alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
<TABLE> <S> <C>

<ARTICLE> 5
<LEGEND>
THIS SCHEDULE CONTAINS SUMMARY FINANCIAL INFORMATION FROM THE CONDENSED
CONSOLIDATED BALANCE SHEET AS OF SEPTEMBER 30, 2000 AND THE CONSOLIDATED
STATEMENT OF INCOME FOR THE NINE MONTHS ENDED SEPTEMBER 30, 2000 AND IS
QUALIFIED IN ITS ENTIRETY BY REFERENCE TO SUCH FINANCIAL STATEMENTS.
</LEGEND>
<MULTIPLIER> 1,000

<S>                             <C>
<PERIOD-TYPE>                   9-MOS
<FISCAL-YEAR-END>                          DEC-31-2000
<PERIOD-START>                             JAN-01-2000
<PERIOD-END>                               SEP-30-2000
<CASH>                                          32,214
<SECURITIES>                                    70,003
<RECEIVABLES>                                   22,055
<ALLOWANCES>                                       481
<INVENTORY>                                     12,379
<CURRENT-ASSETS>                               150,604
<PP&E>                                          16,690
<DEPRECIATION>                                   8,411
<TOTAL-ASSETS>                                 165,660
<CURRENT-LIABILITIES>                           16,153
<BONDS>                                              0
<PREFERRED-MANDATORY>                                0
<PREFERRED>                                          0
<COMMON>                                            16
<OTHER-SE>                                     149,140
<TOTAL-LIABILITY-AND-EQUITY>                   165,660
<SALES>                                         68,558
<TOTAL-REVENUES>                                68,558
<CGS>                                           25,413
<TOTAL-COSTS>                                   25,413
<OTHER-EXPENSES>                                     0
<LOSS-PROVISION>                                     0
<INTEREST-EXPENSE>                                   0
<INCOME-PRETAX>                                (5,410)
<INCOME-TAX>                                     3,762
<INCOME-CONTINUING>                            (9,172)
<DISCONTINUED>                                       0
<EXTRAORDINARY>                                      0
<CHANGES>                                            0
<NET-INCOME>                                   (9,172)
<EPS-BASIC>                                   (0.61)
<EPS-DILUTED>                                   (0.61)


</TABLE>
No. 90-6125.

#### Holmes, aka Richards *v.*Hardy et al.

C. A. 5th Cir. Certiorari denied.
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# Strengthening Ties with Bilateral Exchange

By Senior Airman Gabrielle Spalding374th Airlift WIng Public Affairs

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Washington Bancorp
Computation of Earnings per Common Share

                                                                      Exhibit 11


                                        For the three months ended September 30,
                                        ----------------------------------------
                                          2001      2000       2001      2000
                                          Basic     Basic    Diluted   Diluted
                                           EPS       EPS       EPS       EPS
                                         ---------------------------------------

Computation of weighted average
  number of common shares
  outstanding:
Common shares outstanding
  at the beginning of the period ...     651,133   651,133   651,133   651,133
Unreleased common shares held by the
  Employee Stock Ownership
  Plan (ESOP) at the beginning
    of the period ..................     (28,219)  (33,283)  (28,219)  (33,283)
Weighted average common shares
  released by the ESOP during
  the period .......................         657       609       657       609
Weighted average common shares
  outstanding - Stock Option Plan ..          --        --    12,584     7,466
Weighted average common shares
  into treasury ....................    (132,531) (109,766) (132,531) (109,766)
                                       ---------------------------------------
Total average shares outstanding ...     491,040   508,693   503,624   516,159
                                       =======================================

Net income .........................   $ 309,850  $259,348  $309,850  $259,348

Net income per share ...............   $    0.63  $   0.51  $   0.62  $   0.50
                                       =======================================
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsBrochures Prepared by NRC Staff

# Let's Talk!  Improving Performance Feedback Discussions for Employees and Supervisors (NUREG/BR-0347)

On this page:
        - Publication Information

Download complete document
        - NUREG/BR-0347 (PDF - 798.55 KB)

