2010 April IEEE SC2 Vegas · 2017. 6. 26. · Phase 1 RG1 26 Phase 2 RG 1 210 Phase 3 RG 140 Phase...

KinectricsKinectrics

Industry Impact of the New y pU.S. Reactor Design Regulations and Standards

April 2010

Presented by:

Serena Krause

KinectricsKinectrics

An established independent companyFormerly the Technical Division of Ontario Hydro, one of North America’s largest most reliable utilitieslargest, most reliable utilitiesAlmost 100 years of advanced technical expertise & experienceOver 300 scientists, engineers & professional staffC h i f iliti & d dComprehensive facilities & advanced specialized laboratories near Toronto, ON Canada

A View from Above…

h i l / l i lEnvironmentalQualification

Chemical / AnalyticalServices

ElectricalServices

85 years’ experience in providing Nuclear & ConventionalSupport to UtilitiesMetallurgical

Services

NEW USA OFFICE! CINCINNATI, OHIO

Industry Impact of the New U.S. Reactor Design, Regulations and Standards

Much has changed in theMuch has changed in the last thirty years.


1979 – TI‐99/4 2009 – Blackberry World Edition/ y


1979 – The WALKMAN! 2009 – The iPod Touch


1979 – All In The Family 2009 – Jon & Katey(or is it just now Kate?)


1979 – Global Cooling! 2009 – Global Warming!


And Some More Serious Events Have Redefined Impossible

April 1986March 1979 May 1980 October 1989January 1986 April 1986March 1979 May 1980 October 1989January 1986

August 1992 July 1993 April 1995 September 2001 May 2007


Let’s just say a lot hasLet’s just say a lot has happened since the lasthappened since the last time we embarked on a

major nuclear construction effort!

Equipment Qualification f dfor Power Actuated

ValvesValvesa refresher…. a refresher…..

EQ Test ProgramEQ Test Program

AgingSeismic & Dynamic

TestingHarsh Environment

Testing

Accelerated Thermal AgingRadiation AgingOperational Aging

Resonance SearchSeismic (OBE/SSE)Hydrodynamic

LOCAMSLB/FWLBHELBp g g y y HELBSubmergence

Qualification of Valve Actuator Qualification of Valve Actuator (IEEE 323/344/382)(IEEE 323/344/382)

Collect Design Data to Support Test Test Procedure Receipt Inspection

Radiation Aging to Si l 60 d i

Accelerated Thermal A i Si l 60

Operational AgingSupport Test Procedure

Development

Test Procedure Approval

Receipt Inspection Baseline Testing

Simulate 60 yr design life

Aging to Simulate 60 yr Life.

Operational Aging (e.g., cycle aging)

3 ‐ 6 months+

Resonance Search Test SRV Aging Test Seismic AgingFaulted Seismic

TestingDynamic Chugging

Test

1 week

LOCA/HELB Testing Submergence TestingFinal Functional Tests/Inspection

Develop Test Report

2 months

Functional Qualification of Power Operated Valve Functional Qualification of Power Operated Valve Assembly (ASME QMEAssembly (ASME QME--1)1)

Collect Design Data to Support Test Test Procedure Receipt Inspection

Radiation Aging to Si l 60 d i

Accelerated Thermal A i Si l 60

Operational AgingSupport Test Procedure

Development

Test Procedure Approval

Receipt Inspection Baseline Testing

Simulate 60 yr design life

Aging to Simulate 60 yr Life.

Operational Aging (e.g., cycle aging)

3 ‐ 6 months+

Fundamental Frequency

Determination

Cold Cycle Functional Test

Hot Cycle Functional Test

End Loading TestDetermination

2 weeks

Flow Interruption and Functional Capability

Demonstration

Final Functional Tests/Inspection

Develop Test Report

2 months


What’s new?What is new about the Workforce?

What s new?

What is new about the Supply Chain?

What is new about the new regulations and standards?

What is new about the new nuclear plant designs?

How will the Operating Fleet be Affected?p g

What is new about the Workforce?


“Never before has the American workforce been made up of employees from four distinct generations. Each of these p y ggenerations came of age at a distinct moment in history and thegenerational beliefs and behaviors of these employees extend to their view of work and management ”to their view of work and management.

Ref: “GENERATIONAL COHORTS AND THEIR ATTITUDES TOWARD WORK RELATED ISSUES INCENTRAL KENTUCKY,” Midway College, Business & Teacher Education Divisions, September 2009


For EQ (in particular) experienced personnel are in shortFor EQ (in particular) experienced personnel are in short supply.

Couple that with….p

EQ has little margin of error before a significant impact on cost AND schedule.


Supply chain has shrunk over the last 30 years.pp y y

New interest fostered by industry, e.g., NEI Manufacturing Outreach Workshop

Those wishing to enter recognize the investment and impact on operations.

Both existing and new players in the supply chain need to learn about new standards, new requirements.


Sk i i iSkepticism remains.

Is the renaissance real?

How big will the market be?

First specifications are just starting to be sent out for bidbid.

