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Issue date | Title | |
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ML18200A181 | 8 August 2018 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident |
ML17363A145 | 21 December 2017 | Response to Request for Additional Information Regarding 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 Reactor |
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. |
L-2016-171, Comment (1) of Larry Nicholson, on Behalf of NextEra Energy and Florida Power and Light, on Consideration of Rulemaking to Address Prompt Remediation of Residual Radioactivity During Operations | 19 August 2016 | Comment (1) of Larry Nicholson, on Behalf of NextEra Energy and Florida Power and Light, on Consideration of Rulemaking to Address Prompt Remediation of Residual Radioactivity During Operations |
ML15174A257 | 1 September 2015 | Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events |
ML15195A201 | 28 July 2015 | Issuance of Amendments Regarding Relocation of Surveillance Frequencies to Licensee Control |
ML14111A147 | 9 May 2014 | Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights |
ML14030A046 | 20 February 2014 | Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 |
IR 05000266/2013002 | 13 May 2013 | IR 05000266-13-002, 05000301-13-002, on 01/01/2013 - 03/31/2013, Point Beach, Units 1 & 2, Fire Protection, Heat Sink Performance, Occupational Dose Assessment, Identification & Resolution of Problems, Follow-Up of Events & Notices of Enfor |
ML12061A079 | 15 March 2012 | G20120096/LTR-12-0053/EDATS: SECY-2012-0082 - Ltr. David Lochbaum Renewed Reactor Operating Licenses |
ML12054A735 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12054A679 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation |
ML12056A045 | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12056A044 | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | 14 July 2011 | G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 |
ML103190653 | 8 November 2010 | Draft Requests for Additional Information, (Srxb) EPU LAR Review |
NRC 2009-0026, Transmittal of Supplement to License Amendment Request 241 Regulatory Guide 1.183 Compliance Matrix | 8 May 2009 | Transmittal of Supplement to License Amendment Request 241 Regulatory Guide 1.183 Compliance Matrix |
ML082910093 | 6 November 2008 | Summary of the October 14, 2008, Pre-Application Meeting with FPL Energy Point Beach, LLC, on the Proposed Alternative Source Term Amendment Request |
ML053430121 | 2 December 2005 | Comment (14) of Leonard L. Sueper on the Reactor Oversight Process |
NRC 2005-0128, Confirmatory Action Letter CAL 3-04-01, Excellence Plan - Revision 7 | 30 September 2005 | Confirmatory Action Letter CAL 3-04-01, Excellence Plan - Revision 7 |
L-HU-05-014, Comment (14) of Edward J. Weinkam Re Draft Generic Letter 2005-XX: Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power | 13 June 2005 | Comment (14) of Edward J. Weinkam Re Draft Generic Letter 2005-XX: Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power |
ML031110449 | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
NRC Generic Letter 1983-11 | 24 June 1999 | NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis |
NRC Generic Letter 1998-01 | 14 January 1999 | NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants |
ML20154C056 | 30 September 1998 | Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval |
NRC Generic Letter 1998-04 | 14 July 1998 | NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i |
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 |
ML20198L115 | 8 January 1998 | SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 |
NPL-98-0110, 1997 Annual Results & Data Rept for Pbnp,Units 1 & 2. W/ | 31 December 1997 | 1997 Annual Results & Data Rept for Pbnp,Units 1 & 2. W/ |
NRC Generic Letter 1997-06 | 30 December 1997 | NRC Generic Letter 1997-006: Degradation of Steam Generator Internals |
NRC Generic Letter 1997-05 | 17 December 1997 | NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques |
NRC Generic Letter 1997-04 | 30 September 1997 | NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules |
NRC Generic Letter 1997-02 | 15 May 1997 | NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report |
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents | 24 February 1997 | Implementation of a New Constraint on Radioactive Air Effluents |
ML20134L989 | 12 February 1997 | Forwards Documentation to Support Restart Issues Identified on Unit 2 Startup Commitment List.Review of Documentation Requested |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program |
ML20134M234 | 13 November 1996 | Responds to NRC Re Resolution of Spent Fuel Pool Safety Issues & Issuance of Final Staff Rept & Notification of Plans to Perform plant-specific,safety-enhancement Backfit Analyses |
NRC Generic Letter 1996-05 | 18 September 1996 | NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves |
NRC Generic Letter 1996-04 | 26 June 1996 | NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks |
NRC Generic Letter 1996-03 | 31 January 1996 | NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits |
NRC Generic Letter 1989-10 | 24 January 1996 | NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors |
NRC Generic Letter 1996-01 | 10 January 1996 | NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits |
NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation |
NRC Generic Letter 1995-07 | 17 August 1995 | NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves |
NRC Generic Letter 1995-04 | 28 April 1995 | NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues |
ML20078F483 | 20 December 1994 | Comment on Proposed Rule 10CFR50 Re Shutdown & low-power Operations for Np Reactors.Informs That Util of Belief That NRC Already Has Appropriate Regulatory Authority Over Shutdown & low-power Operations,As Provided in Maint Rule |
ML20077E836 | 1 December 1994 | Comment Opposing Proposed Rule 10CFR50 Re Shutdown & Low- Power Operations for Nuclear Power Reactors |