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Responding to Fukushima:

Real-time, Interactive, Beyond Design Basis Modeling
for SAMG, PRA and Training

info@gses.com
Outline
I. Industry changes, drivers, challenges
II. Desktop simulator
III.Examples of PWR and BWR
IV. Applications and Flexibility
V. Conclusions

2
Changes Affecting Training
• Emergency response organization (ERO) staffing
changes
• Knowledge, skills and proficiency requirements

• Severe accident management guideline (SAMG)
changes
• Extensive damage mitigation guideline (EDMG)
changes

3
Change Drivers
• Post-9/11 revisions to NUREGs/FEMA REP
• Post-Fukushima initiatives
– NEI 12-01 – Guideline for assessing beyond design basis
accident response staffing and communications capabilities

– NEI 12-06 – Diverse and flexible coping strategies (FLEX)
implementation guide

– INPO IER 13-10 – Nuclear accident at the Fukushima Daiichi
nuclear power station

– US NRC SECY-11-0124 - “Recommended actions to be taken
without delay from the near-term task force report”

4
Challenges for Industry
• Near-term challenges
– Develop, write, train and drill on new SAMG/EDMG
processes and procedures
– Install, maintain, train and drill on FLEX equipment
– Increase in number of staff needing training/drills
– Multiple-unit scenarios with single-unit simulators
– More challenging PRA/PSA

• Long-term challenges
– SBO and beyond DBA scenarios
– Limited simulator capabilities
– Integrated training of NOP, EOP, SAMG and EDMG

5
GSE Desktop Simulator
• Used by EPRI and ERIN Engineering to demonstrate
capability of MAAP5 computer code “Modular Accident
Analysis Program”
• Users easily interact with equipment controls and code
models through modern human-machine interface
• Interface with plant DOSE model to project offsite DOSE
• Users visually observe the event unfolding via graphical
depiction of scenarios

6
GSE Desktop Simulator
• Take plant data and run myriad SAMG/EDMG scenarios

• Simulate parallel events in multiple units
• Provide “what if” analysis of user-interactive actions and
resulting consequences
• Provide interactive access to all model internal variables
• Assist with verification/validation of results against plant
data
• Collect, assimilate and report a large amount of data

7
PWR with 2 Units and Spent Fuel
Ex-plant DOSE
simulation
MAAP5

In-plant
DOSE simulation

In-plant
DOSE simulation

Unit 2
Containment
MAAP5

Unit 1
Containment
MAAP5

SG
MAAP5

RCS
MAAP5

Core

Auxiliary
Building
MAAP5
Spent Fuel Pool

RCS
MAAP5

SG
MAAP5

Core

8
Reactor Core

Unit 1

Time 4:2:56

Unit 2
9
Containment and Flammability

Time 4:2:56
10
Off-Site Radiological Dose

Time 6:20:06
11
Multi-Unit Displays

12
Vessel Failure – Unit 1

13
Core Melt – Unit 2

14
Core Melt – Unit 3

15
Applications
Can be:
–
–
–
–

Run as stand-alone machine for individual use
Synched with other desktop simulators
Controlled/managed by an instructor
Used for training as individuals or teams

16
Flexibility and Growth
• Can add additional modules, such as:
–
–
–
–
–
–

Balance of plant
ECCS
Electrical
Main steam
Main feed water
MIDAS, RASCAL

• Advanced 3D visualizations coupled with simulation
models can be added to inform the user of conditions
inside containment and reactor during severe accident
scenarios
• Can integrate with your simulator

17
Conclusions
• Provides cost saving and lessens burden imposed by
regulations
• Allows frequent and realistic training
• Uses the most advanced analysis models as daily
training tools
• Backed and supported by reputable engineering/simulator
teams
• Streamlines data communications

18
Conclusions
• Prepares personnel
– Supports operational decision making to support
transient analysis

• Supports development and implementation of
challenging and realistic drills
• Does not require plant simulator time
• Supports remote training

19
EPRI MAAP Code
•

''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program
that performs severe accident analysis for nuclear power plants including
assessments of core damage and radiological transport. A valid license to
MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a
customer being able to use MAAP 5.0 with [LICENSEE PRODUCT].

•

EPRI (www.epri.com) conducts research and development relating to the
generation, delivery and use of electricity for the benefit of the public. An
independent, nonprofit organization, EPRI brings together its scientists
and engineers as well as experts from academia and industry to help
address challenges in electricity, including reliability, efficiency, health,
safety and the environment. EPRI does not endorse products or services,
and specifically does not endorse [NEW PRODUCT NAME] or GSE.
Interested vendors may contact EPRI for a license to MAAP 5.0."

20
GSE Systems, Inc.

Thank you!

21
For more information:
Go to:

www.GSES.com

Follow us on:

Call:

800.638.7912

Twitter @GSESystems

Email:

info@gses.com

Facebook.com/GSESystems

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Responding to Fukushima: Real-Time, Interactive, Beyond Design Basis Modeling for SAMG, PRA and Training

