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| Issue date | From | Title | Project stage | |
|---|---|---|---|---|
| B11972, Forwards Results of Evaluation of Ref Temp for Pressurized Thermal Shock from Time of Submittal to Expiration Date of Ol.Values Do Not Exceed Screening Criteria.Paragraphs (b)(3)-(6) of 10CFR50.61 Inapplicable to Facilities | 23 January 1986 | Opeka J Sears C CONNECTICUT YANKEE ATOMIC POWER CO. Northeast Nuclear Energy | Forwards Results of Evaluation of Ref Temp for Pressurized Thermal Shock from Time of Submittal to Expiration Date of Ol.Values Do Not Exceed Screening Criteria.Paragraphs (b)(3)-(6) of 10CFR50.61 Inapplicable to Facilities | Other |
| ML20215M617 | 20 October 1986 | Jaffe D Office of Nuclear Reactor Regulation | Forwards Request for Addl Info Re Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Justification for Copper & Nickel Contents & Initial RTNDT Values Requested | RAI |
| A06174, Forwards Response to 861020 Request for Addl Info Re Review of 860123 Submittal Concerning Matl Properties for Fracture Toughness Requirements for Protection Against PTS | 19 December 1986 | NORTHEAST UTILITIES Mroczka E Northeast Nuclear Energy | Forwards Response to 861020 Request for Addl Info Re Review of 860123 Submittal Concerning Matl Properties for Fracture Toughness Requirements for Protection Against PTS | Request |
| ML20209H034 | 24 April 1987 | Jaffe D Office of Nuclear Reactor Regulation | Forwards Request for Addl Info in Order to Continue Review of 861222 Application Re Expiration of Facility OL & 860123 Submittal Re Pressurized Thermal Shock | RAI |
| ML20235H757 | 6 July 1987 | NORTHEAST UTILITIES Mroczka E Northeast Nuclear Energy | Submits Response to NRC 870424 Request for Addl Info Re PTS & Info Requested During 870701 Telcon Re Satisfaction of 10CFR50.61 Requirements Concerning Pts,Including Neutron Fluence on 860123 | Request |
| A06530, Responds to NRC Request for Addl Info Re Fluence Calculation Performed to Assess Compliance w/10CFR50.61 Re Pts.Predicted Controlling Rt(Pts) Value Based on Worst Case Assumption of 40% Uncertainty in Estimated Fluence Listed | 31 July 1987 | NORTHEAST UTILITIES Mroczka E Northeast Nuclear Energy | Responds to NRC Request for Addl Info Re Fluence Calculation Performed to Assess Compliance w/10CFR50.61 Re Pts.Predicted Controlling Rt(Pts) Value Based on Worst Case Assumption of 40% Uncertainty in Estimated Fluence Listed | Request |
| ML20237G728 | 24 August 1987 | Office of Nuclear Reactor Regulation | Safety Evaluation Re Fast Neutron Fluence for Fracture Toughness Requirements for Protection Against PTS Events. Plant Satisfies Fracture Toughness Requirements for Protection Against PTS | Approval |
| ML20237G717 | 24 August 1987 | Jaffe D Office of Nuclear Reactor Regulation | Forwards Safety Evaluation Re Util 860123,870706 & 31 Submittals Concerning Pts.Estimated Value of Fast Neutron Fluence to Pressure Vessel to Have Conservative Error Margins & Acceptable | Approval |