alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
Submitted on record and briefs November 28,

affirmed without opinion December 3, 1973

#### STATE OF OREGON, *Respondent, v.*JAMES DELBERT WILLIAMS (No. 73-959-C), *Appellant.*

516 P2d 86

Gary D. Babcock, Public Defender, Salem, for appellant.

Lee Johnson, Attorney General, and W. Michael Gillette, Solicitor General, Salem, for respondent.

Before Schwab, Chief Judge, and Foley and Thornton, Judges.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Recommendations for Addressing Axial Burnup in PWR Burnup Credit Analyses (NUREG/CR-6801)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6801 (PDF - 4.42 MB)

## Publication Information

**Manuscript Completed:** October 2002**Date Published:** March 2003

**Prepared by:** J.C. Wagner, M. D. DeHart, C.V. Parks

Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6370

R.Y. Lee, NRC Project Manager

NRC Job Code W6479

**Prepared for**: 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 studies performed to support the development of a technically justifiable approach for addressing the axial-burnup distribution in pressurized-water reactor (PWR) burnup-credit criticality safety analyses. The effect of the axial-burnup distribution on reactivity and proposed approaches for addressing the axial-burnup distribution are briefly reviewed. A publicly available database of profiles is examined in detail to identify profiles that maximize the neutron multiplication factor, keff, assess its adequacy for PWR burnup credit analyses, and investigate the existence of trends with fuel type and/or reactor operations. A statistical evaluation of the keff values associated with the profiles in the axial burnup-profile database was performed, and the most reactive (bounding) profiles were identified as statistical outliers. The impact of these bounding profiles on keff is quantified for a high-density burnup credit cask. Analyses are also presented to quantify the potential reactivity consequence of loading assemblies with axial-burnup profiles that are not bounded by the database. The report concludes with a discussion on the issues for consideration and recommendations for addressing axial burnup in criticality safety analyses using burnup credit for dry cask storage and transportation.

Page Last Reviewed/Updated Wednesday, March 24, 2021
#### Dickenson *v*. Dickenson.

■ Where an absolute deed is made, parol evidence is not admissible to prove that the deed was made under any special trust, and that a valuable consideration was not paid.

The bill charged, that David Dickenson, the elder, in the year 1782, conveyed by deed, a slave to Shadraek *280Dickenson, which deed, on its face, purported to be ab« soltite, and made lor a valuable consideration, whereas, ^j,e ,je¿(j wag m¿d¿ in trust, for the benefit of David, and underlay agreement on the part 6f SJiadrack, that the slave should be conveyed and delivered to David^ or to such person as lie should at any time direct. The bill further charged that no consideration was paid, find that the complainant being a judgment creditor of Dát id’s, the látter did, in 1810, assign all his right in the said slave to *him;*pf which assignment, Shadrábk bad notice, but refused to give lip the property, insisting that he was hti absolute purchaser for valuable cion-* sideration. '

The answer denied the trust, averred a Valuable con* sideration to .hard been paid, and atledged that the transaction was an absolute sale arid purchase.

The only question submitted to the decision of this Court was, whether parol evidence was admissible, to she w that the deed whs made under the trust specified in the bill, and that a valuable Consideration was not paid*

Tayxor, Chief Justice.

The Court have looked into the cases of *Smith*v. *Williams,*(1 *Murph.*426,) and *Streator*v. *Jones, (Id.*449,) heretofore decided, and are of opinion that this case is governed by them, and that, consequently, itis not competent for the Plaintiff to give parol evidence for either of the purposes stated in tk« base,
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  EXHIBIT 4.1    
    

 






 



					
	Number

A-

	 	Incorporated Under the Laws of the State of Delaware	 	Shares

-0-

Cusip No.




 

  
 

  LIBERTY SPLITCO, INC.
  
    Series A Splitco Capital Common Stock, par value $.01 per share
  
    Specimen Certificate    
    


        This Certifies that
                                         
                                        is the owner
of
                                         
                                        FULLY
PAID AND NON-ASSESSABLE SHARES OF SERIES A SPLITCO CAPITAL COMMON STOCK, PAR VALUE $0.01 PER SHARE, OF LIBERTY SPLITCO, INC. (hereinafter called the "Corporation") transferable on
the books of the Corporation by the holder hereof in person or by duly authorized attorney upon surrender of the Certificate properly endorsed. This Certificate is not valid unless countersigned by
the Transfer Agent and registered by the Registrar. 


