alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
[Federal Register Volume 80, Number 15 (Friday, January 23, 2015)]
[Notices]
[Page 3624]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-01211]


-----------------------------------------------------------------------

DEPARTMENT OF JUSTICE

[CPCLO Order No. 001-2015]


Privacy Act of 1974; Systems of Records

AGENCY: Office of Legal Counsel, Department of Justice.

ACTION: Notice of termination of two systems of records.

-----------------------------------------------------------------------

SUMMARY: Pursuant to the Privacy Act of 1974 (5 U.S.C. 552a), the 
United States Department of Justice, Office of Legal Counsel, is 
terminating the systems of records entitled ``Office of Legal Counsel 
Attorney Assignment Reports, JUSTICE/OLC-001'' and ``Office of Legal 
Counsel Central File, JUSTICE/OLC-003.'' The Department is eliminating 
the Attorney Assignment Reports system because the reports no longer 
exist and have been destroyed. The Department is eliminating the 
Central File system because the 5 x 7 card index no longer exists and 
the records maintained in the Central File are not retrieved by the 
name of individuals or by other identifying information assigned to 
individuals.
    Accordingly, the Privacy Act system of records notices last 
published in the Federal Register on September 4, 1985, 50 FR 35878, 
35879, are removed from the Department's compilation of Privacy Act 
systems.

    Dated: January 8, 2015.
Erika Brown Lee,
Chief Privacy and Civil Liberties Officer.
[FR Doc. 2015-01211 Filed 1-22-15; 8:45 am]
BILLING CODE 4410-23-P
<PAGE>

                                                                  Exhibit 10.17A


                    FIRST AMENDMENT TO EMPLOYMENT AGREEMENT

          THIS FIRST AMENDMENT (this "Amendment") is made as of  this 1st day of
                                                                      ---
January, 2000 to that certain EMPLOYMENT AGREEMENT, dated as of November 30,
l999 (the "Employment Agreement"), by and between ROBERT HENSLEY ("Employee")
and JOS. A. BANK CLOTHIERS, INC. ("Employer").

          WHEREAS, the offer letter pursuant to which the Employment Agreement
was negotiated stated that Employee would receive, among such other compensation
as may be due and payable, a car allowance in the amount of $800.00 per month;
and

          WHEREAS, the car allowance was inadvertently omitted from the
Employment Agreement; and

          WHEREAS, Employer and Employee have agreed to amend the Employment
Agreement to reflect the original terms of the offer letter with regard to the
car allowance.

          NOW THEREFORE, FOR GOOD AND VALUABLE CONSIDERATION, the receipt and
adequacy of which are hereby acknowledged, Employer and Employee, being the sole
parties to the Employment Agreement, hereby amend the Employment Agreement by
adding thereto a new Section 3.7 as follows:

          3.7 Car Allowance. In addition to such other compensation as may be
              -------------
due and payable hereunder, Employer shall pay to Executive a car allowance in
the amount of $800.00 per month during the Employment Period.

          Except as specifically amended hereby, the Employment Agreement shall
remain in full force and effect according to its terms. To the extent of any
conflict between the terms of this Amendment and the terms of the remainder of
the Employment Agreement, the terms of this Amendment shall control and prevail.
Capitalized terms used but not defined herein shall have those respective
meanings attributed to them in the Employment Agreement. This Amendment shall
hereafter be deemed a part of the Employment Agreement for all purposes.

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

JOS. A. BANK CLOTHIERS, INC.

