alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Zinc-Zircaloy Interaction in Dry Storage Casks (NUREG/CR-6732)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6732 (PDF 2.28 MB)

## Publication Information

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

**Prepared by:** H. Tsai, Y. Yan

Argonne National Laboratory Argonne, IL 60439

D. N. Kalinousky, NRC Project Manager

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

NRC Job Code Y6373

Availability Notice

## Abstract

Due to limited storage capacity in spent-fuel pools, some nuclear power plants are storing spent-fuel assemblies in inert-atmosphere dry casks until long-term geological depositories are available. VSC-24 is one such type of cask being used by utilities. During spent-fuel loading, the VSC-24 casks are submerged in the borated pool water and then dried and sealed. To mitigate contamination of the pool water and corrosion of the cask, a zinc-based primer coating, CarboZinc11, is applied to the cask structure, such as the fuel assembly sleeves and the cask shell. A series of laboratory tests was conducted to evaluate possible metallurgical interactions between zinc from the CarboZinc11 primer and the Zircaloy-4 cladding. The postulated transport mechanism of zinc is vaporization. If such interaction occurs during spent-fuel storage, performance of the Zircaloy-4 cladding as the primary barrier for fuel and fission products could be degraded.

The tests were designed to simulate realistic cask loading and storage conditions, including borated water immersion, vacuum drying, helium backfill, and elevated temperature holds. Prototypical cladding and coating materials were used and the cladding was preoxidized to form a surface layer comparable to those on irradiated fuel rods at medium burnup. The test temperature was 300°C (which envelops the peak cladding temperature of 282°C at a realistic cask heat load of 12 kW) and the maximum hold time at temperature was 90 days. No zinc Zircaloy interaction was found in any of the tests. These results differ from those of earlier tests conducted under less prototypical and generally more aggressive conditions. The major influence on the test results apparently was the oxide layer on the cladding specimens in the present tests. The oxide layer appears to be effective in blocking the migration of zinc vapor to the Zircaloy metal substrate. Because an oxide layer is always formed on fuel rod cladding from in-reactor service, the cladding would be protected as long as the oxide layer remains intact and adherent to the Zircaloy metal.

Page Last Reviewed/Updated Wednesday, March 24, 2021
CERTIFICATION PURSUANT TO
                  SECTION 906 OF THE SARBANES-OXLEY ACT OF 2002
                            (18 U.S.C. SECTION 1350)


     In connection  with the  accompanying  Annual  Report of  Electronic  Media
Central  Corporation  (the  "Company")  on Form 10-KSB for the fiscal year ended
March 31, 2005 (the "Report"),  I, Roger Casas,  Chief Executive  Officer of the
Company, hereby certify that to my knowledge:

     (1) The Report fully complies with the requirements of Section 15(d) of the
Securities Exchange Act of 1934 (15 U.S.C. ss.78o(d)); and

     (2)  The  information  contained  in the  Report  fairly  presents,  in all
material  respects,  the  financial  condition  and results of operations of the
Company.

Dated:  June 28, 2005

                                                          /s/ Roger Casas
                                                         -----------------------
                                                         Roger Casas
                                                         Chief Executive Officer


     The above  certification is furnished solely pursuant to Section 906 of the
Sarbanes-Oxley Act of 2002 (18 U.S.C. ss.1350) and is not being filed as part of
the Form 10-KSB or as a separate disclosure document.











                                                                Exhibit 32
                                                                Page 1 of 1 Page
No. 91-688.

#### Aerovias Nacionales de Colombia, S. A., et al. *v.*Alvarez, Personal Representative of the Estate of Alvarez, Deceased, et al.

