ML081620304

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Meeting Minutes of the ACRS Plant License Renewal Subcommittee, April 14, 2004
ML081620304
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 06/10/2004
From: Leitch G
Advisory Committee on Reactor Safeguards
To:
References
Download: ML081620304 (90)
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 - 0001 June 10, 2004 MEMORANDUM TO: ACRS Me~rs ~ 01 ~ FROM: Marvin D7t~~neer Technical Support Staff ACRS/ACNW

SUBJECT:

CERTIFICATION OF THE MINUTES OF THE MEETING OF THE ACRS SUBCOMMITTEE ON DRESDEN/QUAD CITIES LICENSE RENEWAL, APRIL 14, 2004 - ROCKVILLE, MARYLAND The minutes of the subject meeting, issued on April 14, 2004 have been certified as the official record of the proceedings of that meeting. A copy of the certified minutes is attached.

Attachment:

As stated cc: J. Larkins H. Larson S. Duraiswamy ACRS Staff Engineers

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555 *0001 June 2,2004 MEMORANDUM TO: Graham Leitch, Chairman ACRS Plant~e.n~e R ewal Su rnittee FROM: Marvin D. 7f~,o a f Engineer, ACRS

SUBJECT:

WORKING COpy OF THE MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE DRESDEN AND QUAD CITIES NUCLEAR POWER PLANTS LICENSE RENEWAL APPLICATION, APRIL 14, 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 in the pre-addressed envelope attached.

Attachment:

Minutes (DRAFT) cc wlo

Attachment:

J. Larkins H. Larson S. Duraiswamy ACRS File

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, DC 20555

  • 0001 MEMORANDUM TO:

Marvin D. Sykes, Senior Staff Engineer, ACRS FROM: Graham Leitch, Chairman ACRS Plant License Renewal Subcommittee

SUBJECT:

CERTIFICATION OF THE

SUMMARY

MINUTES OF THE MEETING OF THE ACRS PLANT LICENSE RENEWAL ON THE DRESDEN AND QUAD CITIES NUCLEAR PLANTS, ARIL 14,2004 ROCKVILLE, MARYLAND I hereby certify, to the best of my knowledge and belief, that the minutes of the subject meeting on April 14, 2004, are an accurate record of the proceedings for that meeting. Graham Leitch, Date Plant License Renewal Subcommittee Chairman

CERTIFIED 6/10/04 By Graham Leitch Issued: 6/02/04 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MINUTES OF ACRS PLANT LICENSE RENEWAL SUBCOMMITTEE MEETING ON DRESDEN AND QUAD CITIES NUCLEAR PLANTS APRIL 14, 2004 ROCKVILLE, MARYLAND On April 14, 2004, the Plant License Renewal Subcommittee held a meeting in Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to review and discuss the Dresden and Quad Cities License Renewal Application and related Safety. Evaluation Report (SER) with Open Items. 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. Marvin Sykes was the Designated Federal Official for this meeting. The meeting was convened at 8:30 a.m. and . adjourned at 3:55 p.m. on April 14, 2004. ATTENDEES: ACRS MEMBERS/STAFF Graham Leitch, Chairman Stephen Rosen, Member Mario Sonaca, Member Peter Ford, Member George Apostolakis, Member Tom Kress, Member Marvin Sykes, ACRS Staff John Barton, Consultant NRC STAFF/PRESENTERS P.T. Kuo, NRR S. Lee, NRR T. Kim, f\\lRR K. Corp, NRR Greg Galletti, NRR B. Elliot, NRR Carol Lauron, NRR Laura Kozak, Region III Antony Vegel, Rill Stephen Hoffman, NRR Larry Rossbach, NRR Tilda Liu, NRR Amar Pal, NRR OTHER ATTENDEES Wiliam Bohlke, Exelon Fred Polaski, Exelon Mark Kluge, Exelon Jaryam Patel, Exelon Paul Doverspike, Exelon John Nosko, Exelon Sill Porter, Exelon David Tubbs, Mid-American Energy Keith Jury, Exelon Elliott Flick, Exelon Jim Meister, Exelon Michael Hayse, Exelon The presentation slides and handouts used during the meeting and a complete list of attendees is attached to the Office Copy of the meeting minutes. The presentation to the Subcommittee is summarized below.

