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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20212G496 | 28 October 1997 | SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel | |
| ML20214E363 | 17 March 1986 | Safety Evaluation Supporting Amend 2 to CPPR-105 | |
| ML20216J586 | 4 September 1997 | Safety Evaluation Re Third 10-year IST Program.Approves Valve Relief Requests 1,3 & 4.Valve Relief Request 2 Not Required.Authorizes Pump Relief Requests 1,2,3 & 4 | Safe Shutdown Stroke time Incorporated by reference Power-Operated Valves |
| ML20217J531 | 8 October 1997 | Safety Evaluation Re First,Second & Third 10-year Interval Inservice Inspection Program Plan Requests for Relief for Plant,Units 1 & 2 | Boric Acid VT-2 Incorporated by reference Through Wall Leak Scaffolding |
| ML20217J589 | 7 October 1997 | Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1 | |
| ML20234E053 | 8 December 1987 | Safety Evaluation Accepting Design Changes to Be Implemented During Unit 1 Cycle 7 Fuel Reload.Tech Spec Change Unnecessary | Shutdown Margin |
| ML20236X494 | 9 November 1987 | Safety Evaluation Granting Util 860617 Relief Request from Performing Volumetric & Visual Exam Requirements of ASME Section XI for Reactor Coolant Pumps Casing Welds & Internal Surfaces | Hydrostatic VT-2 |
| ML20236Y534 | 28 December 1979 | SER Re Inadvertent Safety Injection During Cooldown.Typical Nozzle Could Withstand at Least Fifty Injection Events W/ Temp Differential as High as About 500 F | |
| ML20237B165 | 21 October 1987 | Safety Evaluation Supporting Elimination of Primary Component Support Snubbers from Primary Coolant Loops | Design basis earthquake Earthquake |
| ML20245C315 | 12 July 1977 | Safety Evaluation Supporting Amend 9 to License DPR-66 | |
| ML20246D550 | 26 April 1989 | Safety Evaluation Accepting Util Submittals on Natural Circulation Cooldown for Unit | Boric Acid Shutdown Margin |
| ML20246M179 | 10 May 1989 | Safety Evaluation Re Verification & Validation Plan for Plant Safety Monitoring Sys.Hardware Design of Sys Found Acceptable.Verification & Validation Plan Found Incomplete & Unacceptable.Software Design Process Inadequate | |
| ML20247N356 | 30 May 1989 | SER Supporting Util Actions to Comply W/Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing | |
| ML20248D768 | 29 September 1989 | Supplemental Safety Evaluation Supporting Util Actions in Response to Open Items in 890510 Safety Evaluation Re Plant Safety Monitoring Sys |