alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
<TABLE> <S> <C>

<ARTICLE> 9
<LEGEND>
THIS SCHEDULE CONTAINS SUMMARY FINANCIAL INFORMATION EXTRACTED FROM THE DECEMBER
31, 1997 FORM 10-QSB FOR WASHINGTON BANCORP AND IS QUALIFIED IN ITS ENTIRETY BY
REFERENCE TO SUCH FINANCIAL STATEMENTS
</LEGEND>
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</TABLE>
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# A Preliminary Report on Fire Protection Research Program, Fire Barriers and Suppression (September 15, 1978 Test) (NUREG/CR-0596, SAND78-2238)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-0596 (PDF - 2.21 MB)

## Publication Information

**Manuscript Completed:**November 1978**Date Published:**December 1978

**Prepared by:** Leo J. Klamerus Sandia Laboratories Albuquerque, NM 87185 Operated by Sandia Corporation for the for the U.S. Department of Energy

**Prepared for:** Division of Reactor Safety Research Office of Water Reactor Safety Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Under Interagency Agreement DOE 40-550-75

 NRC FIN A-1010

Availability Notice

## Abstract

 A full-scale fire test was conducted at Underwriters Laboratories Inc. on September 15, 1978. The test was to demonstrate the effectiveness of a ceramic fiber blanket and automatic fire suppression system to protect cables in a vertical cable tray configuration that is currently permitted by separation criteria guidelines. An open pool fire fueled by liquid hydrocarbon was used. This was one of a series of tests to demonstrate the response of various cable arrangements and fire protection features in exposure fires.

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Human Factors Engineering (HFE) Insights for Advanced Reactors Based Upon Operating Experience (NUREG/CR-6400)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6400 (PDF - 2.60 MB)

## Publication Information

**Manuscript Completed:**December 1996**Date Published:**January 1997

**Prepared by:** J. Higgins, K. Nasta 

Brookhaven National Laboratory Upton, NY 11973 

**Prepared for:** Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

 The NRC Human Factors Engineering Program Review Model (HFE PRM, NUREG-0711) was developed to support a design process review for advanced reactor design certification under 1OCFR52. The HFE PRM defines ten fundamental elements of a human factors engineering program. An Operating Experience Review (OER) is one of these elements. The main purpose of an OER is to identify potential safety issues from operating plant experience and ensure that they are addressed in a new design. Broad-based experience reviews have typically been performed in the past by reactor designers. For the HFE PRM the intent is to have a more focused OER that concentrates on HFE issues or experience that would be relevant to the human-system interface (HSI) design process for new advanced reactors. This document provides a detailed list of HFE-relevant operating experience pertinent to the HSI design process for advanced nuclear power plants. This document is intended to be used by NRC reviewers as part of the HFE PRM review process in determining the completeness of an OER performed by an applicant for advanced reactor design certification. 

Page Last Reviewed/Updated Wednesday, March 24, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsBrochures Prepared by NRC Staff

# Effective Risk Communication (NUREG/BR-0308)

## The Nuclear Regulatory Commission's Guideline for External Risk Communication

On this page:
        - Publication Information
        - Acknowledgements

Download complete document
        - NUREG/BR-0308 (PDF - 1.53 MB)

Download Quick Reference Guide
        - This 2 page  Quick Reference Guide  accompanied the printed version of this document.   (PDF - 166 KB)

## Publication Information

**Date Published:** January 2004

**Prepared by:** J. Persensky, S. Browde, A. Szabo/NRC L. Peterson, E. Specht, E. Wight/WPI

 Division of Systems Analysis and Regulatory Effectiveness Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

WPI 6 Montgomery Village Avenue Suite 650 Gaithersburg, MD 20879

## Acknowledgements

These guidelines are a reflection of the risk communication understanding of researchers, trainers, and practitioners from numerous federal, state, private, and educational organizations. NRC and WPI are indebted to individuals from the organizations listed below as well as staff throughout the NRC for sharing their knowledge and experience. The completeness of these guidelines and their relevance to situations faced by NRC staff are the direct result of the time they generously spent with the authors both in interviews and collaborating on actual risk communication projects.

We are grateful to 
> 
Alabama Emergency Management Agency Centers for Disease Control Creighton & Creighton Decision Partners Exelon Federal Emergency Management Agency Fulton Communications George Washington University JKR Associates Maine Yankee Maryland Department of Environment National Aeronautics and Space Administration National Transportation Safety Board New Jersey Department of Environmental Protection  Nuclear Energy Institute Pennsylvania Department of Environmental Protection University of Colorado University of Pittsburgh, Graduate School of Public Health U.S. Air Force U.S. Army Center for Health Promotion and Preventive Medicine U. S. Department of Defense U.S. Environmental Protection Agency 

We also are grateful to the more than 50 NRC staff members that we interviewed from all levels, offices, and regions of the organization who provided essential insight into the agency and feedback on early drafts. Their involvement has been instrumental in shaping the content and structure of the final guide.

