This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and

Size: px
Start display at page:

Download "This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and"

Transcription

1 This document is the property of and contains Proprietary Information owned by Westinghouse Electric Company LLC and/or its subcontractors and suppliers. It is transmitted to you in confidence and trust, and you agree to treat this document in strict accordance with the terms and conditions of the agreement under which it was provided to you. 1

2 Westinghouse Non-Proprietary Class 3 Westinghouse AP1000 Classification of Systems, Structures and Components (SSC) Jurie van Wyk Small Modular Reactor Development April NESCC Meeting, Washington DC 2

3 SCC Classification Basis Documents A 51.1 Nuclear Safety Criteria NRC Regulatory Guide 1.26 Quality Group Classification NRC Regulatory Guide 1.29 Seismic Design Classification NRC Regulatory Guide 1.97 Criteria for Accident Monitoring AP1000 DCD Chapter 3.2: 3 Leverage the knowledge of existing fleets and AP1000 for the historical classification basis on SSC s

4 Safety-related function Basis of A 51.1 Safety Related Functions are provided during or following a design basis event: Integrity of the reactor coolant pressure boundary Capability to shut down the reactor and maintain shut down Capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10 CFR The three basic safety related functions 4

5 Seismic Classification (Regulatory Guide 1.29) Seismic Category I SSC that perform safety related function SSC that support or protect SSC s with safety related function Seismic Category II (Westinghouse class) SSC designed to prevent their collapse under the safe shutdown earthquake SSC to preclude their structural failure during a safe shutdown earthquake or interaction with Seismic Category I items which could degrade the functioning of a safety-related SSC to an unacceptable level, or could result in incapacitating injury to occupants of the main control room. Non Seismic Class - Follow Uniform Building Code Westinghouse Seismic Class II criterion is in conformance with the definition of Regulatory Guide

6 Purpose Westinghouse SMR(AP1000) Classification System The classification system provides how SSC relate to Safety related function and seismic classification Quality Group classification related to codes and standards The classification system provides how SSC related to: A nuclear safety classification NRC quality groups, ASME Code, Section III classification, Electrical and other applicable industry standards Test and Inspection Maintenance requirements Clear relation between SSC safety function and their quality requirement 6

7 Westinghouse AP1000 or SME Safety Classification Equipment Class A Same as A 51.1 Safety Class 1 Most Passive Safety components received this classification (Core make up tank, ADS valves etc..) Equipment Class B Same as A 51.1 Safety Class 2 Equipment Class C Same as A 51.1 Safety Class 3 Equipment Class D Same as A 51.1 Non Nuclear Safety Class SSC that directly acts to prevent unnecessary actuation of the passive safety systems which support those which directly act to prevent the actuation of passive safety systems Equipment Class E,F,G,L,P,R,W - Same as A 51.1 None Nuclear Safety Related Class. NRC Approved the Passive Safety Approach in the AP1000 DCD 7

8 Westinghouse AP1000 or SME Comparison of Safety Classification Requirements COMPARISON OF SAFETY CLASSIFICATION REQUIREMENTS AP1000 Code Letter A Equipment Safety Class RG 1.29 Seismic Design Reqmnts ASME Code, Sec. III Class IEEE Requirements RG 1.26 NRC Quality Group 10 CFR 50 Appendix B Inspection & Testing Requirements Required Test & Maint. A SC-1 I 1 NA GROUP A YES YES T+A B SC-2 I 2 NA GROUP B YES YES T+A C SC-3 I 3 1E GROUP C YES YES T+A D N II or ASME VIII C37 GROUP D YES or NO YES A E,F,L P,R,W N II or NA NA NA YES or NO NA NA Seismic 1&II follow ASCE Standard 4-98 or IEEE-344 follow UBC T= Tech Specs (ASME XI) A= Administrative Reliability Assurance Program Safety Classifications are related to quality standards based on their function 8

9 SMR Classification Requirements Structures SEISMIC CLASSIFICATION OF BUILDING STRUCTURES Structure Nuclear Island Basemat Containment Interior Shield Building Auxiliary Building Containment Air Baffle Containment Vessel Plant Vent and Stair Structure Turbine Building First bay adjacent to Nuclear Island outlined by Columns I.1 to R and to 11.2 Turbine Building All portions of Turbine Building except first bay adjacent to Nuclear Island as outlined by Columns H.05 to R and 12.1 to 20 Turbine Building Annex Building Area Outlined by Columns A - D and 8-13 Area Outlined by Columns A - G and Category C-I C-I C-II C-II Annex Building Area Outlined by Columns E - I.1 and 2-13 C-II Radwaste Building Diesel-Generator Building Circulating Water Pumphouse and Towers Category II prevent their collapse under the safe shutdown earthquake 9

10 SMR Classification Requirements System AP1000 CLASSIFICATION OF MECHANICAL AND FLUID SYSTEMS, COMPONENTS, AND EQUIPMENT Tag Number Description AP1000 Class Seismic Category Principal Construction Code Passive Containment Cooling System Location: Containment Shield Building and Auxiliary Building PCS-MT-05 Passive Containment Cooling D II API 650 Ancillary Water Storage Tank Comments PCS-PL-V001A PCCWST Isolation C I ASME III-3 PCS-PL-V047A/B PCS Recirculation Pump Discharge Isolation line D AI B16.34 Equipment Anchorage is Seismic Category II Passive Core Cooling System (PXS) Location: Containment PCS-PL-V004 Recirculation Bypass D AI B16.34 Equipment Anchorage is Seismic Category II PXS-PL-V015B CMT B Discharge Isolation A I ASME III-1 PXS-MT-03 In-Containment Refueling Water Storage Tank C I ACI 349/AISC N690 ACI 349 is used for Evaluation of Structural Boundary More than 75 pages of AP1000 component safety classifications to be used as basis for passive safety plants 10

11 Questions 11

Westinghouse. U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555. February 16, 2010

Westinghouse. U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555. February 16, 2010 Westinghouse Westinghouse Electric Company Nuclear Power Plants P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C.

More information

3. Design of Structures, Components,

3. Design of Structures, Components, 3.2 ification of Structures, Components, and Systems Structures, systems, and components in the are classified according to nuclear safety classification, quality groups, seismic category, and codes and

More information

U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION

U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGULATION NUREG-0800 (Formerly NUREG-75/087) 9.2.2 REACTOR AUXILIARY COOLING WATER SYSTEMS REVIEW RESPONSIBILITIES Primary

More information

AP1000 Overview. 2011 Westinghouse Electric Company LLC - All Rights Reserved

AP1000 Overview. 2011 Westinghouse Electric Company LLC - All Rights Reserved AP1000 Overview AP1000 is a registered trademark in the United States of Westinghouse Electric Company LLC, its subsidiaries and/or its affiliates. This mark may also be used and/or registered in other

More information

2. System Based Design Descriptions and ITAAC AP1000 Design Control Document

2. System Based Design Descriptions and ITAAC AP1000 Design Control Document 2.3.2 Chemical and Volume Control System Design Description The chemical and volume control system (CVS) provides reactor coolant system (RCS) purification, RCS inventory control and makeup, chemical shim

More information

Westinghouse AP1000 PWR and the Growing Market for New Nuclear Power Plants

Westinghouse AP1000 PWR and the Growing Market for New Nuclear Power Plants Westinghouse AP1000 PWR and the Growing Market for New Nuclear Power Plants Westinghouse Electric Company & The Nuclear Fuel Cycle Royal Commission - South Australia November 4, 2015 1 AP1000 is a trademark

More information

Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]

Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1] Nuclear Safety Council Instruction number IS-22, of July 1st 2009, on safety requirements for the management of ageing and long-term operation of nuclear power plants Published in the Official State Gazette

More information

Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants

Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants Published in the Official State Gazette (BOE) No 283 of November 24 th 2009 Nuclear Safety Council Instruction

More information

AP1000DCDFileNPEm Resource

AP1000DCDFileNPEm Resource AP1000DCDFileNPEm Resource From: Ray, Thomas J. [raytj@westinghouse.com] Sent: Tuesday, August 17, 2010 3:07 PM To: Buckberg, Perry; Jaffe, David Cc: Patterson, Malcolm; Brehm, Jason A. Subject: RE: Seismic

More information

This occurrence is considered to be of no significance with respect to the health and safety of the public.

This occurrence is considered to be of no significance with respect to the health and safety of the public. Serial No. MNS-15-072 September 10, 2015,. DUKESteven Vice D. President Capps, ENERGYMcGuire Nuclear Station Duke Energy MGOIVP 1 12700 Hagers Ferry Road Huntersville, NC 28078 0: 980.875.4805 f: 980.875.4809

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS WASHINGTON, DC 20555-0001.

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS WASHINGTON, DC 20555-0001. OMB Control No.: 3150-0012 ML12074A115 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION OFFICE OF NEW REACTORS WASHINGTON, DC 20555-0001 July 27, 2012 NRC BULLETIN 2012-01:

More information

How To Clean Up A Reactor Water Cleanup

How To Clean Up A Reactor Water Cleanup General Electric Systems Technology Manual Chapter 2.8 Reactor Water Cleanup System TABLE OF CONTENTS 2.8 REACTOR CLEANUP SYSTEM... 1 2.8.1 Introduction... 2 2.8.2 System Description... 2 2.8.3 Component

More information

OWestinghouse 7I~J_6B. Westinghouse Electric Company Nuclear Power Plants P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA

OWestinghouse 7I~J_6B. Westinghouse Electric Company Nuclear Power Plants P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA OWestinghouse Westinghouse Electric Company Nuclear Power Plants P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C.

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001. June 16, 2011

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001. June 16, 2011 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, DC 20555-0001 June 16, 2011 NRC INFORMATION NOTICE 2011-12: REACTOR TRIPS RESULTING FROM WATER INTRUSION INTO

More information

Boiling Water Reactor Systems

Boiling Water Reactor Systems Boiling Water (BWR) s This chapter will discuss the purposes of some of the major systems and components associated with a boiling water reactor (BWR) in the generation of electrical power. USNRC Technical

More information

APPENDIX B SUPPLEMENTAL INSPECTION PROGRAM A. OBJECTIVES AND PHILOSOPHY OF THE SUPPLEMENTAL INSPECTION PROGRAM

APPENDIX B SUPPLEMENTAL INSPECTION PROGRAM A. OBJECTIVES AND PHILOSOPHY OF THE SUPPLEMENTAL INSPECTION PROGRAM APPENDIX B SUPPLEMENTAL INSPECTION PROGRAM A. OBJECTIVES AND PHILOSOPHY OF THE SUPPLEMENTAL INSPECTION PROGRAM The supplemental inspection program is designed to support the NRC s goals of maintaining

More information

Westinghouse - NEI ML022260412. To meet with Westinghouse to discuss their construction. scheduling software. TITLE. Sr.

Westinghouse - NEI ML022260412. To meet with Westinghouse to discuss their construction. scheduling software. TITLE. Sr. I -. - -4 NRC FORM 658 (9-1999) U.S. NUCLEAR REGULATORY COMMISSION TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed)

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001. June 1, 2005

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001. June 1, 2005 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 June 1, 2005 NRC INFORMATION NOTICE 2005-14: FIRE PROTECTION FINDINGS ON LOSS OF SEAL COOLING

More information

AP1000 Technology: Passive & Proven

AP1000 Technology: Passive & Proven AP1000 Technology: Passive & Proven The Right Fit for Brazil Jeff Benjamin Senior Vice President Nuclear Power Plants (NPP) AP1000 is a trademark or registered trademark of Westinghouse Electric Company

More information

DRAFT REGULATORY GUIDE DG-1154 (Proposed Revision 2 of Regulatory Guide 1.128, dated October 1978)

DRAFT REGULATORY GUIDE DG-1154 (Proposed Revision 2 of Regulatory Guide 1.128, dated October 1978) U.S. NUCLEAR REGULATORY COMMISSION October 2006 OFFICE OF NUCLEAR REGULATORY RESEARCH Division 1 DRAFT REGULATORY GUIDE Contact: W.S. Raughley (301) 415-7577 DRAFT REGULATORY GUIDE DG-1154 (Proposed Revision

More information

Reconsideration of Application of GDC-4 Exclusion of Local Dynamic Effects to Local Debris Generation

Reconsideration of Application of GDC-4 Exclusion of Local Dynamic Effects to Local Debris Generation Reconsideration of Application of GDC-4 Exclusion of Local Dynamic Effects to Local Debris Generation April 2010 In October 1987, General Design Criterion (GDC) 4 in Appendix A to 10 C.F.R. Part 50 was

More information

Nuclear Power Plant Electrical Power Supply System Requirements

Nuclear Power Plant Electrical Power Supply System Requirements 1 Nuclear Power Plant Electrical Power Supply System Requirements Željko Jurković, Krško NPP, zeljko.jurkovic@nek.si Abstract Various regulations and standards require from electrical power system of the

More information

STEP 3 ELECTRICAL SYSTEMS ASSESSMENT OF THE WESTINGHOUSE AP1000 DIVISION 6 ASSESSMENT REPORT NO. AR 09/019-P

STEP 3 ELECTRICAL SYSTEMS ASSESSMENT OF THE WESTINGHOUSE AP1000 DIVISION 6 ASSESSMENT REPORT NO. AR 09/019-P Health and Safety Executive NUCLEAR DIRECTORATE GENERIC DESIGN ASSESSMENT NEW CIVIL REACTOR BUILD STEP 3 ELECTRICAL SYSTEMS ASSESSMENT OF THE WESTINGHOUSE AP1000 DIVISION 6 ASSESSMENT REPORT NO. AR 09/019-P

More information

Quality Management System-A Revision 7 (NRC-approved Version)

Quality Management System-A Revision 7 (NRC-approved Version) Westinghouse Non-Proprietary Class 3 2013 Westinghouse Electric Company LLC. All Rights Reserved. Quality Management System-A (NRC-approved Version) Westinghouse Electric Company Quality Management System

More information

C.I.8.2 Offsite Power System. C.I.8.2.1 Description

C.I.8.2 Offsite Power System. C.I.8.2.1 Description C.I.8 Electric Power The electric power system is the source of power for station auxiliaries during normal operation, and for the reactor protection system and ESF during abnormal and accident conditions.

More information

Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos.

Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. Exelon Generation 200 Exelo11 Way Kennett Square. PA 19348 www.pxeloncoroi.c cm 10 CFR 50.55a August 13, 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Peach

More information

L.S. de Carvalho, J. M de Oliveira Neto 1. INTRODUCTION IAEA-CN-164-5P01

L.S. de Carvalho, J. M de Oliveira Neto 1. INTRODUCTION IAEA-CN-164-5P01 IAEA-CN-164-5P01 Advanced Technology Application Station Blackout Core Damage Frequency Reduction The Contribution of AN AC Independent Core Residual Heat Removal System L.S. de Carvalho, J. M de Oliveira

More information

Results and Insights of Internal Fire and Internal Flood Analyses of the Surry Unit 1 Nuclear Power Plant during Mid-Loop Operations*

Results and Insights of Internal Fire and Internal Flood Analyses of the Surry Unit 1 Nuclear Power Plant during Mid-Loop Operations* BNL-NUREG-61792 Results and Insights of Internal Fire and Internal Flood Analyses of the Surry Unit 1 Nuclear Power Plant during Mid-Loop Operations* Tsong-Lun Chu, Zoran Musicki, and Peter Kohut Brookhaven

More information

INTRODUCTION. Three Mile Island Unit 2

INTRODUCTION. Three Mile Island Unit 2 INTRODUCTION here was an accident at Three Mile Island Unit 2 on March 28,1979. It caused extensive damage to the plant's nuclear fuel core. Most of the plant's major systems were relatively undamaged.

