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| Issue date | Title | |
|---|---|---|
| ML20093B632 | 5 May 2020 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident |
| CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. | 20 October 2016 | Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. |
| RIS 2016-02, Design Basis Issues Related to Tube-To-TubeSheet Joints in Pressurized-Water Reactor Steam Generators | 23 March 2016 | Design Basis Issues Related to Tube-To-TubeSheet Joints in Pressurized-Water Reactor Steam Generators |
| ML15253A405 | 11 March 2016 | Enclosure 1 Seven Screening Criteria |
| ML16069A222 | 9 March 2016 | Speech-S-16-004: Perspectives from Commissioner Baran Remarks by NRC Commissioner Jeff Baran 2016 Regulatory Information Conference March 9, 2016 |
| 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 |
| ML12132A468 | 11 May 2012 | Motion to Strike |
| 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-2012-0068, 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 |
| 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 |
| ML11206B008 | 20 July 2011 | Update of Nuclear Regulatory Commission (NRC) Distribution List for Documents Containing Safeguards (Sgi), Official Use Only (Ouo), and Routine Information - (Catawba Nuclear Station) |
| 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 |
| ML073020585 | 8 November 2007 | License Amendments 238 and 234 Regarding Emergency Core Cooling System Strainer Modification |
| ML060730210 | 6 March 2006 | Comment (11) Submitted by Duke Power Company, James R. Morris on Proposed Rule PR-50 Regarding Risk-Informed Changes to Loss-of-Coolant Accident (LOCA) Technical Requirements |
| NRC Generic Letter 2006-01 | 20 January 2006 | NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications |
| ML051020364 | 31 March 2005 | Relief, Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities at Catawba Nuclear Station, Unit 2 in Accordance with 10 CFR 50.55a(g) (4) (IV) |
| ML052430384 | 12 July 2004 | Response to NRC Regulatory Issue Summary 2004-10, Preparation and Scheduling of Operator Licensing Examinations. |
| ML041330364 | 5 May 2004 | Duke Energy Corporation'S First Supplemental Response to Blue Ridge Environmental Defense League'S First Discovery Request |
| ML033490056 | 4 December 2003 | Transcript of Oral Argument Held in Charlotte, Nc on 12/04/03; Pp. 330 - 576 |
| ML033100591 | 24 October 2003 | Catawba/Mcguire 10/24/03 Letter from Antonio Fernandez to Administrative Judges Regarding Handling of Protected Information |
| ML032940512 | 15 October 2003 | Proposed Technical Specifications Amendments for 3.9.2, Nuclear Instrumentation and 3.9.7, Unborated Water Source Isolation Valves |
| ML032390517 | 11 August 2003 | Comment (15) Submitted by Duke Power Co., W. R. Mccollum on Proposed Rule PR-50 Re Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors |
| ML031210049 | 24 April 2003 | Duke Energy Topical Report Response to Request for Additional Information Letter Dated April 4, 2003 |
| ML030910364 | 18 March 2003 | Transcript of Hearing Held in Rockville, MD on 03/18/03; Pp. 1204 - 1359 |
| L-84-001, Proposed Staff Guidance on the Scoping of Fire Protection Equipment for License Renewal (Cover Letter) | 13 November 2002 | Proposed Staff Guidance on the Scoping of Fire Protection Equipment for License Renewal (Cover Letter) |
| ML023190479 | 13 November 2002 | Proposed Staff Guidance on the Scoping of Fire Protection Equipment for License Renewal (Cover Letter) |
| ML022180220 | 5 August 2002 | 07/23/2002, Summary of License Renewal Meeting Between NRC Staff, Nuclear Energy Inst. (NEI) & Utilities to Discuss Status of License Renewal Activities |
| ML022040546 | 23 July 2002 | SRM-M020723 - Affirmation Session: I. SECY-02-0096-Final Rule, Electronic Maintenance & Submission of Info; Ii. SECY-02-0113-Duke Energy (McGuire, Catawba) Appeal of LBP-02-04: SAMA Contention |
| ML022040633 | 23 July 2002 | Commission Memorandum and Order (CLI-02-17) |
| ML022120027 | 22 July 2002 | Response of Duke Energy Corporation to July 15, 2002 Licensing Board Order |
| ML022120040 | 20 July 2002 | Blue Ridge Environmental Defense League'S and Nuclear Information and Resource Service'S Concise Written Filing in Response to Order of July 15, 2002 |
| ML021120015 | 15 April 2002 | Response to Request for Additional Information in Support of the Staff Review of the Application to Renew the Facility Operating Licenses |
| ML020240330 | 24 January 2002 | LB Memorandum and Order (Ruling on Standing and Contentions) |
| 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 |
| ML031110449 | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
| ML20211M445 | 30 August 1999 | Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting |
| 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 |
| ML20236R954 | 23 July 1998 | Forwards Hearing File & Table of Contents Re R Herring,Per Presiding Officer Order of 980630 & 10CFR2.1231(b). W/Certificate of Svc |
| 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 |
| ML20199A552 | 22 January 1998 | Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2 |
| 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 |