L-08-154, Report of Facility Changes, Tests and Experiments
| ML082260308 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/11/2008 |
| From: | Sena P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-08-154 | |
| Download: ML082260308 (2) | |
Text
FENOC FrstEne Nuclea Opetngotpny Peter P. Sena III Site Vice President 724-682-5234 FAX: 724-643-8069 August 11, 2008 L-08-154 10 CFR 50.59(d)(2)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 ReDort of Facility Chanaes. Tests and ExDeriments In accordance with 10 CFR 50.59(d)(2), the Report of Facility Changes, Tests, and Experiments for the Beaver Valley Power Station Unit No. 1 is provided as. The report covers the period of April 20, 2006, through October 24, 2007.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -
FENOC Fleet. Licensing, at (330) 761-6071.
Sincerely, Peter P. Sena III
Attachment:
Report of Facility Changes, Tests and Experiments c:
Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
IJE47 L-08-154 Report of Facility Changes, Tests and Experiments Page.1 of 1 Change Title Implementation of Reduced Atmospheric Steam Dump Valve Capacity Change The Beaver Valley Power Station Unit No. 1 Steam Generator Tube Rupture (SGTR) analysis was updated to address~changes as a result of the Extended Power Uprate (EPU) analyses. These EPU analyses used atmospheric steam dump and residual heat release valve capacities without accounting for the impact of the valve inlet and outlet piping. The following impacts were evaluated:
Main Steam Atmospheric Dump valve interface criteria Steam generator margin to overfill Dose (increase due to extended cooldown times to residual heat removal system entry conditions at 3500F)
The evaluation of the above impacts concluded that the BV1 SGTR analysis could be updated for implementation of EPU without submittal of a license amendment request.
Change Title Containment Sump Strainer Change This change replaced the existing containment sump screens with a new containment sump strainer to address new regulatory requirements as a result of NRC Generic Letter 04-02, dated September 13, 2004, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors". It analyzed the use of a common strainer to provide protection for both trains of Recirculation Spray and Low Head Safety Injection systems and the inability of the wide range level transmitters to monitor the containment water level from the bottom of containment for a short period of time post accident. The evaluation concluded that this design is acceptable without submittal of a license amendment request.