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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

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NRC Staff Notification to Commission.

January 19, 2016 Chairman Stephen G. Burns Commissioner Kristine L. Svinicki Commissioner William C. Ostendorff Commissioner Jeff Baran In the Matter of Nuclear Innovation North America LLC (South Texas Project, Units 3 and 4) Docket Nos. 52-012 and 52-013 Dear Chairma...

Forwards Rev 5 to Crisis Mgt Plan Implementing Procedure EDA-4, "Offsite Dose Projections for Oconee Nuclear Station."

DUKE POWER COMPANY EMERGENCY DOSE ASSESSMENT MANUAL August 9, 1990TABLE OF CONTENTS EDA-1 Procedure for Estimating Food Chain Doses Under Post-Accident Conditions (Rev. 2) EDA-2 Off-Site Dose Projections for Catawba Nuclear Station (Rev. 5) EDA-3 Off-Site Dose Projections for ...

Proposed Tech Specs re increase in boron concentration in RWST & safety injection accumulators & spray additive tank & boric acid tank levels.

ENCLOS TO SERIAL NLS-92-052Page 1 of 1ENCLOSURE 5SHEARON HARRIS NUCLEAR POWER PLANTDOCKET NO. 50-400/LICENSE NO. NPF-63REQUEST FOR LICENSE AMENDMENTCHANGE IN RWST AND SAFETY INJECTION ACCUMULATOR BORON CONCENTRATIONCHANGE IN SPRAY ADDITIVE TANK AND BORIC ACID TANK LEVELSTECHNI...

Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 3, Appendix A-C.

SEABROOK UPDATED FSARAPPENDIX 3APIPE BREAK ANALYSIS SUMMARYSEABROOK UPDATED FSARAPPENDIX 3APIPE BREAK ANALYSIS SUMMARYIntroductionThis appendix summarizes the results of the failure mode and effects analysesof breaks in high and moderate energy piping systems.SummaryMain Steam...

NuScale Power, LLC - Response to NRC Request for Additional Information No. 414 (eRAI No. 9430) on the NuScale Design Certification Application.

RAIO-0618-60376NuScale Power, LLC1100 NE Circle Blvd., Suite 200 Corvalis, Oregon 97330, Office: 541.360.0500, Fax: 541.207.3928www.nuscalepower.comJune 11, 2018 Docket No. 52-048U.S. Nuclear Regulatory CommissionATTN: Document Control DeskOne White Flint North11555 Rockville ...

Susquehanna, Unit 1 - Technical Requirements Manual.

• MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2018-11503 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#:028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: GERLACH*ROSEY M 06/18/2018 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCS...

Watts Bar Nuclear Plant, Unit 1 - Issuance of Amendment No. 121, Modify Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified Intervals (EPID L-2018-LLA-0187).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A Chattanooga, TN 37402-2801 August 16, 2018 SUBJECT: WATTS BAR NUCLEAR PLANT, ...

Susquehanna Steam Electric Station Unit 1 - Technical Requirements Manual.

• MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2017-25366 USER INFORMATION: GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION: TO: 12/19/2017 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) JJC\..o • ...

Harris Initial Exam 2014-302 Final Sim_IN-Plant JPMs.

Appendix C Job Performance Measure Form ES-C-1 Worksheet 2014 HNP NRC Exam Simulator JPM CR a Rev. FINAL Facility: Shearon Harris Task No.: 001001H201 Task Title: Perform Control Rod and Rod Position Indicator Exercise JPM No.: 2014 NRC Exam Simulator JPM CR a K/A ...

AREVA Design Control Document Rev. 7 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.0 System Based Design Description of ITAAC - 2.1.1 Structures

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 7 Page 2.1-12.0 System Based Design Description of ITAAC2.1 Structures2.1.1 Nuclear IslandDesign Description1.0 System DescriptionThe Nuclear Island (NI) consists of the structures supported by the NI Common Basemat and t...

IMC 2515 Appendix D Plant Status

Issue Date: 09/04/15 1 IMC 2515 App D Effective Date: 07/01/16 NRC INSPECTION MANUAL IRIB MANUAL CHAPTER 2515 APPENDIX D PLANT STATUS 2515D-01 OBJECTIVES AND PHILOSOPHY OF PLANT STATUS ACTIVITIES The Reactor Oversight Process recognizes that resident inspectors hav...

Enclosure 4 to Holtec Letter 2178006-NRC, HI-2125175, Rev. 2, "Safety Analysis Report on The HI-STAR 180D Package"

Enclosure 4 to Holtec Letter 21 t8UUb-N1

Chapter 20 - Fukushima Near-Term Task Force Recommendations.

20-1 20.0 REQUIREMENTS RESULTING FROM FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATIONS This chapter addresses the Fukushima Near-Term Task Force (NTTF) recommendations that are applicable to the Fermi 3 Combined License (COL). The applicable recommendations address four to...

