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A FRAMEWORK FOR SAFETY DECISIONMAKING GIVEN NEW SEISMIC HAZARD INFORMATION Annie Kammerer, Kevin Coppersmith, Nilesh Chokshi, Robert Budnitz INL Seismic RiskInformed Methodology Independent Review Panel SMiRT 23 August 2015
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Page 1: AFRAMEWORKFORSAFETY DECISION1MAKINGGIVENNEW ...anniekammerer.com/...53...Presentaition-SMiRT-23.pdf · Paper 53_kammerer_SHPRM Presentaition SMiRT 23.pptx Author: Annie Kammerer Created

A  FRAMEWORK  FOR  SAFETY  DECISION-­‐MAKING  GIVEN  NEW  SEISMIC  HAZARD  INFORMATION  

Annie  Kammerer,  Kevin  Coppersmith,  Nilesh  Chokshi,  Robert  Budnitz  INL  Seismic  Risk-­‐Informed  Methodology  Independent  Review  Panel  

SMiRT  23    August  2015  

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MoVvaVon  

¨  Earth  science  informaVon  conVnues  to  evolve  leading  to  the  need  for  a  process  for  reevaluaVon.  The  process  should  be  applicable  to  periodic  reevaluaVon,  as  well  as  to  the  assessment  of  new  informaVon.  The  process  must  be  risk-­‐informed  and  account  for  the  radiological  risk  of  the  facility.  ¤  NRC  Generic  Issue  199  and  resulVng  major  regional  studies  

n  Central  and  Eastern  US  Seismic  Source  CharacterizaVon  Study  n  Next  GeneraVon  A\enuaVon  RelaVonships  for  Eastern  North  America)  

¤  DOE  order  420.1C  requires  a  10-­‐year  reevaluaVon  process  ¤  NRC  Post-­‐Fukushima  50.54(f)  

n  Subsumed  GI-­‐199  and  also  incorporated  flooding  in  a  reevaluaVon  process  ¤  NRC  Near  Term  Task  Force  RecommendaVon  2.2  

n  Recommends  10-­‐year  periodic  reevaluaVon  n  SVll  under  review/development  

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Background  &  Overview  

¨  Developed  as  a  convergence  of  early  work  by  the  authors  focused  on  NPPs  and  a  new  project  for  re-­‐evaluaVon  of  INL  faciliVes  (SDC-­‐3)  

¨  Incorporates  a  graded  approach  using  Seismic  Design  Categories  ¨  Incorporates  periodic  reevaluaVon  requirements/guidance  

under  DOE  Order  420.1C  and  the  NRC  50.54(f)  process.  Can  also  be  used  as  a  framework  for  assessing  new  hazard  informaVon.  

¨   Incorporates  the  SSHAC  Process  with  appropriate  levels  ¨  Can  be  used  for  other  reevaluaVon  of  other  natural  hazards  ¨  Detailed  in  SMiRT  Paper:  “A  Framework  for  Safety  Decision  

Making  Given  New  Seismic  Hazard  InformaVon”  ¨  S"ll  a  work-­‐in-­‐progress.  The  figures  have  changed  since  the  

SMiRT  paper  was  wri<en.  

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Senior  Seismic  Hazard  Analysis  (SSHAC)  Process  

¨  Originally  described  in  NUREG/CR-­‐6372  (1989).  AddiVonal  guidance  provided  in  NUREG-­‐2117  (2012)  

¨  The  SSHAC  reports  described  a  structured  approach  for  incorporaVng  a  variety  of  data  types  and  expert  judgment  into  the  model  development  process  

¨  The  process  objecVve  is  to  develop  a  model  that  represents  the  center,  body,  and  range  of  the  technically  defensible  interpretaVons  within  a  composite  model  

¨  4  Levels  of  complexity  described  in  2  NUREG  reports  

¨  The  objecVves  are  the  same  regardless  of  SSHAC  Level  

NUREG/CR-6372 (1989)

NUREG 2117 (2012)

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SSHAC  Levels  

1

2

3

4

}  TI  confers  with  members  of  technical  community  to  understand  alternaVve  viewpoints  

}  Gather  data  and  informaVon  from  literature  }  TI  makes  assessments  including  uncertainty  

}  Expert  panel  responsible  for  making  technical  assessments  

}  TFI  facilitates  expert  interacVons  and  aggregates  expert  assessments  

}  Workshops  are  held  to  discuss:  ◦  Significant  issues  and  available  data  ◦  AlternaVve  hypotheses  ◦  Feedback  

}  ParVcipatory  peer  review  of  process  and  technical    }  TI  team  responsible  for  technical  assessments  

*The  above  roles  and  levels  are  described  in  detail  in  NUREG-­‐2117.  

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SSHAC  Levels  

1

2 }  TI  confers  with  members  of  technical  community  to  understand  alternaVve  viewpoints  

}  Gather  data  and  informaVon  from  literature  }  TI  makes  assessments  including  uncertainty  

•  Levels  1  and  2  are  simpler,  faster,  and  require  fewer  resources,  but  have  the  same  objecVves  as  Levels  3  and  4  in  terms  of  developing  models  that  capture  the  center,  body  and  range  of  the  technically  defensible  interpretaVons.    

•  Level  2  studies  are  currently  used  for  performing  site-­‐specific  enhancements  to  Level  3  regional  models  (like  the  CEUS  SSC).  

•  Level  1  and  2  studies  conducted  to  the  standards  outlined  in  the  SSHAC  Guidance  NUREGs  are  appropriate  for  assessing  whether  or  not  a  new  higher  level  study  is  required  and  for  providing  an  interim  esVmate  of  hazard.  

