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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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U.S. Nuclear Regulatory Commission Report of Regulatory Audit for Nuscale Power, LLC Seismic Category 1 Equipment and Environment Qualification of Electrical Equipment Specifications.

October 25, 2018 MEMORANDUM TO: Samuel S. Lee, Chief Licensing Branch 1 Division of Licensing, Siting, and Environment Analysis Office of New Reactors FROM: Marieliz Vera Amadiz, Project Manager /RA/ Licensing Branch 1 Division of Licensing, Siting, and ...

NuScale Power, LLC - Supplemental Response to NRC Request for Additional Information No. 116 (eRAI No. 8926) on the NuScale Design Certification Application.

RAIO-0818-61553NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comDocket No. 52-048 August 27, 2018U.S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North11555 Rockvi...

Attachment 7: 0098-0189-CALC-OO1, Revision 1, Palisades SLUR Time Delay Calculation.

PNP 2018-010 ATTACHMENT 7 Palisades SLUR Time Delay Calculation 150 pages follow ~ MPR 0098-0189-CALC-OO 1 Revision 1 Palisades SLUR Time Delay Calculation Prepared for: Palisades Preparer: Alex Dean ~ E-signed by: Alex Dean on 2017-05-17 17:06:55 Checker: Gregory Vozza ~ E-si...

Redacted - AREVA - 380-B Transport Package, Safety Analysis Report, Revision 2.

-:\ (~ ' ·~ A DOCKET 71-9370 AREVA 380-B TRANSPORT PACKAGE Safety Analysis Report AREVA Federal Services LLC Revision 2 August 2017 • • \. 380-8 Package Safety Analysis Report Docket No. 71-9370 Rev.2,August2017 TABLE OF CONTENTS 1.0 GENERAL INFORMATION ..........................

Watts Bar Nuclear Plant, Units 1 & 2, Amendment 2 to Updated Final Safety Analysis Report, Table of Contents

PAGE 1 OF 15 WATTS BAR NUCLEAR PLANT DIVISION OF RESPONSIBILITY (DOR) ABBREVIATIONS BOP SYSTEM ENGINEERING - BALANCE OF PLANT CHEM CHEMISTRY CIVIL DESIGN ENGINEERING - CIVIL ENGINEERING PGM/PGMS PROGRAM/COMPONENT PROGRAM ENGINEERING EIC SYSTEM ENGINEERING - ELECT...

Susquehanna, Unit 1, Technical Requirements Manual

• MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2019-12962 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 08/23/2019 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUC...

Forwards response to Generic Ltr 88-14, "Instrument Air Supply Sys Problems Affecting Safety-Related Equipment." Weekly tests conducted to ensure that diesel generator compressors start upon reduction of air pressure in tanks.

_ - - -- - - - - - --- - ._ .-e..VERMONT YANKEENUCLE 5R POWER CORPORATION.RD 5 Box 169, Ferry Road Brattleboro, VT 05301 BVY 89-17 i ..s9REPLY TOENGINEERING OFFICE580 MAIN STREET*BoLToN, MA 01740*(508)779-6711February 16, 1989U.S. Nuclear Regulatory CommissionWashington, D.C. ...

Susquehanna Steam Electric Station Unit 1, Amendment 38, Revision to Technical Specifications to Change the Setpoint for Main Steam Isolation Valve Closure on Reactor Vessel Water Low Level From Level 2 to Level 1.

IW UNITED STATES 0NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 APR 2 31IM Docket No.: 50-387 Mr. Norman W. Curtis Vice President Engineering and Construction - Nuclear Pennsylvania Power and Light Company 2 North Ninth Street- . Allentown, Pennsylvania 18101 Dear Mr....

Amendment 93 to Facility Operating License DPR-26 for the Indian Point Nuclear Generating, Unit 2.

Docket No. 50-247February 28, 1985Mr. John D. O'Toole Vice President Nuclear Engineering and Quality Assurance Consolidated Edison Company of New York, Inc. 4 Irving Place New York, New York 10003Dear Mr. O'Toole:RIBUTIJWý L PDR ORB#1 Rdg MSlosson SECY EJordan TBarnhart 4 1/e...

Forwards info re auxiliary feedwater sys flow requirements as appplicable to design basis transients & accident conditions.Info transmitted in response to Encl 2 of 790921 ltr.

REGULAT*O INFORMATION DISTRIBUTION* STEM (RIDS)ACCESSION N8R:8108190113 DC.0ATE: 81/08/14 NOTARIZED: NO FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servie AUTH.NAME AUTHOR AFFILIATION MATHEWS,E.R, Wisconsin Public Service Corp, RECIPNIAME! RECIPIENT AFFILIATION...

Enclosure 3, UAP-HF-08083, Rev. 0, Response Package to NRC's Requests for Additional Information on Topical Report MUAP-07012-P(R0) LOCA Mass and Energy Release Analysis Code Applicability Report for US-APWR.

Enclosure 3UAP-HF-08083, Rev.0Response Package to NRC's Requestsfor Additional InformationonTopical Report MUAP-07012-P(RO)LOCA Mass and Energy Release AnalysisCode Applicability Report for US-APWRApril 2008(Non-Proprietary)Response Package to NRC's RAIs onLOCA Mass and Energy...

Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendments Re: Intermittent Opening of Isolated Flow Paths and Tip Isolation (TAC Nos. MB6665 and MB6666).

June 5, 2003Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear OfficerPPL Susquehanna, LLC769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCEOF AMENDMENT RE: INTERMITTENT OPENING OF ISOLATED FLOWPA...

Palo Verde-12-2004-FINAL-Outline.

Here are the changes requested upon the initial review. I will determine if more changes are required as I develop exam questions. The password is the same as before. PVNGS Draft Outline Comments (completed 9/13/04) Changes marked in red and line outs Operating Exam ...

08/08/2002 - Summary of Telecommunication with Omaha Public Power District (OPPD) to Discuss Draft Requests for Additional Information (RAIS) for the Renewal of the Operating License for Fort Calhoun Station, Unit 1 (FCS).

April 10, 2003LICENSEE: Omaha Public Power DistrictFACILITY: Fort Calhoun Station, Unit 1SUBJECT: SUMMARY OF TELECOMMUNICATION WITH OMAHA PUBLIC POWERDISTRICT (OPPD) TO DISCUSS DRAFT REQUESTS FOR ADDITIONALINFORMATION (RAIs) FOR THE RENEWAL OF THE OPERATING LICENSEFOR FORT CAL...

Ginna, RAI Response Clarifications & Commitment Schedule Update.

Always at Your ServiceRobert C. MecredyVice PresidentNuclear OperationsJuly 30, 2003U.S. Nuclear Regulatory CommissionDocument Control DeskAttn: Mr. Russell Arrighi (Mail Stop 0-12D-3)Office of Nuclear Reactor RegulationWashington, D.C. 20555-0001Subject: RAI Response Clarific...

Design Control Document for the US-APWER, Chapter 14, Verification Programs, MUAP-DC0014, Rev. 2.

©2009 Mitsubishi Heavy Industries, Ltd.All Rights Reserved DESIGN CONTROL DOCUMENT FOR THE US-APWR Chapter 14 Verification Programs MUAP- DC0014 REVISION 2 OCTOBER 2009 MITSUBISHI HEAVY INDUSTRIES, LTD. US-APWR Design Control Document © 2009 MITSUBISHI HEAVY INDUS...

Browns Ferry, Unit 1 - Generic Letter 89-10 and Supplements 1 to 7, Safety-Related Motor-Operated Valve (MOV) Testing and Surveillance.

May 5, 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen: In the Matter of ) Docket No. 50-259 Tennessee Valley Authority ) BROWNS FE...

Revision 4, Maine Yankee's License Termination Plan.

Maine Yankee321 OLD FERRY RD. * WISCASSET, ME 04578-4922February 28, 2005MN-05-010 RA-05-012UNITED STATES NUCLEAR REGULATORY COMMISSIONAttention: Document Control DeskWashington, DC 20555References:Subject:(1) License No. DPR-36 (Docket No. 50-309)(2) MYAPC Letter to USNRC, MN...

Arkansas Nuclear One, Units 1 and 2, RAI, Proposed Upgraded Emergency Actions Levels (EALs).

July 2004Arkansas Nuclear Onecc: Senior Vice President & Chief Operating OfficerEntergy Operations, Inc.P. O. Box 31995Jackson, MS 39286-1995Director, Division of Radiation Control and Emergency ManagementArkansas Department of Health4815 West Markham Street, Slot 30Little ...

Point Beach Plant, License Amendment 96 & 100, Amendments Remove Restrictions On Movement Of Loads Over Spent Fuel Pool Following Crane Modification To Meet Sinlgle Failure Criteria & To Delete Limit Switch Inspection Criteria Previously In TS.

September 3, 1985Docket Nos. 50-266 and 50-301 Mr. C. W. Fay, Vice President Nuclear Power Department Wisconsin Electric Power Company 231 West Michigan Street, Room 308 Milwaukee, Wisconsin 53201gl;BUTTON: NRC PDR L PDR ORB#3 Rdg HThompson PMKreutzer-3 TCol burn OELD SECY LHa...

MFN 05-105, Enclosure 2, Reactor Pressure Vessel (RPV) Level Response for the Long Term PCCS Period Phenomena Identification and Ranking Table Major Design Changes from the Pre-Application Review Design to DCD Design.

MFN 05-105 Enclosure 2 General Electric Company ENCLOSURE 2 MFN 05-105 Reactor Pressure Vessel (RPV) Level Response for the Long Term PCCS Period Phenomena Identification and Ranking Table Major Design Changes from Pre-Application Review Design to DCD D...

Safety Evaluation Report for Brunswick Steam Electric Plant, Units 1 and 2, License Renewal Application.

Safety Evaluation ReportRelated to the License Renewal of the BrunswickSteam Electric Plant, Units 1 and 2Docket Nos. 50-325 and 50-324Carolina Power & Light CompanyU.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDecember 2005THIS PAGE IS INTENTIONAL...

Brief for the Federal Respondents, 8/6/04.

REQ ,e UNITED STATES0 ANUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555-001OFFICE OF THE Ags ,20GENERAL COUNSEL August 6, 2004Roseann B. MacKechnie, ClerkUnited States Court of Appealsfor the Second Circuit40 Foley SquareNew York, New York 10007RE: Connecticut Coalition Aga...

50-370, 50-369, IMPROVED TECHNICAL SPECIFICATIONS, MCGUIRE NUCLEAR STATION, UNITS NO. 1 AND 2 (VOLUME 1).

50-37050-369IMPROVEDTIECIINICALSPi!CIFiCATioNSMcGuire Nuclear Station,Units No. 1 and 2(Volume I)TABLE OF CONTENTS1.0 USE AND APPLICATION ................................................. 1.1-11.1 Definitions ................................................. 1.1-11.2 Logical C...

GE Hitachi Nuclear Energy - Revised Response to Portion of NRC Request for Additional Information Letter No. 300 Related to ESBWR Design Certification Application ESBWR RAI Numbers 19.2-95 S01 and 19.2-100 S01.

MFN 08-801, Supplement 1, Revision 1 Docket No. 52-010 June 11, 2009 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Subject: Revised Response to Portion of NRC Request for Additional Information Letter No. 300 Related to E...