31
www.inl.gov Application of the Seismic Hazard Periodic Reevaluation Methodology Using a SSHAC Level 1 Study at the Idaho National Laboratory Suzette Payne, Idaho National Laboratory Kevin Coppersmith, Coppersmith Consulting, Inc. Ryan Coppersmith, Coppersmith Consulting, Inc. Valentina Montaldo Falero, Wood. Robert Youngs, Wood. Adrian Rodriguez-Marek, Virginia Tech Walt Silva, Pacific Engineering and Analysis November 16, 2017 –Seismic Lessons Learned DOE Meeting

Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

  • Upload
    others

  • View
    3

  • Download
    0

Embed Size (px)

Citation preview

Page 1: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

ww

w.in

l.govApplication of the Seismic Hazard Periodic Reevaluation Methodology Using a SSHAC Level 1 Study at the Idaho National Laboratory

Suzette Payne, Idaho National LaboratoryKevin Coppersmith, Coppersmith Consulting, Inc.Ryan Coppersmith, Coppersmith Consulting, Inc.Valentina Montaldo Falero, Wood.Robert Youngs, Wood.Adrian Rodriguez-Marek, Virginia Tech Walt Silva, Pacific Engineering and Analysis

November 16, 2017 –Seismic Lessons Learned DOE Meeting

Page 2: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Presentation Overview• INL Seismic Risk Assessment (SRA) Project and

candidate existing nuclear facility• Implementation of SSHAC Level 1 PSHA study at INL• Application of the Seismic Hazard Periodic Reevaluation

Methodology (SHPRM) evaluation process for SDC-3– Emphasis on the approaches used to identify changes

in hazard– Results of SSHAC Level 1 study as inputs

• Outcome of the SHPRM implementation• Lessons Learned

PSHA – Probabilistic Seismic Hazard AnalysisSSHAC – Senior Seismic Hazard Analysis Committee

Page 3: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

INL Seismic Risk Assessment (SRA) Project• Developed and implemented the Seismic Hazard Periodic

Reevaluation Methodology (or SHPRM)• Selected a SSHAC Level 1 PSHA to produce:

– Mean-centered definition of the seismic hazard with appropriate treatment of uncertainties and technical justification

– Defensible, well-documented basis to make comparisons with the existing technical underpinnings of the current seismic design basis for the existing nuclear facility of interest

• Implemented the SHPRM to determine if the existing INL PSHA needed to be updated

• Selected the Fuels Manufacturing Facility (FMF) as the candidate existing nuclear facility

Page 4: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Fuels Manufacturing Facility (FMF)

Classified as SDC-3 with a Hazard Exceedance Probability of 4x10-4

Located at the Materials and Fuels Complex (MFC)

Page 5: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

FMF Information and Design Basis Ground Motion (DBGM)

DBE – Design Basis EarthquakePC – Performance Category

SiteConditions

Structure, System, &

Component

Frequency Range of

Significance (Hz)

BaselinePSHA(year)

AuthorizationSafetyBasis

5-15 ft Soil overlying

basalt rock

1-Story structure (104 ft x 50 ft)covered by earthen berm

6 to 9 Hz 1996PC-3 Soil

DBE at 2,500 yr

Risk Objective: Demonstrate adequate safety against a seismically-induced collapse of the FMF structure which leads to release of nuclear material

Page 6: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

INL SSHAC Level 1 Study Had the 5 Required Attributes1. Cleary defined roles and responsibilities for participants2. Objective evaluation of available data, models, and

methods3. The outcome of the evaluation process was integrated

into SSC and GMC models that reflected both the best estimate and the associated uncertainty

4. Thoroughly documented study including database, evaluation and integration processes, hazard inputs, and peer review

5. Technical and procedural reviews throughout the entire study performed by a Participatory Peer Review Panel (PPRP)

GMC - Ground Motion CharacterizationSSC - Seismic Source Characterization

Page 7: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Features of INL SSHAC L1 Study• Work Plan defined and scheduled key tasks and activities

– Developed at 3-day kick-off meeting held at INL and issued in 3 weeks– Involved the Technical Integration (TI) Team and PPRP– All attended a 1-day field trip at INL

• Project SharePoint site setup for the database and to exchange files and work on documents

• TI Team and PPRP held conference calls every 3-4 weeks (7 calls)

• On-site review and presentation of preliminary hazard to the SRA project and PPRP

• SSHAC Level 1 study for FMF was completed in 10 months

Page 8: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

DNFSB - Defense Nuclear Facilities Safety BoardDOE - US Department of EnergyPRA – Probabilistic Risk Assessment

INL SSHAC Level 1 Organization & Participants

Page 9: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Participatory Peer Review Panel• Two-member panel provided technical and procedural

reviews from start to finish• Technical reviews ensured:

