ML15112A692
| ML15112A692 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/20/1998 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | Mccollum W DUKE POWER CO. |
| References | |
| NUDOCS 9811250141 | |
| Download: ML15112A692 (5) | |
Text
November 20, 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-1 001), 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 Section 3.5.8 of OLRP-1001.
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, original signed by:
Joseph M. Sebrosky, Project Manager 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\\RAI10.WPD OFFICE LA PM:PDLR PDLR:D NAME LBerry JSebrosky DATE 11/ (198 11/ m 19V 11/1p/98 OFFICIAL RECORD COPY 9112501 41 981 N
PDR ADOCK 05000269 P
PDR ti "f
DISTRIBUTION: Hard copy Docket File PUBLIC PDLR RF M. EI-Zeftawy ACRS T2E26 E-mail; F. Miraglia T. 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. 0. 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 Washington, DC 20006-3708 Chattooga River Watershed Coalition DJW@NEI.ORG P. 0. Box 2006 Clayton, GA 30525
REQUEST FOR ADDITIONAL INFORMATION OCONEE NUCLEAR STATION, UNITS 1. 2. AND 3 LICENSE RENEWAL APPLICATION, EXHIBIT A OLRP-1001 Section No.
3.5.8 Air Conditioning, Heating, Cooling and Ventilation Systems 3.5.8-1 Section 3.5.8 of OLRP-1001 includes a statement that the heating ventilation and air conditioning (HVAC) systems are those systems designed to maintain the ambient air conditions within the auxiliary building and include the auxiliary building ventilation (ABV) system, control room pressurization and filtration (CRPF).system, and penetration room ventilation (PRV) system. Are there safety-related HVAC systems other than these three systems located in other buildings (such as reactor building) that need to be considered in the aging management review? If yes, provide a basis not to include them in the aging management review.
3.5.8-2 For the ABV, CRPF and PRV systems, Subsections 3.5.8.1.1, 3.5.8.2.1 and 3.5.8.3.1 state that these system components are exposed externally to the ambient conditions within the auxiliary building. Internally, these system components are exposed to a ventilation air environment. In Subsections 3.5.8.1.2, 3.5.8.2.2, and 3.5.8.3.2, the OLRP states that these three systems contain ductwork and other components constructed of aluminum, galvanized steel and stainless steel. No applicable aging effects have been identified for the components constructed from these materials in a ventilation air environment. Based on the bases stated above, Duke concludes in Subsections 3.5.8.1.3, 3.5.8.2.3 and 3.5.8..3.3 that because no applicable aging effects have been identified for the components of the ABV, CRPF and PRV systems within the scope of license renewal, no aging management program is required for these three systems during the period of extended operation.
Provide a basis and justification to demonstrate that the conclusion that no aging management program is required for these three systems during the period of extended operation is also applicable for the portion of these systems exposed to the ambient conditions.
3.5.8-3 According to the staffs past review experience of other nuclear power plants, cracking of ductworks due to vibration-induced fatigue and loosening fasteners due to dynamic loading are very common types of aging effects identified in HVAC systems, especially in the vicinity of attached device types exposed to dynamic loads such as fans. Provide a justification of why these types of aging effects are not applicable for the HVAC systems at Oconee.
3.5.8-4 Provide a basis of why the attached devices (or device types) such as filters, hand valves (bodies), temperature transmitter (if performing a function subject to license renewal requirements), and heat exchangers, etc. are not considered in the aging management review.
3.5.8-5 Provide a justification of why loss of material due to mechanical wear of the ductwork systems is not considered a potential aging effect at Oconee.
Enclosure
2 3.5.8-6 It is the staff's understanding that the intended function for HVAC duct systems and attached devices (such as fan casings, filters, valves (bodies), and heat exchangers, etc.) is "pressure retaining" (passive intended function). However, no description of how to maintain this passive intended function is discussed in the application.
Provide an explanation, of how this passive intended function will be maintained.
3.5.8-7 Are there any parts of the systems and attached devices within the HVAC systems that are inaccessible for inspection? If yes, provide a description in the application of how the potential aging effects will be identified and what aging management program (or programs) will be relied on to maintain the integrity of the inaccessible parts of the HVAC systems. If the aging management program for the inaccessible areas is an evaluation of the acceptability of inaccessible areas based on conditions found in surrounding accessible areas, please provide information to show that conditions would exist in accessible areas that would indicate the presence of or result in degradation to such inaccessible areas. If different aging effects or aging management techniques are needed for the inaccessible areas, please provide a summary to address the following elements for the inaccessible areas: (1)
Preventive actions that will mitigate or prevent aging degradation. (2) Parameters monitored or inspected relative to degradation of specific structure and component intended functions. (3) Detection of aging effects before loss of structure and component intended functions. (4) Monitoring, trending, inspection, testing frequency, and sample size to ensure timely detection of aging effects and corrective actions. (5) Acceptance criteria to ensure structure and component intended functions. (6) Operating experience that provides objective evidence to demonstrate that the effects of aging will be adequately managed.