ML12198A050

E-mail Point Beach Nuclear Plant Units 1 and 2 - Draft Request for Additional Information Re Reactor Vessel Internals Inspection Plan (TAC Nos. ME8235 and ME8236)

ML12198A050
Person / Time
Site:	Point Beach
Issue date:	07/10/2012
From:	Beltz T A Plant Licensing Branch III
To:	Hennessy W J Point Beach
Beltz T A
References
TAC ME8235, TAC ME8236
Download: ML12198A050 (2)

Text

file:///Cl/...20re%20%20Reactor%20Vessel%20Internals%20Inspection%20Plan%20(TAC%20Nos.%20ME8235%20and%20ME8236).htm[7/16/2012 8:53:14 AM]From: Beltz, TerrySent: Tuesday, July 10, 2012 8:56 AMTo: 'Hennessy, William'Cc: 'Costedio, James'; Purtscher, Patrick; Frankl, Istvan

Subject:

Point Beach Nuclear Plant, Units 1 and 2 - Draft Request for Additional Information re: ReactorVessel Internals Inspection Plan (TAC Nos. ME8235 and ME8236)

Dear Mr. Hennessy:

By letter dated December 19, 2011, NextEra Energy Point Beach, LLC (NextEra, the licensee), submitted aninspection plan for the reactor vessel internals components at the Point Beach Nuclear Plant (PBNP), Units 1 and 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113540301). The U.S.Nuclear Regulatory Commission (NRC) staff has reviewed the inspection plan and determined that additional information is needed to complete its review.

The NRC staff provided NextEra requests for additional information (RAIs) in an e-mail dated June 7, 2012 (ADAMS Accession No. ML12159A113). On July 5, 2012, the NRC staff participated in a conference call todiscuss the RAIs and to provide any additional clarification. During the conference call, it was identified that anadditional RAI would be required. The additional RAI is provided below:

RAI-7

MRP-227-A, Table 3-3, indicates that control rod guide tube support pins (commonly referred to as split pins), Alloy X-750, are classified under the "Existing Inspection Program." That would suggest that they are ASME Section XI, Examination Category B-N-3 components. However, the split pinsare NOT included in the existing inspection program Table 4-9 in MRP-227-A or Attachment D in the PBNP inspection plan.

MRP-227-A, Section 4.4.3, states that the performance of the split pins should follow the supplier recommendations. However, the guideline included in Section 3.2.5.3 of the staff's safety evaluationfor the MRP-227-A report is more specific and summarized below.

Westinghouse guide tube support pins are made from either 316 stainless steel or Alloy X750.

There have been issues with cracking of the original Alloy X750 pins that were originally discovered during the ASME Section XI B-N-3 inspections. Many licensees have replaced them with type 316stainless steel materials. Licensees shall evaluate the adequacy of their plant-specific existingprogram and ensure that the aging degradation is adequately managed during the extended period of operation regardless of the material used for the guide tube support pins (split pins). Therefore, the NRC staff recommends that the evaluation consider the need to replace the Alloy X750 support pins (split pins), if applicable, or inspect the replacement type 316 stainless steel support pins (split pins) to ensure that cracking has been mitigated and that aging degradation due to any of the potential mechanisms is adequately monitored during the extended period of operation.

In the December 19, 2011, submittal, NextEra stated that the split pins were replaced with more SCC resistant 316 stainless steel material. The licensee did not indicate that it will inspect these pins during the license renewal period. Therefore, the NRC staff requests that the NextEra provide anexplanation for not performing routine ASME Code,Section XI, inspections on the 316 stainless steel split pins.

You may accept this e-mail as the formal RAI. The current RAI response date is July 20, 2012, for the six RAIsprovided to NextEra on June 7, 2012. Please don't hesitate to contact me to discuss this additional RAI and the file:///Cl/...20re%20%20Reactor%20Vessel%20Internals%20Inspection%20Plan%20(TAC%20Nos.%20ME8235%20and%20ME8236).htm[7/16/2012 8:53:14 AM]response date. If you desire a conference call, please let me know. Sincerely, Terry A. Beltz, Senior Project ManagerDivision of Operating Reactor LicensingOffice of Nuclear Reactor Regulation(301) 415-3049 Terry.Beltz@nrc.gov