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| | issue date = 06/25/1999 | | | issue date = 06/25/1999 |
| | title = 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 | | | title = 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 |
| | author name = ABNEY T E | | | author name = Abney T |
| | author affiliation = TENNESSEE VALLEY AUTHORITY | | | author affiliation = TENNESSEE VALLEY AUTHORITY |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:CATEGORY 1 REGULA'i Y tINFORMATION DISTRZBUTIO | | {{#Wiki_filter:CATEGORY 1 REGULA'i Y tINFORMATION DISTRZBUTIO ~ SYSTEM (RIDS) |
| ~SYSTEM (RIDS)ACCESSION NBR:9907070288 DOC.DATE: 99/06/25 NOTARIZED: | | ACCESSION NBR:9907070288 DOC.DATE: 99/06/25 NOTARIZED: NO DOCKET 4 FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296. |
| NO DOCKET 4 FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296.AUTH.NAME AUTHOR AFFILIATION ABNEY,T.E. | | AUTH. NAME AUTHOR AFFILIATION ABNEY,T.E. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION @pp+S Records Management Branch (Document Control Desk) |
| Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION | |
| @pp+S Records Management Branch (Document Control Desk) | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Requests permanent relief from inservice insp requirements of 10CFR50.55a(g)'or volumetric exam of BFN,Unit 3 circumferential RPV welds.D1STRIBUTION CODE:, A047D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: | | Requests permanent relief from inservice insp requirements of 10CFR50.55a(g)'or volumetric exam of BFN,Unit 3 circumferential RPV welds. |
| Inservice/Testing/Relief from ASME Code-GL-89-04 NOTES: RECIPIENT ID CODE/NAME LPD2-2 LA COPIES LTTR ENCL 1 1 RECIPIENT ID CODE/NAME LONG,'W COPIES LTTR ENCL 1 1 E G 0 INTERNAL: ACRS NUDOCS-ABSTRACT RES/DET/EZB EXTERNAL: LITCO ANDERSON NRC PDR FZL'D.CENTER 01 RES/DET/EMMEB NOAC 1 1 1 0 1 1 1 1 D C N!NOTE TO ALL"RIDS" RECIPIENTS: | | D1STRIBUTION CODE:, A047D COPIES RECEIVED:LTR ENCL SIZE: |
| 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 11 ENCL 10 | | TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES: E RECIPIENT COPIES RECIPIENT COPIES G ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD2-2 LA 1 1 LONG,'W 1 1 0 INTERNAL: ACRS FZL'D. CENTER 01 1 1 NUDOCS-ABSTRACT 1 0 RES/DET/EZB RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON NOAC 1 1 NRC PDR D |
| ~I 5 S' Tennessee Valley Authority, Post Office Box 2000, Decatur, Ahbama 35609-2000 June 25, 1999 10 CFR 50.55a (a)(3)(i)U,.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
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| In the Matter of)Tennessee Valley Authority)Docket No.50-296 BROWNS FERRY NUCLEAR PLANT (BFN)-UNIT 3-REQUEST FOR RELIEF r 3 I S I 1 t REVI S ION 1 r RE~ING REACTOR PRESSURE VESSEL (RPV)SHELL WELDS r AUGMENTED AND AMERI CAN SOC IE TY OF MECHANICAL ENGINEERS (ASME)SECTION XI INSPECTIONS In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting permanent relief (i.e., for the remaining term of operation under the existing license)fro'm inservice inspection requirements of 10 CFR 50.55a(g)for the volumetric examination of the BFN Unit 3 circumferential reactor pressure vessel welds.The proposed alternative in TVA's request for relief provides an acceptable level of quality and safety and is consistent with the guidance and criteria described in NRC Generic Letter (GL)98-05,"Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds." TVA has previously requested relief, for one operating cycle (Cycle 8), from performing successive examinations of the Unit 3 reactor.pressure vessel (RPV)circumferential shell 9907070288 990625 PDR ADQCK'-'OS000296
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| '8.PDR
| | 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 11 ENCL 10 |
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| U.S.Nuclear Regulatory Commission Page 2 June 25, 1999 weld flaws and was granted relief by the NRC in a letter dated August 17, 1998.Subsequent to NRC's approval of TVA's request for relief, the staff completed its review of the BWRVIP-05 Report and issued its final Safety Evaluation Report (SER).This SER authorizes permanent relief from inservice inspection requirements for circumferential BWR reactor pressure vessel welds.The staff's SER also accepted the BWRVIP-05 Report recommendation to eliminate successive examinations for"non threatening" flaws (e.g., such as embedded flaws from material manufacturing or vessel fabrication which experience negligible or no growth during the life of the vessel)provided certain conditions are met.In the enclosed request for relief (3-ISI-1, Revision 1), TVA provides assurance it has met the required conditions to eliminate successive examinations for the.previously identified 15 circumferential weld flaws in the BFN Unit 3 RPV.NRC issued GL 98-05 on November 10, 1998, which stated that licensees of BWRs may request permanent relief from the inservice inspection requirements of 10 CFR 50.55a(g)for the volumetric examination of circumferential reactor pressure welds by demonstrating that: (1)at the expiration of the operating license, the circumferential welds will continue to satisfy the limiting conditional failure probability for circumferential welds in the staff's BWRVIP-05 Report SER dated July 28, 1998, and (2)licensee has implemented operator training and established procedures that limit the frequency of cold over-pressure events to the amount specified in the staff's July 30, 1998 SER.The enclosed request for relief demonstrates that TVA meets the guidance in GL 98-'05 for permanent relief from the inservice inspection requirements of 10 CFR 50.55a(g)for the volumetric examination of the BFN Unit 3 RPV circumferential welds.TVA requests approval of this relief request by December 31, 1999.This is to allow for resource planning for the Unit 3 Cycle 9 (Spring 2000)refueling outage to support scheduled ASNE Section XI outage activities. | | 5 |
