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 Issue dateTitleFromTo
ML20083N86910 April 1984Requests Permission to Restore Reactor Cavity Seal Rings to Stowage Location Sufficiently Above Floor to Permit Cooling Air Flow Through AnnulusFay C
WEC Energy Group
John Miller
Office of Nuclear Reactor Regulation
Harold Denton
ML20129B27530 May 1985Requests 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 84-04Fay C
WEC Energy Group
John Miller
Office of Nuclear Reactor Regulation
Harold Denton
NRC Generic Letter 1989-2119 October 1989NRC Generic Letter 1989-021: Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) RequirementsPartlow J
Office of Nuclear Reactor Regulation
NPL-97-0281, Forwards Documentation to Support Restart Issues Identified on Unit 2 Startup Commitment List,Per 970131 Telcon19 May 1997Forwards Documentation to Support Restart Issues Identified on Unit 2 Startup Commitment List,Per 970131 TelconWEC Energy Group
Dante Johnson
Office of Information Resources Management
ML20211H63829 September 1997Responds 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 970627WEC Energy Group
Grigg R
Office of Information Resources Management
IR 05000266/199900210 March 1999Insp Repts 50-266/99-02 & 50-301/99-02 on 990105-0222. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant SupportNRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
ML02249035230 July 2002Attachment 6, Enclosure 3, Point Beach, Units 1 & 2, 1.4% Mur Power Uprate Support NRC RAI Responses Set 1 Question 4 (Non-Proprietary)WestinghouseOffice of Nuclear Reactor Regulation
NRC 2003-0105, Request for Review of Dynamic Effects Design Basis and Leak-Before-Break Analysis5 November 2003Request for Review of Dynamic Effects Design Basis and Leak-Before-Break AnalysisNuclear 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 Analysis9 December 2003Request for Review of Correction to Dynamic Effects Design Basis and Leak-Before-Break AnalysisNuclear Management Co
Cayia A
Office of Nuclear Reactor Regulation
Document Control Desk
ML0403601044 February 2004IR 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 2Caldwell J
Region 3 Administrator
Vanmiddlesworth G
Nuclear Management Co
ML0433602956 June 2005Issuance of Amendments Leak-Before-Break Evaluation for the Primary Loop PipingChernoff H
NRC/NRR/DLPM/LPD3
Nuclear Management Co
Koehl D
ML16251A1671 September 2016Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging AnalysisPoint BeachOffice 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 Analysis1 September 2016Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety AnalysisPoint BeachOffice 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 Analysis1 September 2016Point 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 AnalysisPoint BeachOffice of Nuclear Reactor Regulation
ML16251A1661 September 2016Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety AnalysisPoint BeachOffice of Nuclear Reactor Regulation
ML21102A3542 April 2021Update to Final Safety Analysis Report, Chapter 14, Safety AnalysisPoint BeachOffice of Nuclear Reactor Regulation
ML21102A3462 April 2021Update to Final Safety Analysis Report, Chapter 15, Aging Management Programs and Time Limited Aging AnalysisPoint BeachOffice of Nuclear Reactor Regulation