C. A. 11th Cir. Certiorari denied.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC ContractorsFRAPTRAN-1.4 and FRAPTRAN-1.5 (NUREG/CR-7023)

# FRAPTRAN 1.5: Integral Assessment (NUREG/CR-7023, Volume 2, Revision 1)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-7023, Volume 2, Revision 1 (PDF - 794.75 KB)

## Publication Information

**Manuscript Completed:** May 2014**Date Published:** October 2014

**Prepared by:** K. J. Geelhood, W. G. Luscher, and J. M. Cuta

Pacific Northwest National Laboratory Richland, WA 99352

P. Raynaud, NRC Project Manager

 NRC Job Code V6197

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

Availability Notice

## Abstract

An integral assessment has been performed for the U.S. Nuclear Regulatory Commission by Pacific Northwest National Laboratory to quantify the predictive capabilities of FRAPTRAN, a transient fuel behavior code designed to analyze fuel behavior during a range of power and coolant transients with fuel burnup up to 62 gigawatt-days per metric ton of uranium. The FRAPTRAN code calculations are shown to compare satisfactorily to a set of experimental data from reactivity-initiated accident and loss-of-coolant-accident operating conditions.

This document describes the assessment of FRAPTRAN-1.5, which is the latest version of FRAPTRAN, released May, 2014.

Page Last Reviewed/Updated Wednesday, March 24, 2021
HomeNRC LibraryDocument CollectionsInspection ManualChange Notices1999

# Change Notice 99-002

Issue Date: 02/03/99

NRC INSPECTION MANUAL IIPB

 

----

 

END

Page Last Reviewed/Updated Friday, April 17, 2020
# Attendee Report GoToWebinar

Webinar Name Webinar ID ASRAC Commercial HVAC, CRE, and WH Working Group: Meeting and Webinar464441521 Actual Start Date/Time Actual Duration (minutes) Jul 10, 2013 08:56 AM EDT 162 Total Attended 27 

# Session Details

First Name Last Name Email CountryAddress City StateOrganization Zip Code Karim Amrane US 2111 Wilson Blvd, #500 Arlington VA AHRI 22201 ashley armstrong US 1000 Indepdendence Ave Washington DCDOE 20585 Jeff Bauman US 539 Dunksferry Rd. Bensalem PA National Refrigeration & Air Conditioning19020 John Bean US 801 Corporate Centre DriveO'fallon MOSchneider 63368 Rodney Beever US 491 E. princess St. York PA United CoolAir Corp. 17403 Kevin Eicher US 10001 reunion place suite 500San ANtonio TX Friedrich A/C 78216 Jeremiah Freeman US DOE Washington DCNew West 20585 Kevin Grundy CA 54117 Best LIne Aylmer ONChange'Air Products N5H2R3 Larry Howington US 1925 Ruffin Mill Road Colonial HeightsVA AHRI 23834 Dave Kelley US 1050 Dearborn Dr. Columbus OHEmerson Network Power 43085 Greg Kohler US 1500 Dekoven Ave Racine WI Modine Manufacturing Company 53403 Michael Kojak US 8932 Cedar Breaks Drive Plano TX UL 75025 Yan Lu US 755 College Rd. East Princeton NJ research 08540 Ted Marwitz US 230 W. Blueridge Ave. Orange CA Data Aire Inc 92865 David Mecadon US 539 Dunksferry Road Bensalem PA National Refrigeration and Air Conditioning19020 George Morehouse US 99 Washington Ave. Albany NY NYS Dept. of State, Codes Division 12231 Vincent Mucciola US 539 Dunksferry Road Bensalem PA National Comfort Products 19020 Wes Roan US 1914 Randolph Drive Bryan OHBard Manufacturing Co., Inc. 43506 Carl Roberts US 110 N. Oakridge Dr North Prairie WI Zero Zone, Inc 53153 Alicia Simonsson US 202 S. Walnut Fairmount IN Solar Retrofit & Restoration 46928 Knute Svenson US 1200 19th St NW Washington DCNavigant Consulting 20001 Matt Thornblad US 1101 Pennsylvania Avenue, N.W.Washington DCUnited Technologies Corporation 20004 Yoolanda Williams US AP2-121, Appliance Park Louisville KY General Electric 40225 Dave Winningham US 215 Metropolitan Drive West ColumbiaSCAllied Air Enterprises 29072 Bruce Womack US 1725 Venice Circle Stockton CA Brucesgreengardener.com 95206 Michael Woodford US 2111 Wilson Blvd., Suite # 500Arlington VA AHRI 22201 Frank Xu US 1998 FM 2011 Longview TX National Coil Company 75603 

