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| Issue date | Title | |
|---|---|---|
| ML20138K312 | 31 January 1997 | Rev 43 to RP 1A, Preparation for Refueling |
| ML20148T597 | 25 January 1988 | Forwards Requests for Inservice Insp Relief from ASME Section XI for Second 10-yr Insp Interval for Plant.Approval Requested by Sept 1988 to Allow Time Prior to Spring 1989 Unit 1 Refueling During Which Time Exams Scheduled.Fee Paid |
| ML20151R677 | 2 August 1988 | Safety Evaluation Granting Request for Relief from ASME Code,Section XI Evaluation Requirements |
| ML20154M692 | 11 March 1986 | Requests Date for Insp of Inadequate Core Cooling Instrumentation to Verify 850305 & 29 Responses to 850129 Request for Addl Info.Insp Will Include Operating Procedures,Training,Calibr Records & Startup Test Data |
| ML20206T520 | 30 June 1986 | Forwards Safety Analysis of Spds,Including Discussion of Electrical Isolation for Safety Assessment Sys,Per Requirements of Suppl 1 to NUREG-0737 |
| ML20211Q723 | 31 December 1986 | Annual Results & Data Rept 1986 |
| ML20234E328 | 18 September 1987 | Responds to Generic Ltr 87-12, Loss of RHR While RCS Partially Filled. Each Facility Operated Annually in Partially Drained Condition to Permit Preparation for & Recovery from Core Refueling Operation |
| ML21102A348 | 2 April 2021 | Update to Final Safety Analysis Report, Chapter 7, Instrumentation and Control |
| ML993630482 | 23 December 1999 | Revised Epips, Including Revision 25 to EPIP 1.3, Revision 18 to EPIP 2.1, Revision 29 to EPIP 4.1, Revision 14 to EPIP 4.2, Revision 22 to EPIP 4.3, Revision 0 to EPIP 4.7, Revision 12 to EPIP 5.1and Revision 11 to EPIP 5.2. with 12/23/99 |
| NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with | 31 December 1998 | 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with |
| NRC 2003-0012, Emergency Plan Implementing Procedure Revisions, Point Beach Nuclear Plant, Units 1 & 2 | 7 February 2003 | Emergency Plan Implementing Procedure Revisions, Point Beach Nuclear Plant, Units 1 & 2 |
| NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate | 8 December 2009 | License Amendment Request 261, Supplement 3 Extended Power Uprate |
| NRC 2010-0022, License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate | 25 February 2010 | License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate |
| NRC 2010-0105, License Amendment Request 261, Supplement 6 Extended Power Uprate | 28 July 2010 | License Amendment Request 261, Supplement 6 Extended Power Uprate |
| NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate | 2 August 2010 | License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate |
| NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control | 1 September 2016 | Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control |
| NRC 2017-0028, License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. | 23 June 2017 | License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. |
| NRC 2017-0041, to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors | 21 August 2017 | to License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors |
| NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
| NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
| NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
| NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
| NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
| NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |