ML063450305

Summary of 11/17/2006 Discussions Steam Generator Tube Inspections - Refueling Outage 14 (TAC No. MD3204) - Letter to Licensee and Summary of Conference Call

ML063450305
Person / Time
Site:	San Onofre
Issue date:	12/18/2006
From:	Kalyanam N NRC/NRR/ADRO/DORL/LPLIV
To:	Rosenblum R M Southern California Edison Co
Kalynanam N, NRR/DORL/LP4, 415-1480
References
TAC MD3204
Download: ML063450305 (5)

Text

December 18, 2006Mr. Richard M. RosenblumSenior Vice President and Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 -

SUMMARY

OFNOVEMBER 17, 2006, DISCUSSIONS OF STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MD3204)

Dear Mr. Rosenblum:

On November 17, 2006, the Nuclear Regulatory Commission (NRC) staff participated in conference calls with Southern California Edison (SCE) representatives regarding the 2006 steam generator tube inspections at San Onofre Nuclear Generating Station, Unit 3.

The information supplied by SCE in support of these discussions (handouts) is enclosed. The NRC staff did not identify any issues that would warrant preventing the plant from starting up following its 14th refueling outage.Sincerely,/RA/N. Kalyanam, Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-362

Enclosures:

1. Summary of conference call2. Information supplied by SCE in support of these discussions (handouts)cc w/encls: See next page

Package ML063450313 (Ltr/Summary ML063450305, Licensee Info ML063460072)OFFICENRR/DORL/LPL4/PMNRR/DORL/LPL4/LAEMGB/BCNRR/DORL/LPL4/BCNAMENKalyanamLFeizollahiAHiserDTerao DATE12/18/0612/18/0612/4/0612/18/06 March 2006San Onofre Nuclear Generating Station Units 2 and 3 cc:Mr. Daniel P. Breig Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128Mr. Douglas K. Porter, EsquireSouthern California Edison Company 2244 Walnut Grove Avenue Rosemead, CA 91770Mr. David Spath, ChiefDivision of Drinking Water and Environmental Management P.O. Box 942732 Sacramento, CA 94234-7320Chairman, Board of SupervisorsCounty of San Diego 1600 Pacific Highway, Room 335 San Diego, CA 92101Mark L. ParsonsDeputy City Attorney City of Riverside 3900 Main Street Riverside, CA 92522Mr. Gary L. Nolff Assistant Director - Resources City of Riverside 3900 Main Street Riverside, CA 92522Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064Mr. Michael R. OlsonSan Diego Gas & Electric Company 8315 Century Park Ct. CP21G San Diego, CA 92123-1548Director, Radiologic Health BranchState Department of Health Services P.O. Box 997414, MS 7610 Sacramento, CA 95899-7414Resident Inspector/San Onofre NPS c/o U.S. Nuclear Regulatory Commission Post Office Box 4329 San Clemente, CA 92674Mayor City of San Clemente 100 Avenida Presidio San Clemente, CA 92672Mr. James T. Reilly Southern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128Mr. James D. Boyd, CommissionerCalifornia Energy Commission 1516 Ninth Street (MS 31)

Sacramento, CA 95814Mr. Ray Waldo, Vice PresidentSouthern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92764-0128Mr. Brian KatzSouthern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92764-0128Mr. Steve HsuDepartment of Health Services Radiologic Health Branch MS 7610, P.O. Box 997414 Sacramento, CA 95899Mr. A. Edward SchererSouthern California Edison Company San Onofre Nuclear Generating Station P.O. Box 128 San Clemente, CA 92674-0128

