1
On August 3, 2010, the Offices
of Nuclear Regulatory Research
(RES) and Federal and State
Materials and Environmental
Management Programs (FSME)
hosted a 3-day workshop on
Engineered Barrier Performance
Related to Low-Level Radioactive
Waste, Decommissioning, and ...
. . . . .SnS. m. nUNITED STATES OF' AMERICANUCLEAR REGULATORY COMMISSIONATOMIC SAFETY AND LICENSING BOARD,50-E9[4)["df?IN THE MATTER OF 5 DOCKET NOS.I 50-499 d1HOUSTON LIGHTING AND 5POWER COMPANY, ET AL. 5'84 00T 18 #1 :41(SOUTH TEXAS PROJECT, iUNITS 1 AND 2)5t.FJL5_t --:ius ....
- . . _ .. . ..|,,e 1hU.S. Department of Energyl" "GrandJunction Office',*2597 B 3/4 Road;Grand Junction, CO 81503JUN 181997Mr. Joseph J. Holonich, ChiefUranium Recovery BranchDivision of Waste ManagementOffice of Nuclear Material Safety and Safeguards)Mail Stop T7J-9U. S. Nuc...
10 CFR 72.212(b)(2),4h4lm A subsidiary of Pinnacle West Capital CorporationThomas N. Weber Mail Station 7636Palo Verde Nuclear Department Leader, Tel. 623-393-5764 PO Box 52034Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034102-06482-TNW/CJSMa...
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _DO.UNITED STATES OF AMERICANUCLEAR REGULATORY COMMISSIONBEFORE THE ATOMIC SAFETY AND LICENSING BOARD DOLMETED'JS N.'t cIn the Matter of:Docket Nos. 50-445 C: 50-446 5 AUG 19 P12:24TEXAS UTILITIES ELECTRIC :COMPANY, et al.:GF...
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION IV
1600 E. LAMAR BLVD
ARLINGTON, TX 76011-4511
March 4, 2015
Mr. Eric W. Olson, Site Vice President
Entergy Operations, Inc.
River Bend Station
5485 U.S. Highway 61N
St. Francisville, LA 70775
SUBJECT:...
-April 14,2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 WECTEC LLC 128 South Tryon Street Charlotte, NC 28202 Tel: +1 704 343 7500 10 CFR 21.21 SUBJECT: INTERIM 10 CFR PART 21 REPORT REGARDING SHIELD BUILDING WALL PANEL DIMENSION...
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402-2801March 18, 2011U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555-0001In the Matter of )Tennessee Valley Authority )Docket Nos. 50-39150-43850-43952-01452-015Projec...
On this page:Publication InformationAbstractDownload complete documentNUREG/CR-5694 (PDF - 10.5 MB)Publication InformationManuscript Completed: May 1999 Date Published: June 1999Prepared by: M.H. Young*, P.J. Wierenga, A.W. Warrick, L.L. Hofmann S.A. Musil, M. Yao, C.J. Mai, Z...
1PMSTPCOL PEmailsFrom: Govan, TekiaSent: Wednesday, June 03, 2009 5:08 PMTo: 'Head, Scott'Cc: STPCOL; 'Bense, Richard'Subject: REQUEST FOR ADDITIONAL INFORMATION LETTER No. 116 and 117Attachments: ML091540452.pdf; ML091540472.pdfAttached you will find the publically available ...
_'} SAFEGUARDS INFORMATIONThe Lightcompanyg, g, g; g p4 South Texas Project Electric Generating StationP. O. Box 289 Wadsworth Texas 77483June 29, 1995 4ST-HL-AE-5116 IFile No.: G09.0910CFR73.5510CFR50.54(p)U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWas...
Initial Test Program g(ITP) (ITP)November 20, 2013Tony SpringSNC ITP DirectorTopics Construction Updatep ITP Objectives Testing Phases (how the program is organized) Implementation Sequence Test Phase/Procedure Overview2Vogtle Unit 3 Turbine BuildingVogtle Unit 3 Nuclear ...
Emergency Core Cooling Systems 6.3-1STP 3 & 4 Final Safety Analysis Report 6.3 Emergency Core Cooling SystemsThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the following departures a...
Computer Programs Used in the Design of Components, Equipment and Structures 3D-1/2STP 3 & 4 Final Safety Analysis Report Tier 23D Computer Programs Used in the Design of Components, Equipment and StructuresThe information in this appendix of the reference ABWR DCD, including...
PRA as a Design Tool 19.7-1STP 3 & 4 Final Safety Analysis Report Tier 219.7 PRA as a Design ToolThe information in this section of the reference ABWR DCD, including all subsections, is incorporated by reference with the following departures. STD DEP T1 3.4-1STD DEP 19.7-1STP...
Increase in Reactor Coolant Inventory 15.5-1/2STP 3 & 4 Final Safety Analysis Report Tier 215.5 Increase in Reactor Coolant InventoryThe information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with no...
Control Rod Licensing Acceptance Criteria 4C-1/2STP 3 & 4 Final Safety Analysis Report Tier 2 4C Control Rod Licensing Acceptance CriteriaThe information in this appendix of the reference ABWR DCD, including all subsections, is incorporated by reference with the following sta...
Requirements for Further Technical Information 1.5-1/2STP 3 & 4 Final Safety Analysis Report Tier 21.5 Requirements for Further Technical InformationThe information in this section of the reference ABWR DCD is incorporated by reference with no departures or supplements.Rev. 13
Fuel Licensing Acceptance Criteria 4B-1/2STP 3 & 4 Final Safety Analysis Report Tier 2 4B Fuel Licensing Acceptance CriteriaThe information in this appendix of the reference ABWR DCD, including all subsections and tables, is incorporated by reference with no departures or sup...
Method of Compliance For Regulatory Guide 1.150 5A-1/2STP 3 & 4 Final Safety Analysis Report Tier 25A Method of Compliance For Regulatory Guide 1.150The information in this appendix of the reference ABWR DCD, including all subsections and figures, is deleted (STD DEP 5A-1).Re...
Systems Required for Safe Shutdown 7.4-1STP 3 & 4 Final Safety Analysis Report Tier 27.4 Systems Required for Safe ShutdownThe information in this section of the reference ABWR DCD, including all subsections, tables and figures, is incorporated by reference with the following...
Secondary Containment and Divisional Separation Zones – Barrier Considerations 3.13-1/2STP 3 & 4 Final Safety Analysis Report Tier 23.13 Secondary Containment and Divisional Separation Zones – Barrier ConsiderationsThe information in this section of the reference ABWR DCD, in...