ML033390305
| ML033390305 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/02/2003 |
| From: | Tilda Liu NRC/NRR/DRIP/RLEP |
| To: | |
| Liu T, NRR/DRIP/RLEP, 415-1315 | |
| References | |
| GL-96-003, RG-1.190, TAC MC0774, TAC MC0775 | |
| Download: ML033390305 (8) | |
Text
December 2, 2003 LICENSEE:
Southern Nuclear Operating Company FACILITY:
Joseph M. Farley Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF CONFERENCE CALL BETWEEN THE NRC AND THE SOUTHERN NUCLEAR OPERATING COMPANY CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAIs) ON JOSEPH M. FARLEY NUCLEAR PLANT, UNITS I AND 2, LICENSE RENEWAL APPLICATION (TAC NOS. MC0774 AND MC0775).
The U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the Southern Nuclear Operating Company (SNC) participated in a conference call on October 27, 2003, to discuss the staffs questions on Section 4, Time Limited Aging Analysis (TLAA), of the Joseph M. Farley, Unit 1 and 2, license renewal application (LRA). On the basis of the discussion, the applicant was able to better understand the staff's questions. No staff decisions were made during the conference call. In some cases, the applicant agreed to provide information for clarification.
A summary of the questions discussed and the applicant's proposed actions are presented below:
D-RAI 4.2.1-1:
Section 4.2.1 states that vessel fluence to 54 effective full-power years (EFPYs) has been calculated in accordance with the guidance in RG 1.190, Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence. Please provide information (or a reference) which explains how the guidance in RG 1.90 was followed.
The SNC indicated that the question is clear. The applicant stated that it will submit its formal response to this question once the request of additional information (RAI) is issued by the staff for this item.
D-RAI 4.2.3-1:
The LRA lists the low-temperature overpressure protection (LTOP) TLAA being provided in Section 4.2.3 of the application. However, LRA Section 4.2.3 is TLAA on pressurized thermal shock. Is the LTOP TLAA actually provided in LRA Section 4.5.3?
The staff and the applicant discussed this issue. The applicant agreed to provide the information on its particular Cold Overpressure Mitigation Analysis as requested by the staff. The applicant also stated that it will provide Reference 20, SM-90-1706-001, Revision 6, "Evaluate RHR Relief Valve Flow," Southern Nuclear Operating Company, July 1998, that is listed in Section 4.6 of LRA under References, in order to resolve this issue.
D-RAI 4.2.5-1 For Section 4.2.5, have the pressure-temperature limits report (PTLR) references been updated to include fluence methods in agreement with the guidance in RG 1.190?
The staff and the applicant discussed whether the PTLR references are updated.
Based on the discussion, the applicant agreed to provide a copy of the PTLR references, including those referenced in GL 96-03, "Relocation of the pressure temperature limits curves and low temperatures overpressure protection system limits,"
dated January 31, 1996.
A copy of the e-mail containing the staffs questions or D-RAIs that was sent to the applicant is provided in the Enclosure 1. A list of the participants in the conference call is provided in. The SNC has had an opportunity to review and comment on this summary.
/RA/
Tilda Y. Liu, Project Manager License Renewal Section License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos: 50-348 and 50-364
Enclosures:
As stated cc w/enclosures: See next page D-RAI 4.2.5-1 For Section 4.2.5, have the pressure-temperature limits report (PTLR) references been updated to include fluence methods in agreement with the guidance in RG 1.190?
The staff and the applicant discussed whether the PTLR references are updated.
Based on the discussion, the applicant agreed to provide a copy of the PTLR references, including those referenced in GL 96-03, "Relocation of the pressure temperature limits curves and low temperatures overpressure protection system limits,"
dated January 31, 1996.
A copy of the e-mail containing the staffs questions or D-RAIs that was sent to the applicant is provided in the Enclosure 1. A list of the participants in the conference call is provided in. The SNC has had an opportunity to review and comment on this summary.
