alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
APPENDIX C Page 1

SMALL COMMUNITY AIR SERVICE DEVELOPMENT PROGRAM

DOCKET DOT-OST-2012-0069

SUMMARY INFORMATION

All applicants must submit this information with their proposal, along with a completed form SF424 on http://www.grants.gov

.

A. A PPLICANT I NFORMATION : ( CHECK ALL THAT APPLY ) ⌧ Not a Consortium Interstate Consortium Intrastate ConsortiumCommunity now receives EAS subsidy ⌧ Community (or Consortium member) previously recei ved a Small Community Grant If previous recipient: Date of grant: 09/15/2004 Expiration date of grant: 08/17/2006 Federal Funds Requested: $625,000.00 Carrier(s) Service Obtained: Northwest Air lines Destination(s) Served: Detroit

B. P UBLIC /P RIVATE P ARTNERSHIPS : (L IST ORGANIZATION NAMES )

Public Private 1. Wilkes-Barre/Scranton International Airport 1. Greater Pittston Chamber of Commerce 2. Luzerne County 2. Greater Pocono Chamber of Commerce 3. Lackawanna County 3. Greater Scranton Chamber of Commerce
4. 4. Greater Wilkes-Barre Chamber of Comm.
5. 5. Lackawanna Co. Conv. & Visitors Bur.
6. Luzerne Co. Conv. & Visitors Bureau 7. W-B/Scranton Penguins AAA Hockey
C. P ROJECT P ROPOSAL : ( CHECK ALL THAT APPLY ) ⌧ Marketing ⌧ Upgrade Aircraft ⌧ New RouteTravel Bank ⌧ Service Restoration ⌧ SubsidySurface Transportation ⌧ Regional Service Revenue Guarantee ⌧ Launch New Carrier ⌧ Start-Up Cost Offset First ServiceStudy ⌧ Secure Additional Service Other (explain below)APPENDIX C Page 2
D. E XISTING L ANDING A IDS AT L OCAL A IRPORT : ⌧ Full ILS Outer/Middle Marker ⌧ Published Instrument Approach ⌧ Localizer Other (specify)

E. P ROJECT C OST : D O NOT ENTER TEXT IN SHADED AREA
L INE D ESCRIPTION S UB T OTAL T OTAL A MOUNT 1 Federal Amount Requested $ 500,000
2 State cash financial contributions $ 0 Local cash financial contribution
3a Airport cash funds $ 100,000
3b Non-airport cash funds $ 200,000
3 Total local cash funds ( 3a + 3b ) $ 300,000 4 TOTAL CASH FUNDING ( 1+2+3 ) $ 800,000
In-Kind Contribution
5a Airport In-Kind contribution** $ 280,000 (est.)

5b Other In-Kind contribution** $ 30,400
5 TOTAL IN-KIND CONTRIBUTION (5 a + 5b ) $ 310,400 (est.) 6 TOTAL PROJECT COST ( 4+5 ) $ 1,110,400 (est.)

F. IN-KIND CONTRIBUIONS** For funds in lines 5a (Airport In-Kind contribution ) and 5b (Other In-Kind contribution, please descri be the source(s) of fund(s) for each. 5a. minimum 6 month waiver of landing fees/space rentals, billboard usage, direct mail campaigns 5b. ad placements, trade show exposure, staff fulf illments, mailings, web site exposure/ads, newslett er insertsAPPENDIX C Page 3

F. I S THIS APPLICATION SUBJECT TO REVIEW BY S TATE UNDER E XECUTIVE O RDER 12372 PROCESS ?a. This application was made available to the St ate under the Executive Order 12372 Process for review on (date) _____________.b. Program is subject to E.O. 12372, but has not been selected by the State for review. ⌧ c. Program is not covered by E.O. 12372.

G. I S THE A PPLICANT DELINQUENT ON ANY F EDERAL DEBT ? ( IF “ YES ”, PROVIDE EXPLANATION ) ⌧ No Yes (explain) __________________________________

___________
HomeNRC LibraryDocument CollectionsNews Releases1997

# NRC Names New Resident Inspectors at Dresden Nuclear Power Plant

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----

NEWS ANNOUNCEMENT: RIII-97-81

September 3, 1997

**NRC NAMES NEW RESIDENT INSPECTORS AT DRESDEN NUCLEAR POWER PLANT**

Nuclear Regulatory Commission officials in Lisle, Illinois, have announced the assignment of Kenneth Riemer and Billy Dickson as the agency's Senior Resident Inspector and Resident Inspector, respectively, at the Dresden Nuclear Power Station, located near Morris, Illinois.

Riemer joined the NRC in 1990 as a reactor engineer at the Region III Office in Illinois. Most recently, he had been a senior resident inspector at the Duane Arnold nuclear plant in Iowa. Prior to joining the NRC, he worked at the Norfolk Naval Shipyard where he directed reactor plant testing evolutions on nuclear powered submarines. He received a Bachelor of Science in Nuclear Engineering from the University of Illinois. Riemer and his wife, son, and daughter reside in Plainfield, Illinois.

Dickson joined the NRC in 1996 as a reactor engineer at the Region III Office in Illinois. Prior to joining the NRC, he worked as a nuclear engineer at Jupiter Corporation in Maryland. Also, for one year, he was a system engineer at the Grand Gulf Nuclear Power Station in Mississippi. Dickson received a Bachelor of Science in Nuclear Engineering from the Mississippi State University. Dickson and his wife and son reside in Downers Grove, Illinois.

Riemer and Dickson join NRC Resident Inspector David Roth at Dresden. They can be reached at 815/942-9267.

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

# Risk Methods Insights Gained from Fire Incidents (NUREG/CR-6738,  SAND2001-1676P)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6738            - Cover – Page A9-5 (PDF - 9.42 MB)
          - Appendix 10 – 25 (PDF - 8.68 MB) 

## Publication Information

**Manuscript Completed:**August 2001**Date Published:**September 2001

**Prepared by:** S.P. Nowlen, Sandia National Laboratories Dr. M. Kazarians, Kazarians and Associates F. Wyant, Sandia National Laboratories

Sandia National Laboratories Albuquerque, New Mexico 87185-0748 Operated by Sandia Corporation 

Kazarians and Associates Glendale , California 91205

H.W. Woods, 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 Y6037

Availability Notice

## Abstract

This report presents the findings of an effort to gain new fire probabilistic risk assessment (PRA) methodology insights from fire incidents in nuclear power plants. The study is based on the review of a specific set of 25 fire incidents including fires at both U.S. and foreign reactors. The sequence of actions and events observed in each fire incident is reconstructed based on the available information. This chain of events is then examined and compared to typical assumptions and practices of fire PRA. The review focuses on two types of actions and events. First are events that illustrate interesting insights regarding factors that fall within the scope of current fire PRA methods. Second are events observed in actual fire incidents that fall outside the scope of current fire PRA methods. Fire PRA insights are then drawn based on these observations. The review concludes that the overall structure of a typical fire PRA can appropriately capture the dominant factors involved in a fire incident. However, several areas of potential methodological improvement are identified. A few factors are also identified that fall outside the scope of current fire PRAs including the occurrence of multiple initial fires or secondary fires, multiple simultaneous initiating events, and some aspects of the smoke control and human response assessment.

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNews Releases1999

# NRC to Discuss Latest SONGS Unit 1 Decommissioning Plans with Public

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RIV: 99-04 February 17, 1999 CONTACT:    Breck Henderson (817) 860-8128/e-mail: bwh@nrc.gov

**NRC TO DISCUSS LATEST SONGS UNIT 1 DECOMMISSIONING PLANS WITH PUBLIC**

**Interested citizens and media invited to attend**

The U.S. Nuclear Regulatory Commission will hold a meeting with the public on Thursday, February 25, from 7 to 9 p.m. to discuss updated plans for decommissioning San Onofre Nuclear Generating Station (SONGS) Unit 1. Southern California Edison (SCE), owner of SONGS Unit 1 located four miles south of San Clemente, submitted an updated Post-Shutdown Decommissioning Activities Report (PSDAR) in December of last year.

