ML15261A214

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Summary of 981015 Meeting with DPC Re Overview of DPC License Renewal Application for Oconee.List of Meeting Attendees & DPC Presentation Materials Encl
ML15261A214
Person / Time
Site: Oconee, Cooper  
Issue date: 11/16/1998
From: Christopher Regan
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
PROJECT-690 NUDOCS 9811240262
Download: ML15261A214 (62)
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Text

tr t REGI,

.40 917 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 November 16, 1998 LICENSEE:

Duke Energy Corporation FACILITY:

Oconee Nuclear Station, Units 1, 2, and 3

SUBJECT:

SUMMARY

OF MANAGEMENT MEETING WITH DUKE ENERGY CORPORATION CONCERNING THE LICENSE RENEWAL APPLICATION FOR OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 On October 15, 1998, the Nuclear Regulatory Commission (NRC) and Duke Energy Corporation (Duke) management met to provide an overview of Duke's license renewal application for Oconee Nuclear Station, Units 1, 2, and 3 (Oconee) for NRC management. A list of meeting attendees is provided in Enclosure 1. Duke's presentation materials are contained in Enclosure 2.

Duke began the meeting with a brief history of the license renewal efforts at Oconee. Duke stressed that it has played a lead role in development of the license renewal process by being involved in, and being principle members of, the activities coordinated by the Babcock and Wilcox Owners Group (B&WOG) and the Nuclear Energy Institute (NEI). Duke originally viewed license renewal as a research effort and began by taking a scientific mechanistic approach to developing a license renewal application and the supporting technical information.

This later evolved into a concerted effort to submit an application for license renewal using experience gained from the license renewal demonstration project (the results of which are documented in NUREG-1568), activities associated with development of the "Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule," NEI-95 10, and other industry sponsored activities.

Duke noted that its efforts were strongly focused on establishing a firm technical basis for its findings related to license renewal. However, difficulties in locating records in a form suitable for justifying a basis for license renewal in some cases required initiation of activities to provide the data necessary for making such a finding. Duke stated it worked to make the license renewal solution a practical engineering solution and not one based on a scientific or legalistic solution. The staff questioned whether any of these efforts were similar in nature to design reconstitution efforts taking place throughout the industry. Duke responded that much of the research done by Duke is commensurate with design reconstitution and that much of the 0

material catalogued can be used in areas outside of license renewal.

Duke provided the staff with a synopsis of the Oconee license renewal application and explained the reasoning for the structure of the application as it was submitted to the staff.

Specifically, the application is split by discipline, which follows Duke's organizational structure.

The application is also grouped on the theory that generic aging management programs cross disciplinary boundaries with cross disciplinary programs being documented separately and referenced where they are applicable.

V -EL4L 2 '

FRO7~V 00-T6 1

November 16, 1998 Duke stated that it had found much of the programmatic oversight necessary for license renewal was already in place but there were some areas that would require enhancement. The staff pointed out that this was the finding also made by the Commission during license renewal rulemaking. Duke described its use of the "license renewal equation," structure/component +

aging effects + aging management program + demonstration = reasonable assurance. The staff noted that Duke is using the term "potential" in lieu of the staffs term "plausible" when.

performing the analysis of aging effects. Concerns were raised by the staff that use of these terms interchangeably might, in the future, create confusion amongst potential license renewal applicants. Duke noted the inconsistency.

Duke clarified the nexus between the conversion of Oconee's technical specifications (TS) to the standardized TS and the Final Safety Analysis Report (FSAR) supplement for license renewal. The staff's review of Duke's TS conversion is expected to be completed in December of 1998. Duke noted that the program attributes cited in the Oconee license renewal application will be summarized in the FSAR supplement and that any necessary changes will be made to the standardized TS when the staffs review is complete. The FSAR supplement will essentially be a list of Duke commitments for license renewal.

The staff questioned Duke on the information described in the license renewal application concerning selected aging management programs that are yet to be developed. Duke stated that the attributes of the programs have been submitted to the NRC and are currently under review by the staff. Also, Duke stated that it has committed to take the necessary actions and will implement programs for license renewal pending the completion and findings of the staffs review. For aging management programs lacking sufficiently accurate or detailed historical information or basis, Duke has committed to perform inspections to collect data in support of its findings for license renewal. The staff stressed that attention should be given to the timing of one-time inspections to avoid mischaracterization of material condition, i.e., an aging effect might not be detectable if the inspections are performed too early.

Duke presented its methodology concerning the determination of time limited aging analyses within the scope of the license renewal review and its disposition of the time limited aging analyses that were determined to be applicable to license renewal. Duke affirmed with the staff that all applicable generic safety issues (GSls), although not resolved, have been addressed in the license renewal application. The staff noted that concerns existed over the use of resolution" vs. "addressing" when describing disposition of GSIs in the license renewal application by Duke. These inconsistencies would be examined by the staff during the course of the application review. Duke also stated that there were no 10 CFR Part 50.12 exemptions that were identified for Oconee in accordance with the requirements of Section 54.21(c).

Duke provided the staff with a brief description of excerpts (Enclosure 3) taken directly from the Oconee license renewal application pointing out areas that provide good starting points from which to understand the format of the application and to begin a review.

Noveiber 16, 1998 Duke stressed that the license renewal review should not be abused as a means for resolving technical issues. These technical issues should be addressed by the NRC staff, the research community, and industry in the appropriate forum.

original signed by:

Christopher M. Regan, Mechanical Engineer License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 690

Enclosures:

As stated (3) cc: w/enclosures: See next page Distribution: See next page DOCUMENT NAME:G:\\WORKING\\REGAN\\DUKE1015.WP

  • See previous concurrence

[

OFFICE LA PDLR IPDLR PDLR:D NAME LBerry*

CMRegan STHoffman CIGrimes DATE 10/12/98 10/29 /98*

10/29 /98*

(J /((p/98-'

OFFICIAL RECORD COPY

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 1 Street, NW Suite 400 W. R. McCollum, Jr., Vice President Washington, DC 20006-3708 Oconee Site DJW@NEI.ORG Duke Energy Corporation P. 0. Box 1439 Chattooga River Watershed Coalition Seneca, SC 29679 P. 0. Box 2006 Clayton, GA 30525

Distribution:

Hard copy PUBLIC "Docket File PDLR RF M. EI-Zeftawy, ACRS T2E2 E-mail:

F. Miraglia 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 J. Peralta R. Gill, Duke D. Walters, NEI

ATTENDANCE LIST NRC MANAGEMENT MEETING WITH DUKE ENERGY CORPORATION SEPTEMBER 28, 1998 NAME ORGANIZATION 1,

Steve Hoffman NRC/NRR/DRPM/PDLR

2.

Joe Sebrosky NRC/NRR/DRPM/PDLR

3.

Mike Schoppman FTI - Rockville

4.

Greg Robison Duke Energy

5.

Robert Gill Duke Energy

6.

Nancy Chapman Serch/Bechtel

7.

Ben Rodhill Virginia Power

8.

Mike Neal NUS, Information Services

9.

Gus Lainas NRC/NRR/DE

10.

Jack Strosnider NRC/NRR/DE

11.

Dick Wessman NRC/NRR/DE/EMEB

12.

Christopher M. Regan NRC/NRR/DRPM/PDLR

13.

Emmett Murphy NRC/NRR/DE/EMCB

14.

Kamal Manoly NRC/NRR/DE/EMEB

15.

Juan Peralta NRC/NRR/DRCH/HQMB

16.

Stepahni Mertz NRC/OGC

17.

Marian Zobler NRC/OGC

18.

Mary Miller NRC/Office of the Chairman

19.

Dale Thatcher.

NRC/NRR/DE/EELB

20.

R. M. Latta NRC/NRR/DRCH/HQMB

21.

Anne Cottingham Winston and Strawn

22.

Keith Wichman NRC/NRR/DE/EMCB

23.

Goutam Bagchi NRC/NRR/DE/EGCB

24.

Jose A. Calvo NRC/NRR/DE/EELB

25.

C.I Grimes NRC/NRR/DRPM/PDLR

26.

Edmund Sullivan NRC/NRR/DE

27.

Norihisa Yuki NRC/NRR/DRPM/PDLR

28.

Robert Prato NRC/NRR/DRPM/PDLR

Duke EEnergy.

Oconee License Renewal Duke/NRC Management Application Overview Meeting October 15, 1998 Bob Gill Greg Robison

Duke Energy.

Agenda

1. Background

W (n

2. Process II

'I IV

3. Results Oconee Nuclear Station Units 1, 2& 3 Application for Renewed Operating Licenses October 15, 1998 Oconee License Renewal Project 2

Duke Energy.

Background

1985 1990 1995 Today industry

  • Industry Reports
  • Owners Groups
  • Yankee & Monticello
  • BG&E
  • NRC/Utility Demos Scientific perspective
  • Engineering perspective
  • Aging mechanisms
  • Aging effects Duke
  • Industry Participant in Oconee LR Team AIF, NUMARC, EPRI Formed - 1992 Leader in Industry Designed Oconee LR Solution Report development
  • Active in BWOG WOG, EPRI, NEI, Industry &M fforts
  • Sought NRC feedback through slices in 1997
  • July 6, 1998 Application Submittal October 15, 1998 Oconee License Renewal Project 3

uke Guiding Principles For An Effective LR Solution A License Renewal Solution must:

m Comply with the requirements in the license renewal rule (10 CFR 54) m Create a solid engineering basis for licensing actions a Foster long term plant ownership for licensing commitments October 15, 1998 Oconee License Renewal Project 4

PnDuke Meeting The Guiding Principles To meet the guiding principles, Duke:

a Assembled a solid core engineering team

  • Developed as simple and as holistic a solution as possible m Worked to make the license renewal solution a practical engineering solution (vs. a scientific or legalistic solution)

October 15, 1998 Oconee License Renewal Project 5

Duke A Practical Engineering WEnergym Solution a The complete Application is intended to provide sufficient information for the NRC to complete its technical and environmental reviews and is designed to allow the NRC to make the finding require by §54.29 in support of the issuance of renewed operating licenses for Oconee.

  • Special attention was focused on the Reactor Building (Containment) and the Reactor Coolant System because they are important elements in the radioactive release defense-in-depth.

m The remaining systems, structures and components within the scope of license renewal are divided along engineering discipline lines traditional to Duke (i.e., mechanical, electrical, and civil/structural).

  • Application Sections 2.2 through 2.7 contain the technical information required by §§54.21(a)(1) and (a)(2).

...from Application Section 1. 1 Purpose (Volume I)

October 15, 1998 Oconee License Renewal Project

NEI 95-10 REVISION 0 March 1, 1996 FIGURE 2.0 -1 LICENSE RENEWAL IMPLEMENTATION PROCESS Identify systems, structures, & components &

entifLs intended functions within the scope exemptions [55 of license renewal [§ 54.4]

(Section 5.0)

(Section 3.0)

Methods to Identify structures & com ponents subject to aging management review

[§ 54.21(a)(1)(i) & (ii)] [5 5421(a)(2)]

(Section 4.1)

Methods for demonstrating that Methods for evaluating TLAAs &

the effects of aging are adequately managed m4exemptions

[§ 54.21(c)(1), (2)]

[. 54.21(a)(3)]

(Section 5.0)

(Section 4-2)

Content of Application Technical Information:

4dentify long-lived passive SCs [§54.21(a)(1)]

- Describe & justify methods [§ 54.21(a)(2)]

-Demonstrate aging effects managed [§ 54-21(a)(3)]

- Evaluation of TLAAs [§ 5.4.21(c)]

(Section 6.0)

CLB Changes affecting LRA FSAR Supplement Technical

[§ 54.21(b)]

[554-21(d)]

Specification changes

[§ 54-22]

Duke Integrated Plant EEnergy.

Assessment U Integrated plant assessment (IPA) is a licensee assessment that demonstrates that a nuclear power plant facility's structures and components requiring aging management review in accordance with § 54.21(a) for license renewal have been identified and that the effects of aging on the functionality of such structures and components will be managed to maintain the CLB such that there is an acceptable level of safety during the period of extended operation. (§ 54.3)

C+A+P+D=R.A.

October 15, 1998 Oconee License Renewal Project 8

W Duke Integrated Plant Energy.

Assessment m C

= structures and components & their intended functions m A

= applicable aging effects m P

= aging management programs & activities m D

= demonstration, operating experience, objective evidence a R.A. = reasonable assurance... that activities will be conducted in accordance with the CLB and will manage aging (thus allowing the findings of §54.29 to be made).

October 15, 1998 Oconee License Renewal Project 9

Duke Integrated Plant Energy Assessment

  • 0= structures and components & their intended functions
  • Divided by traditional engineering discipline for Oconee
  • Consistent with Oconee CLB, engineering basis and the guidance of NEI 95-10.
  • Recognize some differences among the discipline approaches and still satisfy the equation.
  • Results documented in engineering basis documents, new Oconee drawings and in Chapter 2 (Volume 1) of the Application.
  • NRC staff 1997 feedback shaped final presentation of results in the application.

October 15, 1998 Oconee License Renewal Project 10

Duke Integrated Plant Energy*

Assessment mA= applicable aging effects Potentialaging effects - Broad set of how aging mechanisms can manifest themselves. Examples: Loss of material, cracking, embrittlement.

  • Applicable aging effects - The set of aging effects applicable for the conditions at Oconee.
  • Operating experience, industry and plant-specific, helped reinforce our confidence in our set of applicable aging effects.
  • Results documented in engineering basis documents & in Chapter 3 (Volume II) of the Application.

October 15, 1998 Oconee License Renewal Project

Duke Conditions for Aging Effects Material Conditions for aging effects to exist at intersection Stress

.Environment October 15, 1998 Oconee License Renewal Project 12

Duke Integrated Plant Assessment mP = aging management programs & activities

  • Defined attributes for programs & activities in application.
  • NRC staff 1997 feedback shaped attribute definitions.
  • Recognized that plant programs overlap disciplines & many programs are mature and at steady-state.
  • New programs & activities are grouped in application (Section 4.3) to facilitate a consistent review.
  • Results documented in engineering basis documents, in Chapter 4 (Volume Ill) of the Application and in the UFSAR Supplement.

October 15, 1998 Oconee License Renewal Project 13

Oconee Nuclear Station License Renewal - Technical Information Programs and Activity Attributes 4.2 PROGRAM AND ACTIVITY ATTRiBUTEs Attributes that are utilized in most of the program and activity descriptions for license renewal, with a few exceptions [Footnote 1], are described in Section 4.2. The following information sources served as primary inputs to the attribute definitions used in Chapter 4:

1. NEI 95-10, Revision 0, Sections 4.2 and 4.3 [Reference 4.2-1]
2. Working Draft Standard Review Plan, Section 3.0 [Reference 4.2-2]
3. August 13, 1997, letter from the NRC to Duke Power-Comments on the License Renewal Inspection Program Example on the Reactor Coolant System Flow Nozzle [Reference 4.2-3]

The attribute definitions used to describe new and existing programs and activities are provided below.

Purpose - A clear statement of the reason why the program or activity exists for Oconee license renewal.

Scope - A description of the set of Oconee structures and components encompassed by the actions of the program or activity.

Aging Effects - A description of the applicable aging effects to be managed or the relevant physical conditions to be monitored for the identified scope of structures and components.

Method - A description of the type of action or technique used to identify or manage the aging effects or relevant conditions (e.g., visual examination of the component).

Sample Size - For new programs or activities, a sample population can be identified from the total population of affected structures and components for inspection or monitoring.

If a sample population is chosen for inspection or monitoring, a description of the sample population is provided.

1. The following programs are described in a narrative style rather than using the attributes: the Coatings Program, which is a special process as defined in the Duke Quality Assurance Program; the Chemistry Control Program, which contains more detail than can be included in this report; the Duke Quality Assurance Program and the Reactor Vessel Internals Aging Management Program, which is a long term developmental program.

4.2-1 Revision 2 Volume Idoc June 1998

Oconee Nuclear Station License Renewal - Technical Information Programs and Activity Attributes Industry Codes or Standards - A description of an industry code (e.g., ASME Section XI, IEEE) or an industry standard (e.g., ASTM or NRC-approved BWOG report) that guides or governs the program or activity. This attribute may not be applicable to some programs and activities.

Frequency - A description of the frequency of action that is established detection of aging effects or of relevant physical conditions.

Acceptance Criteria or Standard - Acceptance criteria or standards are described for the relevant conditions to be monitored or the chosen examination methods.

Corrective Action - A description of the action to be taken when the established acceptance criteria or standard is not met. Generally, the Duke Quality Assurance Program is applicable.

Timing of New Program or Activity - For any new programs or activities, an identification of the specific timing for the new program or activity.

Administrative Controls - An identification of the Oconee administrative structure under which the programs and activities are executed. The Duke Quality Assurance Program is applicable.

Regulatory Basis - For existing programs and activities, an identification of any existing Oconee regulatory basis for these actions such as the Technical Specifications. This attribute may be not applicable to some programs and activities.

4.

2.1 REFERENCES

FOR SECTION 4.2 4.2-1.

Industry Guideline for Implementing the Requirements of 10 CFR Part 54 The License Renewal Rule, NEI 95-10, Revision 0, Nuclear Energy Institute, March 1996.

4.2-2.

Standard Review Plan for the Review of License Renewal Applications for Nuclear Power Plants, Working Draft, NRC, September 1997.

4.2-3.

S. T. Hoffman (NRC) letter dated August 13, 1997, to W. R. McCollum (Duke), License Renewal Inspection Program Example for Oconee Nuclear Station, Units 1, 2, and 3, Docket Nos. 50-269, -270, and -287.

4.2-2 Revision 2 Volume III.doc June 1998

Existing Programs and Activities Credited in the Application for Renewed Operating Licenses for Oconee Nuclear Station Existing Regulatory Basis Program or Activity

1.

Battery Rack Inspections Oconee Improved Technical Specifications (ITS)

SR 3.8.1.3, SR 3.8.3.2, and SR 3.10.1.10

2.

Boric Acid Wastage Surveillance Commitment to GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components

3.

Chemistry Control Program Commitments to EPRI Water Chemistry Documents, ITS 5.5.14, ASTM D975, Standard Specification for Diesel Fuel Oils

4.

Coatings Program Commitment to RG 1.54, Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants

5.

Containment Inservice Inspection 10 CFR §50.55a ASME Code,Section XI, Subsections IWE, IWL

6.

Containment Leak Rate Test Program 10 CFR 50, Appendix J and Oconee ITS 3.6.1 and 5.5.2.

7.

Control Rod Drive Mechanism Nozzle and Commitment to GL 97-01, Degradation of Control Other Vessel Closure Penetrations Inspection Rod Drive Mechanism Nozzle and Other Vessel Program head Closure Penetrations

8.

Crane Inspection Program 29 CFR XVII, § 1910.179, Occupational Safety and Health Administration, Overhead and Gantry Cranes

9.

Duke Power Five-Year Underwater Inspection 18 CFR Part R, Water Power Project Works Safety of Hydroelectric Dams and Appurtenances

10. Duke Quality Assurance Program 10 CFR 50, Appendix B
11. Elevated Water Storage Tank Civil Inspection None
12. FERC Five Year Inspection 18 CFR Part 12, Subpart D, Safety of Water Power projects and Project Works

Existing Regulatory Basis Program or Activity

13. Fire Protection Program 10 CFR §50.48 10 CFR 50, Appendix R License Condition 3.E Oconee Selected Licensee Commitments (UFSAR Chapter 16)
14. Heat Exchanger Performance Testing Commitment to GL 89-13, Service Water System Problems Affecting Safety-Related Equipment
15. Inservice Inspection Plan 10 CFR §50.55a ASME Code Section XI, Subsections IWB, IWC, IWF
16. Inspection Program for Civil Engineering 10 CFR §50.65 Structures and Components (NEI 96-03 Industry Guideline for Monitoring the Condition of Structures at Nuclear Power Plants)
17. Penstock Inspection 18 CFR Part 12, Water Power Projects and Project Works Safety
18. Piping Erosion/Corrosion Program Commitment in response to BL 87-01, thinning of Pipe Walls in Nuclear Power Plants Commitment in response to GL 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning
19. Program to Inspect the High Pressure Commitment in response to GL 85-20, BL 88-08 Injection Connections to the RCS and event at Oconee in 1997
20. RCS Operational Leakage Monitoring Oconee ITS 3.4.13 2 1. Reactor Vessel Integrity Program 10 CF.R §50.60 10 CFR 50 Appendix G, H Technical Specifications - P/T Limits) 10 CFR §50.6 1, Pressurized Thermal Shock
22. Service Water Piping Corrosion Commitment to GL 89-13, Service Water System Problems Affecting Safety-Related Equipment
23. Steam Generator Tube Surveillance Program Oconee ITS 5.5. 10
24. System Performance Testing Commitment to GL 89-13, Service Water System Problems Affecting Safety-Related Equipment
25. Tendon - Secondary Shield Wall -

No ne Surveillance Program

26. 230 kV Keowee Transmission Line Inspection National Electric Safety Code, Part 2,,Safety Rules for Overhead Lines, Rule 214, Inspection and Tests of Lines and Equipment
23. tea Geeraor ubeSureilanc Prgra OcneeITS5.5107

Duke Integrated Plant Assessment m D = Demonstrations

  • Operating experience - industry and plant-specific
  • Objective evidence of program's past service
  • Results documented in engineering basis documents and in Chapter 4 (Volume III) of the Application.

October 15, 1998 Oconee License Renewal Project 18

Duke Integratea Plant 1& Energy.

At Plant Assessment

  • New Programs & Activities Some aging effects judged applicable for license renewal can be characterized today.

The program review found these effects may not be managed by current programs, so they must have new oversight for the renewal period.

Some aging effects judged applicable for license renewal can not be fully characterized today nor have they ever manifested themselves.

Additional information is required to complete this characterization. One time inspections are identified to provide reasonable assurance and to determine appropriate course of action.

  • All New Programs & Activities are described in Section 4.3 (Volume Ill) of the Application October 15, 1998 Oconee License Renewal Project 19

Duke Time Limited Aging Energy.

Analyses

  • 6 part criteria defined by Rule ( 54.3) a 3 ways to evaluate ( 54.21(c))

Duke Actions

  • Reviewed Oconee-specific & generic source documents to identify items meeting 6 part criteria
  • Evalutated these items for 60 years of service
  • Documented results in engineering basis documents
  • Presented results in Chapter 5 (Volume Ill) of the Application October 15, 1998 Oconee License Renewal Project 20

M Duke Source Documents Reviewed a Oconee Specific Source Documents

  • Duke/NRC Licensing Correspondence Files
  • Final Safety Analysis Report
  • Engineering Design Documents (e.g., Piping Installation Specification, Tank Design Drawings, etc.)
  • Technical Specifications
  • Safety Evaluation Report (original licensing) m Generic Source Documents
  • BWNT Topical Reports
  • Codes & Standards applicable to Oconee
  • NRC Generic Communications October 15, 1998 Oconee License Renewal Project 21

Source Documents Used to Identify Oconee Time-limited Aging Analyses Oconee Specific Source Documents Generic Source Documents TLA Duke/NRC Engr Tech Safety BWNT Codes &

Standard NRC Licensing FSAR Design Specs Evaluation Topicals Standards Review Generic File Doc's Report Plan Comms

1. Containment Liner Plate and n

no no no no no no Penetrations /

Thermal Fatigue

2.

Containment Post-Tensioning no S

no no no no no no System / Loss of Prestress

3.

Reactor Coolant System and Class 1 Components/

V V

V no no V

Thermal Fatigue, Fracture Mechanics Analyses for ISI reportable indications (fatigue)

4.

Reactor Vessel /

Embrittlement, Upper Shelf Energy Toughness, V

V no no no

/

no 6

no Thermal Shock, PTS, under clad crack growth.

Source Documents Used to Identify Oconee Time-limited Aging Analyses Oconee Specific Source Documents Generic Source Documents TLAA Duke/NRC Engr Tech Safety BWNT Codes &

Standard NRC Licensing FSAR Design Specs Evaluation Topicals Standards Review Generic File Doc's Report Plan Comms

5.

Reactor Vessel Internals / Loss of no no no no no no fracture toughness, fatigue

6.

Reactor Coolant Pump Flywheel /

no no no no 6

no no no Fatigue no

_no noo__nnn

7. Mechanical Component /

Thermal Fatigue no V

no

8. Electrical Equipment /

Environmental V

V no no no no V

Qualification

9. Polar Crane /

Fatigue, heavy load cycle la no no no no no no no V

cycles_______

10. Spent Fuel Rack Boraflex / Aging no no no no no no no of non-metallic no material

Duke

  1. Energy Exemptions a Section 50.12 exemptions to be identified and reviewed (§ 54.21(c))

Duke Actions

  • Reviewed licensing files to identify exemptions
  • Addressed exemptions found - results were that none involved TLAA
  • Documented results in engineering basis documents
  • Presented results in Chapters 1 & 5 of the Application (Volumes I and III)

October 15, 1998 Oconee License Renewal Project 24

Duke Energy.

Generic Safety Issues a NEI Review Results (Fatigue & EQ identified)

  • NRC Guidance Letters 1/98 & 6/98 (these two plus RCP Seals and Spent Fuel Pool identified)

Duke Actions

  • Addressed fatigue, EQ, RCP Seals and Spent Fuel Pool GSI for Oconee
  • Addressed each independent of any future generic resolution
  • Documented results in engineering basis documents and in Section 1.5 (Volume 1) of the Application
  • Recognize research challenge still exists October 15, 1998 Oconee License Renewal Project 25
  1. Energy.

Research Challenge m Developing a license renewal solution leads to a more mature understanding of plant aging management.

m Developing this solution also leads to contemplation of what may not be fully understood.

  • The academic research community has a mature research process in place to do such contemplation.

m Care must be taken by the utilities and the NRC to trust and use this research process, not placing a scientific research burden on the plant engineering staff.

m Duke discussed this challenge with Chairman Jackson in March 1998.

October 15, 1998 Oconee License Renewal Project 26

Duke WEnergy Observations & Results a Duke has a track record of proactively addressing and managing plant aging issues.

m The real license renewal challenge is the story telling needed to share our awareness and efforts.

a The Oconee License Renewal Team performed a solid engineering review and we have confidence in our results.

m The Application reports these results in a form aimed at facilitating NRC staff review.

m We recognize the NRC staff's challenge and made a conscious effort to package our license renewal solution to allow a finding in a timely and efficient manner.

  • We encourage additional interaction on the engineering basis information via site visits, if needed October 15, 1998 Oconee License Renewal Project 27

eg.Duke Engineering Basis avEne r gy..

Documents m Oconee Reactor Building Containment Aging Management Review for License Renewal m Oconee Reactor Coolant System Aging Management Review for License Renewal a

Oconee Mechanical System Scoping for License Renewal a

Oconee Mechanical Component Screening for License Renewal n

Oconee Mechanical Component Aging Management Review for License Renewal m Oconee Electrical Component Aging Management Review for License Renewal n

Oconee Structures and Structural Components Aging Management Review for License Renewal n

Time-Limited Aging Analyses of Electrical Components for License Renewal n

Time-Limited Aging Analyses of Mechanical System Thermal Fatigue for License Renewal m Identification and Evaluation of Exemptions to 10 CFR for Oconee Nuclear Station m Identification and Evaluation of Time Limited Aging Analyses Per 10 CFR 54.21(c) n Review of Environmental Issues for Oconee License Renewal October 15, 1998 Oconee License Renewal Project 28

Duke hEnergy.

Application Organization Criteria used to organize the Oconee application:

a Follow the license renewal rule - Solve the Integrated Plant Assessment & Time-limited Aging Analyses

  • Address applicable Generic Safety Issues a Follow discipline results, sticking with the defense-in-depth segregation priority a Follow the Oconee UFSAR organizational pattern when reporting the technical results to allow a matchline with the CLB m Provide a clear basis for commitment management with a new UFSAR Chapter 18 in the UFSAR Supplement.

October 15, 1998 Oconee License Renewal Project 29

Application for Renewed Operating Licenses Oconee Nuclear Station Format Overview Topic Component +

Aging Effect +

Program +

Demonstration Time-Limited Aging Analyses Containment 2.3 3.3 4

45.3 RCS Components 2.4 3.4 4

4 5.4 Mechanical System 2.5 3.5 4

4 5.5 Components Electrical Components 2.6 3.6 4

4 5.6 Structures &

Structural 2.7 3.7 4

Components I

Exhibit A (OLRP-1001)

Chapter 2 Chapter 3 Chapter 4 Chapter 4 Chapter 5 Regulatory Requirement

§54.21(a)(1) &

§54.21(a)(3) 54.21(c)

______________(a)(2)

Finding

§54.29(a)(1) 9(

54.29(a)(2)

October 15, 1998

OWnergy.. Oconee License Renewal Excerpts from the Application for Renewed Operating Licenses for Oconee Nuclear Station October 15, 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Volume I, Exhibit A, Table of Contents Volume I, Exhibit A Table of Contents

1. INTRODUCTION......................................******................

1.14 1.1 PURPOSE 1.1-1

1.2 DESCRIPTION

OF OCONEE NUCLEAR STATION...........................1.2-1 1.2.1 OCONEE NUCLEAR STATION....................

1.2-1 1.2.2 KEOWEE HYDROELECTRIC STATION.................................................

........ 1.2-2 1.2.3 STANDBY SHUTDOWN FACILITY.....................-.-...

1.2-2 1.3 TECHNICAL INFORMATION REQUIRED FOR AN APPLICATION...........................

1.3-1 1.3.1 INTEGRATED PLANT ASSESSMENT............................................................................1.3-1 1.3.2 TIME-LIMITED AGING ANALYSES AND EXEMPTIONS.............................................1.3-14 1.4 PROCESS TO UPDATE TECHNICAL INFORMATION 1.4-1 1.5 GENERIC SAFETY ISSUES.............................................

l.5-1 1.

5.1 BACKGROUND

1.5-1 1.5.2 GSI 23 - REACTOR COOLANT PUMP SEAL FAILURES.............

1.5-4 1.5.3 GSI 168 - ENVIRONMENTAL QUALIFICATION OF ELECTRICAL COMPONENTS......... 1.5-5 1.5.4 GSI 173.A - SPENT FUEL STORAGE PoOL: OPERATING FACILITIES........................1.5-6 1.5.5 GSI 190 - FATIGUE EVALUATION OF METAL COMPONENTS FOR 60-YEAR PLANT LIFE 1.5-7 1.

5.6 REFERENCES

FOR SECTION 1.5.

1.5-12

2. IDENTIFICATION OF STRUCTURES & COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW..................................
      • .********.***..........................................1.5-1

2.1 INTRODUCTION

.......................................................2.1-1 2.2 IDENTIFICATION OF SYSTEMS, STRUCTURES, AND COMPONENTS WITHIN THE SCOPE OF LICENSE RENEWAL................................

.....2.2-1 2.2.1 REVIEW TO CRITERIA IN §§54.4(a)(1) AND (a)(2)....................................................

2.2-1 2.2.2 REVIEW TO CRITERIA IN §54.4 (a)(3)...................................

2.2-4 2.2.3 R ESULTS..................................................

2.2-8 2.

2.4 REFERENCES

FOR SECTION 2.2......................-.--.-..

2.2-9 2.3 REACTOR BUILDING (CONTAINMENT) STRUCTURAL COMPONENTS....... 2.3-1 2.

3.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY REACTOR BUILDING CONTAINMENT)

STRUCTURAL COM PONENTS...........................-.-...--.-..-..--...-....................................2.3-1 2.3.2 CONCRETE COM PONENTS............................--.-..-...-....-.....---...................................

.2.3-4 2.3.3 STEEL COMPONENTS................................................2.3-6 Ill Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Volume I, Exhibit A, Table of Contents Volume I, Exhibit A Table of Contents 2.3.4 POST-TENSIONING SYSTEM............................................2.3-13 2.

3.5 REFERENCES

FOR SECTION 2.3...............................---...-..-..--..-................................2.3-14 2.4 REACTOR COOLANT SYSTEM MECHANICAL COMPONENTS AND CLASS I COMPONENT SUPPORTS................................

..... 2.4-1 2.

4.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY REACTOR COOLANT SYSTEM COMPONENTS AND CLASS I COMPONENT SUPPORTS SUBJECT TO AGING MANAGEMENT REVIEW.....................

...................... 2.4-1 2.4.2 PROCESS To INCORPORATE APPROVED B&WOG TOPICAL REPORTS BY REFERENCE............................................................................

2.4-4 2.4.3 REACTOR COOLANT SYSTEM PIPING....................................

2.4-5 2.4.4 PRESSURIZER.....................................................------.

2.4-6 2.4.5 REACTOR VESSEL........................

2.4-7 2.4.6 REACTOR VESSEL INTERNALS.......................................................2.4-8 2.4.7 ONCE THROUGH STEAM GENERATORS.................-.-----.-...--....--...--...........................2.4-9 2.4.8 REACTOR COOLANT PUMPS.................................

........2.4-11 2.4.9 CONTROL ROD DRIVE MECHANISM MOTOR TUBE HOUSINGS...............................2.4-13 2.4.10 LETDOWN COOLERS 2.4-14 2.4.11 CLASS I COMPONENT SUPPORTS..............................................2.4-15 2.4.12 REFERENCES FOR SECTION 2.4...............................--....--......-.--...-........................2.4-21 2.5 MECHANICAL SYSTEM COMPONENTS...................................2.5-1 2.5.1 PROCESS USED To IDENTIFY MECHANICAL COMPONENTS SUBJECT TO AGING M ANAGEMENT REVIEW.........................................

2.5-1 2.5.2 DETAILED PROCESS DESCRIPTION..................................................2.5-2 2.5.3 CONTAINMENT HEAT REMOVAL SYSTEMS.........................-..-...-..............................2.5-4 2.5.4 CONTAINMENT ISOLATION SYSTEM..........................-

2.5-6 2.5.5 EMERGENCY CORE COOLING SYSTEMS..........................-....-...

2.5-11 2.5.6 AUXILIARY SYSTEMS...............---..

2.5-14 2.5.7 PROCESS AUXILIARIES..............................-.--..--.-..

2.5-18 2.5.8 AIR CONDITIONING, HEATING, COOLING AND VENTILATION SYSTEMS.................2.5-20 2.5.9 STEAM AND POWER CONVERSION SYSTEMS....................-.-.--...-............................

2.5-22 2.5.10 PosT-ACCIDENT HYDROGEN CONTROL...............................2.5-25 2.5.11 REACTOR COOLANT PUMP MOTOR OIL COLLECTION SYSTEM............................

2.5-27 2.5. 12 REACTOR COOLANT SYSTEM VENTS, DRAINS, AND INSTRUMENT LINES............ 2.5-28 2.5.13 KEOWEE HYDROELECTRIC STATION......................-..--..-----.....

........................ 2.5-29 2.5.14 STANDBY SHUTDOWN FACILITY...........................--.-.---.-...

2.5-34 2.5.15 REFERENCES FOR SECTION 2.5..............

..................... 2.5-39 2.6 ELECTRICAL COMPONENTS 2.6-1 Iv Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Volume 1, Exhibit A, Table of Contents Volume I, Exhibit A Table of Contents 2.

6.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY ELECTRICAL COMPONENTS SUBJECr TO AGING M ANAGEMENT REVIEW.......................--........----..-...-....-.-.............................

2.6-1 2.6.2 Bus............................................

2.6-2 2.6.3 INSULATED CABLES AND CONNECTIONS............................-..-.......-..........................2.6-4 2.6.4 INSULATORS...................................................

-.---..-...................................................2.6-5 2.6.5 TRANSMISSION CONDUCTORS.......................................-.--

.-............................ 2.6-6 2.6.6 ELECTRICAL COMPONENTS NOT SUBJECT TO AGING MANAGEMENT REVIEW........ 2.6-7 2.6.7 STRUCTURES AND AREAS CONTAINING ELECTRICAL COMPONENTS SUBJECT TO AGING M ANAGEMENT REVIEW.....................

2.6-13 2.

6.8 REFERENCES

FOR SECTION 2.6............................-........-..

2.6-14 2.7 STRUCTURES & STRUCTURAL COMPONENTS.........................................................2.7-1 2.

7.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY STRUCTURAL COMPONENTS SUBJECT TO AGING MANAGEMENT REVIEW.................................-............................2.7-1 2.7.2 STRUCTURAL COMPONENTS..........................................

2.7-4 2.7.3 AUXILIARY BUILDINGS...............

2.7-9 2.7.4 EARTHEN EMBANKMENTS....................

2.7-11 2.7.5 INTAKE STRUCTURE................................-.........................

2.7-13 2.7.6 KEOWEE STRUCTURES.............................................

2.7-14 2.7.7 REACTOR BUILDINGS INTERNAL STRUCTURE AND THE UNIT VENT STACKS.........2.7-18 2.7.8 STANDBY SHUTDOWN FACILT Y.........................--..---....-.-.--...-.-.............................

2.7-21 2.7.9 TURBINE BUILDING..................................................................2.7-22 2.7.10 YARD STRUCTURES.................................................................2.7-24 2.7.11 REFERENCES FOR SECTlON 2.7................-.-..............................-........................2.7-29 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Volume II, Exhibit A, Table of Contents Volume II, Exhibit A Table of Contents

3. IDENTIFICATION OF APPLICABLE AGING EFFECTS.

3.1 INTRODUCTION

3.2 DESCRIPTION

OF THE PROCESS TO IDENTIFY APPLICABLE AGING EF E.......................................................................................

3.2-1 3.2.1 PROCESs OVERVIEW...................................

................... 3.2-1 3.2.2 SERVICE ENVIRONMENTS............................................

3.2-2 3.

2.3 REFERENCES

FOR SECTION 3.2......................................3.2-4 3.3 AGING EFFECTS FOR REACTOR BUILDING (CONTAINMENT) STRUCTURAL COMPONENTS..............................................................3.3-1 3.

3.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY THE APPLICABLE AGING EFFECTS FOR REACTOR BUILDING (CONTAINMENT) STRUCTIjRAL COMPONENTS...........-.-.......3.3-1 3.3.2 APPLICABLE AGING EFFECTS FOR CONCRETE COMPONENTS....-.-.................

3.3-2 3.3.3 APPLICABLE AGING EFFECTS FOR STEEL COMPONENTS....................

3.3-8 3.3.4 APPLICABLE AGING EFFECTS FOR THE POST-TENSIONING SYSTEM

........... 3.3-13 3.

3.5 REFERENCES

FOR SECTION 3.3...........

3.3-17 3.4 AGING EFFECTS FOR REACTOR COOLANT SYSTEM COMPONENTS & CLASS I COMPONENT SUPPORTS..........................................................3.4-1 3.

4.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY THE APPLICABLE AGING EFFECTS FOR REACTOR COOLANT SYSTEM COMPONENTS & CLASS I COMPONENT SUPPORTS............3.4-1 3.4.2 PROCESS TO INCORPORATE APPROVED B&WOG TOPICALS REPORTS BY REFERENCE..............................................

--................34-3 3.4.3 REACTOR COOLANT SYSTEM PIPING...................................

3.4-4 3.4.4 PRESSURIZER.........................................

3.4-7 3.4.5 REACTOR VESSEL.............................................................3.4-10 3.4.6 REACTOR VESSEL INTERNALS..............................................3.4-12 3.4.7 ONCE THROUGH STEAM GENERATOR........................................3.4-15 3.4.8 REACTOR COOLANT PUMPS.....................................................3.4-21 3.4.9 CONTROL ROD DRIVE TUBE MOTOR HOUSINGS 3.4-23 3.4.10 LEhowN COOS........................

3.4-25 3.4.11 CLASS I COMPONENT SUPPORTS..............................-*----.....--------------------..............3.4-28 3.4.12 REFERENCES FOR SECTION 3.4.......

-............................... 3.4-31 3.5 AGING EFFECTS FOR MECHANICAL SYSTEM COMPONENTS

............. 3.5-1 3.

5.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY THE APPLICABLE AGING EFFECTS FOR MECHANICAL SYSTEM COMPONENTS....................................3.5-1 3.5.2 APPLCABLE AGING EFFECTS FOR MECHANICAL SYSTEM COMPONENTS........

3.5-1 3.5.3 CONTAINMENT HEAT REMOVAL SYSTEMS..............................3.5-43 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewa! - Technical Information Volume I, Exhibit A, Table of Contents Volume II, Exhibit A Table of Contents 3.5.4 CONTAINMENT ISOLATION SYSTEM...................................................3.5-47 3.5.5 EMERGENCY CORE COOLING SYSTEMS................................

3.5-54 3.5.6 AuxILiARY SYSTEMS.........................................

3.5-60 3.5.7 PROCESS AUxIARIES 3.5-68 3.5.8 AIR CONDITIONING, HEATING, COOLING AND VENTILATION SYSTEMS................ 3.5-70 3.5.9 STEAM AND POWER CONVERSION SYSTEMS...................

3.5-72 3.5. 10 PosT-ACCIDENT HYDROGEN CONTROL...............................

3.5-78 3.5.11 REACTOR COOLANT PUMP MOTOR OIL COLLECTION SYSTEM.........

.....3.5-80 3.5.12 REACTOR COOLANT SYSTEM VENTS, DRAINS, AND INSTRUMENT LINES......

3.5-81 3.5.13 KEOWEE HYDROELECTRIC STATION...........................*

.*.... 3.5-82 3.5.14 STANDBY SHUTDOwN FACILITY...............................................3.5-91 3.6 AGING EFFECTS FOR ELECTRICAL COMPONENTS................

............ 3.6-1 3.6.1 DESCRIPHON OF THE PROCESS TO IDENTIFY THE APPLICABLE AGING EFFECTS FOR ELECTRICAL COMPONENTS...............................................

3.6-1 3.6.2 Bus 3.6-2 3.6.3 INSULATED CABLES AND CONNECTIONS................................3.6-7 3.6.4 INSULATORS...........-.............................-

3.6-13 3.6.5 TRANSMISSION CONDUCTORS...--.....................-...

......... 3.6-16 3.

6.6 REFERENCES

FOR SECTION 3.6.......................................................3.6-18 3.7 AGING EFFECTS FOR STRUCTURAL COMPONENTS.............

................ 3.7-1 3.

7.1 DESCRIPTION

OF THE PROCESS TO IDENTIFY THE APPLICABLE AGING EFFECTS FOR STRUCTURAL COMPONENTS......................................

............... 3.7-1 3.7.2 APPLICABLE AGING EFFECTS FOR STRUCTURAL COMPONENTS..........................3.7-2 3.7.3 AUXILIARY "'ALIING.............................................3.7-22 3.7.4 EARTHEN EMBANKMENTS........................

.................. 3.7-25 3.7-5 INTAKE STRUCTURE................

..... 3.7-29 3.7.6 KEOWEE STRUCTURES.....................................

3.7-31 3.7.7 REACTOR BUILDING (INTERNAL STRUCIT RAL COMPONENTS AND THE UNIT VENT STACKS)...............---...............................................3.7-33 3.7.8 STANDBY SHrowN FACILITY.....................................3.7-38 3.7.9 TURBINE BUILDING.--................----..........-..........

3.7-40 3.7.10 YARD STRUCTURES.....-.--.--..........

3.7-42 3.7.11 REFERENCES FOR SECON 37.....................................3.7-44 11 Revision 2 Volume II.doc June 1998

Oconee Nuclear Station License Renewal - Technical Information Volume Ell, Exhibit A, Table of Contents Volume III, Exhibit A Table of Contents

4. AGING MANAGEMENT PROGRAMS AND ACTIVITIES.....................................4.0-1 4.1 INTRO D UCTIO N..........................................-..-..-..--.-....---..---.---..--.............................
4. 1-1 4.2 PROGRAM AND ACTIVITY ATTRIBUTES...............................4.2-1 4.

2.1 REFERENCES

FOR SECION 4.2...............................--.---.---...-....---............................4.2-2 4.3 NEW PROGRAMS AND ACTIVITIES.........................................................................4.3-1 4.3.1 ALLOY 600 AGING MANAGEMENT PROGRAM.................--...----..--............................4.3-2 4.3.2 CAST IRON SELECTIVE LEACHING INSPECTION................--..----................................4.3-5 4.3.3 GALVANIC SUSCEPTIBILITY INSPECTION...................---.....--....--..............................4.3-7 4.3.4 KEOWEE AIR AND GAS SYSTEMS INSPECTION.....................................................

4.3-10 4.3.5 KEOWEE OIL SAMPLING PROGRAM...........................................4.3-12 4.3.6 ONCE THROUGH STEAM GENERATOR UPPER LATERAL SUPPORT INSPECTION.....4.3-14 4.3.7 PRESSURIZER EXAMINATIONS............................-.--....-..-..--...

...................... 4.3-16 4.3.8 PREVENTIVE MAINTENANCE AcnTVrrY ASSESSMENT...............-.-........................

4.3-21 4.3.9 REACTOR BUILDING SPRAY SYSTEM INSPECTION..................................................4.3-24 4.3.10 REACTOR COOLANT PUMP MOTOR OIL COLLECTION SYSTEM INSPECTION........4.3-26 4.3.11 REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM........................ 4.3-28 4.3.12 SMALL BORE PIPING INSPECTION...............-...--.....---.---.-...-..--..............................4.3-29 4.3.13 TREATED WATER SYSTEMS STAINLESS STEEL INSPECTION................................

4.3-31 4.3.14 REFERENCES FOR SECTION 4.3........................-

...-..-....-.--........................... 4.3-34 4.4 BATTERY RACK INSPECTIONS 4.4-1 4.4.1 PROGRAM DESCRIPTION 4.4-1 4.4.2 OPERATING EXPERIENCE AND DEMONSTRATION............-....-............................

4.4-2 4.

4.3 REFERENCES

FOR SECTION 4.4....................

4.4-3 4.5 BORIC ACID WASTAGE SURVEILLANCE PROGRAM..........................................4.5-1 4.5.1 PROGRAM DESCRIPTION.............................................4.5-1 4.5.2 OPERATING EXPERIENCE AND DEMONSTRATION............---.-----.--...........................4.5-2 4.

5.3 REFERENCES

FOR SECTION 4.5...............................---...............................4.5-3 4.6 CHEMISTRY CONTROL PROGRAM.......................................................................4.6-1 4.

6.1 BACKGROUND

4.6-1 4.6.2 PRIMARY CHEMISTRY CONTROL SPECIFICATIONS...........................4.6-4 4.6.3 SECONDARY CHEMISTRY CONTROL SPECIFICATIONS...........-...--....-........................4.6-7 4.6.4 COMPONENT COOLANT CHEMISTRY CONTROL SPECIFICATIONS.............................4.6-9 4.6.5 STANDBY SHUTDOWN FACILITY FUEL OIL SURVEILLANCES............................4.6-11 4.

6.6 REFERENCES

FOR SECTION 4.6..........................-...-...---..-.-.....................................4.6-12 4.7 COATINGS PROGRAM...................

4.7-1 4.

7.1 REFERENCES

FOR SECTION 4.7....................................-....--.-..........................

4.7-2 Revision 2 Volume III.doc June.1998

Oconee Nuclear Station License Renewal - Technical Information Volume I, Exhibit A, Table of Contents Volume III, Exhibit A Table of Contents 4.8 CONTAINMENT INSERVICE INSPECTION PLAN.......................4.8-1 4.8.1 ASME SECTION XI, SUBSECION IWE EXAMINATIONS....................

4.8-3 4.8.2 ASME SECTION XI, SUBSECTION IWL EXAMINATIONS 4.8-6 4.

8.3 REFERENCES

FOR SECTION 4.8 4.8-9 4.9 CONTAINMENT LEAK RATE TESTING PROGRAM.....................4.9-1 4.9.1 REACTOR BUILDING TYPE A INTEGRATED LEAK RATE TEST.................................4.9-2 4.9.2 REACTOR BUILDING TYPE B LOCAL LEAK RATE TEST...........................................

4.9-4 4.

9.3 REFERENCES

FOR SECTION 4.9.........

4.9-5 4.10 CONTROL ROD DRIVE MECHANISM NOZZLE AND OTHER VESSEL CLOSURE PENETRATIONS INSPECTION PROGRAM 4.10-1 4.10.1 PROGRAM DESCRIPTION............................................4.10-1 4.10.2 OPERATING EXPERIENCE AND DEMONSTRATION 4.10-2 4.

10.3 REFERENCES

FOR SECTION 4.10.....................................4.10-3 4.11 CRANE INSPECTION PROGRAM 4.11-1 4.11.1 PROGRAM DESCRIPTION............................................

4.11-1 4.11.2 OPERATING EXPERIENCE AND DEMONSTRATION................................................4.11-2 4.

11.3 REFERENCES

FOR SECTION 4.11 4...1...

............. 4.11-3 4.12 DUKE POWER FIVE-YEAR UNDERWATER INSPECTION OF HYDROELECTRIC DAMS AND APPURTENANCES

..................................................4.12-1 4.12.1 PROGRAM DESCRIPTION...........................................4.12-1 4.12.2 OPERATING EXPERIENCE AND DEMONSTRATION 4.12-2 4.13 DUKE QUALITY ASSURANCE PROGRAM..............................................

4.13-1 4.13.1 CORRECTVE ACTION 4..............

.................... 4.13-1 4.13.2 DOCUMENT CONTROL

....4.13-2 4.

13.3 REFERENCES

FOR SECTION 4.13..........................................................................4.13-3 4.14 ELEVATED WATER STORAGE TANK CIVIL INSPECTION..............................4.14-1 4.14.1 PROGRAM DESCRIPTION...........................--..-.-----...-.-..........................................4.14-1 4.14.2 OPERATING EXPERIENCE AND DEMONSTRATION.................................................4.14-2

4. 15 FEDERAL ENERGY REGULATORY COMMISSION (FERC) FIVE YEAR INSPECTION 4.15-1 4.15.1 PROGRAM DESCRIPTION.......................

4.15-1 4.15.2 OPERATING EXPERIENCE AND DEMONSTRATION.................................................4.15-2 4.

15.3 REFERENCES

FOR SECTION 4.15 4.15-3 4.16 FIRE PROTECTION PROGRAM 4.16-1 4.16.1 FIRE BARRIER INSPECIONS.......

4.16-1 4.16.2 FIRE WATER SYSTEM TEST.........................................4.16-3 4.

16.3 REFERENCES

FOR SECTION4.16.....................................4.16-6 Revision 2 Volume U.doc June 1998

Oconee Nuclear Station License Renewal - Technical Information Volume III, Exhibit A, Table of Contents Volume III, Exhibit A Table of Contents 4.17 HEAT EXCHANGER PERFORMANCE TESTING ACTIVITIES

............ 4.17-1 4.

17.1 REFERENCES

FOR SECTION 4.17...............................4.17-2 4.18 INSERVICE INSPECTION PLAN.......

4.18-1 4.18.1 ASME SECTION XI, SUBSECTION IWB AND IWC INSPECTIONS 4.18-2 4.18.2 CAST AUSTENITIC STAINLESS STEEL FLAW EVALUATION 4.18-4 4.18.3 ASME SECTION XI, SUBSECTION IWF INSPECIONS..........................................

4.18-6 4.18.4 OPERATING EXPERIENCE AND DEMONSTRATION............................................4.18-7 4.

18.5 REFERENCES

FOR SECTION 4.18.................

.......................... 4.18-8 4.19 INSPECTION PROGRAM FOR CIVIL ENGINEERING STRUCTURES AND C O M PO NENTS...................................---...--.-.-..-.-.--.....-...-.-.........................................

4.19-1 4.19.1 PROGRAM DESCRPTION.........................-----...-....-.-

4.19-1 4.19.2 OPERATING EXPERIENCE AND DEMONSTRATION...............................................4.19-3 4.20 PENSTOCK INSPECTION.......................................

4.20-1 4.20.1 PROGRAM DESCRIPTION................................----.-..-..

4.20-1 4.20.2 OPERATING EXPERIENCE AND DEMONSTRATION............................................4.20-2 4.21 PIPING EROSION/CORROSION PROGRAM.....................................................4.21-1 4.21.1 PROGRAM D ESCRIPTION.....................................--.-..-.--.-..-...................................

4.21-1 4.21.2 OPERATING EXPERIENCE AND DEMONSTRATION.................................................4.21-3 4.21.3 REFERENCE FOR SECTION 4.21.........................----..--...--......................................4.21-3 4.22 PROGRAM TO INSPECT THE HIGH PRESSURE INJECTION CONNECTIONS TO THE REACTOR COOLANT SYSTEM...................-.-.-....--.-..................................4.22-1 4.22.1 PROGRAM DESCRIPTION..........

4.22-1 4.22.2 OPERATING EXPERIENCE AND DEMONSTRATION.................................................4.22-3 4.

22.3 REFERENCES

FOR SECTION 4.22.........................................................................4.22-4 4.23 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE MONITORING...4.23-1 4.23.1 PROGRAM DESCRIPTION.............

4.23-1 4.23.2 OPERATING EXPERIENCE AND DEMONSTRATION.................................................4.23-2 4.

23.3 REFERENCES

FOR SECION 4.23....................-...--.....-.-...

4.23-3 4.24 REACTOR VESSEL INTEGRITY PROGRAM 4.24-1 4.24.1 MASTER INTEGRATED REACTOR VESSEL SURVEILLANCE PROGRAM..................4.24-3 4.24.2 CAVITY DOSIMETRY PROGRAM.......

.-.............................. 4.24-5 4.24.3 FLUENCE AND UNCERTAINTY CALCULATIONS.................--..................................4.24-7 4.24.4 PRESSURE TEMPERATURE LIMIT CURVES.............----..---.-..-...---..........................4.24-9 4.24.5 EFFECTIVE FULL POWER YEARS......................--...-.----.-.--.--...............................

4.24-11 4.

24.6 REFERENCES

FOR SECION 4.24.............................-.-.......-...-.--..........................4.24-13 4.25 SERVICE WATER PIPING CORROSION PROGRAM..........................................4.25-1 4.25.1 PROGRAM DESCRIPTION...........................................4.25-1 Revision 2 Volume U.doc June 1998

Oconee Nuclear Station License Renewal - Technical Information Volume m, Exhibit A, Table of Contents Volume III, Exhibit A Table of Contents 4.25.2 OPERATING EXPERIENCE AND DEMONSTRATION...................--.-.....................4.25-3 4.

25.3 REFERENCES

FOR SECTION 4.25.....................................4.25-4 4.26 STEAM GENERATOR TUBE SURVEILLANCE PROGRAM...............................

4.26-1 4.26.1 PROGRAM DESCRIPIHON...........................................4.26-1 4.26.2 OPERATING EXPERIENCE AND DEMONSTRATION.........................4.26-2 4.

26.3 REFERENCES

FOR SECTION 4.26.....................................4.26-2 4.27 SYSTEM PERFORMANCE TESTING ACTIVITIES.........

4.27-1 4.

27.1 REFERENCES

FOR SECTION 4.27..................................4.27-2 4.28 TENDON - SECONDARY SHIELD WALL - SURVEILLANCE PROGRAM........4.28-1 4.28.1 PROGRAM DESCRIPTION......................................................4.28-1 4.28.2 OPERATING EXPERIENCE AND DEMONSTRATION..............-..........4.28-2 4.

28.3 REFERENCES

FOR SECTION 4.28.....................................4.28-3 4.29 230 KV KEOWEE TRANSMISSION LINE INSPECTION................... 4.29-1 4.29.1 PROGRAM DESCRIPTION.........................

4.29-1 4.29.2 OPERATING EXPERIENCE AND DEMONSTRATION........................4.29-2 4.

29.3 REFERENCES

FOR SECTION 4.29.....................................4.29-2

5. TIME-LIMITED AGING ANALYSES AND EXEMPTIONS REVIEW......................5.0-1

5.1 INTRODUCTION

.............. 5.1-1 5.2 PROCESS OVERVIEW...............................................-.-.-.....

-.......... 5.2-1 5.2.1 IDENTIFICATION AND EVALUATION OF TIME-LIMITED AGING ANALYSES....... 5.2-1 5.2.2 IDENTIFICATION OF EXEMPTIONS....................................................5.2-3 5.

2.3 REFERENCES

FOR SECTION 5.2...............................................5.2-4 5.3 TIME-LIMITED AGING ANALYSES FOR THE REACTOR BUILDING (CONTAINMENT) STRUCTURAL COMPONENTS.

5.3-1 5

. 1 CONTAiNmENT

..................... 5.3-1 5.3.2 CONTAINMENT POST-TENSIONG SYSTEM..............................5.3-4 5.

3.3 REFERENCES

FOR SECTION 5.3...................................................5.3-5 5.4 TIME-LIMITED AGING ANALYSES FOR THE REACTOR COOLANT SYSTEM AND CLASS I COMPONENTS..........................................

5.4.1 REACTOR COOLANT SYSTEM PIPING AND COMPONEN

.................... 5.4-2 5.4.2 REACTOR VESSEL.................-.................................................

5.4-11 5.4.3 REACTOR VESSEL......

5.4 -18 5.4.4 REACTOR COOLANT PUMP FLYWHEEL.................................

5.4-19 5.

4.5 REFERENCES

FOR SECTION 5.4.........-................................................

5.4-20 5.5 TIME-LIMITED AGING ANALYSES FOR MECHANICAL COMPONENTS..........5.5-1 5.5.1 MECHANICAL COMPONENT THERMAL FATIGUE...............................

5.5-1 Iv Revision 2 Volume U.doc June 1998

Oconee Nuclear Station License Renewal -Technical Information Volume H, Exhibit A, Table of Contents Volume IH, Exhibit A Table of Contents 5.6 TIME-LIMITED AGING ANALYSES FOR ELECTRICAL EQUIPMENT................5.6-1 5.6.1 ACCELEROMETERS, TEC MONITOR....................................5.

3 5.6.2 ACTUATORS, LIMIORQUE

.... 5.6-3 5.6.3 ACTUATORS, ROTORK.................................................................5.6-4 5.6.4 CABLES, ANACONDA EPR/HYPALON & EPRINEOPRENE

.................. 5.6-4 5.6.5 CABLES, BIW CSPE...........................................5.6-4 5.6.6 CABLES, BRAND-REX & SAMUEL MOORE PVC 5.6-5 5.6.7 CABLES, BRAND-REX FLAME RETARDANT XLPE.......5.6-6 5.6.8 CABLES, ITT SUPRENANT & RAYCHEM CROSS-LINKED POLYALKENE HOOK-UP W IRE..........

-................................................. 5 6-6 5.6.9 CABLES, KERITE-HTK.............................................

5.6-7 5.6.10 CABLES, OKONITE EPR/NEOPRENE..................-.---.....--..-.-....................................

5.6-8 5.6.11 CABLES, SAMUEL MOORE EPDM/HYPALON..............................5.6-8 5.6.12 CONNECTION & SEALING ASSEMBLIES, SCOTCHCAST 9 AND SWAGELOK QUICK-CONNECT ASSEMBLIES......................-..--.--.-.....--...-....................................

5.6-9 5.6.13 HEAT SHRINK TUBING, RAYCHEM NCBK NUCLEAR CABLE BREAKOUT SPLICE ASSEMBLIES...............................-.-......-...-...-.................

5.6-10 5.6.14 HEAT SHRINK TUBING, RAYCHEM NPKV NUCLEAR PLANT STUB CONNECTION K IT.............................--.--.-..--..

5.6-10 5.6.15 HEAT SHRINK TUBING, RAYCHEM WCSF-N IN-LINE SPLICE ASSEMBLIES.........5.6-11 5.6.16 HEAT SHRINK TUBING, EGS GRAYBOOTS...............

........................ 5.6-12 5.6.17 HEAT SHRINK TUBING, EGS CONNECTORS.........................................................

5.6-12 5.6.18 MOTORS, JOY/RELIANCE..........................................5.6-12 5.6.19 M OTORS, LOUIs-ALLIS.............................-..-----..-.-.-.-.....--....................................5.6-12 5.6.20 M OTORS, RELIANCE.....................--......-.-...-...---......-....-...................................

5.6-12 5.6.21 M OTORS, W ESTINGHOUSE..........................-....-.-..-----..--..-....................................5.6-13 5.6.22 PENETRATION ASSEMBLIES, CONAX..............................

5.6-14 5.6.23 PENETRATION ASSEMBLIES, D.G. O'BRIAN....................................................

5.6-14 5.6.24 PENETRATION ASSEMBLIES, VIKING.....................----...-.................................5.6-15 5.6.25 RTD, CONAX.............................................---..-...................................................

5.6-15 5.6.26 RTD, ROSEMOUNT.......................

5.6-16 5.6.27 RTD, W EED.....................................

5.6-16 5.6.28 SOLENOID VALVES, VALCOR...................---..--.-.--...-..-..-..-..-..--............................

5.6-16 5.6.29 SWITCHES, BARTON/W ESTINGHOUSE......................---.-...--..................................

5.6-16 5.6.30 TERMINAL BLOCKS, STATES & STANWICK...................-.......--............................5.6-16 5.6.31 TRANSMITIERS, GEMS DELAVAL................

.-----.................................5.6-17 5.6.32 TRANSMITIERS, BARTON MODEL 764...................-..-.--................................

5.6-17 5.6.33 TRANSMITTERS, ROSEMOUNT.....................--....-.-.-......

-...............................5. 6-18 5.6.34 REFERENCES FOR SECTION 5.6..................................

5.6-18 v

Revision 2 Volume HI.doc June 1998

Oconee Nuclear Station License Renewal - Technical Information Volume III, Exhibit A, Table of Contents Volume II, Exhibit A Table of Contents 5.7 TIME-LIMITED AGING ANALYSES FOR STRUCTURES & STRUCTURAL COM PONENTS......................................

5.7-1 5.7.1 POLAR CRANE 5.7-1 5.7.2 SPENT FUEL RACK BORAFLEx.........................-.......---............

5.7-3 5.

7.3 REFERENCES

FOR SECTION 5.7.......................................

5.7-5 vi Revision 2 Volume Ifl.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal Technical Information Technical Information Required for an Application Table 13-1 Index of the Results of the Oconee Integrated Plant Assessment System, Structure, and Scoping EAgig Programs Component Section Section (Section)

Oconee Mechanical Systems Auxiliary Building Ventilation 2.5.8 3.5.8.1 None Required Auxiliary Service Water System 2.5.6 3.5.6.2 Cast Iron Selective Leaching Inspection (4.3.2)

Galvanic Susceptibility Inspection (4.3.3)

Preventive Maintenance Activities (4.3.8)

Service Water Piping Corrosion Program (4.25)

System Performance Testing Activities (4.27)

Breathing Air System 2.5.4 3.5.4.1 None Required Chemical Addition System 2.5.7 3.5.7.1 Treated Water Systems Stainless Steel Inspection (4.3.13)

Chemistry Control Program (4.6)

Component Cooling System 25.4 35.4.2 Treated Water Systems Stainless Steel Inspection (4.3.13)

Chemistry Control Program (4.6)

Condensate System 25.9 35.9.2 Cast Iron Selective Leaching Inspection (4.3.2)

Galvanic Susceptibility Inspection (4.3.3)

Preventive Maintenance Activities (4.3.8)

Chemistry Control Program (4.6)

Service Water Piping Corrosion Program

___(4.25) 1.3-5 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1.3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping EAffe Programs Component Section Section (Section)

Oconee Mechanical Systems (Continued)

Condenser Circulating Water 2.5.6 3.5.6.3 Galvanic Susceptibility Inspection (4.3.3)

System Preventive Maintenance Activities (4.3.8)

Service Water Piping Corrosion Program (4.25)

Containment Hydrogen Control 2.5.10 3.5.10.1 None Required System Control Room Pressurization and 2.5.8 3.5.8.2 None Required Filtration System Coolant Storage System 2.5.7 3.5.7.2 Chemistry Control Program (4.6)

Core Flood System 2.5.5 3.5.5.1 Chemistry Control Program (4.6)

Demineralized Water System 2.5.4 35.4.3 Treated Water Systems Stainless Steel Inspection (4.3.13)

Emergency Feedwater System 25.9 3.5.9.3 Chemistry Control Program (4.6)

Feedwater System 2.5.9 3.5.9.4 Chemistry Control Program (4.6)

Piping Erosion/Corrosion Program (4.21)

Filtered Water System 2.5.4 3.5.4.4 Treated Water Systems Stainless Steel Inspection (4.3.13)

Gaseous Waste Disposal System 2.5.4 3-5.4.5 None Required High Pressure Injection System 2.5.5 3.5.5.2 Chemistry Control Program (4.6)

Reactor Coolant Operational Leakage Monitoring (4.23) 1.3-6 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1.3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping Aging Programs tr Effect Porm Component Section Section (Section)

Oconee Mechanical Systems (Continued)

High Pressure Service Water System 2.5.6 3.5.6.4 Cast Iron Selective Leaching Inspection (4.3.2)

Galvanic Susceptibility Inspection (4.3.3)

Fire Protection Program (4.16)

Service Water Piping Corrosion Program (4.25)

Instrument Air System 2.5.4 3.5.4.6 None Required Leak Rate Test System 2.5.4 3.5.4.7 None Required Liquid Waste Disposal System 2.5.4 3.5.4.8 Treated Water Systems Stainless Steel Inspection (4.3.13)

Low Pressure Injection System 2.5.5 3.5.5.3 Galvanic Susceptibility Inspection (4.3.3)

Preventive Maintenance Activities (4.3.8)

Chemistry Control Program (4.6)

Heat Exchanger Performance Testing Acities (4.17)

Service Water Piping Corrosion Program (4.25)

Low Pressure Service Water System 2..6 3.5.6.5 Galvanic Susceptibility Inspection- (4.3.3)

Preventive Maintenance Activities (4.3.8)

Chemistry Control Program (4.6)

Service Water Piping Corrosion Program (4.25)

System Performance Testing Activities (4.27)

Main Steam System 2.5.9 3.5.9.1 Chemistry Control Program (4.6)

Piping Erosion Control Program (4.21) 1.3-7 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1.3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

Aging System, Structure, and Scoping Effect Programs Component Section Section (Section)

Oconee Mechanical Systems (Continued)

Nitrogen Purge and Blanket System 2.5.4 3.5.4.9 Reactor Building Spray System Inspection (4.3.9)

________Chemistry Control Program (4.6)

Penetration Room Ventilation 2.5.8 3.5.8.3 None Required System Post Accident Monitoring System 2.5.10 None Required Reactor Building Cooling System 2.5.3 3.5.3.1 Preventive Maintenance Activities (4.3.8)

Heat Exchanger Performance Testing Syste2.5.4Activities (4.17)

Reactor Building Purge System 2.5.4 3.5.4.10 None Required Rectr uidigSpray Syste 2._5.3 Reactor Coolaint p System2.

at.Syste 25.3.2 Reactor Building Spray System Inspection (4.3.9)

Chemistry Control Program (4.6)

Reactor Coolant System 2.4 3.4 Alloy 600 Aging Management Program 2.5.12 3.5.12 (4.3.1)

OTSG Upper Lateral Support Inspection (4.3.6)

Pressurizer Examinations (43)

Reactor Vessel Internals Aging Management Program (4.3.11)

Small Bore Piping Inspection (4.3.12)

Boric Acid Wastage Surveillance Program (4.5)

Chemistry Control Program (4.6)

CRDM Nozzle and Other Vessel Closure Penetrations Inspection Program (4.10)

Inservice Inspection Plan (4.18)

Inspection Program for Civil Engineering Structures and Components (4.19) 1.3-8 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1-3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping EAgn Programs Component Section Sect (Section)

Oconee Mechanical Systems (Continued)

Reactor Coolant System 2.4 3.4 Program to Inspect the HPI Connections (Continued) 2.5.12 3.5.12 to the RCS (4.22)

Reactor Coolant System Operational Leakage Monitoring (4.23)

Reactor Vessel Integrity Program (4.24)

Steam Generator Tube Surveillance Program (4.26)

Reactor Coolant Pump Motor Oil 25.11 35.11 Reactor Coolant Pump Motor Oil Collection System Collection System Inspection (4.3.10)

Spent Fuel Cooling System 2.5.6 3.5.6.1 Chemistry Control Program (4.6)

Keowee Mechanical Systems Carbon Dioxide 2.5.13 3.5.13.1 Keowee Air and Gas Systems Inspection (4.3.4)

Depressing Air System 2.5.13 3.5.13.2 Keowee Air and Gas Systems Inspection (4.3.4)

Generator High Pressure Oil System 2.5.13 3.5.13.3 None Required Governor Air System 2.5.13 3.5.13.4 Keowee Air and Gas Systems Inspection (4.3.4)

Governor Oil System 2-5.13 3.5.13.5 Keowee Oil Sampling Program (4.3.5)

Service Water System 2.5.13 3.5.13.6 Cast Iron Selective Leaching Inspection (4.3.2)

Galvanic Susceptibility Inspection (4.3.3)

Fire Protection Program (4.16)

Service Water Piping Corrosion Program (4.25) 1.3-9 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1-3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping EA Programs Component Section Section (Section)

Keowee Mechanical Systems (Continued)

Turbine Generator Cooling Water 2.5.13 3.5.13.7 Galvanic Susceptibility Inspection (4.3.3)

Preventive Maintenance Activities (4.3.8)

Service Water Piping Corrosion Program (4.25)

System Performance Testing Activities (4.27)

Turbine Guide Bearing Oil System 2.5.13 3.5.13.8 Keowee Oil Sampling Program (4.3.5)

Turbine Sump Pump System

.2.5.13 3.5.13.9 Galvanic Susceptibility Inspection (4.3.3)

Service Water Piping Corrosion Program (4.25)

System Performance Testing Activities (4.27)

SSF Mechanical Systems Air Intake and Exhaust System 2.5.14 3.5.14.1 None Required Diesel Generator Fuel Oil System 2.5.14 3.5.14.2 Chemistry Control Program (4.6)

Drinking Water System 2.5.14 3.5.14.3 Treated Water Systems Stainless Steel Inspection (4.3.13)

HVAC System 25.14 3.5.14.4 Heat Exchanger Performance Testing Activities (4.17)

Reactor Coolant Makeup System 2.5.14 3.5.14.5 Chemistry Control Program (4.6)

Sanitary Lift System 2.5.14 3.5.14.6 Treated Water Systems Stainless Steel Inspection (4.3.13) 1.3-10 Revision 2 Volume I.doc June 1998

I0 Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1.3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping EAfec Programs Component Section Sectio (Section)

SSF Mechanical Systems (Continued)

SSF Auxiliary Service Water 2.5.14 3.5.14.7 Galvanic Susceptibility Inspection (4.3.3)

Heat Exchanger Performance Testing Activities (4.17)

Service Water Piping Corrosion Progradi (4.25)

System Performance Testing Activities (4.27)

Starting Air System 2.5.14 3.5.14.8 None Required Structures Auxiliary Building 2.7.3 3.7.3 Battery Rack Inspections (4.4)

Chemistry Control Program (4.6)

Crane Inspection Program (4.11)

Fire Protection Program (4.165 Inservice Inspection Plan (4.18)

Inspection Program for Civil Engineering Stnctures and Components (4.19)

Earthen Structures 2.7.4 3.7.4 FERC Five Year Inspection (4.15)

Intake Structure 2.7.5 3.7.5 Inservice Inspection Plan (4.18)

Inspection Program for Civil Engineering Structures and Components (4.19) 1.3-11 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1.3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping Aging Programs Effect Component Section Section (Section)

Structures (Continued)

Keowee Structures 2.7.6 3.7.6 Battery Rack Inspections (4.4)

Crane Inspection Program (4.11)

Duke Power Five-Year Underwater Inspection of Hydroelectric Dams and Appurtenances (4.12)

FERC Five Year Inspection (4.15)

Inservice Inspection Plan (4.18)

Inspection Program for Civil Engineering Structures and Components (4.19)

Penstock Inspection (4.20)

Reactor Buildings (Containment),

23 3.3 Coatings Program (4.7)

Containment Inservice Inspection Plan (4.8)

Containment Leak Rate Testing Program (4.9)

Reactor Building Internal Structures Boric Acid Wastage Surveillance Program and Unit Vent (4.5)

Chemistry Control Program (4.6)

Crane Inspection Program (4.11)

Inservice Inspection Plan (4.18)

Inspection Program for Civil Engineering Structures and Components (4.19) 1.3-12 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station Application for Renewed Operating Licenses License Renewal - Technical Information Technical Information Required for an Application Table 1.3-1 Index of the Results of the Oconee Integrated Plant Assessment (Continued)

System, Structure, and Scoping Egiec Programs Component Section Section (Section)

Structures (Continued)

Standby Shutdown Facility 2.7.8 3.7.8 Battery Rack Inspection (4.4)

Crane Inspection Program (4.11)

Inservice Inspection Plan (4.18)

Inspection Program for Civil Engineering Structures and Components (4.19)

Turbine Buildings 2.7.9 3.7.9 Crane Inspection Program (4.11)

Fire Protection Program (4.16)

Inspection Program for Civil Engineering Structures and Components (4.19)

Yard Structures 2.7.10 3.7.10 Battery Rack Inspections (4.4)

Elevated Water Storage Tank Civil Inspection (4.14)

Inspection Program for Civil Engineering Structures and Components (4.19) 230 kV Keowee Transmission Line Inspection (4.29)

Electrical 2.6 3.6 None Required 1.3-13 Revision 2 Volume I.doc June 1998

Oconee Nuclear Station UFSAR Supplement For License Renewal New Chapter 18 Table 18-1 Summary Listing of the Changes Contained in the UFSAR Supplement for License Renewal Program /

UFSAR ITS Topic Activity or Location Location TLAA New Programs and Activities:

Program 18.1

  • Cast Iron Selective Leaching Inspection
  • Galvanic Susceptibility Inspection
  • Keowee Air and Gas Systems Inspection
  • Keowee Oil Sampling Program
  • Pressurizer Examinations
  • Preventive Maintenance Activity Assessment
  • Reactor Building Spray System Inspection
  • Small Bore Piping Inspection
  • Treated Water Systems Stainless Steel Inspection Battery Rack Inspections Program/

ActivitySR38.2 Boric Acid Wastage Surveillance Program Program/

Activity Chemistry Control Program Program/

18.3 UFSAR Supplement - page 42 Revision 0 UFSAR.doc June 1998

Oconee Nuclear Station UFSAR Supplement For License Renewal New Chapter 18 Table 18-1 Summary Listing of the Changes Contained in the UFSAR Supplement for License Renewal (continued)

Program /

UFSAR ITS Topic Activity or Location Location TLAA Coatings Program Program/

3.12 Activity Containment Inservice Inspection Plan Program/

18.4 Containment Leak Rate Testing Program Program/

5.5.2 Containment Liner Plate and Penetrations TLAA 3.8.1.5.3 Containment Post-Tensioning System TLAA 3.8.1.5.2, 16.6.2 Control Rod Drive Mechanism Nozzle Program!

18.5 and Other Vessel Closure Penetrations Activity Inspection Program Crane Inspection Program Program/

18.6 Activity Duke Power Five-Year Underwater Program/

18.7 Inspection of Hydroelectric Dams and Activity Appurtenances Duke Quality Assurance Program Program/

17 Environmental Qualification of Electrical TLAA 3.11 Equipment Elevated Water Storage Tank Inspection Program/

18.8 Federal Energy Regulatory Commission Program/

18.9 (FERC) Five Year Inspections

-Activit UFSAR Supplement - page 43 Revision 0 UFSAR.doc June 1998

Oconee Nuclear Station UFSAR Supplement For License Renewal New Chapter 18 Table 18-1 Summary Listing of the Changes Contained in the UFSAR Supplement for License Renewal (continued)

Program /

UFSAR ITS Topic Activity or Location Location TLAA Fire Protection Program Program/

16.9.1, Activity 16.9.2, 16.9.4, 16.9.5 Heat Exchanger Performance Testing Program/

18.10 Activities Activity Inservice Inspection Plan Program/

18.11 Inspection Program for Civil Engineering Program/

18.12 Structures and Components Activity Penstock Inspection Program/

18.13 Piping Erosion/Corrosion Program Program/

18.14 Activity Program to Inspect High Pressure Program/

18.15 Injection Connections to the Reactor Activity Coolant System Non-Class I Piping TLAA 3.2.2.2 Polar Crane TLAA 3.13 Reactor Coolant Pump Flywheel TLAA 5.5.8 Reactor Coolant System Operational Program/

3.4.13 Leakage Monitoring Activity Reactor Coolant System and Class 1 TLAA 5.2.1.4 Components UFSAR Supplement - page 44 Revision 0 UFSAR.doc June 1998

Oconee Nuclear Station UFSAR Supplement For License Renewal New Chapter 18 Table 18-1 Summary Listing of the Changes Contained in the UFSAR Supplement for License Renewal (continued)

Program /

UFSAR ITS Topic Activity or Location Location TLAA Reactor Vessel TLAA 5.2.3.3.4, 5.2.3.3.6, 5.2.3.13 Reactor Vessel Integrity Program Program/

18.16 Activity Reactor Vessel Internals TLAA 4.5.1.2 Service Water Piping Corrosion ogramn Program/

18.17 Activity Spent Fuel Rack Boraflex TLAA 9.1.2.5 Steamn Gnerator Tube Surveillance Program/

5.5.10 Program Activity System Performance Testing Activities Program/

18.18 ActiRity Tendon - Secondary Shield Wall -

Program/

18.19 Surveillance Program Activity 230 kV Keowee Transmission Line Program/

18.20 Inspections Activity UFSAR Supplement - page 45 Revision 0 UFSAR.doc June 1998

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