ML081680556
| ML081680556 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/16/2004 |
| From: | Cayetano Santos NRC/ACNW, Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| Download: ML081680556 (56) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555
- 0001 December 16, 2004 MEMORANDUM TO:
FROM:
ACRS Members e""
~
I'A.. I.k.~~ /~...) t.
Caye~~~"'~osJr., Senior Staff Engineer Technical Support Staff ACRS/ACNW
SUBJECT:
CERTIFICATION OF THE MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE ARKANSAS NUCLEAR ONE UNIT 2 LICENSE RENEWAL APPLICATION, DECEMBER 1, 2004 ROCKVILLE, MARYLAND The minutes of the subject meeting were certified on December 15, 2004, as the official record of the proceedings of that meeting. A copy of the certified minutes is attached.
Attachment:
As stated cc:
J. Larkins S. Duraiswamy J. Flack M. Snodderly
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITIEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 Cayetano Santos Jr., Senior Staff Engineer, Technical Support Staff ACRS/ACNW FROM:
Mario Bonaca, Chairman ACRS Plant License Renewal Subcommittee
SUBJECT:
CERTIFICATION OF THE MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE ARKANSAS NUCLEAR ONE, UNIT 2 LICENSE RENEWAL APPLICATION, DECEMBER 1, 2004 ROCKVILLE, MARYLAND I hereby certify, to the best of my knowledge and belief, that the minutes of the subject meeting on December 1, 2004, are an accurate record of the proceedings for that meeting.
tYJc~ ~
J2.l l sjoy.
Mario Bonaca,
Date Plant License Renewal Subcommittee Chairman
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 December 15, 2004 MEMORANDUM TO:
Mario Bonaca, Chairman ACRS Plant License Renewal Subcommittee I'j.-b_~,
Sa.:J; Y.
FROM:
Caye(a~~~ntosJr., Senior Staff Engineer, Technical Support Staff ACRSIACNW
SUBJECT:
WORKING COPY OF THE MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE ARKANSAS NUCLEAR ONE UNIT2 LICENSE RENEWAL APPLICATION, DECEMBER 1, 2004 ROCKVILLE, MARYLAND A working copy of the minutes for the subject meeting is attached for your review. Please review and comment on them at your earliest convenience. If you are satisfied with these minutes please sign, date, and return the attached certification letter.
Attachments: Certification Letter Minutes (DRAFT) cc wlo
Attachment:
J. Larkins J. Flack S. Duraiswamy M. Snodderly
CERTIFIED 12/15/04 By Mario Bonaca Issued: 12/13/04 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MINUTES OF ACRS PLANT LICENSE RENEWAL SUBCOMMITTEE MEETING ON THE ARKANSAS NUCLEAR ONE, UNIT 2 NUCLEAR POWER PLANT DECEMBER 1, 2004 ROCKVILLE, MARYLAND On December 1, 2004, the Plant License Renewal Subcommittee held a meeting in Room T2B3, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to review and discuss the Arkansas Nuclear One, Unit 2 License Renewal Application (LRA) and Draft Safety Evaluation Report (SER).
The meeting was open to the public. No written comments or requests to make oral statements were received from members of the public related to this meeting. Mr. Cayetano Santos was the Designated Federal Official for this meeting. The meeting convened at 1:30 pm and adjourned at 5:45 pm on December 1, 2004.
ATTENDEES:
ACRS MEMBERS/STAFF Mario Bonaca, Chairman Stephen Rosen, Member Richard Denning, Member Peter Ford, Member John Sieber, Member Graham Wallis, Member Victor Ransom, Member Graham Leitch, Consultant Cayetano Santos Jr., ACRS Staff NRC STAFF/PRESENTERS P. Kuo, NRR G. Suber, NRR J. Rowley, NRR R. Dipert, NRR L. Lois, NRR J. Ayala, NRR J. Medoff, NRR K. Cozens, NRR R. Nease, Region IV G. Cranston, NRR G. Georgiev, NRR D. Nguyen, NRR R. McNally, NRR S. Lee, NRR D. Merzke, NRR M. Lintz, NRR L. Tran, NRR J. Guo, NRR C. Li, NRR T. Le, NRR S. Hoffman, NRR M. Morgan, NRR T. Liu, NRR R. Auluck, NRR B. Rogers, NRR S. Mitra, NRR M. Mitchell, NRR J. Tsao, NRR M. Hartzman, NRR V. Rodriguez, NRR J. Hernandez, NRR K. Hsu, NRR K. Chang, NRR J. Zimmerman, NRR 1
Y. Li, NRR J. Ma, NRR P. Kang, RES T. Cheng, NRR A. Stone, Region III OTHER ATTENDEES G. Young, Entergy M. Rinckel, AREVA M. Miller, AREVA B. Kalinowski, AEP M. Stroud, Entergy D. Wooten, Dominion R. Rucker, Entergy D. Lach, Entergy J. Ivy, Entergy N. Haggerty, AEP A. Cox, Entergy D. Johnson, NMC-LLC R. Ahrabus, Entergy P. Aitken, Dominion J. Knorr, NMC-LLC M. Patterson, Metamorph K. Green, ISL R. Grumbir, AEP P. Schoepf, AEP S. Pope, ISL D. Mlynarczyk, ISL K. Prasad, ISL R. Vincent, NMC The presentation slides, handouts used during the meeting, and a complete list of attendees are attached to the Office Copy of the meeting minutes. The presentation to the Subcommittee is summarized below.
Opening Remarks Mr. Bonaca, Chairman of the Plant License Renewal Subcommittee, convened the meeting and made a few introductory remarks. The purpose of this meeting is to review Entergy's license renewal application (LRA) and the related Draft Safety Evaluation Report (SER) for Arkansas Nuclear One, Unit 2 (AN02). Mr. Bonaca called upon Mr. Kuo of the Office of Nuclear Reactor Regulation (NRR) to begin the discussion.
Staff Introduction Mr. Kuo introduced several members of the staff including Mr. Suber (license renewal program manager), Ms. Nease (inspection team leader), and Mr. Cranston (audit team leader). Mr. Kuo also noted that AN02 is the second plant to be reviewed with a new process that uses on-site audits to verify consistency with the Generic Aging Lessons Learned Report (GALL).
AN02 License Renewal Application Mr. Young, Entergy, greeted the Subcommittee and introduced accompanying members of the Entergy and AREVA staff. The key elements of Mr. Young's presentation included a description of AN02, its operating history, the scoping methodology, the application of GALL, and commitment tracking.
Background and Plant Description On October 15, 2003, Entergy submitted an application to the NRC for renewal of the AN02 operating license for an additional 20 years. The current operating license for AN02 expires on July 17, 2018. Entergy also identified staff approved past precedents that are not in GALL and provided this information to the staff.
2
AN02 is a pressurized water reactor (PWR) unit with a dry ambient containment. AN02 began initial operations in 1978 and has a capacity of 3026 MWt or 1023 MWe. Mr. Young also noted some differences between ANa Unit 1 and 2. Unit 1 is a Babcock and Wilcox PWR that uses once through cooling, while Unit 2 is a Combustion Engineering PWR with a cooling tower.
Operating Historv/Major Equipment Replacements and Repairs In 2002, a power uprate of 7.5% increased capacity by 210 MWe. In 2000 the steam generators were replaced with Westinghouse Delta 109 U-tube steam generators.
Scoping and Screening Method The scoping methodology was applied on a plant system basis per the requirements of 10 CFR 54.4(a) and screening was performed per the requirements of 10 CFR 54.21 (a)1. Mr. Young added that all components located in a room that contains both safety and non-safety related equipment were assumed to be in scope.
Application of GALL The AN02 license renewal application focused on consistency with GALL but since some material/environment/program combinations were not addressed in GALL some plant-specific programs were used. Mr. Young stated that information from Entergy's past precedent review was provided separately from the LRA. This information is being considered by the staff in an update of the GALL report.
Of the 33 aging management programs (AMPs) at AN02, 15 are consistent with GALL with enhancements, 7 are consistent with GALL with exceptions, and 11 are plant-specific. Of the 11 plant-specific programs, 8 are based on past precedents. Mr. Young stated that the One Time Inspection Program was added after the LRA was submitted.
Commitment Tracking Mr. Young stated that all commitments made through the LRA, the audit/inspection process, and requests for additional information are tracked with the ANO Licensing Commitment Tracking System.
Mr. Young concluded by stating that the use of past precedents and the on-site audits increase the efficiency of the license renewal process.
SER Overview Mr. Suber discussed the staff's license renewal activities. The key elements of the staff's presentation described an overview of the Draft SER, the aging management program reviews and audits, and the time-limited aging analyses.
The Draft SER did not contain any open or confirmatory items but did list the following license conditions:
- 1.
The FSAR should be updated upon issuance of the renewed license.
- 2.
The future activities should be completed as described in the FSAR Supplement prior to entering the period of extended operation.
3
- 3.
The reactor vessel surveillance capsules should be removed and tested in accordance with ASTM E185-82 and any changes to the withdrawal schedule or storage requirements should be approved by the NRC.
Mr. Suber listed the dates of the various audits and inspections performed by the staff.
Scoping and Screening Mr. Suber stated that the scoping and screening methodology is adequately described in the LRA and satisfies the requirements in 10 CFR 54.4 and 10 CFR 54.21 (a)(1). In addition, the review of the scoping and screening results found that the systems, structures, and components (SSCs) within scope of license renewal and subject to an aging management review (AMR) have been identified. As a result of the staff's review, the feedwater outboard block valve and the power transmission conductors were brought into scope, and the intake canal structure was included in an aging management program.
Onsite Inspection Results Ms. Nease, Region IV, described the license renewal inspections performed by the Region.
These inspections were performed in accordance with License Renewal Manual Chapter MC2516, Inspection Procedure IP 71002, and a site-specific inspection plan. The scoping and screening inspection was performed in March 2004 and concluded that the scoping and screening process successfully identified those SSCs requiring an AMR. As a result of this inspection the spent fuel pool cooling pumps and the switchyard control house were brought into scope of license renewal. The aging management review inspection was performed in November 2004 to confirm that the applicant has or will implement AMPs to manage the effects of aging. The results of this inspection will be documented in a future inspection report.
Ms. Nease also described the recent performance of AN02. All of the NRC performance indicators for the third quarter of 2004 are green. However, AN02 is in the Regulatory Response Column of the NRC Action Matrix because of a white finding in the area of fire protection. Ms. Nease concluded by stating that the Annual Assessment Letter for AN02 identified a substantive issue regarding Problem Identification and Resolution.
Aging Management Program Review and Audits Mr. Suber described the staff's review of the aging effects associated with various plant systems and components. The staff's review of the reactor vessel, internals and reactor coolant systems resulted in 1 license condition and 3 commitments to submit AMPs for NRC review and approval. As a result of the staff's review the One-Time Inspection Program was added to supplement the System Walkdown AMP and the intake canal structure was included in the Structures Monitoring Program. Even though the pH, chloride and sulfate levels of the below grade water environment are nonaggressive, the Structures Monitoring Program will be used to manage the effects of aging of inaccessible concrete. Mr. Suber also noted that the power transmission conductors which were brought in scope as a result of the staff's review, did not require an AMP.
Mr. Cranston, NRR, stated that AMPs are divided into 4 categories: consistent with GALL, consistent with GALL with exceptions, consistent with GALL with enhancements, and based on previously approved staff positions. Mr. Cranston also noted that information regarding NRC approved precedents was supplementary information provided voluntarily by the applicant. It 4
was not part of the LRA. For the AMPs based on past precedents, the audit team evaluated the applicability of the previously approved staff position, determined if the program was bounded by the conditions for which the previous staff position was approved, and verified that the program contains the attributes of the referenced precedent. Mr. Cranston described several of the AMPs including the Structures Monitoring - Masonry Wall Program, the Diesel Fuel Monitoring Program, the Fire Water System Program, and the Cast Austenitic Stainless Steel Evaluation Program.
The Structures Monitoring - Masonry Wall Program is an existing AMP that is consistent with GALL. During the audit of this AMP, the team found that the initial baseline examinations were not documented properly, the first 5 year reexamination was not performed, and qualifications for personnel qualified to perform walkdowns were not established. The applicant generated a condition report to document and correct these deficiencies.
The Diesel Fuel Monitoring Program is new AMP that is consistent with GALL with exceptions.
The exceptions are the use of fewer additives, the use of ASTM standard D 1796 instead of D 2709, the use of a smaller filter pore size, and a lack of ultrasonic measurements of tank bottoms. The staff found these exceptions acceptable because a vendor recommended additive package was used, ASTM D2709 did not apply, the smaller pore size is more conservative, the bottom of the tank is not likely to be exposed to water, accessible tank surfaces undergo a periodic visual inspection, and operating experience at AN02 has not shown any wall thinning problems.
The Fire Water System is an example of an AMP that is consistent with GALL with enhancements. The program enhancement is to inspect sprinkler heads consistent with Interim Staff Guidance (ISG) 04.
The Cast Austenitic Stainless Steel (CASS) Evaluation Program was originally submitted based on a previously approved staff position but was changed to be consistent with GALL. The audit team determined that the code case to perform only external visual inspections was not applicable to AN02. Therefore, the applicant revised the AMP to be consistent with GALL. An example of a plant-specific AMP based on a previously approved staff position is the Wall Thinning Monitoring Program. This AMP was previously approved by the staff for AN01.
The staff concluded that the applicant has demonstrated the effects of aging will be managed so that the intended functions will be maintained consistent with the current licensing basis for the period of extended operation.
Time Limited Aging Analyses (TLAAs)
Mr. Suber stated that the applicant has identified the appropriate TLAAs. Of the 11 TLAAs at AN02, 5 were identified from NUREG 1800 and 6 were identified by the applicant. The applicant has also demonstrated that (1) the TLAAs are valid for the period of extended operation, (2) the TLAAs are projected to the end of the period of extended operation, or (3) that aging effects will be adequately managed for the period of extended operation.
Embrittlement of the reactor vessel affects TLAAs associated with upper shelf energy (USE),
pressurized thermal shock (PTS), and pressure temperature limits. Calculations by the staff and applicant demonstrate that the beltline materials continue to meet the USE acceptance 5
criterion in 10 CFR 50 Appendix G through 48 Effective Full Power Years (EFPY). The staff also performed independent calculations of RTPTS values and concluded that the limiting beltline material continues to meet the screening criterion in 10 CFR 50.61 through 48 EFPY.
The staff concluded that analyses associated with fatigue of ASME Class 1 components; fatigue of ASME Non-Class 1 piping components; fatigue of containment liner plate and penetrations; fracture of reactor coolant pump casings, and Leak-Before-Break of RCS piping systems remain valid for the period of extended operation.
The staff made the following conclusions regarding the other TLAAs:
- 1.
The loss of prestress in containment tendons will be adequately managed for the extended period of operation.
- 2.
The Environmental Qualification Program is consistent with GALL and will continue to manage equipment in accordance with 10 CFR 50.49.
- 3.
The analyses of Alloy 600 nozzle repairs projected through the period of extended operation are valid.
Mr. Suber concluded by stating that the applicant has met the requirements for license renewal and there is reasonable assurance that activities will continue to be conducted in the renewal term in accordance with the current licensing basis.
Member Comments General Chairman Bonaca and Member Rosen asked about the replacement steam generators. Mr.
Young replied that the replacement steam generators were of the same design as the original steam generators but were designed for a higher power rating and contained tube materials constructed from Alloy 690.
Several Members and Consultant Leitch asked questions regarding the reactor pressure vessel head. The applicant stated that an inspection of the head in 2002 did not indicate any leakage even though AN02 is a high susceptibility plant. Since some of the penetrations are covered by a shroud which prevents a complete 360 0 bare metal visual inspection, alternative eddy current and ultrasonic inspections were performed. The results of these volumetric inspections did not show any cracking. The applicant has plans to replace the head, but the earliest this could be done is 2008. In the meantime the applicant plans to modify the shroud covering the penetrations to allow increased access for visual inspections.
In response to a question from Consultant Leitch, Ms. Nease stated that the material condition of the plant was very good.
