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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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l . ,
e TENNESSEE VALLEY AUTHORIT,Yw P.Fd- ,
CH ATT A NGOG A. TENNESSEE 374o'1 -
400 Chestnut Street Tower II oo NOV 19 AB 2*
November 15, 1982' U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Enclosed is our response to R. C. Lewis' September 29, 1982 letter to H. G. Parris transmitting Inspection Report Nos. 50-259/82-27,
-260/82-27, -296/82-27 regarding activities at our Browns Ferry Nuclear Plant which appeared to have been in violation of NRC regulations. We have enclosed our response to Appendix A, Notice of Violation.
The GET program and the implementing Standard Practice BF 4.5 were completely revised on October 1, 1982. The revision included the standardization of the GET program, realignment of program requirements and condensing content into six courses, realignment of responsibilities for sections charged with instructional duties, and establishment of administrative controls regarding classroom attendance. In addition, the revised program requires all persons to demonstrate comprehension by satisfactorily passing a written examination for each subject area.
Standardized training modules for each GET course have been prepared.
Personnel assigned to Browns Ferry are being retrained on all required GET courses. To date, approximately 35 percent of assigned plant employees and approximately 17 percent of field services employees have been trained. All persons will be retrained by January 31, 1983 A 17-day extension was discussed with and granted by OIE-NRC Inspector Ross Butcher on October 25, 1982. If you have any questions, please call Jim Domer at FTS 858-2725.
To the best of my knowledge, I declare the statements contained herein i are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY l
M L. M. Mills, Kanager Nuclear Licensing l
8301040603 821202 PDR ADOCK 05000259 0 PDR
- O ENCLOSURE RESPONSE TO NRC INSPECTION REPORT NOS.
50-259/82-27, -260/82-27, -296/82-27 R. C. LEWIS' LETTER TO H. G. PARRIS DATED SEPTEMBER 29, 1982 Appendix A Item A - (259, 260, 296/82-27-03) 10 CFR 50, Appendix B Criterion XVIII requires that a comprehensive system of planned and periodic audits be carried out to verify compliance with all aspects of the quality assurance program. Table 17.2-5 of the accepted QA Program endorses the requirements of ANSI N45.2.12, Draft 3, Revision 4 - February 1974, for auditing of quality assurance programs.
Section 4 3 2 3 of this Standard requires that selected elements of the program be audited to the depth necessary to determine whether or not they are being implemented ef fectively. The accepted QA Program, TVA-TR75-1A Revision 5, Section 17.2.18 states that audits shall be conducted to ensure compliance with training requirements.
Contrary to the above, the training program was not audited to the depth necessary to determine whether or not the program is being implemented effectively in that Audit OPQAA-CH-82TS-01 dated April 12 - May 7,1982, identified only one failure to follow training program procedural requirements when in fact multiple failures existed as identified in Violation B below. This audit stated in the overall assessment section that implementation of the general employee training program was inadequate; however, this was not identified as a finding and as a result the audited organization did not take any action to correct this inadequacy.
This is a Severity IV Violation (Supplement I).
- 1. Admission or Denial of the Alleged Violation TVA admits the violation.
- 2. Reasons for the Violation if Admitted Due to workload requirements there was inadequate manpower assigned to the portion of the training audit conducted at Browns Ferry. The scope of the audit included five separate topics. We do not attempt to verify all aspects of a specific area in each scheduled audit.
The objective is to selectively include certain aspects in a particular audit with other aspects to be covered in subsequent audits so that the entire range is covered over a reasonable length of time.
3 Corrective Steps Which Have Been Taken and Results Achieved The need for additional manpower in the Operations Quality Assurance Branch has bcen identified by TVA management responsible for this function. TVA is reorganizing its overall quality assurance program and has already increased the manpower of the Operations Quality Assurance Branch. Upon completion of preliminary training and qualification, this manpower will be available for auditing.
- 4. Corrective Steps Which Will Be Taken to Avoid Further Violations
- a. Manpower sufficient to perforia required audits to the depth necessary will be assigned on future audits.
- b. A training audit of the depth necessary will be performed by April 30, 1983
- 5. Date When Full Compliance Will Be Achieved Full compliance will be achieved on the completion of the training audit April 30, 1983.
Appendix A item n - (259, 260, 204/82-27-01) 10 CFR 50, Appnndix B Criterion V and Section 17.2.5 of the necepted OA Program requires that activities affecting ouality shall be prescribed in procedures and shall he accomplished in accordance with those procedures.
Activities affecting quality were not accomplished in accordance with procedures in that:
- 1. Standard Practice BF 4.5, Plant General Employee Training Program, dated June 23, 1982, requires that personnel who do not receive retraining have their unescorted access badges pulled. This requirement was instituted as a result of a violation identified in IE Reports 50-259, 260, 296/81-02 dated March 18, 1981. This violation identified that all personnel had not received required general employee. training.
Contrary to tbc nbove, a review of training records of site personnel indicates grenter than 10 percent of these people have not received all required training and have not had their unescorted access badges pulled. This is similar to the violation identified in IE Reports 50-259, 260, 296/81-02.
- 2. Standard Practice BF 4.5 requires that the outage organization train all outage annual personnel.
Contrary to the atove, of 147 outage annual persornel training records reviewed, a total of 106 of these people had not received all required F.eneral employee training. These records included 13 out of a total 21 general foremen that had not received QA/QC indoctrination or training.
?. Operational quality Assurance Manual (00AM) Part III, Section 6.1, l felection and Training of Personnel of Nuclenc Power Plants, dated June 15, 1981, paragraph 1.9.1 recuires a continuing progrem for training of replacement personnel and for retreining necessary to ensure that personnel remain proficient.
9 Contrary to the above, there are no plant procedural requirements to assure proficiency is maintained in areas of OA/CC indoctrination, standard practices and plant instructions, document control and authorization of work performance, temporary conditions, plant modificationn, and procurement and material control. Petraining is not being provided in these subjects and a method has not been established to determine that proficiency is being maintained in these arens as required by the 00AM.
- 4. 00AM Part III, Section 6.1 paragraph 1.5.1 requires that training programs be kept up to date to reflect plant modifications and changes to procedures.
Contrary to the above, plant procedural requirements do not specify that the training department receive information on plant modifications oa changes to procedures.
This is a Severity Level IV Violation (Supplement I). The examoles cited above are not all inclusive.
P-1
- 1. Admission or Denial of the Alleged Violation TVA admits the violation occurred as stated.
- 2. _ Reasons for the Violation if Admitted Prowns Ferry Standard Practice 4.5 governing general employee training (GET) at the time of the audit was inadequate with regards to delegating and implementing responsibilities and requirements.
- 3. Corrective Steps Fhich Itave noen Taken and the Results Achieved The Drowns Ferry GET progran and Standard Practice BF 4.9 were revised on October 1, 1982 to improve the GET program. This included:
standardization of the program, realigning the program to six courses, obtainine training nodules from the Muclear Training Branch, realigning responsibilities for sections charged with instructional duties, and establishment of administrative controls regarding classroom i attendance. Standard Practice BF 4.R, as revised, still contains I
requirements regarding removing unescorted access status. This will be rigidly enforced after all individuals have had the opportunity to attend required revised training.
4 Corrective Steos Which Will Be Taken To Avoid Further Violations All Browns Ferry personnel (with the exception of operations personnel) are being scheduled by their respective section supervisors to attend required classes in the revised GET program. Operations personnel will receive their GET training along with their scheduled annual retraining.
- 5. Date Vhen Full Compliance Will Be Achieved Full compliance will be achieved by January 31,19R3 when all currently assigned plant emplovees (except operations personnel) should have received all required GFT training.
Full compliance for operations personnel will he nchieved by December $1}~'
1983 when all annual retraining is complete. Considering the'
~
training and c perience of these personnel, we believe this is an acceptable date.
D-2
- 1. Admission or Denial of the Alleged Violation TVA admits the violation occurred as stated.
- 2. Reasons for the Violation if Admitted Browns Ferry Standard Practice 4.5 governing GET at time of audit was inadequate with regard to implementing program responsibilities and requirements.
- 3. Corrective Steps Which Have Been Taken nnd the Results Achieved The GFT program han heen revised nn stated in Item B-1. All field l' services personnel will be trained on required GET courses. GET classes have been scheduled for each k'onday, Wednesday, and Friday starting on October 8,1982 to accomplish this.
4 Corrective Steps Which Will Be Taken To Avoid Further Violations All field services personnel will be given required revised training.
A Browns Ferry forn BF-54, Individual Training Record, will be maintained to ensure training is accomplished by each individual within
, the prescribed time linits.
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A 4
- 5. Date When Full Compliance Will 9e Achieved Full compliance vill be achieved by January 31, 1083 when all currently assigned field services personnel should complete the required revised training.
