alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
Exhibit 99.2



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 Quarterly Report of Star Gas
Partners, L.P. (the Partnership) on Form 10-Q for the quarterly period ended December 31, 2002 as filed with the Securities and Exchange Commission on the date hereof (the Report), I, Ami Trauber, Chief Financial Officer of
the Partnership, certify pursuant to 18 U.S.C. Section 1350, as adopted pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, following due inquiry, I believe 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 Partnership.
| | --- |  | -------------------------------------------------------------------------------------------------------------------------------------------------------



STAR GAS PARTNERS, L.P. By: STAR GAS LLC (General Partner)May 8, 2003





By:

/s/    AMI TRAUBERAmi Trauber Chief Financial Officer
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# LBLOCA Uncertainty Analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP and DAKOTA (NUREG/IA-0509)

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        - Publication Information
        - Abstract

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        - NUREG/IA-0509 (PDF – 1.80 MB)

## Publication Information

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

**Prepared by:** Chunkuan Shih, Jong-Rong Wang, Jian-Ting Chen, Yuh-Ming Ferng, Shao-Wen Chen, Ting-Yi Wang *, and 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

* Department of Nuclear Safety, Taiwan Power Company 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:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

Availability Notice

## Abstract

The objective of this study is to assess the applicability of the RELAP5/MOD3.3 model of Maanshan NPP on LBLOCA transient. Maanshan NPP was the first three-loop PWR in Taiwan constructed by Westinghouse. The total power of the two units of the power plant is 2785 MWt, which consist of 2775 MWt for reactor power and 10 MWt for cooling pumps. For the last few years, the TRACE model of Maanshan NPP was developed and several kinds of transient event including the LOCA, AOO and the URG transient were performed and verified. Recently, the RELAP5/MOD3.3 code is another important development priority for our group. In 2015, the RELAP5/MOD3.3 model of Maanshan NPP was developed with SNAP interface. 

An uncertainty analysis methodology of the postulated LBLOCA for Maanshan NPP using RELAP5/MOD3.3, DAKOTA, and SNAP codes are established in this study. The uncertainty parameters are related to ECCS property. The ranges of uncertainty analysis are based on FSAR and Training Manual of Maanshan. The maximum PCT of the uncertainty analysis is 1293 K. The PCT of FSAR is 1383.7 K. Hence, the result of the uncertainty analysis is below the FSAR data. The difference of uncertainty analysis results and FSAR data may be caused by the different calculation procedures, phenomenological modeling, and nodalization, etc. Additionally, the PCT criteria of 10 CFR 50.46 is 1477.6 K (2200°F). The prediction of the uncertainty analysis is below the criteria of 10 CFR 50.46. This implies that Maanshan NPP in LBLOCA transient is at a safety situation when ECCS is performed. 

Page Last Reviewed/Updated Tuesday, March 09, 2021
<PAGE>

                                                                    EXHIBIT 99.2

                    CERTIFICATION OF CHIEF FINANCIAL OFFICER
            PURSUANT TO SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002

           In connection with the Quarterly Report of Form 10-Q of Kensey Nash
Corporation (the "Company") for the three months ended December 31, 2002 as
filed with the Securities and Exchange Commission on the date hereof (the
"Report"), I, Wendy F. DiCicco, Chief Financial 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 section 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.


Dated: February 14, 2003                          /s/ Wendy F. DiCicco, CPA
                                                  ------------------------------
                                                  Wendy F. DiCicco, CPA
                                                  Chief Financial Officer





                                       24
# Fourth Court of Appeals **San Antonio, Texas**

MEMORANDUM OPINION

N o. 04

- 19

- 00821

- CV

Larry LANGSTON

, Appellant

v.

Tom HAYDEN and Shirley Hayden, Appellees

From the County Court a t Law No

. 2, Guadalupe County, Texas Trial Court No. 2019

- CV

- 0211 Honorable Bill Squires, Judge Presiding

PER CURIAM

Sitting: Rebeca C. Martinez, Justice Patricia O. Alvarez, Justice Luz Elena D. Chapa, Justice

Delivered and Filed: Apr il 29, 2020

DIS MISSED FOR WANT OF PROSECUT ION

Appellant’s brief was due to be filed by February 6, 2020 . Neither the brief nor a motion

for extension of time was filed. By order dated March 11, 2020 , appellant was ordered to show

cause in writing by March 26, 2020 , why this appeal should not be dismissed for want of

prosecution. T EX

. R. A PP

. P. 38.8(a). Appellant did not respond to this court’s order. Because

appellant failed to timely file a brief in this appeal, this appeal is dismissed for want of prosecution.

See T EX

. R. A PP

. P. 38.8(a), 42.3(b ).