Opening Remarks (Subcommittee Chair/Designee) Mr. Graham Leitch, Chairman of the Subcommittee on Plant License Renewal convened the meeting. After a few introductory remarks, Mr. Leitch stated that the purpose of the meeting was to review the Exelon Generating Company (Exelon) application and the related Safety Evaluation Report (SER) with Open Items for Dresden, Units 2 and 3, and Quad Cities, Units 1 and 2. Mr. Leitch called upon Mr. Samson Lee of the Office of Nuclear Reactor Regulation (NRR) to begin the discussions. Purpose and Introduction Samson Lee provided brief introductory remarks for the staff and introduced Mr. Bill Bohlke, Exelon Senior Vice President to begin the discussion. Presentation by Exelon Generating Company (Exelon) Mr. Bohlke greeted the committee, introduced the accompanying members of the Exelon staff and summarized the key elements of his presentation which included a plant overviews and differences, operating performance history, and recent operating experience. By letter dated January 3,2003, Exelon submitted its application to the NRC for renewal of the Dresden and Quad Cities operating licenses for up to an additional 20 years. The current operating licenses for Dresden, Units 2 and 3 expire on December 22,2009 and January 12, 2011, respectively. The current licenses for both Quad Cities plants expire on December 14, 2012. Plant Descriptions and Notable Design Differences Mr. Bohlke explained that the Dresden Nuclear Power Station is located in Grundy County, Illinois, and the Quad Cities Nuclear Power Station is located in Rock Island County, Illinois. All four plants are BWR-3's designed and supplied by GE Nuclear Energy with 251 inch vessels. The primary containment of each unit is of the Mark 1 design that consists of a drywell, a suppression chamber in the shape of a torus and a connecting vent system between the drywell and the suppression chamber. Each unit is authorized to operate at a steady state reactor power level not to exceed 2957 megawatts-thermal or approximately 850 megawatts-electric. Exelon is the sole owner of all four plants and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility. Dresden Units, 2 and 3 share the site and surrounding area with Unit 1, a dual-cycle boiling water reactor owned by Exelon that has been placed in a safe storage condition (SAFSTOR) until Units 2 and 3 are ready for decommissioning. Unit 1 systems, structures, and components (SSCs) which support the operation of Units 2 and 3 are included in the scope of this application and these components are expected to be adequately managed so that the intended functions will be maintained consistent with the current licensing basis throughout the period of extended operation. The Dresden units were designed with isolation condensers for core isolation cooling rather than the typical reactor core isolation cooling systems found at other BWRs. The Dresden units also have a separate shutdown cooling system rather than the more typical arrangement in which shutdown cooling is achieved as an operational mode of the residual heat removal system. Both Dresden and Quad Cities were approved for an extended power uprate to a new licensed power level of 2957 MWt. This increased power output by 17% at Dresden and 17.8% at Quad Cities. However, shortly after operating at the new power level, Quad Cities Unit 2 experienced unexpectedly high moisture carryover which required a plant shutdown to investigate. The applicant identified damage to the steam dryer that was repaired and the unit was returned to

