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Title: TMI-2: Lessons learned by the US Department of Energy: A programmatic perspective

Technical Report ·
DOI:https://doi.org/10.2172/6977840· OSTI ID:6977840
;  [1]; ;  [2]
  1. EG and G Idaho, Inc., Idaho Falls, ID (USA)
  2. ENCORE Technical Resources, Inc., Middletown, PA (USA)

This report is a summary of the lessons learned by the US Department of Energy during its decade-long participation in the research and accident cleanup project at Three Mile Island Nuclear Power Station Unit 2 near Harrisburg, Pennsylvania. It is based on a review of a wide range of project documents and interviews with personnel from the many organizations involved. The lessons are organized into major subjects with a brief background section to orient the reader to that subject. The subjects are divided into sub-topics, each with a brief discussion and a series of lessons learned. The lessons are very brief and each is preceded with a keyword phrase to highlight its specific topic. References are given so that the details of the subject and the lesson can be further investigated. 99 refs., 24 figs.

Research Organization:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Organization:
DOE/NE
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6977840
Report Number(s):
DOE/ID-10276; ON: DE90007981; TRN: 90-011710
Country of Publication:
United States
Language:
English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
REACTOR ACCIDENTS
TECHNOLOGY ASSESSMENT
THREE MILE ISLAND-2 REACTOR
CESIUM 137
CLEANING
COMPUTERIZED SIMULATION
CONTAINMENT BUILDINGS
CONTAMINATION
DATA ACQUISITION
DATA ANALYSIS
DECISION MAKING
DECONTAMINATION
DESIGN
DOCUMENTATION
FAILURE MODE ANALYSIS
FISSION PRODUCTS
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL COOPERATION
MATERIALS HANDLING
MEASURING INSTRUMENTS
MEASURING METHODS
OCCUPATIONAL SAFETY
PERFORMANCE
PROGRAM MANAGEMENT
QUALITY ASSURANCE
RADIATION DOSE UNITS
RADIATION MONITORING
RADIATION PROTECTION
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIONUCLIDE KINETICS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR LICENSING
REACTOR MAINTENANCE
REACTOR SAFETY
REACTOR VESSELS
RECOMMENDATIONS
REMOTE CONTROL
RESEARCH PROGRAMS
RISK ASSESSMENT
ROBOTS
STEAM GENERATION
SURVEYS
THERMODYNAMICS
TRAINING
VACUUM SYSTEMS
WASTE TRANSPORTATION
WATER CHEMISTRY
ACCIDENTS
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDINGS
CESIUM ISOTOPES
CHEMISTRY
CONTAINERS
CONTAINMENT
CONTROL
COOPERATION
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
ISOTOPES
LICENSING
MAINTENANCE
MANAGEMENT
MATERIALS
MECHANICS
MONITORING
NUCLEI
ODD-EVEN NUCLEI
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTORS
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
TRANSPORT
UNITS
WASTE DISPOSAL
WASTE MANAGEMENT
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES
054000* - Nuclear Fuels- Health & Safety
052002 - Nuclear Fuels- Waste Disposal & Storage
220900 - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210700 - Nuclear Power Plants- Regulation & Licensing