ML071030023

10/18/2006 Summary of Conference Call with PSEG Nuclear LLC to Discuss the Fall 2006 Steam Generator Tube Inspections at Salem Nuclear Generating Station, Unit No. 2

ML071030023
Person / Time
Site:	Salem
Issue date:	05/10/2007
From:	Richard Ennis NRC/NRR/ADRO/DORL/LPLB
To:	Levis W Public Service Enterprise Group
Ennis R, NRR/DLPM, 415-1420
Shared Package
ML071310308	List: ML071030023
References
TAC MD3326
Download: ML071030023 (5)

Text

May 10, 2007Mr. William LevisSenior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038

SUMMARY

OF CONFERENCE CALL WITH PSEG NUCLEAR LLC TODISCUSS THE FALL 2006 STEAM GENERATOR TUBE INSPECTIONS AT SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 (TAC NO. MD3326)

Dear Mr. Levis:

On October 18, 2006, the Nuclear Regulatory Commission (NRC) staff participated in aconference call with PSEG Nuclear LLC (PSEG) to discuss the 2006 steam generator (SG) tube inspection activities taking place during refueling outage 2R15 at Salem Nuclear Generating Station, Unit No. 2. To facilitate the discussion, PSEG provided a summary of the 2R15 SG base scope tube inspection and expansion plans, and a table showing the most significant tube indications identified as of October 18, 2006. Enclosed is a brief summary of the conference call as well as the information provided by PSEG. This completes the NRC staff efforts for TAC No. MD3326.

If you have any questions regarding this matter, I may be reached at 301-415-1420.Sincerely,/ra/Richard B. Ennis, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-311

Enclosures:

1. Summary of Conference Call

2. Summary of 2R15 SG Base Scope Tube Inspection and Expansion Plans

3. Table of Tube Indicationscc w/encls: See next page

.Package: ML071310308 Letter and Enclosure 1: ML071030023 Enclosures 2 and 3: ML071310403*By memo dated 11/7/06OFFICELPL1-2/PMLPL1-1/LACSGB/BC*LPL1-2/BC NAMEREnnisSLittleAHiserHChernoff DATE4/18/074/18/200711/07/065/10/07 Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:

Mr. Dennis WinchesterVice President - Nuclear Assessment PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Thomas P. JoyceSite Vice President - Salem PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George H. GellrichPlant Support Manager PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Carl J. FrickerPlant Manager - Salem PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038Mr. James MallonManager - Licensing 200 Exelon Way, KSA 3-E Kennett Square, PA 19348Mr. Steven MannonManager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038Jeffrie J. Keenan, EsquirePSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038Township ClerkLower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038Mr. Paul Bauldauf, P.E., Asst. DirectorRadiation Protection Programs NJ Department of Environmental Protection and Energy

CN 415 Trenton, NJ 08625-0415Mr. Brian BeamBoard of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102Regional Administrator, Region IU.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406Senior Resident InspectorSalem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038

