Closeout of IE Bulletin 79-17: Pipe cracks in stagnant borated water systems at PWR (pressurized water reactors) plants
Documentation is provided in this report for the closeout of IE Bulletin 79-17 and its revision on the safety-related subject of pipe cracks in stagnant borated water systems at operating plants with pressurized water reactors (PWRs). Closeout is based on the implementation and verification of actions required by the bulletin. Evaluation of utility responses and NRC/Region inspection reports indicates that the bulletin is closed for all of the 41 operating PWRs to which it was issued for action. It is concluded that the concerns of the bulletin have been resolved. Background information is supplied in the Introduction and Appendix A.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Operational Assessment; Parameter, Inc., Elm Grove, WI (USA)
- Sponsoring Organization:
- NRC
- OSTI ID:
- 7156744
- Report Number(s):
- NUREG/CR-5286; PARAMETER/IE--177; ON: TI90007264
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420500 -- Engineering-- Materials Testing
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CHEMISTRY
CONTROL SYSTEMS
COOLING SYSTEMS
CORROSION
CRACKS
DESIGN
DOCUMENTATION
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
FRACTURE MECHANICS
HEAT TRANSFER
HIGH ALLOY STEELS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LEAKS
LICENSING
LOSS OF COOLANT
MATERIALS TESTING
MECHANICS
OPERATION
PERSONNEL
PIPES
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR LICENSING
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
REGULATIONS
SAFETY
STAGNATION
STAINLESS STEELS
STEELS
STRESS ANALYSIS
TESTING
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
42 ENGINEERING
420500 -- Engineering-- Materials Testing
ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CHEMISTRY
CONTROL SYSTEMS
COOLING SYSTEMS
CORROSION
CRACKS
DESIGN
DOCUMENTATION
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
FRACTURE MECHANICS
HEAT TRANSFER
HIGH ALLOY STEELS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
LEAKS
LICENSING
LOSS OF COOLANT
MATERIALS TESTING
MECHANICS
OPERATION
PERSONNEL
PIPES
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR LICENSING
REACTOR OPERATION
REACTOR OPERATORS
REACTOR SAFETY
REACTORS
REGULATIONS
SAFETY
STAGNATION
STAINLESS STEELS
STEELS
STRESS ANALYSIS
TESTING
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS