ML20245B405
ML20245B405 | |
Person / Time | |
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Site: | Browns Ferry, Sequoyah, 05000000 |
Issue date: | 04/14/1989 |
From: | Black S Office of Nuclear Reactor Regulation |
To: | Buggs E AFFILIATION NOT ASSIGNED |
Shared Package | |
ML20245B391 | List: |
References | |
NUDOCS 8906230159 | |
Download: ML20245B405 (1) | |
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 PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA MONTHYEARIA-89-409, Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6)1989-09-26026 September 1989
[Table view]Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247R3361989-09-26026 September 1989 Final Response to FOIA Request.App a & B Records Available in PDR & Encl.Portions of App B Record Withheld (Ref FOIA Exemption 6) ML20247Q4601989-09-19019 September 1989 Responds to to Chairman Carr Re RWCU Sys Sample Panel Being Installed at Plant.Potential of Glass Rotameter to Rupture Due to Mechanical Failure of Veriflow Pressure Regulating Valve Assessed ML20245J7001989-08-0404 August 1989 Forwards Public Notice for Plant for Publication in 890808 Chattanooga New-Free Press & Chattanooga Times.Advertising Order Approving Publication Also Encl ML20245F4671989-08-0303 August 1989 Responds to to Chairman Carr Re Concerns.Concerns Have Technical Merits But Do Not Constitute Nuclear Safety Issues ML20247F0481989-07-25025 July 1989 Partial Response to FOIA Request for Records.App L Record Available in Pdr.App M Records Partially Withheld Ref (FOIA Exemption 7).App N Record Provided to Requestor But Not Made Publicly Available at This Time ML20246J9791989-07-0303 July 1989 Responds to Re Potential Industrial Safety Hazard Resulting from Inclusion of Glass Rotameter in RWCU Sample Line at Plant.Nrc Will Continue Monitoring Util Implementation of Corrective Action ML20245D1911989-06-19019 June 1989 Forwards Public Notice Re Util 890616 Application for Amends for Licenses DPR-77 & DPR-79,revising Spec Re Position Indication sys-operating.Requests Publication in Chattanooga News-Free Press & Chattanooga Times on 890621 ML20245B3881989-06-15015 June 1989 Responds to Re Flow & Pressure Drop Calculations for RWCU & Feedwater & Condensate Sample Panels.Util Actions Do Not Have Adverse Impact on Nuclear Reactor Safety to Extent That Protection of Safety of Environ Affected ML20245B4531989-06-0808 June 1989 Forwards Encl Listed Info on Decommissioned & Shutdown Reactors Requested During Discussions at Saxton on 890511 ML20248B4001989-06-0101 June 1989 Responds to to Chairman Zech Re Articles from Chattanooga News-Free Press.Nrc Conducting Extensive Program of Surveillance & Operations at Facility,Including Evaluations of Allegations Made About Plant Operation ML20245B4051989-04-14014 April 1989 Responds to 881004 & 890119,23 & 0310 Ltrs Re Status of Investigation of Concerns About Corrosion Inhibitors & Design of Sampling Sys.Low Velocity of Liquid in Hotwell Sampling Considered Satisfactory ML20246N1521989-02-22022 February 1989 Responds to Re Amended Indemnity Agreement W/ Utils to Permit Storage of Spent Nuclear Fuel.Fr Notice Encl ML20206D9201988-11-0909 November 1988 Responds to Re NRC 880331 Response to Questions Raised Concerning Conditions at Plants & Recipient Proposal to Station Senior Operator in Control Room at All Nuclear Plants to Oversee Plant Operations ML20195G5361988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App a Documents.App a Documents Also Available in PDR ML20195G2121988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App D Document & Releasable Portions of Documents E/1 Through E/3. App D & Releasable Portions of Documents E/4 Through E/6 Available in Pdr.Portions Withheld (Ref FOIA Exemption 5) ML20206H4511988-11-0808 November 1988 Final Response to FOIA Request for Documents.Forwards App U Documents.App U Documents Also Available in Pdr.App U Document Withheld (Ref FOIA Exemption 5) ML20206D8871988-11-0808 November 1988 Responds to 881015 Postcard Recommending Keeping Seabrook & Pilgrim Facilities Closed & Question Re Nuclear Waste Disposal.Two Levels of Waste for Commercial Nuclear Power Plants Considered ML20205S3841988-10-13013 October 1988 Partial Response to FOIA Request for Documents.App D,E & F Records Encl & Available in Pdr.App F Records Partially Withheld (Ref FOIA Exemption 6) DD-88-12, Advises That Time Provided by NRC Regulation for Commission to Review Director'S Decision DD-88-12 Expired.Commission Declined Review & Decision Became Final Agency Action on 880829.Served on 8809071988-09-0707 September 1988 Advises That Time Provided by NRC Regulation for Commission to Review Director'S Decision DD-88-12 Expired.Commission Declined Review & Decision Became