ML040230175
| ML040230175 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/22/2004 |
| From: | Lui T NRC/NRR/DRIP/RLEP |
| To: | Stinson L Southern Nuclear Operating Co |
| Liu T, NRR/DRIP/RLEP, 415-1315 | |
| References | |
| Download: ML040230175 (8) | |
Text
January 22, 2004 Mr. L. M. Stinson Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION
Dear Mr. Stinson:
By letter dated September 12, 2003, Southern Nuclear Operating Company, Inc. (SNC or the applicant) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, for review by the U.S. Nuclear Regulatory Commissions (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review. Specifically, the enclosed requests for additional information (RAIs) are from Sections 4.3.1, Fatigue of American Society of Mechanical Engineers (ASME) Class 1 Components; 4.3.3, Fatigue of ASME Non-Class 1 Components; and 4.3.4, Containment Tendon Pre-Stress.
These RAIs, in a draft format, have been provided to Mr. Jan Fridrichsen of your staff on November 25, 2003. The NRC staff has discussed draft versions of these RAIs, via a conference call, to provide clarifications to the SNC staff on December 11, 2003. Your responses to these RAIs are requested within 30 days from the date of this letter.
Mr. Fridrichsen has agreed to this request. If needed, the NRC staff is willing to meet or discuss with SNC again prior to the submittal of the applicants responses to provide clarifications to the staffs RAIs.
If you have any questions, please contact me at 301-415-1315 or e-mail tyl1@nrc.gov.
Sincerely,
/RA/
Tilda Liu, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
As stated cc w/encl: See next page
January 22, 2004 Mr. L. M. Stinson Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION
Dear Mr. Stinson:
By letter dated September 12, 2003, Southern Nuclear Operating Company, Inc. (SNC or the applicant) submitted an application pursuant to 10 CFR Part 54, to renew the operating licenses for Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, for review by the U.S. Nuclear Regulatory Commissions (NRC). The NRC staff is reviewing the information contained in the license renewal application (LRA) and has identified, in the enclosure, areas where additional information is needed to complete the review. Specifically, the enclosed requests for additional information (RAIs) are from Sections 4.3.1, Fatigue of American Society of Mechanical Engineers (ASME) Class 1 Components, 4.3.3, Fatigue of ASME Non-Class 1 Components, and 4.3.4, Containment Tendon Pre-Stress.
These RAIs, in a draft format, have been provided to Mr. Jan Fridrichsen of your staff on November 25, 2003. The NRC staff has discussed draft versions of these RAIs, via a conference call, to provide clarifications to the SNC staff on December 11, 2003. Your responses to these RAIs are requested within 30 days from the date of this letter.
Mr. Fridrichsen has agreed to this request. If needed, the NRC staff is willing to meet or discuss with SNC again prior to the submittal of the applicants responses to provide clarifications to the staffs RAIs.
If you have any questions, please contact me at 301-415-1315 or e-mail tyl1@nrc.gov.
Sincerely,
/RA/
Tilda Liu, Project Manager License Renewal Section A License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION: See next page Accession no.: ML040230175 Document Name: C:\\ORPCheckout\\FileNET\\ML040230175.wpd OFFICE LA:RLEP PM:RLEP SC:RLEP NAME YEdmonds TLiu SLee DATE 1/22/04 1/21/04 1/22/04 OFFICIAL RECORD COPY
DISTRIBUTION: Letter to Mr. L.M. Stinson, SNOC, Dated: January 22, 2004 Accession no.: ML040230175 HARD COPY RLEP RF T. Liu (PM)
H. Ashar J. Fair E-MAIL:
PUBLIC J. Craig D. Matthews F. Gillespie R. Barrett C. Grimes RidsNrrDe E. Imbro G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski S. Black B. Boger D. Thatcher G. Galletti C. Li J. Moore M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy B. Jain Y. (Renee) Li RLEP Staff C. Julian (R-II)
C. Patterson (R-II)
R. Fanner (R-II)
S. Peters L. Whitney D. Cummings/M. Lemoncelli (OGC)
Joseph M. Farley Nuclear Plant cc:
Mr. Don E. Grissette Mr. Charles R. Pierce General Manager - Plant Farley Manager - License Renewal Southern Nuclear Operating Company Southern Nuclear Operating Company Post Office Box 470 40 Inverness Center Parkway Ashford, Alabama 36312 Post Office Box 1295 Birmingham, Alabama 35201 Mr. B. D. McKinney Mr. Fred Emerson Licensing Manager Nuclear Energy Institute Southern Nuclear Operating Company 1776 I Street, N.W., Suite 400 Post Office Box 1295 Washington, DC 20006-3708 Birmingham, Alabama 35201-1295 Mr. M. Stanford Blanton, Esq.
Mr. William D. Oldfield Balch and Bingham Law Firm SAER Supervisor Post Office Box 306 Southern Nuclear Operating Company 1710 Sixth Avenue North Post Office Box 470 Birmingham, Alabama 35201 Ashford, Alabama 36312 Mr. J. B. Beasley, Jr.
Executive Vice President Southern Nuclear Operating Company 40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35201 Dr. D. E. Williamson State Health Officer Alabama Department of Public Health The RSA Tower 201 Monroe Street, Suite 1500 Montgomery, AL 36130-1701 Chairman Houston County Commission Post Office Box 6406 Dothan, Alabama 36302 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319
Enclosure JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION (RAI)
Section 4.3.1: Fatigue of ASME Class 1 Components RAI 4.3.1-1 Table 4.3.1 of the LRA provides the current cycle counts and estimated cycle counts at 60 years of plant operation for transients used in the design of Class 1 components. Note 5 of the table indicates that step load change transients were not counted prior to the installation of fatigue monitoring software, and that the number of these prior transients would be estimated using the current fatigue monitoring software. Describe the method that will be used to estimate the number of transient cycles that occurred prior to the installation of the fatigue monitoring software. Provide a list of the transients that will be monitored by the fatigue monitoring program.
RAI 4.3.1-2 The Westinghouse Owners Group issued Topical Report WCAP-14577, Revision 1-A, Aging Management for Reactor Internals, to address the aging management of the reactor vessel internals. Section 2.3.1 of the LRA indicates that WCAP-14577, Revision 1-A, was reviewed as a source of input information for FNP. The staffs review of WCAP-14577, Revision 1-A, identified a number of issues that should be addressed on a plant specific basis. Renewal Applicant Action Item 11 specified in WCAP-14577, Revision 1-A, indicates that the fatigue TLAA of the reactor vessel internals should be addressed on a plant specific basis. Discuss the design basis for the components listed in Table 3-3 of WCAP-14577, Revision 1-A. Indicate how fatigue of these components is managed.
RAI 4.3.1-3 The Westinghouse Owners Group has issued the generic Topical Report WCAP-14574-A to address aging management of pressurizers. Section 2.3.1 of the LRA indicates that WCAP-14577, Revision 1-A was reviewed as a source of input information for FNP. The staffs review of WCAP-14574-A identified a number of issues that should be addressed on a plant specific basis. Renewal Applicant Action Item 1 requests the applicant to demonstrate that the pressurizer sub-component cumulative usage factors (CUFs) remain below 1.0 for the period of extended operation. Table 2-10 of WCAP-14574-A indicates that the ASME Section III Class 1 fatigue CUF criterion could be exceeded at several pressurizer sub-component locations during the period of extended operation. WCAP-14574-A also identified recent unanticipated transients that were not considered in the original ASME Section III Class 1 fatigue analyses, including inflow/outflow thermal transients. Provide the following information:
a.
Confirm that the additional transients discussed in WCAP-14574-A, not considered in the original design, have been addressed at FNP.
b.
Show the ASME Section III Class 1 current licensing basis (CLB) CUFs for the applicable sub-components of the FNP pressurizers specified in Table 2-10 of WCAP-14574-A and the corresponding CUFs for the extended period of operation.
c.
Discuss the impact of the environmental fatigue correlations provided in NUREG/CR-6583, Effects of light-water reactor (LWR) Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, and NUREG/CR-5704, Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels, on the above results.
RAI 4.3.1-4 Section 4.3.1 of the LRA indicates that the fatigue usage for the surge line is not expected to exceed 1.0 during the period of extended operation. The LRA also indicates that stress based fatigue monitoring software was used to analyze the fatigue usage of the surge line hot leg nozzle. Describe the stress based fatigue monitoring of the surge line hot leg nozzle. Indicate whether there were any changes in the plant operations since the startup of Units 1 and 2 that could affect the fatigue usage of the surge line hot leg nozzle. Provide a copy of Reference 11.
Section 4.3.3: Fatigue of ASME Non-Class 1 Components RAI 4.3.3-1 Section 4.3.3 of the LRA indicates that the number of thermal cycles for the emergency diesel generator (EDG) air start subsystem may exceed 7,000 during the period of extended operation. The LRA also indicates that the equivalent number of full-temperature cycles will be less than 7,000 cycles. Describe the method used to calculate the equivalent number of full-temperature cycles.
Section 4.3.4: Containment Tendon Pre-Stress RAI 4.3.4-1 10 CFR 54.21(c)(1)(ii) requires that the applicant demonstrate the adequacy of the analysis projected for the extended period of operation. In order for the staff to make a reasonable assurance conclusion, the applicant is requested to provide the following information:
a.
Minimum required pre-stressing forces for each group of tendons, b.
Trend lines of the projected pre-stressing forces for each group of tendons based on the regression analysis of the measured pre-stressing forces (see NRC Information Notice 99-10 for more information).
c.
Plots showing comparisons of pre-stressing forces projected to the end of the extended period of operation with the minimum required pre-stress for each group of tendons.
RAI 4.3.4-2 In Section A.4.3 in the updated final safety analysis report (UFSAR) Supplement of the LRA, the applicant states, The calculation indicates that acceptable containment pre-stress will continue to exist throughout the extended period of operation. In order for the summary to be meaningful, as a minimum, the applicant should provide a Table showing the minimum required pre-stressing forces and the projected (to 60 years) pre-stressing forces for each group of
tendons which would demonstrate the validity of the analysis results. The applicant is requested to supplement this information in Section A.4.3 of the UFSAR Supplement.