Report a Safety Concern
Search
Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Entergy Pre-Filed Hearing Exhibit ENT000028, Entergy's Statement of Position Regarding Contention RK-TC-2 (Flow-Accelerated Corrosion).

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of ) Docket Nos. 50-247-LR and ) 50-286-LR ENTERGY NUCLEAR OPERATIONS, INC. ) ) (Indian Point Nuclear Generating Units 2 and 3) ) ) March 28, 2...

Transcript of Advisory Committee on Reactor Safeguards Subcommittee on Human Factors Meeting, December 2, 2003, pages 1-143.

Official Transcript of Proceedin____NUCLEAR REGULATORY COMMISSIONTitle: Advisory Committee on Reactor SafeguardsSubcommittee on Human FactorsM..j7"0=0MIMC'..fx=-,;SmCarl;::.Docket Number:Location:(not applicable)Rockville, MarylandDate: Tuesday, December 2, 2003Work Order No...

Indian Point, Unit 2, Fuel Storage Building Single-Failure-Proof Gantry Crane.

- EntergyEntergy Nuclear NortheastIndian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 10511-0249Tel 914 734 6700Fred DacimoSite vice PresidentAdministrationJune 16, 2004Re: Indian Point, Unit No. 2Docket No. 50-247NL-04-011U.S. Nuclear Regulatory CommissionATTN...

Enclosure 1: Safety Evaluation Report (SER) for the USEC American Centrifuge Plant Feed and Withdrawal Amendment, SNM-2011, Amendment 1.

Enclosure 1 Safety Evaluation Report (SER) for the USEC American Centrifuge Plant Feed and Withdrawal Amendment SNM-2011, Amendment 1 1.0 GENERAL INFORMATION The design of the American Centrifuge Plant (ACP), located in Piketon, Ohio, was previously found to meet the appli...

Forwards SSER input for Section 13.5.2,including consideration of TMI Action Items I.C.1,I.C.7 & I.C.8 re ATWS & procedures.Program for operating & maint procedures acceptable.Item I.C.8 resolved.

f. ,#*D*.DTSTRTBUTTONDMBPSRB ReadingDHFS R/FDockot No. 50-397DLZiemannHBClaytonWCMiddletonRJUrbanHOV 17 1983RFroelichMEMORANDUM FOR: Thomas M. Novak, Assistant Directorfor LicensingDivision of LicensingFROM:William T. Russell, Deputy DirectorDivision of Human Factors SafetySUB...

mPower Design Specific Review Standard 7.0 Appendix D Rev. 1 Draft for Interim Use and Comment.

DRAFT for Interim Use and Comment mPowerTM -DSRS 7.0 APPD 7.0 APPD-1 U. S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD FOR mPowerTM iPWR DESIGN Appendix D References 1. ANSI/ASME NQA-1-1983, Quality Assurance Program Requirements for Nuclear Facilit...

July 23, 2019 FPRA FAQ Meeting Summary +jsh +MR.

August 8, 2019 MEMORANDUM TO: Mehdi Reisi-Fard, Acting Chief PRA Licensing Branch B Division of Risk Assessment Office of Nuclear Reactor Regulation FROM: Brian Metzger, Fire Protection Engineer /RA/ PRA Licensing Branch B Division of Risk Assessment Of...

Diablo Canyon Plant, License Amendment 135, Converts Current TS for DCPP to Improved TS.

N;11 -,VA Docket % UNITED STATES 0 NUCLEAR REGULATORY COMMISSION T-5-C-3 WASHINGTON, D.C. 20565-0001 May 28, 1999 Mr. Gregory M. Rueger -, Senior Vice President and General Manager Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant P.O. Box 3 Avila Beach, CA 93...

Comment (44) of Robert F. Stewart, on Behalf of U.S. Dept. of the Interior, on Supplemental Environmental Impact Statement for the Ross In-Situ Uranium Recovery Project in Crook County, Wyoming.

