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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
- IR 05000483/2015002 +
- IR 05000277/2015002 +
- ML15208A034 +
- ML15211A593 +
- CAC:MF6553 +
- CAC:MF6557 +
- ML15216A279 +
- ML15215A650 +
- ML16048A330 +
- ML16015A386 +
- ML15314A539 +
- RA15-049, Registration of Use of Cask to Store Spent Fuel +
- ML15243A208 +
- ML15205A306 +
- ML15180A334 +
- ML15217A038 +
- CNS-15-071, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) +
- ML15216A530 +
- CNL-15-153, Response to Request for Additional Information Related to Application to Revise Technical Specifications for Component Cooling Water and Essential Raw Cooling Water to Support Dual Unit Operation +
- ML15215A590 +
- ML15215A485 +
- ML15215A408 +
- ML15215A407 +
- ML15215A148 +
- TAC:MF6405 +
- ML15215A047 +
- TAC:MF3959 +
- ML15209A424 +
- TAC:MF3729 +
- ML15203A833 +
- SECY-14-0140, Response to Wallace Taylor, Sierra Club - SRM-M150309-I, SECY-14-0140 - Omaha Public Power District (Fort Calhoun Station, Unit 1), Petition to Intervene and Request for Adjudicatory Hearing by Sierra Club (April 23, 2014) +
- ML15153A497 +
- Press Release-II-15-040, NRC Launches Special Inspection at Honeywell Metropolis Works +
- M150309, Response to Wallace Taylor, Sierra Club - SRM-M150309-I, SECY-14-0140 - Omaha Public Power District (Fort Calhoun Station, Unit 1), Petition to Intervene and Request for Adjudicatory Hearing by Sierra Club (April 23, 2014). +
- NL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. +
- NRC-2014-0271, Withdrawal of an Amendment Request, Enclosure 1, Federal Register Notice +
- CP-201500777, Relief Request B-10, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CP-201500778, Relief Request B-11, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CP-201500780, Relief Request C-2, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CP-201500779, Relief Request B-15, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CP-201500781, Relief Request C-4, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CP-201500775, Relief Request B-3, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CP-201500776, Relief Request B-9, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August +
- CNL-15-146, Response to NRC Request for Information Regarding the Review of the License Renewal Application, Set 25 +
- CNL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor +
- JAFP-15-0092, CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models +
- 05000285/LER-2015-004, Regarding Inoperability of Auxiliary Feedwater Trains Due to Failure of Steam Generator Isolation Valve +
- 05000266/LER-2015-004, Regarding Emergency Diesel Generator Switchgear Room Exhaust Fan Removal from Service Results in Operation or Condition Prohibited by Technical Specifications +
- ML14260A454 +
- ML15187A129 +