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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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CATEGORY 1 A~iSULATOY TMFORMATTOM DTSTRTBUTYOPSYSTEM (RTDS)
'CCESSION NBR:9806020008 DOC.DATE: 98/05/20 NOTARIZED: YES DOCKET ¹ FACIL:50-296 Browns Ferry Nuclear. Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION ABNEY,T.N. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch. (Document Control Desk) repair plan for
SUBJECT:
Forwards 3
description of TVA insp E core spray sys piping internal to reactor vessel &.
forwarding proprietary GE drawings. Proprietary encls ltrUnit BFN withheld.
'DISTRIBUTION CODE: D030D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: TVA Facilities Routine Correspondence NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 PD2-3 1 1 PD2-3-PD 1 1 DEAGAZIO,A 1 1 INTERNAL: ACRS 1 ILE CE , 1 1 1 OGC/HDS3 0 RES/DE/SSEB/SES 1 1 EXTERNAL: NOAC 1~ NRC PDR Q'%
0 N
NOTE TO ALL MRIDSE RECIPIENTS PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 8
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Tennessee Vattey Authority. Post Otfice Box 2000, Decatur, Alabama 35609 May 20, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of Docket No. 50-296 Tennessee Valley Authority BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 REACTOR PRESSURE VESSEL INTERNALS I AUGMENTED WELD INSPECT ION I IND CATIONS AT THE CORE SPRAY SYSTEM PIPING COLLAR-TO-SHROUD WELD INSPECTION AND REPAIR PLANS FOR THE CYCLE 8 REFUELING OUTAGE (TAC NO. M98059)
On March 7, 1997, TVA submitted a description of flaws identified during an inspection of Core Spray System piping within the reactor vessel for BFN Unit 3. TVA also provided an evaluation of the effect of the identified flaws on the structural integrity of the core spray piping. In addition, TVA provided supplemental information, by letters dated March 9, 1997 and March 10, 1997.
In the March 10, 1997 letter, TVA committed to work with the Boiling Water Reactor Vessel and Internals Project (BWRVIP)
Committee to develop inspection methods and repair criteria for the P4d weld. TVA also committed to reinspect or repair the Core Spray System piping and to provide its plans to the NRC staff 120 days prior to the start of the BFN Unit 3 Cycle 8 (Fall 1998) refueling outage.
The enclosure to this letter describes TVA's inspection and repair plan for the BFN Unit 3 Core Spray System piping internal to the reactor vessel. Attachment A to the 9'806020008 980520 PDR ADOCK 05000296 P PDR Q~
4l igi I
U.S. Nuclear Regulatory Commission Page 2 Hay 20, 1998 enclosure contains information proprietary to General Electric (GE). GE requests that these documents be withheld from public disclosure in accordance with 10 CFR 2.790(a)(4).
An affidavit supporting this request is provided in the enclosure in accordance with 10 CFR 2.790(b)(1).
If you have further questions regarding this information please call me at (256) 729-2636.
S'erely, E.
Manager of Lice ng and Industry Affai s Enclosure cc (Enclosure):
Mr. 'Harold O.. Christensen, Branch Chief U.S. Nuclear .Regulatory Commission Region II 61 Forsyth Street, S.W.
.Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. Albert W. De Agazio, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
0 ( ~ i ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 CORE SPRAY SYSTEM ~ AUGMENTED WELD INSPECT ION ~
INDICATIONS AT CORE SPRAY SYSTEM PIPING COLLAR-TO-SHROUD WELD INSPECTION AND REPAIR PLANS FOR THE CYCLE 8 REFUELING OUTAGE BACKGROUND In response to instances of cracking in core spray spargers, NRC requested in IE Bulletin 80-13, "Cracking In Core Spray Spargers," that all operating boiling water reactor facilities perform a visual inspection of the core spray spargers and the segment of piping between the inlet nozzle and the vessel shroud. NRC requested this inspection be performed at the next scheduled refueling outage and each subsequent refueling outage until further notice. The bulletin also requested that any identified cracking be evaluated and reported to NRC. TVA complied with this request.
On March 7,, 1997, TVA submitted by letter, a description and structural evaluation of indications identified during the Unit 3 Cycle 7 examination of the Core Spray System piping. As a result of verbal requests for additional information from the NRC staff, TVA submitted supplemental information on March 9 and 10, 1997. In the March 10, 1997 letter, TVA committed to (1) work with the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Committee to develop an inspection methodology and criteria for repair of the P4d weld (which had shown indications upon visual examination), and (2) provid'e TVA's plan for inspection of the P4d weld to the staff 120 days prior to the start of the Unit 3 Cycle 8 (Fall 1998) refueling outage.
