RS-10-199, Clarification of Information Contained in NRC Safety Evaluation for Alternative Source Term License Amendment
| ML103230113 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  (NPF-011, NPF-018) |
| Issue date: | 11/18/2010 |
| From: | Simpson P Exelon Nuclear, Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RS-10-199 | |
| Download: ML103230113 (2) | |
Text
Exelon Generation 4300 Winfield Road Warrenville, ll60555 RS-10-199 www.exeloncorp.com Nuclear November 18, 201 0 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001
Subject:
laSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Clarification of Information Contained in NRC Safety Evaluation for Alternative Source Term License Amendment
References:
- 1. Letter from C. Gratton (U.S. NRC) to M. J. Pacilio (Exelon Nuclear), "LaSalle County Station, Units 1 and 2 - Issuance of Amendments Re: Application of Alternative Source Term (TAC Nos. ME0068 and ME0069)," dated September 6, 2010
- 2. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term," dated October 23,2008
- 3. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U.S. NRC, "Additional Information Supporting Request for License Amendment Regarding Application of Alternative Source Term," dated November 18, 2009 In the Reference 1, the NRC issued license amendments in response to Exelon Generation Company, LLC's (EGC's) request dated October 23,2008 (i.e., Reference 2). The license amendments support the application of alternative source term (AST) methodology with respect to the loss-of-coolant accident and the fuel handling accident. During review of the NRC safety evaluation associated with the license amendments, EGC identified the need to clarify information documented in the NRC safety evaluation related to the classification of the Standby Liquid Control (SLC) system at laSalle County Station (LSCS). Therefore, EGC is providing the following clarification regarding the system's classification.
November 18, 2010 U.S. Nuclear Regulatory Commission Page 2 Specifically, page 4 of the NRC safety evaluation states:
.., the licensee indicated that the SLC system at LSCS was classified as a safety-related system.
In addition, page 9 of the NRC safety evaluation states:
LSCS states that the SLC system is a safety-related system and meets the following requirements...
Sections 9.3.5.1.1 and 9.3.5.3 of the LSCS Updated Final Safety Analysis Report describe the SLC system as a special safety system. EGC stated in Reference 2 that the SLC system is a safety related system; however, clarifying information regarding the actual classification of the system was provided in the Attachment to Reference 3. Specifically, in response to NRC Request 5, EGC stated:
The SLC system components are currently classified as augmented quality with special requirements, and as such, these components are treated as safety related for design, procurement, and maintenance/testing to meet the requirements of 10 CFR 50, Appendix B, "Quality Assurance Program," and General Design Criterion 4.
The response to NRC Request 5 further states:
The devices were originally procured, installed, and maintained as environmentally qualified to the requirements of 10 CFR 50.49. The components are currently classified as "augmented quality" and will continue to be treated as safety related and thus, will ensure that the environmental criteria are met.
The classification of the SLC system as augmented quality, in lieu of safety related, has no impact on the SLC system's ability to perform its AST function. As stated above, the SLC system components are treated as safety related for design, procurement, and maintenance/testing.
There are no regulatory commitments being made in this submittal. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.
R Patrick R. Simpson Manager - Licensing cc:
NRC Regional Administrator, Region III NRC Senior Resident Inspector - LaSalle County Station Illinois Emergency Management Agency - Division of Nuclear Safety