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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Donald C. Cook Nuclear Plant, Unit 2 - Letter, Public Notice of Application for Exigent Amendment to Facility Operating License (TAC No. ME3129).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 27, 2010 Mr. Joseph N. Jensen Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 SUBJECT: DONALD C. COOK NU...

Rev 15 to Sys Operating Procedure 4.2.1, "RHR Sys Operation."

All pages Rev. 15INDIAN POINT STATIONUNIT 2SYSTEM OPERATING PROCEDURE 4.2.1RESIDUAL HEAT REMOVAL SYSTEM OPERATIONWritten bySNSC Review Mtg. No./ Date Approved by / Date Effective DateSB;7i o 00047 PDR P R PREV. 15I ISOP 4.2.1 Rev. 15 RESIDUAL HEAT REMOVAL SYSTEM OPERATION 1 PR...

Decision in Case 72-2177 granting HK Brooks petition for summary reversal of Commission 721026 order granting CP extension.Petitioners must be granted opportunity for hearing.

* S A 1*'No. 72-2177HARRIET K. BROOKS, ET AL, PetitionersTIE ATOMIC ENERGY COMMISSION AND UNITED STATES OF 1-U.1ERICA, Respondents INDIANA & MICHIGAN ELFCTRIC CO., AND INDIANA & MICHIGAN POWER COMPANY, IntervenorOn Petitioners' Motion for Summary Reversal of a Final of the Ato...

Filing of Owner's Inservice Inspection Summary Report for Point Beach Nuclear Plant Refueling Outage U1R29.

I -~ tSuNMC Point Beach Nuclear PlantCommitted to NuclearExcelnce Operated by Nuclear Management Company, LLCFebruary 22, 2006 NRC 2006-001910 CFR 50.55aU.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Point Beach Nuclear Plant, Unit 1Docket 50-...

Arkansas Nuclear One, Units 1 and 2 - Approval of Second Extension Request for Corrective Actions re GL-2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During DBAs at PWRs" (TAC MD8570, MD8546).

April 30, 2008 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S. R. 333 Russellville, AR 72802 SUBJECT: ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 - APPROVAL OF EXTENSION REQUEST FOR CORRECTIVE ACTIONS RE: GENERIC LETTER 2004-02, "POTENTIAL IMP...

Surry, Units 1 & 2, Updated Final Safety Analysis Report, Revision 39, Chapter 7: Instrumentation and Control.

Revision 39—09/27/07 SPS UFSAR 7-i 7.1 INTRODUCTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.1-17.1.1 General Design Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....

NRC Supporting Document Examination for the AREVA NP, Inc. US Evolutionary Pressurized Reactor Design Certification Application Chapter 19 Review.

September 11, 2008 Ms. Sandra Sloan Manager AREVA NP, Inc. 3315 Old Forest Road P.O. Box 10935 Lynchburg,VA 24506-0935 SUBJECT: NRC SUPPORTING DOCUMENT EXAMINATION FOR THE AREVA NP, INC. U.S. EVOLUTIONARY PRESSURIZED REACTOR DESIGN CERTIFICATION APPLICATION CHAPTER 19...

Westinghouse Electric Co., Submittal of Response to Request for Additional Information on SRP Section 19.0.

OWestinghouseU.S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, D.C. 20555Westinghouse Electric CompanyNuclear Power PlantsP.O. Box 355Pittsburgh, Pennsylvania 15230-0355USA412-374-6206412-374-5005sisklrb@westinghouse.comDirect tel:Direct fax:e-mail:...

Luminant - Comanche Peak Units 3 and 4 COLA (Environmental Rpt), Rev. 0 - ER Chapter 03 - Plant Description - Sections 03.00 - 03.10

Revision: 0 3-iComanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 3 - Environmental ReportComanche Peak Nuclear Power Plant, Units 3 & 4COL ApplicationPart 3 - Environmental ReportCHAPTER 3PLANT DESCRIPTIONTABLE OF CONTENTSSection Title Page3.0 PLANT DESCRIPTION...

South Texas Project Units 3 & 4 COLA (FSAR), Rev. 2 - Chapter 02 - Final Safety Analysis Report- Tier 1 - Core Cooling Systems - Section 2.4 - Pages 1-14

Core Cooling Systems 2.4-1STP 3 & 4 Tier 12.4 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.STD DEP T1 2.4-1 (Figure 2.4.1a, Table 2.4.1...

Palisades Nuclear Plant - Generic Letter 2004-02 "Potential Impact of Debris Blockage On Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors" Extension Request Approval For Palisades Nuclear Plant (TAC No. MC4701).

December 21, 2007 Mr. Michael Balduzzi Sr. Vice President, Regional Operations NE Entergy Nuclear Operations, Inc. 440 Hamilton Avenue White Plains, NY 10601 SUBJECT: GENERIC LETTER 2004-02 “POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN B...

Provides suppl to util 880819 request for approval of alternative acceptance to ASME Section III requirements. After approval,util will add paragraph to FSAR,Section 3.8, listing two welds exceeding acceptance criteria.

TENNESSEE VALLEY AUTHORITYCHATTANOOGA, TENNESSEE 374015N 157B Lookout PlaceMAY 05 1989U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555Gentlemen:In the Matter of the Application of ) Docket Nos. 50-390Tennessee Valley Authority )WATTS BAR NUCL...

Rev 0 to Nuclear Safety Review Staff Ofc Procedure 0310, "Assessing Potential Impact of Unvalidated Employee Concerns on Watts Bar Nuclear Plant Startup Schedule."