Chairman Bonaca and Member Rosen asked about the issue identified in the Annual Assessment Letter regarding Problem Identification and Resolution. Ms. Nease responded that errors in the prioritization, implementation, and effectiveness of corrective actions were found across the board at the plant. This is a concern because AMPs depend upon the effectiveness of the Corrective Action Program.
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Chairman Bonaca and Member Wallis commented that the audit report for AMPs and AMRs is very valuable to reviewers.
Several Members commented that there are no issues regarding the AN02 license renewal application or draft SER.
Scoping and Screening Several Members and Consultant Leitch asked questions regarding the justification for the scoping and screening classification of components.
In response to a question from Consultant Leitch, the applicant stated that there were no problems associated with the scoping of systems shared between Units 1 and 2.
Consultant Leitch asked if the scoping process considers situations in which the disintegration of non safety-related components affects the operation of safety-related components. Except for steam dryers in BWRs, operating experience has shown that this type of interaction has not been a problem. The staff added that active components are examined routinely as part of the maintenance program.
Aging Management Consultant Leitch asked why buried components are inspected opportunistically and not at a scheduled frequency as recommended by GALL. Mr. Young replied that operating experience has shown that underground pipes are excavated every 5 to 10 years and inspected at that time. Mr. Young added that excavating a pipe has the potential to damage its external coating.
In response to a question from Member Sieber, the applicant stated that no inspections are performed on the inside of buried pipes because other AMPs are credited for managing corrosion on these interior surfaces.
Consultant Leitch asked about the schedule for implementing new AMPs and suggested that this information be discussed at the Full Committee meeting. The applicant stated that the new AMPs will be phased in such that they will all be in place at least 2 years before the 40th year of operation. A detailed implementation schedule will be developed after the renewed license has been issued.
Several Members asked questions regarding the staff's review of the quality of the AMPs. The headquarters staff and audit team assess the quality of the programs while the regional inspection team verifies that the programs are implemented as described. In determining the effectiveness of current AMPs, the staff considers operating experience, performs walkdowns, and examines Condition Reports.
Member Ford asked about the inspection program for reactor vessel internals. The staff responded that the reactor vessel internals programs have not been finalized but the applicant has committed to submitting these programs for staff review 2 years before entering the period of extended operation.
Member Ford asked if corrosion of carbon steel pipes could clog up the nozzles in the fire protection systems. The applicant responded that if this clogging occurred, it would be identified during the periodic flushing performed as part of the AMP for the fire protection systems.
7
Members Ford and Rosen asked about the aging management of inaccessible concrete. The most recent tests of groundwater chemistry indicate that the below grade environment is not aggressive. Since well water is no longer available for periodic monitoring, the applicant chose to use the Structures Monitoring Program to manage the effects of aging. Under this program concrete exposed to lakewater will be periodically inspected. Since the chemistry of lakewater and ground water are similar, these inspection results will be representative of underground concrete exposed to groundwater.
Member Rosen asked if the root cause of the discrepancies in the Structures Monitoring Masonry Wall Program was identified. The applicant stated that some of these discrepancies were simply the result of the wrong date used in determining the time for the next inspection.
TLAAs The TLAAs for reactor vessel embrittlement assumed a constant capacity factor of 80% for 60 years resulting in 48 EFPY. Consultant Leitch and Member Rosen questioned the basis for this assumption and asked if the USE and PTS requirements could still be met at 54 EFPY. The applicant stated that the basis for this assumption was that the LRA for AN01 assumed 48 EFPY and that operating experience to date has shown an 80% capacity factor for AN02. The staff stated that at 54 EFPY the RTPTS value for the limiting beltline material increases by only 2 degrees and would continue to meet the PTS screening criterion. The staff added that the Reactor Vessel Integrity Program will ensure that fluence values are updated as needed.
Several Members and Consultant Leitch asked why cumulative usage factors greater than 1 are acceptable for some components. The staff stated that these analyses are conservative and the actual number of cycles are much lower than those used in these analyses. The staff added that if the usage factor of a component exceeds 1, the licensee would have to repair the component, replace the component, refine the analysis, or implement an aging management program. The applicant added that fatigue calculations are updated every fuel cycle to verify that cumulative usage factors won't exceed 1 during the next cycle.
Member Wallis asked what data was used to analyze the loss of prestress in concrete containment tendons. The applicant stated that data from the containment of AN01 was extrapolated to 60 years and is above the minimum requirements.
Staff Commitments The staff will calculate the USE of the limiting beltline material at 54 EFPY and report the results to the Committee.
Subcommittee Decisions and Follow-up Actions The Subcommittee will summarize the discussions to the full Committee during the December 2004 ACRS meeting.
Background Materials Provided to the Committee
- 1.
License Renewal Application for Arkansas Nuclear One Unit 2, October 14, 2003 8
- 2.
NRC Inspection Report 05000368/2004-06, License Renewal Scoping and Screening Inspection Report, April 19, 2004
- 3.
Information Systems Laboratories, Inc., Audit and Review Report for Plant Aging Management Reviews and Programs, Arkansas Nuclear One Unit 2, july 29,2004
- 4.
Draft Safety Evaluation Report Related to the License Renewal of the Arkansas Nuclear One, Unit 2, dated November 2004 NOTE:
Additional details of this meeting can be obtained from a transcript of this meeting available in the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Rockville, MD, (301) 415-7000, downloading or view on the Internet at http://www.nrc.gov/reading-rm/doc-collections/acrs/ can be purchased from Neal R. Gross and Co., 1323 Rhode Island Avenue, NW, Washington, D.C. 20005, (202) 234-4433 (voice), (202) 387-7330 (fax), nrgross@nealgross.com (e-mail).
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67372 Federal Register/Vol. 69, No. 221/Wednesday, November 17, 2004/Notices NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards Meeting of the Subcommittee on Plant License Renewal; Notice of Meeting The ACRS Subcommittee on Plant License Renewal will hold a meeting on December 1, 2004, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland.
The entire meeting will be open to public attendance.
The agenda for the subject meeting shall be as follows:
Wednesday, December 1,2004-1 p.m. until 4:30 p.m.
The purpose of this meeting is to review the License Renewal Application and associated Draft Safety Evaluation Report (SER) related to the License Renewal of the Arkansas Nuclear One, Unit 2. The Subcommittee will hear presentations by and hold discussions with representatives of the NRC staff, Entergy Operations, Inc., arid other interested persons regarding this matter.
The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate. for deliberation by the full Committee.
Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official, Mr. Cayetano Santos (telephone 301/415-7270) five days prior to the meeting. if possible, so that appropriate arrangements can be made.
Electronic recordings will be permitted.
Further information regarding this meeting can be obtained by contacting the Designated Federal Official between 7:30 a.m. and 4:15 p.m. (e.t.). Persons planning to attend this meeting are urged to contact the above named individual at least two working days prior to the meeting to be advised of any potential changes to the agenda.
Dated: November 9, 2004.
John H. Flack, Acting Branch Chief, ACRSIACNW.
[FR Doc. 04-25508 Filed 11-16-04; 8:45 am]
BILLING CODE 7590-o1-P OFFICE OF MANAGEMENT AND BUDGET Public Availability of Year 2004 Agency Inventories Under the Federal Activities Inventory Reform Act of 1998 (PUb. L. 105-270) ("FAIR Act")
AGENCY: Office of Management and Budget Executive Office of the President.
ACTION: Notice of public availability of agency inventory of activities that are not inherently governmental and of activities that are inherently governmental.
SUMMARY
- In accordance with the "Federal Activities Inventory Reform Act of 1998" (Pub. L. 105-270) ("FAIR Act"), agency inventories of activities FIRST FAIR ACT RELEASE 2004 that are not inherently governmental are now available to the public from the agencies listed below. The FAIR Act requires that OMB publish an announcement of public availability of agency inventories of activities that are not inherently governmental upon completion of OMB's review and consultation process concerning the content of the agencies' inventory submissions. After review and consultation with OMB, agencies make their inventories available to the public, and these inventories also include activities that are inherently governmental. This is the first release of the 2004 FAIR Act inventories.