## Publication Information

**Date Published:** June 2008

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

Page Last Reviewed/Updated Wednesday, March 24, 2021
```

[Congressional Bills 115th Congress]
[From the U.S. Government Publishing Office]
[H.R. 184 Engrossed in House (EH)]

<DOC>
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
  
115th CONGRESS
  2d Session
                                H. R. 184

_______________________________________________________________________

                                 AN ACT

 
To amend the Internal Revenue Code of 1986 to repeal the excise tax on 
                            medical devices.

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

SECTION 1. SHORT TITLE.

    This Act may be cited as the ``Protect Medical Innovation Act of 
2018''.

SEC. 2. REPEAL OF MEDICAL DEVICE EXCISE TAX.

    (a) In General.--Chapter 32 of the Internal Revenue Code of 1986 is 
amended by striking subchapter E.
    (b) Conforming Amendments.--
            (1) Subsection (a) of section 4221 of such Code is amended 
        by striking the last sentence.
            (2) Paragraph (2) of section 6416(b) of such Code is 
        amended by striking the last sentence.
    (c) Clerical Amendment.--The table of subchapters for chapter 32 of 
such Code is amended by striking the item relating to subchapter E.
    (d) Effective Date.--The amendments made by this section shall 
apply to sales after December 31, 2019.

            Passed the House of Representatives July 24, 2018.

            Attest:

                                                                 Clerk.
115th CONGRESS

  2d Session

                               H. R. 184

_______________________________________________________________________

                                 AN ACT

To amend the Internal Revenue Code of 1986 to repeal the excise tax on 
                            medical devices.
```
EXHIBIT 32.1
                            CERTIFICATION PURSUANT TO
                                 18 U.S.C. 1350,
                             AS ADOPTED PURSUANT TO
                  SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002


In connection with the annual Report of AMERALINK,  INC. (the "Company") on Form
10-KSB for the period ended  December 31, 2001, as filed with the Securities and
Exchange  Commission  on the date hereof (the  "Report"),  I, Kevin  Ericksteen,
Chief Executive Officer of the Company,  certify, pursuant to 18 U.S.C. 1350, as
adopted pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, that:

The Report fully complies with the requirements of Section 13(a) or 15(d) of the
Securities Exchange Act of 1934; and

The  information  contained  in the  Report  fairly  presents,  in all  material
respects, the financial condition and results of operations of the Company.


                                                  /s/ Kevin Ericksteen
                                                  ---------------------------
Date: October 31, 2003                                Kevin Ericksteen
                                                      Chief Executive Officer
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC Grants GPU Nuclear's Request to Reduce Insurance Coverage for Shut-Down Three Mile Island Unit 2

----

----

No. 99-170 August 9, 1999

**NRC GRANTS GPU NUCLEAR'S REQUEST TO REDUCE INSURANCE COVERAGE FOR SHUT-DOWN THREE MILE ISLAND UNIT 2**

The Nuclear Regulatory Commission has granted a request from GPU Nuclear, operator of Three Mile Island Unit 2 (TMI-2), to reduce insurance coverage on the reactor shut down near Harrisburg, Pennsylvania.

Over ninety-nine percent of the fuel has been removed from TMI-2, which never operated after the 1979 accident. The reduction in insurance coverage was granted based on the substantially reduced risk that the permanently shut-down reactor presents to public health and safety.

Currently, under NRC regulations, all nuclear power plant licensees are required to maintain approximately $1 billion of on-site insurance to stabilize and decontaminate each reactor, and to provide coverage for on-site damage in the event of an accident. They are also required under the terms of the Price-Anderson Act, to obtain a minimum of $200 million for financial protection and to participate in a secondary financial protection system totaling about $8.7 billion, against damages and injuries which could occur off site. However, over a dozen other nuclear power plants have been permitted by NRC to reduce insurance coverage for on-site damage after permanently shutting down and removing fuel from the reactor vessels.

The NRC staff has completed its review of GPU Nuclear's March 9 request to reduce insurance coverage on TMI-2. That review concluded that the licensee's proposed insurance protection of $50 million would be sufficient to provide adequate funds for any problems that might arise.

Page Last Reviewed/Updated Wednesday, March 24, 2021
No. 86-497.

No. 86-531.

#### Agency Holding Corp. et al. *v.*Malley-Duff & Associates, Inc.; and Crown Life Insurance Co. et al. *v.*Malley-Duff & Associates, Inc., et al.

C. A. 3d Cir. [Certiorari granted, *ante,*p. 983.] Motion of petitioners for divided argument granted, and the time is to be divided as follows: 10 minutes for petitioners in No. 86-497 and 20 minutes for petitioners in No. 86-531.
HomeNRC LibraryDocument CollectionsNews Releases1998

# NRC Licensing Board to Hold Prehearing Conference on Proposed Spent Nuclear Fuel Storage Facility in Utah

----

----

No. 98-02

January 6, 1998

**NRC LICENSING BOARD TO HOLD PREHEARING CONFERENCE ON PROPOSED SPENT NUCLEAR FUEL STORAGE FACILITY IN UTAH**

Page Last Reviewed/Updated Wednesday, March 24, 2021
fp0002383_agencyagt1.htm


 



Agreement No.__________


 







 


Agency Agreement









 


Shaanxi Baishui Dukang Brand Management Co., Ltd.