PER CURIAM
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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Assessment Against ACHILLES Reflood Experiment with TRACE V5.0 Patch3 (NUREG/IA-0441)

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        - Publication Information
        - Abstract

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        - NUREG/IA-0441 (PDF - 2.99 MB)

## Publication Information

**Manuscript Completed:** November 2013**Date Published:** February 2014

**Prepared by:**O. A. Berar, A. Prošek

Jožef Stefan InstituteJamova cesta 39Sl-1000 Ljubljana, Slovenia

Kirk 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

At present time, the development of the U.S. Nuclear Regulatory Commission RELAP5 has been ceased in favor of the newer TRACE best estimate system code. The present work presents the assessment of the Achilles natural reflood experiment with the TRACE V5.0 Patch 3. In addition, comparison calculations with TRACE V5.0 Patch 1 and latest RELAP5/MOD3.3 Patch 4 were performed. The TRACE input deck has been obtained by conversion of the already existing RELAP5 input deck. The calculated results were compared against the experimental data. The results show that both TRACE and RELAP5 are capable of reproducing the reflood phenomena at a satisfactory level. However, some discrepancies between the predicted variables and the experimental data suggest further investigation of the TRACE reflood model.

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

# Aging Effects on Fire-Retardant Additives in Organic Materials for Nuclear Plant Applications (NUREG/CR-2868,SAND82-0485)

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        - Publication Information
        - Abstract

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        - NUREG/CR-2868 (PDF - 1.36 MB)

## Publication Information

**Manuscript Completed:**August 1982****Date Published:****August 1982

**Prepared by:** Roger L. Clough Sandia National Laboratories Albuquerque, New Mexico 87185 Operated by Sandia Corporation for the U.S. Department of Energy Under Contract No. DE-AC04-76DP00789 

**Prepared for:** Electrical Engineering Branch Division of Engineering Technology 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-1051

Availability Notice

## Abstract

Inhibiting fire is a major concern of nuclear safety. One of the most widely used commercial fire-retardant additives incorporated into cable insulation and other organic materials to reduce their flammability has been the halocarbon (usually a chlorinated hydrocarbon), typically in combination with antimony oxide. Such materials may be installed for the design lifetime of a nuclear plant; this report describes an investigation of the long-term aging behavior of these fire-retardant additives in polymeric materials.

Extensive aging experiments on fire-retarded formulations of ethylene propylene rubber (EPR) and of chlorosulfonated polyethylene (CSPE) have been carried out, with chemical analysis of halogen and antimony content performed as a function of aging time and conditions. Oxygen index flammability measurements were also performed on selected samples. Significant fire-retardant losses (both chlorine (Cl) and antimony (Sb)) were found to occur in certain of the fire-retardant materials but not in others, depending on the molecular structure of the particular halogen-containing component. The Cl:Sb loss ratios indicate that a chemical reaction takes place under the aging conditions to form the volatile compound, antimony trichloride (SbC1 3). The EPR formulations showed a modestly increased flammability with fire-retardant loss on aging. CSPE materials exhibited a significant decrease in flammability on aging despite the loss of flame retardants. This appears to be correlated with the loss of flammable, volatile components from the formulation.

Using the activation energy of 34 kcal/mol derived from Arrhenius treatment of the antimony loss data for the EPR formulation having the most rapid loss rate, it is predicted that fire-retardant loss should become appreciable for this material only at substantially elevated temperatures or exceedingly long times. The data indicate that the loss of halogen- and antimony-based fire retardants appears to be insignificant under ambient conditions expected for nuclear plants.

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

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<MULTIPLIER> 1,000

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<PERIOD-START>                            JUL-01-2000        JAN-01-2000
<PERIOD-END>                              SEP-30-2000        SEP-30-2000
<CASH>                                          8,490              8,490
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<EPS-BASIC>                                     $0.24              $0.58
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</TABLE>
**Exhibit 32.2**

 

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

 

In connection with the Annual Report on Form 10-K of TransmeridianExploration, Inc. (the “Company”) for the period ended December 31, 2004as filed with the Securities and Exchange Commission on the date hereof (the “Report”),I, Earl W. McNiel, Vice President and Chief Financial Officer of the Company,certify pursuant to 18 U.S.C. Section 1350, as adopted pursuant to Section 906of the Sarbanes-Oxley Act of 2002, that:

 

(1)     TheReport fully complies with the requirements of Section 13(a) or 15(d) ofthe Securities Exchange Act of 1934, as amended; and

 

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

 
| Date: March 14, 2005 |   |
|----------------------|--------|
|                 |   |
|                 |   |
|                 | By:    | /s/ Earl W. McNiel |   |
|                 |   | Earl W. McNiel |
|                 |   | Vice President and Chief Financial Officer |

 

----
The Honorable Dean Whipple, United States District Judge for 1

the Western District of Missouri.

