ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

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ASME B&PV Code for ASME B&PV Code for In-Service In-Service Inspection of Inspection of Nuclear Containment Nuclear Containment Buildings Buildings Steven G. Brown, PE Steven G. Brown, PE

Transcript of ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Page 1: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

ASME B&PV Code for In-ASME B&PV Code for In-Service Inspection of Service Inspection of Nuclear Containment Nuclear Containment

Buildings Buildings

Steven G. Brown, PESteven G. Brown, PE

Page 2: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IntroductionIntroduction Why is this of interest outside the nuclear industry?Why is this of interest outside the nuclear industry?

Professional Development HourProfessional Development Hour More than that – sharing information across various industries More than that – sharing information across various industries

for improvement of the professionfor improvement of the profession AcknowledgementsAcknowledgements

K. R. Rao – Campion Guide to ASME Boiler and Pressure K. R. Rao – Campion Guide to ASME Boiler and Pressure Vessel CodeVessel Code

Working Group ContainmentWorking Group Containment EntergyEntergy

Disclaimer – The views presented are my ownDisclaimer – The views presented are my own If it’s right, it’s because my mentors got it right, If it’s right, it’s because my mentors got it right, If it’s messed up, it’s probably my original idea.If it’s messed up, it’s probably my original idea.

Page 3: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Terminal ObjectiveTerminal Objective

At the conclusion of the class the engineer At the conclusion of the class the engineer will have a basic understanding of the will have a basic understanding of the current rules requiring inservice inspection current rules requiring inservice inspection of nuclear containment vessels. of nuclear containment vessels.

Page 4: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Enabling ObjectivesEnabling Objectives

State the purpose of containment vessel as State the purpose of containment vessel as used at commercial nuclear power plants in used at commercial nuclear power plants in the USthe US

Describe the general types of containment Describe the general types of containment vessels currently used in the US commercial vessels currently used in the US commercial nuclear power industry.nuclear power industry.

State the difference between Class MC and State the difference between Class MC and Class CC components.Class CC components.

State the regulations requiring inservice State the regulations requiring inservice inspection of nuclear containment buildings.inspection of nuclear containment buildings.

Page 5: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Enabling Objectives (cont)Enabling Objectives (cont)

Be able to state the section of ASME Code Be able to state the section of ASME Code providing requirements for inservice providing requirements for inservice inspection of Class CC components of nuclear inspection of Class CC components of nuclear containment vessels.containment vessels.

Discuss the type and frequency of inservice Discuss the type and frequency of inservice examinations for nuclear power plant examinations for nuclear power plant containment vessels.containment vessels.

Page 6: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Purpose of ContainmentPurpose of Containment

10 CFR 50 - GDC 16 10 CFR 50 - GDC 16 Containment Containment DesignsDesigns - Key design requirement for all - Key design requirement for all U.S. commercial nuclear plants. U.S. commercial nuclear plants. Establish an essentially leak tight barrier Establish an essentially leak tight barrier

against the uncontrolled release of against the uncontrolled release of radioactivity into the environmentradioactivity into the environment

Ensure that the containment design Ensure that the containment design conditions important to safety are cont conditions important to safety are cont exceeded for as long as required for post-exceeded for as long as required for post-accident conditions.accident conditions.

Page 7: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Typical Steel Containment VesselsTypical Steel Containment Vessels

Steel Pressure Vessel – Steel Pressure Vessel – Class MCClass MC

Typically Carbon SteelTypically Carbon Steel Approx. 40 to 60 psiApprox. 40 to 60 psi > 100 Feet Diameter> 100 Feet Diameter > 200 Feet Tall> 200 Feet Tall Shell thickness 1.5” or Shell thickness 1.5” or

moremore Concrete Shield BuildingConcrete Shield Building

Containment Design Diagrams on this and subsequent slides are from EPRI TM-102C

Page 8: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Typical Steel Containment VesselsTypical Steel Containment Vessels

BWR Mark I – BWR Mark I – Class MC (typical)Class MC (typical)

Nominal 62 psiNominal 62 psi Removable HeadRemovable Head Torus suppression Torus suppression

pool pool

Page 9: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Typical Steel Containment VesselsTypical Steel Containment Vessels

BWR Mark II (Shown) – BWR Mark II (Shown) – Clas MC TypicalClas MC Typical

Nominal 45 psiNominal 45 psi Removable HeadRemovable Head Suppression pool belowSuppression pool below

