Responds to Generic Ltr 91-11, Resolution of Generic Issues 48, 'Lcos for Class 1E Vital Instrument Buses' & 49, 'Interlocks & LCOs for Class 1E Tie Breakers.' Evaluation Concluded That Controls in Place Are SatisfactoryML20101B062 |
Person / Time |
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Site: |
Browns Ferry |
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Issue date: |
04/30/1992 |
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From: |
Zeringue O TENNESSEE VALLEY AUTHORITY |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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REF-GTECI-048, REF-GTECI-049, REF-GTECI-NI, TASK-048, TASK-049, TASK-48, TASK-49, TASK-OR GL-91-11, NUDOCS 9205050199 |
Download: ML20101B062 (10) |
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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
[Table view] |
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Temessee Va4+y Authority. Post 0%ce Scd ?J)3 Decats Al2wN Ef.09 APR 3 01992 O L %e' Zeringue L;e Presukot, Bw rs Ferry Operahnns
- U.S. Nuclear Regulatory Commission ATTN
- Document Control Desk washington, D.C. 20555 o
'lentlemen:
Jn the'datter-of _ ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 - GENERIC LETTER (GL) 91-11, RESOLUTION OF GENERIC ISSUES (GIs) 48, "LCOs FOR CLASS lE VITAL INSTRIDiENT BUSES," AND 49, " INTERLOCKS AND LCOs FOR CLASS lE TIE BREAKERS"
[ Rhferences: 1. TVA to NRC letter dated January 29, 1992, same subject.
This letter provides NRC with BFN's response, pursuant to 10 CFR 50.54(f), to Generic Letter 91-11, R6 solution of Generic Issues 48,
'LCOn For Class lE Vital Instrument Buses,' and 49, ' Interlocks And LCOs For Class lE T.le Breakers," dated July 18, 1991. GL 91-1.1 directed
' licensees to evaluate the applicability of.GIs 4P and 49 to their plant and-to implement procedural centrols (or to provide justification that such controla are not necessary) to fulfill the following requirements:
l-L 1. Limit the time that a plant is in possible violation of the single-failure criterion with reLard to the Class 1E vital instrument buses and' tie-breakers,
- 2. Require surveillances of these components, and
- 3. Ensun that, except for the times covered in Item (1), the plant is operating in an electrical configuration consistent with the regulations and its design bases.
.DFh has completed its evaluation and-has concluded that the
. administrative controls in place satisfy the recommendations of the GL.
The bases for this conclusion are provided in the Enclosure.
9205050199 920430 PDP zADOCX. 05000239-(1037 ip-_
2 U.S. Nuclear Regulatory Commission April 30, 1992 If you have any questi s, please contact Raul R. Enron at (205) 729-7566.
Sincerely,
/
, i J. R. Rupe t Engineering and Modifications Manager In the absence of O. J. Zeringue Vice President, Browns Ferry Operations Enclosure cc (Enclosure):
NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. W. Wilson Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Subscribqd and sworn to before me on is f uth day of M(d 1992.
dAtU k. h h d q1 !.n u Notary Public gwei Waos WW^**
My Commission Expires g o. So _Ci Q
--- _ - - . _ _2____.___-.___.:..__ _ _ _ , _ _ _ _ _ _ _ _ , _ _ _ _ _ __ _ _ _ _ _ __ _ _ _ __
e ENCLOSURE The following is the proposed resolution of Generic Issues (Gis) 48 and 49 for BFN Units 1, 2, and 3 utilizing the guidan e provided in Enclosure I cf Generic Letter (GL) 91-11.
The GL recommended that each licensee " ensure that your plant has procedures that include tinie limitations and surveillance requirements for
- 1. Vital instrument buses (typically 120VAC buses),
- 2. Inverters or other onsite power sources to the vital instrument buses, and
- 3. Tie breakers that can connect redundant Class IE buses (AC or DC) at one unit or that can connect Class lE buses between units at the same site."
LMpfqnse To GI-48. "LCOs for Class 1E Vital Instrument. Buses" Two BFN electrical systems satisfy the definition of a " vital instrument bus" (VIB) provided in GL 91-11. These are 1) the 208/120VAC Instrument and Control Power System, and 2) the 120VAC Reactor Protection (RPS) System Power Supply. A brief description of each system along with TVA's rerponse to the GI for each system is provided below.
1, 208\1,20VAC Instrument and Control (I & C) Power System One [, air of I & C buses is provided for each unit. Each bus in the pair is energized by an indeliendent Class IE 480V shutdawn board source via a 480-208\l20VAC transformer in series with a 208\l20-208\l20VAC regulating transformer, and is ultimately backed by the shutdown board's associated diesel generator (DG). To increase the reliability of the system, the alternate supplies are frcm the same division of another unit. The following table summarizes the normal and alternate power supply arrangements for each bus:
BUS NORMAL ALTERNATE DIVISION 1&C Bus A (Ul) 480V Shutdown Bd la 480V Shutdown Bo 2A I I&C Bus B (Ul) 480V Shutdown Bd IB 480V Shutdown Bd 3B 11 I&C Bus A (U2) 480V Shutdown Bd 2A 480V Shutdown Bd 3A I I&C Bus B (U2) 480V Shutdown Bd 2B 480V Shutdown Bd IB II I&C Bus A (U3) 480V Shutdown Bd 3A 430V Shutdown Bd 1 A I I&C Bus B (U3) 480V Shutdown Bd 3B 480V Shutdown Bd 2B II An auto-transfer switch is provided on sch unit to transfer to the alternate supply after a three second time delay when the normal supply voltagefecreases to 70% of nominal bus voltage. Auto transfer back to the normal supplyjppfl occur when the l normal supply voltage increases to 90% of its nominal value.'Th61&C bas transfer scheme is shown pictorially on Figure 1.
Enclosure
- Page 2 of 3 The I&C transformer capabilities are adequate to supply normal ioads plus the additional I&C bus load from another unit. Transfer to the alternae supply (same division from another unit) maint? ins the divisional integrity of the I&C buses and does not expose the I & C t,uses to the potential for a violation of the single failure criterion. Therefore, no time limitations or additional utrols are recessary to ensure the reliability and avai'. ability of the 208\120VAC I & Tower System.
- 2. Desiption of the 120VAC RPS Power Supply Two redundant and electrically separated RPS channels, A and B, including power supplies, are provided on each unit. Each RPS power supply consists of a motor-generator (MG) set and two series circuit protectors. Each unit's RPS Channel A MG set is powered from that unit's 480V RMOV board A. Each unit's Channel B MG set ia powered from the corresponding 480V RMOV board B. The MG sets have no alternate power supplies. For Unit 2, the Unit Preferred Regulating trnasformer provides the capability for a common alternate power supply to both RPS channels' distribution buses from the Standby Auxii ary Power System. The Unit Preferred Transformer is a 4d0-240\120VAC stepdown transformer fed from the Unit 2 480V RMOV Board 2B. For Units 1 and 3 the kPS alternate supply capability for each bus is provided by each unit's RPS regulating transformer. The RPS Regulating Transformers are supplied from the Standby Auxiliary Power System via 480V Shutdown board IB for Unit 1 and 480V RMOV Board 3B for Unit 3. A switch is provided on each unit battery board to align a RPS channel to its alternate supply.
l The RPS bus transfer scheme is shown on Figure 7. Interlocks are provided to prevent the alterrate supply from supplying both channels simultaneously, and to prevent closing both the normal supply breaker and the alternate supply breaker to any one channel simultaneously. The design of the RPS is such that on a loss of normal or alternate power, components go to their fail-safe condition and a icactor scram occurs. The RPS bus must be manually re-energized following a loss of power.
Taerefore, no single-failure exposure exists for the RPS power supply.
As described above, the concerns presented in the GL are not applicable to the 208/120V AC I&C Power System and the RPS Power Supply due to inherent design features. Therefore, we have concluded that GI-48 is resolved for the BFN VIBs.
