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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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Vogtle, Units 3 and 4 - Revision to Request for License Amendment and Exemption: Addition of Steam Generator System (SGS) Thermal Relief Valves (LAR-17-012 R1).

B. H. Whitley Southern Nuclear Director Operating Company, Inc. Regulatory Affairs 42 Inverness Center Parkway Birmingham, AL 35242 Tel 205.992.7079 Fax 205.992.5296 August 15, 2017 Docket...

12/14/2017 Summary of Meeting on Regulatory Improvements for Advanced Reactors, Slide Presentations.

Presentations for December 14, 2017 Public Meeting Regulatory Improvements for Advanced Reactors In order of discussion, the meeting included the following topics and presentations 1) NRC Slides• Opening / Outline• Future Meetings2) Licensing Modernization Project Slides on De...

Transmittal of TSTF-566, Revision 0, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems."

11921 Rockville Pike, Suite 100, Rockville, MD 20852 Phone: 301-984-4400, Fax: 301-984-7600 Administration by EXCEL Services Corporation TECHNICAL SPECIFICATIONS TASK FORCEA JOINT OWNERS GROUP ACTIVITYTSTF January 19, 2018 TSTF-17-18 PROJ0753 Attn: Document Control Des...

Vogtle Electric Generating Plant, Unit 1 and 2 - Tornado Missile Risk Evaluator: SNC Response to NRC Request for Additional Information.

Cheryl A. Gayheart Regulatory Affairs Director 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5316 tel 205 992 7601 fax cagayhea@southernco.com July 26, 2018 Docket Nos.: 50-424 NL-18-0815 50-425 10 CFR 50.90 U. S. Nuclear Regulatory Com...

Wolf Creek Generating Station, Revision 32 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls.

WOLF CREEK TABLE OF CONTENTS CHAPTER 7.0 INSTRUMENTATION AND CONTROLS Section Page 7.1 INTRODUCTION 7.1-1 7.1.1 IDENTIFICATION OF SAFETY-RELATED...

Transmittal Of Final Perry Nuclear Power Plant Accident Sequence Precursor Report (Licensee Event Report 440-2016-003-01).

UNITED STATES NUCLEAR REGULATORY COMMISSION Mr. David B. Hamilton Site Vice President WASHINGTON, D.C. 20555-0001 September 25, 2018 FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 SUBJECT: TRANSMITTAL OF FINAL PERRY N...

Forwards amend to License DPR-68 changing Tech Specs to accommodate Reload 2 Cycle 3 operation & to eliminate LPCI loop selection logic per Amend 23 of License DPR-68.Fuel cycle reload rept justifying changes encl.

_ _ _ _ _ . _ . _ . . . . . _ _ . _ . _ _ _ _ _ _ .TENNESSEE VALLEY AUTHORITY-~CH ATTANOOG A. TEN;4 ESSEE 37401400 Chestnut Street Tower IIAugust 6, 1979TVA BFNP TS 127Mr. Harold R. Dentou, DirectorOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashingto...

Browns Ferry Nuclear Plant, Units 1, 2 & 3, Amendment 28 to Updated Final Safety Analysis Report, Chapter 6, Emergency Core Cooling Systems

BFN-26 6.0-i TABLE OF CONTENTS 6.0 EMERGENCY CORE COOLING SYSTEMS 6.1 Safety Objective................................................................................................................................... 6.1-1 6.2 Safety Design Basis ........................

Amend 1 to CESSAR-F.

. . _ . - . . . . - - ~ ..-_. . - - . . _ _ _ _ . = . .- . _. . . .. ....._.. .- _- .411:!Oiii AMENDMENT NUMBER 1l''CESSAR-Fi:DOCKET STN-50-470F;!i;.'The following sheets of CESSAR-F are to be removed and inserted:. i':!- REMOVE THE FOLLOWING INSERT THE FOLLOWINGi ).!Chapter 3...

Susquehanna, Unit 1, Technical Requirements Manual

U U!! • 4 U 1 4 U ..L::, MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2019-10033 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 06/20/2019 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUM...

Forwards revised GPU nuclear analysis re subcooling margin monitor,per 840824 response to Commission 840727 memorandum concerning conclusions reached in SECY-84-237.Svc list encl.

|5|g, . _. . _ _ - - . ...#--SHAw, PITTMAN, PoTTs & TROWBRIDGE, $ - [E' A PARTNER $ Map or enorESSiONAL CompORATeONS1t$00 M STREET N. W.WASHINGTON. D. C. 20036*".RC2) 8224000 mAMSAT o. pOTTS. p C. CMante S e. TrumsN. p C. . s o,, , ,,, ,oy , ,,, so,,, ,, ,e,,*. SE"/[c'rYTEOw"e...

McGuire Nuclear Station, Units 1 and 2 - Updated Final Safety Analysis Report, Chapter 11

McGuire Nuclear Station UFSAR Chapter 11 (13 OCT 2018) 11 - i Table of Contents 11.0 Radioactive Waste Management 11.1 Source Terms 11.1.1 Activities in the Reactor Coolant 11.1.1.1 Fission Products 11.1.1.2 Activated Corrosion Products 11.1.1.3 Tritium 11.1.1.3.1 Fissi...

Rev 2 to Procedure 1040-001-030, "TMI Action Items."

_ _ _ _ _\CALCULATION / PROBLEM COVER SHEET__Calculation / Problem No: 1040-001-029Title: Display Instrumentation - Technical Specification 3.1Client: Toledo Edison Company Project: Davis-BesseUnit 1J 1o40-001-671I&E Bulletin 79-olBJob No:Equipment QualificationDe:Ign input /R...

"Equipment Evaluation Rept by Ofc of Nuclear Reactor Regulation Equipment Qualification Branch for AL Power Co JM Farley Unit 1," partial review.

. .OPartial ReviewEQUIPMENT EVALUATION REPORT BY THE~OFFICE OF NUCLEAR REACTOR REGULATIONEQUIPMENT QUALIFICATION BRANCHFOR ALABAMA POWER COMPANYJOSEPH M. FARLEY UNIT 1DOCKET NO. 50-3488103 2 0 0ggyt a_Partial ReviewEQUIPMENT EVALUATION REPORT BY THEOFFICE OF NUCLEAR REACTOR RE...

Beaver Valley Power Station, Unit 1, Technical Specification Bases Change Submittal, Technical Specification Bases Update Status, Section B-I, Change No. 013-Section B 3/4 10-1 Amendment No. 2.

TECHNICAL SPECIFICATIONBASES UPDATE STATUSUNIT: 1ChangeNo.PagesIssuedImplementationDate1-006 none 08/07/021-010 B 3/4 5-1B 3/4 5-1aB 3/4 5-1b04/18/031-012 B 3/4 3-1hB 3/4 6-11B 3/4 6-1204/21/031-013 B-IB-IIB-IIIB-IVB-VB-VI7/10/031-008 B 3/4 4-11a 8/13/031-014 B-VIB 3/4 4-1B 3/...

Licensee Post Exam Written Comments (INITIAL COMMENTS).

Grading summary spreadsheet u Summary of finalized corrections Question 23 Question 25 Question 37 Question 71 Question SRO 3 Question SRO 7 Question SRO 12 Question SRO 22 Question SRO 23 1 1 1 1 1 1 Question SRO 25 t I’ Summary of finalized corrections: - 0 Question 19: acce...

Proposed NRC - Authorized Written Examination Fro The LaSalle Initial Examination - April 2002.

PROPOSED NRC-AUTHORIZED WRITTEN EXAMINATION FOR THE LASALLE INITIAL EXAMINATION - APRIL 2002*QNUM *HNUM *ANUM *QCHANGED *ACHANGED *QDATE *FAC *RTYP *EXLEVEL *EXMNR *QVAL *SEC *SUBSORT *KA *QUESTION001FALSE FALSE 2002/04/08 373 BWR-GE5 R WALTON 1.00295031A202Given the following...

Shearon Harris Nuclear Power Plant, Emergency Response Data System (ERDS) Data Point Library Changes.

6- P rogress Energy SERIAL: HNP-05-059 10 CFR 50 Appendix E U. S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 MAY 1 2 2005 SHEARON HARRIS NUCLEAR POWER PLANT Emergency Response Data System (ERDS) Data Point Library Changes DOCKET NO. 50-...

Point Beach Nuclear Plant U1R28 OCC Interactive Turnover Meeting Agenda.

Ni1 .Comniltted to Nuclcar ExceIlence I D L Y lFPW 3am * UIR23Point Beach Nuclear PlantU1R28OCC Interactive TurnoverMeeting AgendaSunday, May 30, 2004Start Time: 1800 NSB Cafeteria BRIEFING NOTE!ATTENDEESShift Outage DirectorsShift Outage Managers (SOM)Operations Coordinators ...

GE Response to Results of NRC Acceptance Review for ESBWR Design Certification Application - Item 2.

-GE EnergyDavid H. HindsManager. ESBWRPO Box 780 M/C L60Wilmington, NC 28402-0780USAT 910 675 6363F 910 362 6363david.hinds@ge.comMFN 05-109 Project 717October 20, 2005U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555-0001Subject: GE Response to Res...

04/24/06 - LTR R. Nelson to R. Boyle (DOT), Recommendation for Revalidation of Canadian Package Design Certificate no. CDN/2078/B(U)-96 for the Model nos. F-458/F-245, F-458/F-247, F-458/F-251, F-458/F-251 MK2, F-458/F-318, F-458/F-448 Packages.

April 24, 2006Mr. Richard W. BoyleRadioactive Materials BranchOffice of Hazards Material TechnologyU.S. Department of Transportation400 Seventh Street, S.W. Washington, DC 20590SUBJECT: REVALIDATION OF CANADIAN PACKAGE DESIGN CERTIFICATENO. CDN/2078/B(U)-96 FOR THE MODEL NOS. ...

Transcript of ACRS Regulatory Policies and Practices and Thermal Hydraulic Phenomena Meeting on Wednesday, January 25, 2006 in Rockville, MD. Pages 1-160 with related documentation.

Official Transcript of Proceedings A Gsr-133z8NNUCLEAR REGULATORY, COMMISSIONFa"r(%,! !7:'W~e' L tZfIt t 0,,@111 .0' _( ).C,Title:Docket Number:Location:Advisory Committee on Reactor SafeguardsRegulatory Policies and Practices andThermal hydraulic Phenomena(not applicable)PROC...

EDF-NSNF-029, Rev. 0, "Analytical Evaluation of the MCO for Repository-Defined and Other Related Drop Events."

NATtONAL SPENT NUCLEAR FUEL PROGRA E GINEERI G DESIG FtLEDF· S F·MOL.200 0510.0105Revls'onA ALYTICAL EVALUATIO OF THE CO FOR REPOSITORY·DEFIRELATED DROP EVE TS1. Activity Title: Transportation and Packaging - Canis er Bas e2. WBS No. C.1.07.02.01.05.023. Approv I Ty d arne DaP...

2010/03/03 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 323, FSAR Ch 6, Supplement 1

1ArevaEPRDCPEm ResourceFrom: BRYAN Martin (EXT) [Martin.Bryan.ext@areva.com]Sent: Wednesday, March 03, 2010 10:01 AMTo: Tesfaye, GetachewCc: DELANO Karen V (AREVA NP INC); BENNETT Kathy A (OFR) (AREVA NP INC); ROMINE Judy (AREVA NP INC); GUCWA Len T (EXT)Subject: Response to ...

Toshiba Design Control Document Rev. 0 - Tier 2 - Chapter 12 - Radiation Protection - Section 12.02 - Radiation Sources

Radiation Sources 12.2-1RS-5146900 Rev. 0Design 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...