ML16169A002

Request for Information Prairie Island Relief Requests 1-RR-4-11 and 2-RR-11

ML16169A002
Person / Time
Site:	Prairie Island
Issue date:	06/16/2016
From:	Robert Kuntz Plant Licensing Branch III
To:	Carlson G Xcel Energy
References
MF7210, MF7211
Download: ML16169A002 (3)

Text

NRR-PMDAPEm Resource From: Kuntz, Robert Sent: Thursday, June 16, 2016 2:23 PM To: Carlson, Glenn A.

Subject:

Request for Information RE: Prairie Island relief requests 1-RR-4-11 and 2-RR-11

Glenn, Below is a final request for additional information from the NRC staff. During the clarification call held today it a response date of July 13, 2016 was agreed upon. If additional consideration is needed contact me.

Robert Kuntz Senior Project Manager (Monticello and Prairie Island)

NRC/NRR/DORL/LPL3-1 (301)415-3733 REQUEST FOR ADDITIONAL INFORMATION ON THE FOURTH TEN YEAR 10-YEAR INSERVICE INSPECTION INTERVAL REQUESTS FOR RELIEF PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 (CAC NOS.: MF7210, AND MF7211) 1.0 SCOPE By letter dated December 21, 2015, (Agencywide Documents Access and Management System (ADAMS), Accession No. ML15355A253), Xcel Energy (the licensee), submitted Requests for Relief Nos. 1-RR-4-11, and 2-RR-4-11 (Relief Requests) from certain requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code (ASME Code), under the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(g)(5)(iii), for the fourth 10-year inservice inspection (ISI) Program for Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2. The licensees request for relief applies to the fourth ISI interval, in which the licensee adopted the 1998 Edition through the 2000 Addenda of ASME Code Section XI as the code of record.

2.0 REQUEST FOR ADDITIONAL INFORMATION 2.1 Table 1 of the Relief Requests specifies the code used for the volumetric examination procedure for the Category C-A welds, but not for the surface examination procedure for the Category C-C welds. Provide the applicable code for the surface examination of the Category C-C attachment welds (e.g., ASME Code Section V, Article 6.). Also provide the applicable code criteria used to determine extent of surface to be examined (e.g., ASME Code Figure IWC-2500-5.)

2.2 Section 6 of the Relief Requests states that only one support of PINGP, Unit 1 was surface examined and that the coverage was limited to 71%, but both supports of PINGP, Unit 2 were surface examined. Describe why one of the supports of PINGP, Unit 1 was not surface examined, or clarify your statement. Also, explain why the maximum obtainable coverage of 75% (as stated in Table 2) was not achieved for this surface examination.

2.3 Section 6 of the Relief Requests states that Weld 2 of the PINGP, Unit 1 residual heat removal heat exchanger 12 was ultrasonically examined and found to be limited to 27% coverage. However, Figure 3 stated that the total examination coverage for this weld was 32%. Clarify this apparent discrepancy.

1

2.4 Table 2 of the Relief Requests states that Other Examination Results include a System Pressure test. Explain how the system pressure test is relevant to determine the acceptability of the two Category C-C attachment welds.

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Hearing Identifier: NRR_PMDA Email Number: 2906 Mail Envelope Properties (Robert.Kuntz@nrc.gov20160616142300)

Subject:

Request for Information RE: Prairie Island relief requests 1-RR-4-11 and 2-RR-11 Sent Date: 6/16/2016 2:23:10 PM Received Date: 6/16/2016 2:23:00 PM From: Kuntz, Robert Created By: Robert.Kuntz@nrc.gov Recipients:

"Carlson, Glenn A." <Glenn.Carlson@xenuclear.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 2988 6/16/2016 2:23:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

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