  





  











  




 




AGENCY AGREEMENT







Party A: Shaanxi Baishui Dukang Brand Management Co., Ltd.


Party B: Ms. Dong, Sue   ID card No.:   612101196306260468


 


In view of that Party B agrees to renewal the nationwide franchise buyout of the products of Party A — “Baishui Dukang · Twenty-year Age Liquor” which has already circulated in the market, Party A and B have reached an agreement through friendly consultation to conclude the following contract:








	
1.  

	
Party B buy out the nationwide franchise of the products of Party A — “Baishui Dukang · Twenty-year Age Liquor” which has already circulated in the market.








	
2.  

	
The term of the buyout is from May 15, 2010 to May 14, 2011. When the agreement terminates and Party B is willing to renewal it, Party B owns the rights to first renew the agreement.








	
3.  

	
The fee for the buyout is for RMB1,000,000 (RMB one million yuan), 60% of the fee shall be paid before May 30, the remaining 40% of it shall be paid before Sept. 30, 2010, otherwise there shall be an overdue fine for 5‰ per day.








	
4.  

	
During the period of the buyout, Party A shall guarantee the requirements of Party B for products and ensure that the product quality should meet the national quality standards.








	
5.  

	
During the period of the buyout, Party B shall in charge of the product sales network of Party A, and Party A can not sell any of the buyout products.








	
6.  

	
Party B assures of completing the sales target for RMB 3,000,000 during the period of the buyout, or each 10 percent decrease on the uncompleted sales target will result in 5 percent increase on the buyout fee.








	
7.  

	
The Agreement is in duplicate with the equal legal effect and each party holds one copy.







 




  





  











  






 



	
Party A:

	
Party B:


	
Shaanxi Baishui Dukang Brand Management Co., Ltd.

	
Ms. Dong, Sue


	  	  
	  	  
	
Date: May 8, 2010

	
Date: May 8, 2010
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC Amends Regulations to Expand Opportunities for Participation by Indian Tribal Governments in NRC Hearings

----

----

No. 99-110 May 26, 1999

**NRC AMENDS REGULATIONS TO EXPAND OPPORTUNITIES FOR PARTICIPATIONBY INDIAN TRIBAL GOVERNMENTS IN NRC HEARINGS**

The Nuclear Regulatory Commission is amending its regulations to provide federally recognized Indian tribes with the option to participate in NRC adjudicatory proceedings as an "interested governmental participant," rather than requiring them to intervene as a formal "party" in any proceeding in which they wish to participate.

Formal intervention is currently the only course of action available to tribal governments. This amendment to the NRC's Rules of Practice recognizes that tribes exercise inherent sovereign powers over their members and territories, similar to the powers exercised by state and local governments. Accordingly, the amendment ensures that tribes have the same options now available to state governments, units of local governments, and their official subdivisions, any of which can take part in NRC proceedings as an "interested governmental participant."

The rule is being published in final form because NRC considers this action noncontroversial and routine. It will become effective 60 days from the date of publication in an upcoming edition of the Federal Register, unless significant adverse comments are received within 30 days of publication of the notice.

Interested persons are invited to submit comments to: Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Rulemakings and Adjudications Staff. Comments may also be submitted electronically through the NRC homepage: http://www.nrc.gov by selecting the "comments" link on the rulemaking web site.

Page Last Reviewed/Updated Wednesday, March 24, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# RELAP5/MOD3.3 Analysis of Event with Actuation of Safety Injection System at the Loss of External Power (NUREG/IA-0458)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0458 (PDF - 1.78 MB)

## Publication Information

**Manuscript Completed:**November 2014**Date Published:** December 2015

**Prepared by:** A. Prošek, M. Matkovič

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

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:** 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

Measured plant data are of great importance for the assessment of thermal-hydraulic system codes. Namely, the integral effects facilities contain atypicalities and scaling distortions relative to full scale plants. On the other hand, the accidents in the plants are very rare and the plant specific data are generally available only for startup tests and operational events. However, the measured plant data may be limited for the full understanding of event. The purpose of this study was therefore both code assessment and better understanding of the plant response to abnormal event, which occurred on 23 March 2011 in Krško nuclear power plant (NPP). The abnormal event was called "Reactor trip and actuation of safety injection system at the loss of external power". For the analysis the latest RELAP5/MOD3.3 Patch 04 best-estimate thermalhydraulic computer code and standard Krško NPP input deck for RELAP5 have been used. The results show good agreement between measured and simulated data, when all plant system responses and operator actions were considered. This suggests that the RELAP5 code using standard plant input deck is good representative of the plant and could be used for better understanding of the plant response when information on all physical phenomena and processes is not available by plant measured data.

