Mark II lead plant topical report: pool boundary and main vent chugging loads justification. [BWR]

Technical Report · Thu Sep 01 04:00:00 EDT 1977

OSTI ID:5354916

Bilanin, W J; Ernst, R J; Healzer, J M; Marriott, P W; Moody, F J; Singh, A; Wilson, S A

This report provides justification for the continued use of the existing documented pressure suppression pool boundary and main vent chugging loads specified for Mark II lead plant assessment evaluations. It provides a technical basis for permitting the licensing review cycle of the Mark II lead plants to continue on schedule. The first part of the report justifies the use of pool boundary chugging loads documented in the Mark II Phase I, II, and III Temporary Tall Tank Test (4T) Facility Application Memorandum and indicates that these loads are conservative for Mark II Lead Plant evaluations. This position is supported by a comparison of the 4T Application Memorandum chugging specification with both the expected loading condition predicted by a recently developed three-dimensional multivent hydrodynamic model and additional test data analyzed since publication of the Application Memorandum. The second part justifies the use of the main vent lateral chugging loads documented in the Mark II Dynamic Forcing Function Information Report (DFFIR). This specification, based on test results employed by General Electric, is presented and Mark II 4T data is used to expand the full scale single vent data base and to better define the application to the Mark II system. In addition, recent multivent test data is used to demonstrate that the current probabilistic multivent lateral load methodology presented as part of the load specification in the DFFIR is conservative.

• Research Organization: General Electric Co., San Jose, Calif. (USA). Boiling Water Reactor Systems Dept.
• OSTI ID: 5354916
• Report Number(s): NEDO-23617
• Country of Publication: United States
• Language: English

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
ACCIDENTS
BWR TYPE REACTORS
CONDENSATION CHAMBERS
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
PRESSURE SUPPRESSION
REACTOR ACCIDENTS
REACTORS
SIMULATION
STRESS ANALYSIS
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS