A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant

Sean S. Roshan, Weimin Ma, Tomasz Kozlowski, Truc Nam Dinh

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

On Tuesday the 25th of July 2006 at around 13:15, Forsmark-1 nuclear power plant experienced a loss of external power event, initiated by a short circuit in the offsite 400 kV switchyard. Due to voltage and frequency fluctuations that followed, together with additional component failures, two of the four auxiliary diesel generators did not start, causing loss of power in 2 of four redundant trains existing in the power plant. The loss of power in trains A&B resulted in reactor shutdown and abnormal intervention of safety systems. After 20 minutes, the water level inside the Reactor Pressure Vessel (RPV) decreased to 1,9 m above the reactor core, and the pressure inside the RPV decreased to 1,5 MPa. The aim of the present study is to evaluate the capabilities of U.S. NRC codes RELAPS and MELCOR to simulate the Forsmark-1 event, and then to reconstruct the sequence of the event based on the known behavior of the plant systems, such as activation of depressurization valves. To examine the safety margin, it is of interest to address "what if" questions related to this event, such as i) what if the operator would delay the recovery of the two failing diesel generators, and ii) what if all four diesel generators would fail. The results show that both RELAP5 and MELCOR codes are able to reproduce the system thermal-hydraulic behavior during such an event. The intervention of emergency cooling systems and effort of operators to start the remaining two auxiliary generators have prevented the core from becoming uncovered. The analysis also shows that even in case of failure of all four auxiliary generators, the timely action of the plan operator, as demonstrated in the action during the event, would prevent a core damage from occurring.

Original languageEnglish (US)
Title of host publicationSociete Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
Pages2642-2651
Number of pages10
StatePublished - Sep 26 2008
Externally publishedYes
EventSociete Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" - Nice, France
Duration: May 13 2007May 18 2007

Publication series

NameSociete Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
Volume4

Other

OtherSociete Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"
CountryFrance
CityNice
Period5/13/075/18/07

Fingerprint

Pressure vessels
Reactor shutdowns
Reactor cores
Water levels
Cooling systems
Security systems
Short circuit currents
Nuclear power plants
Power plants
Chemical activation
Hydraulics
Recovery
Electric potential
Hot Temperature

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Roshan, S. S., Ma, W., Kozlowski, T., & Dinh, T. N. (2008). A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant. In Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" (pp. 2642-2651). (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; Vol. 4).

A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant. / Roshan, Sean S.; Ma, Weimin; Kozlowski, Tomasz; Dinh, Truc Nam.

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 2008. p. 2642-2651 (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"; Vol. 4).

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Roshan, SS, Ma, W, Kozlowski, T & Dinh, TN 2008, A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant. in Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", vol. 4, pp. 2642-2651, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", Nice, France, 5/13/07.
Roshan SS, Ma W, Kozlowski T, Dinh TN. A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant. In Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 2008. p. 2642-2651. (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work").
Roshan, Sean S. ; Ma, Weimin ; Kozlowski, Tomasz ; Dinh, Truc Nam. / A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant. Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work". 2008. pp. 2642-2651 (Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work").
@inproceedings{62686ed51a464e3ca91c8338e63a1b69,
title = "A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant",
abstract = "On Tuesday the 25th of July 2006 at around 13:15, Forsmark-1 nuclear power plant experienced a loss of external power event, initiated by a short circuit in the offsite 400 kV switchyard. Due to voltage and frequency fluctuations that followed, together with additional component failures, two of the four auxiliary diesel generators did not start, causing loss of power in 2 of four redundant trains existing in the power plant. The loss of power in trains A&B resulted in reactor shutdown and abnormal intervention of safety systems. After 20 minutes, the water level inside the Reactor Pressure Vessel (RPV) decreased to 1,9 m above the reactor core, and the pressure inside the RPV decreased to 1,5 MPa. The aim of the present study is to evaluate the capabilities of U.S. NRC codes RELAPS and MELCOR to simulate the Forsmark-1 event, and then to reconstruct the sequence of the event based on the known behavior of the plant systems, such as activation of depressurization valves. To examine the safety margin, it is of interest to address {"}what if{"} questions related to this event, such as i) what if the operator would delay the recovery of the two failing diesel generators, and ii) what if all four diesel generators would fail. The results show that both RELAP5 and MELCOR codes are able to reproduce the system thermal-hydraulic behavior during such an event. The intervention of emergency cooling systems and effort of operators to start the remaining two auxiliary generators have prevented the core from becoming uncovered. The analysis also shows that even in case of failure of all four auxiliary generators, the timely action of the plan operator, as demonstrated in the action during the event, would prevent a core damage from occurring.",
author = "Roshan, {Sean S.} and Weimin Ma and Tomasz Kozlowski and Dinh, {Truc Nam}",
year = "2008",
month = "9",
day = "26",
language = "English (US)",
isbn = "9781604238716",
series = "Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, {"}The Nuclear Renaissance at Work{"}",
pages = "2642--2651",
booktitle = "Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, {"}The Nuclear Renaissance at Work{"}",

