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Comment (3) from Ellen Ginsberg on behalf of NEI on NRC Enforcement Policy Revision.

* ;,---- -.ME: INUCLEAR ENERGY INSTITUTEEllen C. GinsbergVICE PRESIDENT, GENERAL COUNSELAND SECRETARYNovember 14, 2008BY ELECTRONIC MAIL5/~3 ~$i3Z~4Mr. Michael T. LesarChief, Rulemaking, Directives, and Editing BranchOffice of AdministrationMail Stop: T-6D59U.S. Nuclear Regula...

Holtec International, Response to RAI on Certificate of Compliance (CoC) License Application for HI-STAR 60 Package.

nEu,,HOLTECINTERNATIONALHoltec Center, 555 Lincoln Drive West, Marlton, NJ 08053Telephone (856) 797-0900Fax (856) 797-0909November 21, 2008U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Reference:Subject:Docket No. 71-9336, TAC No. L24121...

Millstone Power Station Units 2 and 3 - Appendix A to Quality Assurance Program (QAP).

APPENDIX A QUALITY ASSURANCE PROGRAM (QAP) Unit 2/3 CATEGORY I STRUCTURES, SYSTEMS AND COMPONENTS TOPICAL REPORT - MILLSTONE POWER STATION (Note: This Appendix is not applicable to Unit 1 - See DSAR, or to the ISFSI - See the FSAR for the Standardized NUHOMS Horizontal Modular...

Calvert Cliffs Nuclear Power Plant - "Development of Evacuation Time Estimates," Cover Page through Appendix F.

Enclosure 2Calvert Cliffs Nuclear Power PlantDevelopment of Evacuation Time EstimatesLLiCalvert Cliffs Nuclear Power PlantDevelopment of Evacuation Time EstimatesPrepared for:Constellation Energyby:KLD Associates, Inc.47 Mall Drive, Suite 8Commack, NY 11725satya@kldassociates....

NUREG/BR-0007, Rev. 6, "Instructions for the Preparation and Distribution of Material Status Reports (DOE/NRC Forms 742 and 742C)."

7U.S.NRCUnited States Nuclear Regulatory CommissionProtecting People and the EnvironmentNUREG/BR-0007, Rev. 6Instructions for thePreparation andDistribution of MaterialStatus Reports(DOE/NRC Forms 742 and 742C)Effective Date: January 1, 2009Office of Nuclear Material Safety an...

Regulatory Guide 5.71, "Cyber Security Program for Nuclear Facilities".

U.S. NUCLEAR REGULATORY COMMISSION January 2010 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of t...

SECY-07-0209 - Enclosure 2: 2007 Annual Report - Decommissioning Program

Status of the NRC Decommissioning Program 2007 Annual Report Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs U.S. Nuclear Regulatory Commission Washington...

3/15/2007 - Final Brief for Petitioner State of Utah; Nos. 05-1419, 05-1420 and 06-1087.

PUBLIC COPY -SEALED MATERIAL DELETEDORAL ARGUMENT SCHEDULED FOR APRIL 24, 2007IN THE UNITED STATES COURT OF APPEALSFOR THE DISTRICT OF COLUMBIA CIRCUITNos. 05-1419, 05-1420, and 06-1087OHNGO GAUDADEH DEVIA, andSTATE OF UTAH,Petitioners,V.U.S. NUCLEAR REGULATORY COMMISSIONand t...

Forest Stewardship Plan for the Susquehanna Riverlands Property of PP & L, Inc., April 1999.

Attachment 43 to PLA-6219Forest Stewardship Plan for theSusquehanna Riverlands Property of PP&L, Inc.April 1999(NRC Document Request 98)Forest Stewardship Planfor the Susquehanna RiverlandsProperty of PP&L, Inc.Townships of Salem, Conyngham,Hollenback and NescopeckLuzerne Coun...

NUREG-1614, Volume 4. "U.S. Nuclear Regulatory Commission, FY 2008-2012 Strategic Plan" - DRAFT

FY 2007 - FY 2012 Strategic Plan July 2007 2About the NRC The United States Nuclear Regulatory Commission (NRC or agency) was established by the Energy Reorganization Act of 1974, and began operations in 1975. The NRC was established to regulate the civili...

Technical Evaluation Report: The Acceptability of Fort St. Vrain Upgraded Technical Specifications for Structures, Systems, and Components with Safety-Related and Important-to-Safety Cooling Functions, July 1988.

vTECHNICAL EVALUATION REPORTFORT ST. VRAIN NUCLEAR GENERATING STATIONDOCKET 50-267LICENSEE: PUBLIC SERVICE CO. OF COLORADOTHE ACCEPTABILITY OF FORT ST. VRAIN UPGRADEDTECHNICAL SPECIFICATIONS FOR STRUCTURES, SYSTEMS, AND COMPONENTSWITH SAFETY-RELATED AND IMPORTANT-TO-SAFETY COO...

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

INSTITUTE FOR RESOURCE AND SECURITY STUDIES 27 Ellsworth Avenue, Cambridge, Massachusetts 02139, USA Phone: 617-491-5177 Fax: 617-491-6904 Email: info@irss-usa.org Environmental Impacts of Storing Spent Nuclear Fuel and High-Level Waste from Commercial Nuclear Reacto...

IMC 1252 App A, "Construction Inspector Basic-Level Training and Certification Journal."

Appendix A Construction Inspector Basic-Level Training and Certification Journal Issue Date: 11/25/08 i 1252, Appendix A Table of Contents Introduction ....................................................................................................................

Holtec International, Final Safety Analysis Report for the HI-STORM 100 Cask System, HI-2002444, Rev. 6, "Safety Significant," Chapter 9: Acceptance Criteria and Maintenance Program.

