alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
<PAGE>

                                                                   Exhibit 10.24

                    AMENDMENT NO. 2 TO EMPLOYMENT AGREEMENT

     AMENDMENT NO. 2 TO EMPLOYMENT AGREEMENT made as of March 21, 2001 between
GLOBIX CORPORATION, a Delaware corporation ( the "Company"), having an office at
139 Centre Street, New York, New York, and  MARC H. BELL ("Executive"), residing
at ________________________.

     WHEREAS, the Company and Executive are parties to the Employment Agreement
dated April 10, 1998 between the Company and Executive, as amended by an
Agreement dated as of March 2, 1999 between the Company and Executive (as so
amended, the "Employment Agreement");

     WHEREAS, the Company and Executive desire to amend the Employment
Agreement;

     NOW, THEREFORE, it is agreed as follows:

     1.   The first sentence of Section 2 is hereby amended to read as follows:

               Executive shall be Chairman and Chief Executive Officer of
               Company.

     2.   The following is hereby added at the end of Section 3.02 of the
Employment Agreement:

               The foregoing calculation shall be appropriately adjusted to take
               account of stock splits, stock dividends and other similar
               transactions as determined by the Company.

     3.   For a period of five years after the date of termination of
Executive's employment with the Company, the Company shall continue to provide
Executive, at the Company's cost, with family medical insurance coverage at
least equal to the coverage provided by the Company to Executive at the time of
the termination of his employment.

     4.   During his employment and for a period of five years after the
termination of Executive's employment with the Company, the Company shall
continue to pay or reimburse Executive for all costs and expenses incurred by
Executive in installing and maintaining a T-1 data transmission line, or the
then current technological equivalent, at up to two locations of Executive's
choosing.

     5.   For a period of six months after the termination of Executive's
employment with the Company, the Company will continue to provide Executive with
the exclusive use of an office equivalent to the office occupied by him at the
date of termination and secretarial and other office services consistent with
past practice.

          IN WITNESS WHEREOF, the parties hereto have duly executed this
Agreement as of the date first above written.

                                    GLOBIX CORPORATION


                                    By   /s/ Brian L. Reach
                                      ------------------------------------------
                                            Brian L. Reach, Senior V.P.
                                            and Chief Financial Officer

                                    EXECUTIVE:

                                         /s/ Marc H. Bell
                                    --------------------------------------------
                                            Marc H. Bell
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsConference Proceedings Prepared by NRC Staff or Contractors

# Proceedings of the Information-Sharing Workshop on High Energy Arcing Faults (HEAFS) (NUREG/CP-0311)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG CP-0311 (PDF - 13 MB)

## Publication Information

**Manuscript Completed:** July 2018**Date Published:** July 2019

**Prepared by:** G. Taylor K. Hamburger N. Melly K. Miller S. Gardocki T. Boyce

Mark Henry Salley, NRC Project Manager

Office of Nuclear Regulatory Research U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Availability Notice

## Abstract

The U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Regulatory Research, organized this *Information-Sharing Workshop on High Energy Arcing Faults (HEAFs)*. The workshop took place April 18–19, 2018, at the NRC Headquarters' Professional Development Center, Building Three, 11601 Lansdown Street, Rockville, MD. The workshop had the following four objectives:

(1) Inform interested stakeholders about the status of PRE-GI-018 and related research.

(2) Review and resolve public comments received on the phase II draft test plan.

(3) Solicit and review information from industry partners regarding common equipment types and configurations to inform future testing.

(4) Provide an opportunity for public feedback on future testing.

The workshop was a Category 3 public meeting and open to the public for participation. The NRC broadcasted the meeting via webinar to encourage participation among interested parties for whom travel was not possible. The agency coordinated the workshop with the Electric Power Research Institute (EPRI) and the National Fire Protection Association (NFPA). The organizers advertised the workshop at recent nuclear industry information forums and during NRC public meetings related to fire protection. The workshop's technical topics focused on HEAF hazards and recently completed and ongoing research initiatives. The workshop also covered the NRC's Generic Issues (GI) program as it relates to the aluminum HEAF issue. This proceedings report documents the recommendations and insights from the session presentations and follow-on discussions.

Page Last Reviewed/Updated Thursday, March 25, 2021
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<PAGE>
<ARTICLE> 5
<LEGEND>
THIS SCHEDULE CONTAINS SUMMARY FINANCIAL INFORMATION EXTRACTED FROM THE
CONSOLIDATED INCOME STATEMENTS.  THE CONSOLIDATED BALANCE SHEETS AND THE
ACCOMPANYING NOTES TO THE CONSOLIDATED FINANCIAL STATEMENTS, AND IS QUALIFIED IN
ITS ENTIRETY BY REFERENCE TO SUCH FINANCIAL STATEMENTS.
</LEGEND>
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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Survey of Waste Solidification Process Technologies (NUREG/CR-6666)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6666 (PDF - 11.04 MB)

## Publication Information

**Manuscript Completed:** January 2001**Date Published:** February 2001

**Prepared by:** V. Jain

Center for Nuclear Waste Regulatory Analyses Southwest Research Institute 6220 Culebra Road San Antonio, Texas 78238-5166

R E. Shewmaker, NRC Project Manager

**Prepared for:** Division of Fuel Cycle Safety and Safeguards Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission****Washington, DC 20555-0001

NRC Job Code J5164

Availability Notice

## Abstract

This report provides a current status of the high-temperature solidification technologies that have been used or proposed in the United States and abroad. The technologies presented in this report can be broadly classified into the following categories: Inconel-based, jouleheated melters; high-temperature, joule-heated melters; induction melters; cold-crucible induction melters; plasma melters; combustion melters; microwave melters; molten metal technology; and Synroc technology. The operating experience and safety issues associated with major solidification technologies are summarized.

Page Last Reviewed/Updated Thursday, March 25, 2021
No: II-19-002 February 26, 2019

Contact: Roger Hannah, 404-997-4417

 Joey Ledford, 404-997-4416

NRC Schedules Meeting to Discuss TVA Confirmatory Orders

The Nuclear Regulatory Commission staff has scheduled a public meeting for March 6, at the 

request of the Tennessee Valley Authority, to discuss proposed changes to Confirmatory Orders issued 

in 2009 and 2017. The meeting will also address safety conscious work environment issues at TVA’s 

three nuclear power plants.

The meeting is scheduled to begin at 9 a.m., in Classroom 4A at the NRC Technical Training 

Center, located in the Osborne Office Center, 5746 Marlin Road, in Chattanooga, Tenn.

The NRC Order issued in 2017 contained a list of corrective actions agreed upon by TVA 

officials to address the work environment issues at Browns Ferry in Alabama, and Sequoyah and 

Watts Bar in Tennessee.

The 2017 Order was a result of NRC inspections conducted beginning in 2014 through 2016. 

Inspectors found that TVA failed to properly implement a process to ensure that adverse employment 

actions at the Watts Bar plant complied with employee protection regulations and that the actions 

would not negatively impact the safety conscious work environment. 

The public will have the opportunity to observe the meeting and to communicate with the NRC 

staff following the business portion of the meeting. A toll-free teleconference line will also be provided 

for those unable to attend. Anyone wanting to participate by phone should contact Manuel Crespo at 

404-997-4733 or Manuel.Crespo@nrc.gov by March 4.
UNPUBLISHED

UNITED STATES COURT OF APPEALS

FOR THE FOURTH CIRCUIT

No. 95-7900

TERRY R. FOREMAN,

Plaintiff - Appellant,

versus

ALTON BASKERVILLE, Warden; JOHN METZGER, Parole Board Member; SANDRA COMBS, Parole Board

Member; LINDA PITTMAN, Parole Board Member;

WINNIE R. DIXON, Parole Board Member,

Defendants - Appellees.