Interested parties who disagree with the agency's initial judgment can challenge the inclusion or the omission of an activity on the list of activities that are not inherently governmental within 30 working days and, if not satisfied with this review, may demand a higher agency review/appeal.
The Office of Federal Procurement Policy has made available a FAIR Act User's Guide through its Internet site:
http://www.whitehouse.gov/OMB/
procurementlfair-index.html. This User's Guide will help interested parties review 2004 FAIR Act inventories, and gain access to agency inventories through agency Web site addresses.
Joshua B. Bolten, Director.
Attachment Armed Forces Retirement Home Mr. Steve McManus, (202) 730-3533 www.afrh.com.
Chemical Safety Board Ms. Bea Robinson, (202) 261-7627 www.csb.gov.
Commission on Fine Arts Mr. Frederick Lindstrom, (202) 504-2200 www.cfa.gov.
Committee for Purchase from People Who are Blind or Severely Dis-Mr. Leon Wilson, 70~04-7740 www.jwod.gov.
abled.
Consumer Product Safety Commission Mr. Edward Quist, (301) 504-7655 www.cpsc.gov.
Council on Environmental Quality Mr. Ted Boling, (202) 395-3449 www.whitehouse.gov.lceq.
Department of Energy..............................................................................
Mr. Dennis O'Brien, (202) 586-1690 www.doe.gov.
Department of Health and Human Services Mr. Michael Colvin, (202) 690-7887 www.hhs.gov.logam/oamlfairl.
Department of Transportation Mr. David Litman, (202) 366-4263 www.dot.gov.
Department of Transportation (IG)
Ms. Jackie Weber, (202) 366-1495 www.oig.dot.gov.
Federal Communications Commission IG Mr. Charles Willoughby, (202) 418-0472 www.fcc.gov/oig.
Federal Energy Regulatory Commission..
Ms. Kimberly Fernandez, (202) 208-1298 www.ferc.gov.
Federal Mine Safety and Health Review Commission Mr. Richard Baker, (202) 434-9905 www.fmshrc.gov.
Holocaust Museum Ms. Helen Shepherd, (202) 314-0396 www.ushmm.gov.
Institute of Museum and Library Services Ms. Teresa LaHaie, (202) 606-8637 www.imls.gov.
International Trade Commission Mr. Stephen McLaughlin, (202) 205-3131 www.usitc.gov.
Japan-United States Friendship Commission Ms. Margaret Mihori, (202) 418-9800 office.jusfc.gov/commissnl FAIRAct.htm.
Kennedy Center Mr. Jared Barlage, (202) 416-8731 www.kennedy-center.org.
National Aeronautics and Space Administration Mr. Kenneth Sateriale, (202) 358-D491 www.nasa.gov.
National Commission on Libraries and Information Sciences Ms. Madeleine McCain, (202) 606-9200 www.nclis.gov.
National Council on Disability...................
Ms. Ethel Briggs, (202) 272-2004 www.ncd.gov.
National Gallery of Art Mr. William Roache, (202) 842-6329 www.nga.gov.
National Labor Relations Board Mr. Emil George, (202) 273-1966 www.nlrb.gov.
National Labor Relations Board (IG)
Mr. Emil George, (202) 273-1966 www.nlrb.gov/igligindex.htm.
National Science Foundation Mr. Joseph Burt, (703) 292-5034 www.nsf.gov.
Nuclear Regulatory Commission Ms. Kathryn Greene, (301) 415-7305 www.nrc.gov.
Nuclear Regulatory Commission (OIG)
Mr. David Lee, (301) 415-5930 www.nrc.gov/insp-gen.html.
Occupational Safety and Health Review Commission Ms. Ledia Bernal, (202) 606-5390 www.oshrc.gov.
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 November 9,2004 MEMORANDUM TO:
John H. Flack, Acting Branch Chief, ACRS/ACNW
~ >~-Sr.
FROM:
Cayetano Santos, Senior Staff Engineer
SUBJECT:
FEDERAL REGISTER NOTICE REGARDING THE MEETING OF THE ACRS SUBCOMMITTEE ON PLANT LICENSE RENEWAL, DECEMBER 1,2004, ROCKVILLE, MARYLAND Attached is a Federal Register Notice regarding the subject meeting. Please have this Notice transmitted for publication as soon as possible.
Attachment FR Notice cc with
Attachment:
M. Bonaca, ACRS J. Larkins, ACRS J. Szabo, OGC A. Bates, SECY R. Tadesse, OEDO S. Burnell, OPA R. W. Borchardt, NRR D. Matthews, NRR P. Kuo, NRR T. Liu, NRR PMNS Public Document Room
[7590-01-Pl NUCLEAR REGULATORY COMMISSION ADVISORY COMMITIEE ON REACTOR SAFEGUARDS MEETING OF THE SUBCOMMITIEE ON PLANT LICENSE RENEWAL Notice of Meeting The ACRS Subcommittee on Plant License Renewal will hold a meeting on December 1, 2004, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland.
The entire meeting will be open to public attendance.
The agenda for the subject meeting shall be as follows:
Wednesday, December 1, 2004 - 1:00 p.m. until 4:30 p.m.
The purpose of this meeting is to review the License Renewal Application and associated Draft Safety Evaluation Report (SER) related to the License Renewal of the Arkansas Nuclear One, Unit 2. The Subcommittee will hear presentations by and hold discussions with representatives of the NRC staff, Entergy Operations, Inc., and other interested persons regarding this matter. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the full Committee.
Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official, Mr. Cayetano Santos (telephone 301/415-7270) five days prior to the meeting, if possible, so that appropriate arrangements can be made.
Electronic recordings will be permitted.
Further information regarding this meeting can be obtained by contacting the Designated Federal Official between 7:30 a.m. and 4:15 p.m. (ET). Persons planning to attend this meeting are urged to contact the above named individual at least two working days prior to the meeting to be advised of any potential changes to the agenda.
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,,-j)~g J6hntH. Flack, Acting Branch Chief, ACRS/ACNW
Advisory Committee on Reactor Safeguards Plant License Renewal Subcommittee Meeting Arkansas Nuclear One - Unit 2 December 1, 2004 Rockville, MD
-PROPOSED SCHEDULE-Cognizant Staff Engineer: Cayetano Santos Jr. CXS3@NRC.GOV (301) 415-7270 Topics Presenters Time Opening Remarks M. Bonaca, ACRS 1:30 pm - 1:35 pm II Staff Introduction P.T. Kuo, NRR 1:35 pm - 1:40 pm III ANO-2 License Renewal Application G. Young 1:40 pm.e:4B=p;.r I ~212 Of /VI Entergy Operations, Inc.
A.
Application Background B.
Description of ANO-2 C.
Operating History D.
Scoping Discussion E.
Application of GALL F.
Commitment Process
'U'Z,...Or ""
31'" () I""
'ii:1Q 13m - ~Q 131'11 R. Nease, Region IV L. Smith, Region IV A.
Scoping and Screening Methodology Results B.
Onsite Inspection Results BREAK 3 ~I ~ f /11 Sl8e pm - 3T=I-5-pmJ;z.;- pt'1 1~~~
~
V Aging Management Program Review G.Suber,NRR
.a:1oplll-~OOpnl {h~p~
and AUdits G. Cranston, NRR VI Time Limited Aging Analyses (TLAAs)
G. Suber, NRR 'fI""I"\\~:OO I'm - ~O pill ~~<['~1'1
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VII Subcommittee Discussion M. Sonaca, ACRS
~m - ~ S 4'::-('~
VIII Adjourn M. Bonaca, ACRS 50Q0 pi IT" >Ifs(?""
NOTE:
Presentation time should not exceed 50 percent of the total time allocated for a specific item. The remaining 50 percent of the time is reserved for discussion.
50 copies of the presentation materials to be provided.
