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Agenda Item W8.1 DS407 Version 4 Track Changes Draft Safety Guide on Criticality Safety for Facilities and Activities Handling Fissionable Material 11-11-10.

DS407-Safety Committee Review(V4)-Track Changes.doc DS407 Version 4 TRACK CHANGES IAEA SAFETY STANDARDS for protecting people and the environment CRITICALITY SAFETY FOR FACILITIES AND ACTIVITIES HANDLING FISSIONABLE MATERIAL DRAFT SPECIFIC SAFETY GUIDE SSG D...

"Evaluation of Computer-Assisted Cross Section Balancing Methods for Analysis of Subsurface Fault Geometry in the Vicinity of Yucca Mountain, Nevada: A Pilot Study."

A9* 0EVALUATION OF COMPUTER-ASSISTED CROSS SECTIONBALANCING METHODS FOR ANALYSIS OF SUBSURFACE FAULTGEOMETRY IN THE VICINITY OF YUCCA MOUNTAIN, NEVADA:A PILOT STUDYPrepared forThe U. S. Nuclear Regulatory CommissionContract No. NRC-02-88-005Account No. 20-3702-002Activity No. ...

"Basalt Waste Isolation Project, Quality Assurance Program Requirements Manual."

R HO-QA-MA-3BASALT WASTE ISOLATION PROJECTRockwell Hanford Orerations QUALITY ASSURANCE PROGRAM REQUIREMENTS MANUALMescr1tED QUALITY ASSURANCE PROGRAM Section E Chapter N/A Revision3Dr C. BBS ~'A Mana 1IP issue Date Page< G~~A f 128 _ alOfl'~~1~'~~1~~G~fET0 R?%&~ 1JOHIN SON Na...

"Project Management Procedures Manual, Basalt Waste Isolation Project."

RH1O-8W4A17CRockwell International PROJECT MANAGEMENT PROCEDURES MANUALRockwell Hanford operations BASALT WASTE ISOLATION PROJECTRichland. WA 993S2k.2RAED QUALITY ASSURACEPenaring Org. Issue Oate 'Rev. Numef 1Paig SCIENCE AND z1;^t'EERING 02/25/87 0 4-121 l 3 2 !.~~~~~~~~~~~~~...

Part 3 of 21 - Revision 1 to Final Safety Analysis Report for Holtec International Storage & Transfer Operation Reinforced Module Cask System (HI-STORM 100 Cask System), Volume I of II.

CHAPTER 2t: PRINCIPAL DESIGN CRITERIA This chapter contains a compilation of design criteria applicable to the HI-STORM 100 System. The loadings and conditions prescribed herein for the MPC, particularly those pertaining to mechanical accidents, are far moir severe in most cas...

Part 16 of 21 - Revision 1 to Final Safety Analysis Report for Holtec International Storage & Transfer Operation Reinforced Module Cask System (HI-STORM 100 Cask System), Volume I of II.

CHAPTER 6': CRITICALITY EVALUATIONThis chapter documents the criticality evaluation of the HI-STORM 100 System for the storage of spent nuclear fuel in accordance with 10CFR72.124. The results of this evaluation demonstrate that the HI-STORM 100 System is consistent with the S...

2009/02/06-Environmental Impacts of Storing Spent Nuclear Fuel and High-Level Waste from Commercial Nuclear Reactors: A Critique of NRCs Waste Confidence Decision and Environmental Impact Determination.

DOCKETEDUSNRCOctober 27, 2009 (8:30am)OFFICE OF SECRETARYINSTITUTE FOR RESOURCE AND SECURITY STUDIES RULEMAKINGS AND27 Ellsworth Avenue, Cambridge, Massachusetts 02139, USA ADJUDICATIONS STAFFPhone: 617-491-5177 Fax: 617-491-6904Email: infojirss-usa.orgEnvironmental Impacts of...

Comanche Peak Nuclear Plant, Unit 3 & 4, Response to Request for Additional Information No. 3183.

