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Advanced Nuclear Technology (ANT) Program Overview for CMBG. Ken Barry, Senior Project Manager Russell Adams, Dominion June 23, 2010. © 2008 Electric Power Research Institute, Inc. All rights reserved. EPRI Portfolio Spans the Entire Electricity Sector. Generation. Nuclear Power.

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advanced nuclear technology ant program overview for cmbg

Advanced Nuclear Technology (ANT) ProgramOverview for CMBG

Ken Barry, Senior Project Manager

Russell Adams, Dominion

June 23, 2010

epri portfolio spans the entire electricity sector
EPRI Portfolio Spans the Entire Electricity Sector

Generation

Nuclear Power

Power Delivery & Utilization

Environment

  • Advanced Coal Plants, Carbon Capture and Storage
  • Combustion Turbines
  • Environmental Controls
  • Generation Planning
  • Major Component Reliability
  • Operations and Maintenance
  • Renewables
  • Material Degradation/Aging
  • Fuel Reliability
  • High-Level Waste and Spent Fuel Management
  • Nondestructive Evaluation and Material Characterization
  • Equipment Reliability
  • Instrumentation and Control
  • Risk and Safety Management
  • Advanced Nuclear Technology
  • Low-Level Waste and Radiation Management
  • Distribution
  • Energy Utilization
  • Grid Operations and Planning
  • Substations and Asset Planning
  • Transmission and Increased Power Flow
  • Air Quality
  • Global Climate Change
  • Land and Groundwater
  • Occupational Health and Safety
  • T&D Environmental Issues
  • Water and Ecosystems

© 2008 Electric Power Research Institute, Inc. All rights reserved.

advanced nuclear technology program objectives
Advanced Nuclear Technology Program Objectives
  • New nuclear power plants must overcome a number of regulatory, economic, technical, and social challenges prior to becoming a reality
  • Program efforts focused around:
    • Facilitating standardization across the new fleet
    • Transferring technology to new plant designs
    • Ensuring top plant performance from start of operations
    • Reduce overall deployment risk and uncertainty
    • Supporting development of advanced nuclear plants and associated strategic initiatives
epri s response the ant program
EPRI’s Response …The ANT Program

Materials and Fuels Research

Maintenance Optimization

Seismic/NDE/Cooling Technologies

Advanced Nuclear Technology (ANT) Program

Current Plant

Technology

Near-Term

Deployment of ALWRs

Strategic Initiatives

NPP Cooling Water Utilization

Fusion Energy Assessments

Integrated Spent Fuel Management

Technology Transfer/Lessons Learned

Technology Assessment (URD)

New Plant Materials

Seismic Issues Resolution

New Plant Equipment Reliability

Non-Destructive Evaluation Initiatives

Advanced Nuclear

Plants

Next Generation Nuclear Plant (NGNP)

Small Modular Reactors (SMRs)

Advanced Reactor Concepts

2010 ant membership breakdown
2010 ANT Membership Breakdown

Current 2010 Membership…$4.225M

2010 Potential…

2008 ant projects
2008 ANT Projects

* Projects completed

2009 ant projects
2009 ANT Projects

* Projects completed

2009 01 achieving new nuclear virtual plant configuration management
2009-01 Achieving New Nuclear Virtual Plant Configuration Management

Project Goal

  • We need a common data language and interoperability standard that will be used by the nuclear plant sub-tier suppliers through the suppliers, through the EPC and reactor vendors, and finally through to the owner and operator
2009 01 achieving new nuclear virtual plant configuration management1
2009-01 Achieving New Nuclear Virtual Plant Configuration Management

Progress

Standard Configuration Management Reference Model

  • The Standard Configuration Management Reference Model draft is undergoing a complete re-write.

