Systematic evaluation program review of NRC Safety Topic VI-7. 3 associated with the electrical, instrumentation and control portions of the ECCS actuation system for the Dresden II Nuclear Power Plant [electronic resource].
- Published:
- Livermore, Calif. : Lawrence Livermore Laboratory, 1980.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 25 : digital, PDF file
- Additional Creators:
- Lawrence Livermore Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- This report documents the technical evaluation and review of NRC Safety Topic VI-7.A.3, associated with the electrical, instrumentation, and control portions of the classification of the ECCS actuation system for the Dresden II nuclear power plant, using current licensing criteria.
- Report Numbers:
- E 1.99:ucid-18698(vol.1)
ucid-18698(vol.1) - Subject(s):
- Other Subject(s):
- Dresden-2 Reactor
- Eccs
- Evaluation
- Electrical Equipment
- Reactor Instrumentation
- Reactor Licensing
- Us Nrc
- Bwr Type Reactors
- Engineered Safety Systems
- Enriched Uranium Reactors
- Equipment
- Licensing
- National Organizations
- Power Reactors
- Reactor Protection Systems
- Reactors
- Thermal Reactors
- Us Organizations
- Water Cooled Reactors
- Water Moderated Reactors
- Note:
- Published through SciTech Connect.
11/01/1980.
"ucid-18698(vol.1)"
St. Leger-Barter, G. - Funding Information:
- W-7405-ENG-48
View MARC record | catkey: 14370930