alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Computational Benchmark for Estimation of Reactivity Margin from Fission Products and Minor Actinides in PWR Burnup Credit (NUREG/CR-6747)

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        - NUREG/CR-6747 (PDF 4.71 MB)

## Publication Information

**Manuscript Completed:** July 2001**Date Published:** October 2001

**Prepared by:** J. C. Wagner

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

R. Y. Lee, NRC Project Manager

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

NRC Job Code W6479

Availability Notice

## Abstract

This report proposes and documents a computational benchmark problem for the estimation of the additional reactivity margin available in spent nuclear fuel (SNF) from fission products and minor actinides in a burnupcredit storage/transport environment, relative to SNF compositions containing only the major actinides. The benchmark problemlconfiguration is a generic burnup credit cask designed to hold 32 pressurized water reactor (PWR) assemblies. The purpose of this computational benchmark is to provide a reference configuration for the estimation of the additional reactivity margin, which is encouraged in the U.S. Nuclear Regulatory Commission (NRC) guidance for partial burnup credit (ISG8), and document reference estimations of the additional reactivity margin as a function of initial enrichment, burnup, and cooling time. Consequently, the geometry and material specifications are provided in sufficient detail to enable independent evaluations. Estimates of additional reactivity margin for this reference configuration may be compared to those of similar burnup-credit casks to provide an indication of the validity of design-specific estimates of fission-product margin. The reference solutions were generated with the SAS2H-depletion and CSAS25-criticality sequences of the SCALE 4.4a package. Although the SAS2H and CSAS25 sequences have been extensively validated elsewhere, the reference solutions are not directly or indirectly based on experimental results. Consequently, this computational benchmark cannot be used to satisfy the ANS 8.1 requirements for validation of calculational methods and is not intended to be used to establish biases for burnup credit analyses.

Page Last Reviewed/Updated Thursday, March 25, 2021
No. 90-6176.

#### Abuelhawa *v.*United States.

C. A. 4th Cir. Certiorari denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# The Use of a Field Model To Assess Fire Behavior in Complex Nuclear Power Plant Enclosures: Present Capabilities and Future Prospects (NUREG/CR-4479, BNL-NUREG-51948)

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        - NUREG/CR-4479 (PDF - 2.56 MB)

## Publication Information

**Manuscript Completed:**November 1985**Date Published:**December 1985

**Prepared by:**John L. Boccio and John L. UsherReliability and Physical Analysis GroupDepartment of Nuclear EnergyBrookhaven National LaboratoryUpton, NY 11973Under Contract No. DE-AC02-76CH00016

**Prepared for:**Electrical Engineering BranchDivision of Engineering TechnologyOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

NRC FIN A-3252

Availability Notice

## Abstract

This report provides a summary of the work conducted during FY-1984 by Brookhaven National Laboratory (BNL), under FIN A-3252 "Fire Protection Research Program." It was undertaken under the cognizance of the Electrical Engineering Branch in the Division of Engineering Technology within the Office of Nuclear Regulatory Research. The report describes a mathematical model for predicting the thermal environment within complex nuclear power plant enclosures. It demonstrates the capability of the existing numerical code by direct comparisons with electrical cable fire/large enclosure tests performed by Sandia National Laboratories (SNL) for the NRC and by the Factory Mutual Research Corporation (FMRC) for the Electric Power Research Institute (EPRI). It further demonstrates the potential usefulness of the existing code in addressing fire-protection issues. This is done through a parametric study of the thermal environment resulting from a series of fires within cabinets in a nuclear power plant control room (similar to LaSalle). Also, it presents an example of how the code can be utilized by addressing an Appendix R exemption request which deals with the vulnerability of containment fans to a fire emanating from a reactor coolant pump bay. Recommendations are also given as to how the model/code can be further enhanced and where current effort is proceeding.

Page Last Reviewed/Updated Wednesday, March 24, 2021
Exhibit 24.8

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/ J. Alex ThramerJ. Alex Thramer




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

On this 20thday of March, 2007, before me, a Notary public qualified for said County, personally came J. Alex Thramer, 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
I 

115TH CONGRESS 

1ST SESSION H. R. 1820 

To authorize Department of Veterans Affairs health care providers to provide 

recommendations and opinions to veterans regarding participation in 

State marijuana programs. 

IN THE HOUSE OF REPRESENTATIVES 

MARCH 30, 2017 

Mr. BLUMENAUER (for himself, Mr. GARRETT, Mr. POLIS, Mr. AMASH, Ms. 

