ML14098A335
| ML14098A335 | |
| Person / Time | |
|---|---|
| Site: | Harris  (NPF-063) |
| Issue date: | 04/09/2014 |
| From: | Duke Energy Progress |
| To: | Andrew Hon Plant Licensing Branch II |
| Hon A DORL/LPL2-2 301-415-8480 | |
| References | |
| Download: ML14098A335 (12) | |
Text
GAIA Lead Test Assembly Project - Harris Nuclear Plant NRC Meeting - April 9, 2014
Agenda
Introductions
Duke Energy Paul Bailey, Nuclear Engineering John Caves, Regulatory Affairs Eric Geyer, Nuclear Engineering Colin Lancaster, Nuclear Engineering AREVA Scott DOrio, GAIA Design GAIA LTA program Licensing Perspectives Summary 2
GAIA LTA Program GAIA Lead Test Assemblies planned for Spring 2015 installation Program purpose is to obtain PIE data to support batch implementation GAIA design described in 2013 AREVA-NRC update (ML13163A406)
Lead Test Assemblies Eight LTAs in non-limiting locations Will be analyzed with NRC approved codes and methods AREVA will provide the NRC a generic mechanical design criteria evaluation summary consistent with EMF 92-116(P)(A) methodology 3
LFA Program - Summary GAIA is mechanically compatible with co-resident fuel, in-core components, fuel storage racks, fuel handling equipment, fuel inspection equipment and is similar in physical design to the initial core loading and the current HTP fuel design.
GAIA has in-core operating experience in Europe that has completed 18 months of operation and will continue to precede Harris.
Based on the operating experience and examinations of lead GAIA assemblies there are no outstanding concerns for the functionality and reliability of the GAIA fuel assemblies.
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Licensing Perspectives Harris has not implemented Improved Technical Specifications (NUREG-1431)
ITS specifically addresses use of LTAs Current Harris TS do not address use of LTAs NRC staff positions on use of LTAs considered ITS as baseline Generic Letter 90-02 (as supplemented) supported implementation of verbiage as a line item improvement, although no TSTF traveler was developed 5
Licensing Perspectives Current Harris TS Design Feature 5.3.1 Fuel Assemblies The core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4 or M5. Limited substitution of fuel rods by filler rods (consisting of Zircaloy-4 or M5 clad stainless steel or zirconium), or vacancies may be made in fuel assemblies if justified by a cycle specific evaluation. Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling, a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup.
Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum enrichment of 3.5 weight percent U 235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 5.0 weight percent U-235.
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Licensing Perspectives ITS Design Feature 4.2.1 Fuel Assemblies The reactor shall contain [157] fuel assemblies. Each assembly shall consist of a matrix of [Zircalloy or ZIRLO] fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
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Licensing Perspectives Proposed change to align with ITS would be a clarification, not a technical change, and not required to load LTAs Remove Reload fuel shall be similar in physical design Replace with Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
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Licensing Perspectives Remove detail beyond requirements of 50.36 and NUREG-1431 with each fuel assembly normally containing 264 fuel rods Should more than a total of 30 fuel rods or more than 10 fuel rods in any one assembly be replaced per refueling, a Special Report describing the number of rods replaced will be submitted to the Commission, pursuant to Specification 6.9.2, within 30 days after cycle startup Each fuel rod shall have a nominal active fuel length of 144 inches The initial core loading shall have a maximum enrichment of 3.5 weight percent U 235 Fuel material is enriched to 5.0% weight percent U-235 9
Licensing Perspectives Resulting Design Feature 5.3.1 Fuel Assemblies The reactor shall contain 157 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy-4 or M5 clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of Zircaloy-4 or M5 clad stainless steel or zirconium filler rods for fuel rods, or vacancies may be made in fuel assemblies if justified by a cycle specific evaluation. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
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Summary LTAs planned for loading in Spring 2015 Revision to Design Features TS for clarification, not required for LTA program AREVA will provide to the NRC a generic mechanical design criteria evaluation summary consistent with EMF 92-116(P)(A)
LTA implementation under 50.59 Anticipate LAR submittal this month, with 1 year approval requested No Regulatory Commitments in this meeting 11
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