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 Issue dateTitle
IR 05000317/198500912 June 1985Insp Repts 50-317/85-09 & 50-318/85-09 on 850401-0506. Violation Noted:Vol Adjustment for Audible Count Rate of Source Range Neutron Flux in Control Room Reduced to Inaudible Point
IR 05000317/198502827 November 1985Insp Repts 50-317/85-28 & 50-318/85-28 on 851001-1104.No Violation Noted.Significant Concerns Identified Re Testing of Steam Generator Safety Valves.Major Areas Inspected: Control Room Physical Security & LERs
IR 05000317/198600931 July 1986Insp Repts 50-317/86-09 & 50-318/86-09 on 860501-0630. Violation Noted:Failure to Maintain Proper Administrative Control Over High Radiation Area Keys & Untimely Pursuit & Identification of Cause of 860521 & 27 Reactor Trips
IR 05000317/198801824 August 1988Exam Repts 50-317/88-18OL & 50-318/88-18OL on 880622.Exam Results:Single Candidate Passed Written Exam.No Strengths or Weaknesses in Training Program Identified
IR 05000317/19900242 October 1990Insp Rept 50-317/90-24 on 900904-07.No Violations Noted
IR 05000317/20030027 May 2003IR 05000317-03-002, 05000318-03-002; Calvert Cliffs Nuclear Plant, Inc.; on 12/29/2002 -3/29/2003; Calvert Cliffs Nuclear Power Plant, Units 1 & 2; Drill Evaluation and Event Follow-up
IR 05000317/20080028 May 2008IR 05000317-08-002, 05000318-08-002; on 01/01/2008 - 03/31/2008; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Maintenance Risk Assessments; Operability Evaluations; and Refueling Outage Activities
IR 05000317/201400522 January 2015IR 05000317-14-005, 05000318-14-005; 10/01/2014 - 12/31/2014; Calvert Cliffs Nuclear Power Plant (Ccnpp), Units 1 and 2; Maintenance Effectiveness
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position27 September 2021Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML02239047011 July 2002Draft - Section a Operating
ML03062024321 February 2003Reactor Vessel Water Level Monitoring System Special Report
ML03093005528 March 2003Request for Exemption to 10 CFR 50.44 & 10 CFR Part 50, Appendix E, Section VI & Proposed License Amendments for Relaxation of Post Accident Hydrogen Monitoring & Control Requirements
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML03297017521 October 2003Technical Specification Bases, Revision 14
ML0334404165 December 2003Withdrawal of Request for Exemption to 10 CFR 50.44 and Appendix E, Section VI
ML0406401302 March 2004Technical Specification Amendment No. 262 & 236
ML04208010120 July 2004License Amendment Request: Change to Technical Specifications Related to the Removal of Hydrogen Control from the Design Basis
ML0431001303 November 2004Units 1 & 2; Technical Specification Bases, Revisions 15. 16, 17, 18, 19, 20. 21, and 22
ML0525600988 September 2005Technical Specification Bases, Revisions 23 and 24
ML06104026610 April 2006Emergency Response Data System
ML0616403278 June 2006Reactor Vessel Water Level Monitoring System Special Report
ML06284017227 September 2006Technical Specifications Bases Unit Nos. 1 & 2. Bases B 3.3 Instrumentation, Pages B 3.3.1-1 Through B 3.3.12-4
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML07106008510 April 2007Emergency Response Data System
ML07141007817 May 2007Post-Accident Monitoring Report
ML0728301515 September 2007Technical Specification Bases, B 3.3 Instrumentation, Pages B 3.3.1-1 Through B 3.3.12-4
ML0826603529 May 2008Technical Specification Bases, Revisions 33 Through 35, Page B 3.3.1-1 Through B 3.3.12-4
ML08268004231 July 2008Post Exam Question SRO-10, NRC Exam, Comments, and Reference Documents
ML09119015824 April 2009Post-Accident Monitoring Report
ML09267027315 September 2009Technical Specification Bases, Revisions 36 and 37, B 3.3, Instrumentation
ML10243020227 August 2010Reactor Vessel Water Level Monitoring System Special Report
ML10266055417 September 2010Technical Specification Bases, Revisions 38 & 39, Section B 3.3 - Instrumentation
ML10320027910 November 2010Independent Spent Fuel Storage Installation, Changes to the Emergency Response Plan and Implementing Procedures
ML11039022418 February 2011License Amendment, Transition from Westinghouse Nuclear Fuel to Areva Nuclear Fuel
ML11039026318 February 2011Non-Prop SE - Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 - License Amendment Transition from Westinghouse Nuclear Fuel to Areva Nuclear Fuel
ML1107002571 February 2011Independent Spent Fuel Storage Installation, EAL Technical Bases (Strike Out Version). Part 1 of 13