ML16202A028

LTR-16-0388-1 - Response to the Advisory Committee on Reactor Safeguards Report on the Safety Aspects of the License Renewal Application for LaSalle County Station, Units 1 and 2

ML16202A028
Person / Time
Site:	LaSalle
Issue date:	09/14/2016
From:	Mccree V NRC/EDO
To:	Dennis Bley Advisory Committee on Reactor Safeguards
Mitchell J, NRR/DLR, 301-415-3019
Shared Package
ML16230A285	List: ML16202A028 ML16230A284
References
EDO-002, LTR-16-0388-1
Download: ML16202A028 (4)

Text

Dennis C. Bley, Chairman UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 2016 Advisory Committee on Reactor Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR LASALLE COUNTY STATION, UNITS 1AND2

Dear Dr. Bley:

During the 635th meeting of the Advisory Committee on Reactor Safeguards (the Committee, ACRS) held on July 6-8, 2016, the Committee completed its review of the license renewal application for LaSalle County Station, Units 1 and 2 (LSCS). The Committee also reviewed the U.S. Nuclear Regulatory Commission (NRC) staff's final safety evaluation report (SER) for this application.

In the Committee's final report dated July 18, 2016, the Committee recommended that the NRC renew the operating licenses for LSCS. The NRC staff appreciates the Committee's objective and in-depth review of the license renewal application and the staff's final SER. The NRC staff acknowledges the Committee's insights regarding the resolution of the two open items that were closed between the ACRS subcommittee and full committee meetings, as documented in the final SER:

Assurance that the aging management program for the vessel inner-diameter attachment welds will provide acceptable weld examination coverage and include additional acceptable actions taken in the event of limited weld examination coverage.

Assurance that the aging management program for stress corrosion cracking will require documented bases for crediting limited coverage weld inspections, to include an engineering technical evaluation.

The NRC staff recognizes the Committee's commitment to safety and appreciates its continued support of the license renewal process.

cc: Chairman Burns Commissioner Svinicki Commissioner Baran SECY Si~*

Victor M. Mee~

Executive Director for Operations

ML16230A285 (Package),

ML16200A156 (Incoming),

ML16202A028 (Letter)

OFFICE LA:RPB1 :DLR*

NAME I Betts DATE 71 21 /16 OFFICE BC:RPB1 :DLR NAME YDiaz-Sanabria DATE 8/29/16 PM:RPB1 :DLR Tech Editor*

JMitchell JDougherty 81 18 /16 81 23 /16 D:DLR:NRR D:NRR JMarshall WDean (BMcDermott for) 8/30/16 9/9/16

Letter to D. Bley from V. Mccree dated September 14, 2016

SUBJECT:

RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR LASALLE COUNTY STATION, UNITS 1 AND 2 DISTRIBUTION: LTR-16-0388-1-NRR E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRsrg Resource RidsNrrPMLaSalle Resource J. Mitchell R. Plasse D. Drucker J. Danna T. Clark, OEDO T. Inverso, OEDO J. Wachutka, OGC D. Mcintyre, OPA M. Kunowski, Riii V. Mitlyng, Riii P. Chandrathil, Riii H. Logaras, Riii C. Lipa, Riii S. Sheldon, Riii R. Ruiz, Riii J. Robbins, Riii Attachment