TITUS, and Mr. ROHRABACHER) introduced the following bill; which was 

referred to the Committee on Veterans’ Affairs 

A BILL 

To authorize Department of Veterans Affairs health care 

providers to provide recommendations and opinions to 

veterans regarding participation in State marijuana programs. 

1 Be it enacted by the Senate and House of Representa2 tives of the United States of America in Congress assembled, 

3 SECTION 1. SHORT TITLE. 

4 This Act may be cited as the ‘‘Veterans Equal Access 

5 Act’’. 


lotter on DSK5VPTVN1PROD with BILLS
2 

•HR 1820 IH

1 SEC. 2. PROVISION BY DEPARTMENT OF VETERANS AF2 FAIRS HEALTH CARE PROVIDERS OF REC3 OMMENDATIONS AND OPINIONS REGARDING 

4 VETERAN PARTICIPATION IN STATE MARI5 JUANA PROGRAMS. 

6 Notwithstanding any other provision of law, the Sec7 retary of Veterans Affairs shall authorize physicians and 

8 other health care providers employed by the Department 

9 of Veterans Affairs to— 

10 (1) provide recommendations and opinions to 

11 veterans who are residents of States with State 

12 marijuana programs regarding the participation of 

13 veterans in such State marijuana programs; and 

14 (2) complete forms reflecting such recommenda15 tions and opinions. 

Æ 


lotter on DSK5VPTVN1PROD with BILLS
44 F. (2d) 881

#### In re Thomas J. Dixon

(No. 2542)

United States Court of Customs and Patent Appeals,

December 1, 1930

*Harry F. Riley*(C?. *J. Rollandet*and *George 0. Shoemaker*of counsel) for appellant.

*T. A. Hostetler*for the Commissioner of Patents.

[Oral argument November 20, 1930, by Mr. Riley and Mr. Hostetler]

Before Graham, Presiding Judge, and Bland, Hatfield, Garrett, and Lenroot, Associate Judges

Graham, Presiding Judge,

delivered the opinion of the court::

The appellant has prepared a form of a promissory judgment note with attorney’s fee clause, and a declaration of lien written therein, and seeks to patent it under application, serial No. 123,682, filed July 20, 1926. Both the examiner and the Board of Appeals rejected the application on the ground that the alleged invention did not constitute a new and useful art, machine, manufacture, or composition of matter, or any new and useful improvements thereof, *712as required by section 4886, K.. S. We are in entire accord with the decisions of the Patent Office tribunals. The law is well settled by *Hotel Security, etc.,*v. *Lorraine Co.,*160 Fed. 467; *Berardini*v. *Tocci,*200 Fed. 1021; *Moore*v. *United States,*50 Ct. Cl. 120; *In re*Moeser, 27 App. D. C. 307.

The decision of the Board of Appeals is *affirmed.*
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Assessment of MSIV Full Closure for Santa Maria De Garoila Nuclear Power Plant Using TRAC-BFl (G1J1) (NUREG/IA-0122, ICSP–GA–MSIV–T)

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        - NUREG/IA-0122 (PDF 999.54 KB)

## Publication Information

**Date Published:** June 1993

**Prepared by:** J. L. Crespo/University of Cantabria R. A. Fernandez/Nuclenor, S. A.

University of Cantabria FAC Ciencias. Seccion De Fisicas. Nuclenor c/Hernan Cortes, 26 39080 Santander, Spain

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)

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

Availability Notice

## Abstract

This document presents a spurious MSIV closure analysis for Santa Maria de Garoña Nuclear Power Plan describing the problems found when comparing calculated and real data.

The plant is a General Electric Boiling Water Reactor 3, containment type Mark I. It is operated by NUCLENOR, S.A. and was connected to the grid in 1971.

The analysis has been performed by the Applied Physics Department from the University of Cantabria and the Analysis and Operation Section from NUCLENOR, S.A. as a part of an agreedment for developing an engineering simulator of operational transients and accidents for Santa Maria de Garoña Power Plant.

The analysis was performed using the frozen version of TRAC-BF1 (G1J1) code and is the second of two NUCLENOR contributions to the International Code Applications and Assessment Program (ICAP).

The code was run in a Cyber 932 with operating system NOS/VE, property of NUCLENOR, S.A.. A programming effort was carried out in order to provide suitable graphics from the output file.

