ML091070042

Request for Additional Information Related to Request for Relief No. CR-26

ML091070042
Person / Time
Site:	LaSalle
Issue date:	04/24/2009
From:	Sands S Plant Licensing Branch III
To:	Pardee C Exelon Nuclear
Sands S,NRR/DORL, 415-3154
References
TAC MD9817, TAC MD9818
Download: ML091070042 (3)

Text

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• • • • 1l Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SU B..IECT: LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF NO. CR-26 (TAC NOS. MD9817 AND MD9818)

Dear Mr. Pardee:

By letter to the Nuclear Regulatory Commission (NRC) dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760276), as supplemented by letter dated November 18, 2008 (ADAMS Accession No. ML083260525),

Exelon Generation Company, LLC (the licensee), submitted a request for its second 10-year interval inservice inspection program plan Request for Relief No. CR-26, for the LaSalle County Station, Units 1 and 2. The licensee requested NRC approval of relief from existing American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plants Components," requirements on the basis that compliance with the specified requirements was impractical due to plant design.

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 March 26, 2009, it was agreed that you would provide a response 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 NRC's 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) 415-3154.

Sin.cerel y ,. ..... ~ .

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'. .' It t:,,--, d ." ; : . " 1t-ddJ St~p: n P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegUlation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION, UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 In reviewing the Exelon Generation Company's (Exelon's) submittal dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760276), as supplemented by letter dated November 18,2008 (ADAMS Accession No. ML083260525), related to Exelon's submittal for its second 10-year interval inservice inspection (lSI) program plan Request for Relief No. CR-26 for the LaSalle County Station (LSCS), Units 1 and 2, the NRC staff has determined that additional information is needed to complete the review of your submittal. Exelon requested Nuclear Regulatory Commission (NRC) approval of relief from existing American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"

requirements on the basis that compliance with the specified requirements were impractical due to plant design. Exelon submitted this relief request for those ASME code,Section XI weld examinations performed during the second 10-year lSI interval where the inspection coverage achieved was less than or equal to 90 percent.

The ASME Code of record for LSCS, Units 1 and 2, second 1O-year interval lSI program is the 1989 Edition of the ASME Code,Section XI with no Addenda. The NRC staff has determined that the following information is needed in order to complete its review:

1. Reorganize and label information from the November 18, 2008, supplemented submittal, and clearly indicate how the information from the original and supplemented submittals are connected.

2. Provide additional information to better describe the impracticalities associated with each of the limited examinations.

3. Several of the cross-sectional drawings seem to indicate a higher percentage of coverage than is stated in the original submittal. Verify that the coverage percentages cited in the original submittal are accurate and consistent with the cross-sectional drawings.

4. Address whether or not additional coverage of the subject welds could have been achieved if advanced inspection technologies (e.g., phased array ultrasonic transducers) had been applied.

5. For those subject welds associated with pump casings encased in concrete, identify any actions Exelon intends to take regarding inspection of these welds if access is gained due to pump disassembly in the future.

6. Identify if any indications were observed in the subject welds based upon the limited examinations that were performed, and discuss how these indications were dispositioned.

ENCLOSURE

Mr. Charles G. Pardee April 24, 2009 President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF NO. CR-26 (TAC NOS. MD9817 AND MD9818)

Dear Mr. Pardee:

By letter to the Nuclear Regulatory Commission (NRC) dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760276), as supplemented by letter dated November 18, 2008 (ADAMS Accession No. ML083260525),

Exelon Generation Company, LLC (the licensee), submitted a request for its second 10-year interval inservice inspection program plan Request for Relief No. CR-26, for the LaSalle County Station, Units 1 and 2. The licensee requested NRC approval of relief from existing American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plants Components," requirements on the basis that compliance with the specified requirements was impractical due to plant design.

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 March 26, 2009, it was agreed that you would provide a response 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 NRC's 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) 415-3154.

Sincerely, IRAJ Stephen P. Sands, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:

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