ML031970605

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Summary of Pre-Outage Conference Call with FPL Energy Seabrook, LLC Regarding the Inspection Scope for the Upcoming Steam Generator Inspections at the Seabrook Station, Unit No. 1
ML031970605
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 07/23/2003
From: Nerses V
NRC/NRR/DLPM/LPD1
To: Warner M
Florida Power & Light Energy Seabrook
Nerses V, NRR/DLPM, 415-1484
References
TAC MB8928
Download: ML031970605 (4)


Text

July 23, 2003 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874

SUBJECT:

SUMMARY

OF PRE-OUTAGE CONFERENCE CALL WITH FPL ENERGY SEABROOK, LLC REGARDING THE INSPECTION SCOPE FOR THE UPCOMING STEAM GENERATOR INSPECTIONS AT THE SEABROOK STATION, UNIT NO. 1 (TAC NO. MB8928)

Dear Mr. Warner:

On June 16, 2003, the U. S. Nuclear Regulatory Commission held a conference call with FPL Energy Seabrook, LLC, the licensee for the Seabrook Station, Unit No.1 (Seabrook), to discuss the inspection scope for the scheduled upcoming steam generator inspections at Seabrook during the next refueling outage. Currently, the planned scope includes inspection of 100% of the tubes in all four steam generators using a bobbin coil, with supplementary inspections using a rotating coil in tube locations with increased susceptibility to degradation.

Enclosed is a summary of the conference call.

Sincerely,

/RA/

Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

Summary of Pre-Outage Conference Call cc w/encl: See next page

July 23, 2003 Mr. Mark E. Warner, Site Vice President c/o James M. Peschel Seabrook Station FPL Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874

SUBJECT:

SUMMARY

OF PRE-OUTAGE CONFERENCE CALL WITH FPL ENERGY SEABROOK, LLC REGARDING THE INSPECTION SCOPE FOR THE UPCOMING STEAM GENERATOR INSPECTIONS AT THE SEABROOK STATION, UNIT NO. 1 (TAC NO. MB8928)

Dear Mr. Warner:

On June 16, 2003, the U. S. Nuclear Regulatory Commission held a conference call with FPL Energy Seabrook, LLC, the licensee for the Seabrook Station, Unit No.1 (Seabrook), to discuss the inspection scope for the scheduled upcoming steam generator inspections at Seabrook during the next refueling outage. Currently, the planned scope includes inspection of 100% of the tubes in all four steam generators using a bobbin coil, with supplementary inspections using a rotating coil in tube locations with increased susceptibility to degradation.

Enclosed is a summary of the conference call.

Sincerely,

/RA/

Victor Nerses, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

Summary of Pre-Outage Conference Call cc w/encl: See next page DISTRIBUTION:

PUBLIC PDI-2 Rdg. CHolden JClifford VNerses CRaynor OGC ACRS GHill(2) BMcDermott, RGN-I ADAMS Accession Number: ML031970605 OFFICE PDI-2/PM PDI-2/LA EMCB/SC PDI-2/SC NAME VNerses CRaynor LLund JClifford DATE 7/21/03 7/21/03 7/21/03 7/23/03 OFFICIAL RECORD COPY

SUMMARY

OF PRE-OUTAGE CONFERENCE CALL REGARDING THE INSPECTION SCOPE FOR THE UPCOMING STEAM GENERATOR INSPECTION AT THE SEABROOK STATION, UNIT NO. 1 As part of a U.S, Nuclear Regulatory Commission (NRC) normal oversight activity with plants that have steam generator issues (SG), the NRC, on June 16, 2003, held a conference call with FPL Energy Seabrook, the licensee for the Seabrook Station, Unit No. 1 (Seabrook). The purpose of the call was to discuss the planned SG inspection scope at Seabrook during the upcoming refueling outage. The scope is preliminary as the plants SG tube degradation assessment is not yet complete.

Seabrook uses four Westinghouse Model F steam generators with thermally-treated Alloy 600 tubing, and is the first domestic plant to identify axial outside-diameter stress corrosion cracking (ODSCC) of SG tubes fabricated from this material. This degradation was identified during the Spring 2002 refueling outage and was attributed to non-optimal tube processing during the fabrication of the SG. Additional details are contained in NRC Information Notice (IN) 2002-21, "Axial Outside-Diameter Cracking Affecting Thermally Treated Alloy 600 Steam Generator Tubing" (Agencywide Document Access and Management System (ADAMS) Accession No. ML021770094); IN 2002-21, Supplement 1, "Axial Outside-Diameter Cracking Affecting Thermally Treated Alloy 600 Steam Generator Tubing" (ADAMS Accession No. ML030900517);

and in the licensees root cause analysis report (ADAMS Accession Nos. ML023300457 and ML023240524). The planned inspection scope consists of:

  • inspection of 100% of the active tubes in all four SGs with a bobbin probe
  • inspection of 50% of the tubes in all four SGs with a rotating probe in the hot leg top-of-tubesheet region (i.e., inspection from 3 inches above to 3 inches below the top-of-tubesheet region)
  • inspection of 50% of the row 1 and 2 tubes in the U-bend region in all four SGs with a rotating probe
  • inspection of 50% of dents and dings greater than 5 volts in the hot leg tubes in all four SGs with a rotating probe
  • inspection of indications with a rotating probe that are identified as I Codes, based on examination with a bobbin probe Six tubes displaying an eddy current signal offset, characteristic of the tubes with axial ODSCC, will be plugged during the next refueling outage. These six tubes were determined to display the offset after completion of the 2002 refueling outage and exhibited no ODSCC crack-like indications during the 2002 SG inspection. Eddy current testing will be performed on these tubes prior to plugging, in order to assess their condition. Refer to ADAMS Accession No. ML023170187, Summary of Conference Call With North Atlantic Energy Service Corporation Regarding The Seabrook Steam Generator Laboratory Examination Results, for additional information regarding the eddy current signal offset.

Eddy current analysis of site-specific orientation and testing will incorporate samples from the thermally-treated Alloy 600 tubing with ODSCC. The licensee indicated this was an enhancement to their training program, since the previous level of training had been sufficient to detect the ODSCC flaws in the previous outage.

Enclosure

Seabrook Station, Unit No. 1 cc:

Mr. J. A. Stall Mr. Stephen McGrail, Director Senior Vice President, Nuclear and ATTN: James Muckerheide Chief Nuclear Officer Massachusetts Emergency Management Agency Florida Power & Light Company 400 Worcester Road P.O. Box 14000 Framingham, MA 01702-5399 Juno Beach, FL 33408-0420 Philip T. McLaughlin, Attorney General Mr. Peter Brann Steven M. Houran, Deputy Attorney Assistant Attorney General General State House, Station #6 33 Capitol Street Augusta, ME 04333 Concord, NH 03301 Resident Inspector Mr. Donald Bliss, Director U.S. Nuclear Regulatory Commission New Hampshire Office of Emergency Seabrook Nuclear Power Station Management P.O. Box 1149 State Office Park South Seabrook, NH 03874 107 Pleasant Street Concord, NH 03301 Town of Exeter 10 Front Street Mr. Daniel G. Roy Exeter, NH 03823 Nuclear Training Manager Seabrook Station Regional Administrator, Region I FPL Energy Seabrook, LLC U.S. Nuclear Regulatory Commission P.O. Box 300 475 Allendale Road Seabrook, NH 03874 King of Prussia, PA 19406 Mr. Gene F. St. Pierre Office of the Attorney General Station Director One Ashburton Place, 20th Floor Seabrook Station Boston, MA 02108 FPL Energy Seabrook, LLC P.O. Box 300 Board of Selectmen Seabrook, NH 03874 Town of Amesbury Town Hall Mr. M. S. Ross, Attorney Amesbury, MA 01913 Florida Power & Light Company P.O. Box 14000 Mr. Dan McElhinney Juno Beach, FL 33408-0420 Federal Emergency Management Agency Region I Mr. Rajiv S. Kundalkar J.W. McCormack P.O. & Vice President - Nuclear Engineering Courthouse Building, Room 401 Florida Power & Light Company Boston, MA 02109 P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Jack Devine Polestar Applied Technology One First Street, Suite 4 Los Altos, CA 94019