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Part 2 of 2, Review of the DOE Report: "The Origin of Calcit-Silica Deposits at Trench 14 and Busted Butte and Methodologies Used to Determine Their Origin", Special Report No.18 Submitted to the Nuclear Waste Project Office, State of Nevada.

Appendix IIIPaleotemperature Environment At Yucca Mountain,Nevada (Status Report)TRAC Technology and Resource Assessment Corporation3800 Arapahoe Avenue, Suite 225Boulder, Colorado 80303(303) 443-3700 FAX No. (303) 443-8626Annual Report - NevadaPart I - GeologyCONTRACT No. 94/...

NRC Generic Letter 1988-020: Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54.

Individual Plant Examination for Severe Accident Vulnerabilities - 10 CFR 50.54(f) Page 1 of 25Index Site Map I FAQ I Help I Glossary I Contact Us A Search Ai .S.S. Nuclear Regulatory CommissionHome || Who We Are What We Do Nuclear Nuclear Radioactive PublicI Reactors fl Mater...

1993/07/27-PFS - APPLICANT EXHIBIT 154 - REC'D 07/01/02: REPORT OF F-16 ACCIDENT WHICH OCCURRED ON 07/27/93

:177J1DOCKETED USHRC 2003 JN 17 PH 1: 36 iFFC if-,pT [ S .... AljtlAD TOlNGS SATNAFFFI 6C -SN 86-0275 AND F-I6C SN 87-0335*' --.. .. ~..,-ASSIO 0f . ,O 8TH FIGHTER WING (PACAF),.3 KUNSAN-AIR BASE, REPUBLIC OF-KOREA 27 JULY1 993 CONDUCTED IN ACCORDANCE WITH AFR 110-14IAPPOINT...

Publication of Final Staff Technical Position on Regulatory Considerations in Design & Construction of Exploratory Shaft Facility.

MAY 2 4 9I89001353.MEYER/FINAL STP-. MEMORANDUM FOR:FROM:SUBJECT:-1-David L. Meyer, ChiefRegulatory Publications BranchDivision of Freedom of Informationand Publications ServicesOffice of AdministrationJohn J. Linehan, Acting DirectorRepository Licensing and Quality AssuranceP...

Technical Position on Repository Design - Thermal Loads.

VrI_ _ wTechnical Position onRepository Design Thermal Loads_ _ _-.01-M_ _ _ -U.S. Nuclear Regulatory CommissionOffice of Nuclear Material Safety and SafeguardsDivision of High-Level Waste ManagementJohn T. Buckley#NS TE6NAL V190060611-900531 '1''ABSTRACTThis technical positio...

Rev 0 to SSP-10.C, "Evaluation of Installed Safety-Related Replacement Items." Site Std Practice (SSP) defines administrative,technical & quality controls used by nuclear engineering at plant.

ENCLOSURE 2CONTENTS1. SSP-lO.C, "Evaluation of Installed Safety-Related Replacement Items"(Replacement Items Project)2. SSP-lO.B, "Materials Improvement Project"3. SSP-10.5, "Technical Evaluation for Procurement of Materials and Services"9202110130 920203PDR ADOCK 05000390A PD...

Forwards DCRDR supplementary rept addressing open issues identified by 890428 safety evaluation,per 890803 ltr.

TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 374015N 157B Lookout PlaceFEB 23 1990U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555Gentlemen:In the Matter of the Application of )Docket Nos. 50-390Tennessee Valley Authority )50-391WATTS BAR...

Progress Energy Harris Nuclear Units 2 & 3 COLA (Emergency Plan), Rev. 0 - HAR_EP_SUPP_KLD_Harris_ETE_Part1

47 Mall Drive, Suite 8 Commack, NY 11725 USA Phone: 631.543.6500 Fax: 631.543.4330 www.kldassociates.com August 23, 2007 Mrs. Teresa Gildersleeve Progress Energy Carolinas, Inc. P.O. Box 1551 PEB 5 Raleigh, NC 27602-1551 Ref: Harris ETE Report Dear Teresa: Enclose...

