ML20153F531
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| ML20153F531 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah, 05000000 |
| Issue date: | 04/28/1988 |
| From: | Barr K NRC OFFICE OF SPECIAL PROJECTS |
| To: | White S TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8805100359 | |
| Download: ML20153F531 (2) | |
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M4461999-10-20020 October 1999
[Table view]Forwards Rev 8 to Sequoyah Nuclear Plant Physical Security/ Contingency Plan, IAW 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 05000327/LER-1999-002, Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project1999-10-15015 October 1999 Forwards LER 99-002-00 Re Start of Units 1 & 2 EDGs as Result of Cable Being Damaged During Installation of Thermo- Lag for Kaowool Upgrade Project ML20217J4151999-10-15015 October 1999 Forwards Request for Addl Info Re Util 990624 Application for Amend of TSs That Would Revise TS for Weighing of Ice Condenser Ice Baskets ML18039A9021999-10-15015 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 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 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. ML20217G1141999-10-0707 October 1999 Responds to from P Salas,Providing Response to NRC Risk Determination Associated with 990630 Flooding Event at Sequoyah Facility.Meeting to Discuss Risk Determination Issues Scheduled for 991021 in Atlanta,Ga ML20217B2981999-10-0606 October 1999 Discusses Closeout of GL 92-01,rev 1,suppl 1, Reactor Vessel Integrity, for Sequoyah Nuclear Plant,Units 1 & 2. NRC Also Hereby Solicits Any Written Comments That TVA May Have on Current Rvid Data by 991101 ML20217B8431999-10-0505 October 1999 Requests NRC Review & Approval of ASME Code Relief Requests That Were Identified in Plant Second 10-yr ISI Interval for Both Units.Encl 3 Provides Util Procedure for Calculation of ASME Code Coverage for Section XI Nondestructive Exams ML20212J5981999-10-0101 October 1999 Forwards SE Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plnat,Unit 1 ML20217C7101999-10-0101 October 1999 Forwards Response to NRC 990910 RAI Re Sequoyah Nuclear Plant,Units 1 & 2 URI 50-327/98-04-02 & 50-328/98-04-02 Re Ice Weight Representative Sample IR 05000327/19990041999-10-0101 October 1999 Ack Receipt of Providing Comments on Insp Repts 50-327/99-04 & 50-328/99-04.NRC Considered Comments for Apparent Violation Involving 10CFR50.59 Issue 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 ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program 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 ML20216J9351999-09-27027 September 1999 Responds to NRC Re Violations Noted in Insp Repts 50-327/99-04 & 50-328/99-04.Corrective Actions:Risk Determination Evaluation Was Performed & Licensee Concluded That Event Is in Green Regulatory Response Band ML20217A9451999-09-27027 September 1999 Forwards Insp Repts 50-327/99-05 & 50-328/99-05 on 990718- 0828.One Violation Identified & Being Treated as Non-Cited Violation ML20212F0751999-09-23023 September 1999 Forwards SER Granting Util 981021 Request for Relief from ASME Code,Section XI Requirements from Certain Inservice Insp at Sequoyah Nuclear Power Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) ML20212F4501999-09-23023 September 1999 Forwards Amends 246 & 237 to Licenses DPR-77 & DPR-79, Respectively & Ser.Amends Approve Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212M1911999-09-21021 September 1999 Discusses Exercise of Enforcement Discretion Re Apparent Violation Noted in Insp Repts 50-327/99-04 & 50-328/99-04 Associated with Implementation of Procedural Changes Which Resulted in Three Containment Penetrations Being Left Open ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML20211Q0311999-09-10010 September 1999 Requests Written Documentation from TVA to Provide Technical Assistance to Region II Re TS Compliance & Ice Condenser