– Full range of data, models, and methods were considered– Captured the center, body, and range of technically defensible

interpretations – Technical decisions were adequately justified– Hazard Input Document (HID) was complete and adequate for the

PSHA calculations

• Procedural reviews ensured:– Work Plan was implemented– TI Team addressed issues and implemented recommendations that

were identified during conference calls – INL SSHAC Level 1 PSHA conformed to the SSHAC process

• Concurrence provided through a PPRP Closure Letter

Page 10: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

CBR – Center, Body and RangeTDI – Technically Defensible Interpretations

INL SSHAC Level 1 Work Flow Process

Modified from NUREG-2213

Compiled project databaseSSC Data summary tableNo interactions with experts

Produced preliminary hazardReceived feedback from PPRP

Prepared SSC and GMC HIDs

SSHAC Level 1 Report included inputs to SHPRM

Page 11: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

INL SSHAC Level 1 PSHA – SSC Model• Compiled data and information from literature and existing

studies including:– Expansion of the regional earthquake catalog 1850-2014– New data such as geodetic data and interpretations– Source geometries, recurrence rates, maximum magnitudes, and

associated uncertainties

• Considered methods and models from other SSHAC studies and previous INL PSHAs

– Hanford SSHAC Level 3 PSHA (PNNL, 2014)– INL fault sensitivity analysis (AMEC, 2013)

• INL SSHAC Level 1 SSC model included – Updates of earthquakes sources used in 1996 and 2000 INL PSHAs– New earthquakes sources– Cascadia plate interface source as a sensitivity analysis

Page 12: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

SSHAC L1 SSC Sensitivity Analyses

ESRP

Cascadia PlateInterface Source

~900 km from INL≥M 9 earthquakesHigh recurrence rates

Included the SSHAC Level 3 BC Hydro (2012) model with the PNNL (2014) modifications

Page 13: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

SSHAC L1 SSC ModelRegional source zones- Eastern Snake River Plain (ESRP)

host zone- 10 tectonic source zones

Volcanic source zones- INL Volcanic Regional Zone (IVRZ)- Great Rift (GRF)

Local faults- Lost River (LRF), Lemhi (LF), and

Beaverhead (BF)

New Source Models- Centennial Shear Zone (CSZ#)- Big Lost fault (BLF)- 12 Regional faults

Page 14: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

INL SSHAC Level 1 PSHA – GMC Model• Compiled subsurface data and information from literature

and existing studies for MFC, INL site-wide, and ESRP• Considered models and methods for GMC from other

SSHAC studies• Implemented the Southwestern U.S. (SWUS) GMC model:

– Specifically developed for normal faulting– Has SSHAC Level 3 pedigree and Hazard Input Document– Adjusted the model to site-specific conditions at MFC– Used the SWUS partially non-ergodic variability model

• Estimated kappa and its uncertainty using 27 earthquakes (M 3-5) recorded at the MFC seismic station

• Updated the site-specific Vs profiles using measured Vs in nearby shallow boreholes and a 600-m-deep borehole

Page 15: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

INL SSHAC Level 1 PSHA Products• Preliminary and final seismic hazard products

– Rock outcrop conditions for MFC– Site-specific soil surface for FMF

• Dissection of hazard uncertainty contributions• Sensitivities to the hazard for SSC and GMC models and

specific sensitivity analysis • Mean seismic hazard curves at AEFs 10-2 – 10-8

• At PGA, mean seismic hazard curves at the 5th, 15th, 50th, 85th, and 95th percentiles

• Horizontal mean UHRS at return periods 2,500, 10,000, 25,000, and 100,000 yrs

AEF – Annual Exceedance FrequencyPGA – Peak Ground AccelerationUHRS – Uniform Hazard Response Spectrum

Page 16: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

SHPRMEvaluation

Processfor

Existing SDC-3

NuclearFacilities

Identifies changesbetween the

SSHAC Level 1 and baseline hazards

Page 17: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Evaluation Criteria for the SHPRM Change Relative to the Baseline PSHA Supporting the Design Basis Ground Motion

EvaluationCriterion 1

EvaluationCriterion 2

Evaluation Criterion 3

Evaluation Criterion 4

Changes to data, models, and methods?

Changes to input SSC or GMC models?

Change in mean hazard?

Changes to the technical bases?

Requires that all relevant new and updated data, models, and methods used in the current hazard be identified to assess how they differ from what was used in the baseline PSHA supporting design basis

Requires that changes to the SSC and GMC inputs (including associated aleatory and epistemic uncertainties) in the current PSHA model be identified based on the changes identified under Evaluation Criterion 1

Requires a comparison of the baseline PSHA hazard results with the SSHAC Level 1 or 2 to determine if there are significant changes

Requires an evaluation of whether or not the technical bases for the SSHAC Level 1 or 2 hazard have changed, even if the calculated hazard does not indicate a significant change

Page 18: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Approach to Identify Changes (Qualitative) • Evaluation Criterion 1

– New means was not previously available or the technical justification was insufficient to be included in baseline hazard

– Updated data means combining new data with existing data• Evaluation Criterion 2

– New means model inputs were not used in the baseline hazard– Updated means model inputs are similar to models used baseline hazard

and can include different aleatory and epistemic uncertainties• Evaluation Criterion 4

– Updated Technical Basis: Updated data or new methods led to input of the same or similar models with associated uncertainties

– Change to Technical Basis: New data, models or methods led to new and different input models or uncertainties

– New Technical Basis: New data, models, and methods led to new SSC or GMC models supported by new justifications that are distinctly and largely different than baseline hazard

Page 19: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Approach to Identify Changes For Evaluation Criterion 3• Defined Hazard Significance in two ways 1.Qualitative measure as meaning

– Specifies the implications to the current hazard for the identified changes under Evaluation Criteria 1, 2, and 4

– Defines why quantitative changes occur in the current hazard– Can be used to identify future data collection needs

2.Quantitative measure as impact – Comparison of seismic hazard curves for the baseline hazard and

SSHAC Level 1 or 2 hazard– Identifies the AEFs or spectral frequencies where changes occur– Is used to determine the yes or no response

Page 20: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Updated Data & New Methods --> Updated SSC ModelChange Relative to the 1996 and 2000 INL PSHAs Evaluation Criterion 3

Significance (or Meaning) to

INL SSHAC L1 Hazard

EvaluationCriterion 1

EvaluationCriterion 2

Evaluation Criterion 4

Changes to data, models, and methods?

Changes to input SSC or GMC models?

Changes to the technical bases?

Implications or why changes occur to the current hazard

Updated 1850-2014 earthquake catalogNew methods (e.g., updated conversion relations for expected moment magnitude E[M] and N* for magnitude uncertainties)

Updated recurrence models and uncertainties for tectonic source zones

Updated technical basis for earthquake recurrence within tectonic source zones

More appropriate treatment of uncertainties for earthquake magnitude and recurrence estimates

Yes Yes Yes

Page 21: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

New Model --> New SSC ModelChange Relative to the 1996 and 2000 INL PSHAs Evaluation Criterion 3

Significance (or Meaning) to

INL SSHAC L1 Hazard

EvaluationCriterion 1

EvaluationCriterion 2

Evaluation Criterion 4

Changes to data, models, and methods?

Changes to input SSC or GMC models?

Changes to the technical bases?

Implications or why changes occur to the current hazard

Included the Cascadia Plate Interface source model

New fault source added to the SSC model

Change to the technical basis to include a new and very distant fault source, which had not been included previously

Include all earthquake sources that may contribute more than 1% to total hazard (per DOE-STD-1020)

Yes Yes Yes

Page 22: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

New Model --> New GMC ModelChange Relative to the 1996 and 2000 INL PSHAs Evaluation Criterion 3

Significance (or Meaning) to

INL SSHAC L1 Hazard

EvaluationCriterion 1

EvaluationCriterion 2

Evaluation Criterion 4

Changes to data, models, and methods?

Changes to input SSC or GMC models?

Changes to the technical bases?

Implications or why changes occur to the current hazard

Applied the GMM developed by the SWUS Ground Motion Characterization project

Implemented the SWUS median GMM for shallow crustal earthquakes for the tectonic source zones, volcanic zones, regional fault sources and local fault sources

Change to the technical basis to include only empirical GMPEs for the GMM at INL

Incorporates a SSHAC Level 3 GMM that is applicable to extensional environments and has complete characterization of median ground motions and their aleatory variability

Yes Yes Yes

GMM – Ground Motion ModelGMPEs – Ground Motion Prediction EquationsSWUS – Southwestern United States

Page 23: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

New Model --> New GMC Model for Aleatory & Epistemic UncertaintiesChange Relative to the 1996 and 2000 INL PSHAs Evaluation Criterion 3

Significance (or Meaning) to

INL SSHAC L1 Hazard

EvaluationCriterion 1

EvaluationCriterion 2

Evaluation Criterion 4

Changes to data, models, and methods?

Changes to input SSC or GMC models?

Changes to the technical bases?