}

TY - GEN

T1 - A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant

AU - Roshan, Sean S.

AU - Ma, Weimin

AU - Kozlowski, Tomasz

AU - Dinh, Truc Nam

PY - 2008/9/26

Y1 - 2008/9/26

N2 - On Tuesday the 25th of July 2006 at around 13:15, Forsmark-1 nuclear power plant experienced a loss of external power event, initiated by a short circuit in the offsite 400 kV switchyard. Due to voltage and frequency fluctuations that followed, together with additional component failures, two of the four auxiliary diesel generators did not start, causing loss of power in 2 of four redundant trains existing in the power plant. The loss of power in trains A&B resulted in reactor shutdown and abnormal intervention of safety systems. After 20 minutes, the water level inside the Reactor Pressure Vessel (RPV) decreased to 1,9 m above the reactor core, and the pressure inside the RPV decreased to 1,5 MPa. The aim of the present study is to evaluate the capabilities of U.S. NRC codes RELAPS and MELCOR to simulate the Forsmark-1 event, and then to reconstruct the sequence of the event based on the known behavior of the plant systems, such as activation of depressurization valves. To examine the safety margin, it is of interest to address "what if" questions related to this event, such as i) what if the operator would delay the recovery of the two failing diesel generators, and ii) what if all four diesel generators would fail. The results show that both RELAP5 and MELCOR codes are able to reproduce the system thermal-hydraulic behavior during such an event. The intervention of emergency cooling systems and effort of operators to start the remaining two auxiliary generators have prevented the core from becoming uncovered. The analysis also shows that even in case of failure of all four auxiliary generators, the timely action of the plan operator, as demonstrated in the action during the event, would prevent a core damage from occurring.

AB - On Tuesday the 25th of July 2006 at around 13:15, Forsmark-1 nuclear power plant experienced a loss of external power event, initiated by a short circuit in the offsite 400 kV switchyard. Due to voltage and frequency fluctuations that followed, together with additional component failures, two of the four auxiliary diesel generators did not start, causing loss of power in 2 of four redundant trains existing in the power plant. The loss of power in trains A&B resulted in reactor shutdown and abnormal intervention of safety systems. After 20 minutes, the water level inside the Reactor Pressure Vessel (RPV) decreased to 1,9 m above the reactor core, and the pressure inside the RPV decreased to 1,5 MPa. The aim of the present study is to evaluate the capabilities of U.S. NRC codes RELAPS and MELCOR to simulate the Forsmark-1 event, and then to reconstruct the sequence of the event based on the known behavior of the plant systems, such as activation of depressurization valves. To examine the safety margin, it is of interest to address "what if" questions related to this event, such as i) what if the operator would delay the recovery of the two failing diesel generators, and ii) what if all four diesel generators would fail. The results show that both RELAP5 and MELCOR codes are able to reproduce the system thermal-hydraulic behavior during such an event. The intervention of emergency cooling systems and effort of operators to start the remaining two auxiliary generators have prevented the core from becoming uncovered. The analysis also shows that even in case of failure of all four auxiliary generators, the timely action of the plan operator, as demonstrated in the action during the event, would prevent a core damage from occurring.

UR - http://www.scopus.com/inward/record.url?scp=52249089150&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=52249089150&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:52249089150

SN - 9781604238716

T3 - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

SP - 2642

EP - 2651

BT - Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

ER -