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ADVISORY COMMITIEE ON REACTOR SAFEGUARDS SUBCOMMITTEE MEETING ON PLANT LICENSE RENEWAL December 1! 2004 Date NRC STAFF SIGN IN FOR ACRS MEETING PLEASE PRINT NAME NRC ORGANIZATION fY\\ \\l-(-\\Ah-l h~
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uec. 1,~UU4 Entergy Arkansas Nuclear One - Unit 2 License Renewal Presentation to ACRS Subcommittee Garry G. Young Entergy Nuclear December 1, 2004 e
........Entergy Introduction
- Application Background
- Description of ANO-2
- Operating History
- Scoping Discussion
- Application of GALL
- Cornrnitment Process Dec. 1,2004 2
1
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Entergy Application Background
- Application subrrlitted October 15, 2003
- Original license expiration:
- Unit 2 - JUly 17,2018
- New Process
- Consistent with GALL Audits Dec. 1.2004 3
Description of ANO-2 Entergy
- Combustion Engineering PWR
- Bechtel - Architect /
Engineers
- Initial Ops: 1978
- Capacity: 3026 MWt 1023MWe Dec. 1,2004 4
2
UVV. I, £.VV't Entergy Operating History
- Uprated: Unit 2 - 2002
- 7.50/0 power uprate
-Increased capacity by 210 MWt
- SGs replaced in 2000
- Westinghouse Delta 109 U-tube Dec. 1,2004 5
Entergy ANO-2 Scoping Method
- Scoping applied on a plant system basis
- System scoping per
- Safety-related -10CFR 54.4(a)(1)
- Non-sa.fety that could affect safety function 10CFR 54.4(a)(2)
- Criteria for Regulated Events - 10CFR 54.4(a)(3)
- Screening per 10CFR 54.21 (a)(1)
Dec. 1,2004 6
3
u\\:;\\". I I ~UU...
Entergy GALL Comparison
- ANO-2 focused on consistent with GALL
- Some material/environment/program combinations not addressed in GALL
- Plant-specific programs used as needed
- Past precedent table provided separate from application Dec. 1,2004 7
~
- ===
-Entergy Consistent with GALL
- 33 total aging management programs
- 15 programs consistent with GALL and with enhancements
- 7 programs consistent with exceptions
- 11 programs not consistent with GALL and plant speci"fic
- 1 AMP added - One Time Inspection Dec. 1.2004 8
4
~
-=-
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Entergy Commitment Tracking
- Commitments
- Commitments documented in the LRA and revised as needed during audit / inspection process
- Tracked with AND Licensing Commitment Tracking System Dec. 1,2004 9
Commitment Tracking System Entergy Dec. 1,2004 10 5
ut::\\". I I '::'VV't.
Closing Remarks Entergy
- New process with audit team was thorough and rigorous
- Consistent with GALL process and past precedent added new opportunity for process efficiency Dec. 1,2004 11 6
ACRS License Renewal Subcommittee Arkansas Nuclear One, Unit 2 License Renewal Application Draft Safety Evaluation Report December 01, 2004 Gregory F. Suber Project Manager NRC Review Highlights
- No Open Items
- No Confirmatory Items
- Brought into scope and subjected to AMH
- Five (5) components/commodities
- 1 new AMP - One-Time Inspection December 1, 2004 ACRS Subcommltlee Meeling Arkansas Nuclear One. Unit 2 1
NRC Review Highlights
- Three (3) License Conditions
- Update FSAR upon issuance of the renewed license
- Complete future activities described in the FSAR Supplement prior to entering the period of extended operation
- Reactor Vessel Surveillance Program
- Remove and test capsule in accordance with ASTM E 185-82
- Obtain NRC approval prior to changing capsule withdrawal schedule or changing storage requirements December 1. 2004 ACRS Subcomminee Meeting 3
Arkansas Nuclear One, Unit 2 NRC Audits and Inspections
- Aging Management Programs Audit
- December 1 - 5, 2003
- Scoping and Screening Methodology Audit
- January 20 - 22, 2004
- Aging Management Review Audit
- February 9 - 13, 2004
- Scoping and Screening Inspection
- March 1 - 5, 2004
- Aging Management Program Inspection
- November 1 - 19, 2004 December " 2004 ACRS Subcomminee Meeting Mensas Nuclear One. Unit 2 2
Section 2 - Structures & Components Subject to an AMR 2.1 - Scoping and Screening Methodology
- Describes methodology used to identify SSCs that are within the scope of.the license.renewal rule and subject tOCln AMR
- Staff audit determined that the applicant's m.~lhodology sati?fiesth~>rule.
December 1, 2004 ACA.S Subcommln** Meeting ArkansB8Nuclear One, Unit 2 Section 2 - Structures & Components Subject to an AM R SectiOn 2.2 - Plant Level Scoping Results
- Staff reviewed Section 2.2 tocietermine if any systems, structures, and components required to be withigsG9pewere omitted.
- Three (3) components brought into scope
- Feedwater Outboard Block Valve
- Intake Canal Structure
- Power Transmission Conductors December 1, 2004 ACRS Subcomml"ee Meeting Arkansas Nuclear One, Unit 2 3
Section 2 - Structures & Components Subject to an AMR Section 2.3 - Scoping and Screening of Mechanical Systems
- Includes the following systems:
- Engineered Safety Features Systems
- Auxiliary Systems
- Steam and Power ConverSion Systems
- One (1) Component added by NRC Staff Review:
Feedwater Outboard Block Valve Decembw 1, 2004 ACR$ SlbcommlUee MooUng Monaos Nuclear One, UnR 2 Section 2 - Structures & Components Subject to an AMR Section 2.4 - Structures and Structural Components
- Describes structures and structural components
- Containment
- Auxiliary Building, Turbine Building, Yards Structures
- Intake Canal and Emergency Cooling Pond
- Bulk Commodities
- One (1) Component brought into scope by NRC Staff Review: Intake Canal Structure December " 2004 ACAS SubcommitCee Meeting 8
Arkansas Nuclear One, Unil 2 4
Section 2 - Structures & Components Subject to an AMR Section 2.5 - Electrical and Instrumentation an~ Controls
- Structures andComponent/Cql1lmodities
- Electrical cables
- ElectricaIGQi1r:t~ptQts
- High voltage transmission conductors and insulators
- One (1) Gomponentadded by NRC ~t(lff Review:
Power Transmission Conductors December 1. 2004 ACRS SubcommltteEt Meeling 9
ArkBIlBBSI Nuclear One, Unit 2 LicenseJF\\enewal Inspections
.. Scheduled to Support Pilot ReView Program
- Scoping al1d Screening Inspection (March 2004)
- Aging Management Review Inspection (November 2004)
- Third Inspection - Optional December 1, 2004 ACRS SubcommiUee Meeling 10 Arkansas Nuclear One, Uni12 5
License Renewal Inspection Pro ram 1m lementation
- License Renewal Manual Chapter-MC2516
- Inspection Procedure-IP 71002
- Site-specific Inspection Plan December 1. 2004 ACRS Subcomml_ Meeting 11 MaNa. Nucf8er One. Unil2 License Renewal Inspections Scoping and Screening Inspection
- Objective: to confirm that the applicant has included SSCs in the scope of license renewal as required by the rule
- Resources: 3 regional inspectors 1 resident inspector
- One week in length: March 1 - 5, 2004 December 1, 2004 ACRS Subcommittee Meeting 12 Mansas Nuclear One, Unil 2 6
License Renewal Inspections Scoping and Screening Inspection Results
Conclusion:
Scoping and screening process was succes~ful in identifyihQJfuose SSCs requiring an.~Qingrna.l1~g~ment review.
- Two items broLlghlinto~g9pe:.
Spent FuelP>bdl~oollrtgPumps.
Svvilchyard Control House December 1, 2004 ACRS Subcommltt** Meeting 13
.Ark8ness Nuolear OnSi Unit 2 License.Renewallrist>~qtions Aging Management Review Inspection
- Objective: to confirm that applicant has implemented or plans to implement AMPs to manage aging eff~cts forjrH§cope SSCs
- Two weeks: November 1-5 and 15-19, 2004
- Results will be summarized in a future report.
December 1, 2004 ACAS Subcommittee Meeting 14 Arkansas Nuclear One, Unil 2 7
ANO-2 30/2004 Performance Summary Perform.Rca Indicators December 1, 2004 ACRS SlbcOnvnlnoe Meeting 15 Manoa. Nucleer One, Una 2 ANO-2 Pertormance Summa
- Midcycle Performance Review (August 30, 2004)
- Licensee is in the Regulatory Response Column of the NRC's Action Matrix due to a white finding in the area of fire protection (issued April 7, 2004).
