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{{Adams
#REDIRECT [[NL-07-0803, Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12)]]
| number = ML071080311
| issue date = 04/13/2007
| title = Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12)
| author name = George B J
| author affiliation = Southern Nuclear Operating Co, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/ADRO
| docket = 05000425
| license number =
| contact person =
| case reference number = NL-07-0803, TAC MD2794, TAC MD2795, TAC MD2796, TAC MD2797
| document type = Drawing, Graphics incl Charts and Tables, Letter
| page count = 10
| project = TAC:MD2794, TAC:MD2795, TAC:MD2796, TAC:MD2797
| stage = Other
}}
 
=Text=
{{#Wiki_filter:I -T Southern Nuclear Operating Company, Inc.Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERNAZ COMPANY April 13, 2007 Energy to Serve Your Worlds" Docket No.: 50-425 NL-07-0803 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant -Unit 2 Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12)Ladies and Gentlemen:
Southern Nuclear Operating Company (SNC) completed the last performance demonstration initiative (PDI) qualified ultrasonic examination (UT) of Vogtle Electric Generating Plant (VEGP) Unit 2 pressurizer nozzle full structural weld overlays (FSWOLs) on April 1, 2007. This activity was accomplished in accordance with SNC's alternative ISI-GEN-ALT-06-03, Rev. 2, which was approved per NRC safety evaluation report (SER) (TAC Nos. MD2794, MD2795, MD2796 AND MD2797). Page 18 of the SER includes the following statement: "the Licensee will provide the NRC, within 14 days after the completion of the ultrasonic examination of the weld overlay installations, (1) the examination results of the weld overlays, (2) a discussion of any repairs to the overlay material and/or base metal and the reason for repair, and (3) will perform the subsequent ISI in accordance with Q-4300 of Appendix Q to the ASME Code, Section XI." Enclosure 1 contains the requested examination and repair information.
Enclosure 2 contains the SNC commitment to perform subsequent ISI on the pressurizer FSWOLs, in accordance with Q-4300 of Appendix Q to the 2004 Edition of Section XI with Addenda through 2005.This letter contains one NRC commitment.
If you have any questions, please advise.Sincerely, B. J. Georl Manager, Nuclear Licensing ,4o7 U. S. Nuclear Regulatory Commission NL-07-0803 Page 2 BJG/DRG/daj
 
