alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
# L_2015146EN.01002901.xml

| 11.6.2015 | EN | Official Journal of the European Union | L 146/29 |
| --- | --- | --- | --- |

11.6.2015

EN

Official Journal of the European Union

L 146/29

---

COMMISSION DECISION (EU) 2015/894

of 10 June 2015

appointing a member of the European Statistical Advisory Committee

THE EUROPEAN COMMISSION,

Having regard to the Treaty on the Functioning of the European Union,

Having regard to Decision No 234/2008/EC of the European Parliament and of the Council of 11 March 2008 establishing the European Statistical Advisory Committee and repealing Council Decision 91/116/EEC (1), and in particular Article 4(1)(a) thereof,

Whereas:

| (1) | The European Statistical Advisory Committee (ESAC) comprises 24 members. |
| --- | --- |

(1)

The European Statistical Advisory Committee (ESAC) comprises 24 members.

| (2) | Under Article 4(1) of Decision No 234/2008/EC, 12 members of the ESAC shall be appointed by the Commission. |
| --- | --- |

(2)

Under Article 4(1) of Decision No 234/2008/EC, 12 members of the ESAC shall be appointed by the Commission.

| (3) | By Commission Decision No 2014/C 138/02 of 5 May 2014, the Commission appointed 8 members of the ESAC and established a reserve list to be used in case of resignation or unexpected unavailability of an appointed member. |
| --- | --- |

(3)

By Commission Decision No 2014/C 138/02 of 5 May 2014, the Commission appointed 8 members of the ESAC and established a reserve list to be used in case of resignation or unexpected unavailability of an appointed member.

| (4) | As one of the members appointed by Decision No 2014/C 138/02 has resigned, the Commission should appoint a new member of the ESAC from the reserve list, for a term expiring on the same day as that of the members appointed by Decision No 2014/C 138/02. |
| --- | --- |

(4)

As one of the members appointed by Decision No 2014/C 138/02 has resigned, the Commission should appoint a new member of the ESAC from the reserve list, for a term expiring on the same day as that of the members appointed by Decision No 2014/C 138/02.

| (5) | Selection from the reserve list should endeavour to maintain the balance between user groups, |
| --- | --- |

(5)

Selection from the reserve list should endeavour to maintain the balance between user groups,

HAS ADOPTED THIS DECISION:

Article 1

Ms Asta Manninen is hereby appointed as a member of the European Statistical Advisory Committee for a term expiring on 8 May 2019.

Article 2

This Decision shall enter into force on the day following that of its publication in the Official Journal of the European Union.

Done at Brussels, 10 June 2015.

For the Commission

The President

Jean-Claude JUNCKER

---

(1)  
  OJ L 73, 15.3.2008, p. 13.

1

---
I 

115TH CONGRESS 

1ST SESSION H. R. 177 

To bar Supreme Court decisions in certain Patient Protection and Affordable 

Care Act cases from citation. 

IN THE HOUSE OF REPRESENTATIVES 

JANUARY 3, 2017 

Mr. KING of Iowa introduced the following bill; which was referred to the 

Committee on the Judiciary 

A BILL 

To bar Supreme Court decisions in certain Patient Protection 

and Affordable Care Act cases from citation. 

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

3 SECTION 1. BARRING PPACA SUPREME COURT CASES 

4 FROM CITATION. 

5 Under Article 3, Section 2, which allows Congress to 

6 provide exceptions and regulations for Supreme Court con7 sideration of cases and controversies, the following cases 

8 are barred from citation for the purpose of precedence in 

9 all future cases after enactment: Nat’l Fed’n of Indep. 

10 Bus. v. Sebelius, 132 S. Ct. 2566, 2573, 183 L. Ed. 2d 


rfrederick on DSKBCBPHB2PROD with BILLS
2 

•HR 177 IH

1 450 (2012) and King v. Burwell, 135 S. Ct. 2480, 2485, 

2 192 L. Ed. 2d 483 (2015) and Burwell v. Hobby Lobby 

3 Stores Inc., 134 S. Ct. 2751, 2782, 189 L. Ed. 2d 675 

4 (2014). 

