Letter Sequence Other |
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Results
Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin
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MONTHYEARML20235S2971987-10-0202 October 1987 Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc Project stage: Meeting ML20236A6141987-10-16016 October 1987 Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation Project stage: Other ML20236A8491987-10-16016 October 1987 Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702 Project stage: Other ML20236D1051987-10-21021 October 1987 Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo Project stage: Other ML20236F5471987-10-23023 October 1987 Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure Project stage: Other ML20236F9651987-10-27027 October 1987 Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker Project stage: Meeting ML20236S0181987-11-18018 November 1987 Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl Project stage: Other ML20149M1981988-02-16016 February 1988 Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility Project stage: Other 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420 Project stage: Other ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility Project stage: Other ML20147G8541988-03-0101 March 1988 Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers Project stage: Other ML20147F9981988-03-0404 March 1988 Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility Project stage: Other ML20150B1821988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant Project stage: Other ML20148A8901988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035 Project stage: Other ML20150A8991988-03-0909 March 1988 Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant Project stage: Other ML20150C4071988-03-11011 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant Project stage: Other BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988 Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001 Project stage: Other ML20148B6661988-03-16016 March 1988 Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant Project stage: Other NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers Project stage: Other ML20148K2251988-03-25025 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225 Project stage: Other ML20151G7911988-03-28028 March 1988 Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin Project stage: Other ML20151A9451988-03-30030 March 1988 Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility Project stage: Other 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant Project stage: Other ML20151B2021988-04-0404 April 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl Project stage: Other RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant Project stage: Other ML20148Q7241988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch Project stage: Other ML20151H7791988-04-0707 April 1988 Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program Project stage: Other ML20151E4191988-04-0808 April 1988 Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants Project stage: Other ML20151E8681988-04-11011 April 1988 Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed Project stage: Other ML20151H9651988-04-13013 April 1988 Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed Project stage: Other ML20151G1151988-04-13013 April 1988 Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed Project stage: Other ML20205P6881988-04-20020 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant Project stage: Other ML20155E3921988-06-0909 June 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp Project stage: Other ML20150B5261988-06-30030 June 1988 Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers Project stage: Other ML20150D3971988-07-0505 July 1988 Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151E0181988-07-14014 July 1988 Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151Q9201988-08-0202 August 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154D2331988-09-0909 September 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary Project stage: Other ML20154E1541988-09-0909 September 1988 Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20155A4561988-09-29029 September 1988 Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date Project stage: Other ML20235J1681989-02-17017 February 1989 Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant Project stage: Other ML20235J1651989-02-17017 February 1989 Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers Project stage: Other ML20247C7191989-05-15015 May 1989 Forwards Supplemental Response to NRC Bulletin 88-001 Re Westinghouse Series Ds Circuit Breakers.Insp Info Corrected Project stage: Supplement ML20247K0751989-05-24024 May 1989 Responds to NRC Bulletin 88-001 Re Defects of Westinghouse Circuit Breakers.All forty-seven Westinghouse Type Ds Breakers Inspected Were Found to Have Acceptable Breaker Mechanism Alignment Project stage: Other A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage1989-07-24024 July 1989 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage Project stage: Other 1988-03-07
[Table View] |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211P4961999-09-0909 September 1999 Revised Notification of 990916 Meeting with Tva.Meeting Will Be Closed to Public Due to Proprietary Info Contained in Westinghouse TR WCAP-15128 to Be Discussed ML20211H7841999-08-31031 August 1999 Notification of 990916 Meeting with Util in Rockville,Md to Discuss TVA Intent to Aply for License Amend to Use Alternate Steam Generator Repair Criteria for Stress Corrosion Cracking Evaluated in W TR WCAP-15128 ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20210G9951999-07-20020 July 1999 Discusses 990628 Meeting Re New NRC Reactor Insp & Oversight Process.List of Attendees & Matl Used in Presentation Enclosed ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20207A4771999-05-18018 May 1999 Notification of 990629 Meeting with Util in Rockville,Md to Discuss long-range Planning with Regard to Dry Storage of Sf at Sequoyah Site ML20206M0061999-05-12012 May 1999 Notification of 990616 Meeting with TVA in Rockville,Md to Discuss long-range Planning with Regard to SG Replacement.Draft Agenda Encl ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20207M6711999-03-12012 March 1999 Forwards Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 Administered on 980928-1001,with as Given Written Exam Encl ML20204B5541999-03-12012 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980928-1001 ML20196H1561998-12-0303 December 1998 Notification of 981215 Meeting with TVA in Rockville,Md to Discuss Current & Future Licensing Activities ML20151X3091998-09-11011 September 1998 Notification of 980930 Meeting with Util in Rockville,Md to Discuss License Amend Request for Extending Sequoyah Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20237D4351998-08-21021 August 1998 Notification of 980901 Meeting W/Util in Rockville,Md to Discuss Planned SG Insp During Sequoyah Unit 1 Cycle 7 Refueling Outage in September 1998 ML20236X7041998-06-22022 June 1998 Notification of 980714 Meeting W/Tva in Rockville,Md to Discuss Status of Current Licensing Activities Re Sequoyah Nuclear Plant.Meeting Replaces Meeting W/Tva Scheduled for 980715 ML20249B7451998-06-19019 June 1998 Notification of 980708 Meeting W/Util in Rockville,Md to Discuss NRC Review of Installation of Lead Use Assemblies Containing U-236 Into Plant Core ML20249B7391998-06-19019 June 1998 Notification of 980715 Meeting W/Util in Rockville,Md to Discuss Status of Current Licensing Activities Re Plant ML20216B7171998-05-0707 May 1998 Notification of 980514 Meeting W/Util in Rockville,Md to Discuss NRC RAI Re TS Change Request to Extend Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20236N6021998-02-25025 February 1998 Responds to 980203 Memo Requesting Assistance in Responding to Operator License Appeal.Ts Branch Concurred in Interpretation ML20203K3261998-02-19019 February 1998 Revised Notification of 980305 Meeting W/Tvs in Rockville, Md.Meeting Being Held at Request of Utility to Discuss Special Project Being Pursued W/Doe,Use of Downblended Highly Enriched U in Fuel Used at Sequoyah Nuclear Plant ML20202D1571998-02-12012 February 1998 Requests That Encl Documents Be Placed on Docket for Sequoyah,Units 1 & 2 & in PDRs for Plant ML20202C5291998-02-11011 February 1998 Requests That Encl Documents Be Placed on Docket & in PDRs for Plant ML20202D1681998-02-11011 February 1998 Discusses MOV Terminal Voltage Issue,Per GL 98-10 Program at Plant.Concludes That Licensee Approach for Determining Operating Voltage for safety-related Movs,Acceptable ML20203A0311998-02-0505 February 1998 Notification of 980305 Meeting W/Tva in Rockville,Md to Discuss Special Projects Being Pursued W/Doe Including Use of Downblended Highly Enriched U in Fuel Used at Plant ML20236N5961997-12-31031 December 1997 Responds to Request for Technical Assistance (TIA 97-019) Re Interpretation of Intent of Sequoyah Nuclear Plant TS 4.10.3.2 ML20203B2651997-12-0303 December 1997 Notification of Meeting W/Tva on 971218 in Rockville,Md to Discuss Plans to Employ Electrosleeving Process to Repair Minor Cracks in Plants SG ML20202H9991997-12-0303 December 1997 Notification of 971210 Meeting W/Util in Rockville,Md to Discuss Current Licensing Activities Re Plant ML20236N4851997-10-16016 October 1997 Responds to 961016 Memo from Region II Requesting Technical Assistance (TIA 96-017) Re Interpretation of Sequoyah TS 3.2.4 on Quadrant Power Tilt Ratio ML20236N4471997-10-0101 October 1997 Responds to 961003,request from Region II for Technical Assistance Re Interpretation of Sequoyah TS 3/4.3.1, Specifically Items 10 & 11 on Table 3.3-1 ML20217D9131997-09-25025 September 1997 Notifies of 971002 Meeting W/Tva in Rockville,Md to Discuss Plans to Employ an Electrosleeving Process to Repair Minor Cracks in Plant SG ML20217P3451997-08-20020 August 1997 Notification of Licensee Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant Unit 1 SG Tube Insp Conducted in Apr 1997.Time & Meeting Room Changed ML20210K3301997-08-15015 August 1997 Notification of 970822 Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant,Unit 1 SG Tube Insp Conducted in Apr 1997 ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20205D9761997-07-0202 July 1997 Ack Receipt of Licensee Response to NOV (SL-IV) on Firewatches (EA 97-092).Licensee Requested That Region II Reconsider Violation as NCV ML20140F6191997-06-11011 June 1997 Forwards Documents Re Snp to Be Placed on Docket & in PDR ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20141K7251997-05-28028 May 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication. W/O Encl ML20140F6471997-05-0707 May 1997 Forwards P Blanch Comments Re Snp Pressurizer Draindown Event for Review ML20140F6351997-05-0505 May 1997 Forwards P Blanch Comments on TVA Evaluation of 970324 Pressurizer Draindown Event.Disagrees W/Conclusion That TVA Failed to Identify Root Cause ML20138D1481997-04-29029 April 1997 Forwards Documents Re Meetings W/Tva Ig Ofc Concerning Review of TVA Nuclear Employees Concerns Resolution Program. Documents Should Be Forwarded to NRC PDR ML20138B5721997-04-25025 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant,Units 1 & 2 to Upgrade Fire Barriers That Contain Thermo-Lag Matl ML20140F4151997-04-25025 April 1997 Notification of 970425 Meeting W/Tva in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant to Upgrade Fire Barriers That Contain Thermo-Lag Matl.Meeting Cancelled ML20205M1931997-04-14014 April 1997 Informs That Lieberman Offers No Objection to Releasing TVA OI Report 2-96-009 to Licensee & PDR Provided That Report Released in Accordance with Guidance in Section 8.2.4 of Investigative Procedures Manual ML20205E3591997-04-10010 April 1997 Discusses Sequoyah NOV Response Extension.Two Weeks Extension Has Been Granted ML20137F7941997-03-28028 March 1997 Requests Technical Assistance Re Design of AFW Control Sys at Plant ML20137C1841997-03-20020 March 1997 Notification of Upcoming Meeting W/Tva on 970321 in Rockville,Md to Discuss Status of Currently Ongoing Applications for Amend of TS for Plant ML20137A6441997-03-19019 March 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication ML20135A6471997-02-25025 February 1997 Notification of 970227 Meeting W/Util in Rockville,Md to Discuss Response to NRC Request for Info Re Plant Amend Request 96-01 ML20203C0591997-02-12012 February 1997 Discusses OI Rept 2-96-009 Re Alleged Falsification of Firewatch Journals.Both Individuals Were Subsequently Terminated ML20205D9591997-02-11011 February 1997 Forwards Copy of OI Rept 2-96-009 Issued on 970124 Re Alleged Falsification of Firewatch Journals at Sequoyah Nuclear Plant.Concludes That Both Firewatch Personnel Failed to Patrol All Assigned Areas & Falsified Firewatch Journals ML20133E8681997-01-0909 January 1997 Notification of 970116 Meeting W/Framatome Cogema Fuels in Rockville,Md to Discuss Use of Bwu Critical Heat Flux Correlation at Sequoyah 1999-09-09
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211P4961999-09-0909 September 1999 Revised Notification of 990916 Meeting with Tva.Meeting Will Be Closed to Public Due to Proprietary Info Contained in Westinghouse TR WCAP-15128 to Be Discussed ML20211H7841999-08-31031 August 1999 Notification of 990916 Meeting with Util in Rockville,Md to Discuss TVA Intent to Aply for License Amend to Use Alternate Steam Generator Repair Criteria for Stress Corrosion Cracking Evaluated in W TR WCAP-15128 ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20210G9951999-07-20020 July 1999 Discusses 990628 Meeting Re New NRC Reactor Insp & Oversight Process.List of Attendees & Matl Used in Presentation Enclosed ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20207A4771999-05-18018 May 1999 Notification of 990629 Meeting with Util in Rockville,Md to Discuss long-range Planning with Regard to Dry Storage of Sf at Sequoyah Site ML20206M0061999-05-12012 May 1999 Notification of 990616 Meeting with TVA in Rockville,Md to Discuss long-range Planning with Regard to SG Replacement.Draft Agenda Encl ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20204B5541999-03-12012 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980928-1001 ML20207M6711999-03-12012 March 1999 Forwards Operator Licensing Exam Repts 50-327/98-302 & 50-328/98-302 Administered on 980928-1001,with as Given Written Exam Encl ML20196H1561998-12-0303 December 1998 Notification of 981215 Meeting with TVA in Rockville,Md to Discuss Current & Future Licensing Activities ML20151X3091998-09-11011 September 1998 Notification of 980930 Meeting with Util in Rockville,Md to Discuss License Amend Request for Extending Sequoyah Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20237D4351998-08-21021 August 1998 Notification of 980901 Meeting W/Util in Rockville,Md to Discuss Planned SG Insp During Sequoyah Unit 1 Cycle 7 Refueling Outage in September 1998 ML20236X7041998-06-22022 June 1998 Notification of 980714 Meeting W/Tva in Rockville,Md to Discuss Status of Current Licensing Activities Re Sequoyah Nuclear Plant.Meeting Replaces Meeting W/Tva Scheduled for 980715 ML20249B7451998-06-19019 June 1998 Notification of 980708 Meeting W/Util in Rockville,Md to Discuss NRC Review of Installation of Lead Use Assemblies Containing U-236 Into Plant Core ML20249B7391998-06-19019 June 1998 Notification of 980715 Meeting W/Util in Rockville,Md to Discuss Status of Current Licensing Activities Re Plant ML20216B7171998-05-0707 May 1998 Notification of 980514 Meeting W/Util in Rockville,Md to Discuss NRC RAI Re TS Change Request to Extend Emergency Diesel Generator Allowed Outage Time from 3 Days to 7 Days ML20236N6021998-02-25025 February 1998 Responds to 980203 Memo Requesting Assistance in Responding to Operator License Appeal.Ts Branch Concurred in Interpretation ML20203K3261998-02-19019 February 1998 Revised Notification of 980305 Meeting W/Tvs in Rockville, Md.Meeting Being Held at Request of Utility to Discuss Special Project Being Pursued W/Doe,Use of Downblended Highly Enriched U in Fuel Used at Sequoyah Nuclear Plant ML20202D1571998-02-12012 February 1998 Requests That Encl Documents Be Placed on Docket for Sequoyah,Units 1 & 2 & in PDRs for Plant ML20202C5291998-02-11011 February 1998 Requests That Encl Documents Be Placed on Docket & in PDRs for Plant ML20202D1681998-02-11011 February 1998 Discusses MOV Terminal Voltage Issue,Per GL 98-10 Program at Plant.Concludes That Licensee Approach for Determining Operating Voltage for safety-related Movs,Acceptable ML20203A0311998-02-0505 February 1998 Notification of 980305 Meeting W/Tva in Rockville,Md to Discuss Special Projects Being Pursued W/Doe Including Use of Downblended Highly Enriched U in Fuel Used at Plant ML20236N5961997-12-31031 December 1997 Responds to Request for Technical Assistance (TIA 97-019) Re Interpretation of Intent of Sequoyah Nuclear Plant TS 4.10.3.2 ML20202H9991997-12-0303 December 1997 Notification of 971210 Meeting W/Util in Rockville,Md to Discuss Current Licensing Activities Re Plant ML20203B2651997-12-0303 December 1997 Notification of Meeting W/Tva on 971218 in Rockville,Md to Discuss Plans to Employ Electrosleeving Process to Repair Minor Cracks in Plants SG ML20236N4851997-10-16016 October 1997 Responds to 961016 Memo from Region II Requesting Technical Assistance (TIA 96-017) Re Interpretation of Sequoyah TS 3.2.4 on Quadrant Power Tilt Ratio ML20236N4471997-10-0101 October 1997 Responds to 961003,request from Region II for Technical Assistance Re Interpretation of Sequoyah TS 3/4.3.1, Specifically Items 10 & 11 on Table 3.3-1 ML20217D9131997-09-25025 September 1997 Notifies of 971002 Meeting W/Tva in Rockville,Md to Discuss Plans to Employ an Electrosleeving Process to Repair Minor Cracks in Plant SG ML20217P3451997-08-20020 August 1997 Notification of Licensee Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant Unit 1 SG Tube Insp Conducted in Apr 1997.Time & Meeting Room Changed ML20210K3301997-08-15015 August 