# General Information
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Advanced Information Systems Design: Technical Basis and Human Factors Review Guidance (NUREG/CR-6633)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6633 (PDF - 9.41 MB)

## Publication Information

**Manuscript Completed:** January 2000**Date Published:** March 2000

**Prepared by:** J. M. O'Hara, J. C. Higgins/BNL J. Kramer/NRC

Brookhaven National Laboratory Upton, NY 11973

J. Kramer, NRC Project Manager

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

NRC Job Code J6012

Availability Notice

## Abstract

Plant information systems provide operators with information supporting situation assessment, monitoring and detection of disturbances, response planning, and response implementation. The importance of the design of information systems for human performance and reliability has long been recognized. Recent advances in design go beyond the 'one sensor -one indicator' display systems of conventional plants. Computer-based systems provide a variety of ways to process and present data. These characteristics of design represent a trend toward making displays more immediately meaningful to personnel by mapping display representations to important aspects of plant processes and to underlying cognitive mechanisms, such as perceptual processes and mental models. The objective of this study was to develop guidance for human factors review of advanced information systems based on a technically valid methodology for developing guidance. To support this objective, we developed a characterization framework for describing key design characteristics of information systems. The characterization includes the following major components: information requirements, representation systems, interface management functions, and display devices. Representation systems were further hierarchically divided into display elements (basic building blocks of displays, such as axes, alphanumeric elements, and icons), display formats (such as mimic displays, configural displays, and novel graphics), display pages (a defined set of information that is intended to be displayed as a single unit), and display networks (the organization of display pages). Then, we examined research in the following areas: (1) generic cognitive tasks that an information system must support, (2) information requirements analysis, (3) information representation, and (4) information organization. This research was used to provide the technical basis on which guidelines for review of design were developed. These guidelines address both the design process and the implementation of advanced information systems. However, there were aspects of information systems for which the technical basis was insufficient to support the development of guidance. These were identified as issues to be addressed in future research.

Page Last Reviewed/Updated Thursday, March 25, 2021
Exhibit 99.2

           CERTIFICATION 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 Southborrough Ventures, Inc. (the
"Company") on Form 10-KSB for the period ending November 30, 2002 as filed with
the U.S. Securities and Exchange Commission on the date hereof (the "Report"),
I, John Taylor, President and Chief Financial Officer of the Company, 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, as amended; and

     2.   the information contained in the Report fairly presents, in all
          material respects, the financial condition and result of operations of
          the Company.



     The foregoing certification is made solely for the purpose of 18 U.S.C.
Section 1350, subject to the knowledge standard contained therein, and not for
any other purpose.

         EXECUTED this 14th day of March, 2003.
                       ----



                                          /s/  John ???? Taylor
                                          --------------------------------------
                                          John Taylor
                                          President and Chief Financial Officer
HomeNRC LibraryDocument CollectionsNews Releases

# News Releases - 2011

> 
January • February • March • April • May • June • July • August • September • October • November • December

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

Page Last Reviewed/Updated Thursday, February 04, 2021

Section Navigation

#### Navigation

          - 2024
          - 2023
          - 2022
          - 2021
          - 2020
          - 2019
          - 2018
          - 2017
          - 2016
          - 2015
          - 2014
          - 2013
          - 2012
          - 2011
          - 2010
          - 2009
          - 2008
          - 2007
          - 2006
          - 2005
          - 2004
          - 2003
          - 2002
          - 2001
          - 2000
          - 1999
          - 1998
          - 1997
          - 1996