By:    /s/: Robert N. Wildrick                    /s/: Robert Hensley
  ----------------------------------------        -------------------
  Robert N. Wildrick,                             ROBERT HENSLEY
   Chief Executive Officer
```

[Federal Register Volume 79, Number 65 (Friday, April 4, 2014)]
[Notices]
[Page 18908]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-07584]

=======================================================================
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ENVIRONMENTAL PROTECTION AGENCY

[ER-FRL-9014-3]

Environmental Impact Statements; Notice of Availability

    Responsible Agency: Office of Federal Activities, General 
Information (202) 564-7146 or http://www.epa.gov/compliance/nepa/.

Weekly receipt of Environmental Impact Statements Filed 03/24/2014 
Through 03/28/2014 Pursuant to 40 CFR 1506.9.

Notice:

    Section 309(a) of the Clean Air Act requires that EPA make public 
its comments on EISs issued by other Federal agencies. EPA's comment 
letters on EISs are available at: http://www.epa.gov/compliance/nepa/eisdata.html.

EIS No. 20140100, Final EIS, BLM, CO, Colorado River Valley Proposed 
Resource Management Plan, Review Period Ends: 05/05/2014, Contact: 
Brian Hopkins 970-876-9073.
EIS No. 20140101, Final EIS, FHWA, NY, New York Gateway Connections 
Improvement Project to the US Peace Bridge Plaza, Review Period Ends: 
05/05/2014, Contact: Jonathan McDade 518-431-4127.
EIS No. 20140102, Final EIS, USFS, ID, Lost Creek-Boulder Creek 
Landscape Restoration Project, Review Period Ends: 05/12/2014, Contact: 
Holly Hutchinson 208-347-0325.
EIS No. 20140103, Final EIS, FERC, AZ, Sierrita Pipeline Project, 
Review Period Ends: 05/05/2014, Contact: David Hanobic 202-502-8312.
EIS No. 20140104, Final Supplement, FHWA, WI, Wisconsin State Highway 
23, Fond du Lac to Plymouth, Contact: George Poirier 608-829-7500. 
Under MAP-21 section 1319, FHWA has issued a single SFEIS and ROD. 
Therefore, the 30-day wait/review period under NEPA does not apply to 
this action.
EIS No. 20140105, Draft EIS, NOAA, CA, Cordell Bank and Gulf of the 
Farallones Boundary Expansion, Comment Period Ends: 06/30/2014, 
Contact: Maria Brown 541-561-6622.

Amended Notices

EIS No. 20140074, Final EIS, USAF, 00, KC-46A Formal Training Unit 
(FTU) and First Main Operating Base (MOB 1) Beddown, Review Period 
Ends: 04/21/2014, Contact: Jean Reynolds 210-925-4534. Revision to the 
FR Notice Published 03/21/2014; Correction to the Agency Contact Phone 
Number 210-925-4534.

    Dated: April 1, 2014.
Cliff Rader,
Director, NEPA Compliance Division, Office of Federal Activities.
[FR Doc. 2014-07584 Filed 4-3-14; 8:45 am]
BILLING CODE 6560-50-P
```
exv10w10






Exhibit 10.10




	 	 	 

	

	Special Operations Equipment Solutions	 






July 27, 2010




	 	 	 

	To:

	 	Jason Wallace
	From:

	 	Dan Clarkson/Luke Hillier
	Re:

	 	2010 Compensation Plan Details






Jason:



Below are the details for your 2010 Executive Compensation Plan. This plan goes into
effect January 1, 2010.




Annual Base Salary

$9,773.08 paid bi-weekly, annualizes to $254,100




Annual Bonus Opportunity 

$231,931



Bonuses will be paid as a combination of quarterly achievement bonuses and a year-end EBITDA bonus.





	 	•	 	Quarterly Bonus Goal: $69,000 — $17,250/quarter
	 
	 	•	 	Year-End EBITDA Bonus Goal: $162,931 (at 100% EBITDA)






	 	o	 	Please note, there will be no cap to the EBITDA portion of this bonus plan.
Should the company surpass its EBITDA goal, bonus payout will multiply by the
same percentage at which this goal is exceeded. (i.e., if company EBITDA exceeds
plan by 20%, the EBITDA bonus target will be 120% of stated bonus goal)





Commission

0.124% of company’s overall gross margin

Gross Margin Goal = $158,000,000

Commission Target:      $195,920




Total Target Earnings

$681,951



This compensation plan is subject to change at the sole discretion of the company. Please be
advised that business needs may require occasional shifts in goals, territories, and personnel.
Compensation information is private and confidential and for your sole use. Any employee found to
be sharing compensation information may be subject to disciplinary action up to and including
termination. This document in no way implies a contract for continued
employment. Employment with
ADS is At-Will.




