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Issue date | Title | From | To | |
---|---|---|---|---|
ML20083N869 | 10 April 1984 | Requests Permission to Restore Reactor Cavity Seal Rings to Stowage Location Sufficiently Above Floor to Permit Cooling Air Flow Through Annulus | Fay C WEC Energy Group | John Miller Office of Nuclear Reactor Regulation Harold Denton |
ML20129B275 | 30 May 1985 | Requests Exemption from Provisions of 10CFR50,App A,Gdc 4 to Eliminate Consideration of Large RCS Primary Loop Pipe Breaks in Structural Design Basis,Per Generic Ltr 84-04 | Fay C WEC Energy Group | John Miller Office of Nuclear Reactor Regulation Harold Denton |
NRC Generic Letter 1989-21 | 19 October 1989 | NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements | Partlow J Office of Nuclear Reactor Regulation | |
NPL-97-0281, Forwards Documentation to Support Restart Issues Identified on Unit 2 Startup Commitment List,Per 970131 Telcon | 19 May 1997 | Forwards Documentation to Support Restart Issues Identified on Unit 2 Startup Commitment List,Per 970131 Telcon | WEC Energy Group Dante Johnson | Office of Information Resources Management |
ML20211H638 | 29 September 1997 | Responds to NRC Re Violations Noted in Insp Repts 50-266/96-18,50-301/96-18,50-266/97-05 & 50-301/97-05, Respectively.Corrective Actions:Rev 3 to DCS 3.1.20, Offsite Power Operability, Issued on 970627 | WEC Energy Group Grigg R | Office of Information Resources Management |
IR 05000266/1999002 | 10 March 1999 | Insp Repts 50-266/99-02 & 50-301/99-02 on 990105-0222. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | |
ML022490352 | 30 July 2002 | Attachment 6, Enclosure 3, Point Beach, Units 1 & 2, 1.4% Mur Power Uprate Support NRC RAI Responses Set 1 Question 4 (Non-Proprietary) | Westinghouse | Office of Nuclear Reactor Regulation |
NRC 2003-0105, Request for Review of Dynamic Effects Design Basis and Leak-Before-Break Analysis | 5 November 2003 | Request for Review of Dynamic Effects Design Basis and Leak-Before-Break Analysis | Nuclear Management Co Cayia A | Office of Nuclear Reactor Regulation Document Control Desk |
NRC 2003-0115, Request for Review of Correction to Dynamic Effects Design Basis and Leak-Before-Break Analysis | 9 December 2003 | Request for Review of Correction to Dynamic Effects Design Basis and Leak-Before-Break Analysis | Nuclear Management Co Cayia A | Office of Nuclear Reactor Regulation Document Control Desk |
ML040360104 | 4 February 2004 | IR 05000266-03-007 and IR 05000301-03-007, on 7/28/2003 - 12/16/2003, for Nuclear Management Company, LLC; Point Beach Nuclear Plant, Units 1 and 2 | Caldwell J Region 3 Administrator | Vanmiddlesworth G Nuclear Management Co |
ML043360295 | 6 June 2005 | Issuance of Amendments Leak-Before-Break Evaluation for the Primary Loop Piping | Chernoff H NRC/NRR/DLPM/LPD3 | Nuclear Management Co Koehl D |
ML16251A167 | 1 September 2016 | Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis | Point Beach | Office of Nuclear Reactor Regulation |
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis | 1 September 2016 | Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis | Point Beach | Office of Nuclear Reactor Regulation |
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis | 1 September 2016 | Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis | Point Beach | Office of Nuclear Reactor Regulation |
ML16251A166 | 1 September 2016 | Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis | Point Beach | Office of Nuclear Reactor Regulation |
ML21102A354 | 2 April 2021 | Update to Final Safety Analysis Report, Chapter 14, Safety Analysis | Point Beach | Office of Nuclear Reactor Regulation |
ML21102A346 | 2 April 2021 | Update to Final Safety Analysis Report, Chapter 15, Aging Management Programs and Time Limited Aging Analysis | Point Beach | Office of Nuclear Reactor Regulation |