Generic Technical Specification Traveler (GTST)ap1000sts3707_gtst_o47_v0.

GTST AP1000-O47-3.7.7, Rev. 0 Date report generated: Monday, May 19, 2014 Page 1 Advanced Passive 1000 (AP1000) Generic Technical Specification Traveler (GTST) Title: Changes Related to LCO 3.7.7, Startup Feedwater Isolation and Control Valves I. Technical Specificatio...

Safety Analysis Report Safkeg-HS Design No. 3977A Package Docket 71-9338, CTR 2008/11, Rev 4.

SAFKEG-HS 3977A Docket No. 71-9338 CTR 2008/11 Revision 4 CTR2008-11-R4-Sc0-v1-Status and Contents.docx December 2013 Safety Analysis Report Safkeg–HS Design No. 3977A Package Docket 71-9338 Application for Approval by the NRC Applicant: Croft Associates Limited S...

Grand Gulf 2012-12 Final Outlines.

ES-401 BWR Examination Outline - RO Form ES-401-1 Facility: Grand Gulf Nuclear Station Date of Exam: October 19,2012 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* TotalA2 G* Total 1. Emergency & A...

IR 05200025-13-005 & 05200026-13-005; 10/01/2013 through 12/31/2013; Vogtle, Unit 3 & 4, Routine Integrated Inspection Report.

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 January 24, 2014 Mr. B. L. Ivey Vice President, Regulatory Affairs Southern Nuclear Operating Company P.O. Box 1295 Bin B022 Birmingham, AL...

LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Appendix A.

LSCS-UFSAR A.0-1 REV. 13 APPENDIX A GLOSSARY Appendix A of the FSAR contained a glossary defining key terminology and acronyms. This glossary is included in the UFSAR as Section 1.2.4. B.0-1 REV. 19, APRIL 2012 APPENDIX B CONFORMANCE TO REGULATORY GUIDES B.0 I...

AREVA Design Control Document Rev. 4 - Tier 1 Chapter 02 - System Based Design Descriptions and ITAAC - Section 2.0 System Based Design Description of ITAAC - 2.1.1 Structures

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 4 Page 2.1-12.0 System Based Design Description of ITAAC2.1 Structures2.1.1 Nuclear IslandDesign Description1.0 System DescriptionThe Nuclear Island (NI) consists of the structures supported by the NI Common Basemat and t...

AREVA Design Control Document Rev. 4 - Tier 2 Chapter 09 - Auxiliary Systems - Section 9.5 Other Auxiliary Systems - 9.5.1 Fire Protection System

U.S. EPR FINAL SAFETY ANALYSIS REPORT Revision 4 Page 9.5-19.5 Other Auxiliary Systems9.5.1 Fire ProtectionThe purpose of the fire protection program (FPP) is to protect plant systems and equipment which provide the capability to safely shut down the reactor, maintain it in...

CP-2012-06 Final Outlines.

ES-401 PWR Examination Outline Form ES-401-2 Page 1 of 15 CP-2012-06 FINAL Written Exam Outline.doc Him Facility: CPNPP 1 & 2 Date of Exam: 06/11/12 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total 1. Emergency & Abnormal Pl...

2012/03/06 NRR E-mail Capture - ME7110 Kewaunee Amendment Request- Chi-over-Q - AADB Request for Additional.

1NRR-PMDA-ECapture ResourceFrom: Feintuch, KarlSent: Friday, March 02, 2012 6:07 PMTo: Craig D SlyCc: Jack Gadzala; Blumberg, MarkSubject: ME7110 Kewaunee Amendment Request Re: Chi-over-Q - AADB Request for Additional Information (RAI) Attachments: ME7110 AADB (Blumberg) RAII ...

Watts Bar, Unit 2 - Final Safety Analysis Report, Amendment 108. Chapter 3 - Design of Structures, Components, Equipment, and Systems.

REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 3-iWATTS BARTABLE OF CONTENTSSection Title Page3.0 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 3.1-13.1.1 INTRODUCTION 3.1-13.1.2 WBNP CONFORMANCE WITH GDCS 3.1-13.1.2.1...

Nine Mile Point Station, Unit 1 - Final Written Examination with Answer Key (401-5 Format) (Folder 2).

ES-401 Written Examination Question Worksheet Examination Outline Cross-Reference: Level RO Tier # 1 Group # 1 KIA # 295001 AK3.03 Importance Rating 2.8 Partial or Complete Loss of Forced Core Flow Circulation Knowledge of the reasons for the following responses as they apply...

Monticello Nuclear Generating Plant - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies (TAC No. MF0923).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Ms. Karen D. Fili Site Vice President November 25, 2013 Northern States Power Company - Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362-9637 SUBJECT: MONTICELLO ...