alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
* Pursuant to 5 TH C IR . R. 47.5, the court has determined that

this opinion should not be published and is not precedent except under the limited circumstances set forth in 5 TH C IR . R. 47.5.4. United States Court of Appeals

Fifth Circuit 

## FILED June 20, 2006 Charles R. Fulbruge III Clerk IN THE UNITED STATES COURT OF APPEALS

FOR THE FIFTH CIRCUIT

No. 05-41103 Summary Calendar

UNITED STATES OF AMERICA, Plaintiff-Appellee,

versus PAUL DANA WILLIAMS, also known as Paul William Dana, Defendant-Appellant.

-------------------- Appeal from the United States District Court for the Eastern District of Texas USDC No. 4:91-CR-34-ALL

-------------------- Before SMITH, GARZA, and PRADO, Circuit Judges. PER CURIAM: * Paul Dana Williams, federal prisoner # 07339-051, appeals the denial of his 18 U.S.C. § 3582(c) motion for modification of sentence. He argues that retroactive Amendments 433, 506, and 591 to the Sentencing Guidelines coupled with the holding of United States v. Booker , 125 S. Ct. 738 (2005), affected the method by which U.S.S.G. § 4B1.1 (Career Offender) was applied to his kidnapping and firearms convictions.No. 05-41103 -2- Our review of Williams’s sentencing reveals that none of the cited amendments have any application to the sentence the district court imposed. To the extent that Williams invokes Booker , such an argument is not cognizable in the context of a 18 U.S.C. § 3582(c)(2) motion because it is not based on a retroactive amendment to the Guidelines. See United States v. Shaw , 30 F.3d 26, 29 (5th Cir. 1994). In light of the foregoing, the district court did not abuse its discretion in denying the motion. See United States v. Pardue , 36 F.3d 429, 430 (5th Cir. 1994). AFFIRMED.
<TABLE> <S> <C>

<ARTICLE>                     5

<LEGEND>
The schedule contains summary financial information extracted from the Company's
financial  statements for the six months ended June 30, 1996 and is qualified in
its entirety by reference to such statements.
</LEGEND>
       
<S>                                         <C>
<PERIOD-TYPE>                               6-MOS
<FISCAL-YEAR-END>                                                DEC-31-1996
<PERIOD-START>                                                   JAN-01-1996
<PERIOD-END>                                                     JUN-30-1996
<CASH>                                                                     0
<SECURITIES>                                                               0
<RECEIVABLES>                                                              0
<ALLOWANCES>                                                               0
<INVENTORY>                                                                0
<CURRENT-ASSETS>                                                           0
<PP&E>                                                                     0
<DEPRECIATION>                                                             0
<TOTAL-ASSETS>                                                             0
<CURRENT-LIABILITIES>                                                  5,294
<BONDS>                                                                    0
<PREFERRED-MANDATORY>                                                      0
<PREFERRED>                                                                0
<COMMON>                                                               1,500
<OTHER-SE>                                                           (6,794)
<TOTAL-LIABILITY-AND-EQUITY>                                               0
<SALES>                                                                    0
<TOTAL-REVENUES>                                                           0
<CGS>                                                                      0
<TOTAL-COSTS>                                                              0
<OTHER-EXPENSES>                                                       6,167
<LOSS-PROVISION>                                                           0
<INTEREST-EXPENSE>                                                         0
<INCOME-PRETAX>                                                      (6,167)
<INCOME-TAX>                                                               0
<INCOME-CONTINUING>                                                        0
<DISCONTINUED>                                                             0
<EXTRAORDINARY>                                                            0
<CHANGES>                                                                  0
<NET-INCOME>                                                         (6,176)
<EPS-PRIMARY>                                                              0
<EPS-DILUTED>                                                              0
        

</TABLE>
|CERTIFICATION PURSUANT TO18 U.S.C. SECTION 1350,AS ADOPTED PURSUANT TOSECTION 906 OF THE SARBANES-OXLEY ACT 0F 2002
|-------------------------------------------------------------------------------------------------------------------

In connection with the Annual Report of Signature Leisure, Inc. (the "Company") on Form 10-KSB for the period ending December 31, 2007, as filed with the Securities and Exchange Commission on
the date hereof (the "Report"), I, Stephen W. Carnes, President, Principal Executive Officer and Principal Accounting Officer of the Company, certify, pursuant to 18 U.S.C. Section 1350, as adopted 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) | The information contained in the Report fairly presents, in all material respects, the financial condition and result of operations of the Company.
|   

|\s\ Stephen W. CarnesStephen W. CarnesPresidentPrincipal Executive Officer and Principal Accounting Officer
|-----------------------------------------------------------------------------------------------------------

|April 14, 2008
|--------------

---
HomeNuclear Security

# Post 9/11 Information

On this page:
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*This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.*

## Correspondence

## Fact Sheets

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Page Last Reviewed/Updated Thursday, March 12, 2020

Section Navigation

#### Navigation

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Page Last Reviewed/Updated Thursday, March 12, 2020
N OTE : This disposition is nonprecedential. 

