alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
[Federal Register Volume 80, Number 20 (Friday, January 30, 2015)]
[Notices]
[Page 5116]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-01817]


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

DEPARTMENT OF HEALTH AND HUMAN SERVICES

Centers for Disease Control and Prevention


Disease, Disability, and Injury Prevention and Control Special 
Emphasis Panel (SEP): Initial Review

    The meeting announced below concerns Occupational Safety and Health 
Education and Research Centers (ERC) PAR 10-217, initial review.
    In accordance with Section 10(a)(2) of the Federal Advisory 
Committee Act (Pub. L. 92-463), the Centers for Disease Control and 
Prevention (CDC) announces the aforementioned meeting:

    Times and Dates:
    6:00 p.m.-8:00 p.m., February 23, 2015 (Closed).
    8:00 a.m.-6:00 p.m., February 24, 2015 (Closed).
    8:00 a.m.-6:00 p.m., February 25, 2015 (Closed).
    8:00 a.m.-6:00 p.m., February 26, 2015 (Closed).
    Place: Renaissance Atlanta Midtown Hotel, 866 West Peachtree 
Street NW., Atlanta, Georgia 30308, Telephone: (678) 412-2400.
    Status: The meeting will be closed to the public in accordance 
with provisions set forth in Section 552b(c) (4) and (6), Title 5 
U.S.C., and the Determination of the Director, Management Analysis 
and Services Office, CDC, pursuant to Public Law 92-463.
    Matters for Discussion: The meeting will include the initial 
review, discussion, and evaluation of applications received in 
response to ``Occupational Safety and Health Education and Research 
Centers (ERC) PAR 10-217.''

FOR FURTHER INFORMATION CONTACT: George Bockosh, M.S., Scientific 
Review Officer, National Institute for Occupational Safety and Health 
(NIOSH), CDC, 2400 Century Center Parkway NE., 4th Floor, Mailstop E-
74, Atlanta, Georgia 30345, Telephone: (412) 386-6465, <a href="/cdn-cgi/l/email-protection#a6e1e1e496e6e5e2e588e1e9f0"><span class="__cf_email__" data-cfemail="90d7d7d2a0d0d3d4d3bed7dfc6">[email protected]</span></a> and 
Donald Blackman, Ph.D., Scientific Review Officer, NIOSH, CDC, 2400 
Century Center Parkway NE., 4th Floor, Room 4204, Mailstop E-74, 
Atlanta, Georgia 30345, Telephone: (404) 498-6185, <a href="/cdn-cgi/l/email-protection#4b0f12097c0b080f08650c041d"><span class="__cf_email__" data-cfemail="53170a1164131017107d141c05">[email protected]</span></a>.
    The Director, Management Analysis and Services Office, has been 
delegated the authority to sign Federal Register notices pertaining to 
announcements of meetings and other committee management activities, 
for both the Centers for Disease Control and Prevention and the Agency 
for Toxic Substances and Disease Registry.

Elaine L. Baker,
Director, Management Analysis and Services Office, Centers for Disease 
Control and Prevention.
[FR Doc. 2015-01817 Filed 1-29-15; 8:45 am]
BILLING CODE 4163-18-P


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#### Knutson, Respondent, vs. Munson, Appellant.

*April 14*

May *9, 1933.*

For the appellant there was a brief by *Beck, Smith & Heft*of Racine, and oral argument by *Lawrence H. Smith.*

For the respondent there was a brief by *Thompson, Myers & Helm*of Racine, and oral argument by *Peter J. Myers*and *Samuel P. Myers.*

Rosenbeery, C. J.

We shall not enter upon any extended consideration of the matters involved in this case which were before this court and reported in *Knutson v. Munson,*207 Wis. 248, 240 N. W. 542. We have carefully examined the record and the judgment entered appears to conform with the mandate of this court. Upon the oral argument it was stated that a motion was pending in the lower court at the time the appeal was taken to correct the judgment in some particular. It was conceded by the defendant that if the plaintiff prevailed the correction should be made. The judgment will be affirmed, therefore, without prejudice to the right of the plaintiff to have the motion already pending determined and the judgment corrected accordingly.

*536After the case had been heard in this court and the record remanded to the trial court, the defendant sought to have the state made a party on the ground that the lands involved were at one time submerged and that the title thereto was in the state. It does not follow that, because the level of the lake was lowered by artificial means, the state has title to the lands which were formerly submerged. However, we shall not determine or discuss that question here as the state is not a necessary or even a proper party to a determination of the controversy between the plaintiff and the defendant.

Error is also assigned because judgment was rendered in favor, of the plaintiff and against the defendant for $50 damages. The judgment is sustained by the findings. There being no bill of exceptions and the findings sustaining the judgment, the judgment must be affirmed. *Weyerhaeuser v. Earley,*99 Wis. 445, 78 N. W. 80.

*By the Court.*— Judgment affirmed, and cause remanded for further proceedings as indicated in the opinion.
<TABLE> <S> <C>

<ARTICLE> 5
<LEGEND>
THIS SCHEDULE CONTAINS SUMMARY FINANCIAL INFORMATION EXTRACTED FROM THE
FINANCIAL STATEMENTS OF PETRACOM HOLDINGS, INC. FOR THE THREE MONTHS ENDED MARCH
31, 1997 AND IS QUALIFIED IN ITS ENTIRETY BY REFERENCE TO SUCH FINANCIAL
STATEMENTS.
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<CURRENCY> U.S. DOLLARS
       
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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Standard Review Plan for Transportation Packages for Radioactive Material (NUREG-1609)

 

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff for Knowledge Management

# Reflections on Fukushima: NRC Senior Leadership Visit to Japan, 2014 (NUREG/KM-0008)

On this page: 
        - Publication Information
        - Introduction

Download complete document
        - NUREG/KM-0008 (PDF - 5.15 MB)

## Publication Information

**Date Published:** December 2014

**Prepared by:** C. Rosales-Cooper, M. Johnson, E. Leeds, G. Tracy, J. Wiggins, B. Dean, V. McCree, C. Pederson, M. Dapas, K.S. West, S. Flanders, D. Skeen, R. Hannah, K. Foggie

Office of the Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Introduction

The senior leadership of the U.S. Nuclear Regulatory Commission's (NRC's) reactor and preparedness programs visited Japan from February 16- 23, 2014. The purpose of that visit was to provide an opportunity for the group to gain firsthand experiences and insights into the March 2011 accident at the Fukushima Daiichi Nuclear Power Plant site.

This NUREG report is a compilation of personal reflective essays from the group of senior managers and staff that participated in the February 2014 visit to Japan and includes a video of individual interviews and the April 24, 2014 Knowledge Management Seminar: Reflections on Fukushima.

The titles and offices of the senior managers and staff reflect individual positions as of February 2014.

Page Last Reviewed/Updated Wednesday, March 24, 2021
Exhibit 32.2

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

I, Robert Krebs, certify, pursuant to 18 U.S.C. Section 1350, as adopted
pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, that the Quarterly
Report of TelePlus Enterprises, Inc. on Form 10-KSB for the year ended December
31, 2005 fully complies with the requirements of Section 13(a) or 15(d) of the
Securities Exchange Act of 1934 and that information contained in such Form
10-QSB fairly presents in all material respects the financial condition and
results of operations of TelePlus Enterprises, Inc.

Date:  March 31, 2006

                                       By: /s/ Robert Krebs
                                           -------------------------------------
                                           Robert Krebs
                                           Chief Financial Officer
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC Approves Transfer of License for Colorado Spent Fuel Storage Facility to DOE

----

----

No. 99-120 June 7, 1999

**NRC APPROVES TRANSFER OF LICENSE FOR COLORADO SPENT FUEL STORAGE FACILITY TO DOE**

The Nuclear Regulatory Commission has approved transfer of the license for the Fort St. Vrain spent nuclear fuel storage installation from Public Service Company of Colorado to the Department of Energy (DOE).

The facility is located adjacent to the former Fort St. Vrain nuclear power plant in Platteville, Colorado. Public Service, which operated the nuclear power plant, is the current license holder for the storage facility. The facility and spent fuel will remain in the same location, but DOE will assume responsibility for it.

DOE submitted an application for transfer of the license in December 1996. The NRC staff conducted an extensive review of the application and performed on-site inspections of DOE's readiness to assume license responsibilities. The results of the staff's licensing review are documented in a safety evaluation report.

Copies of the report and an NRC order and license amendment authorizing the transfer will be available from the NRC Public Document Room, 2120 L Street, N.W., Washington D.C. 20555; telephone 202/634-3273.

The agency published a Federal Register notice in March 1997 describing the proposed license transfer and offering an opportunity to request a hearing on the action. No requests were received.

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

# Investigation of Distorted-Geometry Simulation of Pool Dynamics in Horizontal-Vent BWR Containments

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-1444 (PDF - 1.57 MB)

## Publication Information

**Manuscript Completed:**May 1979 **Date Published:**April 1980

**Prepared by:** N.G. Ruggieri, A.A. Sonin Department of Mechanical Engineering Massachusetts Institute of Technology Cambridge, MA 02139

**Prepared for:** Division of Reactor Safety Research Office of Nuclear Regulatory Research U. S. Nuclear Regulatory Commission Washington, D.C. 20555

NRC FIN No. B6167

Availability Notice

## Abstract

Experiments were conducted to investigate the accuracy of distorted-geometry testing of pool dynamics in horizontal-vent BWR containments. Distorted-geometry testing implies testing in systems where the flow-wise dimensions are full scale, but all dimensions transverse to the flow are reduced in the same proportion. The assumption is that flow velocities, pressures and other thermodynamic properties can be interpreted as being the same in the distorted-geometry system as in its correctly proportioned counterpart. Our experiments, which were done at small scale using the established scaling laws, showed that the geometric distortions can have a significant effect on the pool swell under conditions which are roughly representative of horizontal-vent BWR containment systems during a LOCA. Breakthrough occurred later, the water ligament was thicker, and pool velocity lower in a system where the cross-sectional areas were reduced by a factor of three. Some reasons for the differences are discussed.

Page Last Reviewed/Updated Wednesday, March 24, 2021
No. 86-992.

#### Reardon *v.*Reardon et al.

C. A. 3d Cir. Certiorari denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# RELAP5 Extended Station Blackout Analyses

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0424 (PDF - 2.63 MB)

## Publication Information

**Manuscript Completed:** January 2013**Date Published:** March 2013

**Prepared by:** A. Prošek, B. Mavko

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

A. Calvo, NRC Project Manager

**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

Following the accident at the nuclear power plant Fukushima in Japan the stress test were performed in European countries. Considering the stress tests specifications it was necessary to evaluate the consequences of loss of safety functions from any initiating event (earthquake or flooding) for loss of electrical power, including Station Blackout (SBO), loss of the ultimate heat sink or combination of both. In this report long term station blackout sequences for Krško twoloop pressurized water reactor with loss of normal or all secondary side heat sinks were performed. For calculations the latest RELAP5/MOD3.3 Patch 04 computer code was used. The verified standard RELAP5/MOD3.3 input model delivered by Krško nuclear power plant was used.

SBO scenario involves a loss of offsite power, failure of the redundant emergency diesel generators, failure of alternate current power restoration and the eventual degradation of the reactor coolant pump seals resulting in a long term loss of coolant. In the study different reactor coolant pump seal leaks were studied due to SBO. Besides, scenarios were performed for different primary side depressurizations performed by operator through the secondary side power operated relief valves, providing that turbine driven auxiliary feedwater pump is available. Finally, the effect of having some injection into the reactor coolant system was also evaluated. It can be concluded that calculated results obtained by RELAP5 give good indication about time available before core degradation started. The results suggest that RELAP5 can be used for extended SBO studies until core damage started. It is especially useful in studying maintaining core cooling function and time available before core uncovers as part of severe accident management. The benefit of using RELAP5 is in the fact that best estimate system codes are more accurate than severe accident codes in phases before core degradation started.

Page Last Reviewed/Updated Tuesday, March 09, 2021
#### Arnold and others, Respondents, vs. Rock and others, Defendants: Schwartz and others, Appellants.

For the appellants: *Salen ■& Brenner*of Waukesha, attorneys, and *Harvey L. Cavender*of Chicago, Illinois, of counsel.

For the respondents: *Frame & Blackstone*of Waukesha.

*By the Court.*

Judgment affirmed.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Evaluation of Human Reliability Analysis Methods Against Good Practices (NUREG-1842)

 On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG-1842 (PDF - 17.2 MB)

## Publication Information

**Manuscript Completed:**August 2006**Date Published:**September 2006

**Prepared by:** J. Forester, Sandia National Laboratories A. Kolaczkowski, Science Applications International Corporation E. Lois, U.S. Nuclear Regulatory Commission D. Kelly, Science Applications International Corporation

Sandia National Laboratories P.O. Box 58000, MS-0748 Albuquerque, NM 87185

Science Applications International Corporation 405 Urban Street, Suite 400 Lakewood, CO 80220

E. Lois, NRC Project Manager

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

Job Code Number Y6497

Availability Notice

## Abstract

The U.S. Nuclear Regulatory Commission (NRC) has developed guidance for performing or evaluating human reliability analyses (HRAs) to support risk-informed regulatory decision-making and, in particular, the implementation of Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," dated February 2004. The NRC's detailed HRA guidance was developed in two phases. The first phase focused on developing "Good Practices for Implementing Human Reliability Analysis," as documented in NUREG-1792, dated April 2005. The second phase, summarized in this report, evaluated the various HRA methods that are commonly used in regulatory applications in the United States, with a particular focus on the extent to which they provide guidance to satisfy the good practices. Since the good practices closely parallel the requirements of the Probabilistic Risk Assessment (PRA) Standard (RA-S-2002) promulgated by the American Society of Mechanical Engineers (ASME), the HRA methods are also evaluated against that standard by implication. Toward that end, this report includes observations regarding the respective strengths and limitations of the HRA methods, as well as summaries of the scope, underlying knowledge base, and sources of quantification data associated with each method.

