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| issue date = 10/23/2015
| issue date = 10/23/2015
| title = 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
| title = 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
| author name = McCree V M
| author name = Mccree V
| author affiliation = NRC/EDO
| author affiliation = NRC/EDO
| addressee name = Stetkar J W
| addressee name = Stetkar J
| addressee affiliation = NRC/ACRS
| addressee affiliation = NRC/ACRS
| docket = 05000454, 05000455, 05000456, 05000457
| docket = 05000454, 05000455, 05000456, 05000457
Line 14: Line 14:
| page count = 4
| page count = 4
| project =  
| project =  
| stage = RAI
| stage = Other
}}
}}


=Text=
=Text=
{{#Wiki_filter: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  
{{#Wiki_filter: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:==
==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
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:==
==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.  
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.


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:
J. Stetkar                              The NRC staff recognizes the Committees commitment to safety and appreciates its continued support of the license renewal process.
* 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
Sincerely,
* 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. 
                                          /RA Michael R. Johnson Acting for/
Victor M. McCree Executive Director for Operations cc: Chairman Burns Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY


The NRC staff recognizes the Committee's commitment to safety and appreciates its continued support of the license renewal process. Sincerely,       
ML15267A775 (Package) ML15264A955 (Incoming) ML15274A038 (Letter)
            /RA Michael R. Johnson Acting for/        Victor M. McCree Executive Director for Operations  cc:  Chairman Burns        Commissioner Svinicki Commissioner Ostendorff Commissioner Baran SECY 
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


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


==SUBJECT:==
==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  
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
-------------------------------------
-------------------------------------
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}}
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}}

Latest revision as of 06:09, 31 October 2019

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  Constellation icon.png
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)
v • d • e


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

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

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