ML14128A319

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Response to NRC Request for Additional Information Regarding Relief Request RR-003, Implementation of a Risk-Informed/Safety-Based Lnservice Inspection Program Based on ASME Boiler and Pressure Code Case N-716 for ASME Class 1 and 2 Piping
ML14128A319
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/08/2014
From: Fili K
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L -MT-14-048, TAC MF3050
Download: ML14128A319 (3)


Text

Monticello Nuclear Generating Plant Xcel Energy@ 2807 W County Road 75 Monticello, MN 55362 May 8, 2014 L-MT-14-048 10 CFR 50.55a(g)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22

Subject:

Response to NRC Request for Additional Information Regarding Relief Request RR-003, Implementation of a Risk-Informed/Safety-Based lnservice Inspection Program Based on ASME Boiler and Pressure Code Case N-716 for ASME Class 1 and 2 Piping Welds (TAG No. MF3050)

References:

1) Letter from Northern States Power Company, a Minnesota corporation (NSPM) d/b/a Xcel Energy to Document Control Desk, "Request to Utilize an Alternative to the Requirements of 10 CFR 50.55a(g) for Implementation of a Risk-Informed, Safety-Based lnservice Inspection Program Based on ASME Code Case N-716", dated October 31, 2013 (ADAMS Accession Number ML13308A390).
2) E-mail from Terry Beltz to Randy Rippy, "Monticello Nuclear Generating Plant-Draft Requests for Additional Information re: Request RR-003 (TAG No. MF3050)", dated March 20, 2014 (ADAMS Accession Number ML14094A397).

By letter dated October 31, 2013, Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy requested authorization to implement a risk-informed, safety-based inservice inspection (lSI) program based on American Society of Mechanical Engineers (ASME) Code Case N-716, "Alternative Piping Classification and Examination Requirements,Section XI, Division 1,"for the Monticello Nuclear Generating Plant (Reference 1).

Subsequently, by e-mail dated March 20, 2014 (Reference 2), the NRC provided a draft Request for Additional Information (RAI) for additional information required to complete its review. In an e-mail dated April 11, 2014, NSPM accepted the draft RAI.

The formal response is provided in the enclosure.

If you have any questions or require additional information, please contact Mr. Randy Rippy at 612-330-6911.

Document Control Desk Page 2 Summary of Commitments This letter makes no new commitments and no revisions to existing commitments.

Karen D. Fili Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce

ENCLOSURE RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING RR-003 RAI EPNB-1 Section 3.3.4 of Enclosure 1, states that relief requests for cases where less than 90 percent coverage is obtained will be submitted.

Please describe the efforts in weld selection such that greater than 90 percent coverage is attainable in the RIS_B inservice inspection program.

Response to RAI EPNB-1 Weld joint configurations that are favorable to attaining the required coverage were selected for the proposed RIS_B program to the extent practicable, e.g., pipe-to-pipe welds, pipe-to-elbow welds, pipe-to-safe end welds, etc. Selections were made primarily by the lnservice Inspection (lSI) Program Owner and Site Nondestructive Examination Level Ill based on their knowledge of weld locations and configurations, examination application, relative dose conditions, and scaffold and insulation needs.

Piping welds that required relief requests in past lSI Intervals, because greater than 90 percent coverage could not be attained at that time, were not selected for examination in the proposed RIS_B Program.

Although final coverage will not be known for future exams selected for the RIS_B Program until they are actually completed, the twenty-one weld exams completed in the 2013 refueling outage all attained the required coverage.

RAI EPNB-2 Section 4 of Enclosure 1, states that welds were selected for examination in the 1st period that met the requirements of both ASME Section XI and Code Case N-716, and that credit will be taken for these welds.

a. What were the results of the examinations?
b. Was greater than 90 percent coverage attained?

Response to RAI EPNB-2

a. Twenty-one weld exams were completed during the 2013 refueling outage, and no flaw indications were reported.
b. The twenty-one weld exams were completed with no coverage limitations, i.e. 'greater than 90 percent' was attained.

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