alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
HomeNRC LibraryDocument CollectionsNews Releases2000

# NRC Staff to Meet with Public to Discuss Future Zion Decommissioning Activities

----

----

----

**NRC Staff to Meet with Public to Discuss Future Zion Decommissioning Activities**

Nuclear Regulatory Commission staff members will conduct a public meeting April 26 to discuss the future decommissioning plans of Units 1 and 2 of the Zion Nuclear Power Station. The two-unit plant is located in Zion, Illinois.

The two units have not operated since February 1997. Commonwealth Edison Co., operator of the plant, permanently shut down the plant in February 1998 and all fuel had been removed from the reactor vessels by March 1998. Currently, used fuel is stored in the spent fuel pool facility on the site.

The public meeting will begin at 7 p.m., April 26, at the Zion-Benton High School which is located at 3901 21st Street in Zion, Illinois.

During the meeting, officials will discuss the Post-Shutdown Decommissioning Activities Report submitted by Commonwealth Edison. The report discusses decommissioning activities, estimated costs, and environmental impacts. The meeting also will include presentations by the NRC on the regulatory process for decommissioning. A question and answer session will follow the general meeting.

Both units at Zion began operating in 1973. Currently there are four other nuclear power reactors in the Midwest region that are undergoing decommissioning.

Under NRC decommissioning regulations, utilities are permitted to immediately dismantle a plant or to place it in safe storage for a period of time before dismantlement, provided certain regulations are met. Commonwealth Edison chose to put the Zion units in safe storage.

Two years before it is ready to terminate the Zion units' licenses, Commonwealth Edison is required to submit a final plan to the NRC. This plan, among other things, must describe any remaining radioactivity on the site, the final radiation survey details and the site's planned end-use. NRC will conduct a public meeting near the plant to discuss the utility's plans and receive public comments. There also will be an opportunity for a public hearing regarding the utility's license termination plans.

NRC and the Illinois Department of Nuclear Safety currently are conducting inspections at both Zion units, and will continue to do so during the decommissioning process. The NRC also will independently evaluate the radiological condition of the plant site during the final phase.

The Post-Shutdown Decommissioning Activities Report is available for public review at the NRC's Public Document Room located at the Gelman Building, 2120 L Street, NW, in Washington, D.C. It also is accessible electronically from the ADAMS Public Library component on the NRC web site which is http://www.nrc.gov. The ADAMS Accession number for the document is ML003685889.

Page Last Reviewed/Updated Wednesday, March 24, 2021
Document Headings

                    Document headings vary by document type but may contain                    the following:                  
                -                       the agency or agencies that issued and signed a document                    
                -                       the number of the CFR title and the number of each part                      the document amends, proposes to amend, or is directly                      related to                    
                -                       the agency docket number / agency internal file number                    
                -                       the RIN which identifies each regulatory action listed in                      the Unified Agenda of Federal Regulatory and Deregulatory                      Actions                    

                    See the                                          Document Drafting Handbook                                        for more details.                  

###### International Trade Commission

          - [Investigation Nos. 701-TA-603-604 and 731-TA-1413-1415 (Review)]

## Determinations

                    On the basis of the record [1]                                          developed in the subject five-year reviews, the United States International Trade Commission (“Commission”) determines, pursuant to the Tariff Act of 1930 (“the Act”), that revocation of the antidumping duty orders on glycine from India, Japan, and Thailand, and the countervailing duty orders on glycine from China and India would be likely to lead to continuation or recurrence of material injury to an industry in the United States within a reasonably foreseeable time.                

## Background

The Commission instituted these reviews on May 1, 2024 (89 FR 35237) and determined on August 5, 2024, that it would conduct expedited reviews (89 FR 76507, September 18, 2024).

                    The Commission made these determinations pursuant to section 751(c) of the Act (19 U.S.C. 1675(c)). It                           ( print page 94762)                        completed and filed its determinations in these reviews on November 22, 2024. The views of the Commission are contained in USITC Publication 5564 (November 2024), entitled                     *Glycine from China, India, Japan, and Thailand: Investigation Nos. 701-TA-603-604 and 731-TA-1413-1415 (Review).*

By order of the Commission.

