alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
No: 19-042 August 23, 2019

CONTACT: David McIntyre, 301-415-8200

Atomic Safety and Licensing Board Admits One Contention in 

Proceeding on Texas Spent Fuel Storage Proposal

An Atomic Safety and Licensing Board of the Nuclear Regulatory Commission has admitted 

one contention in an adjudicatory proceeding on the application by Interim Storage Partners LLC to 

construct and operate a consolidated interim spent fuel storage facility in Andrews County, Texas.

The admitted contention, proposed by the Sierra Club, argues that the Environmental Report 

submitted by ISP as part of its application failed to sufficiently address the potential impacts of the 

facility on the habitats of the dune sagebrush lizard and the Texas hound lizard. The Environmental 

Report cited five studies in support of ISP’s claim that any impacts would not be substantial. The 

Board agreed with the Sierra Club that the ER did not sufficiently describe those studies to allow 

others to judge their technical adequacy or make them available for independent review.

Interim Storage Partners, a joint venture of Waste Control Specialists and Orano USA, has 

applied for a license to build and operate a dry cask storage site for commercial spent nuclear fuel 

adjacent to the WCS low-level waste disposal facility in Andrews County.

The Board is composed of three administrative judges from the NRC’s Atomic Safety and 

Licensing Board Panel. Boards conduct adjudicative hearings on major licensing actions by the 

NRC, and they are independent of the NRC staff. A Board’s rulings may be appealed to the 

Commission, the five-member body that sets NRC policy.

Petitions for hearing and proposed contentions were filed by Sierra Club; Beyond Nuclear; 

Permian Basin Land and Royalty Organization and Fasken Land and Minerals; and a coalition of 

Don’t Waste Michigan, Citizens’ Environmental Coalition, Citizens for Alternatives to Chemical 

Contamination, Nuclear Energy Information Service, Public Citizen, San Luis Obispo Mothers for 

Peace, Sustainable Energy and Economic Development Coalition, and Leona Morgan. The Board 

heard oral arguments July 10-11, in Midland, Texas, on the standing of petitioners and the 

admissibility of their contentions.

In addition to Sierra Club, the Board granted standing to Beyond Nuclear, the Sustainable 

Energy and Economic Development Coalition, the Permian Basin Land and Royalty Organization, 

and Fasken, but ruled that only the Sierra Club raised an admissible contention.
HomeNRC LibraryDocument CollectionsNews Releases1998

# NRC Rates Farley Nuclear Plant "Superior" in Three Areas, "Good" in One Area ofLatest Assessment Report

----

----

No: II-98-49

July 2, 1998

**NRC RATES FARLEY NUCLEAR PLANT "SUPERIOR" IN THREE AREAS,"GOOD" IN ONE AREA OF LATEST ASSESSMENT REPORT**

The Farley nuclear power plant received performance ratings of "superior" in three areas and "good" in the one remaining area of the Nuclear Regulatory Commission's latest systematic assessment of licensee performance (SALP) of the facility.

The SALP report was issued June 29 to Southern Nuclear Operating Company, which operates the facility near Columbia, Alabama. It evaluates the plant's performance from November 24, 1996 through May 30 of this year.

NRC and Southern Nuclear officials will discuss the report during a meeting set for 10:00 a.m. (CDT) Wednesday, July 15, at the Farley site. The meeting will be open for public observation, and NRC officials will be available after the meeting to speak with reporters, state and local officials, and members of the public.

The NRC SALP process rates licensees in four functional areas -- plant operations, maintenance, engineering, and plant support -- and assigns ratings of Category 1, 2 or 3 depending on whether their performance in those areas was superior, good or adequate.

The report on Farley gives the plant a Category 1 rating in plant operations, maintenance and engineering indicating "superior" performance, and a Category 2 rating in plant support, indicating "good" performance. The ratings in the plant's previous SALP report, issued in January 1997, were Category 1's in plant operations and engineering and Category 2's in maintenance and plant support.

In his cover letter to the report, NRC Regional Administrator Luis Reyes said "reliable equipment performance was a key contributor to performance improving to superior in the maintenance area." He said performance in the plant support area remained at a good level, but "adherence to radiological control procedures and material condition of fire protection equipment and systems detracted from attaining a superior rating."