The meeting will be at the San Clemente Community Center, 100 N. Calle Seville, San Clemente. All interested citizens are invited to attend and participate in the discussion. A sign-up period will begin at 6:30 p.m. for anyone wishing to make comments to the NRC or obtain a transcript of the meeting. Mayor Lois Berg of the City of San Clemente will serve as the meeting chairman.

SONGS Unit 1 ceased power operation in 1992 and has been mothballed since that time awaiting dismantlement and cleanup. SCE also operates SONGS Units 2 & 3 and had planned to decommission all three units at the same time. The current operating licenses of Units 2 & 3 expire in 2013.

However, SCE has elected to proceed with dismantling Unit 1 as early as next year to take advantage of economic benefits from doing the work earlier. At the meeting, SCE will deliver a short presentation on planned decommissioning activities, followed by a brief discussion by the NRC on the decommissioning process and NRC programs for monitoring the work. The bulk of the meeting will be devoted to hearing comments and answering questions from the public.

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

# Uncertainty and Sensitivity Investigations with TRACE-SUSA and TRACE-DAKOTA by Means of Post-test Calculations of NUPEC BFBT Experiments

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0462 (PDF - 16.60 MB)

## Publication Information

**Manuscript Completed:** January 2014**Date Published:** August 2017

**Prepared by:** Wadim Jaeger, Victor Hugo Sanchez Espinoza* Francisco Javier Montero Mayorga, Cears Queral**

*Karlsruher Institute of Technology (KIT) Institute for Neutron Physics and Reactor Technology (INR) Hermann-von-Helmholtz-Platz 1 76344, Eggenstein-Leopoldshafen, Germany

**Universidad Politecnica de Madrd, Departmento de Sistemas Energeticos ETSI Minas 28003 Madrid, Alenza 4, Spain

Kirk Tien, NRC Project Managerr

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

**Published by:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

Availability Notice

## Abstract

Uncertainty and sensitivity investigations are performed with TRACE-SUSA and with TRACE-DAKOTA for thermal hydraulic simulations of selected BWR related experimental scenarios based on the NUPEC BFBT data base. Steady state as well as transient scenarios are selected to conduct a comprehensive investigation of BWR like phenomena. The steady state investigations include single and two phase flow pressure drop analyses, axial void fraction profiles and critical power predictions. The pressure losses and the void fractions are also predicted during two postulated BWR transients; a turbine trip and a trip of a re-circulation pump. The average error for the pressure losses, the void fractions and the critical power scenarios is in the order of ± 5 %. Parameters of the input and of the source code are selected for the uncertainty and sensitivity study. By means of sensitivity coefficients, a quantitative way of evaluating the system response is given. The analysis shows that even small variations can cause a rather large spread of the output parameter(s). The investigations show also that the width of the predicted uncertainty band is a function of parameters like the inlet sub cooling or the hydraulic diameter. In addition, shortcomings of the thermal hydraulic code/modeling or of the uncertainty and sensitivity tool(s) are given in order to help to improve the prediction capabilities.

Page Last Reviewed/Updated Tuesday, March 09, 2021
FILED 

U.S. COURT OF APPEALS

 ELEVENTH CIRCUIT 

 December 30, 2005 

 THOMAS K. KAHN 

 CLERK

[DO NOT PUBLISH]

IN THE UNITED STATES COURT OF APPEALS

FOR THE ELEVENTH CIRCUIT

________________________

No. 05-14680

Non-Argument Calendar

________________________

D. C. Docket No. 04-00659-CV-F-S

CHRISTOPHER STOVALL, 

Plaintiff-Appellee, 

versus 

CLARK ALLUMS, 

in his individual capacity, 

Defendant-Appellant, 

THE CITY OF DOTHAN, ALABAMA, 

a muncipality, 

Defendant. 

