ML20151E018
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MONTHYEARML20235S2971987-10-0202 October 1987
[Table View]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 ML20149J2421987-12-29029 December 1987 Ack Receipt of Responding to NRC 870826 Request for Info Re Unplanned Automatic Startups of Diesel Generators at Facility.Diesel Startup on Startup & Emergency Transformer Secondaries May Be Unnecessary 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 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 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 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 ML20154E1541988-09-0909 September 1988 Advises That 880408 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 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 NLS8900111, Discusses Actions Taken Prior to & During Spring 1989 Refueling Outage.Engineering Study Determined That Removal of Diesel Generator auto-start Signals Due to Loss of Individual Offsite Power Sources Would Resolve Concern1989-06-19019 June 1989 Discusses Actions Taken Prior to & During Spring 1989 Refueling Outage.Engineering Study Determined That Removal of Diesel Generator auto-start Signals Due to Loss of Individual Offsite Power Sources Would Resolve Concern 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 |
| ML20151E018 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/14/1988 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| References | |
| IEB-88-001, IEB-88-1, TAC-65936, TAC-65955, TAC-67698, NUDOCS 8807250331 | |
| Download: ML20151E018 (2) | |
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Category:CORRESPONDENCE-LETTERS
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Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. 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[Table view]Forwards List of Unimplemented Generic Safety Issues at Facility,Per Generic Ltr 90-04 ML20058J0451990-11-0909 November 1990 Forwards Insp Rept 50-219/90-20 on 901022-26.No Violations Noted.Review of Preparations for Drywell Occupancy During Fuel Movement Identified Areas of Concern ML20058C7291990-10-24024 October 1990 Discusses Insp Rept 50-219/90-80 on 900625 & 29 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Violation Considered Severity Level III & Involved Unqualified Operators at Reactor Controls IR 05000219/19890811990-10-18018 October 1990 Ack Receipt of Informing NRC of Actions Taken to Correct Violations Noted in AIT Insp Rept 50-219/89-81 Re RPS Low Vacuum Setting ML20058A8241990-10-18018 October 1990 Forwards Safety Insp Rept 50-219/90-16 on 900823-0922 & Notice of Violation ML20058A6381990-10-18018 October 1990 Forwards SE Conditionally Accepting Util Insp & Repairs for Igscc,Per Generic Ltr 88-01 ML20058A6601990-10-16016 October 1990 Forwards Request for Addl Info Re Drywell Corrosion Program, Including Sampling of Shell Surfaces for UT Measurements ML20062B8641990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20062A6871990-10-11011 October 1990 Documents Review of Util 900921 Integrated Schedule ABC List Update.Listed Projects Acceptable Except for Items B/A-328 ADA & B/A-402946 ML20058F3211990-10-0303 October 1990 Forwards Safety Insp Rept 50-219/90-17 on 900918-21.No Violations Noted.Schedule for Identification & Disposal of Contents of Tanks in Old Radwaste Bldg Requested within 45 Days of Ltr Date IR 05000219/19900091990-10-0101 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/90-09 ML20059M5201990-09-21021 September 1990 Forwards Safeguards Insp Rept 50-219/90-15 on 900820-24.No Violations Noted ML20059J8021990-09-11011 September 1990 Advises That Util 900621 Response to Open Item Re USI A-46 & Schedule,Acceptable.Requests That Util Confirm Seismic Adequacy of CRD Hydraulic Control Units within 30 Days of Completion of Walkdown ML20059H3291990-09-0606 September 1990 Advises That 900831 Commitment to Install Hardened Wetwell Vent at Plant Acceptable ML20059G3911990-09-0505 September 1990 Recognizes Efforts of G Bond & W Douglas Re Implementation of Emergency Response Data Sys (ERDS) Link at Facility. ERDS Link at Facility Operational & Should Be Implemented in Emergency Response Planning ML20058Q4361990-08-15015 August 1990 Forwards Safety Insp Rept 