alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
Human Factors Information System (HFIS)

U.S. Nuclear Regulatory Commission

From 01/01/2008 to 12/31/2008Page 218 of 22605/29/2009 10:01:12

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: Vogtle 2 Docket (050- 00425)

Human-System Interface & Environmnt / IR170 - HSI or information availability / quality LTA C - Chemistry M - Maintenance / Repair 170 - HSI or information availability / quality LTA I - Instrumentation & Control T - Testing 

220

Number of Items for this Docket: 

Percent of Total for this Docket: 

Procedures & Reference Document / IR111 - Procedure / reference document technical content G - Engineering M - Maintenance / Repair 111 - Procedure / reference document technical content I - Instrumentation & Control T - Testing 113 - Procedure / reference document development and maintenance LT G - Engineering G - Design 

330

Number of Items for this Docket: 

Percent of Total for this Docket: 

Work Planning & Practices / IR186 - Failure to take action / meet requirements H - Health Physics H - Health Physics 186 - Failure to take action / meet requirements O - Operations O - Control Room Ops 187 - Action implementation LTA G - Engineering G - Design 189 - Recognition of adverse condition / questioning attitude LTA T - Testing 

I - Instrumentation & Control

190 - Failure to stop work / non-conservative decision making T - Testing 

I - Instrumentation & Control

550

Number of Items for this Docket: 

Percent of Total for this Docket: 

Total Items for this Docket: 10
**Exhibit 31.2**

I, Edward W. Stone, certify that: 

1. I have reviewed this Quarterly Report on Form 10-Q for the quarter and six months ended December 29,2007, of Velocity Express Corporation; 

2. Based on my knowledge, this report does not contain any untrue statement of a material fact or omit to state amaterial fact necessary to make the statements made, in light of the circumstances under which such statements were made, not misleading with respect to the period covered by this report; 

3. Based on my knowledge, the financial statements, and other financial information included in this report, fairly present in all material respects the financialcondition, results of operations and cash flows of the registrant as of, and for, the periods presented in this report; 

4. The registrant’s othercertifying officer and I are responsible for establishing and maintaining disclosure controls and procedures (as defined in Exchange Act Rules 13a-15(e) and 15d-15(e)) for the registrant and have: 

(a) Designed such disclosure controls and procedures, or caused such disclosure controls and procedures to be designed under our supervision, to ensurethat material information relating to the registrant, including its consolidated subsidiaries, is made known to us by others within those entities, particularly during the period in which this report is being prepared, 

(b) Evaluated the effectiveness of the registrant’s disclosure controls and procedures and presented in this report our conclusions about theeffectiveness of the disclosure controls and procedures, as of the end of the period covered by this report based on such evaluation, and 

(c) Disclosed in this report any change in the registrant’s internal control over financial reporting that occurred during the registrant’s most recent fiscal quarter (the registrant’s fourth fiscal quarter in the case of anannual report) that has materially affected, or is reasonably likely to materially affect, the registrant’s internal control over financial reporting; 

5. The registrant’s other certifying officer and I have disclosed, based on our most recent evaluation of internal control over financial reporting, to the registrant’s auditors and the audit committee of the registrant’sboard of directors (or persons performing the equivalent functions): 

(a) All significant deficiencies and material weaknesses in the designor operation of internal control over financial reporting which are reasonably likely to adversely affect the registrant’s ability to record, process, summarize and report financial information; and 

(b) Any fraud, whether or not material, that involves management or other employees who have a significant role in the registrant’s internal controlover financial reporting. 

Date: February 12, 2008 

 

A signed original of this written statement required by Section 906 has been provided to VelocityExpress Corporation and will be retained by Velocity Express Corporation and furnished to the Securities and Exchange Commission or its staff upon request.
#### Will of Heckert: Wissman and another, Trustees, Appellants, vs. Heckert, Respondent.

*December 4, 1929*

January *7, 1930.*

*387For the appellants there was a brief by *Ryan, Cary & Ryan*of Appleton, and oral argument by *Patricia Ryan*and *Paul V. Cary.*

For the respondent the cause was submitted on the brief of *Albert H. Krugmeier*and *Joseph Witmer,*both of Appleton.

Fowler, J.

It is fundamental that a will should be so construed as to carry out the intention of the testator. From the provisions stated it is clear that the testator, for some reason deemed by him sufficient, probably because he wanted to assure that his property should go. eventually to his children or grandchildren and not to strangers, intended that the trustees should hold the respective shares of Herman and Clara until he or she should have a living child or *388should die and pay to him or her the income therefrom until one or the other event; that if the event were the birth of a living child, the bequest should then be paid to the one or both to whom a child was born; and if the event should be death, the share should then go to the brothers and sisters, or the heirs of any not then living, under the same conditions that their respective shares under their principal bequests were given to them. There is nothing in the will to indicate to the contrary. This requires reversal of the judgment so far as it provides for termination of the trust and payment to Herman and Clara of their shares at this time.

*By the Court.*— The portion of the judgment appealed from is reversed, and the cause remanded with directions to modify the judgment in accordance with the opinion.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Heavy-Section Steel Irradiation Program: Progress Report April 1997 - March 1998 (NUREG/CR-5591, Volume 8, No. 2)

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        - Publication Information
        - Abstract

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        - NUREG/CR-5591, Volume 8, No. 2 (PDF 3.55 MB)

## Publication Information

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

**Prepared by:** T.M. Rosseel

Oak Ridge National Laboratory Managed by Lockheed Martin Energy Research Corporation Oak Ridge, TN 37831-6158

C.J. Fairbanks, 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 L1098

Availability Notice

## Abstract

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiationinduced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established. Its primary goal is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and, in particular, the fracture-toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into eight tasks: (1) program management, (2) irradiation effects in engineering materials, (3) annealing, (4) microstructural analysis of radiation effects, (5) in-service irradiated and aged material evaluations, (6) fracture-toughness curve shift method, (7) special technical assistance, and (8) foreign research interactions. The work is performed by Oak Ridge National Laboratory.

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Assessment of Channel Coolant Voiding in RD-14M Test Facility using TRACE (NUREG/IA-0446)

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        - Publication Information
        - Abstract

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        - NUREG/IA-0446 (PDF - 4.58 MB)

## Publication Information

**Manuscript Completed:** December 2013**Date Published:** August 2014

**Prepared by:** Andrew Oussoren Aleksandar Delja

Canadian Nuclear Safety Commission 280 Slater Street P.O. Box 1046 Station B Ottawa, Ontario, Canada K1P 5S9

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

Coolant voiding in fuel channels of CANDU reactors during a Loss of Coolant Accident (LOCA) is important to reactor behaviour due to the power pulse arising from positive void reactivity. The prediction of voiding in fuel channels is therefore of fundamental importance to LOCA safety analysis. The CNSC is evaluating the applicability of the TRACE thermal hydraulics code to CANDU reactor simulation.

In this study, inlet header LOCA test B0106 from AECL’s RD-14M thermal hydraulic test facility was modeled using TRACE. RD-14M is a scaled CANDU heat transport system containing 10 electrically heated fuel channels and full elevation feeders and boilers. In this test, a break in an inlet header is simulated using a fast opening valve. The size of the break is such that it creates near stagnation flow in the affected loop. A neutron scatterometer installed on one of the test channels measures void fraction in the channel during the transient.

The TRACE code was capable of predicting channel voiding trends with good accuracy, while the extent of voiding was generally over predicted. System pressure is predicted very well over the first several seconds of the transient; however pressure is under-predicted later in the transient. This under-prediction can be corrected through modifying the multiplying coefficients in the TRACE critical flow model. Fuel sheath temperature was under predicted for most of the test; this is due to limitations in the ability to represent a horizontal fuel channel in TRACE.

Page Last Reviewed/Updated Tuesday, March 09, 2021
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Exhibit 23.2

**CONSENT OF INDEPENDENT PETROLEUM ENGINEERS**

Cawley, Gillespie and Associates, Inc. hereby consents to the use of its name and the information from its reports regarding estimated quantities of proved reserves, the future net revenues from those reserves and their present value as of January 1, 2007 in Foothills Resources, Inc.’s Annual Report on Form 10-K for the year ended December  31, 2006, and to the incorporation by reference thereof into Foothills Resources, Inc.’s previously filed Registration Statement No. 333-137925 on Form SB-2, as amended.

CAWLEY, GILLESPIE AND ASSOCIATES, INC.

 

Ft. Worth, Texas

April 12, 2007
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Nuclear Power Plant Fire Protection Research Program (NUREG-1148)

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        - Publication Information
        - Abstract

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        - NUREG-1148 (PDF - 1.05 MB)

## Publication Information

**Manuscript Completed:**April 1985**Date Published:**July 1985

**Prepared by:** A. Datta

Division of Engineering Technology Office of Nuclear Regulatory Research

In cooperation with Office of Nuclear Reactor Regulation

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

Availability Notice

## Abstract

A program plan for nuclear power plant fire protection research has been presented in this report. The principal objective of the program is to create a data base that would reduce the uncertainties in fire probabilistic risk assessment of plants. A three-pronged approach of characterization of potential fires, determination of the ensuing environment, and determination of failure thresholds of safetyrelated equipment in that environment is described. The techniques are to be applied to estimating the fire safety margin, available in a control room.