________________________

Appeal from the United States District Court

for the Middle District of Alabama

_________________________

(December 30, 2005)

Before CARNES, BARKETT and PRYOR, Circuit Judges.

PER CURIAM:
2

This is an appeal from the denial of qualified immunity stemming from the

defendant officer’s arrest of the plaintiff for disorderly conduct. Viewing the

evidence in the light most favorable to the plaintiff, as we are required to do at this

stage of the proceedings, we conclude that no officer reasonably could have

believed that the plaintiff had violated the state code provision prohibiting

disorderly conduct. Accordingly, the district court’s denial of summary judgment

is AFFIRMED.
#### CALIFORNIA STATE BOARD OF EQUALIZATION, appellant, v. WESTERN MARINA CORPORATION, dba Shelter Island Inn.

No. 82-8.

Supreme Court of the United States.

Oct. 4, 1982.

The appeal is dismissed for want of jurisdiction. Treating the papers whereon the appeal was taken as a petition for writ of certiorari, certiorari is denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Review of Information for Spent Nuclear Fuel Burnup Confirmation (NUREG/CR-6998)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6998 (PDF - 8.68 MB)

## Publication Information

**Manuscript Completed:** June 2009**Date Published:** December 2009

**Prepared by**: B.B. Bevard, J.C. Wagner and C.V. Parks (ORNL) M. Aissa (NRC)

Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6170

M. Aissa, NC Project Manager

NRC Job Code Y6517

Availability Notice

## Abstract

The Interim Staff Guidance on burnup credit (ISG-8, revision 2) for pressurized-water-reactor spent nuclear fuel in storage and transport casks, issued in 2002 by the U.S. Nuclear Regulatory Commission's Spent Fuel Project Office, recommends an out-of-core burnup measurement to confirm the reactor record and compliance with the assembly burnup value used for cask loading acceptance. This recommendation is intended to prevent unauthorized loading (i.e., misloading) of assemblies due to inaccuracies in reactor burnup records and/or improper assembly identification, thereby ensuring that the appropriate subcritical margin is maintained. The purpose of this report is to detail information and issues relevant to preshipment burnup measurements when using burnup credit in pressurized-water-reactor spent nuclear fuel transport and storage casks. In particular, this report reviews the role of burnup measurements in the regulatory guidance for demonstrating compliance with burnup loading criteria, burnup measurement capabilities and experience, generation and accuracy of utility burnup records, fuel movement and misloading experience, and the consequences of misloading assemblies in casks designed for burnup credit.

Page Last Reviewed/Updated Thursday, March 25, 2021
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.
 Department of Justice Drug Enforcement Administration [Docket No. DEA-392]
 ACTION: Notice of registration.
 SUMMARY: Lin Zhi International, Inc., applied to be registered as a manufacturer of certain basic classes of controlled substances. The DEA grants Lin Zhi International, Inc. registration as a manufacturer of those controlled substances.


SUPPLEMENTARY INFORMATION: By notice dated May 28, 2014, and published in the 
                    **Federal Register**
                     on June 4, 2014, 79 FR 32321, Lin Zhi International, Inc., 670 Almanor Avenue, Sunnyvale, California 94085, applied to be registered as a manufacturer of certain basic classes of controlled substances. No comments or objections were submitted to this notice. The Drug Enforcement Administration (DEA) has considered the factors in 21 U.S.C. 823(a) and determined that the registration of Lin Zhi International, Inc. to manufacture the basic classes of controlled 
                    ( print page 3983)
                    substances is consistent with the public interest and with United States obligations under international treaties, conventions, or protocols in effect on May 1, 1971. The DEA investigated the company's maintenance of effective controls against diversion by inspecting and testing the company's physical security systems, verifying the company's compliance with state and local laws, and reviewing the company's background and history. Therefore, pursuant to 21 U.S.C. 823(a), and in accordance with 21 CFR 1301.33, the above-named company is granted registration as a bulk manufacturer of the basic classes of controlled substances listed: Controlled substance
ScheduleCocaine (9041)
IIOxycodone (9143)
IIHydrocodone (9193)
IIMethadone (9250)
IIMorphine (9300)
II
 The company plans to manufacture the listed controlled substances as bulk reagents for use in drug abuse testing. Dated: January 9, 2015. Joseph T. Rannazzisi, Deputy Assistant Administrator.


[FR Doc. 2015-01305 Filed 1-23-15; 8:45 am] BILLING CODE P
<TABLE> <S> <C>


<ARTICLE>                     5
<LEGEND>
     This RESTATED  schedule contains summary  financial  information  extracted
     from the Condensed  Consolidated  Balance Sheet as of June 30, 1997 and the
     Consolidated Statement of Income for the six months ended June 30, 1997 and
     is qualified in its entirety by reference to such financial statements.
</LEGEND>
<MULTIPLIER>                                   1,000
       
<S>                             <C>
<PERIOD-TYPE>                   6-MOS
<FISCAL-YEAR-END>                              DEC-31-1997
<PERIOD-START>                                 JAN-01-1997
<PERIOD-END>                                   JUN-30-1997
<CASH>                                         22,134
<SECURITIES>                                        0
<RECEIVABLES>                                   7,993
<ALLOWANCES>                                      185
<INVENTORY>                                     3,765
<CURRENT-ASSETS>                               36,509
<PP&E>                                          5,735
<DEPRECIATION>                                  4,175
<TOTAL-ASSETS>                                 38,279
<CURRENT-LIABILITIES>                           6,133
<BONDS>                                             0
<PREFERRED-MANDATORY>                               0
<PREFERRED>                                         0
<COMMON>                                            9
<OTHER-SE>                                     32,137
<TOTAL-LIABILITY-AND-EQUITY>                   38,279
<SALES>                                        18,117
<TOTAL-REVENUES>                               18,124
<CGS>                                           7,066
<TOTAL-COSTS>                                   7,066
<OTHER-EXPENSES>                                    0
<LOSS-PROVISION>                                    0
<INTEREST-EXPENSE>                                  0
<INCOME-PRETAX>                                 3,778
<INCOME-TAX>                                    1,436
<INCOME-CONTINUING>                             2,342
<DISCONTINUED>                                      0
<EXTRAORDINARY>                                     0
<CHANGES>                                           0
<NET-INCOME>                                    2,342
<EPS-PRIMARY>                                    0.26
<EPS-DILUTED>                                    0.24
        


</TABLE>
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# A Risk Comparison (NUREG/CR-1916, BNL-NUREG-51338)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-1916 (PDF - 2.81 MB)

## Publication Information

**Manuscript Completed:**January 1981**Date Published:**February 1981

**Prepared by:** A. Coppola and R.E. Hall Department of Nuclear Energy Brookhaven National Laboratory Upton, New York 11973 

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

NRC FIN-A3222

Availability Notice

## Abstract

This report presents data for the comparison of societal risk from natural and man-made hazards. Only fatalities resulting from the hazards are used in the comparison, with the data and the comparative analysis taken from current literature. In comparing societal risks for most of the hazards, both expected values and frequency vs. consequence curves are presented. For a subset of hazards, notably the power generation technologies (nuclear, coal, oil, and gas), which have not exhibited high consequence events (catastrophes), the comparisons are based on estimated expected values only.

Individual risk data are presented in two ways, a probability of death within a year and the amount of life shortening of an average life span.

Page Last Reviewed/Updated Wednesday, March 24, 2021
**Exhibit
      23.1**




[LETTERHEAD
      OF WILLIAMS
& WEBSTER, P.S.]




CONSENT
      OF INDEPENDENT REGISTERED PUBLIC ACCOUNTING FIRM




We
        consent to the use of our audit report dated February, 24, 2006, on the
        financial statements of AmeriChip International Inc. as of November 30, 2005
        and
        2004, of the annual Form 10-KSB and associated with the Form S-8, File No.
        333-130352.


/s/
      Williams & Webster, P.S.




**INDEPENDENT
      REGISTERED PUBLIC ACCOUNTING FIRM**




Spokane,
      Washington


February
      28, 2006