        Witness,
the seal of the Corporation and the signatures of its duly authorized officers. 

 










					
	Dated:	 	 	 	 
	

 	
 	
Liberty Splitco, Inc.

[Corporate Seal]	
 	

 
	






  President	 	 	 	






  Secretary




 

 








QuickLinks



EXHIBIT 4.1


LIBERTY SPLITCO, INC. Series A Splitco Capital Common Stock, par value $.01 per share Specimen Certificate
mm01-2111_8ke101.htm


Exhibit 10.1


Information Concerning Executive Compensation







It has been the policy of Leucadia National Corporation (the “Company”) since the current management took over in 1978 to emphasize performance based compensation through the payment of discretionary bonuses.







On January 21, 2011, the Company’s Board of Directors, upon the recommendation of the Compensation Committee in consultation with Ian M. Cumming, Chairman of the Board, and Joseph S. Steinberg, President of the Company, approved annual salary increases (effective January 1, 2011) and discretionary 2010 cash bonuses for each of the Company’s executive officers who were included as named executive officers in the Company’s 2010 proxy statement (other than Mr. Cumming and Mr. Steinberg1 ).













	
Name

	
Base Salary in 2011

	
Bonus Award for 20102


	  	  	  
	  	  	  
	
Thomas E. Mara

	
$371,000

	
$3,610,920


	  	  	  
	
Joseph A. Orlando

	
$338,000

	
$2,809,930


	  	  	  
	
Justin R. Wheeler

	
$306,000

	
$3,849,000












 


 


 


 


 


 


 


 


 


 


 


 


 


 


 


________________________________________________


1 Consistent with past practice, bonuses for 2010 for Messrs. Cumming and Steinberg will be considered by the Compensation Committee of the Board of Directors at the Board of Directors meeting to be held following the Company’s 2011 annual meeting of shareholders.


  

2Includes an annual holiday bonus paid to all employees based on a percentage of salary of $10,920 for Mr. Mara, $9,930 for Mr. Orlando and $9,000 for Mr. Wheeler.
Exhibit 24.1

POWER OF ATTORNEY

Know all by these presents, that I, the undersigned, do hereby appoint Mike
Kinney and Robert E. Brummels, or either of them, as my attorney-in-fact with full power of substitution, to execute in their respective names, individually and in my capacity as director, the Annual Report on Form 10-K for the year ended
December 31, 2006 (the 2006 Annual Report) of Husker Ag, LLC and any and all amendments thereto, and to file the 2006 Annual Report, any and all such amendments, and exhibits and documents thereto required in connection therewith
with the Securities and Exchange Commission, granting unto each attorney-in-fact and any substitute, full power and authority to do and to perform each and every act and thing requisite and necessary to be done in connection therewith, as fully as I
might or could do in person, hereby ratifying and confirming all that said attorneys-in-fact and their substitutes may lawfully do or cause to be done by virtue hereof.

IN WITNESS WHEREOF, I have hereunto set my hand this 20thday of March, 2007.



/s/ Kent A. FriedrichKent A. Friedrich




|                  |  |   |  |    
|----------------- |  | - |  | ---
|STATE OF NEBRASKA |  | ) |  |    
|                  |  | ) |  | ss.
|COUNTY OF PIERCE  |  | ) |  |    

On this 20thday of March, 2007, before me, a Notary public qualified for said County, personally came Kent A. Friedrich, known to me to be
the identical person who signed the foregoing instrument and acknowledged the execution thereof to be his voluntary act and deed.