	 	 	 	 	 	 	 

	/s/ Luke Hillier

	 	 	 	/s/ Jason
Wallace
	 	7/27/10
	 	 	   
	Luke Hillier

	 	date
	 	Jason Wallace
	 	date
HomeNRC LibraryDocument CollectionsRegulatory Guides (by Division)Division 10 - General

# General (Division 10): Regulatory Guides 10.1 - 10.12

This page lists the number, title, publication date, and revisions for each regulatory guide in Division 10, "General," with references to draft guides and related documents (where applicable).

See also Draft Regulatory Guides for Public Comment.

See NRC Regulatory Guides for more general information.

Regulatory Guides are reviewed about every 10 years, although a guide may be reviewed more frequently if the staff believes an emerging issue affects the guide. The NRC began these reviews in 2010, and began posting the results of its reviews on this site in 2013. The review dates are hyperlinked to the review memorandum, which provide useful information about the status and any known issues with the associated regulatory guide.

*This page includes links to files in non-HTML format. See Plugins, Viewers, and Other Tools for more information.*

Page Last Reviewed/Updated Wednesday, April 03, 2024
By order of the Bankruptcy Appellate Panel, the precedential effect 

of this decision is limited to the case and parties pursuant to 

6th Cir. BAP LBR 8024-1(b). See also 6th Cir. BAP LBR 8014-1(c). 

File Name: 17b0004n.06 

BANKRUPTCY APPELLATE PANEL 

OF THE SIXTH CIRCUIT 

In re: JOHN JOSEPH LOUIS JOHNSON III, 

Debtor. 

___________________________________________ 

JOHN JOSEPH LOUIS JOHNSON III, 

Plaintiff-Appellee, 

v. 

RFF FAMILY LIMITED PARTNERSHIP, LP, 

Defendant-Appellant. 

┐

│

│

│

│

│

│

│

│

│

│

┘

No. 16-8035 

Appeal from the United States Bankruptcy Court 

for the Southern District of Ohio at Columbus. 

No. 14-57104—John E. Hoffman, Judge. 

Argued: May 9, 2017 

Decided and Filed: June 2, 2017 

Before: HARRISON, OPPERMAN and WISE, Bankruptcy Appellate Panel Judges. 

_________________ 

COUNSEL 

ARGUED: Jeffrey M. Levinson, LEVINSON LLP, Cleveland, Ohio, for Appellant. Jeffrey A. 

Yeager, HAHN LOESER & PARKS, LLP, Columbus, Ohio, for Appellee. ON BRIEF: Jeffrey 

M. Levinson, LEVINSON LLP, Cleveland, Ohio, for Appellant. Jeffrey A. Yeager, Marc J. 

Kessler, Daniel A. DeMarco, Rocco I. Debitetto, HAHN LOESER & PARKS, LLP, Columbus, 

Ohio, for Appellee. 

>
No. 16-8035 In re Johnson Page 2

_________________ 

OPINION 

_________________ 

MARIAN F. HARRISON, Bankruptcy Appellate Panel Judge. RFF Family Partnership, 

LP (“RFF”), appeals the decision of the bankruptcy court to enter summary judgment for John 

Joseph Louis Johnson, III (“debtor”) on his complaint for declaratory relief seeking a declaration 

that: (1) RFF does not have a valid security interest in, or assignment of, debtor’s player contract 

or the salary payments under the contract; and (2) even if it did, RFF’s interest with respect to 

the salary debtor earned postpetition was cut off by Bankruptcy Code § 552. 

After carefully reviewing the record, the applicable law, and the parties’ briefs, the Panel 

finds that the bankruptcy court correctly set forth the facts and the governing law. This Panel’s 

issuance of a full opinion would serve no jurisprudential purpose and would be duplicative, and 

so we affirm the grant of summary judgment, adopting the reasoning of the bankruptcy court’s 

August 16, 2016, opinion, 554 B.R. 448 (Bankr. S.D. Ohio 2016). Accordingly, the bankruptcy 

court’s order granting the debtor’s motion for summary judgment is AFFIRMED.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# A Summary of Aging Effects and Their Management in Reactor Spent Fuel Pools, Refueling Cavities, Tori, and Safety-Related Concrete Structures (NUREG/CR-7111, ORNL/TM-2011/410)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7111 (PDF - 2.40 MB)

## Publication Information

**Manuscript Completed:**November 2011**Date Published:**January 2012

**Prepared by:** D.A. Copinger,1 C.B. Oland,2 and D.J. Naus1

1Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6165

2XCEL Engineering 1066 Commerce Park Drive Oak Ridge, TN 37830-8026

A.H. Sheikh and A. Prinaris, NRC Program Managers

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

Availability Notice

## Abstract

The Oak Ridge National Laboratory conducted an independent review of operating experience at U.S. commercial nuclear power plants regarding spent fuel pool and reactor cavity leakage, boiling-water reactor Mark I containment torus corrosion and cracking, and aging degradation of safety-related concrete structures. The review was restricted to information in publicly available sources, including license renewal applications submitted by the licensees and safety evaluation reports prepared by the staff. Information compiled for spent fuel pool and reactor refueling cavity leakage focused on the cause and extent of leakage, the effects of borated water on materials, the effects on concrete and steel degradation, corrective actions, and the effects of material degradation on load-carrying capacity. The review of boiling-water reactor Mark I containment information involved identification of the causes of torus corrosion and cracking, the locations of corrosion and cracking, and engineering evaluations and acceptance criteria. The review of operating experience for age-related degradation of concrete structures concentrated on corrosion; loss of prestressing force; concrete cracking, scaling, and spalling, including freeze-thaw; loss of bond between the concrete and embedded steel reinforcement; loss of strength; and increase in porosity and permeability. The results of the review are summarized in a series of degradation occurrence tables and discussed in plant-specific case studies.

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

# Generic Environmental Impact Statement for In-Situ Leach Uranium Milling Facilities (NUREG-1910)

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

# Proceedings of the 22nd DOE/NRC Nuclear Air Cleaning Conference, Sessions 9-16 (NUREG/CP-0130, Vol. 2)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG CP-0130, Volume 2 (PDF - 40.1 MB)

## Publication Information

**Date Published:** July 1993

**Edited by:**M. W. First

**Sponsored by:**Office of Nuclear SafetyU. S. Department of EnergyWashington, DC 20585

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

International Society of Nuclear Air Treatment Technologies, Inc.P. 0. Box 29246Columbus, OH 43229

Harvard School of Public HealthThe Harvard Air Cleaning Laboratory665 Huntington AvenueBoston, MA 02115

**Proceedings prepared by:**The Harvard Air Cleaning Laboratory

Availability Notice

## Abstract

This document contains the papers and the associated discussions of the 22nd DOE/NRC Nuclear Air Cleaning Conference. Major topics are: (1) advanced reactors, (2) reprocessing, (3) filter testing, (4) waste management, (5) instruments and sampling, (6) reactor accidents, (7) filters and'filter performance, (8) adsorber testing and performance, (9) carbon testing, and (10) ventilation systems.

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

# Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Base Welds Near Dissimilar Metal Weld Interfaces (NUREG/CR-7226)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7227 (PDF – 97.7 MB)

## Publication Information

**Manuscript Completed:** February 2016**Date Published:** January 2018

**Prepared by:** B. Alexandreanu, Y. Chen, K. Natesan, and W. J. Shack

Argonne National Laboratory Argonne, IL 60439

M. Audrain, NRC Project Manager

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

Availability Notice

## Abstract

The report summarizes the results of a testing program to evaluate the stress corrosion cracking (SCC) susceptibility at or near the interface between Alloy 52 and 152 weld metals and other weld or base metals. Alloys 52 and 152 are high-chromium weld metals used in reactor pressure vessel head penetration nozzles and as overlays, inlays, or onlays for dissimilar metal piping welds. Alloys 52 and 152 typically show very low SCC growth rates in laboratory testing and are not known to have cracked in service. Nevertheless questions remain as to whether the localized dilution of chromium content or the presence of microstructural features near the interface with the low-chromium weld metals Alloy 82 and 182, as in the case of a weld overlay (WOL), or with steel, as in the case of a head penetration nozzle, could affect the SCC response. For this study, SCC growth rates were measured on a WOL mockup with Alloy 52M (a compositional variant of Alloy 52) on Alloy 182 and on a butt weld mockup with Alloy 152 joined to low-alloy steel (LAS). For the WOL mockup, tests were performed in which the crack growth direction was either from Alloy 182 directly into Alloy 52M or along their interface. In the butt weld mockup, measurements were made in the first layer of weld butter beads, within about 1 mm of the interface with LAS. The tests on both mockups resulted in crack growth rates in Alloy 52M and 152 that are higher than have been previously reported for the weld metals, even though the dendrites were not favorably oriented for cracking. In the WOL mockup, crack branching along the interface was observed when the cracking direction was perpendicular to the interface. In the butt weld mockup, material compositional analyses taken along the crack path indicated that locations with the highest measured crack growth rates did not necessarily correlate with the lowest chromium content. This suggests that microstructural factors, in addition to the chromium content, could affect the SCC susceptibility near the interface.

