Search by property

Jump to navigation Jump to search

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.

Search by property

A list of all pages that have property "Title" with value "Correction of Statements Made in Relief Request RR-ENG-2-15". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

View (previous 50 | next 50) (20 | 50 | 100 | 250 | 500)


    

List of results

  • ML21130A601  + (Correction of Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B)
  • ML062060257  + (Correction of Recently Issued Technical Specification Pages)
  • ML23065A109  + (Correction of Relief Request HNP-ISI-RR-05-02 Allowing to Continue Operation with a Flaw Indication on One Reactor Pressure Vessel Closure Bolt Until December 31, 2025)
  • ML031180728  + (Correction of Renewed Facility Operating License Nos NPF-4 and NPF-7, DPR-32 and DPR-37)
  • ML17252A173  + (Correction of Report Numbers for Letters 229-75 and 323-75 from B. B. Stephenson)
  • ML17053B273  + (Correction of Response to Apparent Violation in Office of Investigations Report No. 1-2015-005)
  • L-10-047, Correction of Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.  + (Correction of Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.)
  • ML100890226  + (Correction of Response to Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients)
  • ML030350275  + (Correction of Response to Nuclear Regulatory Commission Requests for Additional Information Regarding Proposed License Amendment for Unit 2 Reactor Coolant System Pressure-Temperature Curves)
  • TSTF-437  + (Correction of Rod Position Indication Condition)
  • ML022800308  + (Correction of Safety Evaluation (SE) for Amendment No. 176)
  • ML022950222  + (Correction of Safety Evaluation (SE) for Risk-Informed Inservice Inspection Program (ISI))
  • ML063420033  + (Correction of Safety Evaluation Associated with Authorization of an Alternative)
  • ML110420278  + (Correction of Safety Evaluation Associated with Amendment No. 207 Regarding Technical Specification Conversion to ITS Format)
  • ML020380684  + (Correction of Safety Evaluation Associated with Amendment No. 223)
  • ML013540443  + (Correction of Safety Evaluation Associated with Amendment No. 99)
  • ML12184A130  + (Correction of Safety Evaluation Regarding Cyber Security Plan License Amendment)
  • ML003688537  + (Correction of Safety Evaluation Related to Amendment No. 90 Regarding Surveillance Capsule Withdrawal Schedule)
  • ML040711193  + (Correction of Safety Evaluation Supporting Amendment No. 216 - Minimum Critical Power Ratio Safety Limits and Reference Changes)
  • ML030700131  + (Correction of Safety Evaluation and Transmittal Letter Associated with Amendments Shutdown Cooling)
  • ML23026A318  + (Correction of Safety Evaluation for Amendment Nos. 325, 348, and 308, Application of Advanced Framatome Methodologies, and Adoption of TSTF-564-A, Revision 2 (EPID L-2021-LLA-0132) (Letter))
  • ML063250127  + (Correction of Safety Evaluation for Amendment Dated October 27, 2006)
  • ML24159A265  + (Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project)
  • ML21064A408  + (Correction of Safety Evaluation for License Amendment Nos. 143 and 50 (EPID L-2020-LLA-0005) (Non-Proprietary))
  • ML021970360  + (Correction of Safety Evaluation on Alternative Excess Flow Check Valve Testing Frequency)
  • TSTF-067  + (Correction of Shutdown Margin Definition)