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.
List of results
- ML20206U937 + (Rev 1 to Employee Concerns Special Program C011306-SQN, Testing of Anchors)
- ML20212J545 + (Rev 1 to Employee Concerns Special Program Rept 223.1(B), Instrument Support Design,Instrument Line Support Connections)
- ML20212J590 + (Rev 1 to Employee Concerns Special Program Rept 222.6(B), Pipe Support Weld Design,American Inst of Steel Const Min Weld Criteria)
- ML20206U880 + (Rev 1 to Employee Concerns Special Program C011103-SQN, Methods Used During Installation)
- ML20213D469 + (Rev 1 to Employee Concerns Task Group Operations,Maint, Adequacy of Procedures)
- ML20214R399 + (Rev 1 to Employee Concerns Task Group Operations,Health Physics,Exposure Limits & Records)
- ML20213D454 + (Rev 1 to Employee Concerns Task Group Operations,Mechanical Equipment Reliability/Design,Questionable Design & Const Practices)
- ML20214R423 + (Rev 1 to Employee Concerns Task Group Operations, Operations/Operational,Operator Qualifications)
- ML20214R439 + (Rev 1 to Employee Concerns Task Group Operations, Mechanical Equipment Reliability/Design,Kerotest Valve Leakage & Corrosion)
- ML20214R413 + (Rev 1 to Employee Concerns Task Group Operations,Nuclear Power Site Programs & Procedures.Handling of Safeguards Info)
- NL-92-012, Rev 1 to Engineering Analysis (EA) EA-A-NL-92-012-02, Offsite Doses and CR Habitability Following Large Break LOCA to Justify Continued Operation Until Cycle 12 + (Rev 1 to Engineering Analysis (EA) EA-A-NL-92-012-02, Offsite Doses and CR Habitability Following Large Break LOCA to Justify Continued Operation Until Cycle 12)
- ML20087N489 + (Rev 1 to Engineering Assurance Dept Procedure EAD-6, Contracting & Administering Third-Party Design Assessments)
- ML20210P605 + (Rev 1 to Engineering Calculation E4C-098, 4 Kv Switchgear Protective Relay Setting Calculation)
- ML20236E294 + (Rev 1 to Engineering Change Notice Process & Scope of Engineering Required for Mods, TVA Employee Concerns Special Program Element Rept)
- ML20092H314 + (Rev 1 to Engineering Departmental Procedure EDP-ZZ-00005, Assessing Core Damage)
- ML20138B873 + (Rev 1 to Engineering Evaluation & Analysis of IGSCC in Low Pressure Discs at Grand Gulf Nuclear Station Unit 1)
- ML20034F531 + (Rev 1 to Engineering Evaluation 92-42, PRA Evaluation: Change in Primary Component Cooling TS 3.7.3)
- ML20036A451 + (Rev 1 to Engineering Evaluation 93-02, ASME Code Classification for Containment Penetrations HVAC-1 & HVAC-2)
- ML20202H223 + (Rev 1 to Engineering Evaluation Rept, Core Damage Precursor Event at Trojan)
- ML20024C184 + (Rev 1 to Engineering Evaluation for Design of Condensate Water Storage Tank & Refueling Water Tank,Palo Verde Nuclear Generating Station, for Deficiency Evaluation Repts 82-56 & 82-63)
- ML20205G514 + (Rev 1 to Engineering Procedure EP-3-007, Engineering Change Notice)
- ML20034C307 + (Rev 1 to Engineering Procedure HEP-183, 10CFR21 Evaluation/ Reporting Procedure)
- ML13312A872 + (Rev 1 to Engineering Procedure SO23-SPE-017, Standby Power Capacity Test. Related Info Encl)
- ML20204H140 + (Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3)
- ML20237J471 + (Rev 1 to Enrico Fermi Atomic Power Plant Unit 2 Primary Containment Negative Pressure Analysis)
- ML20247F741 + (Rev 1 to Enviralloy High Integrity Containers)
- ML20138A949 + (Rev 1 to Environ Analysis of Silicone Rubber Boot Seals)
- ML20046C700 + (Rev 1 to Environ Assessment of Remedial Action at Naturita Processing Site Near Naturita,Co)
- ML20099L450 + (Rev 1 to Environ Qualification Document, Vols 1 & 2)
- ML20092P316 + (Rev 1 to Environ Qualification Master Equipment List)
- ML20204F664 + (Rev 1 to Environ Qualification Rept of Two Duct Sealants)
- ML20214V910 + (Rev 1 to Environ Qualification of Mechanical Equipment, Vol 2)
- ML20214P639 + (Rev 1 to Environmentally Qualified Static-O-Ring Differential Pressure Switches Operability Evaluation Test)
- ML20237K270 + (Rev 1 to Envirostone Cement Encapsulation of Solid Radioactive Matls)
- ML20247Q667 + (Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods)
- ML20247Q677 + (Rev 1 to Epop 4428I, Direction of Posl Field Sampling)
- ML20247R749 + (Rev 1 to Epop 4455, Manager of Public Info)
- ML20247R754 + (Rev 1 to Epop 4455A, Nuclear News Manager)
- ML20247R785 + (Rev 1 to Epop 4455C, Technical Assistant)
- ML20247R792 + (Rev 1 to Epop 4455D, News Releases)
- ML20247R808 + (Rev 1 to Epop 4455F, Rumor & Inquiry Control)
- ML20247Q690 + (Rev 1 to Epop 4475A, External Resources Coordinator)
- ML20247Q701 + (Rev 1 to Epop 4490, Implementation of Recovery Operations)
- ML20207N438 + (Rev 1 to Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Environ Qualification SERs & TMI Action Plan Installed Equipment, Request for Addl Info)
- ML17214A321 + (Rev 1 to Equipment Qualification Radiation Dose Map Development)
- ML20196H816 + (Rev 1 to Es QP 02, 10CFR21 Reporting of Defects & Noncompliance)
- ML16340C228 + (Rev 1 to Estimate of Tsunami Effect at Diablo Canyon Nuclear Generating Station)
- ML18096A583 + (Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations)
- ML20216F243 + (Rev 1 to Estimation of Spent Fuel Pit Heat-Up Rate Incorporating Actual Plant Data & Thermal Losses)
- ML20133D366 + (Rev 1 to Evaluation & Disposition of Flaws at Quad-Cities Nuclear Power Plant Unit 2)
- ML20155C057 + (Rev 1 to Evaluation & Disposition of Flaws at Quad Cities Nuclear Power Plant Unit 1 (1987 Outage))