Barsebäck

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Control rods from Barsebaeck to be used for Forsmark-3 repairs

Sunday, November 16, 2008

Stockholm (Platts) - 13 Nov 2008 Forsmark management said it will try to use control rods from the closed Barsebaeck nuclear power plant to replace rods with broken and cracked shafts in Forsmark-3.

About 25% of the Swedish unit's 197 rods are cracked and at least one is broken. In a November 13 statement, Forsmark management said it wants to use the Barsebaeck rods because it would be difficult to quickly order and install so many new rods.

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Nuclear energy? Still 'no thanks'

Monday, February 4, 2008

04.02.2008 The Copenhagen Post - Despite nuclear energy's growing popularity worldwide, Danes remain sceptical

Danish opposition to nuclear energy remains staunch even though the controversial energy source has received a renaissance in recent years.

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INES-event
INES 1

Underdimensioned rupture disc installed in the FILTRA-system

System 361 (FILTRA) provides a filtered pressure relief for the reactor containment in the event of its failure (pressure increase). System 361 is activated via a rupture disc V1 which should rupture at a differential pressure of 5.08 - 5.4 bar across the disc. During the refuelling outage it is possible to replace the rupture disc. After replacement during the outage in 2001, the rupture disc was tested and failed at 3.36 bar instead of as expected at a pressure of at least 5.08 - 5.4 bar. The reason was found to be that the wrong rupture disc had been installed during the outage in 2000.

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 2

Temporary Loss of the seawater cooling systems

When performing recurrent inspection of the system for auxiliary cooling, eight valves were manually closed by mistake. This caused cooling capacity unavailability during six minutes in the component cooling system. This in turn caused safety system unavailability, i.e. containment spray, residual heat removal and diesel generators manual scram was initiated and one minute later cooling capacity re-established.
Justification of the Rating:
Part III-2.4.1 Table I.

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 1

Degraded pressure subpression (PS) function

During start up a test revealed that no pressure difference existed between the dry well and the wet well. The reason was an erroneously left open valve. This reduced the containment pressure subpression function.

Justification:
Initiator did not occur. Structural defect exists, would not have led to an initiator. Availability of the safety function inadequate. Initiator: Major LOCA.

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 1

UNINTENTIONAL RELEASE TO THE SEA OF A MINOR AMOUNT OF SLIGHTLYCONTAMINATED WATER

During routine surveillance some water was found in a non radioactive culvert. The shift personnel pumped this water - approx. 1.6 cubic meter - into a tunnel system leading to the sea. Later investigation showed that the water was drained through a half open valve from a system containing purified slightly contaminated process water. The total release was about 1 MBq, mainly Cr51, Co58 and Co60. The release is less than 1% of the normal weekly release which is less than one pro mille of the permitted value.

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 1

MISSING LUBRICATION GREASE TO THE ECC SYSTEM'S CORE SPRAY PUMPS

At the annual control of the lubrication grease pumps to the Emergency Core Cooling system's core spray pumps it was detected that the lubrication pumps were unable to press the grease to the bearings of the core cooling pumps.
If there was a flooding e.g. because of a pipe break, the pump bearings would have not been protected against penetrating water.
Justification of level 1: Table 1. degradation of defence in depth without an initiator. Safety function availability, adequate, initiator frequency low.

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 1

PROTECTION SYSTEM FOR INITIATING BLOW DOWN NOT COMPLETELY REESTABLISHED AFTER REFUELLING OUTAGE

Against instructions a connecting wire was not inserted to its place and thereby the corresponding relay's function was inhibited. The blowdown system would have not worked automatically if called upon.
Justifaction of level 1: Table 1, degradation of defence-in-depth without an initiator. Safety function availability. Within opertional limits and conditions. Additional factor: Safety culture deficiencies (in the quality assurance process).

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 1

LEAKING ISOLATION VALVES IN THE EMERGENCY CORE COOLING SYSTEM

A leakage was observed during periodical testing of the core spray system at a valve aligned to the suction side of one of the core spray pumps, in the Emergency Core Cooling System. To repair the valve, the reactor was shut down. Inspection of the system revealed another leaking valve, an isolation valve, at the suction side of the same pump. During inspection of the other circuit of the core spray system it was detected that the corresponding valves were leaking there too.

Category: Power Reactor Barsebäck Sweden »

INES-event
INES 1

IMPENETRABILITY TEST OF CONTAINMENT NOT APPROVED

At the normal impenetrability test of containment at Barsebaeck 2 high leakage value was received.
A penetration testing plate was damaged due to corrosion.
The damage cause is under investigation.

Category: Power Reactor Barsebäck Sweden »