Gallagher, CarolSubject: FW: Ross ISR DSEIS, WY - DOI CommentsAttachments: Ross ISR DSEIS - DOI Comments.pdfFrom: Robert Stewart [mailto:robert f stewart(ýios.dloi.qov'lSent: Wednesday, May 08, 2013 10:22 AMTo: Bladey, CindyCc: Moore, JohariSubject: Ross ISR DSEIS, WY - DOI Co...

November 30, 2012 Category 2 Public Meeting Nuclear Regulatory Commission and Nuclear Energy Institute Presentation on Identification, Discussion, and Prioritization of Fire PRA Methods by Nuclear Energy Institute.

Identification, Discussion, and Prioritization of Fire PRA Prioritization of Fire PRAMethodsNRC Meeting on Methods for FPRAsNovember 30, 2012Proposed Process OverviewClarification (simple yes/no answer)?Application-specific for NFPA 805? YES YES805 FAQ ProcessNONO NONew FAQ Pr...

Topical Report APR1400-F-A-TR-12004(RO) Realistic Evaluation Methodology for Large-Break LOCA of APR1400 (CAREM)

1/31 Non-Proprietary 2/31 APR1400 Introduction  Request for additional information 1-7425 • Issue date: 03 / 10 / 2014 • 3 questions; Responses for all questions were provided. (MKD/NW-14-0007L, Apr. 10, 2014) / ML14100A671  Question #1; Provide a co...

Union of Concerned Scientists, Comments on "Station Blackout Risk Evaluation for Nuclear Power Plants (Draft)" dated January 2005.

En Union ofdConcernedScientistsCJMens and Sdentists for ENvironmental SoutdonsMarch 8, 2005Charles E. Ader, DirectorDivision of Risk Analysis and ApplicationsOffice of Nuclear Regulatory ResearchUnited States Nuclear Regulatory CommissionWashington, DC 20555-0001Dear Mr. Ader:...

Request for Additional Information Letter No. 449 Related to SRP Chapter 1 for Nuclear Innovation North America, LLC (NINA) Combined License Application.

August 18, 2014 Mr. Scott Head, Manager Regulatory Affairs Nuclear Innovation North America, LLC 122 West Way, Suite 405 Lake Jackson, TX 77566 SUBJECT: REQUEST FOR ADDITIONAL INFORMATION LETTER NO. 449 RELATED TO SRP CHAPTER 1 FOR NUCLEAR INNOVATION NORTH AMERICA, LL...

Response to Request for Additional Information Related to the Duane Arnold Energy Center License Renewal Application - Response to Requests for Additional Information on Implementation.

NExTeraENERGY?).Q,DUANEARNOLDNG-1 0-058010 CFR 54November23, 2010U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Duane Arnold Energy CenterDocket 50-331License No. DPR-49Response to Request for Additional Information Related to the Duane A...

Sky Testing Services, Inc.; Deficiency Request Letter dtd 9/6/2016; Control No. 591655.

9/6/2016 Mr. Hubert Florit, Corp. Radiation Safety Officer Sky Testing Services, Inc. 25 Kinkel Street Westbury, NY 11590 License No.: 31-35370-01 Docket No: 03038989 Control No: 591655 Mr. Hubert Florit, This refers to your application for a new license dated July 20,...

Integrated Decommissioning Improvement Plan Revision 3- FY2010 Knowledge Management and Other Improvement Tasks for Uranium Recovery Closure and Decommissioning.

June 8, 2010 MEMORANDUM TO: Larry W. Camper, Director Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs THRU: Keith I. McConnell, Deputy Director /RA/ Decommissioning...

Catawba, Units 1 and 2, License Amendment, Reflects Full Conversion from Current Technical Specifications to a Set of TS Based on NUREG-1431, "Standard Technical Specifications -- Westinghouse Plant," Revision 1.

