alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC Staff Proposes $110,000 Fine Against Commonwealth Edison for Discriminating Against Worker Who Raised Safety Issues

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R-III-99-47 November 5, 1999

 

**NRC Staff Proposes $110,000 Fine Against Commonwealth Edison for Discriminating Against Worker Who Raised Safety Issues**

The Nuclear Regulatory Commission staff has proposed a $110,000 fine against Commonwealth Edison Company for discriminating against an employee who raised safety issues in October 1997 at the Zion Nuclear Power Station.

The utility subsequently ceased operation of the Zion Station, located at Zion, Illinois.

NRC regulations prohibit employers at nuclear facilities from discriminating against employees who raise safety issues.

An NRC investigation determined that a mid-level manager at the plant discriminated against a Senior Reactor Operator who recommended that a pump be removed from service for troubleshooting as a result of an oil leak and who questioned the performance of a component in the emergency diesel generator system.

According to the investigation, the manager deferred the worker's planned participation in a program which would qualify him for a supervisory position and lowered a performance appraisal prepared by the worker's direct supervisor.

The results of the investigation, conducted in 1998, were discussed with the utility in a predecisional enforcement conference on July 7.

In notifying the utility of the proposed fine, James E. Dyer, NRC Regional Administrator, stated: "The NRC is concerned that discrimination by a mid-level plant official, along with the many additional employment discrimination allegations that were made about the management of the Zion Station at the same time, may have the potential to create a chilling effect among the employees who remain at the Zion Station and the employees transferred from the Zion Station to other NRC-licensed facilities operated by Commonwealth Edison."

The NRC staff directed the company to respond to the specific violation and, in addition, address whether employees at its nuclear facilities are working in a "safety conscious" work environment in which they feel free to readily report nuclear safety concerns.

The company has until December 3 to pay the fine or protest it. If the fine is protested and subsequently imposed by the NRC staff, Commonwealth Edison may request a hearing. 

Page Last Reviewed/Updated Wednesday, March 24, 2021
No. 82-969.

#### Aeronautical Machinists Lodge 709, International Association of Machinists & Aerospace Workers, AFL-CIO *v.*Lockheed Georgia Co., Division of Lockheed Corp.

C. A. 11th Cir. Certiorari denied.
EXHIBIT 32.1

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

I, Christopher D. Strong, certify, pursuant to 18 U.S.C. Section 1350, as adopted pursuant to Section 906 of the Sarbanes-Oxley Act of 2002, that the Annual Report of Union Drilling, Inc. on Form 10-K for the year ended December  31,  2006 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 Annual Report of Union Drilling, Inc. on Form 10-K fairly presents in all material respects the financial condition and results of operations of Union Drilling, Inc.

|        |  |  |        |  |  |                                                                           |
|--------|--|--|--------|--|--|---------------------------------------------------------------------------|
|   |  |  | By:    |  |  | /s/ Christopher D. Strong         |
|   |  |  | Name:  |  |  | Christopher D. Strong                                                     |
|   |  |  | Title: |  |  | President and Chief Executive Officer                                     |
|   |  |  | Date:  |  |  | March  15,  2007                                                          |
|        |

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I 

115TH CONGRESS 

1ST SESSION H. R. 180 

To amend title XIX of the Social Security Act to eliminate the requirement 

for 3 months of retroactive coverage under the Medicaid program. 

IN THE HOUSE OF REPRESENTATIVES 

JANUARY 3, 2017 

Mr. MULLIN (for himself and Mr. GUTHRIE) introduced the following bill; 

which was referred to the Committee on Energy and Commerce 

A BILL 

To amend title XIX of the Social Security Act to eliminate 

the requirement for 3 months of retroactive coverage 

under the Medicaid program. 

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

3 SECTION 1. ELIMINATION OF 3-MONTH RETROACTIVE COV4 ERAGE UNDER THE MEDICAID PROGRAM. 

5 (a) IN GENERAL.— 

6 (1) STATE PLAN REQUIREMENTS.—Section 

7 1902(a)(34) of the Social Security Act (42 U.S.C. 

8 1396a(a)(34)) is amended by striking ‘‘in or after 

9 the third month before the month in which he made 


SSpencer on DSK4SPTVN1PROD with BILLS
2 

•HR 180 IH

1 application’’ and inserting ‘‘in or after the month in 

2 which the individual made application’’. 

3 (2) DEFINITION OF MEDICAL ASSISTANCE.— 

4 Section 1905(a) of the Social Security Act (42 

5 U.S.C. 1396d(a)) is amended by striking ‘‘in or 

6 after the third month before the month in which the 

7 recipient makes application for assistance’’ and in8 serting ‘‘in or after the month in which the recipient 

9 makes application for assistance’’. 

10 (b) EFFECTIVE DATE.—The amendments made by 

11 subsection (a) shall apply to medical assistance with re12 spect to individuals whose eligibility for such assistance 

13 is based on an application for such assistance made (or 

14 deemed to be made) after the date of the enactment of 

15 this Act. 

Æ 


SSpencer on DSK4SPTVN1PROD with BILLS
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Human Event Repository and Analysis (HERA) System (NUREG/CR-6903)

Page Last Reviewed/Updated Wednesday, March 24, 2021
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# TMI-2 Lessons Learned Task Force Final Report (NUREG-0585)

On this page:
        - Publication Information 
        - Abstract

Download complete document 
        - NUREG-0585 (PDF - 3.53 MB)

## Publication Information

**Manuscript Completed:**October 1979**Date Published:**October 1979

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

Availability Notice

## Abstract

In its final report reviewing the Three Mile Island accident, the TMI-2 Lessons Learned Task Force has suggested change in several fundamental aspects of basic safety policy for nuclear power plants. Changes in nuclear power plant design and operations and in the regulatory process are discussed in terms of general goals. The appendix sets forth specific recommendations for reaching these goals.

Page Last Reviewed/Updated Tuesday, March 09, 2021
FIRST DISTRICT COURT OF APPEAL

STATE OF FLORIDA

_____________________________

No. 1D2024-0665

_____________________________

WEAVER HASTINGS,

Petitioner,

v.

STATE OF FLORIDA,

Respondent.

_____________________________

Petition for Writ of Prohibition—Original Jurisdiction.

May 14, 2024

PER CURIAM.

DISMISSED.

ROBERTS, RAY, and NORDBY, JJ., concur.

_____________________________

Not final until disposition of any timely and 

authorized motion under Fla. R. App. P. 9.330 or 

9.331.

_____________________________

Weaver Hastings, pro se, Petitioner.
2

Ashley Moody, Attorney General, Tallahassee, for Respondent.
No. 82-5930.

#### Shaumyan et al. *v.*Commissioner of Internal Revenue.

C. A. 2d Cir. Certiorari denied.
Unassociated Document


    
    

     

    
      	 	

              January
      26, 2011

            


    

     

    
      


      CDSI
Holdings Inc.

      100 SE
2nd
Street; 32nd
Floor

      Miami, FL
33131

      


      Re: Amendment
No. 1 to Revolving Credit Promissory Note

      


      Reference
is made to the Revolving Credit Promissory Note (the “Revolver”) dated March 26,
2009.  In consideration of the mutual agreements and covenants
contained therein and other good and valuable consideration, the parties hereto
agree to increase the Commitment Amount, as defined in the Revolver, from
$50,000 to $100,000.

      


      


      IN WITNESS WHEREOF, the
parties hereto have caused this Amendment No. 1 to the Revolving Credit
Promissory Note to be duly executed and attested, all as of the date first above
written.

      


      


      BORROWER:

      


      CDSI
HOLDINGS INC., a Delaware Corporation

       

      
        
          	 	 	 	 	 
	
                  By:
      

                	/s/
      Robert M. Lundgren	 	 
	 	Name: 	Robert
      M. Lundgren	 	 
	 	 	Director	 	 
	 	 	 	 	 


        

      

      


      LENDER

      


      VECTOR
GROUP LTD., A Delaware Corporation

      
         

        
          
            	 	 	 	 	 
	
                    By:
      

                  	/s/
      Marc N. Bell	 	 
	 	Name: 	Marc
      N. Bell	 	 
	 	 	Vice
      President, General Counsel and Secretary
No. 90-6348.

#### Griffin *v.*United States.

C. A. 8th Cir. Certiorari denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Allowable Shipment Frequencies for the Transport of Toxic Gases Near Nuclear Power Plants(NUREG/CR-2650,SAND82-0774)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-2650 (PDF - 1.69 MB)

## Publication Information

**Manuscript Completed:**October 1982 **Date Published:**October 1982

**Prepared by:** David E. Bennett, Nuclear Facility Analysis Division David C. Heath, Fuel Cycle Risk Analysis Division (Cornell University, College of Engineering) Sandia National Laboratories Albuquerque, New Mexico 87185 Operated by Sandia Corporation for the U.S. Department of Energy Under Contract No. DE-AC04-76DP00789

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

Under Memorandum of Understanding DOE-40-550-75

NRC FIN A-1214

Availability Notice

## Abstract

One part of the safety analysis of offsite hazards for a nuclear power plant is consideration of accidents which could release toxic gases or vapors and thus jeopardize plant safety through incapacitation of the control room operators. The purpose of this work is to provide generic, bounding estimates of the maximum allowable shipping frequencies for the transport of a chemical near the plant, such that the regulatory criteria for the protection of the operators are met. A probabilistic methodology was developed and then applied to the truck and rail transport of an example chemical, chlorine. The current regulatory criteria are discussed in detail. For this study, a maximum allowable probability of occurrence of operator incapacitation of 10-5 per year was used in the example calculation for each mode of transport. Comprehensive tables of conditional probabilities are presented. Maximum allowable shipping frequencies are then derived. These frequencies could be used as part of a generic, bounding criterion for the screening of toxic hazards safety analyses.