HI-2002444, Rev. 06, "Final Safety Analysis Report for the HI-STORM 100 Cask System," Chapter 3 through Chapter 5, Appendix 5.G.

CHAPTER 3: STRUCTURAL EVALUATIONt3.0 OVERVIEWIn this chapter, the structural components of the HI-STORM 100 System that are important to safety(ITS) are identified and described. The objective of the structural analyses is to ensure that theintegrity of the HI-STORM 100 System...

V. C. Summer Nuclear Station Units 2 & 3 COLA (Emergency Plan), Rev. 0 - Evacuation Time Estimates for V. C. Summer - Part 1

August, 2007 Final Revision KLD TR – 411 Virgil C. Summer Nuclear Station Development of Evacuation Time Estimates Prepared for: South Carolina Electric & Gas Company by: KLD Associates, Inc. 47 Mall Drive, Suite 8 Commack, NY 11725 mailto:rgoldblatt@kldassociates....

Holtec International, Final Safety Analysis Report for the HI-STORM 100 Cask System, HI-2002444, Rev. 6, "Safety Significant," Chapter 3: Structural Evaluation.

CHAPTER 3: STRUCTURAL EVALUATIONt3.0 OVERVIEWIn this chapter, the structural components ofthe HI-STORM 100 System that are important to safety(ITS) are identified and described. The objective of the structural analyses is to ensure that theintegrity of the HI-STORM 100 System ...

Handout 1: TR WCAP-16308-NP.

Revised Table A-2 for WCAP-16308-NP – based on NRC Feedback from March 3, 2008 Telephone Conference Call 4/11/08 Page 1 of 16 Table A-2 Changes in ASME Code Case N-660, Revision 0 for PWROG Passive Categorization N-660, R0 Section ASME Code Case N-660 Revision 0 Proposed...

04/09/2008 Meeting Handout 3: TR WCAP-16308-NP.

OG-07-459 Page 1 of 15 Table A-2a Methodology/Process Changes in ASME Code Case N-660 for WCGS Categorization N-660 Section Endorsed Revision 0 WCGS IDP Version Basis for Change -1200(a) “… failure potential is conservatively assumed to be 1.0 in determining a consequenc...

"Watts Bar Nuclear Plant Verification & Validation Plan for Eagle-21 Digital Instrumentation."

@0ENCLOSURE 1WATTS BAR NUCLEAR PLANTVERIFICATION AND VALIDATION PLANFOREAGLE-21 DIGITAL INSTRUMENTATION8701050197 861229PDR ADOCK 05000390A PDR*0@0WATTS BAR NUCLEAR PLANTVERIFICATION AND VALIDATION PLANFOREAGLE-21DIGITAL INSTRUMENTATION0 *TABLE OF CONTENTSTitle Paq(1.0 Introdu...

Vol 1 of "Nuclear Performance Plan,Corporate."

TENNESSEE VALLEY AUTHORITY KNOXVILt.E. TENNESSEE 37902 Pý- ICK OF THE BOARD OF DIRECTORS TVA Tennessee Valley Authority N O V 1 1 9 8 W 1 1f l l a a e I Licensing and Risk Kr. William J. Dircks 5N15 Hum Looaoer Plc Executive Director of Operations 1101 wetmt, TN U1.S. Nuclear ...

Dept of Homeland Security PAG Radiological Dispersal Device Improvised Nuclear Device Guidance.

1Billing Code: 9110-21-P DEPARTMENT OF HOMELAND SECURITY Federal Emergency Management Agency Docket ID FEMA-2004-0004 Z-RIN 1660-ZA02 Planning Guidance for Protection and Recovery Following Radiological Dispersal Device (RDD) and Improvised Nuclear Device (IND) Incidents AGEN...

