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| issue date = 12/13/2007 | | issue date = 12/13/2007 | ||
| title = Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004 | | title = Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004 | ||
| author name = Hamilton B | | author name = Hamilton B | ||
| author affiliation = Duke Energy Carolinas, LLC, Duke Energy Corp, Duke Power Co | | author affiliation = Duke Energy Carolinas, LLC, Duke Energy Corp, Duke Power Co | ||
| addressee name = | | addressee name = | ||
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=Text= | =Text= | ||
{{#Wiki_filter:BRUCE H HAMILTON Duke Vice President Energye Oconee Nuclear Station Duke Energy Corporation ONO] VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy. | {{#Wiki_filter:BRUCE H HAMILTON Duke Vice President Energye Oconee Nuclear Station Duke Energy Corporation ONO] VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy.com December 13, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 | ||
com December 13, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 | |||
==Subject:== | ==Subject:== | ||
Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2, and 3 Docket No. 50-270,-287 Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004 By letters dated January 31, 2007 (ADAMS Accession | Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2, and 3 Docket No. 50-270,-287 Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004 By letters dated January 31, 2007 (ADAMS Accession # | ||
ML070390049) and February 22, 2007 (ADAMS Accession # | |||
ML070600169), Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC (Duke) committed to a mitigation schedule regarding Alloy 82/182 butt welds on Pressurizer piping for Units 2 and 3 of the Oconee Nuclear Station (Oconee). The NRC Confirmatory Action Letter (CAL) of March 27, 2007 (ADAMS Accession # ML070790113) regarding Alloy 82/182 butt welds requires a report within 60 days of unit restart of any mitigative actions taken on the subject welds. | |||
The NRC Confirmatory Action Letter (CAL) of March 27, 2007 (ADAMS Accession | In order to support these mitigative actions, on March 12, 2007 Duke submitted Relief Requests (RR) 07-ON-001 (ADAMS Accession # | ||
# ML070790113) regarding Alloy 82/182 butt welds requires a report within 60 days of unit restart of any mitigative actions taken on the subject welds.In order to support these mitigative actions, on March 12, 2007 Duke submitted Relief Requests (RR) 07-ON-001 (ADAMS Accession | ML070790293) to support application of full structural weld overlays on various pressurizer nozzle to flange, nozzle-to-safe end, and surge line welds. NRC verbally approved this request on May 17, 2007 and provided written approval by letter dated August 6, 2007 (ADAMS Accession #. ML071280781). In this request Duke committed to provide a report summarizing the results of the UT examinations of the weld overlays within 14 days of completion of the UT examinations. | ||
By letter dated May 29,. 2007, (ADAMS Accession # ML071560504) | |||
#. ML071280781). | Duke notified the NRC of the completion of the actions ' | ||
In this request Duke committed to provide a report summarizing the results of the UT examinations of the weld overlays within 14 days of completion of the UT examinations. | applicable to Unit 2 within the scope of the CAL, and included www. duke-energy. com 0 W | ||
By letter dated May 29,. 2007, (ADAMS Accession | |||
# ML071560504) | U. S. Nuclear Regulatory Commission Page 2 December 13,. 2007 the report relative to UT examinations for associated weld overlays as committed in RR 07-ON-001. | ||
Duke notified the NRC of the completion of the actions 'applicable to Unit 2 within the scope of the CAL, and included www. duke-energy. | In addition, on September 13, 2007, Duke submitted RR 07-ON-004 (ADAMS Accession # ML072620149), applicable to all three Oconee units, to seek similar relief related to full structural weld overlays on the Decay Heat Removal (DHR) Drop line to Hot Leg Nozzle welds. These welds are not subject to the CAL, but the RR also included a commitment to provide the results of the UT examinations within 14 days of completion of examinations on the DHR line overlay. The NRC staff provided verbal approval of RR 07-ON-004 on November 27, 2007. | ||
com 0 W U. S. Nuclear Regulatory Commission Page 2 December 13,. 2007 the report relative to UT examinations for associated weld overlays as committed in RR 07-ON-001. | This letter is to inform you of the completion of the mitigative repairs for Oconee Unit 3 as listed oh Enclosure 4 of our January 31, 2007 letter. These actions were completed during 3EOC23 refueling outage and complete the actions related to all three Oconee units to satisfy the CAL. Enhanced leakage detection requirements committed to in our February 22, 2007 letter are no longer required on any Oconee unit due to the completion of mitigation of the subject welds. | ||
In addition, on September 13, 2007, Duke submitted RR 07-ON-004 (ADAMS Accession | Also, the Unit 3 UT examinations of the Pressurizer and DHR drop line weld overlays were completed November 30, 2007. No flaws outside the IWB-3514 criteria were identified, and no.repairs were made to. the weld overlays, the original base materials or original 82/182 weld materials. The attached Enclosure provides a report summarizing the results of these examinations, per the commitments contained in RR 07-ON-001 and RR 07-ON-004, respectively. | ||
# ML072620149), applicable to all three Oconee units, to seek similar relief related to full structural weld overlays on the Decay Heat Removal (DHR) Drop line to Hot Leg Nozzle welds. These welds are not subject to the CAL, but the RR also included a commitment to provide the results of the UT examinations within 14 days of completion of examinations on the DHR line overlay. The NRC staff provided verbal approval of RR 07-ON-004 on November 27, 2007.This letter is to inform you of the completion of the mitigative repairs for Oconee Unit 3 as listed oh Enclosure 4 of our January 31, 2007 letter. These actions were completed during 3EOC23 refueling outage and complete the actions related to all three Oconee units to satisfy the CAL. Enhanced leakage detection requirements committed to in our February 22, 2007 letter are no longer required on any Oconee unit due to the completion of mitigation of the subject welds.Also, the Unit 3 UT examinations of the Pressurizer and DHR drop line weld overlays were completed November 30, 2007. No flaws outside the IWB-3514 criteria were identified, and no.repairs were made to. the weld overlays, the original base materials or original 82/182 weld materials. | Thus this letter provides the required response for the CAL and its Enclosures satisfy the RR commitments for work performed during 3E0C23. | ||
The attached Enclosure provides a report summarizing the results of these examinations, per the commitments contained in RR 07-ON-001 and RR 07-ON-004, respectively. | If there are any questions, please contact Randy Todd at (864) 885-3418. | ||
Thus this letter provides the required response for the CAL and its Enclosures satisfy the RR commitments for work performed during 3E0C23.If there are any questions, please contact Randy Todd at (864)885-3418.Very truly yours, Vice President Oconee Nuclear Site Enclosure 2 of 5 U. S. Nuclear Regulatory Commission Page 3 December 13, 2007 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D.C. 20555 Dr. W. D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission | Very truly yours, B.H.*Hamilton Vice President Oconee Nuclear Site Enclosure 2 of 5 | ||
-Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. D. W. Rich Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Section Manager Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.Columbia, SC 29201 U. S. Nuclear Regulatory Commission Page 4 December 13, 2007 bxc w/att: R. L. Gill, Jr.T. J. Coleman D. W. Peltola P. A. Wells D. H. Llewellyn C. R. Frye J. M. Shupping W. R. Cauthen V. B. Dixon B. W. Carney, Jr.R. P. Todd M. A. Pyne E. B. Miller, Jr.L. C. Keith G. L. Brouette (ANII)J. J. Mc Ardle III D. B. Coyle J. E. Smith ISI Relief Request File'NRIA File/ELL EC050 Document Control 4 of 5 U. S. Nuclear Regulatory Commission December 13, 2007 Enclosure Weld Overlay Ultrasonic Examination 3EOC23 Summary Report Pressurizer Weld Overlays Reference Relief Request 07-ON-001 Safety/Relief Nozzle Weld: 3-PZR-WP91-3 Safety/Relief Nozzle Weld: 3-PZR-WP91-1 Safety/Relief Nozzle Weld: 3-PZR-WP91-2 Spray Nozzle Welds: 3-PZR-WP45; 3-PSP-1 Surge Nozzle Weld: 3-PZR-WP23 Hot Leg Surge Nozzle Welds: 3-PHB-17; 3-PSL-10 Decay Heat Removal Drop Line Weld Overlay Reference Relief Request 07-ON-004 Hot Leg Decay Heat Nozzle Welds: 3-PHA-17; 3-53A-18-11 1 of 5 Ultrasonic Examination Procedure SI-UT-126 Revision 3, | |||
This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center. No flaws outside the ASME Section XI Table IWB-3514-1, Table IWB-3514-2, or Table IWB-3514-3 acceptance standards were identified and no repairs were made to the weld overlays, the original base materials or original 82/182 weld materials. | U. S. Nuclear Regulatory Commission Page 3 December 13, 2007 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D.C. 20555 Dr. W. D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. D. W. Rich Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Section Manager Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St. | ||
Safety/Relief Nozzle Weld Overlay Examination Component Identification: | Columbia, SC 29201 | ||
Nozzle to Flange Weld: 3-PZR-WP91-3 Examination Date: November 22, 2007 Examination Time: 12:23 -13:25 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | |||
100% coverage of the Code-required volume was achieved during the examinations. | U. S. Nuclear Regulatory Commission Page 4 December 13, 2007 bxc w/att: | ||
R. L. Gill, Jr. | |||
T. J. Coleman D. W. Peltola P. A. Wells D. H. Llewellyn C. R. Frye J. M. Shupping W. R. Cauthen V. B. Dixon B. W. Carney, Jr. | |||
R. P. Todd M. A. Pyne E. B. Miller, Jr. | |||
L. C. Keith G. L. Brouette (ANII) | |||
J. J. Mc Ardle III D. B. Coyle J. E. Smith ISI Relief Request File' NRIA File/ELL EC050 Document Control 4 of 5 | |||
U. S. Nuclear Regulatory Commission December 13, 2007 Enclosure Weld Overlay Ultrasonic Examination 3EOC23 Summary Report Pressurizer Weld Overlays Reference Relief Request 07-ON-001 Safety/Relief Nozzle Weld: 3-PZR-WP91-3 Safety/Relief Nozzle Weld: 3-PZR-WP91-1 Safety/Relief Nozzle Weld: 3-PZR-WP91-2 Spray Nozzle Welds: 3-PZR-WP45; 3-PSP-1 Surge Nozzle Weld: 3-PZR-WP23 Hot Leg Surge Nozzle Welds: 3-PHB-17; 3-PSL-10 Decay Heat Removal Drop Line Weld Overlay Reference Relief Request 07-ON-004 Hot Leg Decay Heat Nozzle Welds: | |||
3-PHA-17; 3-53A-18-11 1 of 5 | |||
Ultrasonic Examination Procedure SI-UT-126 Revision 3, Procedurefor the PhasedArray UltrasonicExamination of Weld OverlaidSimilar and DissimilarMetal Welds, was used during the examinations. This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center. No flaws outside the ASME Section XI Table IWB-3514-1, Table IWB-3514-2, or Table IWB-3514-3 acceptance standards were identified and no repairs were made to the weld overlays, the original base materials or original 82/182 weld materials. | |||
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-3 Examination Date: November 22, 2007 Examination Time: 12:23 - 13:25 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | |||
Axial Examination Angles: 0' through 830 (in 10 Increments Circumferential Examination Angles: 0' through 64' (in 1' Increments) | Axial Examination Angles: 0' through 830 (in 10 Increments Circumferential Examination Angles: 0' through 64' (in 1' Increments) | ||
Examination Summary: One subsurface flaw indication in the weld overlay material (above the interface of the butt weld and the inconel buttering) was observed during the examinations. | Examination Summary: One subsurface flaw indication in the weld overlay material (above the interface of the butt weld and the inconel buttering) was observed during the examinations. The flaw was not crack-like and is believed to be welding-related. The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3 514-2 and was found to be acceptable. The following Table provides flaw evaluation details: | ||