Implications or why changes occur to the current hazard

New model incorporated the effective total sigma (combined aleatory and epistemic) for the GMM

Implemented the SWUS partially non-ergodic variability model that separately evaluates the two components, event-to-event variability and single station within-event variability

Change to the technical basis to incorporate the combined aleatory and epistemic sigmas for GMM

Use of a partially non-ergodic variability rather than a fully ergodic variability as used in baseline PSHA

Yes Yes Yes

Page 24: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Evaluation Criterion 3

Requires a comparison of the baseline PSHA hazard results with the SSHAC Level 1 or 2 results to determine if there are changes to the calculated seismic hazard and to identify the significance of those changes

MFC (Rock)1996 PSHA vs. 2015 SSHAC L1 PSHA

Changes in use of E[M] and N* approach for recurrence models for source zones produced lower hazard

Baseline 1996

Hazard

2015SSHAC L1

Hazard

Page 25: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Evaluation Criterion 3MFC (Rock)

1996 PSHA vs. 2015 SSHAC L1 PSHA

Changes to the recurrence models of the Lost River and Lemhi faults and the addition of the regional faults produces higher hazard

Yes – Changes occurred to the mean hazard

- Lower median motions from the adjusted SWUS GMPEs compared to1996 - Lower effective total sigma (combined aleatory and epistemic) in 2015 than the 1996 PSHA ergodic sigmas

Page 26: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

SHPRMEvaluation

Processfor

Existing SDC-3

NuclearFacilities

Changes in hazardsignificant

to facility riskobjectives

Page 27: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

0.01

0.1

1

0.1 1 10 100

Hor

izon

tal S

pect

ral A

ccel

erat

ion

(g)

Frequency (Hz)

2015 UHRS, AEF 4E-4

2006 DBGM

Evaluation Criterion 5

Requires a comparison between the estimated mean hazard, expressed as the UHRS at the Hazard Exceedance Probability specified for the SDC category (ASCE/SEI 43-05) of the facility of interest and the DBGM that exists for the facility

FMF (5-15 ft Soil) DBGM vs. UHRS (AEF 4x10-4) at SDC-3

Yes – DBGM>UHRS

Page 28: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

0.01

0.1

1

0.1 1 10 100

Hor

izon

tal S

pect

ral A

ccel

erat

ion

(g)

Frequency (Hz)

2015 FMF GMRS

2006 DBGM

Evaluation Criterion 6

Requires a comparison between the GMRS (or DRS) at the SDC category (ASCE/SEI 43-05) for the facility of interest and the DBGM that exists for the facility

FMF (5-15 ft Soil)DBGM vs. GMRS at SDC-3

Yes – DBGM>GMRS

Page 29: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

SHPRMEvaluation

Processfor

Existing SDC-3

NuclearFacilities

Outcome:Baseline PSHA is

not updated; DBGM provides an

adequate safety basis

Page 30: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

Lessons Learned• SHPRM provided a defensible determination that INL’s

PSHA does not need to be updated for existing facilities– SHPRM cost: $360,000 – SSHAC Level 1 cost: $320,000– Total cost: $680,000

• Demonstrated a short-duration, low-cost SSHAC Level 1 study (10 months with small team and two-person PPRP)

• SSHAC Level 1 can be used as the starting point for a future SSHAC Level 3 update of the INL PSHA

– Compiled initial database– Completed sensitivity analyses to assess hazard impacts– Identified new data collection needs for GMC

• Any new nuclear facility (SDC≥3) at INL will need to perform the SSHAC Level 3 update

Page 31: Application of the Seismic Hazard Periodic Reevaluation ... · • INL Seismic Risk Assessment (SRA) Project and candidate existing nuclear facility • Implementation of SSHAC Level

ReferencesINL, 2016. Proposed Risk Informed Seismic Hazard Periodic Reevaluation

Methodology for Complying with DOE Order 420.1C. Battelle Energy Alliance, External Report INL/EXT-15-36510, Revision 1, 27.

INL 2016. SSHAC Level 1 Probabilistic Seismic Hazard Analysis for the Idaho National Laboratory. Battelle Energy Alliance External Report INL/EXT-15-36682, Revision 2, doi: 10.2172/1367865.

Kammerer, A., Coppersmith, K., Coleman, J., Payne, S., Chokshi, N., Budnitz, R.J., 2017. Development and application of the seismic hazard periodic reevaluation methodology for meeting DOE Order 420.1C at Idaho National Laboratory. Transactions of the 24th Conference on Structural Mechanics in Reactor Technology SMiRT-24, BEXCO, Busan, Korea, 11 p.

Payne, S.J., Coppersmith, K.J., Coppersmith, R.T., Montaldo Falero, V., Youngs, R.R., Rodriguez-Marek, A., and Silva, W., 2017. Assessing the Need for an Update of a Probabilistic Seismic Hazard Analysis Using a SSHAC Level 1 Study and the Seismic Hazard Periodic Reevaluation Methodology. Nuclear Engineering and Design, 323, 103-119.