Æ 


rfrederick on DSKBCBPHB2PROD with BILLS
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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# GSI-191: Thermal-Hydraulic Response of PWR Reactor Coolant System & Containments to Selected Accident Sequences (NUREG/CR-6770)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6770            - Cover - Appendix A (PDF - 5.83 MB)
          - Appendix B - End (PDF - 3.21 MB) 

## Publication Information

**Manuscript Completed:** January 2002**Date Published:** August 2002

**Prepared by:** D. V. Rao, K. W. Ross* S. G. Ashbaugh

Los Alamos National Laboratory Los Alamos, NM 87545

**Subcontractors:** *OMICRON 2500 Louisiana, N.E.  Albuquerque, NM 87110

M. L. Marshall, NRC Project Manager

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

NRC Job Code Y6041

Availability Notice

## Abstract

This report documents the results of calculations performed, as part of the resolution of the Nuclear Regulatory Commission (NRC) GenericSafety-Issue (GSI) 191, to simulate reactor coolant system (RCS) and containment thermalhydraulic response to a number of accidents that could potentially cause insulation debris to be collected on the sump screen. The purpose of the GSI-1 91 study is to determine if the transport and accumulation of debris in a containment following a loss-of-coolant accident (LOCA) will impede the operation of the ECCS in operating PWRs. In the event of a LOCA within the containment of a PWR, thermal insulation and other materials in the vicinity of the break will be damaged and dislodged. A fraction of this material would be transported to the recirculation (or emergency) sump and accumulate on the screen thereby forming a debris bed. Excessive head loss across this bed could prevent or impede the flow of water into the core or containment.

The calculations were performed using the NRC-approved computer codes RELAP5 and MELCOR. These calculations identified important RCS and containment thermalhydraulic parameters that influence the generation and/or transport of debris in PWR containments. The calculations determined the time-dependent system response parameters. The system responses were used to construct accident progression sequences that form the basis for strainer blockage evaluations and probabilistic risk evaluations.

Page Last Reviewed/Updated Wednesday, March 24, 2021
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AN A WING S CO. , LTD .
No: I-19-006 April 4, 2019

Contact: Diane Screnci, 610-337-5330

 Neil Sheehan, 610-337-5331

NRC to Hold Webinar to Discuss Salem and Hope Creek Nuclear

Power Plants 2018 Safety Performance

The Nuclear Regulatory Commission staff will hold a public webinar on April 10 to address 

the agency’s annual assessment of safety performance at the Salem and Hope Creek nuclear power 

plants.

The online meeting is scheduled to begin at 4:30 p.m. Participants will be able to view slides 

prepared by NRC staff and ask questions in writing via a web page set up to host the session. 

Advanced online registration is required to participate.

The purpose of the webinar is to provide information on the Hancocks Bridge (Salem 

County), N.J., plants’ safety performance in 2018 and the NRC’s oversight activities at the 

facilities, which are operated by PSEG Nuclear.

Salem and Hope Creek operated safely during 2018. At the conclusion of 2018, all 

inspection findings and performance indicators for the plants were green, or of very low safety 

significance. As a result, the plants will receive the normal level of oversight in 2019, which entails 

thousands of hours of inspection each year.

The NRC Reactor Oversight Process uses color-coded inspection findings and indicators to 

describe plant performance. The colors start at green and increase to white, yellow or red, 

commensurate with the safety significance of the issues involved. Inspection findings or 

performance indicators with more than very low safety significance trigger increased NRC 

oversight.

Inspections are performed by two NRC resident inspectors assigned to Salem and Hope 

Creek, respectively, and specialists from the agency’s Region I Office in King of Prussia, Pa.

The annual assessment letters for Salem and Hope Creek, as well as the webinar notice, are 

available on the NRC website. Current plant performance information for Salem Unit 1 and Unit 2

and Hope Creek is also available on the website.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# A Comprehensive Strategy of Hydrogeologic Modeling and Uncertainty Analysis for Nuclear Facilities and Sites (NUREG/CR-6805)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6805 (PDF - 6.41 MB)

## Publication Information

**Manuscript Completed:**December 2002**Date Published:**July 2003

**Prepared by:** S.P. Neuman and P.J. Wierenga

 Department of Soil, Water and Environmental Science University of Arizona Tucson, Arizona 85721