- Annual Assessment Letter (dated March 3, 2004) identified a substantive cross-cutting issue concerning PI&R.
December 1t 2004 ACRS SLbcommlnee Meeting 16 Arkansas Nuclear One. Unit 2 8
Scoping and Screening Summary
- Scoping and screening methodology is adequately described and justified in the LRA and satisfieSJhe requirements of 10 CFR 54.4 and 10.QfR 54.21 (a)(1).
- Scoping ands.Qr~~Hlhgreview results fgiJnd th?ttheS~Cs ~;ll~~i;n the scope of liceQ~e ren~}Nal,'asr,equire~.byto CFR 54.1(a) and those;~ubject to an AMR, as requiredby 10 CFR54.21 (a)(1), have been identified.
December 1, 2004 AC~ SubcommiUee Meeting 17 Ar.kanaB& Nuclear One, Unit 2 Section 3 ;'AgingManagement Review
- Aging Management Program
- Aging ManagemefltReview Results December 1, 2004 AcRS Subcomminee MeeUng 18 Arkansas Nuclear One, Unit 2 9
Section 3 - Aging Management Review
- Reactor Vessel, Internals, and Reactor Coolant System
- (Section 3.1)
- Engineered Safety Features Systems (Sections 3.2)
- Auxiliary Systems (Section 3.3)
- Steam and Power Conversion Systems (Section 3.4)
- Containments, Structures and Component Supports (Section 3.5)
- Electrical and Instrumentation and Controls (Section 3.6)
December 1, 2004 ACRS Slb:ommlftee. Meoting 19 Artcanoao Nuclear One, Unti 2 Section 3 - Aging Management Review Section 3.1 - Reactor Vessel, Internals and Reactor Coolant Systems
- One License Condition
- Three commitments to submit programs for NRC review and approval Section 3.2 - Engineered Safety Features System December 1. 2004 ACRS Subcommlnee Meeting 20 Arkansas Nuclear One. Unit 2 10
Section 3 - Aging Management Review
- Section 3.3 - Auxiliary Systems
- One-Time inspection to supplement System Walkdown.AMP
- Fire ProtectJCi)n
- S~Gtion 3.4 -
St.~am and power Conversion Systems December 1, 2004
- ACRS SubcommlueeMeeUng 21 Mansas Nuclear One; Unit 2 Section 3--.. Agin~**Mqnagement Review Section 3.5 - Containment, Structures,and Component Supports 1111 Intake canal structure was added to the scope of license renew,..and the c;lQing effects will be managed by ttle Strutttires Monitoring Program.
December 1, 2004 ACRS SubcommlUse Meeting 22 Arkansss Nuclear One, Unit 2 11
Aging Management of In-Scope Inaccessible Concrete Aggressive Limit ANO*2 pH
<5.5 7.23 Chlorides
>500 ppm
<5 ppm Sulfates
> 1500 ppm 20.3 ppm
- Below grade soil/water environment non-aggressive
- Use of Structural Monitoring Program to manage aging as if the environment were aggressive December 1, 2004 ACRS S_mlttee MeeIIng 23 Martlu Nuclear One. UnIl 2 Section 3 - Aging Management Review Section 3.6 - Electrical and Instrumentation and Controls
- Power transmission conductors were added to the scope of license renewal, however, there were no aging effects requiring management and no AMP was required.
December 1, 2004 ACAS Subcommin911 Meeting 24 Arkansas Nuclear On8, Unit 2 12
AGING MANAGEMENT PROGRAM CATEGORIES
- CONSISTENT WITH GALL
- CONSISTENT WITH GALL, WITH EXCEPTIONS
- CONSISTENT WITH GALL, WITH ENHANCEMENTS
- PREVIOUSLY-APPROVED STAFF POSITIONS December 1, 2004 ACRS SubcOmmittee Meeting 25 Arkansas Nuclear One, Unit 2 NRC AP~RbvED PRECEDENTS PRECEDENT INFORMATION
.Sl!pplementary information voluntarily provided
- Roadmap, reviewers aid
- Not a part of LRA
- Basis must be verified AUDUT TEAM DETERMINES
- Applicability of previously-approved staff position
- Program bounded by the conditions for which the staff position was evaruated and approved
- Piant program contains the SRP-LR program elements (or attributes)
December 1, 2004 ACRS Subcommittee Meeting 26 Arkansas Nuclear One, Unit 2 13
LRA AMP CONSISTENT WITH GALL AMP
- LRAAMP
- 8.1.10.2, Structures Monitoring - Masonry Wall
- Existing program
- XI.S5, Masonry Wall Program
- AUDITTEAM IDENTIFIED PROGRAM DISCREPANCIES
- Initial baseline examinations not properly documented.
- First 5 year re-exam not performed
- Qualifications for structural walkdown personnel not established
- APPLICANT GENERATED CONDITION REPORT TO IDENTIFY AND CORRECT DEFICIENCIES.
December 1. 2004 ACRS Slb:ommlttee Meeting 27 Arkansas Nuclear One, Un" 2 LRA AMP CONSISTENT WITH GALL AMP WITH EXCEPTIONS LRAAMP
- B.l.7, Diesel Fuel Monitoring
- ASTM standard D 1796 used; D 2709 not used
- Smaller filter pore size
- No ultrasonic measurements of tank bottoms BASIS FOR ACCEPTING Use vendor recommended additive package. including biocide and oxidation inhibitor; proven successful from operating experience
- ASTM D 1796 applies to viscosity of fuel oils used at ANO-2; D 2709 does not apply
- Smaller filter pore size acceptable
- Tank bottom sealed to above ground, concrete foundation preventing water intrusion.
- Accessible tank external surfaces & internal surfaces periodically. visually inspected
- AN02 operating experience shows no tank bottom or wall thinning problems December 1. 2004 ACRS Subcomminee Meeling 28 Arkansas Nuclear One. Unit 2 14
LRA AMP CONSISTENT WITH GALL AMP WITH ENHANCEMENTS
- LRAAMP
- B.1.10.2, Fire Water System
- .'XI.M27, Fire Sen/ice Water
- PROGRAM ENH)\\N9EM~
- Sprinkler head inspechtjh§'
consistent with NRC Interim Staff Guidance (ISG) 04
- BA$I$ FORACCEPTI~QEf'J.!-i~f'J!i.:;E.MENT/;
- I§~ 04 revised GALL AMP){ljM2fcriteria. Applicant COl1sistent wit~ISG-4 and using the guidance of NFPA 25 December 1, 2004 P,tC~_s SUbcOm!Jlltle~ Mee'Ung 29 Arkansas Nuclear °':18; Unit 2 LRA AMP BASEI:),.RN~I?~~,!IRUSL V-APPROVED STAFF POSITION CHANGEDTO CONSISTEN WITH GALL AMP LRAAMP
- B.1.5,Cast Austenitic Stainless Steel (CASS)
- Nellli Program - submitted based on NRC preViously-approved staff position PROGRAM AUDIT EVALUATION
- Applicant originally Cited'~r~~ibusly-approved staff position to only do external, visuallnspectiohS based on an approved code case
- Application of code case rejected by Audit Team as not applicable to ANO-2.
- XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel December 1, 2004 ACRS SUlx:ommlnee Meellng 30 Arkansas Nuclear One, Unit 2 15
LRA AMP - PREVIOUSLY-APPROVED STAFF POSITION
- 6.1.29, Wall Thinning Monitoring
- PREVIOUSLY-APPROVED STAFF POSITION
- ANO-2 Plant Specific,AMP based on NRC previously-approved staff position for ANO-1
- PROGRAM REVIEW CRITERIA
- AMP reviewed by Audit Team against AMP elements in SRP LR, Appendix A, and ANO-1 approved program December 1, 2004 ACRS SubconvnIfteo Meetlng 31
.... Nuclear One, Unlt 2 Aging Management Review Summa
- Aging management review found that the applicant has demonstrated that the effects of aging will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation, as required by 10 CFR 54.21 (a)(3).
