ML15254A168
| ML15254A168 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Calvert Cliffs  |
| Issue date: | 12/04/1998 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-3133, NUDOCS 9905210184 | |
| Download: ML15254A168 (9) | |
Text
CATEGORY 1 REGULATE INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR:9905210184 DOC.DATE: 98/12/04 NOTARIZED: NO DOCKET #
FACIL:50-269 Oconee Nuclear Station, Unit 1, Duke Power Co.
05000269 50-270 Oconee Nuclear Station, Unit 2, Duke Power Co.
05000270 50-287 Oconee Nuclear Station, Unit 3, Duke Power Co.
05000287 50-317 Calvert Cliffs Nuclear Power Plant, Unit 1, Baltimore 05000317 50-318 Calvert Cliffs Nuclear Power Plant, Unit 2, Baltimore 05000318 AUTH.NAME AUTHOR AFFILIATION ACRS -
Advisory Committee on Reactor Safeguards RECIP.NAME RECIPIENT AFFILIATION C
ACRS -
Advisory Committee on Reactor Safeguards A
SUBJECT:
Summary of ACRS Plant License Renewal Subcommittee 981118 meeting in Rockville,MD re generic issues related to license T
renewal,selected technical TRs & status of staff review of Calvert Cliffs & Oconee NPPs license renewal applications.
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Date Issued: 12/4/98 T. Kress -12/4/98 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS PLANT LICENSE RENEWAL SUBCOMMITTEE MEETING MINUTES NOVEMBER 18,1998 ROCKVILLE, MARYLAND The Advisory Committee on Reactor Safeguards (ACRS) Subcommittee on Plant License Renewal held a meeting on November 18, 1998, in Room T-2 B3, 11545 Rockville Pike, Rockville, Maryland, with representatives of the U.S. Nuclear Regulatory Commission (NRC).
The purpose of this meeting was to hear presentations by and hold discussions with the NRC staff regarding generic issues related to license renewal, selected technical topical reports, and the status of the staffs review of the Calvert Cliffs and Oconee nuclear power plants applications for license renewal. Dr. Medhat EI-Zeftawy was the cognizant ACRS staff engineer for this meeting. The meeting was convened at 8:30 a.m. and adjourned at 11:00 a.m.
ATTENDEES ACRS T. Kress, Acting Chairman R. Uhrig, Member D. Miller, Member M. EI-Zeftawy, Staff W. Shack, Member NRC C. Grimes, NRR S. Vias, NRR S. Hoffman, NRR J. Sebrosky, NRR S. Cooke, NRR P. Shemanski, NRR D. Solorio, NRR R. Hermann, NRR B. Elliot, NRR S. Lee, NRR P. Kuo, NRR R. Jolly, NRR C. Carpenter, NRR D. Thatcher, NRR G. Bagchi, NRR K. Silverman, NRR W. Liu, NRR C. Regan, NRR F. Grubelich, NRR C. Sochor, NRR OTHERS D. Walters, NEI S. Toney, Duke Eng.
M. Hager, DE&S A. Carson, Bechtel T. Taminami, Tokyo Elec.
B. Lee, Dow Jones P. Negus, GE 9905210184 981204 PDR ACRS 3133 PDR Certif ied By
Plant License Renewal 11/18/98 Subcommittee Minutes No written comments or requests for time to make oral statements were received from members of the public. A list of attendees is available in the ACRS Office and will be made available upon request.
OPENING REMARKS BY THE SUBCOMMITTEE CHAIRMAN Dr. Thomas Kress, Acting Subcommittee Chairman, convened the meeting at 8:30 a.m. and stated that the purpose of this meeting is to discuss with the NRC staff the status of two application reviews (Calvert Cliffs and Oconee); the on-going and planned reviews of license renewal technical reports; and the resolution process for some identified generic license renewal issues. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions as appropriate for deliberation by the full Committee.
NRC STAFF PRESENTATION Mr. Chris Grimes, NRR, outlined the background and the objectives of the staff's reviews. He noted that pursuant to 10 CFR Part 50.51, licenses to operate nuclear power plants are issued by the NRC for a fixed period of time not to exceed 40 years. However, these licenses may be renewed by the NRC for an additional period of up to 20 years before expiration of the current operating term. The revised license renewal rule, 10 CFR 54, published on May 8, 1995 and effective on June 7, 1995, sets forth the requirements for the renewal of operating licenses for nuclear power plants.
Applicants for license renewal are required to perform, among other things, an integrated plant assessment (IPA) and an evaluation of time-limited aging analysis (TLAA). The first two steps of the IPA, 10 CFR 54.21(a) (1) and 10 CFR 54.21(a) (2), require the applicant to identify and list, from those systems, structures, and components (SCCs) within the scope of the license renewal rule, those structures and components (SCs) that are subject to an aging management review and to describe and justify the methods used to determine those structures and components subject to review.
SCs subject to an aging management review (AMR) are those that meet the criteria of CFR 54.21(a)(1)(1) and (ii). Specifically, SCs that perform an intended function without moving parts or without a change in configuration or properties (i.e.,Passive) and those that are not subject to replacement based on a qualified life or specified time period (i.e., long-lived) are subject to an aging management review.
