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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ENS 41781  + (Unit Commenced a Tech Spec Required Shutdown Due to an Electrical Problem Affecting a Safety Related Battery)
• ML20129H893  + (Unit Cooldown to Cold Shutdown)
• ML052350675  + (Unit Cycle 13 90-Day Inservice Inspection Summary Report)
• ML20108D867  + (Unit Cycle 6 Operating Limits Rept)
• 05000321/FIN-2016003-01  + (Unit Downpower Caused by RFP Vent Line Failure)
• 05000321/FIN-2014004-01  + (Unit Downpower Caused by Relief Valve Failure)
• ENS 42406  + (Unit Entered a T.S. Required Shutdown After Declaring Both Condenser Offgas Radiation Monitors Inoperable)
• ENS 45403  + (Unit Experienced a Valid Rps Actuation During Plant Cooldown on Low Steam Generator Levels)
• ENS 41790  + (Unit Experienced an Automatic Reactor Scram Due to a Loss of Feedwater Flow)
• ENS 47489  + (Unit Experienced an Automatic Reactor Scram During a Planned Shutdown)
• BSEP 11-0040, Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me.  + (Unit I & 2, Additional Information Supporting License Amendment Request to Add Analytical Methodology ANP-10298PA to Technical Specification 5.6.5,Core Operating Limits Report (COLR) (NRC TAC ME3856 & Me.)
• ML051300602  + (Unit I (TMI Unit 1), Additional Information Regarding Kinetic Expansion Inspection and Repair Criteria)
• ML12003A209  + (Unit I - Anticipated License Amendment Requests)
• ML041460495  + (Unit I - CRDM Top Head Analysis, PWSCC Crack Growth Correlations and Fatigue Crack Growth Calculations for Point Beach Unit 1)
• ML13234A356  + (Unit I - Revised Evacuation Time Estimates)
• ML20265C173  + (Unit I Aux Bldg 150 Ton Crane Miscellaneous Steel Runway Plan & Details)
• 05000335/LER-2004-002, Unit I Re Train B Emergency Core Cooling System Room Ventilation System Inoperable  + (Unit I Re Train B Emergency Core Cooling System Room Ventilation System Inoperable)
• NL-04-0610, Unit I Reactor Vessel Surveillance Capsule V Results  + (Unit I Reactor Vessel Surveillance Capsule V Results)
• LR-N04-0208, Unit I Withdrawal of Relief Request S1-RR-W02, Proposed Alternative Repair Method for Reactor Vessel Head Penetrations  + (Unit I Withdrawal of Relief Request S1-RR-W02, Proposed Alternative Repair Method for Reactor Vessel Head Penetrations)
• ML011160272  + (Unit I and Unit 2 Operating License No. DPR-50 and Possession Only License No. DPR 73 Docket Nos. 50-289 and 50-320 Combined 2000 Annual Radioactive Effluent Releases Report)
• ML12333A240  + (Unit I, Application to Modify Technical Specification 3.7.10, Control Room Emergency Ventilation System (WBN-TS-12-01))
• RS-04-068, Unit I, Dresden Nuclear Power Station, Units 2 and 3, Supplemental Response to Issuance of Order to Modify License for Revised Design Basis Threat  + (Unit I, Dresden Nuclear Power Station, Units 2 and 3, Supplemental Response to Issuance of Order to Modify License for Revised Design Basis Threat)
• ML042400316  + (Unit I, License Amendment Request Pursuant to 10 CFR 50.90: Addition of 24 Hours for Restoration of Primary Containment Oxygen Concentration)
• RBG-46301, Unit I, NRC Temporary Instruction 2515/156 Offsite Power System Operational Readiness  + (Unit I, NRC Temporary Instruction 2515/156 Offsite Power System Operational Readiness)
• ML13142A199  + (Unit I, Path Forward for Resolution of Generic Safety Issue (GSI)-191)

• 05000528/LER-2004-003, Unit I, Regarding Manual Reactor Trip - Slipped Control Element Assembly  + (Unit I, Regarding Manual Reactor Trip - Slipped Control Element Assembly)

• 05000335/LER-2004-001, Unit I, Regarding PSB-I Analysis Non-Conservatisms Led to Past Operation Prohibited by TSs  + (Unit I, Regarding PSB-I Analysis Non-Conservatisms Led to Past Operation Prohibited by TSs)
• ML042300509  + (Unit I, Special Report 1-SR-2004-003 Report of Boron Deposit at Control Element Drive Mechanism Vent)
• ML051300368  + (Unit I, Thirty-Day Report of Loss-Of-Coolant Accident Evaluation Model Changes)
• ML040350402  + (Unit I, Unit 1 Vessel Head Inspection Results)
• ML18088A094  + (Unit II Plants ECCS Performance Results)
• ML12227A873  + (Unit ISI Request for Information)
• ML24039A160  + (Unit L & 2, Supplement to Modify the Implementation Date for License Amendment Request to Revise Alternate Source Term Dose Calculation)
• ML12200A183  + (Unit Licensing Basis Seismic Ground Motion Concern)
• 05000413/LER-2004-002, Unit Manual Reactor Trip Initiated Due to the Closure of a Main Feedwater Isolation Valve  + (Unit Manual Reactor Trip Initiated Due to the Closure of a Main Feedwater Isolation Valve)
• 05000261/LER-2003-003, Unit N0. 2, Regarding Discovery of Two New Appendix R Safe Shutdown Vulnerabilities  + (Unit N0. 2, Regarding Discovery of Two New Appendix R Safe Shutdown Vulnerabilities)
• ML072600195  + (Unit No .1 - Authorization Under 10 CFR 50.55a(a)(3)(i) for Modification of Core Shroud Stabilizer Assemblies)
• ML063340158  + (Unit No .2 - Final Accident Precursor Analysis of January 23, 2004, Operational Event)
• ML102590213  + (Unit No .3-Relief from the Examination Area for Reactor Vessel Head Penetration Nozzles)
• ML20265E317  + (Unit No 1 Electrical Auxiliary Board Sec 1B 230 Kv Substation Control)
• ML20265D758  + (Unit No 1 Electrical Auxiliary Board Sec 1B 230KV Substation Control)
• ML20266A335  + (Unit No 8-137 Type Beu Excess Letdown He)
• ML12142A304  + (Unit No, 2 - Request for Additional Information Related to Relief Requests RR-2 for the Fifth 10-Year Interval Inservice Testing Program)
• ML080590022  + (Unit No. - 3 - 10 CFR Part 50 Appendix H, Test Report Requirements: Review of Report WCAP - 16629-NP, Revision 0, Analysis of Capsule W from the Dominion Nuclear Connecticut Millstone Unit 3 Reactor Vessel Radiation Surveillance.)
• ML14069A534  + (Unit No. - Request for Additional Information Regarding the Steam Generator License Amendment Request to Revise Technical Specification for Permanent Alternate Repair Criteria)
• ML030570683  + (Unit No. 1 - Delegation of Authority)
• ML18110A133  + (Unit No. 1 - Issuance of Amendment No. 180 Concerning Changes to Technical Specifications Regarding Implementation of the Alternative Source Term (CAC No. MF9818; EPID L-2017-LLA-0241))
• ML19031A704  + (Unit No. 1, Radioactive Effluent Release Report, January - June 1977, Report No. RERR-2)
• ML19031A705  + (Unit No. 1, Radioactive Effluent Release Report, December 11, 1976 - December 31, 1976, Report No. RERR-1)
• LR-N11-0126, Unit No. 2, Proposed Clarifications to License Renewal Safety Evaluation Report Associated with the Salem Nuclear Generating Station, Units 1 and 2 License Renewal Application  + (Unit No. 2, Proposed Clarifications to License Renewal Safety Evaluation Report Associated with the Salem Nuclear Generating Station, Units 1 and 2 License Renewal Application)
• 05000261/LER-2016-002, Unit No. 2, Regarding Unanalyzed Condition Related to Main Steam Line Break Inside Containment  + (Unit No. 2, Regarding Unanalyzed Condition Related to Main Steam Line Break Inside Containment)