/s/ Kristine C. WackerNotary PublicMy commission expires: 2-28-2010
HomeNRC LibraryDocument CollectionsMemoranda of Understanding

# Memoranda of Understanding - 2019

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

Page Last Reviewed/Updated Tuesday, October 13, 2020

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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Main Steam Line Break Analysis for Lungmen ABWR (NUREG/IA-0476)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0476 (PDF – 3.54 MB)
        - NUREG/IA-0476, Errata (PDF – 126 KB) 

## Publication Information

**Manuscript Completed:** February 2016**Date Published:** November 2016

**Prepared by:** Chunkuan Shih, Jong-Rong Wang, Ai-Ling Ho, Shao-Wen Chen, Show-Chyuan Chiang*, Tzu-Yao Yu*

Institute of Nuclear Engineering and Science, National Tsing Hua University; Nuclear and New Energy Education and Research Foundation 101 Section 2, Kuang Fu Rd., HsinChu, Taiwan

242, Section 3, Roosevelt Rd., Zhongzheng District, Taipei, Taiwan

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

Availability Notice

## Abstract

The object of this paper is to develop methodologies for analyzing the behaviors of fuel rod, vessel, and containment during main steamline break (MSLB) transient. The broken area of the RPV side was assumed to be 0.0984m2 (flow limiter). And the broken area of the main steam header side was assumed to 0.319m2 (main steam line area). According to FSAR, for conservative assumption, MSIVs started to close at 0.5sec and fully closed at 5.0sec after the transient started. The results of TRACE/PARCS coupling calculation were compared with those of both FSAR and GOTHIC data, indicating that the TRACE/PARCS coupling model has the ability to predict the MSLB transient, and both RPV integrity and containment integrity criteria are met. After that, the output data from TRACE/PARCS calculation was put into FRAPTRAN code as boundary conditions to analyze the thermo-mechanical behavior and calculate the stress, strain, oxide thickness, etc. The values of these factors were compared with the criteria. And the final results show that the fuel rod integrity criteria are met.

Page Last Reviewed/Updated Tuesday, March 09, 2021
# L_2015195DE.01004901.xml

| 23.7.2015 | DE | Amtsblatt der Europäischen Union | L 195/49 |
| --- | --- | --- | --- |

23.7.2015

DE

Amtsblatt der Europäischen Union

L 195/49

---

Berichtigung der Durchführungsverordnung (EU) Nr. 1329/2014 der Kommission vom 9. Dezember 2014 zur Festlegung der Formblätter nach Maßgabe der Verordnung (EU) Nr. 650/2012 des Europäischen Parlaments und des Rates über die Zuständigkeit, das anzuwendende Recht, die Anerkennung und Vollstreckung von Entscheidungen und die Annahme und Vollstreckung öffentlicher Urkunden in Erbsachen sowie zur Einführung eines Europäischen Nachlasszeugnisses

(
  Amtsblatt der Europäischen Union L 359 vom 16. Dezember 2014
  )

(
  Amtsblatt der Europäischen Union L 359 vom 16. Dezember 2014

Auf Seite 71, Anhang V, Formblatt V („Europäisches Nachlasszeugnis“), Punkt 8.1:

anstatt:

| „8.1. | Auf die Rechtsnachfolge von Todes wegen ist das Recht des folgenden Staates anzuwenden (*)
  ☐ Belgien ☐ Bulgarien ☐ Tschechische Republik ☐ Deutschland ☐ Estland ☐ Griechenland ☐ Spanien ☐ Frankreich ☐ Kroatien ☐ Italien ☐ Zypern ☐ Lettland ☐ Litauen ☐ Luxemburg ☐ Ungarn ☐ Malta ☐ Niederlande ☐ Österreich ☐ Polen ☐ Portugal ☐ Rumänien ☐ Slowenien ☐ Slowenien ☐ Finnland ☐ Schweden
  ☐ Sonstiges (bitte ISO-Code angeben): ...“ |
| --- | --- |

„8.1.

Auf die Rechtsnachfolge von Todes wegen ist das Recht des folgenden Staates anzuwenden (*)

☐ Belgien ☐ Bulgarien ☐ Tschechische Republik ☐ Deutschland ☐ Estland ☐ Griechenland ☐ Spanien ☐ Frankreich ☐ Kroatien ☐ Italien ☐ Zypern ☐ Lettland ☐ Litauen ☐ Luxemburg ☐ Ungarn ☐ Malta ☐ Niederlande ☐ Österreich ☐ Polen ☐ Portugal ☐ Rumänien ☐ Slowenien ☐ Slowenien ☐ Finnland ☐ Schweden

☐ Sonstiges (bitte ISO-Code angeben): ...“

muss es heißen:

| „8.1. | Auf die Rechtsnachfolge von Todes wegen ist das Recht des folgenden Staates anzuwenden (*)
  ☐ Belgien ☐ Bulgarien ☐ Tschechische Republik ☐ Deutschland ☐ Estland ☐ Griechenland ☐ Spanien ☐ Frankreich ☐ Kroatien ☐ Italien ☐ Zypern ☐ Lettland ☐ Litauen ☐ Luxemburg ☐ Ungarn ☐ Malta ☐ Niederlande ☐ Österreich ☐ Polen ☐ Portugal ☐ Rumänien ☐ Slowenien ☐ Slowakei ☐ Finnland ☐ Schweden
  ☐ Sonstiges (bitte ISO-Code angeben): ...“ |
| --- | --- |

„8.1.

Auf die Rechtsnachfolge von Todes wegen ist das Recht des folgenden Staates anzuwenden (*)

☐ Belgien ☐ Bulgarien ☐ Tschechische Republik ☐ Deutschland ☐ Estland ☐ Griechenland ☐ Spanien ☐ Frankreich ☐ Kroatien ☐ Italien ☐ Zypern ☐ Lettland ☐ Litauen ☐ Luxemburg ☐ Ungarn ☐ Malta ☐ Niederlande ☐ Österreich ☐ Polen ☐ Portugal ☐ Rumänien ☐ Slowenien ☐ Slowakei ☐ Finnland ☐ Schweden

☐ Sonstiges (bitte ISO-Code angeben): ...“

---
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Probabilistic Dose Analysis Using Parameter Distributions Developed For RESRAD and RESRAD-BUILD Codes (NUREG/CR-6676)

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        - Publication Information
        - Abstract

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        - NUREG/CR-6676 (PDF - 10.17 MB)

## Publication Information

**Manuscript Completed:** May 2000**Date Published:** July 2000

**Prepared by:** S. Kamboj, D. LePoire, E. Gnanapragasam, B. M. Biwer, I. Cheng, J. Arnish, C. Yu, S. Y. Chen

Argonne National Laboratory 9700 South Cass Avenue Argonne, IL 60439

T. Mo, NRC Project Manager

**Prepared for:** Division of Risk Analysis and Applications Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission****Washington, DC 20555-0001

NRC Job Code Y6112

Availability Notice

## Abstract

The existing RESRAD 6.0 and RESRADBUILD 3.0 codes for site-specific radiation dose modeling applications are being developed and adapted for use with the U.S. Nuclear Regulatory Commission's (NRC's) Standard Review Plan for decommissioning and as tools for demonstrating compliance with the license termination rule in a risk-informed manner. Computer interfaces and software modules have been developed under NRC sponsorship to perform the probabilistic simulation of dose. RESRAD and RESRAD-BUILD are part of the RESRAD family of codes that have been developed by the U.S. Department of Energy (DOE) and for many years have been successfully applied to cleanup efforts at sites contaminated with radioactive materials. Specifically, the RESRAD code applies to cleanup of soil, and RESRAD-BUILD applies to the cleanup of buildings and structures at a site. This report describes the use of these codes to perform probabilistic dose analysis. The dose analysis presented in this report has fully demonstrated the process of using the integrated system of RESRAD 6.0 and RESRAD-BUILD 3.0 codes and the probabilistic modules, together with distributions of input parameters, for dose assessment at a relatively complex site. This demonstration enables sitespecific application of the codes for dose analysis where pertinent parameters and their distributions are available or can be developed. Results of the uncertainty analysis and sensitivity analysis of dose to input parameter values indicated that because the dependence of dose on the input parameters is complex, no single correlation or regression coefficient can be used alone to identify sensitive parameters in all cases. However, the results could give an indication of the degree of sensitivity of the calculated dose to changes in input parameter values for each exposure situation. Therefore, the coefficients are useful guides, but they have to be used in conjunction with the other aids, such as scatter plots and further analysis, to accurately identify the sensitive parameters.

