Report a Safety Concern
Search

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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Watts Bar 2008-301 Draft Simulator Scenarios.

6oe 1 i riôAppendix D Scenario Outline Form ES-D-1]Facility: Watts Bar Scenario No.: 1 Op Test No.: 1Examiners:Operators:Initial Conditions: 45% Power BOL.1A Containment Spray Pump OOS for maintenance.Turnover: The Plant is stable at 45% power following a forced outage to repa...

Proposed,revised TS Table 4.1-1, "Min Frequencies for Checks,Calibrs & Tests of Instrument Channels."

Table 4.1-1 Minimum Freauencies for Checks. Calibrations and Tests of Instrument ChannelsChannelOcj ;Do 00 00O 0 r3 010 Or's 0010. Rod Position Bank Counters 11. Steam Generator Level 12. Charging Flow 13. Residual Heat Removal Pump Flow 14. Boric Acid Tank Level 15. Refueling...

Partial Response to NRC Request for Additional Information Letter No. 362 Related to ESBWR Design Certification Application Quality Assurance - RAI Numbers 17.4-23 S02 and 17.4-55.

MFN 09-560 Docket No. 52-010 August 23, 2009 U.S. Nuclear Regulatory Commission 11555 Rockville Pike Document Control Desk Rockville, MD 20852 Subject: Partial Response to NRC Request for Additional Information Letter No. 362 Related to ESBWR Design Certificatio...

'IJames S. Baumstark Vice President Nuclear EngineeringConsolidated Edison Company of New York. Inc. Indian Point 2 Station Broadway & Blealdey Avenue Buchanan, New York 10511Internet: baumstarkj@coned.corn Telephone: (914) 734-5354 Cellular (914) 391-9005 Pager-. (917) 457-9...

Cooper, Technical Specification Bases Changes.

Nebraska Public Power DistrictAlways these when you need usNLS2003098September 5, 2003U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555-0001Subject: Technical Specification Bases ChangesCooper Nuclear StationNRC Docket No. 50-298, DPR-46...

Modular Accident Analysis Program for CANDU Reactors.

MODULAR ACCIDENT ANALYSIS PROGRAM FOR CANDU REACTORS C. BLAHNIK: C.S. KIM: S. NIJHAWAN'. R. THURAISINGHAM Ontario Hydro. 700 University Avenue. Toronto. Ontario. M5G IX6 "MIR Consulting Inc. Halifax. N.S. B3H 3P2Abstract MAAP-CANDU is an integrated computer code for the best e...

Final - RO & SRO Written

2LOT4 NRC Written ExamExamination Outline Cross-reference: Level RO SRO Tier # 2 2 Group # 1 1 K/A # 001 K5.09 Importance Rating 3.5 3.7 Knowledge of the following operational implications as they apply to the CRDS: Relationships between reactivity due to boron and reactivity ...

Draft - Outlines.

ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: FENOC BVPS Unit 2 Date of Exam: 12/2002 Exam Level: SRO K/A Category Point Point Tier Group K K K K K K A A A A G Total 1 2 3 4 5 6 1 2 3 4 * 1 2 2 5 5 7 3 24 Emergency & 2 0 0 0 7 6 3 16 Abnormal Plant 3 1 0 00 1 1 3 ...

Vogtle Electric Generating Plant, Report of Facility Changes, Tests & Experiments.

JDon E. GrissetteVice PresidentSouthern NuclearOperating Company, Inc.40 Inverness Center ParkwayPost Office Box 1295Birmingham, Alabama 35201Tel 205.992.6474Fax 205.992.0341November 15, 2004SOUTHERN ANCOMPANYEnergy to Serve YourWorld'NL-04-2207 Docket Nos.: 50-42450-425U. S. ...

Waterford - INIT EXAM - 11/2006 - Draft Outlines.

ES-401 Record of Rejected K/As Form ES-401-4 Waterford 3 11/10/2006 Tier / Group Randomly Selected K/A Reason for Rejection 1/2 RO 003/AK3.03 Knowledge of the reasons for the following responses as they apply to the Dropped Contro...

AREVA Design Control Document Rev. 0 - Tier 2 Chapter 06 - Engineered Safety Features - Section 6.3 Emergency Core Cooling System

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 0 Page 6.3-16.3 Emergency Core Cooling SystemThe safety injection system (SIS) provides emergency core cooling for the U.S. EPR. Four supply and return trains comprise the system, one for each of the reactor coolant syst...

Response to NRC Request for Additional Information Letter No. 51 Related to ESBWR Design Certification Application - Classification of Structures, Systems and Components - RAI Numbers 3.2.1 Through 3.2-62.

GE EnergyDavid H. Hinds Manager. ESBWR PO Box 780 M/C L60 Wilmington, NC 28402-0780 USA T 910 675 6363 F 910 362 6363 david.hinds@ge.comMFN 06-308 Docket No. 52-010September 8, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001Subject: Re...

Evaluation of Krypton 85 Contents for Transportation in the Model No. 6400 Packaging.

9Revision 1EVAWATION OF KRYPTON 85 CONTENTS FOR TRANSPORTATION IN THE MODEL NO. 6400 PACKAGINGIDAHO NATIONAL ENGINEERING LABORATORY Managed by the U.S. Department of EnergyPrepared by: Westinghouse Idaho Nuclear Co., Inc. March 1988 Contracting to the U.S. Department of Energ...