UNITED STATES o NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 30, 1998 Mr. Gary R. Peterson Site Vice President Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, South Carolina 29745-9635 SUBJECT: ISSUANCE OF AMENDMENTS - CATAWBA NUC...

Task Order No. NRC-HQ-60-17-T-0006 Under Interagency Agreement No. NRC-HQ-60-17-D-0005.

INTERAGENCY AGREEMENT1. IAA NO. PAGE OF2. ORDER NO. 3. REQUISITION NO. 4. SOLICITATION NO.5. EFFECTIVE DATE 6. AWARD DATE 7. PERIOD OF PERFORMANCENRC-HQ-60-17-T-0006RES-17-042207/01/2017 07/19/2017 07/01/2017 TO 06/30/2022 15 18. SERVICING AGENCY 9. DELIVER TOPOCTEL...

OFFICIAL EXHIBIT - NRC000179-00-BD01 - Regulatory Guide 1.207, Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors (Mar. 2007).

The U.S. Nuclear Regulatory Commission (NRC) issues regulatory guides to describe and make available to the public methods that the NRC staffconsiders acceptable for use in implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating sp...

Communication Plan for the State-of-the-Art Reactor Consequence Analysis (Revision 5).

Communication Plan for theState-of-the-Art Reactor Consequence Analysis(Revision 5)OverviewThe State-of-the-Art Reactor Consequence Analysis (SOARCA) project involves the analyses ofsevere reactor accidents and the development of the best estimate of the offsite radiologicalhe...

Perspectives on Severe Accident Mitigation Alternatives for U.S. Plant License Renewal.

Perspectives on Severe Accident Mitigation Alternatives for U.S. Plant License Renewal Tina Ghosh U.S. Nuclear Regulatory Commission, Rockville, MD, USA Robert Palla U.S. Nuclear Regulatory Commission, Rockville, MD, USA Donald Helton U.S. Nuclear Regulatory Commissio...

Regulatory Guide 1.207, "Guidelines for Evaluating Fatigue Analyses Incorporating The Life Reduction of Metal Components Due to the Effects of LWR reactor Environments for New Reactors" (Formerly Draft Regulatory Guide DG-1144).

The U.S. Nuclear Regulatory Commission (NRC) issues regulatory guides to describe and make available to the public methods that the NRC staffconsiders acceptable for use in implementing specific parts of the agency’s regulations, techniques that the staff uses in evaluating sp...

Northwest Medical Isotopes, LLC - Request For Additional Information For Construction Permit Application Regarding Emergency Response Plan.

January 25, 2017 Ms. Carolyn C. Haass, Vice President Northwest Medical Isotopes, LLC 815 Northwest 9th Street, Suite 256 Corvallis, OR 97330 SUBJECT: NORTHWEST MEDICAL ISOTOPES, LLC – REQUEST FOR ADDITIONAL INFORMATION FOR CONSTRUCTION PERMIT APPLICATION REGARDING EME...

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 7 - Chapter 02 - Figure 2.5.2-325

Duke Energy FloridaLevy Nuclear PlantUnits 1 and 2Part 2, Final Safety Analysis ReportComparison of Hazard Computed in thisStudy to Results in NUREG-2115 for theCentral Illinois Demonstration SiteFIGURE 2.5.2-325 Rev 6 LNP COL 2.5-21.E-071.E-061.E-051.E-041.E-031.E-020 1 1 1 ...

Progress Energy Levy Units 1 and 2 COLA (Final Safety Analysis Report), Rev. 7 - Chapter 02 - Figure 2.5.2-329

Duke Energy FloridaLevy Nuclear PlantUnits 1 and 2Part 2, Final Safety Analysis ReportFIGURE 2.5.2-329 Rev 6Comparison of Hazard Computed in thisStudy to Results in NUREG-2115 for theManchester Demonstration SiteLNP COL 2.5-21.E-071.E-061.E-051.E-041.E-031.E-020 1 1 1 . 0Annu...