Final Agency Action on 880829.Served on 880907 ML20207H8251988-08-25025 August 1988 Forwards Staff Response to to J Keppler Re Comments on TVA Proposed Cable Test Program ML20154D3891988-08-22022 August 1988 Partial Response to FOIA Request for Documents.Forwards App T Documents.Apps & T Documents Available in PDR ML20151Z1421988-08-16016 August 1988 Forwards Response to Stated Ltrs Re Diesel Generator Inadequacies,Used by Petitioners to Request Emergency Suspension of Full Power Operation Pending Completion of Remedial Action.Petition Denied.Encls in Central Files ML20245D6581988-08-0404 August 1988 Discusses to Congressman Hastert Re Concern That Maint & Operations Employees of Listed Nuclear Power Plants in Vicinity of Seneca,Il Working Excessive Hrs ML20206E0051988-07-27027 July 1988 Responds to Enclosing Prior Correspondence W/Nrc Re Conditions at Ref Plants & 10CFR50.54(x) & (Y).Issues Raised Will Be Given Wide Dissemination in Fr & Careful Consideration by NRC ML20207D1121988-07-0505 July 1988 Partial Response to FOIA Request for Documents.Forwards App M Documents.App L Documents Maintained in Pdr.Apps N & O Documents Partially & Totally Withheld,Respectively (Ref FOIA Exemption 5) ML20196A7521988-06-21021 June 1988 Responds to Re Effect of Proposed Landfill on Emergency Evacuation at Plant.Proposed Landfill Would Be Taken Into Account in Emergency Plan Review to Reflect Increased Traffic ML20195F8041988-06-15015 June 1988 First Partial Response to FOIA Request for Documents. Forwards Apps B & C Documents.Documents Available in Pdr.App a Documents Also Available in Pdr.Apps D Through G Documents Withheld (Ref FOIA Exemption 5).Releasable Portion Encl ML20155K0211988-06-13013 June 1988 Partial Response to FOIA Request for Documents.Forwards App D Documents.App C Documents Available in Pdr.App E Documents Completely Withheld (Ref FOIA Exemption 5) ML20151M6061988-04-19019 April 1988 Responds to FOIA Request for Info Re Scores of Reactor Operators & Senior Reactor Operators.Forwards Requalification Exam Summary Source Sheets Listed in Encl App W/Personal Privacy Info Deleted ML20151Y4681988-04-15015 April 1988 Partial Response to FOIA Request for Documents Re Event Involving Problems W/Msiv.App a & B Documents Available in Pdr.App B Documents Also Encl ML20151C6641988-04-0404 April 1988 Partial Response to FOIA Request for Documents Re Info Assessment Team Notification & Alleged Valve Tampering. App a Documents Available in Pdr.Forwards App B Documents. App B Documents Also Available in PDR ML20148K6521988-03-28028 March 1988 Denies 880324 Request for Emergency Relief.Remainder of Request Will Be Treated as Petition for Enforcement Action Under 10CFR2.206 & Will Issue Director'S Decision Shortly. Ltr Raised No New Issues Not Already Considered by NRC ML20150D9721988-03-18018 March 1988 Informs of NRC Relocation to Stated Address.Mailing Address Unchanged.A Adams Project Manager & TS Michaels back-up Project Manager ML20150D8641988-03-18018 March 1988 Informs of Relocation of NRR to Rockville,Md.Official Mailing Address Still Remains Same & Project Managers Have New Locations & Phone Numbers.Ts Michaels Still Lead Project Manager for Facility & a Adams Will Serve as Backup ML20149H8811988-02-18018 February 1988 Partial Response to FOIA Request for Documents.Forwards App a Documents.Documents Also Available in PDR ML20149G0731988-02-10010 February 1988 Responds to Re Announced Reorganization of NRC at TMI-2.NRC Personnel Stationed at Site,Region I & NRC Headquaters Will Continue to Provide Effective Regulatory Oversight of Cleanup Activities ML20147E6621988-01-19019 January 1988 Partial Response to FOIA Request.App G Documents Already Available in Pdr.App H Documents,Re INPO Accreditation Training,Encl & Available in PDR ML20147C0281988-01-12012 January 1988 Final Response to FOIA Request for Documents Re Safeteam Program.Forwards App I & J Documents.App H & I Documents Available in Pdr.Other Records Available in Pdr.App J Documents Partially Withheld (Ref FOIA Exemption 6) ML20147D4821988-01-0606 January 1988 Partial Response to FOIA Request for Documents.Forwards App B Documents.Documents Also Available in Pdr.Portions of App B Documents Withheld (Ref FOIA Exemptions 6 & 7) ML20236V7511987-12-0202 December 1987 Partial Response to FOIA Request for All NRC Records & Info Re Petition for Issuance of Show Cause Order.Forwards App N Documents.App M & N Documents Available in Pdr.Portions of App N Documents Deleted (Ref FOIA Exemption 6) ML20236L6761987-11-0909 November 1987 Ninth Partial Response to FOIA Request for Records,Including Notes of Interview of K Mcmahon.Forwards App K Documents. App K & L Documents Partially & Completely Withheld (Ref FOIA Exemptions 6 & 7,respectively) ML20245C4051987-10-29029 October 1987 Final Response to FOIA Request for Records.App a & B Documents Available in Pdr.App a Documents Encl ML20236D4491987-10-23023 October 1987 Partial Response to FOIA Request for Documents,Including Rd Martin 850716 Memo Re Allegation Processing Programs.Encl App E & F Documents in Pdr.App F & G Documents Partially & Completely Withheld (Ref FOIA Exemptions 5 & 6) ML20235R8521987-09-30030 September 1987 Responds to Re EIS for Meltdown of Large Reactors & NRC Compliance W/Nepa.As Result of TMI-2 Accident on 790329,NRC Included Class 9 Accidents in Assessments in Fes Re Licensing of Plants.Related Info Encl ML20235K3461987-09-30030 September 1987 Partial Response to FOIA Request.App C Documents Re Deficient Practices by Util Bolt Supplier Encl & Available in PDR ML20235F8141987-09-24024 September 1987 Partial Response to FOIA Request for Documents.Forwards App B,C & D Documents.App a & B Available in Pdr.App C Documents Partially Withheld (Ref FOIA Exemption 4).App D Documents Withheld in Entirety (Ref FOIA Exemptions 5 & 6) ML20235A4371987-09-17017 September 1987 Final Response to Appeal Re Denial of FOIA Request for Documents Re Concerns of Individual About Util & S&W Technical Svcs.Records Two Through Five on Encl App Forwarded.Record One Withheld (Ref FOIA Exemption 7) ML20238F7581987-09-14014 September 1987 Partial Response to FOIA Request Re Lers.App C Documents Available in Pdr.App D Documents Encl & Available in Pdr.App E Documents Partially Withheld (Ref FOIA Exemption 4).Listed LERs Not Issued Bu Licensees IA-87-512, Partial Response to FOIA Request Re Lers.App C Documents Available in Pdr.App D Documents Encl & Available in Pdr.App E Documents Partially Withheld (Ref FOIA Exemption 4).Listed LERs Not Issued Bu Licensees1987-09-14014 September 1987 Partial Response to FOIA Request Re Lers.App C Documents Available in Pdr.App D Documents Encl & Available in Pdr.App E Documents Partially Withheld (Ref FOIA Exemption 4).Listed LERs Not Issued Bu Licensees 1989-09-26 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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.- 1 g UNITED STATES L
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- 7. t g-j NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
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- April 14,1989 s
Mr. Eugene D. Buggs 409 Cameron Circle, #2402 j E ~ Chattanooga, Tennessee 37402 l
Dear Mr. Buggs:
This is in reply to your letters of October 4,1988; January 19, 1989; January 23, 1989 and March 10, 1989 in which you inquired about the status of !
the investigation of your concerns about corrosion inhibitors and the design of ;
sampling systems. You had also written to the Department of Labor because you !
felt that your job was eliminated in retaliation for raising technical concerns. i The Nuclear Regulatory Commission (NRC) has the responsibility for protecting public health and safety and the environment from effects associated with nuclear facilities and materials subject to licensing. The Commission's range of regulation is generally limited to nuclear safety-related and associated systems and as such, the choice of corrosion inhibitors for c1osed cooling water systems is an issue that does not fall within its area of control. In a similar manner, engineering decisions such as the design of the main sample line and establishing the allowable humidity for dry layups are the responsibility of the licensee.
The low velocity of the liquid in the hotwell sampling line is considered satisfactory since the purpose of the sampling is to measure conductivity and dissolved oxygen. Corrosion in both trains of cooling water systems do occur, but simultaneous catastrophic failure is extremely unlikely. The drawings for the new instrument panels were reviewed by TVA and the pressure taps were shown in the-correct location. The NRC staff monitors these systems to assure safe. operation and shutdown of the nuclear power facility.
In its letter to you dated December 16, 1988, the Department of Labor did not find evidence of discrimination under the Energy Reorganization Act.
While we understand the thrust of your technical concerns and recognize the value of your project, it is not appropriate for us to discuss your resuming employment with TVA.
We appreciate your efforts to inform us of'your concerns. Should you have further questions regarding this matter, please feel free to contact Paul Cortland at (301) 492-0754.
Sincerely, ,
/tk. a 7t. (MWy[L NdL-.
Suzanne . Black, Ass tant Director
( for Projects TVA Projects Division Office of Nucleer Reactor Regulation 8906230159 PDR ADOCK h PNV h59 .
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