Semantic search
Jump to navigation
Jump to search
Issue date | Title | |
---|---|---|
ML21278A297 | 7 September 2021 | 6 to Technical Specification Bases |
ML18071A197 | 28 March 2018 | Plan, Units 1 and 2 - Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident |
ML18262A096 | 6 March 2018 | Technical Specification Bases, Revisions 62 Through 63 |
ML20311A624 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
ML20311A619 | 6 November 2017 | 2017 Q1-Q4 ROP Inspection Findings |
ML17261A229 | 19 July 2017 | Bases 3.4, Reactor Coolant System(Rcs), Revisions; B 3.4.1-1 Through B 3.4318-8 |
IR 05000317/2016004 | 10 February 2017 | Integrated Inspection Report 05000317/2016004 and 05000318/2016004 |
IR 05000317/2016008 | 9 November 2016 | NRC Triennial Fire Protection Inspection Report 05000317/2016008 and 05000318/2016008 and Exercise of Enforcement Discretion |
IR 05000317/2016003 | 31 October 2016 | Integrated Inspection Report 05000317/2016003 and 05000318/2016003 and Independent Spent Fuel Storage Installation Report 07200008/2016001 |
ML16258A078 | 8 September 2016 | Technical Specification Bases B 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits |
05000317/LER-2016-004 | 20 July 2016 | High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to be Inoperable LER 16-004-00 for Calvert Cliffs, Unit 1 Regarding High Energy Line Break Barrier Breeched Due to Human Performance Error Causing Both Service Water Trains to be Inoperable |
IR 05000317/2015010 | 30 November 2015 | Problem Identification and Resolution Inspection Report 05000317/2015010 and 05000318/2015010 |
ML15257A199 | 4 September 2015 | Technical Specification Bases, Revisions 49 Through 55. Part 7 of 12 |
IR 05000317/2015009 | 27 May 2015 | IR 05000317/2015009, 05000318/2015009; 04/13/2015 to 04/17/2015; Calvert Cliffs Nuclear Power Plant (Ccnpp), Units 1 and 2; Special Inspection to Review the April 7, 2015, Dual Unit Reactor Trip; Inspection Procedure 93812, Special Inspecti |
IR 05000317/2015001 | 27 April 2015 | IR 05000317-15-001, 05000318-15-001; 01/01/2015 - 03/31/2015; Calvert Cliffs Nuclear Power Plant (Ccnpp), Units 1 and 2; Equipment Alignment, Operability Determinations and Functionality Assessments |
ML14267A229 | 19 September 2014 | B 3.4.1-1, RCS Pressure, Temperature and Flow DNB Limits Through B 3.4.18-8, SG Tube Integrity |
ML14191A255 | 10 July 2014 | Nine Mile Point and Ginna, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process |
ML14170B022 | 26 June 2014 | Staff Assessment of Flooding Walkdown Reports Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Accident |
ML14134A133 | 2 June 2014 | Constellation Plants Seismic Walkdown - Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Nine Mile Point Nuclear Station, Units 1 and 2 and Ginna Nuclear Power Plant.(Tac MF0104, MF0105, MF0127, MF0145 and MF0146) |
ML14125A015 | 1 May 2014 | License Amendment Request: Adoption of Technical Specification Task Force Traveler (TSTF) - 425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b |
ML14099A196 | 31 March 2014 | Constellation Energy Nuclear Group, LLC - Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task. |
ML13325A891 | 23 December 2013 | Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns |
ML13281A397 | 24 September 2013 | Revision 46 to Technical Specification Bases. Sections B 3.4.1-1 to B 3.4.18-8 |
ML13193A150 | 28 June 2013 | Supplemental Response to 10 CFR 50.54(f) Request for Information Recommendation 2.3, Seismic |
ML13154A374 | 29 May 2013 | Response to 10 CFR 50.54(f) Request for Information: Near-Term Task Force Recommendation 2.3, Flooding |
ML13078A010 | 12 March 2013 | Flood Hazard Reevaluation Report |
ML12349A282 | 27 November 2012 | Seismic Walkdown Report - Cover Page, Table of Content - Page C-50 |
ML12339A350 | 27 November 2012 | Attachment (1) Seismic Walkdown Report, Attachment (2) Equipment Lists and Attachment (3) Walkdown Checklists. Part 1 of 8 |
ML12335A029 | 27 November 2012 | R. E. Ginna - Response to 10CFR50.54(f) Request for Information, Recommendation 2.3 Flooding |
ML12284A253 | 2 October 2012 | Technical Specification Bases, Revisions 44 and 45, B 3.4, Reactor Coolant System (RCS) |
ML12053A340 | 12 March 2012 | Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident |
ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
ML12056A050 | 12 March 2012 | Enclosure 4 - Recommendation 2.3: Flooding |
ML11287A132 | 4 October 2011 | Technical Specification Bases, Revisions 40 Through 43, Section B 3.4 - Reactor Coolant System (RCS) |
ML12038A135 | 29 August 2011 | Email from G. Kulesa, NRR to P. Boyle, NRR FW: Request for Assistance - Confirmation That OBE Was Not Exceeded at Surry and Calvert Cliffs |
ML102660560 | 17 September 2010 | Technical Specification Bases, Revisions 38 & 39, Section B 3.4 - Reactor Coolant System (RCS) |
ML092670274 | 15 September 2009 | Technical Specification Bases, Revisions 36 and 37, B 3.4, Reactor Coolant System (RCS) |
ML082660354 | 9 May 2008 | Technical Specification Bases, Revisions 33 Through 35, Page B 3.4.1-1 Through B 3.4.18-8 |
ML072830155 | 5 September 2007 | Technical Specification Bases, B 3.4 Reactor Coolant System, Pages B 3.4.1-1 Through B 3.4.18-8 |
IR 05000317/2006005 | 2 February 2007 | NRC Integrated Inspection Report 05000317-06-005 and 05000318-06-005 |
ML062840174 | 27 September 2006 | Technical Specifications Bases Unit Nos. 1 & 2. Bases B 3.4 Reactor Coolant System (Rcs), Pages B 3.4.1-1 Through B 3.4.1-2 |
ML043100130 | 3 November 2004 | Units 1 & 2; Technical Specification Bases, Revisions 15. 16, 17, 18, 19, 20. 21, and 22 |
ML033040019 | 29 October 2003 | Transmittal of Airs Database Operating Experience Reports |
ML031270300 | 1 May 2003 | License Amendment Request Re Increase to Spent Fuel Pool Maximum Enrichment Limit with Soluble Boron Credit, Attachments 1 Through G |
ML20212G052 | 22 September 1999 | Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors |
ML20154R148 | 22 October 1998 | Discusses Insp That Was Conducted at Plant During Wk of 980706 to Review App R Related Open Items.Meeting to Discuss Issues Re App R self-assessment Issues Scheduled for 981118 |
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures | 9 July 1997 | Inadequate or Inappropriate Interim Fire Protection Compensatory Measures |
ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
IR 05000317/1993030 | 30 November 1993 | Insp Repts 50-317/93-30 & 50-318/93-30 on 931010-1113. Violations Noted But Not Cited.Major Areas Inspected:Plant Operations,Maint,Engineering & Plant Support,Including Emergency Preparedness,Security & Fire Protection |
NRC Generic Letter 1992-02 | 6 March 1992 | NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown. |