December 1t 2004 ACRS Subcommittee Meeting 32 Arkansas Nuclear One. Unit 2 16
Section 4 - Time-Limited Aging Analyses (TLAA)
- Reactor Vessel and Interna.ls Neutron Embrittlement
- Metal Fatigu,e
- EnvironmentalQualific~tion
- Loss of Presfress!rHJohcrete Containment Tendons
- Containment Liner and Penetration F<<:itigue Analysis
- Other Plar:lt-Specific TLAAs December 1, 2004 ACRS Subcommltte. M**llng 33 Arkansas Nuclear One, Unit 2 Section 4-TLAA Section 4.1 - Identification of TLAAs
- Five TLAAs were identified 'from Table 4.1-2 Potential List Of Time-Limited Aging Analyses in NUREG-1800.
- Five Other Plant-Specific TLAAs were identi'fied by the applicant.
December 1, 2004 ACRS Subcommittee Meeting 34 Mansa.s Nuclea.r One, Unil 2 17
Section 4 - TLAA RVI Section 4.2 - Reactor Vessel and Internals Neutron Embrittlement
- Three analyses affected by irradiation embrittlement identified as TLAAs
- Upper Shelf Energy
- Pressurized Thermal Shock
- Pressure Temperature Limits December 1. 2004 ACRS Sl.tJcomminee Meeting 35 Arksnaaa Nuclear One. Unit 2 Section 4 - TLAA on Upper Shelf Energy (USE)
Section 4.2 - Reactor Vessel and Internals Neutron Embrittlement Limiting Material USE Acceptance Calculated 48 EFPY Conclusion For USE Criterion USE value Intermediate Axial Weld 2-203A 50 ft-Ib Staff:
54 ft-Ib Entergy: 54 ft-Ib Criterion is met for 48 EFPY December 1, 2004 ACAS Subcommihee Meeting 36 Arkansas Nuclear One, Unll2 18
Section 4 - TLAA on Upper Shelf Energy (USE)
- Calculation of USE values for 48 effective full power years (EFPY) identified as a time limited aging analysis (TLAA) for license renewal
- Applicant perforrne!d updat~d USE value~9alculations oUhe rl'l~ctor vessel (RV)beltline materials ij$projected through 48 EFPY.
- Staff perfo(l!led indepe!rident calculations of the USE "alues for the RV beltline materials through 48 EFPY.
- Both the applicanta~~~t~ff'l=l palculationsdemonstrafethe USE acceptance criterion forthelimiting beltline material Will be met through 48 EFPY. TLAA' an~lysis meets the requirements of 10 CFR part15P,..AppendiX G,and the acceptanc..e.,criterion in 10 CFR 54.21(c)J3){ii).'<.;
December 1, 2004 P.CRS Subcommittee M**~ng 37 Mat188s Nuclear Onei' Unil2 Section 4;;;-;TLAAof'lPressurized Thermal 'Shock (PTS)
Section 4.2 - Reactor Vessel and Internals Neutron Enibrittlement Limiting Material For PTS ScreElning Criterion Calculated 48 EFPY RTPl:S vlilue Conclusion Lower Shell Plate C-B010-1 Staff:
122.62F Entergy: 122.6QF Screening Criterion is met December 1, 2004 ACAS Subcommittee Meeting 38 Arkansas Nuclear One, Unil2 19
Section 4 - TLAA on Pressurized Thermal Shock (PTS)
- Calculation of RTPTS values for 48 effective full power years (EFPY) identified as a time limited aging analysis (TLAA) for license renewal
- Applicant performed updated RTPJsvalues calculations of the reactor vessel (RV) beltline matenals as projected through 48 EFPY.
- Staff performed independent calculations of the RTPTS values for the RV beltline materials through 48 EFPY.
- Both the applicant and staff's calculations demonstra.te the applicable screening criterioh for the IimitinQ beltline RV material will be met through 48 EFPY. TLAA analysIs meets the requirements of 10 CFR 50.61 and the acceptance criterion for in 10 CFR 54.21 (cH3Hii).
ACRS S__ MeeUng December 1, 2004 39 Arka...... Nuclear One, Unit 2 Section 4 - TLAA Metal Fatigue Section 4.3 - Metal Fatigue
- Two analyses affected by Metal Fatigue
- ASME Class 1 Components (RCS)
- Remains valid under 10 CFR 54.21 (c)(1 Hi)
- ASME Non-Class 1 Piping
- Remains valid under 10 CFR 54.21 (c)(1 Hi)
- ASME NOFl
~ss 1 Components
- Fatigue evaluations are not required for these components.
December 1t 2004 ACRS SLJx:omminee Meeting 40 Arkansas Nuclear One, Unil 2 20
Section 4 - TLAA EO Section 4.4 - Environmental Qualification
- Applicant's EOprogfamJsconsistent with GALL X.E1.
/i;:'1
- Staff concluded EO Program will conti~~~to manage equipment in accordance will110 CFR 50.49, and meets 10CFR 54.21 (c)(1) (iii).
December 1, 2004 ACRS SUbcom"Jinee, Meetlng 41 Artcsnsss Nuolear One, Unit 2 Section 4..... TlAA Concrete Tendons Section 4.5 - Concrete ContainmentTendon Prestress
- Based on the applicant's commitment, the staff concludes the effect~of aging on the intended fUnctiQr1$WIII be-adequately managed for the extended period ot' operation in accordance with 10 CFR 54.21 (c)(1 )(iii).
December 1, 2004 ACRS Subcommlrtee Meeting 42 Arkansas Nuclear One, Unll2 21
Section 4 - TLAA Containment Liner Plate and Penetrations Section 4.6 -Containment Liner Plate and Penetrations
- Remains valid in accordance with 10 CFR 54.21 (c)(1)(i)
December 1, 2004 ACRS SlJJcommibee Meeting Arkansaa Nldear One, Unit 2 Section 4 - TLAA Plant-Specific Section 4.7 - Other Plant-Specific TLAAs
- Licensee-Identified TLAAs
- Steam Generator Tubes - Flow-Induced Vibration
- Alloy 600 Nozzle Repair
- High Energy Line Break Analyses
Section 4 - TLAA Plant-Specific
- Section 4.7 - Other Plant-SpecificTLAAs ALLOY 600 Nozzle Repair
- Projected thtbugHft1epefibd of extended operation under 10 CFR54.21 (c)(1)(ii)
December 1, 2004 ACRS SubcommitteeMeeting 45 Man&u Nuclaar One, Unit 2 Section 4 - TLAAPlant-Specific
- S~~tion 4.7 - Other Plant-Specific'Tl-AAs R~'actor Coolant Pump Code Case N-481
- Use of alternative inspection method in code case reqUires flaw tolerance (crack growth) which is a time-limited effect
- Remains valid in accordance with 10 CFR 54.21 (c)(1 )(i)
December 1, 2004 ACRS Subcommittee Meeting 46 Arkansas Nuclear One, Unil2 23
Section 4 - TLAA Plant-Specific
- Section 4.7 - Other Plant-Specific TLAAs ReS Piping Leak Before Break (LBB)
- LBB is a TLAA and requires that growth of postulated flaws should meet a safety factor of two (2) on critical crack size. The thermal aging of CASS piping components can reduce critical crack size.
- Cycles in fatigue growth analysis were determined to be bounding for 60 years. Critical crack size l,Jsed in the analysis were determined to be bounding*for saturated thermally-aged CASS material.
- Remains valid in accordance with 10 CFR 54.21 (c)(1 )(i)
December 1. 2004 ACRS Subcommlnoe Meeting 47 ArttaI1888 Nuclear One, unn 2 TLAA Summary
- Will remain valid for the period of extended operation,
- Have been projected to the end of the period of extended operation.
or
- The aging effects will be adequately managed for the period of extended operation.
December 1, 2004 ACRS Subcommlnee Meeting 48 Arkansas Nuclear One, Unft 2 24
Staff Conclusions The Applicant has met the requirements for license renewal, as required by 10 CFR 54;29:
- Actions have been identified and have been or will be taken sucbfllatctner~ is reasonable assurance that activities will continue to be cdnductedin thet:~enewal term in*accordance with tDe current licensing basis.
