ML12340A680

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Official Exhibit - NRC000150-00-BD01 - ASME Section XI, Appendix C (Excerpt)
ML12340A680
Person / Time
Site: Indian Point  
Issue date: 07/01/2011
From:
American Society of Mechanical Engineers (ASME)
To:
Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 23327, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML12340A680 (2)


Text

NRC000150 Submitted: August 20, 2012 United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of:

Entergy Nuclear Operations, Inc.

(Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #:

Identified:

Admitted:

Withdrawn:

Rejected:

Stricken:

Other:

NRC000150-00-BD01 10/15/2012 10/15/2012 AN INTERNATIONAL CODE 2010 ASM,E'Boller 's. '

Pressure Vessel Code 2011a Addenda JuLy 1,2011 LES F R INS RVIC PECTIO OF N A

OWE P C MP TS ASME Boiler and Pressure Vessel Committee on Nuclear Inservice Inspection X011 11

ASME 2011a SECTION XI NONMANDATORY APPENDIX C NONMANDATORY APPENDIX C EVALUATION OF FLAWS IN PIPING ARTICLE C-I000 INTRODUCTION C-1100 SCOPE This Article provides the general scope and application of the evaluation methodology for flawed pipe.

(a) This Appendix provides a method for determining the acceptability for continued service of piping containing flaws that exceed the acceptance standards of IWB-3S14 or IWC-3S14. The evaluation methodology is based on the following conditions that govern pipe failure.

(1) Limit load (fully plastic) analysis of the pipe cross-section which is reduced by the flaw area, for ductile materials when the ability to reach limit load is assured.

(2) Elastic-plastic fracture mechanics when ductile flaw extension occurs prior to reaching limit load.

(3) Linear elastic fracture mechanics for brittle fracture conditions. The procedures are applicable to flaws in weld materials or base material as defined in Fig. C-ll00-1.

(b) This Appendix provides a screening procedure to detennine the failure mechanism based on metal tem-perature, applied loads, flaw size, and material properties.

Flaws are evaluated by comparing the maximum flaw dimensions at the end of the evaluation period with the allowable flaw size, or by comparing the applied pipe stress with the allowable stress for the flaw size at the end of the evaluation period.

(e) This Appendix also provides procedures for flaw modeling and evaluation. Flaw growth analysis is based on fatigue. When stress corrosion cracking (SCC) is active, the growth shall be added to the growth from fatigue. The flaw acceptance criteria ofC-2600 include structural factors on failure for the three failure mechanisms described in (a).

The acceptance criteria shall be used to determine acceptability of the flawed piping for continued service for a specified evaluation time period or to detennine the time interval until a subsequent inspection.

Figure C-1100-1 Weld Material-Base Material Interface Definition for Flaw Location B.~

Weld B.~

material material material x = lesser of tl2 or 0.5 in. (13 mm) 325