ML060730573

Memo 03/13/06 LaSalle DRS Input to DRP IR 06-003 Dej

ML060730573
Person / Time
Site:	LaSalle
Issue date:	03/13/2006
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Burgess B NRC/RGN-III/DRS/EB2
References
IR-06-003
Download: ML060730573 (5)

Text

March 13, 2006MEMORANDUM TO:Bruce L. Burgess, ChiefReactor Projects Branch 2 Division of Reactor ProjectsFROM:David E. Hills, Chief /RA by Ann Marie Stone Acting For/Engineering Branch 1Division of Reactor Safety

SUBJECT:

LASALLE NUCLEAR POWER STATIONDRS INPUT TO INTEGRATED REPORT 50-373/2006-003; 50-374/2006-003Attached is the report input for the LaSalle County Station, Units 1 and 2, InspectionReport No. 05000373/2006003; 5000374/2006003. This report input documents completion of Inspection Procedure (IP) 71111.08 Inservice Inspection (ISI) Activities. I have reviewed this input and have determined it is ready for distribution to the licensee and dissemination to the

public.POST INSPECTION DATA INPUT TO INSPECTION REPORT 50-373/2006-003; 50-374/2006-003:Procedure Status and Sample Size:IP 71111.08 Status - Incomplete Sample size = 1 CONTACT:Don Jones, DRP(630) 829-9622DOCUMENT NAME:C:\FileNet\ML060730573.wpd G Publicly Available G Non-Publicly Available G Sensitive G Non-SensitiveTo receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copyOFFICERIIIRIIINAMEDJones: lsAMStone for DHillsDATE03/09/0603/13/06OFFICIAL RECORD COPY Cover LetterTitle PageInspector:D. Jones, Reactor Inspector

SUMMARY

OF FINDINGSADAMS boilerplate - Inspectable areas: Routine Baseline Inspection Activities,Modify second paragraph as follows:The inspection was conducted by an ins pector based in the NRC Region III office. A.Inspector-Identified and Self-Revealing FindingsNone. REPORT DETAILS1.REACTOR SAFETYCornerstone: Mitigating Systems1R08Inservice Inspection (ISI) Activities (71111.08).1Piping Systems ISI a.Inspection ScopeFrom February 27, 2006 to March 2, 2006, the inspectors conducted a review of theimplementation of the licensee's ISI program for monitoring degradation of the reactor coolant system (RCS) boundary, and the risk significant piping system boundaries during the Unit 1 outage (L1R11). The inspectors selected the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI required examinations and Code components in order of risk priority as identified in Section 71111.08-02 of IP 71111.08, "Inservice Inspection Activities," based upon the ISI activities available for review during the on-site inspection period.The inspectors conducted an on-site review of the following types of nondestructiveexamination activities to evaluate compliance with the ASME Code Section XI, and Section V requirements, and to verify that indications and defects, (if present) were dispositioned in accordance with the ASME Code Section XI requirements. Specifically, the inspectors observed/reviewed the following examinations:*Ultrasonic examination (UT) of a pipe-to-valve weld (weld 1-RH-1003-2), residualheat removal;

• Magnetic Particle examination (MT) of the reactor pressure vessel top head-to-flange weld (GEL-1009-AG) from 180 to 360 degrees azimuth; and *an automated phased array UT of reactor core shroud weld H6.

The inspectors reviewed an examination with recordable indications that was acceptedfor continued service to verify that the licensee's acceptance was in accordance with the ASME Code or an NRC approved alternative. Specifically, the inspectors reviewed the following record:*The inspectors reviewed L1R10 UT record (Data Report Number 1R10-70) of afeedwater (FW) valve-to-pipe weld (1FW-1001-21) performed on February 13, 2004. A recordable indication was dispositioned as being outside the required examination volume, however, it was evaluated and found to be acceptable per ASME Section XI, IWB-3514.There were no pressure boundary welds, for Class 1 or 2 systems, completed by thelicensee, and hence the inspectors did not perform the step of the inspection procedure that verifies that the welding process, and welding examinations were performed in accordance with ASME Code requirements, or an NRC approved alternative. The inspectors performed a review of ISI related problems that were identified by thelicensee, and entered into the corrective action program. Additionally, the inspectors' review included confirmation that the licensee had an appropriate threshold for identifying issues, and had implemented effective corrective actions. The inspectors evaluated the threshold for identifying issues through interviews with licensee staff, and review of licensee actions to incorporate lessons learned from industry issues related to the ISI program. The inspectors performed these reviews to ensure compliance with 10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Action," requirements. The corrective action documents reviewed by the inspectors are listed in the attachment to this report. In addition, the inspectors verified that the licensee correctly assessed operating experience for applicability to the Inservice Inspection group. The reviews as discussed above counted as one inspection sample. b.FindingsNo findings of significance were identified.4OA6Meetings.2Interim Exit MeetingsInterim exits were conducted for:

• Inservice inspection (IP 71111.08) with Ms. S. Landahl on February 2, 2006.

KEY POINTS OF CONTACT LicenseeS. Landahl, Site Vice PresidentD. Enright, Plant Manager P. Holland, Regulatory Assurance - NRC Coordinator A. Kochis, ISI Coordinator H. Madronero, Engineering Programs Manager T. Simpkin, Regulatory Assurance ManagerNuclear Regulatory CommissionB. Burgess, Chief, Reactor Projects Branch 2LIST OF DOCUMENTS REVIEWED 1R08Inservice Inspection Activities (IP 71111.08)AR00458950; Jet Pump 12 Main Wedge Wear; No Change; dated February 26, 2006 AR00458993; Jet Pump 13 Main Wedge Wear; No Change; dated February 26, 2006 IR 457474; Stud nut on the north rod from can to the clamp was loose; datedFebruary 24, 2006 GE ROP-002; Reactor and Field Services Operating Experience Program; datedJanuary 2005GE ROP-004; Briefings and Shift Turnover; dated January 2005 GE-PDI-UT-1; PDI Generic Procedure for the Ultrasonic Examination of Ferritic PipeWelds; dated July 2005GE-MT-100; Procedure for Magnetic Particle Examination (Dry Particle, Color Contrastor Wet Particle, Fluorescent); dated September 2004 LIST OF ACRONYMS USEDASMEAmerican Society of Mechanical EngineersCFRCode of Federal Regulations DRSDivision of Reactor Safety FW Feedwater IPInspection Procedure ISIInservice Inspection MTMagnetic Particle Examination NDENondestructive Examination RCSReactor Coolant System RHRResidual Heat Removal UTUltrasonic Examination