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Inservice Inspection and Testing Requirements for Light-Water Cooled Nuclear Power Plants, Exercises of High Pressure Vessels and Boilers

The requirements for inservice inspection and testing of light-water cooled nuclear power plants. It covers the scope, jurisdiction, application, and owner's responsibilities for various components, classifications, and examinations. The document also includes provisions for accessibility and referenced standards.

Typology: Exercises

2011/2012

Uploaded on 07/17/2012

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ASME B&PVC SEC11$$U10 05-15-00 15:47:10 pd: sec11 Rev 15.04
A99
A00
ARTICLE IWA-1000
SCOPE AND RESPONSIBILITY
IWA-1100 SCOPE
This Division provides requirements for inservice
inspection and testing of light-water cooled nuclear
power plants. The requirements identify the areas subject
to inspection, responsibilities, provisions for accessibil-
ity and inspectability, examination methods and proce-
dures, personnel qualifications, frequency of inspection,
record keeping and report requirements, procedures
for evaluation of inspection results and subsequent
disposition of results of evaluations, and repair/replace-
ment activity requirements, including procurement, de-
sign, welding, brazing, defect removal, installation,
examination, and pressure testing.
IWA-1200 JURISDICTION
The jurisdiction of this Division covers individual
components and complete plants that have met all the
requirements of the Construction Code, commencing
when the Construction Code requirements have been
met, irrespective of physical location. When portions
of systems or plants are completed at different times,
jurisdiction of this Division shall cover only those
portions for which all of the construction requirements
have been met. Prior to installation, an item that has
met all requirements of the Construction Code may be
corrected using the rules of either the Construction
Code or this Division, as determined by the Owner.
IWA-1300 APPLICATION
IWA-1310 COMPONENTS SUBJECT TO
INSPECTION AND TESTING
Components identified in this Division for inspection
and testing shall be included in the inservice inspection
plan. These components include nuclear power plant
items such as vessels, containments, piping systems,
pumps, valves, core support structures, and storage
tanks, including their respective supports. The selection
of components for the inservice inspection plan is
11
subject to review by the regulatory and enforcement
authorities having jurisdiction at the plant site.
IWA-1320 CLASSIFICATIONS
(a) Application of the rules of this Division shall
be governed by the group classification criteria of the
regulatory authority having jurisdiction at the plant site
as follows.
(1) The rules of IWB shall be applied to those
systems whose components are classified ASME Class 1.
(2) The rules of IWC shall be applied to those
systems whose components are classified ASME Class 2.
(3) The rules of IWD shall be applied to those
systems whose components are classified ASME Class 3.
(4) The requirements of IWE shall be applied to
components classified ASME Class MC and to metallic
shell and penetration liners classified ASME Class CC.
(5) The requirements of IWF shall be applied to
supports classified ASME Class 1, 2, 3, or MC.
(6) The requirements of IWL shall be applied to
reinforced concrete and post-tensioning systems classi-
fied ASME Class CC.
(b) Optional construction of a component within a
system boundary to a classification higher than the
minimum class established in the component Design
Specification (either upgrading from Class 2 to Class
1 or from Class 3 to Class 2) shall not affect the
overall system classification by which the applicable
rules of this Division are determined.
(c) Where all components within the system bound-
ary or isolable portions of the system boundary are
classified to a higher class than required by the group
classification criteria, the rules of IWA-1320(a) may
be applied to the higher classification, provided the
rules of the applicable Subsection are applied in their
entirety.
(d) The portion of piping that penetrates a contain-
ment vessel, which is required by Section III to be
constructed to Class 1 or 2 rules for piping and which
may differ from the classification of the balance of
the piping system, need not affect the overall system
A99
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A A

ARTICLE IWA-

SCOPE AND RESPONSIBILITY

IWA-1100 SCOPE

This Division provides requirements for inservice inspection and testing of light-water cooled nuclear power plants. The requirements identify the areas subject to inspection, responsibilities, provisions for accessibil- ity and inspectability, examination methods and proce- dures, personnel qualifications, frequency of inspection, record keeping and report requirements, procedures for evaluation of inspection results and subsequent disposition of results of evaluations, and repair /replace- ment activity requirements, including procurement, de- sign, welding, brazing, defect removal, installation, examination, and pressure testing.

IWA-1200 JURISDICTION

The jurisdiction of this Division covers individual components and complete plants that have met all the requirements of the Construction Code, commencing when the Construction Code requirements have been met, irrespective of physical location. When portions of systems or plants are completed at different times, jurisdiction of this Division shall cover only those portions for which all of the construction requirements have been met. Prior to installation, an item that has met all requirements of the Construction Code may be corrected using the rules of either the Construction Code or this Division, as determined by the Owner.

IWA-1300 APPLICATION

IWA-1310 COMPONENTS SUBJECT TO

INSPECTION AND TESTING

Components identified in this Division for inspection and testing shall be included in the inservice inspection plan. These components include nuclear power plant items such as vessels, containments, piping systems, pumps, valves, core support structures, and storage tanks, including their respective supports. The selection of components for the inservice inspection plan is

11

subject to review by the regulatory and enforcement authorities having jurisdiction at the plant site.

