alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
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# Evaluation of WF-70 Weld Metal From the Midland Unit 1 Reactor Vessel (NUREG/CR-5736)

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## Publication Information

**Manuscript Completed:** February 1998**Date Published:** November 2000

**Prepared by:** D. E. McCabe, R. K. Nanstad, S. K. Iskander, D. W. Heatherly, R. L. Swain

Oak Ridge National Laboratory Managed by Lockheed Martin Energy Research Corporation

Oak Ridge National Laboratory Oak Ridge, TN 37831-6151

C. J. Fairbanks, 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 W6953

Availability Notice

## Abstract

Low upper-shelf (LUS) weld metal was sampled from the Midland Unit 1 reactor vessel. The weld metal was designated to be WF-70 by Babcock and Wilcox Company code. The sampling was taken from both the nozzle course and beltline girth welds. The as-received materials characterization using Charpy curves, drop-weight nil-ductility transition, tensile tests, and chemical analysis surveys indicated that the materials from the two locations were essentially the same except for the copper content. The expected nominal copper contents were 0.40 and 0.26 wt % for the nozzle course and beltline welds, respectively. Because the experiment involved detailed evaluations of both unirradiated and irradiated (1 x 1019 n/cm2) conditions, the two weld metals were evaluated separately.

Fracture mechanics data were obtained for both the unirradiated and irradiated conditions; two methods of evaluating the transition temperatures were (1) the American Society of Mechanical Engineers (ASME) *Boiler and Pressure Vessel Code*, augmented with the American Society for Testing and Materials (ASTM) MethodE 185, and (2) the relatively new master curve method. The ASME method uses a reference temperature determination (RTNDT) from nonfracture mechanics test practices; the master curve method uses a transition temperature, To, obtained from fracture mechanics-based data. The deficiencies of the ASME method as applied to LUS materials were evident. The master curve method, supplemented with fracture mechanics-based R-curve data, proved to have sufficient sensitivity to show differences between the nozzle course and beltline materials. The ASME-recommended methods failed to detect differences, thereby revealing the lower sensitivity of the empirical methods associated with RTNDT.

Page Last Reviewed/Updated Thursday, March 25, 2021
Exhibit 10.31

AMENDMENT NO. 2 TO
AMENDED AND RESTATED SEVERANCE AGREEMENT

This Amendment No. 2, dated March 29, 2001, amends a certain Amended and Restated Severance Agreement dated as of August 15, 1997 by and
between Silicon Image, Inc., a Delaware corporation (the "Company"), and David D. Lee
("Executive"), as amended by Amendment No. 1 thereto dated January 24, 2000 (the "Severance
Agreement").

WHEREAS,
the Severance Agreement aimed to enhance Executive's ability to perform effectively by providing him with employment security;

WHEREAS,
with a view to that purpose, the Severance Agreement was scheduled to expire on December 31, 2003, covering the period that Executive's equity compensation continued
to vest;

WHEREAS,
Executive is eligible, pursuant to the Company's option repricing program for executive officers, to exchange an option granted to him in November 1999 for a new
option to be granted in April 2001 that will be subject to vesting until April 2005 and is also eligible to be awarded additional equity compensation by the Company in the future; and

WHEREAS,
the Company accordingly desires to extend the term of the Severance Agreement;

NOW,
THEREFORE, the parties hereto agree as follows:

1.  The
Severance Agreement is hereby amended to replace the date, "December 31, 2003" with the date, "December 31, 2006", each place that it appears
(including, without limitation, Sections 3(i), 3(ii), and 7).

2.  Except
as amended by this Amendment No. 2, the terms of the Severance Agreement remain in full force and effect.

IN
WITNESS WHEREOF, the undersigned parties have executed this Amendment No. 2 (or have caused this Amendment No. 2 to be executed by their duly authorized
representatives) as of March 29, 2001.

Silicon
Image, Inc.

|By: |  | /s/STEVE TIRADOSteve Tirado
Chief Operating Officer |  | /s/DAVID D. LEEDavid D. Lee
|--- |  | --------------------------------------------------- |  | ---------------------------

---

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HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC StaffNUREG-1885

# Report to Congress on the Security Inspection Program for Commercial Power Reactor and Category I Fuel Cycle Facilities: Results and Status Update - Annual Report for Calendar Year 2006 (NUREG-1885)

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        - NUREG - 1885 (PDF - 2.13 MB)

## Publication Information

Manuscript Completed: August 2007 Date Published: September 2007

Division of Security Operations Office of Nuclear Security and Incident Response U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

This report fulfills the requirements of Chapter 14, Section 170D of the Atomic Energy Act of 1954 (42 U.S.C. 2201 et seq.), as amended by the Energy Policy Act of 2005, which states, “not less often than once each year, the Commission shall submit to the Committee on Environment and Public Works of the Senate and the Committee on Energy and Commerce of the House of Representatives a report, in classified form and unclassified form, that describes the results of each security response evaluation conducted and any relevant corrective action taken by a licensee during the previous year.” This is the second annual report which covers calendar year 2006. In addition to information on the security response evaluation program (force-on-force exercises), the NRC is providing additional information regarding the overall security performance of the commercial nuclear power industry and selected fuel cycle facilities to keep Congress and the public informed of the NRC's efforts to protect the nation's electric power infrastructure and special nuclear material against terrorist attacks.

**Paperwork Reduction Act Statement**

This NUREG does not contain information collection requirements and, therefore, is not subject to the requirements of the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.).

**Public Protection Notification**

The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC StaffStandard Review Plan for Transportation Packages for Radioactive Material (NUREG-1609)

# Standard Review Plan for Transportation Packages for MOX-Radioactive Material (NUREG-1609, Supplement 1)

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        - NUREG-1609, Supplement 1 (PDF - 457 KB)

## Publication Information

**Manuscript Completed:**September 2005**Date Published:**September 2005

**Prepared by:** R.S. Hafner, G.C. Mok, J. Hovingh, C. K. Syn, E.W. Russell, S.C. Keaton, J.L. Boles, D.K. Vogt, P. Prassinos

Lawrence Livermore National Laboratory 7000 East Avenue Livermore, CA 94550-9234

J.A. Smith, NRC Project Manager

Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 NRC Job Code A0291

Availability Notice

## Abstract

The NRC contracted with LLNL to compile this supplement to NUREG-1609 to incorporate additional information specific to mixed uranium-plutonium oxide (MOX) radioactive material (RAM). This supplement provides details on package review guidance resulting from significant differences between low-enriched uranium (LEU) oxide radioactive material (RAM) and that from MOX RAM. While comparisons of MOX RAM with LEU RAM include powder, fresh-fuel rods, and fresh-fuel assemblies, they do not include comparisons with high-enriched uranium (HEU) or plutonium as metal, oxide, or nitrate in like forms that are covered by NUREG-1609. The principal purpose of this supplement is to ensure the quality and uniformity of staff reviews of packagings intended for transport of MOX RAM. It is also the intent of this plan to make information about regulatory matters widely available, and improve communications between NRC, interested members of the public, and the nuclear industry, thereby increasing the understanding of the NRC staff review process. In particular, this supplemental guidance, together with NUREG-1609, assists potential applicants by indicating one or more acceptable means of demonstrating compliance with the applicable regulations.

Page Last Reviewed/Updated Wednesday, March 24, 2021
#### In the Matter of G. H. Miner Co., Inc., Respondent, v Lone Wolf Insulation, Inc., Respondent, and ABL Plumbing & Heating Corp., Appellant.

[632 NYS2d 372]

Order unanimously affirmed with costs. Memorandum: Petitioner, the judgment creditor in an underlying action, commenced this "turnover” special proceeding pursuant to CPLR 5225 (b) to enforce the judgment in that action out of money due to the judgment debtor from a third party, respondent ABL Plumbing & Heating Corp. (ABL). ABL appeals from an order denying its motion to dismiss the proceeding for lack of subject matter jurisdiction, based upon petitioner’s failure to obtain a new index number prior to commencing the special proceeding. Supreme Court denied ABL’s motion on the ground, *inter alia,*that the requirements of CPLR article 3 were satisfied when the court clerk accepted the order to show cause and petition for filing under the index number pertaining to the underlying action. The court properly denied the motion to dismiss. Under the new "commencement by filing” system, a litigant must purchase an index number before filing the summons and complaint in an action, or before filing the notice of petition and petition in a special proceeding, and must place that index number on the papers before serving them on the defendant *(see,*CPLR 105 [b]; 304, 305 [a]; 306-a [a]). Thus, a new index number was required for commencement of this special proceeding pursuant to CPLR 5225 (b), and that requirement was not satisfied by petitioner’s use of the index number pertaining to the underlying action. Nevertheless, ABL was not entitled to an order of dismissal as a result of petitioner’s use of the old number. The failure to obtain an index number *832is a correctable, non-jurisdictional defect *(see,*CPLR 306-a [b]; *cf., Cellular Tel. Co. v Village of Tarrytown,*209 AD2d 57, 64). Here, petitioner timely rectified the defect by purchasing a new index number during the pendency of ABL’s motion. In any event, ABL was not entitled to dismissal without complying with the procedure outlined in CPLR 306-a (b). (Appeal from Order of Supreme Court, Onondaga County, Stone, J.— Execution on Judgment.) Present — Denman, P. J., Lawton, Fallon, Balio and Boehm, JJ.
p. 1 

