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A list of all pages that have property "Title" with value "100 F Sacs Design Temp Limit Evaluation". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML071980485  + (10/22 & 29/2007 - Corporate Notification Letter)
  • ML023240516  + (10/23-24/2002 Summary of Meetings with Carolina Power & Light Re Robinson Nuclear Plant License Renewal Application)
  • ML022840438  + (10/23-24/2002, Meeting with H. B. Robinson Steam Electric Plant, Unit 2, to to Discuss the Review Tools Provided by the Applicant for the License Renewal Application. the Application Is Available on the NRC Web Site at Http://Www.Nrc.Gov)
  • ML18285A643  + (10/23-24/2018 Doe/Nrc Natural Phenomena Hazards Meeting Draft Agenda)
  • ML072770508  + (10/3/07 Meeting Handout, Steam Dryer Evaluation Approach for Monticello Extended Power Uprate (Epu))
  • ML112840114  + (10/3/11 Summary of Meeting Via Conference Call with STP Nuclear Operating Company to Discuss Risk-Informed GSI-191, Assessment of Debris Accumulation on Pressurized-Water Reactor (PWR) Sump Performance, Resolution Approach for South Texas)
  • ML13275A269  + (10/3/13 Presentation Slides from Meeting with Duke Energy Carolinas, LLC, Oconee Nuclear Station Units 1, 2, and 3, Protected Service Water Alternate Cooling)
  • ML13281A697  + (10/3/13 Summary of Meeting with Duke Energy Carolinas, LLC to Discuss the Protected Service Water System Operation - Oconee Nuclear Station Units 1, 2, and 3)
  • ML11277A113  + (10/3/2011 State of Nj V. USNRC; 11-3228 - Certified Index of the Record)
  • ML12240A080  + (10/3/2012 Notice of Forthcoming Meeting with Tennessee Valley Authority Regarding Voluntary Fire Protection Risk Initiative)
  • ML13262A343  + (10/3/2013 Meeting Notice with Duke Energy Carolinas, LLC, to Discuss the Proposed LAR Protected Service Water System Operation for the Oconee Nuclear Station, Units 1, 2, and 3 (TAC Nos. ME7737, ME7738, ME7739, ME7746, ME7747, and ME7748)
  • ML18290A529  + (10/4/18 - Summary of Public Meeting Southern Nuclear Operating Company to Discuss Issues Associated with the Safety Review of Licensing Actions for Vogtle Electric Generating Plant, Units 3 and 4)
  • ML12223A477  + (10/4/2012 Notice of Significant NRC Meeting with Northern States Power Company to Discuss Prairie Island Nuclear Generating Plant, Unit 2)
  • ML042800208  + (10/5/2004 - Letter to Diane Curran Specific Interrogatory 4)
  • ML092530702  + (10/6-7/2009 Public Meeting to Discuss the U.S. Nuclear Regulatory Commissions Revised Fuel Cycle Oversight Process)
  • ML102880492  + (10/6/09 Crystal River 3 Nuclear Safety Review Committee Handout Page)
  • ML062970043  + (10/6/2006 E-Mail to M. Crawford and R. Byrd, Entergy Operations, Inc., from B. Vaidya, DORL/LPL4/PM - Draft Request for Additional Information)
  • ML23048A064  + (10/6/22 Request for Withholding Information from Public Disclosure for Holtec SMR, LLC)
  • ML042660055  + (10/8/04, BWROG - Safety Evaluation of NEDC-33046, Technical Justification to Support Risk-Informed Primary Containment Isolation Valve AOT Extensions for BWR Plant)
  • ML042920182  + (10/8/04, Watts Bar, Unit 1, Attachment 1, Meeting Summary of 8/26/04)
  • ML042920186  + (10/8/04, Watts Bar, Unit 1, Attachment 2, Meeting Summary of 8/26/04)
  • ML072820399  + (10/9/07 Telephone Call Log Regarding Wisconsin State Review of Draft Environmental Assessment for La Crosse Boiling Water Reactor Request for Exemption from 10 CFR 74.19)
