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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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MM4 MM%eJ JW 4 d REGULAT INFORMATION DZSTRZBUTIO STEM (RZDS)
ACCESSION NBR:9807270403 DOC.DATE: 98/07/16 NOTARIZED: NO DOCKET FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME ' AUTHOR AFFILIATION CRANE,C.M. Tennessee, Valley Authority RECIP.NAME', RECIPIENT AFFZLIATION Records Management Branch (Document Control Desk)
SUBJECT:
Forwards summary of plans R schedule re completion of quantitive analysis of adequacy of stroke times of direct current MOVs under design basis conditions. Summary submitted in. res P onse to RAI re ins P re P ts.
DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR- ENCL SIZE:
TITLE: General (50 Dkt) -Insp Rept/Notice of Violation Response NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-3-PD 1 1 DEAGAZZO,A 1 1 INTERNAL: ACRS 2 2 AEOD/SPD/RAB 1 1 AEOD TC 1 1, DEDRO 1 1 I CENTER 1 1 NRR/DRCH/HOHB 1 1 NRR PECB 1 1 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 OE DIR 1 1 OGC/HDS3 1 1 RGN2 FILE 1 1
'1 01'OAC EXTERNAL:'LITCO BRYCE,J H 1 1 1 NRC PDR 1 1 NUDOCS FULLTEXT 1 1 NOTE TO ALL "RIDS" 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 CONTRO!
DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL 19
Cl Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Christopher M. (Chris) Crane Vice President, 8rowns Feny Nuclear Plant July 16, 1998 U.S. Nuclear Regulatory Commission ATTN:, Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-296 Tennessee Valley Authority )
BROWNS FERRY NUCLEAR PLANT (BFN) REPLY 'TO REQUESTED INFORMATION IN INSPECTION REPORT 50 259 I 2 60 I 2 96/98 03 During the subject inspection, the inspectors determined certain assumptions for implementing Generic Letter 89-10 for Unit 3 were not adequately justified. As a result, NRC requested TVA to submit its plans and schedule for obtaining and analyzing, applicable test data for certain motor operated valves (MOVs).
In addition, NRC requested TVA to submit its plans and schedule to complete a quantitative analysis of the adequacy of the stroke times of its Direct Current MOVs under design basis conditions.
The Enclosure to this letter complies with these requests.
There are no commitments contained in this letter.,
If you have any questions please call me at (256) 729-2636.
cerely C. M. rane closure See page 2
'7807270403 9807%6 PDR ADQCK 05000296 PDR p
4l U.S. Nuclear Regulatory Commission Page' July 16, 1998 Enclosure cc: (Enclosure)
Mr. H. O. Christensen, Branch Chief U ~ ST Nuclear Regulatory Commission 61 Forsyth Street, S.W.
Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. A. W. DeAgazio,-Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. E. H. Girard, Reactor Inspector U.S. Nuclear Regulatory Commission 61 Forsyth Street, S.W..
Suite 23T85 Atlanta, Georgia 30303 Mr. T. G. Scarbrough, Sr. Mechanical Engineer U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
~I ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 3 REQUESTED INFORMATION ON BFN's STATUS FOR UNIT 3 GENERIC LETTER (GL) 89-10 ISSUES BACKGROUND:
BFN Calculation MD-Q0999-980001, "Design Input Parameters" formed the basis for valve factors selected for various valve groups in the BFN GL 89-10 program. During the development of the appropriate valve factors, it was determined that various types of information were available which could be used as the technical basis for valve factors. The objective was to obtain information which was directly applicable to BFN valves. Therefore, valve testing at BFN was considered the best available information.
