ML14217A011

NRR E-mail Capture - Request for Additional Information: Palisades Againg Management Program for Reactor Vessel Internals (ME9569)

ML14217A011
Person / Time
Site:	Palisades
Issue date:	08/01/2014
From:	Jennivine Rankin Plant Licensing Branch III
To:	Erickson J Entergy Nuclear Operations
References
ME9569
Download: ML14217A011 (6)

Text

NRR-PMDAPEm Resource From: Rankin, Jennivine Sent: Friday, August 01, 2014 9:19 AM To: ERICKSON, JEFFREY S (JERICKS@entergy.com); Hardy, Jeffery A (jhardy@entergy.com)

Subject:

Request for Additional Information: Palisades Againg Management Program for Reactor Vessel Internals (ME9569)

Attachments: RAI.docx Mr. Erickson and Mr. Hardy, By letter dated September 13, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12257A352), as supplemented by letters dated April 4, 2013, January 7, April 3, and July 1, 2014 (ADAMS Accession Nos. ML13094A414, ML14007A151, ML14097A376, and ML14183A014, respectively), Entergy Nuclear Operations, Inc.

(ENO) submitted the Revised Program Plan for Aging Management of Reactor Vessel Internals for U.S. Nuclear Regulatory Commission (NRC) review. The NRC staff has reviewed the information provided and determined that additional information is required in order to complete its review. This request for additional information can be found in the attached document. The subject of this RAI was discussed in a clarification call on July 29, 2014 with your organization.

Please provide a response to this RAI within 30 days from the date of this email. If circumstances result in the need to revise the requested response date, please contact me at 301.415.1530.

Thanks, Jennie Jennie Rankin, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1

Hearing Identifier: NRR_PMDA Email Number: 1470 Mail Envelope Properties (Jennivine.Rankin@nrc.gov20140801091800)

Subject:

Request for Additional Information: Palisades Againg Management Program for Reactor Vessel Internals (ME9569)

Sent Date: 8/1/2014 9:18:44 AM Received Date: 8/1/2014 9:18:00 AM From: Rankin, Jennivine Created By: Jennivine.Rankin@nrc.gov Recipients:

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

Tracking Status: None "Hardy, Jeffery A (jhardy@entergy.com)" <jhardy@entergy.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1225 8/1/2014 9:18:00 AM RAI.docx 509302 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION REGARDING AGING MANAGEMENT PROGRAM FOR REACTOR VESSEL INTERNALS AT PALISADES NUCLEAR PLANT ENTERGY NUCLEAR OPERATIONS, INC.

DOCKET NO. 50-255 RAI-4-1:

Background

In Table 2, C-E [Combustion Engineering] Plants Primary Components from MRP-227-A, of Palisades Nuclear Plants (PNP) Revised Program Plan for Aging Management of Reactor Vessel Internals (Reference 1), the component Core Support Barrel Assembly Lower Flange Weld, has a note stating Not Applicable to Palisades. In Table 3, C-E Plants Expansion Components from MRP-227, the component Core Support Barrel Assembly Lower Core Barrel Flange, has a note stating Not Applicable to Palisades. However, MRP-227-A Table 4-2, CE Plants Primary Components, lists the Core Support Barrel Assembly Lower Flange Weld, as applicable to All Plants, and MRP-227-A, Table 4-5, CE Plants Expansion Components, lists the Core Support Barrel Assembly Lower Core Barrel Flange, as applicable to All Plants.

This is an apparent error in MRP-227-A, in that it should have identified that the Core Support Barrel Assembly Lower Flange Weld, is not applicable to PNP.

The upper left corner of Figure 14 (Reference 1), shows an elevation cross section of the PNP core support barrel and has four circled areas corresponding to portions to be inspected (Figure A below). The caption states the following:

Primary: EVT-1 examination of core of upper flange weld and lower cylinder girth welds no later than 2 RFOs [refueling outages] from the beginning of the LR [license renewal]

period (ten year intervals)

Coverage: 100% of accessible surfaces of upper flange weld and lower cylinder girth welds Figure 8 of Reference 1 shows a typical CE core support barrel, while Figure 9 and 10 of Reference 1 show the PNP-specific design. The PNP-specific design appears to have no core support barrel lower flange, but it appears to have a weld (Figure B below) joining the very bottom of the core support bottom to the plate that forms the bottom of the lower core support structure (the corresponding MRP-191 component designation appears to be the Lower Support Structure - Bottom Plate, Reference 2).

Requested Information

1. Please confirm that the weld joining the very bottom of the core support barrel to the plate that forms the bottom of the lower core support structure (Figure B), is considered a Core Support Barrel Lower Girth Weld, at PNP and is subject to EVT-1 visual examination as a Primary inspection category component.

2. Please confirm that Entergy Nuclear Operations, Inc. understands there to be an error in MRP-227-A, Tables 4-2 and 4-5 in that both the Core Support Barrel Lower Flange Weld, and Core Support Barrel Lower Core Barrel Flange, should have been identified as not applicable to PNP.

References

1. Palisades Nuclear Plant, Revised Program Plan for Aging Management of Reactor Vessel Internals, dated September 13, 2012 (ADAMS Accession No. ML12257A352)

2. 1013234, "Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191)," dated November 30, 2006 (ADAMS Accession No. ML091910130)

Figure A - Excerpt from Figure 14 of Reference 1 Figure B - PNP Lower Core Support Structure - Oval shows presumed location of weld