| 0 t U,.S.'Nuclear Regulatory Commission Page 3 June 25, 1999 There are no new commitments contained in this letter.If you have any questions, please telephone me at (256)729-2636.Si cere T.E.Abney Manager of icensi and In stry Aff g'.rs Enclosure cc: (Enclosure,: | | ~I S' |
| Mr.William 0.Long, Senior Project Manager U.S.Nuclear Regulatory Commission One White Fli;nt, North 11555 Rockville Pike Rockville, Maryland 20852 Mr.Paul E.Fredrickson, 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 Cl 0 r}} | | |
| | Tennessee Valley Authority, Post Office Box 2000, Decatur, Ahbama 35609-2000 June 25, 1999 10 CFR 50.55a (a) (3) (i) |
| | 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 REQUEST FOR II RELIEF r 3 S 1 t REVIS ION 1 r RE~ ING REACTOR PRESSURE VESSEL (RPV) SHELL WELDS r AUGMENTED AND AMERICAN SOC IE TY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSPECTIONS In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting permanent relief (i.e., for the remaining term of operation under the existing license) fro'm inservice inspection requirements of 10 CFR 50.55a(g) for the volumetric examination of the BFN Unit 3 circumferential reactor pressure vessel welds. The proposed alternative in TVA's request for relief provides an acceptable level of quality and safety and is consistent with the guidance and criteria described in NRC Generic Letter (GL) 98-05, "Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds." |
| | TVA has previously requested relief, for one operating cycle (Cycle 8), from performing successive examinations of the Unit 3 reactor. pressure vessel (RPV) circumferential shell 9907070288 990625 PDR ADQCK'-'OS000296 |
| | '8 . PDR |
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| | U.S. Nuclear Regulatory Commission Page 2 June 25, 1999 weld flaws and was granted relief by the NRC in a letter dated August 17, 1998. Subsequent to NRC's approval of TVA's request for relief, the staff completed its review of the BWRVIP-05 Report and issued its final Safety Evaluation Report (SER). This SER authorizes permanent relief from inservice inspection requirements for circumferential BWR reactor pressure vessel welds. The staff's SER also accepted the BWRVIP-05 Report recommendation to eliminate successive examinations for "non threatening" flaws (e.g., such as embedded flaws from material manufacturing or vessel fabrication which experience negligible or no growth during the life of the vessel) provided certain conditions are met. |
| | In the enclosed request for relief (3-ISI-1, Revision 1), |
| | TVA provides assurance it has met the required conditions to eliminate successive examinations for the .previously identified 15 circumferential weld flaws in the BFN Unit 3 RPV. |
| | NRC issued GL 98-05 on November 10, 1998, which stated that licensees of BWRs may request permanent relief from the inservice inspection requirements of 10 CFR 50.55a(g) for the volumetric examination of circumferential reactor pressure welds by demonstrating that: (1) at the expiration of the operating license, the circumferential welds will continue to satisfy the limiting conditional failure probability for circumferential welds in the staff's BWRVIP-05 Report SER dated July 28, 1998, and (2) licensee has implemented operator training and established procedures that limit the frequency of cold over-pressure events to the amount specified in the staff's July 30, 1998 SER. The enclosed request for relief demonstrates that TVA meets the guidance in GL 98-'05 for permanent relief from the inservice inspection requirements of 10 CFR 50.55a(g) for the volumetric examination of the BFN Unit 3 RPV circumferential welds. |
| | TVA requests approval of this relief request by December 31, 1999. This is to allow for resource planning for the Unit 3 Cycle 9 (Spring 2000) refueling outage to support scheduled ASNE Section XI outage activities. |
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| | U,.S. 'Nuclear Regulatory Commission Page 3 June 25, 1999 There are no new commitments contained in this letter. If you have any questions, please telephone me at (256) 729-2636. |
| | Si cere T. E. Abney Manager of icensi g'.rs and In stry Aff Enclosure cc: (Enclosure,: |
| | Mr. William 0. Long, Senior Project Manager U.S. Nuclear Regulatory Commission One White Fli;nt, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Paul E. Fredrickson, 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 |
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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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Text
CATEGORY 1 REGULA'i Y tINFORMATION DISTRZBUTIO ~ SYSTEM (RIDS)
ACCESSION NBR:9907070288 DOC.DATE: 99/06/25 NOTARIZED: NO DOCKET 4 FACIL:50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296.
