05000373/FIN-2016001-02: Difference between revisions
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| identified by = NRC | | identified by = NRC | ||
| Inspection procedure = IP 71111.18 | | Inspection procedure = IP 71111.18 | ||
| Inspector = B Dickson, D Chyu, G Hansen, J Cassidy, J Robbins, R Ruiz, R Zuffab, | | Inspector = B Dickson, D Chyu, G Hansen, J Cassidy, J Robbins, R Ruiz, R Zuffab, Dicksonc Hunt, G Roach, J Robbins, R Ruiz, R Zuffa, T Bilik, T Go | ||
| CCA = N/A for ROP | | CCA = N/A for ROP | ||
| INPO aspect = | | INPO aspect = | ||
| description = (Opened) Unresolved Item 05000373; 05000374/201600102: Partial Length Rods Exceeded Burnup Limit in Design Basis Method of Analysis Introduction: The inspectors identified an URI related to the licensees use of partial length fuel rods beyond the burnup limit specified in their design basis method of analysis. The inspectors could not resolve the issue of concern during the inspection period due to the need for additional information. Description: In action request (AR) 01647125, Exelon-corporate identified a concern with the potential excessive exposure in partial length rods for LaSalle Unit 1 Cycle 16. This issue also affects the core design of the current Unit 2 cycle. Subsequently, AR 02537519 was written to document the condition as it relates to the Regulatory Guide (RG) 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, July 2000. Footnote 11 of the RG, provides an applicability limitation of 62,000 megawatt days per metric ton of uranium for non-loss-of-coolant accident gap release fractions specified in Table 3 of the RG. This RG is the licensees NRC-approved method of analysis for alternate source term as described in the LaSalle UFSAR, and is therefore a part of the licensees design and licensing basis. With this proposed change to the application of RG 1.183, the licensee performed a 50.59 evaluation to review the potential impact of partial length rods operating above 62,000 megawatt days per metric ton of uranium burnup to determine if prior NRC approval was necessary to implement the change. The inspectors have reviewed the licensees 50.59 evaluation, FCP 397411, Revision 1, and calculation, L003067, Revision 2C, and have identified an issue of concern. Specifically, the licensee concluded that prior NRC review and approval were not needed to operate its fuel in a manner that deviated from the limitations delineated within the NRC-approved methodology of RG 1.183 in their current licensing basis. The inspectors are opening this URI because more information/guidance is needed from the NRC Headquarters Office of Nuclear Reactor Regulation to determine if this issue of concern represents a violation of regulatory requirements. (URI 05000373; 05000374/201600102: Partial Length Rods Exceeded Burnup Limit in Design Basis Method of Analysis). | | description = (Opened) Unresolved Item 05000373; 05000374/201600102: Partial Length Rods Exceeded Burnup Limit in Design Basis Method of Analysis Introduction: The inspectors identified an URI related to the licensees use of partial length fuel rods beyond the burnup limit specified in their design basis method of analysis. The inspectors could not resolve the issue of concern during the inspection period due to the need for additional information. Description: In action request (AR) 01647125, Exelon-corporate identified a concern with the potential excessive exposure in partial length rods for LaSalle Unit 1 Cycle 16. This issue also affects the core design of the current Unit 2 cycle. Subsequently, AR 02537519 was written to document the condition as it relates to the Regulatory Guide (RG) 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, July 2000. Footnote 11 of the RG, provides an applicability limitation of 62,000 megawatt days per metric ton of uranium for non-loss-of-coolant accident gap release fractions specified in Table 3 of the RG. This RG is the licensees NRC-approved method of analysis for alternate source term as described in the LaSalle UFSAR, and is therefore a part of the licensees design and licensing basis. With this proposed change to the application of RG 1.183, the licensee performed a 50.59 evaluation to review the potential impact of partial length rods operating above 62,000 megawatt days per metric ton of uranium burnup to determine if prior NRC approval was necessary to implement the change. The inspectors have reviewed the licensees 50.59 evaluation, FCP 397411, Revision 1, and calculation, L003067, Revision 2C, and have identified an issue of concern. Specifically, the licensee concluded that prior NRC review and approval were not needed to operate its fuel in a manner that deviated from the limitations delineated within the NRC-approved methodology of RG 1.183 in their current licensing basis. The inspectors are opening this URI because more information/guidance is needed from the NRC Headquarters Office of Nuclear Reactor Regulation to determine if this issue of concern represents a violation of regulatory requirements. (URI 05000373; 05000374/201600102: Partial Length Rods Exceeded Burnup Limit in Design Basis Method of Analysis). | ||
}} | }} | ||
Latest revision as of 19:54, 20 February 2018
| Site: | LaSalle  |
|---|---|
| Report | IR 05000373/2016001 Section 1R18 |
| Date counted | Mar 31, 2016 (2016Q1) |
| Type: | URI: |
| cornerstone | Mitigating Systems |
| Identified by: | NRC identified |
| Inspection Procedure: | IP 71111.18 |
| Inspectors (proximate) | B Dickson D Chyu G Hansen J Cassidy J Robbins R Ruiz R Zuffab Dicksonc Hunt G Roach J Robbins R Ruiz R Zuffa T Bilik T Go |
| INPO aspect | |
| ' | |