ML24023A576
| ML24023A576 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/08/2024 |
| From: | Klos L NRC/NRR/DORL/LPL2-1 |
| To: | Carr E Virginia Electric & Power Co (VEPCO) |
| Jack Minzer Bryant, NRR/DORL/LPL2-1 | |
| References | |
| EPID L-2022-LLA-0167 | |
| Download: ML24023A576 (1) | |
Text
March 8, 2024 Eric S. Carr President - Nuclear Operations and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNIT NOS. 1 AND 2 - CORRECTION TO ISSUANCE OF AMENDMENT NOS. 315 AND 315, REGARDING REVISED EMERGENCY PLAN FOR RELOCATION OF THE TECHNICAL SUPPORT CENTER (EPID L-2022-LLA-0167)
Dear Eric Carr:
On November 7, 2023 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML23242A229), the U.S. Nuclear Regulatory Commission (NRC, the Commission) issued Amendment No. 315 to Subsequent Renewed Facility Operating License No. DPR-32 and Amendment No. 315 to Subsequent Renewed Facility Operating License No. DPR-37 for the Surry Power Station, Unit Nos. 1 and 2, respectively. The amendments revised the license and Emergency Plan in response to your application dated November 18, 2022 (ML22322A182), as supplemented by letters dated May 31 (ML23167B007) and August 7, 2023 (ML23220A148). This amendment approved the relocation of the Technical Support Center (TSC) from its current location adjacent to the Main Control Room to a building outside the protected area that was used previously as the Local Emergency Operations Facility.
Subsequently, your staff by letter dated January 3, 2024 (ML24003A902) identified a discrepancy in the license amendment requests submittal, ML23167B007, Table 4-1, Summary of TSC Dose Results, which typographically presented an error in the Refueling Water Storage Tank leakage dose rate of 0.2100 rather than the correct value for that parameter of 0.0210 rem TEDE. That corrected value is now utilized on the associated page of the issued amendment and enclosed.
Therefore, consistent with NRC staff guidance dated January 16, 1997 (ML103260096), based on the NRCs policy established by SECY-96-238 and the corresponding SRM, these errors can be corrected by a letter to the licensee from the NRC staff.
Enclosed please find the corrected page 20 of Amendments Nos. 315 and 315 for Surry, Units 1 and 2, respectively. The corrections do not change any of the conclusions in the safety evaluations or no significant hazards consideration determination as previously noticed in the Federal Register.
Sincerely,
/RA/
L. John Klos, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280 and 50-281 cc: Listserv
CORRECTED PAGE, SURRY AMENDMENT NOS. 315 AND 315 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-280 AND 50-281 Summary of TSC Dose Results Data (see ML23167B007):
LOCA Dose Component TSC Dose [rem TEDE]
TSC Relocation
[CLB]
AST TSC Dose SI-Based Isolation 60-min Isolation Dose Containment Leakage 0.0700 0.5866 0.135 ECCS Leakage 0.2055 0.2691 0.111 RWST Leakage 0.0162 0.0173 0.021 Containment Direct Shine 0.0050 0.0050 0.047 Containment Skyshine 1.6028 1.6028 0.381 Cloudshine1 0.0361 0.0361 0.195 Filter Shine 0.1000 0.1000 0.16 Containment Shine through Main Steam Line Penetrations 0.005 SI Piping under Main Steam Valve House & OS Pump House 0.194 Hydrogen Re-combiner Vault 0.004 Total 2.04 2.62 1.30 Sources indicated with a result of -- were deemed negligible with respect to the new TSC location due to source/receptor geometry.
3.6.2.5 TSC Dose Consequence Analysis Conclusion The results of the licensees calculation indicate that the TSC personnel will be protected from radiological hazards, including direct radiation and airborne radioactivity from in plant sources under accident conditions, to the same degree as MCR personnel (radiation exposures shall not exceed 5 rem TEDE for the duration of the postulated accident). Also requirements contained in Clarification of TMI Action Plan Requirements NUREG-0737 (ML051400209) were considered in this SE.
The staff used RADTRAD version 5.0.3 and MicroShield version 13 to perform independent confirmatory calculations. These confirmatory calculations utilizing the LOCA analysis initial conditions, inputs and assumptions provided in the LAR and CLB documents and obtained results similar to those provided in the application and within acceptance criteria. Based on its
ML24023A576 NRR-106 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NAME JMinzerBryant JKlos KGoldstein DATE 01/23/2024 01/23/2024 03/01/2024 OFFICE NRR/DRA/ARCB/BC NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME KHsueh MMarkley JKlos DATE 01/29/2024 03/08/2024 03/08/2024