New Nuclear Plant XML Equipment Schemas

  • The Schema viewer is complete. The project is working with the Hydraulic Institute, NIST and a pump vendor to conduct a pump procurement pilot to determine nuclear specific fields. Also planning pilots with valve operators and electric motors
  • We are running into more issues with the standardization of XML schemas that anyone had anticipated. The original concern that a few “nuclear specific” fields may be missing has turned into an effort involving schema terminology, complexity, architecture refinement, document maturity validity, etc. Feedback to FIATECH

Information Handover Guide

  • The Handover Guide was published in December 2009 (1019221).
  • Developing Handover Life Cycle and data requirements.
slide17

The Must

Nuclear Configuration Management

“What needs to be there”

Design Requirements

Design

Basis

Conform

Conform

Plant

Docs

Facility Configuration Information

“What we say is there”

“What is actually there”

Physical

Configuration

Physical

Plant

Conform

Work Processes must assure that:

Elements conform all the time

All changes are authorized

Conformance can be verified

slide18

The Challenge

Nuclear Configuration Management

Knowledge Workers

EDB

Challenge

Conform

Challenge

Conform

Paper-based

Quality Assurance

Process

PD

Plant

Documentation

Automation Systems

AS

Conform

Challenge

Lots of Tribal Knowledge , Semi-Connected and Disconnected Systems, Manual Processes

and yes……

Paper

keeping the ship heading in the right direction sustainability
Keeping the Ship Heading in the Right Direction - Sustainability

2011

2009

2010

SCMRM

Developed Concept

Publish SCMRM & Templates

Organize SCMRM UG?

XML Schemas

Reviewed Existing XML Schemas

Conduct XML schema pilots*

EPC/Supplier Implement?

Info Handover

Published Info Handover Guide

Publish Templates

Organize Info Handover UG?

* Also participate in POSC Caesar / FIATECH ISO 15926 project

2009 04 guidance on emi protection
2009-04 Guidance on EMI Protection

Eliminating Exclusion Zones

Immunity, Φ2

Immunity = immunity of system, not of individual component

Φ2 > Φ1

E = allowable field strength (V/m)

Pt = effective radiated power of emitter (source)

Gt= gain of the source

Source

Pt , Gt

Immunity, Φ1

DigitalDevice

d

Which variables will affect the E (electric field); reduce it?

Receptor

Path

Source

2009 04 guidance on emi protection1
2009-04 Guidance on EMI Protection

Execution2010

Implementation2011

Analysis2009

Develop Base Linefrom Historical Dataof Emissions Datafor Nuclear Plants

Develop New RFImmunityRequirements forANPs

  • New test protocols
  • Testing & test reporting
  • In-situ testing
  • Test report review & system certification

New Layers ofEMC ProtectionEliminateExclusionZones

Data from 1993to 2009

Done

Evaluate PresentEMC Performanceof I&C Equipment

Develop SpectrumManagement Planfor ANPs

  • Initiates required frequency protection margin
  • Establishes frequency budget
  • Defines transmitter spacing
  • Reduces probability of transmitter causing EMI problems

New Layers ofEMC ProtectionEliminateExclusionZones

Use EPRI TR-102323for Input

Use Existing (New)IEEE Standard

In Process

Analyze FactorsCausing Change inthe ElectromagneticEnvironment for ANPs

Initiate Developmentof New Standards(ANSI/IEEE) toAddress these Needs

  • Establishes normative standards for:
    • a) Recommended design practices
    • b) I&C product qualification & In-situ evaluation
    • c) Refine & keep standards current

New Layers ofEMC ProtectionEliminateExclusionZones

Incorporate NewWireless Standards

In Process

Conduct InterferenceAnalysis on FutureI&C Systems forANPs

Design a ConformityAssessment Systemto Provide forRF Immunity forANP I&C Equipment

  • Assures required level of RF immunity
  • Encompasses process to assure I&C equipment complies with the installed environment with requirements
  • Conformity assessment systems are ISO standardized

I&C EquipCertificationSystem

Use Existing (New)IEEE Std. 1900.2

Upcoming

  • Develop staged process for deployment
  • Initial testing in laboratory environments
  • Alpha, then Beta testing in a staged process

SupportDeploymentof ImprovedI&C Systems

ANSI ASC C63Approved a Study ofNeed for New Stds

ConstituteAlpha & Beta TestRecommendationsin ANP Designs

Started

2008 06 nde and reduction of repairs in nuclear construction
2008-06 NDE and Reduction of Repairs in Nuclear Construction

Project Goals

  • Eliminate unnecessary repairs during construction
    • Influence ASME Code Section III
  • Establish UT qualification programs
    • Provide assurance of accurate and reliable weld inspections during the construction
  • Regulatory acceptance of fitness-for-service philosophy
    • Cost savings and elimination of delays during construction
    • Improved resistance to stress corrosion cracking during plant ops
2009 08 safety related stationary battery qualification
2009-08 Safety Related Stationary Battery Qualification

Project Description

  • EPRI Utility Requirements Document (URD) states that Advanced Light Water Reactors (ALWRs) shall utilize passive safety systems to mitigate design basis events up to 72 hours in duration
    • Passive systems must rely upon stored energy, e.g., batteries
  • Passive plants (AP1000, ESBWR) require batteries that are qualified to a 72 hour duty cycle
  • IEEE 535 standard for battery qualification (endorsed by RG 1.158) did not cover duty cycles beyond 8 hours
  • IEEE 535 only covers Vented Lead Acid (VLA or flooded) batteries – Valve Regulated Lead Acid (VRLA) batteries are not addressed

Value

  • Providing a industry solution to a first-of-a-kind technical challenge for passive plants
  • Reducing risk through a collaborative approach
2010 02 digital rt
2010-02 Digital RT

Summary of Issue

  • Currently, the industry is unable to address the evaluation and qualification of filmless radiography systems to detect planar and volumetric fabrication flaws with selected digital detector panels (DR), phosphor plates (CR), and high energy electronic radiation sources capable of penetrating the material thicknesses typically encountered in plant applications

Potential Benefit of Project

  • Expedited ASME Section III volumetric examination of piping welds with CR or DR
  • Volumetric option/complement to UT
  • Minimization of weld repairs with ASME Section III volumetric examination
  • Digital storage of images instead of processed film and associated chemical processing
2010 05 nde digital data
2010-05 NDE Digital Data

Summary of Issue

  • Archival data is required by the Nuclear Regulatory Commission (NRC) to last for the plant's working lifetime
  • Many utilities' document control departments will not accept digital non-destructive examination (NDE) data for archival storage and require it to be converted to a hard copy format

Potential Benefit of Project

  • This guide will assist utilities in transferring, retrieving, and archiving their NDE data and allow them a path for any future digital NDE data needs
  • A consistent and acceptable process is needed for archiving digital NDE records, versus converting them to paper records
2010 10 concrete embedded sensors
2010-10 Concrete Embedded Sensors

Summary of Issue

  • Large concrete structures in nuclear power plants are typically not feasible to replace. These structures can show signs of concrete degradation by the time they go for license renewal
  • There is a distinct need for frequent inspections of these types of concrete structures. One of the largest hindrances to concrete inspection is the lack of accessibility to many concrete structures

Potential Benefit of Project

  • Optimize inspections
  • Better positioned for long-term asset management
2010 11 technical basis for hdpe above ground use
2010-11 Technical Basis for HDPE Above-Ground Use

Summary of Issue

  • There is no ASME approved code case for above-ground HDPE pipe. One has been developed for below-ground use only
  • Several new plant designs plan on using HDPE for above-ground application

Potential Benefit of Project

  • Use of HDPE for above-ground applications will require development of appropriate design and construction rules, along with determining the engineering and material properties needed to ensure safe and reliable design and operation 
  • Critical technical issues that will be addressed include:
    • seismic qualification (including vents and drains)
    • large displacements and interactions during thermal expansion and transients
    • fire
    • structural damping values
    • damage during operations
2011 project cooling tower sourcebook for new nuclear plants
2011 Project - Cooling Tower Sourcebook for New Nuclear Plants

Description

  • Create a sourcebook to support
    • Design / Application
    • Operation
    • Maintenance
  • Addressing
    • Natural draft
    • Mechanical
    • Dry
    • Hybrid
project a double walled hdpe piping evaluation
Project A – Double-walled HDPE Piping Evaluation

Issue

  • 10 CFR 20.1406, “Minimization of Contamination,” requires licensees to minimize contamination and radioactive waste generation
  • RG 1.143 states that plastic pipe should not be used.
  • Doubled walled HDPE is a desired option

Description

  • Review the double walled HDPE piping options available to meet the current regulations, including hardware and leak detection / monitoring options.
  • This work would include further understanding the HDPE materials degradation properties and limitation for exposure to radioactive fluids.
  • Work to inform a revision to RG 1.143 to acknowledge the option of using double walled plastic pipe (HDPE), with built-in leak detection capability,
  • Value
  • HDPE is viewed as a superior material to steel in some applications and is preferred for buried systems
  • Providing an alternative in the RG will provide greater flexibility
  • Cost savings on materials, installation and long term operations
project b epri groundwater protection guidelines for new nuclear power plants
Project B – EPRI Groundwater Protection Guidelines for New Nuclear Power Plants

Issue

  • The EPRI Groundwater Protection Guidelines for Nuclear Power Plants (1015118) provides technical guidance for implementing a groundwater protection program that meets the requirements of NEI 07-07. However, it currently does not provide technical guidance for implementing groundwater protection programs, namely the evaluation of plant design and operational procedures, for new plants as outlined in NEI 08-08.

Description

  • EPRI will develop an extension to the EPRI Groundwater Protection Guidelines that provides technical guidance for implementing a groundwater protection program per 10CFR20.1406, RG 4.21, and NEI 08-08.

Value

  • Understanding and preparing for any potential leaks or spills during construction will allow nuclear power plant operator to quickly identify and address any leaks or spills during operation.
  • Timely leak detection and response will increase stakeholder confidence that utilities are protecting public and environmental health and safety.
project f nde techniques for concrete void detection and sizing
Project F – NDE Techniques for Concrete Void Detection and Sizing

Issue

  • The main types of degradation related to concrete are the existence of honeycombs and voids due to lack of adequate concrete placement and vibration.
  • These types of problems are related to poor design and construction, which are the leading causes of age-related degradation in concrete structures

Description

  • Voids (the focus will be on detection capabilities during the placement so that issues can be corrected immediately before curing.)
  • Wall separation due to concrete shrinkage
  • Damage under loadings (internal cracks, excessive stress and strain, etc...)

Value

  • Voids in concrete severely reduce the structural and shielding capacity of the concrete structure. The ability for early void detection in a nuclear construction environment will result in both financial and safety improvements.
  • Long term asset management will also benefit from early detection and correction of construction issues with concrete structures.
project g urd update project
Project G - URD Update Project

Issue

  • No formal process exists to maintain the URD
  • No comprehensive listing of EPRI reports applicable to new plants exists

Description

  • Review and disposition the “Margins and Monitoring” work to ensure those recommendations are incorporated into the appropriate URD sections.
  • Establish EPRI report reference sections for each chapter of the URD
  • Establish a process for a) collecting input from URD users for review under a specific schedule and b) review newly issued EPRI reports and industry references for inclusion into the URD where appropriate.

Value

  • The results of the Margins work will be visible and reflected in the URD.
  • Relevant EPRI nuclear sector reports on designing, procuring and constructing new nuclear plants will be comprehensively identified in the URD
  • URD users will benefit from a process to ensure that their input for changes to the URD are managed in a systematic and timely manner.
project i qa for 2d and 3d design and modeling software and v v for quality software
Project I - QA for 2D and 3D Design and Modeling Software and V&V for Quality Software

Issue

  • The 2D and 3D design and modeling software currently being used to design and ultimately construct the next generation of nuclear power plants do not have to meet NQA-1 requirements for software and data quality. Hence, in order for these systems to be used for the operation of the nuclear power plant – a qualification of the software and data will have to occur.

Description

  • Configuration Control of the Data in Engineering Applications that will have Plant Life Cycle use
  • Quality Control of the 2D / 3D design and modeling software and other associated databases and software in a commercial grade dedication method prescribed by NQA-1

Value

  • An industry standard approach to software and data quality for the 2D and 3D design and modeling software and other associated databases and software.
project r high strength rebar use in nuclear power plants
Project R – High Strength Rebar use in Nuclear Power Plants

Issue

  • The use of higher strength rebar in the design and construction of safety related concrete structures and / or containment structures could result in cost savings for new nuclear power plants by reducing the quantity of rebar required. Cost savings would result from reduced rebar material purchase costs and reduced construction cost due to reduction in the quantity of rebar placed

Description

  • Develop and implement a concrete testing program to support adoption of higher strength rebar use in ACI 349 and ACI 359.
  • Involve the NRC to facilitate endorsement of the higher strength rebar in a future revision of Reg. Guide 1.142.

Value

  • The use of High Strength Rebar in the general construction industry has made high strength concrete in seismic zones cheaper and easier to construct due to the lower density of rebar in structures.
  • High Strength Rebar has greater resistance to corrosion over convention rebar, providing a potential longer life in nuclear plant application.