4 B-3
- 1. Admission or Denial of the Alleged Violation TVA admits the violation occurred as stated.
- 2. Reasons for the Violation if Admitted
- At the time of the audit, Browns Ferry Standard Practice 4.5, regarding j training, did not recuire retraining in all areas.
i I Correctivo Steps Which Pave Been Taken and the Results Achieved 3
The GET program and Standard Practice 4.5 were revised on October 1, 100?, to require retraining and testing in all GET areas.
4 Corrective Stens Which Will Be Taken To Avoid Further Violations l All assirned personnel (with the exception of operations personnel) are i currently being retrained in the required areas and must demonstrate satisfactory proficiency on a written eyamination. Operations personnel vill reserve their GET training along with their scheduled l annual retraining.
- 5. Date When Full Compliance Will Be Achinved
- Full conpliance will he achieved by January 31, 1983 when all plant
! personne] (except operations personnel) currently assigned will he retrained.
Full _ compliance .for . operations _ p.ersonnel will be achieved by _Decemh.er_$Y,_,
1983 when all annual retraining is complete. Considering the ~
training and experience of these personnel, we S~elieve this is an
~
! acceptable date.
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B4
- 1. Admission or Denial of the A11eaed Violation TVA denies this portion of the violation occurred as stated. The training office does in fact receive plant memorandums and reading lists of revised standard practices and procedures that could have a bearing on the content of CET course material. However, Standard Practice BF 4.5 was revised October 1,1982 to assign responsibility to the designated sections for GET course presentations for receiving changes to plant equipment, layout, procedures, instructions, and implementation of changes as needed to the GET courses.
Item C (259, 260, 296/82-27-02) 10 CF9 50, Appendix B Criterion II and the accepted OA Program, Section 17.2.2, require a training and indoctrination program to assure that oersonnel responsible for performing qualitv-affecting activities are instructed as to the purpose, scope, and inplementation of the quality assurance program.
i Contrary to the above, a training and indoctrination program has not been provided to assure that all personnel responsible for performing quality-affecting activities are instructed as to the purpose, scope, and implementation of the quality assurance program in that:
- 1. There are no requirements to train temporary outage craftsmen in the OA program requirements.
- 2. The training program described in Standard Practice 4.5 allows a period of six nonths to corolete all required general enployee training;
, however, reasures have been provided to assure that craft personnel k have received the required QA indoctrination prior to performing quality-affecting activities.
This is a Severity Level IV Violation (Supplement I).
C-1 1
- 1. Admission or Denial of the Alleged Violation TVA ndmits the viointion occurred as stated.
2 Peasons for the Violation if Admittad l
l At the time of the audit, Browns Ferrv Standard Practice 4.9 I specifically did not require that all ter.porary outage personnel be l trained in OA requirerents.
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3 Corrective Steps hich Have Been Taken and the Results Achieved Standard Practice BP h.5 was revised October 1, 10AP to add all temporary field services personnel to GA progran training requirements or to perform work under the direct supervision of OA-trained individuala until such training is complete. ,
4 Corrective Steps Which Will Be Taken To Avoid Further Violations TiPhter administrative controls are being applied to ensure that craftsmen receive necessary training. The Field Fervices training supervisor is scheduling classes to meet this need.
5 Date Phen Full Compliance Will Be Achieved FulJ compliance was achieved on October 1, 1982 when Standard Practice DF 4.5 was revised.
C-?
- 1. Admission or Denial of the Alleged Violation TVA admits the violation occurred as stated.
- 2. Reasons for tha Violation if Admitted Inadequate detail within proceduros inhibited meeting the objective of ensuring craft personnel responsible for performing quality-affecting activities were instructad in quality assurance (OA) indoctrination.
- 3. Corrective Steps Which Have Deen Taken and the Results Achieved
, The revised Browns Feery Ftandard Penetice 4.5 bas included a l requirenent for all craftsnen, site personnel, contractors, and J Construction Services Franch personnel to nttend a PA indoctrination progran prior to performing cuality-affecting activities or to work under the direct supervision of OA-trained individuals until such training is complete.
! 4 Corrective Steos Which Wil) De Taken To Avoid Further Violations All craftenen will be scheduled for OA training classes and tested to demonstrate proficiency.
- 5. Date Eten Full Compliance Will Be Achieved
! Full compliance will be achieved by January 31, 1993 when all currentiv assigned crnftsnan will have been trained in OA procedures, i
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