ML092380129

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PINGP Lr - Reactor Vessel Internals Program Clarifications
ML092380129
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 08/19/2009
From:
- No Known Affiliation
To:
Division of License Renewal
References
Download: ML092380129 (3)


Text

PrairieIslandNPEm Resource From: Eckholt, Gene F. [Gene.Eckholt@xenuclear.com]

Sent: Wednesday, August 19, 2009 4:13 PM To: Plasse, Richard

Subject:

Reactor Vessel Internals Program Clarifications Rick Here is the final version of the reactor internals program responses. We have made some editorial changes from the previous version, they do not affect the technical content. These will be formally transmitted to the NRC on Friday 8/21/09.

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.

1

Gene Eckholt Project Manager License Renewal Project Prairie Island Nuclear Generating Plant Phone: 651-388-1121 ext. 4137 2

Hearing Identifier: Prairie_Island_NonPublic Email Number: 1094 Mail Envelope Properties (7A9B2084CC9CEC45828E829CBF20D638033F6E8A)

Subject:

Reactor Vessel Internals Program Clarifications Sent Date: 8/19/2009 4:13:27 PM Received Date: 8/19/2009 4:28:29 PM From: Eckholt, Gene F.

Created By: Gene.Eckholt@xenuclear.com Recipients:

"Plasse, Richard" <Richard.Plasse@nrc.gov>

Tracking Status: None Post Office: enex02.ft.nmcco.net Files Size Date & Time MESSAGE 2816 8/19/2009 4:28:29 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: