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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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ESBWR Chapter 14 Open Items.

June 25, 2008 Mr. Robert E. Brown Senior Vice President, Regulatory Affairs GE Hitachi Nuclear Energy 3901 Castle Hayne Road MC A-45 Wilmington, NC 28401 SUBJECT: ECONOMIC SIMPLIFIED BOILING WATER REACTOR (ESBWR) CHAPTER 14 OPEN ITEMS Dear Mr. Brown: As you are aware, ...

Final Precursor Analysis - Brunswick 2 (LER 324/06-001).

Final Precursor Analysis Accident Sequence Precursor Program – Office of Nuclear Regulatory Research Brunswick Unit 2 Reactor Trip and Loss of Offsite Power Caused by Line-to-Ground Fault on the Startup Auxiliary Transformer EVENT DATE: 11/01/2006 LER: 324/2006-001 IR: 50-...

Turkey Point Initial Exam 2009-301 Final SRO Written Examination.

ES-401, Rev. 9 Site-Specific SRO Written Examination Cover Sheet Form ES-401-8 U.S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name: Date: 3/18/09 Facility/Unit: Turkey Point 3 & 4 Region:1 IIX III IV Reactor Type: WX CE BW GE Sta...

Calvert Cliffs Post Exam Comments.

Calvert Cliffs Post Exam Comments In accordance with the guidance provided in NUREG 1021, “Operating Licensing Examination Standards for Power Reactors” (Revision 9 Supp 1), ES-403 “Grading Initial Site-Specific Written Examinations” justification for modification to the orig...

AREVA Design Control Document Rev. 1 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.2.3 Safety Injection System and Residual Heat Removal System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Tier 1 Revision 1 Page 2.2-65 2.2.3 Safety Injection System and Residual Heat Removal System 1.0 Description The safety injection system and residual heat removal system (SIS/RHRS) is a safety-related system. The SIS/RHRS has four divi...

Oyster Creek, License Amendment Request Increase Safety Valve As-Found Setpoint Tolerance from ±1% to ±3%.

AmerGen SMAmerGen Energy Company, LLC www.exeloncorp.comn An Exelon Company200 Exelon WayKennett Square, PA 1934810 CFR 50.902130-05-20233December 2, 2005U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Oyster Creek Generating StationFacil...

Request for Additional Information Letter No. 101 Related to ESBWR Design Certification Application.

June 21, 2007Mr. Robert E. BrownSenior Vice President, Regulatory AffairsGE-Hitachi Nuclear Energy Americas LLC3901 Castle Hayne Rd MC A-45Wilmington NC 28401SUBJECT: REQUEST FOR ADDITIONAL INFORMATION LETTER NO. 101 RELATED TOESBWR DESIGN CERTIFICATION APPLICATION Dear Mr. ...

Westinghouse AP1000 Design Control Document Rev. 16 - Tier 2 Chapter 19 - Probabilistic Risk Assessment - Sections 19.55 to 19.58

19. Probabilistic Risk Assessment AP1000 Design Control Document Tier 2 Material 19.55-1 Revision 9 19.55 Seismic Margin Analysis 19.55.1 Introduction In accordance with Section II.N, Site-Specific Probabilistic Risk Assessments and Analysis of External Events, of SECY-93...

Susquehanna, Units 1 and 2, Technical Specifications Bases Unit 2 Manual, TSB2, Revision 72.

May. 11, 2006Page1 of 2MANUAL HARD COPY DISTRIBUTIONDOCUMENT TRANSMITTAL 2006-23420USER INFORMATION:GERLACH*ROSE M EMPL#:028401 CA#: 0363Address: NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:TO: GERLACH*ROSE M 05/11/2006LOCATION: USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CE...

Sequoyah, Units 1 & 2, Technical Specifications (TS) Change 06-03 "Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes - Request for Information (RAI) No. 2" (TAC Nos. MD2621 & MD2622).

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000August 14, 2007TVA-SQN-TS-06-03 10 CFR 50.90U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D. C. 20555-0001Gentlemen:In the Matter ofTennessee Valley Authority))Docket ...

General Electric Company - ESBWR 26A6642AT Revision 02 to Design Control Document Tier 2, Advance Copy.

26A6642AT Rev. 02 ESBWR Design Control Document/Tier 2 6.3-18 6.3.2.9.4 Testing and Inspection Requirements Refer to Subsection 5.4.6.4. 6.3.2.9.5 Instrumentation Requirements Refer to Subsection 5.4.6.5 and 7.4.4. 6.3.2.10 Standby Liquid Control System 6.3.2.10.1 Desig...

5.4.13 - 2007 Highlighted Working File (Enclosure).

[Month] 2007USNRC STANDARD REVIEW PLANThis Standard Review Plan, NUREG-0800, has been prepared to establish criteria that the U.S. Nuclear Regulatory Commission staff responsible for the review of applications to construct and operate nuclear power plants intends to use in eva...

2006/08/03-EMAIL: (PA) FYI: Forwarding Attachment 1 & Attachments 3-7 on Audit Report TLAA Sections.

James Davis - FYI: Forwarding Attachment 1 and Attachments 3 - 7 on Audit Report TLAA Sections. Page 1 1From: James MedoffTo: James Davis; Peter WenDate: 08/03/2006 11:33:55 AMSubject: FYI: Forwarding Attachment 1 and Attachments 3 - 7 on Audit Report TLAA Sections.Jim, Peter:...

Transmittal of Survey Packages in Support of Big Rock Point Phased License Termination.