Testing data from other TVA plants was considered desirable, since the data acquisition and analysis methods used were the same as those used't BFN. Beyond these two sources, definitive analysis of test data, from Electric Power Research Institute (EPRI) and NRC/INEL valve testing was also considered. EPRI report test data were cons'idered to have been performed at conditions similar to BFN's design basis accidents. After these data sources, test information from other utilities was considered. Due to variations in MOV program technical approaches, some utility sources were not considered directly applicable. For example, some utilities use valve factor while others use valve friction .
factor. However, information was obtained from the utilities where valve specific and data analysis methodology information were applicable.
TVA also participates in the Boiling Water Reactor Owner's Group Valve Technical Resolution Group which- includes 22 utility members. TVA's participation in this group was used to identify utilities that would have comparable valves and associated test data. It is not the intent of the design input parameters calculation to document every case where information was sought and not used.
In addition, BFN used two industry consultant firms for developing the valve factors used to meet the requirements of GL 89-10. These firms had access to a significant amount
0 of other utility data and provided this data for BFN use, where it was applicable. r BFN has expended significant effort to obtain industry data which can be used to support valve factors for BFN valves.
In cases, where the data is technically applicable, used ~
it was NRC GL 89-10 issues/TVA re lies TVA's implementation of Generic Letter 89-10 remained partly incomplete since TVA did not appear to satisfactorily obtain and/or analyze Motor-Operated Valve (MOV) test data to support the following assumptions for its MOVs:
ASSUMPTION 1 Assumption of 0.55 valve factor in calculating the design basis thrust requirements for gate valve group 3b and 7.
TVA's REPLY In development of the technical basis for valve factors for Group 3b .(Crane 900 pound gate valves), BFN found no valve test data available on valves with Stellite 21 hardfacing material. TVA procured Stellite 21 material valves to comply with sound AL2GV principles for reducing the amount of cobalt at BFN. TVA considered the test data from the EPRI TR-103119 "Friction Separate Effects Test Report" to be the best available data in regards to the performance of these materials. The EPRI program which generated this report, undertook an extensive review 'of various valve designs and materials. Appendix A of the EPRI report found that the populat'ion of valves with Stellite 21 hardfacing materials was small. A comparison of the data shows that the performance properties under similar contact stress and fluid conditions for Stellite 6 and Stellite 21 materials are very similar. .Therefore, BFN concluded that valve factors for Stellite 21 valves would not be significantly different than a valve of similar design which had Stellite 6 material.
EPRI performed .testing on a Crane 900 pound class valve with Stellite 6 hardfacing which was shown to exhibit a valve friction 'factor of 0.44. It was not practical for BFN to perform a differential pressure test for this valve since its function as the HPCI injection valve would potentially cause reactivity excursions which were deemed adverse to E-2
4l II reactor safety. Therefore, BFN added a 25% margin of safety on the Satellite 6 valve friction factor and thereby established the 0.55 valve friction factor selected for 'the Stellite 21 hardfacing materials valve.
Similarly, for Group 7 valves, BFN was unable to locate any available test data for valves which use Deloro hardfacing.
The primary differences between Deloro and Stellite 6 are that the Deloro friction coefficient (from material testing) does not decrease with increasing temperature, and that in edge-on-edge contact mode, the Deloro shows a greater susceptibility to mechanical damage. The BFN valves which contain the Deloro material are parallel seat valves which will not experience edge-on-edge contact. Therefore, the valve friction factor of 0.55 for these valves was used.
BFN is also aware that some valve testing with these Deloro hardfacing materials will be performed under the Joint Owner's Group Periodic Verification (JOG PV) program. TVA is a participant in the JOG PV program. Therefore,, TVA will monitor test data from the JOG PV program and incorporate data applicable to Deloro and Stellite 21 materials into the design input parameters calculation, as it becomes available. The differential pressure test program for the JOG PV program is currently scheduled for completion in 2003. Within three months of receipt of test data from the JOG PV program, TVA plans to incorporate the applicable data.
ASSUMPTION 2 Assumption of a 0.60 valve gate factor in calculating the design basis thrust requirements for gate valve group 11a and 11b.
