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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20248F744 | 31 May 1998 | Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity | |
| ML17353A434 | 31 October 1995 | Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. | |
| ML20107M893 | 31 October 1995 | Nonproprietary DPC Fuel Reconstitution Analysis Methodology | Anticipated operational occurrence Safe Shutdown Earthquake Earthquake Fuel cladding Affidavit Depleted uranium |
| ML17264A118 | 31 July 1995 | Response to Part (1) of GL 92-01,Rev 1,Suppl 1. | |
| ML20064L200 | 31 January 1994 | Final Rept EPRI TR-103591, Burnup Verification Measurements on Spent-Fuel Assemblies at Oconee Nuclear Station | |
| ML20097G042 | 31 May 1992 | Analysis of Capsule OCIII-D Duke Power Company Oconee Nuclear Station Unit-3 | Anticipated operational occurrence Hydrostatic Fuel cladding |
| ML20067A524 | 31 December 1990 | Final Submittal in Response to NRC Bulletin 88-011, 'Pressurizer Surge Line Thermal Stratification.' | Operating Basis Earthquake Finite Element Analysis Code Reconciliation Commercial Grade Power change |
| ML19332D539 | 31 October 1989 | Core Thermal-Hydraulic Methodology Using VIPRE-01. | Power change Affidavit |
| ML20042F232 | 31 August 1989 | Nonproprietary DCHF-1 Correlation for Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies. | |
| ML20239A699 | 30 November 1987 | Addendum 1 to Rev 2 to Integrated Reactor Vessel Matl Surveillance Program (Addendum) | |
| ML20138M421 | 30 September 1985 | Justification for Raising Setpoint for Reactor Trip on High Pressure, Transient Assessment Program | |
| ML20135A557 | 31 August 1985 | B&W Owners Group Cavity Dosimetry Program | |
| ML20100F096 | 30 November 1984 | Abnormal Transient Operating Guidelines (Atog) Comparison of Davis-Besse Unit 1 to Oconee Unit 3 | |
| ML20071N926 | 31 May 1983 | B&W Owners Group Bolting Task Force Summary Rept of Nrc/B&W Owners Group 830506 Meeting on Reactor Vessel Internals Bolting | Safe Shutdown Operating Basis Earthquake Earthquake Flow Induced Vibration |
| ML20062D617 | 1 July 1982 | Evaluation,Repair & Replacement of Damaged Internal Auxiliary Feedwater Header at Davis Besse 1,Oconee 3 & Rancho Seco | |
| ML19331D742 | 31 August 1980 | Cycle 6 Reload Rept. | Shutdown Margin |
| ML19276G647 | 24 July 1979 | Topical Rept DUKE-2,Section 13.1 Re Conduct of Operations | Hydrostatic |
| ML19312C138 | 31 January 1978 | Cycle 4 Quadrant Flux Tilt. | |
| ML19322B865 | 30 September 1977 | Analysis of Capsule OCI-E,Reactor Vessel Matls Surveillance Program. | Hydrostatic |
| ML19308B535 | 31 July 1977 | Analysis of Capsule OC111-A from Duke Power Co:Reactor Vessel Matls Surveillance Program. | Anticipated operational occurrence Hydrostatic |
| ML19308B550 | 31 May 1977 | Analysis of Capsule OC111-A from Duke Power Co;Reactor Vessel Matls Surveillance Program. | |
| ML19322C154 | 31 January 1976 | Irradiation of Two 17x17 Demonstration Assemblies in Cycle 2. | |
| ML19322C136 | 31 March 1974 | Fuel Densification Rept (Non-Proprietary Version of BAW-1399). | Fuel cladding |
| ML19322B860 | 31 July 1973 | Fuel Densification Rept, Revision 1 Nonproprietary Version of BAW-1387 | Fuel cladding Power change |
| ML19322B868 | 31 December 1970 | Analysis & Resolution of Dye-Penetrant Indications in Submerged Arc Weld Cladding of Reactor Coolant Sys Straight Piping. | Hot Short Eddy Current Testing Liquid penetrant |
| ML19322B870 | 31 December 1970 | Analysis & Resolution of Dye-Penetrant Indications in AISI-304 Alloy Cladding of RCS Elbows. | Eddy-Current Testing |