Consurs EneWjA CMS Energy Company Big Rock Point Nuclear Plant10269 US-31 NorthCharlevoix, MI 49720Kurt A. HaasGeneral ManagerOctober 24, 2006U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555-0001DOCKETS 50-155 AND 72-043 - LICENSE DPR-6 - BIG ROCK PO...

Perry Power Plant, Corrections To Amendment 67, Table 4.3.2.1-1, Designating Main Steam Line Radiation Monitor As An Instrument Common To RPS Instrumentation Should Not Have Been Included. Additionally Footnote Should Not Have Referenced 2b.

Mr. Robert A. Stratm Vice President Nucle, - Perry Centerior Service Company P. 0. Box 97, A200 .Perry, OH 44081January 24, 1995SUBJECT: CORRECTIONS TO AMENDMENT NO. 67 TO FACILITY OPERATING LICENSE NO. NPF-58 - PERRY NUCLEAR POWER PLANT, UNIT NO. I (TAC NO. M84057) Dear Mr. ...

License Amendment Request for Administrative Revisions to Fort Calhoun Station, Unit No. 1 Technical Specifications.

Fort Calhoun Station PO. Box 550 Fort Calhoun, NE 68023 December 20,2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Reference: Docket No. 50-285 SUBJECT: License Amendment Request, "Administrative Revisions to Fort Calhoun Station, Uni...

Safety Evaluation of Relief Requests for the Fourth 10-Year Interval of the Inservice Testing Program for Salem Nuclear Generating Station, Unit 1 & 2 (TAC ME0322, ME0323, ME0324, ME0325, ME0326, ME0327, ME0328, ME0329, ME0330, ME0331, ME033).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 11, 2009 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear P.O. Box 236, N09 Hancocks Bridge, NJ 08038 SUBJECT: SAFETY EVALUATION OF RELIEF REQUESTS FOR THE FOURTH 10-YEAR INTERVA...

H.B. Robinson, Unit 2, License Amendment 17, Incorporates Into the TS Changes to Administrative Controls and Relocates Environmental Reporting Requirements to Appendix B.

JAN 1 9 1976 Docket No.: 50-261 Carolina Power & Light Company ATTN: Mr. J. A. Jones Senior vice President 336 Fayetteville Street Raleigh, North Carolina 27602 Gentlemen: The Commission has issued the enclosed Amendment No. 17 to Facility Operating License No. DPR-23 for the ...

Joseph M. Farley Nuclear Plant, Ltr forwarding Revision 48 of PNP-0-EIP-9.0 - Emergency Classification & Actions.

Southern Nuclear Operating Company, Inc. Post Office Drawer 470 Ashford, Alabama 36312 Date: November 5, 2001FNP-'127-EP-DCDirector, Office of NRC AUt: Document Control Desk C/O Jim McKnight US Nuclear Regulatory Commission Washington, DC 20555 Dear Sir: Attached is Revision ...

Browns Ferry, Units 1, 2, and 3, License Amendments, changing Technical Specifications to allow extension of surveillance intervals, and clarify various instrumentation requirements.

AUG 1 q 1984Docket Nos. 50-259/260/296 Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401 Dear Mr. Parris: The Commission has issued the enclosed Amendment Nos. 108, 102 and 75 to Facility Operating Licens...

Millstone Nuclear Power Station, Unit 2, License Amendment, Extension of Implementation Dates for Liquid & Gaseous Release Limits & Correction of Typographical Errors.

D__'RIBUTION: ACRS (16) D--'kbt NRC PDR Local PDR ORB-3 Reading KRGoller/TJCarter FEB 2 1976 CParrish DJaffe Docket No. 50-336 Attorney, OELD OI&E (3) BJones (4) BScharf (15) Northeast Nuclear Energy Company JMcGough ATTN: Mr. D. C. Switzer JSaltzman, OAI President NDube P. 0...

Prairie Island Generating Plant - Emergency Plan Implementing Procedures - F3.

Committed to Nuclear ExcellenceNuclear Management Company, LLC Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East * Welch MN 55089April 17, 2002 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLAN...

Oconee Nuclear Station - Technical Specification Bases (TSB) Change.

SDuke rEnergy. W. R. McCollum, Jr. Vice PresidentDuke Energy Oconee Nuclear Station 7800 Rochester Highway Seneca, SC 29672 (864) 885-3107 OFFICE (864) 885-3564 FAXApril 29, 2002 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control DeskSubj...

Draft/Final - Section C Operating (Final used Spare Scenario in place of #2).

SCENARIO TITLE: SCENARIO NUMBER: EFFECTIVE DATE: EXPECTED DURATION: REVISION NUMBER: PROGRAM:02-01 NRC EXAMINATION SCENARIO GUIDE1 1.5 Hours 00 L.O. REQUAL SX INITIAL LICENSE OTHERREVISION SUMMARY:Page 1 of 14Enabling Objectives A.B. M#AJOR EVNS A. Place 3rd Reactor Feed Pump...

IR 05000341-98-002, on 01/14-15, 01/20-02/06 & 09-13/1998, Detroit Edison, Enrico Fermi, Unit 2.

U.S. NUCLEAR REGULATORY COMMISSIONREGION IIIDocket No:License No:50-341NPF-43Report No:Licensee:Facility:Location:Dates:Inspectors:50-341/98002(DRS)Detroit Edison Company (DECo)Enrico Fermi, Unit 26400 N. Dixie HwyNewport, MI 48166January 14-15,1998 (On-site)January 20 through...