BWR Mark III (Not BWR Mark III (Not Shown) – May be MC or Shown) – May be MC or CCCC

Large vessel with internal Large vessel with internal drywelldrywell

Suppression pool internal Suppression pool internal around drywellaround drywell

Page 10: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Typical Concrete ContainmentTypical Concrete Containment

Concrete Structure Concrete Structure with steel linerwith steel liner

Concrete provides Concrete provides structural element – structural element – Class CCClass CC

Steel liner provides Steel liner provides leak tightness – Class leak tightness – Class MCMC

Page 11: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Typical Concrete ContainmentTypical Concrete Containment

Post-Tensioned Concrete Post-Tensioned Concrete ContainmentContainment

Concrete is kept under Concrete is kept under compression by a system compression by a system of steel tendonsof steel tendons

Tendon system and rebar Tendon system and rebar are Class CC.are Class CC.

Page 12: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Provisions for Containment Provisions for Containment Inspections and TestingInspections and Testing

10 CFR 50 - GDC 53 – Containments shall 10 CFR 50 - GDC 53 – Containments shall be designed to permitbe designed to permitAppropriate periodic inspection of all Appropriate periodic inspection of all

important areas, such as penetrationsimportant areas, such as penetrationsAn appropriate surveillance programAn appropriate surveillance programPeriodic testing at containment design Periodic testing at containment design

pressure of the leak tightness of penetrationspressure of the leak tightness of penetrations

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Philosophy of Containment Philosophy of Containment ExaminationExamination

ASME IWE and IWL define requirements for ASME IWE and IWL define requirements for containment examinationcontainment examination PreservicePreservice InserviceInservice Requirements based on Industry Experience and Requirements based on Industry Experience and

Environmental ConditionsEnvironmental Conditions Visual Examination of Containment Visual Examination of Containment Testing for TendonsTesting for Tendons Pressure / Leakage Testing per 10 CFR App JPressure / Leakage Testing per 10 CFR App J

Page 14: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

History of Code RequirementsHistory of Code Requirements

IWE 1IWE 1stst published 1981 (Class MC Components) published 1981 (Class MC Components) Weld Based ExaminationsWeld Based Examinations Very similar to rules for Class 1 and 2 nuclear Very similar to rules for Class 1 and 2 nuclear

components.components. Subsequently addressed general degradation of Subsequently addressed general degradation of

surface areassurface areas

Incorporated by rulemaking (10 CFR 50.55a) in Incorporated by rulemaking (10 CFR 50.55a) in 19961996 Required all containments to be treated as MC or CCRequired all containments to be treated as MC or CC Included conditions for useIncluded conditions for use

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History of Code RequirementsHistory of Code Requirements IWL 1IWL 1stst published 1988 (Class CC Components) published 1988 (Class CC Components)

Provided rules for examination of concrete surfacesProvided rules for examination of concrete surfaces Similar to regulatory requirements already in Similar to regulatory requirements already in

Regulatory Guides 1.35 and 1.35.1Regulatory Guides 1.35 and 1.35.1 Regulatory Guides only required for post tensioned Regulatory Guides only required for post tensioned

containmentscontainments Incorporated by rulemaking (10 CFR 50.55a) in Incorporated by rulemaking (10 CFR 50.55a) in

19961996 IWL replaced use of the Regulatory GuidesIWL replaced use of the Regulatory Guides Transition period was allowed for plants using Transition period was allowed for plants using

regulatory guidesregulatory guides Applicable to ALL concrete containmentsApplicable to ALL concrete containments

Page 16: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Current Regulatory RequirementsCurrent Regulatory Requirements

10 CFR 50.55a10 CFR 50.55a Incorporates ASME B&PV Code Section XI by Incorporates ASME B&PV Code Section XI by

reference with conditionsreference with conditionsReferences ASME Section XI Sub-Section References ASME Section XI Sub-Section

IWE for Class MC containments and Liners of IWE for Class MC containments and Liners of Class CC containmentsClass CC containments

References ASME Section XI Sub-Section References ASME Section XI Sub-Section IWL for Class CC containmentsIWL for Class CC containments

Page 17: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Containment Leak TestingContainment Leak Testing