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Analysis of the Critical Flow Model in TRAC-BF1 (NUREG/IA-0160)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0160 (PDF 2.02 MB)

## Publication Information

**Date Published:** May 1999

**Prepared by:** M. Gómez, E. Valero, I. E. Parra

Department of Applied Mathematics and Statistics Universidad Politécnica de Madrid Spain

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)

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

Availability Notice

## Abstract

Five Marviken Tests are modelled using TRAC-BF1. The code simulations are compared to Marviken data so as to analyse the capacity of TRAC-BF1 to reproduce subcooled and saturated blowdowns under critical conditions. Consequently, the critical flow model included in TRAC-BF1 will be validated.

Owing to the quasi-steady flow arising through the waste pipe, conserved quantities are useful to check the results accuracy. The influence of mesh refinement is also analysed.

Conclusions indicate that critical conditions must be imposed at the adequate sections to assure the calculations admissibility. However, the critical flow model introduces intrinsic errors that cannot be eliminated by means of mesh refinement.

Page Last Reviewed/Updated Tuesday, March 09, 2021
# L_2017098DE.01004401.xml

| 11.4.2017 | DE | Amtsblatt der Europäischen Union | L 98/44 |
| --- | --- | --- | --- |

11.4.2017

DE

Amtsblatt der Europäischen Union

L 98/44

---

Berichtigung der Verordnung (EU) 2015/995 der Kommission vom 8. Juni 2015 zur Änderung des Beschlusses 2012/757/EU über die technische Spezifikation für die Interoperabilität des Teilsystems „Verkehrsbetrieb und Verkehrssteuerung“ des Eisenbahnsystems in der Europäischen Union

(
  Amtsblatt der Europäischen Union L 165 vom 30. Juni 2015
  )

Seite 47, Anhang zur Ersetzung von Anhang I des Beschlusses 2012/757/EU, Anlage C Nummer 1.1 Satz 1:

Anstatt:

„In dieser Anlage werden Regeln für die sicherheitsrelevante Kommunikation zwischen dem Zugpersonal, in erster Linie dem Triebfahrzeugführer, und dem Zugfahrten zulassenden Personal des Infrastrukturbetreibers festgelegt und insbesondere die Struktur und Methodik dieser Kommunikation definiert.“

muss es heißen:

„In dieser Anlage werden Regeln für die sicherheitsrelevante Kommunikation zwischen dem Zugpersonal, in erster Linie dem Triebfahrzeugführer, und dem Fahrdienstleiter festgelegt und insbesondere die Struktur und Methodik dieser Kommunikation definiert.“

---
UNPUBLISHED UNITED STATES COURT OF APPEALS FOR THE FOURTH CIRCUIT
No. 97-6738
UNITED STATES OF AMERICA, Plaintiff - Appellee, versus RANDY JAY MILLER, Defendant - Appellant.Appeal from the United States District Court for the Eastern District of Virginia, at A lexandria. Albert V. Bryan, Jr., Senior District Judge. (CR-89-109-A, CA-97-612-AM) Submitted: January 22, 1998 Decided: February 4, 1998 Before WIDENER, MICHAEL, and MOTZ, Circuit Judges. Dismissed by unpublished per curiam opinion. Randy Jay Miller, Appellant Pro Se. Constance Harriet Frogale, OFFICE OF THE UNITED STATES ATTORNEY, Alexandria, Virginia, for Appellee. Unpublished opinions are not binding precedent in this circuit. See Local Rule 36(c).2 PER CURIAM: Appellant seeks to appeal from the district court's orders dismissing for failure to obtain autho rization pursuant to 28 U.S.C.A. § 2244 (West Supp. 1997), his second motion filed under 28 U.S.C.A. § 2255 (West 1994 & Supp. 1997). We have reviewed therecord and the district court's opinion and find no abuse of discretion and no reversible error. Accordingly, we deny a certificate of appealability and dismiss the appeal on the reasoning of the district court. United States v. Miller , Nos. CR-89-109-A; CA-97- 612-AM (E.D. Va. Apr. 29, 1997). We dispense with oral argument because the facts and legal contentions are adequately presented inthe materials before the court and argument would not aid the decisional process.

DISMISSED