Issued: November 22, 2024.

Lisa Barton,

Secretary to the Commission.

# Footnotes

1.                             The record is defined in § 207.2(f) of the Commission's Rules of Practice and Procedure (19 CFR 207.2(f)).                    
        Back to Citation      

[FR Doc. 2024-28018 Filed 11-27-24; 8:45 am]

BILLING CODE 7020-02-P
<PAGE>
 
                                   EXHIBIT 11
                 STATEMENT RE COMPUTATION OF PER SHARE EARNINGS

<TABLE> 
<CAPTION> 
 
                                                                Three Months                 Nine Months
                                                             Ended September 30,         Ended September 30,
                                                         ------------------------     ------------------------
                                                             1996         1995           1996           1995      
                                                          (Unaudited)  (Unaudited)    (Unaudited)    
                                                            ------       ------         ------         ------     
<S>                                                        <C>          <C>           <C>             <C>         
Net income available to common stockholders                $602,351     $218,355      $1,269,938      $864,203    
Accrued dividends on preferred stock                              -      (87,720)              -      (343,000)   
                                                         ----------   ----------      ----------    ----------    
Net income for computing pro forma net income per share     602,351      130,635       1,269,938       521,203
                                                         ==========   ==========      ==========    ==========    
                                                                                                                  
Pro forma weighted average common shares outstanding      5,282,517    2,986,239       4,848,039     2,898,354    
                                                                                                                  
Shares of common stock assumed to be issued upon                                                                  
     exercise of common stock options and warrants to                                                             
     purchase common stock using treasury stock method,                                                           
     including "cheap" options and warrants as outstanding                                                         
     for all periods                                        424,483      412,761         510,961       413,646    
                                                         ----------   ----------      ----------    ----------    
Weighted average number of common and common                                                                      
     equivalent shares outstanding during the period      5,707,000    3,399,000       5,359,000     3,312,000    
                                                         ==========   ==========      ==========    ==========    
Pro forma net income per share                                $0.11        $ .06           $0.24         $0.26    
                                                         ==========   ==========      ==========    ==========    
</TABLE> 

                                      14
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Hydrogeologic Performance Assessment of the Commercial Low-Level Radioactive Waste Disposal Facility Near West Valley, New York (NUREG/CR-5737)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-5737 (PDF - 5.79 MB)

## Publication Information

**Manuscript Completed:** April 1991**Date Published:** June 1991

**Prepared by:** K. P. Bergeron, J. L Smoot, K. L Kenmer, W. E. Cronin

Pacific Northwest Laboratory Richland, WA 99352

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

NRC FIN B2485

Availability Notice

## Abstract

A hydrogeologic performance assessment of the commercial low-level waste site near West Valley, New York, was performed for two pathways: a shallow lateral pathway where trench water can potentially migrate laterally through fractured and weathered till to nearby streams and a deep vertical pathway where leachate can migrate downward through unweathered till and laterally offsite in a lacustrine unit.

Along the shallow pathway, little physical site evidence is available to Indicate what the degree of lateral migration can be. Past modeling showed that overflowing trench water would migrate laterally some distance before migrating downward into the unweathered till. If water did reach a nearby stream, calculations show that decay, adsorption, and stream dilution would reduce leachate concentration to acceptable levels.

Within the deep pathway, tritium and 14C were the only radionuclides released in any significant concentrations. Predicted tritium levels are well below regulatory limits; however, predicted peak 14C concentrations, while meeting the 25 mrem/yr limit using the drinking-water-only exposure scenario, exceed the limit for the full garden scenario. Site Information on 14C release rates and geochemical behavior has considerable uncertainty and would need to be more fully evaluated in a licensing situation.

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

# Analysis of the UPTF Separate Effects Test 11 (Steam-Water Countercurrent Flow in the Broken Loop Hot Leg) Using RELAP5/MOD2 (NUREG/IA-0071, AEEW–M2555)

On this page:
        - Publication Information
        - Summary

Download complete document
        - NUREG/IA-0071 (PDF 1.24 MB)

## Publication Information

**Date Published:** June 1992

**Prepared by:** M. J. Dillistone

Winfrith Technology Centre United Kingdom Atomic Energy Authority Dorchester, Dorset, DT2 8DH United Kingdom

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

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

Availability Notice

## Summary

RELAP5/MOD2 predictions of countercurrent flow limitation in the UPTF Hot Leg Separate Effects Test (test 11) are compared with the experimental data. The code underestimates, by a factor of more than three, the gas flow necessary to prevent liquid runback from the steam generator, and this is shown to be due to an oversimplified flow-regime map which does not allow the possibility of stratified flow in the hot leg riser. The predicted countercurrent flow is also shown to depend, wrongly, on the depth of liquid in the steam generator plenum.

The same lest is also modelled using a version of the code in which stratified flow in the riser is made possible. The gas flow needed to prevent liquid runback is then predicted quite well, but at all lower gas flows the code predicts that the flow is completely unrestricted - i.e. liquid flows between full flow and zero flow are not predicted. This is shown to happen because the code cannot calculate correctly the liquid level in the hot leg, mainly because of a numerical effect of upwind donoring in the momentum flux terms of the code's basic equations. It is also shown that the code cannot model the considerable effect of the ECCS injection pipe (which runs inside the hot leg) on the liquid level.

Page Last Reviewed/Updated Tuesday, March 09, 2021
EXHIBIT
      32.1





CERTIFICATIONS
      PURSUANT TO 18 U.S.C. SECTION 1350,


AS
      ADOPTED PURSUANT TO SECTION 906 OF THE SARBANES-OXLEY


ACT
      OF 2002





In
      connection with the Annual Report of DealerAdvance, Inc. (the "Company") on
      Form
      10-K for the year ended December 31, 2007, as filed with the Securities and
      Exchange Commission on the date hereof (the "Report"), I, Steven E. Humphries,
      Chief Executive Officer, certify, pursuant to 18 U.S.C. Section 1350, as adopted
      pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, that:





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




(2)  The
      information contained in the Report fairly presents, in all material respects,
      the financial condition and result of operations of the Company, as of, and
      for
      the periods presented in the Report.




April
              14, 2008
            
            /s/ *Steven
              E. Humphries*Steven
              E. Humphries, Chief Executive
              Officer




A
      signed original of this written statement required by Section 906 has been
      provided to DealerAdvance, Inc. and will be retained by DealerAdvance, Inc.
      and
      furnished to the Securities and Exchange Commission or its staff upon
      request.
<PAGE>

                                                                    EXHIBIT 32.2

                CERTIFICATION PURSUANT TO 18 U.S.C. SECTION 1350
        AS ADOPTED PURSUANT TO SECTION 906 OF SARBANES-OXLEY ACT OF 2002

I, Jack M. Rapport, Chief Financial Officer of Zanett, Inc. (the "Company"),
hereby certify, pursuant to 18 U.S.C. Section 1350, as adopted pursuant to
Section 906 of the Sarbanes-Oxley Act of 2002, that (1) the Form 10-KSB of the
Company for the annual period ended December 31, 2004 ("Form 10-KSB"), fully
complies with the requirements of Section 13(a) or 15(d) of the Securities
Exchange Act of 1934 (15 U.S.C. 78m or 78o(d)); and (2) the information
contained in the Form 10-KSB fairly presents, in all material respects, the
financial condition and results of operations of the Company.


/s/ Jack M. Rapport                                              March 31, 2005
-----------------------------------------                        --------------
Jack M. Rapport - Chief Financial Officer                              Date
#### Frederick, Plaintiff, vs. The State, Defendant.

*February 8*

March *5, 1929.*

*400
      *A. E. Frederick*of Sparta, for the plaintiff.

For the defendant the cause was submitted on the brief of the *Attorney General*and /. *E. Messerschmidt)*assistant attorney general.

Stevens, J.

No question is raised as to the amount due plaintiff. The only questions presented are as to the right of the plaintiff to recover interest and costs.

(1) Claims against the State do not bear interest “unless its consent to pay interest has been manifested by an act of its legislature, or by a lawful contract of its executive officers.” *Schlesinger v. State,*195 Wis. 366, 368, 218 N. W. 440. There is neither a statute nor a contract imposing such liability in this case.