10 CFR 50 – Appendix J10 CFR 50 – Appendix JPeriodic testing of containment vessel and Periodic testing of containment vessel and

penetrationspenetrationsType A tests – Integrated Leak Rate TestType A tests – Integrated Leak Rate TestType B and C tests – Local Leak Rate TestsType B and C tests – Local Leak Rate Tests

Page 18: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWE ExaminationsIWE Examinations

IWE-1100 SCOPEIWE-1100 SCOPE

This Subsection provides requirements for This Subsection provides requirements for inservice inspection of Class MC pressure inservice inspection of Class MC pressure retaining components and their integral retaining components and their integral attachments, and of metallic shell and attachments, and of metallic shell and penetration liners of Class CC pressure penetration liners of Class CC pressure retaining components and their integral retaining components and their integral attachments in light-water cooled plants.attachments in light-water cooled plants.

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IWE ExaminationsIWE Examinations

Exempted ComponentsExempted ComponentsComponents outside the boundaries of the Components outside the boundaries of the

containment systemcontainment systemEmbedded or inaccessible portions of Embedded or inaccessible portions of

containment (with limitations on what containment (with limitations on what modifications to plant can embed)modifications to plant can embed)

Piping, pumps, and valves (examined per Piping, pumps, and valves (examined per either IWB or IWC)either IWB or IWC)

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IWE ExaminationsIWE Examinations

General Schedule for InserviceGeneral Schedule for Inservice 10 year inspection interval10 year inspection interval Divided into 3 inspection periods (3 or 4 years)Divided into 3 inspection periods (3 or 4 years) Provisions for shifting interval (and one of the periods) Provisions for shifting interval (and one of the periods)

by one year by one year

Preservice (in general)Preservice (in general) Exam conducted prior to placing component inservice Exam conducted prior to placing component inservice Includes repair or replacementIncludes repair or replacement Same exam as required for periodic inservice examSame exam as required for periodic inservice exam

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IWE Examination TablesIWE Examination Tables

Page 22: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWE Examination TablesIWE Examination Tables

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IWE DetailsIWE Details

Category E-A Containment SurfacesCategory E-A Containment Surfaces E1.11 – Accessible Surfaces E1.11 – Accessible Surfaces

General Visual Each Period.General Visual Each Period. Includes Bolted Connections – VT-3 per 10 CFR 50.55aIncludes Bolted Connections – VT-3 per 10 CFR 50.55a

E1.12 – Wetted Surfaces of Submerged Areas E1.12 – Wetted Surfaces of Submerged Areas General Visual Each IntervalGeneral Visual Each Interval VT-3 per 10 CFR 50.55aVT-3 per 10 CFR 50.55a

E1.20 – BWR Vent System (Mark I) E1.20 – BWR Vent System (Mark I) General Visual Each IntervalGeneral Visual Each Interval VT-3 per 10 CFR 50.55aVT-3 per 10 CFR 50.55a

E1.30 – Moisture Barriers E1.30 – Moisture Barriers General Visual Each PeriodGeneral Visual Each Period

Page 24: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWE Details – Moisture BarriersIWE Details – Moisture Barriers

Page 25: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWE DetailsIWE Details

Category E-C Augmented ExaminationCategory E-C Augmented ExaminationApplicable to areas subject to accelerated Applicable to areas subject to accelerated

degradation or with previously noted degradation or with previously noted degradationdegradation

E4.11 – Visible Surfaces E4.11 – Visible Surfaces Detailed Visual Each Period.Detailed Visual Each Period.VT-1 per 10 CFR 50.55aVT-1 per 10 CFR 50.55a

E4.12 – Surface Area Grid E4.12 – Surface Area Grid Ultrasonic Thickness Measurement (UT) Each Ultrasonic Thickness Measurement (UT) Each

PeriodPeriod

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IWL ExaminationsIWL Examinations

IWL-1100 SCOPEIWL-1100 SCOPE

This Subsection provides requirements for This Subsection provides requirements for preservice examination, inservice inspection, preservice examination, inservice inspection, and repair/replacement activities of reinforced and repair/replacement activities of reinforced concrete and the post-tensioning systems of concrete and the post-tensioning systems of Class CC components, herein referred to as Class CC components, herein referred to as concrete containments as defined in CC-1000 concrete containments as defined in CC-1000 {Section III Design Code}. {Section III Design Code}.

