Single channel fuel clad melt (May 1967) Fuel in a single channel in Reactor 2 that was loaded with fuel elements under evaluation for the commercial reactor programme experienced a partial blockage, attributed to the presence of graphite debris (see
fuel element failure). The fuel overheated and the Magnox
cladding failed, causing contamination to be deposited in one region of the core. The reactor was restarted in 1969 after successful clean-out operations and was the final reactor to cease operation in February 2004.
Fatal accident (ca. 1978) BNFL was fined £200 in 1978 for a fatal accident at Chapelcross.
Boiler shell defect (June 1997) Cracks associated with brackets in Heat Exchanger 6 on Reactor 2 were discovered during routine
ultrasonic testing. Metallurgical examination of samples of the defect showed that: • It originated during fabrication in the workshop and prior to an over-pressure test of 2.35 times the design pressure (a loading significantly in excess of a modern
pressure vessel code requirement). • There was no evidence of in-service
fatigue crack growth. • The material in which the crack was located was different from that specified in the design. Similar material was also identified in other heat exchangers, and no additional cracks of structural significance were revealed during comprehensive inspections. The NII considered the material to be adequate and within the bounds of the heat exchanger safety case.
Exposure of workers to an irradiated fuel element (first quarter 2001) During refuelling operations on Reactor 2, an irradiated fuel element failed to release from the grab which holds an element while it is withdrawn from a reactor. Routine methods were used to release the grab. However, the irradiated fuel element snagged during the operation and was lifted out of its shielding, resulting in the operators on the pile cap being exposed to the intense radiation being emitted from the irradiated fuel element. Personnel responded quickly, and the radiological dose they received was small. The event revealed shortfalls in the safety of the refuelling operation and the licensee took the immediate step of halting all refuelling while it investigated the event and reviewed the safety of the equipment. The NII investigated the event and judged that it was due to inadequate design and operation of the equipment. The incident was classified as Level 1 (anomaly) on the
International Nuclear Event Scale (INES).
Leak of Magnox depleted uranium trioxide (July 2001) A small amount of
Magnox depleted uranium (MDU) leaked from some corroded
mild steel drums due to rainwater ingress and leaching. MDU is a dense
yellow powder that is less
radiologically toxic than naturally occurring uranium but
chemotoxic in a similar manner to lead. Owing to its high density and low solubility, it does not tend to disperse far and dry spills are easy to clean up. This material was stored at the larger sites, including
Capenhurst in mild steel drums. BNFL upgraded the fabric of the building and the original drums were overpacked into
stainless steel drums and dispatched to Capenhurst for long-term storage.
Dropped basket of irradiated fuel elements (July 2001) During routine defuelling activities on Reactor 3, a basket containing 24 low-rated irradiated Magnox fuel elements fell a few feet within the discharge machine onto the door at the top of the fuel discharge well. Remote TV camera inspections revealed that twelve of the elements had fallen just over down the discharge well into a water-filled transport flask at the bottom. The NII initiated an investigation because dropping irradiated fuel elements is a serious issue even when, as in this event, BNFL had advised NII that there had been no release of radiological activity.
Charge pan movement relative to the core (September 2001) Because of known shrinkage of the
graphite moderator bricks in the core due to in-service
irradiation effects, some of the steel charge pans on top of them had become dislocated from their design position in the interstitial channel and were suspended from the Burst Can Detection (BCD) pipework. This was most prevalent in Reactor 1 because of the different core design to Reactors 2, 3 and 4. BNFL were unable to make an adequate safety case or effect an economic repair and therefore, Reactor 1 did not return to power from its annual outage in August 2001. The core of Reactor 4 was repaired but this reactor did not return to power after the repair. ==Interim storage facility==