Page Last Reviewed/Updated Thursday, March 25, 2021
<PAGE>
 
                                                                    Exhibit 11.1

                           REUNION INDUSTRIES, INC.

                       COMPUTATION OF EARNINGS PER SHARE
                        (IN THOUSANDS, EXCEPT PER DATA)

<TABLE> 
<CAPTION> 
                                                Three Months         Six Months
                                               Ended June 30,       Ended June 30
                                           --------------------   -------------------
                                             1998       1997        1998       1997
                                           --------   ---------   --------   --------
<S>                                        <C>        <C>         <C>        <C> 
Net (loss)                                 $(10,530)  $ (418)     $(10,256)  $ (123)
                                           ========   ======      ========   ======
Weighted average common shares
outstanding--Basic                            3,865    3,855         3,861    3,855

Net additional shares outstanding
assuming all stock options exercised
using the Treasury Stock Method                  --       --            --       --
                                           --------   ------      --------   ------
Average common shares and
common share equivalents
outstanding--Diluted                         3,865     3,855         3,861    3,855
                                           ========   ======      ========   ======
Net (loss) per share:

Basic                                      $ (2.72)   $(0.11)     $  (2.66)  $(0.03)
                                           ========   ======      ========   ======
Diluted                                    $ (2.72)   $(0.11)     $  (2.66)  $(0.03)
                                           ========   ======      ========   ======
</TABLE> 
Notes:
#### Schmidt, Appellant, vs. Riess and another, Respondents.

*March 11*—

April *7, 1925.*

*Schmidt v. Riess, ante,*p. 574, followed.

Appeal from a judgment of the circuit court for Milwaukee county: Chester A. Fowler, Judge.

*Affirmed.*

The appeal is from a judgment dismissing plaintiff’s complaint upon the merits, with costs.

*W. T. Sullivan*of Milwaukee, for the appellant.

For the respondents there was a brief by *Leahy & Kenney*of Milwaukee, and oral argument by *John J. Kenney.*

Doerfler, J.

The judgment in this case is affirmed, and the opinion in the case of *Schmidt v. Riess,*decided herewith *(ante,*p. 574, 203 N. W. 362), is applicable to this case.

*By the Court.*— Judgment affirmed.

Crownhart, J., dissents.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Steam Generator Tube Integrity Issues:Pressurization Rate Effects, Failure Maps, Leak Rate Correlation Models, and Leak Rates in Restricted Areas (NUREG/CR-6879, ANL-05/16)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6879 (PDF - 6.18 MB)

## Publication Information

**Manuscript Completed:** October 2008**Date Published:** July 2009

**Prepared by:** S. Majumdar, K. Kasza, S. Bakhtiari, J.Y. Park, J. Oras  J. Franklin, C. Vulyak, Jr., and W.J. Shack Nuclear Engineering Division  Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439

Margaret Stambaugh, NRC Project Manager

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

NRC Job Code Y6582

Availability Notice

## Abstract

This report summarizes results obtained under the Third International Steam Generator Tube Integrity Program (ISG-TIP-3). Tests were conducted to determine the effect of pressurization rate on rupture of flawed tubes. Based on analysis and tests, failure maps were developed that delineate ranges of ligament and crack sizes that could be susceptible to ligament rupture and/or unstable burst due to pressure drops of ΔPNO (normal operation), ΔPMSLB (main steam-line break), 1.4ΔPMSLB, and 3ΔPNO. Tests were conducted to determine the limits of applicability with respect to the through wall crack length and crack tightness of the simple orifice model for predicting leak rates of cracked tubes. Finally, leak rates were calculated for degraded tubes in restricted areas during postulated design-basis and severe accident conditions.

Page Last Reviewed/Updated Wednesday, March 24, 2021