NL-11-0482, Edwin I. Hatch, Units 1 and 2, Request for Additional Information (RAI) Re Fourth 10-Year Interval Lnservice Inspection Program: Difference between revisions

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{{Adams
#REDIRECT [[NL-11-0482, Request for Additional Information (RAI) Re Fourth 10-Year Interval Lnservice Inspection Program]]
| number = ML110820261
| issue date = 03/22/2011
| title = Edwin I. Hatch, Units 1 and 2, Request for Additional Information (RAI) Re Fourth 10-Year Interval Lnservice Inspection Program
| author name = Ajluni M J
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/NRR, NRC/Document Control Desk
| docket = 05000321, 05000366
| license number =
| contact person =
| case reference number = NL-11-0482
| document type = Letter type:NL
| page count = 6
}}
 
=Text=
{{#Wiki_filter:Mark J. Ajluni, P.E. Southern Nuclear Nuclear Licensing Director Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 March 22, SOUTHERN'\'
COMPANY Docket 50-321 NL-11-0482 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant, Units 1 and Request for Additional Information Fourth 10-Year Intervallnservice inspection Ladies and Gentlemen:
By letter dated July 8, 2010, Southern Nuclear Operating Company, Inc. (SNC), submitted relief requests for the Fourth 10-Year Intervallnservice Inspection Program for Edwin I. Hatch Nuclear Plant, Units 1 and 2. By letter dated November 23,2010, SNC provided response to NRC requested additional information in letters dated October 5, 2010, regarding review of relief requests ISI-RR-02, ISI-RR-06 and ISI-RR-07, and October 22,2010, regarding review of relief requests ISI-RR-03, ISI-RR-04, ISI-RR-05, ISI-RR-08, ISI-RR-09, 10, and ISI-RR-11.
By letter dated February 23, 2011, the NRC requested additional information in support of review of relief requests ISI-RR-04 and ISI-RR-10.
The SNC response to the NRC RAls is provided in the Enclosure.
This letter contains no NRC commitments.
If you have any questions, please contact Jack Stringfellow at (205) 992-7037.
Respectfully submitted, M. J. Ajluni Nuclear licensing Director MJA/LPHllac
 
==Enclosure:==
 
Hatch Nuclear Plant -Units 1 and 2, Response to Request for Additional Information Regarding Proposed Relief Requests for the Fourth ISllntervaIISI-RR-04 and ISI-RR-10 U. S. Nuclear Regulatory Commission NL-11-0482 Page 2 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President
-Hatch Ms. P. M. Marino, Vice President
-Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Mr. V.M. McCree, Regional Administrator Mr. P. G. Boyle, NRR Project Manager Mr. E. D. Morris, Senior Resident Inspector
-Hatch Edwin I. Hatch Nuclear Plant, Units 1 and Response to Request for Additional Information Proposed Relief Requests for the Fourth lSI Interval ISI-RR-04 and ISI-RR-10 
 
Response to Request for Additional Information Proposed Relief Requests for the Fourth ISllntervaIISI-RR-04 and ISI-RR-04, (HNP, Unit 2) ASME Code, Section XI, Examination Category B-J, Dissimilar Metal Pressure Retaining Welds in Piping NPS 4 or Larger Circumferential Weld NRCRAI For Weld 2B21-1FW-12AA-8: What is the weld metal? What is the Generic Letter 88-01 category of this weld? Please discuss the susceptibility of this weld to Intergranular Stress Corrosion Cracking. The NRC staff acknowledges that the weld overlay was applied prior to the Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a mandated implementation of Appendix VIII, and that the subject welds has been mitigated by the mechanical stress improvement process. However, the significant lack of creditable coverage for Appendix VIII examinations as a result of the licensee's decision to stop the overlay at the toe of the weld concerns the staff. Please discuss whether plans are in place to increase the creditable coverage of this weld by means such as extending the overlay or performing a Supplement 11 qualification demonstration on a site-specific mockup and if not, then why not? SNC Response Weld 2B21-1 FW-12AA-8 joins an Inconel600 Safe End Extension to a Steel Transition Piece using Inconel 182 weld material.
This is shown on The Generic Letter 88-01 category of weld 2B21-1 FW -12AA-8 is Category This is due to the weld material not being made of Intergranular Stress Cracking (IGSCC) resistant material, and the weld has been given a improvement (SI) after more than two years of operation.
The weld received mechanical stress improvement process (MSIP) in Per the NRC staff positions in Generic Letter 88-01, carbon steel is resistant to IGSCC, while Inconel 82 is the only nickel base alloy considered be resistant to IGSCC. Therefore, MSIP was used to reduce the susceptibility the Inconel portions of this weldment to Due to the significant lack of coverage for Appendix VIII examinations, this is scheduled to receive an overlay prior to the end of the 4th Inservice Interval which ends December 31 , 
 
Response to Request for Additional Information Proposed Relief Requests for the Fourth lSI Interval ISI-RR-04 and 151-RR-10, (HNP, Unit 2) ASME Code, Section XI, Examination Category B-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzle-to Safe End Welds NPS 4 or Larger NRC RAI In the response to the NRC's Request for Additional Information, it was noted that two subsurface, circumferentially oriented, planar flaws were detected in Weld 10A-21 and one subsurface, circumferentially oriented, planar flaw was detected in weld 2E21-1 CS-1 OB-20. Please describe how these flaws were determined to be subsurface.
Is there a reinspection plan in place for these welds? Also, please explain how it is that weld shrinkage created the exact same examination limitation on two different welds. SNC Response SNC is aware of previous examination issues in the industry where only the upper portion of a flaw was detected during an examination and was evaluated as a subsurface flaw. Subsequently, after further weld preparation and re-examination, it was determined that the flaw was actually connected to the inside surface. This situation occurred at Hatch on a recirculation inlet nozzle-to-safe end weld during the same 2009 outage in which the subject Core Spray welds were examined.
However, for the Core Spray welds, the automated phased-array display clearly showed that no flaws are closer than 1/4" to the inside surface. Prior to the Core Spray weld examinations, the weld crowns were removed and the only examination interference was from shrinkage at the downstream toe of the welds. A review of the data sheets indicates that there was no interference during the examination of the welds for circumferentially-oriented flaws; therefore, the circumferentially-oriented indications were determined to be subsurface. These flaws were evaluated as subsurface and acceptable in size. Therefore, there are no plans to re-inspect these welds per IWB-2420(b). These Core Spray welds are both safe end-to-nozzle welds (Train A and B) that have essentially the same configuration.
Therefore, the weld shrinkage area causing the limitation was in the same location. 
 
Response to Request for Additional Information Proposed Relief Requests for the Fourth lSI Interval ISI-RR-04 and 1!lEHTlflCA 11111 1/110 . liJrn.r TO vtSS!1 2N4A, B, C, 2. I(JZ1lE Ilt&#xa3;lI RADIUS 10 3. TRANS-PlECE m lelzm BJ BJ B!' BJ IJI' 8. PIP[ m TRANS PIW BJ 12' sct! 80 Sl\-11l6 ij/ B (CARD SITED Il!V N.lllY VELD 182 TlIANSTIlllH PIIT&#xa3; CARD STm p[rc(CARD mEl. <12' FTEDIrIATER NOZZLE ASSEMBL Y-4 NOZZl ES) R[ACI(Ji I'R[SSLIIf GIl D ClASS 1 _____ L w,* " '--"""-'9.7'
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