ML17293A267

Review of the Fall 2016 Refueling Outage Steam Generating Tube Inspection Report (CAC No. MF9094; EPID L-2017-LRO-0001)

ML17293A267
Person / Time
Site:	Salem
Issue date:	10/26/2017
From:	Carleen Parker Plant Licensing Branch 1
To:	Sena P Public Service Enterprise Group
Parker C, NRR/DORL/LPLI, 415-1603
References
CAC MF9094, EPID L-2017-LRO-0001
Download: ML17293A267 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 26,2017 Mr. Peter P. Sena, Ill President and Chief Nuclear Officer PSEG Nuclear LLC - N09 P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

. REVIEW OF THE FALL 2016 REFUELING OUTAGE STEAM GENERATOR TUBE INSPECTION REPORT - SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 (CAC NO. MF9094; EPID L-2017-LR0-0001)

Dear Mr. Sena:

By letter dated January 20, 2017, as supplemented by letter dated August 7, 2017 (Agencywide Documents Access and Management System Accession Nos. ML17020A111 and ML17219A166, respectively), PSEG Nuclear LLC (PSEG or the licensee) submitted information summarizing the results of the fall 2016 steam generator tube inservice inspections at Salem Nuclear Generating Station (Salem), Unit No. 1. These inspections were performed during refueling outage 24. The information was submitted in accordance with Salem, Unit No. 1, Technical Specification (TS) 6.9.1.1 O, "Steam Generator Tube Inspection Report."

The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of PSEG's submittals, as documented in the enclosed evaluation. The NRC staff concludes that PSEG has provided the information required by the TSs and that no additional followup is required at this time. This completes the NRC staff's efforts for CAC No. MF9094/EPID L-2017-LR0-0001.

If you have any question regarding this matter, I may be reached at 301-415-1603 or by e-mail to Carleen.Parker@nrc.gov.

erely,

~~J- I

~

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/-~--

Carleen J. Pc(rke , Project Manager Plant Licensi~g, ranch I Division of Ope'rating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-272

Enclosure:

Evaluation of Steam Generator Tube lnservice Inspection Report cc w/

Enclosure:

Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET NO. 50-272

1.0 INTRODUCTION

By letter dated January 20, 2017, as supplemented by letter dated August 7, 2017 (Agencywide Documents Access and Management System Accession Nos. ML17020A111 and ML17219A166, respectively), PSEG Nuclear, LLC (PSEG or the licensee) submitted information summarizing the results of the fall 2016 steam generator (SG) tube inservice inspections at Salem Nuclear Generating Station (Salem), Unit No. 1. These inspections were performed during refueling outage 24 (RFO 24). The information was submitted in accordance with Salem, Unit No. 1, Technical Specification (TS) 6.9.1.10, "Steam Generator Tube Inspection Report."

2.0 BACKGROUND

Salem, Unit No. 1, has four Westinghouse Model F SGs, each of which contains 5,626 U-bend thermally treated Alloy 600 tubes. Each tube has a nominal outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. During SG fabrication, the tubes were hydraulically expanded at both ends over the full depth of the tubesheet. The tubesheet was drilled on a square pitch with 0.98-inch spacing. The U-bends in rows 1 through 1O were stress relieved after bending. The tubes are supported by eight Type 405 stainless steel support plates that have broached quatrefoil holes. Chrome-plated Alloy 600 anti-vibration bars support the U-bend section of the tubes.

3.0 EVALUATION The licensee provided the scope, extent, methods, and results of its SG tube inspections in the letters referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.

After review of the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comment/observation:

The active degradation mechanisms reported by the licensee during RFO 24 included tube wear from anti-vibration bars, tube support plates, the flow baffle plate, and foreign objects. Salem, Unit No. 1, has not identified any crack indications as of RFO 24.

Enclosure

4.0 CONCLUSION

Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by its TSs. In addition, the NRC 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.

Principal Contributor: Alan Huynh Date: October 26, 2017

SUBJECT:

REVIEW OF THE FALL 2016 REFUELING OUTAGE STEAM GENERATOR TUBE INSPECTION REPORT-SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 (CAC NO. MF9094; EPID L-2017-LR0-0001) DATED OCTOBER 26, 2017 DISTRIBUTION:

PUBLIC RidsRgn1 MailCenter Resource RidsACRS_MailCTR Resource RidsNrrPMSalem Resource RidsNrrDorlLpl1 Resource RidsNrrLALRonewicz Resource RidsNrrDlrRccb Resource PKlein, NRR AJohnson, NRR AHuynh, NRR SBloom, NRR ADAMS Access1on No.: ML17293A267 *b1y memoran d um d ated OFFICE DORL/LPL 1/PM DORL/LPL 1/LA DLR/RCCB/BC* DORL/LPL 1/BC DORL/LPL 1/PM NAME CParker LRonewicz SBloom Joanna CParker DATE 10/25/2017 10/23/2017 09/20/2017 10/25/2017 10/26/2017 OFFICIAL RECORD COPY