SUMMARY

OF NOVEMBER 17, 2006, CONFERENCE CALL WITH SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3REGARDING THE 2006 STEAM GENERATOR TUBE INSPECTION RESULTSOn November 17, 2006, the Nuclear Regulatory Commission (NRC) staff conducted a phonecall with representatives from San Onofre Nuclear Generating Station, Unit 3 (SONGS 3) to discuss the ongoing steam generator (SG) tube inspections during their Cycle 14 refueling outage (3C14). SONGS 3 has two Combustion Engineering Model 3410 SGs, designated SG 88 and SG 89, each with 9,350 tubes made from mill-annealed Alloy 600. The tubes have an outside diameter of 0.75 inch and a nominal wall thickness of 0.048 inch. The tubes are explosively expanded for the full depth of the tubesheet and are supported by carbon steel lattice grids (eggcrates). The tubes are also supported by carbon steel vertical and diagonal bars in the U-bend section. The hot-leg temperature has been approximately 598 to 600 degrees Fahrenheit for the last five operating cycles. The SONGS 3 SGs are scheduled to be replaced after two more operating cycles (i.e., one more inspection is planned for these SGs after the 2006 inspection).The last inspection of the SG tubes at SONGS 3 was performed during the Cycle 13 refuelingoutage completed in October 2004. The number of tubes remaining in service at the start of the 3C14 outage was 8,646 in SG 88 and 8,699 in SG 89. Prior to the conference call, the licensee provided a written response to a set of questions from the NRC staff. The response is attached to this call summary. Additional clarifying information and information not included in the attached document is summarized below.Throughout the operating cycle prior to the outage, the amount of primary-to-secondaryleakage was below the 0.1 gallons per day (gpd) threshold detection level of the normal monitoring system. However, leakage at a rate of approximately 2 x 10

-5 gpd was detectedbeginning on June 2, 2006, in weekly charcoal filter samples collected continuously from the condenser off-gas. The source of the leakage could not be determined, but the licensee suspects it is leakage past a plug. Monitoring will continue following the plant restart.In discussing the scope of the inspections, the licensee clarified that the rotating probeinspections conducted in the upper region of the tubesheet extended from 4 inches above the top of the tubesheet (TTS) to 13 inches below the TTS on the hot-leg side, and from 2 inches above the TTS to 13 inches below the TTS on the cold-leg side. All of the tubes in service are fully expanded. The licensee also explained that dents are defined as tube diameter distortions located at a support plate, while dings are defined as tube diameter distortions located in a freespan.At the time of the call, there were approximately 28 tubes in SG 88 and 10 tubes in SG 89identified for plugging due to either wear indications at tube supports or cracking indications ator near the top of the hot-leg portion of the tubesheet. These included 7 tubes with indications of cracking and 31 tubes with indications of wear. Two of the cracking indications in each SG were circumferential and located near the TTS. The other 3 indications of cracking (in SG 88) were oriented axially. None of the indications of cracking were located within volumetric flaws.

No indications were being left in service as a result of the C-star amendment, which permits flaws of any size to remain in service if located at least 10.4 inches below the TTS in the hot-legregion and 11.0 inches below the TTS in the cold-leg region. The licensee was preparing to install plugs in all of the tubes with cracking indications, as well as stabilizers in the tubes in which these indications were circumferential.Since the number of cracking indications was low, the staff asked the licensee to discusswhether eddy current noise or other factors may have caused a reduction in flaw detection.

The licensee explained that their inspections continue to detect indications of cracking at the TTS that have very small eddy current signals, as well as wear scars with signals comparable to the small TTS cracking indications. In general, they have seen no changes in the appearance of the eddy current signals (including noise levels) that would indicate a loss of detectioncapability.With respect to the wear indications, in each case the depth of the wear scar (i.e.,wall-thickness reduction) was less than the plant's technical specification repair limit of 44 percent. However, for the approximately 31 tubes identified for plugging due to wear, the depth of the wear scars exceeded an administrative plugging limit. No wear indications were found at locations that do not correspond to the support structure (and might therefore indicate the failure of a support member). In addition, there were no indications that a support was not at its proper location.A visual exam was performed on the secondary side using remote video camera equipment.The inspection concentrated on the periphery and the open tube lane. This inspection detected one unidentified loose part in SG 89 at the periphery of the cold-leg TTS region. The part was approximately 0.375 inch by 0.375 inch by 0.06 inch, apparently made of plastic, and was removed from the SG. The eddy current data indicated no damage from the part.There was no sludge lancing performed during this outage. The licensee reported that at thetime of the conference call, no new degradation mechanisms had been found, no tube pulls or in-situ pressure tests were planned, and no sleeves were being installed. At the end of the call, the licensee was asked to inform the staff if during the remainder of the inspections there were any unexpected results such as new degradation mechanisms.