2008/04/21-Vermont Yankee July 2008 Evidentiary Hearing - Intervenor Exhibit NEC-JH_03, Joram Hopenfeld, "Review of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. ("Entergy") Analyses of the Effects of Reactor Water...."

P-A-s H -/nIggNEC-JH_03[CORRECTED VERSION]Review of Entergy Nuclear Vermont Yankee, LLC andEntergy Nuclear Operations, Inc. ("Entergy") Analyses ofthe Effects of Reactor Water Environment on Fatigue Life ofRisk-significant Components During the Period of ExtendedOperationDr. J...

Final Safety Analysis Report for the HI-STORM 100 Cask System, Revision 7 - Chapter 2: Principal Design Criteria.

CHAPTER 2t: PRINCIPAL DESIGN CRITERIAThis chapter contains a compilation ofdesign criteria applicable to the HI-STORM 100 System. Theloadings and conditions prescribed herein for the MPC, particularly those pertaining to mechanicalaccidents, are far more severe in most cases t...

Final Safety Analysis Report for the HI-STORM 100 Cask System, Revision 7 - Chapter 6: Criticality Evaluation.

CHAPTER 6t: CRITICALITY EVALUATIONThis chapter documents the criticality evaluation of the HI-STORM 100 System for the storageof spent nuclear fuel in accordance with 1OCFR72.1 24. The results of this evaluationdemonstrate that the HI-STORM 100 System is consistent with the St...

IMC 1247 App A, "Basic-Level Training and Certification Journal Fuel Facility Inspector".

Issue Date: 02/18/09 A-1 1247 Appendix A: Basic-Level Training and Certification Journal Fuel Facility Inspector Issue Date: 02/18/09 A-2 1247 Table of Contents Introduction .......................................................................................

Response to Request for Additional Information on HI-STORM 100 System - Supplement 2 (100U License Amendment Request 1014-6.

MENEMHOLTECINTERNATIONALHoltec Center, 555 Lincoln Drive West, Marlton, NJ 08053Telephone (856) 797-0900Fax (856) 797-0909Mr. John Goshenc/o Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001April 6, 2009Subject:Reference:Response to Request for ...

Progress Energy Levy Units 1 and 2 COLA (Emergency Plan), Rev. 0 - Supplemental - KLD Harris ETE Part1

47 Mall Drive, Suite 8 Commack, NY 11725 USA Phone: 631.543.6500 Fax: 631.543.4330 www.kldassociates.com April 1, 2008 Mr. John Stephenson Emergency Preparedness Supervisor Progress Energy Crystal River EOF 8200 West Venable Street Crystal River, FL 34429-5492 Ref: R...

TDR-WIS-MD-000003, Rev. 00, Interim Change No. 01, "The Development of Information Catalogued in REV00 of the YMP FEP Database".

QA: QATDR-WIS-MD-000003 REV 00 ICN 01February 2001The Development of Information Catalogued inREV00 of the YMP FEP DatabasebyGeoff A. Freeze, Nancy S. Brodsky, and Peter N. SwiftPrepared for:U.S. Department of EnergyYucca Mountain Site Characterization OfficeP.O. Box 30307Nort...

VA Medical Center, New Orleans, Louisiana Escalated Enforcement Background Information.

VA Medical Center, New Orleans, Louisiana Escalated Enforcement Backmound Information 1. On October 27,2004, the medical center discovered and reported the inadvertent disposal of 10 mCi (>lo00 x 10 CFR 20, Appendix C) '*'I in a local landfill. 2. Per 10 CFR 20 reporting requi...

Cabrera Services, Radiological Final Status Survey dtd 11/2004.

$MdO FINAL REPORT ap9 Q 63QY Radiological Final Status Survey Transonic Range - Land Areas Depleted Uranium Study Area Aberdeen Proving Ground, Aberdeen, MD Contract Number DAAA09-02-C-0057 Prepared for: US. Army Field Support Command AMSIO-ACE-D Bldg.., 350 51h Floor Rock Isl...