scholarly journals Joint US/Russian study on the development of a decommissioning strategy plan for RBMK-1000 unit No. 1 at the Leningrad Nuclear Power Plant

1997 ◽  
Author(s):  
1982 ◽  
Vol 52 (2) ◽  
pp. 141-144
Author(s):  
V. M. Sedov ◽  
P. G. Krutikov ◽  
N. V. Nemirov ◽  
S. T. Zolotukhin ◽  
A. V. Devochkin ◽  
...  

2000 ◽  
Author(s):  
Garill Coles ◽  
Sam McKay ◽  
Jon Young ◽  
Yuri Skok

Abstract Engineering assessment that supports the safety basis for a reactor plant operating license is defined as: “An assessment of a system to determine its adequacy to successfully perform its safety-related function(s) when required.” The approach to engineering assessment of systems at the Leningrad Nuclear Power Plant (LNPP), as part of its in-depth safety assessment (ISA), is unique. The content and format of engineering assessments for western Safety Analysis Reports (SARs) have evolved over time and current requirements are somewhat scattered in the governing documents (USNRC, 1978). Many regulatory guides and requirements (western or eastern) have not kept up with changes in safety analysis technology. Performance of the ISA for LNPP affords the opportunity to rethink the approach to engineering assessments, and to incorporate current methods and latest technology in safety analysis. As an example, for many systems, information about system reliability obtained from a modem Probabilistic Safety Assessment is more comprehensive than that from a Single Failure Analysis as prescribed in SAR content and format guides. Overall, the engineering assessment of LNPP systems looks at five major assessment elements: 1) assessment of regulatory compliance, 2) assessment of operability, 3) assessment of vulnerability, 4) assessment of environmental qualifications, and 5) assessment of reliability. By reorganizing the approach to meeting regulatory requirements, and by looking at engineering assessment in various ways, information can be obtained that goes beyond simply demonstrating regulatory compliance to more fully supporting the safety basis for a plant operating license.


Atomic Energy ◽  
1999 ◽  
Vol 87 (2) ◽  
pp. 565-568
Author(s):  
V. I. Lebedev ◽  
Yu. V. Garusov ◽  
A. V. Makushkin ◽  
Yu. G. Skok ◽  
S. V. Kukhar ◽  
...  

2000 ◽  
Vol 36 (2) ◽  
pp. 97-107 ◽  
Author(s):  
V.G Artemov ◽  
A.V Elshin ◽  
A.S Ivanov ◽  
A.N Pimenov ◽  
V.G Shevchenko

2017 ◽  
Vol 42 (2) ◽  
pp. 113-120
Author(s):  
A. A. Apukhtin ◽  
G. N. Bessan ◽  
S. M. Gordeeva ◽  
M. K. Klevannaya ◽  
K. A. Klevannyy

Author(s):  
Alexandr Matveev ◽  
I Popivchak

Appropriate protective measures are required to ensure the evacuation of staff to a safe area under the conditions of a potential impact on a nuclear power plant by dangerous fire factors. The article analyzes possible fire scenarios in one of the buildings of the Leningrad nuclear power plant. An approach to assessing the effectiveness of the use of protective equipment for nuclear power plant personnel during a fire is considered.


Atomic Energy ◽  
2003 ◽  
Vol 95 (3) ◽  
pp. 591-596 ◽  
Author(s):  
B. K. Bylkin ◽  
V. A. Shaposhnikov ◽  
Yu. K. Sadovoi ◽  
V. L. Tikhonovskii

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