ML18228A846

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Review of the Spring 2017 Steam Generator Tube Inservice Inspections During Refueling Outage 21
ML18228A846
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/20/2018
From: April Pulvirenti
Plant Licensing Branch IV
To:
Entergy Operations
Pulvirenti A
References
EPID L-2017-LRO-0064
Download: ML18228A846 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 20, 2018 Site Vice President Entergy Operations, Inc.

Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - REVIEW OF THE SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTIONS DURING REFUELING OUTAGE 21 (EPID L-2017-LR0-0064)

Dear Sir or Madam:

By letter dated November 21, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML173256762), Entergy Operations, Inc. (the licensee) submitted information to the U.S. Nuclear Regulatory Commission (NRC) summarizing the results of the spring 2017 steam generator tube inspections performed at Waterford Steam Electric Station, Unit 3 (Waterford 3). These inspections were performed during refueling outage 21.

The NRC staff has completed its review of the information provided and concludes that the licensee provided the information required by the Waterford 3 technical specifications. No additional followup is required at this time. The staff's review summary is enclosed.

If you have any questions, please contact me at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov.

Sincerely, April L. Pulvirenti, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

Review of the Steam Generator Tube Inspection Report cc: Listserv

REVIEW OF SPRING 2017 STEAM GENERATOR TUBE INSERVICE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 21 ENTERGY OPERATIONS, INC.

WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382 By letter dated November 21, 2017 (Agencywide Documents Access and Management System Accession No. ML17325B762), Entergy Operations, Inc. (the licensee) submitted information summarizing the results of the spring 2017 steam generator (SG) tube inspections performed at Waterford Steam Electric Station, Unit 3 (Waterford 3). These inspections were performed during refueling outage 21 (RFO 21 ).

Waterford 3 has two Westinghouse Delta 110 SGs that were installed in 2013. Each SG contains 8,968 thermally treated Alloy 690 tubes with a nominal outside diameter of 0. 75 inches and nominal wall thicknesses of 0.044 inches (for rows 1 and 2) and 0.043 inches for the remaining rows. The tubes are hydraulically expanded at both ends for the full depth of the tubesheet and are supported by eight Type 405 stainless steel tube support plates (TSPs) with trefoil-shaped holes arranged on a triangular pitch. Five sets of anti-vibration bars provide support for the U-bend region of the tube bundle.

The licensee provided the scope, extent, methods, and results of its SG tube inspections in the letter dated November 21, 2017. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.

After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments/observations:

  • Tube wear from the TSPs {TSP wear) was noted for the first time in the RFO 21 inspections. Two tubes with TSP wear were plugged in SG 31.
  • The licensee performed visual inspections of the upper steam drum components and reported that there were no identified anomalies. The steam drum region inspections included the: steam outlet nozzle venturis, mid-deck region, primary separator inside diameter {ID) above the swirl vanes, lower deck region, feedring spray cans and ID region, feedring structural supports, thermal sleeve to nozzle/pipe welds, and the sludge collector internals. The licensee also noted that the moisture separation equipment is constructed using carbon steels with measurable chrome content or nickel-based alloys, and therefore, erosion/corrosion of these components is not expected.

Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by the Waterford 3 technical specifications. In addition, the staff concludes that there are no technical issues that warrant followup action at this time, since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.

Enclosure

ML18228A846 *via memorandum OFFICE NRR/D0RULPL4/PM NRR/D0RULPL4/LA NRR/DMLR/MCCB/BC* NRR/D0RULPL4/BC NRR/D0RULPL4/PM NAME APulvirenti PBlechman $Bloom RPascarelli APulvirenti DATE 08/20/18 08/20/18 08/09/18 08/20/18 08/20/18