ML14234A275

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NRR E-mail Capture - Request for Additional Information Regarding St. Lucie Unit 2 Relief Request 16 for 3rd Interval (MF4340)
ML14234A275
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 08/21/2014
From: Farideh Saba
Division of Operating Reactor Licensing
To: Frehafer K
Florida Power & Light Co
References
MF4340
Download: ML14234A275 (3)


Text

NRR-PMDAPEm Resource From: Saba, Farideh Sent: Thursday, August 21, 2014 5:22 PM To: ken.frehafer@fpl.com Cc: Lewis, Atanya (Atanya.Lewis@fpl.com); eric.katzman@fpl.com; Render, Diane

Subject:

Request for additional information regarding St. Lucie Unit 2 Relief Request 16 for 3rd Interval (MF4340)

Attachments: MF4340_ SL-2 RR-16 RAI.docx Importance: High

Ken, By letter dated June 30, 2014 (Accession No. ML14203A007), Florida Power & Light Company (the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for examination coverage of welds at the St. Lucie, Unit 2. The U.S. Nuclear Regulatory Commission (NRC) determined that additional information needed to complete its review.

The NRC staff request for additional information (RAI) is attached. As discussed in the clarification call on August 21, 2014, you agreed to respond to the RAI by September 26, 2014.

Thank you, Farideh Farideh E. Saba, P.E.

Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8G9A Farideh.Saba@NRC.GOV 1

Hearing Identifier: NRR_PMDA Email Number: 1520 Mail Envelope Properties (Farideh.Saba@nrc.gov20140821172200)

Subject:

Request for additional information regarding St. Lucie Unit 2 Relief Request 16 for 3rd Interval (MF4340)

Sent Date: 8/21/2014 5:22:19 PM Received Date: 8/21/2014 5:22:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients:

"Lewis, Atanya (Atanya.Lewis@fpl.com)" <Atanya.Lewis@fpl.com>

Tracking Status: None "eric.katzman@fpl.com" <eric.katzman@fpl.com>

Tracking Status: None "Render, Diane" <Diane.Render@nrc.gov>

Tracking Status: None "ken.frehafer@fpl.com" <ken.frehafer@fpl.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 816 8/21/2014 5:22:00 PM MF4340_ SL-2 RR-16 RAI.docx 26586 Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION THIRD TEN-YEAR INTERVAL RELIEF REQUEST NO. 16 FLORIDA POWER & LIGHT ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 2 DOCKET NO. 50-389

RAI 1

For each weld in Relief Request 16: (a) provide the corresponding piping system (e.g., reactor coolant system and chemical volume and control system); and (b) discuss whether the licensee identified any indication(s) during preoperational inspection (i.e., radiographic testing or surface examination(s), or both) on the volume not covered by UT of the affected welds.

RAI 2

On page 3 of the relief request, in the Section, Basis, the licensee stated, While the coverage is not included in the Table, the techniques employed for the single sided examinations provided for a best effort examination. Although the licensee noted that its best effort examinations (i.e.,

examining the far side of the weld in a single-sided examination by the refracted longitudinal waves) were not included in the Table in the attachment to the relief request and were not credited, please discuss whether the licensees best effort examinations covered the weld root and the heat affected zone of the base material near the inside diameter surface of the joint typically susceptible to higher stress and degradation.

RAI 3

Discuss whether there has been any plant-specific, fleet, or industry operating experience regarding potential degradation of the subject welds caused by known degradation mechanisms (e.g., fatigue and/or stress corrosion cracking) that would lead to leakage. If yes, discuss whether any compensatory measures have been taken.

RAI 4

Discuss leakage detection capabilities at the plant, or any measures taken, to monitor and identify leakage during operation in an unlikely event of a through-wall leak in the welds under consideration.

RAI 5

The licensee stated that weld SI-409-FW-2003 was installed in 2011. If this weld was replaced as a result of degradation, discuss in detail the root cause of the degradation and extent-of-condition.

Enclosure