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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20248F744 | 31 May 1998 | Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity | |
| ML20217E081 | 24 March 1998 | Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident | |
| ML20202D849 | 6 November 1997 | Rev 0 to Topical Rept 116, Leakage Assessment Methodology for TMI OTSG Kinetic Expansion Examination | Shutdown Margin |
| ML17353A434 | 31 October 1995 | Rev 1 to BAW-2245, Initial Rt of Linde 80 Welds Based on Fracture Toughness in Transition Range. | |
| ML17264A118 | 31 July 1995 | Response to Part (1) of GL 92-01,Rev 1,Suppl 1. | |
| ML20084C983 | 9 May 1995 | Rev 0 TMI-1 Evaluation of Thermo-Lag Fire Barriers | Safe Shutdown Fire Barrier Exemption Request Fire Protection Program |
| ML20080R525 | 23 January 1995 | Steady State Reactor Physics Methodology for TMI-1 | Boric Acid |
| ML20081G273 | 6 January 1995 | TMI-1 Transient Analyses Using Retran Computer Code | Shutdown Margin |
| ML20137J402 | 31 December 1993 | External Circumferential Crack Growth Analysis for B&W- Design Rv Head CR Drive Mechanism Nozzles | Finite Element Analysis |
| 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 |
| ML20247N591 | 18 May 1989 | Rev 2 to TMI-1 Cycle 7 Core Operating Limits Rept | |
| ML20245L635 | 20 April 1989 | Rev 1 to TMI-1 Cycle 7 Core Operating Limits Rept | |
| ML20236E015 | 30 June 1987 | Analysis of Capsule TMI1-C,...Vessel Matl Surveillance Program,Suppl 1 Pressure-Temp Limits | Hydrostatic |
| ML20237J610 | 30 April 1987 | TMI-1 Nuclear Power Plant Leak-Before-Break Evaluation of Margins Against Full Break for RCS Primary Piping | Safe Shutdown Earthquake Earthquake |
| ML20137M863 | 31 January 1986 | Pressurized Thermal Shock Evaluations in Accordance W/10CFR50.61 for B&W Owners Group Reactor Pressure Vessels | |
| ML20154H149 | 30 December 1985 | Rev 0 to Final Verification & Validation Rept on TMI-1 Spds | |
| ML20151N769 | 19 December 1985 | Rev 0 to Comparison of Steam Generator Tube Plugging W/TMI-1 Design Basis | |
| ML20135A557 | 31 August 1985 | B&W Owners Group Cavity Dosimetry Program | |
| ML20138P154 | 2 July 1985 | Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation, Topical Rept | |
| ML20126L288 | 2 July 1985 | Rev 1 to TMI-1 Nuclear Generating Station Natural Circulation Cooldown Analysis W/O Reactor Vessel Upper Head Void Formation | |
| ML20093K296 | 31 August 1984 | TMI-1 Reactor Coolant Pump Shaft Failure Analysis | |
| ML20084F676 | 30 April 1984 | TMI Safety Parameter Display Sys Safety Analysis,Topical Rept 018 | Reactor Vessel Water Level |
| ML20077H863 | 29 March 1983 | Rev 2 to Topical Rept 008, Assessment of TMI-1 Plant Safety for Return to Svc After Steam Generator Repair | Boric Acid Non-Destructive Examination Grab sample Liquid penetrant Pressure Boundary Leakage Power change Flow Induced Vibration |
| ML20072K730 | 28 February 1983 | Evaluation of Small Break LOCA Operating Procedures & Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating Nsss | |
| ML20065T433 | 30 November 1982 | B&W Small Break LOCA ECCS Evaluation Model | Boric Acid Loop seal |
| ML20076J859 | 31 August 1979 | Integrated Control Sys Reliablilty Analysis | |
| ML20027A767 | 7 August 1979 | Sys Response to Total Loss of Steam Generator Heat Sink. | |
| ML20125D902 | 30 September 1977 | Decay Heat Removal Problems Associated W/Recovery from Very Small Break LOCA for B&W 205-Fuel Assembly Pwr | |
| ML19332B238 | 31 July 1977 | to ECCS Analysis of B&W 177-Fuel Assembly-Loop Nss. Related Correspondence | Boric Acid Coast down |
| ML19260A122 | 31 January 1977 | Analysis of Capsule TMI-1E from Met Ed TMI-1:Reactor Vessel Matls Surveillance Program, Jan 1977.Prepared for Met Ed | |
| ML19337A425 | 31 May 1972 | Overpressure Protection for B&W Pwr. Related Correspondence |