ML14360A014
| ML14360A014 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/19/2014 |
| From: | Mark D. Sartain Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 14-286A, TAC MF3402 | |
| Download: ML14360A014 (4) | |
Text
010Domninioiil Dominion Nuclear Connecticut, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com December 19, 2014 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
NSSL/WDC Docket No.
License No.
14-286A RO 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNIT 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING AGING MANAGEMENT PROGRAM DESCRIPTION: INSERVICE INSPECTION - REACTOR VESSEL INTERNALS, LICENSE RENEWAL COMMITMENT #13 (MF3402)
By letter dated July 31, 2013, Dominion Nuclear Connecticut, Inc. (DNC) submitted the "Aging Management Program
Description:
Inservice Inspection - Reactor Vessel Internals" to address License Renewal Commitment #13 for Millstone Power Station Unit 2 (MPS2).
The submittal contains an updated Reactor Vessel Internals (RVI)
Aging Management Program and RVI Inspection Plan in accordance with topical report, "Material Reliability Program: Pressurized Water Reactor Inspection and Evaluation Guidelines" (MRP-227-A).
In an e-mail dated May 14, 2014, the Nuclear Regulatory Commission transmitted a request for additional information (RAI) related to the submittal.
DNC provided a response to the RAI in a letter dated July 21, 2014 except for Question 1.1, which required input from Westinghouse. Attachment 1 to this letter contains DNC's response to RAI Question 1.1.
If you have any questions or require additional information, please contact Wanda Craft at (804) 273-4687.
Sincerely, Mark D. Sartain Vice President - Nuclear Engineering NOT*RY PUDLIC Commotnwtelth of Virginia Reg. #140542 mly-Comnsi5Ion Expires May 31, 2018 COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO
))
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mark D. Sartain, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this /.4,9day of.&e,,,2014.
My Commission Expires:
5.--2111 4ol
/ D 60ý Notary Public f
Serial No. 14-286A Docket No. 50-336 Page 2 of 2 Commitments made in this letter: None
Attachment:
1.
Response to Request for Additional Information Regarding License Renewal Commitment #13 - Question 1.1 cc:
U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd Suite 100 King of Prussia, PA 19406-2713 Mohan C. Thadani Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 B1 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station
6 Serial No 14-286A Docket No. 50-336 Response to Request for Additional Information Regarding License Renewal Commitment #13 - Question 1.1 Dominion Nuclear Connecticut, Inc.
Millstone Power Station Unit 2
A I.
Serial No 14-286A Docket No. 50-336, Page 1 of 1 Response to Request for Additional Information Regarding License Renewal Commitment #13 - Question 1.1 By letter dated July 31, 2013, Dominion Nuclear Connecticut, Inc. (DNC) submitted the "Aging Management Program
Description:
Inservice Inspection - Reactor Vessel Internals" to address License Renewal Commitment #13 for Millstone Power Station Unit 2 (MPS2).
The submittal contains an updated Reactor Vessel Internals (RVI) Aging Management Program (AMP) and RVI Inspection Plan in accordance with topical report "Material Reliability Program: Pressurized Water Reactor Inspection and Evaluation Guidelines" (MRP-227-A).
In an e-mail dated May 14, 2014, the Nuclear Regulatory Commission transmitted a request for additional information (RAI) related to the submittal. DNC provided a response to the RAI in a letter dated July 21, 2014 except for Question 1.1, which required input from Westinghouse. The response to RAI Question 1.1 is as follows:
RAI 1
- 1. Do the MPS2 RVI have non-weld or bolting austenitic stainless steel components with 20 percent cold work or greater, and if so do the affected components have operating stresses greater than 30 kilopounds per square inch?
DNC Response
- 1. Westinghouse performed a plant-specific review of documentation associated with austenitic stainless steel cold work in accordance with the current industry guidance issued in EPRI letter MRP 2013-025, "MRP-227-A Applicability Guidelines for Combustion Engineering and Westinghouse Pressurized Water Reactor Designs,"
dated October 14, 2013 (ADAMS Accession No. ML13322A454).
The review considered both original fabrication of reactor vessel internals and modifications completed through November, 2014.
Following the process described in MRP 2013-025, the materials of the reactor vessel internals components were binned into five categories, including "cold worked austenitic stainless steel (without subsequent solution annealing)".
The review determined that the RVI at MPS2 have no non-weld, non-bolting austenitic stainless steel components with 20 percent or greater cold work.