Page Last Reviewed/Updated Tuesday, March 09, 2021
#### JOHN C. PETTIJOHN AND ANOTHER *against*HENRY WILLIAMS AND ANOTHER.

It is too late for a party to complain of a fraud in the quality of the thing sold, and seek for a rescission of the contract after he has used it for two years — has tested its qualities — has assigned his interest in it, and the thing itself has so deteriorated in value, that it cannot be restored in the same ¡slight and condition as when it was received by him.

This cause was before the Court upon an appeal from an interlocutory order of the Court of Equity of Martin County, and heard at the December Term, 1855, (ante 302.) The case is now brought up for a final hearing, and the facts are sufficiently stated in the report of that decision. «

liodmcm, for plaintiffs.

Smith, for defendants.

PbaRsoN, J.

When this case was before us at December Term, 1855, (ante 302,) a suggestion was made (for the consideration of counsel) that the plaintiff was too late in making his application, for the reasons which are there stated, and reference was made to the principle established by the case of *McDowell*v. *Simms,*Busb. Eq. 130. The question is now presented for a direct decision. There has been no amendment of the pleadings; no additional facts are brought out by the proofs, nor have we been favored with any argument of counsel to meet the difficulties which are there plainly pointed out as standing in the way of the plaintiffs. The consideration which we then bestowed upon the subject, inclined us to an opinion against the plaintiffs; the reflection which we have since bestowed upon it, satisfies us that the plaintiffs, at the time the bill was filed, had no equity, and that the principle established by McDowell v. Simms applies to our case.

Pee OueiaM. Bill dismissed.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsConference Proceedings Prepared by NRC Staff or Contractors

# Proceedings of the Workshop on Probabilistic Flood Hazard Assessment (PFHA): Held at the U.S. Nuclear Regulatory Commission Headquarters, Rockville, MD, January 29–31, 2013 (NUREG/CP-0302)

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        - NUREG/CP-0302 (PDF - 3.81 MB)

## Publication Information

**Manuscript Completed:**June 2013**Date Published:**October 2013

**Prepared by:**T. J. Nicholson and W. A. Reed

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

Availability Notice

## Abstract

The U.S. Nuclear Regulatory Commission's (NRC's) Offices of Nuclear Regulatory Research (RES), Nuclear Reactor Regulation (NRR) and New Reactors (NRO) organized this Workshop on Probabilistic Flood Hazard Assessment (PFHA). The workshop was held January 29-31, 2013 at the NRC headquarters auditorium, 11545 Rockville Pike, Rockville, MD. The workshop was coordinated with Federal agency partners: the U.S. Department of Energy (DOE), U.S. Department of the Interior's Bureau of Reclamation (BoR) and U.S. Geological Survey (USGS), U.S. Army Corps of Engineers (USACE), and Federal Energy Regulatory Commission (FERC). The research workshop was devoted to the sharing of information on probabilistic flood-hazard assessments for extreme events (i.e., annual exceedance probabilities much less than 2.0E3 per year) from the Federal community. The topics included: Federal agencies interests and needs in PFHA; State of the Practice in Identifying Extreme Flood Hazards; Extreme Precipitation Events; Flood-Induced Dam and Levee Failures; Tsunami Flooding; Riverine Flooding; Extreme Storm Surges for Coastal Areas; and Combined Events Flooding. The workshop objectives included to: (1) assess, discuss, and inform workshop participants on the state of the practice for extreme flood assessments within a risk context, (2) facilitate the sharing of information between both Federal agencies and other interested parties to bridge the current state of knowledge between extreme flood assessments and risk assessments of critical infrastructures, (3) seek ideas and insights on possible ways to develop a PFHA for use in probabilistic risk assessments, (4) identify potential components of floodcausing mechanisms that lend themselves to probabilistic analysis and warrant collaborative study, and (5) establish realistic plans for coordination of PFHA research studies. Observations and insights provided during session presentations and subsequent panel discussions that followed were documented by the panel reporters and are included in this report.

