ML13025A084
| ML13025A084 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/14/2013 |
| From: | Lane N Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 12-766, CMP-008, CMP-010 | |
| Download: ML13025A084 (4) | |
Text
VIRGINi.A ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 14, 2013 United States Nuclear Regulatory Commission Serial No.12-766 Attention: Document Control Desk SPS-LIC/CGL RO Washington, D.C. 20555 Docket Nos.
50-280/281 License No.
DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
SURRY POWER STATION UNITS I AND 2 ASME SECTION Xl INSERVICE INSPECTION (ISI) PROGRAM SUPPLEMENTAL INFORMATION RELATED TO ALTERNATIVE EXAMINATION REQUIREMENTS FOR REACTOR VESSEL NOZZLE TO SAFE END BUTT WELDS RELIEF REQUESTS CMP-008 AND CMP-010 By a letter dated November 9, 2012 (Serial No.12-687), Virginia Electric and Power Company (Dominion) submitted Relief Requests CMP-008 and CMP-010 for Surry Units 1 and 2, respectively.
These relief requests proposed use of an alternate depth-sizing qualification for volumetric examinations of the reactor vessel (RV) nozzle to safe end dissimilar metal butt end welds from the inside surface and use of a root mean square error flaw sizing criterion that is greater than that allowed by the ASME Code.
On December 18, 2012, the NRC provided acceptance review feedback electronically regarding Relief Requests CMP-008 and CMP-010 and offered Dominion the opportunity to supplement the relief requests. A December 20, 2012 conference call was held between Dominion and the NRC Technical Staff to discuss the supplemental information needed for the NRC to complete its review.
Information supplementing Relief Requests CMP-008 and CMP-010 is provided in the attachment.
As indicated in our November 9, 2012 letter, Dominion requests approval of Relief Requests CMP-008 and CMP-010 by September 30, 2013 to support RV nozzle to safe end butt welds examinations scheduled for the Surry Units 1 and 2 refueling outages in Fall 2013 and Spring 2014, respectively.
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Serial No.12-766 Docket Nos. 50-280/281 Page 2 of 2 If you have further questions or require additional information, please contact Mrs. Candee G. Lovett at (757) 365-2178.
Sincerely, N. L. Lane Site Vice President - Surry Power Station
Attachment:
Supplemental Information Related to Alternative Examination Requirements for Reactor Vessel Nozzle to Safe End Butt Welds - Relief Requests CMP-008 and CMP-010 Commitments made by this letter: Items 1, 2, and 3 detailed in the attachment.
cc:
U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 State Health Commissioner, Virginia Department of Health James Madison Building - 7th floor 109 Governor Street, Suite 730 Richmond, Virginia 23219 NRC Senior Resident Inspector Surry Power Station Ms. K. R. Cotton, NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852 Dr. V. Sreenivas, NRC Project Manager - North Anna U. S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 G9A 11555 Rockville Pike Rockville, Maryland 20852 Mr. R. A. Smith Authorized Nuclear Inspector Surry Power Station
Serial No.12-766 Docket Nos. 50-280/50-281 Attachment Supplemental Information Related to Alternative Examination Requirements for Reactor Vessel Nozzle to Safe End Butt Welds -
Relief Requests CMP-008 and CMP-010 Virginia Electric and Power Company (Dominion)
Surry Power Station Units I and 2
Serial No.12-766 Docket Nos. 50-280/50-281 Attachment Page 1 of 1 Supplemental Information Related to Alternative Examination Requirements for Reactor Vessel Nozzle to Safe End Butt Welds - Relief Requests CMP-008 and CMP-01 0 By a letter dated November 9, 2012 (Serial No.12-687), Virginia Electric and Power Company (Dominion) submitted Relief Requests CMP-008 and CMP-010 for Surry Units 1 and 2,
respectively.
These relief requests proposed use of an alternate depth-sizing qualification for volumetric examinations of the reactor vessel (RV) nozzle to safe end dissimilar metal butt end welds from the inside surface and use of a root mean square error flaw sizing criterion that is greater than that allowed by the ASME Code.
On December 18, 2012, the NRC provided acceptance review feedback electronically regarding Relief Requests CMP-008 and CMP-010 and offered Dominion the opportunity to supplement the relief requests. A December 20, 2012 conference call was held between Dominion and the NRC Technical Staff to discuss the supplemental information needed for the NRC to complete its review.
Consistent with the September 24, 2012 NRC Safety Evaluation approving the McGuire Unit 2 Relief Request 12-MN-003 and the August 22, 2012 Duke Energy letter transmitting the response to an NRC request for additional information regarding the McGuire Unit 2 Relief Request 12-MN-003, the following information supplementing Surry Relief Requests CMP-008 and CMP-010 is provided.
- 1. The welds under consideration will be examined using an ultrasonic technique (UT) which is qualified for flaw detection and length sizing.
- 2. Indications connected to the inside surface with measured depths of less than 50 percent of the wall thickness will be dispositioned in accordance with an indication the depth of which is the measured depth plus the root mean square error minus 0.125 inches.
- 3. For indications connected to the inside surface with measured depths of 50 percent of the wall thickness or greater, the indication will be repaired or a flaw evaluation of the observed indication will be performed.
In addition to the information normally contained in flaw evaluations, the evaluation will include:
- a. Information concerning the mechanism which caused the crack,
- b. Information concerning the surface roughness/profile in the area of the pipe/weld required to perform the inspection (i.e., for the area in which the examination is required to be performed, the inner surface profile will be provided), and
- c. Information concerning areas in which the UT probe may "lift off' from the surface of the pipe/weld.
This flaw evaluation shall be submitted to the NRC for review and approval prior to reactor startup.