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Issue date | Title | |
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ML21047A314 | 2 April 2021 | Issuance of Amendment No. 184 Regarding Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times RITSTF Initiative 4B |
ML20212L594 | 29 September 2020 | Issuance of Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type |
ML18338A088 | 4 December 2018 | Attachment FormerFAQResponses_11302018 |
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 |
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 |
ML13044A561 | 1 March 2013 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Re Flooding Hazard Reevaluation for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident |
HNP-12-116, License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values | 29 November 2012 | License Amendment Request to Revise Technical Specification Table 3.3-4 Re Degraded Voltage Time Delay Values |
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 |
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 |
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 |
ML12056A045 | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML11206A552 | 25 July 2011 | Update of Nuclear Regulatory Commission (NRC) Distribution List for Documents Containing Safeguards (Sgi), Official Use Only (Ouo), and Routine Information - (Shearon Harris Nuclear Plant) |
ML102140387 | 30 July 2010 | Nuclear Regulatory Commission Biweekly Notice - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations - Publication Date of August 10, 2010 |
ML072150447 | 3 August 2007 | LB Memorandum and Order (Ruling on Standing and Contentions of Petitioners North Carolina Waste Awareness and Reduction Network and Nuclear Information and Resource Service) (LBP-07-11) |
ML071650065 | 27 July 2007 | Summary of Clarification Telephone Call with Progress Energy Regarding Pilot Plant (Shearon Harris) Transition to National Fire Protection Association Standard 805 |
ML072000457 | 17 July 2007 | Transcript of Oral Argument Held in Raleigh, Nc; Pp. 1 - 186 |
ML071840568 | 29 June 2007 | Pilgrim - Pilgrim Watch'S Answer Opposing Entergy'S Motion for Summary Disposition of Pilgrim Watch Contention 3 |
ML071760121 | 18 June 2007 | Carolina Power & Light Company'S Answer to Petition for Leave to Intervene of Ncwarn and Nirs |
ML071700627 | 18 June 2007 | Shearon Harris - NRC Staff Response to Petition for Leave to Intervene and Request for a Hearing Filed by the North Carolina Waste Awareness and Reduction Network and the Nuclear Information and Resource Service |
ML071430566 | 18 May 2007 | Petition for Leave to Intervene and Request for a Hearing with Respect to Renewal of Facility Operating License NPF-63 by the North Carolina Waste Awareness and Reduction Network and Nirs |
ML071270183 | 4 May 2007 | Audit and Review Plan for Plant Aging Managment Programs, Aging Management Reviews, and Time-Limited Aging Analyses for the Harris Nuclear Plant. |
ML063450098 | 29 November 2006 | G20060793 - John D. Runkle Ltr. 2.206 Petition - Shearon Harris Fire Safety |
ML051520404 | 27 May 2005 | FOIA/PA-2004-0277 - Resp 33 - Final |
ML021700049 | 4 June 2002 | Joint Appendix Volume II: Pages 542 - 767, Petition to Review a Final Decision of the Nrc. Case Scheduled for Oral Argument September 5, 2002 |
ML061930439 | 20 November 2000 | Volume 1, Exhibit 1, Sections 5-7 & Appendices A-G to Summary of Facts, Data and Arguments on Which Applicant... - Redacted Version |
ML003673316 | 4 January 2000 | Detailed Summary of Facts, Data and Arguments and Sworn Submission on Which Orange County Intends to Rely at Oral Argument to Demonstrate the Existence of a Genuine and Substantial Dispute of Fact with the Licensee Regarding the Proposed Ex |
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 |
ML18016B013 | 9 July 1999 | Proposed Tech Specs,Relocating 3/4.3.3.3,3/43.3.4,3/4.3.3.9 & 3/4.3.3.11 to Plant Procedure PLP-114, Relocated Tech Specs & Design Basis, IAW GL 95-10 |
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 |
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 |
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 |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program |
ML20128G575 | 3 October 1996 | Forwards Ltr to Be Sent to Licensees of Six Pressurized Water Reactor Plants That Have Used Fuel Mfg by Siemens Power Corp Since 1986.Licensees Requested to Verify Compliance of 10CFR50.46 W/Regulations |
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 |