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Enclosure Page 3 of 8 FIGURE 1 '
BFN I & C BUS TRANSFER SCHEME 4 80 S H U T DO'./N BOA RD 1 A 480 SHUTDOWN BOARD 2A 480 SHUTDOWN BOARD 3 A I
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FIGURE'2 Enclosure RPS BUS TRANSFER SCHEME rage 4 0r s -
UNIT 1 UNIT. 2 UNIT 3 480V SHUTDOWN BD 1B 480V RMOV- BD 2A 480V RMOV BD 1 A 480V RMOV BD 3A 4UOV RMOV BD 1B 480V RMOV BD 2P 480V RMOV BD 3B RPS REG. UNIT RPS TRANSFORMER P REF'D REG.
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e-Enclosure Page 5 of 8 B13ponse to GT-49. " Interlocks and 14 2s for Class IE Tle Breakers"
- 1. Standby At;xiliary Power System The Class IE standby AC electrical supply and distribution system for Units 1 and 2 consists of four DGs, four 4KV Shutdown Boards (Boards A, B, C, ud Dj, n,ar 480V Shutdown Boards, ten 480V Reactor Motor-operated Valve (RMOV) Boards
[i.e. Unit 1(2) 480V RMOV boards 1(2)A,1(2)B,1(2)C,1(2)D, and 1(2)E], eight MC sets, two DG 480V Auxiliary Boc.rds, and one 480V Control Bay Ventilation Board. The Class lE stanooy AC supply and distribution system for Unit 3 is separate from that of Units 1 and 2. It consists of four DGs, four 4KV Shutdown Boards (Poards 3EA,3EB,3EC, and 3ED), two 480V Shutdown Boards, five 480V RMOV Boards (3A,3B,3C,3D, and 3E), four MG sets, two DG 480V Auxiliary Boards, one 480V Standby Gas Trt.atment System Board, and one 480V Control Bay Ventilation Board.
Each 480V RMOV board has a normal and an alternate power supn . 'The n! ternate power supply is the other divisional 480V Shutdown Board in each uni: Electrical interlocks are provided to prevent the paralleling of the normal and alternate supplies.
Each unit's 480V RMOV Boards A, B, and C must be manually transferred to their alternate source. 480V RMOV Boards D and E are automatically transferred to their respective alternate saurce on a loss of vol Tge. 480V RMOV Boards D and E supply those valves necessary for Low Pressure Coolant Injection. These boards are connected to both the normal and alternate sources via MG sets to prevent fault propagation followmg an automatic transfer. Prior to the transfer of 480V RMOV boards l A, IB, IC,2A,2B, 3A,3B, and 3C to the alternate feeders, the following criteria must be adhered to:
A. While a unit is operating at power, transfer of the associated 480V RMOV Board to the alternate feeder is only p"missible when there is a failure of normal supply. Return to the normal supply shall be within twelve hours or the reactor shall be in cold shutdown within the n ~xt twenty four hoes. Indefinite operation on the alternate feeder'is permitted o.Jy during the shutdown condition.
B. The loading limitations shown on the 480V Shutdown and 480V RMO\ Board single line drawings shall not be exceeded.
C. Preventive maintenance on the ncrmal feeder breakers for the 480V RMOV Boards or their feeders is permitted only during the shutdown condition.
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Enclosure Page 6 of 8 D. When a 480V Shutdown Board is being fed from its emergency transformer
. the altemate feeder breaker to a RMOV Board fed from the Shutdown Board cannot be closed.-
These testrictions are also applicable to the Unit 3 DG 480V Auxiliary Boards when Unit 3 is in operation.
When a 480V Shutdown Board or Unit 1 or 2 DG 480V Auxiliary Board is placed on its alternate source, thJ board may be considered operable as long as the technical specification limiting condition for operation associated with the normal source 4KV
' Shutdown Board is adhered to.
These restrictions have been incorporated into Operr, ting Instruction 0-01-57B, 480V/240V AC Electrical System. The alignment c.f the 480V RMOV and Shttdown Boards for system operability is performed in accordance with 0-OI-57B and is independently verified. Board alignment is then monitored by the BFN System Status Control Program.
2, 4KV Shur awn Board Tie-breakers Each of the 4KV Shutdown Boards _on Units 1 and 2 (Board A, B, C, and D) may be connected to its respective (same division) Unit 3 4KV Shutdown Board (Boards 3EA, 3EB, 3EC, and 3ED, respectivelyY via cross-tie breakers. This A.gn feature enables a Unit 1 or a Unit 2 Diesel Ger.erator (DG) to be operated in parallel with its respective Unit 3 DG. For example, DG A can be paralleled only with DG 3A.These
-interconnections are through manrally_ controlled circuit breakers which are
- electrically interlocked to prevent the tie-breaker from being closed when the normal upply breaker is closed. Additionalinterlocks are provided to ensure that the DGs are properly synchromzed prior to interconnection. The alignment of the 4KV LShutdown ~Boacds is monitored in accordance with the System Status Control Program.
Parallel operation of two DGs is administratively limited to a condition where an
. accident signal is present in any unit and offsite power is not available and 10 minutes have elapsed since the accident began.' Parallel DG operation is controlled by Abnormal Operating Instruction 0-AOI-57-1 A, Loss .of Offsite Power.
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Enclosure Page 7 of 8
- 3. Maintenance Tie-Breakers for the 480V RMOY Boards D and E As described above, the normal / alternate power supplies to each uait's 480V RMOV Baards D (Division I) and E (Division II) are MG sets. A third power source, a maintenance feeder, from 480V RMOV board C (non-Divisional)is also available for supplying 480V RMOV boards D and E. Use of this feeder allows maintenance to be performed on th^ MG sets.
The use of the maintenance feeders from each unit's 480V RMOV board C to 480V RMOV boards D and E is administratively controlled by BFN Operating Instcuction 0-01-57B,480V/240VAC Electrical System, and may be used only during periods of reactor shutdown. During reactor operation, the maintenance feeder breakeii are controlled by the System Status Control Program.
- 4. 250V DC Power System Tie-Breakers The 250V DC Power System is consists of two subsystems:
A. The 250V plant DC system, which consists of four 120-cell lead-acid batteries (on'. Class 1E unit battery and battery charger per unit, one non-Class lE statica battery and battery charger, and one Class lE spare charger). 250V plant DC system power is distributed to its safety-related loads via three 250V DC battery boards and nine (three per unit) divisionalized DC RMOV boards.
An alternate power supply for each DC RMOV Board is provided ,, another unit's 250V DC battery.
B. The 250V DC Control power system (250V DC control power supplies A, B, C, D, and 3EB for 4KV Shutdown Boards A, B, C, D, and 3EB, and 480V Shutdown Boards I A, 2A, iB and 2B, respectively), which consists of five lead-acid baueries (one battery and battery charger for each Hutdown board, and one spare battery charger). Alternate power sources are provided by the 250V plant LC system. Electrical interlocks prevent paralleling the normal and alternate power supplies.
The use of alterna*: supplies for the 4KV Shutdown Boards,480V Shutdown Boards, and tne DC kMOV Wards are administratively controlled by 0-OI-57D, DC Electrical System Operating Instruction and BFN Technical Specifications, Section 3.9, Auxiliary Electrical Systems. During the use of alternate control power sources for the 4KV Shutdown Boards and the 480V Sbutdown Boards, continued reactor operation is permissible during the succeeding the days. During the use of the
- c. _ ., ,
s Enclosure Page 8 of 8 alternate feeders to the DC RMOV Boards continued po_wer operation is permissible during the succeeding seven days. The ^]ignment of the 250V DC Power Systerr is controlled by 0-OI-57D, DC Electrical System Operating Instruction and is monitored by the System Status Control Program, BFN . has evaluated the use of Class IE tie-breakers against the NRC staff's recommendations contained in the GL and has determined that the existing controls are sufficient to resolve the GI-49 concern.
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