Report a Safety Concern
Search

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any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home Site Help

NRC Site Search: Search All Sites

Filter by Document Type

Sort Documents by

Insp Repts 50-295/88-09 & 50-304/88-10 on 880225-0413. Violation noted.Major areas inspected:licensee action on previous insp findings,summary of operations & erroneous setting of main steam safety valve lift setpoints on 880329.

>. ...U.S. NUCLEAR REGULATORY COMMISSIONREGION IIIReport Nos. 50-295/88009(DRP); 50-304/88010(DRP)'Docket Nos. 50-295; 50-304 License Nos. DPR-39; DPR-48Licensee: Commonwealth Edison CompanyP. O. Box 767Chicago, IL 60690Facility Name: Zion Nuclear Power Station, Units 1 and 2I...

IMC 2515 Appendix D Plant Status

Issue Date: 10/05/20 1 2515 Appendix D NRC INSPECTION MANUAL IRIB INSPECTION MANUAL CHAPTER 2515 APPENDIX D PLANT STATUS Effective Date: 01/01/2021 2515D-01 PURPOSE The Reactor Oversight Process recognizes that resident inspectors have a specific responsibility, ou...

Insp Rept 50-285/89-03 on 890101-31.Violation noted.Major areas inspected:previously identified items,LER followup, operational safety verification,plant tours,monthly maint observations & monthly surveillance observations.

_,,'-...-,APPENDIX B-U. S. NUCLEAR REGULATORY COMMISSIONREGION IVpS-NRC Inspection Report: .50-285/89-03 License: OPR-40- Docket: .50-285'Licensee:Omaha Public Power District.(0 PPD)1623 Harney Street ~Omaha, Nebraska .68102Facility Name:Fort.Calhoun' Station (FCS).Inspection ...

"B&W Owners Group Tech Spec Committee:Application of Selection Criteria to B&W STS."

--47-1170689-00)# P A T l L l ."|1 f A T C 1 f l eiApplication of Selection Criteria to theB&W Standard Technical Specificationspu "l#E3 iM$Babcock & Wilcox0 a McDermott company- _ - -__-_-_ _ _ _ _ _-_-_______ ___ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.i'47-1...

OFFICIAL EXHIBIT - COMMISSION MANDATORY HEARING - SNC000005-MA-CM01 - Southern Nuclear Operating Company's Response To the Commission's Order of August 31, 2011.

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION ____________________________________ ) In the Matter of ) Docket Nos. 52-025-COL and 52-026...

Watts Bar Nuclear Plant, Unit 2 - Amendment 102 to Final Safety Analysis Report (FSAR), Section 3 C, Redacted.

Concrete Shield Building 3.8.1-1WATTS BAR WBNP-102m3.8 DESIGN OF CATEGORY I STRUCTURES3.8.1 Concrete Shield BuildingThe Shield Building is a Category I structure in its entirety and is designed to remain functional in the event of a Safe Shutdown Earthquake (SSE) or a tornad...

Prairie Island Nuclear Generating Plant, Units 1 and 2 - Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) (TAC Nos. MF0834 and MF0835).

Mr. Kevin K. Davison Site Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 27, 2014 Northern States Power Company - Minnesota Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East Welch, MN 55089-9642 SUBJECT: PRAIRIE I...

SECY-14-0114: Enclosure 1 - Update on Tier 1 Activities

Enclosure 1 Update on Tier 1 Activities Mitigation Strategies Order EA-12-049 On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued Order EA-12-049, “Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis Exte...

AREVA Design Control Document Rev. 6 - Tier 2 Chapter 03 - Design of Structures, Components, Equipment and Systems - Section 3.4 Water Level (Flood) Design

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 6 Page 3.4-13.4 Water Level (Flood) DesignIn accordance with GDC 2 and RG 1.29, the Seismic Category I structures, systems, and components (SSC) identified in Table 3.2.2-1 can withstand the effects of flooding due to nat...

Attachment 9: Discussion of Revision to the Radiological Emergency Plan Annex for Peach Bottom Atomic Power Station, Cover through Page PBAPS 3-76.

ATTACHMENT 9DISCUSSION OF REVISIONTO THERADIOLOGICAL EMERGENCY PLAN ANNEXFORPEACH BOTTOM ATOMIC POWER STATIONEP-AA-1007Enclosures* Enclosure 9A - EAL Comparison Matrix Document* Enclosure 9B - EAL Red-Line Basis Document* Enclosure 9C - EAL Basis DocumentNEI 99-01REVISION 6DEV...

0522 - 504B - GE BWR4 Advanced Technology - Chapt 4.2 ATWS (0912).

General Electric Advanced Technology Manual Chapter 4.2 Anticipated Transient Without Scram Rev 0912 4.2-i USNRC HRTD TABLE OF CONTENTS 4.2 ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) ................................... 1 4.2.1 Introduction ..........

2012/10/25 Areva EPR DC - Response to U.S. EPR Design Certification Application RAI No. 550 (6501), FSAR Ch. 9 - NEW PHASE 4 RAI - Fukushima, Supplement 1

1ArevaEPRDCPEm ResourceFrom: WILLIFORD Dennis (AREVA) [Dennis.Williford@areva.com]Sent: Thursday, October 25, 2012 2:51 PMTo: Snyder, AmyCc: Hearn, Peter; BENNETT Kathy (AREVA); DELANO Karen (AREVA); LEIGHLITER John (AREVA); ROMINE Judy (AREVA); RYAN Tom (AREVA); KOWALSKI Davi...

Sequoyah, Units 1 and 2, Enclosure 2 - Volume 3 - Improved Technical Specifications Conversion, ITS Chapter 1.0, Use and Application, Revision 0.