  • 1. Responding to Fukushima: Real-time, Interactive, Beyond Design Basis Modeling for SAMG, PRA and Training info@gses.com
  • 2. Outline I. Industry changes, drivers, challenges II. Desktop simulator III.Examples of PWR and BWR IV. Applications and Flexibility V. Conclusions 2
  • 3. Changes Affecting Training • Emergency response organization (ERO) staffing changes • Knowledge, skills and proficiency requirements • Severe accident management guideline (SAMG) changes • Extensive damage mitigation guideline (EDMG) changes 3
  • 4. Change Drivers • Post-9/11 revisions to NUREGs/FEMA REP • Post-Fukushima initiatives – NEI 12-01 – Guideline for assessing beyond design basis accident response staffing and communications capabilities – NEI 12-06 – Diverse and flexible coping strategies (FLEX) implementation guide – INPO IER 13-10 – Nuclear accident at the Fukushima Daiichi nuclear power station – US NRC SECY-11-0124 - “Recommended actions to be taken without delay from the near-term task force report” 4
  • 5. Challenges for Industry • Near-term challenges – Develop, write, train and drill on new SAMG/EDMG processes and procedures – Install, maintain, train and drill on FLEX equipment – Increase in number of staff needing training/drills – Multiple-unit scenarios with single-unit simulators – More challenging PRA/PSA • Long-term challenges – SBO and beyond DBA scenarios – Limited simulator capabilities – Integrated training of NOP, EOP, SAMG and EDMG 5
  • 6. GSE Desktop Simulator • Used by EPRI and ERIN Engineering to demonstrate capability of MAAP5 computer code “Modular Accident Analysis Program” • Users easily interact with equipment controls and code models through modern human-machine interface • Interface with plant DOSE model to project offsite DOSE • Users visually observe the event unfolding via graphical depiction of scenarios 6
  • 7. GSE Desktop Simulator • Take plant data and run myriad SAMG/EDMG scenarios • Simulate parallel events in multiple units • Provide “what if” analysis of user-interactive actions and resulting consequences • Provide interactive access to all model internal variables • Assist with verification/validation of results against plant data • Collect, assimilate and report a large amount of data 7
  • 8. PWR with 2 Units and Spent Fuel Ex-plant DOSE simulation MAAP5 In-plant DOSE simulation In-plant DOSE simulation Unit 2 Containment MAAP5 Unit 1 Containment MAAP5 SG MAAP5 RCS MAAP5 Core Auxiliary Building MAAP5 Spent Fuel Pool RCS MAAP5 SG MAAP5 Core 8
  • 9. Reactor Core Unit 1 Time 4:2:56 Unit 2 9
  • 13. Vessel Failure – Unit 1 13
  • 14. Core Melt – Unit 2 14
  • 15. Core Melt – Unit 3 15
  • 16. Applications Can be: – – – – Run as stand-alone machine for individual use Synched with other desktop simulators Controlled/managed by an instructor Used for training as individuals or teams 16
  • 17. Flexibility and Growth • Can add additional modules, such as: – – – – – – Balance of plant ECCS Electrical Main steam Main feed water MIDAS, RASCAL • Advanced 3D visualizations coupled with simulation models can be added to inform the user of conditions inside containment and reactor during severe accident scenarios • Can integrate with your simulator 17
  • 18. Conclusions • Provides cost saving and lessens burden imposed by regulations • Allows frequent and realistic training • Uses the most advanced analysis models as daily training tools • Backed and supported by reputable engineering/simulator teams • Streamlines data communications 18
  • 19. Conclusions • Prepares personnel – Supports operational decision making to support transient analysis • Supports development and implementation of challenging and realistic drills • Does not require plant simulator time • Supports remote training 19
  • 20. EPRI MAAP Code • ''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program that performs severe accident analysis for nuclear power plants including assessments of core damage and radiological transport. A valid license to MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a customer being able to use MAAP 5.0 with [LICENSEE PRODUCT]. • EPRI (www.epri.com) conducts research and development relating to the generation, delivery and use of electricity for the benefit of the public. An independent, nonprofit organization, EPRI brings together its scientists and engineers as well as experts from academia and industry to help address challenges in electricity, including reliability, efficiency, health, safety and the environment. EPRI does not endorse products or services, and specifically does not endorse [NEW PRODUCT NAME] or GSE. Interested vendors may contact EPRI for a license to MAAP 5.0." 20
  • 22. For more information: Go to: www.GSES.com Follow us on: Call: 800.638.7912 Twitter @GSESystems Email: info@gses.com Facebook.com/GSESystems

Editor's Notes

  1. Tier 1Recommendations that should be started without unnecessary delay and for which the agency already has enough resources (such as staff with proper skills).Tier 2Recommendations that had to wait for factors such as further technical assessment, resolution of Tier 1 issues, or availability of critical staff skills.Tier 3Recommendations that require further staff study to support a regulatory action, rely on resolution of a higher-tier action, are dependent on critical skill sets, or depend on the NRC’s actions on the first recommendation.
  2. Tier 1Recommendations that should be started without unnecessary delay and for which the agency already has enough resources (such as staff with proper skills).Tier 2Recommendations that had to wait for factors such as further technical assessment, resolution of Tier 1 issues, or availability of critical staff skills.Tier 3Recommendations that require further staff study to support a regulatory action, rely on resolution of a higher-tier action, are dependent on critical skill sets, or depend on the NRC’s actions on the first recommendation.
  3. demo case was applied to both desktop psa-hd & full-scope simulator PSA-HD.Desktop PSA-HD does not include S3R & BOP. Has successfully run the different transient for 32 hours.Full-scope PSA-HD has interfaces built-in and integrated with full-scope simulator. Has successfully run LOCA for more than 8 hours.
  4. 3-D like modern GUI for PSA-HD. Much better illustration to the real nuclear plant condition. Details and scales are preserved to give correct impression to the operator & code users.
  5. 3-D like modern GUI for PSA-HD. Much better illustration to the real nuclear plant condition. Details and scales are preserved to give correct impression to the operator & code users.
  6. This is an example that how ex-plant dose could be displayed.Max 10 calculation points can be modeled in maap code.Plume dispersion in atmosphere can be modeled in maap.Rain, wind as well as building blocking can be taken into consideration.Max 10 calculation points can be modeled in maap code.