Unless a transport survey assures shipping frequencies within 8 km of the plant on the order of or lower than 4/week for rail or 35/week for truck, the control room should be isolatable and the shipping frequency then determines the degree of isolation needed. The need for isolation implies the need for toxic chemical detection at the air intake.

For a self-detection case in which the smell threshold is significantly lower than the incapacitation threshold and the control room is isolatable, the corresponding shipping frequencies are 11/week for rail or 115/week for truck. Self-contained breathing equipment is assumed to be used after 5 minutes.

Page Last Reviewed/Updated Thursday, March 25, 2021
<TABLE> <S> <C>

<PAGE>
<ARTICLE> 7
<MULTIPLIER> 1,000

<S>                             <C>
<PERIOD-TYPE>                   3-MOS
<FISCAL-YEAR-END>                          DEC-31-2000
<PERIOD-END>                               MAR-31-2000
<DEBT-HELD-FOR-SALE>                                 0
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<POLICY-LOSSES>                              1,319,412
<UNEARNED-PREMIUMS>                            166,412
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<COMMON>                                           140
<OTHER-SE>                                     269,479
<TOTAL-LIABILITY-AND-EQUITY>                 1,943,058
<PREMIUMS>                                      81,398
<INVESTMENT-INCOME>                             15,404
<INVESTMENT-GAINS>                                 797
<OTHER-INCOME>                                       0
<BENEFITS>                                      61,351
<UNDERWRITING-AMORTIZATION>                     30,315
<UNDERWRITING-OTHER>                                 0
<INCOME-PRETAX>                                  2,521
<INCOME-TAX>                                       555
<INCOME-CONTINUING>                                  0
<DISCONTINUED>                                       0
<EXTRAORDINARY>                                      0
<CHANGES>                                            0
<NET-INCOME>                                     1,966
<EPS-BASIC>                                        .15
<EPS-DILUTED>                                      .15
<RESERVE-OPEN>                                       0
<PROVISION-CURRENT>                                  0
<PROVISION-PRIOR>                                    0
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</TABLE>
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# NRC Editorial Style Guide (NUREG-1379, Revision 3)

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        - Publication Information
        - Abstract

Download complete document
        - NUREG-1379, Revision 3 (PDF - 1.10 MB)

## Publication Information

**Manuscript Completed:** February 2022**Date Published:** April 2022

**Prepared by:**J. Dougherty

L. Ronewicz, NRC Project Manager

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

Availability Notice

## Abstract

NUREG-1379, Revision 3, "NRC Editorial Style Guide," presents style guidance for U.S. Nuclear Regulatory Commission (NRC) documents. It addresses editorial issues that the staff and NRC contractors often handle, and it contains guidance specific to the language of nuclear technology and regulation.

This style guide also links writers and editors to external authorities and agency resources for additional information on the topics covered, including the principles of plain writing, which support the agency’s goals of transparency and accessibility. Additionally, the guide modernizes agency guidance on typography, updates the spelling and use of computer-related terminology, and guides the staff to use more inclusive language.

This revision substantially aligns NRC style with these well-known authorities: *The Chicago Manual of Style Online (Chicago)*, the *GPO Style Manual*, and *Federal Plain Language Guidelines*. It is important to note that these references often present more than one acceptable way to write; moreover, they do not always agree. In most cases, *Chicago* style is used. In those cases where *Chicago* is not followed, the preferred or required source for certain types of agency documents is usually identified.

This guidance will make agency documents more accessible to those for whom they are written and support the Commission’s values of openness and clarity.

Page Last Reviewed/Updated Thursday, April 28, 2022
SECRETARY'S CERTIFICATE
                             -----------------------

         The undersigned Secretary of Pharmaceutical Product Development, Inc.
(hereinafter referred to as the "Corporation") hereby certifies that the
following resolution to amend the Pharmaceutical Product Development, Inc.
Employee Stock Purchase Plan was duly adopted by the shareholders of the
Corporation at the Annual Meeting of Shareholders held on May 16, 2000:

         "Increase in Employee Stock Purchase Plan Shares. The number of shares
         of the Corporation's common stock reserved for issuance under the
         Corporation's Employee Stock Purchase Plan is increased from 500,000 to
         1,250,000 shares effective this 16th day of May, 2000."