Maint Practices at Plant 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 ML20216F5441999-09-0707 September 1999 Provides Results of Risk Evaluation of 990630,flooding Event at Sequoyah 1 & 2 Reactor Facilities.Event Was Documented in Insp Rept 50-327/99-04 & 50-328/99-04 & Transmitted in Ltr, ML20211N5681999-09-0101 September 1999 Submits Clarification of Two Issues Raised in Insp Repts 50-327/99-04 & 50-328/99-04,dtd 990813,which Was First Insp Rept Issued for Plant Under NRC Power Reactor Oversight Process Pilot Plant Study ML20211G5881999-08-27027 August 1999 Submits Summary of 990820 Management Meeting Re Plant Performance.List of Attendees & Matl Used in Presentation Enclosed 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 ML20211F8891999-08-25025 August 1999 Forwards Sequoyah Nuclear Plant Unit 1 Cycle 9 Refueling Outage, Re Completed SG Activities,Per TSs 4.4.5.5.b & 4.4.5.5.c ML20211A1851999-08-16016 August 1999 Forwards Proprietary TR WCAP-15128 & non-proprietary Rept WCAP-15129 for NRC Review.Repts Are Provided in Advance of TS Change That Is Being Prepared to Support Cycle 10 Rfo. Proprietary TR Withheld,Per 10CFR2.790 ML20210V1471999-08-13013 August 1999 Forwards Insp Repts 50-327/99-04 & 50-328/99-04 on 990601- 0717.One Potentially Safety Significant Issue Identified.On 990630,inadequate Performance of Storm Drain Sys Caused Water from Heavy Rainfall to Backup & Flood Turbine Bldg ML20211A1921999-08-12012 August 1999 Requests Proprietary TR WCAP-15128, Depth-Based SG Tube Repair Criteria for Axial PWSCC at Dented TSP Intersections, Be Withheld from Public Disclosure Per 10CFR2.790 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 ML20210Q5011999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at Sequoyah Nuclear Plant. Sample Registration Ltr Encl ML20210L4291999-08-0202 August 1999 Forwards Sequoyah Nuclear Plant Unit 2 Cycle 9 12-Month SG Insp Rept & SG-99-07-009, Sequoyah Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept. Repts Submitted IAW TS 4.4.5.5.b & TS 4.4.5.5.c 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 ML20210L1611999-07-30030 July 1999 Forwards Request for Relief RV-4 Re ASME Class 1,2 & 3 Prvs, Per First ten-year Inservice Test Time Interval.Review & Approval of RV-4 Is Requested to Support Unit 1 Cycle 10 Refueling Outage,Scheduled to Start 000213 ML20210G5301999-07-28028 July 1999 Forwards Sequoyah Nuclear Plant Unit 2 ISI Summary Rept That Contains Historical Record of Repairs,Replacement & ISI & Augmented Examinations That Were Performed on ASME Code Class 1 & 2 Components from 971104-990511 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) ML20211B9661999-07-26026 July 1999 Informs That Sequoyah Nuclear Plant Sewage Treatment Plant, NPDES 0026450 Outfall 112,is in Standby Status.Flow Has Been Diverted from Sys Since Jan 1998 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 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 1999-09-09 Category:NRC TO UTILITY MONTHYEARML20062G7711990-11-20020 November 1990
[Table view]Forwards Computer Printout of Generic & Plant Specific Info Contained in NRC Sims for Facility.Requests That Sims Printout Be Updated W/Actual or Projected Completion Dates for MPA Items within 90 Days of Receipt of Ltr ML20062F5491990-11-16016 November 1990 Forwards Insp Repts 50-327/90-34 & 50-328/90-34 on 901006- 1105 & Notice of Violation ML20217A5461990-11-14014 November 1990 Ack Receipt of 901026 Response to Violations Noted in Insp Repts 50-327/90-28 & 50-328/90-28.Implementation of Corrective Actions Will Be Examined During Future Insp IR 05000327/19900221990-11-13013 November 1990 Ack Receipt of Addl Response to Violations Noted in Insp Repts 50-327/90-22 & 50-328/90-22.Corrective Actions Will Be Examined During Future Insps ML20217A5361990-11-13013 November 1990 Confirms Arrangements for 901119 Mgt Meeting at Plant Site to Discuss Shutdown from Outside Control