Page Last Reviewed/Updated Wednesday, March 24, 2021
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# A Summary of Nuclear Power Plant Fire SafetyResearch at Sandia National Laboratories, 1975–1987 (NUREG/CR-5384, SAND89-1359)

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        - NUREG/CR-5384 (PDF - 7.17 MB)

## Publication Information

**Manuscript Completed:**December 1989**Date Published:**December 1989

**Prepared by:** Steven P. Nowlen Sandia National Laboratories  Albuquerque, New Mexico 87185

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

NRC FIN A-1010

Availability Notice

## Abstract

This report summarizes the results and conclusions generated by the U.S. Nuclear Regulatory Commission sponsored Fire Protection Research Program at Sandia National Laboratories. Efforts conducted from the program's inception in 1975 through 1987 are discussed. The individual efforts are discussed within a framework based on specific areas of investigation. Early efforts are presented in the context of investigations of specific regulatory concerns. Later efforts are presented within the context of an integrated investigation of fire safety issues. This integrated approach considers the fire safety issue in terms of (1) source fire characterization, (2) detection and suppression system effectiveness, (3) room effects, (4) equipment response, and (5) room-to-room fire effects. The report provides a complete bibliography of reports and journal articles generated as a result of these efforts with a cross-reference listing of major reports to specific efforts.

Among the topics investigated by various experimental efforts are the effectiveness of fire retardant cable coatings and cable tray fire barrier systems in the prevention of fire spread and fire induced damage, the effectiveness of suppression methods for cable tray fires, testing of cable penetration seals, transient fuel fire characterization testing, investigation of electrical cabinet and control room fires, equipment damageability testing, and large scale enclosure fire testing for the validation of computer fire simulation codes. Topics investigated as a part of analytical efforts include a review of the fire regulations which bear relevance to nuclear plants, investigation of the standards and strategies invoked in the design of various fire protection subsystems, the modeling of cable fire behavior, the identification of reported transient fuel sources, and the development of a fire occurrence data base.

Page Last Reviewed/Updated Wednesday, March 24, 2021
<PAGE>

                                                                    Exhibit 99.2

                            CERTIFICATION PURSUANT TO
                               18 U.S.C. (S)1350,
                             AS ADOPTED PURSUANT TO
                  SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002

In connection with the Quarterly Report of Velocity Express Corporation (the
"Company") on Form 10-Q for the period ended December 28, 2002 as filed with
the Securities and Exchange Commission on the date hereof (the "Report"), I,
Mark E. Ties, Chief Financial Officer of the Company, certify, pursuant to 18
U.S.C. (S)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 results of operations
          of the Company.


                                          /s/ Mark E. Ties
                                          ----------------------------------
                                          Mark E. Ties
                                          Chief Financial Officer
                                          February 11, 2003
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsConference Proceedings Prepared by NRC Staff or Contractors

# Proceedings of the Advisory Committee on Nuclear Waste Transportation Working Group Meeting:November 19–20, 2002, and April 22, 2003 (NUREG/CP-0182)

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        - NUREG/CP-0182            - Cover through Chapter 1 (PDF - 695 KB)            - Chapter 2 (PDF - 12.1 MB)
          - Chapter 3 (PDF - 9.66 MB)
          - Chapter 4 through Appendices (PDF - 8.47 MB) 

## Publication Information

**Manuscript Completed:**June 2003**Date Published:**September 2003

**Proceedings****Edited by:** Timothy J. Kobetz, Senior Staff Engineer

**Proceedings Prepared by:** Advisory Committee on Nuclear Waste U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

This report contains the information presented at the Advisory Committee on Nuclear Waste Transportation Working Group (TWG) Meeting held at the U.S. Nuclear Regulatory Commission (NRC) headquarters in Rockville, Maryland, on November 19-20, 2002. Summaries of participant discussions and the presentation material provided during the meeting are included. In addition, Appendix D to this report contains information presented at the TWG Follow-On Meeting conducted on April 22, 2003.

The objective of these two meetings was to examine the technical aspects of spent fuel transportation package design, analysis, and testing to determine whether sufficient evidence exists or additional evidence needs to be obtained to substantiate that spent fuel can be transported safely. In addition, spent fuel and high-level waste transportation experience was reviewed to determine whether the transportation packages used have performed as designed. Various national laboratories, cask vendors, industry groups, and NRC staff who have been directly involved in the transportation of spent fuel and high-level waste over the past 30 years made presentations at the meetings. Past and future transportation safety studies were also discussed at the meetings. Special emphasis was placed on the transportation package because, if no significant package failure occurs, there can be no significant radiation consequences.

Page Last Reviewed/Updated Thursday, March 25, 2021
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# Evaluation of the Hualien Quarter Scale Model Seismic Experiment (NUREG/CR-6584)

Page Last Reviewed/Updated Wednesday, March 24, 2021