December 1, 2004 ACRS SutK:ommlnee:.Meeting 49 Arkansas Nuclear One. Unit 2 ACRS License Renewal Subcommittee Arkansas Nuclear One - Unit 2 Nuclear Power Plant License Renewal Application Draft Safety Evaluation Report December 1, 2004 Gregory F. Suber Project Manager 25
BACKUP SLIDES December 1. 2004 ACRS S.mcommiboe Meeting 51 Arttareu Nudear One, Unit 2 cerpt 'from ANO-2 LRA Table 1 for Reactor Coolant System Table3.1.1: Reactor CoolanlSyslam, NUREG 1801 Vol. 1 i
i AgIng j
Further
]
Aging EIfectJ Item Management Component
[
Ev.IRtion I Discussion Mechanism Number Programs i Recommended.
I TLAA. evalualed in iYes. TlAA ICracking due to ratigue IS an aging eneer pressure latlgue damage' 3.1.1-1 RBaclOr cootlnl CumulaUve accordance wtth i
! applicable 10 reacror coolant pressure boundary boundaty
'0 CFA 54.2'(0)
IItems subject to BgU:lg management revieW.
I components 1Because of the uniform applicability of this effect. I I the effect and the compartson to the associated
'I NUREG-fSOllino items have not been. listed H1 I'
I Ill. Cia** 1 lobi** (3.1.2-1 through 3.1.2-5) i below. The metal fafigue TIM aSSOCIated with l' Class 1 components is addressed In 5ecllon 4.3.
! -----+--------~-
3.'.1-2 Sleam generator This grouping includos the s1eam g9neratot shen shalt assembly Los.S 01 ma1(N'ial
! Inservlce Inspectlon: Yes. dRt9Crion of assembly and attached components. and componenls of the secondary side lnternaJa. The l due 10 pilling and Iwater chemistry aging offect!;; Is to crevtce corrosion I
- ~~::
I concems 01 IN 90-04 are not appncable to ANO-2 I since lhe atOilfTl genomlors were replaced in 2000 and phting cDlTosion 01 tho steam g¢nOfatot !
! sholl is not known to currently exist. ANO-2 Ics-edits the waler chemistry control program and
! the inservJce inspection program for managing j loss of material due to pitting and crevICe l corrosiol"! on the inlernal SIJrfacRs of the steam generator shen. For further evaluation, see l
f Seclion 3.1.2.2.2. lnservice inspection is a planl- !
I spoctfic program for ANO-2.
f--__-+-
L._~
._L
-~-'-~~~-'----'---'-""'--"
3.1.1*3
~ BWH only
--_._--~~-_..~--
December 1. 2004 ACAS Subcommihee Meeting 52 Arkansas Nuclear One, Unit 2 26
cerpt from ANO-2 LRA Table 2 for Reactor Coolant System
l Aging Management Programs Aging Effect Requiring Management Loss 0' tm,llerlal
~::on 1Air (eX1emal) iii Ma1erral Environment In{ended Function Pr05GUra boundary Cons,iS1..ent with NUREG*1B01 Item fOr component. malarial, environrl\\ent. aging effect and a~lng management program. AMP Is consistent Wllh NUREG*1601 AMP, B. Consl~tent with NUREG-180 I "em for.component, milierial, environfTll,ml, agIng effect and aging managemontprogram, AMP Ilas elfceptions.to NUREG*1801 AMP.
C. Componont Is ~ltferent. but consistenl. Wft.h NURE9-1801 jtem lor material, EmvlronmenL a{lln9 effect and aging managlilment program.
AMP Is COf1$iS10nf With NUREG-I801 AMP.
O. Component is different, bl1t: consistent with NUREQ*1801 i1em for material, envirOOffllil"!r.. ag~9 eflact and aging m~nagomenl program.
AMP h8~ ~u(cepttonG to NURE'G-180tAMp.
E. ConslstefTI. With NUREG-1a01 material. ttpvlronrtlent, and agin9 eHact but a different aging rnnnagement program Is credited.
F. Malarial nolln NUREG*1801 for" thIS component.
Table 3.1.2:-3 Class 1 P"lping. Valves, and Reac.1or Coolant Pumps G. Environment not In NUREG-1,80' for thlSc:omponent and materiaJ.
H. Aging 9f1eet not In NURIS"(~*'80i rot this cornponQht. malarial and envlrol'lment' combination.
I.
Aging effect. in NUREG-l~011or'lhlscOmponent. inst$rlat..and enVinJllmenl CQmbjn8t.~on i" nq,1 applICable.
J, Nei1h8f the component nor the moterlnl an~ environmorir com'blnatlon is evalualed In NUAEG-1501.
elant~§QMifjgootm 101. The matoda' nod en...mJmnenl L-omblnallon is fn NUREG*i801 but no!lhot the plant component. nor 'Ii reasonable substitute. oxist9.
December 1, 2004 ACRS SUbcommittee Meeting 53 Arkensas"NucleEu Onei Unit 2 xcerpt from ANO-2LRA Precedent 8eterence Table December 1, 2004 ACRS Subcommittee Meeting 54 Arkansas Nuclear One, Unil2 27
ELEMENTS OF AN AGING MANAGEMEI\\IT PROGRAM FOR LICENSE RENEWAL Scope of program Scope of progrem should include the specific structures and components subject to an AMR for license renewal.
2 Preventive actions Preventive actions should prevent or mtigate aging degradation.
3 Parameters monitored or inspected Parameters monitored or inspected should be linked to the. degradation of the particular structure or component intended function(s).
4 Detection of aging effects Detection of aging effects should occur before there Is a loss of structure or component intended function(s). This includes aspects such as method or technique (i.e., visual, volumetric, surface inspection), frequency, sample size, data collection and timing of new/one-time inspections to ensure timely detection of aging effects.
5 Monitoring and trending Monitoring and trending should provide predictability 01 the extent of degradation, and timely corrective or mtigative actions.
6 Acceptance criteria Acceplance criteria, agalnst Which the need for conectlve action will be eval uated.
should ensure that the structure or component intended function(s) are maintained under all CLB design conditions during the period of extended operation, 7*
Corrective actions Audited by DivisiOn of Inspection Program Menagement S*
Confirmation process Audited by DivIsion of Inspection Progrem Management 9*
Administrative controls Audited by Division of Inspection Program Menagement 10 Operating experience Operating experience of the aging management program, Including pest corrective actions resulting in program enhancements or additional programs, should provide objective evidence to support the conclusion that the effects of aging will be managed adequately so that the structure and component intended function(s) will be rn8.intained dUring the period of elden.ded operation.
December 1, 2004 ACAS Suboommlnee Meeting
_noaa Nuclear One, Unit 2 55 Aging Management Reviews lRASKtlon TotalAMR AssIgned to RL£P-B Asslgne<lto Tech Staff GALL fJ'recadenCII 3.1 580 47% (274) 16%(94) 37% (212) 3.2 235 30% {1O1 36% (85) 34% (80) 3.3 667 53% {353) 9% {OO) 38% (254) 3.4 160 45% (72)
'8% {28) 31% (60) 3.5
'24 51% (63) 9% (11) 40% (ro) 3.6 6
2 (33%)
O{O%)
4 (67'1\\.)
Total MlR 834 278 660 Total %
63%
37%
December 1, 2004 ACRS Subcommlnee MeeUng 56 Arkall&88 Nuclear One, Unit 2 28
S&S Inspection Results
- Spent Fuel Pool Cooling Pumps SFPC pump casing could fail and spray EFW Pump inlet iso valve and the bypass valve. This could interrupt steam to the TD EFW Pump.
Applicant agreed to include the SFPC pump casing.
- Switchyard Control HoUse THe applicant included the SUT bkt control cables; howe\\(~r. did not include the cables' supporting structure.
Applicant agreed to include the entire structure.
December 1, 2004 ACRS Subcommittee Meeting 57 Arlcanssa Nuc:1ear One, Unit 2 AMR Insp Preliminary Results
- Coniplated S&S wrt the SER