ML19164A150
| ML19164A150 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/13/2019 |
| From: | Kimberly Green Plant Licensing Branch III |
| To: | Simpson P Exelon Generation Co |
| Green K, NRR/DORL/LPLIII, 415-1627 | |
| References | |
| EPID L-2019-LLA-0045 | |
| Download: ML19164A150 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Patrick R. Simpson Manager - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 June 13, 2013
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2-ACCEPTANCE.
FOR REVIEW OF APPLICATION TO INCREASE TECHNICAL SPECIFICATION ALLOWABLE MAIN STEAM ISOLATION VALVE LEAKAGE RATES AND REVISE SECONDARY CONTAINMENT SURVEILLANCE REQUIREMENT (EPID L-2019-LLA-0045)
Dear Mr. Simpson:
By letter dated March 5, 2019, as supplemented by letter dated May 23, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML190646368 and ML19143A347, respectively), Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) for Quad Cities Nuclear Power Station, Units 1 and 2 (QCNPS).
Specifically, the amendment would revise Technical Specification (TS) 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," Surveillance Requirement (SR) 3.6.1.3.10 to increase the combined main steam isolation valve (MSIV) leakage rate limit for all four steam lines, as well as the leakage rate through each MSIV leakage path; create a new TS 3.6.2.6, "Residual Heat Removal (RHR) Drywell Spray," to reflect the crediting of the drywell sprays for fission product removal as part of the revised loss-of-coolant accident analysis; and revise TS 3.6.4.1, "Secondary Containment," SR 3.6.4.1.1 to address short-duration conditions during which the secondary containment pressure may not meet the SR pressure requirement, in accordance with Technical Specifications Task Force Traveler (TSTF) 551, "Revise Secondary Containment Surveillance Requirements," Revision 3.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of the proposed LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations, an amendment to the license must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
The NRC staff has reviewed your application, as supplemented, and concludes that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact
the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
The NRC staff will review the QCNPS LAR to ensure that it meets the NRC regulations specified in 10 CFR 50.67, Accident source term. The staff will conduct the review using the guidance contained in NUREG-0800, Chapter 15, Section 15.0.1, Revision. 0, "Radiological Consequence Analysis Using Alternate Source Terms," dated July 2000 (ADAMS Accession No. ML003734190), which identifies Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," dated July 2000 (ADAMS Accession No. ML003716792). In its review, the staff will also consider Regulatory Issue Summary 2006-04, "Experience with Implementation of Alternative Source Terms," dated March 7, 2006 (ADAMS Accession No. ML063460347), and the previously issued safety evaluation on the MSIV leakage pathway (ADAMS Accession No. ML062070290) that discussed technical concerns with AEB 98-03, "Assessment of Radiological Consequences for the Perry Pilot Plant Application Using the Revised (NUREG-1465) Source Term," dated December 6, 1998 (ADAMS Accession No. ML011230531 ), which was used as the basis for the aerosol model in QCNPS's alternative source term amendment request.
Based on the information provided in your submittal, as supplemented, the NRC staff has estimated that this licensing request will take approximately 1,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> to complete. The NRC staff expects to complete this review by June 30, 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates will be communicated, during the routine interactions.
These estimates are based on the NRC staffs initial review of the application and they could change due to several factors including requests for additional information (RAls), timely responses to RAls (i.e., within 30 days), ability of EGC to support any audit requests, unanticipated addition of scope to the review, and review by ~RC advisory committees or hearing-related activities. Delays by EGC in responding to RAls or inability to support audits will likely impact the NRC staff's ability to adhere to the review schedule.
If you have any questions, please contact me at (301) 415-1627.
Docket Nos. 50-254 and 50-265 cc: Listserv Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML19164A150 OFFICE NRR/DORL/LPL3/PM N RR/DORL/LPL3/LA NAME KGreen SRohrer DATE 06/13/19 06/13/19 OFFICE NRR/DSS/SRXB/BC NRR/DSS/SCPB/BC NAME JWhitman Sanderson DATE 04/01/19 05/28/19 OFFICE NRR/DORL/LPL3/BC (A)
NRR/DORL/LPL3/PM NAME LRegner (JWiebe for)
KGreen DATE 06/13/19 06/13/19