1997 Notification of 970822 Meeting W/Util in Rockville,Md to Discuss Test Methods Used & Results of Plant,Unit 1 SG Tube Insp Conducted in Apr 1997 ML20205M3331997-07-28028 July 1997 Provides Final Agenda for Region II Enforcement Meeting to Be Held on 970730.OI Attendance Requested for Issue Involving Termination of Turkey Point Radwaste Operator Who Failed to Follow Procedure ML20205D9761997-07-0202 July 1997 Ack Receipt of Licensee Response to NOV (SL-IV) on Firewatches (EA 97-092).Licensee Requested That Region II Reconsider Violation as NCV ML20140F6191997-06-11011 June 1997 Forwards Documents Re Snp to Be Placed on Docket & in PDR ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20141K7251997-05-28028 May 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication. W/O Encl ML20140F6471997-05-0707 May 1997 Forwards P Blanch Comments Re Snp Pressurizer Draindown Event for Review ML20140F6351997-05-0505 May 1997 Forwards P Blanch Comments on TVA Evaluation of 970324 Pressurizer Draindown Event.Disagrees W/Conclusion That TVA Failed to Identify Root Cause ML20138D1481997-04-29029 April 1997 Forwards Documents Re Meetings W/Tva Ig Ofc Concerning Review of TVA Nuclear Employees Concerns Resolution Program. Documents Should Be Forwarded to NRC PDR ML20140F4151997-04-25025 April 1997 Notification of 970425 Meeting W/Tva in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant to Upgrade Fire Barriers That Contain Thermo-Lag Matl.Meeting Cancelled ML20138B5721997-04-25025 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Methods & Schedule to Be Employed at Plant,Units 1 & 2 to Upgrade Fire Barriers That Contain Thermo-Lag Matl ML20205M1931997-04-14014 April 1997 Informs That Lieberman Offers No Objection to Releasing TVA OI Report 2-96-009 to Licensee & PDR Provided That Report Released in Accordance with Guidance in Section 8.2.4 of Investigative Procedures Manual ML20205E3591997-04-10010 April 1997 Discusses Sequoyah NOV Response Extension.Two Weeks Extension Has Been Granted ML20137F7941997-03-28028 March 1997 Requests Technical Assistance Re Design of AFW Control Sys at Plant ML20137C1841997-03-20020 March 1997 Notification of Upcoming Meeting W/Tva on 970321 in Rockville,Md to Discuss Status of Currently Ongoing Applications for Amend of TS for Plant ML20137A6441997-03-19019 March 1997 Forwards Signed Original of Order Imposing Civil Monetary Penalty (Tva),For Transmittal to Ofc of Fr for Publication ML20135A6471997-02-25025 February 1997 Notification of 970227 Meeting W/Util in Rockville,Md to Discuss Response to NRC Request for Info Re Plant Amend Request 96-01 ML20203C0591997-02-12012 February 1997 Discusses OI Rept 2-96-009 Re Alleged Falsification of Firewatch Journals.Both Individuals Were Subsequently Terminated ML20205D9591997-02-11011 February 1997 Forwards Copy of OI Rept 2-96-009 Issued on 970124 Re Alleged Falsification of Firewatch Journals at Sequoyah Nuclear Plant.Concludes That Both Firewatch Personnel Failed to Patrol All Assigned Areas & Falsified Firewatch Journals ML20133E8681997-01-0909 January 1997 Notification of 970116 Meeting W/Framatome Cogema Fuels in Rockville,Md to Discuss Use of Bwu Critical Heat Flux Correlation at Sequoyah 1999-09-09
[Table view] |
Text
_
Docket Nos.: E0-327 and 50-328 . gg.
LICENSEE: Tennessee Valley Authority FACILITY: Sequoyah Nuclear Plant, Units 1 and 2
SUBJECT:
SEQUOYAH 2. CIRCUIT BREAKER POLE SHAFT WELD FAILURE (TACs 65955/65956)
Reference:
' Memorandum from D. Hood dated.0ctober 23, 1987
" Record of Telephone Conversation Regarding Sequoyah.2 Circuit Breaker Pole Shaft Weld Failure," Docket Nos. 50-327 and 50-328 The above reference sumarized an October 20, 1987 telephone discussion between the NRC and Tennessee Valley Authority regarding two broken fillet-welds on the pole shaft assembly of the circuit breaker that energizes the emergency fire protection pumps for Sequoyah Unit 2. The reference acknowledged that TVA's preliminary findings from the engineering analysis by its Material Engineering Section were discussed in J. B. Hosmer's memorandum dated July 10,1987 (same as enclosure 2 of D. Hood memorandum, "Sumary of September 23, 1987 Meeting on- Westinghouse Switchgear Failures,"
dated October 2, 1987). The NRC's copy of photographs attached to Hosmer's July 10, 1987 memorandum were of poor' reproduction quality and better copies were to be forwarded to NRC.
Accordingly, the NRC has received the enclosed Technical Report No..M86-87-A216-dated October 3,1987 with attached Figures I through 4.