Room Test to Be Conducted in Startup Test Program ML20062E6601990-11-13013 November 1990 Confirms Arrangements for 901119 Mgt Meeting at Plant Site to Discuss Unit 2 Restart & Project Plan & Separation of Units 1 & 3 from Unit 2.Proposed Meeting Agenda Encl ML20217A6051990-11-0909 November 1990 Forwards Augmented Insp Team Repts 50-327/90-36 & 50-328/90-36 on 901011-19.NRC Concludes That Multiple Failures of Main Steam Check Valves on 901008 Resulted from Inadequate Recognition & Correction of Deficiencies ML20062F1831990-11-0808 November 1990 Advises That 901015 Rev 25 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20062D5421990-11-0707 November 1990 Forwards List of Unimplemented Generic Safety Issues at Facilities,Per Generic Ltr 90-04 ML20058E1111990-11-0202 November 1990 Grants 901023 Request for Extension of 60-day Reporting Requirement for Cycle 5 Radial Peaking Factor Limit Rept ML20058F1141990-11-0101 November 1990 Forwards Insp Repts 50-327/90-32 & 50-328/90-32 on 900906- 1005 & Notice of Violation IR 05000327/19900181990-10-31031 October 1990 Ack Receipt of Addressing Open Unresolved Items in Insp Repts 50-327/90-18 & 50-328/90-18 ML20062B2371990-10-12012 October 1990 Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address ML20058A8441990-10-11011 October 1990 Forwards Insp Repts 50-327/90-29 & 50-328/90-29 on 900827-31 & Notice of Violation ML20062A0611990-10-0909 October 1990 Expresses Appreciation to Util for Prompt and Extensive Support Extended to NRC Following Fire at Inspector Home ML20059N0711990-10-0202 October 1990 Requests Util to Provide within 45 Days of Receipt of Ltr Listing of All Commitments Made to Justify Restart of Plant ML20059N5811990-10-0202 October 1990 Forwards Insp Repts 50-327/90-31 & 50-328/90-31 on 900910-14.No Violations or Deviations Noted IR 05000327/19900231990-09-19019 September 1990 Confirms 900924 Mgt Meeting in Atlanta,Ga to Discuss ALARA Program & Weaknesses Noted in Insp Repts 50-327/90-23 & 50-328/90-23 ML20059M8281990-09-14014 September 1990 Confirms Conversation Between P Carier,Pj Kellogg on 900910 Re Management Meeting Scheduled for 900921 ML20059F9071990-09-10010 September 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,per NRC ML20059H3741990-08-31031 August 1990 Forwards Insp Repts 50-327/90-26 & 50-328/90-26 on 900706-0805.Noncited Violations Noted ML20059H0311990-08-30030 August 1990 Forwards Insp Repts 50-327/90-23 & 50-328/90-23 on 900625-29 & 0730.Weaknesses Noted.Util Encouraged to Provide Increased Mgt Attention to Radiological Controls to Assure That Significant Decline in ALARA Program Does Not Occur ML20059H3531990-08-29029 August 1990 Forwards Insp Repts 50-327/90-27 & 50-328/90-27 on 900730-0803.No Violations or Deviations Noted ML20056B4991990-08-21021 August 1990 Forwards Evaluation of Westinghouse Owners Group Bounding Analysis,Per Util Response to Bulletin 88-011, Pressurizer Surge Line Thermal Stratification ML20058Q1901990-08-13013 August 1990 Ack Receipt of 900705 & 0802 Ltrs,Transmitting Objectives & Scenario Package,Respectively,For Exercise Scheduled for Wk of 900917 ML20058Q1191990-08-13013 August 1990 Forwards Insp Repts 50-259/90-20,50-260/90-20 & 50-296/90-20 on 900625-29 & 0709-13.No Violations or Deviations Noted ML20058N8001990-08-13013 August 1990 Requests Provision of Listed Info Prior to Restart of Units 1 & 3.Performance of PRA for Unit 2 in Manner That Takes Into Account Dependencies to Equipment Located in Other Two Units Also Requested ML20058P8111990-08-0303 August 1990 Forwards Insp Repts 50-327/90-21 & 50-328/90-21 on 900709-13.No Violations or Deviations Noted ML20056A6101990-08-0202 August 1990 Advises of Closure of NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow, Per Util ML20056A4751990-07-26026 July 1990 Forwards Insp Repts 50-327/90-22 & 50-328/90-22 on 900606- 0705 & Notice of Violation.Nrc Decided Not to Hold Enforcement Conference or