ML15127A210

NRR E-mail Capture - LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding Relief Request I3R-14

ML15127A210
Person / Time
Site:	LaSalle
Issue date:	05/07/2015
From:	Blake Purnell Plant Licensing Branch III
To:	Simpson L Exelon Corp
References
TAC MF5654, TAC MF5655
Download: ML15127A210 (3)

Text

NRR-PMDAPEm Resource From: Purnell, Blake Sent: Thursday, May 07, 2015 9:13 AM To: Lisa Simpson (Lisa.Simpson@exeloncorp.com)

Cc: David Gullott (David.Gullott@exeloncorp.com); Tate, Travis

Subject:

LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding Relief Request I3R-14 (TAC Nos. MF5654 and MF5655)

Attachments: LaSalle RR I3R-14 RAI.docx Ms. Lisa Simpson:

On January 29, 2015, Exelon Generation Company, LLC (the licensee) submitted relief request (RR) I3R-14 for LaSalle County Station (LSCS), Units 1 and 2 (Agencywide Documents Access and Management System Accession No. ML15030A175). RR I3R-14 is intended to apply American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-702, Alternative Requirements for Boiling Water Reactor (BWR) Nozzle Inner Radius and Nozzle-to-Shell Welds, to reactor pressure vessel nozzles at LSCS.

The U.S. Nuclear Regulatory Commission staff has reviewed the RR and determined that it needs additional information to complete its review. The licensee is requested to respond to the attached request for additional information within 30 days of this email. If you have any questions about this request, contact me at (301) 415-1380.

Sincerely, Blake Purnell, Project Manager Plant Licensing Branch III-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Docket Nos. 50-373 and 50-374 1

Hearing Identifier: NRR_PMDA Email Number: 2046 Mail Envelope Properties (Blake.Purnell@nrc.gov20150507091300)

Subject:

LaSalle County Station, Units 1 and 2 - Request for Additional Information Regarding Relief Request I3R-14 (TAC Nos. MF5654 and MF5655)

Sent Date: 5/7/2015 9:13:12 AM Received Date: 5/7/2015 9:13:00 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:

"David Gullott (David.Gullott@exeloncorp.com)" <David.Gullott@exeloncorp.com>

Tracking Status: None "Tate, Travis" <Travis.Tate@nrc.gov>

Tracking Status: None "Lisa Simpson (Lisa.Simpson@exeloncorp.com)" <Lisa.Simpson@exeloncorp.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1174 5/7/2015 9:13:00 AM LaSalle RR I3R-14 RAI.docx 23806 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUESTS I3R-14 LASALLE COUNTY STATION, UNITS 1 AND 2 TAC NOS. MF5654 AND MF5655 On January 29, 2015, Exelon Generation Company, LLC (the licensee) submitted relief request (RR) I3R-14 for LaSalle County Station (LSCS), Units 1 and 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15030A175).RR I3R-14 is intended to apply American Society of Mechanical Engineers(ASME) Boiler and Pressure Vessel Code (ASME Code), Code Case N-702, Alternative Requirements for Boiling Water Reactor (BWR)

Nozzle Inner Radius and Nozzle-to-Shell Welds, to reactor pressure vessel nozzles at LSCS.

The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the RR and determined that it needs additional information to complete its review.

Background

By letter dated April 19, 2013 (ADAMS Accession No. ML13071A240), the NRC staff approved the Boiling Water Reactor Vessel Internals Project (BWRVIP) topical report, BWRVIP-241, Fracture Mechanics Evaluation for the Boiling Water Reactor Nozzle-to-Vessel Shell Welds and Nozzle Blend Radii, submitted on April 26, 2011 (ADAMS Accession No. ML11119A041). The staffs safety evaluation (SE) states that BWRVIP-241 may be referenced as the technical basis for the use of ASME Code Case N-702 as an alternative. The staffs SE further states that the licensee should address the conditions and limitations specified in the SE to demonstrate that BWRVIP-241 is applicable to the plant.

The RR states that the recirculating outlet nozzles for LSCS Unit 2 did not meet Condition 4 of the SE. Section 6, Summary and Conclusions, of BWRVIP-241 states:

For plants having recirculation outlet nozzles with Condition 4 greater than 1.15

[i.e., does not meet Condition 4 of SE], a plant specific analysis following the approach described in this report may be able to justify values greater than 1.15.

The analysis would need to be submitted to the NRC as part of a relief request to implement Code Case N-702 for the subject nozzles.

The RR does not provide an analysis to justify a value for Condition 4 greater than 1.15, but instead provides only the summary and results of the analysis.The RR indicates that the analysis is contained in Design Analysis L-003976, Probability of Failure Analysis for Reactor Pressure Vessel Nozzles.

Request Provide a plant-specific analysis for the recirculating outlet nozzles for LSCS Unit 2 to justify a value for Condition 4 greater than 1.15.