The flaw was not crack-like and is believed to be welding-related. | Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t% | ||
The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3 514-2 and was found to be acceptable. | 1.0" 0.025" 0.025 5.56% 9.22% | ||
The following Table provides flaw evaluation details: Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%1.0" 0.025" 0.025 5.56% 9.22%The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
Safety/Relief Nozzle Weld Overlay Examination Component Identification: | coupling effectiveness during the examination. | ||
Nozzle to Flange Weld: 3-PZR-WP91-1 Examination Date: November 22, 2007 Examination Time: 02:34 -02:59 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-1 Examination Date: November 22, 2007 Examination Time: 02:34 - 02:59 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | ||
100% coverage of the Code-required volume was achieved during the examinations. | |||
Axial Examination Angles: 00 through 830 (in 10 Increments) | Axial Examination Angles: 00 through 830 (in 10 Increments) | ||
Circumferential Examination Angles: 00 through 640 (in 10 Increments) | Circumferential Examination Angles: 00 through 640 (in 10 Increments) | ||
Attachment to SIR-07-393, Rev. 1 2 of 5 Structural | Attachment to SIR-07-393, Rev. 1 2 of 5 Structural IntegrityAssociates, Inc. | ||
Examination Summary: No suspected flaw indications were observed during the examinations. | Examination Summary: No suspected flaw indications were observed during the examinations. | ||
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
Safety/Relief Nozzle Weld Overlay Examination Component Identification: | coupling effectiveness during the examination. | ||
Nozzle to Flange Weld: 3-PZR-WP91-2 Examination Date: November 22, 2007 Examination Time: 02:34 -03:04 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-2 Examination Date: November 22, 2007 Examination Time: 02:34 - 03:04 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | ||
100% coverage of the Code-required volume was achieved during the examinations. | |||
Axial Examination Angles: 0' through 830 (in 10 Increments) | Axial Examination Angles: 0' through 830 (in 10 Increments) | ||
Circumferential Examination Angles: 00 through 64' (in 10 Increments) | Circumferential Examination Angles: 00 through 64' (in 10 Increments) | ||
Examination Summary: No suspected flaw indications were observed during the examinations. | Examination Summary: No suspected flaw indications were observed during the examinations. | ||
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
Spray Nozzle Weld Overlay Examination Component Identification: | coupling effectiveness during the examination. | ||
Nozzle to Safe End Weld: 3-PZR-WP45 Safe End to Pipe Weld: 3-PSP-1 Examination Date: November 22, 2007 Examination Time: 03:05 -03:44 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | Spray Nozzle Weld Overlay Examination Component Identification: Nozzle to Safe End Weld: 3-PZR-WP45 Safe End to Pipe Weld: 3-PSP-1 Examination Date: November 22, 2007 Examination Time: 03:05 - 03:44 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | ||
100% coverage of the Code-required volume was achieved during the examinations. | |||
Axial Examination Angles: 00 through 820 (in 1V Increments) | Axial Examination Angles: 00 through 820 (in 1V Increments) | ||
Circumferential Examination Angles: 0' through 640 (in 10 Increments) | Circumferential Examination Angles: 0' through 640 (in 10 Increments) | ||
Examination Summary: No suspected flaw indications were observed during the examinations. | Examination Summary: No suspected flaw indications were observed during the examinations. | ||
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
Attachment to SIR-07-393, Rev. 1 3 of 5 Structural | coupling effectiveness during the examination. | ||
Surge Nozzle Weld Overlay Examination Component Identification: | Attachment to SIR-07-393, Rev. 1 3 of 5 Structural IntegrityAssociates, Inc. | ||
Nozzle to Safe End Weld: 3-PZR-WP23 Examination Date: November 23, 2007 Examination Time: 23:28 to 01:26 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | |||
100% coverage of the Code-required volume was achieved during the examinations. | Surge Nozzle Weld Overlay Examination Component Identification: Nozzle to Safe End Weld: 3-PZR-WP23 Examination Date: November 23, 2007 Examination Time: 23:28 to 01:26 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | ||
Axial Examination Angles: 00 through 830 (in 10 Increments) | Axial Examination Angles: 00 through 830 (in 10 Increments) - Circumferential Examination Angles: 00 through 68' (in 10 Increments) | ||
-Circumferential Examination Angles: 00 through 68' (in 10 Increments) | Examination Summary: One subsurface flaw indication in the ferritic nozzle material (about 0.50" below the ferritic steel surface and 0.35" from the nozzle buttering) was observed during the examinations. The flaw was not crack-like and is believed to be nozzle material-related. The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3514-1 and was found to be acceptable. The following Table provides flaw evaluation details: | ||
Examination Summary: One subsurface flaw indication in the ferritic nozzle material (about 0.50" below the ferritic steel surface and 0.35" from the nozzle buttering) was observed during the examinations. | Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t% | ||
The flaw was not crack-like and is believed to be nozzle material-related. | 1.0" 0.033" 0.03 2.88% 12.37% | ||
The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3514-1 and was found to be acceptable. | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
The following Table provides flaw evaluation details: Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%1.0" 0.033" 0.03 2.88% 12.37%The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | coupling effectiveness during the examination. | ||
Hot Leg Surge Nozzle Weld Overlay Examination Component Identification: | Hot Leg Surge Nozzle Weld Overlay Examination Component Identification: Nozzle to Butter/Safe End Weld: 3-PHB-17 3-PSL-10 Examination Date: November 30, 2007 Examination Time: 14:46 to 16:49 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | ||
Nozzle to Butter/Safe End Weld: 3-PHB-17 3-PSL-10 Examination Date: November 30, 2007 Examination Time: 14:46 to 16:49 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | |||
100% coverage of the Code-required volume was achieved during the examinations. | |||
Axial Examination Angles: 00 through 830 (in 10 Increments) | Axial Examination Angles: 00 through 830 (in 10 Increments) | ||
Circumferential Examination Angles: 00 through 650 (in 10 Increments) | Circumferential Examination Angles: 00 through 650 (in 10 Increments) | ||
Examination Summary: Two subsurface flaw indications in the weld overlay material (about 0.05" above the surface of the inconel buttering) were observed during the examinations. | Examination Summary: Two subsurface flaw indications in the weld overlay material (about 0.05" above the surface of the inconel buttering) were observed during the examinations. The flaw was not crack-like and is believed to be welding-related. The flaw indications were sized, Attachment to SIR-07-393, Rev. 1 4 of 5 Structural IntegrityAssociates, Inc. | ||
The flaw was not crack-like and is believed to be welding-related. | |||
The flaw indications were sized, Attachment to SIR-07-393, Rev. 1 4 of 5 Structural | characterized and compared to the acceptance standards of Table IWB-3514-2 and were found to be acceptable. The following Table provides flaw evaluation details: | ||
characterized and compared to the acceptance standards of Table IWB-3514-2 and were found to be acceptable. | Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t% | ||
The following Table provides flaw evaluation details: Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%2.90" 0.004" 0.00 0.55% 8.85%2.30" 0.006" 0.00 0.79% 8.85%The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | 2.90" 0.004" 0.00 0.55% 8.85% | ||
Hot Leg Decay Heat Nozzle Weld Overlay Examination Component Identification: | 2.30" 0.006" 0.00 0.79% 8.85% | ||
