ML13233A284

Request for Additional Information Regarding Relief Request RR-04-15

ML13233A284
Person / Time
Site:	Millstone
Issue date:	08/22/2013
From:	James Kim Plant Licensing Branch 1
To:	Heacock D Dominion Nuclear Connecticut
Kim J
References
TAC MF1405
Download: ML13233A284 (3)

Text

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Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-04-15 (TAC NO. MF1405)

Dear Mr. Heacock:

By letter dated April 9, 2013, Dominion Nuclear Connecticut, Inc. (the licensee) submitted alternative relief request RR-04-15 covering eight cold leg dissimilar metal welds from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-770-1 "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities."

The request for relief applies to the fourth 10-year inservice inspection interval at Millstone Power Station Unit 2.

The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has determined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided within 45 days of the date of this letter.

If you have any questions regarding this matter, please contact me at 301-415-4125.

Sincerely, James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosure:

As stated cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REGARDING MILLSTONE POWER STATION, UNIT 2 RELIEF REQUEST RR-04-15 DOCKET NO. 50-336 In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(a)(3)(ii), the licensee has submitted the request for alternative for limited examinations of dissimilar metal welds. The licensee stated that achieving 100 percent of the American Society of Mechanical Engineers (ASME) Code Case N-770-1 required volumes, for the welds would result in a hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The staff has reviewed and evaluated the information provided by the licensee and has determined that the following information is needed in order to complete its review of the request.

1. The relief request states that phased-array probes will be used and that the ASME Code coverage for the axial scans is based on using both 45 and 60 degree inspection angles.

Phased-array probes can produce a large number or a small number of angles, depending on the delay laws used. What angles are produced by the phased-array probes during the upcoming examination?

2. Appendix A of the 2013 report by the Electric Power Research Institute (EPRI)

"Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds, Revision 1" contains a flow chart detailing when encoded examinations should be used for dissimilar metal welds. This guidance on the use of encoded scanning is an NEI-03-08 "Needed" requirement for the first inspection after January 2014. Based on the inspection plans and the EPRI guidance, which welds will be inspected using encoded and non-encoded techniques?

Enclosure

August 22,2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST RR-04-15 (TAC NO. MF1405)

Dear Mr. Heacock:

By letter dated April 9, 2013, Dominion Nuclear Connecticut, Inc. (the licensee) submitted alternative relief request RR-04-15 covering eight cold leg dissimilar metal welds from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Case N-770-1 "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities."

The request for relief applies to the fourth 1O-year inservice inspection interval at Millstone Power Station Unit 2.

The U.S. Nuclear Regulatory Commission staff has reviewed the information provided by the licensee and has determined that the enclosed request for additional information (RAI) is needed in order to complete the review. A response to this RAI is requested to be provided within 45 days of the date of this letter.

If you have any questions regarding this matter, please contact me at 301-415-4125.

Sincerely, Ira!

James Kim, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-336

Enclosure:

As stated cc w/encl: Distribution via Listserv Distribution:

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NAME JKim KGoldstein TLupold* RBeall (DPickett for)

DATE 08/22113 08/22/13 811512013 08122/13