#### Spotlight

#### Choose a Section

                - The Commission
                - License Renewal Generic Environmental Review
                - Job Openings
                - Palisades Restart
                - Environmental Justice 
                - Pilgrim Water Releases
                - Monticello Tritium Issue
                - International Strategy 2021-2025
                - Tribal Liaison Program
                - MAP-X
                - Transformation at the NRC - Updated
                - OIG Hotline
                - Rulemaking Activity
                - Commission Documents
                - Advanced Reactors
                - Nuclear Security
                - Strategic Plan

#### Search News Releases

#### Related Information

            - Speeches

Page Last Reviewed/Updated Thursday, February 04, 2021
<PAGE>

                                                                  EXHIBIT 10.194

                     AMENDMENT NO. 1 TO EMPLOYMENT AGREEMENT

     THIS AMENDMENT NO. 1 (the "Amendment"), made as of this 1st day of June,
2002 (the "Effective Date"), by and between PPD Development, LP ("PPD
Development") and W. Richard Staub ("Employee"), amends that certain Employment
Agreement dated May 1, 2002 between PPD Development and Employee (the
"Employment Agreement").

     FOR AND IN CONSIDERATION OF the mutual promises, covenants and conditions
contained herein, and other good and valid consideration, the receipt and
sufficiency of which is hereby acknowledged, the parties hereby amend the
Employment Agreement as follows:

     1. Amendment to Section 4. The first sentence of Section 4 of the
Employment Agreement is hereby stricken and replaced in full by the following:
"Employee shall have overall responsibility for business development of (a) PPD
Development and all of its subsidiaries except Pharmaco Investments, Inc., (b)
PPD Global Ltd., (c) Leicester Clinical Research Centre Ltd., (d) Chelmsford
Clinical Trials Unit Ltd., (e) Piedmont Research Center, Inc., (f) Medical
Research Laboratories International, LLC, and (g) Medical Research Laboratories
International, BVBA (collectively, the "Businesses").

     2. New Appendix I. All references to Appendix I in the Employment Agreement
shall be deemed to refer to Appendix I attached to this Amendment.

     3. Binding Effect. The Employment Agreement, as herein amended, shall
continue in full force and effect.

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

                                     PPD DEVELOPMENT, LP
                                     By:  PPD GP, LLC, its general partner

                                     By:     /s/ Fred B. Davenport, Jr.
                                            ----------------------------------
                                     Name:  Fred B. Davenport, Jr.
                                            ----------------------------------
                                     Title: Vice President
                                            ----------------------------------


                                     /s/ W. Richard Staub               (SEAL)
                                     ------------------------------------
                                     W. Richard Staub
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Assessment of the TRACE Code Using Transient Data from Maanshan PWR Nuclear Power Plant (NUREG/IA-0241)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0241 (PDF - 1.84 MB)

## Publication Information

**Manuscript Completed:**May 2010**Date Published:**June 2010

**Prepared by:**1Jong-Rong Wang, 1Hao-Tzu Lin, 2Chunkuan Shih

1Institute of Nuclear Energy Research Atomic Energy Council, R.O.C. 1000, Wenhua Rd., Chiaan Village, Lungtan, Taoyuan, 325 TAIWAN

2Institute of Nuclear Engineering and Science National Tsing Hua University 101 Section 2, Kuang Fu Rd., HsinChu TAIWAN

Antony Calvo, NRC Project Manager

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the International Code Assessment and Maintenance Program (CAMP)

