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| number = ML101050241
| number = ML101050241
| issue date = 04/16/2010
| issue date = 04/16/2010
| title = Braidwood Station, Unit 1 - Review of Spring 2009 Steam Generator Tube Inservice Inspection Report
| title = Review of Spring 2009 Steam Generator Tube Inservice Inspection Report
| author name = David M J
| author name = David M
| author affiliation = NRC/NRR/DORL/LPLIII-2
| author affiliation = NRC/NRR/DORL/LPLIII-2
| addressee name = Pardee C G
| addressee name = Pardee C
| addressee affiliation = Exelon Generation Co, LLC
| addressee affiliation = Exelon Generation Co, LLC
| docket = 05000456
| docket = 05000456
Line 14: Line 14:
| page count = 3
| page count = 3
| project = TAC:ME1811
| project = TAC:ME1811
| stage = RAI
| stage = Approval
}}
}}


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 16, 2010 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB~IECT:        BRAIDWOOD STATION, UNIT 1 - REVIEW OF SPRING 2009 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT (TAC NO. ME1811)
 
==Dear Mr. Pardee:==
 
By letter to the Nuclear Regulatory Commission (NRC) dated July 16, 2009 (Agencywide Documents Access and Management System Accession No. ML092050259), Exelon Generation Company, LLC (the licensee), submitted information pertaining to the 2009 steam generator tube inspections at Braidwood Station, Unit 1, in accordance with the station's technical specifications (TSs). This was the 14th refueling outage for Braidwood Station, Unit 1.
The NRC staff has completed its review of the report and concludes that the licensee has provided the information required by the station's TSs, and that no additional follow-up is required at this time. A copy of the NRC staff's evaluation is enclosed.
                                            ~;t4J;;oQ M~all    J. Davi'k::'lr Project Manager Plant licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456
 
==Enclosure:==
 
Review of Spring 2009 Steam Generator Tube Inservice Inspections cc w/encl: Distribution via ListServ
 
OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF SPRING 2009 STEAM GENERATOR TUBE INSERVICE INSPECTIONS BRAIDWOOD STATION. UNIT 1 DOCKET NO. 50-456 By letter to the Nuclear Regulatory Commission (NRC) dated July 16, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092050259), Exelon Generation Company, LLC (the licensee), submitted information pertaining to the 2009 steam generator (SG) tube inspections at Braidwood Station, Unit 1, in accordance with the station's technical specifications (TSs). This was the 14th refueling outage for Braidwood Station, Unit 1.
Braidwood Station, Unit 1, has four recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 6,633 thermally-treated, Alloy 690 tubes that have an outside diameter of 0.6875 inches, and a nominal wall thickness of 0.040 inches. The tubes are supported by Type 410 stainless steel, lattice-grid tube supports, and flat fan bars. The tubes were hydraulically-expanded at each end for the full depth of the tubesheet.
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
By letter dated June 5, 2009 (ADAMS Accession No. ML091560518), the licensee submitted Licensee Event Report 2009-001-00 that documented a tube that should have been plugged during the fall 2007, refueling outage per the licensee's TSs. The tube contained an indication that was caused by a loose part.
The NRC staff summarized this finding in Information Notice 2010-05 "Management of Steam Generator Loose Parts and Automated Eddy Current Data Analysis," (ADAMS Accession No. ML093640691 ).
Based on a review of the information provided by the licensee, the NRC staff concludes that the licensee provided the information required by their TSs. The SG tube inspections at Braidwood Station, Unit 1, appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. No additional follow-up is required at this time.
Principal Contributor: A. Johnson Date: April 16, 2010 ENCLOSURE
 
ML101050241                          *SE Memo Date                NRR-106 OFFICE            LPL3-21PM              LPL3-2/LA              DCIICSGB/BC          LPL3-2/BC NAME              MDavid                THarris                  RTaylor              SCampbell IIDATE            4/15/10              14/1 5/10                3/8/10              4/16/10}}

Latest revision as of 01:17, 12 March 2020

Review of Spring 2009 Steam Generator Tube Inservice Inspection Report
ML101050241
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 04/16/2010
From: David M
Plant Licensing Branch III
To: Pardee C
Exelon Generation Co
David Marshall NRR/DORL/LPL3-2 415-154
References
TAC ME1811
Download: ML101050241 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 16, 2010 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUB~IECT: BRAIDWOOD STATION, UNIT 1 - REVIEW OF SPRING 2009 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT (TAC NO. ME1811)

Dear Mr. Pardee:

By letter to the Nuclear Regulatory Commission (NRC) dated July 16, 2009 (Agencywide Documents Access and Management System Accession No. ML092050259), Exelon Generation Company, LLC (the licensee), submitted information pertaining to the 2009 steam generator tube inspections at Braidwood Station, Unit 1, in accordance with the station's technical specifications (TSs). This was the 14th refueling outage for Braidwood Station, Unit 1.

The NRC staff has completed its review of the report and concludes that the licensee has provided the information required by the station's TSs, and that no additional follow-up is required at this time. A copy of the NRC staff's evaluation is enclosed.

~;t4J;;oQ M~all J. Davi'k::'lr Project Manager Plant licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456

Enclosure:

Review of Spring 2009 Steam Generator Tube Inservice Inspections cc w/encl: Distribution via ListServ

OFFICE OF NUCLEAR REACTOR REGULATION REVIEW OF SPRING 2009 STEAM GENERATOR TUBE INSERVICE INSPECTIONS BRAIDWOOD STATION. UNIT 1 DOCKET NO. 50-456 By letter to the Nuclear Regulatory Commission (NRC) dated July 16, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092050259), Exelon Generation Company, LLC (the licensee), submitted information pertaining to the 2009 steam generator (SG) tube inspections at Braidwood Station, Unit 1, in accordance with the station's technical specifications (TSs). This was the 14th refueling outage for Braidwood Station, Unit 1.

Braidwood Station, Unit 1, has four recirculating SGs designed and fabricated by Babcock and Wilcox International. Each SG has 6,633 thermally-treated, Alloy 690 tubes that have an outside diameter of 0.6875 inches, and a nominal wall thickness of 0.040 inches. The tubes are supported by Type 410 stainless steel, lattice-grid tube supports, and flat fan bars. The tubes were hydraulically-expanded at each end for the full depth of the tubesheet.

The licensee provided the scope, extent, methods, and results of its SG tube inspections in the document referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the inspection findings.

By letter dated June 5, 2009 (ADAMS Accession No. ML091560518), the licensee submitted Licensee Event Report 2009-001-00 that documented a tube that should have been plugged during the fall 2007, refueling outage per the licensee's TSs. The tube contained an indication that was caused by a loose part.

The NRC staff summarized this finding in Information Notice 2010-05 "Management of Steam Generator Loose Parts and Automated Eddy Current Data Analysis," (ADAMS Accession No. ML093640691 ).

Based on a review of the information provided by the licensee, the NRC staff concludes that the licensee provided the information required by their TSs. The SG tube inspections at Braidwood Station, Unit 1, appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. No additional follow-up is required at this time.

Principal Contributor: A. Johnson Date: April 16, 2010 ENCLOSURE

ML101050241 *SE Memo Date NRR-106 OFFICE LPL3-21PM LPL3-2/LA DCIICSGB/BC LPL3-2/BC NAME MDavid THarris RTaylor SCampbell IIDATE 4/15/10 14/1 5/10 3/8/10 4/16/10

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