Finally, we thank the entire Risk Communication Steering Committee for their supportive guidance, steady commitment, and unwavering enthusiasm throughout the development of the guidelines.

Page Last Reviewed/Updated Wednesday, March 24, 2021
IN THE SUPREME COURT OF THE STATE OF MONTANA

No. DA 21-0404

STATE OF MONTANA, 

Plaintiff and Appellee, 

v. 

CIMMARON STEVEN DRENNAN,

Defendant and Appellant. 

ORDER

Upon consideration of Appellant’s motion for extension of time, and 

good cause appearing,

IT IS HEREBY ORDERED that Appellant is granted an extension 

of time to and including February 4, 2022, within which to prepare, file, 

and serve Appellant’s opening brief on appeal.

Electronically signed by:

Mike McGrath

Chief Justice, Montana Supreme Court

December 17 2021

12/17/2021

Case Number: DA 21-0404
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Accident Source Terms for Light-Water Nuclear Power Plants (NUREG-1465)

On this page: 
        - Publication Information
        - Abstract

Download complete document
        - NUREG-1465 (PDF - 2.27 MB) 

## Publication Information

**Manuscript Completed:**February 1995**Date Published:**February 1995

**Prepared by:** L. Soffer, S.B. Burson, C.M. Ferrell, R.Y. Lee, J.N. Ridgely

Division of Systems Technology Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

In 1962 the U.S. Atomic Energy Commission published TID-14844, "Calculation of Distance Factors for Power and Test Reactors" which specified a release of fission products from the core to the reactor containment in the event of a postulated accident involving a "substantial meltdown of the core." This "source term," the basis for the NRC's Regulatory Guides 1.3 and 1.4, has been used to determine compliance with the NRC's reactor site criteria, 10 CFR Part 100, and to evaluate other important plant performance requirements. During the past 30 years substantial additional information on fission product releases has been developed based on significant severe accident research. This document utilizes this research by providing more realistic estimates of the "source term" release into containment, in terms of timing, nuclide types, quantities, and chemical form, given a severe core-melt accident. This revised "source term" is to be applied to the design of future Light Water Reactors (LWRs). Current LWR licensees may voluntarily propose applications based upon it. These will be reviewed by the NRC staff.

Page Last Reviewed/Updated Tuesday, March 09, 2021
MESSAGE TO INTERNET USERS:

JANUARY 29, 1998

RE: 95-5224 FREUNDT-ALBERTI v. MERRILL, LYNCH

----------------------------------------------------------------------

The one page attachment referred to in the above opinion, does not appear in this text. It will,

however, appear when loaded in approximately 10 days.

Nancy Gilman, Opinions Clerk

US Court of Appeals for the Eleventh Circuit

(404) 335-6151
<TABLE> <S> <C>

<ARTICLE> 5
<CURRENCY> U.S. DOLLARS
       
<S>                             <C>
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</TABLE>
```

[Federal Register Volume 89, Number 229 (Wednesday, November 27, 2024)]
[Notices]
[Pages 93606-93607]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2024-27856]

-----------------------------------------------------------------------

DEPARTMENT OF HEALTH AND HUMAN SERVICES

Centers for Disease Control and Prevention

Notice of Closed Meeting

    Pursuant to 5 U.S.C. 1009(d), notice is hereby given of the 
following meeting.
    The meeting will be closed to the public in accordance with the 
provisions set forth in sections 552b(c)(4) and 552b(c)(6), Title 5 
U.S.C., as amended, and the Determination of the Director, Office of 
Strategic Business Initiatives, Office of the Chief Operating Officer, 
Centers for Disease Control and Prevention, pursuant to Public Law 92-
463. The grant applications and the discussions could disclose 
confidential trade secrets or commercial property such as patentable 
material, and personal information concerning individuals associated 
with the grant applications, the disclosure of which would constitute a 
clearly unwarranted invasion of personal privacy.
    Name of Committee: Disease, Disability, and Injury Prevention and 
Control Special Emphasis Panel; (SEP)--CE25-025, Rigorous Evaluation of 
Community- and Societal-Level Primary Prevention Approaches to Prevent 
Adverse Childhood Experiences (ACEs): Expanding the Best Available 
Evidence.
    Dates: February 25-26, 2025.
    Times: 10 a.m.-5 p.m., EST.
    Place: Web Conference.
    Agenda: To review and evaluate grant applications.

[[Page 93607]]

    For Further Information Contact: Aisha L. Wilkes, M.P.H., 
Scientific Review Officer, National Center for Injury Prevention and 
Control, Centers for Disease Control and Prevention, 4770 Buford 
Highway NE, Mailstop S106-9, Atlanta, Georgia 30341. Telephone: (404) 
639-6473; Email: [email protected].
    The Director, Office of Strategic Business Initiatives, Office of 
the Chief Operating Officer, Centers for Disease Control and 
Prevention, has been delegated the authority to sign Federal Register 
notices pertaining to announcements of meetings and other committee 
management activities, for both the Centers for Disease Control and 
Prevention and the Agency for Toxic Substances and Disease Registry.

Kalwant Smagh,
Director, Office of Strategic Business Initiatives, Office of the Chief 
Operating Officer, Centers for Disease Control and Prevention.
[FR Doc. 2024-27856 Filed 11-26-24; 8:45 am]
BILLING CODE 4163-18-P
```
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Draft Environmental Impact Statement on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Waste (NUREG-0782)

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Drywell Debris Transport Study (NUREG/CR-6369)

Page Last Reviewed/Updated Wednesday, March 24, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# A Subsurface Decision Model for Supporting Environmental Compliance (NUREG/CR-7021)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7021 (PDF - 4.53 MB)

## Publication Information

**Manuscript Completed:** December 2009**Date Published:** January 2012

**Prepared by:**Robert StewartUniversity of Tennessee1416 Circle Park DriveKnoxville, TN 37996

Dr. George Powers, NRC Project Manager

NRC Job Code N6232

Office of Nuclear Regulatory Research

Availability Notice

## Abstract

This document provides a geospatial modeling and decision framework for conducting a subsurface compliance survey and analysis for sites that have been remediated for radioactive contamination. This framework proposes a method to extend the Multi-Agency Site Survey Investigation Manual (MARSSIM) guidance, which only treats surface surveys, into the subsurface. It combines and organizes survey methods into a highly flexible sampling, modeling, and decision analysis approach that emphasizes the quality of decision making throughout the investigation. Major challenges face this goal, including lack of clear exposure mechanisms, inaccessibility of the subsurface, lack of comprehensive scans, and an increase in media complexity.

The US EPAs Triad model focuses on decision quality and methods that maximize available information, technologies, and expertise to address and mitigate sources of uncertainty. This document uses Triad to extend MARSSIM into the subsurface using a substantial and continually advancing set of tools including spatial analysis, modeling, and the GIS community. Recommendations are made on information that forms, updates, and evolves a spatial variation of the conceptual site model, called the Contamination Concern Map. This map focuses on the likelihood of exceeding a decision criterion at a local scale and directly addresses uncertainty in volume extent and location. The map matures over each major phase of the investigation and provides a decision framework. Results of this approach can inform investigators and regulators alike of a reasonable course of action in the final site assessment.

Page Last Reviewed/Updated Wednesday, May 12, 2021
ex4-1.htm


 EXHIBIT 4.1







THE GRAYSTONE COMPANY.


 


A DELAWARE CORPORATION


 


700,000,000 SHARES COMMON STOCK, NO PAR VALUE












This certifies that _________________________________________________ is hereby issued ____________________________________________________ fully paid and non-assessable Shares of Common Stock of The Graystone Company., transferable on the books of the Corporation by the holder hereof, in person or by duly authorized Attorney upon surrender of this Certificate properly endorsed.







In Witness Whereof, The Graystone Company. has caused this Certificate to be signed by its duly authorized officers and its Corporate Seal to be hereunto affixed as of this ______ day of __________________ 20_____.


 


 







____________________________                                                                         _____________________________


President                                                                                                                             Secretary
EXHIBIT
32.1





CERTIFICATION
PURSUANT TO 18 U.S.C. SECTION 1350,


AS
ADOPTED PURSUANT TO SECTION 906


OF
THE SARBANES-OXLEY ACT OF 2002








In connection with the Annual Report of
Morris Business Development Company (the “Company”) on Form 10-K for the year
ended March 31, 2009, as filed with the Securities and Exchange Commission on or
about the date hereof (the “Report”), I, George Morris, Chief Executive Officer
of the Company, certify, pursuant to Section 906 of the Sarbanes-Oxley Act of
2002, that:





(1)           The
Report fully complies with the requirements of Section 13(a) or 15(d) of the
Securities Exchange Act of 1934; and





(2)           Information
contained in the Report fairly presents, in all material respects, the financial
condition and results of operations of the Company.




Date:  July
13, 2009
 /s/
George Morris
 George
Morris
 Chief
Executive Officer





A signed
original of this written statement required by Section 906 has been provided to
Morris Business Development Company and will be retained by Morris Business
Development Company and furnished to the Securities and Exchange Commission or
its staff upon request.