ML15114A383

Request for Additional Information Regarding the Spring 2014 Steam Generator Tube Inspections

ML15114A383
Person / Time
Site:	Saint Lucie
Issue date:	05/11/2015
From:	Farideh Saba Plant Licensing Branch II
To:	Nazar M Florida Power & Light Co, Nextera Energy
Saba F DORL/LPL2-2 301-415-1447
References
TAC MF4847
Download: ML15114A383 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 11, 2015 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P. 0. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE SPRING 2014 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF4847)

Dear Mr. Nazar:

By letter dated September 18, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14279A237), Florida Power and Light Company (FPL, the licensee) submitted "St. Lucie Unit 2 Steam Generator Inspection Report for SL2-21 [Refueling Outage 21 )"summarizing the results of the spring 2014 refueling steam generator tube inspections performed at St. Lucie Plant, Unit No. 2. These inspections were conducted from March 17 to March 23, 2014. The licensee provided this report to meet the requirements of St. Lucie, Unit 2 Technical Specification 6.9.1.12, "Steam Generator Tube Inspection Report."

The U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call held with the licensee on March 20, 2014, in a letter dated August 8, 2014 (ADAMS Accession No. ML14189A090). The licensee responded to the NRC staff first round of request for additional information (RAI) by letter dated March 23, 2015 (ADAMS Accession No. ML15091A306).

The NRC staff has reviewed the information the licensee provided and determined that additional information is needed to complete the review. The NRC staff's draft second round RAI was sent to FPL staff by e-mail dated April 7, 2015. The NRC staff and FPL staff discussed the draft RAI during a clarification conference call on April 21, 2015. The enclosure to this letter contains the NRC staff's modified and finalized second RAI. This request was discussed with Mr. William Cross, and it was agreed that a response would be provided by June 23, 2015.

M. Nazar If you have any questions, please contact me at (301) 415-1447 or farideh.saba@nrc.gov.

Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION 1 REGARDING THE SPRING 2014 STEAM GENERATOR TUBE INSPECTIONS FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT. UNIT NO. 2 DOCKET NO. 50-389 By letter dated September 18, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14279A237), Florida Power and Light Company (FPL, the licensee) submitted "St. Lucie Unit 2 Steam Generator Inspection Report for SL2-21 [Refueling Outage 21 ]" summarizing the results of the spring 2014 refueling steam generator tube inspections performed at St. Lucie Plant, Unit No. 2. These inspections were conducted from March 17 to March 23, 2014. The licensee provided this report to meet the requirements of St. Lucie, Unit 2 Technical Specification 6.9.1.12, "Steam Generator Tube Inspection Report."

The U.S. Nuclear Regulatory Commission (NRC) staff summarized a conference call held with the licensee on March 20, 2014, in a letter dated August 8, 2014 (ADAMS Accession No. ML14189A090). The licensee responded to the NRC staff first round of request for additional information (RAI) by letter dated March 23, 2015 (ADAMS Accession No. ML15091A306).

The NRC staff has reviewed the information the licensee provided and determined that the following additional information is needed to complete the review.

RAl-8 The Florida Power and Light Company (FPL), in its response to request for additional information (RAl)-3, by letter dated March 23, 2015, indicates that no degradation related to Nuclear Safety Advisory Letter 12-01 was detected, which could imply that some corrosion degradation was detected. Confirm that no corrosion related degradation was found in the channel head.

RAl-9 FPL, in its response to RAl-4, by letter dated March 23, 2015, indicates that the analysis performed for the loose parts has been evaluated within the corrective action program, but no results were provided. Confirm that the analysis supported a full cycle of operation.

RAl-10 Clarify the difference between U-bend apex (AV4/5) wear, AVB [anti-vibration bar]-transition tube wear, V-shaped support pad wear, and V-shaped support bar wear. For example, does U-bend apex (AV4/5) wear mean wear at the apex on the extrados of the tube as a result of the tube interacting with the bottom edge of the AVB? Does A VB-transition tube wear mean wear at the apex on the flank of the tube as a result of the tube interacting with side of an AVB? Does V-shaped support pad wear mean wear as a result of the tube interacting with the support pad "sitting" 1

Started from RAl-8 as a continuation to the previously asked RAls.

Enclosure

on that tube, whereas V-shaped support bar wear is wear on a tube from the tube interacting with a neighboring tube's V-shaped support bar?

RAl-11 FPL, in its response to RAl-6 by letter dated March 23, 2015, indicates that the tube is supported by the V-shaped support pad. Clarify whether the tube is supported by the V-shaped support pad or whether the V-shaped support pad supports the U-bend supports (by "sitting/resting" on the tube).

RAl-12 The U.S. Nuclear Regulatory Commission staff noticed that the number of indications reported in FPL's response to RAl-5, by letter dated March 23, 2105, is slightly different than what was provided during a conference call on March 20, 2014 (refer to summary of conference call dated August 8, 2014, (ADAMS Accession No. ML14189A090)). Confirm that the values in response to RAl-5 are correct. Is the difference in the number of indications/tubes due to various factors such as completing the inspection (including confirming the nature/presence of the indication with a rotating or array probe), performing quality assurance checks, and possibly reclassifying some of the March 2014 indications as other types of wear (V-shaped support pad/bar wear, etc.)? Also, confirm whether there were 16 indications in 16 tubes attributed to U-bend apex wear in Steam Generator (SG) A (or whether the 16 indications were in 15 tubes since your September 18, 2014, report implies that the 16 indications were in 15 tubes rather than 16 tubes in SG A).

ML15114A383 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LAiT NRR/DORL/LPL2-2/LA NAME FSaba LRonewicz BClayton DATE 4/28/15 4/28/15 4/28/15 OFFICE NRR/DE/ESGB/BC NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME GKulesa SHelton FSaba DATE 5/1/15 5/11/15 5/11/15