Examples of the SCs subject to review (Passive) include:
Reactor Vessel Containment Reactor Coolant System Pressure Boundary Steam Generators Pressurizer Piping Valve Bodies
Plant License Renewal 11/18/98 Subcommittee Minutes Core Shroud Heat Exchangers Component Support Cable Trays and Electrical Cabinets Examples of the SCs not subject to review (Active) include:
Pumps (except casing)
Valves (except body)
Motors Diesel Generators Control Rod Drive Pressure indicators Water level indicators Cooling Fans Air Compressors The final step in the IPA, 10 CFR 54.21 (a)(3), requires an applicant to demonstrate, for all SCs identified as subject to an aging management review, that the effects of aging will be adequately managed so that the intended function(s) of the SCs will be maintained consistent with the plants current licensing basis including all design basis conditions for the period of extended operation.
The license renewal rule requires a Final Safety Analysis Report (FSAR) supplement that summarizes the description of the programs and activities for managing the effects of aging and evaluation of TLAAs. Section 54.22 of the rule requires the Technical Specification changes and their justification necessary for managing the effects of aging during the period of extended operation. In addition, an environmental report supplement is required to be submitted in compliance with 10 CFR Part 51, Subpart A.
The staff developed a draft Standard Review Plan for License Renewal (SRP-LR). The SRP-LR offers guidance to the staff for reviewing applications for license renewal. The SRP-LR consists of four chapters. Chapter 1-Administrative review; Chapter 2-Screening methodology for identifying SC subject to aging; Chapter 3-IPAs and AMR; Chapter 4-TLAAs.
The staff plans to use the working draft of the SRP-LR in its future reviews of plant-specific technical reports and owners group topical reports. By focusing on the review of aging management of actual plant structures and components, the staff and industry would gain a better understanding of the implementation issues involved in the license renewal rule. Lessons learned from the trial use of the working draft SRP-LR and draft regulatory guide would provide feedback to further improve the working draft.
The staff plans to focus on plant-specific and owners group reviews of actual plant structures and components to gain needed experience with implementation of the rule and the draft SRP LR. The draft SRP-LR is tentatively scheduled to be published for public comment in early
Plant License Renewal 11/18/98 Subcommittee Minutes 2001. Other NRC staff activities include developing a regulatory guide; reviewing the industry guidance document NEI 95-10, that would be endorsed by the regulatory guide if found acceptable; preparing inspection program for license renewal; environmental reviews under 10 CFR Part 51; and reviewing license renewal applications.
The staff is continuing to develop inspection guidance for license renewal. The staff plans to complete the draft inspection guidance to support the review of the first license renewal application. Consistent with the development of the SRP-LR and REG, the inspection guidance will be finalized after completing the review of several license renewal applications.
Calvert Cliffs Nuclear Power Plant (CCNPP). Mr. D. Solorio, NRR, stated that Units I and 2, operated by Baltimore Gas and Electric Company (BG&E) submitted to the NRC on April 8, 1998 an application for License Renewal. BG&E requests that the licenses be extended 20 years beyond the expiration dates.
(Calvert Cliffs Unit 1 expiration license date is year 2014 and Calvert Cliffs Unit 2 is year 2016).
Calvert Cliffs began looking at the plant life cycle in late eighties and formally established life cycle management (LCM) unit in 1990. The LCM unit is responsible for long-term strategic planning, plant aging management, and renewing the licenses of both units. BG&E formal aging management assessment efforts are complete. BG&E is teaming with EPRI, NEI, and other utilities and institutions.
BG&E's findings indicate continued operation can be safe and reliable for the extended 20 years operation. Impact on plant programs to monitor aging are well within the benefit. There were 254 activities identified as necessary to manage the aging issue. 217 (85%) already exist, 28 (11%) already exist but require modification, and 9 (4%) new inspection programs/activities require development.
A final ACRS meeting is scheduled for February 14, 2000.
Duke Power Company. Mr. J. Sebrosky, NRR, stated that Duke Power Company operating the Oconee units submitted on July 6, 1998 an application for license renewal for unitsl, 2, and
- 3. (Oconee Units 1 and 2 expiration current license year date is year 2013 and Oconee Unit 3 is year 2014). The submittal contained the technical information required by 10 CFR Part 54.21, including an integrated plant assessment (IPA). The IPA demonstrates that the effects of aging on long-lived passive SCs will be adequately managed such that their intended functions will be maintained, consistent with the current licensing basis, during the renewed term of plant operation.
A final ACRS meeting is scheduled for May 12, 2000.
Generic License Renewal Issues: (Mr.Sam Lee, NRR) stated that as a result of the NRC staffs review of the license renewal applications, NEI comments, and EPRI studies, several
Plant License Renewal 11/18/98 Subcommittee Minutes generic issues were identified. The staff after discussions with NEI, EPRI, and interested parties, consolidated the total number of these generic issues applicable to license renewal to
- 98. The staff prioritized these issues into four categories:
PRIORITY 1-These are issues requiring resolution to support the staff review of a license renewal application. These issues have a mandatory due date driven by the application review schedule. The staff identified 18 issues. These are:
(1)
Industry concerns with SRP application of ASME IWE/IWL code requirements relative to basemat requirements.
