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| Issue date | Title | Topic | |
|---|---|---|---|
| 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed | 15 July 1999 | Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed | Unanalyzed Condition |
| 05000414/LER-1999-002, Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 | 3 June 1999 | Forwards Abstract of LER 99-002-00 Re Forced Shutdown of Plant as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Final LER Will Be Submitted No Later than 990708 | |
| 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev | 31 August 1999 | Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER | |
| 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments | 27 September 1999 | Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments | |
| 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments | 20 September 1999 | Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments | |
| ET-NRC-92-3742, Requests That Proprietary Ltr NSD-TAP-2092 Re Addl Technical Support for Catawba Unit 1 Steam Generator Tube Interim Plugging Criteria,Be Withheld (Ref 10CFR2.790) | 4 September 1992 | Requests That Proprietary Ltr NSD-TAP-2092 Re Addl Technical Support for Catawba Unit 1 Steam Generator Tube Interim Plugging Criteria,Be Withheld (Ref 10CFR2.790) | Affidavit |
| LG-83-163, Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 | 18 February 1983 | Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 | |
| M950159, Forwards Voluntary Results of Control Rod Drop & Drag Testing on Catawba Unit 2 at End of Cycle 8,in Response to NRC Bulletin 96-01 | 21 May 1997 | Forwards Voluntary Results of Control Rod Drop & Drag Testing on Catawba Unit 2 at End of Cycle 8,in Response to NRC Bulletin 96-01 | |
| ML110830236 | 3 May 1993 | Forwards Rev 1 to NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. Submittal Made on Behalf of Eight Utils Having Enterprize EDGs for Emergency Standby Ac Power | |
| ML15217A103 | 28 February 1990 | Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals | Offsite Dose Calculation Manual Process Control Program |
| ML15261A070 | 16 October 1991 | Forwards Nonproprietary & Proprietary Handouts Presented in 911007 & 08 Meeting W/Nrc & Contract Reviewers to Discuss Outstanding Issues Associated W/Topical Repts DPC-NE-2004, DPC-NE-3000 & DPC-NE-3001.Proprietary Handouts Withheld | Affidavit |
| ML16148A932 | 31 October 1990 | Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 37 to CMIP-1,Rev 27a to CMIP-2,Rev 33 to CMIP-4,Rev 37 to CMIP-5 & Rev 42 to CMIP-6.W/901114 Release Memo | |
| ML16152A870 | 30 October 1989 | Forwards Public Version of Rev 32 to Crisis Mgt Plan for Nuclear Stations. W/891113 Release Memo | |
| ML16152A873 | 1 November 1989 | Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8 & Rev 31 to CMIP-9.W/891020 Release Memo | |
| ML16152A909 | 18 January 1990 | Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo | |
| ML16152A953 | 2 May 1990 | Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld | |
| ML16152A962 | 9 May 1990 | Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo | |
| ML16162A379 | 6 August 1982 | Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 5.3.1 Re Recovery Manager & Immediate Staff Group Plan & 5.3.4 Re Scheduling/Planning Support Group | |
| ML16162A401 | 29 October 1982 | Forwards Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures 5.3.1 Re Recovery Manager & Immediate Staff Group Plan & 5.3.6 Re Radiological Support Group | |
| ML16162A405 | 2 December 1982 | Forwards Public Version of Revision 7 to Crisis Mgt Plan & Revisions to Crisis Mgt Plan Implementing Procedures | |
| ML16259A239 | 22 August 1990 | Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo | |
| ML17277B681 | 26 March 1985 | Advises of Personnel Changes Effective 850415.Prof Qualifications for Listed Individuals Available in FSAR Apps 13.1A & 13.1B | |
| ML18010A950 | 8 December 1992 | Forwards NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. Submittal Made on Behalf of Eight Utils Having Enterprise EDGs for Emergency Standby Ac Power | |
| ML18018A736 | 6 September 1983 | Comments on Reg Guide 1.97,identified as Instrumentation & Control Sys Branch Draft SER Open Item 223,in Response to NUREG-0737,Suppl 1.Design & Qualification Criteria for Instrumentation Consistent W/Guide | Boric Acid |
| ML18024B534 | 7 May 1979 | Responds to NRC 790413 Ltr Re Violations Noted in IE Insp Repts 50-413/79-05 & 50-414/79-05.Corrective Actions: Nitrogen Blanket Placed on Heat Exchanger & Personnel Instructed Re Nonconforming Item Rept | |
| ML19207B026 | 16 July 1979 | Responds to IE Bulletin 79-09.No GE Type AK-2 Circuit Breakers Used or Planned for Use in safety-related Sys | |
| ML19207C183 | 31 August 1979 | Requests That Review of License Application,Fsar & Environ Rept Be Completed as Soon as Possible.Will Update Application in mid-1980.Facility Correspondence Should Be Addressed to WO Parker | |
| ML19208A544 | 15 August 1979 | Notifies That 790814 Teledyne Engineering Svcs Technical Rept TR-3501-1,submitted by WO Parker,Serves as Final Response to IE Bulletin 79-02,Revision 1 | |
| ML19208A620 | 9 August 1979 | Ack Receipt of Two Revisions to C-E Generic Rept Atypical Matl in Reactor Pressure Vessel Welds. | |
| ML19208A789 | 21 August 1979 | Forwards Interim Deficiency Rept Re Steam Generator Water Level Measurement Sys Errors | |
| ML19209A605 | 10 September 1979 | Forwards Response to 790815 Ltr Re Request for Suppl to 790806 Submittal Regarding IE Insp Repts 50-413/79-12 & 50-414/79-12.Discusses Each Generic Example Re QA Procedure P-1 | |
| ML19209A771 | 7 September 1979 | Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies. Two Bingham-Willamette Model 30 by 44C-VTM Vertical Turbine Deep Draft Pumps Utilized in safety-related Applications in Each Facility.Pumps Not Yet Operational | |
| ML19210E245 | 7 November 1979 | Responds to IE Bulletins 78-12,78-12A & 78-12B Re Weld Matl Documentation.Info Pertinent to Catawba Unit 1 Reactor Vessel Included in Rdm Rept Which Was Submitted 791029. Westinghouse Transmittal Ltr Encl | |
| ML19210E249 | 29 October 1979 | Forwards Rept Weld Matl Documentation of Eleven Reactor Pressure Vessels Fabricated by Rdm for Westinghouse, in Response to IE Bulletin 78-12.Complete Records Search Made & No Atypical Weld Matl Found | |
| ML19211A411 | 5 December 1979 | Ack Receipt of IE Insp Repts 50-413/79-19 & 50-414/79-19 on 791009-12.No Proprietary Info | |
| ML19224C539 | 16 May 1979 | Discusses Schedule of Response to IE Bulletins 78-12,12A, & 12B.C-E to Submit Generic Rept Directly to NRC by 790629. Westinghouse Submittal Re Rotterdam Vessel Expected in July 1979 | |
| ML19225A390 | 29 May 1979 | Responds to IE Bulletin 79-07 Re Use of Particular Computer Programs.Superpipe Used on All Piping Analyses Except Analysis Performed by Westinghouse | |
| ML19225A400 | 25 May 1979 | Responds to NRC 790502 Ltr Re Violations Noted in IE Insp Repts 50-413/79-06 & 50-414/79-06.Corrective Actions: Exterior Surface Dome Pour Number 32 Reinspected & Repaired & Area Cleared of Debris | |
| ML19225B542 | 20 June 1979 | FOIA Request for Summary Sheet of Power Plant Operator Exam Results Presented to NRC on 790420 & License Exams & Test Results for Duke Power Co Employees from 750101 to Present | |
| ML19225D047 | 19 July 1979 | Responds to IE Bulletin 79-11.No Westinghouse DB-50 or DB-75 Circuit Breakers Are Used or Planned for Use in safety-related Sys | |
| ML19241B018 | 4 June 1979 | Ack Receipt of IE Insp Repts 50-413/79-09 & 50-414/79-09 on 790508-11.No Proprietary Info | |
| ML19242A772 | 27 July 1979 | Responds to 790706 Request Re Info on Potential Impact on NRC Resource Needs & Priorities Associated W/Decision to Delay Commercial Operation of Cherokee 1 & 2 & Postpone Financial Commitments for Cherokee 3 & Perkins 1,2 & 3 | |
| ML19242C416 | 22 June 1979 | Responds to NRC 790605 Ltr Re Violations Noted in IE Insp Repts 50-413/79-04 & 50-414/79-04.Corrective Actions:Bank Opposite Low Pressure Svc Water Intake Structure Was Riprapped on 790525 to Control Erosion | |
| ML19242D189 | 20 July 1979 | Forwards Significant Deficiency 413-414/79-1 | |
| ML19246C039 | 24 May 1979 | Ack Receipt of IE Insp Repts 50-413/79-08 & 50-414/79-08.No Proprietary Info | |
| ML19247B227 | 5 July 1979 | Responds to IE Bulletin 79-02,Revision 1.Base Plate Flexibility Will Be Accounted for in Calculation of Expansion Anchor Bolt Loads for All Seismic Category 1 Pipe Support Base Plates | |
| ML19248D227 | 6 August 1979 | Notifies That Projected Dates for Fuel Loading & Commercial Operation Are Delayed.Will Forward Request & Justification for Extension of CP to Accommodate Relay | |
| ML19248D258 | 8 August 1979 | Requests Use of ASME Code Case N-242 for Steam Generator Power Operated Relief Valves.B&W Certificate of Conformance Encl | |
| ML19249B544 | 2 July 1979 | Responds to IE Bulletins 78-12,78-12A & 78-12B.Weld Matl Data & Other Required Info Included in C-E Rept | |
| ML19249B549 | 8 June 1979 | Forwards Info Requested by IE Bulletin 78-12,Atypical Weld Matl in Reactor Pressure Vessel Welds Which Addresses All Applicable Matls Used in Fabrication of Reactor Vessels. W/O Encl |