Time is short; schedule is compressing.


Supply chain also includes EQ service providers.

Limited number of labs capable of achieving new conditions.

Assuming:

EQ facility can perform 8 programs/year.

Programs will be conducted overPrograms will be conducted over the next 5 years.

Maybe five facilities capable of performing testsperforming tests.

This gives you 200 programs.

Are 200 programs enough for 5 new plant designs?

Is this another choke‐point?


USNRC Regulatory Guide Update Process

Phase 1

RG1 26

Phase 2

RG 1 210

Phase 3

RG 1 40

Phase 4

RG 1 12RG1.26RG 1.29RG 1.57RG 1.61

RG 1.210RG 1.211RG 1.213

RG 1.40RG 1.73RG 1.156RG 1.158

RG 1.12RG 1.54RG 1.89RG 1.100

RG 1.92RG 1.97RG 1.128RG 1.208

RG 1.122RG 1.155

RG 1.209


What’s Going On with theWhat s Going On with the Motherhood Documents?

Regulatory Guide 1.89 Regulatory Guide 1.100

IEEE 323 IEEE 344IEEE 323 IEEE 344

ASME QME‐1


IEEE 323TM‐2003, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating StationsEquipment for Nuclear Power Generating Stations

Reg. Guide 1.89 still endorses the 1974 version of IEEE‐323.

Reg. Guide 1.209 endorses parts of the 2003 version.

Standard may also be utilized for the qualification of equipment in mild environments.

Test margins have been updated; the performance of two transients is no longer recommended.

Incorporation of EMI/RFI/EMC Requirements.

Differentiation between qualified life and qualified condition.


IEEE 344TM‐2004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear PowerQualification of Class 1E Equipment for Nuclear Power

Generating Stations

R i i h b i d b NRC t d i i i 3 fRevision has been reviewed by NRC as noted in revision 3 of Regulatory Guide 1.100 issued in September of 2009.

Standard revised to incorporate specific guidance on usingStandard revised to incorporate specific guidance on using Earthquake and Testing Experience as a Basis for Seismically Qualifying New Equipment.

NRC may allow use of experience based methods on a case‐by‐case basis.


ASME QME ‐1‐2007, Qualification of Active Mechanical Equipment Used in Nuclear Power PlantsMechanical Equipment Used in Nuclear Power Plants

Historically, the functional qualification of power operated active valves has been governed by ANSI B16.41 (an extension of ANSI N278.1, endorsed by Regulatory Guide 1.148). The requirements of this standard have been incorporated into ASME QME‐1 which, for the first time, have been endorsed by the USNRC via revision 3 of Regulatory Guide 1.100.revision 3 of Regulatory Guide 1.100.

“We have received comments from testing labs that certain tests … were very difficult to perform at best, and very dangerous to perform at worst.”

“There have been inquiries that we have discussed and had to say, “Yes that is what it says”; while within the committee we wonder, “How are they going to do that?””

Reference: “Qualifying Active Valves for use in Nuclear Power Plants, A new Revision to ASME QME‐1 Section QV,” NUREG/CP‐0152, Volume 5.


Other IEEE Qualification Standards In Revision Process

IEEE 7‐4.3.2‐2003, Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations

IEEE 317‐1983, IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations

IEEE 323‐2003, Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations

IEEE 336‐2005, IEEE Guide for Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Nuclear Facilities

IEEE 344‐2004, IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations

IEEE 387‐1995, IEEE Standard Criteria for Diesel‐Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations

IEEE 497‐2002, IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

IEEE 535‐2006, IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations

IEEE 627‐1980, IEEE Standard for Design Qualification of Safety Systems Equipment Used in Nuclear Power Generating Stations

IEEE 628‐2001, IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations

IEEE 638‐1992, IEEE Standard for Qualification of Class 1E Transformers for Nuclear Power Generating Stations

IEEE P1682, Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems of Nuclear Power Generating Stations (new standard)

C3 10 S d d f Q lif i Cl 1 i l d ili i f l G i S iIEEE PC37.105, Standard for Qualifying Class 1E Protective Relays and Auxiliaries for Nuclear Power Generating Stations


AND, Don’t Forget…~4500 Other Standards Cited in Regulatory Documents4500 Other Standards Cited in Regulatory Documents

ASA

ACI AISC

ANSI ANS API

APHA ASCE ASHRAE ASMEAPHA ASCE ASHRAE ASME

ASNT ASQC ASTM ATC AWWA

AWS CMAA DEMA FM HPS HEI

ICEA IEEE ISA ICRP ISO MSS MIL

NCMA NACE NCRP NEMA NETA NFPA NIST UL

Reference: NUREG/CR‐5973, PNL‐8462 Rev. 3, “Codes and Standards and Other Guidance Cited in Regulatory Documents,” Published August 1996.


Nuclear Energy Standards Coordination Collaborative

The Nuclear Energy Standards Coordination Collaborative (NESCC) is a cross‐stakeholder forum to identify and respond to the current needs of the nuclear industry.

