Inspection accessibility study of the Millstone Unit 1 Reactor Pressure Vessel

Technical Report · Sun Jul 01 04:00:00 EDT 1990

OSTI ID:6792575

Davis, J B ^[1]

---

1. Westinghouse Electric Corp., Pittsburgh, PA (USA)

The need for more extensive ultrasonic examination of the Reactor Pressure Vessel (RPV) shell welds at some of the BWR plants is becoming apparent. Recent NRC comments regarding limits on future inspection relief requests and proposed revisions to the ASME Boiler and Pressure Vessel Code, Section 11 have caused BWR plant owners and vendors of inspection services to look at inspection tooling that would allow for the ultrasonic examination of RPV shell welds previously considered inaccessible. One approach to inspection of the RPV shell welds that will allow for greater coverage at some BWR plants is to perform these inspections from inside the vessel. Such inside the vessel examinations are routinely performed in the BWRs in Sweden and Finland. In late 1988, Westinghouse received a contract from Northeast Utilities to examine the flange ligament areas and the shell welds in the upper portion of the Millstone Unit 1 RPV during an outage scheduled to begin in April 1989. This examination was performed with an inspection tool placed inside of the vessel and the UDRPS data acquisition system. The inspection tool was based on tooling used routinely at the Swedish and Finnish BWRs. The object of RP C105-1 was to use the information gathered prior to and during and prepare a report covering the lessons learned during the examination that would benefit other BWR utilities considering similar inspections. This document, Volume 2, describes the Millstone Unit 1 inspection and the lessons learned as a result. 9 figs.

• Research Organization: Electric Power Research Inst., Palo Alto, CA (USA); Westinghouse Electric Corp., Pittsburgh, PA (USA)
• Sponsoring Organization: EPRI
• OSTI ID: 6792575
• Report Number(s): EPRI-NP-6899-D-Vol.2
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACOUSTIC TESTING
BWR TYPE REACTORS
CHEMICAL ANALYSIS
CONTAINERS
ENRICHED URANIUM REACTORS
INSPECTION
JOINTS
MATERIALS TESTING
MILLSTONE-1 REACTOR
NONDESTRUCTIVE ANALYSIS
NONDESTRUCTIVE TESTING
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR SAFETY
REACTORS
SAFETY
TESTING
THERMAL POWER PLANTS
ULTRASONIC TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS