ML072270701

Request for Additional Information Related to Requests for Relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for the Second Inservice Inspection Interval

ML072270701
Person / Time
Site:	Byron
Issue date:	08/17/2007
From:	Robert Kuntz NRC/NRR/ADRO/DORL/LPLIII-2
To:	Crane C Exelon Generation Co
Kuntz, Robert , NRR/DLPM, 415-3733
References
TAC MD4097, TAC MD4098, TAC MD4099, TAC MD4100, TAC MD4101, TAC MD4102, TAC MD4103, TAC MD4104, TAC MD4105, TAC MD4106
Download: ML072270701 (6)

Text

August 17, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SECOND TEN-YEAR INTERNAL RELIEF REQUESTS (TAC NOS. MD4097, MD4098, MD4099, MD4100, MD4101, MD4102, MD4103, MD4104, MD4105, AND MD4106)

Dear Mr. Crane:

By letter to the Nuclear Regulatory Commission (NRC) dated January 12, 2007, Exelon Generation Company, LLC submitted requests for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for the second inservice inspection interval, for Byron Station, Unit Nos. 1 and 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. During a discussion with your staff on August 15, 2007, it was agreed that you would provide a response 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. 50-454 and 50-455

Enclosure:

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

Mr. Christopher M. Crane August 17, 2007 President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO SECOND TEN-YEAR INTERNAL RELIEF REQUESTS (TAC NOS. MD4097, MD4098, MD4099, MD4100, MD4101, MD4102, MD4103, MD4104, MD4105, AND MD4106)

Dear Mr. Crane:

By letter to the Nuclear Regulatory Commission (NRC) dated January 12, 2007, Exelon Generation Company, LLC submitted requests for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for the second inservice inspection interval, for Byron Station, Unit Nos. 1 and 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. During a discussion with your staff on August 15, 2007, it was agreed that you would provide a response 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. 50-454 and 50-455

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 RidsNrrDciCvib CSydnor, NRR ADAMS Accession Number: ML072270701 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME RKuntz EWhitt RGibbs DATE 8/16/07 8/16/07 8/17/07 OFFICIAL RECORD COPY

Byron Station, Unit Nos. 1 and 2 Chairman Will County Board of Supervisors cc: Will County Board Courthouse Joliet, IL 60434 Illinois Emergency Management Agency Division of Disaster Assistance & Director - Licensing and Regulatory Affairs Preparedness via e-mail 1035 Outer Park Dr Springfield, IL 62704 Manager Regulatory Assurance - Byron via e-mail Document Control Desk - Licensing via e-mail Associate General Counsel via e-mail Mr. Dwain W. Alexander, Project Manager Westinghouse Electric Corporation Vice President - Regulatory Affairs via e-mail via e-mail Howard A. Learner Manager Licensing - Braidwood/Byron Environmental Law and Policy via e-mail Center of the Midwest 35 East Wacker Drive Senior Vice President - Midwest Operations Suite 1300 via e-mail Chicago, IL 60601-2110 Vice President - Regulatory Affairs U.S. Nuclear Regulatory Commission via e-mail Byron Resident Inspectors Office via e-mail Manager Licensing - Braidwood, Byron and LaSalle Ms. Lorraine Creek via e-mail RR 1, Box 182 Manteno, IL 60950 Senior Vice President - Midwest Operations via e-mail Chairman, Ogle County Board P.O. Box 357 Mr. Barry Quigley Oregon, IL 61061 3512 Louisiana Rockford, IL 61108 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, IL 61107 Attorney General 500 S. Second Street Springfield, IL 62701 Plant Manager - Byron Station via e-mail Site Vice President - Byron Station via e-mail Senior Vice President - Operations Support via e-mail

REQUEST FOR ADDITIONAL INFORMATION BYRON STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454 AND STN 50-455 In reviewing the Exelon Generation Companys (Exelons) submittal dated January 12, 2007, related to requests for relief from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for the second inservice inspection interval (ISI), for Byron Station, Units 1 and 2 (Byron), the NRC staff has determined that the following information is needed in order to complete its review:

Relief Request (RR) I2R-21 I2R-21-1:

RR I2R-21 did not indicate whether the limited scope surface examination of the seismic lug welds provided any indication of the presence of unacceptable flaws or conditions in accordance with the acceptance criteria of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Article IWB-3000. Therefore, the Nuclear Regulatory Commission (NRC) staff requests that you discuss whether the limited scope surface examination of these welds provided any indication of the presence of flaws or other relevant conditions that were determined to be unacceptable according to the acceptance criteria of the ASME Code,Section XI, Article IWB-3000.