Nozzle to Butter/Safe End Weld: 3-PHA-17 3-53A-18-11 Examination Date: November 30, 2007 Examination Time: 20:30 to 21:30 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
100% coverage of the Code-required volume was achieved during the examinations. | coupling effectiveness during the examination. | ||
Hot Leg Decay Heat Nozzle Weld Overlay Examination Component Identification: Nozzle to Butter/Safe End Weld: 3-PHA-17 3-53A-18-11 Examination Date: November 30, 2007 Examination Time: 20:30 to 21:30 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations. | |||
Axial Examination Angles: 00 through 830 (in 10 Increments) | Axial Examination Angles: 00 through 830 (in 10 Increments) | ||
Circumferential Examination Angles: 00 through 700 (in 10 Increments) | Circumferential Examination Angles: 00 through 700 (in 10 Increments) | ||
Examination Summary: No suspected flaw indications were observed during the examinations. | Examination Summary: No suspected flaw indications were observed during the examinations. | ||
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /coupling effectiveness during the examination. | The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact / | ||
coupling effectiveness during the examination. | |||
Attachment to SIR-07-393, Rev. 1 5 of 5 U StructuralIntegrityAssociates, Inc.}} |
Latest revision as of 00:49, 23 November 2019
ML073532226 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 12/13/2007 |
From: | Brandi Hamilton Duke Energy Carolinas, Duke Energy Corp, Duke Power Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
Download: ML073532226 (9) | |
Text
BRUCE H HAMILTON Duke Vice President Energye Oconee Nuclear Station Duke Energy Corporation ONO] VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax bhhamilton@duke-energy.com December 13, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Station, Unit 2, and 3 Docket No. 50-270,-287 Completion of Confirmatory Action Letter Requirements and Summary Ultrasonic Examination Results of Completed Alloy 82/182 Weld Overlays Relief Requests 07-ON-001 and 07-ON-004 By letters dated January 31, 2007 (ADAMS Accession #
ML070390049) and February 22, 2007 (ADAMS Accession #
ML070600169), Duke Power Company LLC, d/b/a Duke Energy Carolinas, LLC (Duke) committed to a mitigation schedule regarding Alloy 82/182 butt welds on Pressurizer piping for Units 2 and 3 of the Oconee Nuclear Station (Oconee). The NRC Confirmatory Action Letter (CAL) of March 27, 2007 (ADAMS Accession # ML070790113) regarding Alloy 82/182 butt welds requires a report within 60 days of unit restart of any mitigative actions taken on the subject welds.
In order to support these mitigative actions, on March 12, 2007 Duke submitted Relief Requests (RR) 07-ON-001 (ADAMS Accession #
ML070790293) to support application of full structural weld overlays on various pressurizer nozzle to flange, nozzle-to-safe end, and surge line welds. NRC verbally approved this request on May 17, 2007 and provided written approval by letter dated August 6, 2007 (ADAMS Accession #. ML071280781). In this request Duke committed to provide a report summarizing the results of the UT examinations of the weld overlays within 14 days of completion of the UT examinations.
By letter dated May 29,. 2007, (ADAMS Accession # ML071560504)
Duke notified the NRC of the completion of the actions '
applicable to Unit 2 within the scope of the CAL, and included www. duke-energy. com 0 W
U. S. Nuclear Regulatory Commission Page 2 December 13,. 2007 the report relative to UT examinations for associated weld overlays as committed in RR 07-ON-001.
In addition, on September 13, 2007, Duke submitted RR 07-ON-004 (ADAMS Accession # ML072620149), applicable to all three Oconee units, to seek similar relief related to full structural weld overlays on the Decay Heat Removal (DHR) Drop line to Hot Leg Nozzle welds. These welds are not subject to the CAL, but the RR also included a commitment to provide the results of the UT examinations within 14 days of completion of examinations on the DHR line overlay. The NRC staff provided verbal approval of RR 07-ON-004 on November 27, 2007.
