ML13193A052

Request for Additional Information Related to Administrative Change to Remove Obsolete License Condition Related to Boraflex Degradation

ML13193A052
Person / Time
Site:	LaSalle
Issue date:	07/23/2013
From:	Nicholas Difrancesco Plant Licensing Branch III
To:	Pacilio M Exelon Generation Co, Exelon Nuclear
Nicholas DiFrancesco, NRR/DORL 415-1115
References
TAC ME9799
Download: ML13193A052 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 23, 2013 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB.JECT: LASALLE COUNTY STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO ADMINISTRATIVE CHANGE TO REMOVE OBSOLETE LICENSE CONDITION RELATED TO BOREFLEX DEGRADATION (TAC NO. ME9799)

Dear Mr. Pacilio:

By letter to the U.S. Nuclear Regulatory Commission (!\IRC) dated October 15, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML12290A111), Exelon Generation Company, LLC, (the licensee), requested changes to the facility operating license for LaSalle County Station (LSCS), Unit 2. The proposed changes would remove License Condition 2.C.(30), 2.C.(31), and 2.C.(32) which controlled the spent fuel pool (SFP) configuration in the interim period until !\IETCO-SNAP-IN were installed into accessible SFP cell locations.

The NRC staff reviewed 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 July 18, 2013, it was agreed that you would provide a response by August 19, 2013.

Please note that if you do not respond to this letter by the agreed-upon date, or provide an acceptable alternate date in writing, the NRC staff may reject your request for approval under the provisions of Title 10 of the Code of Federal Regulations, 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.

M. Pacilio -2 If circumstances result in the need to revise the requested response date, please contact me at (301)415-1115.

Sincerely, Nicholas J. DiFrancesco, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor licensing Office of Nuclear Reactor Regulation Docket No. 50-374

Enclosure:

Request for Additional Information cc w/encl: ListServ

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING SPENT FUEL POOL ADMINISTRATIVE CHANGES EXELON GENERATION COMPANY, LLC LASALLE COUNTY STATION, UNIT 2 DOCKET NO. 50-374 In reviewing the Exelon Generation Company, LLC (EGC) submittal dated October 15, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12290A111), for LaSalle County Station (LSCS), Unit 2, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:

1.

Background:

10 CFR 50.36, 'Technical Specifications [TS]," states that:

Design features to be included are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section.

The application did not discuss impacts to the Design Features TS Section 4.3.1

'Criticality' with the removal of License Conditions 2.(C).30, 2.(C).31, and 2.(C).32. The licensee should propose appropriate changes to the Design Features section to reflect the facilities current design and prior approval of Amendment 199 and 186 for Unit 1 and Unit 2, respectively.

Issue:

By letter dated January 28, 2011 (ADAMS Accession No. ML110250051), "LaSalle County Station, Units 1 and 2, Issuance of Amendments [199 and 186 for Unit 1 and Unit 2, respectively] Concerning Spent Fuel Neutron Absorbers," the NRC approved the use of NETCO SNAP IN rack insert to ensure that degradation of Boraflex material located in spent fuel pool cells would not challenge criticality safety. For the interim period until the installation of inserts was completed, the amendment introduced License Conditions 2.(C).30 and 2.(C).31 to ensure criticality safety when Boraflex material was credited. Following the campaign, a few inaccessible/non-insert cell locations still contain only Boraflex for neutron absorption.

Request:

With the removal of the License Conditions 2.(C).30 and 2.(C).31, how will EGC maintain control and prevent storage of fuel or fissile material in inaccessible/non-insert cell locations?

-2

2.

Background:

In review of the Unit 2 criticality safety methodologies described Chapter 9 of the LSCS Updated Final Safety Analysis Report (USFAR) Revision 19 dated April 12. 2012 (ADAMS Accession No. ML121580191). it contained criticality methodologies which allow use of both Boraflex and NETCO SNAP IN rack inserts.

Request:

Does EGC plan to remove obsolete criticality methodologies which credit Boraflex material for LSCS Unit 2 as part of implementing this proposed request (or has EGC already removed the methods from its current UFSAR)?

... ML13193A052 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME NDiFrancesco SRohrer JBowen NDiFrancesco DATE 7/16/13 7/15/13 7/23/13 7/23/13