ML13182A080

Surry, Units 1 and 2 - Response to Request for Additional Information Request for Approval to Use a Subsequent ASME Section Xi Code and Addenda for Examination Categories B-L-1 and C-B in the Fourth Inservice Inspection Interval

ML13182A080
Person / Time
Site:	Surry
Issue date:	06/24/2013
From:	Lane N L Virginia Electric & Power Co (VEPCO)
To:	Document Control Desk, Office of New Reactors
References
13-362
Download: ML13182A080 (4)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 24, 2013 United States Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555 Serial No.SPS-LIC/CGL Docket Nos.License No.13-362 RO 50-280/281 DPR-32/37 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

SURRY POWER STATION UNITS 1 AND 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR APPROVAL TO USE A SUBSEQUENT ASME SECTION XI CODE AND ADDENDA FOR EXAMINATION CATEGORIES B-L-1 AND C-B IN THE FOURTH INSERVICE INSPECTION (ISI) INTERVAL By a letter dated May 1, 2013 (Serial No.13-264), Virginia Electric and Power Company (Dominion) submitted a request for approval to use a subsequent ASME Code edition and addenda for the ASME Section Xl, Examination Categories B-L-1 and C-B, in the fourth ISI interval.On June 5, 2013, the NRC requested additional information in order to complete its technical review of our request. The response to the NRC's request for additional information is provided in the attachment.

As indicated in our May 1, 2013 letter, Dominion requests approval of the use of the subsequent Code edition and addenda by September 30, 2013 to support use of the later Code edition and addenda during the Surry Units 1 and 2 refueling outages in Fall 2013 and Spring 2014, respectively.

If you have further questions or require additional Mrs. Candee G. Lovett at (757) 365-2178.information, please contact Since N. L. Lane Site Vice President

-Surry Power Station

Attachment:

Response to Request for Additional Information Regarding Request for Approval to Use a Subsequent ASME Code Edition and Addenda for Examination Categories B-L-1 and C-B in the Fourth ISI Interval Commitments made by this letter: Noneý,DO Serial No.13-362 Docket Nos. 50-280/281 Page 2 of 2 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.13-362 Docket Nos. 50-280/50-281 Attachment Response to Request for Additional Information Regarding Request for Approval to Use a Subsequent ASME Code Edition and Addenda for Examination Categories B-L-1 and C-B in the Fourth ISI Interval Virginia Electric and Power Company (Dominion)

Surry Power Station Units 1 and 2 Serial No.13-362 Docket Nos. 50-280/281 Attachment 1 Page 1 of 1 Response to Request for Additional Information Regarding Request for Approval to Use a Subsequent ASME Code Edition and Addenda for Examination Categories B-L-1 and C-B in the Fourth ISI Interval Request for Additional Information Question 1: Section 1 of the request specifies one of the affected ASME Code Section Xl components as Residual Heat Removal (RHR) Heat Exchanger Reinforcement Plate Welds to Vessel (C-B). The NRC staff notes that many components are listed under examination category C-B in Table IWC-2500-1 of the 2007 edition of the ASME Code,Section XI. The component items range from C2.10 to C2.33. For example, the reinforcement plate welds to vessel is classified as Item C 2.31. Based on Section 1 of the request, it appears that the only component that will be affected under Examination Category C-B is Item C2.31, reinforcing plate welds to nozzle and vessel.Section 3 of the request states: "Flaw Acceptance Standards for Class 2 austenitic Pressure Retaining Welds of Nozzles in Vessels (ASME Category C-B) exists in IWC-351 1, of the 2007 Edition, 2008 Addenda, "Standards for Examination Category C-B, Pressure Retaining Welds of Nozzles," by referring to Table IWB-3514.2.

Acceptance criteria do not exist for the RHR Heat Exchangers using the current ASME Code Edition and Addenda of record for Surry Units 1 and 2." As stated above, IWC-3511 is applicable to Examination Category C-B pressure retaining welds of nozzles to vessels. Therefore, it appears that all components under Examination Category C-B in Table IWC-2500-1 are affected by the request. This seems to be contradicting Section 1 of the request, which implies only Item C2.31 is the affected component.

Please identify the exact component(s) (specify the component Item number) under Examination Category C-B in Table IWC-2500-1 that will use the 2007 edition through the 2008 addenda of the Code and that will be affected by the request.Response to Question 1: The exact component(s) under Examination Category C-B in Table IWC-2500-1 that will use the 2007 edition through the 2008 addenda of the Code and that will be affected by the request is Item No. C2.31, Reinforcing Plate Welds to Nozzle and Vessel.Request for Additional Information Question 2: Please identify the material specification of the reactor coolant pump casing welds (e.g., stainless steel ER 308L).Response to Question 2: The 1969 Westinghouse material specification for the reactor coolant pump casing welds is SA-298 or SA-371.