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 Issue dateTitle
PNP 2021-008, 5 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis14 April 20215 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis
IR 05000255/202000313 November 2020Integrated Inspection Report 05000255/2020003
ML18278A28010 October 2018Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 10/23/2018
IR 05000255/20170028 August 2017NRC Integrated Inspection Report and Exercise of Enforcement Discretion 05000255/2017002
ML16014A31822 August 2016Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML15035A21930 January 2015NRR E-mail Capture - Issuance of Proposed Director'S Decision Associated with Your 10 CFR 2.206 Petition Regarding Impellers
ML14357A59315 December 2014Chapter 14 UFSAR, Rev. 31, Section 14.1 -Table 14.14-7, Revision 28, Page 1 of 1
IR 05000255/20120038 August 2012IR 05000255-12-003, 04/01/2012 - 06/30/2012, Palisades Nuclear Plant; Inservice Inspection Activities, Operability Determinations and Functional Assessments, Refueling and Other Outage Activities
IR 05000255/20090036 August 2009IR 05000255-09-003 on 04/01/2009 - 06/30/2009 for Palisades Power Plant
IR 05000255/20070066 November 2007IR 05000255-07-006, on 07/01/2007 - 09/30/2007; Palisades Nuclear Plant, Integrated Inspection Report
ML04357038530 September 2004NUREG/CR-6858, RELAP5 Thermal Hydraulic Analysis to Support PTS Evaluations for the Oconee-1, Beaver Valley-1, and Palisades Nuclear Power Plants.
ML03323022512 November 2003Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application.
ML18066A34122 April 1998Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events.
ML18066A85831 January 1997Rev 2 to C-PAL-96-1063-01, Operability Assessment for Transient Conditions at Palisades Nuclear Plant in Response to GL 96-06.
Information Notice 1996-45, Potential Common-Mode Post-Accident Failure of Containment Coolers12 August 1996Potential Common-Mode Post-Accident Failure of Containment Coolers
ML18059A37531 August 1993Rev 1 to Palisades Cycle 11:Disposition & Analysis of SRP Chapter 15 Events.
ML18058B39121 December 1992Cycle 11:Disposition & Analysis of Standard Review Plan Chapter 15 Events.
ML18057B35131 October 1991Cycle 10:Disposition & Analysis of SRP Chapter 15 Events.
ML18057A9669 November 1990Review & Analysis of SRP Chapter 15 Events for Palisades W/ 15% Variable High Power Trip Reset.
ML18054A70627 April 1989Provides Requested Safety Evaluation & Discusses Util Plans for Revising Electrical Sys Tech Spec Requirements,Per NRC 880518 Request.Restructured Tech Spec Program Will Standardize Electrical Section of Tech Specs
ML20154J4347 September 1988Rev 1 to Palisades Cycle 8:Disposition & Analysis of SRP Chapter 15 Events
ML20154H2602 August 1988Cycle 8:Disposition & Analysis of SRP Chapter 15 Events
ML20195H03013 June 1988Nonproprietary Low Flow Trip Setpoint & Thermal Margin Analysis for Three Primary Coolant Pump Operation of Palisades Reactor
NRC Generic Letter 1987-1612 November 1987NRC Generic Letter 1987-016: Transmittal of NUREG-1262, Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses
ML20214Q50419 September 1986Submits Followup to Util 860815 pre-startup Commitment Status Rept,Per 860521 Confirmatory Action Ltr & Requests Authorization for Restart of Facility.Summary of 860815-27 Events & Corrective Actions Re Encl LERs Provided
ML20203C81719 May 1986Rev 1 to Administrative Procedure 4.08, Post-Trip Review Requirements
ML18344A26319 May 1986Appendix E - Palisades Plant Equipment Problems Related to the May 19, 1986 Reactor Trip
ML20087J8199 March 1984Plant Transient Analysis for Palisades Nuclear Power Plant W/50% Steam Generator Plugging
ML14092A30131 December 1981Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for C-E Nsss.
ML18046A74617 February 1981Provides Status on SEP Containment Analysis for Facility. Containment Design Temp Is Exceeded in Some Cases.W/O Stated Encls
ML18044A45621 January 1980Responds to NRC 791221 Request for Info Re Applicability of Main Steam Line Break Analysis.Current Means of Manual Actuation of Auxiliary Feedwater Sys & Proposed Control Grade Sys Acceptable
ML18347B30418 July 1977Plant Transient Analysis of the Operation at 2530 Mwt