service. Similar damage was identified in Unit 1 and again in Unit 2. The applicant has since chosen to operate the Quad Cities plants at pre-EPU power levels until more information can be gathered on the possible cause for the dryer damage. Mr. Bohlke concluded his portion of the presentation and introduced Mr, Fred Polaski of Exelon to discuss other major equipment replacement and repairs that had been completed in accordance with existing aging management programs. Major Equipment Replacement and Repairs Mr. Polaski discussed the plant's operating history and described a few major projects completed at the plant focusing mainly on the recent extended power uprates and associated equipment upgrades at both plants. The changes included installation of new high pressure turbine rotors and replacement of three main power transformers. Mr. Polaski briefly discussed the recirculation piping replacement at Dresden Unit 3, core shrouds repairs at both plants, and the introduction of hydrogen water chemistry and zinc injection to mitigate Intergranular stress-corrosion cracking at both plants. Mr. Polaski also discussed Exelon's Long Term Asset Management Program. He noted that the asset management plan is already in place for all Exelon nuclear plants and is updated annually. According to MR. Polaski, the plan factors into Exelon's long range budget planning activities and complements routine Preventive Maintenance and Performance Centered Maintenance Programs. Mr. Polaski concluded his portion of the presentation and introduced Mr. Stachniak of Exelon to discuss the applicants scoping and screening of plant SSCs. Unique Scoping Topics Mr. Stachniak discussed Dresden Unit 2 and Unit 3 Fire Protection System scoping. He noted that those portions of the Unit 1 system that are in the scope of the Maintenance Rule Program were included in the scope of license renewal for Units 2 and 3. He also discussed the scoping of non-safety-related piping. Mr. Stachniak noted that the applicant had expanded their initial scoping decisions to include all non-safety related piping and components attached to safety-related piping up to the first two supports in each orthogonal direction. Mr. Stachniak also discussed consistency of the exisitng programs with those referenced in the GALL report. HE explained that 38 of 47 agining management programs were related to GALL Le., 18 consistent and 20 consistent with exceptions. All exceptions contained alternative aging management activities that have been accepted by NRC. According to Mr. Stachniak, the applicant had provided responses to several RAls associated with open items included in the SEA. Mr. Stachniak stated that 1 item had been resolved and 4 were still being reviewed by the staff. Of the 16 confirmatory items listed in the SER, 15 had been resolved and 1 remained under review. He also noted that all technical issues identified during the NRC inspections and audits had been resolved, however, a followup inspection is necessary to confirm the adequacy of the action tracking system for license renewal commitments. NRC Staff Discussion of the Dresden-Quad Cities SER

Mr. T. J. Kim, the project manager, and Kimberley Corp of NRR were introduced to discuss the license renewal activities and the Draft SER for Dresden and Quad Cities. The key points of their presentation were: Overview Mr. Kim began by providing an overview of the Dresden Quad Cities application and summarized the current status of the license renewal review process. He noted that the SER included 5 open items and 16 confirmatory items. Inspections and Audits Laura Kozak, Region III, discussed the results of the inspections focused on Scoping and Screening and Aging Management Program reviews that were conducted by NRC staff. The inspections were implemented in accordance with Inspection Procedure IP 7002 to determine whether the applicant has included all appropriate structures, systems, and commodities in the scope of license renewal and to determine whether the existing aging management programs are adequately managing current age related degradation as required by 10CFR 54. Mrs. Kozak informed the ACRS that MR. Caudle Julian, Region II provided technical support to Region III since this was the first license renewal application to be submitted by Region III licensees. She also stated that staff had identified a few items that appeared to have been omitted from scope but once these issues were brought to the attention of the licensee, they were promptly resolved to the satisfaction of the inspection staff. She stated that the existing aging management programs (AMPs) were working well and materiel condition of the plant has been adequately maintained. She noted that the applicant's documentation of existing AMPs were of good quality. The staff has scheduled a followup on-site inspection to confirm that the applicant had established an appropriate commitment action tracking program. Overall, the staff concluded that the applicant's scoping and screening approach had successfUlly identified equipment and structures needing aging management review and that the eXisting aging management programs (AMPs) met the requirements of 10 CFR 54. An audit of AMPs was conducted by NRR's License Renewal Branch with contractor support from Argonne and Brookhaven National Laboratories, to confirm the applicants assertions that the AMPs were consistent with GALL. They reviewed all attributes of the AMPs and concluded that the AMPS were, indeed, consistent with GALL. Because of current staff concerns associated with steam dryer cracking at the Quad Cities facility, the staff and applicant discussed the possibility of additional license conditions that may be necessary to ensure that apprpriate procedures and programs are developed to monitor the new and unexpected steam dryer aging effects. Time Limited Aging Analyses (TLAAs) Kimberley Corp discussed the staff's evaluation of the applicants use of Time Limited Aging Analyses. She noted that the remaining 5 open items identified in the SER were associated with Reactor Vessel and Internals Neutron Embrittlement. According to Mrs. Corp, our items had been resolved since issuance of the SER and the remaining item was still under review. She also noted that for PTS (heatup/cooldown), the applicant will be required to submit revised P-T curves for the period of extended operation and update the Technical Specifications in accordance with Appendix G and H of 10 CFR 50. She concluded by stating that applicant had identified the appropriate TLAAs and has demonstrated the TLAAs will remain valid for the