TVA' REPLY The group 11a consists of 600 pound Walworth,valves of 6" and 20" sizes. TVA used test data from valves of similar
'esign (internal design and material type) as the basis for the valve friction factor. Information from EPRI Report TR-103237 R2 "EPRI MOV Performance Prediction. Program Topical Report," indicated that valve friction factors tend to decrease with increasing pressure class due to the. higher
,contact stresses, and with increasing valve size. A comparison of valve friction factors for this model of valve were made across a range of pressure classes and valve sizes. This data showed that valve friction factors ranged from 0.56 for 300 pound class valves to 0.45 for 900 pound E-3
0 ~I class valves. BFN established that the 0.6 valve friction factor was more conservative than the test data obtained for various pressure classes and valve sizes. In addition, BFN had reviewed valve, test data from NRC/INEL on a 6" 600 pound class valve which showed a valve friction factor of 0.27.
Therefore, the NRC/INEL valve friction factor enveloped BFN's valve friction factor of 0.6 for similar contact stress levels and fluid conditions.
The group 11b consists of 600 pound Walworth valves of 12" and 24" sizes. These valves are the same model as the valves in group 1la. The only difference between these two groups is the body and disc materials. The group 11b valves are stainless, and group 1la valves are carbon steel. Based on the valve application (i.e., low contact stresses and fluid temperatures) the stainless steel valves were not susceptible to any mechanisms which would induce "unpredictable" valve behavior. Therefore, BFN uses the same valve friction factor as for group 1la.
An additional attempt at obtaining test data for 600 pound class Walworth valves was made. Using the EPRI GIDATA database, various utilities with these types of valves were contacted. None of the utilities contacted had differential pressure test data on 600 pound Walworth valves. Most of the facilities contacted used a valve friction factor for the 600 pound Walworth valves based on test data from 300 pound and 900 pound class valves. Test data from another TVA facility was located for 600 pound'alworth valves of 16" size which showed a maximum valve. friction factor of 0.5. Therefore, the additional review confirmed that a 0.6 valve friction factor is reasonable for the group 1la and lib valves.
ASSUMPTION 3 Assumption of a 1.2 valve factor in calculating the design basis 'thrust requirements for globe valve group 2 and 3.
TVA~s REPLY
, TVA used the guidance provided by the EPRI Report TR-103237 for globe valve performance data. This report addresses balanced and unbalanced disc globe valve designs. The BFN globe valves in groups 2 (guide based) and 3 (seat based) are unbalanced disc design valves. EPRI test data for unbalanced disc globe valves show that the internal disc design is a major .contributor to differential pressure thrust requirements. The internal disc designs for the BFN
Ol.
valves were evaluated in accordance with the guidance provided in this EPRI report. Table 6-1, of the EPRI report, shows that the differential pressure force uses a valve safety factor of 1.0 for seat and guide based valves.
BFN added a 20% margin of safety to derive the 1.2 valve safety factor used for globe valve thrust requirements.
Therefore, TVA considers the 1.2 valve safety factor reasonable for the group '2 and 3 globe valves.
ASSUMPTXON 4 Assumption of a 10 percent rate of loading in calculating design basis thrust requirements for HOVs with roller screw stem nuts.
TVA' REPLY TVA is aware of the testing being performed at another nuclear facility. TVA contacted the utility and was informed that the testing will be complete by September 1998-. Therefore, within three months of receipt of the test data, TVA plans to review the test data, and make adjustments to the rate of loading value for .roller screw stem nuts.
DC MOVs In addition, NRC requested TVA to submit its plans and schedule to complete a quantitative analysis of the adequacy of the stroke times of its Direct Current (DC) HOVs under design basis conditions.
TVA's REPLY TVA has perfor'med a quantitative analysis of the BFN DC MOVs. This analysis used the design basis conditions for valve operation and has determined that, the valves with specific stroke time requirements are capable of performing their safety function within the stroke times required.
This analysis is available for NRC review onsite.
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