T.J. Nicholson, 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 W6790 

Availability Notice

## Abstract

This report describes a strategy that embodies a systematic and comprehensive approach to hydrogeologic conceptualization, model development and predictive uncertainty analysis. The strategy is comprehensive in that it considers all stages of model building and accounts jointly for uncertainties that arise at each of them. The stages include regional and site characterization, hydrogeologic conceptualization, development of conceptual-mathematical model structure, parameter estimation on the basis of monitored system behavior, and assessment of predictive uncertainty. In addition to parameter uncertainty, the strategy concerns itself with uncertainties arising from incomplete definitions of (a) the conceptual framework that determines model structure, (b) spatial and temporal variations in hydrologic variables that are either not fully captured by the available data or not fully resolved by the model, and (c) the scaling behavior of hydrogeologic variables. The strategy is generic but designed to be of practical use to NRC licensing staff in their review of decommissioning plans, and performance assessment of high-level and low-level radioactive waste disposal sites as well as uranium recovery facilities. An important component of the strategy is a systematic sequence of logical questions, guidelines and criteria with analytical methods appropriate for NRC review and performance evaluation.

Page Last Reviewed/Updated Wednesday, March 24, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Recommendations To The Nuclear Regulatory Commission On Trial Guidelines For Seismic Margin Reviews Of Nuclear Power Plants: Draft Report for Comment (NUREG/CR-4482, UCID-20579)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-4482, Draft Report for Comment (PDF - 4.76 MB)

## Publication Information

**Manuscript Completed:**December 1985**Date Published:**March 1986

**Prepared by:**P. G. Prassinos, M. K. Ravindra, and J. B. Savy, under the guidance and with. the concurrence of the Expert Panel on the Quantification of Seismic Margins: R. J. Budnitz (Chairman), P. J. Amico, C. A. Cornell, W. J. Hall, R. P. Kennedy, J. W. Reed, and M. Shinozuka.

Lawrence Livermore National Laboratory7000 East AvenueLivermore, CA 94550

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

NRC FIN No. A-0398

Availability Notice

## Abstract

This report is the third report of the Expert Panel on the Quantification of Seismic Margins. The objective of this report is to present detailed guidelines for the performance of seismic margin reviews of nuclear power plants. The guidelines presented in this report are based on the Panel's second report entitled "An Approach to the Quantification of Seismic Margins in Nuclear Power Plants."

It is intended that these guidelines be used in at least one trial plant review to demonstrate whether the approach and the quantification techniques are adequate. Based on lessons learned from these trial reviews, the Panel can then be more prescriptive about defining guidelines for general use.

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



                                CERTIFICATE OF MERGER
                                          OF
                                A DELAWARE CORPORATION
                                       INTO A 
                                 FOREIGN CORPORATION
                          (UNDER SECTION 252 OF THE GENERAL 
                      CORPORATION LAW OF THE STATE OF DELAWARE)
                                           

    NEW PHYSIO CORPORATION hereby certifies that:
 
         1. The name and state of incorporation of each of the constituent
    corporations are:

        (a) Physio-Control International Corporation, a Delaware 
            corporation; and

        (b) New Physio Corporation, a Washington corporation.

         2. An agreement and plan of merger has been approved, adopted,
    certified, executed and acknowledged by Physio-Control International
    Corporation and New Physio Corporation in accordance with the provisions of
    subsection (c) of Section 252 of the General Corporation Law of the State
    of Delaware.

         3. The name of the surviving corporation is New Physio Corporation

         4. The certificate of incorporation of New Physio Corporation shall 
be the certificate of incorporation of the surviving corporation.

         5. The surviving corporation is a corporation of the State of 
Washington.

         6. The executed agreement and plan of merger is on file at the 
principal place of business of New Physio Corporation at 11811 Willows Road 
N.E., Redmond WA  98052.

         7. A copy of the agreement and plan of merger will be furnished by 
New Physio Corporation, on request and without cost, to any stockholder of 
Physio-Control International Corporation or New Physio Corporation.

         8. New Physio Corporation hereby agrees that it may be served with 
process in Delaware in any proceeding for enforcement of any obligation of 
Physio-Control International Corporation, as well as for enforcement of any 
obligation of New Physio Corporation arising from the merger, including any 
suit or other proceeding 

<PAGE>

to enforce the right of any stockholders as determined in appraisal 
proceedings pursuant to 8 DEL.C. Section 262 and New Physio Corporation 
hereby irrevocably appoints the Secretary of State of the State of Delaware 
as its agent to accept service of process in any such suit or other 
proceedings and a copy of such process shall be mailed by the Secretary of 
State to New Physio Corporation at the following address: 11811 Willows Road 
N.E., Redmond WA  98052.

         IN WITNESS WHEREOF, New Physio Corporation has caused this 
certificate to be signed by V. Marc Droppert, its authorized officer, on the 
20th day of May, 1997.

                                  NEW PHYSIO CORPORATION

                                       /s/ V. Marc Droppert
                                  By______________________________
                                       V. Marc Droppert
                                       Secretary
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC ContractorsFRAPTRAN-1.4 and FRAPTRAN-1.5 (NUREG/CR-7023)

# FRAPTRAN-1.5:  A Computer Code for the Transient Analysis of Oxide Fuel Rods (NUREG/CR-7023, Volume 1, Revision 1)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7023, Volume 1, Revision 1 (PDF - 2.60 MB)

## Publication Information

**Manuscript Completed:** May 2014**Date Published:** October 2014

**Prepared by:**K. J. Geelhood, W. G. Luscher, and J. M. Cuta

Pacific Northwest National LaboratoryRichland, WA 99352

P. Raynaud, NRC Project Manager

NRC Job Code V6197

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

Availability Notice

## Abstract

The Fuel Rod Analysis Program Transient (FRAPTRAN) is a Fortran language computer code that calculates the transient performance of light-water reactor fuel rods during reactor transients and hypothetical accidents such as loss-of-coolant accidents, anticipated transients without scram, and reactivity-initiated accidents. FRAPTRAN calculates the temperature and deformation history of a fuel rod as a function of time-dependent fuel rod power and coolant boundary conditions. Although FRAPTRAN can be used in "standalone" mode, it is often used in conjunction with, or with input from, other codes. The phenomena modeled by FRAPTRAN include a) heat conduction, b) heat transfer from cladding to coolant, c) elastic-plastic fuel and cladding deformation, d) cladding oxidation, e) fission gas release, and f) fuel rod gas pressure. FRAPTRAN is programmed for use on Windowsbased computers but the source code may be compiled on any other computer with a Fortran-90 compiler.

Burnup-dependent parameters may be initialized from the FRAPCON-3 steady-state single rod fuel performance code.

This document describes FRAPTRAN-1.5, which is the latest version of FRAPTRAN.

Page Last Reviewed/Updated Wednesday, March 24, 2021
Michigan Supreme Court

Lansing, Michigan

Stephen J. Markman

, Chief Justice

Robert P. Young, Jr.

Brian K. Zahra

Bridget M. McCormack

David F. Viviano

Richard H. Bernstein

Joan L. Larsen,

Justices

I, Larry S. Royster , Clerk of the Michigan Supreme Court, certify that the

foregoing is a true and complete copy of the order entered at the direction of the Court.

April 5, 2017

jam 

# Order

Clerk April 5, 2017

1 55566 ( 13 )

In re BROOKS

_________________________________________

TERRY BROOKS

,

Plaintiff

- Appellant,

v SC: 1 55566

COA: 336912

INGHAM CIRCUIT COURT CHIEF JUDGE

,

Defendant

- Appellee.

___________________________________ _______/

On order of the Chief Justice, the motion to waive fees is considered and it

is DENIED because MCL 600.2963 requires that a prisoner pursuing a civil action be

liable for filing fees.

Within 21 days of the certification of this order, plaintiff shall pa y to the

Clerk of the Court the initial partial filing fee of $ 4 .00, shall submit a copy of this order

with the payment, and shall refile the copy of the pleadings which is being returned

with this order. Failure to comply with this order shall result in the appeal not being

filed in this Court.

If plaintiff timely files the partial fee and refiles the pleadings, monthly

payments shall be made to the Department of Corrections in an amount of 50 percent of

the deposits made to plaintiff’s account until th e payments equal the balance due of

$3 71 .00. This amount shall then be remitted to this Court.

Pursuant to MCL 600.2963(8) plaintiff shall not file further appeals in civil

actions in this Court until the entry fee in this case is paid in full.

The Clerk of the Court shall furnish two copies of this order to plaintiff and

return plaintiff’s pleadings with this order.