NRC letter dated March 11, 1997, informed TVA that the staff had not identified any technical issues, during its initial review, that would prevent the restart of BFN Unit 3 from the Cycle 7 refueling outage. As part of its ongoing review, the NRC staff subsequently identified a question regarding the structural integrity of weld P9. The staff requested
t5 additional information, by letter dated May 28, 1997, regarding the structural integrity of weld P9 in order to assess the effect of the failure of welds P9 and P8, which could result in degraded Core Spray System function. TVA provided the information requested by letter dated June 10, 1997. In addition, TVA letter dated June 24, 1997, provided information to clarify the methodology used for the calculation of peak cladding temperature for loss of coolant accidents. NRC issued a safety evaluation report by letter dated September 22, 1997. In that evaluation, the NRC staff determined that continued operation of BFN Unit 3 for the current fuel cycle (Cycle 8) was acceptable.
TVA's commitments and actions taken regarding the BFN Unit 3 Core Spray piping weld indications are summarized below.
TVA Commitment TVA will submit its plans to the NRC for the reinspection or repair of the BFN Unit 3 Core Spray System piping, internal to the reactor vessel, 120 days prior to the start of the Cycle 8 refueling outage. (TVA letter to NRC dated March 7, 1997)
Actions Taken TVA's inspection and repair plans for the BFN Unit 3 Core Spray System piping, internal to the reactor vessel, are as follows:
Replacement of the lower section piping of downcomer C will be performed to address the crack indications found during the Unit 3 Cycle 7 refueling outage in welds P8b and P4d.
This replacement consists of a General Electric (GE) supplied designed repair which will replace the piping from upstream of the slip joint down to the shroud attachment.
As shown on the attached sketches (Attachment A), this repair will eliminate the hidden P9 weld. The lower section replacement was designed in accordance with the guidance provided in the BWRVIP-16, "Internal Core Spray Piping and Sparger Replacement Design Criteria," which has been submitted for NRC review. The replacement design will be consistent with the existing BFN design/licensing basis, and will be evaluated pursuant to 10 CFR 50.59 to determine whether prior NRC approval is required.
The core spray spargers and associated piping will be inspected using the guidance provided in the currently issued "BWRVIP-18, BWR Core Spray Internals Inspection E-2
41 (Qi and Flaw Evaluation Guidelines." Visual inspections will be performed on the Unit 3 core spray t-box repair brackets of
'both loops. Ultrasonic (UT) examination will be performed on the accessible areas of piping welds P4a, P4b, P4c, P4d, P5, P6, P7, PSa, and PSb of downcomers A, B, and D. The accessible areas of P4a and P4b piping welds of downcomer C will be examined by UT. Piping welds from upstream of the slip joint to the shroud (welds P4c, P4d, P5, P6, P7, P8a, and PSb) of downcomer C will be replaced as part of the planned repair effort. The accessible areas of piping welds and brackets (P2, P3, and PB) not being replaced or receiving a UT examination will receive a visual inspection. The accessible areas of core spray sparger brackets (Sb) and sparger welds (Sl, S2, S3, and S4) will be visually inspected. As previously committed, arc strikes and linear indications identified during previous inspection efforts will receive a visual reinspection. These indications have received repeated inspections with no growth noted.
Since the issuance of IE Bulletin 80-13, TVA has conducted inspections which included examination of the piping general surface area away from welds. The inspection of these areas away from welds has not resulted in the identification of any crack indications. Therefore, in accordance with the guidance listed in BWRVIP-18, no inspection of the piping general surface area away from the welds is planned. As stated in BWRVIP-18, it is expected that portions of surfaces be observed on a regular basis as cameras move past 'ill these areas to inspect the core spray welds or other reactor internal components.
TVA Commitment TVA will work with the BWRVIP Committee to develop an inspection methodology and criteria for repair of the P4d weld. (TVA letter to NRC dated March 10, 1997)
Actions Taken TVA has actively participated in the BWRVIP Committees which have prepared and submitted the reactor internals inspection and evaluation documents for NRC review. Additionally, TVA has worked with GE on the application of a methodology which provides the capability to perform ultrasonic examination of the accessible areas of weld P4d. This ultrasonic methodology was used successfully during the recent Unit 2 Cycle 9 refueling outage and will also be utilized during the Unit 3 Cycle 8 (Fall 1998) refueling outage.
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Ql <Qi TVA Commitment The inspection plan for the P4d weld will be submitted 120 days prior to the start of the Unit 3 Cycle 8 refueling outage currently scheduled for October 1998. (TVA letter to NRC dated March 10, 1997)
Actions Taken As described above, the subject P4d weld on downcomer C will be removed as part of the planned lower section replacement.
The accessible area of the P4d welds on the other three downcomers are scheduled to be inspected using UT techniques during the Unit 3 Cycle 8 (.Fall 1998) refueling outage.
