ML17072A275

NRR E-mail Capture - Palisades Nuclear Plant - Final Request for Additional Information Regarding Relief Request No. RR 4-25

ML17072A275
Person / Time
Site:	Palisades
Issue date:	03/10/2017
From:	Jennivine Rankin Plant Licensing Branch III
To:	Erickson J, Miksa J Entergy Nuclear Operations
References
MF8886
Download: ML17072A275 (3)

Text

NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Friday, March 10, 2017 1:24 PM To: ERICKSON, JEFFREY S (JERICKS@entergy.com); MIKSA, JAMES P (jmiksa@entergy.com)

Subject:

Palisades Nuclear Plant - Final Request for Additional Information regarding Relief Request No. RR 4-25 (CAC No. MF8886)

Attachments: Final RAIs Palisades RR 4-25.docx Mr. Erickson and Mr. Miksa, By letter dated November 30, 2016 (Agencywide Documents Access and Management System Accession No. ML16335A032), Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted relief request number RR 4-25 to the U.S. Nuclear Regulatory Commission (NRC) for the fourth 10-year inservice inspection interval (ISI) at Palisades Nuclear Plant. In RR 4-25, Entergy requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 welds and components as listed in Table 1 of the enclosure. Entergy determined that conformance with the examination requirements of Section XI of the ASME Code for the welds and components is impractical. Title 10 of the Code of Federal Regulations, Part 50, Paragraph 50.55a(g)(5)(iii) requires the licensee to submit information to the NRC to support the determination of impracticality.

The NRC staff has reviewed the information provided and determined that additional information is required in order to complete its review. A draft request for additional information (RAI) was transmitted on March 9, 2017.

Entergy subsequently informed the NRC staff that the information requested by the NRC staff was understood and no additional clarification of the RAI was necessary. Mr. Miksa agreed to provide a response to this final RAI within 30 days from the date of this correspondence. If you wish to alter the date of your response, please contact me at (301) 415-1530.

Please treat this e-mail as the final transmittal of the RAIs.

Thanks, Jennie Jennie Rankin, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1

Hearing Identifier: NRR_PMDA Email Number: 3395 Mail Envelope Properties (927b9261540a4b29b0c0c4e20b3c77eb)

Subject:

Palisades Nuclear Plant - Final Request for Additional Information regarding Relief Request No. RR 4-25 (CAC No. MF8886)

Sent Date: 3/10/2017 1:23:59 PM Received Date: 3/10/2017 1:24:01 PM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:

"ERICKSON, JEFFREY S (JERICKS@entergy.com)" <JERICKS@entergy.com>

Tracking Status: None "MIKSA, JAMES P (jmiksa@entergy.com)" <jmiksa@entergy.com>

Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 1769 3/10/2017 1:24:01 PM Final RAIs Palisades RR 4-25.docx 39341 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST NUMBER RR 4-25 FOURTH TEN-YEAR INSERVICE INSPECTION INTERVAL PALISADES NUCLEAR PLANT DOCKET NUMBER 50-255 By letter dated November 30, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16335A032), Entergy Nuclear Operations, Inc. (Entergy, the licensee) submitted relief request number RR 4-25 to the U.S. Nuclear Regulatory Commission (NRC) for the fourth 10-year inservice inspection interval (ISI) at Palisades Nuclear Plant. In RR 4-25, the licensee requested relief from the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 welds and components as listed in Table 1 of the licensees enclosure. The licensee determined that conformance with the examination requirements of Section XI of the ASME Code for the welds and components is impractical. Title 10 of the Code of Federal Regulations, Part 50, Paragraph 50.55a(g)(5)(iii) requires the licensee to submit information to the NRC to support the determination of impracticality.

The NRC staff has reviewed the application and determined that additional information is needed for the staff to complete its review.

RAI-1

Table 1 of Attachment 1, Examination Limitation Details in the application states that two indications were recorded in RPV Circumferential Weld 10-112 (Examination Category B-A, Item No. B1.11).

Clarify whether the two indications were determined to be fabrication flaws or service-induced flaws. If they are fabrication flaws, state whether the two flaws were recorded in previous ISI intervals. If they were not recorded, please explain why they were not recorded.

If they are service-induced flaws, state whether the two flaws were recorded in previous ISI intervals. If they were not recorded, please explain why they were not recorded. In addition, please state whether the indications have grown, and discuss how the two indications were dispositioned including the plans for re-inspecting the indications.

The NRC staff requests this information to determine whether these two indications present a challenge to the structural integrity of RPV Circumferential Weld 10-112.