WITNESS the hand of the undersigned Secretary and the seal of the Corporation as
of this 16th day of May, 2000.



                                                 /s/ Fred B. Davenport, Jr.
                                                 --------------------------
                                                 Fred B. Davenport, Jr.



                                                 [Corporate Seal]
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Data Base for Radioactive Waste Management (NUREG/CR-1759)

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

# A Characterization of Faults in the Appalachian Foldbelt  (NUREG/CR-1621)

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        - Publication Information
        - Abstract

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        - NUREG/CR-1621 (PDF – 12.6 MB)

## Publication Information

**Manuscript Completed:** July 1980**Date Published:** September 1980

**Prepared By:** A. L. Odom, R. D. Hatcher, Jr. 

Contributing Authors: D. E. Dunn – University of New Orleans T. J. Engelder – Lamont-Doherty Geologic Observatory P. A. Geiser – University of Connecticut S. A. Kish – University of North Carolina S. Schamel – Lafayette College D. U. Wise – University of Massachusetts

Florida State University Tallahassee, FL 32306

**Prepared for** Division of Siting, Health and Safeguards Standards Office of Standards Development U.S. Nuclear Regulatory Commissions Washington, D.C. 20555 NRC FIN No. 81053-8 

Availability Notice

## Abstract

The characterization is a synthesis of available data on geologic faults in the Appalachian foldbelt regarding their description, generic implications, rate of movement, and potential as geologic-seismic hazards. It is intended to assist applicants and reviewers in evaluating faults at sites for nuclear facilities. Appalachian faults were found to fall into 13 groups which can be defined on either their temporal, generic, or descriptive properties. They are as follows: Group 1, faults with demonstrable Cenozoic movement; Group 2, Wildflysch type thrust sheets; Group 3, bedding plane thrusts – décollements; Group A, pre- to synmetamorphic thrusts in medium to high grade terranes; Group 5, post-metamorphic thrusts in medium to high grade terranes; Group 6, thrusts rooted in low crystalline basement; Group 7, high angle reverse faults; Group 8, strike slip faults; Group. 9, .normal (block) faults; Group 10, compound faults; Group 11, structural lineaments; Group 12, faults associated with local centers; and Group 13, faults related to geomorphic phenomena. Unhealed faults (Groups 1, 6, 8, 9, and 12) must be considered candidates for reactivation. Heated brittle or auctile faults (Groups 4, 5, and 10) are not places of mechanical discontinuity and are unlikely candidates for reactivation. The remaining groups (2, 3, 7, 11, and 13) should be individually assessed as to their potential for reactivation. 

Page Last Reviewed/Updated Thursday, March 25, 2021
No. 82-6012.

#### Fiorini *v.*United States.

C. A. 6th Cir. Certiorari denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Comparison of Estimated Ground-Water Recharge Using Different Temporal Scales of Field Data (NUREG/CR-6653)

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        - Publication Information
        - Abstract

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        - NUREG/CR-6653 (PDF - 4.11 MB) 

## Publication Information

**Manuscript Completed:** February 2000**Date Published:** April 2000

**Prepared by:** D. Timlin, J. Starr, USDA  R. Cady, T. Nicholson, NRC

U.S. Department of Agriculture Agricultural Research Service Beltsville Agricultural Research Center Beltsville, MD 20705-2350

T. Nicholson, 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 W6896

Availability Notice

## Abstract

This study investigated field instrumentation [multi-sensor capacitance probes (MCP)] and analytical methods for estimating "real-time" infiltration and subsequent ground-water recharge and their attendant uncertainties. The research design was to apply a selected subset of existing field characterization data from the Beltsville Agricultural Research Center to technical issues identified by the NRC staff involving ground-water recharge estimates at nuclear facilities. The datasets allow comparisons of ground-water recharge estimates using near-continuous, water content measurements to recharge estimates based on less frequent water content observations (e.g. hourly or daily), intermittently measured piezometric data or analytical models. Drainage was underestimated by only using changes in water contents measured by MCP. Differences in water content did not always accurately represent fluxes when the system was at steady state. The estimate of net ground-water recharge decreased as measurement frequency decreased. The MCP data provided better estimates of recharge and timing than the piezometer data. Estimates of ground-water recharge were also compared to simulated recharge using a PNNL water budget model. The optimization of data in combination with a model can significantly reduce errors associated with using changes in water contents alone. A model optimized for hydraulic conductivity and moisture release parameters can calculate the fluxes using boundary conditions provided by the MCP and rainfall data. Further studies should move to larger scales (i.e., watershed) and lysimeters.

Page Last Reviewed/Updated Thursday, March 25, 2021