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 M NRC/EDO
To:	Stetkar J W 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) staff's associated final safety evaluation report (SER) for this application.

In the Committee's 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 Committee's objective and in-depth review of the license renewal application and the staff's final SER. The NRC staff acknowledged the Committee's 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.

The NRC staff recognizes the Committee's 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 NAME YDiaz-Sanabria CMiller WDean (MEvans for)

VMcCree (MJohnson for) DATE 10/02/15 10/07/1510/15/1510/ 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

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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