ML13310A385

Request for Additional Information Related to Notification of Impracticality for the Third Year Interval

ML13310A385
Person / Time
Site:	Davis Besse
Issue date:	11/15/2013
From:	Ellen Brown Plant Licensing Branch III
To:	Lieb R FirstEnergy Nuclear Operating Co
Eva Brown, NRR/DORL 415-2315
References
TAC MF0750
Download: ML13310A385 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 15, 2013 Mr. Raymond A. Lieb Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 North State, Route 2 Oak Harbor, OH 43449-9760

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1- REQUEST FOR ADDITIONAL INFORMATION RELATED TO NOTIFICATION OF IMPRACTICALITY FOR THE THIRD YEAR INTERVAL (TAC NO. MF0750)

(L-13-076)

Dear Mr. Lieb:

By letter dated February 27, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13059A321), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a request for relief (RR-A36) pursuant to Section 50.55a(g)(5)(iii) to Title 10 to the Code of Federal Regulations ( 10 CFR) for the Davis-Besse Nuclear Power Station, Unit No. 1. Specifically, the licensee requests relief from the vessel weld and nozzle inner radii examination coverage requirements specified in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Sect1on XI, 1995 Edition through 1996 Addenda and ASME Code Case N-648-1 with applicable conditions defined in Regulatory Guide 1.147.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Mr. Phil Lashley of your staff on October 23, 2013, it was agreed that you would provide a response by November 15, 2013.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for NRC staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.

R. Lieb If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2315.

Sincerely, IRA I Eva A Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosure:

Request for Additional Information cc wlencl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION RR-A36 ALTERNATIVE WELD EXAMINATION COVERAGE DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO.1 FIRSTENERGY NUCLEAR OPERATING COMPANY DOCKET NO. 50-346

1. The recordable indications found by ultrasonic testing in welds RC-RPV-WR-34 and RC-RPV-WR-35 are described as embedded and indicative of slag. Describe the process used to confirm that the defects are embedded and that they are caused by slag and not caused by lack of fusion defects or some other fabrication flaw types.

2. Address whether the indications in welds RC-RPV-WR-34 and RC-RPV-WR-35 are visible on the radiographs of the welds made during construction.

3. Describe the visual testing camera system and lighting used to conduct the enhanced visual resolution demonstrations (EVT-1) tests on the RC-RPV-WR-54/55-W-IR and RC-RPV-WR-54/55-Y-IR nozzle inner radii.

4. Describe the cleaning process used in the EVT-1 examinations for RC-RPV-WR-54/55-W-IR and RC-RPV-WR-54/55-Y-IR. If the nozzles were cleaned, discuss whether the nozzle inner radii were examined prior to cleaning, after cleaning, or both.

Enclosure

ML13310A385 OFFICE LPL3-21PM LPL3-21LA EPNBIBC LPL3-21BC NAME EBrown SRohrer Tlupold by e- TTate mail DATE 1117113 1116113 912512013 11115113