ML15274A038

LTR-15-0480 - Response to the Advisory Committee on Reactor Safeguards Reports on the Safety Aspects of the License Renewal Application for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2

ML15274A038
Person / Time
Site:	Byron, Braidwood
Issue date:	10/23/2015
From:	Mccree V NRC/EDO
To:	John Stetkar Advisory Committee on Reactor Safeguards
Daily J,NRR/DLR,415-3873
References
LTR-15-0480
Download: ML15274A038 (4)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 23, 2015 John W. Stetkar, Chairman 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 BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2

Dear Mr. Stetkar:

During the 627th meeting of the Advisory Committee on Reactor Safeguards (the Committee) held on September 9-12, 2015, the Committee completed its review of the combined license renewal application for the Byron and Braidwood stations. The Committee also reviewed the U.S. Nuclear Regulatory Commission (NRC) staffs associated final safety evaluation report (SER) for this application.

In the Committees final report, dated September 21, 2015, the Committee recommends the NRC renew the operating licenses for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The NRC staff appreciates the Committees objective and in-depth review of the license renewal application and the staffs final SER. The NRC staff acknowledged the Committees insights regarding the resolution of the following open items as documented in the final SER:

• Ensuring there is adequate aging management through nondestructive testing of reactor vessel head control rod drive mechanism nozzles at the locations of wear near the J-groove welds caused by the thermal sleeve centering tabs; and

• Ensuring appropriate leading candidates and representative materials are included in the evaluation for environmentally assisted fatigue cumulative usage factors for reactor coolant pressure boundary systems and components.

J. Stetkar The NRC staff recognizes the Committees commitment to safety and appreciates its continued support of the license renewal process.

Sincerely,

/RA Michael R. Johnson Acting for/

Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY

ML15267A775 (Package) ML15264A955 (Incoming) ML15274A038 (Letter)

OFFICE LA:RPB1:DLR* PM:RPB1:DLR* Tech Editor* OGC NAME YEdmonds JDaily JDougherty MYoung (NLO)

DATE 10/01/15 10/01/15 10/01/15 10/06/15 OFFICE BC:RPB1:DLR D:DLR:NRR D:NRR EDO WDean VMcCree NAME YDiaz-Sanabria CMiller (MEvans for) (MJohnson for)

DATE 10/02/15 10/07/15 10/15/15 10/ 23 /15

Letter to J. Stetkar from V. McCree dated October 23, 2015

SUBJECT:

RESPONSE TO THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS REPORT ON THE SAFETY ASPECTS OF THE LICENSE RENEWAL APPLICATION FOR BYRON STATION, UNITS 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 DISTRIBUTION : LTR-15-0480 PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDeEvib Resource RidsNrrDeEpnb Resource RidsNrrDeEsgb Resource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsEdoMailCenter Resource RidsNrrMailCenter Resource RidsNrrOd Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR

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JDaily RBaum LJames DMcIntyre, OPA JWiebe, DORL EDuncan, RIII SSheldon RIII AStone RIII ABarker RIII JMcGhee, Byron Station, RIII JDraper, Byron Station, RIII VMitlyng, RIII PChandrathil, RIII