Page 27: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL ExaminationsIWL Examinations

Exempted ComponentsExempted ComponentsSteel portions not backed by concreteSteel portions not backed by concreteShell metallic linersShell metallic linersPenetration linersPenetration liners Inaccessible tendon end anchorages (with Inaccessible tendon end anchorages (with

limitations)limitations)Concrete surfaces covered by the liner, Concrete surfaces covered by the liner,

foundation material, or backfill or otherwise foundation material, or backfill or otherwise obstructed. (Aging concerns for buried obstructed. (Aging concerns for buried concrete addressed in later editions of code.)concrete addressed in later editions of code.)

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IWL ExaminationsIWL Examinations General Schedule for Inservice ExaminationGeneral Schedule for Inservice Examination

1, 3, and 5 years following Structural Integrity Test 1, 3, and 5 years following Structural Integrity Test (SIT)(SIT)

Within 6 months on either side of anniversary Within 6 months on either side of anniversary Total inspection window of 1 yearTotal inspection window of 1 year

10 years after SIT and every 5 years thereafter10 years after SIT and every 5 years thereafter Within 1 year on either side of anniversaryWithin 1 year on either side of anniversary Total inspection window of 2 yearsTotal inspection window of 2 years

1 year plus or minus 3 months for concrete repairs1 year plus or minus 3 months for concrete repairs Preservice Preservice

Similar to IWESimilar to IWE Unique role of RPEUnique role of RPE

Page 29: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL ExaminationsIWL Examinations

Two Major DivisionsTwo Major DivisionsCategory L-A – Concrete SurfacesCategory L-A – Concrete Surfaces

All concrete containmentsAll concrete containmentsCategory L-B – Unbonded Post-Tensioning Category L-B – Unbonded Post-Tensioning

SystemSystemPost tension design onlyPost tension design onlyTendons divided by typeTendons divided by typeSeparate population for tendons impacted by Separate population for tendons impacted by

repairsrepairsProvisions for sites with multiple plants / unitsProvisions for sites with multiple plants / units

Page 30: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL Examination TablesIWL Examination Tables

Page 31: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL DetailsIWL Details

Category L-A Concrete SurfacesCategory L-A Concrete SurfacesL1.11 – All Accessible AreasL1.11 – All Accessible Areas

General Visual Each Inspection to identify suspect General Visual Each Inspection to identify suspect areasareas

Resolution per RPEResolution per RPEL1.12 – Suspect AreasL1.12 – Suspect Areas

Detailed VisualDetailed VisualUp close exam to determine if the area is a problemUp close exam to determine if the area is a problem

Performed by or under the direction of a Performed by or under the direction of a Registered Professional EngineerRegistered Professional Engineer

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IWL DetailsIWL Details

Category L-B Unbonded Post-Tensioning Category L-B Unbonded Post-Tensioning SystemsSystemsSample SizeSample Size

Sample of Tendons Sample of Tendons 4 % of Each Type4 % of Each Type Minimum of 4 and Maximum of 10Minimum of 4 and Maximum of 10

Reduced sample for good inspection history Reduced sample for good inspection history 2 % of Each Type2 % of Each Type Minimum of 3 and Maximum of 5Minimum of 3 and Maximum of 5

Separate population with reduced sample size for Separate population with reduced sample size for tendons affected by repairtendons affected by repair

Page 33: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Overview of Post-Tension Overview of Post-Tension ContainmentContainment

Page 34: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Parts of a Tendon AnchorageParts of a Tendon Anchorage

Page 35: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Exposed Tendon AnchorageExposed Tendon Anchorage

Page 36: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Uninstalled TendonUninstalled Tendon

Page 37: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Parts of a Tendon AnchorageParts of a Tendon Anchorage

Page 38: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL DetailsIWL Details

L2.10 – TendonL2.10 – TendonTendon Force / Elongation Test Tendon Force / Elongation Test

Hydraulic Ram connected to end of tendonHydraulic Ram connected to end of tendon Load cell measures force needed to lift tendon off of the Load cell measures force needed to lift tendon off of the

shimsshims

Common TendonCommon Tendon One tendon is measured in each inspectionOne tendon is measured in each inspection

Results trended to ensure tendon stress remains Results trended to ensure tendon stress remains above the minimum needed by design for life of the above the minimum needed by design for life of the plantplant

Page 39: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL DetailsIWL Details

L2.20 – Wire or StrandL2.20 – Wire or StrandDestructive sample of one wire (typical tendon up to Destructive sample of one wire (typical tendon up to