CHAPTER 9t: ACCEPTANCE CRITERIA AND MAINTENANCE PROGRAM9.0 INTRODUCTIONThis chapter identifies the fabrication, inspection, test, and maintenance programs to beconducted on the HI-STORM 100 System, including the HI-TRAC transfer cask to verify thatthe structures, systems and c...

Transcript of the Independent External Review Panel Meeting, March 6, 2008, Pages 1-43.

Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION Title: Independent External Review Panel Meeting 7th Meeting Docket Number: (n/a) Location: Rockville, Maryland Date: Thursday, March 6, 2008 Work Order No.: NRC-2055 Pages 1-4 ...

2008/04/21-Corrected Version, Review of Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, Inc. Analyses of the Effects of Reactor Water Environment on Fatigue Life of Risk-Significant Components During the Period of Extended Operation.

I2-A-S N- qNEC-JH_03DOCKETED.USNRC [CORRECTED VERSION]April 30, 2008 (2:31pm)OFFICE OF SECRETARYRULEMAKINGS ANDADJUDICATIONS STAFFReview of Entergy Nuclear Vermont Yankee, LLC andEntergy Nuclear Operations, Inc. ("Entergy") Analyses ofthe Effects of Reactor Water Environment o...

Transmittal of Final Interim Staff Guidance - Notice of Availability of the Final Interim Staff Guidance DC/COL-ISG-007 to ACRS and CRGR on the Assessment of Normal and Extreme Winter Precipitation Loads on the Roofs of Seismic Category 1 Structures.

July 7, 2009 MEMORANDUM TO: Edwin M. Hackett, Executive Director Advisory Committee on Reactor Safeguards Advisory Committee on Nuclear Waste and Materials James E. Lyons, Chairman The Committee to Review Generic Requirements FROM: William F. Burton, Branch Chief /...

05/2709 - 05/28/09-Summary of Open Meeting with AREVA, General Electric-Hitachi, and Westinghouse on Accident Uncertainty Methodology Issues.

June 11, 2009 MEMORANDUM TO: William H. Ruland, Director Division of Safety Systems Office of Nuclear Reactor Regulation FROM: Timothy E. Collins, Senior Advisor /RA/ Division of Safety Systems Office of Nuclear Reactor Regulation SUBJECT: SUMMARY OF MAY ...

Holtec International Final Safety Analysis Report for the HI-STORM 100 Cask System. Chapter 2: Principal Design Criteria.

CHAPTER 2t: PRINCIPAL DESIGN CRITERIAThis chapter contains a compilation of design 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 ...

Contract No. NRC-38-10-714.

AWARD/CONTRACT 1. THIS CONTRACT IS RATED ORDER RATINGN PAGE1 OF 3PAGAUNDER PAS (15 C4R 700) NN A R NO2. ZCNTRACT NO. (Proc. Inst. Ident) 3. EFFECTIVE DATE 4. REQUiSITIONIPURCHASE REOUEST/PROJECT NO.NRC-38-10-714 See Block 19c. HR-08-714 & HR-10-7145. ISSUED BY CODE 3100 6. ADM...

"Intervenors' Contentions Regarding Applicant's Submittal Under 10 CFR 52.80 and 10 CFR 50.54(hh)(d) and Request for Subpart G Hearing."

CONTAINS SENSITIVE UNCLASSIFIED NON-SAFEGUARDS INFORMATIONWITHHOLD PER 10 C.F.R. § 2.390 AND JULY 1, 2009 PROTECTIVE ORDERUNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARDIn the Matter ofLuminant Generation Co., LLC Docket Nos. 5...

Grant No. NRC-38-10-968.

U.S. NUCLEAR REGULATORY COMMISSION_ NOTICE OF GRANT/ASSISTANCE AWARD1. G[NT/AGRW.MENT NO. 2. MODIFICAIION NO. 3. PERIOD OF PERFORMANCE 4. AUTHORITYNRC-38-10-968 FROM: 7/1/2010 TO: 6/30/2012 to Pursuant to Section 31bb and 141b of theAoiEnergy Act of 1954, as amended5. TYPE OF...

Fermi 2 - Request for Approval of Revised Cyber Security Plan.

Joseph H. PlonaSite Vice President6400 N. Dixie Highway, Newport, MI 48166Tel: 734.586.5910 Fax: 734.586.4172Security-Related Information - Withhold Under 10 CFR 2.39010 CFR 50.90July 27, 2010NRC-10-0050U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashing...

Comment (35) of Patrick Mulligan, on Behalf of Conference of Radiation Control Program Directors, on NRC-2010-0080-0009, NUREG-0654/FEMA-REP-1, Rev. 1, Suppl 3, Guidance for Protective Action Recommendations for General Emergencies; Draft for Comment.

Page 1 of 1As of: August 06, 2010Received: August 04, 2010IStatus: Pending-PostPUBLIC $0"U 7 91S S 7ON ITracking No. 80b2954eComments Due: August 09, 2010Submission Type: WebDocket: NRC-2010-0080Notice of Availability of NUREG-0654/FEMA-REP-1, Revision 1, Supplement 3, Guidanc...

NUREG/BR-0024 "Working Safely in Gamma Radiography: A Training Manual for Industrial Radiographers."

-- 4wk -144% ýýAIMMCoe DesignTh cove fetue a stlied crsseto vie of a raigah cam-era Th fin lie an .hadinsyboiz raito and th flo of Sraiaio thog inutra objectsOffice of Nuclear Regulatory ResearchU.S. Nuclear Regulatory CommissionWashington, DC 20555Working Safely inGamma Radio...