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A list of all pages that have property "Title" with value "Rev 8 ASME Code Cases Not Approved for Use". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20098E029  + (Rev 7 to West Valley Nuclear Svcs (Wvnsc) Wvns SAR-004, Supernatant Treatment Sys)
  • ML20085C208  + (Rev 7 to Wolf Creek Generating Station Odcm)
  • ML20203E492  + (Rev 7 to Wpat, Welding Procedure Application Table Downcomer Bracing & Quencher Support & Liner Work)
  • ML20195C409  + (Rev 7 to, Design Criteria for Junction Boxes Seismic Category I Electrical Conduit Sys, Third Party Record Copy)
  • ML20248L989  + (Rev 7 to, Security Force Training & Qualification Plan)
  • ML18093A378  + (Rev 7 to, Westinghouse Engineering Svcs Rept for Salem Nuclear Generating Station Units 1 & 2 Concerning RHR Sys Mid-Loop Operation Re NRC Generic Ltr 87-12)
  • ML20082N390  + (Rev 7,Change 1 of Inservice Testing Plan Re Pumps & Valves)
  • ML20135A752  + (Rev 7,Change 1 to Preface for Process Safety Requirements)
  • ML20134J434  + (Rev 7,Change 2 to Preface for Process Safety Requirements)
  • ML20138B226  + (Rev 7,Change 3 to Preface for Process Safety Requirements)
  • ML20056F206  + (Rev 7,Change 4 of Waterford Unit 3 IST Plan for Pumps & Valves)
  • ML20210J239  + (Rev 7,Draft 6 to SL-TR-1A, QA Assurance Program)
  • ML20072T491  + (Rev 7,Issue E,To General Welding Spec GWS-1)
  • ML20202B206  + (Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm)
  • ML20216E949  + (Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual)
  • ML20202D629  + (Rev 7,change 1 to WVDP-218, Preface for Process Safety Requirements)
  • ML20070P870  + (Rev 7,change 5 to Waterford III Pump & Valve IST Plan)
  • ML19354E021  + (Rev 71 to ANF-1, Advanced Nuclear Fuels Corp QA Manual for Nuclear Fuels)
  • ML20198J914  + (Rev 73 to OP-417, Containment Operating Procedure)
  • ML20083K735  + (Rev 74 to Emergency Response Manual (Sser))
  • ML20212P484  + (Rev 75 to Operating Procedure OP-202, Plant Heatup)
  • ML20059D833  + (Rev 76 to EPIP FNP-0-EIP-008)
  • ML063050377  + (Rev 77 to Technical Specification Bases Unit 2 Manual)
  • ML20128N559  + (Rev 7A to Topical Rept CENPD-210A, QA Program Description)
  • ML20245E917  + (Rev 7A to Topical Rept PCC-QAPD, QA Program Description)
  • ML23291A007  + (Rev 8 ASME Code Cases Not Approved for Use)
  • ML18011A111  + (Rev 8 of ISI Program ISI-203, ASME Section XI Pump & Valve Program Plan)
  • ML20080T517  + (Rev 8 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan)
  • ML20141H206  + (Rev 8 to 17.2 to QA During Operation Phase)
  • ML20137T233  + (Rev 8 to 1OM-53C.4.1.6.4(ISS3A), SG Tube Leakage)
  • ML20137T220  + (Rev 8 to 2OM-53C.4.2.6.4(ISS1A), SG Tube Leakage)
  • ML20197H604  + (Rev 8 to 80A4536, Preservice Insp Program Plan:Hpci Sys. Two Oversize Drawings Encl.Aperture Cards Are Available in PDR)
  • ML20248D407  + (Rev 8 to 9100-PLN-4200.02, TMI Emergency Dose Calculation Manual)
  • ML20202B146  + (Rev 8 to AP-250, Radiation Monitor Actuation)
  • ML20203J833  + (Rev 8 to AP-513, Toxic Gas)
  • ML20199E431  + (Rev 8 to AP-961, Earthquake)
  • ML17262A539  + (Rev 8 to AP-ELEC.1, Loss of 12A &/Or 12B Transformer)
  • ML17261B112  + (Rev 8 to AP-RHR.1, Loss of Rhr)
  • ML17261A991  + (Rev 8 to AP-TURB.2, Automatic Turbine Runback)
  • ML20211M798  + (Rev 8 to AR-952, Wdb Annunciator Response)
  • ML20204F958  + (Rev 8 to ASME Code Section XI Inservice Insp & Testing Program & Info Required for NRC Review of Requests for Relief from ASME Code Section XI Requirements)
  • ML20237J792  + (Rev 8 to ASME Code Section XI Inservice Insp & Testing Program Manual,Second 10-Yr Insp Interval 810630- 920530)
  • ML20237H517  + (Rev 8 to Abnormal Operating Instruction AOI-35, Loss of Offsite Power)
  • ML20237H274  + (Rev 8 to Abnormal Operating Instruction AOI-15, Loss of Component Cooling Water)
  • ML20245D071  + (Rev 8 to Abnormal Operating Instruction AOI-14, Loss of RHR Shutdown Cooling)
  • ML20073P443  + (Rev 8 to Analysis of Hydrogen Control Measures at McGuire Nuclear Station, Insertion Instructions,Vol 3)
  • ML20235L958  + (Rev 8 to Anchors Cut Off Re Const, Final Element Rept)
  • ML20035F589  + (Rev 8 to Annunciator Response (AR) Procedure AR-502, ICS J Annunciator Response)
  • ML17261A638  + (Rev 8 to App C - Ginna Station Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1989 Period)
  • ML20081C522  + (Rev 8 to CNS Process Control Program)
  • ML20082M497  + (Rev 8 to COLR, Updating COLR to Reflect Cycle 16 Setpoints & Restrictions Defined in EA-FC-95-009,Rev 0 Cycle 16 Setpoints & COLR)