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Westinghouse AP1000 Design Control Document Rev. 18 - 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 18 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...

NEI 04-07, Volume 2, "Pressurized Water Reactor Sump Performance Evaluation Methodology. Safety Evaluation by the Office of Nuclear Reactor Regulation re to NRC Generic Letter 2004-02, Rev. 0."

NEI 04-07 PRESSURIZED WATER REACTOR SUMP PERFORMANCE EV ALUATION METHODOLOGY Revision 0 December 2004 V olume 1 – Pressurized Water Reactor Sump Performance Evaluation Methodology Volume 2 – Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Gen...

AREVA Design Control Document Rev. 2 - Tier 2 Chapter 19 - Probabilistic Risk Assessment and Severe Accident Evaluation - Appendix 19A

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 2 Revision 2 Page 19A-119A Event Trees for Core Damage Sequences Initiated During Power OperationAppendix 19A presents the event trees that delineate the core-damage sequences for internal events initiated during power operation. T...

Submittal of Technical Report (4S Response to 73 FR 60612,"Policy Statement on the Regulations of Advanced Reactors" and SECY-10-0034,"Potential Policy, Licensing, and Technical Issues for Small Modular Nuclear Reactor Designs").

TOSHIBALeading Innovation >>>TOSHIBA CORPORATION1-1 ,SHIBAURA 1-CHOME, MINATO-KU TOKYO 105-8001,JAPANTOS-CR-4S-2010-0005October 12, 2010 Project Number 0760U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, DC 20555-0001Subject: Submittal of Technical Report [4...

Braidwood, Units 1 & 2 and Byron, Units 1 & 2 - Updated Final Safety Analysis Report, Revision 11, Attachment - H, "Braidwood Technical Specifications Bases," Stack 1 of 1.

ATTACHMENT - HBRAIDWOODTechnical Specifications Bases(TS Bases)Stack 1 of 1NuclearBraidwood Nuclear StationTechnical Specification Bases(TS Bases)December 2006Braidwood Station, Units 1 and 2Facility Operating License Nos. NPF-72 and NPF-77NRC Docket Nos. STN 50-456 and STN 50...

"Summary Technical Rept on Type A,B & C Leak Rate Tests Performed at Kewaunee Nuclear Power Plant From 1985 to 1987."

Attachment I Summary Technical Report on Type A, B, and C Leak Rate Tests Performed at the Kewaunee Nuclear Power Plant From 1985 to 1987 8707090194 870702 PDR ADOCK 05000305 p PDRTABLE OF CONTENTSI. II. III. IV.FIGURE II.1 FIGURE 11.2 TABLE III.1 TABLE 111.2 TABLE 111.3 /A...

McGuire, Units 1 and 2, Revision 52 of Offsite Dose Calculation Manual, 2011.

Offsite DoseCalculation Manual2011ODCMMcGuire Nuclear StationUnits 1 and 2 McGuire Nuclear Station Units 1 and 2 OFFSITE DOSE CALCULATION MANUAL (ODCM) Prepared By: C. D. Ingram General Office Radiation Protection Approved By: L. E. Haynes Fleet Sc...

Enclosure 4: Industry Handout Regarding the Overview of EPRI RI-ISI Methodologies for the May 4, 2011 Public Workshop.

Overview of the EPRI RI-ISI Methodologies2© 2011 Electric Power Research Institute, Inc. All rights reserved.Contents• Background• Status• EPRI Traditional RI-ISI Methodology• EPRI Streamlined RI-ISI Methodology3© 2011 Electric Power Research Institute, Inc. All rights reserve...

Forwards response to request for addl info re environ qualification of safety-related electrical equipment.Listing of design change requests in response to NUREG-0737, "Clarification of TMI Action Plan Items" encl.

REGULATOR INFORMATION DISTRIBUTION %TEM (RIDS) ACCESSION NBR:8208050276 D0C.DATE: 82/08/02 NOTARIZEO; NO FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic AUTHNAME AUTHOR AFFILIATION GIESLERC.W. Wisconsin Public Service Corp. RECIP.NAML RECIPIENT AFFILIATION ...

Diablo Canyon Power Plant, Unit Nos. 1 and 2 - Safety Evaluation for Topical Report on Diversity and In-Depth of New Process Protection System Replacement (TAC Nos. ME4094 and ME4095).

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 19,2011 Mr. John T. Conway Senior Vice President-Energy Supply and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant 77 Beale Street, Mail Code B32 San Francisco, CA 94...

Brunswick Initial Exam 2010-302 Draft SRO Written Exam.

76. S203000 G2.4.21 001During a LOCA with a LOOP the following plant conditions exist: 2B RHR pump Injecting and has just exceeded its NPSH Limit 2B CS pump Injecting and approaching its NPSH Limit All other ECCS Pumps Unavailable Reactor Water Level 2/3 core height and steady...

Attachment 1 - Volume 10, Kewaunee Power Station, Improved Technical Specifications Conversion, ITS Section 3.5, Emergency Core Cooling System (ECCS) , Revision 0.

ATTACHMENT 1 VOLUME 10 KEWAUNEE POWER STATION IMPROVED TECHNICAL SPECIFICATIONS CONVERSION ITS SECTION 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) Revision 0 Attachment 1, Volume 10, Rev. 0, Page 1 of 133Attachment 1, Volume 10, Rev. 0, Page 1 of 133LIST OF ATTACHMENTS 1....

2009 Dresden Initial License Examination Proposed Simulator Scenarios.

Dresden Generating Station ILT-N-1 SHUTDOWN U2 EDG FOLLOWING SURVEILLANCE TESTING CONTROL ROD RPIS FAILURE RFP VENT FAN TRIPS WITH FAILURE OF STANDBY TO AUTO START SPURIOUS ERV OPENING FWLC CONTROLLER SETPOINT DRIFTS HIGH RBCCW PUMP TRIP LOSS OF RBCCW DUE TO LEAK / MANUAL SCRA...

LER 08-002-01 for Callaway, Unit 1, Regarding Void Found in Line EM-023-HCB - Residual Heat Removal Pump "A" to Safety Injection Pumps.

~~ wAmeren UE AmerenUE Callaway Plant November 5,2009 u. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen: ULNRC-05660 PO Box 620 Fulton, MO 65251 1 OCFR50. 73(a)(2)(i)(B), 1 OCFR50. 73(a)(2)(v)(B), lOCFR50.73(a)(2)(v)...

Submittal of AP1000 Standard Technical Report APP-GW-GLN-108, Revision 2 (TR 108), "AP1000 Site Interface Temperature Limits".

PfWestinghouse Westinghouse Electric CompanyNuclear Power PlantsP.O. Box 3 5 5Pittsburgh, Pennsylvania 15230-0355USAU.S. Nuclear Regulatory Commission Direct tel: 412-374-6306ATTENTION: Document Control Desk Direct fax: 412-374-5005Washington, D.C. 20555 e-mail: sterdia@westin...

Vogtle - Request for Additional Information Regarding the Analysis of Severe Accident Mitigation Alternatives.

Tom TynanVice President - VogtleSouthern NuclearOperating Company, Inc.7821 River RoadWaynesboro, Georgia 30830Tel 706.826.3151Fax 706.826.3321SOUTHERNCOMPANYEnergy to Serve Your World'December 20, 2007Docket Nos. 50-424 & 50-425 NL-07-2255U.S. Nuclear Regulatory CommissionDoc...

Status Update on Issues Resulting from Review of a Condition Report on Feedwater Isolation Valves.

-FENOC Perry Nuclear Power Plant,% 10 Center RoadFirstEnergy Nuclear Operating Company Perry Ohio 44081Richard Anderson 440-280-5579Vice President-Nuclear Fax: 440-280.8029September 29, 2005PY-CEIINRR-2841 LUnited States Nuclear Regulatory CommissionDocument Control DeskWashin...

APP-GW-GLN-002, Rev. 0, "Zinc Addition."

AP1000 DOCUMENT COVER SHEETTDC:RFS#:Permanent File:RFS ITEM #:APY:AP1000 DOCUMENT NO. REVISION NO. ASSIGNED TOAPP-GW-GLN-002 I 0 | Page of IW-A. SterdisALTERNATE DOCUMENT NUMBER: WORK BREAKDOWN #:ORIGINATING ORGANIZATION: Westinghouse Electric CompanyTITLE: Zinc AdditionATTACH...

Changes from Revision 01 to Revision 02, DCD Tier 1, Section 1.

Changes From Revision 01 to Revision 02 Page 1 of 31 DCD Tier 1, Section 1 Item Location (e.g., subsection with paragraph/sentence/item, table with column/row, or figure) Description of Change 1 S1.1.1 Deleted “main transformer” in the paragraph that starts “Buildings and...

Vogtle, Units 1 and 2, Inservice Inspection Summary Report.

Southern Nuclear Operating Company, Inc. Post Off ice Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 January 22, 2007 Docket Nos.: 50-424 50-425 Energy to Serve bur WorldSY U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 V...

Response to U.S. EPR Design Certification Application RAI No. 22, Supplement 1, Revision 0, SRP Section: 19 - Probabilistic Risk Assessment and Severe Accident Evaluation Application Section: 19 SPLB Branch.

Response to Request for Additional Information No. 22, Supplement 1, Revision 0 7/3/2008 U. S. EPR Standard Design Certification AREVA NP Inc. Docket No. 52-020 SRP Section: 19 - Probabilistic Risk Assessment and Severe Accident Evaluation Application Section: 19 SPLB Branc...

Watts Bar 2013-302 Final SRO Written Exam.

Name: __________________________ _ 2013-302 SRO Exam Form: 0 Version: 0 76. Given the following: - The operating crew has entered 1-ES-1.1, "SI Termination," following an inadvertent Safety Injection. - As the crew is placing letdown in service, the OAC reports the following: ...

Comanche Peak, Units 1 and 2 - FSAR Amendment 108, Figures - Chapter 06 thru 08.

ll> '"'--:::=;; '~ 0 260 .._ m 0.. E Z40 ~ .2:2:0 200 0 400 Time (s) 800 Comanche Peak Final Safety Analysis Report Units 1 and 2 Containment Atmosphere Temperature Transient 4.3 te Split SLB Figure 6.2.1-3 Amendment No. 1 03 soo eoo Comanche Peak Final Safety Analysis Report ...

Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 5, Figure 5.2.2-3.

UNITS NO. 1 & 2 CONTAINMENT SECTIONAL ELEVATION MECH1 RIVERSIDE PLAZACOLUMBUS, OH 43215AEP SERVICE CORP.FSAR FIG. 5.2.2-3ARCH ELEC STRNUCLEAR PLANTDONALD C. COOKINDIANA MICHIGAN POWER COMPANYBRIDGMAN MICHIGANREVISED PER UCR 637 17113'-0"SPRINGLINE

AREVA Design Control Document Rev. 0 - Tier 1 Chapter 03 - Non-System Based Design Descriptions and ITAAC - List of Figures

U.S. EPR FINAL SAFETY ANALYSIS REPORTTier 1 Revision 0 Page 3-iiiCHAPTER 3—NON-SYSTEM BASED DESIGN DESCRIPTIONS AND ITAACLIST OF FIGURES Figure 3.5-1—Representative Containment Isolation Valve Arrangement ........... 3.5-23