ML091120056
| ML091120056 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/27/2009 |
| From: | Gettys E License Renewal Projects Branch 1 |
| To: | Spence W Susquehanna |
| Gettys Evelyn, NRR/DLR/RLRA 415-4029 | |
| References | |
| TAC MD3019, TAC MD3020 | |
| Download: ML091120056 (7) | |
Text
April 27, 2009 Mr. William H. Spence President and Chief Nuclear Officer PPL Susquehanna, LLC Two N. Ninth St.
Allentown, PA 18101-1179
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION
Dear Mr. Spence:
By letter dated September 13, 2006, PPL Susquehanna, LLC submitted an application pursuant to Title 10 of the Code of Federal Regulation Part 54 (10 CFR Part 54), to renew the operating licenses for Susquehanna Steam Electric Station, Units 1 and 2, for review by the U.S. Nuclear Regulatory Commission (NRC or the Staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Duane Filchner, 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 at 301-415-4029 or e-mail evelyn.gettys@nrc.gov.
Sincerely,
/RA/ Jay Robinson for Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
As stated cc w/encl: See next page
ML091120056 OFFICE LA:DLR PM:RPB1:DLR BC: RPB1:DLR NAME SFigueroa EGettys (JRobinson for)
DPelton (JRobinson for)
DATE 04/24/09 04/27/09 04/27/09
ENCLOSURE SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION (RAI)
RAI 4.3.1-1 The Susquehanna Steam Electric Station (SSES) Fatigue Monitoring Program (FMP) relies on transient cycle monitoring to evaluate the fatigue usage described in the license renewal application. It is essential that all thermal and pressure activities are bounded by the design specifications and cycles of all significant thermal events are captured and logged. In the response to RAI B.3.1-1, dated August 01, 2008, it states that SSES FMP cycle counting assumes every event has a severity equal to that assumed in the design basis.
To ensure effectiveness and validity of the fatigue monitoring program, the staff requests additional information, as described below:
(a) Confirm that all monitored transient events were bounded by the design specifications.
(b) Specify the time (years) over which actual transient monitoring and cycle tracking activities took place. If there have been periods in which transient data are not recorded since the plant startup, for any type of transient, specify the affected time frame. For the time periods for which transients were not monitored, provide justification to demonstrate that the projected cycles for this unmonitored period are conservative.
RAI 4.3.1-2 LRA Section 4.3.1 states that Normal, upset, and test conditions used in the fatigue analyses of the RPV assembly are summarized in Table 4.3-1. Design cumulative usage factors for the limiting RPV assembly locations are obtained from applicable design reports and are summarized in Table 4.3-2. LRA Tables 4.3-1 and 4.3-2 include 60-year cycle projections and 60-year CUF projections, respectively, for Units 1 and 2.
- 1. LRA Table 4.3-1 shows that the 60-year projected cycles for a majority of transients are lower than the respective design cycles, approximately by a factor between 2 and 3 for both units. For startup and shutdown transients, the 60-year projected cycles are higher than the design cycles, by approximately 30%. LRA Table 4.3-2 shows that for some of the limiting RCPB locations, the 60-year projected CUF values are much lower than the 40-year design CUF values, up to a factor of 10 and even greater.
Describe the basis for the large reductions in CUF values with relatively minor reduction in cycle projections, in spite of some cases having projected cycles higher than the design cycles.
- 2. LRA Table 4.3-1 indicates that the ratios of the design cycles to the 60-year projected cycles are distinct for each transient. Describe how 60-year CUF projections were made.
RAI 4.3-9R In letter dated November 26, 2008, the applicant responded to RAI 4.3-9 by stating the following:
The dissolved oxygen levels in the SSES Unit 1 and Unit 2 feedwater systems, before and after the implementation of hydrogen water chemistry, are maintained at less than 50 parts per billion (ppb).
In addition, footnotes to the tables on page 4 and 5 of Enclosure 1 to PLA-6464 state that the environmental CUF values were determined assuming the following dissolved oxygen levels for the Feedwater system: 47 ppb with Normal Water Chemistry, 40 ppb with Hydrogen Water Chemistry for Unit 1; 40 ppb with Normal Water Chemistry and 39 ppb with Hydrogen Water Chemistry for Unit 2.
To facilitate its review and evaluation, the staff is requesting that the applicant:
a) Provide dissolved oxygen (DO) data for the SSES at full power for the three summer months of each of the following years: 1985, 1988 and 1991, for both Units 1 and 2. If the unit was not at full power during these periods, provide data from the next 3 month period that the unit was at full power.
b) Describe the methodology of Fen calculation which SSES used to deal with the situations where DO content in the feedwater system, over certain periods, has been consistently greater than 50 ppb.
c) Describe how water samples were taken, including the sampling locations, and justify that the DO data in the feedwater system shown in PLA-6464 are applicable to all NUREG/CR-6260 components for Fen calculations.
Letter to W. Spencer from E. Gettys, dated April 27, 2009 DISTRIBUTION:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSrxb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter EGettys FJaxheimer
Susquehanna Steam Electric Station, Units 1 and 2 cc Cornelius J. Gannon Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Robert M. Paley General Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Michael H. Crowthers Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Ronald E. Smith General Manager - Site Preparedness and Services PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Michael H. Rose Manager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Joseph J. Scopelliti Community Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467 Board of Supervisors Salem Township Bryan A. Snapp, Esq.
P.O. Box 405 Berwick, PA 18603-0035 Associate General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 Document Control Services PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Director, Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803
Susquehanna Steam Electric Station, Units 1 and 2 cc Dayne R. Brophy Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467