ML20207H816
| ML20207H816 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/18/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Tam P Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8607250104 | |
| Download: ML20207H816 (2) | |
Text
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'Af Telephone (412) 393-6000 Nuclear Group
[0;,8Q,*
JU1Y 10' 1986 ort, PA 15077-0004 irector of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission f
Attn:
Mr. Peter S. Tam, Project Manager Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail Stop 340 -
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Reconstituted Fuel Assembly Evaluation Gentlemen:
This letter provides notification that an evaluation has been performed to determine the impact of including a reconstituted fuel assembly in the Beaver Valley Unit No. 1 Cycle 6 reload core.
The Cycle 6
Reload Safety Evaluation Report (RSER) and Radial Peaking Factor Limit Report (RPFLR) were provided to the NRC by separate letters dated May 2,
1986.
A proposed amendment to technical specification Design Feature Section 5.3.1 has been submitted to the NRC by letter dated July 11, 1986 which would allow the use of a reconstituted fuel assembly for Cycle 6.
During the fifth refueling outage an inspection of the fuel assemblies confirmed that baffle jetting damage had occurred in fuel assembly E-37 in core location D-13 during Cycle 5.
A modification was then made to fuel assembly G-15 so that it could be located in core location D-13 during Cycle 6.
The fuel assembly modification included upending the fuel assembly, removal of the bottom nozzle, substitution of 7 stainless steel rods for fuel rods and reattachment of a replacement bottom nozzle.
The dummy rods would then reduce the probability of baffle jetting damage to the fuel rods in the assembly.
The reconstituted fuel assembly was then inspected and accepted for insertion in the core.
A safety evaluation of the modification to fuel assembly G-15 has been performed and it has been verified that the results and conclusions of the Cycle 6 RSER are still valid.
This evaluation was accomplished utilizing the methodology described in WCAP-9272,
" Westinghouse Reload Safety Evaluation Methodology".
In addition, it has been confirmed that there is no change to the Cycle 6 RPFLR due to the fuel assembly modifications, therefore, the RPFLR is still applicable for Cycle 6.
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B3 aver Valley Power Station, Unit No. 1 Dockat No. 50-334, Licen:o No. DPR-66 Reconstituted Fuel Assembly Evaluation Page 2 The Onsite Safety Committee (CSC) and Offsite Review Committee (ORC) have reviewed these conclusions and determined that the Cycle 6 reload core
- design, including the reconstituted fuel assembly, will not adversely affect the safety of the plant and does not involve an unreviewed safety question.
Very truly yours, J. Cr V
e President, Nuclear cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 l
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