/RA/
Tilda Y. Liu, Project Manager License Renewal Section License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket Nos: 50-348 and 50-364
Enclosures:
As stated cc w/enclosures: See next page DISTRIBUTION: See next page Accession No. ML033390305 Document Name: C:\\ORPCheckout\\FileNET\\ML033390305.wpd OFFICE LA:RLEP Intern:RLEP PM:RLEP SC:RLEP NAME MJenkins ZCruz-Perez TLiu for TLiu SLee DATE 11/28/03 12/1/03 12/1/03 12/2/03 OFFICIAL RECORD COPY
DISTRIBUTION:
HARD COPY RLEP RF T. Liu (PM)
F. Rinaldi C. Hawes Z. Cruz E-MAIL:
PUBLIC J. Craig D. Matthews F. Gillespie C. Grimes RidsNrrDe E. Imbro G. Bagchi K. Manoly W. Bateman J. Calvo R. Jenkins P. Shemanski H. Nieh J. Fair S. Black B. Boger D. Thatcher R. Pettis G. Galletti C. Li J. Moore R. Weisman M. Mayfield A. Murphy S. Smith (srs3)
S. Duraiswamy Y. L. (Renee) Li RLEP Staff C. Julian (R-II)
J. Medoff T. Johnson (R-II)
F. Rinaldi D. Cummings (OGC)
J. Cushing OPA B. Jain L. Whitney L. Lois
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 Post Office Box 1295 Ashford, Alabama 36312 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 Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 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
From: Tilda Liu To:
Jan Fridrichsen Date: 10/22/03 7:30PM
Subject:
Questions on Farley LRA Section 4 TLAAs Jan, Following are the questions that we currently have. If you would take sometime to review these and we can discuss this on the phone with DE reviewers (Jim Medoff and Lambro Lois) either Monday or Tuesday of next week. Just let me know.
~~~~~~~~
Questions/Comments on Section 4, TLAAs (Medoff)
Item 1:
The Farley LR applicant includes five subsections to the TLAA on neutron irradiation embrittlement (LRA Section 4.2):
4.2.1 - Neutron Fluence 4.2.2 - Upper Shelf Energy 4.2.3 - Pressurized Thermal Shock 4.2.4 - Adjusted Reference Temperature Calculations 4.2.5 - Pressure Temperature Limits Section 4.2.4 discusses the applicants calculation of the adjusted reference temperatures (RTndt) values for the 1/4 thickness (1/4T) locations of the Farley reactor vessels. These 1/4T RTndt values are used as inputs to the calculations of the pressure-temperature (P-T) limit values for the vessel, which the applicant discusses in Section 4.2.5 of the application.
However, the RTndt value calculations for the 3/4 thickness locations of the vessels are also used in the calculation of P-T limits for the vessels - which the applicant has failed to address in section 4.2.4 of the LRA. Usually the calculations of the RTndt values for the 1/4T and 3/4T locations are treated as a subset of the TLAA for the P-T limits and, up to now, have not yet been included as a separate TLAA subsection to the neutron embrittlement TLAA (4.2). Why is the calculation of the RTndt values for the 3/4 thickness locations of the vessels not included?
Item 2:
Application lists LTOP TLAA being provided in Section 4.2.3 of the application. However, LRA 4.2.3 is TLAA on pressurized thermal shock. Is the LTOP TLAA actually provided in 4.5.3 or where is it?
Item 3:
The LRA does not contain sufficient information for the review of Section 4.3.2, RCP flywheel.
(We will talk more about this in the call)
Item 4 Section 4.2.1, states that vessel fluence to 54 EFPYs has been calculated in accordance with the guidance in RG 1.190. Please provide information (or a reference) which explains how the guidance in RG 1.190 was followed.
Item 5 Section 4.2.5. Have the PTLR references been updated to include fluence methods in agreement with the guidance in RG 1.190?
ENCLOSURE 1
LIST OF PARTICIPANTS FOR CONFERENCE CALL ON DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAIs)
October 27, 2003 Participants Affiliation Tilda Liu NRC Zahira Cruz NRC Lambros Lois NRC Jan E. Fridrichsen SNC Jon E. Hornbuckle SNC William P. Evans SNC Michael A. Macfarlane SNC Charles R. Pierce SNC ENCLOSURE 2