O//3 ry'1f 331-2-2 0 

(M. 

November 18, 2010 

Jim Willis 

Director, Chemical Control Division (7405M) 

Room 4146 EPA East 

U.S. Environmental Protection Agency 

1201 Constitution Avenue, NW 

Washington, DC 20004 

202-564-4760 

Attn: EPA Docket ID Number OPPT-2004-0113 

PFOA Site-Related Environmental Assessment Program 

Memorandum of Understanding (MOU) between the U.S . Environmental Protection Agency 

(EPA) and E. 1 . DuPont de Nemours and Company (DuPont) for a Perfluorooctanoic Acid 

(PFOA) Site-Related Environmental Assessment Program (November 3, 2005) 

Re : Future Work Plan - Phase III DuPont Washington Works (OPPT-2004-0113 

PFOA Site Environmental Assessment Program) November 18, 2010 

Dear Mr. Willis, 

Pursuant to Section V.F.1 of the MOU, please find attached the Future Work Plan - Phase III DuPont 

Washington Works (dated November 18, 2010) in two formats, one hardcopy and one electronic copy on 

CD. This work plan is based on recommendations presented in the Future Data Needs Assessment, the 

Peer Consultation Report, discussions between EPA and DuPont in our May 13, 2010 meeting, and the 

land-use survey conducted by DuPont in the summer of 2010 . 

In addition, with respect to work being completed related to historical disposal of PFOA containing 

sludge and solid waste referenced in your March 3, 2010 letter to DuPont, we wish to note that historical 

off-site disposal locations are being addressed with EPA Region's III and V and that on-site activity is 

being addressed through the Washington Works site RCRA Corrective Action program (EPA Region III) . 

Please contact me at 302-999-6197 if further information or additional discussion is needed. 

Andrew S. Hartten 

Project Director 

DuPont Corporate Remediation Group 

cc: Document Control, EPA (one hardcopy and one electronic copy on CD) 

Laurence Libelo, EPA (two hard copies) 

CONTAINS NO CBI 

DuPont Corporate Remediation Group 

Chestnut Run Plaza, Building 715 

4417 Lancaster Pike 

Wilmington, DE 19805 

E .I . du Pont de Nemours and Company
Exhibit 23.1



LOGO



June 17, 2004



The Board of Directors

ChipMOS TECHNOLOGIES (Bermuda) LTD.

No.1, R&D Road 1

Hsinchu Science Park

Hsinchu, Taiwan

Republic of China



Attention: Mr.
S.J. Cheng



Dear Sirs,



INDEPENDENT AUDITORS CONSENT



We consent to the incorporation by reference in Registration Statement No. 333-85290 of
ChipMOS TECHNOLOGIES (Bermuda) LTD. on Form S-8 of our report dated May 21, 2004, appearing in this Annual Report on Form 20-F of ChipMOS TECHNOLOGIES (Bermuda) LTD. for the year ended December 31, 2003 (the Annual Report). We also
consent to the inclusion of our report in the Annual Report.



Yours faithfully,



/s/    Moore Stephens

Moore Stephens

Certified Public Accountants

Hong Kong
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# RELAP5/MOD3.3 Assessment by Comparison with PKL III G3.1 Experiment (small break in the main steam line) (NUREG/IA-0447)

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## Publication Information

**Manuscript Completed:** April 2014**Date Published:** July 2014

**Prepared by:** A.Zaruba, K. Krezeminski, A. Benkert

AREVA-NP Germany.

