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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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CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RZDS)
CCESSION NBR:9902020320 FACZL:5'0-259 Browns DOC.DATE: 99/01/21 NOTARIZED: NO Ferry Nuclear Power Station, Unit 1, Tennessee DOCKET 05000259 I
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50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION ABNEY,T.E. Tennessee Valley Authority l RECIP . NAME RECIPIENT AFFILIATION UN
SUBJECT:
Records Management Branch (Document Control Desk)
C 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.
DISTRIBUTION CODE: IEOZD COPIES RECEIVED:LTR i ENCL TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response 5 SIZE:
E'OTES:
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 AEOD/SPD/RAB 1 1 AEOD TTC 1 1 DEDRO 1 1 E E 1 1 NRR/DRCH/HOHB 1 1 NRR/DRPM/PECB 1 1 NRR/DRPM/PERB 1 1 NUDOCS-ABSTRACT 1 1 OE DIR 1 1 OGC/HDS3 1 1 RGN2 FILE 01 1 1 D
EXTERNAL: LZTCO BRYCE,J H 1 1 NOAC 1 1 NRC PDR 1' NUDOCS FULLTEXT 1 i 1 N
~ I 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 19 ENCL 19
Tennessee Valley Authority, Post Office Box 2000, Decatur, Aiabarna 35609.2000 January 21, 1999 U. S. Nuclear Regulatory Commission 1'0 CFR 2.201 ATTN: Document Control Desk Washington, D.C. 20555 Gentleman:
In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) NRC INSPECTION REPORT 50 259 r 50 260 r 50 296/98 07 COMMENTS ON VIOLATION 50 260 r 296/98-07-04 This letter provides TVA's comments on the subject NOV transmitted by letter from Mr. H. 0. Christensen, NRC, to Mr. J. A. Scalice, TVA, dated December 9, 1998. In the letter, two violations of NRC requirements50-296/98-07-01). were identified.
TVA agrees with the first violation (VIO This violation does not require a response since the corrective actions are already adequately addressed on the docket in the inspection report.
The second violation (VIO 50-260, 296/98-07-04) in the letter was associated with the procurement and receipt activities for a valve part. This violation does not require a response since the corrective actions are already adequately addressed in the inspection report. While TVA agrees with the violation, the discussion in the inspection report is not correct in all aspects. For clarity, we have provided our.
comments in the Enclosure. These comments do not affect the 9902020320 990i2i PDR ADOCK 05000259 8 PDR
U.S. Nuclear Regulatory Commission Page 2 January 21, 1999 corrective a'ctions addressed on the docket in the inspection report.
There are no commitments in this letter. If you have any questions on these comments, please contact me at (256) 729-3675.
Si cerel Abney Site Licen ng a d Industry Affair Manager Enclosure cc: See page 3
0 U.S. Nuclear Regulatory Commission Page 3 January 21, 1999 Enclosure cc (Enclosure):
Regional Administrator U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street S.W.
Suite 23T85 Atlanta, Georgia 30303 Mr. P. E. Fredrickson 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 '5611 Mr. L. Raghavan, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
0 ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 INSPECTION REPORT NUMBER 50 259 50 260 g 50 296/98 07
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COMMENTS ON NOTICE OF. VIOLATION (NOV)
RESTATEMENT OF VIOLATION (VIO) 50-260, 296/98-07-04 10 CFR 50 Appendix B, Criterion V, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
The licensee' Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision (Rev.) 8, Section 6.1, states that the Quality Assurance Program requires that quality-related activities shall be prescribed by documented instructions appropriate to the circumstances. Activities shall be accomplished in accordance with these procedures and instructions.
TVA nuclear power mechanical design standard DS-M18.2.18, Rev. 10, Note T2054, requires nonconformances to the requirements of the contract to be handled in accordance with the vendor's quality assurance program. Nonconformances with a disposition of "Accept As-Is" or "Repair" shall be submitted to TVA for approval.'VA standard program and process procedure SPP-4.2, Material Receipt 'and Inspection, Rev. 0, implements the requirements of TVA NQA-PLN89-A concerning receipt and inspection requirements for quality-related materials. Section 3.6 of this procedure specifically implements the requirements of DS-M18.2.18 and requires responsible engineering personnel to disposition material nonconforming conditions and document the results of the disposition on a Receiving Unsatisfactory Report (RUR).
