ML15112A340
| ML15112A340 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/03/1998 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| NUDOCS 9812070286 | |
| Download: ML15112A340 (5) | |
Text
December 3, 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-1001 and has identified, in the enclosure, areas where additional information is needed to complete its review. Specifically, the enclosed questions are from the Civil Engineering and Geosciences Branch regarding OLRP-1001 Section 4.16.
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, Project Manager 9812070286 981203 1
License Renewal Project Directorate PDR ADOCK 05000269 Division of Reactor Program Management P
PDR 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:
07 QQ43 See next page DOCUMENT NAME:G:\\SEBROSKY\\RA137.WPD OFFICE PM:PDLR D:PDLR NAME JSebrosky:_____
ClGrime_
_0 DATE 12/
198 12 198 OFFICIAL RECORD COPY
DISTRIBUTION: Hard copy bocket File PUBLIC PDLR RF M. EI-Zeftawy ACRS T2E26 E-mal R. Zimmerman Tom Cheng 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 M. Banic G. Hornseth 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
Oconee Nuclear Station (License 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, Ill, 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 Framatome 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 Chattooga River Watershed Coalition Washington, DC 20006-3708 P. 0. Box 2006 DJW@NEI.ORG Clayton, GA 30525
REQUEST FOR ADDITIONAL INFORMATION OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION, EXHIBIT A OLRP-1001 Section No.
4.16 Fire Protection Program 4.16-8 With regard to the "sample size" and "frequency" of the fire barrier inspection program, the application (Page 4.16-2) states that the sample size is not applicable for an existing program (fire barrier inspection program). The application also states that, at an inspection frequency of at least once every 18 months, exposed surfaces of fire walls are visually inspected and at least 10 percent of each type of fire barrier penetration seal is inspected. Clarify the inconsistency between the statement, sample size is not applicable for an existing program" and the statement, "at least 10 percent of each type of fire barrier penetration seal is inspected."
4.16-9 Clarify that the acceptance criteria of the fire barrier inspection program contains attributes necessary to manage all aging effects for those structures and components within the scope of the program. Discuss whether the aging effects "managed" by the acceptance criteria should be at least the same as those specified under the "Aging Effects" as shown in Page 4.16-2. Expand the coverage of aging effects listed in the "Acceptance Criteria" to include all aging effects listed in the "Aging Effects." (e.g., for fire doors, the acceptance criteria (no indication of loss of material) cannot cover the aging effects listed under the "Aging Effects.")
4.16-10 The following regard the fire water system test program:
- a.
Are there any buried sections of the high pressure service water system, low pressure service water system and service water system (Keowee)?
If yes, how will the corrosion and settlements of supports of the buried piping sections be detected and managed and which aging management programs are you relying on for license renewal? For the above ground portions of the fire water piping system, discuss how the cumulative aging effects on their supports will be managed?
- b.
With regard to the "Method" of this program, the application only mentions periodic performance or flow tests for piping, pumps, fire hydrants and deluge valves, and visual inspections for hose racks and some sprinkler heads. Provide a description of the methods that are to be used for detecting and managing corrosion (loss of material) of these piping systems and components. The description of these methods should Enclosure
2 address the detection of cumulative aging effects prior to an observed failure.
- c.
With regard to the "sample size," the application states that "the components that serve a fire protection function within the high pressure service water system, low pressure service water system and Keowee service water s, stem are tested or inspected and maintained on a periodic basis." Are all piping and components of these three systems associated with the fire protection function to be periodically "tested or inspected and maintained" at the same time? If not, what is the sample size for each test and/or inspection and provide the basis for this criteria.
- d.
On Page 4.16-4, the application states that the inspection and test frequencies are established based on the type of component and managed by plant procedures. It also states that acceptance criteria are specifically stated in the plant procedures that govern each inspection or test. Provide the demonstration that the inspection and test frequencies, and acceptance criteria associated with the current programs are adequate and will address the aging management of cumulative degradation due to aging during the extended period of operation.
4.16-11 Clarify if the fire barrier inspection program and fire water system test program are to be used to detect and manage loss of material, e.g., from corrosion, for the high pressure service water system, low pressure service water system and service water system (Keowee). If not, explain how the loss of material will be detected and managed for these systems, and which program will be credited as an aging management program for the management of this aging effect.