K. Tien, NRC Project Manager

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

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

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

Availability Notice

## Abstract

The behavior of the PKL facility during a small main-steam-line break was investigated by using the RELAP model of the main facility components, including the reactor pressure vessel, steam generators, pressurizer, primary piping, and main steam lines. The calculations were performed using the computer code RELAP5/MOD3.3.

The main objectives of the study are to compare the simulation results with experimental data and to assess the accuracy of the calculated data. The major parameters and phenomena for simulating a main steam line break, e.g. primary and secondary pressures and temperatures, break flow rate and water level in SG and PZR, were analyzed. The results of the calculations were found to be in good agreement with experimental results.

All the analytical activities were performed as part of the Organization for Economic Cooperation and Development/Nuclear Energy Agency (OECD/NEA) projects of Test G3.1.

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC StaffResearch Activities (NUREG-1925)

# Research Activities FY 2015-FY 2017 (NUREG-1925, Revision 3)

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        - NUREG-1925, Revision 3 (PDF - 28.23 MB)

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## Publication Information

**Manuscript Completed:** September 2015**Date Published:** February 2016

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

Availability Notice

## Abstract

The Office of Nuclear Regulatory Research (RES) supports the regulatory mission of the U.S. Nuclear Regulatory Commission (NRC) by providing technical advice, tools, and information to identify potential safety issues and resolve them as appropriate, make regulatory decisions, and issue regulatory requirements and guidance. This includes conducting confirmatory experiments and analyses, developing technical bases that support the NRC's safety decisions, and preparing the agency for the future by evaluating the safety aspects of new technologies and designs for nuclear reactors, materials, waste, and security.

The NRC faces challenges as the industry matures including potential emergent safety issues, the availability of new technologies, technical issues associated with the deployment of new reactor designs, and knowledge management. The NRC focuses its research primarily on near-term needs related to the oversight of operating reactors as well as to new and advanced reactor designs. RES develops technical tools, analytical models, and experimental data to allow the agency to assess potential safety and regulatory issues. The RES staff uses its own expertise as well as contracts with commercial entities, national laboratories, and universities, or collaborations with international organizations, to develop these tools, models, and data.

This NUREG describes research being conducted by NRC's Office of Nuclear Regulatory Research across a wide variety of disciplines, ranging from fuel behavior under accident conditions to seismology to health physics. This is the fourth issuance of NUREG-1925, revised to capture new research and to update ongoing research projects. This research helps provide the technical bases for regulatory decisions and confirms licensee analyses. RES works closely with the NRC's regulatory offices in the review and analysis of operational events and provides its expertise to support licensing. RES has organized this collection of information sheets by topical areas that summarize projects currently in progress. Each sheet provides the names of the RES technical staff who can be contacted for additional information.

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

# Accident-Induced Flow and Material Transport in Nuclear Facilities: A Literature Review (NUREG/CR-3735,LA-10079-MS)

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        - NUREG/CR-3735 (PDF - 2.46 MB)

## Publication Information

**Manuscript Completed:**March 1984**Date Published:**April 1984

**Prepared by:** J.W. Bolstad, W.S. Gregory, R.A. Martin, P.K. Tang,  R.G. Merryman, J.D. Novat, H.L. Whitmore Los Alamos National Laboratory Los Alamos, New Mexico 87545

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

NRC FIN A-7029

Availability Notice

## Abstract

The reported investigation is part of a program that was established for deriving radiological source terms at a nuclear facility's atmospheric boundaries under postulated accident conditions. The overall program consists of three parts:  (1) accident delineation and survey, (2) internal source term characterization and release, and (3) induced flow and material transport. This report is an outline of pertinent induced-flow and material transport literature. Our objectives are to develop analytical techniques and data that will permit prediction of accident-induced transport of airborne material to a plant's atmospheric boundaries.

Prediction of material transport requires investigation of the areas of flow dynamics and reentrainment/deposition. A review of material transport, fluid dynamics, and reentrainment/deposition literature is discussed. In particular, those references dealing, with model development are discussed with special emphasis on application to a facility's interconnected ventilation system.

Page Last Reviewed/Updated Wednesday, March 24, 2021
<TABLE> <S> <C>


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THIS  SCHEDULE  CONTAINS  SUMMARY  FINANCIAL   INFORMATION  EXTRACTED  FROM  THE
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