# United States **Court of Appeals**  **for the Federal Circuit**

______________________ JACK LEON CLARKE, Claimant

- Appellant

v.

DAVID J. SHULKIN, SECRETARY OF VETERAN S AFFAIRS, Respondent

- Appellee

______________________

2016

- 2420

______________________ Appeal from the United States Court of Appeals for Veterans Claims in No. 14

- 2699, Senior Judge Bruce E. Kasold.

______________________
JUDGMENT

______________________

R EBECCA H ARKER D UTTRY , McDermott, Will & Emery LLP, Washington, DC, argued for claimant

- appellant. Also represented by J OSHUA D AVID R OGACZEWSKI

.

N ATHANAEL Y ALE , Commercial Litigation Branch, Ci vil Division, United States Department of Justice, Was hington, DC, argued for respondent

- appellee. Also represented by C HAD A. R EADLER , R OBERT E. K IRSCHMAN , J R

. , M ARTIN F. H OCKEY , J R

. ; S AMANTHA A NN S YVERSON , Y.K EN L EE , Office of General Counsel, United States D epartment of Veterans Affairs, W ashington, DC.

______________________

T HIS C AUSE having been heard and considered, it is

O RDERED and A DJUDGED :

P ER C URIAM (L OURIE , T ARANTO , and C HEN , Circuit Judges ).

AFFIRMED

. See Fed. Cir. R. 36.

E NTERED BY O RDER OF THE C OURT

June 12, 2017 /s/ Peter R. Marksteiner Date Peter R. Marksteiner Clerk of Court
```

[Federal Register Volume 76, Number 66 (Wednesday, April 6, 2011)]
[Proposed Rules]
[Pages 19004-19005]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-8172]

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

ENVIRONMENTAL PROTECTION AGENCY

40 CFR Part 271

[EPA-R06-RCRA-2010-0307; FRL-9290-9]

Oklahoma: Final Authorization of State Hazardous Waste Management 
Program Revisions

AGENCY: Environmental Protection Agency (EPA).

ACTION: Proposed rule.

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

SUMMARY: The State of Oklahoma has applied to EPA for Final 
authorization of the changes to its hazardous waste program under the 
Resource Conservation and Recovery Act (RCRA). EPA proposes to grant 
Final

[[Page 19005]]

authorization to the State of Oklahoma. In the ``Rules and 
Regulations'' section of this Federal Register, EPA is authorizing the 
changes by an immediate final rule. EPA did not make a proposal prior 
to the immediate final rule because we believe this action is not 
controversial and do not expect comments that oppose it. We have 
explained the reasons for this authorization in the preamble to the 
immediate final rule. Unless we get written comments which oppose this 
authorization during the comment period, the immediate final rule will 
become effective on the date it establishes, and we will not take 
further action on this proposal. If we receive comments that oppose 
this action, we will withdraw the immediate final rule and it will not 
take effect. We will then respond to public comments in a later final 
rule based on this proposal. You may not have another opportunity for 
comment. If you want to comment on this action, you must do so at this 
time.

DATES: Send your written comments by May 6, 2011.

ADDRESSES: Send written comments to Alima Patterson, Region 6, Regional 
Authorization Coordinator, (6PD-O), Multimedia Planning and Permitting 
Division, at the address shown below. You can examine copies of the 
materials submitted by the State of Oklahoma during normal business 
hours at the following locations: EPA Region 6, 1445 Ross Avenue, 
Dallas, Texas 75202-2733, phone number (214) 665-8533; or Oklahoma 
Department of Environmental Quality, 707 North Robinson, Oklahoma City, 
Oklahoma 73101-1677, (405) 702-7180. Comments may also be submitted 
electronically or through hand delivery/courier; please follow the 
detailed instructions in the ADDRESSES section of the immediate final 
rule which is located in the Rules section of this Federal Register.

FOR FURTHER INFORMATION CONTACT: Alima Patterson (214) 665-8533.

SUPPLEMENTARY INFORMATION:
    For additional information, please see the immediate final rule 
published in the ``Rules and Regulations'' section of this Federal 
Register.

    Dated: March 19, 2011.
Al Armendariz,
Regional Administrator, Region 6.
[FR Doc. 2011-8172 Filed 4-5-11; 8:45 am]
BILLING CODE 6560-05-P
```
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Assessment of the TRAC-M Codes Using Flecht-Seaset Reflood and Steam Cooling Data (NUREG-1744)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG-1744 (PDF 3.59 MB)

