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14.7 - Fault and Protection Schedule - EDF Hinkley Point

14.7 - Fault and Protection Schedule - EDF Hinkley Point

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PRE-CONSTRUCTION SAFETY REPORT<br />

CHAPTER 14: DESIGN BASIS ANALYSIS<br />

SUB-CHAPTER : <strong>14.7</strong><br />

PAGE : 47 / 48<br />

Document ID.No.<br />

UKEPR-0002-149 Issue 02<br />

Action Defence line System<br />

RCP [RCS] depressurisation<br />

First line Normal <strong>and</strong> auxiliary spray<br />

Second line Pressuriser safety valves<br />

RCP [RCS] boration to ensure core First line Chemical <strong>and</strong> volume control system<br />

sub criticality<br />

Second line Extra boration system<br />

RCP [RCS] cooldown<br />

First line Main steam bypass<br />

Second line Main steam relief trains<br />

First line Residual heat removal system<br />

Long term residual heat removal<br />

Containment heat removal system<br />

Second line<br />

<strong>and</strong> direct safety injection<br />

Due to the absence of detailed EOPs, no additional detailed actions are presented (e.g.<br />

accumulator isolation, heaters cut-off, etc). The present analysis assumes that these actions are<br />

safely carried out. The containment of radioactive material is performed <strong>and</strong> ensured<br />

automatically, when necessary, while reaching the controlled state.<br />

The procedures use the available systems to perform these actions <strong>and</strong> the diverse means to<br />

reach the safe shutdown state is presented at the system level. Sub-chapter 3.2 provides<br />

information on the classification of the systems credited in the current analysis.<br />

Note: Class 1 manual actions with F1A architecture requirements are not required for the safe<br />

state. If they are provided to reach the safe state, it is due to their implementation in order to<br />

reach the controlled state in the following PCCs: Steam Line Break, Feedwater Line Break, <strong>and</strong><br />

pipework failure on a main cooling train (states A to F).

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