V-1 safety analysis reports
safety analysis report
The initial safety analysis report was drafted in 1978 as a document entitled “NPP
V-1 Pre-Operation Safety Report“. Its structure and contents accounted for the
requirements of the amended version of the document „Guidelines for the Setting up and
Contents of Safety Reports“ issued by ČSKAE in 1977, extended by the following
- Principal Criteria
- Operation Limits and Conditions for NPP V-1 unit 1.
Later amendments to the initial Pre-Operation Safety Analysis Report
An amendment was made in 1990 to replace the chapter „Safety Analyses“ of the initial
report, due to the existence of more modern computer codes and in connection with some
changes in „opinions“ concerning approaches to nuclear safety. Within the amendment,
chapters were drafted to replace chapter V „Safety Analyses“.
In connection with the „small“ reconstruction of NPP V-1 units in preparation, a
solution was adopted according to which no other chapters of the initial 1978 Safety
Report were rewritten.
Upgrading of NPP V-1 units (so-called „small reconstruction“) was performed based on
ČSKAE decisions Nos. 5/91 and 213/92. As a result of the above mentioned upgrading, some
chapters concerning safety analyses of the NPP V-1 Safety Report issued in 1990 had to be
amended. This amendment to the chapter „Safety Analyses“ was done by VÚJE in 1993.
A safety analysis report for gradual upgrading of NPP Bohunice V-1 has been placed in
Safety Analysis Report after the gradual upgrading
Within the project preparations for the gradual upgrading of NPP V-1, the extent of the
amendment to the Safety Report due to the extent of the gradual upgrading was reassessed,
resulting in the decision to prepare a new Safety Analysis Report as a whole under the
title „NPP V-1 Safety Report after Gradual Upgrading“. In clarifying the structure of
the Report, it was decided and approved by ÚJD that base the new Report will follow the
structure of the NRC Guideline 1.70, updated based on specific conditions prevailing at
NPP V-1, while accounting for the applicable IAEA Guidelines and regulations for safety
reviews of WWER units.
The objective was to prepare the NPP V-1 SAR to account for any changes in the
technological systems implemented both during the previous operation and during the
„gradual upgrading“. In doing this, safety analyses were required to meet all the
requirements of the guidelines for the conduction of safety analyses for power plants
operating WWER reactors with respect to both the range of initiating events and the
approach to the solution and use of programme codes. The structure of the Safety Report is
comparable with that of the NPP V-2 Safety Report.
The objectives of the individual chapters remained preserved, although the contents of
some parts were adjusted and updated for the conditions of NPP V-1 since the Guideline RG
1.70 has been intended for the drafting of the safety report of new NPPs in the legal
environment of the US.
Any principal deviations from the Guidelines RG 1.70 arise from the guidelines developed
and issued by IAEA and ÚJD after 1993, thus accounting for the most recent level of
knowledge and approaches to analyses, and approaches and taking into account also the
specifics of WWER-440 reactor units.