ML15112A313
| ML15112A313 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/18/1998 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| NUDOCS 9811240166 | |
| Download: ML15112A313 (5) | |
Text
November 18, 1998 Mr. William R. McCollum, Jr.
Vice President, Oconee Nuclear Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3, LICENSE RENEWAL APPLICATION
Dear Mr. McCollum:
By letter dated July 6, 1998, Duke Energy Corporation (Duke) submitted for the Nuclear Regulatory Commission's (NRC's) review an application pursuant to 10 CFR Part 54, to renew the operating licenses for the Oconee Nuclear Station (Oconee), Units 1, 2, and 3. Exhibit A to the application is the Oconee Nuclear Station License Renewal Technical Information Report (OLRP-1001), which contains the technical information required by 10 CFR Part 54. The NRC staff is reviewing the information contained in OLRP-1 001 and has identified, in the enclosure, areas where additional information is needed to complete its review. Specifically, the enclosed questions are from the Mechanical Engineering Branch regarding the following Sections of OLRP-1001: 3.5.6, 3.5.7, and 3.5.13.
Please provide a schedule by letter, electronic mail, or telephonically for the submittal of your responses within 30 days of the receipt of this letter. Additionally, the staff would be willing to meet with Duke prior to the submittal of the responses to provide clarifications of the staff's requests for additional information.
Sincerely, Joseph M. Sebrosky, Projectanager License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
Request for Additional Information cc w/encl: See next page Distribution: See next page DOCUMENT NAME: G:\\SEBROSKY\\RAI6.WPD OFFICE LA PDLR PDLR:D NAME ILBerry JSebrosky CGrime DATE i /98 k7
/1298v 14W/g8 OFFICIAL RECORD COPY 9811240166 981118.
PDR ADOCK 05000269 P
Oconee Nuclear Station tense Renewal) cc:
Paul R. Newton, Esquire Duke Energy Corporation Mr. J. E. Burchfield 422 South Church Street Compliance Manager Mail Stop PB-05E Duke Energy Corporation Charlotte, North Carolina 28201-1006 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Anne W. Cottingham, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice P. O. Box 629 Mr. Rick N. Edwards Raleigh, North Carolina 27602 Framatorne Technologies Suite 525 L. A. Keller 1700 Rockville Pike Manager - Nuclear Regulatory Licensing Rockville, Maryland '20852-1631 Duke Energy Corporation 526 South Church Street Manager, LIS Charlotte, North Carolina 28201-1006 NUS Corporation 2650 McCormick Drive, 3rd Floor Mr. Richard M. Fry, Director Clearwater, Florida 34619-1035 Division of Radiation Protection North Carolina Department of Senior Resident Inspector Environment, Health, and.
U. S. Nuclear Regulatory Commission Natural Resources 7812B Rochester Highway 3825 Barrett Drive Seneca, South Carolina 29672 Raleigh, North Carolina 27609-7721 Regional Administrator, Region II Gregory D. Robison U. S. Nuclear Regulatory Commission Duke Energy Corporation Atlanta Federal Center Mail Stop EC-12R 61 Forsyth Street, SW, Suite 23T85 P. 0. Box 1006 Atlanta, Georgia 30303 Charlotte, North Carolina 28201-1006 Virgil R. Autry, Director Robert L. Gill, Jr.
Division of Radioactive Waste Management Duke Energy Corporation Bureau of Land and Waste Management Mail Stop EC-12R Department of Health and P. 0. Box 1006 Environmental Control Charlotte, North Carolina 28201-1006 2600 Bull Street RLGILL@DUKE-ENERGY.COM Columbia, South Carolina 29201-1708 Douglas J. Walters County Supervisor of Oconee County Nuclear Energy Institute Walhalla, South Carolina 29621 1776 I Street, NW Suite 400 Washington, DC 20006-3708 Chattooga River Watershed Coalition DJW@NEI.ORG P. 0. Box 2006 Clayton, GA 30525
Distribution: Hard copy PUBLIC Docket File PDLR RF M. EI-Zeftawy, ACRS T2E2 F. Miraglia Y. Li J. Roe D. Matthews C. Grimes T. Essig G. Lainas J. Strosnider G. Bagchi H. Brammer T. Hiltz G. Holahan S. Newberry C. Gratton L. Spessard R. Correia R. Latta J. Peralta J. Moore R. Weisman M. Zobler E. Hackett A. Murphy T. Martin D. Martin W. McDowell S. Droggitis PDLR Staff H. Berkow D. LaBarge L. Plisco C. Ogle R. Trojanowski M. Scott C. Julian R. Architzel J. Wilson R. Wessman E. Sullivan R. Gill, Duke D. Walters, NEI
REQUEST FOR ADDITIONAL INFORMATION OCONEE NUCLEAR STATION, UNITS 1. 2. AND 3 LICENSE RENEWAL APPLICATION, EXHIBIT A OLRP-1001 Section No.
3.5.6 Auxiliary Systems 3.5.6-1 Based on the staffs experience, degradation of piping systems (e.g., cracking of weld) may potentially be caused by vibration (mechanical or hydrodynamic) loading.
Clarify whether this loading effect has been considered in the aging review for the auxiliary systems discussed in Section 3.5.6, and, if this effect is excluded, provide the basis for its exclusion.
3.5.6-2 Section 2.5.6 indicates that some portions of the auxiliary systems within the scope of license renewal are not designed to withstand the effects of a design basis earthquake. Clarify which components and piping segments within the category of "Seismic II over I" (a nonseismic Category I system, structure, or component whose failure could cause loss of safety function of a seismic Category I system, structure, or component) would be subject to aging management review. Additionally, clarify which aging management program will address these components and piping segments and specifically discuss implementation of the program to manage the applicable aging effects during the period of extended operation.
3.5.7 Process Auxiliaries 3.5.7-1 Based on the staffs experience, degradation of piping systems (e.g., cracking of weld) may potentially be caused by vibration (mechanical or hydrodynamic) loading.
Clarify whether this loading effect has been considered in the aging review for the process auxiliaries discussed in Section 3.5.7, and, if this effect is excluded, provide the basis for its exclusion.
3.5.7-2 Section 2.5.7 indicates that some portions of the process auxiliaries within the scope of license renewal are not designed to withstand the effects of a design basis earthquake. Clarify which components and piping segments within the category of "Seismic II over I" (a nonseismic Category I system, structure, or component whose failure could cause loss of safety function of a seismic Category I system, structure, or component) would be subject to aging management review. Additionally, clarify which aging management program will address these components and piping segments and specifically discuss implementation of the program to manage the applicable aging effects during the period of extended operation.
3.5.13 Keowee Hydroelectric Station 3.5.13-1 Based on the staffs experience, degradation of piping systems (e.g., cracking of weld) may potentially be caused by vibration (mechanical or hydrodynamic) loading.
Clarify whether this loading effect has been considered in the aging review for the Enclosure
2 Keowee Hydroelectric Station discussed in Section 3.5.13, and, if this effect is excluded, provide the basis for its exclusion.
3.5.13-2 Section 2.5.13 indicates that some portions of the Keowee Hydroelectric Station piping systems within the scope of license renewal are not designed to withstand the effects of a design basis earthquake. Clarify which components and piping segments within the category of "Seismic II over I" (a nonseismic Category I system, structure, or component whose failure could cause loss of safety function of a seismic Category I system, structure, or component) would be subject to aging management review. Additionally, clarify which aging management program will address these components and piping segments and specifically discuss implementation of the program to manage the applicable aging effects during the period of extended operation.