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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
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ACCELERATED DISTRIBUTION DEMONSTPA.TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9402150228 DOC.DATE: 94/02/02 NOTARIZED: NO FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee
'OCKET 05000259~
50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION SALAS,P. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Requests that NRC not schedule full scope NRC SWS D operational performance insp at plant, as part of operating 6 maint cost reduction program. Util plans to util conduct self-assessment of plant EECW 6 RHRSW sys.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: Co TITLE: OR Submittal: General Distribution NOTES:
D RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-4 1 1 PD2-4-PD 1 1 TRIMBLE,D 2 2 WILLIAMS,J. 2 2 S INTERNAL: ACRS 6 6 NRR/DE/EELB 1 1.'
NRR/DORS/OTSB 1 1 NRR/DRCH/HICB 1 1 NRR/DRPW 1 1 NRR/DSSA/SPLB 1 "1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OG/BPD'CB 1 0 OGC/HDS3 1 0 R FILE Ol 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D
A D
D NOTE TO ALL "RIDS" RECIPIENTS:
'S PLEASE HELP US TO REDUCE WASEE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISI'RIBUTION LIPID FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22
Tennessee Valley Authority. Post Of(ice Box 2000. Decatur. Alabama 35609 FEB 02 1994 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 ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1~ 2p AND 3 OPERATING & MAINTENANCE (O&M) COST REDUCTION PROGRAM REQUEST FOR NRC REVIEW AND APPROVAL OF COST BENEFICIAL LICENSING ACTION (CBLA) RLA-03: REDUCED SCOPE NRC SERVICE WATER SYSTEM INSPECTION As part of TVA's Operating & Maintenance Cost Reduction Program, TVA requests that NRC not schedule a full scope NRC Service Water System Operational Performance Inspection (SWSOPI) at BFN. TVA bases this request on its plans to conduct a self-assessment of BFN's Emergency Equipment Cooling Water (EECW) and Residual Heat Removal Service Water (RHRSW) systems, which are the "service water systems" at BFN. In accordance with NRC Inspection Procedure (IP) 40501, "Licensee Self-Assessments Related to Area-of-Emphasis Inspections," TVA proposes that NRC conduct a reduced scope inspection of TVA's self-assessment instead of the full scope inspection.
TVA's self-assessment will meet the criteria for acceptability identified in IP 40501 and will provide assurance that BFN's EECW and RHRSW systems are capable of performing their safety-related functions. TVA is confident that its self-assessment will identify weaknesses or deficiencies in these systems if they exist. Any identified weaknesses and deficiencies will be addressed by TVA's corrective action programs, as appropriate. Therefore, a full-scope NRC SWSOPI is not necessary.
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U. S. Nuclear Regulatory Commission Page 2 FEB 0 8 994 Currently, TVA is developing the detailed plan to conduct the BFN self-assessment. This plan will not be finalized until lessons learned from forthcoming self-assessment activities at Sequoyah Nuclear Plant (SQN), as well as any results from the NRC SWSOPI at SQN (currently planned for mid-July 1994),
are available. Once the lessons learned are incorporated into the BFN self-assessment plan, and TVA has finalized the team makeup, TVA will submit the plan to NRC for approval, in accordance with IP 40501. TVA expects to submit the BFN self-assessment plan to NRC within 60 days of issuance of the NRC inspection report for the SQN inspection.
Following NRC review and approval of the BFN self-assessment plan, TVA will conduct the self-assessment of the BFN EECW and RHRSW systems. TVA expects to commence the self-assessment within 90 days of NRC approval of the self-assessment plan. Following completion of the self-assessment, TVA will issue a report which documents the findings of the self-assessment as well as planned corrective actions to address identified weaknesses and deficiencies.
TVA expects to issue the report within 60 days of completion of the self-assessment.
TVA is submitting this request as a CBLA since a reduced scope NRC inspection of TVA's self-assessment involves significant savings of resources and will provide equivalent assurance of safety. TVA estimates that a reduced scope inspection, in lieu of the full-scope inspection, would result in one-time savings to TVA exceeding $ 300,000. to this letter provides the specifics of TVA's request. Enclosure 2 lists the commitments made in this letter.
If you telephone have any questions regarding me at (205) 729-2636.
this request, please Sincerel Pedro Salas Manager of Site Licensing Enclosures cc: See page 3
)
T P Q S I'
U.S. Nuclear Regulatory Commission FEB 0 2 1994 Enclosures CC (Enclosures):
Mr. R. V. Crlenjak, Project Chief U.S. Nuclear Regulatory Commission Region 101 II Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. A. F. Gibson, Director Division of Reactor Safety U.S. Nuclear Regulatory Commission Region 101 II Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. F. P. Gillespie, Director Program Management Policy Development and Analysis Staff U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. E. W. Merschoff, Director Division of Reactor Projects U.S. Nuclear Regulatory Commission Region 101 II Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Regional Administrator U.S. Nuclear Regulatory Commission Region 101 II Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611
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U.S. Nuclear Regulatory Commission Page 4 FEB 02 l994 Mr. D. C. Trimble, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Z. F. Williams, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. R. P. Zimmerman U. S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNZTS 1q 2q AND 3 OPERATING & MAINTENANCE (O&M) COST REDUCTION PROGRAM REQUEST FOR COST BENEFICIAL LICENSING ACTION RLA-03 REDUCED SCOPE NRC SERVICE WATER SYSTEM ZNSPECTZON I'UMMARYOF RLA-03 As part of TVA's 0&M Cost Reduction Program, TVA requests that NRC not schedule a Service Water System Operational Performance Inspection (SWSOPI) at BFN based on TVA's plans to conduct a self-assessment of BFN's Emergency Equipment Cooling Water (EECW) and Residual Heat Removal Service Water (RHRSW) systems. In accordance with the guidance of NRC Inspection Procedure (IP) 40501, "Licensee Self-Assessments Related to Area-of-Emphasis Inspections,"
TVA proposes that NRC conduct a reduced scope inspection of TVA's self-assessment, rather than a full scope inspection.
TVA's self-assessment will meet the criteria for acceptability identified in IP 40501, and will provide equivalent assurance that BFN's EECW and RHRSW systems are capable of performing their safety-related functions.
Therefore, a full-scope NRC SWSOPI is not necessary.
TVA estimates that performance of a reduced scope NRC inspection of TVA's self-assessment would result in one-time savings to TVA exceeding $ 300,000.
II'ACKGROUND In 1989, following NRC review of industry operating experience and internal NRC studies, NRC questioned the compliance of nuclear plant service water systems with certain general design criteria and quality assurance requirements. As a result, NRC issued Generic Letter (GL) 89-13, "Service Water System Problems Affecting Safety-Related Equipment." This GL required that licensees and applicants take several actions to ensure that their service water systems comply with, and are maintained to comply with, the applicable general design criteria and quality assurance requirements.
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In SECY 92-355, dated October 20, 1992, "Implementing Service Water System Operational Performance Inspections (SWSOPIs),>> the NRC noted that since the GL was issued, a number of plant specific service water system design and operational concerns have been identified. Due to these continuing concerns, NRC announced plans for a major team inspection program of plant service water systems. On November 23, 1992, the Commission approved this inspection program.
Following Commission approval, NRC initiated performance of SWSOPIs in accordance with NRC Temporary Instruction (TI) 2515/118, "Service Water System Operational Performance Inspection (SWOPI)." The purpose of SWSOPIs is to assess planned or completed actions in response to GL 89-13, and verify that service water systems are capable of fulfilling their thermal and hydraulic performance requirements and are operated consistent with their design bases. In addition, the inspections would assess service water system operational controls, maintenance, surveillance and other testing, and personnel training to determine if service water systems are operated and maintained to ensure the capability to perform their safety-related functions.
According to TI 2515/118, NRC will be focusing these inspections on plants licensed prior to 1979, such as BFN (currently, BFN has not been formally scheduled). For these plants, the TI provides for inspection implementation latitude up to complete waiver if a recent in-depth NRC inspection has been conducted which provides the equivalent of a SWSOPI in scope. Although the TI provides for waiver of the inspection at plants licensed after 1979 that have conducted self-assessments, it not specifically address inspection waiver for pre-1979 does plants that have conducted self-assessments.
Subsequently, NRC issued IP 40501. In this IP NRC notes that it will "recognize a licensee's good performance and quality self-assessment by reducing the scope of [an] NRC inspection." This reduced-scope inspection is contingent on the licensee self-assessment meeting certain criteria outlined in the IP. Specifically, the self-assessment must be at least equivalent in scope and depth to the inspection criteria outlined in the TI associated with the area of emphasis inspection. In addition, the self-assessment team must have the necessary credentials and experience to perform a technically creditable self-assessment.
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III~ REQUESTED NRC LICENSING ACTION TVA requests that a full scope SWSOPI not be scheduled for BFN. In accordance with IP 40501, TVA proposes that NRC perform a reduced scope inspection of TVA's planned self-assessment of the BFN EECW and RHRSW systems, in lieu of the full-scope inspection.
IV BASIS FOR REQUESTED NRC LICENSING ACTION TVA will be performing a self-assessment of the BFN EECW and RHRSW systems modeled after NRC TI 2515/118. This self-assessment will meet the criteria for acceptability identified in NRC IP 40501. TVA plans to use a multidisciplined team to conduct the assessment, including experienced personnel from BFN and TVA's corporate office.
In addition, TVA plans to supplement the team with outside expertise, as necessary.
TVA's self-assessment will demonstrate that BFN's EECW and RHRSW systems are designed, operated, and maintained to ensure their capability to'erform their safety-related functions. TVA's self-assessment will assess the effectiveness of planned and completed actions in response to GL 89-13. TVA's self-assessment will also assess the capability of BFN's EECW and RHRSW systems to fulfill their thermal and hydraulic performance requirements.
TVA routinely uses NRC inspection guidance, including temporary instructions, to conduct self-assessments and to help prepare for major team inspections such as Electrical Distribution System Functional Inspections (EDSFIs) and SWSOPIs. In the most recent Systematic Assessment of Licensee Performance (SALP) for BFN Unit 2 (NRC Inspection Report 50-260/93-31, dated November 4, 1993), NRC recognized the quality of TVA's self-assessments by stating that TVA's "self-assessment efforts . . . are generally effective, in-depth and normally identify and correct weaknesses in [TVA's] programs." Accordingly, TVA is confident that its proposed self-assessment will identify weaknesses or deficiencies in these systems if they exist. Furthermore, deficiencies are if identified, any weaknesses or TVA will address them in accordance with appropriate elements of its corrective action program. Therefore, a full-scope NRC SWSOPI would not be necessary.
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t II Currently, TVA is developing the detailed plan to conduct the BFN self-assessment. This plan will not be finalized until lessons learned from forthcoming self-assessment activities at Sequoyah Nuclear Plant (SQN), as well as any results from the NRC SWSOPI at SQN (currently planned for mid-July 1994), are available. Once the lessons learned from the Sequoyah self-assessment and results from the NRC inspection are incorporated into the BFN self-assessment plan, and TVA has finalized the team makeup, TVA will submit the BFN plan to NRC for approval, in accordance with IP 40501. This plan will include the scope and depth of the self-assessment, as well as the composition of the team that will conduct the assessment. TVA expects to submit the BFN self-assessment plan to NRC within 60 days of issuance of the NRC inspection report for the SQN inspection.
Following NRC review and approval of the BFN self-assessment plan, TVA will conduct the self-assessment of the BFN EECW and RHRSW systems. TVA expects to commence the self-assessment, within 90 days of NRC approval of the self-assessment plan. Following completion of the self-assessment, TVA will issue a report which documents the findings of the self-assessment as well as planned corrective actions to address identified weaknesses and deficiencies. TVA expects to issue the report within 60
, days of completion of the self-assessment.
JUSTIFICATION FOR HIGHER PRIORITY REVIEW A. RLA-03 Is Safet Neutral As noted above, NRC IP 40501 establishes acceptance criteria for licensee self-assessments and provides guidance for NRC to evaluate these self-assessments.
Consequently, a self-assessment that is conducted by TVA in accordance with an NRC-approved plan, and evaluated by NRC per the guidance of NRC IP 40501, provides equivalent assurance of safety as a full-scope NRC inspection. Therefore, TVA's request that NRC conduct a reduced scope inspection of this self-assessment in lieu of a full scope NRC team inspection is safety neutral.
B. RLA-03 Provides 8i nificant Cost Bavin s and Other Benefits TVA estimates that waiver of a full-scope NRC SWSOPI at BFN will result in cost savings exceeding
$ 300,000. TVA bases this estimate on the cost of previous similar scope inspections (e.g., EDSFIs or Integrated Design Inspections), with appropriate adjustments for current NRC fees, and the approximate internal costs associated with supporting such inspections.
In addition to significant cost savings for TVA, a reduced scope NRC inspection would also allow NRC to focus its resources on other safety significant issues.
VIE CONCLU8ION TVA is fully capable of performing an effective self-assessment of the BFN EECW and RHRSW systems. TVA's self-assessment will provide assurance that BFN's EECW and RHRSW systems are capable of performing their safety-related functions. Consequently, a full-scope is not necessary. Furthermore, a reduced scope NRC'nspection NRC inspection of TVA's self-assessment would significantly reduce the burden on TVA resources, and would also conserve NRC resources, without adversely impacting safety.
TVA has determined that RLA-03 (inclusive of TVA~s forthcoming IP 40501 submittal noted above) is a cost beneficial licensing action since it is safety neutral and provides significant cost savings.
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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1g 2g AND 3 OPERATING 6 MAINTENANCE (OSM) COST REDUCTION PROGRAM REQUEST FOR COST BENEFICIAL LICENSING ACTZON RLA-03 REDUCED SCOPE NRC SERV1CE WATER SYSTEM INSPECTION List of Commitments
- 1. TVA will submit to NRC for review and approval its plan for conducting a self-assessment of the BFN Emergency Equipment Cooling Water (EECW) and Residual Heat Removal Service Water (RHRSW) systems. This plan will include the scope and depth of the self-assessment, as well as the composition of the team that will conduct the assessment. TVA expects to submit the plan within 60 days of issuance of the NRC inspection report for the NRC Service Water System Operational Performance Inspection of Seguoyah Nuclear Plant.
- 2. Following NRC review and approval of TVA's plan for conducting a self-assessment of the BFN EECW and RHRSW systems, TVA will perform the self-assessment. TVA expects to commence this self-assessment within 90 days of NRC approval of the self-assessment plan.
- 3. Following completion of TVA's self-assessment of the BFN EECW and RHRSW systems, TVA will issue a report which documents the findings of the self-assessment as well as planned corrective actions to address identified weaknesses and deficiencies. . TVA expects to issue the report within 60 days of completion of the self-assessment.
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