Reyes also highlighted the Farley plant's self-assessment program, saying "assessments were thorough and corrective actions resulted in few repetitive problems."

EDITORS: A copy of the full SALP report is available from this office. SALP reports are also available on the NRC's Internet web site (www.nrc.gov/OPA) and by e-mail subscription. To receive SALP reports by e-mail as they are issued, send an e-mail to listproc@nrc.gov with the following message: subscribe salp yourfirstname yourlastname.

Page Last Reviewed/Updated Thursday, March 25, 2021
```

[Congressional Bills 115th Congress]
[From the U.S. Government Publishing Office]
[H.R. 1894 Introduced in House (IH)]

<DOC>

115th CONGRESS
  1st Session
                                H. R. 1894

To facilitate construction of a bridge on certain property in Christian 
               County, Missouri, and for other purposes.

_______________________________________________________________________

                    IN THE HOUSE OF REPRESENTATIVES

                             April 4, 2017

   Mr. Long introduced the following bill; which was referred to the 
             Committee on Transportation and Infrastructure

_______________________________________________________________________

                                 A BILL

 
To facilitate construction of a bridge on certain property in Christian 
               County, Missouri, and for other purposes.

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

SECTION 1. RIVERSIDE BRIDGE PROJECT.

    (a) In General.--The Riverside Bridge Project is authorized to be 
carried out notwithstanding--
            (1) any agreement entered into under, or restriction 
        pursuant to, section 404(b)(2) of the Robert T. Stafford 
        Disaster Relief and Emergency Assistance Act (42 U.S.C. 
        5170c(b)(2)); or
            (2) any other Federal restriction that requires the covered 
        property to be maintained for open space, recreation, or 
        wetland management.
    (b) Conditions.--As a condition of the authorization under 
subsection (a), Christian County, Missouri--
            (1) shall carry out the Riverside Bridge Project in a 
        manner that ensures that no flood damage attributable to the 
        Project occurs; and
            (2) shall be liable for any such flood damage that does 
        occur.
    (c) Disaster Assistance Prohibited.--No Federal financial 
assistance pursuant to the Robert T. Stafford Disaster Relief and 
Emergency Assistance Act (42 U.S.C. 5121 et seq.) may be provided with 
respect to the covered property or any improvements thereon.
    (d) Definitions.--In this Act, the following definitions apply:
            (1) Covered property.--The term ``covered property'' means 
        the property--
                    (A) in Christian County, Missouri;
                    (B) conveyed to such County by the Riverside Inn, 
                Inc.; and
                    (C) that is approximately 1.5 acres and 482 lineal 
                feet adjacent to the westerly line of Riverside Road to 
                the center of Finley Creek.
            (2) Riverside bridge project.--The term ``Riverside Bridge 
        Project'' means the project to construct and operate a bridge 
        on and over the covered property.
                                 <all>
```
No. 91-702.

#### In re Houck.

Petition for writ of mandamus denied.
<TABLE> <S> <C>

<ARTICLE> 5
<MULTIPLIER>    1,000
       
<S>                             <C>
<PERIOD-TYPE>                   9-MOS
<FISCAL-YEAR-END>                             JAN-02-1998
<PERIOD-END>                                  SEP-12-1997
<CASH>                                             93,200
<SECURITIES>                                            0
<RECEIVABLES>                                      29,600
<ALLOWANCES>                                            0
<INVENTORY>                                        43,200
<CURRENT-ASSETS>                                  193,700
<PP&E>                                            688,300
<DEPRECIATION>                                    401,700
<TOTAL-ASSETS>                                    571,200
<CURRENT-LIABILITIES>                             186,900
<BONDS>                                           407,200
<PREFERRED-MANDATORY>                                   0
<PREFERRED>                                             0
<COMMON>                                                0
<OTHER-SE>                                        (76,100)
<TOTAL-LIABILITY-AND-EQUITY>                      571,200
<SALES>                                           896,400
<TOTAL-REVENUES>                                  896,400
<CGS>                                             260,600
<TOTAL-COSTS>                                     841,900
<OTHER-EXPENSES>                                        0
<LOSS-PROVISION>                                        0
<INTEREST-EXPENSE>                                 27,600
<INCOME-PRETAX>                                    29,400
<INCOME-TAX>                                        9,700
<INCOME-CONTINUING>                                19,700
<DISCONTINUED>                                          0
<EXTRAORDINARY>                                         0
<CHANGES>                                               0
<NET-INCOME>                                       19,700
<EPS-PRIMARY>                                        0.54
<EPS-DILUTED>                                        0.54
        