Propose Civil Penalty Because Significant Changes in Plant Mgt Occurred ML20055H9261990-07-25025 July 1990 Advises That 900119 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable ML20055H8851990-07-25025 July 1990 Considers 900425 Request for Approval to Eliminate Site Local Recovery Ctrs Withdrawn.Review Terminated IR 05000327/19900091990-07-20020 July 1990 Discusses SALP Repts 50-327/90-09 & 50-328/90-09 & Forwards Summary of 900530 SALP Meeting.Improvements Noted.Encourages Pursuance & Monitoring of Effectiveness of Corrective Actions ML20055G5651990-07-20020 July 1990 Forwards Order Imposing Civil Penalty in Amount of $75,000, Per 900412 Notice of Violation.Violation Regards RHR Pump Deadheading.Requests Listed Info within 30 Days of Ltr Date ML20055F9181990-07-19019 July 1990 Discusses Corrective Actions for Feedwater Control Problems During Unit 2,Cycle 3 Restart.Nrc Concludes That Feedwater Control Study Addresses Problems of feedwater-related Trips That Occurred in 1988 & 1989 ML20055G3381990-07-18018 July 1990 Advises of Closure of Review of Generic Ltr 83-28,Item 2.2.2 Re Vendor Interface for safety-related Components ML20055F7971990-07-16016 July 1990 Advises That 900126 Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment, Acceptable.Documentation Re Implementation of Generic Ltr & Results of Programs Should Be Retained in Plant Records ML20055D8231990-07-0303 July 1990 Advises That Util 890223,0512 & 900204 Responses to Generic Ltr 88-14 Re Instrument Air Sys Acceptable ML20055H3901990-06-29029 June 1990 Forwards Insp Repts 50-327/90-20 & 50-328/90-20 on 900506-0606.No Violations or Deviations Noted ML20055D2611990-06-29029 June 1990 Requests Addl Info Re Alternative Testing of Reactor Vessel Head & Internals Lifting Rigs IR 05000327/19900141990-06-25025 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-327/90-14 & 50-328/90-14 ML20059M8551990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C7691990-06-12012 June 1990 Advises That 900615 SALP Meeting Cancelled Until Later Date ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248E2291989-09-28028 September 1989 Requests Addl Info Re Implementation of Suppl 3 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, within 30 Days of Ltr Receipt ML20248B2521989-09-27027 September 1989 Forwards Summary of 890914 Mgt Meeting in Region II Ofc to Discuss Problems Encountered When NRC Administered Exams During Wks of 890710 & 17,to Employees Currently Holding Licenses to Operate Plant 1990-09-19 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217J4151999-10-15015 October 1999
[Table view]Forwards Request for Addl Info Re Util 990624 Application for Amend of TSs That Would Revise TS for Weighing of Ice Condenser Ice Baskets 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 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 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 ML20217G1141999-10-0707 October 1999 Responds to from P Salas,Providing Response to NRC Risk Determination Associated with 990630 Flooding Event at Sequoyah Facility.Meeting to Discuss Risk Determination Issues Scheduled for 991021 in Atlanta,Ga ML20217B2981999-10-0606 October 1999 Discusses Closeout of GL 92-01,rev 1,suppl 1, Reactor Vessel Integrity, for Sequoyah Nuclear Plant,Units 1 & 2. NRC Also Hereby Solicits Any Written Comments That TVA May Have on Current Rvid Data by 991101 ML20212J5981999-10-0101 October 1999 Forwards SE Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plnat,Unit 1 IR 05000327/19990041999-10-0101 October 1999 Ack Receipt of Providing Comments on Insp Repts 50-327/99-04 & 50-328/99-04.NRC Considered Comments for Apparent Violation Involving 10CFR50.59 Issue ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program 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 ML20217A9451999-09-27027 September 1999 Forwards Insp Repts 50-327/99-05 & 50-328/99-05 on 990718- 0828.One