ANS 55.1-1992(R2017)
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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SOLID RADIOACTIVE WASTE PROCESSING SYSTEM FOR LIGHT-WATER-COOLED REACTOR PLANTS
Hardcopy , PDF
19-09-2022
English
12-01-2013
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1 Scope
2 Definitions
2.1 Limitations
2.2 Glossary of terms
3 Objectives
3.1 Performance objectives
3.2 Safety objectives
4 System requirements
4.1 Process design
4.2 System design
5 Equipment requirements and recommendations
5.1 General
5.2 Tanks
5.3 Pumps
5.4 Valves and piping
5.5 Instrument connections
5.6 Waste pretreatment equipment
5.7 Solidification agent handling system
5.8 Processing and packaging
5.9 Containers and container handling
5.10 Cartridge filter disposal
5.11 Dry active waste compaction
5.12 De-watering systems and high-integrity containers
6 Controls and instrumentation
6.1 System control
6.2 Requirements
6.3 Programmable controller applications
7 Physical arrangement
7.1 General requirements
7.2 Arrangement for maintenance
7.3 Shielding
7.4 Equipment arrangement
7.5 Fire protection
8 System capacity and redundancy
8.1 System capacity design basis
8.2 Redundancy of components
9 Operation and maintenance
9.1 Operational considerations
9.2 Maintenance considerations
10 System construction and testing
10.1 Construction
10.2 System integrity testing
10.3 Cleaning and flushing
10.4 System tests
11 References
Appendices
A Federal regulations and state compacts
B Testing for free liquids in solidified matrices
C Mixed-waste management
D Alternative solidification technologies
E Product quality control requirements
Figures
1 Process flow
2 Solid radwaste data logging sheet
Tables
1 Equipment codes
2 Radiation zone classifications
3 Controls and instrumentation
4 Boiling water reactor radioactive solid waste
processing design basis inputs
5 Pressurized water reactor radioactive solid waste
processing design basis inputs
Describes Solid Radioactive Waste Processing System for light-water-cooled reactor plants for design purposes.
| DocumentType |
Standard
|
| Pages |
52
|
| PublisherName |
American Nuclear Society
|
| Status |
Superseded
|
| SupersededBy | |
| Supersedes |
| ANS 57.7-1988(R1997) | DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (WATER POOL TYPE) |
| ANS 57.9-1992(R2000) | DESIGN CRITERIA FOR AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (DRY TYPE) |
| ANS 40.35-1991 | VOLUME REDUCTION OF LOW-LEVEL RADIOACTIVE WASTE OR MIXED WASTE |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
| ANS 52.1-83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
| ANS 51.1-1983(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS |
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