ML20098E919
| ML20098E919 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/24/1984 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20098E920 | List: |
| References | |
| NUDOCS 8410020119 | |
| Download: ML20098E919 (2) | |
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Telephone (412) 393-6000
=. r-Shippmg, port, PA 15077-0004 September 24, 1984 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Cycle 5 Reload Safety Evaluation Report Gentlemen:
Enclosed are ten (10) copies of the Beaver Valley Power Station, Unit No.1 Cycle 5 Reload Safety Evaluation Report (RSER). This report presents an evaluation of the Cycle 5 design which demonstrates that the core reload will not adversely affect the safety of the plant.
Duquesne Light Company has performed a detailed review of the Cycle 5 RSER including a review of the core characteristics to detennine those parameters affecting all postulated accidents described in the UFSAR. The consequences of those incidents which could potentially be affected by the reload core characteristics were reanalyzed, and we have verified that the reanalysis were perfonned in accordance with the methodology described in WCAP-9272, " Westinghouse Reload Safety Evaluation Methodology". The affects of the reload on the design basis and postulated incidents analyzed in the UFSAR were accommodated within the conservatism of the initial assumptions and are bounded by the current limits.
No changes to the Technical Specifications are required as a result of the Cycle 5 reload core design or the RSER.
The RSER evaluates the reload core utilizing the Wet Annular Burnable Absorber (WABA) rods. The WABA burnable poison rods provide significantly enhanced nuclear characteristics and the design has been approved by the NRC SER incorporated into WCAP-10021-P-A Revision 1, " Westinghouse Wet Annular Burnable Absorber Evaluation Report".
The NRC approved dropped rod methodology used for the Cycle 4 design evaluation was also used in the Cycle 5 design evaluation and confinned that the DNB design basis is met for all dropped rod events initiated from full power. Therefore, as in Cycle 4, no restrictions on rod control, either manual rod control or restricted rod insertion limits when in automatic rod control above 90% power are required for Cycle 5 operation.
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Beaver Valley Power Station, Unit No.*1
- Docket No. 50-334, License No. DPR-66 Cycle 5 Reload Safety Evaluation Report Page 2 The reload core design will be verified by perfoming the standard Westinghouse reload core startup physics tests. The results of the follow-ing startup tests will be submitted in accordance with Technical Specifica-tion 6.9.1.3:
1.
Control rod drive tests and rod drop time measurements 2.
Critical boron concentration measurements 3.
Control rod bank worth measurement 4.
Moderator temperature coefficient measurement 5.
Startup power distribution measurements using the incore flux mapping system.
The Beaver Valley Onsite Sofety Committee (OSC) and the Duquesne Light Company Offsite Review Committee (0RC) have reviewed this RSER and determined that the Cycle 5 reload core design will not adversely affect the safety of the plant and does not involve an unreviewed safety question.
Very truly yours, J. J. Carey Vice President, Nuclear cc:
U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 Director, Safety Evaluation & Control Virginia Electric and Power Company P. O. Box 26666 One James River Plaza Richmond, VA 23261
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