ML083570552
| ML083570552 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  (DPR-049) |
| Issue date: | 01/07/2009 |
| From: | Maurice Heath Division of License Renewal |
| To: | |
| Heath, M, NRR/DLR/RLRA, 415-3137 | |
| References | |
| Download: ML083570552 (7) | |
Text
January 7, 2009 LICENSEE: FPL Energy Duane Arnold, LLC FACILITY: Duane Arnold Energy Center
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON DECEMBER 16, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FPL ENERGY DUANE ARNOLD, LLC, PERTAINING TO DEFICIENCIES DISCUSSED IN LETTER DATED DECEMBER 11, 2008, REVIEW STATUS OF THE LICENSE RENEWAL APPLICATION FOR THE DUANE ARNOLD ENERGY CENTER On December 16, 2008, the U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FPL Energy Duane Arnold, LLC held a telephone conference call to discuss the deficiencies discussed in the staffs December 11, 2008, letter, Review Status of the License Renewal Application for the Duane Arnold Energy Center (ML083290275). During this telephone conference, the applicant stated that they understood the deficiencies discussed, agreed to correct the deficiencies, and agreed to re-review the LRA to identify and correct similar deficiencies that may exist elsewhere in the application.
provides a listing of the participants.
The applicant has had an opportunity to comment on this summary.
/RA/ Dave Pelton for Maurice Heath, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-331
Enclosure:
List of Participants cc w/encl: See next page
ML083570552 OFFICE LA:DLR PM:RPB!:DLR BC:RPB1:DLR NAME SFigueroa MHeath DPelton DATE 1/6/08 1/7/08 1/7/08
ENCLOSURE 1 TELEPHONE CONFERENCE CALL DUANE ARNOLD ENERGY CENTER LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS DECEMBER 16, 2008 PARTICIPANTS AFFILIATIONS Maurice Heath U.S. Nuclear Regulatory Commission (NRC)
James Medoff NRC David Pelton NRC Garry Armstrong NRC Stanley Gardocki NRC Edward Smith NRC Ken Putnam FPL Energy Duane Arnold, LLC (DAEC)
Mike Fairchild DAEC Curt Bock DAEC Clara Rushworth DAEC Ken Chew DAEC Steve Carton DAEC Herb Giorgio DAEC Tom Byrne DAEC Miles Railey DAEC Bill Bryant DAEC
ENCLOSURE 2 REVIEW STATUS OF THE LICENSE RENEWAL APPLICATION FOR DUANE ARNOLD ENERGY CENTER DECEMBER 16, 2008 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FPL Energy Duane Arnold, LLC held a telephone conference call on December 16, 2008, to discuss and clarify the acceptance review status of the license renewal application for the Duane Arnold Energy Center (DAEC). The following items were identified as requiring additional information to complete the staffs acceptance review.
- 1. Table 3.1.2-1 of the application contains information on the reactor vessel (RV) that is not consistent with the plants current licensing basis documentation. General Electric Capsule Report No. GE-NE-B1100716, Revision 0, for Duane Arnold, which was submitted to the NRC in accordance with 10 CFR 50, Appendix H, identifies that the RV has four RV shells: an upper shell, an upper intermediate shell, a lower intermediate shell, and a lower shell. However, Table 3.1.2-1 of the application only lists three shells for the RV: an upper shell, an intermediate shell, and a lower shell. Furthermore, of these three shells, the application only identifies the RV intermediate shell as within the beltline of the RV. However, the Capsule Report identifies the RV lower intermediate shell and the RV lower shell as within the RV beltline region.
- 2. The condensation service environment is not consistently characterized in the application. For example, for the compressed air system, Table 3.3-1 of the application indicates that condensation is wet air/gas. Table 3.3.2-27 indicates that it is air/gas.
Table 3.0-1, under wet air/gas, indicates that condensation is considered raw water.
However, under raw water in Table 3.0-1, it does not discuss condensation.
- 3. Metal fatigue of non-Class 1 components is not addressed as time-limited aging analysis (TLAA) as indicated in the application. For example, Sections 3.3.2.2.1 and 3.3.3 indicate that metal fatigue of the auxiliary system is evaluated in Section 4.3 of the application. However, Section 4.3 only addresses metal fatigue of the reactor vessel, Class 1 piping, and core plate rim hold-down bolts.
