ML12206A501: Difference between revisions

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| document type = Letter, Request for Additional Information (RAI)
| document type = Letter, Request for Additional Information (RAI)
| page count = 4
| page count = 4
| project = TAC:ME8098, TAC:ME8296, TAC:ME8297, TAC:ME8299
}}
}}
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 1, 2012 Mr. Michael Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR REVISE TECHNICAL SPECIFICATIONS 5.5.9 AND 5.6.9, FOR PERMANENT ALTERNATE REPAIR CRITERIA (TAC NOS. ME8296, IVIE8297, IVIE8298, AND ME8299)
==Dear Mr. Pacilio:==
By letter dated March 20,2012 (Agencywide Document Access and Management System (ADAMS) Accession No. IVIL120830222), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise the technical specifications of Byron Station, Unit Nos.1 and 2, and Braidwood Station, Units 1 and 2 (the Stations). Specifically, the proposed license amendment would establish permanent alternate repair criteria for portions of the steam generator (SG) tubes within the tubesheet of the Stations SGs. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information required is addressed in the enclosure to this letter. During a discussion with your staff on July 24, 2012, it was agreed that you would provide a response within 30 days from the date of this letter. The NRC staff considers that a timely response to requests for additional information help ensure sufficient time is available for staff review and contributes to the NRC's goal of efficient and effective use of staff resources. If you have any questions regarding this matter, please contact me at (301 Si7l' /J /'Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor Docket Nos. STN 50-454, STN STN 50-456, and STN Request for additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNIT NOS. 1 AND. 2 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-45, STN 50-456, and STN 50-457 By letter dated March 20, 2012 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 120830222), Exelon Generation Company, LLC (the licensee), submitted a license amendment request (LAR) to revise the technical specifications (TS) of Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2 (the Stations). The proposed changes would establish permanent alternate repair criteria for portions of the steam generator (SG) tubes within the tubesheet of the Stations SGs. The NRC staff has determined that the following information is required in order to complete its review: TS 5.5.9.f.2.i lists acceptable sleeve repair methods for the Stations. What portions of tubing are approved for repair by sleeving? Are any of the approved sleeving methods applicable to the tubesheet region, anywhere below the top of the tubesheet? If yes, what changes to the requested amendment are needed to ensure that the proposed permanent alternate repair criteria in TS 5.5.9.c.1 are not applicable to sleeved tubes. [Note, if the lower joint of the sleeve is located approximately 4 inches below the top of the tubesheet, then the upper 4 inches of the tube to tubesheet jOint may not be effective in resisting tube pull-out.] What changes to TS 5.5.9.d in the LAR are needed to ensure that sleeved tubes are subject to inspection from the tube-to-tubesheet weld at the tube inlet to the tubesheet weld at the tube outlet? If you have any questions regarding this matter, please contact me at (301)-415-3867.
Sincerely,IRAI Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, and STN 50-457 Request for additional cc w/enci: Distribution via DISTRIBUTION: PUBLIC RidsNrrDorlLpl3-2 Resource RidsNrrDeEsgb Resource RidsNrrPMByron Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrPMBraidwood Resource LPL3-2 RIF ADAMS Accession No. ML 12206A50 *Memo Dated LPL3-2/PM LPL3-2/LAOFFICE DE/ESGB/BC LPL3-2/BC LPL3-2/PM I : SRohrerNAME MMahoney GKulesa MDudek MMahoney I 8/1 112 17/2/12* 8/1 112 I 8/1 112II DATE 811 112 1 1 I OFFICIAL RECORD}}

Revision as of 08:29, 16 March 2018

Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2 - Request for Additional Information Related to License Amendment Request for Revise Technical Specifications 5.5.9 and 5.6.9, for Permanent Alternate Repair Criteria
ML12206A501
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 08/01/2012
From: Michael Mahoney
Plant Licensing Branch III
To: Pacilio M J
Exelon Nuclear
References
TAC ME8098, TAC ME8296, TAC ME8297, TAC ME8299
Download: ML12206A501 (4)


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 1, 2012 Mr. Michael Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 BYRON STATION, UNIT NOS. 1 AND 2, AND BRAIDWOOD STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR REVISE TECHNICAL SPECIFICATIONS 5.5.9 AND 5.6.9, FOR PERMANENT ALTERNATE REPAIR CRITERIA (TAC NOS. ME8296, IVIE8297, IVIE8298, AND ME8299)

Dear Mr. Pacilio:

By letter dated March 20,2012 (Agencywide Document Access and Management System (ADAMS) Accession No. IVIL120830222), Exelon Generation Company, LLC (the licensee), submitted a license amendment request to revise the technical specifications of Byron Station, Unit Nos.1 and 2, and Braidwood Station, Units 1 and 2 (the Stations). Specifically, the proposed license amendment would establish permanent alternate repair criteria for portions of the steam generator (SG) tubes within the tubesheet of the Stations SGs. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information required is addressed in the enclosure to this letter. During a discussion with your staff on July 24, 2012, it was agreed that you would provide a response within 30 days from the date of this letter. The NRC staff considers that a timely response to requests for additional information help ensure sufficient time is available for staff review and contributes to the NRC's goal of efficient and effective use of staff resources. If you have any questions regarding this matter, please contact me at (301 Si7l' /J /'Plant Licensing Branch Division of Operating Reactor Office of Nuclear Reactor Docket Nos. STN 50-454, STN STN 50-456, and STN Request for additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNIT NOS. 1 AND. 2 BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-45, STN 50-456, and STN 50-457 By letter dated March 20, 2012 (Agencywide Document Access and Management System (ADAMS) Accession No. ML 120830222), Exelon Generation Company, LLC (the licensee), submitted a license amendment request (LAR) to revise the technical specifications (TS) of Byron Station, Unit Nos. 1 and 2, and Braidwood Station, Units 1 and 2 (the Stations). The proposed changes would establish permanent alternate repair criteria for portions of the steam generator (SG) tubes within the tubesheet of the Stations SGs. The NRC staff has determined that the following information is required in order to complete its review: TS 5.5.9.f.2.i lists acceptable sleeve repair methods for the Stations. What portions of tubing are approved for repair by sleeving? Are any of the approved sleeving methods applicable to the tubesheet region, anywhere below the top of the tubesheet? If yes, what changes to the requested amendment are needed to ensure that the proposed permanent alternate repair criteria in TS 5.5.9.c.1 are not applicable to sleeved tubes. [Note, if the lower joint of the sleeve is located approximately 4 inches below the top of the tubesheet, then the upper 4 inches of the tube to tubesheet jOint may not be effective in resisting tube pull-out.] What changes to TS 5.5.9.d in the LAR are needed to ensure that sleeved tubes are subject to inspection from the tube-to-tubesheet weld at the tube inlet to the tubesheet weld at the tube outlet? If you have any questions regarding this matter, please contact me at (301)-415-3867.

Sincerely,IRAI Michael Mahoney, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, and STN 50-457 Request for additional cc w/enci: Distribution via DISTRIBUTION: PUBLIC RidsNrrDorlLpl3-2 Resource RidsNrrDeEsgb Resource RidsNrrPMByron Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource RidsNrrPMBraidwood Resource LPL3-2 RIF ADAMS Accession No. ML 12206A50 *Memo Dated LPL3-2/PM LPL3-2/LAOFFICE DE/ESGB/BC LPL3-2/BC LPL3-2/PM I : SRohrerNAME MMahoney GKulesa MDudek MMahoney I 8/1 112 17/2/12* 8/1 112 I 8/1 112II DATE 811 112 1 1 I OFFICIAL RECORD