50-219/90-11 on 900610-0711. Unresolved Item Noted ML20058P0801990-08-0909 August 1990 Forwards Requalification Program Evaluation Rept 50-219/90-05OL on 900409-0608.Util Should Respond within 30 Days of Receipt of Ltr Confirming Corrective Actions Committed to During 900424 Interim Exit Meeting ML20058M3581990-08-0808 August 1990 Requests Addl Info Listed in Encl Re Util 900521 & 0720 Responses to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow. Info Requested within 10 Days of Receipt of Ltr ML20058N0771990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Managers Forum to Share Experiences ML20056A6071990-07-20020 July 1990 Forwards Insp Rept 50-219/90-09 on 900422-0609 & Notice of Violation.Util Should Identify & Correct Any Programmatic Weaknesses Re Failure to Perform Adequate Radiation Surveys ML20055G4141990-07-11011 July 1990 Requests Util Provide Ref Matls Listed in Encl for Senior Reactor Operator Licensing & Requalification Exams Scheduled for 901015 ML20058K5061990-06-28028 June 1990 Forwards Supplemental Safety Evaluation for Plant Dcrdr. NRC Concludes That Licensee Submittal Meets NUREG-0737, Suppl 1 Dcrdr Requirements & Therefore,Issue Considered Resolved ML20055E3021990-06-15015 June 1990 Forwards Backfit Analyses for Plant Re Installation of Hardened Wetwell Vent,Per Generic Ltr 89-16 ML20059M8321990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3171990-02-16016 February 1990 Forwards Safety Insp Rept 50-219/89-29 on 891203-900106 & Ack Receipt of 900115 & 19 Responses to Insp Repts 50-219/89-21 & 50-219/89-27 ML20248B5511989-09-27027 September 1989 Informs of Correction to NRC Re Util Response to Generic Ltr 88-11 IR 05000219/19890031989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/89-03 NUREG-1382, Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review1989-09-20020 September 1989 Forwards Draft NUREG-1382, SER Re Full-Term Operating License for Oyster Creek Nuclear Generating Station, for Review ML20247K4491989-09-14014 September 1989 Forwards Insp Rept 50-219/89-18 on 890724-28.No Violations Noted IR 05000219/19890051989-09-14014 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/89-05 ML20247K9771989-09-12012 September 1989 Forwards Safety Insp Rept 50-219/89-20 on 890829-30.No Violations Noted ML20247H7201989-09-0808 September 1989 Forwards Corrected SALP Rept 50-219/87-99 for Oct 1987 - Jan 1989 ML20246M7261989-08-30030 August 1989 Forwards Safety Evaluation Accepting Licensee 890624 Response to Integrated Plant Safety Assessment Section 4.11, Seismic Design Consideration, Items 4.11(1), Piping Sys & 4.11(3), Electrical Equipment ML20246J5961989-08-24024 August 1989 Forwards Safety Insp Rept 50-219/89-16 on 890702-29 & Notice of Violation.Attention Required to Ensure Engineering Evaluations of Potential Safety Problems Performed ML20246G1641989-08-21021 August 1989 Forwards SALP Final Rept 50-219/87-99 on Oct 1987 - Jan 1989 ML20246H5751989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits & Requests to Ensure That Licensee Procedures Incorporate Applicable Dose Limits of 10CFR20 ML20246C3671989-08-15015 August 1989 Forwards Safety Insp Rept 50-219/89-19 on 890802-04.No Violations or Deviations Noted ML20247K0981989-08-15015 August 1989 Requests That Licensee Take Listed Actions Re Upgrade of Pipe Supports & Anchorages to Meet IE Bulletin 79-02 & 79-14 Requirements Using New Response Floor Spectra for Plant. Response Re Compliance Requested within 30 Days ML20246B0561989-08-14014 August 1989 Forwards Safety Insp Rept 50-219/89-15 on 890627-30.No Violations Noted.Items of Concern Noted in Area of Appointments to Technical & Supervisory Positions & Training Programs to Maintain & Upgrade Personnel Qualifications ML20245G1091989-08-10010 August 1989 Advises That Licensee 890726 Response to Generic Ltr 88-11, NRC Position on Embrittlement of Reactor Vessel Matls & Impact on Plant Operations, Acceptable ML20245G4931989-08-10010 August 1989 Advises That Util 890719 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program Meets Intent of NUMARC Program.Records & Results from Implementation Should Be Maintained ML20245L1971989-08-0808 August 1989 Forwards Safety Insp Rept 50-219/89-14 on 890604-0701.No Violations Noted.Insp Focused on Open Items Over 