SUMMARY

OF CONFERENCE CALL WITH PSEG NUCLEAR LLCFALL 2006 STEAM GENERATOR TUBE INSPECTIONSSALEM NUCLEAR GENERATING STATION, UNIT NO. 2DOCKET NO. 50-311On October 18, 2006, the Nuclear Regulatory Commission (NRC) staff participated in aconference call with PSEG Nuclear LLC (PSEG or the licensee) to discuss the 2006 steam generator (SG) tube inspection activities taking place during refueling outage 2R15 at Salem Nuclear Generating Station, Unit No. 2 (Salem Unit 2). Salem Unit 2 has four Westinghouse Model 51 SGs. Each SG contains approximately3400 mill-annealed Alloy 600 tubes. Each tube has a nominal outside diameter of 0.875-inch and a nominal wall thickness of 0.050-inch. The tubes were explosively expanded (WEXTEX) at both ends for the full length of the tubesheet and are supported by a number of drilled-hole carbon steel tube supports. The row 1 tubes were preventatively plugged. The SGs are scheduled to be replaced during the next refueling outage in spring 2008 (2R16).To facilitate the discussion, PSEG provided a summary of the 2R15 SG base scope tubeinspection and expansion plans, and a table showing the most significant tube indications identified as of October 18, 2006 (Enclosures 2 and 3). In addition to the written material provided by the licensee, the following additional clarifying information was discussed during the conference call. The licensee took two exceptions to the Pressurized Water Reactor (PWR) SG ExaminationGuidelines. The first exception was to calibrate the rotating coil with a 20% inside diameter (ID) axial and circumferential notch rather than with a 40% ID notch. An analysis was performed using data from a sister plant that has both the 20% and 40% throughwall notches in its calibration standard to demonstrate that the technique used at Salem Unit 2 is essentially equivalent to that recommended in the guidelines. The second exception was that analysts were not required to review overcalls. These two exceptions have been in place since 2R13.At the time of the conference call, the licensee had acquired 50% to 60% of the data, and hadanalyzed approximately 32% to 50%. Bobbin coil inspections were almost completed and the licensee had completed about 15% of rotating pancake coil (RPC) inspections in the tubesheet region of one SG. The RPC inspections of the U-bend region of the row 9 and 10 tubes were almost complete, and no indications had been detected. At the time of the call, there were a lower number of bobbin indications (I-codes) than had been observed in previous inspections.

Most of the I-codes identified are manufacturing burnish marks (MBMs). During the past two inspections, 100% of the MBMs were inspected with a rotating probe. The licensee performed a historical review of the bobbin data associated with these MBMs to determine if there was any significant voltage change, but none was identified. In addition, a historical review of the RPC data for these MBMs was performed to confirm none of the indications are flaw-like. A list of the most significant indications identified as of October 18, 2006, is shown inEnclosure 3. In this table, there are two cold leg thinning indications: one with a 58%

throughwall depth and a voltage of 3.75 volts and the other one with a 64% throughwall depth and a voltage of 0.95 volts. A historical review of these indications showed that, during the previous outage, the 58% throughwall indication measured 39% throughwall and had a voltage of 2.3 volts, while the 64% throughwall indication measured 34% throughwall and had a voltage of 1.15 volts. The licensee indicated that it is not uncommon to have such changes in voltage and depth given the low voltages for these indications. Both indications have adequate tube integrity. The licensee plans to plug all wear indications caused by loose parts in addition to any stress-corrosion cracking (SCC) degradation.At the time of this call, no in-situ pressure tests or tube pulls were planned, however, ifnecessary, Electric Power Research Institute (EPRI) in-situ guidelines will be followed.At the time of the conference call, inspections to detect loose parts were ongoing. Eddy currentinspections identified some possible loose part indications. These indications were scheduledto be investigated visually. In addition, the licensee identified the presence of one part by eddy current that had been previously left in service. No wear has been associated with any of the possible loose part indications identified.Historically, the licensee has detected primary water stress-corrosion cracking (PWSCC) nearthe top of the tubesheet, PWSCC and outside diameter stress corrosion cracking (ODSCC) at the tube support plate (TSP) elevations, ODSCC at the top of the tubesheet, ODSCC at the TSP elevations (only a few indications primarily at the 4 th hot leg TSP and not associated withdents), and SCC (typically PWSCC) at dents (typically at the 1 st hot leg tube support: five weredetected at the 1 st hot leg tube support during the last outage). No degradation has beenidentified in dings.The data quality is monitored per revision 6 of the EPRI PWR SG Examination Guidelines.The data quality is similar to past inspections.On October 20, 2006, another conference call was conducted with the licensee to discuss anaxially-oriented ODSCC indication found at a 6.83-volt ding in SG 24. The indication was 1.55 inches above the top of the tubesheet on the hot leg side of the SG. The indication was reported to be 0.26 inch long with a voltage of 0.47 volts. The licensee was expanding the scope of their inspection consistent with the EPRI PWR SG Examination Guidelines.Based on the information provided, the NRC staff did not identify any technical issues thatwarranted follow-up action at this time.