Appeal from the United States District Court for the Eastern District of Virginia, at Richmond. James R. Spencer, District Judge.

(CA-95-64)

Submitted: February 7, 1996 Decided: February 29, 1996

Before MURNAGHAN and WILLIAMS, Circuit Judges, and PHILLIPS, Senior

Circuit Judge.

Affirmed by unpublished per curiam opinion.

Terry R. Foreman, Appellant Pro Se. Mary Elizabeth Shea, OFFICE

OF THE ATTORNEY GENERAL OF VIRGINIA, Richmond, Virginia, for

Appellees.

Unpublished opinions are not binding precedent in this circuit.

See Local Rule 36(c).
2

PER CURIAM:

Appellant appeals from the district court's order denying

relief on his 42 U.S.C. § 1983 (1988) complaint. We have reviewed

the record and the district court's opinion and find no reversible

error. Accordingly, we affirm on the reasoning of the district

court. Foreman v. Baskerville, No. CA-95-64 (E.D. Va. Nov. 3,

1995). We dispense with oral argument because the facts and legal

contentions are adequately presented in the materials before the

court and argument would not aid the decisional process.

AFFIRMED
No. 85-6660.

#### Green *v.*Illinois.

App. Ct. Ill., 1st Dist. Motion of petitioner for leave to proceed *in forma pauperis*and certiorari granted. Judgment vacated and case remanded for further consideration in light of *Griffith*v. *Kentucky, ante,*p. 314.
No. 86-6024.

#### Rosberg *v.*Nebraska.

Sup. Ct. Neb. Certiorari denied.
Human Factors Information System (HFIS)

U.S. Nuclear Regulatory Commission

From 01/01/2007 to 12/31/2007Page 1 of 210/09/2008 15:13:13

2x N

Total 

N

Document Types: IR, LER IR/LER Category Analysis by Docket Report

N

Average for Se

Details Department Work Type 

Facility Name: Nine Mile Point 2 Docket (050- 00410)

Fitness for Duty / IR120 - Testing LTA O - Operations O - Control Room Ops 

121 - Assessment LTA O - Operations O - Control Room Ops 128 - Non-compliance O - Operations O - Control Room Ops 

316

Number of Items for this Docket: 

Percent of Total for this Docket: 

Oversight / IR130 - Inadequate suprevision / command and control O - Operations O - Control Room Ops 

131 - Management expectations or directions LTA O - Operations O - Control Room Ops 

211

Number of Items for this Docket: 

Percent of Total for this Docket: 

Procedures & Reference Document / IR111 - Procedure / reference document technical content D - Emergency Planning Q - Fire Protection 

111 - Procedure / reference document technical content M - Mechanical M - Maintenance / Repair 

211

Number of Items for this Docket: 

Percent of Total for this Docket: 

Problem Identification & Resolution / IR142 - Operating experience (OE) review LTA O - Operations O - Control Room Ops 

142 - Operating experience (OE) review LTA O - Operations O - Control Room Ops 144 - Audit / self-assessment / effectiveness review LTA O - Operations O - Control Room Ops 146 - Evaluation LTA O - Operations O - Control Room Ops 

421

Number of Items for this Docket: 

Percent of Total for this Docket: 

Training / IR101 - Training process problem T - Training N - Training 

102 - Individual knowledge LTA O - Operations O - Control Room Ops 102 - Individual knowledge LTA O - Operations O - Control Room Ops 

316

Number of Items for this Docket: 

Percent of Total for this Docket: 

Work Planning & Practices / IR182 - Work package quality LTA D - Emergency Planning Q - Fire Protection 

185 - Procedural adherence LTA I - Instrumentation & Control S - Surveillance 186 - Failure to take action / meet requirements O - Operations O - Control Room Ops 
Human Factors Information System (HFIS)

