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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
- ML20006B381 + (Specific Memorandum of Agreement Between DOE & Ukaea Re Solvent Extraction Centrifugal Contactors)
- ML17249A518 + (Specific Operating Procedures for Site)
- 3F0893-12, Specific Procedure for Seismic Verification of Nuclear Plant Equipment, Rev 0 + (Specific Procedure for Seismic Verification of Nuclear Plant Equipment, Rev 0)
- ML20247J504 + (Specific Reference Material List for SA-109)
- ML20024H527 + (Specific Topics in Severe Accident Management)
- TSTF-033 + (Specification 3.1.3, Required Action A.2 Completion Time Note)
- TSTF-480 + (Specification 3.10.8 Typographical Corrections)
- TSTF-083 + (Specification 3.3.3 Condition a Note Was Made Into a Second Condition)
- TSTF-198 + (Specification 3.8.6 - Unlimited Use of Battery Charging Current in Lieu of Specific Gravity)
- PLA-8135, Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135 + (Specification 5.5.12, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type Leak Rate Testing Frequencies and Permanently Extend the Drywell Bypass Leakage Test Frequency - PLA-8135)
- ML070590672 + (Specification IS-328227-004, Revision 13, Specification for Oyster Creek, Function Requirements for Drywell Containment Vessel Thickness Examinations)
- ML20265C838 + (Specification Radioactive Source Vibration Assy Incoming F USA Built Densometers Only.Sheet 1 of 2)
- ML20265C843 + (Specification Radioactive Source Vibration & Assy Incomeing. Sheet 2 of 2)
- ML20053E659 + (Specification and Verification of Nuclear Power Plant Training Simulator Response Characteristics.Part II: Conclusions and Recommendations)
- ML20040D164 + (Specification and Verification of Nuclear Power Plant Training Simulator Response Characteristics:Part I.Summary of Current Practices for Nuclear and Non-Nuclear Simulators)
- ML20237B953 + (Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3)
- ML20135E868 + (Specification for Replacement SGs Re Release for Bids, Rev a)
- ML20049J190 + (Specification of Changes Required in Emergency Planning Per ASLB 800118 Order & 820301 Stipulation.Certificate of Svc Encl)
- ML20042A139 + (Specification of Changes Required in Emergency Planning Re Christa-Maria Contention 9.Certificate of Svc Encl)
- ML20236T851 + (Specification of Claims.* Rl Herring Claims That Answer Given on Exam Was Correct When TSs Are Considered & When Design Basis Document Considered in Conjunction W/Duke Power Nuclear Sys Div.W/Certificate of Svc.Served on 980727)
- ML20116N061 + (Specification of a Human Reliability Data Bank for Conducting HRA Segments of Pras for Nuclear Power Plants)
- ML082690016 + (Specifications (TS) Change TS-418 - Extended Power Uprate (EPU) - Supplemental Response to Request for Additional Information (RAI) Round 3 & 18 & Response to Round 20 Fuels Methods RAIs)
- ML19341C509 + (Specifications of Computational Approach)
- ULNRC-06478, Specifications to Adopt TSTF-545 Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, (LDCN 18-0021) + (Specifications to Adopt TSTF-545 Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, (LDCN 18-0021))
- ML19256A796 + (Specifications,Tests, & Installation of Wires & Cables for the Diablo Canyon Nuclear Power Project, IEEE Rept F 76-430-9.Describes Process of Selecting Wires & Cables & Criteria for Fire & Environ Tests)
- ML19341C929 + (Specificiation of Computational Approach)
- ML20155G311 + (Specifics of Eddy Current Steam Generator Insp in French Nuclear Power Plants)
- ENS 56089 + (Specified System Activation)
- ENS 42942 + (Specified System Actuation)
- ENS 53736 + (Specified System Actuation)
- ENS 55458 + (Specified System Actuation)
- ENS 55503 + (Specified System Actuation)
- ENS 56373 + (Specified System Actuation)
- ENS 57645 + (Specified System Actuation)
- ENS 46905 + (Specified System Actuation - Afw Initiation)
- ENS 55692 + (Specified System Actuation - Auto Start Emergency Diesel Generator)
- ENS 54605 + (Specified System Actuation - Auto Start Emergency Diesel Generators)
- ENS 56877 + (Specified System Actuation - Auto Start of Emergency Diesel Generator)
- ENS 56997 + (Specified System Actuation - Automatic Start of Emergency Diesel Generators)
- ENS 57694 + (Specified System Actuation - Automatic Start of Emergency Diesel Generator)
- ENS 57298 + (Specified System Actuation - Automatic Start of Diesel Generators)
- ENS 56190 + (Specified System Actuation - Auxiliary Feedwater System Actuation)
- ENS 44383 + (Specified System Actuation - Both Auxiliary Boiler Feedwater Pumps Started Unexpectedly)
- ENS 42974 + (Specified System Actuation - Emergency Diesel Generator Auto Start)
- ENS 45745 + (Specified System Actuation - Feedwater Isolation Due to High Steam Generator Water Level)
- ENS 51940 + (Specified System Actuation - Loss of 1 B-B Electrical Buss)
- ENS 46906 + (Specified System Actuation - Manual Reactor Scram Due to Dual Recirc Pump Trip During Startup)
- ENS 53903 + (Specified System Actuation - Trip of Safety Related Bus)
- ENS 51701 + (Specified System Actuation After Loss of One Offsite Power Source)
- 05000528/LER-2025-003, Specified System Actuation Due to Loss of Power (Lop)/Load Shed (LS) Signal + (Specified System Actuation Due to Loss of Power (Lop)/Load Shed (LS) Signal)
- ENS 50872 + (Specified System Actuation Due to Loss of One Reserve Station Service Offsite Power Source)