atw 2018-05v6
You also want an ePaper? Increase the reach of your titles
YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.
<strong>atw</strong> Vol. 63 (<strong>2018</strong>) | Issue 5 ı May<br />
OPERATION AND NEW BUILD 300<br />
(currently revised due to new<br />
Atomic Law).<br />
• UJV, Proposal of Methodological<br />
Procedure for Performing of Safety<br />
Analysis of Beyond Design Basis<br />
Accident, UJV Rez, 2010.<br />
Analyses of DEC-A scenarios use the<br />
best estimate computer codes with<br />
combination of realistic initial and<br />
conservative (or realistic) boundary<br />
conditions. The robust design of VVER<br />
reactors and their safety features<br />
enable to fulfil DBA acceptance<br />
criteria in most DEC-A cases including<br />
radiological consequences. For the<br />
most severe conditions comprising<br />
multiple failures of safety systems or<br />
safety groups providing protection in<br />
the level 3a of Defense in Depth (like<br />
SBO), the new measures imple mented<br />
after post-Fukushima Stress tests in<br />
the level 3b of the DiD provide an<br />
additional robust protection against<br />
the evolution of these scenarios into<br />
the DEC-B category (severe accident).<br />
The acceptance criteria applied to<br />
DEC-A analyses are identical to those<br />
applied to DBA analysis with exception<br />
of criterion on primary and<br />
secondary pressure and radiological<br />
consequences.<br />
The computer code used for NPP<br />
safety analyses in the Czech Republic<br />
must be approved by the regulatory<br />
body according to the SUJB directive<br />
VDS-030.<br />
2.2 Selection of DEC-A events<br />
to be analysed and<br />
documented in SAR<br />
The basic set of DEC-A (BDBA) events<br />
to be analyzed is specified in<br />
BN-JB-1.7 0. Supplemental events<br />
and scenarios could be specified by<br />
PSA outcomes and engineering<br />
judgement.<br />
It is important to mention that in<br />
analyses of DEC (which are often<br />
complex sequences or combinations<br />
of events and failures) it is logical to<br />
transfer from “frequency of initial<br />
events” to “frequency of occurrence of<br />
scenarios”.<br />
The SUJB directive BN-JB-1.7 0<br />
requires besides the standard set of<br />
ATWS analyses, the following DEC-A<br />
(BDBA) events to be analyzed:<br />
• Total long-term loss of inner and<br />
outer AC power sources;<br />
• Total long-term loss of feed water<br />
(„feed-and-bleed„ procedure);<br />
• LOCA combined with the loss of<br />
ECCS;<br />
• Uncontrolled reactor level drop or<br />
loss of circulation in regime with<br />
open reactor or during refueling;<br />
• Total loss of the component cooling<br />
water system;<br />
• Loss of residual heat removal<br />
system;<br />
• Loss of cooling of spent fuel pool;<br />
• Loss of ultimate heat sink (from<br />
secondary circuit);<br />
• Uncontrolled boron dilution;<br />
• Multiple steam generator tube<br />
rupture;<br />
• Steam generator tube ruptures<br />
induced by main steam line break<br />
(MSLB);<br />
• Loss of required safety systems in<br />
the long term after a design basis<br />
accident.<br />
The whole set of prescribed DEC-A<br />
analyses was already performed both<br />
for Dukovany NPP (VVER-440) and<br />
for Temelín NPP (VVER-1000).<br />
Analyses of DEC-A events for the<br />
Czech NPP’s have been performed<br />
with the RELAP5 computer code. It is<br />
worth noting that the RELAP5 has<br />
been in the UJV Rez validated against<br />
experimental data from more than 20<br />
tests carried out at various integral<br />
test facilities (ITF) and that approximately<br />
half of these tests were modelling<br />
events of the DEC-A type.<br />
2.3 Example of DEC-A analysis:<br />
SBLOCA in VVER-1000 with<br />
failure of ECCS and operator<br />
start of HPSI at 30 min<br />
The analysis of a small break loss<br />
of coolant accident (SBLOCA) with<br />
the break D50 mm in the cold leg<br />
and with a failure of the start of<br />
emergency core cooling systems<br />
(ECCS) and operator manual start of<br />
high pressure safety injection (HPSI)<br />
at 30 min was performed for the<br />
| | Fig. 1.<br />
Nodalization scheme of VVER-1000 for RELAP5 (only primary circuit and 1 of 4 modeled loops depicted).<br />
Operation and New Build<br />
Continuous Process of Safety Enhancement in Operation of Czech VVER Units ı J. Duspiva, E. Hofmann, J. Holy, P. Kral and M. Patrik