PROCEDURE NO.: 0310 REVISION NO.: 00 PAGE 1 OF 8*PREPARED SUBMI -APPROVED L.* BY:G. G. Brantley BY:M.fA. rrison BY: K. W. WhittNUCLEAR SAFETY REVIEW STAFF OFFICE PROCEDURETITLE: ASSESSING POTENTIAL IMPACT OF UNVALIDATED DATE: 6/8/85EMPLOYEE CONCERNS ON THE WATTS BAR NUCLEAR PL...

Event Notification Report for February 24, 2025: 57567

Power Reactor Facility: Hatch RX Type: [1] GE-4,[2] GE-4 Emergency Class: Non Emergency
Event Text PRIMARY CONTAINMENT DEGRADED The following information was provided by the licensee via phone and email: "At 1111 EST on 02/22/2025, while in mode 5 at 0 percent power, it was determined during local leak rate testing (LLRT) that the Unit 2 primary containment leak...

AREVA Design Control Document Rev. 1 - Tier 1 Chapter 03 - Non-System Based Design Descriptions and ITAAC - List of Figures

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 1 Page 3-iiiCHAPTER 3—NON-SYSTEM BASED DESIGN DESCRIPTIONS AND ITAACLIST OF FIGURES Figure 3.5-1—Representative Containment Isolation Valve Arrangement ............3.5-23Next File

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 14, Figure 14.2.5-6.

Time Title: Steamline Break DER Inside Containment with Power Reactivity and Core Boron Concentration Versus Sheet 1 of 1UFSAR Figure: 14.2.5-6 AMERICAN ELECTRIC POWER COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN Change Description: UCR-1962 Revision: 23...

Closed Generic Communication TACs (PA No. 101122CA/B) Summary Report (As of 08/31/2010).

Closed Generic Communication TACs (PA No. 101122CA/B) Summary Report (AS OF 08/31/2010) TAC NO. TAC TITLE STATUS AGE (Mon) TAC CLOSED LEAD ORG ME3877 IN ‘Containment Concrete Surface Condition Examination Frequency and Acceptance’ C 3.0 08/09/2010 DLR

Columbia Fuel Fabrication Plant - Application for Certificate of Compliance for the Traveller PWR Fuel Shipping Package, Table of Contents.

Docket 71-9297 Traveller Safety Analysis Report Rev. 0, 3/2004 6437-TOC-rev1.doc TABLE OF CONTENTS 1 GENERAL INFORMATION...............................................................................................1-1 2 STRUCTURAL EVALUATION.................................

Event Notification Report for May 05, 2025: 57689

Power Reactor Facility: Callaway RX Type: [1] W-4-LP Emergency Class: Non Emergency
Event Text BOTH TRAINS OF EMERGENCY CORE COOLING SYSTEM INOPERABLE The following information was provided by the licensee via phone and email: "On May 4, 2025, with the plant in mode 4 during restart from a refueling outage, operators were flushing the chemical volume and cont...

LaSalle County Station, Units 1 and 2 - APLA Request for Additional Information re: LAR 50.69 and TSTF-505 (EPIDS L-2020-LLA-0017) and (EPID L-2020-LLA-0018)

September 29, 2020 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: LASALLE COUNTY STATION, UNIT NOS. 1 AND 2 – REQUEST FOR ADDITIONAL IN...

Requests approval of encl rev to SRP Section 3.6.2, "Determination of Rupture Locations & Dynamic Effects Associated w/Postulated Rupture of Piping" for publication in FR for public comment.

_ _ _.,#UNITED STATES -?/(NUCLEAR REGULATORY COMMISSION - A)c . % -,f3. wAsmNGTON, D. C. 206559-11- 64-x....J"* -AUGts q,MEMORANDUM FOR: James H. Sniezek, Chairman ., " .Comittee to Review Generic Requirements,,FROM:Denwood F. Ross, Acting DirectorOffice of Nuclear Regulatory ...

GE Hitachi Nuclear Energy - NRC Inspection Report 05000018/2020001, 05000070/2020001, and 05000183/2020001

October 20, 2020 Mr. Matt Feyrer, Site Manager Vallecitos Nuclear Center GE Hitachi Nuclear Energy 6705 Vallecitos Road Sunol, CA 94586-8524 SUBJECT: GE HITACHI NUCLEAR ENERGY - NRC INSPECTION REPORT 050-00018/2020-001, 050-00070/2020-001, AND 050-00183/2020-001 ...

Provides addl info to support environ qualification per 10CFR50.49 of Bunker-Ramo,per 880322 telcon.Attachment I identifies Bunker Ramo instrumentation penetration info.Addl info will be transmitted as described.

. - . -'/~NCommonwealth Edison'*9 ,,IOne Fir:t Ndonal Plaza, Chicago, Ilkno:sk O ~]Address Reply to: Post Offics Box 767N/ Chicago, Illinois 60690 - 0767March 23, 1968Mr. T. E. MurleyOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory Cumnis91onWashington, DC. 20555Att...

Vogtle Electric Generating Plant, Units 1 & 2 - Integrated Inspection Report 05000424/2020003 and 05000425/2020003

November 13, 2020 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc. 3535 Colonnade Parkway Birmingham, AL 35243 SUBJECT: VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 & 2 – INTEGRATED INSPECTION REPORT 05000424/2020003 AND 05000425/202000...

Forwards response to 890223 request for addl info re Chapter 6 of ALWR util requirements document.

.. .-_;__ _ _ _ _ -,"|,*;~ Electric Power*Research institutet..,' July.3, 1989'*Mr. Tom Kenyon, Project ManagerStandardization and Non-PowerReactor Projects DirectorateDivision of. Reactor Projects III, IV,V, and Special Projects.Office of Nuclear RegulationiU.S.-Nuclear Regul...