B Darl Hood, Project Manager Project Directorate II-3 Division of Reactor Projects, I/II-
Enclosure:
As stated cc: E. Pugh, TVA J. Hosmer, TVA J. Jelovich, W_
TI C.D. Sellers EMcKenna NRC PDR JRichardson Local PDR ccheng PRC System VHodge MRood KNaidu DHood TPeebles, RII ySH J J f4 PD#II-3/DRP-I/II PD#II-3/DRP-I/II DHood/mac DHood, Acting PD 11/ g /87 11/,y/87 hDR DOC 27 F PDR
'4
[# "
UNITED STATES -
NUCLEAR REGULATORY COMMISSION
\
E WASHINGTON, D. C. 20555 NOV 161987 Docket Nos.: 50-327 and 50-328 i
LICENSEE: Tennessee Valley Authority FACILITY: Sequoyah Nuclear Plant, Units 1 and 2
SUBJECT:
SEQUOYAH 2 CIRCUIT BREAKER POLE SHAFT WELD FAILURE (TACs 65955/65956)
Reference:
Memorandum from D. Hood dated October 23, 1987
' " Record of Telephone Conversation Regarding Sequoyah 2 Circuit Breaker Pole Shaft Weld -
Failure," Docket Nos. 50-327 and 50-328 The above reference sumarized an October 20, 1987 telephone discussion between the NRC and Tennessee Valley Authority regarding two broken fillet i
welds on the pole shaf t assembly )f the circuit breaker that energizes the emergency fire protection pumps for Sequoyah Unit 2. The reference acknowledged that TVA's preliminary findings from the engineering analysis by its Material Engineering Section were discussed in J. B. Hosmer's memorandum dated July 10,1987 (same as enclosure 2 of D. Hood memorandum,
" Summary of September 23, 1987 Meeting on Westinghouse Switchgear Failures,"
dated October 2, 1987). The NRC's copy of photographs attached to Hosmer's July 10, 1987 memorandum were of poor reproduction quality and better copies were to be forwarded to NRC.
Accordingly, the NRC has received the enclosed Technical Report No. M86-87-A216 dated October 3, 1987 with attached Figures 1 through 4. -
eL
- Darl Hood, Project Manager Project Directorate II-3 Division of Reactor Projects. I/II i
Enclosure:
As stated cc: E. Pugh, TVA J. Hosmer, TVA J. Jelovich, W _
s m___ _
'E 13
~
. 871014 254 aggagy 30,: 336_87-A216 !
TECHNICAL REPORT
, SHEET NO.: i 1 of I sheets DATE OF REPORT: 10/3/87 LOCATION: Central Laboratories - PSC - Chattanooga
SUBJECT:
CONTROL ROD DS-15 BREAKER, SEQUOYAH NUCLEAR PLANT - CUSTOMER j SAMPLE NUMBER 87-33 x i
\ l
\ I
-) A COPIES SENT TO: Robert L._Phillins-T2). RIMS, Lab Files; Wa-~f$d /W A AY) 0t7n PREPARED 'B?: Delsa L. Fraz3er' CHECKED BY: RebecceNUoins APPROVED BY: R.~ lb.~ Morley l l
-1 The Metallurgical Laboratory Section received the subject sample (Figure la) with a- 1 request to determine the fracture mode. Visual examination of the sample showed that the plate in Area 3 had completely separated from the rod at the weld and that cracking was observed at the weld in Area 4 (Figures Ib and 2). Porosity was also observed in the weld of Area 4.
{
Cross sections through Areas 1, 3,'and 4 (Figure 3) showed porosity in-the weld'in l Area 4. 'Also, the weld in this area did not appear to penetrate into the plate and rod, resulting in a poor bond. Fracture surfaces were ductile (Figure 48) in Area 3 l I
and Area 4. Poor welding techniques were determined to be the cause of failure.
l The microstructure of the rod consisted of ferrite and pearlite, while'the microstructure of the plate consisted of ferritic grains (Figure 4b and c). l If any additional information is required, please refer to Metallurgical Laboratory Report No. M86-87-A216.
I DLF:SAV (2333)
Attachments: Figures 1 through 4 l .
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Figure 1 - Control Rod DS-15 Breaker, Seguoyah Nuclear Plant - M86-87-A216, Customer Sample No. 87-33.
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Figure 2 - Control Rod DS-IS Breaker, Seguoyah Nuclear Plant - M86-87-A216, Customer Sample No. 87-33.
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Vigure 3 - Control Rod DS-IS Breaker, Sequoyah Nuclear Plant - M86-87-A216, Customer Sample No. 87 -33.
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- c. Photomicro6raph of the !
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' Figure 4 - Control Rod DS-35 Breaker, Seguoyah Nuclear Plant - M86-87 A216.-
Customer Sample No. 87-33.
- - _ - _ _ _ - _ - -