This letter is to inform you of the completion of the mitigative repairs for Oconee Unit 3 as listed oh Enclosure 4 of our January 31, 2007 letter. These actions were completed during 3EOC23 refueling outage and complete the actions related to all three Oconee units to satisfy the CAL. Enhanced leakage detection requirements committed to in our February 22, 2007 letter are no longer required on any Oconee unit due to the completion of mitigation of the subject welds.
Also, the Unit 3 UT examinations of the Pressurizer and DHR drop line weld overlays were completed November 30, 2007. No flaws outside the IWB-3514 criteria were identified, and no.repairs were made to. the weld overlays, the original base materials or original 82/182 weld materials. The attached Enclosure provides a report summarizing the results of these examinations, per the commitments contained in RR 07-ON-001 and RR 07-ON-004, respectively.
Thus this letter provides the required response for the CAL and its Enclosures satisfy the RR commitments for work performed during 3E0C23.
If there are any questions, please contact Randy Todd at (864) 885-3418.
Very truly yours, B.H.*Hamilton Vice President Oconee Nuclear Site Enclosure 2 of 5
U. S. Nuclear Regulatory Commission Page 3 December 13, 2007 cc: Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D.C. 20555 Dr. W. D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. D. W. Rich Senior Resident Inspector Oconee Nuclear Station S. E. Jenkins, Section Manager Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.
Columbia, SC 29201
U. S. Nuclear Regulatory Commission Page 4 December 13, 2007 bxc w/att:
R. L. Gill, Jr.
T. J. Coleman D. W. Peltola P. A. Wells D. H. Llewellyn C. R. Frye J. M. Shupping W. R. Cauthen V. B. Dixon B. W. Carney, Jr.
R. P. Todd M. A. Pyne E. B. Miller, Jr.
L. C. Keith G. L. Brouette (ANII)
J. J. Mc Ardle III D. B. Coyle J. E. Smith ISI Relief Request File' NRIA File/ELL EC050 Document Control 4 of 5
U. S. Nuclear Regulatory Commission December 13, 2007 Enclosure Weld Overlay Ultrasonic Examination 3EOC23 Summary Report Pressurizer Weld Overlays Reference Relief Request 07-ON-001 Safety/Relief Nozzle Weld: 3-PZR-WP91-3 Safety/Relief Nozzle Weld: 3-PZR-WP91-1 Safety/Relief Nozzle Weld: 3-PZR-WP91-2 Spray Nozzle Welds: 3-PZR-WP45; 3-PSP-1 Surge Nozzle Weld: 3-PZR-WP23 Hot Leg Surge Nozzle Welds: 3-PHB-17; 3-PSL-10 Decay Heat Removal Drop Line Weld Overlay Reference Relief Request 07-ON-004 Hot Leg Decay Heat Nozzle Welds:
3-PHA-17; 3-53A-18-11 1 of 5
Ultrasonic Examination Procedure SI-UT-126 Revision 3, Procedurefor the PhasedArray UltrasonicExamination of Weld OverlaidSimilar and DissimilarMetal Welds, was used during the examinations. This procedure, and the examiners who applied the procedure, are qualified through the PDI Program at the EPRI NDE Center. No flaws outside the ASME Section XI Table IWB-3514-1, Table IWB-3514-2, or Table IWB-3514-3 acceptance standards were identified and no repairs were made to the weld overlays, the original base materials or original 82/182 weld materials.
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-3 Examination Date: November 22, 2007 Examination Time: 12:23 - 13:25 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 0' through 830 (in 10 Increments Circumferential Examination Angles: 0' through 64' (in 1' Increments)
Examination Summary: One subsurface flaw indication in the weld overlay material (above the interface of the butt weld and the inconel buttering) was observed during the examinations. The flaw was not crack-like and is believed to be welding-related. The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3 514-2 and was found to be acceptable. The following Table provides flaw evaluation details:
Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%
1.0" 0.025" 0.025 5.56% 9.22%
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-1 Examination Date: November 22, 2007 Examination Time: 02:34 - 02:59 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 640 (in 10 Increments)
Attachment to SIR-07-393, Rev. 1 2 of 5 Structural IntegrityAssociates, Inc.
