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Clinton Power Station, Revision 21 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems.

CPS/USAR CHAPTER 05 5-i REV. 13, JANUARY 2009 CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS TABLE OF CONTENTS PAGE 5.1 SUMMARY DESCRIPTION 5.1-1 5.1.1 Schematic Flow Diagram 5.1-2 5.1.2 Piping and Instrumentation Diagram 5.1-3 5.1.3 Elevation Drawings 5.1 3 5.2...

Forwards list summarizing completion of util activities re NUREG-0737 requirements.Util will fulfill NUREG-0737 plant requirements upon completion of remaining actions.

REGULATORY ~jFORNATIONDISTRIBUTIONSY+N(RIBS)ACCESS/ON NBR:8504180220, DOC+DATE: 85/04/10 NOTARIZED: NO DOCKET ¹FACIL:50-323 Diablo Canyon Nuclear Power Planti Unit 2r Pacific Ga '5000323AUTH~NAME . AUTHOR AFFILIATION-SHIFFER,J,DE Pacific Gas L Electric Co.REC IP ~NAME REC IP I...

NRC Staff Review of the Documentation Provided by Duke Energy for the Oconee Nuclear Station Concerning Resolution of GL 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors

U.S. NUCLEAR REGULATORY COMMISSION STAFF REVIEW OF THE DOCUMENTATION PROVIDED BY DUKE ENERGY CAROLINAS, LLC FOR THE OCONEE NUCLEAR STATION UNITS 1, 2, AND 3 CONCERNING RESOLUTION OF GENERIC LETTER 2004-02 POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURI...

Attachment 8 - EP-AA-1010, Revised Radiological Emergency Plan Annex Information for Oyster Creek Nuclear Generating Station.

ATTACHMENT 8REVISED RADIOLOGICAL EMERGENCY PLANANNEX INFORMATIONFOROYSTER CREEK NUCLEAR GENERATING STATIONEP-AA-1 010EnclosuresS00Enclosure 8A - Revised EAL Comparison Matrix DocumentEnclosure 8B - Revised EAL Red-Line Basis DocumentsEnclosure 8C - Revised EAL Basis DocumentsN...

2015 Point Beach Nuclear Plant Initial License Examination Administered Written Examination.

Page 1 of 101 2015 PBNPP INITIAL LICENSE EXAMINATION REACTOR OPERATOR QUESTION # 001 Given the following: • Unit 1 is operating at Rated Thermal Power • A leak equivalent to 1/2 inch in diameter has developed on the line connecting the pressurizer to the PORVs Which of the...

Proposed tech specs re reactor protection sys test interval extension.

DUKE POWER COMPANY OCONEE NUCLEAR STATION ATTACHMENT 1 TECHNICAL SPECIFICATIONS Remove Page Insert Page 1-4 1-4 3.5-2 3.5-2 3.5-5c 3.5-5c 4.1-2 4.1-2 4.1-3 4.1-3 4.1-4 4.1-4 4.1-8 4.1-8 4.1-8a 4.1-8a 9212150098 921208 PDR ADOCK 05000269 P PDR1.5..5 Heat Balance Check A heat ba...

Request for Additional Information Letter Number 8 Related to Chapter 6 for GE-Hitachi Nuclear Energy Advanced Boiling-Water Reactor Design Certification Rule Renewal Application- GEH Response to RAI 06.03-2, Revision 1.

• HITACHI MFN-16-034, Revision 1 December 19, 2016 US Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 GE Hitachi Nuclear Energy Jerald G. Head Senior Vice President, Regulatory Affairs 3901 Castle Hayne Road P.O. Box780 M/CA-18 Wilmington, NC 2840...

Dresden Nuclear Power Station, Units 2 and 3 - Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 February 16, 2017 SUBJECT: DRESDEN NUCLEAR ...

Diablo Canyon, Units 1 and 2 - Letter Furnishing Tables and Information Regarding Environmental Qualifications of Class IE Equipment Which Might Be Exposed to Severe Environments.

~ >5}~3REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DISTRIBUTION FOR INCOMING MATERIAL50-27-l3'~:EC: STQt Z J FNRCORG: CRANE P A DOCDATE: 07/23l78PACIFIC GAS 5 ELEC DATE RCVD: 08/02/78DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVEDSUBJECT: LTR 1 ENCL 40;ORWARDING REVISION TO...

Responds to request for addl info re consideration of severe accident mitigation design alternatives.Tables listing current estimated core damage frequency per reactor yr & dominant population dose sequences encl.

, ,.--_ _- _._ . . - -'P ']b 'l it.k,.: 1 ,],PHILADELPHIA ELECTRIC COMPANYlNUCLEAR GROUP HEADQUARTERS1l.|955-65 CHESTERBROOK BLVD. 1'|WAYNE. PA 19087-5691(215) 640 6000June 23, 1989dDocket Nos. 50-352j50-353 ILicense.Nos..NPF-39i-NPF-83]!U.S. Nuclear Regulatory CommissionAttn:...

Transcript of 890413 briefing in Rockville,MD re status of implementation of severe accident master integration plan. Pp 1-44.Viewgraphs encl.

- -~. . .%.+ -'4-:CUNITED STATES OFjAMERICANUCLEAR REGULATORY COMMIS SIONgi''y ah.'1e',.3:. e''*$ 4).f NO BRIEFING ON STATUS OF IMPLEMENTATION OFSEVERE ACCIDENT MASTER INTEGRATION PLAN.,LOCatiOD: ROCKVILLE, MARYLAND..rC:"hDateAPRIL 13, 1989L4$ --- , ,,, .o.m.. j . >r_".,Pa9es:...

Nonproprietary Amend 2 to RESAR-SP/90 PDA Module 11, "Radiation Protection."

_______ _ - _ - _ _ _ ___ _ _ _ _ ___ _ ___ _ _ _ - _--__ _ _____ _ . _ _. . - _ . _ _ _ - - . .*,| ..e.!|' AMENDMENT 2 TO RESAR-SP/90 PDA MODULE 11; RADIATION PROTECTIONij._|9ii-i:;1!;ii-!4;!|9'i- 1i!I-.OWEC'P.O. Bsx 355Pittsburgh, PA 152300WAPWR-RPAMENDMENT 28004e:1...

Forwards "Fire Hazard Safe Shutdown Evaluation," resolving SER open items per 801009 discussion, & updated project status summary of fire protection mods.

---------- ---e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 October 31, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Reactor Licensing U.S. Nuclear Regulato...

Davis-Besse Nuclear Power Station, Unit 1, Revision 32 to Updated Final Safety Analysis Report, Section 12, Radiation Protection.

Davis-Besse Unit 1 Updated Final Safety Analysis Report 12-i UFSAR Rev 30 10/2014 SECTION 12 TABLE OF CONTENTS Section Title Page 12.0 RADIATION PROTECTION 12.1-1 12.1 SHIELDING 12.1-1 12.1.1 Design Objectives 12.1-1 12.1.1.1 Radiation Exposure of Materials and Componen...

St. Lucie, Unit 2 - License Amendment Request to Reduce the Number of Control Element Assemblies.

U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D C 20555-0001 RE: St. Lucie Unit 2 Docket No. 50-389 JUN 2 9 2018 Renewed Facility Operating Licenses NPF-16 L-2018-121 10 CFR 50.90 License Amendment Request to Reduce the Number of Control Element As...

James A. Fitzpatrick Nuclear Power Plant - Integrated Inspection Report 05000333/2019001.

May 14, 2019 Mr. Bryan C. Hanson Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT – INTEGRATED INSPECTION REPORT 05000333...

Robinson 2016-302 Retake ADAMS-2B Final Exam Items Normal Release.

- 1 - Nuclear Training Committed to Excellence OPERATIONS TRAINING N16-2RT-1 Initial Licensed Operator Training Rev 160726 Developed By: Date: Instructor/Developer Concurred By: Date: Line Superintendent...

Rev 1.2 to ODCM,Chapters 10,11,12 & App F.

-X244NRC C/0 30C C(RL DSK, C. PATEL' DIRECTOR OF fdUC. REACTOR REGULATION.U. S. NUC. REGULATORY COMMISSIONMAIL STATION P1-137WASHIhGTOf4DCOctober 25,1994?.0SSSAttached are the recent revisions to the Offsite Dose Calculation Manual's (OfCM) Chapters 10,11,12 and Appendix F for...

Nonproprietary "Amend 2 to RESAR-SP/90 PDA Module 9, 'Instrumentations & Controls & Electric Power.'"

- - . . . . .. - -_ _ -. _-.-... .--.. . _ . _ - _ . . _ . . - - _ . . _-..-__ _ .,s .-,4NESTINGHOUSE CLASS 3AMENDMENT 2 TO RESAR-SP/90 PDA MODULE 9'" INSTRUMENTATIONS & CONTROLS AND ELECTRIC POWER",il4i!ii;i'|IdBi.,,i;i.|: .'!:Ii,'!;;!I..1f:IiHAPHR-I&C/EPAMENDHENT 2i,14904e:I...

Callaway-2014-12 Draft Written Exam.

NRC Site-Specific Written Examination Callaway Plant Reactor Operator Examination Outline Cross-reference: Level RO Rev 0 Tier # 2 059 Main Feedwater Group # 1 K/A # A3.04 Importance Rating 2.5 Ability to monitor automatic operation of the MFW, including: Turbine dr...

Forwards response to open item identified in draft SER re structures,sys & components covered by QA program.Response provides ref to revised FSAR Table 3.2-1 & necessary justification for items not included.

_ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ __ _ ,j /'4.gGULF STATES UTILITIES COMEANYj' POS' OFFICE 8 0 x 2 9 51 .OEAUMONT. TEXAS 77704/AREA CCOE 713 038 6631!/ ,(,,c December 22, 1983RBG- 16,624/File Code: G9.5, G9.B.6.1/. ,V s/Mr. Harold R....

"Technical Evaluation of Oyster Creek Plant Unique Analysis Repts."

-. . .*...Technical Evaluation of the Oyster CreekPlant Unique Analysis Reports..John R'. LehnerGeorge Bienkowski- .-C. C. LinConstantino Economos.'..Reactor' Safety Licensing Assistance DivisionDepartment of Nuclear EnergyBrookhaven National Laboratory,Upton, New York 11973.S...

Rev 8 to EDA-3, "Offsite Dose Projections for McGuire Nuclear Station."

. ..4CRISIS MANAGEMENT PLANIMPLEMENTING PROCEDUREEDA - 3"Off-Site Dose Projections forMcGuire Nuclear Station"Y JJud66/7/Approved By Date|||l||,!|Rev. 8June 6, 1991'9106240343 910617PDRADOCK 05000269FPDRd. .EDA-30FF-SITE DOSE PROJECTIONSFOR MCGUIRE NUCLEAR STATION1.0 PURPOSE:1...

Seabrook - Draft - Outlines (Folder 2).

RANDOMSAMPLING PROCESS . 2010 SEABROOKLOITNRC WRITTENEXAM As required by NUREG 1021, Rev 9, Supplement 1, (ES-401 D.1.b), the licensee shall submit along with the NRC examination outline, a description of the systematic and random selection process used to develop the examin...