the torus and torus related structures will be implemented, in accordance with the Unit 2 criteria and implementation precedent. This work will be completed prior to the restart of Unite 1 and 3, l TVA will;not inspect the Unite 1 and 3 non-eafety-related valve access platforme. TVA's inspection of the non-safety-related Unite 1 and 3 catwalk will be limited to welds and bolted connectione associated with maintaining.
the integrity of the safety related structures. The resolution of catwalk.
discrepancies will be in accordance with the Unit 2-criteria and will.be completed prior to the restart of Unite 1 and 3.
1 1
l .' '
+
)
. , 1 ENCLOSURE 2 l BROWNS FERRY-. NUCLEAR PLANT - UNITS 1 AND 3
SUMMARY
-0F COMMITMENTS I
- 1) -TVA'has determined that the resolution of torus attached piping support l discrepancies will be' implemented, in accordance with the Unit 2 criteria and will use the configurational attributes from the Unit ~2
-implementation precedent. This work will be completed prior to the restart of Unita 1 and 3.
- 2) TVA's-inspection of Unita 1 and 3. safety-related torun and torus related .
structures will exclude the'four attributes which did not result in l modifications on Unit-2. With the exception of these four attributes, theirecolution of discrepancies on the safety-related torus and torus related structures will-be-implemented, in accordance with the Unit 2 criteria and implementation. precedent. This work will be completed prior to the restart of Unite.1 and 3.
- 3) TVA's inspection of the non-eafety-related Unita 1 and 3 catwalk will be limited to welds and' bolted connections asecciated with maintaining the integrity of the safety related structures.- The resolution of catwalk-discrepancies will be in accordance with the Unit 2 criteria and will be.
. completed prior to the restart of Unite 1 and 3.
. - , - ,______.________.__.____a - --
_ - = * . . _ _ _ _ _ - , _ _ . - _ _ --