186 wires) from one tendon of each type – NOT the 186 wires) from one tendon of each type – NOT the common tendoncommon tendon

Visual exam for entire lengthVisual exam for entire lengthSample from each end, the middle and area of most Sample from each end, the middle and area of most

severe degradation tested forsevere degradation tested for Yield Strength, Yield Strength, Ultimate Strength, and Ultimate Strength, and ElongationElongation

Page 40: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL DetailsIWL Details

L2.30 – Anchorage Hardware and Surrounding L2.30 – Anchorage Hardware and Surrounding ConcreteConcreteDetailed Visual – Entire Sample PopulationDetailed Visual – Entire Sample PopulationIncludes: Includes:

bearing plates, bearing plates, anchor heads, anchor heads, wedges, wedges, buttonheads,buttonheads, shims, and shims, and concrete extending 2 feet from edge of the bearing plate.concrete extending 2 feet from edge of the bearing plate.

Page 41: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL DetailsIWL Details

L2.40 – Corrosion Protection MediumL2.40 – Corrosion Protection MediumSample from each end of each examined tendonSample from each end of each examined tendonChemical analysis for:Chemical analysis for:

Water content, Water content, Water soluble chlorides, nitrates, and sulfidesWater soluble chlorides, nitrates, and sulfides Reserve Alkalinity (expressed as milligrams of Potassium Reserve Alkalinity (expressed as milligrams of Potassium

Hydroxide)Hydroxide)

L2.50 – Free WaterL2.50 – Free WaterThe amount of any free water (if any) contained in The amount of any free water (if any) contained in

the tendon cap is documented and analyzed to the tendon cap is documented and analyzed to determine pH.determine pH.

Page 42: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

IWL ExaminationsIWL Examinations

Additional 10 CFR 50.55a exam:Additional 10 CFR 50.55a exam:Grease caps that are accessible must be Grease caps that are accessible must be

visually examined to detect grease leakage or visually examined to detect grease leakage or grease cap deformations. grease cap deformations.

Grease caps must be removed for this Grease caps must be removed for this examination when there is evidence of grease examination when there is evidence of grease cap deformation that indicates deterioration of cap deformation that indicates deterioration of anchorage hardware anchorage hardware

Page 43: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Additional 10 CFR 50.55a Additional 10 CFR 50.55a RequirementsRequirements

The licensee shall evaluate the The licensee shall evaluate the acceptability of inaccessible areas when acceptability of inaccessible areas when conditions exist in accessible areas that conditions exist in accessible areas that could indicate the presence of or result in could indicate the presence of or result in degradation to such inaccessible areas. degradation to such inaccessible areas.

Reporting RequirementsReporting RequirementsOther provisionsOther provisions

Page 44: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

ObjectivesObjectives

State the purpose of containment vessel as State the purpose of containment vessel as used at commercial nuclear power plants in used at commercial nuclear power plants in the USthe US

Describe the general types of containment Describe the general types of containment vessels currently used in the US commercial vessels currently used in the US commercial nuclear power industry.nuclear power industry.

State the difference between Class MC and State the difference between Class MC and Class CC components.Class CC components.

State the regulations requiring inservice State the regulations requiring inservice inspection of nuclear containment buildings.inspection of nuclear containment buildings.

Page 45: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Enabling Objectives (cont)Enabling Objectives (cont)

Be able to state the section of ASME Code Be able to state the section of ASME Code providing requirements for inservice providing requirements for inservice inspection of Class CC components of nuclear inspection of Class CC components of nuclear containment vessels.containment vessels.

Discuss the type and frequency of inservice Discuss the type and frequency of inservice examinations for nuclear power plant examinations for nuclear power plant containment vessels.containment vessels.

Page 46: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

ReferencesReferences

10 CFR 50.55a10 CFR 50.55aASME B&PV Code Section XI, ASME B&PV Code Section XI,

Subsections IWE and IWL, 2004 EditionSubsections IWE and IWL, 2004 EditionRao, K. R. (editor), Companion Guide to Rao, K. R. (editor), Companion Guide to

the ASME Boiler and Pressure Vessel the ASME Boiler and Pressure Vessel Code, 3Code, 3rdrd Edition Edition

EPRI TM-102CEPRI TM-102C

Page 47: ASME B&PV Code for In-Service Inspection of Nuclear Containment Buildings Steven G. Brown, PE.

Questions ?Questions ?