Rafael FloresSenior Vice President &Chief Nuclear Officerrafael.flores@luminant.comLuminant PowerP 0 Box 10026322 North FM 56Glen Rose, TX 76043LuminantT 254.897.5590F 254.897.6652C 817.559.0403CP-200901566Log # TXNB-09069Ref. # 10 CFR 52November 16, 2009U. S. Nuclear Regulato...

Watts Bar. Nuclear Plant Supplemental Condenser Cooling Water Project - Thermal Plume Modeling.

WATTS BAR. NUCLEAR PLANTSUPPLEMENTALCONDENSER COOLING WATER PROJECTThermal Plume ModelingPrepared by WalterHarperTennessee Valley AuthorityEngineering LaboratoryNorris, TennesseeDecember 5, 1997Index No: 444Title: Watts Bar Nuclear PlantSupplemental Condenser Cooling WaterProj...

NEDO-33226, Rev. 2, "ESBWR Licensing Topical Report - Software Management Plan," Enclosure 5.

Enclosure 5MFN 07-384ESBWR Licensing Topical Report -Software Management Plan, Rev. 2 -NEDO-33226Non-Proprietary VersionGE EnergyNuclear3901 Castle Hayne RdWilmington, NC 28401NEDO-33226Revision 2Class IDRF#0000-0051-3897July 2007LICENSING TOPICAL REPORTESBWR I&C SOFTWARE MANA...

1989/12/31- Jefferson Proving Ground October 2007 Evidentiary Hearing - Staff Exhibit 27 - Excerpt -Limiting Values of Radionuc, Federal Guidance Report No. 1.....

STAFF EXHIBIT 27United SitatsErtvionnensth ProtectitonAgenicyOtfice ofRadiation PrograrmWashington, DC 20480EPA-Ml1 -W-O20ssarb I gaRadist.on^ EPALimiting Values ofRadionuclide IntakeAnd Air ConcentrationandDose Conversion FactorsFor Inhalation, Submersion,And IngestionUIPA_ C...

Naval Station Great Lakes, Great Lakes, IL, Work Plan for Remediation of Recreation and Center Tank Areas and Site-Wide Final Status Survey.

Work Plan for the Remediation of the Recreation and Center Tank Areas and Site-Wide Final Status Survey Former Monazite Sand Storage Area Naval Station Great Lakes Great Lakes, Illinois Project USN 2000-003, Phase IV, Modification 1 CABRERA Project No. 05-3060.01 Contrac...

IMC 1245 App A, "Basic-Level Training and Qualification Journal."

Issue Date: 01/10/08 1245Appendix ABasic-Level Training and Qualification JournalIssue Date: 01/10/08 1245 A-2Table of ContentsIntroduction ....................................................... A-4Required Basic-Level Training Courses............................................

"DCRDR Supplemental Summary Rept."

DETAILED CONTROL ROOM DESIGN REVIEWSUPPLEMENTAL SUMMARY REPORTWATTS BAR NUCLEAR PLANTUNITS 1 AND 2PREPARED BY:TENNESSEE VALLEY AUTHORITYWATTS BAR NUCLEAR PLANTSPRING CITY, TENNESSEE 37381FEBRUARY 19901081g90041001S 902PDR ADOCK.: 00Q3'9A -0D0TABLE OF CONTENTS1.0 INTRODUCTION...

DTE Energy - Detroit Edison Fermi 3 COLA (Emergency Plan), Rev. 2 - COL Part 05 - Evacuation Time Estimate - Part 01

October, 2009 Rev. 1, Final KLD TR – 426 Fermi Nuclear Power Plant Development of Evacuation Time Estimates Prepared for: Detroit Edison by: KLD Associates, Inc. 43 Corporate Drive Hauppauge, NY 11788 mailto:kweinisch@kldassociates.com Fermi Nuclear Power Plant ...

Contract No. NRC-42-10-005.

SOLICITATION/CONTRACT/ORDER FOR COMMERCIAL ITEMS 1 - REQUISITION NO. PAGE 1 OFOFFEROR TO COMPLETE BLOCKS 12, 17, 23, 24, & 302. CONTRACT NO, 3. AWARD/EFFECTIVE DATE 4. ORDER NO. 5. SOLICITATION NUMBER 6. SOLICITATION ISSUE DATENRC-42-10-005 ee 30c Below RS-42-10-005 03-01-2010...

