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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
- NLS2024003, 30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector + (30 Day Report - Unauthorized Disassembly of Liquid Scintillation Detector)
- ML24101A273 + (30 Day Report for Eli Lilly and Co. Lost Tritium Exit Sign, EN57025, NMED 240100)
- AEP-NRC-2014-15, 30 Day Report of Changes to or Errors in an Evaluation Model + (30 Day Report of Changes to or Errors in an Evaluation Model)
- ML060540099 + (30 Day Response to Generic Letter 2006-01)
- ML081690051 + (30 Day Response to IR 05000255-08-002, on 05/15/2008 for Palisades Nuclear Plant)
- ML12093A246 + (30 Day Response to March 12, 2012 Information Request Re Near-Term Force Review of Insights from Fukushima Dai-ichi Accident)
- ML12102A136 + (30 Day Response to March 12, 2012 Information Request)
- ML12101A304 + (30 Day Response to March 12, 2012 Information Request)
- NRC 2012-0024, 30 Day Response to March 12, 2012 Information Request + (30 Day Response to March 12, 2012 Information Request)
- NL-12-0626, 30 Day Response to March 12, 2012 Information Request + (30 Day Response to March 12, 2012 Information Request)
- NL-12-0625, 30 Day Response to March 12, 2012 Information Request + (30 Day Response to March 12, 2012 Information Request)
- NL-12-0621, 30 Day Response to March 12, 2012 Information Request + (30 Day Response to March 12, 2012 Information Request)
- WM 11-0011, 30 Day Response to Mid-Cycle Performance Review and Inspection Plan - Wolf Creek Generating Station + (30 Day Response to Mid-Cycle Performance Review and Inspection Plan - Wolf Creek Generating Station)
- ML030170616 + (30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity)
- ML021750046 + (30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity)
- CPSES-200202442, 30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity. + (30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.)
- CPSES-200300054, 30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity. + (30 Day Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.)
- W3F1-2002-0037, 30 Day Response to NRC Bulletins 2001-01 and 2002-01 for Vessel Head Inspection Findings + (30 Day Response to NRC Bulletins 2001-01 and 2002-01 for Vessel Head Inspection Findings)
- ML021190375 + (30 Day Response to NRC Bulletins 2001-01 and 2002-01 for Vessel Head Inspection Findings)
- ML12107A017 + (30 Day Response to the March 12, 2012 Information Request)
- ML20259D557 + (30 Ft X 24 Ft X 30 Ft - MSIV Weld Ends,Carbon Steel,Double Disc,Main Steam Isolation Valve with Anchor/Darling Hydraulic Actuator)
- ML20260A542 + (30 Inches Thru 24 Inches 1200 Nuclear Valve Cross-Section & Matls,Asme Section III Class Flange X Weld End)
- ML20260A538 + (30 Inches Thru 48 Inches 1200 Nuclear Valve Bettis Cylinder Operator Replaceable Packing Bonnet Flange X Weld End)
- ML20261M954 + (30 Inches X 16 Inches Flued Head with 1.422 Inches X 1.006 Inches Min Walls Penetration Type I)
- ML20261M945 + (30 Inches X 16 Inches Penetration Type I)
- ML20266H453 + (30 Inv Logic A.Sheet 2)
- ML24213A102 + (30 July 30, 2024 Hearing Transcript, Pages 150-246)
- ML20014E476 + (30 to 96-inch Pipelines Upgrade Case History - Structural Technologies 1.16.20)
- ML18156A014 + (30-2018 Annual Assessment Meeting Attendee List)
- NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material + (30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material)
- NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers + (30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers)
- NL-21-0909, 30-Day 10 CFR 21 Notification - General Electric Hitachi Trip Unit Rivets Popping Off + (30-Day 10 CFR 21 Notification - General Electric Hitachi Trip Unit Rivets Popping Off)
- NL-12-083, 30-Day 10 CFR 50.46 Report of Change in Emergency Core Cooling System Model + (30-Day 10 CFR 50.46 Report of Change in Emergency Core Cooling System Model)
- NL-16-050, 30-Day 10 CFR 50.46 Report of Change in Emergency Core Cooling System Model + (30-Day 10 CFR 50.46 Report of Change in Emergency Core Cooling System Model)
- ML22123A101 + (30-Day FRN NRC Form 646, Formal Discrimination Complaint)
- ML22123A142 + (30-Day FRN NRC Form 655, Eeo Counselors Report)
- ML22189A141 + (30-Day FRN OMB Clearance for NRC Form 361, 361A, and 361N)
- ML24114A201 + (30-Day FRN for New Collection, ICAM Gold)
- ML19198A155 + (30-Day FRN for Part 25, Access Authorization, Information Collection Renewal, OMB 3150-0046)
- ML20050F770 + (30-Day Notice of Payment from the City of Tallahassee Trust Fund Non-Qualified Nuclear Decommissioning Trust Fund for Crystal River Unit 3)
- ML16305A051 + (30-Day Notification of Upcoming Work Activities on the Retained Premises of the WNYNSC)
- 1CAN120205, 30-Day Post Outage Response to NRC Bulletins 2001-01, 2002-01 & 2002-02 for ANO-1 + (30-Day Post Outage Response to NRC Bulletins 2001-01, 2002-01 & 2002-02 for ANO-1)
- ML030800199 + (30-Day Post Refueling Outage Response to NRC Bulletin 2001-01 Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles, NRC Bulletin 2002-01, Reactor Pressure Boundary Integrity, & NRC Bulletin 2002-02, Reactor Pressure)
- ENS 43344 + (30-Day Report Involving a Loss of Accountability of Less than 1 Gram Snm)
- ML100040066 + (30-Day Report Pursuant to 10 CFR 50.46(a)(3)(ii) and Submittal of Large Break Loss of Coolant Accident Reanalysis Results)
- RA-20-0382, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model + (30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model)
- RA-21-0021, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model + (30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model)
- RA-21-0154, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model + (30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Acceptable Loss of Coolant Evaluation Model)
- ML12073A354 + (30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model)
- ML102360485 + (30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model)
- RA-13-1007, 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model + (30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model)