4l ii INFORM'ATION CONTAINED NITHIN ATTACEB4ENT A, FIL M&S:
BFN-CS-01 BFN-CS-02 BFN-CS-03 BFN-CS-04 BFN-CS-05 BFN-CS-06 BFN-CS-07 PROPRIETARY INFORMATION AFFIDAVIT ATTACHED PER 10 CFR 2. 790 (B) (1)
E-5
<gi GE Nuclear Energy Reactor Modification Services 175 Curtner Avenue, MIC 571 San Jose, CA 95125 May .1'4, 1998 1HHVV-S005 Mr. F. E. Hartwig Browns Ferry Nuclear Plant Tennessee Valley Authority PO Box 2000, MODS 2-A Decatur, AL 35609
SUBJECT:
Core Spray Lower Sectional Replacement - Phase 2 Propietary Drawing'Transmittal PO No. 92NNP-82068D,.Release No. 1227955
Dear Mr. Hartwig:
'This letter transmits. the following GE,proprietary figures contained in Attachment A to TVA:
Figure BFN-CS-Ol Figure BFN-CS-02 Figure BFN-CS-03 Figure BFN-CS-04 Figure BFN-CS-05 Figure BFN-CS-06 Figure BFN-CS-07 Note: This letter with the attached figures and the supplied affidavit are to be submitted as a package.
Please call me (408-925-3770), ifyou have any, questions regarding this, item.
Sine rel,
. P. Svarney Core Spray P 'nager GE Nuclear Energy cc: G. Nelson, J. Rodabaugh
<Qi General Electric. Company AFFIDAVIT I, David J. Robare, being duly sworn, depose and state as follows:
.(1) I am Technical Account Manager, Technical Services, General Electric Company
("GE") and have been delegated;the function of. reviewing. the information described in,paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in a letter &om GE to TVA,
'letter number 1HHVV-S005, dated May 14 1998, subject "Core Spray Lower Sectional Replacement - Phase 2. The proprietary information is the entirety of attached figures BFN-CS-1,2,3,4,5,6,7 of Attachment A.
(3) In making this application for withholding of proprietary information of which it is the owner,.GE relies upon the exemption &om disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), 2.790(a)(4), and 2.790(d)(1) for "trade secrets and commercial or financial information obtained from a person and privileged: or confidential" (Exemption 4). The material for which exemption &om disclosure is here sought is all "confidential commercial information", and some. portions also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Ener Pro'ect v. Nuclear Re ulato Commission 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Grou
- v. FDA 704F2d1280 (DC Cir. 1983).
(4) Some examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by General Electric's competitors without license from General Electric constitutes a competitive economic
, advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the:design, manufacture, shipment,.installation, assurance of quality, or licensing of a similar product; 12/13/93RTH AffidavitPage 1
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- c. Information which reveals cost or price information, production capacities, budget levels, or commercial strategies of General Electric, its customers, or its suppliers;
- d. Information which reveals aspects of past, present, or future General Electric customer-funded development plans and programs, of potential commercial value to General Electric;
- e. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in both paragraphs (4)a., (4)b., and (4)e. above.
(5) The information sought to be withheld is being submitted to NRC in confidence.
The, information is of a sort customarily held'in confidence by GE, and is in fact so held. The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GE, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required transmittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary, agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access to such documents within GE is limited on a "need to know" basis.
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Disclosures outside GE are limited to regulatory bodies, customers, and potential customers, and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains conceptual design information depicting the GE method for replacing the lower segment of the core spray line. Patent disclosures for this design have been submitted . This design was developed at significant expense to GE.
12/l3/93RTH AffidavitPage 2
~I I+I (9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GE's competitive position and foreclose or reduce the availability of profit-making opportunities. The information is part of GE's comprehensive BWR.safety and technology base, and its commercial value extends beyond the original development cost. The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
'The research, development, engineering, analytical and,NRC review costs comprise
. a substantial investment of time and money by GE.
The precise value of the expertise to devise an evaluation process and apply the
- correct analytical methodology is dificult to quantify, but it clearly is substantial.
if GE's competitive advantage will be lost its competitors-are able to-use the results if of the GE:experience to normalize or verify their own process or they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GE would be-'lost ifthe information were disclosed to the public. Making such information available to competitors without their having been required to undertake a similar expenditure of resources. would unfairly provide competitors with a windfall, and deprive GE of the opportunity to exercise its competitive advantage.to seek an adequate return on its large investment in developing these very valuable analytical tools.
12/13/93RTH AffidavitPage 3
<5 I'
STATE OF CALIFORNIA )
) ss:
COUNTY OF SANTA CLARA )
David J. Robare, being duly sworn, deposes and says:
That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his'knowledge, information, and belief.
Executed at San Jose, California, this 14 th day of May 1998.
David J. Robare General Electric Company Subscribed.and sworn before me this 14 th day of May 1998.
Notary Public, State of California
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COMM. 01030164 O- NOTARY PUBLIGCALIFORNIA, Q tL SAN FRANCISCO COUNTY My Comm ExOIres June 19, 1998 12/l3/93RTH AffidavitPage 4
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