L-07-080, Report of Facility Changes, Tests and Experiments for Period 04/12/2005 - 11/12/2006

Report of Facility Changes, Tests and Experiments for Period 04/12/2005 - 11/12/2006

ML072320067
Person / Time
Site:	Beaver Valley
Issue date:	08/15/2007
From:	Sena P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-07-080
Download: ML072320067 (4)

Text

'FENOC F,.stE.rgyNuerOpering 1.0- y Peter P. Sena III 724-682-5234 Site Vice President Fay: 724-643-8069 August 15, 2007 L-07-080 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Report of Facility Changes, Tests and Experiments 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. 2 is provided as . The report covers the period of April 12, 2005, through November 12, 2006.

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:

Beaver Valley Power Station Unit 2, Report of Facility Changes, Tests, and Experiments for the period April 12, 2005, through November 12, 2006.

Beaver Valley Power Station Unit 2 Report of Facility Changes., Tests and Experiments L-07-080 Page 2 c: Ms. N. S. Morgan, NRR Project Manager Mr. D. L. Werkheiser, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

Beaver Valley Power Station Unit 2 Attachment 1 Facility Changes, Tests, and Experiments April 12, 2005 - November 12, 2006 Page 1 of 2 Change Title Elimination of Post-DBA Hydrogen Control System Requirements / Abandon-In-Place BV2 Hydrogen Recombiners Change The change removes references to the post-Design Base Accident (DBA) hydrogen recombiners and the associated design bases from the Beaver Valley Power Station Unit 2 (BV2) UFSAR. The UFSAR-described design function of the hydrogen recombiners was to maintain the hydrogen concentration below the 4 percent lower flammability limit, following a Loss of Cooling Accident. This change is a result of the revised 10 CFR 50.44 rule that eliminated the requirement for the system and Beaver Valley Power Station Unit 2 Technical Specification Amendment 142 that deleted the associated technical specifications.

Change Title Safety Analysis of the Radiological Consequences of a Waste Gas System Rupture DBA at BVPS Unit 2, Control Room, EAB and LPZ Doses Change Gaseous Waste System (GWS) rupture radiological calculations were revised to incorporate changes as a result of the Extended Power Uprate (EPU). As detailed in letter L-05-024, dated 12/30/2005, application of EPU conditions to the gaseous waste system rupture accident was evaluated under this 10 CFR 50.59 evaluation. In the GWS decay tank scenario the Control Room whole body Effective Dose Equivalent (EDE) and skin doses increased. In the GWS line break scenario, Control Room whole body EDE and skin doses increased as did the Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) whole body EDE doses. All of the dose increases were less than 10% of the difference between the current licensing basis values and the 10 CFR 100 or GDC 19 limits.

Beaver Valley Power Station Unit 2 Attachment 1 Facility Changes, Tests, and Experiments April 12, 2005 - November 12, 2006 Page 2 of 2 Change Title Install Temporary Unit 2 Plant Computer System Change A minimum scoped temporary computer system was installed from August 22, 2006 to October 5, 2006 to support plant operations while the existing BV2 Plant Computer and Emergency Response Facility Computer systems were replaced. A temporary modification allowed the use of the temporary computer system which did not provide all of the plant monitoring capabilities as stated in the UFSAR design basis descriptions.

This evaluation for the temporary modification demonstrated that the alternative methods for monitoring plant variables were acceptable.

Change Title Implementation of the SGTR analysis Change The BV2 Steam Generator Tube Rupture (SGTR) analysis was updated to address changes as a result of the EPU analyses. These EPU analyses performed by Westinghouse used atmosheric dump and residual heat release valve capacities without accounting for the impact of the valve inlet and outlet piping. The following impacts were evaluated:

0 Limiting single failure for SGTR 0 Tripping of Auxiliary Feedwater (AFW) pumps to isolate AFW to ruptured SG 0 Crediting of 3 atmospheric steam dump valves for Reactor Cooling System (RCS) cooldown to establish RCS Subcooling 0 Steam generator margin to overfill revised

• Change operator action times in response to a SGTR 0 Cooldown to residual heat removal system entry temp (350'F) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> The evaluation of the above impacts concluded that the BV2 SGTR analysis could be updated for implementation of EPU without without submittal of a license amendment request.