(2) No costs can be taxed against the State unless authorized by statute. *Baxter v. State,*10 Wis. 454, 457. But ch. 285 of the Statutes evinces a legislative intent that those who sue the State pursuant to the provisions of that chapter shall recover costs. Sec. 285.04 of the Statutes provides for an audit of “the amount of damages and *costs”*awarded in such an action. This is sufficient to warrant the imposition of costs.

*By the Court.*— The findings of the referee are confirmed. The clerk is directed to enter judgment in favor of the plaintiff for $9,649.83, together with his taxable costs and disbursements.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Assessment of NEPTUN Reflooding Experiments 5050 and 5052 with TRACE V5.0 Patch 5 (NUREG/IA-0495)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0495 (PDF – 1.79 MB)

## Publication Information

**Manuscript Completed:** December 2017**Date Published:** February 2019

**Prepared by:** S. Hillberg

VTT Technical Research Centre of Finland Ltd  P.O. Box 1000 FI-02044 VTT, Finland

Kirk 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

NEPTUN experiments 5050 and 5052 have been simulated with TRACE V5.0 Patch 5. Calculation results were compared to experiment data received from OECD/NEA databank but, unfortunately, not all original experiment data was available. Uncertainties of the experimental data were not quantified in the original material nor were there enough available data in order to form an estimate. There is also uncertainly about radial placement of those thermocouples for which data is available. 

Both simulations show qualitatively similar results: TRACE predicts higher temperature in the lower parts of the test section which leads to later quenching than in the experiment. In higher elevations temperatures are a closer match but there is still a significant difference in quenching times. Collapsed water level prediction is in reasonably good agreement in both experiments. 

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsConference Proceedings Prepared by NRC Staff or Contractors

# International Collaborative Project to Evaluate Fire Models for Nuclear Power Plant Applications: Proceedings of 5th Meeting (NUREG/CP-0181)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CP-0181 (PDF 28.43 MB)

## Publication Information

**Manuscript Completed:**May 2003**Date Published:**October 2003

**Prepared by:** M. K. Dey Division of Risk Analysis and Applications U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

A. Hamins Building and Fire Research Laboratory National Institute of Standards and Technology Gaithersburg, MD 20899

S. Miles Fire and Risk Sciences Division Building Research Establishment Ltd., UK (BRE)

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

Availability Notice

## Abstract

The 5th Meeting of the International Collaborative Project to Evaluate Fire Models for Nuclear Power Plant Applications was hosted by the National Institute of Standards and Technology (NIST), U.S. Department of Commerce and held at NIST headquarters at Gaithersburg, Maryland on May 2 and 3, 2002. The organizing Committee for the meeting included Moni Dey from the U.S. Nuclear Regulatory Commission (U.S. NRC), and Anthony Hamins from NIST. Thirty three participants from five countries attended the international meeting. 

The purpose of the 5th meeting was mainly to discuss the results of Benchmark Exercise # 2, "Pool Fires in Large Halls," conducted in the project. Validation and regulatory applications of fire models were also presented and discussed in the meeting. The results presented for Part I of Benchmark Exercise # 2 were generally quite encouraging. While the general, qualitative, nature of the experiments had been captured in the simulations, a number of issues had arisen. Furthermore, the parametric analysis undertaken by a number of participants had yielded useful information. Different conclusions have been drawn on the most significant, or controlling, parameters. The combined effect of the choice of heat of combustion, combustion efficiency and radiative fraction was found to be an important factor. The validation and application of several, diverse fire models, ranging from empirical equations organized in worksheets to zone, lumpedparameter, and computational fluid dynamic (CFD) models, were presented and discussed at the meeting. The discussions emphasized the need to validate and determine the accuracy of such models, especially to understand the differences in the predictive capabilities and margins of uncertainty for the different types of models over a range of fire scenarios. This information is needed to establish safety factors and implement effective applications of these models in a regulatory framework. The need to define credible fire scenarios and generate data for fire sources, especially cable tray fires, was emphasized. 

Page Last Reviewed/Updated Wednesday, March 24, 2021