United States Court of Appeals

FOR THE EIGHTH CIRCUIT

___________

No. 96-1181

___________

Joseph H. Brown, Sr., *

*

Appellant, *

* Appeal from the United States

v. * District Court for the

* Western District of Missouri.

United States of America, *

* [UNPUBLISHED]

Appellee. *

___________

 Submitted: April 30, 1997

 Filed: May 3, 1997

___________

Before BOWMAN, WOLLMAN, and BEAM, Circuit Judges.

___________

PER CURIAM.

Joseph H. Brown, Sr., appeals the district court’s denial of his 28 1

U.S.C. § 2255 motion. Upon a de novo review of the record, we are

persuaded that the motion, files, and records of the case conclusively show

Brown is not entitled to relief. See United States v. Duke, 50 F.3d 571,

576 (8th Cir.) (standard of review), cert. denied, 116 S. Ct. 224 (1995).

Accordingly, we affirm for the reasons stated in the district court’s

opinion. See 8th Cir. R. 47B.
-2-

A true copy.

Attest:

CLERK, U. S. COURT OF APPEALS, EIGHTH CIRCUIT.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Evaluation of Available Data for Probabilistic Risk Assessments (PRA) of Fire Events at Nuclear Power Plants (NUREG/CR-4231, BNL-NUREG-51879)

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        - Publication Information
        - Abstract

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        - NUREG/CR-4231 (PDF - 2.78 MB)

## Publication Information

**Manuscript Completed:**February 1985**Date Published:**May 1985

**Prepared by:** L.M. Krasner, C.S. Ganti, B.G. Vincent, Factory Mutual Research P.K. Samanta, J.L. Boccio, Brookhaven National Laboratory

Factory Mutual Research Norwood, MA 02062

**Under Contract to:** Department of Nuclear Energy  Brookhaven National Laboratory  Upton, NY 11973

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

NRC FIN A-3710

Availability Notice

## Abstract

Several crucial parameters are needed in the assessment of fire risk in nuclear power plants. Among those that need to be developed from a data base are: (1) fire frequency, (2) fire detection time, and (3) fire suppression time. Currently, the data base for nuclear power plants is not large enough to develop these parameters, considering fuel location, fuel geometry, combustion properties, enclosure geometry, etc. This study attempts to augment the nuclear data base by investigating the usefulness of other nonnuclear data bases which contain fire incident loss experience of occupancy classes having somewhat similar physical features and fire protection engineering systems normally found in nuclear power plants. This study has found that indeed some useful information can be gleaned from nonnuclear sources; in particular, detection and suppression times. However, other fire-risk data needs such as fire frequency and fire size would require other forms of data searches and data analyses that at this stage can only be conceptualized.

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

# The Atomic Safety and Licensing Board Panel (NUREG/BR-0249)

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

# Development and Application of a Computer Model for Large-Scale Flame Acceleration Experiments (NUREG/CR-4855, SAND87-8203)

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        - Publication Information
        - Abstract

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        - NUREG/CR-4855 (PDF - 3.16 MB)

## Publication Information

**Manuscript Completed:**April 1987**Date Published:**July 1987 

**Prepared by:** K.D. Marx  Sandia National Laboratories  Thermofluids Division (Division 8363) Livermore, California 94550 Operated by Sandia Corporation for the U.S. Department of Energy Under Contract No. DE-AC04-76DP00789

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

Under Memorandum of Understanding DOE 40-550-75

NRC FIN A-1246

Availability Notice

## Abstract

A new computational model for large-scale premixed flames is developed and applied to the simulation of flame acceleration experiments. The primary objective is to circumvent the necessity for resolving turbulent flame fronts; this is imperative because of the relatively coarse computational grids which must be used in engineering calculations. The essence of the model is to artificially thicken the flame by increasing the appropriate diffusivities and decreasing the combustion rate, but to do this in such a way that the burn velocity varies with pressure, temperature, and turbulence intensity according to prespecified phenomenological characteristics. The model is particularly aimed at implementation in computer codes which simulate compressible flows. To this end, it is applied to the two-dimensional simulation of hydrogen-air flame acceleration experiments in which the flame speeds and gas flow velocities attain or exceed the speed of sound in the gas. It is shown that many of the features of the flame trajectories and pressure histories in the experiments are simulated quite well by the model. Using the comparison of experimental and computational results as a guide, some insight is developed into the processes which occur in such experiments.

Page Last Reviewed/Updated Wednesday, March 24, 2021