Violation Identified & Being Treated as Non-Cited Violation ML20212F4501999-09-23023 September 1999 Forwards Amends 246 & 237 to Licenses DPR-77 & DPR-79, Respectively & Ser.Amends Approve Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20212F0751999-09-23023 September 1999 Forwards SER Granting Util 981021 Request for Relief from ASME Code,Section XI Requirements from Certain Inservice Insp at Sequoyah Nuclear Power Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) ML20212M1911999-09-21021 September 1999 Discusses Exercise of Enforcement Discretion Re Apparent Violation Noted in Insp Repts 50-327/99-04 & 50-328/99-04 Associated with Implementation of Procedural Changes Which Resulted in Three Containment Penetrations Being Left Open ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML20211Q0311999-09-10010 September 1999 Requests Written Documentation from TVA to Provide Technical Assistance to Region II Re TS Compliance & Ice Condenser Maint Practices at Plant ML20216F5441999-09-0707 September 1999 Provides Results of Risk Evaluation of 990630,flooding Event at Sequoyah 1 & 2 Reactor Facilities.Event Was Documented in Insp Rept 50-327/99-04 & 50-328/99-04 & Transmitted in Ltr, ML20211G5881999-08-27027 August 1999 Submits Summary of 990820 Management Meeting Re Plant Performance.List of Attendees & Matl Used in Presentation Enclosed 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 ML20210V1471999-08-13013 August 1999 Forwards Insp Repts 50-327/99-04 & 50-328/99-04 on 990601- 0717.One Potentially Safety Significant Issue Identified.On 990630,inadequate Performance of Storm Drain Sys Caused Water from Heavy Rainfall to Backup & Flood Turbine Bldg ML20210Q5011999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006 at Sequoyah Nuclear Plant. Sample Registration Ltr Encl 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 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 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, ML20210B2521999-07-14014 July 1999 Confirms 990712 Telcon Between J Smith of Licensee Staff & M Shannon of NRC Re semi-annual Mgt Meeting Schedule for 990820 in Atlanta,Ga to Discuss Recent Sequoyah Nuclear Plant Performance 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 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 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 ML20209E4071999-06-30030 June 1999 Forwards Insp Repts 50-327/99-03 & 50-328/99-03 on 990328- 0531.Violations Being Treated as Noncited Violations 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 ML20196J8261999-06-28028 June 1999 Forwards Safety Evaluation Authorizing Request for Relief from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Certain Inservice Inspections at Sequoyah Nuclear Plant,Units 1 & 2 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 ML20195E9311999-05-28028 May 1999 Informs of Planned Insp Activities for Licensee to Have Opportunity to Prepare for Insps & Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities ML20207A5721999-05-20020 May 1999 Forwards Correction to Previously Issued Amend 163 to License DPR-79 Re SR 4.1.1.1.1.d Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS 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 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 ML20206C0841999-04-23023 April 1999 Forwards Insp Repts 50-327/99-02 & 50-328/99-02 on 990214-0327.No Violations Noted ML20206B9591999-04-20020 April 1999 Responds to 990417 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in Unit 1 TS 3.1.2.2,3.1.2.4 & 3.5.2 & Documents 990417 Telephone Conversation When NRC Orally Issued NOED ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML20205T3771999-04-0909 April 1999 Informs That on 990317,R Champion & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Are Wks of 000612 & 26 for Approx 16 Candidates ML20205T1751999-04-0909 April 1999 Informs That on 990408 R Driscoll & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Dates Scheduled for Wk of 000807 for Approx Seven Candidates ML20205J2521999-04-0505 April 1999 Informs That Effective 990328,A De Agazio Assigned as Project Manager for Browns Ferry Nuclear Plant,Units 1,2 & 3 ML20205F9231999-04-0101 April 1999 Forwards SE Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST, Valve Program for Plant,Units 1,2 & 3 ML20205B9601999-03-24024 March 1999 Seventh Partial Response to FOIA Request for Documents. Records in App N Already Available in Pdr.App O Records Being Released in Entirety & App P Records Being Withheld in Part (Ref FOIA Exemptions 7C,2 & 5) ML20204J5451999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Sequoyah Plant Performance Review on Feb 1998-Jan 1999.Historical Listing of Plant Issues & Details of NRC Insp Plan for Next 8 Months Encl ML20205A1821999-03-19019 March 1999 Discusses Plant Performance Review of Browns Ferry NPP Completed on 990208.Determined Overall Performance to Be Acceptable.Security,Fire Protection,Radiation Protection & Plant Chemistry Continued to Be Effective ML20204J5721999-03-15015 March 1999 Forwards Insp Repts 50-327/99-01 & 50-328/99-01 on 990103-0213.Violations Noted & Being Treated as non-cited Violations.Weakness Identified in Licensed Operator Training Program & Freeze Protection Program 1999-09-07 |
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,Tp.nessee Valley Authority MITN: Mr. S. A. White Manager of Nuclear Power 6N 3SA Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 -
Gentlemen:
SUBJECT:
DOCKET NOS. 50-259, 50-260, 50-296, 50-327 AND 50-328 As part of the NRC Confirnatory Measurements Program, liquid samples spiked with radionuclides will be sent to the Sequoyah and Browns Ferry facilities for radiochemical analyses. These samples are to be analyzed for tritium, strontium-S9, strontium-90 and iron-55 in accordance with your approved procedures for analysis of liquid waste samples. If routine analyses of this type are normally performed by a vendor, this vendor should be used to analyze the spiked samples. The spiked samples, with instructions, will be sent under separate cover from the Department of Energy's Radiological and Environmental Sciences Laboratory, within approximately 30 days.
We request that the analyses be completed as soon as practicable, but no later than 60 days from receipt of the samples. Results should be sent to:
V. S. Nuclear Regulatory Commission, Attn: Mr. J. B. Kahle. Our evaluation of your results will be discussed with your staff and transmitted in a letter.
Spiked samples will be sent to you on an annual basis as part of our routine inspection program.
If you have any questions regarding this program, please contact Mr. Kahle by telephone at (404) 331-6968.
Sincerely, Kenneth P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division Office of Special Projects cc: (See page 2) i l
8905100359 0G0428 PDR ADOCK 05000259 PDR P
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Tennessee Valley Autnerity 2 cc: / P. Pomrehn, Site Director Browns Ferry Nuclear Plant y L. Gridley, Director Nuclear Safety and Licensing
/ A. Kirkebo, Director, d.NuclearEngineering J. May, Site Licensing Manager (J' G. Walker, Plant Manager JVA Representative, Rockville Office W. L. Abercrombie, Site Director Sequoyah Nuclear Plant ~
f.R. Harding,SiteLicensing Manager d Smith, Chemistry Supervisor M L. Williams, Jr. , Chemistry Supervisor bec: J. N. Grace, RII
& 0, Ebneter, OSP W. D. Richardson, OSP JH G. Zech, OSP LIr. D. Liaw, OSP W. S. Little, OSP/RII G. K. Hunegs, OSP/RII Z Rutberg, 03C
- C Resident Inspectors ORS Technical Assistant NRC Document Control Desk State of Tennessee State of Alabama l F. R. McCoy, OSP/RII R. E. Carroll, OSP/RII l J. B. Brady, OSP/RII i @f E. Gears, OSP l g Moran, OSP l A. J. Ignatonis, OSP/RII
- A. H. Johnson, OSP/RII l
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