L-2004-065, Third 10-Year Intervals Supplement 1 - Repair of Alloy 600 Small Bore Nozzles Without Flaw Removal Unit 1 Relief Request 23 Revision 1 and Unit 2 Relief Request 5 Revision 0

Third 10-Year Intervals Supplement 1 - Repair of Alloy 600 Small Bore Nozzles Without Flaw Removal Unit 1 Relief Request 23 Revision 1 and Unit 2 Relief Request 5 Revision 0

ML040860446
Person / Time
Site:	Saint Lucie
Issue date:	03/24/2004
From:	Jefferson W Florida Power & Light Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2004-065
Download: ML040860446 (2)

Text

Florida Power & Light Company, 6501 S. Ocean Drive, Jensen Beach, FL 34957 March 24, 2004 FPL L-2004-065 10 CFR 50.4 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Inservice Inspection Plans Third 10-Year Intervals Supplement 1 - Repair of Alloy 600 Small Bore Nozzles Without Flaw Removal Unit 1 Relief Request 23 Revision 1 and Unit 2 Relief Request 5 Revision 0 By letter L-2003-285 dated November 21, 2003 and based on the NRC review status of WCAP-15973-P, Florida Power & Light Company (FPL) requested extension of Unit 1 Relief Request (RR) 23 and Unit 2 RR 5 (formerly Unit 2 second ISI interval RR 33).

Unit 1 RR 23 and Unit 2 second interval RR 33 were previously submitted by FPL letter L-2002-247 on January 8, 2003, supplemented by FPL letter L-2003-108 on April 23, 2003. NRC approved the RRs for one operating cycle for each unit by NRC letters dated May 9, 2003 and May 23, 2003. On August 8, 2003, Unit 2 started its third 10-year inspection interval.

The NRC staff stated in their May 9, 2003 and May 23, 2003 letters that prior to use of the half nozzle and sleeved full-nozzle replacements on a permanent basis, FPL will be required to submit a separate relief request for NRC approval. The NRC planned to issue the required conditions for implementing the half nozzle and sleeved full-nozzle repairs on a permanent basis in the NRC staffs safety evaluation of the Westinghouse Topical Report WCAP-15973-P, Revision 00, that was under NRC staff review. The extension of the Unit 1 RR 23 and Unit 2 RR 5 for one additional cycle for each unit will allow time for the NRC staff to complete the topical report review. It will also allow time for FPL to submit and the NRC to review the permanent RRs.

On March 11, 2004, the NRC project manager for St. Lucie requested FPL to docket the recent reactor coolant system (RCS) hot leg nozzle replacements in refueling outages SL1-17 and SL2-14.

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St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 L-2004-065 Page 2 The following nozzles were replaced during the last Unit 2 outage (SL2-14) by plant change/modification (PCM) 02173. Resistance temperature detector (RTD) instruments that had their thermowells and nozzles replaced are TE-1112HA, TE-1112HB, TE-1112HC, TE-1112HD, TE-1111X, TE-1122HA, TE-1122HB, TE-1122HC, TE-1122HD, and TE-1121 X.

Five of the RTD nozzles (TE-1112HA, TE-1111X, TE-1122HC, TE-1122HD, and TE-1121X) were previously replaced with Alloy 600 nozzles in 1989 by PCM 88091. In this PCM, the pressure boundary weld was moved from the ID of the hot leg pipe to the OD and Alloy 690 sleeves were installed in the penetration bore. These five RCS RTD nozzles with an external pressure boundary weld were removed and new Alloy 690 nozzles and thermowells were installed similar to the existing full nozzle design. Five of the RCS hot leg RTD nozzles (TE- 112HB, TE-1112HC, TE-1I12HD, TE-1122HA, and TE-1122HB) had not been previously replaced. These five RCS RTD nozzles with internal pressure boundary welds were replaced using the split nozzle design. For these five nozzles, the upper portion of the existing nozzle was removed and the existing internal weld was not disturbed. A new Alloy 690 outer half nozzle was installed with an external pressure boundary weld design and a new Alloy 690 thermowell was installed.

Unit 1 RCS hot leg instrument nozzle for PDT-1 121 D was replaced using the half nozzle design during the spring 2001 refueling outage (SLI-17) by PCM 01053.

Approval of a one cycle extension for the subject relief was requested to support the upcoming St. Lucie Unit 1 refueling outage (SLI-19) that is currently scheduled to begin on March 22, 2004 and the fall 2004 Unit 2 refueling outage (SL2-15). Please contact George Madden at 772-467-7155 if there are any questions about this submittal.

Very truly yours, William Jeffers Jr.

Vice PresidentL( XV St. Lucie Plant WJ/GRM