==Enclosures:==
: 1. Vogtle Unit No. 2 Weld Overlay Examination Results and Repairs Table 2. Regulatory Commitment List cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President T. E. Tynan, Vice President
-Vogtle Mr. D. H. Jones, Vice President
-Engineering RType: CVC7000 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. B. K. Singal, NRR Project Manager -Vogtle Mr. G. J. McCoy, Senior Resident Inspector
-Vogtle Enclosure I Vogtle Electric Generating Plant Unit 2 Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12)
Enclosure 1 Vogtle Unit No. 2 Weld Overlay Examination Results and Repairs Table Nozzle Results PT of Mitigation Layer PT of Overlay PDI UT Exam Post PDI UT Repairs PDI UT PT of Base Metal Results/Repairs Results/Repairs Results Re-exams N-i1N SFT NRI NRI NRI NRI NONE NA SAFETY UT exams detected an acceptable Numerous rejectable lamination located at the interface of indications found at the 1800 the overlay and the dissimilar metal Quadrant;indications fou he 1weld. The surface area of the Two linear in the range of 0.062-inches lamination is 0.2 square inches with a indications; to 0.250-inches.
The max dimension of 0.62-inches.
07nch and indications were repaired There was no loss of coverage in the 0.07-inch and and a new PT examination overlay material, thus a planar flaw N-2 0.12-inch.
The was performed with NRI was not postulated.
The reduction in NONE NA SAFETY indications were indications observed at 900 coverage of the preservice inspection repaired and a new 1/16-inch to 0.25-inches and volume is less than 0.2% and the PT was performed at 2700 1/16-inch to 0.25- lamination is sufficiently small such with acceptable inches. The indications that there is reasonable assurance that results. were repaired and a new PT a PWSCC indication growing into was performed with the upper 25% (of the original wasceptlerormedith.
dissimilar metal weld) would be acceptable results. detected.
See the attached figure to show indication location.One linear indication with a length of 1/4-inch was detected at the weld toe to pipe interface.
The N-3 indication was SAFETY NRI NRI repaired and a new NRI NONE NA PT was performed with acceptable results.El-i Enclosure 1 Vogtle Unit No. 2 Weld Overlay Examination Results and Repairs Table Nozzle Results PT of Mitigation Layer PT of Overlay PDI UT Exam Post PDI UT Repairs PDI UT PT of Base Metal Results/Repairs Results/Repairs Results Re-exams Two indications due to probable hot cracking: Indication 1 @ 900 Length = 5.6-inches N-4 Indication 2 @ 1800 RELIEF NRI Length = 2.8-inches NRI NRI NONE NA The indications were repaired and a new PT was performed with acceptable results.After the first layer of credited weld overlay was applied, a PT Grinding was performed examination to remove the laminar detected numerous indication.
A PT indications examination of the through the entire An intermittent 3600 laminar excavated area was weldfoband 3600 weld band 360t indication was detected by UT. It performed with around the pipe. was approximately 1/8-inch above acceptable results. In the N-5 The indications the original surface near the interface SPRAY were repaired and NRI NRI of the safe-end to stainless steel the ground-out area, six NRI a new PT was weld. The likely cause was lack of linear PT indications were perfrme wih wld.Thelikey cusewaslac of observed (lengths varied performed with fusion. See the attached figure to from 0.125-inch to 0.250-acceptable results. show indication location.
fo .15ic o020 The remainder of inch). These indications the weld overlay were ground out and the was installed and areas were re-welded.
A the subsequent PT new PT was performed examination with acceptable results.showed no recordable indications.
El-2 Enclosure 1 Vogtle Unit No. 2 Weld Overlay Examination Results and Repairs Table Nozzle Results PT of Mitigation Layer PT of Overlay PDI UT Exam Post PDI UT Repairs PDI UT PT of Base Metal Results/Repairs Results/Repairs Results Re-exams Three linear indications that were 0.1inch long each, plus one 0.3-inch rounded N-6 indication were SRENRI NRI dtce.TeNRI NONE NA SURGE detected.
The indications were repaired and a new PT was performed with acceptable results.NRI -No Recordable Indications El-3 Enclosure 1 Vogtle-2 Figures showing Indication Locations VEGThIE 2 SAFETY NUiZZLE-N?
INDICATION 1 EVALUA~TED AT 0'5500 5.185 5.125 X A INDICATION 1 08B33 08,42 0.828.......,'-'X 4.854 CIRCUMF=30.5 4.735 CIRCUMF=29.75 N2 FINAL 03 2.e97 The acceptable laminar indication for Nozzle N-2 is shown in the figure above and exists at the interface between the final weld overlay and the original Alloy-600 weld.El-4 Enclosure 1 Vogtle-2 Figures showing Indication Locations VDGTLE 2 SPRAY NDZZLE-N5 INDICATIDN 1 EVALUATED AT 18°o 7.13 INDICATION 1 X 11.2001 X X- 0.440 x x ---- ................
°---------------------------
0.555 ., ,, !/ x x ..R3 6 R3020 N 1EV IS D 31 0 ' -0.7.... ...............
... ..REVISED 31 MAR 07 The unacceptable laminar indication for Nozzle N-5 is shown in the figure above and was removed during the fabrication process and therefore, does not exist in the final weld overlay.E1-5 Enclosure 2 Vogtle Electric Generating Plant Unit 2 Pressurizer Nozzle Full Structural Weld Overlay Nondestructive Examination Results Spring 2007 Outage (2R12)Regulatory Commitment List q*Enclosure 2 Regulatory Commitment List The following table identifies those actions committed by Southern Nuclear Operating Company in this document for Vogtle Electric Generating Plant. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
Scheduled Completion Date Commitment Type (If Required)One-Time Continuing Action Compliance Perform subsequent ISI on the VEGP Unit 2 pressurizer FSWOLs in accordance with Q-4300 of X Appendix Q to the 2004 Edition of Section XI with Addenda through 2005 _E2-1}}

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