ML092870453

Request for Additional Information for the Review of the Duane Arnold Energy Center License Renewal Application - Scoping and Screening Review

ML092870453
Person / Time
Site:	Duane Arnold
Issue date:	11/02/2009
From:	Harris B License Renewal Projects Branch 1
To:	Costanzo C NextEra Energy Duane Arnold
Harris B, NRR/DLR, 415-2277
References
TAC MD9769
Download: ML092870453 (6)

Text

November 2, 2009 Mr. Christopher Costanzo Vice President, Nuclear Plant Support NextEra Energy Duane Arnold, LLC P.O. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION -

SCOPING AND SCREENING REVIEW (TAC NO. MD9769)

Dear Mr. Costanzo:

By letter dated September 30, 2008, as supplemented by letter dated January 23, 2009, FPL Energy Duane Arnold, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License DPR-49 for the Duane Arnold Energy Center. The staff of the U.S. Nuclear Regulatory Commission (the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its scoping and screening review from August 24, 2009, through August 28, 2009, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Ken Putnam, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2277 or by e-mail at Brian.Harris2@nrc.gov.

Sincerely,

/RA by Bo Pham For/

Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc w/encl: See next page

November 2, 2009 Mr. Christopher Costanzo Vice President, Nuclear Plant Support NextEra Energy Duane Arnold, LLC P.O. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION -

SCOPING AND SCREENING REVIEW (TAC NO. MD9769)

Dear Mr. Costanzo:

By letter dated September 30, 2008, as supplemented by letter dated January 23, 2009, FPL Energy Duane Arnold, LLC, submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54) for renewal of Operating License DPR-49 for the Duane Arnold Energy Center. The staff of the U.S. Nuclear Regulatory Commission (the staff) is reviewing this application in accordance with the guidance in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. During its scoping and screening review from August 24, 2009, through August 28, 2009, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the Enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Ken Putnam, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2277 or by e-mail at Brian.Harris2@nrc.gov.

Sincerely,

/RA by Bo Pham For/

Brian K. Harris, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

See next page ADAMS Accession No.: ML092870453 OFFICE:

PM:RPB1:DLR LA:RPOB:DLR BC:RPB1:DLR PM:RPB1:DLR NAME:

BHarris YEdmonds BPham BHarris (Signature)

DATE:

10/20/09 10/20/09 10/30/09 11/2/09 OFFICIAL AGENCY RECORD

Letter to Christopher Costanzo from Brian K. Harris dated November 2, 2009

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION -

SCOPING AND SCREENING REVIEW (TAC NO. MD9769)

DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

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Duane Arnold Energy Center cc:

Mr. M. S. Ross Vice President and Associate General Counsel Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Ms. Marjan Mashhadi Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW Suite 220 Washington, DC 20004 Mr. Steven R. Catron Manager, Regulatory Affairs Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324 U.S. Nuclear Regulatory Commission Resident Inspector=s Office Rural Route #1 Palo, IA 52324 Mr. Mano Nazar Senior Vice President and Nuclear Chief Operating Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408 Mr. D. A. Curtland Plant Manager Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785 Abdy Khanpour Vice President, Engineering Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408 Ms. Melanie Rasmussen Radiation Control Program Director Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319-0075 Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404 Mr. Raj Kundalkar, Vice President Fleet Organizational Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. McHenry Cornell Director, Licensing and Performance Improvement Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420

ENCLOSURE DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI 2.1-1 Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 54.4(a)(1), the applicant must consider all safety-related systems, structures and components (SSCs) relied upon to remain functional during and following a design basis event (DBE) to ensure the following functions: (1) the integrity of the reactor coolant pressure boundary; (2) the ability to shut down the reactor and maintain it in a safe shutdown condition; or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1), 10 CFR 50.67(b)(2), or 10 CFR Part 100.11.

As discussed, during the scoping and screening methodology audit performed on-site August 24-28, 2009, the staff determined that the applicant had not included certain components, classified as safety-related in the equipment database, within the scope of license renewal in accordance with 10 CFR 54.4(a)(1).

The staff requests that the applicant perform a review of the issue and provide the basis for not including certain components, classified as safety-related in the equipment database, within the scope of license renewal in accordance with 10 CFR 54.4(a)(1). Indicate if the review concludes that use of the scoping methodology precluded: (1) the identification of safety-related SSCs which should have been included within the scope of license renewal in accordance with 10 CFR 54.4(a)(1), and (2) the identification of nonsafety-related SSCs that could interact with safety-related SSCs, and which were not specifically exempted by your current licensing basis (CLB), and therefore should have been considered within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations to be performed to address the 10 CFR 54.4(a)(1) and (a)(2) criteria. As part of your response, list any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.

RAI 2.1-2 Pursuant to 10 CFR 54.4(a)(2), the applicant must consider all nonsafety-related SSCs, whose failure could prevent the satisfactory accomplishment of safety-related functions, for SSCs relied on to remain functional during and following a DBE to ensure (1) the integrity of the reactor coolant pressure boundary; (2) the ability to shut down the reactor and maintain it in a safe shutdown condition; or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1), 10 CFR 50.67(b)(2), or 10 CFR 100.11. The license renewal application stated that the applicant had used the guidance contained in Appendix F, of NEI 95-10, Industry Guidelines for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule, (NEI 95-10) to identify the nonsafety-related SSCs to be included within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

(A)

As discussed, during the scoping and screening methodology audit, performed on-site August 24-28, 2009, the staff determined that certain nonsafety-related tubing, which is a portion of a nonsafety-related piping system attached to safety-related SSCs, had not been included within the scope of license renewal. The applicant indicated that the interface between the pipe and the tubing identified the boundary of the nonsafety-related component to be included within the scope of license renewal (the pipe was included while the tubing was not). The staff requests that the applicant perform a review of the issue and provide the basis for not including certain nonsafety-related tubing, which is a portion of a nonsafety-related piping system attached to safety-related SSCs, within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

(B) During the scoping and screening methodology audit, performed on-site August 24-28, 2009, the staff determined that the nonsafety-related trash bars and trash rake IS-83, located adjacent to or within the safety-related intake structure, had not been included within the scope of license renewal. The staff requests that the applicant perform a review of the issue and provide the basis for not including the trash bars and trash rake IS-83, located adjacent to or within the safety-related intake structure, within the scope of license renewal in accordance with 10 CFR 54.4(a)(2).

Indicate if the review concludes that use of the scoping methodology precluded the identification of nonsafety-related SSCs that could interact with safety-related SSCs, and which were not specifically exempted by your CLB, and therefore should have been considered within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). Describe any additional scoping evaluations to be performed to address the (a)(2) criteria. As part of your response, list any additional SSCs included within the scope as a result of your efforts, and list those structures and components for which aging management reviews were conducted. For each structure and component, describe the aging management programs, as applicable, to be credited for managing the identified aging effects.