period of extended operation or the aging effects will be adequately managed for the period of extended operation. Mr. Kim concluded the staff's presentation by stating that the pending resolution of the 5 open and 16 confirmatory items, the applicant has met the requirements for license renewal, as required by 10 CFR 54.29 and 10 CFR Part 51. Member Comments In general, the Subcommittee thought the application was well organized and adhered to the GALL format. However, there were several issued raised which required further evaluation by the staff. These issues were primarily focused on recent operating experience with steam dryers and other internal components at BWR plants. They are included in the listing below: Member Leitch A tornado tore several panels off the reactor building because the panels did not function properly. They were either installed improperly or not maintained. Was this an aging management issue. If so, why is it not in scope for structures? Page 248 of the Draft SER, states "The steam dryers are not in scope, because loose parts will not interfere with the ability to isolate the main steam line." However, Mr. Terao of NRR stated that the staff is reVising that portion of the safety evaluation. What is the final resolution of this issue? The oscillation power monitor is not in scope (as mentioned in the LRA in Table 2.2-3). However, the application says "Scram trips generated by the oscillation power range monitor have not been enabled." This is not a valid reason for it not being in scope. It has to be either short-lived or active in order not to be in scope. On page 33 of the Scoping and Screening Inspection Report, it was documented that a diesel driven fire pump is necessary to support the operation of Units 2 and 3, but this pump is not in scope. Why? Consultant Barton The staff stated in the SER that Dresden has problems with its instrument air system. There are debris and corrosion products in the system. A proposed solution is a periodic blowdown program. What is the result of this plan and has the problem been solved? If not, what is the proposed long term solution? Is the problem due to a design issue or a problem with the system? The purpose of the instrument air system is to provide clear, dry air for instrumentation of valves so the plant operates properly. Also, what is the cause of this problem? In Section 2.3 of the LRA, for the Reactor Vessel CCW System, a tank is listed for Dresden only. Is there a tank in Quad Cities? Is it in scope? There was no mention of this issue in the SER nor were there any RAls. Please clarify. Member Wallis If the staff concludes that the the Dresden or Quad Cities steam dryers should be included in the scope of license renewal, why shouldn't the other plants coming in for license renewal also have steam dryers in scope? Are the steam dryers a unique issue or is it a generic issue?

Member Ford A clamping device was used to mitigate the cracking of the core shroud. The clamp was assumed to be a quick fix. However, it appears to have been approved as a long term remedy. How is the degradation going to be monitored? Has anyone on the staff been willing to accept the Rev. 2 (Water Chemistry Guidelines) applications? Has anyone done the risk analysis associated with having those relaxations apply for any station in the future? Member Rosen Is the reactor vessel fit for service for 60 years? Provide Charpy data on all the capsules and the calculation for each of them separately. Staff Commitments The staff committed to provide responses to the the issues requiring further before the full Committee review of the final SEA. Subcommittee Decisions and Follow-up Actions The Subcommittee will summarize the discussions to the full Committee during April 2004 ACRS meeting. Background Materials Provided to the Committee

1.

License Renewal Application for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, dated January 2003.

2.

Safety Evaluation Report with Open items Related to the License Renewal of the Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2, dated February 2004.)

3.

NRC-Region III Inspection Reports # 50-237/03-04; 50-249/03-04 ; 50-254/03-04; 50 265/03-04, dates July 28 through August 1, 2003, and aging management program inspection reports # 50-237/03-04; 50-249/03-04 ; 50-254/03-04; 50-265/03-04 dates September 29 through October 22, 2003. License Renewal Application for the A. E. Ginna Nuclear Power Plant, dated July 30, 2002. 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 A. 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).

UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555*0001 March 16, 2004 MEMORANDUM TO: Maggalean W. Weston, Acting Associate Director for Technical Support, ACRS/ACNW FROM: Bhagwat P. Jain, Senior Staff Engineer

SUBJECT:

FEDERAL REGISTER NOTICE REGARDING THE MEETING OF THE ACRS SUBCOMMITTEE ON PLANT LICENSE RENEWAL, APRIL 14, 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:

G. Leitch, ACRS M. Bonaca, ACRS J. Larkins, ACRS J. Szabo, aGe A. Bates, SECY D. Weaver, OEDO S. Burnell, OPA J. Dyer, NRR D. Matthews, NRR P. Kuo, NRR T. Kim, NRR PMNS Public Document Room

[7590-01-Pl NUCLEAR REGULATORY COMMISSION ADVISORY COMMITIEE 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 April 14, 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, April 14, 2004 -12:30 p.m. until 5:30 p.m. The purpose of this meeting is to review the license renewal application for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2, and the associated draft Safety Evaluation Report with open items prepared by the NRC staff. The Subcommittee will hear presentations by and hold discussions with representatives of the NRC staff, Exelon Generation Company, 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. Bhagwat P. Jain (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. 1 ///..:)jv ;t~,/ / ;/// /7 /t)t 6'7,:( '~I~/**.-/.//k::C:t.--&'-n.._/ ,~{...~.._"_,-,*!.'*Z:'l//)A ~ ~,' ~'. Maggafean W. Weston, Acting ASSOCIate Director for Technical Support, ACRS/ACNW

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS PLANT LICENSE RENEWAL SUBCOMMITTEE MEETING DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 APRIL 14, 2004 ROCKVILLE, MARYLAND

  • PROPOSED SCHEDULE*

ACRS

Contact:

B.P. Jain (301-415-7270) Topics Presenters Time I. Opening Remarks G. Leitch, ACRS 12:30-12:35 p.m. II. Staff Introduction ...p. T. KUb, NRR 12:35-12:40 p.m. "S

  • I..1Ee;

'30 III. Exelon Generation Company W. Bohlke, F. Polaski 12:40-2:j)(rp.m. R. 5tachniak A. Background B. Operating experience/ Power Uprate and Steam dryer cracking C. Major Equipment Replacement/Repairs D. Uniqueness to Scoping and Screening Methodologies E. Any major exceptions to GALL F. Commitments/tracking B1<.~1t~

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  • IV Overview and Resolution T.J. Kim, NRR

~:Q62:2g p.ffl. of Open items, and RAls 2.:"~-.,: I~

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SER Chap. 2: Results of Scoping T.J. Kim, NRR ~ptrP.m. and Screening Methodologies, L. Kozak, Region III Inspections and ROP findings Open Items BREAK i:45=S.OO 1'.1 Ii. ~ 'i:z.o - '/:'I0f*ff. VI. SER Chap. 3: Aging Management T.J. Kim, NRR 3:00-4:l'erp.m. Programs and Review Results, AMP audit 1/: cfa... C{:fiCllI\\ ~ /5 VII. SER Chap. 4: Time Limited Aging ~NRR 4~5:.e(("p.m Analyses Overview ~. Cc>~P VIII Subcommittee Discussion 5:00-:5:30 p.m Adjourn 5:30 p.m NOTE: Presentation time should not exceed 50% of the time allocated for a specific item. The remaining 50% of the time is for Subcommittee questions. Limit total presentation slides to about 50

ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SUBCOMMITTEE MEETING ON PLANT LICENSE RENEWAL April 14. 2004 Date NRC STAFF SIGN IN FOR ACRS MEETING PLEASE PRINT NAME NRC ORGANIZATION A.\\/L 1r=-~-=-l R.~L.D-PI, DRS ! S ~c

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Exelon'M Nuclear Dresden Nuclear Power Station Quad Cities Nuclear Power Station Presentation to Advisory Committee on Reactor Safeguards Subcommittee on License Renewal Exelon Nuclear April 14, 2004 1