</TABLE>
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff for Knowledge Management

# 2002 Davis-Besse Reactor Pressure Vessel Head Degradation Knowledge Management Digest (NUREG/KM-0005)

On this page: 
        - Publication Information
        - Introduction

Download complete document
        - NUREG/KM-0005 (PDF - 2.09 MB)

## Publication Information

**Date Published:**February 2014

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

Availability Notice

## Introduction

The U.S. Nuclear Regulatory Commission (NRC) has an active knowledge management program that captures important historical events and critical information and preserves this knowledge for future generations

The 2002 reactor pressure vessel (RPV) head incident at Davis-Besse Nuclear Power Station (DBNPS) in Oak Harbor, OH, was one of the most serious nuclear safety events in United States history. In March 2002, severe degradation of the reactor pressure vessel head was discovered during a refueling outage at Davis-Besse. Boric acid had eaten away the carbon steel of the RPV head, leaving only a thin layer of stainless steel cladding to withstand the full operating pressure of the coolant in the reactor core. This could have led to a rupture of the reactor pressure vessel head and caused a major public safety event.

Eight years later, in 2010, Davis-Besse experienced another serious safety event involving the reactor pressure vessel head. During an NRC-mandated inspection, plant staff found cracking of the control rod drive mechanism (CRDM) nozzles. Had the plant staff not performed the inspection and found the cracking, the event would have progressed and could have led to a situation similar to the 2002 event.

Fortunately, in both 2002 and 2010, the problems at the Davis-Besse were discovered before they caused a major public safety event. These near-miss accidents have driven NRC policies and research to ensure the continued safe operation of the entire U.S. nuclear fleet.

This knowledge management digest and accompanying DVD contain historical documents relating to the technical and regulatory aspects of these incidents.

These documents can be accessed on the DVD through the interactive timelines or directly through the document listings.

The DVD also includes a multimedia presentation of the special NRC seminar "2002 Davis-Besse Reactor Pressure Vessel Degradation" held in January 2013, which offers a retrospective view of the 2002 incident.

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

# Circuit Analysis: Failure Mode and Likelihood Analysis (NUREG/CR-6834, SAND2002-1942P)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6834 (PDF - 13.18 MB)

## Publication Information

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

**Prepared by:** J.L. LaChance, S.P. Nowlen, F.J. Wyant, V.J. Dandini P.O. Box 5800 Sandia National Laboratories Albuquerque, New Mexico 87185-0748

H.W. Woods, NRC Project Manager

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

NRC Job Code Y6037

Availability Notice

## Abstract

Under existing probabilistic risk assessment (PRA) methods, the analysis of fire-induced circuit faults has typically been conducted on a simplistic basis. While exceptions do exist, a typical fire PRA will assume that given damage to any power or control cables, the associated circuits simply become unavailable. This approach does not address, for example, the potential that certain failures might cause spurious component actuations. In particular, certain cable failure modes, referred to as hot shorts, might lead to spurious operations. Those fire PRAs that have considered potential spurious operations have relied on methodologies that have significant uncertainties with regard to the scope of the assessments, the underlying methods, and the assumptions employed. Nonetheless, some of these fire PRAs have shown that cable hot shorts can be a significant risk contributor.

This report describes the results of a task to address weaknesses in existing fire PRA circuit analysis methods. An extensive review of available cable failure data has been performed and the current state of knowledge regarding cable failure modes and likelihood is characterized. A framework for advanced methods of cable failure mode and likelihood analysis is also presented. Advanced tools for performing PRA circuit analysis that explicitly treat different cable failure modes and the resulting circuit and system impact are outlined. Example applications of the proposed circuit analysis methods are provided.