I2R-21-2:

The NRC staff requests that you discuss the extent to which the seismic lug welds were examined during the first ISI interval and the preservice exam, including the percentage of credible surface examination coverage that was achieved during these previous examinations.

Discuss any relevant conditions that were found during these previous examinations.

I2R-21-3:

The NRC staff notes that a similar request was authorized for Braidwood Station, Units 1 and 2 on January 6, 2000. However, the authorization of this request was granted with the understanding that the licensee would perform a VT-1 visual examination of the accessible areas in the vicinity of the seismic weld lugs during the forthcoming ISI interval. Please discuss whether a VT-1 visual examination has been or will be performed for the accessible areas of the seismic lugs.

RR I2R-22 I2R-22-1:

Please indicate the percentage of credible surface examination coverage that was achieved during the examination of the accessible welded attachments located on the exposed outside surface of the containment penetration. If less than essentially 100 percent coverage was Enclosure

achieved for any of these welds, please provide supplemental information justifying why compliance with the ASME Code,Section XI requirements for essentially 100 percent surface examination coverage of these welds was impractical.

I2R-22-2:

RR I2R-22 did not indicate whether the surface examination of the accessible attachment welds provided any indication of the presence of unacceptable flaws or conditions in accordance with the acceptance criteria of the ASME Code,Section XI, Article IWC-3000. Therefore, the NRC staff requests that you discuss whether the surface examination of these welds provided any indication of the presence of flaws or other relevant conditions that were determined to be unacceptable according to the acceptance criteria of the ASME Code,Section XI, Article IWC-3000.

RR I2R-23 I2R-23-1:

RR I2R-23 did not indicate whether the limited scope volumetric examination of the specified pressurizer nozzle-to-vessel welds provided any indication of the presence of unacceptable flaws or conditions in accordance with the acceptance criteria of the ASME Code,Section XI, Article IWB-3000. Therefore, the NRC staff requests that you discuss whether the limited scope volumetric examination of these welds provided any indication of the presence of flaws or other relevant conditions that were determined to be unacceptable according to the acceptance criteria of the ASME Code,Section XI, Article IWB-3000.

I2R-23-2:

The NRC staff requests that you discuss the extent to which the specified pressurizer nozzle-to-vessel welds were examined during the first ISI interval and the preservice exam, including the percentage of credible surface examination coverage that was achieved during these previous examinations. Discuss any relevant conditions that were found during these previous examinations.

RR I2R-25 I2R-25-1:

RR I2R-25 did not indicate whether the limited scope volumetric examination of the reactor vessel head-to-flange weld provided any indication of the presence of unacceptable flaws or conditions in accordance with the acceptance criteria of the ASME Code,Section XI, Article IWB-3000. Therefore, the NRC staff requests that you discuss whether the limited scope volumetric examination of this weld provided any indication of the presence of flaws or other relevant conditions that were determined to be unacceptable according to the acceptance criteria of the ASME Code,Section XI, Article IWB-3000.

RR I2R-53 I2R-53-1:

RR I2R-53 did not indicate whether the limited scope volumetric examination of the residual heat removal heat exchanger (RHRHX) shell-to-flange weld provided any indication of the presence of unacceptable flaws or conditions in accordance with the acceptance criteria of the ASME Code,Section XI, Article IWC-3000. Therefore, the NRC staff requests that you discuss whether the limited scope volumetric examination of this weld provided any indication of the presence of flaws or other relevant conditions that were determined to be unacceptable according to the acceptance criteria of the ASME Code,Section XI, Article IWC-3000.

I2R-53-2:

The NRC staff requests that you discuss the extent to which the RHRHX shell-to-flange weld was examined during the first ISI interval and the preservice exam, including the percentage of credible volumetric examination coverage that was achieved during these previous examinations. Discuss any relevant conditions that were found during these previous examinations.