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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Toshiba Design Control Document Rev. 1 - Tier 2 - Chapter 12 - Radiation Protection - Section 12.02 - Radiation Sources

Radiation Sources 12.2-1RS-5146900 Rev. 1Design Control Document/Tier 2 ABWR12.2 Radiation Sources12.2.1 Contained Sources12.2.1.1 Source TermsWith the exception of the vessel and drywell shields, shielding designs are based on fission product and activation product sources...

Forwards responses & clarifications to 840206 submittal of 10CFR50,App R,Section III.G,per NRC 840502-03 site visit. Replacement pages to 840206 submittal encl to facilitate NRC review.W/one oversize chart.Aperture card is in PDR.

REGULATURY#NFORMATION DISTRIBUTION SyEM (RIDS) ACCESSION NBR:8406120502 DOC.DATE: 84/06/06 NOTARIZED: NO DOCKET # FACIL:50-261 H. 8. Robinson Plant, Unit 2, Carolina Power and Ligh 05000261 AUTHNAME AUTHOR AFFILIATION CUTTERAB. Carolina Power & Light Co. ,RECIP.NAME RECIPIENT...

Draft For Comment on Design-Specific Review Standard for NuScale SMR Design Section 6.6, Inservice Inspection and Testing of Class 2 and 3 Components.

Draft for Comment ADAMS Accession No. ML15227A136 U.S. NUCLEAR REGULATORY COMMISSION DESIGN-SPECIFIC REVIEW STANDARD FOR NuScale SMR DESIGN 6.6 INSERVICE INSPECTION AND TESTING OF CLASS 2 AND 3 COMPONENTS REVIEW RESPONSIBILITIES Primary - Organization responsible f...

Diablo Canyon, Units 1 and 2 - Response to NRC Request for Additional Information - National Fire Protection Association Standard 805, Enclosure, Attachment 3.

EnclosureAttachment 3PG&E Letter DCL-1 5-119Updates to the License Amendment Request as a Result of Updated Analyses, EditorialChanges, and Reference Corrections1At-r,nwrn I ;ffor fln floe onr ~ Iar~rn ~ non,, A ,-rnn,,rn I ctflat, a0 can nsa ~ I,., .a~Jna nijanny fl~* ,J,, ...

Redacted AREVA, Inc. - Enclosure 2, Revision 16, Safety Analysis Report for the TN-RAM, Non-Proprietary. Part 1 of 2.

Non-ProprietarySAFETY ANALYSIS REPORTfor theTN-RAME-1 0621December 2015Revision 16AREVA Inc.7135 Minstrel Way, Suite 300Columbia, Maryland 21045Enclosure 2 to E-43962TN-RAM SAR, Revision 16(Non-Proprietary)Non-ProprietarySAFETY ANALYSIS REPORTfor theTN-RAME-1 0621December 2015...

Safety Evaluation that Supports License Amendment No. 39 for Vogtle Units 3 and 4.

- 1 - SAFETY EVALUATION BY THE OFFICE OF NEW REACTORS RELATED TO EXEMPTION AND AMENDMENT NO. 39 TO THE COMBINED LICENSE NOS. NPF-91 AND NPF-92 SOUTHERN NUCLEAR OPERATING COMPANY, INC. GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MEAG POWER SPVM, LLC MEAG POWER SP...

James A. Fitzpatrick - Transmittal of Emergency Plan Updates.

"En tergyEntergy Nuclear NortheastEntergy Nuclear Operations, Inc.James A. FitzPatrick NPPP.O. Box 110Lycoming, NY 13093Tel 315-342-3840James D. JonesManager Emergency PlanningJAFP-1 5-0152December 18, 2015United States Nuclear Regulatory CommissionAttn: Document Control DeskW...

Curriculum Vitae of Arnold Gundersen

CURRICULUM VITAE Arnold Gundersen Chief Engineer, Fairewinds Associates, Inc April 2016 Education and Training ME NE Master of Engineering Nuclear Engineering Rensselaer Polytechnic Institute, 1972 U.S. Atomic Energy Commission Fellowship Thesis: Cooling Tower Plume Rise ...

Radioactive Material Transport Packaging System - Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages.

AOS-FM9054 Rev. H-2, June 27, 2016 I (Docket No. 71 -9316) Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages Prepared by Alpha-Omega Services, Inc. Bellflower, CA Revision History Revision Date Des...

App A of S&W SWESSAR-P1, "Encl Bldg W/o Mixing."

[C\ c, , n> / 9u--.- M=.H3O'"C-W hx3~QO-Z ZuJ -*%0. J~,4 3g12J+ CC--3cnO^.OisI.Zf WP%*% *W3--NtmSWESSAR-P1APPENDIX AENCLOSURE BUILDItU WITHOITF MIXINGLIST OF EFFECTIVE PAGESPage, Table (T) , JtwrdmentPage, Table (T) ,a:nendInentor Fiqure (F) No.or Fiqure (F)No.A-a 39A-i23A-ii3...

"Steam Generator Tube Rupture," revised emergency procedures.

,ks-442-EP-4Page 1 of 1105-22-80-VIRGINIA ELECTRIC AND POWER COPJANYNORTH ANNA POWER STATIONUNIT NO. 2STEAM GENERATOR TLTE RUPTUREREFERENCI.S:1. 12050-FM-73A Condensate System2. 12050-FM-87B Waste Disposal System3. FSAR Chapter 154. 12050-LSK-3-15. 12050-FM-93A Reactor Coolant...

Diablo Canyon, Units 1 and 2 - Independent Spent Fuel Storage Installation Emergency Plan Implementing Procedure Update.