## Publication Information

**Manuscript Completed:** May 2001**Date Published:** May 2001

**Prepared by:** F. Odar

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

Availability Notice

## Abstract

This report presents the results of an assessment of the capabilities of the TRAC-M(F77), Version 5.5.2.A, and TRAC-M(F90), Version 3.580, codes to predict reflood and steam cooling phenomena that may occur during a postulated large-break loss-of-coolant accident (LOCA). The assessment is predicated on test data from Flecht-Seaset Runs 31504 and 32753. The assessment shows that predictions of the reflood phenomena derived using both codes are inaccurate; however, it is judged that they can conservatively predict peak clad temperatures in heated rods since the code model expels more water from the test section than measured. The predictions of steam cooling in single-phase flow conditions are acceptable.

Page Last Reviewed/Updated Tuesday, March 09, 2021
**Exhibit      32**

**CERTIFICATIONS      PURSUANT TO SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002**

** **
** **

| Date:                July 29, 2008 | /s/                Steven C. Straus                                          |   |
|------------------------------------|------------------------------------------------------------------------------|--------|
|                               | Steven                C. Straus                                              |
|                               | Chief                Executive Officer                                       |
|                               |                                                                         |
|                               |                                                                         |
| Date:                July 29, 2008 | /s/                Michael J. Celebrezze                                     |   |
|                               | Michael                J. Celebrezze                                         |
|                               | Interim                Chief Financial Officer                               |
|                               | Senior                Vice President of Finance and                Treasurer |

----
No. 86-970.

#### Binker *v.*United States.

C. A. 11th Cir. Certiorari denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Managing Aging Processes In Storage (MAPS) Report: Final Report (NUREG-2214)

This NUREG-series publication was issued for public comment. The comment period is now closed.

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG-2214 (PDF – 9.69 MB)

## Publication Information

**Manuscript Completed:** March 2019**Date Published:** July 2019

Office of Nuclear Materials Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

This Managing Aging Processes in Storage (MAPS) Report provides guidance for the U.S. Nuclear Regulatory Commission (NRC) technical reviewer. It establishes a technical basis for the safety review of renewal applications for specific licenses of independent spent fuel storage installations and certificates of compliance for dry storage systems, as codified in Title 10 of the *Code of Federal Regulations* (10 CFR) Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste."

The MAPS Report evaluates known aging degradation mechanisms to determine if they could affect the ability of dry storage system components to fulfill their safety functions in the 20- to 60-year period of extended operation. The guidance also provides examples of aging management programs that are considered generically acceptable to address the credible aging mechanisms to ensure that the design bases of dry storage systems will be maintained. An applicant for a renewed license or certificate of compliance may reference the information in the MAPS Report to support its aging management review and proposed aging management programs. As new information on materials aging becomes available, applicants may need to supplement the information in the MAPS Report to ensure that newly identified aging mechanisms are appropriately managed.

Page Last Reviewed/Updated Tuesday, March 09, 2021
**Exhibit 23.3**

**CONSENT OF INDEPENDENT RESERVE ENGINEERS**

We hereby consent to the use of our name in this AnnualReport on Form 10-K of Transmeridian Exploration Incorporated for the fiscal year ended December 31, 2007 and to the incorporation by reference of our estimates of the proved reserves and future net revenues from proved reserves ofTransmeridian Exploration Incorporated as of December 31, 2007 into Transmeridian Exploration Incorporated’s previously filed Registration Statements on Form S-3 (File Nos. 333-132389, 333-129250, 333-127674, 333-120930, 333-135318,333-135798 and 333-139923) and on Form S-8 (File Nos. 333-105610, 333-105609 and 333-139232) and the related prospectuses. 

/S/ RYDER SCOTT COMPANY, L.P.

RYDER SCOTT COMPANY, L.P. 