(2)
EQ TLAA requirements for LR (3)
Operating experience-- aging effects and management programs (4)
FSAR Supplement contents (5)
Active/Passive determination-fuses (6)
Thermal aging embrittlement of cast austenitic SS components (7)
IWE/IWL changes, inaccessible areas (8)
Aging management reviews relating to Dams (9)
IWE/IWL, jurisdiction (10)
IWE/IWL, operating experience requirements (11)
Credit for condition monitoring as an aging management program (12)
Crediting Maintenance Rule program for monitoring structural aging (13)
The use of code program and code additions (14)
Reactor vessel fluence (15)
Evaluation of containment temperature program (16)
Inspection of pressurizer heater penetrations (17)
Applicability of IWE/IWL requirements in SRP (18)
Heat tracing, Active/Passive PRIORITY 2-These are generic issues important to license renewal application development and review. These issues have a non-mandatory due date driven by scheduled revisions to the SRP, DG-1 047, and NEI 95-10. The staff identified 24 issues.
The SRP and DG-1047 were scheduled to be issued for public comment in year 2001. Corresponding revision to NEI 95-10 should be made in the same time frame.
PRIORITY 3-These are non-generic issues important to license renewal application development and review and generic issues determined to be important, but not important enough to include under Priority 2. The staff identified 48 issues.
PRIORITY 4-- These are all Low priority issues as recommended by NEI and approved by the staff. The staff identified 8 issues.
Plant License Renewal 11/18/98 Subcommittee Minutes The staff is focusing on the PRIORITY 1 issues in the current review schedule.
Babcock & Wilcox Owners' Group (B&WOG) Topical Report: Mr.S. Vias, NRR, stated that on June 27, 1996, B&WOG (License Renewal Program - GLRP) submitted topical report BAW 2251, "Demonstration of the Management of Aging Effects for The Reactor Vessel", for NRC staff review and approval. The purpose of the topical report is to provide a technical evaluation of the effects of aging of the reactor vessel and demonstrate that the aging effects within the scope of the report are adequately managed for the period of extended operation associated with license renewal. The BAW-2251 applies to the following B&WOG/GLRP member plants:
Arkansas Nuclear One, Unit 1 (ANO-1)
Oconee Nuclear Station, Unit 1,2, and 3 (ONS 1, 2, and 3)
Three Mile Island, Unit 1 (TMI-1)
The NRC staff reviewed BAW-2251, and issued a draft safety evaluation (DSE).The staff will issue a final safety evaluation upon resolution of the open items identified in the DSE. Some of the open items include the intended function of the reactor vessel components, flow stabilizers subject to aging management review, wear of core guide lugs, underclad cracking, neutron fluence, and reactor vessel materials surveillance program.
Other B&W Owners Group reports reviewed or currently under review by the NRC staff include RCS piping, Pressurizer, and Reactor Vessel Internals.
Westinghouse Owners Group submitted RCS supports, Pressurizer, Class 1 Piping, Containment, and Reactor Internals topical reports. BWR Owners Group submitted Vessel Internals Program, and Containment reports.
Future NRC Staff Activities -this include the following:
Promptly identify and address issues, document lessons and resolution Include industry input for generic renewal issues Continue Owners Group's reports reviews consistent with application needs Program oversight by the NRC's Executive Council and a License Renewal Steering Committee Continue dialog with the ACRS
Plant License Renewal 11/18/98 Subcommittee Minutes SUBCOMMITTEE DISCUSSION AND FOLLOW-UP ACTIONS:
Should the ACRS be proactive in reviewing the technical reports submitted by the industry? To what extent?
What the extent of the ACRS involvement in the resolution of the "Generic License Renewal Issues"?
The status of the hearing processes and its effect on the ACRS review and schedule?
How risk-informed regulation be used and applied for license renewal?
What research activities are needed?
What should be the involvement of other ACRS Subcommittees, e.g., Materials and Metallurgy?
What information should be included in the ACRS reports?
Conclusion As a result of this meeting, the Acting Subcommittee Chairman will recommend a course of action, including briefing the Full Committee, as appropriate.
Background Material Provided to the Subcommittee License Renewal Issues Database (98 generic issues)
The B&W Owners Group, "Reactor Vessel", BAW-2251, dated June 1996.
Draft Safety Evaluation regarding B&W Topical Report BAW-2251, dated September 18, 1998.
Presentation Slides and Handouts Provided During the Subcommittee Meeting The presentation slides and handouts used during the meeting are available in the ACRS Office files or as attachments to the meeting transcripts.
0 Plant License Renewal 11/18/98 Subcommittee Minutes NOTE:
Additional details of this meeting can be obtained from a transcript available in the NRC Public Document Room, 2120 L Street, N.W.,
Washington, D.C. 20006, (202) 634-3274, or can be purchased from Ann Riley & Associates LTD, 1025 Connecticut Ave., NW, Suite 1014, Washington, D.C. 20036, (202) 842-0034.