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The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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NRC Hybrid Workshop on Structural Materials: What Research for Beyond 80 Years?

On this page:ObjectivesMotivation & BackgroundWorkshop SessionsWorkshop Sessions Metallic MaterialsWorkshop Session- Civil StructuresNRC-NEA Cosponsored - Harvesting Concrete and ComponentsContact InformationLocation / Date: NRC HQ, TWFN Auditorium, Rockville, MD, October ...

2012/03/26 STP COL - NINA presentation

1PMSTPCOL PEmailsFrom: Chappell, Coley [ccchappell@STPEGS.COM]Sent: Monday, March 26, 2012 5:56 PMTo: Misenhimer, DavidSubject: NINA presentationAttachments: 3-27-2012 STP 3&4 Fukushima Presentation Final.pdfDavid, A copy of the NINA presentation for 3/27/2012 is attached. I...

Susquehanna Electric Station - Technical Requirements Manual Unit 2.

Feb. 23, 2012Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2012-9980USER INFORMATION:GERLACH*ROSE M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRAN5MTTTAT, TNFORMATTONmTO: GERLACH*ROSE M 02/23/2012LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL C...

1036 - R109P - APWR Intro to Diffs - 03 - RCS Text.

Rev 0710 3-i USNRC HRTD TABLE OF CONTENTS 3.0 REACTOR COOLANT SYSTEM ..................................................................... 3-1 3.1 System Description .................................................................................. 3-1 3.2 Component Descri...

McGuire - Technical Specification Bases Updates.

PRIORITY NormalDISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TOTHE TRANSMITTAL SIGNATURE UNLESS RECIPIENT ISOTHERWISE IDENTIFIED BELOW1) 01749 L C GIBBY - MG01VP2) 01820J R ELKINS- ECO813) 02388 BOB SCHOMAKER LYNCHBG, VA4) 02532 RESIDENT NRC INSPECTOR MG01VP5) 02546 WC LIBRARY ...

Susquehanna Steam Electric Station Technical Requirements Manual Unit 2.

Dec. 01, 2011Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2011-66879USER INFORMATION:GERLACH*ROSE M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSE M 12/01/2011LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CE...

Biweekly Sholly Federal Register Notice - FR Publication Date: July 10, 2012.

[7590-01-P] NUCLEAR REGULATORY COMMISSION [NRC-2012-0161] Biweekly Notice Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations Background Pursuant to Section 189a. (2) of the Atomic Energy Act of 195...

IR 05000348-12-003; and 05000364-12-003, on 04/01/2012 through 06/30/2012; Joseph M. Farley; Problem Identification and Resolution, Component Design Basis Inspection, Inservice Inspection Activities, and Radiation Monitoring Instrumentation.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 July 20, 2012 Tom A. Lynch Vice President - Farley Southern Nuclear Operating Company, Inc. 7388 North State Highway 95 Columbia, AL 36319 SUBJEC...

Fort Calhoun Station Unit No. 1 License Amendment Request, "Revisions of Technical Specifications Table 1-1 and Section 4.0."

Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 November 23,2004 LIC-04-0 1 17 U.S. Nuclear Regulatory Commission ATTN.: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285 SUBJECT: Fort Calhoun Station Unit No. 1 License Ame...

Confirmatory Action Letter Response - Management & Human Performance Root Cause Analysis Report on Failure to Identify Reactor Pressure Vessel Head Degradation.

FENOC F O5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Lew W Myers 419-321-7599 Chief Operating Officer Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 1-1286 August 21, 2002 Mr. J. E. Dyer, Administrator United...

Safety Analysis Report, GNS 11, Summary.

I IGNSGNS Gesellschaft fur Nuklear-Service mbH i i. 2I .1 ..6 S:o'DR I:OCK 07 :1.Zweigertstr. 28 - 30 D-4300 Essen Telefon 02 01/72 20-0 Telefax 02 01/72 20-181SAFETY ANALYSIS REPORT GNS 11 - Summary -NSAFETY ANALYSIS REPORT GNS 11 - Sumuary -Report No.: Date:GNS B 40/86 E Oct...

Revision to Technical Specification 3.3.1, "Reactor Trip System Instrumentation," and Technical Specification 3.3.2, "Engineered Safety Feature Actuation System Instrumentation"

W0LF CREEK 'NUCLEAR OPERATING CORPORATION Richard A. Muench Vice President Engineering & Information Services MAR 2 2 2001 ET 01-0012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station: P1-137 Washington, D. C. 20555 Subject: Docket No. 50-482: Revisi...

RHRSW System

RHRSW System 3.7.13.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) SystemLCO 3.7.1 APPLICABILITY:Two RHRSW subsystems shall be OPERABLE. MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHRSW pump A.1 Restore RHRSW pump to 30 days ...

Vermont Yankee - Issuance of Amendment 83 to Facility Operating License DPR-28, authorizing changes to the Technical Specifications.

'aOctober 9, 1984 Docket No. 50-271 Mr. R. W. Capstick Licensing Engineer Vermont Yankee Nuclear Power Corporation 1671 Worcester Road Framingham, Massachusetts 01701 Dear Mr. Capstick: The Commission has issued the enclosed Amendment No. 83 to Facility Operating License No. D...

Catawba, Units 1 and 2 - Response to RAI Regarding Proposed Technical Specifications and Bases Amendment Involving Ventilation Systems.

. \X Ph DukePrPowereA Duke Energy CompanyD.M. JAMILVice PresidentDuke PowerCatawba Nuclear Station4800 Concord Rd. / CNO1 VPYork, SC 29745-9635803 831 4251803 831 3221 faxNovember 13, 2003U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555S...

Peach Bottom, Units 2 and 3, License Amendments 178 and 181 re Revised Surveillance for Logic System Functional Tests.

ov,,pjk REGU4 I.-UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205W-0001lbJuly 15, 1993Docket Nos. 50-277 and 50-278 Mr. George A. Hunger, Jr. Director-Licensing, MC 52A-5 Philadelphia Electric Company Nuclear Group Headquarters Correspondence Control Desk P.O....

Manual #91, consisting of Revised EAL Basis documents Index ( Revision 7), Introduction ( Revision 1), EBD-A Page 1 of 26, EBD-F (Revision 3).

ALLIANT ENERGY DUANE ARNOLD ENERGY CENTER TRANSMITTAL/ACKNOWLEDGMENT MEMORANDUMManual #91 NRC-NRR- Document Control Desk Washington, DC DATE: _November 20, 2000 Emergency Action Level Please make the following changes to your Emergency Action Level Basis Document.MANUAL CONTEN...

Response to NRC Bulletin 2002-01- Request for Additional Information Regarding Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.

PSEG Nuclear LLC P.O Box 236, Hancocks Bndge, New Jersey 08038-0236 JAN 2 4 2003 LR-N03-0023 0 PSEG Nuclear LLC United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 RESPONSE TO NRC BULLETIN 2002-01 - REQUEST FOR ADDITIONAL INFORMATION REGARDIN...

Prairie Island Emergency Plan Implementing Procedures.

NMC Committed to Nuclear Excellence  Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC 1717 Wakonade Dr. East a Welch MN 55089 February 27, 2003 L-PI-03-018 10 CFR 50.4 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRA...

Enclosure - SDP Phase 3 Analysis.

Phase 3 Risk Assessment of Loss of Inventory Event at Oconee Probabilistic Risk Assessment (PRA) Analyst: Jeff Mitman, Senior Reliability and Risk Analyst, NRR/DRA/APOB Probabilistic Risk Assessment (PRA) Analyst: Antonios Zoulis, Reliability and Risk Anal...

Indian Point, Units 2 and 3 - License Amendment Request to Adopt TSTF-448, Revision 3, Regarding Control Room Envelope Habitability.

SEntergy-Enteray Nuclear NortheastIndian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, NY 10511-0249Tel 914 734 6700.I.E. PollockSite Vice PresidentIndian Point Energy CenterDecember 18, 2007.Re: Indian Point Units 2 and 3Docket Nos. 50ý247 and 50-286NL-07-101U.S. ...

Response to Portion of NRC Request for Additional Information Letter No. 111 Related to ESBWR Design Certification Application - Auxiliary Systems - RAI Numbers 9.1-9 S02, 9.1-18 S02, and 9.1-41 S01.

HITACHI GE Hitachi Nuclear EnergyJames C. Kin;eyVice President, ESBWR LicensingPO Box 780 MIC A-55Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinseypge.comMFN 07-646 Docket No. 52-010December 7, 2007U.S. Nuclear Regulatory CommissionDocument Control DeskWashing...