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Westinghouse AP1000 Design Control Document Rev. 16 - Tier 2 Chapter 15 - Accident Analyses - APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS

15. Accident Analyses AP1000 Design Control Document Tier 2 Material 15A-1 Revision 16 APPENDIX 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS This appendix contains the parameters and models that form the basis of the radiolog...

MHI's Response to US-APWR DCD RAI No. 322-1999 (60-Day Response), SRP Section: 03.06.03 - Concrete and Steel Internal Structures of Steel or Concrete Containments.

AkMITSUBISHI HEAVY INDUSTRIES, LTD.16-5, KONAN 2-CHOME, MINATO-KUTOKYO, JAPANJune 4, 2009Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001Attention: Mr. Jeffery A. CioccoDocket No. 52-021MHI Ref: UAP-HF-09278Subject: MHI's Response to US-APWR DCD...

Slides of Browns Ferry Unit 1 Restart Inspection Plan and Schedule (IP&S) Report.

Browns Ferry Unit 1 RestartInspection Plan and Schedule (IP&S) Report In accordance with MC 2509, the NRC staff has developed IP&S which collects and provides inspection requirements for areas that comprise the BF1 Restart Project Inspection Program. This IP&S tracking tool ...

Millstone, Unit 2 and 3, Tech Spec Pages for Amendments 291 and 229 regarding Administrative Changes to Technical Specifications.

INDEXLIMITING CONI)ITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTSSECTION PAGE3/4.0 APPLTCABILITY ............... 3/4 0-13/4.1 REACTIVITY CONTROL SYSTEMS3/4.1.1 REACTIVITY CONTROL .3/4 1-1Shutdown Margin (SDM) . 3/4 1-1DELETED .3/4 1-2Reactivity Balance .3/4 1-3Boron Diluti...

IR 05000369-05-03 and IR 05000370-05-03, on 04/01/2005 - 06/30/2005, McGuire Nuclear Station, Units 1 and 2; Fire Protection and Other Activities.

July 22, 2005Duke Energy CorporationATTN: Mr. G. R. PetersonVice PresidentMcGuire Nuclear Station12700 Hagers Ferry RoadHuntersville, NC 28078-8985SUBJECT: MCGUIRE NUCLEAR STATION - NRC INTEGRATED INSPECTION REPORT05000369/2005003 AND 05000370/2005003Dear Mr. Peterson:On June ...

"Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2 'Post-Trip Review:Data & Info Capabilities' for Indian Point Station,Unit 2 (50-247)."

SA1C-85A1523-7REVIEW OF LICENSEE AND APPLICANT RESPONSES TO NRC GENERIC LETTER 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events), Item 1.2 "POST-TRIP REVIEW: DATA AND INFORMATION CAPABILITIES" FOR INDIAN POINT STATION, UNIT 2 (50-247) Technical Evalua...

Westinghouse Electric Co., Response to Open Item on Chapter 3 in Support of AP1000 Design Certification Amendment Application.

S)WestinghouseU.S. Nuclear Regulatory CommissionATTENTION: Document Control DeskWashington, D.C. 20555Westinghouse Electric CompanyNuclear Power PlantsP.O. Box 3 55Pittsburgh, Pennsylvania 15230-0355USADirect tel: 43-374-6206Direct fax: 724-940-8505e-mail: siskl rb@westinghous...

FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 34 - Partial - Group KK/LL, Part 6 of 6.

OPM4ALALSEONLYApril 26, 2011 0700 EDTOne-Pager - Fukushima DaiichiET Overview and Priorities. ET turnover: WebEOC turnover list, one-pager, list of major documents, tasker list, ET Log Book.- Plant and fuel pool conditions are generally unchanged.- Headquarters Operations Cent...

Indian Point Unit 3, Revision 8 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operations.

IP3 FSAR UPDATE Chapter 13, Page 1 of 38 Revision 08, 2019 CHAPTER 13 INITIAL TESTS AND OPERATIONS [Historical Information 13.1 TESTS PRIOR TO REACTOR INITIAL FUELING] A comprehensive testing program ensured that equipment and systems performed in accordance with the design...

Browns Ferry 2018-301 Exam Administrative Items (ADAMS-2C) - DELAY RELEASE 2 YRS.

ES-301 Administrative Topics Outline Form ES-301-1 Facility Browns Ferry NPP Date of Examination: __ 07-16-18 ___ Examination Level: RO ☒ SRO ☐ Operating Test Number: _18-04_____ Administrative Topic (see Note) Type Code* Describe activity to be perf...

"Response to IE Bulletin 79-01B for JA Fitzpatrick Nuclear Power Plant."

_. ...__ _ _ _ _ . --- _ - - - - - - _ -O*RESPONSE TONRC IE BULLETIN 79-01B'||FORJAMES A. FITZPATRICKNUCLEAR POWER PLANT|@POWER AUTHORITY OF THE STATE OF NEW YORKt!JUNE 1980APrepared ByOstea web ter E=vimeeri-o corner tie-New York8007010t%.. -. _ . . - .. - - - . _ _ _ _|<~wIf...

Watts Bar, Unit 1 - Application to Revise Technical Specifications for Component Cooling Water snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13).

  Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-088 June 17, 2015 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating Licens...

Indian Point, Unit 2, Updated Final Safety Analysis Report (UFSAR), Revision 25, Appendix A, Introduction.

IP2 FSAR UPDATE Page 1 of 33 Appendix A for License Renewal Revision 25, 2014 A.1 INTRODUCTION This appendix provides the information submitted in an Updated Final Safety Analysis Report Supplement as required by 10 CFR 54.21(d) for the Indian Point Energy Center (IPEC) ...

Forwards response to Generic Ltr 87-12, "Loss of Residual RHR While RCS Partially Filled."

.:ACCESSION NOR'ACIL:50-400AUTH. NAMEEURYz L. W.RECIP. NAMEREGULATO INFORMATION DISTRIBUTION STEM (RIDS)8709250145 DOC. DATE: 87/09/21 NOTARIZED: YESShearon Harris Nuclear Power Planti Unit ii CarolinaAUTHOR AFFILIATIONCarolina Power 8c Light Co.RECIPIENT AFFILIATIONDocument C...

Beaver Valley Power Station, Unit 2, Licensing Requirements Manual (LRM), Revision 90, Quick Index.

Unit 2 Licensing Requirements Manual (LRM) Quick Index 1.0 USE AND APPLICATION 1.0-1 1.0.1 General Description 1.0-1 1.0.2 LRM Revisions 1.0-2 1.1 Definitions 1.1-1 1.2 Logical Connectors 1.2-1 1.3 Completion Times 1.3-1 1.4 Frequency 1.4-1 3.0 LR APPLICABILIT...

River Bend Station, Unit 1, Amendment 1 to License Renewal Application.

,. ~ Entergy. Entergy Operations, Inc. River Bend Station :>485 U.S. Highway 61 N RBG-47883 August 2, 2018 Attn: Document Control Desk U.S_ Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852-2738 SUBJECT: Amendment 1 to License Renewal Application River Ben...

Limerick Generating Station, Units 1 & 2, Revision 19 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems.

LGS UFSARCHAPTER 05 5-i REV. 16, SEPTEMBER 2012CHAPTER 5 - REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMSTABLE OF CONTENTS5.1 SUMMARY DESCRIPTION5.1.1 Schematic Flow Diagram5.1.2 Piping and Instrumentation Diagrams5.1.3 Arrangement Drawings5.2...

Palisades Nuclear Plant - Improved Technical Specifications, Volume 20, Chapter 5.0.

·--, I I I ! : I I IMPROVED ! TIECHNICAL . I ' ' I : SPECIFICATIONS : I I ALI SADES UC LEAR LANT I ~------- _J Volume 20 CHAPTER 5.0 I -, t:ons11msrs Energy - . - I •~ • -· PALISADES NUCLEAR PLANT CONSUMERS ENERGY Docket 50-255 Conversion to Improved Technical Specifications L...

"Design Assessment Rept," Revision 6, revised pages.

LSCS-MARK II DAR Rev. 6 10/79TABLE OF CONrENTS (Con t ' d )PAGE4.2 CONTAINMENT LINER ASSESSMENT 4.2-14.2.1 General Description 4.2-14.2.2 Loads 4.2-14.2.3 Design Load Combinations 4.2-24.2.4 Acceptance Criteria 4.2-24.2.5 Analysis4.2-34.2.6 Conclusions4.2-44.3 MAIN DONNCOMER V...

Fermi Power Plant, Unit 2 - Integrated Inspection Report 05000341/2019002 and 07200071/2019001

P. Fessler - 2 - July 26, 2019 Mr. Paul Fessler, Senior VP and Chief Nuclear Officer DTE Energy Company Fermi 2 – 260 TAC 6400 North Dixie Highway Newport, MI 48166 SUBJECT: FERMI POWER PLANT, UNIT 2—INTEGRATED INSPECTION REPORT 05000341/2019002 AND 07200071/2019001 Dear...

Indian Point Unit 3, Revision 8 to Updated Final Safety Analysis Report, Chapter 18, Appendix A, License Renewal.

IP3 FSAR UPDATE Appendix A, Page 1 of 36 Revision 08, 2019 APPENDIX A LICENSE RENEWAL A.1 INTRODUCTION This appendix provides the information submitted in an Updated Final Safety Analysis Report Supplement as required by 10 CFR 54.21(d) for the Indian Point Energy Center (I...

Columbia - Emergency Action Level (EAL) Classification Matrix (Wallcharts) - Enclosure 1, Attachment 3.

GO2-16-104 Enclosure 1, Attachment 3 Emergency Action Level (EAL) Classification Matrix (Wallcharts) (For information only)ALL CONDITIONSGENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENTRG1.1RAbnormal Rad Levels/Rad Effluent1Rad Effluent2IrradiatedFuel EventHHazards...

Safety Evaluation for Vogtle Units 3 and 4 (LAR 17-006).

1 SAFETY EVALUATION BY THE OFFICE OF NEW REACTORS RELATED TO EXEMPTION AND AMENDMENT NOS. 85 AND 84 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 SPVJ...

Proposed tech specs changing TS 3.3.2.1, "Instrumentation - ESFAS Instrumentation," 3.4.9.3, "RCS - Overpressure Protection Sys" & ECCS - ECCS Subsystems - Tavg 300 F."

- ..- -.- - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .. .--~.-_ _ _ _ . . . ...

"Summary of Engineering Evaluation of ANO-1 High Pressure Injection Sys Backflow Condition."

. _ _ _ _ _ _ _ _I',.1,...1SUMMARY 0F ENGINEERING EVAltJATION OF'-ANO-1 HIGH PRESSURE INJECTIONl' SYSTEM BACKROW CONDITION 1.||:I ,!,'iFEBRUARY 14, 1989|0ffK0500034 890214 " DRP3PNh. m .;L,3-,.,e.-.SUMMARY OF. ENGINEERING EVALUATION''0F ANO-1-HIGH PRESSURE' INJECTION.;,.i:. SY...