Pacific Gas and Electric Company .. February 14, 2019 PG&E Letter DCL-19-014 PG&E Letter DIL-19-003 Michael A. Ginn Manager Emergency Planning Diablo Canyon Power Plant P .O. Box 56 Avila Beach, CA 93424 805.545.3446 Internal: 691 .3446 Fax: 805.545.6265 U.S. Nuclear Regulator...

Braidwood Station, Units 1 & 2 and Byron Station, Unit 1 & 2, Submittal of Revision 17 to Updated Final Safety Analysis Report and Amendment 28 to Updated Fire Protection Report.

"I Exelon Generation® RS-18-144 December 17, 2018 1 O CFR 50.4(b)(6) 1 O CFR 50.71 (e) 1 O CFR 54.37(b) U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20055 Subject: Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-...

Dresden Nuclear Power Station, Units 1, 2 & 3, Revision 13 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems

DRESDEN — UFSAR Rev. 8June 20093.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMSTABLE OF CONTENTSPage3-i3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1-13.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-13.1.1 Compliance with Draft De...

Forwards info re abnormal transient operating guidelines program,including RA Fortney "Safety Function & Protection Sequence Analysis" & excessive feedwater safety sequence diagram.Two oversize drawings encl.

.:.._.ARKANSAS POWER & LIGHT COMPANYPOST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000November 7, 1979,1-119-6Director of Nuclear Reactor RegulationATTN: Mr. R. W.Reid, ChiefOperating Reactor Branch #4U. S. Nuclear Regulatory CommissionWashington, D. C. 20555Subjec...

NRC LTP Reponses Letter.

1 1. Introduction On Oct 10, 2017, NRC (J. Hickman) provided Energy Solutions (G. Van Noordennen) with a specific set of comments regarding the NRC staff’s continuing review of the Zion LTP. These comments were divided into a Background section and a section addressing Speci...

IR 05000348-08-005 and 05000364-08-005; 10/01/2008 - 12/31/2008; Joseph M. Farley Nuclear Plant, Units 1 and 2; Routine Integrated Report.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 January 30, 2009 Mr. J. Randy Johnson Vice President - Farley Southern Nuclear Operating Company, Inc. 7388 North State Hig...

Palo Verde, Units 1, 2 and 3, Response to the NRC Request for Additional Information Regarding Risk-Informed Inservice Inspection Program Request.

Palo Verde NuclearGenerating StationJames M. LevineExecutive Vice PresidentGeneration10 CFR 50.55a(a)(3)(i)(g)Mail Station 7605PO Box 52034Phoenix, Arizona 85072-2034Tel (623) 393-5300Fax (623) 393-6077102-05515-CDM/SAB/RJRJune 10, 2006U.S. Nuclear Regulatory CommissionAttn: D...

Response to Portion of NRC Request for Additional Information Letter No. 15 - Reactor Coolant Pressure Boundary (RCPB) - RAI Numbers 5.2-1 S01, 5.2-1 S02, 5.2-2 S01, and 5.2-2 S02.

GE-Hitachi Nuclear Energy Americas LLCJames C. KinseyProject Manager, ESBWR LicensingPO Box 780 M/C A-55Wilmington, NC 28402-0780USAT 910 675 5057F 910 362 5057jim.kinsey@ge.comMFN 06-085 Supplement 3 Docket No. 52-010August 3, 2007U.S. Nuclear Regulatory CommissionDocument Co...

Waterford Steam Electric Station, Unit 3, Emergency Core Cooling System Performance Analysis.

Entergy Nuclear SouthEntergy Operations, Inc.17265 River RoadKillona, LA 70057Tel 504 739 6660Fax 504 739 6678kwalshl@entergy.comKevin T. WalshVice President, OperationsWaterford 3W3F1-2007-0038August 9, 2007U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashingt...

Nine Mile Point, Units 1 and 2 - License Renewal Application, Reformatted Sections, 3.1.2., 3.2.2., 3.3.2., 3.4.2., 3.5.2., 3.6.2. (TAC Nos. MC3272 and MC3273).

- .. .Constellation Energy:A Nine Mile Point Nuclear StationP.O. Box 63Lycoming, NY 13093August 19,2005NMP1L 1976U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001SUBJECT: Nine Mile Point Units 1 and 2Docket Nos. 50-220 and 50-410Facility Op...

Enclosure 1: NEI Response to NRC Request for Additional Information Date October 30, 2008. NEI 07-01, Methodology for the Development of Emergency Action Levels (for) Advanced Passive Light Water Reactors.

Page 1  Enclosure 1 NEI Response to NRC Request for Additional Information – Date October 30, 2008 NEI 07-01, “Methodology for the Development of Emergency Action Levels (for) Advanced Passive Light Water Reactors” # EAL NRC Comment NEI Response 1 General 1. This document sho...

08/12/2009 Summary of Category 1 Public Meeting Held via Conference Call with Indiana Michigan Power Company to Discuss Draft Responses to Requests for Additional Information Associated with GL-04-002.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 25, 2009 LICENSEE: INDIANA MICHIGAN POWER COMPANY FACILITY: DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 SUB..IECT: SUMMARY OF AUGUST 12, 2009, CATEGORY 1 PUBLIC MEETING VIA CONFERENCE CALL TO D...

IR 05000456-10-009; October 18, 2010 - November 1, 2010; Braidwood Station, Unit 1 Supplemental Inspection - Inspection Procedure 95001.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 November 26, 2010 EA-09-259 Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear...

Wolf Creek - Issuance of Amendment No. 191, License Amendment Request for Deviation from Certain Technical Requirements of Approved Fire Protection Program as Described in Appendix 9.5E of Updated Safety Analysis Report (TAC No. ME0797).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 16, 2010 Mr. Matthew W. Sunseri President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 SUBJECT: WOLF CREEK GENERATING STATION - ...