ML100550446

Request for Additional Information Related to Alternative Source Term License Amendment Request

ML100550446
Person / Time
Site:	LaSalle
Issue date:	03/05/2010
From:	Goodwin C Plant Licensing Branch III
To:	Pardee C Exelon Nuclear
Goodwin, Cameron S, NRR/DORL, 415-3719
References
TAC ME0068, TAC ME0069
Download: ML100550446 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 5, 2010 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO ALTERNATIVE SOURCE TERM LICENSE AMENDMENT REQUEST (TAC NOS. ME0068 - ME0069)

Dear Mr. Pardee:

By letter to the Nuclear Regulatory Commission (NRC) dated October 23, 2008 (Agencywide Documents Access and Management System Accession No. ML083100149), Exelon Generation Company, LLC, submitted a request to replace the current accident source term used in design-basis radiological analysis with an alternative source term pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50.67, "Accident Source Term," for the LaSalle County Station, Units 1 and 2.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on February 18, 2010, it was agreed that you would provide a response on April 2, 2010.

Please note that if you do not respond to this letter within the prescribed response time or provide an acceptable alternate date in writing, we may reject your application for amendment under the provisions of 10 CFR Section 2.108 The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.

Sincerely, Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 In reviewing the Exelon Generation Company s (Exelon's) submittal dated October 23, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083100149), related to the request to replace the current accident source term used in design-basis radiological analysis with an alternative source term pursuant to Title 10 of the Code of Federal Regulations Part 50.67, "Accident Source Term," for the LaSalle County Station (LSCS), Units 1 and 2, and the licensee's supplement dated November 18, 2009 (ADAMS Accession No. ML093220838), the Nuclear Regulatory Commission staff has determined that the following information is needed in order to complete its review:

Electrical Engineering Branch

1. The following question is in reference to request for information (RAI) Question #2 response, found in the licensee's letter dated November 18, 2009. Describe changes to the emergency diesel generator (EDG) surveillance testing and how the surveillance testing demonstrates the EDG capability to supply the necessary accident loading given that Division 1 loads now require use of the EDG's 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating. In addition, describe EDG design load margin in more detail and how that design margin is managed.

2. The following question is in reference to RAI #5 response, found in the licensee's letter dated November 18, 2009. Based on your response, a subset of the components for the standby liquid control system is in a harsh environment due to high radiation which would necessitate inclusion in the 50.49, "Environmental qualification of electric equipment important to safety for nuclear power plants," program. Confirm that these components are in the 50.49 program or provide a detailed justification why they should not be.

Enclosure

ML100550446 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME CGoodwin THarris NDiFrancesco for SCampbell DATE 03/5/10 03/4/10 03/5/10