IWA-1320 CLASSIFICATIONS

(a) Application of the rules of this Division shall be governed by the group classification criteria of the regulatory authority having jurisdiction at the plant site as follows. (1) The rules of IWB shall be applied to those systems whose components are classified ASME Class 1. (2) The rules of IWC shall be applied to those systems whose components are classified ASME Class 2. (3) The rules of IWD shall be applied to those systems whose components are classified ASME Class 3. (4) The requirements of IWE shall be applied to components classified ASME Class MC and to metallic shell and penetration liners classified ASME Class CC. (5) The requirements of IWF shall be applied to supports classified ASME Class 1, 2, 3, or MC. (6) The requirements of IWL shall be applied to reinforced concrete and post-tensioning systems classi- fied ASME Class CC. (b) Optional construction of a component within a system boundary to a classification higher than the minimum class established in the component Design Specification (either upgrading from Class 2 to Class 1 or from Class 3 to Class 2) shall not affect the overall system classification by which the applicable rules of this Division are determined. (c) Where all components within the system bound- ary or isolable portions of the system boundary are classified to a higher class than required by the group classification criteria, the rules of IWA-1320(a) may be applied to the higher classification, provided the rules of the applicable Subsection are applied in their entirety. (d) The portion of piping that penetrates a contain- ment vessel, which is required by Section III to be constructed to Class 1 or 2 rules for piping and which may differ from the classification of the balance of the piping system, need not affect the overall system

A

IWA-1320 1998 SECTION XI, DIVISION 1 IWA-

classification that determines the applicable rules of this Division. (e) If systems safety criteria permit a system to be nonnuclear safety Class and an Owner optionally classi- fies and constructs that system, or a portion thereof, to Class 2 or Class 3 requirements, the application of the rules of IWA-1320(a) is at the option of the Owner and is not a requirement of this Division.

IWA-1400 OWNER’S RESPONSIBILITY

The responsibilities of the Owner of the nuclear power plant shall include the following: (a) determination of the appropriate Code class(es) for each component 1 of the plant, and identification of the system boundaries for each class of components subject to inspection and the components exempt from examination requirements; (b) design and arrangement of system components to include allowances for adequate access and clearances for conduct of the examination and tests; (c) preparation of plans, schedules, and inservice inspection summary reports, and submittal of these plans and reports to the enforcement and regulatory authorities having jurisdiction at the plant site; (d) preparation of written examination instructions and procedures, including diagrams or system drawings identifying the extent of areas of components subject to examination; (e) verification of qualification to the required level of responsibility of personnel who perform the examina- tions; (f) possession of an arrangement with an Authorized Inspection Agency to provide inspection services; (g) performance of required examinations and tests; (h) recording of examination and test results that provide a basis for evaluation and facilitate comparison with the results of subsequent examinations; (i) evaluation of examination and test results; (j) performance of repair /replacement activities in accordance with written programs and plans; (k) maintenance of adequate inspection, examination, test, flaw evaluation, and repair /replacement activity records such as radiographs, diagrams, drawings, calcu- lations, examination and test data, description of proce- dures used, and evidence of personnel qualifications; (l) retention of all inspection, examination, test, and repair /replacement activity records and flaw evaluation calculations for the service lifetime of the component or system;

(^1) Classification criteria are specified in 10 CFR 50.

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(m) the retention and maintenance of all basic calibra- tion blocks used for ultrasonic examination of the components; (n) documentation of a Quality Assurance Program in accordance with the following: (1) Title 10, Code of Federal Regulations, Part 50; or (2) ASME NQA-1, Parts II and III, Basic Require- ments and Supplements. (o) recording of regions in ferritic steel components where acceptance standards have been modified as required in IWB-3410.2; (p) recording of regions in components where flaws or relevant conditions exceeding the acceptance stan- dards have been evaluated by analysis to allow continued operation as permitted by IWB-3132.3, IWB-3142.4, IWC-3122.3, IWC-3132.3, IWE-3122.3, IWF-3112.3, IWF-3122.3, and IWL-3212. Any continued operation time or cycle limits inherent in the analysis shall also be recorded.

IWA-1500 ACCESSIBILITY

Provisions for accessibility shall include the following considerations:^2 (a) access for the Inspector, examination personnel, and equipment necessary to conduct the examinations; (b) sufficient space for removal and storage of struc- tural members, shielding, and insulation; (c) installation and support of handling machinery (e.g., hoists) where required to facilitate removal, disas- sembly, and storage of equipment, components, and other materials; (d) performance of examinations alternative to those specified in the event structural defects or indications are revealed that may require such alternative examinations; (e) performance of necessary operations associated with repair /replacement activities.

IWA-1600 REFERENCED STANDARDS

AND SPECIFICATIONS

When standards and specifications are referenced in this Division, their revision date or indicator shall be as shown in Table IWA-1600-1.

(^2) Design considerations other than access provisions may be needed for specific system components to render inservice inspections practi- cal (such as surface finish of components subject to crud or corrosion product buildup, material selection to minimize activation in service, and shielding from irradiation effects).