ML20059D376
| ML20059D376 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/24/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9009070018 | |
| Download: ML20059D376 (2) | |
Text
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Valley Nwer Staten Shwngport. PA 150774)004 t
O.N5?"w.a su a m su August 2%, 1990 U. S. Nucl?ar Regulatory Ccamission Attn:
Document Control Desk Washington, DC 20555 Gentlemen:
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Cycle 3 Reload Beaver Valley Power Station, Unit No. 2 will complete the second cycle of operation on September 4, 1990 with an expected burnup of 13060 MWD /MTU.
This letter describes the Cycle 3 reload design, documents our review in accordance with 10 CFR 50.59, and provides our determination that no technical specification changes or unreviewed safety questions are involved.
The. Cycle 3
core configuration is arranged in a low leakage loading pattern and involves replacing. forty-nine (49) Region 2 and twenty (20)
Region 3 fuel assemblies with twenty (20) Region 5A-fuel assemblies enriched to 3.6 w/o, sixteen (16)
Region 5B fuel assemblies enriched to 3.8 w/o and thirty-two (32) Region 5C' fuel assemblies enriched to 4.2 w/o.
A Region 2 fuel assembly discharged at the end' of Cycle 1
will be. reinserted -as the center fuel assembly.
The mechanical design of the sixty-eight (68) new fuel assemblies is the same as the Region 4 fuel assemblies except that the Region 5 fuel. assemblies incorporate the extended burnup feature of the Fuel Assembly Camponent Update Program.
In addition, the Integral Fuel Burnable Absorbers (IFBA) for Region 5 and subsequent regions may contain enriched boron. ' Fuel rod design evaluations for the Cycle 3 fuel including the extended burnup design were performed using the NRC approved methodology to demonstrate ~that all of the fuel rod design bases are satisfied.
Duquesne Light Company has performed a detailed review of the Cycle 3-reload core design including a
review of' the core-characteristics to determine those parameters.
affecting the postulated accidents described in the UFSAR.
The consequences of those. incidents described in the UFSAR which could potentially be affected by 'the reload core characteristics were reanalyzed, and we have verified, that-the reanalyses were performed in accordance with the NRC approved methodology described in WCAP-9273-A " Westinghouse Reload-Safety Evaluation Methodology".
The effects of the reload on the design basis.and postulated incidents analyzed in the UFSAR were accommodated within the conservation of the initial assumptions.-
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- Be$vorValloyPowarStation,UnitNo.
2 Do'cket No. 50-412, License No. NPF-73 Cycle 3 Reload Page 2 No technical specification changes are required as a result of the cycle 3 reload design.
l The NRC appi;oved dropped
. rod methodology (WCAP-10298-A (Non-Proprietary),
June 1983) was used for Cycle 3 design evaluation l
and confirmed that the.DNB design basis is met for all dropped rod events initiated from fu'l power.
l The reload core design will be verified-by performing the standard Westinghouse reload core startup physics tests.
The results of the following startup tests will be submitted in accordance with Technical Specification 6.9.1.3.
- 1. Control rod drive tests and rod drop time measurements.
- 2. Critical boron concentration measurements.
- 3. Control rod bank worth measurements.
4.
Moderator temperature coefficient measurements.
- 5. Startup power distribution ~ measurements using the incore flux mapping system.
Th9 Beaver Valley Onsite Safety Committee (OSC) and the Duquesne Light Company Offsite Review Committee (ORC) has reviewed the Cycle 3 reload safety evaluation and determined that this reload core design will not adversely affect the safety of the plant and does not involve an unreviewed safety question.
Sincerely,
][J.
D. Sieber Vice President 8
Nuclear Group 4
cc:
Mr. J. Beall, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. A.-DeAgazio, Project Manacer Mr. R. Saunders (VEPCO)
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