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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
- ML061720376 + (Safety Evaluation Related to Extended Power Uprate at Beaver Valley Power Station, Unit Nos. 1 and 2)
- ML20132F491 + (Safety Evaluation Related to Individual Plant Evaluation Omaha Power District,Fort Calhoun Station,Unit 1)
- ML17187A611 + (Safety Evaluation Related to Inservice Testing Program Relief Request by Util)
- ML25153A508 + (Safety Evaluation Related to License Renewal Application)
- ML20149L795 + (Safety Evaluation Related to Licensee 960729 Requests for Relief from Requirements of Section XI of ASME Boiler & Pressure Vessel Code,1980 Edition Through Winter 1981 Addenda)
- ML120870576 + (Safety Evaluation Related to Licensees Responses to NRC Bulletin 2011-01, Mitigating Strategies)
- ML003764385 + (Safety Evaluation Related to Proposed Corporate Restructuring of Commonwealth Edison)
- ML20217J589 + (Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1)
- ML13326A502 + (Safety Evaluation Related to Request for Approval of Revised Loss-of-Coolant Accident (LOCA) Dose Calculations for the ANO-1 Control Room Based on Alternate Source Term)
- ML21292A148 + (Safety Evaluation Related to Request for Direct and Indirect Transfers of Control of Facility Operating License DPR-6 for Big Rock Point and Renewed Facility Operating License DPR-20 for Palisades Nuclear Plant and ISFSI (EPID L-2020-LLM-00)
- ML12244A100 + (Safety Evaluation Related to Request for Alternate Disposal Approval of Humboldt Bay Waste at Use)
- ML13009A292 + (Safety Evaluation Related to Request for Extension of Enforcement Discretion for Fire Protection)
- ML20134N691 + (Safety Evaluation Related to Third ten-year Interval Inservice Testing Program Nebraska Public Power District Cooper Nuclear Station)
- ML19207B420 + (Safety Evaluation Related to Unit Restart.Concludes Licensee Has Complied W/Nrc 790516 Order & May Accordingly Restart Unit)
- ML103120511 + (Safety Evaluation Related to the Decommissioning of the Leslie C. Wilbur Nuclear Reactor Facility at Worcester Polytechnic Institute (Wpi))
- ML24078A230 + (Safety Evaluation Related to the License Renewal of Comanche Peak Nuclear Power Plant, Units 1 and 2)
- ML25251A150 + (Safety Evaluation Related to the License Renewal of Dresden Nuclear Power Station, Units 2 and 3)
- ML25251A146 + (Safety Evaluation Related to the License Renewal of Dresden Nuclear Power Station, Units 2 and 3)
- ML19351C940 + (Safety Evaluation Related to the Operation of Joseph M. Farley Nuclear Power Station.Unit No. 2.Docket No. 50-364. (Alabama Power and Light Company))
- ML16341C210 + (Safety Evaluation Related to the Operation of Diablo Canyon Nuclear Power Plant,Units 1 and 2.Docket Nos. 50-275 and 50-323.(Pacific Gas and Electric Company))
- ML20132F038 + (Safety Evaluation Related to the Operation of Millstone Nuclear Power Station,Unit 3.Docket No 50-423.(Northeast Nuclear Energy Company))
- ML23200A146 + (Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2)
- ML25329A252 + (Safety Evaluation Related to the U.S. Sfr Owner, LLC Construction Permit Application for the Kemmerer Power Station, Unit 1,)
- ML20070U504 + (Safety Evaluation Relating to Allegation Re Potential for Return to Criticality Following Large Break LOCA)
- ML17037B975 + (Safety Evaluation Relating to Application for Authorization to Construct and Operate)
- ML031780245 + (Safety Evaluation Relating to Relief Request for the Fourth 10-year Interval Inservice Testing Program)
- ML20236V489 + (Safety Evaluation Relating to Response to GL 87-02,suppl 1 for Fort Calhoun Station,Unit 1)
- ML20132F865 + (Safety Evaluation Relating to Review of Topical Rept TR-87, Rev 0, TMI-1 Core Thermal-Hydraulic Methodology Using Vipre -01 Computer Code)
- ML15112A257 + (Safety Evaluation Relating to Topical Rept DPC-NE-3005-P, UFSAR Chapter 15 Transient Analysis Methodology for Oconee Nuclear Station,Units 1,2 & 3)
- ML20035E174 + (Safety Evaluation Relief Requests Re IST Program)
- ML090120360 + (Safety Evaluation Report)
- ML072260449 + (Safety Evaluation Report)
- ML19336A027 + (Safety Evaluation Report)
- ML19119A139 + (Safety Evaluation Report)
- ML19100A211 + (Safety Evaluation Report)
- ML20050H016 + (Safety Evaluation Report)
- ML21181A106 + (Safety Evaluation Report)
- ML21202A112 + (Safety Evaluation Report)
- ML22095A232 + (Safety Evaluation Report)
- ML23208A145 + (Safety Evaluation Report)
- ML18221A244 + (Safety Evaluation Report (Cover Letter) Related to the License Renewal of Waterford Steam Electric Station, Unit 3)
- ML17298A135 + (Safety Evaluation Report (Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005))
- ML062710068 + (Safety Evaluation Report (SER) Related to the License Renewal of Palisdes Nuclear Plant - Transmittal Letter)
- ML090890015 + (Safety Evaluation Report (SER) Related to the Renewal of the Operating License for the Mst Research Reactor)
- ML072920148 + (Safety Evaluation Report (SER) Related to the License Renewal of Vermont Yankee)
- ML062090408 + (Safety Evaluation Report (SER) Related to the License Renewal of Monticello Nuclear Generating Plant)
- ML23115A078 + (Safety Evaluation Report (SER) for Revision 13 of the Certificate of Competent Authority Issued by the U.S. DOT, Model No. JRC-80Y-20T)
- ML21342A169 + (Safety Evaluation Report (SER) for the Sacremento Municipal Utility District (Smud) Rancho Seco Qualty Manual, Revision 5)
- ML21342A188 + (Safety Evaluation Report (SER) for the Sacramento Municipal Utility District (Smud) Rancho Seco Quality Manual Revision 5)
- ML052210459 + (Safety Evaluation Report (SER) with Open Items Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1,2, and 3)
- ML043570535 + (Safety Evaluation Report (SER) with Open Items Related to the License Renewal of Donald C. Cook Nuclear Plant, Units 1 and 2)
- ML061020154 + (Safety Evaluation Report (Ser), with Open Items Related to the License Renewal Dated March 2006 - SER Open Item 3.0.3.2.17-1)
- ML22217A052 + (Safety Evaluation Report - 71-9372.r3)
- ML23360A789 + (Safety Evaluation Report - Amendment 1 - Idaho State University Upadated Roster of Officials)
- ML20037A120 + (Safety Evaluation Report - Certificate of Compliance No. 9282. Revision No. 4)
- ML20035F188 + (Safety Evaluation Report - Certificate of Compliance No. 9321, Revision No. 3)
- ML23033A523 + (Safety Evaluation Report - Certificate of Compliance No. 9330, Model No. ATR-FFSC Package)
- ML23030B321 + (Safety Evaluation Report - Certificate of Compliance No. 9269, Revision No. 12, for the Model No. 650L Package)
- ML21162A005 + (Safety Evaluation Report - Certificate of Compliance No. 9320, Revision No. 5, for the Model Number Midus Transport Package (EPID Numbers L 2021 LLA-0090 and L-2021-RNW-0007))
- ML24275A095 + (Safety Evaluation Report - Certificate of Compliance No. 9310, Revision No. 8, for the Model No. F-431 Transport Package)