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Analysis of the THETIS Boildown Experiments Using RELAP5/MOD2 (NUREG/IA-0014)

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        - Publication Information
        - Abstract

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        - NUREG/IA-0014 (PDF 1.64 MB)

## Publication Information

**Date Published:** July 1989

**Prepared by:** M.G. Croxford, P.C. Hall

Central Electricity Generating Board Barnwood, Gloucester GL4 7RS United Kingdom

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)

**Published by:** Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555

Availability Notice

## Abstract

To test the ability of RELAI5iM-OD2 to model two phase mixture level and fuel rod heat transfer when the core has become partially uncovered, post test calculations have been carried out of a series of boildown tests in the AEEW THETIS out-of-pile test facility. This report describes the comparison between the code calculations and the test data.

Excellent agreement is obtained with mixture level boildown rates in tests at pressures of 40 bar and 20 bar. However at pressures below 10 bars the boildown rate is considerably overpredicted. A general tendency for RELAP5/IOD2 to overpredict void fraction below the two-phase mixture level is observed, which is traced to defects in the interphase drag models within the code. The heat up of exposed rods above the two-phase mixture level is satisfactorily calculated by the code.

The results support the use of RELAP5/MOD2 for analysis of high pressure core boildown events in PWRs.

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff for Knowledge Management

# Be riskSMART: Guidance for Integrating Risk Insights into NRC Decisions (NUREG/KM-0016)

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        - Publication Information
        - Abstract

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        - NUREG/KM-0016 (PDF - 5.61 MB)

## Publication Information

**Manuscript Completed:** March 2021**Date Published:** March 2021

**Prepared by:**Mirela GavrilasEric DuncanJason PaigeBrian K. HarrisCandace De MessieresElizabeth BowlinMichael GartmanReed AnzaloneRebecca Richardson

Office of the Executive Director for OperationsBe riskSMART Initiative TeamU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001

Availability Notice

## Abstract

To become a modern, risk-informed regulator, the NRC focused on four transformational areas: (1)managing the workforce, (2) applying risk in decision-making, (3) generating innovative ideas to improve the way that NRC works, and (4) adopting new technologies and approaches to data analytics. The Be riskSMART framework supports the second transformation area by providing a systematic approach to making risk-informed decisions across disciplines. Be riskSMART combines traditional concepts, such as the risk triplet, risk management, the risk heat map and risk appetite, into a plain language framework that gives the staff confidence to apply and communicate risk-insights for all kinds of NRC decisions whether they are in the technical, corporate, or legal arena. This NUREG/KM provides detailed guidance on using the Be riskSMART framework and contains example case studies from across a series of disciplines.

Page Last Reviewed/Updated Monday, November 21, 2022
xml version="1.0" encoding="UTF-8"?


L\_2015108EN.01000702.xml


| | | | |
| --- | --- | --- | --- |
| 28.4.2015 | EN | Official Journal of the European Union | L 108/7 |

---

Corrigendum to the Definitive adoption (EU, Euratom) 2015/366 of Amending budget No 2 of the European Union for the financial year 2014

(
[Official Journal of the European Union L 73 of 17 March 2015](http://publications.europa.eu/resource/oj/JOL_2015_073_R_TOC)
)

On pages 12 to 15, in the column ‘Amending budget No 2/2014’:

for:

‘
2 967 027 640
’

,

read:

‘
1 961 620 715
’

;

on page 12, in the column ‘Amending budget No 2/2014’, in the ‘Grand total’ row:

for:

‘
4 535 027 640
’

,

read:

‘
3 529 620 715
’

.

---
Exhibit 32.1




MUNICIPAL MORTGAGE & EQUITY, LLC


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 Quarterly Report of Municipal Mortgage & Equity, LLC, a Delaware limited liability company (the “Company”), on Form 10-Q for the quarter ended March 31, 2011 as filed with the Securities and Exchange Commission on the date hereof (the “Report”), I, Michael L. Falcone, President, Chief Executive Officer and Director of the Company, certify, pursuant to 18 U.S.C. § 1350, as adopted pursuant to § 906 of the Sarbanes-Oxley Act of 2002, that to the best of my knowledge:





(1)
The Report fully complies with the requirements of Section 13(a) or 15(d) of the Securities Exchange Act of 1934; and





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




Date: May 13, 2011




/s/ Michael L. FalconeMichael L. FalconeChief Executive Officer, President and Director




A signed original of this written statement required by Section 906 has been provided to Municipal Mortgage & Equity, LLC and will be retained by Municipal Mortgage & Equity, LLC and furnished to the Securities and Exchange Commission or its staff upon request.




E-4
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