3 Yrs Old, Including Response to SALP Rept 50-219/85-99 ML20247P9641989-07-31031 July 1989 Advises That Category ABC List of Projects in Semiannual Update for 6 Months Since 881202 Considered in Compliance W/ Approved long-range Planning Program & Acceptable ML20247M4251989-07-26026 July 1989 Confirms Telcon on 890718 W/M Laggart & Eh Gray Re SSFI to Be Conducted at Facility During Wk of 890814-28.Insp to Focus on Design,Operation & Maint of Emergency Svc Water Sys.Background Info Requested by 890807 ML20245F6211989-07-26026 July 1989 Requests Util Provide Ref Matls Listed in Encl for Reactor Operator & Senior Operator Exams Scheduled for Wks of 891009 & 16,by 890905.Delay in Receiving Ref Matl May Result in Exam Being Rescheduled ML20247N1091989-07-25025 July 1989 Forwards Safety Insp Rept 50-219/89-11 on 890606-08.Due to Similarities Between 890524 Dress Rehearsal & 0607 Exercise, Exercise Does Not Qualify as Required Annual Test of Emergency Plan Since Same Staff Used & Scenario Known ML20247L7321989-07-25025 July 1989 Forwards Safety Insp Rept 50-219/89-12 on 890430-0603 & Notice of Violation IR 05000219/19880381989-07-24024 July 1989 Discusses Safety Insp Rept 50-219/88-38 on 881204-890114 & Forwards Notice of Violation.Violation Classified as Severity Level IV Since Unauthorized Entry Occurred as Result of Isolated Lapse in Vigilance by Security Officer ML20247A6731989-07-17017 July 1989 Forwards Safety Evaluation Accepting Licensee Response to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys Reliability on-line Testing ML20246L6291989-07-11011 July 1989 Ack Receipt of Forwarding Payment of Civil Penalty in Amount of $50,000 Proposed in NRC 1990-09-06 Category:OUTGOING CORRESPONDENCE MONTHYEARML20217J3341999-10-19019 October 1999
[Table view]Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20206U3551999-02-0505 February 1999 Refers to Concerns Recipient Expressed to V Dricks on 990126 Related to Oyster Creek About Event Which Occurred on 970801 & About Administrative Control of EDG Vendor Manuals ML20199L2471999-01-22022 January 1999 Discusses GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 & Gpu Nuclear 960418 & 981202 Responses for Ocngs.Informs That Based on Confirming GL 96-01 Commitments Review Effort Closed ML20199G8241999-01-12012 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20199G8631999-01-0707 January 1999 Responds to Ltr to Senator Lt Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20198B2121998-12-0909 December 1998 Advises of Planned Insp Efforts Resulting from Licensee Irpm Review.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20196C6001998-11-25025 November 1998 Forwards Insp Rept 50-219/98-09 on 980914-1025 & Notice of Violation.Inspector Identified That Security Force Member Left Running Unlocked Vehicle Unattended in Protected Area ML20195G8901998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9101998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G8801998-11-17017 November 1998 Responds to to Senator Lt Conners Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20195G9181998-11-17017 November 1998 Responds to to Lt Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community IR 05000219/19980031998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-219/98-03 Issued on 980717.Corrective Actions Will Be Examined During Future Insp of Licensed Program ML20196D1431998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20195C4111998-11-0606 November 1998 Discusses 980825 Gpu Submittal of Proposed Mod for Ocnpp Core Support Plate Which Involved Installation of Wedges During 17R Outage.Licensee Intends to Use Recommendations of BWRVIP-25 & BWRVIP-50.SE Accepting Proposed Mod Encl ML20195B7981998-11-0505 November 1998 Discusses Alternative Evaluation of Flaws in Ferritic Piping.Core Spray Sys Test Line Was Concluded to Have Acceptable Level of Quality & Safety ML20155C6881998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7201998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7051998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7481998-10-29029 October 1998 Responds to Ltr to Assemblyman Morgan, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6241998-10-29029 October 1998 Responds to Ltr to Senator Connors,Dtd 980926,re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7021998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6661998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6841998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6721998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7251998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7371998-10-29029 October 1998 Responds to Ltr to Senator Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6981998-10-29029 October 1998 Responds to Recent Ltr to Senator Connors Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C6481998-10-29029 October 1998 Responds to Ltr to Sentor Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C7091998-10-29029 October 1998 Responds to Ltr to Assemblyman Connors, Re Possible Closure of Oyster Creek Nuclear Generating Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155C8781998-10-29029 October 1998 Informs That Oyster Creek Generating Station Operating License,Paragraph 2.C.5 Re Evaluation of Core Spray Internals Insp Requires Authorization from NRC Before Plant Is Restarted from Refueling Outage.Plant Restart Authorized ML20155C7301998-10-29029 October 1998 Responds to Ltr to 9th District Legislative Offices, Re Possible Closure of Oyster Creek Nuclear Station & Possible Impact That Closure May Have on Economy & Environ of Community ML20155D2041998-10-26026 October 1998 Forwards Synopsis of 980604 Investigation Rept 1-98-027 Re Possible Discrimination Against Employee for Contacting NRC in Nov 1997 with Security & Safety Concerns ML20154Q9021998-10-20020 October 1998 Forwards Insp Rept 50-219/98-08 on 980727-0913.No Violations Noted.Licensee Have Established & Implemented Effective Programs for Initial & Continuing Training of Workers, Especially Those Having Access to Controlled Areas ML20154L3001998-10-14014 October 1998 Forwards Safety Evaluation Re Reduced Scope of IGSCC Insp, During Refueling Outage 17 ML20154J8251998-10-0707 October 1998 Discusses Concerns Raised to NRC on 980913 Re Oyster Creek. Thoroughness of NRC Insps as Documented in NRC Integrated Insp Rept 50-219/98-03 Was of Concern 1999-09-30 |
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-JUA 141988 docketNo.50-219 Mr. E. E. Fitzpatrick Vice President and Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
SUBJECT:
NRC BULLETIN 88-01, "DEFECTS IN WESTINGHOUSE CIRCUIT BREAKERS" TACS 65955/65936/and 67698 On February 5, 1988, NRC Bulletin 88-01 was issued and requested holders of operating licenses or construction permits to provide letters of confirmation to the NRC of the completion of specified inspections on Westinghouse DS series circuit breakers. Addressees who do not have DS series circuit breakers in Class 1E service were requested to provide a letter to the NRC stating this fact.
Your response dated April 7,1988 confirmed that Westinghouse DS series circuit breakers are not used in safety-related applications at the Oyster Creek Plant. Thus, your response to Bulletin 88-01 is satisfactory, and no further reply is necessary.
Sincerely, 41)@Q!UU.E W E Alexander W. Dromerick, Project Manager Project Directorate I-4 Division of Reactor Projects I/II cc: See next page DISTRIBUTION (Docket.Eile @
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Mr. E. E. Fitzpatrick Oyster Creek Nuclear Oyster Creek Nuclear Generating Station Generating Station CC:
Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW , Post Office Box 445 Washington, D.C. 20037 Forked River, New Jersey 00731 --
J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al. New Jersey Cepartment of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07107 Mr. David M. Scott, Chief Regional Administrator, Region i Bureau of Nuclear Engineering U.S. Nuclear Regulatory Conmission Departnent of Environmental Protection 475 Allendale Road CN 411 King of Prussia, Pennsylvania 19406 Trenton, New Jersey 086?S BVR Licensing Manager GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Deputy Attorney General State of New Jersey Departrent of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey lownship 018 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Dyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey 08731
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