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| | number = ML082890152 | | | number = ML082890152 |
| | issue date = 10/21/2008 | | | issue date = 10/21/2008 |
| | title = Summary of Telephone Conference Call Held on October 8, 2008, Between the Usnrc and PPL Susquehanna, Llc. Concerning Draft Requests for Additional Information Pertaining to the, License Renewal Application | | | title = Summary of Telephone Conference Call Held on October 8, 2008, Between the USNRC and PPL Susquehanna, Llc. Concerning Draft Requests for Additional Information Pertaining to the, License Renewal Application |
| | author name = Gettys E | | | author name = Gettys E |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| Line 61: |
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| Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. | | Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI. |
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| ENCLOSURE 2 D-RAI 4.3-11 The August 1, 2008, response to RAI B.3.1-2 indicates the FatiguePro software is used for stress-based fatigue (SBF) monitoring of the feedwater nozzle forgings, feedwater nozzle safe ends, and the control rod drive penetrations. The response to RAI B.3.1-1 also indicates that the SBF monitoring methodology was benchmarked against the relevant design basis stress report for each component to ensure valid fatigue monitoring program fatigue results. | | ENCLOSURE 2 D-RAI 4.3-11 The August 1, 2008, response to RAI B.3.1-2 indicates the FatiguePro software is used for stress-based fatigue (SBF) monitoring of the feedwater nozzle forgings, feedwater nozzle safe ends, and the control rod drive penetrations. The response to RAI B.3.1-1 also indicates that the SBF monitoring methodology was benchmarked against the relevant design basis stress report for each component to ensure valid fatigue monitoring program fatigue results. |
| : a. Describe the procedure used to benchmark the SBF monitoring locations against the relevant design reports. List the transients used for the benchmarking and indicate the design fatigue usage associated with each transient. | | : a. Describe the procedure used to benchmark the SBF monitoring locations against the relevant design reports. List the transients used for the benchmarking and indicate the design fatigue usage associated with each transient. |
| : b. Discuss how the SSES SBF monitoring addresses the concern raised in proposed Regulatory Information Summary, "Fatigue Analysis of Nuclear Power Plant Components," May 1, 2008 (73 FR 24094). Indicate whether any additional benchmarking of the SSES SBF monitoring is planned. | | : b. Discuss how the SSES SBF monitoring addresses the concern raised in proposed Regulatory Information Summary, "Fatigue Analysis of Nuclear Power Plant Components," May 1, 2008 (73 FR 24094). Indicate whether any additional benchmarking of the SSES SBF monitoring is planned. |
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Category:Meeting Summary
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2024-06-03
[Table view]
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Correction of License Authority Files
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Rquest for Additonal Information (RAI) for Emergency Plan (E-Plan) Revisions PLA-5567 - Attachment
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Draft Request for Additional Information (RAI) Response Regarding Amendment Request for Emergency Plan (E-Plan) Revisions
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Memorandum Regarding Report on the Status of Open TIAs Assigned to NRR
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Safety Evaluation Input for Proposed Changes to the Susquehanna, Units 1 & 2 Technical Specifications Implementing Operability Requirements for the Ultimate Heat Sink Spray Valves (TAC Nos. MB2119 & MB2120)
2023-03-31
[Table view] |
Text
October 21, 2008
LICENSEE: PPL Susquehanna, LLC
FACILITY: Susquehanna Steam Electric Station, Units 1 and 2
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 8, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on October 8, 2008, to discuss and clarify the staff's draft request for additional information (D-RAI) concerning the Susquehanna Steam Electric Station, Units 1 and 2, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's D-RAI.
provides a listing of the participants and Enclosure 2 contains a listing of the D-RAI discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
\RA\ Evelyn Gettys, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation
Docket Nos. 50-387 and 50-388
Enclosures:
As stated
cc w/encls: See next page
ML082890152 OFFICE LA:DLR PM:RPB1:DLR BC: RPB1:DLR NAME IKing EGettys DPelton DATE 10/17/08 10/21/08 10/21/08 TELEPHONE CONFERENCE CALL SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS October 8, 2008 PARTICIPANTS AFFILIATIONSEvel yn Gett ys U.S. Nuclear Re gulator y Commission (NRC)John Fair NRCOn Yee NRC C. Yan g NRCDuane Filchner PPL Sus quehanna, LLC (PPL) Dave Fl yte PPLJeff Weik PPL Gar y Stevens ISI
ENCLOSURE 1
DRAFT REQUEST FOR ADDITIONAL INFORMATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 LICENSE RENEWAL APPLICATION October 8, 2008
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of PPL Susquehanna, LLC held a telephone conference call on October 8, 2008, to discuss and clarify the following draft request for additional information (D-RAI) concerning the Susquehanna Steam Electric Station (SSES), Units 1 and 2 license renewal application (LRA).
D-RAI 4.3-8 Section 4.3.2 of the LRA discusses the evaluation of the reactor pressure vessel (RPV) internals. The LRA indicates that structural evaluations were performed to address the effects of operation under extended power uprate conditions and the extended period of operation to 60 years. Explain how the number of reactor design transient cycles for 60 years of plant operation was determined for the analysis of the RPV internals.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 4.3-9 Section 4.3.3 of the LRA discusses the evaluation of the effects of the reactor coolant environment on the fatigue life of components and piping. Table 4.3-3 provides the 60-year environmental cumulative usage factor (CUF) for each component evaluated. Provide a summary of the environmental factor (F en) calculation for each component analyzed; including the values of oxygen level, temperature and strain rate used in the calculations. Also provide the basis for oxygen level, temperature and strain rate values used in the F en calculations.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 4.3-10 Table 4.3-2 of the LRA provides the 60-year CUF projections for the RPV shell at the shroud support for both units. List the transients that are the most significant contributors to the CUFs of both units. Discuss the fatigue analyses that were performed for the shroud support locations. Also include a discussion of any conservative assumptions that may have been used in the analyses.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
ENCLOSURE 2 D-RAI 4.3-11 The August 1, 2008, response to RAI B.3.1-2 indicates the FatiguePro software is used for stress-based fatigue (SBF) monitoring of the feedwater nozzle forgings, feedwater nozzle safe ends, and the control rod drive penetrations. The response to RAI B.3.1-1 also indicates that the SBF monitoring methodology was benchmarked against the relevant design basis stress report for each component to ensure valid fatigue monitoring program fatigue results.
- a. Describe the procedure used to benchmark the SBF monitoring locations against the relevant design reports. List the transients used for the benchmarking and indicate the design fatigue usage associated with each transient.
- b. Discuss how the SSES SBF monitoring addresses the concern raised in proposed Regulatory Information Summary, "Fatigue Analysis of Nuclear Power Plant Components," May 1, 2008 (73 FR 24094). Indicate whether any additional benchmarking of the SSES SBF monitoring is planned.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
Letter to PPL Susquehanna, LLC from E. Gettys, dated October 21, 2008
DISTRIBUTION
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON OCTOBER 8, 2008, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND PPL SUSQUEHANNA, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO 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
Rocco R. Sgarro Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179
Supervisor - Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467
Michael H. Crowthers Supervisor - 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
Joseph J. Scopelliti Community Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467
Bryan A. Snapp, Esq.
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
Susquehanna Steam Electric Station, Units 1 and 2
cc:
Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406 Berwick, PA 18603-0467
Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035
Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803