  • ML12271A248  + (10/9/2012 Notice of Forthcoming Meeting with Entergy Operations, Inc. to Discuss Resubmittal of License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 at Arkansas Nuclear One, Unit 2)
  • MN 13-023, 10/9/2013 - Notice of Public Meeting with NextEra Regarding Concrete Degradation Caused by Alkali-Silica Reaction at Seabrook Station  + (10/9/2013 - Notice of Public Meeting with NextEra Regarding Concrete Degradation Caused by Alkali-Silica Reaction at Seabrook Station)
  • ML20262G360  + (100 Curieir 192 Portable Gamma Ray Projector)
  • ML22356A078  + (100 Meter ISFSI Controlled Area Boundary Exemption)
  • ML20085E981  + (100 Ton Cask Drop Analysis for Concrete Floor Above ANO-1 Control Room)
  • ML20263F145  + (1000 ML and 2000 ML Radioactive Gas Shipping Containers Sub-Assembly. Sheet 5 of 9.No Revision Date)
  • ML24295A215  + (1000 Mir - a Pathway for Achieving a Performance Target in a base-isolated Nuclear Power Plant)
  • ML12321A319  + (1000771.402NP, Revision 2, Life Extension for Core Plate Plugs at Brunswick Nuclear Plant Unit 2)
  • ML110730084  + (1001026.401, Rev 1, Basis for Period of Validity of the Palisades Pressure-Temperature (P-T) Limit Curves, Attachment 6 to Pnp 2011-016)
  • ML063490309  + (1002950, Aging Effects for Structures and Structural Components (Structural Tools), Revision 1, Final Report)
  • ML060400223  + (1003361 - On-Line Monitoring of Instrument Channel Performance, Volume 1: Guidelines for Model Development and Implementation)
  • ML22285A197  + (100622 Email _ SUNSI Action_ Application for Amendment 4 to NUHOMS Eos Certificate of Compliance No. 1042 Revision 0 Docket 72-1042)
  • RC-06-0024, 1007930 - On-Line Monitoring of Instrument Channel Performance, Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation  + (1007930 - On-Line Monitoring of Instrument Channel Performance, Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation)
  • ML16277A125  + (10080-DEC-0246, Rev. 0, Coping Duration for Station Blackout (Sbo))
  • ML20289A640  + (100820 Email from Rebecca Ramsay ISP Deis Public Comments)
  • ML21033A354  + (1014-SR-00001, Rev. 0, Safety Analyses Report Type B(U)F Transport Package Castor geo69)
  • ML22073A011  + (1014-SR-00001, Revision 2, Safety Analyses Report, Type B(U)F Transport Package Castor geo69)
  • ML23124A283  + (1014-SR-00002, Revision 0, Safety Analyses Report Dry Storage System Castor geo69. Part 2)
  • ML23124A285  + (1014-SR-00002, Revision 0, Safety Analyses Report Dry Storage System Castor geo69. Part 1)
  • ML23124A290  + (1014-SR-00002, Revision 1, Safety Analyses Report Dry Storage System Castor geo69. Part 2)
  • ML23124A291  + (1014-SR-00002, Revision 1, Safety Analyses Report Dry Storage System Castor geo69. Part 1)
  • ML18267A097  + (1015 Ni EAF Testing)
  • ML21005A271  + (102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054)
  • ML24295A216  + (1020 Miah - Verification of Earthquake Simulation Capabilities for Small Modular Reactor (SMR) Floating Seismic Isolation Systems)
  • ML111050217  + (1021007NP, TR-105696-R13 (BWRVIP-03NP) Revision 13: BWR Vessel and Internals Project - Reactor Pressure Vessel and Internals Examination Guidelines)
  • ML102360661  + (103-87527, Industrial Wastewater Permit Renewal Application, St. Lucie Power Plant Permit No. FL0002208)
  • L-2011-228, 103-87735, Heated Water Plan of Study  + (103-87735, Heated Water Plan of Study)
  • ML18267A090  + (1030-1045 Hold Time and Chemistry Effects)
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