Information Notice 2010-19, Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States

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Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States
ML102160735
Person / Time
Issue date: 09/16/2010
From: Marissa Bailey
NRC/NMSS/FCSS
To:
Tiannging C., 301-492-3568
References
IN-10-019
Download: ML102160735 (4)


ML102160735 UNITED STATES

NUCLEAR REGULATORY COMMISSION

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS

WASHINGTON, DC 20555-0001

September 16, 2010

NRC INFORMATION NOTICE 2010-19: UPDATED PROBABILISTIC SEISMIC HAZARD

ESTIMATES IN CENTRAL AND EASTERN UNITED

STATES

ADDRESSEES

All licensees, applicants, and holders of a construction authorization and/or certificate issued by

the U.S. Nuclear Regulatory Commission (NRC), for fuel cycle facilities including Fuel

Manufacturing Facilities, Mixed Oxide facilities, and Uranium Enrichment Facilities licensed

under Title 10 of the Code of Federal Regulations (10 CFR) Part 70, Domestic Licensing of

Special Nuclear Material; Gaseous Diffusion Plants Certified under 10 CFR Part 76, Certification of Gaseous Diffusion Plants; and Uranium Conversion/De-conversion Facilities

licensed under 10 CFR Part 40, Domestic Licensing of Source Material (i.e., Honeywell

Metropolis Works).

PURPOSE

NRC is issuing this Information Notice (IN) to inform addressees about the NRCs findings

relating to higher estimated seismic hazards in the Central and Eastern United States (CEUS)

according to the U.S. Geological Survey (USGS)s 2008 seismic hazard model. The seismic

hazard is usually described by the seismic hazard curve or the annual exceedance frequency as

a function of ground motion level (peak ground acceleration or spectral accelerations at certain

frequencies). The increase is due to the updates to ground motion models and seismic sources

in the regions around Charleston, South Carolina, New Madrid, Missouri, southern Illinois and

southern Indiana. The increase is mostly from the comparison between the 1989 Electric Power

Research Institute-Seismicity Owner Group (EPRI-SOG) study, which was updated in 2009, and

the USGS 2008 seismic hazard model.

Licensees, applicants, and holders of a construction authorization and/or certificate should

review this IN and consider actions, as appropriate. However, the suggestions contained in this

IN are not new NRC requirements; therefore, no specific action or written response is required.

BACKGROUND

In support of early site permits (ESP) for new reactors, the NRC staff reviewed updates to the

seismic source and ground motion models provided by applicants, which identified higher

estimate seismic hazards at operating facilities in the CEUS where ESPs were sought. This

finding was addressed in a July 2006 memorandum (ADAMS accession number ML052360044)

to the NRCs Commissioners from the NRCs Executive Director of Operations, and identified

the impact of a higher seismic hazard on currently operating nuclear power plants in the CEUS

as Generic Issue 199. The seismic update information from ESP applicants included new EPRI

models to estimate earthquake ground motion and updated models for earthquake sources in

seismic regions such as eastern Tennessee, and around both Charleston, South Carolina, and ML102160735 New Madrid, Missouri. The NRC staff reviewed and evaluated this new information along with

similar USGS seismic hazard estimates in 2008. From this review, the NRC staff concluded

that the likelihood of exceeding the seismic hazard values used in plant design and in previous

evaluations may be higher than previously understood for some currently operating CEUS sites.

The NRC staffs conclusions were discussed in an NRC public meeting in 2008 that included

many operating reactor licensees and EPRI representatives.

Because many fuel cycle facilities are located in the CEUS, with some located in the above

mentioned seismic source regions, the updated seismic hazard information should be reviewed

and actions be considered as appropriate.

Seismic hazards are considered as natural phenomena hazards (10 CFR 70.64, Appendix A to

Part 70, and 10 CFR 76.87) and may initiate potential accident sequences in a fuel cycle facility.

The new fuel cycle facility designs are required to provide for adequate protection against these

natural phenomena hazards (10 CFR 70.64); all licensed fuel cycle facilities are required to

meet the performance requirements of §70.61 through consequence evaluation as part of the

Integrated Safety Analysis. The increased seismic hazards in the CEUS may have some

impact on the existing and new fuel facilities for these seismic safety evaluations. This focus of

this IN is to: (1) raise attention to potential concerns that not all addressees have considered the

increased USGS 2008 seismic hazard results; and (2) suggest that appropriate actions being

taken.

The USGS 2008 seismic hazard model is available online at

http://earthquake.usgs.gov/hazards/. By utilizing the interactive seismic hazard maps, a user

can calculate the ground motions for any site by inputting the latitude and longitude of the site.

For soil response of a site, the user can input appropriate shear wave velocities for the top 30

meters.

Due to the estimated seismic hazard increase, the NRC encourages fuel cycle facilities in CEUS

to consider the USGS updated seismic hazard estimates to assess the potential for exceeding

the licensing basis on design of the structures, systems, and components and the event

consequences initiated by seismic events, and consider actions as appropriate.

CONTACT

This IN requires no specific action or written response. Please direct any questions about this

matter to the technical contacts listed below or to the appropriate project manager in the Office

of Nuclear Material Safety and Safeguards, Division of Fuel Cycle Safety and Safeguards.

/RA/

Marissa Bailey, Acting Director

Division of Fuel Cycle Safety

and Safeguards

Office of Nuclear Material Safety

and Safeguards

Technical contacts:

Tianqing Cao

Osiris Siurano

301-492-3568

301-492-3117

E-mail: Tianqing.Cao@nrc.gov

Osiris.Siurano-Perez@nrc.gov

CONTACT

This IN requires no specific action or written response. Please direct any questions about this

matter to the technical contacts listed below or to the appropriate project manager in the Office

of Nuclear Material Safety and Safeguards, Division of Fuel Cycle Safety and Safeguards.

/RA/

Marissa Bailey, Acting Director

Division of Fuel Cycle Safety

and Safeguards

Office of Nuclear Material Safety

and Safeguards

Technical contacts:

Tianqing Cao

Osiris Siurano

301-492-3568

301-492-3117

E-mail: Tianqing.Cao@nrc.gov

Osiris.Siurano-Perez@nrc.gov

ML102160735 OFFICE

FCSS/UEB

NMSS/DHLWRS

FCSS/UEB

FCSS/AFCB

FCSS/FMB

NAME

OSiurano

TCao

TRichmond

THiltz

PHabighorst

DATE

8/5/2010

8/5/2010

8/11/2010

8/23/2010

8/20/2010

OFFICE

FCSS/UEB

QTE

FCSS/SPTSD

FCSS

NAME

BSmith

CHsu (via e-mail)

MBailey

DATE

9/16/2010

8/31/2010

9/16/2010

OFFICIAL RECORD COPY