ML21075A078
| ML21075A078 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/15/2021 |
| From: | Grabnar J Energy Harbor Nuclear Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-21 -065 | |
| Download: ML21075A078 (2) | |
Text
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harbor Jol,11 J. Grabnar Site Vice President, Beaver Valley Nuclear March 15, 2021 L-21 -065 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Report of Facility Changes, Tests and Experiments Energy /-/arbor Nllclear Corp.
Beaver Valley Powe,* Station P. 0. Box 4 Shippi11gpo11. PA 15077 724-682-5234 10 CFR 50.59(d)(2)
In accordance with 10 CFR 50.59(d)(2), Energy Harbor Nuclear Corp. hereby submits the attached Report of Facility Changes, Tests and Experiments for the Beaver Valley Power Station, Unit No. 1 (BVPS-1 ). This report reflects the implemented changes, tests and experiments that were evaluated pursuant to 10 CFR 50.59 during the period of March 1, 2019 through February 28, 2021.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Manager - Fleet Licensing, at 330-696-7208.
Si"w--
John J. Grabnar
Attachment:
Beaver Valley Power Station, Unit 1, Report of Facility Changes, Tests, and Experiments cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative
Attachment L-21-065 Beaver Valley Power Station, Unit 1 Report of Changes, Tests, and Experiments Page 1 of 1 Safety Analysis of Radiological Consequences of Waste Gas System Rupture (WGSR)
Design Basis Accident at BVPS-1, Control Room, Exclusion Area Boundary (EAB), and Low Population Zone (LPZ) Doses Activity
Description:
Raising the Beaver Valley Control Room Envelope (CRE) allowable unfiltered inflow from a maximum of 500 cubic feet per minute (cfm) up to a maximum of 1250 cfm requires an update of the BVPS-1 WGSR Dose Consequence Calculation resulting in slightly higher dose consequences.
The WGSR control room doses were based on 500 cfm of unfiltered CRE inflow with a control room emergency ventilation system (CREVS) sensitivity case done at 1030 cfm.
The calculation addendum evaluates the CRE doses at an allowable unfiltered inflow as high as 1250 cfm, which bounds the total CRE inflow in the CREVS pressurization or isolation alignments. No changes to the EAB or LPZ doses result from the CRE ventilation change; however, higher EAB and LPZ whole body radiological dose consequence values are adopted due to rounding figures up to one significant digit.
Summary of Evaluation:
Increasing the CRE allowable unfiltered inleakage from 500 cfm to 1250 cfm and the rounding up of the EAB whole body radiological dose consequence results in increases in the calculated doses to the control room operators and to the public from a postulated WGSR. The evaluation shows that the dose increases are less than the 10 percent allowance of margin to the regulatory limits (or Standard Review Plan limits), and therefore can be made without specific permission from the NRC.