ENCLOSURE 2 VOLUME 3 SEQUOYAH NUCLEAR PLANT UNIT 1 AND UNIT 2 IMPROVED TECHNICAL SPECIFICATIONS CONVERSION ITS CHAPTER 1.0 USE AND APPLICATION Revision 0 Enclosure 2, Volume 3, Rev. 0, Page 1 of 117Enclosure 2, Volume 3, Rev. 0, Page 1 of 117LIST OF ATTACHMENTS 1. ...

Limerick Generating Station, Units 1 and 2 - Issuance of Amendments Re: Elimination of Certain Technical Specifications Reporting Requirements (TAC Nos. MF1399 and MF1400).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 26, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: LIMERICK GENERATING STATION, UNITS 1 AND 2- ISSUANCE OF AMENDMENTS...

McGuire 2012-301 Draft SRO Written Exam.

FOR REVIEW ONLY - DO NOT DISTRIBUTE2012 MNS SRO NRC Examination QUESTION 76A 76 Given the following conditions on Unit 1: • The unit is performing a normal NC system cooldown for refueling • Current NC temperature is 400°F • 1FWST boron is 2650 PPM Per SLC 16.9.11 (Bora...

Palo Verde, Units 1, 2, and 3 - Updated Final Safety Analysis Report, Revision 16. Chapter 7, "Instrumentation & Controls."

PVNGS UPDATED FSAR June 2009 7-i Revision 15 CHAPTER 7 INSTRUMENTATION AND CONTROLS CONTENTS Page 7.1 INTRODUCTION 7.1-1 7.1.1 IDENTIFICATION OF SAFETY-RELATED SYSTEMS 7.1-1 7.1.1.1 Protection System 7.1-1 7.1.1.2 Reactor Trip System 7.1-2 7.1.1.3 Engineered Safety Feature Sys...

Seabrook - Draft Written Exam (Folder 2).

Seabrook Station 2013 Written Exam ES-401.5 I Seabrook Station 2013 Licensed Operator NRC Written Exam ES-401-5 Written Examination Question Worksheet I Examination Outline Cross-reference: Level RO SRO Tier # 1IQ1 I I !• Group # 1 KIA # 007 Reactor Trip i EK3 Knowledge ...

Dresden, Units 2 & 3, LaSalle, Units 1 & 2 and Quad Cities, Units 1 & 2 - License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, "Use of...

Exelon Generation RS-14-322 10 CFR 50.90 December 22, 2014 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 ...

License Amendment Request Revise Technical Specifications Definition for Recently Irradiated Fuel.

o200 Exelon WayEKennett Square. PA 19348Exe~on Generation. www.exeloncorp.com10 CFR 50.90July 25, 2014U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Peach Bottom Atomic Power Station, Units 2 and 3Renewed Facility Operating License Nos. D...

Vermont Yankee change 182 for document entitled, "Implementing Procedures to the E-Plan."

1-U1 IUIN I DOCUMENT TITLE: COPY NUMBER: CHANGE NUMBER: ISSUE DATE: INSTRUCTIONS:IMPLEMENTING PROCEDURES TO THE E-PLAN #182 March 28, 2000a. Attached is an authorized controlled copy to the above listed document for retention as your assigned copy. b. Review the revised mate...

Letter forwarding FR notice, proposed amendment & safety evaluation to license DPR-18

DISTRIBUTION W. Dooly, DR R. Engelken, CO (2) H. K. Shaoar, OGC N. Dube, DRL (5) J. R. Buchanan, ORNL SAN 2 , 0 H. J. McAlduff, OROO W. B. Kenna, NMS, OR T. W. Laughlin, DTIE PDR Docket .lo. 50-244 Docket File DRL Reading Branch Reading Rochester Gas and Electric Corporation 2...

Palisades Nuclear Plant, Emergency Implementing Procedure EI-1,Revision 37, "Emergency Classification and Actions."

Date Entered: Oct 10, 2001TO: USNRC/WASHINGTON JMCKNIGHTCopy Number: 145TRANSMiTAL NUMBER: 202039PROCEDURE NUMBER: El-1 TITLE: EMERGENCY CLASSIFICATION AND ACTIONS TRANSMITTAL: LISTED BELOW ARE NEW/REVISED PROCEDURES WHICH MUST BE IMMEDIATELY INSERTED INTO OR DISCARDED FROM YO...

Vermont Yankee - Request for Alternative Testing for 10CFR50.55a(a)(3)(i) Regarding Inservice Testing Program - Excess Flow Check Valves

VERMONT YANKEE NUCLEAR POWER CORPORATION 185 OLD FERRY ROAD, PO BOX 7002, BRATTLEBORO, VT 05302-7002 (802) 257-5271 October 31, 2000 BVY 00-99 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Subject: Vermont Yankee Nuclear Power Station Li...

Issuance of amendment 53 to license DPR-18 approving provisions which update fire protection system operability & surveillance requirements,safety evaluation & FR notice

July 29, 1982 Dockdt No. 50-244 LS05-82-07-074 11r. John E. Maier Vice President Electric and Steam Production Rochester.Gas & Electric Corporation 89 East Avenue Roohester, New York 14649DISTRIBUTION Docket NRC PDR Local PDR ORB Reading NSIC DCrutchfield HSmith (2) JLyons OEL...

H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-261/LICENSE NO DPR-23 REQUEST FOR TECHNICAL SPECIFICATIONS CHANGE FOR ULTIMATE HEAT SINK (UHS)

10 CFR 50.90CP&L Carolina Power & Light Company Robinson Nuclear Plant 3581 West Entrance Road Hartsville SC 29550 Serial: RNP-RA/00-0053 JUN 5 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNI...