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A list of all pages that have property "Title" with value "Revised 2019-000167". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML031990299  + (Revised 111-111 - TSC Lead Engineer)
  • ML12345A270  + (Revised 12/12/2012 Notice of Forthcoming Meeting with Omaha Public Power District to Discuss Containment Internal Structures Issues to Support Restart of Fort Calhoun Station, Unit 1)
  • ML23186A163  + (Revised 13 June 2023 Hearing Transcript)
  • ML032120340  + (Revised 135 - 135 NRC Communicator, Emergency Plan Position Specific Instruction)
  • ML20136D003  + (Revised 1979 Functional Budget for Operation & Maint Operations)
  • ML18092A173  + (Revised 1983 Semiannual Radioactive Effluent Release Rate Rept)
  • ML20210B972  + (Revised 1985 Annual Landfill Operations Rept for Solid Waste Disposal Site 2)
  • ML20210C021  + (Revised 1985 Annual Landfill Operations Rept for Solid Waste Disposal Site 3)
  • ML20115A645  + (Revised 1988 Occupational Exposure Rept, Consisting of Listing of Recorded Annual Whole Body Exposure)
  • ML20006D262  + (Revised 1988 Solid Waste Release Repts for Arkansas Nuclear One)
  • ML18057A864  + (Revised 1989 Annual Environ Operating Rept)
  • ML20115A639  + (Revised 1989 Occupational Exposure Rept, Consisting of Listing of Recorded Annual Whole Body Exposure)
  • ML20066E628  + (Revised 1990 ILRT Rept, Consisting of Table 2 Re Type B & C Penalties for Listed Penetrations)
  • ML20115A635  + (Revised 1990 Occupational Exposure Rept, Consisting of Listing of Recorded Annual Whole Body Exposures)
  • ML20115A625  + (Revised 1991 Recorded Annual Whole Body Exposure Rept, Consisting of Listing of Std Format for Reporting Number of Personnel & man-rem by Work & Job Function for 1991 & Number of Individuals in Each Range)
  • ML20058Q314  + (Revised 1992 Annual Radiological Environ Monitoring Rept)
  • ML20058Q256  + (Revised 1992 Annual Radiological Environ Monitoring Rept)
  • ML17264A887  + (Revised 1995 Annual Radioactive Effluent Release Rept, for Re Ginna Nuclear Plant)
  • ML033450129  + (Revised 1:30pm Notice of Public Meeting Between NRC and Firstenergy Nuclear Power Operating Co. to Discuss Results of Management and Human Performance Team Inspection)
  • ML032380060  + (Revised 2001 Annual Effluent & Waste Disposal Report for Virgil C. Summer Nuclear Plant)
  • ML101241141  + (Revised 2008 Annual Radioactive Effluent Release Report)
  • L-2013-089, Revised 2011 Annual Radioactive Effluent Release Report - Enclosure 1  + (Revised 2011 Annual Radioactive Effluent Release Report - Enclosure 1)
  • LIC-15-0021, Revised 2011 Refueling Outage Inservice Inspection Results  + (Revised 2011 Refueling Outage Inservice Inspection Results)
  • ZS-2014-0106, Revised 2013 Occupational Radiation Exposure Individual Report  + (Revised 2013 Occupational Radiation Exposure Individual Report)
  • ML15196A039  + (Revised 2015 10 CFR 50.46 Annual Report)
  • BW240053, Revised 2022 Annual Radioactive Effluent Release Report  + (Revised 2022 Annual Radioactive Effluent Release Report)
  • ML24179A075  + (Revised 22 May 2024 Hearing Transcript, Pages 1-151)
  • ML122160120  + (Revised 2nd Draft RAI for Hope Creek and Salem Part 26 Exemption Request (TACs ME7651, ME7652 and ME7653))
  • ML070740473  + (Revised 3/20/07 Meeting with Duke Power Company to Discuss Oconee High-Energy Line Break Mitigation Strategies)
  • ML13105A015  + (Revised 4/22/13 Meeting with Omaha Public Power District - Potential License Amendment Requests for Fort Calhoun, Unit 1 Related to Flood Protection for Raw Water System, Tornado Missile Protection, Piping/Code Use,And Alternate Seismic Cri)
  • ML021540267  + (Revised 6/10-11/2002 Meeting with Florida Power & Light (FPL) to Discuss Proposed Draft Requests for Additional Information Associated with the License Renewal Application for St. Lucie Nuclear Plant, Units 1 and 2. the Proposed Agenda Is a)
  • NOC-AE-12002867, Revised 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident  + (Revised 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
  • ML12163A344  + (Revised 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident)
  • ML20037A960  + (Revised 630917 Application to Amend License DPR-2,App a, Withdrawing Request for Fuel Type 2 Heat Flux Limits Increase)
  • ML19182A086  + (Revised 665th Meeting of the Advisory Committee on Reactor Safeguard - Meeting Notice, July 10-12 2019 - FRN)
  • ML040370811  + (Revised 6:00pm Notice of Public Meeting to Allow Licensee to State Basis for Their Request to Restart Reactor Operations at Davis-Besse Nuclear Power Station. NRC Will Not Be Providing a Response to Restart Request)
  • ML20024G765  + (Revised 730601 Application for Amend to License DPR-22, Consisting of Revised Pages to Exhibits a & B)
  • ML20003A198  + (Revised 761202 Sample Tech Specs Re Facility Fire Protection.Equipment & Administrative Controls Not Changed by Revision.Action Statements Describe More Appropriate Corrective Measures & Some Surveillance Frequencies Changed)
  • 05000219/LER-1979-041-03, Revised 79-041/03L-1:on 791102,radwaste Bldg Ventilation Monitoring Sys Found Not Yielding Accurate Effluent Data Since Oct 1979.Caused by Inadequate Design in Effluent Monitoring Sys.Mod Made for Calibr of Detectors  + (Revised 79-041/03L-1:on 791102,radwaste Bldg Ventilation Monitoring Sys Found Not Yielding Accurate Effluent Data Since Oct 1979.Caused by Inadequate Design in Effluent Monitoring Sys.Mod Made for Calibr of Detectors)
  • 05000346/LER-1979-130-01, Revised 79-130/01T-1:on 791227,clearance Between RCS Hot Leg & Four Large Shims of Pipe Whip Restraints R-4 Determined to Be Insufficient.Caused by Design Error.Pipe Whip Restraints R1 & R4 Modified & R3 Shim Removed  + (Revised 79-130/01T-1:on 791227,clearance Between RCS Hot Leg & Four Large Shims of Pipe Whip Restraints R-4 Determined to Be Insufficient.Caused by Design Error.Pipe Whip Restraints R1 & R4 Modified & R3 Shim Removed)
  • ML19270G455  + (Revised 790510 Final Deficiency Rept Re Control Loop Bistable Failure on Loss of Power.Revision Specifies That Wiring Diagrams for Bistable Have Been Corrected & Physical Wiring Will Be Corrected)
  • ML20003A117  + (Revised 800403 Final Deficiency Rept,Originally Submitted 800305,re Control Room Heating,Ventilation/Air Conditioning Sys.Corrective Actions Described in Final Rept Ineffective in Reducing Air Leakage.Addl Corrective Actions Provided)
  • ML17193A526  + (Revised 800829 Order for Mod of License.Corrects Refs)
  • ML19339B262  + (Revised 800929 Order for Mod of License.Corrects Refs)
  • ML20049J653  + (Revised 810730 Deficiency Rept.Corrective Action Should Indicate All Uninstalled Pipe Will Be Examined to Determine Similar Rejectable Indications.All Rejectable Pipe Installed Will Be Replaced)
  • ML20069N412  + (Revised 820315 Final Deficiency Rept Re Cladding Fissures Adjacent to Weld Seams in Stainless Steel Suppression Pools. Items 2 & 3 of Proposed Corrective Action Deleted.Placement of Annulus Concrete in Pool Region Will Reduce Stress Level)
  • ML20211D233  + (Revised 860401 Application for Amend to License NPF-39, Changing Plant Staff Position Titles & Plant Staff & Offsite Organizations.Rev Adds Safety Analyses,Per NRC 860520 Request.W/Certificate of Svc.Related Correspondence)
  • ML17325A317  + (Revised 870116 & 0625 Applications for Amends to Licenses DPR-58 & DPR-74,modifying Tech Spec 3/4.8.1 Re Diesel Generator Fuel Oil Testing & Adopting 14 Day Requirement for Completion of Offsite Lab Tests)
  • ML17325A318  + (Revised 870116 & 0625 Applications for Amends to Licenses DPR-58 & DPR-74,modifying Tech Spec 3/4.8.1 Re Diesel Generator Fuel Oil Testing & Adopting 14 Day Requirement for Completion of Offsite Lab Tests)
  • ML20237B011  + (Revised 871008 Application for Amends to Licenses NPF-35 & NPF-52,incorporating New Steam Generator Tube Plugging Criteria.Rev Clarifies Proposed Definition of F Distance. Revised Justification & Discussion of NSHC Encl)