ML092380131

2009/08/21 PINGP Lr - L-PI-09-097 Supplemental Information Related to the PWR Vessel Internals Program

ML092380131
Person / Time
Site:	Prairie Island
Issue date:	08/21/2009
From:	- No Known Affiliation
To:	Division of License Renewal
References
Download: ML092380131 (8)

Text

PrairieIslandNPEm Resource From: Fox, Cheryl A. [Cheryl.Fox@xenuclear.com]

Sent: Friday, August 21, 2009 1:30 PM To: Plasse, Richard Cc: Davis, Marlys E.; Anderson, Lori

Subject:

L-PI-09-097 Supplemental Information Related to the PWR Vessel Internals Program Attachments: image001.jpg; image002.gif; 20090827 Supplemental Information Re Rx Vessel Internals Clarification.doc; 20090821 Supplemental Information PWR Vsl Int Pgm.pdf Rick: Attached is L-PI-09-097 - Supplemental Information Related to the PWR Vessel Internals Program

• • NOTE -my new e-mail address is - Cheryl.fox@xenuclear.com Cheryl Fox Project Support Lead - PINGP License Renewal and Steam Generator Replacement Projects 651-388-1121 x 5258 651-267-7207-Fax 1

Hearing Identifier: Prairie_Island_NonPublic Email Number: 1095 Mail Envelope Properties (7A9B2084CC9CEC45828E829CBF20D63802E5254F)

Subject:

L-PI-09-097 Supplemental Information Related to the PWR Vessel Internals Program Sent Date: 8/21/2009 1:29:37 PM Received Date: 8/21/2009 1:29:51 PM From: Fox, Cheryl A.

Created By: Cheryl.Fox@xenuclear.com Recipients:

"Davis, Marlys E." <Marlys.Davis@xenuclear.com>

Tracking Status: None "Anderson, Lori" <Lori.Anderson@xenuclear.com>

Tracking Status: None "Plasse, Richard" <Richard.Plasse@nrc.gov>

Tracking Status: None Post Office: enex02.ft.nmcco.net Files Size Date & Time MESSAGE 376 8/21/2009 1:29:51 PM image001.jpg 5113 image002.gif 1390 20090827 Supplemental Information Re Rx Vessel Internals Clarification.doc 164416 20090821 Supplemental Information PWR Vsl Int Pgm.pdf 1072753 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Page 1 of 1 file://c:\EMailCapture\Prairie_Island_NonPublic\1095\attch1.jpg 8/26/2009

Page 1 of 1 file://c:\EMailCapture\Prairie_Island_NonPublic\1095\attch2.gif 8/26/2009

August 21, 2009 L-PI-09-097 10 CFR 54 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 License Nos. DPR-42 and DPR-60 Supplemental Information Regarding Application for Renewed Operating Licenses By letter dated April 11, 2008, Northern States Power Company, a Minnesota Corporation, (NSPM) submitted an Application for Renewed Operating Licenses (LRA) for the Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2. In a letter dated May 12, 2009, NSPM updated the LRA to incorporate information regarding the new plant-specific PWR Vessel Internals Program. In a conference call on August 12, 2009, the NRC requested clarification of several items in that submittal. Enclosure 1 provides the requested clarifications.

If there are any questions or if additional information is needed, please contact Mr. Eugene Eckholt, License Renewal Project Manager.

Summary of Commitments This letter contains no new commitments or changes to existing commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on August 21, 2009.

/S/ Kevin P. Ryan for M. A. Schimmel Mark A. Schimmel Acting Site Vice President, Prairie Island Nuclear Generating Plant Units 1 and 2 Northern States Power Company - Minnesota Enclosure (1) cc:

Administrator, Region III, USNRC License Renewal Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC Prairie Island Indian Community ATTN: Phil Mahowald Minnesota Department of Commerce 1717 Wakonade Drive East

• Welch, Minnesota 55089-9642 Telephone: 651.388.1121

L-PI-09-097 Enclosure 1 Supplemental Information Related to the PWR Vessel Internals Program In letter L-PI-09-044 dated May 12, 2009, NSPM updated the LRA to incorporate information regarding the PINGP PWR Vessel Internals Program. In a conference call on August 12, 2009, the NRC requested clarification of several items in that submittal.

NSPM agreed to provide clarifying information which is provided below:

NSPM Clarification A Documentation of inspection results associated with the PWR Vessel Internals Program will be in accordance with approved inspection procedures. All necessary program implementing documents, including inspection procedures, will be developed in accordance with the NSPM Quality Assurance Program, which implements the requirements of 10 CFR Part 50, Appendix B.

NSPM Clarification B As stated in Enclosure 1 of letter L-PI-09-044 in the Scope of Program element, The scope does not include consumable items such as fuel assemblies, reactivity control assemblies, and nuclear instrumentation. Fuel assemblies are periodically replaced (i.e.,

short-lived), and, therefore, are not subject to aging management review. Reactivity control assemblies are active components, and, therefore, are not subject to aging management review. Nuclear instruments (i.e., incore neutron flux detectors) are active electrical components, and, therefore, are not subject to aging management review.

NSPM Clarification C As stated in Enclosure 1 of letter L-PI-09-044 in the Scope of Program element, The scope also does not include welded attachments to the reactor vessel. Welded attachments to the reactor vessel interior are subject to examination in accordance with the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Program.

The IWB, IWC and IWD Program conducts visual inspection of the accessible interior attachment welds per ASME Section XI, Table IWB-2500-1, Examination Category B-N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels.

NSPM Clarification D The PINGP PWR Vessel Internals Program is based on the inspection guidance provided in MRP-227, as approved by the NRC, and the ASME Section XI Inservice Inspection, Subsections IWB, IWC, and IWD Program. MRP-227 is based upon industry operating experience, research data, and vendor evaluations. The examination methods, coverage, and schedule prescribed in MRP-227 account for aging experience in both domestic and international reactor vessel internals. Industry operating experience related to the aging degradation of PWR vessel internals is described in the Operating Experience program element. Through participation in EPRI MRP activities, the PINGP PWR Vessel Internals Program will continue to evolve as additional inspection experience is gained.

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