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Safety/Relief Nozzle Weld Overlay Examination Component Identification: Nozzle to Flange Weld: 3-PZR-WP91-2 Examination Date: November 22, 2007 Examination Time: 02:34 - 03:04 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 0' through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 64' (in 10 Increments)
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Spray Nozzle Weld Overlay Examination Component Identification: Nozzle to Safe End Weld: 3-PZR-WP45 Safe End to Pipe Weld: 3-PSP-1 Examination Date: November 22, 2007 Examination Time: 03:05 - 03:44 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 820 (in 1V Increments)
Circumferential Examination Angles: 0' through 640 (in 10 Increments)
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-07-393, Rev. 1 3 of 5 Structural IntegrityAssociates, Inc.
Surge Nozzle Weld Overlay Examination Component Identification: Nozzle to Safe End Weld: 3-PZR-WP23 Examination Date: November 23, 2007 Examination Time: 23:28 to 01:26 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments) - Circumferential Examination Angles: 00 through 68' (in 10 Increments)
Examination Summary: One subsurface flaw indication in the ferritic nozzle material (about 0.50" below the ferritic steel surface and 0.35" from the nozzle buttering) was observed during the examinations. The flaw was not crack-like and is believed to be nozzle material-related. The flaw indication was sized, characterized and compared to the acceptance standards of Table IWB-3514-1 and was found to be acceptable. The following Table provides flaw evaluation details:
Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%
1.0" 0.033" 0.03 2.88% 12.37%
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Hot Leg Surge Nozzle Weld Overlay Examination Component Identification: Nozzle to Butter/Safe End Weld: 3-PHB-17 3-PSL-10 Examination Date: November 30, 2007 Examination Time: 14:46 to 16:49 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 650 (in 10 Increments)
Examination Summary: Two subsurface flaw indications in the weld overlay material (about 0.05" above the surface of the inconel buttering) were observed during the examinations. The flaw was not crack-like and is believed to be welding-related. The flaw indications were sized, Attachment to SIR-07-393, Rev. 1 4 of 5 Structural IntegrityAssociates, Inc.
characterized and compared to the acceptance standards of Table IWB-3514-2 and were found to be acceptable. The following Table provides flaw evaluation details:
Flaw Length Flaw Through-Wall Flaw Aspect Ratio Flaw a/t% Code Allowable a/t%
2.90" 0.004" 0.00 0.55% 8.85%
2.30" 0.006" 0.00 0.79% 8.85%
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Hot Leg Decay Heat Nozzle Weld Overlay Examination Component Identification: Nozzle to Butter/Safe End Weld: 3-PHA-17 3-53A-18-11 Examination Date: November 30, 2007 Examination Time: 20:30 to 21:30 Examination Regions: Weld Overlay Material, Outer 25% Dissimilar Metal Weld & Adjacent Base Material and Outer 25% Safe End-to-Pipe Weld & Adjacent Base Material Examination Coverage: 100% coverage of the Code-required volume was achieved during the examinations.
Axial Examination Angles: 00 through 830 (in 10 Increments)
Circumferential Examination Angles: 00 through 700 (in 10 Increments)
Examination Summary: No suspected flaw indications were observed during the examinations.
The examination gain was adjusted to maintain the procedure-specified baseline noise level from 5% to 20% of full screen height. The lower range of examination angles detected responses from the inside surface of the component which were useful for monitoring search unit contact /
coupling effectiveness during the examination.
Attachment to SIR-07-393, Rev. 1 5 of 5 U StructuralIntegrityAssociates, Inc.