ML12250A771
| ML12250A771 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/06/2012 |
| From: | Kalyanam N Plant Licensing Branch IV |
| To: | Clark R Entergy Operations |
| Kalyanam N | |
| References | |
| TAC ME8272 | |
| Download: ML12250A771 (3) | |
Text
From:
Kalyanam, Kaly To:
CLARK, ROBERT W Cc:
Chen, Qiao-Lynn
Subject:
Request for Additional Information for Relief Request AN)2-ISI-010 Date:
Thursday, September 06, 2012 1:07:19 PM Ms. Chen,
When you get a chance, could you please include this email in ADAMS?
Thanks
Kaly
The SUNSI information as follows:
Plant: Arkansas Nuclear One, Unit 2 Docket No.: 50/368
Subject:
RAI on Request for Relief No. ANO2-ISI-010 TAC NO. ME8272 SUNSI Review Done: Yes. Not Publicly Available, Normal Release, Non-sensitive, From: N. Kalyanam To: Robert Clark
R. Clark:
By letter dated March 26, 2012, Entergy Operations, Inc., submitted proposed alternative ANO2-ISI-010 requesting relief from required volumetric examination coverage of American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, Examination Category B-J welds under the Arkansas Nuclear One, Unit 2 (ANO-2) Risk Informed Inservice Inspection (RI-ISI)
Program.
The NRC has reviewed the information submitted by the licensee and determined the following additional information is required to complete the evaluation. Entergy is requested to provide the response to this request within 45 days of the receipt of this e-mail. If for some reason, additional time is needed, please let us know in advance.
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST ANO2-ISI-010 EXAMINATION REQUIREMENTS FOR CATEGORY B-J WELDS ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT 2
DOCKET NUMBER 50-368
By letter dated March 26, 2012, Entergy Operations, Inc., submitted proposed alternative ANO2-ISI-010 (Reference 1) requesting relief from required volumetric examination coverage of American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, Examination Category B-J welds under the Arkansas Nuclear One, Unit 2 (ANO-2) Risk Informed Inservice Inspection (RI-ISI) Program (Reference2). In order to complete the review, the staff requests the following additional information:
- 1. How many Examination Category B-J welds exist at ANO-2 and how many were to be examined under the RI-ISI Program?
- 2. How many Examination Category B-J welds for which adequate coverage was obtained were examined with ASME Code,Section XI, Appendix VIII qualified procedures?
- 3. Describe the procedure used for calculating the scan coverage
- 4. For each of the 30 subject Examination Category B-J welds for which adequate examination coverage could not be obtained:
- a. Specify the safety significance classification (High or Medium) of each.
- b. Specify whether it was examined using an ASME Code,Section XI, Appendix VIII qualified procedure.
- c. Specify the diameter and wall thickness, and the materials of construction.
- d. Provide accurately proportioned drawings clearly showing the area of missed examination coverage for each weld. Describe the reason for the missed coverage.
- e. Was the weld examined under the RI-ISI program? For those welds that are described by ASME Code,Section XI, Table IWB-2500-1 item numbers (e.g., B9.11, B9.21) identify any potential degradation mechanism the welds may be susceptible to.
- f. For those welds that have a potential degradation mechanism, explain why the examination coverage achieved is adequate to detect the potential degradation mechanism. Was an adjacent weld examined?
- g. For those welds that do not have a potential degradation mechanism, explain why other welds with the same safety significance, for which adequate examination coverage could be achieved, are not being examined.
- h. For those welds where the scan in the axial direction was performed from one side of the weld only, was a best effort attempt made to scan the material on the opposite side of the weld? If not, explain why this was not done and discuss any benefit that a best effort scan may provide.
REFERENCES
- 1. Requests for Relief from American Society of Mechanical Engineers (ASME)
Section XI Volumetric and Surface Examination Requirements - Third 10-Year Interval, Agencywide Documents Access and Management System (ADAMS)
Accession No. ML12086A293
- 2. Safety Evaluation by the Office of Nuclear Reactor Regulation, Proposal to Use ASME Code Case N-578 as an Alternative to ASME Code Section XI, Table IWX-2500, ADAMS Accession Nos. 9901050347 and 9901050353