NRC 2017-0008, Response to Final Request for Additional Information on Steam Generator Tube Inspection Report

Response to Final Request for Additional Information on Steam Generator Tube Inspection Report

ML17054C310
Person / Time
Site:	Point Beach
Issue date:	02/23/2017
From:	Woyak B Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
MF8401, NRC 2017-0008
Download: ML17054C310 (3)

Text

February 23, 2017 NRC 2017-0008 TS 5.6.8 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Point Beach Nuclear Plant, Units 1 Docket 50-266 Renewed License Nos. DPR-24 Response to Final Request for Additional Information, Point Beach Nuclear Plant, Unit 1, Steam Generator Tube Inspection Report

References:

(1) NextEra Energy Point Beach, LLC, letter to NRC, dated September 20, 2016, "Spring 2016 Unit 1 (U 1R36) Steam Generator Tube Inspection Report" (ML16264A202)

(2) NRC e-mail to NextEra Energy Point Beach, LLC, dated January 24, 2017, "Final Request for Additional Information - Point Beach Nuclear Plant, Unit 1, Steam Generator Tube Inspection Report- MF8401" Pursuant to the requirements of Point Beach Nuclear Plant (PBNP) Technical Specification, TS 5.6.8 "Steam Generator Tube Inspection Report", NextEra Energy Point Beach, LLC, (NextEra) submitted the 180 day Spring 2016 Unit 1 (U1 R36) Steam Generator Tube Inspection Report, (Reference 1).

The NRC Staff has determined that additional information (References 2) is required to complete its evaluation. The enclosure provides the NextEra response to the NRC Staff request for additional information.

NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241

Document Control Desk Page 2 This letter contains no new Regulatory Commitments or revisions to existing Regulatory Commitments.

Should you have questions or require additional information, please contact Mr. Edward Korkowski at 561/904-5779.

Sincerely, NextEra Energy Point Beach, LLC Bryan Licensing Manager Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW

Document Control Desk Page 3 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 RESPONSE TO FINAL REQUEST FOR ADDITIONAL INFORMATION STEAM GENERATOR TUBE INSPECTION REPORT - MF8401 On January 19, 2016, the U.S. Nuclear Regulatory Commission (NRC) staff sent NextEra Energy Point Beach, LLC (NextEra)(the licensee) the draft Request for Additional Information (RAJ) provided below. This RAJ relates to the results of their 2016 steam generator inspections performed during refueling outage 36 at Point Beach Nuclear Plant, Unit 1.

A clarification call was held on January 24, 2016, between the NRC staff and the representatives of NextEra. The licensee understood the requested information to be provided on the docket. Tom Schneider from NextEra agreed to provide a response to this final RAJ within 30 days from the date of this correspondence. The NRC staff also informed the licensee that a publicly available version of this final RAJ would be placed in the NRC's Agencywide Documents Access and Management System By Jetter dated September 20, 2016 (Agencywide Documents Access Management System Accession No. ML16264A202), NextEra Energy Point Beach, LLC (the licensee), submitted the results of their 2016 steam generator inspections performed during refueling outage 36 at Point Beach Nuclear Plant, Unit 1.

In order to complete its review, the U.S. Nuclear Regulatory Commission staff requests the following additional information:

1. Regarding the channel head inspections and the upper steam drum internals visual inspections, please clarify the meaning of "no anomalies" and whether any degradation was observed.

Response to RAI 1 The Steam Generator (SG) Tube Inspection Report stated that no anomalies were identified in the channel head bowls (Hot Leg and Cold Leg) of either SG. The report also stated that during the visual inspection of the upper steam drum components in SG B, that no anomalies were observed or reported.

The intent was to convey that no degradation was detected during the visual inspection of the channel head bowls (in either SG), or during the visual inspection of the upper steam drum components in SG B (the only upper steam drum inspected).