L-2004-293, Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information

Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information

ML043650399
Person / Time
Site:	Saint Lucie
Issue date:	12/28/2004
From:	Jefferson W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2004-293
Download: ML043650399 (3)

Text

Florida Power & Light Company, 6501 S.Ocean Drive, Jensen Beach, FL 34957 December 28, 2004 FPL L-2004-293 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE: St. Lucie Unit 2 Docket No. 50-389 Third 10-Year Inservice Inspection Interval Relief Request No. 2 Supplemental Information Florida Power & Light Company (FPL) submitted the Third Interval Inservice Inspection (ISI) Program by FPL letter L-2003-189 dated August 6, 2003. Included in the submittal was ISI Relief Request No. 2 regarding the risk-informed inservice inspection program (RI-ISI) for ASME Class 1 piping. On August 6, 2004, the NRC issued a request for additional information (RAI). FPL responded to the RAI by FPL letter L-2004-210 dated September 17, 2004.

The attachment to this letter provides a revised copy of Table 5-1 in the relief request.

The updated table was requested by the NRC in a conference call on October 26, 2004.

Please contact George Madden at 772-467-7155 if there are any additional questions about this supplement.

Very truly yours, William Jeffert Jr.,tn .f Vice Preside St. Lucie Plant WJ/GRM

,4~c4 7 an FPL Group company

St. Lucie Unit 2 Docket No. 50-389 L-2004-293 Attachment Page 1 if UPDATED Table 5-1 STRUCTURAL ELEMENT SELECTION RESULTS AND COMPARISON TO ASME SECTION Xl 1qq8 A2000 REOUIREMENTS Number of High ASME XI Safety Significant ASME Weld Count Examination Methods RI-ISI Segments (No. of Deradation Code (Volumetric (Vol) and (Note 1)

System HSS in Aug. Meghnsms Cas CaeodeSr Su)

Program / Total Mechanisos Class Category Surface (Sur)) Number of No. of Segments (Note 2) Socket Vol & Sur Sur Only SES Matrix Exam in Aug. Program) Region Locations CH 0 Thermal 1 B-F 0 0 0 0 0 Fatigue B-J 21 99 0 61 Thermal 0 Fatigue, B-F 6 0 3 3 volumetric RC 11 (0/0) Thermal 1 1, 2 24 Transients, Vibration B-J 241 45 66 53 volumetric Fatigue Thermal B-F 0 0 0 0 Si 0 Fatigue, 1 0 ThermalB-J 139 12 13 4 Transients B-F 6 0 3 3 ONDE TOTAL 11(0/0) CL 1 B-J 401 156 79 118 24 NDE TOTAL 407 156 82 121 24 NDE Summary: Current ASME Section Xl selects a total of 82 non-destructive exams (surface only exams not included), wnile the proposed KzI-)l program selects a total of 24 non-destructive exams. This results in a 71% reduction of non-destructive exams.

General Notes:

1-System pressure test requirements and VT-2 visual examinations shall continue to be performed in ASME Class I systems.

2-1998 A2000, Table IWB-2500-1, Category B-J, now includes piping dissimilar metal piping welds. These welds were considered Category B-F, item #'s 5.130 and 5.140 under 1989 ASME Section Xl Table IWB-2500-1 (used for the previously approved submittal).

St. Lucie Unit 2 Docket No. 50-389 L-2004-293 Attachment Page 2 Explanation of Changes in Table 5-1 Total Weld Count:

Second interval table showed 404 butt welds, 157 socket welds.

Updated Table 5-1 shows 407 butt welds, 156 socket welds.

One butt weld previously counted as socket weld is now counted correctly, one new butt weld was installed by a plant modification, and one butt weld was miscounted and previously not included.

Increase in welds identified as reactor coolant (RC) system welds:

Second Interval Table 5-1 showed 222 RC system butt welds (B-F & B-J), 20 socket welds.

Updated Table 5-1 shows 241 RC system butt welds, 45 RC system socket welds.

Charging and letdown (CH) system welds located in transition segments 2-RC-074, 2-RC-075, 2-RC-079, and 2-RC-080 were previously counted as CH welds.

RC system weld count has increased and CH system weld count has decreased to reflect segment assignment. This is administrative only and does not affect the number of RC or CH segments.

Shutdown cooling suction and loop injection welds located in transition segments 2-RC-056, 2-RC-057, 2-RC-058, 2-RC-059, 2-RC-067, and 2-RC-069 were previously counted as safety injection (SI) welds. RC system weld count has increased and SI system weld count has decreased to reflect segment assignment. This is administrative only and does not affect the number of RC or Si segments.

There has been no change to the risk-informed inservice inspection (RI-ISI) analysis due to the redistribution of system weld counts.