Contrary to the above, on October 8, 1997, contract number 121076190ZNU4138 was placed with Fisher Control without imposing the requirements of DS-M18.2.18, Note T2054, for a QA Level 1 purchase order. This failure resulted in an inadequate receipt inspection on November 14, 1997, which was performed for TVA Item Identification Code (TIIC) No. CBW9098C. This procurement action involved-the purchase of three Fisher Pressure Controller Model 4160 flappers, part number 1H2669-41132. The vendor provided nonconformance report (NCR) Nos. 544579-1, -2, and -3 in connection with deviations from the vendor
t specification for the flapper diameter. Fisher design required a diameter of 1.99 to 2.00 inches and the measured, diameter of all three flappers was 1.95 inches. The vendor also provided a recommendation for use as-is. These nonconformances were never dispositioned by Procurement Engineering and the results documented on a RUR, in accordance with the requirements of procedure SPP-4.2.
This is a Severity Level IV Violation (Supplement I).
TVA's COMMENTS ON VIOLATION In the third paragraph of the violation discussion, it is stated that TVA nuclear power mechanical design standard DS-M18.2.18, Rev. 10, Note T2054, requires nonconformances to the requirements of the contract to be handled in accordance with the vendor's assurance program and that nonconformances with a 'uality disposition of "Accept-as-is" or "Repair" be submitted to TVA for approval. It further states that Section 3.6 of TVA SPP-4.2, Materials Receipt and Inspection, specifically implements the requirements of DS-M18.2.18. Actually, as detailed below, DS-M18.2.18 Note T2054 is only applicable if designated on the Procurement Data Sheet (PDS) in accordance with NEDP-8, Technical Evaluation for Procurement of Materials and Services. Thus, SPP-4.2 does not directly implement the subject note.
TVA nuclear power mechanical design standard DS-M18.2.18, Rev. 10, provides procurement personnel with a list of approximately 180 Standardized Procurement Notes which may be used as an aid to procurement activities. When used, these Standardized Procurement Notes communicate applicable engineering requirements and other provisions to procuring organizations, and may be applied to procurement materials or services documents.
The Standardized Procurement Notes are, however, not stand-alone requirements and apply to specific procurements only if prescribed on the contract. For typical contracts the notes that are pertinent to the procurement activity are specific'd by TVA on the purchase contract.
TVA procedure NEDP-8 establishes the procedural requirements to perform technical evaluations and to determine quality requirements for the specification and procurement of materials.
NEDP-8 is used for procuring safety related and non-safety material, as well as equipment of various quality class designations. Section 3.3.6 of NEDP-8 requires the preparation of a PDS which, in turn, establishes the necessary technical and quality requirements for procuring items. Typical attributes listed on the PDS include such items as technical requirements and specifications, receipt inspection requirements, requirements E-2
for 10 CFR Part 21 applicability, handling of nonconformances, arid so forth. These types of standard requirements are incorporated into the procurement contract by the Procurement Engineering Group (PEG) by including the applicable Standardized Procurement Notes from DS-M18.2.18 on the PDS as appropriate for the safety and quality class of the material being procured.
Custom technical or TVA specified design requirements may also be included on the PDS.
The PDS for contract 121076190ZNU4138 did not prescribe any specific TVA technical requirements since the part was a standard vendor supplied replacement part. The PDS did include several Standardized Procurement- Notes from DS-M18.2.18 as enumerated below.
- 1. Note T1061 requires the parts and materials be supplied under a Quality Assurance (QA) program evaluated and accepted by TVA, and which is in accordance with the applicable provisions of ANSI N45.2.
- 2. Note T2050 requires that the vendor review the contents of the bid and communicate any exceptions or changes, including part number changes, to TVA prior to executing the order, and provide an analysis of the effects of .any such changes on form, fit, function, or material.
- 3. Note T2055 specifies that the parts supplied on the order were subject to the provisions of 10 CFR Part 21 regarding the reporting of defects and noncompliances and requires that TVA be informed of each such defect or noncompliance. (Inclusion of Note T2055 is standard on all QA level 1 device requisitions.)
- 4. Note T2056 requires the vendor to provide access to their facilities for quality inspection or audit, if requested.
- 5. Note T4157 requires a Certificate of Conformance (COC) be provided which certifies that the items are in conformance to the product specifications for the part/catalog numbers referenced on the contract.
- 6. Note T5050 requires the item be marked with the TVA purchase order and traceable to the COC.
- 7. Note T6056 specifies ANSI N45.2.2 Level C packing, shipping, handling, and storage requirements.
NEDP-8 step 3.3.6.B.5 requires that arrangements between the supplier and TVA for the identification, and control and disposition of items that do not meet procurement requirements be E-3
established on the PDS. This procedure currently includes a provision that TVA approval is required on procured items which h v a supplier recommended disposition of "Accept-as-is" or "Repair" if procurement requirements are not met by the supp lier.
When invoked, this provision is incorporated by including mechanical design standard DS-M18.2.18 Note T2054 on the PDS which requires nonconformances to the requirements of the contract to be handled in accordance with the vendor's QA program, and that recommended dispositions of "Accept-as-is" or "Repair" be submitted to TVA for approval. If this note is not emp loye d disposition of nonconformances is delegated to the vendor. For the subject contract, Note T2054 was inadverten tly omitted, which is considered by TVA to be a procedure violation of NEDP-8 since current practice is to impose Note T2054 on those contracts where Note T2055 (Part 21) is specified. This omission b quently resulted in not processing the flappers as nonconforming during receipt inspection as explained be low.
For the subject requisition, though not contractually obligated to do so (since Note T2054 was not specified), Fisher provided TVA with an NCR with the each of the 3 delivered flappers. The NCRs described a minor deviation from the manufacturers design specifications in which the flapper diameter dimension was 1.95 inches in lieu of 2.00-1.99 inches. Fisher also provided their luation to "Accept-as-is" indicating that the dimension deviation did not affect the form, fit, or function o f the part, and that all code requirements were met. The vendor also provided a COC as required by contract Note T4157, which warranted that parts were manufactured and shipped in conformance with contract specifications, were satisfactorily tested and t d that the items were free from defects in material/workmanship, and were interchangeable in form, function and material with those originally supplied.
m fit and The, material was subsequently received on site Novembe r 14 1997 and found to be conforming during receipt inspection in accordance with Section 3.4 of SPP-4.2, Material Receipt and Inspection. Section 3.4 states, "items are acceptable if the results of receipt inspections indicate that the items conform with PEG procurement package requirements." Section 3.6 o SPP-4.2 stipulates requirements for resolving unacceptable d't' Acquisition and Material personnel or the PEG, Since, however, Note T2054 had not been specified on t hee PDS SSP-4.2 receipt inspection instruct'ions would not regard the d 'd d "Accept-as-is" dispositions as conditions needing further review by TVA. Thus, the receipt inspection accep e parts for issue and use. Had Note'2054 been included on the PDS, the material would have been determined to be non-conforming during receipt inspection and dispositioned in accordance with SPP-4.2, Section 3.6.
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0 The absence of Note T2054 on a particular contract would allow the vendor to disposition nonconformances in accordance with their own ANSI N45.2 approved QA program and without direct TVA involve'ment. For manufactured parts, the vendor is typically the designer and maintains the engineering drawings and design specifications. Hence, it follows that the vendor is in the best position to provide an engineering disposition regarding the acceptability for use of nonconformances. For procurements where TVA provides specific technical requirements and design specifications, Note T2054 would be applicable and TVA would prime responsibility for the approval of nonconformances. 'ssume Contract 121076190ZNU4138 fits into the former category since TVA requested a replacement part by part number and did not stipulate detailed technical requirements. Since the nonconformance regarding the flapper diameter was a variance from the vendor internal design specifications, Fisher was the most appropriate party to disposition the NCRs. The TVA review, when specified by Note T2054 for this kind of procurement, can best be characterized a's a general oversight review of the vendor disposition rather than an independent engineering review since TVA typically does not have access to the vendor's design specifications. Therefore, the safety significance of the omission of Note T2054 for this procurement is considered low based on the following:
1..The NCRs were written against Fisher's design.
- 2. Fisher dispositioned their NCRs in accordance with their audited ANSI N45.2 program.
- 3. Fisher provided a COC stating: "Fisher Controls certifies that items herein were designed, manufactured, and shipped in.
conformance to contract specifications. All required tests and inspections were performed and the results found to be satisfactory. We further certi'fy that all items shipped herein are free 'from defects in material and/or workmanship.
Parts are certified to be interchangeable in form, fit, function and material with those originally supplied."
Fisher Controls is on TVA's approved vendor list with an ANSI N45.2 QA program. These vendors are periodically audited to verify conformance with their,QA program. Fisher Controls was last audited in June 1997 by the Nuclear Procurement Issues Committee (NUPIC). TVA is a NUPIC participant.
CONCLUSION The characterization in the violation that SPP-4.2, Section 3.6 directly implements standard DS-M18.2.18, Rev. 10, Note T2054 is out of context. As outlined above, DS-M18.2.18 Note T2054 is only applicable if designated on the PDS in accordance with NEDP-8. SPP-4.2, Section 3.6, only applies when material does not conform with PEG package (PDS) requirements.
For a replacement part procurement such as that described in this NOV, TVA considers the inclusion of DS-M18.2.18 Note T2054 as a conservative measure not specifically required by TVA' QA,Plan or by ANSI N45.2.13, Quality Assurance Requirements for Control of Items and Services for Nuclear Power Plants. Accordingly, as discussed in the inspection report, the developed corrective action for recurrence control of this item involves revising procedure NEDP-8 to more clearly describe when vendor nonconformance documentation is to be submitted to TVA and approved by TVA engineering. These corrective actions are unaffected by the preceding comments on this violation.
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