ML12340A686
| ML12340A686 | |
| 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: ML12340A686 (2) | |
Text
NRC000149 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Withdrawn: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:
NRC000149-00-BD01 10/15/2012 10/15/2012 AN INTERNATIONAL CODE 2010 ASM-E BoiLer '&
Pressure VesseL Code 2011a Addenda July 1, 2011 XI ULES FOR INS RVleE NSPECTIO NU AR o ER PLA COMP E
S ASME Boiler and Pressure Vessel Committee on Nuclear Inservice Inspection X011 11
ASME ZOlla SECTION XI NONMANDATORY APPENDIX A NONMANDATORY APPENDIX A ANALYSIS OF FLAWS ARTICLE A-IOOO INTRODUCTION A-HOO SCOPE This Appendix provides a procedure,,"3 for determining the acceptability of flaws that have been detected during inservice inspection (excluding pre service inspection) that exceed the allowable flaw indication standards of IW8*3S00. The procedure is based upon the principles of linear elastic fracture mechanics. This procedure applies to ferritic materials 4 in. (100 mm) and greater in thickness with specified minimum yield strengths of 50.0 ksi (3S0 MPa) or less in components having simple geometries and stress distributions. The basic concepts of the procedure may be extended to other ferritic materials (including clad ferritic materials) and more complex geometries; however, they are not intended to apply to austenitic or high nickel alloys. For purposes of analysis, indications t hat exceed the standards of IW8-3500 are considered flaws. The following is a summary of the analytical procedure.
(a) Determine the actual flaw configuration from the measured flaw in accordance with IWA-3000.
(b) Characterize the flaw in accordance with IW8-36l0.
301 (e) Using A-2000, resolve the actual flaw into a simple shape that can be analyzed.
(d) Determine the stresses at the location of the observed flaw for normal (including upset), emergency, and faulted conditions.
(e) Calculate stress intenSity factors for each condition using the methods outlined in A*3000.
(f) Using the methods outlined in A-4000, determine the necessary material properties, including the effects of irradiation if applicable.
(9) Using the analytical procedures described in A-SOOO, determine the following critical flaw para*
meters:
af = expected end-of-Iife flaw size ae = minimum critical flaw size for normal conditions Qi = minimum critical initiation flaw size for emergency and faulted conditions (h) Using the critical flaw parameters afi ae, and ail apply the flaw evaluation criteria of IWB-3600 to determine whether the observed flaw is acceptable for continued service.