- 4. Information in Appendix C, Responses to BWRVIP Application Action Items, is not consistent with that in the application. For example, Item 4 in Table C-4 states, The DAEC SBLC nozzle has been evaluated for fatigue and shown to be acceptable for 60 years. See Section 4 of this application. However, the staff could not find this information in Section 4 of the application. For another example, Item 4 in Table C-7 states, Of these, fatigue is a TLAA for the CRD stub tube and housing and was determined to be acceptable for 60 years. See Section 4 of this application. However, Table 4.3-2 of the application indicates that these components are exempted.
- 5. Chapter 3 of the application contains inconsistent documentation of the potential degradation of heat transfer capability due to fouling for heat exchanger or air cooler surfaces that are exposed to raw water. Sometimes fouling is indicated as an applicable aging effect and sometimes it is not.
- 6. Chapter 3 of the application identifies the plant water environment as either treated water or raw water. However, the specific water environment, such as reactor coolant, closed-cycle cooling, and borated water (for the standby liquid control system), and specific environmental details, such as water temperature and fluence level, affect the assessment of potential aging effects and aging management. The applicants generalization of water environment causes technical information ambiguities in the application. For example, the application identifies cracking as a potential aging effect for some stainless steel components in treated water but not for others, creating inconsistencies with no explanation.
- 7. Section 2.0 of the application indicates that the plants integrated plant assessment methodology follows the approach recommended in NEI 95-10. However, NEI-95-10, Section 3.3, Documenting the Scoping Process, indicates that the applicant should identify systems, structures, and components functions that meet the requirements of 10 CFR 54.4(b) and therefore are intended functions. The application does not contain this information for specific systems, structures, and components. It merely repeats the rule language in 10 CFR 54.4(a). The staff sampled sections of the FSAR and often could not determine why a system is or is not within the scope of license renewal based on the FSAR description.
- 8. Section 4.7, Other Plant-Specific TLAAs, of the application contains mostly concluding statements of TLAA evaluations. For example, Section 4.7.4, Evaluation of thermal Fatigue Effects on Steam Lead and Inlet to RPV, states that the temperature cycles have been increased by 1.5 and backflow cycles have been added. It then states that the additional cycles during a 60 year life can be tolerated. There is no justification for the assumptions, such as the factor 1.5 and the number of backflow cycles. It also does not discuss the current status, such as the number of cycles experienced, and the acceptance criteria for the TLAA evaluation. Furthermore, no reference for the TLAA is provided in the application.
- 9. The application does not identify any aging effects for rubber, elastomer, or thermoset polymer for system components.
Discussion: Based on the discussion with the applicant, the staff indicated that the items listed required additional information for the staff to complete the acceptance review of the license renewal application. Therefore, the applicant will clarify the information.
Letter to FPL Energy Duane Arnold, LLC From M. Heath Dated January 07, 2009 DISTRIBUTION:
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON DECEMBER 16, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FPL ENERGY DUANE ARNOLD, LLC, PERTAINING TO THE REVIEW STATUS DUANE ARNOLD ENERGY CENTER, LICENSE RENEWAL APPLICATION HARD COPY:
DLR R/F E-MAIL:
PUBLIC RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSrxb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter MHeath KFeintuch
Duane Arnold Energy Center cc:
Mr. J. A. Stall Executive Vice President, Nuclear and Chief Nuclear Officer Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. M. S. Ross Managing Attorney 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 T. O. Jones Vice President, Nuclear Operations Mid-West Region Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408 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 Daniel K. McGhee Iowa Department of Public Health Bureau of Radiological Health 321 East 12th Street Lucas State Office Building, 5th Floor Des Moines, IA 50319-0075 Chairman, Linn County Board of Supervisors 930 1st Street SW Cedar Rapids, IA 52404 Peter Wells, Acting Vice President, Nuclear Training and Performance Improvement Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mark E. Warner Vice President, Nuclear Plant Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Richard L. Anderson Vice President Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785