U.S. Nuclear Regulatory Commission

From 01/01/2007 to 12/31/2007Page 2 of 210/09/2008 15:13:13

2x N

Total 

N

Document Types: IR, LER IR/LER Category Analysis by Docket Report

N

Average for Se

Details Department Work Type 

Facility Name: Nine Mile Point 2 Docket (050- 00410)

Work Planning & Practices / IR186 - Failure to take action / meet requirements O - Operations O - Control Room Ops 

197 - Self-check LTA I - Instrumentation & Control S - Surveillance 

526

Number of Items for this Docket: 

Percent of Total for this Docket: 

Total Items for this Docket: 19
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<PAGE>

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</TABLE>
#### Estate of Daritz: Baraboo National Bank, Executor, Appellant, vs. Dubost and others, Respondents.

For the appellant: *Longer, Gessner & Dana,*of Bara-boo, attorneys, and *Ela, Christianson & Ela*of Madison of counsel.

For the respondents: *Stephens, Sletteland & Cannon*and *A. E. Kilmer*of Madison, and *James H. Hill, Sr.,*of Bara-boo, guardian *ad litem*for Lynn Sulis.

*By the Court.*

Judgment and order affirmed.
#### Guse, Appellant, vs. Flohr and others, Respondents.

*October 9, 1928.*

For former opinion, see 195 Wis. 139.

The following opinion was filed October 9, 1928:

Per Curiam.

A motion has been made in this case in which it is called to our attention that the language of the opinion is not clear. It was the intention of the court to hold that the south line of plaintiff’s land was the line upon which the fence on the south side of the way granted to the predecessors of the défendants was erected. If it fails to conform to the line established by the Allen survey, then the line upon which the fence was built must govern. That is what the court intended to say by its opinion. Otherwise, the motion of the parties is denied, without costs.
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC Issues Performance Review for Peach Bottom Nuclear Plant

----

----

I-99-37 April 13, 1999

 

**NRC ISSUES PERFORMANCE REVIEW FOR PEACH BOTTOM NUCLEAR PLANT**

The Nuclear Regulatory Commission staff, in its latest assessment of performance at the Peach Bottom nuclear power plant, has found that safety performance at the facility remains acceptable. PECO Nuclear Corp. operates the twin-reactor plant, located in Delta, Pa.

In a letter to the company outlining the results of the review, Curtis J. Cowgill, chief of the NRC Region I Division of Reactor Projects branch responsible for inspecting Peach Bottom, wrote that plant management provided strong oversight of activities and took effective actions during the evaluation period of April 1998 through Jan. 15, 1999. Those actions reversed a slight decline in operator performance in early 1998, he said.

Cowgill said operator performance has improved since plant management instituted a "Back to Basics" initiative and enhanced peer reviews and self-checking. Maintenance activities were safely performed, resulting in reliable plant equipment. Engineering continued to safely support plant activities and has improved its investigative and diagnostic activities during the troubleshooting of plant equipment failures. Plant support was consistently strong, with radiation protection activities during the Unit 2 refueling outage particularly effective.

Based on this performance, the NRC staff will conduct normal inspections during the next evaluation period, with a supplemental inspection to review the plant's program for identifying and fixing problems.

The text of the plant performance review (PPR) letter is available from the NRC Region I Office of Public Affairs and on the NRC web site.

NRC reviews safety performance twice a year at every licensed nuclear power plant in the nation. These reviews give the agency staff an integrated assessment of plant performance and provide a basis for planning inspection activities.

PPRs are being used by the NRC as an interim measure to monitor nuclear power plant safety. The agency began using it for this purpose after suspending the Systematic Assessment of Licensee Performance (SALP) process until a new assessment program is developed. Previously, SALP reports were issued every 12 to 24 months.

The new reactor oversight and assessment program being developed will provide quarterly performance reports, based on a number of performance indicators and on inspection findings. This program will be tested at eight sites beginning in June and will be extended to all plants next January. A full description of the new program is available on the NRC web.

Page Last Reviewed/Updated Wednesday, March 24, 2021