ML15261A216
| ML15261A216 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/11/1999 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9901130206 | |
| Download: ML15261A216 (24) | |
Text
January 11, 1999 LICENSEE:
Duke Energy Corporation (Duke)
FACILITY:
Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF DECEMBER MANAGEMENT MEETING BETWEEN THE U.S.
NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND DUKE REPRESENTATIVES TO DISCUSS THE OCONEE LICENSE RENEWAL APPLICATION On December 16, 1998, representatives of Duke met with the NRC staff in Rockville, Maryland, to discuss the Oconee license renewal application. A list of meeting attendees is provided as. A copy.of the staff's and Duke's presentation materials discussed at the meeting are provided as Enclosures 2 and 3, respectively.
The staff discussed the status of the review (see Enclosure 2). The staff noted that all of the technical requests for additional information (RAls) were issued by the scheduled date of December 4, 1998. The staff also noted that the technical RAls sent to Duke included RAls on the containment and that the B&W Owners Group was sent RAls on the Reactor Vessel Internals Report (BAW-2248). Therefore, the commitments that the staff made during the last management meeting, which were documented in a November 16, 1998, meeting summary, were met regarding these issues.
Both Duke's (see Enclosure 3) and the staff's presentation identified areas where discussion between the NRC staff and Duke would be helpful in resolving the staffs RAls. These areas included the definition of inaccessible areas, Generic Safety Issue 190 "Fatigue Evaluation of Metal Components for 60-Year Plant Life," electrical screening, the definition of consumables and timing of new inspections. The staff noted that additional concerns may be identified when the RAI responses are received. The staff committed to work with Duke in arranging meetings and phone calls to help to resolve these issues. The staff also noted that the next management meeting is scheduled for January 14, 1999. Duke and the NRC staff agreed that prior to the January 14 meeting potential management meeting dates for February and March will have been identified.
Joseph M. Sebrosky roject Manager License Renewal Project Directorate Division of Reactor Program Management Docket Nos. 50-269, 50-270, and 50-287 Office of Nuclear Reactor Regulation
Enclosures:
As stated (3) cc w/encls: See next page DISTRIBUTION:
See next page DOCUMENT NAME:G:\\SEBROSKY\\1 2-160CO. SUM OFFICE LA PDLR/DRPM:PM PRLR/DRPM:PM PDLR:D NAME LBerr JSebrosky \\\\
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/4 /99 ie /99 t /99
/It /99 OFFICIAL RECORD COPY PDR 3AD0CKO 0
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Oconee Nuclear Station (License Renewal) cc:
Mr. J. E. Burchfield Ms. Lisa F. Vaughn Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Mail Stop PB-05E P. 0. Box 1439 Charlotte, North Carolina 28201-1006 Seneca, South Carolina 29679 J. Michael McGarry, Ill, Esquire Ms. Karen E. Long Anne W. Cottingham, Esquire Assistant Attorney General Winston and Strawn North Carolina Department of Justice 1400 L Street, NW.
P. O. Box 629 Washington, DC 20005 Raleigh, North Carolina 27602 Mr. Rick N. Edwards L. A. Keller Framatome Technologies Manager - Nuclear Regulatory Licensing Suite 525 Duke Energy Corporation 1700 Rockville Pike 526 South Church Street Rockville, Maryland 20852-1631 Charlotte, North Carolina 28201-1006 Manager, LIS Mr. Richard M. Fry, Director NUS Corporation Division of Radiation Protection 2650 McCormick Drive, 3rd Floor North Carolina Department of Clearwater, Florida 34619-1035 Environment, Health, and Natural Resources Senior Resident Inspector 3825 Barrett Drive U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27609-7721 7812B Rochester Highway Seneca, South Carolina 29672 Gregory D. Robison Duke Energy Corporation Regional Administrator, Region II Mail Stop EC-12R U. S. Nuclear Regulatory Commission P. 0. Box 1006 Atlanta Federal Center Charlotte, North Carolina 28201-1006 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Robert L. Gill, Jr.
Duke Energy Corporation Virgil R. Autry, Director Mail Stop EC-12R Division of Radioactive Waste Management P. 0. Box 1006 Bureau of Land and Waste Management Charlotte, North Carolina 28201-1006 Department of Health and RLGILL@DUKE-ENERGY.COM Environmental Control 2600 Bull Street Douglas J. Walters Columbia, South Carolina 29201-1708 Nuclear Energy Institute 1776 I Street, NW County Supervisor of Oconee County Suite 400 Walhalla, South Carolina 29621 Washington, DC 20006-3708 DJW@NEI.ORG W. R. McCollum, Jr., Vice President Oconee Site Chattooga River Watershed Coalition Duke Energy Corporation P. 0. Box 2006 P. 0. Box 1439 Clayton, GA 30525 Seneca, SC 29679
Distribution:
Hard copy PUBLIC Except for the attendees list in Enclosure 1, an advance copy of the handouts to this meeting summary were sent directly to the PDR on 12/17/98 Docket File PDLR RF M7EI:Z-fK-,,--ACRSJT2E2 E-mail:
R. Zimmerman D. Matthews C. Grimes T. Essig J. Strosnider G. Bagchi H. Brammer T. Hiltz G. Holahan S. Newberry C. Gratton R. Correia R. Latta J. Peralta J. Moore R. Weisman M. Zobler E. Hackett A. Murphy T -M-artin 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. Gill, Duke D. Walters, NEI
ATTENDANCE LIST DECEMBER 16, 1998 NRC MEETING WITH DUKE OCONEE UNITS 1,2 AND 3 NAME ORGANIZATION Mike Tuckman Duke Energy Greg Robison Duke Energy Bob Gill Duke Energy Chris Grimes NRR/DRPM/PDLR Steve Hoffman NRR/DRPM/PDLR Joe Sebrosky NRR/DRPM/PDLR Steven Vias NRR/DRPM/PDLR P. T. Kuo NRR/DRPM/PDLR Jim Wilson NRR/DRPM/PGEB Ralph Architzel NRR/DRPM/PGEB Roy Zimmerman (Part Time)
NRR Jack Strosnider NRR/DE Paul Shemanski NRR/DE/EELB Juan Peralta NRR/DRCH/HQMB Stephanie Martz NRC/OGC Marian Zobler NRC/OGC David Repka Winston and Strawn/Duke Larisa Helfer Winston and Strawn Donald Ferraro Winston and Strawn James Bennett Baltimore Gas & Electric (BGE)
B Doroshuk BGE Don Shaw BGE Chuck Rayburn BGE Marvin Bowman BGE Michael Henig Virginia Power Raj Kundalkar Florida Power and Light (FPL)
Steve Hale FPL Mike Schoppman FPL Washington Representative Dan Fouts Entergy (ANO)
Chuck Pierce Southern Nuclear Doug Walters NEI David Lewiis Shaw Pittman Will Kenworthy GSI Mike Neal NUSIS Alice Carson Bechtel
Oconee License Renewal Application Status Report to Duke Energy December 16, 1998 Jack Roe, Director, Division of Reactor Program Management Chris Grimes, Project Director, License Renewal Project Directorate 1
-Enclosure 2
December 1998 Report Card Schedule Adherence All technical RAls issued by 12/4/98 Duke to respond to technical RAls by 2/17/99 (Duke responded to first set of RAls on 12/14/98)
Environmental RAls to be issued by 1/3/99 Communications Good Fire protection and process/methodology overview meetings held that helped in the development of the staff's RAls Conference Calls held on 12/2/98, 12/10/98, and 12/15/98 to discuss SAMA Review Expect that calls will be held in the future to clarify RAls
Oconee RAI Status 324 RAls' issued from 10/29/98 through 12/4/98 350 300 S250 200 150 0
- 100 50 0 -
F2 3'
3I 3 T4 6
2 4
6 8
10 12 14 16 18 20 22 24 26 28 30 32 34 36 1
3 5
7 9
11 13 15 17 19 21 23 25 27 29 31 33 35 DAYs TOTAL RAIS Does not include 25 RAls that were issued to Duke on 11/14/97 and does not include 14 RAls that were issued to the B&W Owners Group on 12/2/98 3
Accomplishments
- Staff issued 324 technical RAls from 10/29/98 through 12/4/98
- Staff issued Containment RAls on 11/19/98
- Staff issued 14 RAls on the Reactor Vessels Internals Topical Report (BAW-2248) to the Owners Group on 12/2/98
- Environmental scoping period ended 11/19/98 with 6 letters received.
Response to letters and comments from 10/19/98 meeting will be included in Scoping Summary Report to be issued in January Quality
- Duke well prepared for meetings and conference calls that have occurred
- Staff technical RAls had extensive internal review prior to being issued to Duke 4
Concerns
- Credit for existing programs (e.g., Environmental Qualification)
- Based on feedback from Duke meetings/calls would be beneficial for the following issues:
-Definition of inaccessible GSI-190 issue Electrical Screening Treatment of consumables Timing of new inspections
- Additional concerns may be identified when RAI responses are received 5
Hearing Status Chattooga River Watershed Coalition has petitioned to intervene CRWC's contentions filed on 10/30/98
- Staff and Duke responses to contentions filed on 11/16/98 November 19, 1998 Licensing Board Order requested additional information regarding the status of the high level waste transportation rulemaking
Expectations Expectations to be accomplished by next NRC/Duke Management Meeting (January 14)
- Duke will have responded to more of the technical RAls
- Draft Safety Evaluation Report will be issued for the Fluence Methodology Topical (BAW-2241) in January
- Environmental RAls will have been issued
- Monthly meetings will have been tentatively scheduled for February and March of 1999 7
Enewy Oconee License Renewal Duke/NRC Management Meeting December 16, 1998 December 16, 1998 Oconee License Renewal Project Duke ZEnew. Agenda
- Safety Review a License Renewal Key Topics m Environmental Review a Hearing Process m Performance Assessment m Expectations December 16, 1998 Oconee License Renewal Project 2
Duke Enerw Safety Review m Request for Additional Information Status
- All RAls were issued by 12/4/98
- 38 letters to Duke containing 324 RAls
- 2 letters listing 42 sections where no RAls were issued a General Observations on RAls
- RAls reveal some of the challenges reviewers had with the structure of the application and many of the terms and definitions used there.
- To assure response completeness, Duke will need to work to understand how requested information will be used to develop the NRC Safety Evaluation.
- Duke recognizes that some issues are bigger than Duke.
December 16, 1998 Oconee License Renewal Project 3
l Duke f#Enerw License Renewal Key Topics (1) NRC complete review of Containment portion of Application (2) NRC complete review of Reactor Vessel Internals Topical Report (BAW-2248)
(3) BWOG, Duke and NRC coordinate completion of inputs to reactor vessel portion of Oconee Safety Evaluation (4) Duke and NRC to be clear on:
- definition of inaccessible areas
- technical rationale for addressing GSI-190
- electrical screening details
- definition of consumables (5) Duke and NRC to determine appropriate timing of new inspections December 16, 1996 Oconee License Renewal Project 4
2
Duke Reactor Vessel er" Key Topic Reactore vetReport W-2241P Dcconee Reactor Vessel Safety Evaluation Findings 8WOS Bettline Obfernitr Data BAW-2325 n Duke Status
- Preparation of RAI responses in progress
- All responses to be submitted on or before February 17, 1999 e Responses appear to be "group-able" by topic vs. letter-by-letter
- Working level meetings & telecons may be needed on specific technical areas December 16, 1998 Oconee License Renewal Project 6
3
PoDuke fEnegry-Environmental Review n Communications with NRC project manager continue to be effective m SAMA review proceeding in parallel - separate technical discussions ongoing
- Environmental RAls expected by January 3, 1999 m Awaiting issuance of NUREG-1555, Supplement 1 and the regulatory guide a Awaiting HLW transportation proposed rule change to be published in Federal Register December 16, 1998 Oconee License Renewal Project 7
SDuke rEnewy.
Hearing Process a Chattooga River Watershed Coalition supplemental petition to intervene - 10/30/98 m NRC staff and Duke filed responses - 11/16/98 m Board Order to NRC staff - 11/19/98 n NRC staff filed response - 12/02/98 n Duke and petitioners' filed responses - 12/09/98 m Board authorized NRC staff and Duke to file additional information by 12/22/98 December 16, 1998 Oconee License Renewal Project 8
4
- Ene.
Performance Assessment
...from August
- Communications remain open & are satisfactory a Safety RAls were uniquely identified & provided electronically which has expedited the start of response preparation, meeting expectations.
... from October a 'Successful Process/Methodology review meeting conducted a Successful Fire Protection review meeting conducted a Successful Electrical review meetings - canceled a SAMA review technical discussions are being conducted a Safety RAls were issued over several weeks All expectations met except for electrical meetings December 16, 1998 Oconee License Renewal Project 9
Duke wEneW.
Expectations m Expectations to be accomplished by next NRC/Duke Management Meeting (mid-January)
- Develop plans to address Duke License Renewal Key Topics (Duke and NRC Staff)
- Prepare responses to safety RAls, submit to NRC when available (Duke and BWOG)
- Begin preparing responses to environmental RAls (Duke)
- Publish proposed HLW Transportation rule change (NRC)
- Develop schedule for future management meetings past January 14, 1999 (Duke and NRC Staff)
December 16, 1998 Oconee License Renewal Project 10 5
Oconee License Renewal Application RAI Summary December 16, 1998 GENERAL TOPIC RAls 9.
Open 3 -11/18/98D
- 1. INTRODUCTION 0
.pn 6-1//8 1.1 Purpose 0
Closed 12/4/98NC 1.2 Description of Oconee Nuclear Station 0
Closed 12/4/98NC 1.2.1 Oconee Nuclear Station 0
1.2.2 Keowee Hydroelectric Station 0
1.2.3 Standby Shutdown Facility 0
1.3 Technical Information Required for an Application 0
Closed 12/4/98NC 1.3.1 Integrated Plant Assessment 0
1.3.2 Time-Limited Aging Analyses and Exemptions 0
1.4 Process to Update Technical Information 0
Closed 12/4/98NC 1.5 Generic Safety Issues 0
1.5.1 Background 0
Closed 1214/98NC 1.5.2 GSI 23 - Reactor Coolant Pump Seal Failures 1
Open 11/20/98E 1.5.3 GSI 168 - Environmental Qualification of Electrical Components 0
Closed 12/4/98NC 1.5.4 GSI 173.A - Spent Fuel Storage Pool: Operating Facilities 0
Closed 12/4/98NC 1.5.5 GSI 190 - Fatigue Evaluation of Metal Components for 1
Open 11/24/98A 60-Year Plant Life 0
1.5.6 References for Section 1.5 0
NA
- 2. IDENTIFICATION OF STRUCTURES & COMPONENTS 1
Open 12/l/98B SUBJECT TO AGING MANAGEMENT REVIEW 2.1 Introduction 0
Closed 12/4/98NC 2.2 Identification of Systems, Structures, and Components Within the 9
Open 5 - 11/30/98B Scope of License Renewal Open 1 - 12/1/98B 3 - 12/2/98E 2.2.1 Review To Criteria in §§54.4(A)(1) and (A)(2) 0 2.2.2 Review To Criteria in §54.4 (A)(3) 0 2.2.3 Results 0
2.2.4 References for Section 2.2
.0 NA 2.3 Reactor Building (Containment) Structural Components 11 Closed 7 - Pre 7/6/98 7/6/98 Open 3-11/19/98 Open 1 - 12/1/98A 2.3.1 Description of the Process to Identify Reactor Building 0
Closed 12/4/9NC Containment) Structural Components 2.3.2 Concrete Components 0
2.3.3 Steel Components 0
2.3.4 Post-Tensioning System 0
2.3.5 References for Section 2.3 0
NA 2.4 Reactor Coolant System Mechanical Components and Class 1 7
Open 1 l/30/98C Component Supports 2.4.1 Description of the Process to Identify Reactor Coolant System 0
Closed 12/4/98NC Components and Class 1 Component Supports Subject to Aging Management Review 2.4.2 Process to Incorporate Approved B&WOG Topical Reports by 0
Closed 12/4/98NC Reference 0
2.4.3.Reactor Coolant System Piping 0
2.4.4 Pressurizer 0
2.4.5 Reactor Vessel 0
12-16 RAI COUNT.doc Page 1 of 8
g 0
Oconee License Renewal Application RAI Summary December 16, 1998 2.4.6 Reactor Vessel Internals 0
2.4.7 Once Through Steam Generators 0
2.4.8 Reactor Coolant Pumps0 2.4.9 Control Rod Drive Mechanism Motor Tube Housings 0
2.4.10 Letdown Coolers 0
2.4.11 Class 1 Component Supports 0
2.4.12 References for Section 2.4 0
NA 2.5 Mechanical System Components 0
2.5.1 Process Used To Identify Mechanical Components Subject to 0
Closed 12/4/98NC Aging Management Review 2.5.2 Detailed Process Description 0
Closed 12/4/98NC 2.5.3 Containment Heat Removal Systems 6
Open 12/1/98A 2.5.4 Containment Isolation System I
Open 12/1/98A 2.5.5 Emergency Core Cooling Systems 5
Open 11/30/98C 2.5.6 Auxiliary Systems 14 Open 12/2/98C 2.5.7 Process Auxiliaries 2
Open 11/30/98C 2.5.8 Air Conditioning, Heating, Cooling and Ventilation Systems 4
Open 11/24/98C 2.5.9 Steam and Power Conversion Systems 7
Open 11/24/98D 2.5.10 Post-Accident Hydrogen Control 3
Open 12/1/98A 2.5.11 Reactor Coolant Pump Motor Oil Collection System 0
Closed 12/4/98NC 2.5.12 Reactor Coolant System Vents, Drains, and Instrument Lines 0
Closed 12/4/98NC 2.5.13 Keowee Hydroelectric Station 3
Open 11/20/98F 2.5.14 Standby Shutdown Facility 0
Closed 12/4/98NC 2.5.15 References for Section 2.5 0
NA 2.6 Electrical Components 9
Open 1l/25/98A 2.6.1 Description of the Process to Identify Electrical Components 4
Open 12/l/98B Subject to Aging Management Review 2.6.2 Bus 0
2.6.3 Insulated Cables And Connections 0
2.6.4 Insulators 0
2.6.5 Transmission Conductors 2.6.6 Electrical Components Not Subject to Aging Management Review 0
2.6.7 Structures and Areas Containing Electrical Components Subject to 2
Open 12/1/98B Aging Management Review 2.6.8 References for Section 2.6 0
NA 2.7 Structures & Structural Components 10 Open 11 /18/98A 2.7.1 Description of the Process to Identify Structural Components 0
Subject to Aging Management Review 2.7.2 Structural Components 0
2.7.3 Auxiliary Buildings 0
2.7.4 Earthen Embankments 0
2.7.5 Intake Structure 0
2.7.6 Keowee Structures 0
2.7.7 Reactor Buildings Internal Structure and the Unit Vent Stacks 0
2.7.8 Standby Shutdown Facility 0
2.7.9 Turbine Building 0
2.7.10 Yard Structures 0
12-16 RAI COUNT.doc Page 2 of 8
Oconee License Renewal Application RAI Summary December 16, 1998
- 3. IDENTIFICATION OF APPLICABLE AGING EFFECTS 0
3.1 Introduction 0
Closed 174/98NC 3.2 Description of the Process to Identify Applicable Aging 3
Open I - 11/25/98A Open 2 -
11/25/98B Effects 0
3.2.1 Process Overview 0
3.2.2 Service Environments 0
3.2.3 References for Section 3.2 0
NA 3.3 Aging Effects for Reactor Building (Containment) Structural.
21 Closed 18 - pre 7/6/98 7/6/98 Components Open 3-11/19/98 3.3.1 Description of the Process to Identify the Applicable Aging 0
Effects for Reactor Building (Containment) Structural Components 3.3.2 Applicable Aging effects for Concrete Components 0
3.3.3 Applicable Aging Effects for'Steel Components 0
3.3.4 Applicable Aging Effects for the Post-Tensioning System 0
3.3.5 References for Section 3.3 0
NA 3.4 Aging Effects for Reactor Coolant System Components & Class 1 0
Component Supports 3.4.1 Description of the Process to Identify the Applicable Aging 0
Closed 12/4/98NC Effects for Reactor Coolant System Components & Class 1 Component Supports 3.4.2 Process to Incorporate Approved B&WOG Topicals Reports 0
Closed 12/4/98NC by Reference 0
3.4.3 Reactor Coolant System Piping I
Open 12/2/98D 3.4.4 Pressurizer 1
Open 11/20/98A 3.4.5 Reactor Vessel 8
Open 11/20/98G 3.4.6 Reactor Vessel Internals 2
Open 11/20/98C 3.4.7 Once Through Steam Generator 5
Open 3 - 11/18/98B pen 2 - 12/3/98A 3.4.8 Reactor Coolant Pumps 5
Open 3 - 11/18/98B Open 2 -12/3/98A 3.4.9 Control Rod Drive Tube Motor Housings 0
3.4.10 Letdown Coolers 4
Open 11/18/98B 3.4.11 Class 1 Component Supports 7
Open 10/29/98 12/14/98 3.4.12 References for Section 3.4 0
NA 3.5 Aging Effects for Mechanical System Components 0
3.5.1 Description of the Process to Identify the Applicable Aging 0
Closed 12/4/98NC Effects for Mechanical System Components 3.5.2 Applicable Aging Effects for Mechanical System Components 2
Open 12/3/98A 3.5.3 Containment Heat Removal Systems 8
Open 2 - 11/18/98B Open 6 -
12/3/98A 3.5.4 Containment Isolation System I
Open 11/24/98B 3.5.5 Emergency Core Cooling Systems 3
Open I - 11/20/98A Open 2 - 12/3/98A 3.5.6 Auxiliary Systems 2
Open 11/18/98C 3.5.7 Process Auxiliaries 2
Open 11/18/98C 3.5.8 Air Conditioning, Heating, Cooling and Ventilation Systems 8
Open 7 - 11/20/98B Open I -
12/3/98A 3.5.9 Steam and Power Conversion Systems.
4 Open 10/29/98 12/14/98 12-16 RAI COUNT.doc Page 3 of 8
Oconee License Renewal Application RAI Summary December 16, 1998 3.5.10 Post-Accident Hydrogen Control 0
Closed 12/4/98NC 3.5.11 Reactor Coolant Pump Motor Oil Collection System 0
Closed 12/4/98NC 3.5.12 Reactor Coolant System Vents, Drains and Instruent Lines 2
Oe W/8 3.5.13 Keowee Hydroelectric Station 2
Open 11/18/98C 3.5.14 Standby Shutdown Facility 6
Open 4 - 11/18/98B Open 2 -
12/3/98A 3.6 Aging Effects for Electrical Components 4
Open 1l/25/98A 3.6.1 Description of the Process to Identify the Applicable Aging 0
Effects for Electrical Components 3.6.2 Bus 0
3.6.3 Insulated Cables and Connections 0
3.6.4 Insulators 0
3.6.5 Transmission Conductors 0
3.6.6 References for Section 3.6 0
NA 3.7 Aging Effects for Structural Components 0
3.7.1 Description of the Process to Identify the Applicable Aging 2
Open 11/18/98A Effects for Structural Components 3.7.2 Applicable Aging Effects for Structural Components 3
Open I - 11/18/98A Retracted 1 - 11/18/98D Open 2 -
12.3.98A 3.7.3 Auxiliary Building 12 Open 11 - 11/30/98A Open I -
12/3/98A 3.7.4 Earthen Embankments 1
Open 11/18/98E 3.7.5 Intake Structure 3
Open 11/18/98A 3.7.6 Keowee Structures 6
Open 11/30/98A 3.7.7 Reactor Building (Internal Structural Components and the Unit 7
Open I - 1l/18/98A Vent Stacks)
Open 6 - 11/30/98A 3.7.8 Standby Shutdown Facility 0
Closed 124/98NC 3.7.9 Turbine Building 3
Open 11/13/98 3.7.10 Yard Structures 0
Closed 1724/98NC 3.7.11 References for Section 3.7 0
NA
- 4. AGING MANAGEMENT PROGRAMS AND ACTIVITIES 0
4.1 Introduction 0
4.2 Program and Activity Attributes 0
4.2.1 References for Section 4.2 0
NA 4.3 New Programs and Activities 0
Closed 12/4/98NC 4.3.1 Alloy 600 Aging Management Program 6
Open 1 - 11/20/98G Open 5 - 12/3/98A 4.3.2 Cast Iron Selective Leaching Inspection I
Open 10/29/98 12/14/98 4.3.3 Galvanic Susceptibility Inspection 0
Closed 12/4/98NC 4.3.4 Keowee Air and Gas Systems Inspection 0
Closed 124/98NC 4.3.5 Keowee Oil Sampling Program 0
Closed 1 24/98NC 4.3.6 Once Through Steam Generator Upper Lateral Support Inspection 0
Closed 12/4/98NC 4.3.7 Pressurizer Examinations 2
Open I - 11/20/98D 1 -12/3/98A 4.3.8 Preventive Maintenance Activity Assessment 6
Open 10/29/98 12/14/98 4.3.9 Reactor Building Spray System Inspection 5
Open 10/29/98 12/14/98 4.3.10 Reactor Coolant Pump Motor Oil Collection System Inspection 0
Closed 12/4/98NC 4.3.11 Reactor Vessel Internals Aging Management Program 0
Closed 12/4/98NC 12-16 RAI COUNT.doc Page 4 of 8
Oconee License Renewal Application RAI Summary December 16, 1998 4.3.12 Small B ore Piping Inspection 0
Closed 12/4/98NC 4.3.13 Treated Water Systems Stainless Steel Inspection 4
Open 12/3/98A 4.3.14 References for Section 4.3 0
NAn 4.4 Battery Rack Inspections 0
Closed 12/4/98NC 4.4.1 Program Description 0
4.4.2 Operating Experience And Demonstration 0
4.4.3 References for Section 4.4 0
NA 4.5 Boric Acid Wastage Surveillance Program 2
Open 123/98A 4.5.1 Program Description 0
4.5.2 Operating Experience and Demonstration 0
4.5.3 References for Section 4.5 0
NA 4.6 Chemistry Control Program 0
4.6.1 Background 0
Closed 12/4/98NC 4.6.2 Primary Chemistry Control Specifications 4
Open 10/29/98 12/14/98 4.6.3 Secondary Chemistry Control Specifications 2
Open 10/29/98 12/14/98 4.6.4 Component Coolant Chemistry Control Specifications 1
Open 10/29/98 12/14/98 4.6.5 Standby Shutdown Facility Fuel Oil Surveillances 0
Closed 12/4/98NC 4.6.6 References for Section 4.6 0
NA 4.7 Coatings Program 0
Closed 12/4/98NC References for Section 4.7 0
NA 4.8 Containment Inservice Inspection Plan 4
Open 11/19/98 4.8.1 ASME Section XI, Subsection IWE Examinations 0
4.8.2 ASME Section XI, Subsection IWL Examinations 0
4.8.3 References for Section 4.8 0
NA 4.9 Containment Leak Rate Testing Program 3
Open 2 - 12/1/98A 1 - 12/4/98B 4.9.1 Reactor Building Type A Integrated Leak Rate Test 0~(.
4.9.2 Reactor Building Type B Local Leak Rate Test 0
4.9.3 References for Section 4.9 0
NA 4.10 Control Rod Drive Mechanism Nozzle and Other Vessel Closure I
Open 1 1/20/98G Penetrations Inspection Program 4.10.1 Program Description 0
4.10.2 Operating Experience and Demonstration 0
4.10.3 References for Section 4.10 0
NA 4.11 Crane Inspection Program I
Open 123/98C 4.11.1 Program Description 0
4.11.2 Operating Experience and Demonstration 0
4.11.3 References for Section 4.11 0
NA 4.12 Duke Power Five-Year Underwater Inspection of Hydroelectric 3
Open 11/30/98A Dams and Appurtenances 4.12.1 Program Description 0
4.12.2 Operating Experience and Demonstration 0
4.13 Duke Quality Assurance Program 1
Open 12/1/98B 4.13.1 Corrective Action 0
4.13.2 Document Control 0
4.13.3 References for Section 4.13 0
NA 4.14 Elevated Water Storage Tank Civil Inspection 3
Open 11/30/98A 12-16 RAI COUNT.doc Page 5 of 8
Oconee License Renewal Application RAI Summary December 16, 1998 4.14.1 Program Description 0
4.14.2 Operating Experience and Demonstration 0
4.15 Federal Energy Regulatory Commission (FERC) Five Year 6
Open 4 -ll/18/98E Inspection Open 2 - 11/30/98A 4.15.1 Program Description 0
4.15.2 Operating Experience and Demonstration 0
4.15.3 References for Section 4.15 0
NA 4.16 Fire Protection Program 11 Open I - 12/3/98A Open 4 - 12/3/98E Open 6 - 12/4/98A 4.16.1 Fire Barrier Inspections 0
4.16.2 Fire Water System Test 0
t 4.16.3 References for Section 4.16 0
NA 4.17 Heat Exchanger Performance Testing Activities 3
Open 2 - 12/3/98A Open 1 - 12/3/98D 4.17.1 References for Section 4.17 0
NA 4.18 Inservice Inspection Plan 4
Open I - ll/20/98C 3 - 12/7298D 4.18.1 ASME Section XI, Subsection IWB and IWC Inspections 0
4.18.2 Cast Austenitic Stainless Steel Flaw Evaluation 0
4.18.3 ASME Section XI, Subsection IWF Inspections 0
4.18.4 Operating Experience and Demonstration 0
4.18.5 References for Section 4.18 0
NA 4.19 Inspection Program for Civil Engineering Structures and 0
Closed 12/4/98NC Components 4.19.1 Program Description 0
4.19.2 Operating Experience and Demonstration 0
4.20 Penstock Inspection 0
Closed 124/98NC 4.20.1 Program Description 0
4.20.2 Operating Experience and Demonstration 0
4.21 Piping Erosion/Corrosion Program 6
Open 5 - 10/29/98 5 -12/14/
Open 1 - 11/18/98D 4.21.1 Program Description 0
4.21.2 Operating Experience and Demonstration 0
4.21.3 Reference for Section 4.21 0
NA 4.22 Program to Inspect the High Pressure Injection Connections to the 1
Open 11/20/98D Reactor Coolant System 4.22.1 Program Description 0
4.22.2 Operating Experience and Demonstration 0
4.22.3 References for Section 4.22 0
NA 4.23 Reactor Coolant System Operational Leakage Monitoring I
Open 12)2/98A 4.23.1 Program Description 0
4.23.2 Operating Experience and Demonstration 0
4.23.3 References for Section 4.23 0
NA 4.24 Reactor Vessel Integrity Program 0
Closed Telecon - 12/7/98 4.24.1 Master Integrated Reactor Vessel Surveillance Program 0
4.24.2 Cavity Dosimetry Program 0
4.24.3 Fluence and Uncertainty Calculations 0
4.24.4 Pressure Temperature Limit Curves 0
12-16 RAI COUNT.doc Page 6 of 8
Oconee License Renewal Application RAI Summary December 16, 1998 4.24.5 Effective Full Power Years 0