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

Availability Notice

## Abstract

This study consists of two steps. The first step is the establishment of TRACE (TRAC/RELAP Advanced Computational Engine) models for important components, such as pressurizers, steam generators, the feedwater control system, the steam dump control system, and so on, in Maanshan Nuclear Power Plant (NPP) using SNAP (Symbolic Nuclear Analysis Program)/TRACE. These component models were tested and compared with Maanshan startup test data to verify their accuracy. Key parameters were identified to refine the models further. The next step is the incorporation of the above component models into the Maanshan NPP TRACE model. TRACE transient analyses of scenarios such as load reduction and turbine trip were performed and their results were compared with the corresponding plant data from Maanshan startup tests. The TRACE model of Maanshan NPP is also used to analyze Loss of Flow transient as defined in FSAR Chapter 15 which includes Partial Loss of Flow (PLOF), Complete Loss of Flow-Under Voltage (CLOF-UV), and Complete Loss of Flow-Under Frequency (CLOF-UF). Analysis results indicate that the Maanshan NPP TRACE model predicts not only the behaviors of important plant parameters consistent with the plant data, but also their associated numerical values with respectable accuracy.

Page Last Reviewed/Updated Tuesday, March 09, 2021
N O T FO R PUB L ICAT IO N UNITED STATES C OUR T OF APPEALS FOR THE NINTH C IR C UIT M ANUEL C ARR ILLO, Pe titione r, v. ER IC H. HOLDER , Jr., Attorne y Ge ne ra l, R

e sponde nt . No. 12-73681 Age n c y No. A041-111-699 M EM O R ANDUM *

On Pe tition for Re vie w of a n Orde r of the B oa rd of Im m igration Appe a ls Subm itte d

M ay 13, 2014 ** B e fore : C LIFTON, B EA, a nd WATFORD, C irc uit Judge s. M anue l C arrillo, a

native and c itiz e n of M e x ic o, pe titions for re vie w of the B oa rd of Im m igration Appe a l s’ (“ B IA” ) orde r dism issing his a ppe a l from an im m igration judge ’ s de c i sion de ny i ng his m otion to re ope n re m ova l proc e e dings c onduc te d in a

bse ntia . Our jurisdic tion is governe d by 8 U.S.C . § 1252. W e 

# FIL ED MAY27 2014 M OLLY C. DW Y ER, CLERK U . S . CO URT O F APPEALS

* This disposition is not a ppropria te for public at ion a

nd is not pre c e de nt e xc e pt a s provide d

by 9th C ir. R . 36-3. ** The pa

ne l una nim ously c onc lude s this c a se is suita ble for de c ision without oral a

rgum e nt. Se e Fe d. R . App. P. 34(a)(2).re vie w for a

buse of disc re t ion the de nia l of a m otion to re o pe n. Mohamme d v . Gonzale s , 400 F.3d 785, 791 (9th C ir. 2005). W e de ny in pa rt a nd dismiss in pa

rt the p e tition for re v i e w. In his ope ning brie f, C a

rrillo fa ils to ra ise , a

nd the re fore ha s wa ive d, a ny c ha lle nge to the B IA’ s de te rm ination tha t notic e of his Oc tobe r 3, 2005, he aring wa s prope r. Se e Tijani v . Holde r , 628 F.3d 1071, 1080 (9th C ir. 2010). The B IA did not a

buse its disc re tion by

de ny ing C arrillo’ s m otion to re ope n a s untim e ly

whe re C a

rrillo file d his m otion m ore tha n five y e ars a fte r his in a bse ntia re m ova l orde r wa s issue d. Se e 8 U.S.C . § 1229a (b)(5)(C )(i) (an a l ie n ha s 180 da y s to filea

m otion to re o pe n to re s c ind the in a bse ntia orde r if the a lie n c an show tha t he fa ile d to a

ppe ar for the he a

ring due to e x c e ptiona l c irc um sta nc e s). W e la c k jurisdic tion to c onside r C arrillo’ s c onte ntion re ga rding e quita

ble tolling of the

m otion to re ope n filing de a dline be c a use he fa ile d to e xha

ust this c onte ntion be fore the B IA. Se e Tijani , 628 F.3d a t 1080. PE T IT IO N FO R RE V IE WDE NIE D in par t; DISM ISSE D in par t.

1 2 - 7 3 6 8 1 2