PWR reactor pressure vessel license renewal industry report: Revision 1. Final report

Technical Report · Fri Jul 01 04:00:00 EDT 1994

OSTI ID:72958

Kennedy, E ^[1]; Doney, G ^[2]; Nickell, R ^[3]

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1. Failure Analysis Associates, Framingham, MA (United States)
2. ABB Combustion Engineering, Inc., Windsor, CT (United States)
3. Applied Science and Technology, Inc., Poway, CA (United States)

PWR reactor pressure vessels designed by all three US PWR nuclear steam supply system vendors have been evaluated relative to the effects of age-related degradation mechanisms; the capability of current design limits, inservice examination, testing, repair, refurbishment, and other programs to manage these effects; and the assurance that these vessels can continue to perform the their intended safety functions in the license renewal term. This industry report (IR), one of a series of then, provides a generic technical basis for evaluation of PWR reactor pressure vessel components for license renewal.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (United States); Failure Analysis Associates, Inc., Framingham, MA (United States); ABB Combustion Engineering, Inc., Windsor, CT (United States); Applied Science and Technology, Inc., Poway, CA (United States)
• Sponsoring Organization: Electric Power Research Inst., Palo Alto, CA (United States)
• OSTI ID: 72958
• Report Number(s): EPRI-TR--103837
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AGING
CRACK PROPAGATION
CREEP
EMBRITTLEMENT
EROSION
FATIGUE
IN-SERVICE INSPECTION
LICENSE APPLICATIONS
NUCLEAR POWER PLANTS
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR LICENSING
REACTOR MAINTENANCE
RELIABILITY
SERVICE LIFE
STRESS CORROSION
WEAR