Formed in 2009 by the American National Standards Institute (ANSI) and the National Institute for Standards and Technology (NIST), NESCC works to facilitate and coordinate the timely identification, development, and revision of standards for the design, operation, development, licensing, and deployment of nuclear power plants. Standards for other nuclear technologies including advanced reactor concepts will also befor other nuclear technologies, including advanced reactor concepts, will also be addressed.

http://www.ansi.org/standards_activities/standards_boards_panels/nescc/overview.aspx?menuid=3

What is new with the new plants designs?

What is new with the new plant designs?

Standardization, Modular Design

New plants will be constructed in modules.

Equipment supply will be tied to module construction schedule.

This could move EQ activities further ahead in the schedule as compared to previous construction efforts.


Much more reliance on computer based and digital equipment.p g q p

Protect against RFI/EMI; conform to EMC requirements.

Software and Firmware Verification and Validation.

System integration with faster response times.

2 milliseconds used to be considered chatter; now it can be an eternity.


10CFR50.69

Will any new plants use RISC criteria?

This could involve EQ on items not previously considered for qualification.


60 Year Qualified Life vs. 40

T t Q lifi d Lif i 60 YTarget Qualified Life is 60 Years.

• Accelerated thermal aging time will increase by 50%;

• Radiation aging will increase.Radiation aging will increase.

• However, The thermal aging portion is typically the longest segment of a qualification program.

d bCan reduce time by:

• Increasing aging temperature (supplier decision).

• Refining normal environment design temperature profileRefining normal environment design temperature profile (plant design issue).

• Finding materials with more favorable activation energies without sacrificing performance (supplier decision).without sacrificing performance (supplier decision).

• Refine existing activation energies (supplier decision)


Line mounted equipment requirements with higher demand.


New site locations result in new seismic demands; concern with HF associated with Hard Rock Sitesassoc a ed a d oc S es

Existing CEUS plants have been designed to deterministic response spectra that have dominant energy content in the frequency range from 2 to 10 Hzdominant energy content in the frequency range from 2 to 10 Hz.

Recent site‐specific probabilistic hazard‐based ground motion response spectra for new plants have high frequency content which exceeds the design spectra scaled from Reg Guide 1 60 spectral shapesReg. Guide 1.60 spectral shapes.

This may result in exceedances of in‐structure response spectra developed for hard rock sites.

Concerns center on “potentially HF vibration sensitive components.”


The new plant designs have design basis accident d h h h h k d fconditions which require higher peak conditions faster

and have more severe post accident conditions.

Typical transient for in containment application. Steam line compartments have even higher peak temperatures (~500 F). Minimizing overtest is even moreMinimizing overtest is even more critical today than before.

NEW EQ TESTS… NEW CHALLENGES

NEW EQ TESTS… NEW RESULTS

How will the Operating Fleet Be Affected?

How will the Operating Fleet be affected?

More OEM’s in the l h

Competition for Owner/Operator

Supply Chain

New Tech for

Owner/Operator CapEx

Competition for Mods/Replacements

New Data to Support

Skilled Workers

More Attention Given to New Shiny

PLEX

Expanding

Given to New Shiny Plants

New Vulnerabilities p gWorkforce

S I d

Exposed by New EQ

Ob lStronger Industry Obsolescence

Questions?Questions?


THANK YOUTHANK YOU

Serena KrauseKinectrics US, IncSenior Engineer US Nuclear Programs513.600.8410Serena Krause@kinectrics [email protected]

Backup Slides

Backup SlidesBackup Slides

Kinectrics Specialized Facilities

EQ / CGD & Mechanical Testing LaboratoryTesting LaboratoryAnalytical / Radio-Chemistry LaboratoriesR di ti M t i lRadioactive Materials Characterization FacilityTritium LaboratoryyResin Testing / Process ChemistryHigh Voltage / High CurrentHigh Voltage / High Current LaboratoryEnvironmental Testing & T h l iTechnologies

In-house EQ Capability

Typical Standards…

IEEE 323 for environmental qualificationIEEE 344 for seismic qualification IEEE 649 for motor control centresIEEE 649 for motor control centresANSI B16.41 for power operated active valvesASME QME-1 for active mechanical equipmentCSA B51-1994 for pressure retaining devicesIEEE C37 98 and C37 105 for relaysIEEE C37.98 and C37.105 for relaysIEEE 334 for continuous duty Class 1E motorsIEEE 382 for actuators for power operated valvesIEEE 383 for cables and splicesIEEE 650 for battery chargersIEEE 650 for battery chargersIEEE 535 for batteriesMSS SP-100 for valve diaphragms

Environmental ChambersBig and Small

Seismic & Dynamic Testing

Upgraded LOCA/HELB Facilities

Mechanical Testing/Strong Floor

New Decontamination & Refurbishment Facility

High Voltage Testing

High Current Testing

In-house Machining and Prototyping

2010 April IEEE SC2 Vegas · 2017. 6. 26. · Phase 1 RG1 26 Phase 2 RG 1 210 Phase 3 RG 140 Phase...

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