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

# State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analysis of the Unmitigated Short-Term Station Blackout of the Surry Power Station (NUREG/CR-7262)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7262 (PDF – 65.07 MB)

## Publication Information

**Manuscript Completed:** June 2019**Date Published:** December 2022

**Prepared by:**Severe Accident Analysis DepartmentSandia National LaboratoriesP.O. Box 5800 MS-0848Albuquerque, NM 87185-0748

S. Tina Ghosh, NRC Project Manager

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

Availability Notice

## Abstract

The State of the Art Reactor Consequence Analyses (SOARCA) project published best estimate analyses for select accident scenarios at the Peach Bottom Atomic Power Station and Surry Power Station in 2012. This work was followed by an integrated uncertainty analysis (UA) performed on the unmitigated long-term station blackout (LTSBO) scenario for Peach Bottom, a draft UA on the unmitigated short-term station blackout (STSBO) scenario for Surry, and a UA on the unmitigated STSBO scenario for Sequoyah. The approach developed for the Peach Bottom UA was further enhanced for application to the subsequent UAs. Consequently, the current Surry UA not only benefits from additional knowledge gained since the original Surry SOARCA best-estimate calculation but also the other UAs. The UA projects include an integrated Monte Carlo analysis using the MELCOR and MACCS codes. Regression analyses and separate sensitivity analyses were conducted to understand the contributions of uncertain input parameters to the uncertainty in key figures of merit, such as radionuclide release to the environment and individual latent cancer fatality risk to the offsite public. Single realizations were analyzed to investigate individual parameter effects, typically associated with the extreme bounds, and to confirm phenomenological explanations of variations in system behavior and results. Consistent with the previous UAs, rank regression, quadratic regression, recursive partitioning, and multivariate adoptive regression splines (MARS) techniques were used to identify the importance of the input parameters regarding the uncertainty of the results. Using the insights gained from the previous UAs including the draft Surry UA and their respective ACRS reviews, the Surry model, the uncertain parameter definitions, and the uncertainty characterizations were revised for the UA documented in this report. Like the previous UAs, the analyses herein corroborate the conclusions of the original SOARCA study and further extend the body of knowledge on severe reactor accidents.

Page Last Reviewed/Updated Tuesday, December 27, 2022
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Plant Application with TRACE Code of the PKL III G1 Test Series. Study on Heat Transfer Mechanisms in the SG in Presence of Nitrogen, Steam and Water as a Function of the Primary Coolant Inventory in Single & Double Loop Operation (NUREG/IA-0537)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0537 (PDF – 3.98 MB)

## Publication Information

**Manuscript Completed:** December 2021**Date Published:** February 2023

**Prepared by:**C. Berna, A. Escrivá & J.L. Muñoz-Cobo

CoboInstituto de Ingeniería EnergéticaUniversitat Politècnica de ValènciaCamino de Vera 14, 46022 ValènciaSpain

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 main goal of this report is to explain a PWR plant application of the G1 tests series carried out in the PKL III facility through a TRACE model. With this purpose, the experimental data and TRACE V5.0p2 simulation results of PKL III G1.1 and G1.2 tests are used. Then, two TRACE simulations have been carried out, one for a commercial NPP model and the other for an own PKL facility model. The PKL III G1 test series are focused on the occurrence of boron dilution processes following the loss of RHRS during 3⁄4-loop operation. Test G1.1 features a systematic study on heat transfer in SG U-tubes in presence of nitrogen, steam and water with variable Primary Coolant Inventory (PCI) in the PKL III test facility with a single loop configuration. While G1.2 test as the same purpose than G1.1 but with two loops in operation. A goal of this report is to analyse the capacity of TRACE V5.0p2 code to precisely simulate thermal stratification and natural circulation of both single and two-phase flow inside the whole primary circuit of PKL facility.

Page Last Reviewed/Updated Thursday, March 02, 2023