North Anna Unit 3 COLA (Final Safety Analysis Report), Rev. 3 - MACTEC App E.2 - Geovision Downhole and P-S Logging Report - App F - Boring Geophysical Logging Field Measurement Procedures (HiRAT pp13…14)

MACTEC Engineering and Consulting, Inc.North Anna COL Geotechnical Report Attachment E ReportingProject 6468-06-1472January 17, 2007The final report will include the objective and scope of the survey, location of the boreholes, discussion ofinstrumentation and procedures in th...

Comment (28) of Ace Hoffman Opposing San Onofre's Steam Generator Replacement Project. Part 2 of 2.

CONC USIONRenewables give us all the energy we need, and waiting to switch is deadly.Some say "politics" is stopping Yucca Mountain, or stopping an expansion of nuclear power, orstopping reprocessing from restarting, or stopping "mini-nukes, nuclear airplanes, etc. etc..But ac...

Catawba, Units 1 & 2 Request for Relief Number 06-CN-003 Use of Polyethylene Material in Nuclear Safety Related Piping Applications.

DukeEnergy@JAMES R. MORRISVice PresidentCatawba Nuclear Station4800 Concord Rd. / CN01 VPYork, SC 29745-9635803 831 4251803 831 3221 faxOctober 26, 2006U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555Subject: Duke Power Company LLC d/b/a...

Comment (39) of James H. Riley, on Behalf of Nuclear Energy Institute, regarding Draft Regulatory Guide DG-1170, "Fire Protection For Nuclear Power Plants."

NUCLEAR ENERGY INSTITUTE71 FP SS5/ 74James H. RileyDIRECTOR, ENGINEERINGNUCLEAR GENERATION DIVISIONDecember 22, 2006Chief, Rules and Directives BranchOffice of AdministrationU.S. Nuclear Regulatory CommissionMail Stop T6-D59Washington, DC 20555-0001SUBJECT: Draft Regulatory Gu...

Draft Regulatory Guide DG-4010, "Quality Assurance for Radiological Monitoring Programs (Inception Through Normal Operations to License Termination) -- Effluent Streams and the Environment (Proposed Revision 2 of Regulatory Guide 4.15).

1Special terms used in this guide are marked in SMALL CAPITALS the first time they are used, and are definedin the glossary provided in Appendix A of this regulatory guide.This regulatory guide is being issued in draft form to involve the public in the early stages of the deve...

Millstone Power Station Units 1, 2 and 3 and ISFSI Annual Reporting of Changes to the Quality Assurance Program Revision 27 to the Dominion Nuclear Connecticut. Inc. Quality Assurance Program Topical Report.

Dominion Nuclear Connecticut, Inc. XI ill\totic I’owcr Station I

Multiple Letters and Post Exam Comments (Folder 1).

July 11,2005 Mr. John Caruso, Senior Operations Engineer U.S. Nuclear Regulatory Commission Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Subject: 2005 Limerick Generating Station Limited Senior reactor Operator Initial Examination Comments Dear Mr. Camso, Per NUR...

Revision 4 to North Anna Early Site Permit Application, Part 2 - Site Safety Analysis Report.

2-2-328 Revision 4May 2005North AnnaEarly Site Permit ApplicationPart 2 - Site Safety Analysis Report2.5.5 Stability of SlopesThis section presents information on the stability of permanent slopes at the NAPS site. Theinformation has been developed in accordance with Review St...

Roadmap to References Part 5, RAI Responses 18-27.

RAI Responses 18-27RESPONSE TO RAI COMMENT 18ROADMAP TO REFERENCESREFERENCED DOCUMENT *EXCERPT LOCATION REMARKCook et al. 2005 General reference; no excerpt includedwith this response.DOE Order 414.1C, Quality Assurance Excerpt enclosed following response. Attachment 2.SRM414....