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NUCLEAR OPERATING SAFETY: CONTRASTING RESULTS<br />

<strong>on</strong> the Internati<strong>on</strong>al <strong>Nuclear</strong> Event Scale in 2012. This also<br />

decreased to 0.8 per reactor <strong>and</strong> is now lower that for<br />

the French plants. The events corresp<strong>on</strong>ding to violati<strong>on</strong>s<br />

of the technical specificati<strong>on</strong>s for operati<strong>on</strong> substantially<br />

increased (1.67 per reactor), partly due to the way in which<br />

such events are defined to facilitate comparis<strong>on</strong> with the<br />

results of the French plants. I note that, faced with this<br />

deteriorati<strong>on</strong>, <strong>EDF</strong> Energy NG has mobilised an inspecti<strong>on</strong><br />

team to determine the exact causes. The first indicati<strong>on</strong>s<br />

point to the increasing difficulty with procedure adherence<br />

(compliance with process rules) c<strong>on</strong>firming the necessity -<br />

also in the UK - to simplify procedures wherever possible<br />

so the professi<strong>on</strong> of nuclear operator is made easier.<br />

Plant alignment errors were also the subject of the same<br />

initiative <strong>and</strong> I will make a point of having progress<br />

reported to me during my visits to these plants in 2013.<br />

At <strong>EDF</strong> Energy, automatic scrams need to be c<strong>on</strong>sidered<br />

with manual reactor trips as the British procedures more<br />

frequently require the operators to manually trip the<br />

reactor before the automatic functi<strong>on</strong>s operate. The 2012<br />

results show progress (1.48), but are still too far from the<br />

best internati<strong>on</strong>al levels.<br />

As c<strong>on</strong>cerns fire, the increase in the number of outbreaks,<br />

even though minor, c<strong>on</strong>firms that fire hazards need to be<br />

the subject of increasing vigilance <strong>and</strong> determined acti<strong>on</strong>.<br />

During my visits to the plants, I found that the c<strong>on</strong>diti<strong>on</strong> of<br />

the fire protecti<strong>on</strong> systems could be improved <strong>and</strong> noted<br />

that there was a management alert (an internal oversight<br />

Level 2 Advice) <strong>on</strong> <strong>on</strong>e of them. I already pointed out in<br />

2011 that the WANO peer reviews had been finding the<br />

level of fire preventi<strong>on</strong> to be insufficient for a number of<br />

years. The corporate peer review carried out by WANO<br />

at <strong>EDF</strong> Energy in October 2012 reiterated this point. I am<br />

happy to see that the comparis<strong>on</strong> was launched in 2012<br />

with the French plants <strong>and</strong> is focusing <strong>on</strong> the state of fire<br />

protecti<strong>on</strong> systems to properly address the needs.<br />

I would like to emphasise the good levels of availability<br />

of the engineered safety features in the Advanced Gascooled<br />

Reactor plants with unplanned capacity loss factors<br />

of 0.3%, 0.1% <strong>and</strong> 0.3% respectively (WANO indicators)<br />

<strong>and</strong> the excepti<strong>on</strong>al results for the Sizewell B pressurised<br />

water reactor for which the unplanned capacity loss factor<br />

for these safety systems has been zero for a number of<br />

years. This year, I also observe a reducti<strong>on</strong> in the forced<br />

loss rate (units in service) that has been reduced to 8.9%<br />

(compared with more than 19% in 2010).<br />

Finally, I would like to draw attenti<strong>on</strong> to the improved<br />

operating results for the fuel route machines of the<br />

advanced gas-cooled reactors, which have a close<br />

correlati<strong>on</strong> with nuclear safety. The significant progress,<br />

c<strong>on</strong>firmed in 2012, has resulted from the effective use of<br />

a composite performance indicator <strong>and</strong> the c<strong>on</strong>siderable<br />

work performed by the staff.<br />

THE INSPECTOR GENERAL’S REPORT<br />

ON NUCLEAR SAFETY AND RADIATION PROTECTION<br />

In the C<strong>on</strong>stellati<strong>on</strong> Energy <strong>Nuclear</strong> Group<br />

plants<br />

The number of significant nuclear safety events declared<br />

by C<strong>on</strong>stellati<strong>on</strong> <strong>Nuclear</strong> Energy Group (CENG) remained<br />

stable at close to 11 per reactor in 2012, the declarati<strong>on</strong><br />

rules being different in the USA where INPO h<strong>and</strong>les filing<br />

<strong>and</strong> analysis.<br />

N<strong>on</strong>e of the events graded <strong>on</strong> the INES exceeded Level 1 in<br />

2012, the factor slightly increasing to 0.8 per reactor.<br />

At CENG, as at <strong>EDF</strong> Energy, it is necessary to c<strong>on</strong>sider<br />

scrams combined with manual reactor trips as the<br />

American procedures more frequently require the<br />

operators to manually trip the reactor before automatic<br />

functi<strong>on</strong>s operate. The results for 2012 represented a slight<br />

deteriorati<strong>on</strong> (0.87 per reactor), far from the achievements<br />

of the period between 2006 <strong>and</strong> 2009. The results differed<br />

c<strong>on</strong>siderably between the Calvert Cliffs, Ginna <strong>and</strong> Nine<br />

Mile Isl<strong>and</strong> plants.<br />

I would like to draw attenti<strong>on</strong> to the capacity loss factors<br />

for the engineered safety functi<strong>on</strong>s c<strong>on</strong>sisting of the safety<br />

injecti<strong>on</strong> system (0.2 to 0.45% depending <strong>on</strong> the plant), the<br />

auxiliary feedwater system (0.1 to 0.9%) <strong>and</strong> the st<strong>and</strong>by<br />

diesel generators (0.7 to 1.5%). Although these results are<br />

broadly comparable to those of the other reactors in the<br />

USA, they are well below European levels (by a factor of<br />

5 to 10). I am left w<strong>on</strong>dering about the appropriateness<br />

of operating modes for equipment so important for safety<br />

such as the st<strong>and</strong>by diesel generators, <strong>and</strong> I commend the<br />

acti<strong>on</strong> recently begun by INPO to make progress in this area.<br />

I note the good forced loss rate (units in service) for 2012<br />

for the three pressurised water reactors at around 1.5%.<br />

However, with an average factor of 3.1%, the CENG<br />

reactor results are in the lower half when compared with<br />

those of other American operators <strong>and</strong> vigilance is required.<br />

Although the combined unplanned capacity loss factor<br />

covering units in service <strong>and</strong> outage extensi<strong>on</strong> is very low<br />

compared with the figure for the French installati<strong>on</strong>s with<br />

different operating c<strong>on</strong>diti<strong>on</strong>s, they have been worsening<br />

slightly over the last five years. I would like to <strong>on</strong>ce again<br />

emphasise the positive effect <strong>on</strong> nuclear safety, for the<br />

entire group, of such a capacity level with as few unit outage<br />

extensi<strong>on</strong>s <strong>and</strong> hence disturbances for the operators.<br />

I would also like to point out the existence of chemistry <strong>and</strong><br />

fuel indicators which are given the same importance by the<br />

plant managers as the above.<br />

Finally, I am pleased to see the role played by INPO which<br />

is challenging plants <strong>on</strong> their performance levels <strong>and</strong><br />

setting in place an effective benchmarking system. I must<br />

highlight the significant number of indicators for the<br />

CENG nuclear units which are in the INPO last quartile.<br />

13

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