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

# Joint Assessment of Cable Damage and Quantification of Effects from Fire (JACQUE-FIRE) (NUREG/CR-7150)

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

# Study of Transients Related to AMSAC Actuation, Sensitivity Analysis (NUREG/IA-0150)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0150 (PDF 1.43 MB)

## Publication Information

**Date Published:** November 1998

**Prepared by:** J.M. Posada, P.M.S.A., F. Revetos, A.N.A., J. Sanchez-Baptista, A.N.A. A. Perez-Navas, A.N.A., P. Moreno, P.M.S.A.

P.M.S.A. Av. Viñuelas, N°33, 1°D Tres Cantos – 28760 MADRID SPAIN

Asociacion Nuclear ASCO (A.N.A) Paral.lel, 51 08004 BARCELONA 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

The Asociación Nuclear Ascó (ANA) has prepared a model of Ascó NPP using, RELAP5/MOD3.2. This model, which includes thermal-hydraulics, kinetics and protection and control systems, has been qualified in previous calculations of several actual plant transients.

Ascó NPP is a two unit station of three loop Pressurized Water Reactors (PWR) of Westinghouse design operated by ANA. ANA is a spanish utility that contributes to the Code Application and Maintenance Project (CAMP) as a member of UNIDAD ELECTRIICA S. A. (UNESA).

This report summarizes the results obtained with Ascó NPP model for a loss of normal feedwater ATWS event and presents a sensitivity analysis to kinetic parameters for the same transient.

The phenomenology prediction has been useful from the operation and safety point of view.

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

# Metal Fuel Qualification: Fuel Assessment Using NRC NUREG-2246, "Fuel Qualification for Advanced Reactors" (NUREG/CR-7305)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7305 (PDF – 3.74 MB)

## Publication Information

**Manuscript Completed:** April 2023**Date Published:** August 2023

**Prepared by:**W. Williams1, C. Matthews2, Y. Miao3,F. Di Lemma1, L. Capriotti1, Y. Wang1,C. Jensen1 D. Keiser1, C. Adkins1,D. Crawford1, S. Novascone1, D. Wachs1

1Idaho National LaboratoryIdaho Falls, ID 83415

2Los Alamos National LaboratoryLos Alamos, NM 87545

3Argonne National LaboratoryArgonne, IL 60439

James Corson, NRC Project Manager

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

Availability Notice

## Abstract

Companies looking to license reactors with different materials than the current U.S. fleet of lightwater zirconium-clad ceramic fuel are emerging as part of the push toward a more responsible energy economy. As such, the Nuclear Regulatory Commission is tasked with evaluating these new license applications. This report documents the current state of available experiment measurements, simulation capability, and historic knowledge and lessons learned required for evaluating sodium-cooled fast-spectrum metallic fuel, specifically U-10wt%Zr, up to 10at%burnup.

Page Last Reviewed/Updated Friday, August 04, 2023
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  EXHIBIT 4.4    
    

 






 



					
	Number

B-

	 	Incorporated Under the Laws of the State of Delaware	 	Shares

-0-

Cusip No.




 

  
 

  LIBERTY SPLITCO, INC.
  
    Series B Splitco Starz Common Stock, par value $.01 per share
  
    Specimen Certificate    
    


        This Certifies that
                                         
                                        is the owner
of
                                         
                                        FULLY
PAID AND NON-ASSESSABLE SHARES OF SERIES B SPLITCO STARZ COMMON STOCK, PAR VALUE $0.01 PER SHARE, OF LIBERTY SPLITCO, INC. (hereinafter called the "Corporation") transferable on the
books of the Corporation by the holder hereof in person or by duly authorized attorney upon surrender of the Certificate properly endorsed. This Certificate is not valid unless countersigned by the
Transfer Agent and registered by the Registrar. 


        Witness,
the seal of the Corporation and the signatures of its duly authorized officers. 

 










					
	Dated:	 	 	 	 
	

 	
 	
Liberty Splitco, Inc.

[Corporate Seal]	
 	

 
	






  President	 	 	 	






  Secretary




 

 








QuickLinks



EXHIBIT 4.4


LIBERTY SPLITCO, INC. Series B Splitco Starz Common Stock, par value $.01 per share Specimen Certificate