More information

Nuclear power plant systems, structures and components and their safety classification. 1 General 3. 2 Safety classes 3. 3 Classification criteria 3

Nuclear power plant systems, structures and components and their safety classification. 1 General 3. 2 Safety classes 3. 3 Classification criteria 3 GUIDE 26 June 2000 YVL 2.1 Nuclear power plant systems, structures and components and their safety classification 1 General 3 2 Safety classes 3 3 Classification criteria 3 4 Assigning systems to safety

More information

Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT

Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT 24 th September 2014 Table of Content WENRA Safety Reference Levels

More information

Regulatory Guide 1.168 Verification, Validation, Reviews, And Audits For Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Regulatory Guide 1.168 Verification, Validation, Reviews, And Audits For Digital Computer Software Used in Safety Systems of Nuclear Power Plants Regulatory Guide 1.168 Page 1 of 10 September 1997 Regulatory Guide 1.168 Verification, Validation, Reviews, And Audits For Digital Computer Software Used in Safety Systems of Nuclear Power Plants Publication

More information

Generic PCSR Sub-chapter 15.4 : Electrical Equipment

Generic PCSR Sub-chapter 15.4 : Electrical Equipment Form10/00 Document ID : GA91-9101-0101-15004 Document Number : EE-GDA-C284 Revision Number : A Generic Design Assessment Generic PCSR Sub-chapter 15.4 : Electrical Equipment Hitachi-GE Nuclear Energy,

More information

First Quarter 2014 Earnings Conference Call. New Nuclear Presentation Section. April 24, 2014 First Quarter 2014 Earnings Conference Call 1

First Quarter 2014 Earnings Conference Call. New Nuclear Presentation Section. April 24, 2014 First Quarter 2014 Earnings Conference Call 1 First Quarter 2014 Earnings Conference Call New Nuclear Presentation Section April 24, 2014 1 Safe Harbor Statement/Regulation G Information Statements included in this presentation which are not statements

More information

RADIATION MONITORING SYSTEMS

RADIATION MONITORING SYSTEMS RADIATION MONITORING SYSTEMS Area monitors Process monitors In-line, Adjacent-to-Line monitors Local/remote processors, Data Acquisition Systems NUPIC Certified, NRC Approved Vendor Wide Range Sensitivity

More information

Introductions: Dr. Stephen P. Schultz

Introductions: Dr. Stephen P. Schultz Introductions: Dr. Stephen P. Schultz Vienna, Austria 1 3 September 2015 Work Experience Current Member Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 12/2011 Chair, Fukushima

More information

Government Degree on the Safety of Nuclear Power Plants 717/2013

Government Degree on the Safety of Nuclear Power Plants 717/2013 Translation from Finnish. Legally binding only in Finnish and Swedish. Ministry of Employment and the Economy, Finland Government Degree on the Safety of Nuclear Power Plants 717/2013 Chapter 1 Scope and

More information

Public SUMMARY OF EU STRESS TEST FOR LOVIISA NUCLEAR POWER PLANT

Public SUMMARY OF EU STRESS TEST FOR LOVIISA NUCLEAR POWER PLANT 1 (8) SUMMARY OF EU STRESS TEST FOR LOVIISA NUCLEAR POWER PLANT 1 LOVIISA NUCLEAR POWER PLANT Loviisa town is located approximately 90 km eastwards from Helsinki at the coast of Gulf of Finland. Loviisa

More information

WHITE PAPER PROPOSED CONSEQUENCE-BASED PHYSICAL SECURITY FRAMEWORK FOR SMALL MODULAR REACTORS AND OTHER NEW TECHNOLOGIES

WHITE PAPER PROPOSED CONSEQUENCE-BASED PHYSICAL SECURITY FRAMEWORK FOR SMALL MODULAR REACTORS AND OTHER NEW TECHNOLOGIES WHITE PAPER PROPOSED CONSEQUENCE-BASED PHYSICAL SECURITY FRAMEWORK FOR SMALL MODULAR REACTORS AND OTHER NEW TECHNOLOGIES November 2015 ACKNOWLEDGMENT This NEI White Paper was developed by the NEI Small

More information

Office for Nuclear Regulation

Office for Nuclear Regulation ONR GUIDE Essential Services Document Type: Nuclear Safety Technical Assessment Guide Unique Document ID and Revision No: Date Issued: May 2013 Review Date: May 2016 Approved by: D Senior Director Regulatory

More information

WordPerfect Document Compare Summary

WordPerfect Document Compare Summary WordPerfect Document Compare Summary Original document: P:\RG 1.206 draft\c.iii.5.wpd Revised document: @PFDesktop\:MyComputer\C:\Documents and Settings\dlc3.NRCDOMAIN\Application Data\NRC\ADAMSDesktop\Cache\ML0706300310.wpd

More information

Wilfred C. LaRochelle Principal Nuclear Consultant HSB Global Standards, USA

Wilfred C. LaRochelle Principal Nuclear Consultant HSB Global Standards, USA Wilfred C. LaRochelle Principal Nuclear Consultant HSB Global Standards, USA ASME Vice President, Conformity Assessment and Vice Chairman of Committee on Nuclear Certification 2nd NRC Workshop on Vendor

More information

Operational Reactor Safety 22.091/22.903

Operational Reactor Safety 22.091/22.903 Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Lecture 19 Three Mile Island Accident Primary system Pilot operated relief valve Secondary System Emergency

More information

Control of Hazardous Energy LOCKOUT/TAGOUT 29 CFR 1910.147

Control of Hazardous Energy LOCKOUT/TAGOUT 29 CFR 1910.147 Control of Hazardous Energy LOCKOUT/TAGOUT 29 CFR 1910.147 Contents I. Introduction II. Scope and Application III. Definitions IV. Lockout/Tagout Manual V. Energy Control Procedures 1. Applying Energy

More information

7.1 General 5 7.2 Events resulting in pressure increase 5

7.1 General 5 7.2 Events resulting in pressure increase 5 GUIDE YVL 2.4 / 24 Ma r ch 2006 Primary and secondary circuit pressure control at a nuclear power plant 1 Ge n e r a l 3 2 General design requirements 3 3 Pressure regulation 4 4 Overpressure protection

More information

How To License A Nuclear Plant

How To License A Nuclear Plant Contents Introduction... 1 Two-Step Licensing Process (10 CFR Part 50)... 2 Construction Permit... 2 Operating License... 4 Additional Licensing Processes (10 CFR Part 52)... 4 Early Site Permits... 6

More information

9. Auxiliary Systems AP1000 Design Control Document

9. Auxiliary Systems AP1000 Design Control Document 9.3 Process Auxiliaries 9.3.1 Compressed and Instrument Air System The compressed and instrument air system (CAS) consists of three subsystems; instrument air, service air, and high-pressure air. Instrument

More information

3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment

3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment 3.9.2 Dynamic Testing and Analysis of Systems, Components, and Equipment The U.S. EPR systems, components, and equipment retain their structural and functional integrity when subjected to dynamic loads

More information

SECTION 8 Industrial Facilities Field Investigation

SECTION 8 Industrial Facilities Field Investigation SECTION 8 Industrial Facilities Field Investigation Types of Data to Be Collected and Recorded Warehouses, manufacturing facilities, energy-producing facilities, and factories should be inspected for performance

More information

Performance Monitoring of Systems and Active Components

Performance Monitoring of Systems and Active Components CGI Report 06:21 Aging Management Briefing Report Performance Monitoring of Systems and Active Components August 2006 Frank Gregor, P.E. Alan Chockie Prepared for The Petroleum Safety Authority Norway

More information

C. starting positive displacement pumps with the discharge valve closed.

C. starting positive displacement pumps with the discharge valve closed. KNOWLEDGE: K1.04 [3.4/3.6] P78 The possibility of water hammer in a liquid system is minimized by... A. maintaining temperature above the saturation temperature. B. starting centrifugal pumps with the

More information

Status on Spanish Regulations and Industry. actions related to Filtered Containment. Venting Systems (FCVS)

Status on Spanish Regulations and Industry. actions related to Filtered Containment. Venting Systems (FCVS) Status on Spanish Regulations and Industry actions related to Filtered Containment Venting Systems (FCVS) Sara González Systems Engineering Department Consejo de Seguridad Nuclear, Spain Technical Meeting

More information

11. Radioactive Waste Management AP1000 Design Control Document

11. Radioactive Waste Management AP1000 Design Control Document 11.4 Solid Waste Management The solid waste management system (WSS) is designed to collect and accumulate spent ion exchange resins and deep bed filtration media, spent filter cartridges, dry active wastes,

More information

Belgian Stress tests specifications Applicable to all nuclear plants, excluding power reactors 22 June 2011

Belgian Stress tests specifications Applicable to all nuclear plants, excluding power reactors 22 June 2011 Belgian Stress tests specifications Applicable to all nuclear plants, excluding power reactors 22 June 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the European

More information

OWestinghouse. U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555. February 1, 2010

OWestinghouse. U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555. February 1, 2010 OWestinghouse Westinghouse Electric Company Nuclear Power Plants P.O. Box 355 Pittsburgh, Pennsylvania 1 5230-0355 USA U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C.

More information

U.S. EPR Design Overview

U.S. EPR Design Overview U.S. EPR Design Overview Brian A. McIntyre U.S. EPR Design Certification Project Manager WM2009 Conference March 4, 2009 The EPR Story 1989: Agreement between Framatome and Siemens on development of common

More information

Belgian Stress tests specifications Applicable to power reactors 17 May 2011

Belgian Stress tests specifications Applicable to power reactors 17 May 2011 Belgian Stress tests specifications Applicable to power reactors 17 May 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the European Council of March 24 th and

More information

AP1000 European 18. Human Factors Engineering Design Control Document

AP1000 European 18. Human Factors Engineering Design Control Document 18.2 Human Factors Engineering Program Management The purpose of this section is to describe the goals of the AP1000 human factors engineering program, the technical program to accomplish these goals,

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001. February 1, 2006

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001. February 1, 2006 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 20555-0001 February 1, 2006 OMB Control No.: 3150-0011 NRC GENERIC LETTER 2006-02: GRID RELIABILITY AND

More information

BLADDER SURGE CONTROL SYSTEM

BLADDER SURGE CONTROL SYSTEM PART I GENERAL 1.01 Description BLADDER SURGE CONTROL SYSTEM This specification describes the requirements for a Bladder Surge Control System. The purpose of the system is to minimize transient pressures

More information

NUCLEAR REGULATORY COMMISSION. [Docket No. 52-039; NRC-2008-0603] PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant

NUCLEAR REGULATORY COMMISSION. [Docket No. 52-039; NRC-2008-0603] PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant [7590-01-P] NUCLEAR REGULATORY COMMISSION [Docket No. 52-039; NRC-2008-0603] PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant AGENCY: Nuclear Regulatory Commission. ACTION:

More information

Fukushima & Three Mile Island Reactor Accidents: Recovery, Cleanup, Lessons, & Future

Fukushima & Three Mile Island Reactor Accidents: Recovery, Cleanup, Lessons, & Future Fukushima & Three Mile Island Reactor Accidents: Recovery, Cleanup, Lessons, & Future Foundation For Nuclear Studies Congressional Briefing May 18, 2012 Lake H. Barrett Lake@Lbarrett.com Disclaimer: Fukushima

More information

SAFETY STANDARDS. of the. Nuclear Safety Standards Commission (KTA) KTA 3301. Residual Heat Removal Systems of Light Water Reactors.

SAFETY STANDARDS. of the. Nuclear Safety Standards Commission (KTA) KTA 3301. Residual Heat Removal Systems of Light Water Reactors. SAFETY STANDARDS of the Nuclear Safety Standards Commission (KTA) KTA 3301 Residual Heat Removal Systems of Light Water Reactors (November 1984) Editor: Geschäftsstelle des Kerntechnischen Ausschusses

More information

Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP)

Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP) Improving regulatory practices through the OECD-NEA Stress Corrosion Cracking and Cable Ageing Project (SCAP) A. Yamamoto a, A. Huerta a, K. Gott b, T. Koshy c a Nuclear Safety Division, OECD Nuclear Energy

More information

This document was prepared in conjunction with work accomplished under Contract No. DE-AC09-96SR18500 with the U. S. Department of Energy.

This document was prepared in conjunction with work accomplished under Contract No. DE-AC09-96SR18500 with the U. S. Department of Energy. This document was prepared in conjunction with work accomplished under Contract No. DE-AC09-96SR18500 with the U. S. Department of Energy. DISCLAIMER This report was prepared as an account of work sponsored

More information

May 23, 2011 Tokyo Electric Power Company

May 23, 2011 Tokyo Electric Power Company Analysis and evaluation of the operation record and accident record of Fukushima Daiichi Nuclear Power Station at the time of Tohoku-Chihou-Taiheiyou-Oki-Earthquake (summary) May 23, 2011 Tokyo Electric

More information

Guidance on Process Safety Performance Indicators

Guidance on Process Safety Performance Indicators Guidance on Process Safety Performance Indicators Table of contents 01 INTRODUCTION 02 OBJECTIVE 02 SCOPE 03 CRITERIA 06 DATA REPORTING 08 PROCESS SAFETY PERFORMANCE 08 CONCLUSIONS 09 DEFINITIONS 09 REFERENCES

More information

Proposal to Consolidate Post-Fukushima Rulemaking Activities

Proposal to Consolidate Post-Fukushima Rulemaking Activities Proposal to Consolidate Post-Fukushima Rulemaking Activities On January 28, 2014, the U.S. Nuclear Regulatory Commission s (NRC s) Fukushima Steering Committee endorsed an NRC staff proposal for integrating

More information

REGULATORY GUIDE 1.168 (Draft was issued as DG-1267, dated August 2012)

REGULATORY GUIDE 1.168 (Draft was issued as DG-1267, dated August 2012) Purpose U.S. NUCLEAR REGULATORY COMMISSION July 2013 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.168 (Draft was issued as DG-1267, dated August 2012) Technical

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001. June 26, 2014

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001. June 26, 2014 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26, 2014 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

More information

Chemical Decontamination and Fluid Handling Services

Chemical Decontamination and Fluid Handling Services Chemical Decontamination and Fluid Handling Services Westinghouse is a global industry expert in decontamination and fluid handling processes, with proven abilities in decontamination and remediation work.

More information

Westinghouse. Westinghouse Electric Company

Westinghouse. Westinghouse Electric Company Westinghouse Nuclear Power Plants Westinghouse Electric Company P.O. Box 355 Pittsburgh, Pennsylvania 15230-0355 USA U.S. Nuclear Regulatory Commission Directtel: 412-374-6202 ATTENTION: Document Control

More information

BALLOT PREVIEW PRESENTATION P497 STANDARD CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR NUCLEAR POWER GENERATING STATIONS

BALLOT PREVIEW PRESENTATION P497 STANDARD CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR NUCLEAR POWER GENERATING STATIONS BALLOT PREVIEW PRESENTATION P497 STANDARD CRITERIA FOR ACCIDENT MONITORING INSTRUMENTATION FOR POWER GENERATING STATIONS January 21, 2015 Greg M Hostetter (WG-6.1 Chair) & Daryl Harmon (WG-6.1 Vice-Chair)

More information

Source Term Determination Methods of the Slovenian Nuclear Safety Administration Emergency Response Team

Source Term Determination Methods of the Slovenian Nuclear Safety Administration Emergency Response Team IAEA TM on Source Term Evaluation for Severe Accidents, Vienna, 21-23 October 2013 Source Term Determination Methods of the Slovenian Nuclear Safety Administration Emergency Response Team Tomaž Nemec Slovenian

More information

Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 37

Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 37 Vito A. Kaminskas Site Vice President DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.6515 Fax: 734.586.4172 Email: kaminskasv@dteenergy.com DTE Ensergy- 10 CFR 54 September 24,

More information

Life-cycle cost analysis for nuclear power plants with seismic isolated system

Life-cycle cost analysis for nuclear power plants with seismic isolated system Life-cycle cost analysis for nuclear power plants with seismic isolated system Sunyogn Kim 1), Hong-Pyo Lee 2) and Myung-Sug Jo 3) 1), 2), 3) Plant Construction & Engineering Lab, Central Research Institute,

More information

3. Design of Structures, Components,

3. Design of Structures, Components, 3.8 Design of Category I Structures 3.8.1 Concrete Containment This subsection is not applicable to the AP1000. 3.8.2 Steel Containment 3.8.2.1 Description of the Containment 3.8.2.1.1 General This subsection

More information

Options for Cyber Security. Reactors. April 9, 2015

Options for Cyber Security. Reactors. April 9, 2015 Options for Cyber Security Design Requirements for Power Reactors April 9, 2015 Scope Discuss options for including cyber security design requirements for power reactors into NRC regulations Scope does

More information

Diablo Canyon NPP Probabilistic Risk Assessment Program. Workshop Information IAEA Workshop

Diablo Canyon NPP Probabilistic Risk Assessment Program. Workshop Information IAEA Workshop IAEA Training Course on Safety Assessment of NPPs to Assist Decision Making Diablo Canyon NPP Probabilistic Risk Assessment Program Lecturer Lesson Lesson IV IV 3_11.2 3_11.2 Workshop Information IAEA

More information

STP 3 & 4. 11.2 Liquid Waste Management System. 11.2.1 Design Basis

STP 3 & 4. 11.2 Liquid Waste Management System. 11.2.1 Design Basis 11.2 Liquid Waste Management System This section of the reference ABWR DCD including all subsections, figures, and tables (except for P & IDs) is replaced completely. This is due to a departure in the

More information

IV. Occurrence and Progress of Accidents in Fukushima Nuclear Power Stations and Other Facilities

IV. Occurrence and Progress of Accidents in Fukushima Nuclear Power Stations and Other Facilities IV. Occurrence and Progress of Accidents in Fukushima Nuclear Power Stations and Other Facilities 1. Outline of Fukushima Nuclear Power Stations (1) Fukushima Daiichi Nuclear Power Station Fukushima Daiichi

More information

Regulatory Guide 1.169 Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

Regulatory Guide 1.169 Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants Regulatory Guide 1.169Configuration Managemen... Page 1 of 10 September 1997 Regulatory Guide 1.169 Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power

More information

Proposed TG Repair of Reinforced Concrete of Existing Nuclear Power Plants (RCTG) Chiara Ferraris, NIST Nate Sauer, Structural Technologies

Proposed TG Repair of Reinforced Concrete of Existing Nuclear Power Plants (RCTG) Chiara Ferraris, NIST Nate Sauer, Structural Technologies Proposed TG Repair of Reinforced Concrete of Existing Nuclear Power Plants (RCTG) Chiara Ferraris, NIST Nate Sauer, Structural Technologies Status Over 100 NPP in service today and most of them have reached

More information

GENERAL REGULATIONS ON ENSURING SAFETY OF NUCLEAR POWER PLANTS OPB-88/97, NP-001-97 (PNAE G- 01 011-97) Cover page. Contents

GENERAL REGULATIONS ON ENSURING SAFETY OF NUCLEAR POWER PLANTS OPB-88/97, NP-001-97 (PNAE G- 01 011-97) Cover page. Contents GENERAL REGULATIONS ON ENSURING SAFETY OF NUCLEAR POWER PLANTS OPB-88/97, NP-001-97 (PNAE G- 01 011-97) Cover page Contents Federal Nuclear and Radiation Safety Authority of Russia (Gosatomnadzor of Russia)

More information

EMERGENCY PREPAREDNESS FREQUENTLY ASKED QUESTION (EPFAQ) NEI 99 01 REVISIONS 4 THROUGH 6; NUMARC/NESP 007

EMERGENCY PREPAREDNESS FREQUENTLY ASKED QUESTION (EPFAQ) NEI 99 01 REVISIONS 4 THROUGH 6; NUMARC/NESP 007 EPFAQ Number: 2015 001 DATE ACCEPTED 20 Apr 15 ORIGINATOR DAVID YOUNG ORGANIZATION Nuclear Energy Institute (NEI) PHONE # 202 739 8016 RELEVANT GUIDANCE: NEI 99 01 REVISIONS 4 THROUGH 6; NUMARC/NESP 007

More information

ALS Configuration Management Plan. Nuclear Safety Related

ALS Configuration Management Plan. Nuclear Safety Related Westinghouse Non-Proprietary Class 3 Advanced Logic System 6002-00002-NP, Rev. 10 Function Author Nuclear Safety Related July 2014 APPROVALS Name and Signature Anthony C. Pagano* Integrated Process Lead,

More information

REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH. REGULATORY GUIDE 1.174 (Draft was issued as DG-1226, dated August 2009)

REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH. REGULATORY GUIDE 1.174 (Draft was issued as DG-1226, dated August 2009) U.S. NUCLEAR REGULATORY COMMISSION May 2011 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.174 (Draft was issued as DG-1226, dated August 2009) AN APPROACH FOR USING

More information

9.4 Air Conditioning, Heating, Cooling and Ventilating Systems

9.4 Air Conditioning, Heating, Cooling and Ventilating Systems 9.4 Air Conditioning, Heating, Cooling and Ventilating Systems 9.4.1 Control Building HVAC The Control Building (C/B) Heating, Ventilating and Air-Conditioning (HVAC) System is divided into two separate

More information

A-Ow INDIA NA MICHIGAN POW!ER. September 18, 2015 AEP-NRC-201 5-86 10 CFR 50.90. Docket No.: 50-315

A-Ow INDIA NA MICHIGAN POW!ER. September 18, 2015 AEP-NRC-201 5-86 10 CFR 50.90. Docket No.: 50-315 INDIA NA MICHIGAN POW!ER A unit of American Electric Power indiana Michigan Power Cook Nuclear Plant One Cook Place Indiana MichiganPower.com September 18, 2015 AEP-NRC-201 5-86 10 CFR 50.90 Docket No.:

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555-0001. July 17, 2012

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555-0001. July 17, 2012 UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555-0001 July 17, 2012 Mr. R. W. Borchardt Executive Director for Operations U.S. Nuclear Regulatory

More information

NUCLEAR POWER PLANT SYSTEMS and OPERATION

NUCLEAR POWER PLANT SYSTEMS and OPERATION Revision 4 July 2005 NUCLEAR POWER PLANT SYSTEMS and OPERATION Reference Text Professor and Dean School of Energy Systems and Nuclear Science University of Ontario Institute of Technology Oshawa, Ontario

More information

AP1000 Nuclear Power Plant Overview

AP1000 Nuclear Power Plant Overview AP1000 Nuclear Power Plant Overview Gianfranco Saiu, Monica Linda Frogheri ANSALDO Energia S.p.A - Nuclear Division Corso Perrone, 25, 16161 Genoa, ITALY Phone:++39 010 6558591,FAX: ++39 010 64018591 Email:

More information

How To Design An Ap 600 Plant

How To Design An Ap 600 Plant Status report 75 - Advanced Passive pressurized water reactor (AP-600) Overview Full name Acronym Reactor type Coolant Moderator Neutron spectrum Thermal capacity Electrical capacity Design status Designers

More information

ABWR. 3.4 Water Level (Flood) Design

ABWR. 3.4 Water Level (Flood) Design 3.4 Water Level (Flood) Design Criteria for the design basis for protection against external flooding of an ABWR plant site shall conform to the requirements of RG 1.59. The types and methods used for

More information

Nuclear Emergency Response Program

Nuclear Emergency Response Program Nuclear Emergency Response Program NUCLEAR POWER PLANTS In California, there are two operating nuclear power plant sites: Diablo Canyon in San Luis Obispo County has two active units and San Onofre Nuclear

More information

7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION. In the Matter of )

7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION. In the Matter of ) 7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of ) DUKE POWER COMPANY ) Docket Nos. 50-369 (McGuire Nuclear Station, ) and 50-370 Units I and 2) ) EXEMPTION PROVIDING FOR

More information

U.S. NUCLEAR REGULATORY COMMISSION January 2010 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH. REGULATORY GUIDE 5.71 (New Regulatory Guide)

U.S. NUCLEAR REGULATORY COMMISSION January 2010 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH. REGULATORY GUIDE 5.71 (New Regulatory Guide) U.S. NUCLEAR REGULATORY COMMISSION January 2010 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 5.71 (New Regulatory Guide) CYBER SECURITY PROGRAMS FOR NUCLEAR FACILITIES A INTRODUCTION

More information

Interim Staff Guidance on Implementation of a Probabilistic Risk Assessment-Based Seismic Margin Analysis for New Reactors DC/COL-ISG-020

Interim Staff Guidance on Implementation of a Probabilistic Risk Assessment-Based Seismic Margin Analysis for New Reactors DC/COL-ISG-020 Interim Staff Guidance on Implementation of a Probabilistic Risk Assessment-Based Seismic Margin Analysis for New Reactors DC/COL-ISG-020 1.0 Purpose For the licensing process in Title 10 of the Code of

More information

The Piping System Model a New Life Cycle Document. Elements of the Piping System Model

The Piping System Model a New Life Cycle Document. Elements of the Piping System Model Piping System Model as a Life Cycle Document White Paper Introduction When designing piping systems, a variety of documents are created providing the details necessary to design, purchase, build, and test

More information

Valve Services. Comprehensive. Dynamic. Flexible.

Valve Services. Comprehensive. Dynamic. Flexible. Valve Services Comprehensive. Dynamic. Flexible. Compreh Dynamic. Flexible. Delivering Proven Results Established in 1844, Babcock & Wilcox Canada Ltd. (B&W Canada) has grown from a small foundry on the

More information