4.24.6 References for Section 4.24 0
NA 4.25 Service Water Piping Corrosion Program 2
Open 12/3/98A 4.25.1 Program description 0
4.25.2 Operating Experience and Demonstration.
0 4.25.3 References for Section 4.25 0
NA 4.26 Steam Generator Tube Surveillance Program I
Open 113/98A 4.26.1 Program Description 0
4.26.2 Operating Experience and Demonstration 0
4.26.3 References for Section 4.26 0
NA 4.27 System Performance Testing Activities o0 Closed 12)4/98NC 4.27.1 References for Section 4.27 0
NA 4.28 Tendon - Secondary Shield Wall - Surveillance Program 2
Open 11l/1 8/98A 4.28.1 Program Description 0
4.28.2 Operating Experience and Demonstration 0
4.28.3 References for Section 4.28 0
NA 4.29 230 kV Keowee Transmission Line Inspection 0
loed 12/4/98NC 4.29.1 Program Description 0
4.29.2 Operating Experience and Demonstration 0
4.29.3 References for Section 4.29 0
NA
- 5. TIME-LIMITED AGING ANALYSES AND EXEMPTIONS 0
REVIEW 5.1 Introduction 1
Open 11/3/98B 5.2 Process Overview 0
5.2.1 Identification and Evaluation of Time-Limnited Aging Analyses 0
5.2.2 Identification of Exemptions 0
5.2.3 References for Section 5.2 0
NA 5.3 Time-Limited Aging Analyses for the Reactor Building 0
(Containment) Structural Components 5.3.1 Containment Liner Plate and Penetrations 2
Open 11/19/98 5.3.2 Containment Post-Tensioning System 2
Open 11/19/98 5.3.3 References for Section 5.3 0
NA 5.4 Time-Limited Aging Analyses for the Reactor Coolant System and 0
Class Components 5.4.1 Reactor Coolant System Piping and Components 5
Open 11/24/98A 5.4.2 Reactor Vessel Open 1/20/98D 5.4.3 Reactor Vessel Internals 0
Closed 14/98NC 5.4.4 Reactor Coolant Pump Flywheel 0
Closed 11/6/98 na 5.4.5 References for Section 5.4 0
NA 5.5 Time-Limited Aging Analyses for Mechanical Components 0
5.5.1 Mechanical Component Thermal Fatigue 0
Closed 17/4/98NC 5.6 Time-Limited Aging Analyses for Electrical Equipment 3
Open 11/25/98A 5.6.1 Accelerometers, TEC Monitor 0
5.6.2 Actuators, Limitorque 0
5.6.3 Actuators, Rotork 0
,5.6.4 Cables, Anaconda EPR/Hypalon & EPR/Neoprene 0
5.6.5 Cables, BIW CSPE 0
12-16 RAI COUNT.doc Page 7 of 8
Oconee License Renewal Application RAI Summary December 16, 1998 5.6.6Cables, Brand-Rex & Samuel Moore PVC 0
5.6.7 Cables, Brand-Rex Flame Retardant XLPE 0
5.6.8 Cables, ITT Suprenant & Raychem Cross-linked Polyalken~e 0
Hook-up Wire 5.6.9 Cables, Kerite-HTK 0
5.6.10 Cables, Okonite EPRINeoprene 0
5.6.11 Cables, Samuel Moore EPDM/Hypalon 0
5.6.12 Connection & Sealing Assemblies, Scotchcast 9 And Swagelok.
0 Quick-Connect Assemblies 5.6.13 Heat Shrink Tubing, Raychem NCBK Nuclear Cable Breakout 0
Splice Assemblies 5.6.14 Heat Shrink Tubing, Raychem NPKV Nuclear Plant Stub 0
Connection Kit 5.6.15 Heat Shrink Tubing, Raychem WCSF-N In-line Splice 0
Assemblies 5.6.16 Heat Shrink Tubing, EGS Grayboots 0
5.6.17 Heat Shrink Tubing, EGS Connectors 0
5.6.18 Motors, Joy/Reliance 0
5.6.19 Motors, Louis-Allis 0
5.6.20 Motors, Reliance 0
5.6.21 Motors, Westinghouse 0
5.6.22 Penetration Assemblies, Conax 0
5.6.23 Penetration Assemblies, D. G. O'Brian 0
5.6.24 Penetration Assemblies, Viking 0
5.6.25 RTD, Conax 0
5.6.26 RTD, Rosemount 0
5.6.27 RTD, Weed 0
5.6.28 Solenoid Valves, Valcor 0
5.6.29 Switches, Barton/Westinghouse 0
5.6.30 Terminal Blocks, States & Stanwick 0
5.6.31 Transmitters, Gems Delaval 0
5.6.32 Transmitters, Barton Model 764 0
5.6.33 Transmitters, Rosemount 0
References for Section 5.6 0
NA 5.7 Time-Limited Aging Analyses for Structures & Structural 0
Components 5.7.1 Polar Crane 1
Open 10/29/98 12/14/98 5.7.2 Spent Fuel Rack Boraflex 1
Open 12/2/98B 5.7.3 References for Section 5.7 0
NA Total Number of RAIS 349 Reactor Internals Report - BJAW-2248 14 Open 12/298 11 s
I scottThese RAls are associated with RAls 3.4.6-1 and 3.4.6-2 above 12-16 RAI COUNT.doc Page 8 of 8