Exelon," Nuclear Agenda

  • Background Information - Bohlke
  • Operating Experience / Extended Power Uprate - Bohlke
  • Major Equipment Replacements / Repairs - Polaski
  • Unique Scoping Topics - Stachniak
  • Major Exceptions to GALL - Stachniak
  • Commitment Management / Tracking - Polaski 2

Exelon,. Nuclear Application Background

  • January 2003 - Application submitted
  • November 2003-draft Quad Cities Supplemental Environmental Impact Statement issued
  • December 2003 - draft Dresden Supplemental Environmental Impact Statement issued
  • February 2004 - draft Safety Evaluation Report issued 3

Exelon,. Nuclear Plant Description General Electric BWR-3 with Mark I containment Fresh water cooling Licensed power level 2957 MWth Current Dresden licenses expire in 2009, 2011 Current Quad Cities licenses expire in 2012 Extended Power Uprates completed in 2001, 2002 4

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Exelon," Nuclear Significant Plant Differences Dresden Quad Cities Core isolation cooling Isolation Condenser System Reactor Core Isolation Cooling (RCIC) System Residual heat removal Shutdown Cooling System Low Pressure Coolant Injection System Residual Heat Removal (RHR) System Containment Cooling Service Water System RHR Service Water System Appendix R shutdown High Pressure Cooling Injection (HPCI) System Isolation Condenser System HPCI System RCIC System Safe Shutdown Make-up Pump Circulating water Cooling lake and supplemental cooling towers (limited open cycle cooling in summer months) Open cycle cooling using Mississippi River 7

Exelon," Nuclear Performance Indicators

  • All Reactor Oversight Performance Indicators for both plants are Green except for Dresden Unit 3 HPCI unavailability, which is White 8

Exelon'M Nuclear Plant Performance - 5 years Dresden 1999 2000 2001 2002 2003 -,,-" ',.-.-, *." *..._,.",......~"'"," 94.7**_**90:"*f~*_*"*** ..-92~*9-j"--***96.*31 Capacity Factor ~"'.'.~_ ," ~",.,.",..,-~: ', *.'--'"'~, .* ~",p,,_._ _.,._.~,~_, .""'',-"._.....,....._~_ ,..,.",""'_._.;.,.....,"-A.,_<.""',"'""_'" **,,_~~ Refueling Outages 1 l' 11 1! -*"", __..__4,'_*k~**._*...__.~",~ --"""--,.,,,,,~_,,_,-"'~_+_.~ -,..",.~_.."""._-,--,".~.......,~_,.J Refueling Outage length - days 17 19 1 1~ 281

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Exelon,. Nuclear Major Plant Modifications for EPU

  • New high-pressure turbine rotors
  • Condensate demineralizer system changes
  • prefilter system at Dresden
  • new demineralizer at Quad Cities
  • Isolated phase bus duct cooling capacity increase
  • Feedwater heater shell section replacements
  • Steam dryer perforated plates (to reduce moisture carryover)
  • Piping supports and related structural reinforcements
  • Miscellaneous instrument/control setpoint changes
  • Drywell structural steel reinforcements 10

Exelon," Nuclear Dresden Extended Power Uprate Unit !mPlementation Date Post EPU Capacity Factor Dresden 2 December 2001 94.0% Dresden 3 November 2002 91.6% EPU modifications increased licensed power by 17% Post EPU Operating Experience High frequency vibration on main turbine control valve EHC pressure switch caused half scram during Unit 2 startup One Unit 2 RFP suction relief valve weld failed due to vibration during startup Feedwater sample probe failure Structural improvements to dryers resulting from Quad Cities lessons learned installed on both units Dresden 2 continuous run 690 days 11

Exelon," Nuclear Quad Cities Extended Power Uprate Unit Implementation Date Post EPU Capacity Factor Quad Cities 2 March 2002 92.3% Quad Cities 1 December 2002 89.5% EPU modifications increased licensed power by 17.8%

  • Post EPU Operating Experience Main steam low point drain line failed following Unit 2 startup March 2002 Unit 2 shutdown in July 2002 and June 2003 to repair degraded dryer Unit 1 shutdown in November 2003 to repair degraded dryer Vibration related damage discovered on 1 ERV during Nov 2003 outage Unit 2 dryer damage discovered in March 2004 during refueling outage 12