Page Last Reviewed/Updated Wednesday, March 24, 2021
Comment Info: =================

General Comment:Michael C. Himes 
HiRez Productions 
1101 South State Street  Apt 2202 
Chicago, Illinois 60605 
mikehimes9@gmail.com
312.735.0768
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Fire Risk Analysis for Nuclear Power Plants (NUREG/CR-2258)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-2258 (PDF - 5.15 MB)

## Publication Information

**Manuscript Completed:** May 1981**Data Published:** September 1981

**Prepared by:** M. Kazarians, G. Apostollakis

School of Engineering and Applied Science University of California Los Angeles, CA 90024

NRC FIN 86280

**Prepared for:** Division of Risk Analysis Office Of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Availability Notice

## Abstract

A methodology for evaluating the frequency of severe consequences due to fires in nuclear power plants is presented. The methodology produces a 1 of accident scenarios and then assesses the frequency of occurrence of each. Its framework is given in six steps. In the first two steps, the accident scenarios are identified qualitatively and the potential of fires to cause initiating events is investigated. The last four steps are aimed at quantification. The frequency of fires is obtained for different compartments in nuclear power plants using Bayesian techniques. The results are compared with those of classical methods and the variation of the frequencies with time is also examined. The combined effects of fire growth, detection, and suppression on component failure are modeled. The susceptibility of cables to fire and their failure modes are discussed. Finally, the limitations of the methodology and suggestions for further research are given.

Page Last Reviewed/Updated Wednesday, March 24, 2021
Briggs & Stratton Corporation Summary of Director Compensation



 Exhibit 10.5 
 BRIGGS & STRATTON CORPORATION 
 Form 10-Q for Quarterly Period Ended
December 26, 2010 
 Exhibit 10.5 
 SUMMARY OF DIRECTOR COMPENSATION 
 Effective January 26, 2011 







 DIRECTOR COMPENSATION 

Each nonemployee director receives an annual retainer fee of $150,000, of which $75,000 is payable in cash and $75,000 is payable in
deferred shares of the company’s common stock. In addition, the chairs of the Audit, Compensation, Finance and Nominating & Governance Committees each receives $10,000 in deferred stock annually, and each member of the Audit Committee
receives $5,000 in deferred stock annually. 
 The deferred shares are credited to the director’s account in the Deferred
Compensation Plan for Directors (the “Plan”). They vest when the director retires as a director. While the director is serving on the board, the stock accrues additional shares of deferred stock in lieu of a cash dividend. Under the Plan,
any nonemployee director may also elect to defer receipt of all or a portion of his or her director’s cash compensation until any date but no later than the year in which the director attains the age of 73 years. Participants may elect to have
cash deferred amounts (1) credited with interest quarterly at 80% of the prevailing prime rate, or (2) converted into common share units based on the deferral date closing price of the company’s common stock. Any balance in the common
stock account will be credited with an amount equivalent to any dividend paid on the common stock, which will be converted into additional common share units. Common share units may be distributed in cash or stock at the election of the directors.

 Nonemployee directors are provided with $150,000 of coverage under Briggs & Stratton’s Business Travel Accident
Plan while on corporate business. 
 Nonemployee directors are encouraged to use company products to enhance their understanding
and appreciation of the company’s business. Each such director may purchase at retail up to $10,000 annually of company products and products powered by the company’s engines. The company reimburses directors for the purchase price of
these products. The amount of the reimbursement is included in the director’s taxable income.
**Exhibit 32****CERTIFICATIONS PURSUANT TO SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002**Pursuant to Section 906 of the Sarbanes-Oxley Act of 2002 (subsections (a) and (b) of Section 1350,Chapter 63 of Title 18, United States Code), each of the undersigned officers of LCA-Vision Inc.(the “Company”), does hereby certify, to such officer’s knowledge, that:This quarterly report on Form 10-Q for the period ended September 30, 2006 of the Company fullycomplies with the requirements of Section 13(a) or 15(d) of the Securities Exchange Act of 1934 andinformation contained in this Form 10-Q fairly presents, in all material respects, the financialcondition and results of operations of the Company.       Date: October 30, 2006