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3

4

}  Expert  panel  responsible  for  making  technical  assessments  

}  TFI  facilitates  expert  interacVons  and  aggregates  expert  assessments  

}  Workshops  are  held  to  discuss:  ◦  Significant  issues  and  available  data  ◦  AlternaVve  hypotheses  ◦  Feedback  

}  ParVcipatory  peer  review  of  process  and  technical    }  TI  team  responsible  for  technical  assessments  

•  Levels  3  and  4  are  used  for  new  faciliVes  and  major  modificaVons  to  exisVng  faciliVes.      

•  Level  3  is  proposed  for  use  if  it  is  determined  that  a  new  study  in  needed  under  the  DOE  Order.    

•  Level  3  is  far  more  widely  used  than  Level  4  in  US.  The  NRC  has  indicated  that  Levels  3  and  4  provide  similar  levels  of  regulatory  assurance  and  itself  conducts  Level  3  studies  jointly  with  DOE  and  EPRI.  

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7  Criteria  for  Assessing  Need  for  PSHA  Update  or  Follow  up  AcVons  

¨  7  criteria  were  developed  and  used  for  all  SDC  category  faciliVes  ¤  The  Vming  in  which  they  appear  in  the  process  differs  for  the  SDCs  to  account  for  the  level  of  radiological  risk  

¤  Criteria  #1  to  #4  come  directly  from  the  DOE  Order  and  its  supporVng  documents  and  look  at  changes  in  hazard  informaVon  

¤  Criteria  #  5  and  #6  use  informaVon  from  ASCE  43-­‐05  and  NRC  Regulatory  Guide  1.208.  Compares  the  design  basis  ground  moVon  (DBGM)  to  the  new  esVmates  of  hazard  from  a  SL1  or  SL2  and  the  resulVng  Ground  MoVon  Response  Spectrum  (GMRS)  n  The  DBGM  is  the  ground  moVon  to  which  the  plant  has  been  designed  and  is  maintained.  DBGM  is  called  “AuthorizaVon  Ground  MoVon”  in  DOE  faciliVes.  

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7  Criteria  for  Assessing  Need  for  PSHA  Update  or  Follow  up  AcVons  

¨  Criterion  #1:  New  data,  models,  and  methods  developed  since  the  exisVng  PSHA  

¨  Criterion  #2:  New  inputs  to  the  PSHA  model,  including  the  SSC,  GMC,  and  site  response  models  ¤  Includes  the  treatment  of  aleatory  and  epistemic  uncertainVes  ¤  Does  the  model  sVll  capture  the    center,  body,  and  range  of  technically-­‐defensible  interpretaVons  

¨  Criterion  #3:  Changes  in  the  technical  bases  ¤  Technical  arguments  and  jusVficaVons  for  the  hazard  inputs  and  the  associated  treatment  of  uncertainVes  

¨  Criterion  #4:  Significant  changes  in  mean  hazard  ¤  Need  to  consider  the  precision  or  “noise”  levels  of  hazard  calculaVons  

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SSHAC  Process  ObjecVve  

¨  “The  fundamental  goal  of  a  SSHAC  process  is  to  properly  carry  out  and  completely  document  the  acVviVes  of  evaluaVon  and  integraVon,  defined  as:  

¨  EvaluaVon:  The  consideraVon  of  the  complete  set  of  data,  models,  and  methods  proposed  by  the  larger  technical  community  that  are  relevant  to  the  hazard  analysis.  

¨  IntegraVon:  RepresenVng  the  center,  body,  and  range  of  technically  defensible  interpretaVons  in  light  of  the  evaluaVon  process  (i.e.,  informed  by  the  assessment  of  exisVng  data,  models,  and  methods).”  

 Quoted  from  NUREG  2117  

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7  Criteria  for  Assessing  Need  for  PSHA  Update  or  Follow  up  AcVons  

¨  Criterion  #5:  Compare  mean  hazard  at  the  annual  frequency  of  exceedance  (AFE)  for  specific  SDC  level  with  DBGM  

¨  Criterion  #6:  Compare  mean  hazard  at  AFE  for  specific  SDC  level  with  GMRS  ¤  Intended  to  ensure  meeVng  target  performance  goals  ¤ GMRS  includes  a  factor  to  account  for  slope  of  hazard  curve  ¤  ASCE  43-­‐05  and  RG  1.208  define  GMRS  consistently  

¨  Criterion  #7:  Risk  insights:  Compare  mean  risk  with  target  performance  goals  for  SDC  level;  compare  GMRS  with  HCLPF  capacity  

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SDC-­‐3  FaciliVes  

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For  SDC-­‐3  and  SDC-­‐4  and  FaciliVes  

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From

 DOE  Order  and

 supp

orVn

g  do

cumen

ts  

Provides  confident  basis  for  applying  the  methodology  

Intended  for  reevaluaVon  acVviVes  only  

DocumentaVon  requirements  if  no  new  data  model  or  methods  or  if  new  hazard  does  not  

exceed  DBGM  or  GMRS  

Comparison

 of  n

ew  

hazard  inform

aVon

 with

 de

sign  basis  and

 GMRS  

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SDC-­‐5  FaciliVes  

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SDC-­‐5  FaciliVes  

Consistent  with  50.54(f)  approach.  Recognizes  potenVal  impact  from  SDC-­‐5  

faciliVes  

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Thank  You  

QuesVons?