alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
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# The Effect of Thermal and Irradiation Aging Simulation Procedures on Polymer Properties (NUREG/CR-3629, SAND83-2651)

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## Publication Information

**Manuscript Completed**: February 1984****Date Published****: April 1984 

**Prepared by:** L.D. Bustard and E. Minor Sandia National Laboratories Albuquerque. New Mexico 87185, USA Operated by Sandia Corporation for the U.S. Department of Energy  Under Contract No. DE-AC04-76DP00789 

J. Chenion, F. Carlin, C. Alba, and G. Gaussens CEA-ORIS LABRA at Saclay 91190 Gif-sur-Yvette. France

M. LeMeur CEA-DAS-SAF 92260 Fontenay-aux-Roses. France

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

Under Interagency Agreement 40-550-75 

NRC FIN A-1051

Availability Notice

## Abstract

Prior to initiating a qualification test on safety-related equipment, the testing sequence for thermal and irradiation aging exposures must be chosen. Likewise, the temperature during irradiation must be selected. Typically, U.S. qualification efforts employ ambient temperature irradiation, while French qualification efforts employ 70° C irradiations. For several polymer materials, the influence of the thermal and irradiation aging sequence, as well as the irradiation temperature (ambient versus 70° C), has been investigated in preparation for Loss-of-Coolant Accident simulated tests.

 Ultimate tensile properties at completion of aging are presented for three XLPO and XLPE, five EPR and EPDM, two CSPE (HYPALON), one CPE, one VAMAC, one polydiallylphtalate, and one PPS material.

Bend test results at completion of aging are presented for two TEFZEL materials. Permanent set after compression results are presented for three EPR, one VAMAC, one BUNA N, one Silicone, and one Viton material.

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Assessment of RELAP5/MOD 2 Against Marviken Jet Impingement Test 11 Level Swell (NUREG/IA-0006)

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## Publication Information

**Date Published:** September 1986

**Prepared by:** 0. Rosdahl, D. Caraher

Swedish Nuclear Power Inspectorate P.O. Box 27106 S102 #52 Stockholm, Sweden

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

**Published by:** Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555

Availability Notice

## Abstract

RELAP5/MOD2 simulations of level swell of saturated liquid in a large (5 m diameter, 22 m high) vessel are reported. For certain nodalizations RELAP5 is shown to predict the measured void fraction profile with fair accuracy. RELAP5 results are shown to be dependent upon nodalization with the accuracy of computed results deteriorating significantly when a large number of nodes is employed.

Page Last Reviewed/Updated Tuesday, March 09, 2021
#### In re B.D. INTERNATIONAL DISCOUNT CORP., Debtor-Appellant.

No. 82 Civ. 0206 (DNE).

United States District Court, S.D. New York.

June 25, 1982.

*877Orenstein, Snitow, Sutak & Pollack, New York City, Franklyn H. Snitow, New York City, of counsel; Siegel, Sommers & Schwartz, New York City, for appellant.

Milbank, Tweed, Hadley & McCloy, New York City, Briscoe R. Smith, New York City, of counsel, for appellee.

EDELSTEIN, District Judge:

After careful consideration of the arguments presented to this Court by counsel in the memoranda they have submitted and at oral argument, and after reviewing the record of the proceedings before the Bankruptcy Court, 15 B.R. 755, the Court finds that:

1. WHEREAS the Bankruptcy Court correctly found under 11 U.S.C. § 303(h)(1) that appellant B.D. International Discount Corp. is generally not paying its debts as such debts become due so as to justify the entry of an order for relief; and

2. WHEREAS the Bankruptcy Court’s finding that appellant is generally not paying its debts as such debts become due is supported by competent evidence contained in the record of the proceedings before the Bankruptcy Court; and

3. WHEREAS a consideration of the record of the proceedings before the Bankruptcy Court satisfies this Court that the findings of fact and conclusions of law set forth by Bankruptcy Judge Lifland are not clearly erroneous.

IT IS HEREBY ORDERED that the entry by the Bankruptcy Court of an order for relief under Chapter 7 of the Bankruptcy Code, 11 U.S.C. §§ 101*et seq.,*is affirmed.
Fourth Court of Appeals

San Antonio, Texas

JUDGMENT

No. 04-13-00299-CV

IN THE INTEREST OF M.L.R., a Child

From the 150th Judicial District Court, Bexar County, Texas

Trial Court No. 2011-PA-03170

Honorable Gloria Saldaña, Judge Presiding

BEFORE CHIEF JUSTICE STONE, JUSTICE ANGELINI, AND JUSTICE MARTINEZ

In accordance with this court’s opinion of this date, the order of the trial court is 

AFFIRMED.

SIGNED August 21, 2013.

_____________________________

Catherine Stone, Chief Justice
No: IV-19-019 December 19, 2019

Contact: Victor Dricks, 817-200-1128

NRC Proposes $7,250 Fine to Stillwater Mining Co.

The Nuclear Regulatory Commission is proposing a $7,250 fine to the Stillwater Mining 

Co., of Nye, Mont., for failing to have a named individual perform the duties and responsibilities of 

a radiation safety officer. 

The violation of NRC requirements was identified in a Sept. 27, 2019, inspection report. It 

involved a nearly four-year failure by the company. Without a radiation safety officer, the company 

had no individual responsible for implementing the radiation safety program to ensure that safety 

significant issues are identified, corrected and reported to the NRC as required.

Eventual effective comprehensive corrective actions were taken; however, prompt corrective 

actions were not taken to restore compliance when the violation was identified during a third-party 

assessment in February 2019. The violation was not addressed until after it was identified by an 

NRC inspector in June 2019, as noted in a letter to the company.

Company officials responded to the NRC’s preliminary finding in a letter dated 

Oct. 25, 2019. The company has 30 days to dispute the fine or request involvement of a third-party 

mediator to resolve the issue.
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# Design Features for Enhancing InternationalSafeguards of Away-from-Reactor Dry Storage for Spent LWR Fuel (NUREG/CR-4517, PNL-5321)

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## Publication Information

**Manuscript Completed:**February 1986**Date Published:**October 1986

Prepared by: F.P. Roberts, N.L. Harms P.O. Box 999  Pacific Northwest Laboratory  Richland, Washington 99352  Operated by Battelle Memorial Institute 

**Prepared for:** Division of Safeguards Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

NRC FIN B-2475

Availability Notice

## Abstract

The Pacific Northwest Laboratory has performed a study for the Nuclear Regulatory Commission to identify and analyze design features that can facilitate the implementation of IAEA safeguards at away-from-reactor facilities for dry storage of light water reactor spent fuels. Thirteen specific design features are identified that can enhance verification of nuclear material flow and inventory. These are assessed from the viewpoint of safeguards effectiveness and possible impacts on the IAEA and the operator of the AFR facility.

Page Last Reviewed/Updated Wednesday, March 24, 2021
#### The People of the State of New York, Respondent, v Benjamin Heath, Appellant.

[631 NYS2d 964]

Judgment unanimously affirmed. Memorandum: At a *Wade*hearing prior to defendant’s first trial, a prosecution witness testified that she was shown photographs but failed to identify defendant from those photographs. Defendant’s conviction was reversed *(People v Heath,*175 AD2d 562). At the retrial, on cross-examination, that witness testified that she had identified defendant from photographs. When pressed by defense counsel, however, she equivocated and indicated that she believed that she had identified defendant from photographs. On appeal, defendant argues that the People violated CPL 710.30 by failing to provide notice that the witness had previously identified defendant from photographs.

By failing to object on that ground at trial, defendant did not preserve for our review his present argument *(see,*CPL 470.05 [2]). Reversal as a matter of discretion in the interest of justice is not warranted. The failure to identify defendant from photographs is not an identification procedure of which notice must be given *(see, People v Trammel,*84 NY2d 584), and the record supports the contention of the People that the witness did not identify defendant from photographs but was merely mistaken at defendant’s retrial *(see, People v Gholston,*178 AD2d 546, *lv denied*79 NY2d 947).

Defendant was not denied a fair trial when a defense witness made an unresponsive comment on cross-examination by the prosecutor concerning defendant’s prior conviction. The record does not support defendant’s assertion that the prosecutor purposefully elicited that comment. Moreover, the prosecutor did not exploit the situation but ignored the comment and did *805not refer to it on summation *(see, People v Sepulveda,*176 AD2d 196, 197, *lv denied*79 NY2d 864).

The verdict is not against the weight of the evidence. At the retrial, a prosecution witness testified that he observed defendant stab the victim. At defendant’s first trial, however, that same witness testified only that he observed defendant leave the restaurant with a knife in his hand and that he then realized that the victim had been stabbed. Although that testimony at the retrial is suspect, the remaining evidence, while circumstantial, strongly supports the jury’s determination that defendant stabbed the victim. We cannot conclude that the jury failed to give the evidence the weight it should be accorded *(see, People v Bleakley,*69 NY2d 490, 495). We decline to exercise our power to modify defendant’s sentence as a matter of discretion in the interest of justice *(see,*CPL 470.15 [6] [b]). (Appeal from Judgment of Oneida County Court, Murad, J.— Manslaughter, 1st Degree.) Present — Green, J. P., Lawton, Fallon, Doerr and Boehm, JJ.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsBrochures Prepared by NRC Staff

# Guide for Information Technology Security: Policy for Processing Unclassified Safeguards Information (SGI) on NRC Computers (NUREG/BR-0168, Revision 3)

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## Publication Information

**Date Published:**March 2004

Office of the Chief Information Officer U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

## Overview

## Policy for Processing Unclassified Safeguards Information (SGI) on NRC Computers

Safeguards information (SGI) is sensitive unclassified information about the security measures for the physical protection of special nuclear material, source material, byproduct material, and production and utilization facilities. Under NRC regulations, SGI must be protected and unauthorized disclosures of SGI are subject to civil and criminal sanctions.

The protective measures required for SGI are similar to those required for classified data at the confidential level. SGI may be stored, processed or produced only on a stand-alone personal computer (PC)–that is, a PC not physically or in any other way connected to the NRC or any other unclassified network. The standalone PC unit must have a removable storage medium with a bootable operating system. The bootable operating system must be used to load and initialize the computer. The removable storage medium must also contain the software application programs, and all data must be processed and saved on the same removable storage medium. A mobile device (such as a laptop computer) may also be used for the automated processing of SGI provided the device is secured in an appropriate storage container when not in use.

If a stand-alone or mobile personal computer has a removable drive, the operating system and the applications and data used for SGI processing must all reside on the same removable drive. The removable hard drive must be secured in an approved security container when not in use. SGI files may be transmitted across an unclassified network (e.g., a network not approved for the transmission of classified data), only if they have first been properly encrypted using encryption algorithms approved by the National Institute of Standards and Technology (NIST) or the National Security Agency (NSA). Contact the Computer Security Staff (CSS) in the Office of the Chief Information Officer (OCIO) for assistance in identifying approved methods of encryption. The OCIO CSS phone number is (301) 415-7430.

Page Last Reviewed/Updated Wednesday, March 24, 2021
No. 85-2079.

#### Laborers Health and Welfare Trust Fund for Northern California et al. *v.*Advanced Lightweight Concrete Co., Inc.

C. A. 9th Cir. Motions of National Coordinating Committee for Multiemployer Plans, Laborers International Union of North America National (Industrial) Pension Fund, and Construction Laborers’ Trust Funds for Southern California for leave to file briefs as *amici curiae*granted. Certiorari granted.
Summary of EPA Meeting with Textile Rental Services Association of America (TRSA)

October 5, 2011

On Wednesday, October 5, 2011, members from EPA’s Office of Resource Conservation and Recovery 

(ORCR) met with members of TRSA to answer their questions on the Solvent-Contaminated Industrial 

Wipes rulemaking. TRSA asked whether EPA was on track to finish the rulemaking. EPA confirmed that 

the rule is on schedule and is anticipated to be completed June 2012. TRSA also asked whether the 2011 

Definition of Solid Waste proposed rule (published July 22, 2011) would impact the wipes final 

rulemaking. EPA stated that the two rulemakings are separate and that the DSW final rulemaking was not 

expected to impact the schedule for the wipes final rule. TRSA asked whether they could include 

comments on potential impacts of the DSW proposed rule on the wipes rulemaking. EPA confirmed that 

TRSA could include any comments they would like. TRSA also discussed their LaundryESP program.

Attendees:

Amanda Geldard, EPA/ORCR

Richard Huggins, EPA/ORCR

Joseph Ricci, TRSA

Kevin Schwalb, TRSA

Jessica Skerritt, TRSA

John Wittenborn, Kelley Drye, LLP
Washington Bancorp

                    Computation of Earnings per Common Share
                                   Exhibit 11

<TABLE>



                                             For three months ended December 31,           For six months ended December 31,
                                          -----------------------------------------   --------------------------------------------
                                           1997        1996      1997        1996       1997       1996        1997        1996
                                           Basic       Basic    Diluted     Diluted     Basic      Basic      Diluted     Diluted
                                            EPS         EPS       EPS         EPS        EPS        EPS         EPS         EPS
                                          ----------------------------------------------------------------------------------------
<S>                                       <C>         <C>       <C>         <C>         <C>         <C>       <C>         <C>    

Computation of weighted average
number of common shares outstanding:

Common shares outstanding at the 
  beginning of the period ............     651,133    657,519    651,133     657,519    651,133    657,519     651,133     657,519
Unreleased common shares held by 
  the Employee Stock Ownership
  Plan (the "ESOP') at the beginning
  of the period ......................     (45,367)   (49,349)   (45,367)    (49,349)   (46,333)   (50,433)    (46,333)    (50,433)
Weighted average common shares 
  released by the ESOP during
  the period .........................         483        542        483         542        966      1,084         966       1,084
Weighted average common shares 
  equivalent of dilutive effect of
  stock options ......................          --         --     17,779       2,244         --         --      16,838         890
                                         -----------------------------------------------------------------------------------------
Weighted average number of common 
  shares .............................     606,249    608,712    624,028     610,956    605,766    608,170     622,604     609,060
                                         =========================================================================================

Net income ...........................   $ 199,230  $ 194,749  $ 199,230   $ 194,749  $ 356,450  $ 165,387   $ 356,450   $ 165,387
                                         =========================================================================================

Net income per common share ..........   $    0.33  $    0.32  $    0.32   $    0.32  $    0.59  $    0.27   $    0.57   $    0.27
                                         =========================================================================================
</TABLE>
WARNING: THE EDGAR SYSTEM ENCOUNTERED ERROR(S) WHILE PROCESSING THIS SCHEDULE.

<TABLE> <S> <C>


<ARTICLE>                     5
       
<S>                             <C>
<PERIOD-TYPE>                   3-MOS
<FISCAL-YEAR-END>                             DEC-31-1996
<PERIOD-END>                                  SEP-30-1996
<CASH>                                             53,306
<SECURITIES>                                            0
<RECEIVABLES>                                     153,977
<ALLOWANCES>                                            0
<INVENTORY>                                     9,635,910
<CURRENT-ASSETS>                                9,843,193
<PP&E>                                              1,780
<DEPRECIATION>                                          0
<TOTAL-ASSETS>                                  9,844,973
<CURRENT-LIABILITIES>                           9,428,969
<BONDS>                                                 0
<PREFERRED-MANDATORY>                                   0
<PREFERRED>                                             0
<COMMON>                                                0
<OTHER-SE>                                        416,004
<TOTAL-LIABILITY-AND-EQUITY>                    9,844,973
<SALES>                                         2,623,683
<TOTAL-REVENUES>                                2,623,683
<CGS>                                           2,283,981
<TOTAL-COSTS>                                   2,283,981
<OTHER-EXPENSES>                                  324,512
<LOSS-PROVISION>                                        0
<INTEREST-EXPENSE>                                      0
<INCOME-PRETAX>                                    15,190
<INCOME-TAX>                                            0
<INCOME-CONTINUING>                                15,190
<DISCONTINUED>                                          0
<EXTRAORDINARY>                                         0
<CHANGES>                                               0
<NET-INCOME>                                       15,190
<EPS-PRIMARY>                                           0
<EPS-DILUTED>                                           0
                                               


</TABLE>
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# PWR PACTEL Small Break LOCA Experiment SBL-50 Calculation with TRACE Code (NUREG/IA-0518)

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## Publication Information

**Manuscript Completed:** August 2019**Date Published:** January 2020

**Prepared by:** J. Vihavainen

Lappeenranta University of Technology P.O. Box 20 FI-53851 Lappeenranta Finland

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

TRACE is one of the main codes used for performing nuclear power plant thermal hydraulic safety analysis at present. Therefore, the importance of assessing the TRACE code capability to predict various thermal hydraulic transients in reactor systems becomes evident. One such transient that can occur small break loss-of-coolant-accident. The natural circulation is of particular interest for code assessment, as it requires the system code accurately predict temperature and density distributions throughout the system. Specific modeling capabilities are required for heat transfer and two-phase flow phenomena.

This research presents the assessment of the PWR PACTEL small break LOCA experiment SBL-50 with the TRACE V5.0 Patch 4. The PWR PACTEL facility is a modified version of the original PACTEL facility utilizing some parts of the original facility but also including completely new parts, i.e. loops and vertical steam generators (SG). The research focus with PWR PACTEL is set on the loop and vertical steam generator behavior in natural circulation conditions during small break LOCA event.

TRACE code was able to reproduce natural circulation phenomenon and small break LOCA conditions rather well. However, some discrepancies between the predicted variables and the experimental data suggests that further investigation of the TRACE modeling is necessary.

Page Last Reviewed/Updated Tuesday, March 09, 2021
#### O’Leary, Plaintiff in error, vs. The State, Defendant in-error.

*May 12*

June *18, 1928.*

*443The cause was submitted for the plaintiff in error on the brief of *Edward H. Ryan*and *L. A. Avery,*both of Janes-ville, and for the defendant in error on that of the *Attorney General, J. E. Messer schmidt,*assistant attorney general, and *George S. Geffs,*district attorney of Rock county.

Stevens, J.

Under the rule established in *Glodowski v. State,*decided herewith *{ante,*p. 265, 220 N. W. 227), the search warrant should not have been issued. It follows that the testimony of the officers who made the search should not be received in evidence.

But it does not follow that the defendant should be discharged, because the testimony of the witness Blakeley as to the purchase of home brew, which contained 2.05 per cent, of alcohol, is sufficient to sustain a conviction, if believed by the jury. If the evidence secured by the search under the invalid search warrant had not been received, the court would affirm the judgment.

But in view of the sharp conflict on the question whether this witness did in fact purchase any liquor in the home of the defendant, we are not able to say that substantial rights of the defendant were not prejudiced by the proof of the facts disclosed by the testimony of the officers who made the search. He is entitled to have his guilt or innocence determined upon a trial in which the jury shall have before them no proof of the facts discovered by the officers who made the search.

*By the Court.*— Judgment reversed. New trial ordered.