ML020930796

Summary of Conference Call with Florida Power Corp. Regarding 2001 Steam Generator Tube Inspection Results 9TAC MB3015)

ML020930796
Person / Time
Site:	Crystal River
Issue date:	04/03/2002
From:	Goshen J NRC/NRR/DLPM/LPD2
To:	Young D Florida Power Corp
Goshen, JM, NRR/DLPM, 415-1437
References
TAC MB3015
Download: ML020930796 (4)

Text

April 3, 2002 Mr. Dale E. Young, Vice President Crystal River Nuclear Plant (NA1B)

ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708

SUBJECT:

CRYSTAL RIVER UNIT 3

SUMMARY

OF CONFERENCE CALL WITH FLORIDA POWER CORPORATION REGARDING 2001 STEAM GENERATOR TUBE INSPECTION RESULTS (TAC NO. MB3015)

Dear Mr. Young:

On October 17, 2001, the Nuclear Regulatory Commission staff (NRC) participated in a conference call with Florida Power Corporation (FPC) regarding the steam generator tube inspection activities during Refueling Outage 12 at Crystal River Unit 3. Enclosed is a summary of the conference call. Also enclosed are materials provided by FPC to support the call.

Participants included myself, John Tsao, Ken Karwoski, and Mark Lesser.

By letter dated October 19, 2001, FPC submitted a special inspection report prior to ascension to MODE 4. FPC will be submitting a comprehensive inspection report in accordance with the plant technical specifications. We appreciate your support in this matter. If you have any questions, please give me a call at (301) 415-1437.

Sincerely,

/RA/

John M. Goshen, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosures:

1. Summary of 10/17/01 Conference Call

2. FPC Supporting Documentation cc w/enclosures: See next page

ML020930796 OFFICE PDII-2/PM PDII-2/LA PSDII-2/SC NAME JGoshen BClayton RCorreia DATE 3/27/2002 3/27/2002 3/27/2002

SUMMARY

OF OCTOBER 17, 2001, CONFERENCE CALL WITH FLORIDA POWER CORPORATION REGARDING CURRENT STEAM GENERATOR INSPECTION RESULTS AT CRYSTAL RIVER UNIT 3 On October 17, 2001, staff from the Materials and Chemical Engineering Branch of the Division of Engineering participated in conference calls with Florida Power Corporation (FPC) representatives to discuss the results of the steam generator tube inspections during Refueling Outage 12 at Crystal River Unit 3.

FPC representatives discussed the following topics: initial eddy current testing scope, scope expansion plans, indications identified to-date, repair/plugging plans, new inspection findings, in situ pressure test plans and actions taken in response to lessons learned from the Indian Point Unit 2 tube failure.

In accordance with Regulatory Commitments specified in License Amendment No. 198 for the reroll joint repair, dated September 10, 2001, FPC reported that several circumferential indications were detected in the original roll joints and rerolled joints in the tubesheet. These tubes were plugged. As a part of the Regulatory Commitments, FPC reported that the estimated leakage from the reroll joints under large break loss-of-coolant accident conditions for steam generators A and B were within the allowable limits. Additional details may be found in FPCs letter dated October 19, 2001 (Adams Accession No. ML013610008).

FPC also reported observing the following degradation as a result of the steam generator tube inspection: volumetric indications in the transition regions of the roll and reroll joints; axial indications in the tube end regions; volumetric/intergranular attack indications at the first span; and circumferential, axial, and volumetric indications in various locations.

FPC plugged approximately 40 tubes, including a tube that was not expanded in the tubesheet, and a tube with a circumferential indication. This latter indication was located 0.78 inch below the top of the eighth tube support plate, which has a thickness of 1.5 inches. The indication was 0.23-inch in circumferential extent and exhibited a voltage of 0.57 volts. The indication was detected initially by the bobbin probe and subsequently confirmed by a plus point coil as a circumferential indication. The indication had axial branching and was in reality a mixed-mode indication. No other indications were detected in similar locations in other tube support plate locations. The indication was analyzed to be within the conditioning monitoring limits.

On the basis of the information discussed during the calls, the staff did not identify any issues requiring further discussion.

ENCLOSURE 1

Mr. Dale E. Young CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation cc:

Mr. R. Alexander Glenn Chairman Associate General Counsel (MAC-BT15A) Board of County Commissioners Florida Power Corporation Citrus County P.O. Box 14042 110 North Apopka Avenue St. Petersburg, Florida 33733-4042 Inverness, Florida 34450-4245 Mr. Daniel L. Roderick Ms. Sherry L. Bernhoft Plant General Manager Manager Regulatory Affairs Crystal River Nuclear Plant (NA2C) Crystal River Nuclear Plant (NA2H) 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Mr. Michael A. Schoppman Senior Resident Inspector Framatome ANP Crystal River Unit 3 1911 North Ft. Myer Drive, Suite 705 U.S. Nuclear Regulatory Commission Rosslyn, Virginia 22209 6745 N. Tallahassee Road Crystal River, Florida 34428 Mr. William A. Passetti, Chief Department of Health Mr. Richard L. Warden Bureau of Radiation Control Manager Nuclear Assessment 2020 Capital Circle, SE, Bin #C21 Crystal River Nuclear Plant (NA2C)

Tallahassee, Florida 32399-1741 15760 W. Power Line Street Crystal River, Florida 34428-6708 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Mr. Craig Fugate, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100