ML092300028
| ML092300028 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/18/2009 |
| From: | Office of Nuclear Reactor Regulation |
| To: | Division of License Renewal |
| References | |
| Download: ML092300028 (3) | |
Text
1 PrairieIslandNPEm Resource From:
Medoff, James Sent:
Tuesday, August 18, 2009 7:26 AM To:
Plasse, Richard Cc:
Gene.Eckholt@xenuclear.com; Gan, Qi
Subject:
RE: Reactor Vessel Internals Rick:
Very good draft responses. This information will tie down the information OGC is seeking on the PWR Vessels Internals Program. I would have them submit them as written. I will cc Gene Eckholt at Xcel Nuclear and Qi Gan.
Jim Medoff Senior Mechanical Engineer NRR/DLR From: Plasse, Richard Sent: Sunday, August 16, 2009 8:56 AM To: Medoff, James
Subject:
FW: Reactor Vessel Internals From: Eckholt, Gene F. [1]
Sent: Friday, August 14, 2009 2:18 PM To: Plasse, Richard
Subject:
Reactor Vessel Internals Rick Here are preliminary responses.
- 1. Documentation of inspection results 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.
2.a. As stated 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 not subject to aging management review. Reactivity control assemblies are active components, and therefore not subject to aging management review. Nuclear instrumentation (i.e., incore neutron flux detectors) are active electrical components, and therefore not subject to aging management review.
2.b. As stated 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.
- 3. 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 both domestic and international reactor vessel internals aging experience.
2 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.
Gene Eckholt Project Manager License Renewal Project Prairie Island Nuclear Generating Plant Phone: 651-388-1121 ext. 4137
Hearing Identifier:
Prairie_Island_NonPublic Email Number:
1089 Mail Envelope Properties (James.Medoff@nrc.gov20090818072500)
Subject:
RE: Reactor Vessel Internals Sent Date:
8/18/2009 7:25:42 AM Received Date:
8/18/2009 7:25:00 AM From:
Medoff, James Created By:
James.Medoff@nrc.gov Recipients:
"Gene.Eckholt@xenuclear.com" <Gene.Eckholt@xenuclear.com>
Tracking Status: None "Gan, Qi" <Qi.Gan@nrc.gov>
Tracking Status: None "Plasse, Richard" <Richard.Plasse@nrc.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 2985 8/18/2009 7:25:00 AM Options Priority:
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