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- 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)
- ML20206B993 + (Revised 881019 Special Rept on 880921 Event Re Reactor Operation W/Regulating Blade Being Inoperable.Second Sentence in Ltr Corrected)
- IR 05000382/2023040 + (Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter)
- ML23191A901 + (Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter)
- ML040230201 + (Revised 9:00 A.M. Transcript of Public Meeting Between NRC and Firstenergy Nuclear Power Operating Company Results of Restart Readiness Assessment Team Inspection & Management and Human Performance Team Inspection)
- ML17256A630 + (Revised A-103:4.2 Operator Requalification Program)
- ML20045C835 + (Revised ABWR Design Document)
- ML20065B712 + (Revised ABWR Ssar/Certified Design Matl Cross Ref Matl)
- ML21008A017 + (Revised ANS Design Report)
- NG-75-1212, Revised AO 50-261/75-11:on 750527,RCS Oxygen Concentration Found to Be 0.16 Ppm,Exceeding Limit.Caused by Inattention to Hydrogen Concentration & Dilution of RCS to Hot Shutdown Boron Concentration.Vol Control Tank Vented + (Revised AO 50-261/75-11:on 750527,RCS Oxygen Concentration Found to Be 0.16 Ppm,Exceeding Limit.Caused by Inattention to Hydrogen Concentration & Dilution of RCS to Hot Shutdown Boron Concentration.Vol Control Tank Vented)
- NG-75-1089, Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve + (Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve)
- ML20086F674 + (Revised AO 50-261/75-9:on 750501,reactor Coolant Pump Seal Failed,Resulting in Discharge of Reactor Coolant Fluid to Containment Floor.Caused by Pump Running W/Seal Leaking. Seals,Shaft,Impeller & Hearings Replaced)
- ML20085F880 + (Revised AO 74-08 Revises Corrective Action.Present Location of Restraint Anchor Places Anchor Bolts Partially in Tension & Partially in Shear)
- ML20058E875 + (Revised AOP-6.3, Loss of RHR Shutdown Cooling)
- ML20058E835 + (Revised AOP-7.4, Control Room Inaccessibility)
- ML18016A938 + (Revised ASME QA Manual, for Shnpp)
- ML070120268 + (Revised ASME Section XI Inservice Inspection Program Relief Request Partial Examination of Reactor Pressure Vessel Head-to-Flange Welds-CMP-020 R1)
- ML070650521 + (Revised ASME Section XI Inservice Inspection Program Relief Request Partial Examination of Reactor Pressure Vessel Head-To-Flange Welds - CMP-020-R1, Request for Additional Information Response)
- ML051090441 + (Revised ATI Report for NRC Review)
- ML19317D920 + (Revised Abnormal Occurrence Rept AO-269/74-14:on 741005,4 Gallon Per Minute Reactor Coolant Leak Found.Caused by Leaking Diaphragm in Pressure Switch 1PS-364.Switch Isolated & Removed,Piping Capped)
- ML20079M426 + (Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class)
- ML17193B194 + (Revised Abstract & Pages 2-2,4-2,4-5,7-2 & 18-2 of Revision 16 to QA Program)
- ML20147C629 + (Revised Abstract:Performance Test Development,Conduct & Evaluation)
- ML060310393 + (Revised Acceptance for Review of BWROG Licensing Topical Report, NEDO-33160 Regulatory Relaxation for the Post Accident SRV Position Indication System (TAC No. MC54460))
- ML050870389 + (Revised Acceptance of Boiling Water Reactor Owners Group (BWROG) Licensing Topical Report NEDO-33148, Separation of Loss of Offsite Power from Large Break LOCA for Review)
- NL-08-082, Revised Action Plan to Address the Procedure Adequacy Substantive Cross-Cutting Issue for Indian Point Units 2 & 3 + (Revised Action Plan to Address the Procedure Adequacy Substantive Cross-Cutting Issue for Indian Point Units 2 & 3)
- ML20081M660 + (Revised Action Statement & Surveillances for Tech Specs 3.9 & 4.10 Re Control Room Air Conditioning & Isolation Sys)
- ML070600697 + (Revised Actions for the Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds)
- ML070570535 + (Revised Actions for the Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds)
- ML20080K219 + (Revised Actuation Events Data Sheet to 1993 Annual Operating Rept)
- NOC-AE-02001297, Revised Addendum to Proposed Amendment to Technical Specification 6.8.3.j + (Revised Addendum to Proposed Amendment to Technical Specification 6.8.3.j)