E. I. Hatch, Unit 2, Version 1.0, "Pressure Test Section Fourth Ten-Year Examination Plan."

SOUTHERN NUCLEAR OPERATING COMPANY MATERIALS AND INSPECTION SERVICES PRESSURE TEST SECTION FOURTH TEN-YEAR EXAMINATION PLAN E. I. HATCH NUCLEAR PLANT UNIT 2 SNC PREP'D 1 REV'D I APPV. 1 HNP IS1 APPROVAL Written By: SNC-M&lS De artment VER 1 .O DATE 811 0106 DESCRIPTION 4"' Int...

Enclosure: Safety Evaluation Report.

SAFETY EVALAUTION REPORT Model No. TN-BGC1 Package French Certificate of Approval No. F/313/B(U)F-96, Revision Iak Docket No. 71-3034 SUMMARY By letter dated February 20, 2009, the U.S. Department of Transportation (DOT) requested that the Nuclear Regulatory Commission (NR...

IR 05000454-07-002; 05000455-007-002; on 01/01/2007-03/31/2007; Byron Station, Units 1 and 2; Equipment Alignment and Fire Protection.

May 15, 2007Mr. Christopher M. CranePresident and Chief Nuclear OfficerExelon NuclearExelon Generation Company, LLC4300 Winfield RoadWarrenville, IL 60555SUBJECT: BYRON STATION, UNITS 1 AND 2 NRC INTEGRATED INSPECTIONREPORT 05000454/2007002; 05000455/2007002Dear Mr. Crane: O...

IR 05000338-05-007, IR 05000339-05-007, on 03/21-25/2005 & 04/11-15-2005, North Anna Power Station, Units 1 and 2; Safety System Design and Performance Capability Inspection.

May 10, 2005Virginia Electric and Power CompanyATTN: Mr. David A. ChristianSenior Vice President and Chief Nuclear OfficerInnsbrook Technical Center5000 Dominion BoulevardGlen Allen, VA 23060 - 6711SUBJECT: NORTH ANNA POWER STATION - NRC SAFETY SYSTEM DESIGN ANDPERFORMANCE ...

Final Outlines (Folder 3)

ES-401 BWR Examination Outline Form ES-401-1 11 Facilitv: Susauehanna Steam Electric Station Date of Exam: 12 to 22 December 2005 Note: 1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., exce...

IR 05000247-08-006 and 05000286-08-006 on 01/28/20080 - 02/01,11-14/08, 03/31/ - 04/02/08, 6/02-06, 18/08 for Indian Point, Units 2 and 3.

August 1, 2008 Mr. Joseph Pollock Site Vice President Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUBJECT: INDIAN POINT NUCLEAR GENERATING UNITS 2 AND 3 - NRC LICENSE RENEWAL INSPECTION REPORT 05000...

Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report, Amendment 92, Section 6.3 Emergency Core Cooling System - 6.8 Air Return Fans.

Table of Contents 6-iWATTS BAR WBNP-76TABLE OF CONTENTSSection Title Page6.3 EMERGENCY CORE COOLING SYSTEM 6.3-16.3.1 Design Bases 6.3-16.3.1.1 Range of Coolant Ruptures and Leaks 6.3-16.3.1.2 Fission Product Decay Heat 6.3-26.3.1.3 Reactivity Required for Cold Shutdown 6.3-26...

Rev. 1 to Calculation DRE02-0036, "Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms."

ATTACHMENT 4Calculation DRE02-0036, "Re-analysis of Fuel Handling Accident (FHA)Using Alternative Source Terms," Revision I/ICC-AA-309- 1001Revision 2ATTACEDIDNT 1DesLzn Analysis Cover SbeetDesign Analysis (Major Revision) i Last Page No. * 20! At. F-1Analysis No.:-' DRE024036...

Sequoyah, Units 1 & 2, License Amendments 309 and 298 Regarding Changes to Cyclic and Transient Limits with Design Features Revision (TS 05-02).

August 2, 2006Mr. Karl W. SingerChief Nuclear Officer and Executive Vice President Tennessee Valley Authority6A Lookout Place1101 Market StreetChattanooga, TN 37402-2801SUBJECT: SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 — ISSUANCE OFAMENDMENTS REGARDING TECHNICAL SPECIFICATI...

General Electric Co., RAI Regarding ESBWR Design Certification Application.

July 5, 2006Mr. David H. Hinds, Manager, ESBWRGeneral Electric CompanyP.O. Box 780, M/C L60Wilmington, NC 28402-0780SUBJECT: REQUEST FOR ADDITIONAL INFORMATION LETTER NO. 40 RELATED TOESBWR DESIGN CERTIFICATION APPLICATION Dear Mr. Hinds:By letter dated August 24, 2005, Gener...

Redacted Attachment 4, Drawing C-110-B-57922-0002, Sheet, Non-Proprietary.

I& L..-)40-08Attachment 4LiX-30 Consolidated SAR - Public Rev - I.- Ociober 210074.0 CONTAINMENT4.1 Description of Containment SystemThe UX-30 is designed for use in conjunction with a standard 30-inch UF6 cylinder such as themodels 30B or 30C described *in ANSI N14.1, Packagi...

Oconee, Units 1, 2 & 3 - Technical Specification Bases (TSB) Change.

T. PRESTON GILLESPIE, Jr.,Vice PresidentEnue r g Oconee Nuclear StationDuke EnergyONOl VP / 7800 Rochester Hwy.Seneca, SC 29672864-873-4478864-873-4208 faxT. Gillespie@duke-energy. comNovember 3, 2010U. S. Nuclear Regulatory CommissionWashington, D. C. 20555Attention: Document...