March 31, 2008
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Post-Test Analysis of Cold Leg Small Break 4.1% at PSB-VVER Facility using TRACE V5.0 (NUREG/IA-0502)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0502 (PDF – 7.34 MB)

## Publication Information

**Manuscript Completed:** April 2018**Date Published:** March 2019

**Prepared by:** Petr Heralecky

TES Ltd. Prazska 597 674 01 Trebic, Czech Republic 

K. Tien, NRC Project Manager 

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

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP) 

**Published by:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

Availability Notice

## Abstract

The U.S. NRC best estimate thermo-hydraulic computer code TRACE V5.0 has been assessed against the "4.1 % cold leg break (CL-4.1-03)" experiment at the large-scale test facility PSB-VVER. The PSB-VVER facility is a 1:300 volume-power scaled model of VVER-1000 NPP located in Electrogorsk, Russia. An extensive TRACE input deck of PSB-VVER facility was developed. The model includes all important components of the PSB-VVER facility: reactor, 4 separated loops, pressurizer, HPIS and LPIS ECCS, several break units, main circulation pumps, steam generators, and important parts of secondary circuit. The TRACE (TRAC/RELAP Advanced Computational Engine) is the latest in a series of advanced, best-estimate reactor systems codes developed by the U.S. Nuclear Regulatory Commission in frame of CAMP (Code Application and Maintenance Program). The TRACE code is a component-oriented reactor systems analysis codes designed to analyze light water reactor transients up to the point of significant fuel damage. The original validation of the TRACE code was mainly based on experiments performed on experimental facilities of typical PWR design. There are some different features of VVER design comparing to PWR. Therefore the validation of the thermo-hydraulic codes for VVER types of reactors is often required by national regulators. The presented analysis is the latest in series of TRACE and RELAP5 assessment calculations evaluated at the company TES. The purpose of performed analyses is to extend the validation of the TRACE code focused on VVER type of NPPs and to support applicability of the TRACE code in the Czech Republic. 

Page Last Reviewed/Updated Tuesday, March 09, 2021
EXHIBIT 12.1  Section 302 of the Sarbanes-Oxley Act of 2002  CEO Certification  I, Jason S. Weber, certify that:  1. I have reviewed this amended transition report on Form 20-F of Kiska Metals Corporation.  2. Based on my knowledge, this report does not contain any untrue statement of a material fact or omit to state a material fact necessary to make the statements made, in light of the circumstances under which such statements were made, not misleading with respect to the period covered by this report; and  3. Based on my knowledge, the financial statements, and other financial information included in this report, fairly present in all material respects the financial condition, results of operations and cash flows of the Company as of, and for, the periods presented in this report.  Date: November 24, 2010 Jason S. Weber Jason S. Weber President & Chief Executive Officer
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Compendium of Analyses to Investigate Select Level 1 Probabilistic Risk Assessment End-State Definition and Success Criteria Modeling Issues (NUREG/CR-7177, ERI/NRC 13-210)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7177: Main Report (PDF - 10.42 MB)
        - Errata (PDF - 372 KB)

## Publication Information

**Manuscript Completed:** June 2013**Date Published:** May 2014

**Prepared by:**1A. Krall1P. Sawant1S. Choi1M. Khatib-Rahbar2 D. Helton

1Energy Research, Inc. P. O. Box 2034 Rockville, MD 20847

2U.S. Nuclear Regulatory Commission

D. Helton, NRC Project Manager

NRC Job Code V6219

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

Availability Notice

## Abstract

As part of the routine development, maintenance, and application of the US Nuclear Regulatory Commission's (NRC's) risk tools, assumptions are made with respect to how nuclear power plant accidents will be represented. The NRC conducts research, and performs analyses, to investigate the adequacy of these assumptions. Recently, the Office of Nuclear Regulatory Research has increased its use of the MELCOR computer code for investigating assumptions related to the success criteria, sequence timing, and end-state definition aspects of Level 1 probabilistic risk assessment (PRA). This report augments the existing collection of contemporary Level 1 PRA success criteria analyses and complements other ongoing work related to success criteria analyses for the Byron Station that will be documented in an upcoming NUREG report.

This report focuses on investigations of (a) the effect of modeling assumptions on key figures-of-merit such as the time of depletion of the refueling water storage tank; (b) the relative conservatism or non-conservatism associated with commonly used and potential core damage surrogates; (c) the time required to arrest fuel heatup if mitigation equipment is recovered following a core heatup; and (d) the comparison of MELCOR to the Modular Accident Analysis Program (MAAP) for characterizing the safety margins of selected PRA sequences through an uncertainty quantification process.

Page Last Reviewed/Updated Thursday, March 25, 2021