AUTH. NAME AUTHOR AFFILIATION ABNEY,T.E. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION @pp+S Records Management Branch (Document Control Desk)
SUBJECT:
Requests permanent relief from inservice insp requirements of 10CFR50.55a(g)'or volumetric exam of BFN,Unit 3 circumferential RPV welds.
D1STRIBUTION CODE:, A047D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 NOTES: E RECIPIENT COPIES RECIPIENT COPIES G ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD2-2 LA 1 1 LONG,'W 1 1 0 INTERNAL: ACRS FZL'D. CENTER 01 1 1 NUDOCS-ABSTRACT 1 0 RES/DET/EZB RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON NOAC 1 1 NRC PDR D
C N!
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 CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 10
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Tennessee Valley Authority, Post Office Box 2000, Decatur, Ahbama 35609-2000 June 25, 1999 10 CFR 50.55a (a) (3) (i)
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 REQUEST FOR II RELIEF r 3 S 1 t REVIS ION 1 r RE~ ING REACTOR PRESSURE VESSEL (RPV) SHELL WELDS r AUGMENTED AND AMERICAN SOC IE TY OF MECHANICAL ENGINEERS (ASME) SECTION XI INSPECTIONS In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting permanent relief (i.e., for the remaining term of operation under the existing license) fro'm inservice inspection requirements of 10 CFR 50.55a(g) for the volumetric examination of the BFN Unit 3 circumferential reactor pressure vessel welds. The proposed alternative in TVA's request for relief provides an acceptable level of quality and safety and is consistent with the guidance and criteria described in NRC Generic Letter (GL) 98-05, "Boiling Water Reactor Licensees Use of the BWRVIP-05 Report to Request Relief from Augmented Examination Requirements on Reactor Pressure Vessel Circumferential Shell Welds."
TVA has previously requested relief, for one operating cycle (Cycle 8), from performing successive examinations of the Unit 3 reactor. pressure vessel (RPV) circumferential shell 9907070288 990625 PDR ADQCK'-'OS000296
'8 . PDR
U.S. Nuclear Regulatory Commission Page 2 June 25, 1999 weld flaws and was granted relief by the NRC in a letter dated August 17, 1998. Subsequent to NRC's approval of TVA's request for relief, the staff completed its review of the BWRVIP-05 Report and issued its final Safety Evaluation Report (SER). This SER authorizes permanent relief from inservice inspection requirements for circumferential BWR reactor pressure vessel welds. The staff's SER also accepted the BWRVIP-05 Report recommendation to eliminate successive examinations for "non threatening" flaws (e.g., such as embedded flaws from material manufacturing or vessel fabrication which experience negligible or no growth during the life of the vessel) provided certain conditions are met.
In the enclosed request for relief (3-ISI-1, Revision 1),
TVA provides assurance it has met the required conditions to eliminate successive examinations for the .previously identified 15 circumferential weld flaws in the BFN Unit 3 RPV.
NRC issued GL 98-05 on November 10, 1998, which stated that licensees of BWRs may request permanent relief from the inservice inspection requirements of 10 CFR 50.55a(g) for the volumetric examination of circumferential reactor pressure welds by demonstrating that: (1) at the expiration of the operating license, the circumferential welds will continue to satisfy the limiting conditional failure probability for circumferential welds in the staff's BWRVIP-05 Report SER dated July 28, 1998, and (2) licensee has implemented operator training and established procedures that limit the frequency of cold over-pressure events to the amount specified in the staff's July 30, 1998 SER. The enclosed request for relief demonstrates that TVA meets the guidance in GL 98-'05 for permanent relief from the inservice inspection requirements of 10 CFR 50.55a(g) for the volumetric examination of the BFN Unit 3 RPV circumferential welds.
TVA requests approval of this relief request by December 31, 1999. This is to allow for resource planning for the Unit 3 Cycle 9 (Spring 2000) refueling outage to support scheduled ASNE Section XI outage activities.
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U,.S. 'Nuclear Regulatory Commission Page 3 June 25, 1999 There are no new commitments contained in this letter. If you have any questions, please telephone me at (256) 729-2636.
Si cere T. E. Abney Manager of icensi g'.rs and In stry Aff Enclosure cc: (Enclosure,:
Mr. William 0. Long, Senior Project Manager U.S. Nuclear Regulatory Commission One White Fli;nt, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Paul E. Fredrickson, 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
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