ML071840006

RAI, Twelfth Refueling Outage Steam Generator Service Inspection Summary Report

ML071840006
Person / Time
Site:	Braidwood
Issue date:	07/12/2007
From:	Robert Kuntz NRC/NRR/ADRO/DORL/LPLIII-2
To:	Crane C Exelon Generation Co
Kuntz, Robert, NRR/DLPM/PDIII-2 415-3733
References
TAC MD4199
Download: ML071840006 (4)

Text

July 12, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE 12TH REFUELING OUTAGE STEAM GENERATOR INSERVICE INSPECTION

SUMMARY

REPORT (TAC NO. MD4199)

Dear Mr. Crane:

By letter to the Nuclear Regulatory Commission (NRC) dated January 29, 2007, Exelon Generation Company, LLC submitted the refueling outage 12 steam generator inservice inspection summary report for Braidwood Station, Unit 2.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. A response to this request is requested within 30 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733.

Sincerely,

/RA/

Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-457

Enclosure:

Request for Additional Information cc w/encl: See next page

Mr. Christopher M. Crane Jully 12, 2007 President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BRAIDWOOD STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE 12TH REFUELING OUTAGE STEAM GENERATOR INSERVICE INSPECTION

SUMMARY

REPORT (TAC NO. MD4199)

Dear Mr. Crane:

By letter to the Nuclear Regulatory Commission (NRC) dated January 29, 2007, Exelon Generation Company, LLC submitted the refueling outage 12 steam generator inservice inspection summary report for Braidwood Station, Unit 2.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. A response to this request is requested within 30 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3733.

Sincerely,

/RA/

Robert F. Kuntz, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-457

Enclosure:

Request for Additional Information cc w/encl: See next page DISTRIBUTION:

PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMRKuntz RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr ADAMS Accession Number: ML071840006 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME RKuntz EWhitt RGibbs (THarris for)

DATE 7/12/07 7/10/07 7/12/07 OFFICIAL RECORD COPY

Braidwood Station Units 1 and 2 cc:

Document Control Desk - Licensing Chairman, Ogle County Board via e-mail Post Office Box 357 Oregon, IL 61061 Mr. Dwain W. Alexander, Project Manager Westinghouse Electric Corporation Manager Regulatory Assurance - Braidwood via e-mail via e-mail Ms. Bridget Little Rorem Director - Licensing and Regulatory Affairs Appleseed Coordinator via e-mail via e-mail Associate General Counsel Howard A. Learner via e-mail Environmental Law and Policy Center of the Midwest Senior Vice President - Midwest Operations 35 East Wacker Dr., Suite 1300 via e-mail Chicago, IL 60601-2110 Vice President - Regulatory Affairs U.S. Nuclear Regulatory Commission via e-mail Braidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Manager Licensing - Braidwood, Byron and LaSalle Braceville, IL 60407 via e-mail Ms. Lorraine Creek County Executive Secretary RR 1, Box 182 via e-mail Manteno, IL 60950 Illinois Emergency Management Agency Division of Disaster Assistance &

Preparedness 1035 Outer Park Dr Springfield, IL 62704 County Executive via e-mail Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Braidwood Station via e-mail Site Vice President - Braidwood via e-mail Senior Vice President - Operations Support via e-mail

REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNIT 2 DOCKET NO. 50-457 In reviewing the Exelon Generation Company, LLCs (Exelons) submittal dated January 29, 2007, related to the 12th refueling outage steam generator inservice inspection summary report, for Braidwood Station, Unit 2 (Braidwood), the Nuclear Regulatory Commission staff has determined that the following information is needed in order to complete its review:

1. Please discuss the extent to which indications attributed to wear, were inspected with a rotating probe to confirm the absence of cracking at these locations.

2. Please discuss the inspection results for the one previously plugged tube that was inspected at the location where the plug expansion zone existed. Please discuss the location of the plug expansion zone (e.g., is it greater than 17-inches below the top of the tubesheet).

3. Several tubes were identified with wear indications attributed to foreign objects/loose parts. Regarding the inspections performed for loose parts, please address the following:

(a) Discuss the extent to which a foreign object search and retrieval (FOSAR) was performed. If a FOSAR was performed, discuss the scope and results. If any foreign objects/loose parts were identified, discuss the source and nature of the part and the corrective action taken. If any foreign objects/loose parts were left in the steam generator, please discuss whether an analysis was performed to assess the effect the object/part may have on tube integrity.

(b) Two tubes were plugged for wear attributed to foreign objects. These two tubes were located in the interior of the bundle and the indications were located slightly below tube support plates. Given that the foreign object/loose part would have had to migrate through the tube bundle (presumably without causing any discernable damage to the other tubes) and interacted with the subject tubes for some period of time to cause a wear scar, please discuss the extent to which you evaluated the potential that some other degradation mechanism may have caused the indications (i.e., provide the basis for concluding the indications were attributable to wear.)

ENCLOSURE