Exelon,. Nuclear Major Equipment Replacements

  • Reactor water cleanup system piping replacement
  • RHR service water system piping replacement (Quad Cities only)
  • Reactor recirculation piping replacement (Dresden Unit 3 only)
  • Main power transformer replacement
  • Underground fire header replacement (Dresden only)
  • Core shroud repairs
  • Hydrogen water chemistry, zinc injection, and noble metals injection applied 13

Exelon," Nuclear Long Term Asset Management

  • Exelon has a long term asset management plan in place

- Updated yearly - Includes all Exelon Nuclear plants - Factors into long range budget planning - Complements our routine Preventive Maintenance and Performance Centered Maintenance - Provides basis for long term replacements 14

Exelon," Nuclear Examples of Equipment ReplacementslRefurbishments

  • Main generator rewind
  • Main condenser tube replacements
  • Plant process computer upgrades
  • LP turbine rotor replacements
  • Large motor replacements
  • I&C system upgrades to digital 15

Exelon,. Nuclear Dresden Fire Protection Scoping

  • The Dresden Unit 2/3 fire protection system includes portions of the Dresden Unit 1 fire protection system, which are in the scope of the Maintenance Rule program. These include:

- Underground fire protection supply header - Diesel fire pump and screen wash pumps - Unit 1 Cribhouse Building (houses the fire pump)

  • No other Unit 1 equipment is used to support Units 2 and 3 16

Exelon,. Nuclear Scoping ofNon-Safety Related Piping

  • Non-safety related pipe attached to safety related piping Initial scoping included all attached non-safety related pipe and components up to the first support in each orthogonal direction

- Scoping boundaries were later expanded to include pipe and components up to the first two supports in each orthogonal direction

  • Spatial interaction ofnon-safety related piping Initial scoping excluded non-safety related piping systems separated from safety equipment by more than 20 feet The physical separation criterion has been abandoned. Exelon is currently assessing the impact that this methodology change will have on the original scoping results Some previously excluded non-safety related systems have been brought into scope 17

Exelon,. Nuclear Exceptions to GALL

  • 38 of 47 aging management programs are related to GALL
  • 18 programs are consistent with GALL
  • 20 programs are consistent with exceptions
  • All exceptions contain alternative aging management activities acceptable to the NRC
  • Examples of exceptions:

- BWR Penetration Inspection - Fuel Oil Chemistry - Inspection of Overhead Heavy Load Handling Systems 18

Exelon'M Nuclear Below Grade Environment Parameter Aggressive Dresden Quad limit Cities pH < 5.5 7-9 6.9-7.9 Chlorides > 500 ppm 5 -30ppm < 29 ppm Sulfates > 1500 ppm 10 - 30 ppm < 24 ppm 19

Exelon," Nuclear NRC Review Status

  • Draft SER status:

- 5 open items - 1 resolved and 4 under review - 16 confirmatory items - 15 resolved and 1 under review - Closure documentation has been provided to the NRC

  • Inspection and Audit status

- All technical issues have been resolved - A follow-up NRC regional inspection scheduled in May will confirm the adequacy of the action tracking system for license renewal commitments 20

Exelon," Nuclear Commitment Management

  • License renewal commitments are documented in the Exelon commitment tracking system
  • The commitment tracking system is controlled by the Exelon commitment management process described in LS-AA-110, "Commitment Management"
  • Exelon commitment management process is consistent with NEI 99-04, Rev 1, "Guidelines for Managing NRC Commitment Changes", endorsed by the NRC
  • Changes to a commitment require a formal review and evaluation
  • Changes in commitments are provided to the NRC along with the Updated Final Safety Analysis Report revisions 21

Exelon'M Nuclear License Renewal Commitments

  • A unique commitment tracking number has been created for each Aging Management Program and a tracking file has been created for each procedure, work request, and periodic surveillance credited for license renewal
  • Aging management programs are comprised of implementing procedures, work requests, and periodic surveillances that implement activities of a program
  • Steps contained in procedures, work requests, and periodic surveillances that implement license renewal commitments are annotated as license renewal commitments and are tracked on a station specific basis 22

Exelon,. Nuclear Commitment Tracking File Structure Quad Cities License Renewal Master Action Tracking File ATI # 101562 ~ ~ ~ ~ ~ Water Chemistry Selective Leaching Buried Piping and Tanks Program Action Tracking Program Action Tracking Program Action Tracking File File File ATI# 101562.02 ATI# 101562.33 ATI# 101562.34 ~ QCMPM-6600-03 activities with 12 activities with 18 Procedure Action Procedure Action ATI files ATI files Tracking File Tracking File ATI# 101562.34.01 ATI# 101562.34.11 12 implementing 18 implementing SA-AA-117 23 Examples on following slides

Example - Procedure Annotation Exelon,. The following step was annotated as license renewal commitments in Exelon procedure, SA-AA-117, "Excavation, Trenching, and Shoring" 4.7 Exposing Underground Piping, Structural Steel or Concrete During Excavation (CM-2, CM-3, CM-4, CM-5, CM-6) 4.7.1 If underground piping, structural steel or concrete is exposed during excavation, Then PERFORM the following:

1.

NOTIFY Engineering to inspect piping, structural steel or concrete for evidence of coating degradation or corrosion, concrete cracking or spalling, signs of corrosion in steel.

2.

Engineering INSPECT piping or structural steel for evidence of coating degradation (if coated pipe or steel components) or corrosion (if uncoated metal pipe or steel components). Engineering INSPECT concrete components for cracking or spalling. RECORD results of inspections in ACTION TRACKING and record the Action Tracking Number In the Comments Section ofthe Excavation Permit. Nuclear

References:

6.1. Commitments 6.1.1 Limerick (CM-l) A/R# A0789662, (LGS) LER 1-93-011 (T02973 6.1.2 Peach Bottom (CM-2) PBAPS License Renewal Outdoor, Buried, and Submerged Component Inspection Activities (T04329) (Step 4.7) 6.1.3 Dresden (CM-3) Action Tracking Item AR 00101522.34.15, License Renewal Aging Management - NUREG - 1801 "Generic Aging Lessons (GALL) Report, Section XI.M34 Buried Piping and Tanks Inspections. (Step 4.7) (CM-6) Action Tracking Item AR 00101522.40.12, License Renewal Aging Management - NUREG - 1801 "Generic Aging Lessons (GALL) Report, Section XI.S6 Structures Monitoring Program. (Step 4.7) 6.1.4 Quad Cities (CM-4) Action Tracking Item AR 00101562.34.11, License Renewal Aging Management - NUREG - 1801 "Generic Aging Lessons (GALL) Report, Section XI.M34 Buried Piping and Tanks Inspections. (Step 4.7) 24

Procedure Action Tracking File Exelon," Nuclear ATI # 101562.34.11-Quad Cities The following commitment(s) was/were made in the application for the renewed Operating License per 10 CFR 54 and will need to be carried forward into future revisions or subsequent procedures superceding SA-AA-l17, "Excavation, Trenching, and Shoring." Note: The commitment cannot be changed without prior approval from the appropriate individual(s) associated with aging management (License Renewal) compliance. Any deletions or changes to this commitment shall be made in accordance with LS-AA-llO, Commitment Management. Commitment: Periodic inspections of buried piping and tanks to manage the effects ofcorrosion are performed when the opportunity arises. Inspections are performed utilizing procedures SA-AA-117, Excavation, Trenching, and Shoring, and ER-MW-450, Structures Monitoring, whenever said components are excavated during station yard area maintenance or general yard excavations to detect coating or base metal degradation Basis for Commitment.:. This procedure is credited in AMR M08, Appendix IV XI.M34 (Elements 3, 4, 5, 6, 7).

References:

Letter to Nuclear Regulatory Commission from Jefferey A, Benjamin, Quad Cities Nuclear Power Station, Units 1 and 2, Dresden Nuclear Power Station, Units 2 and 3, Application for Renewed Operating Licenses, dated January 3, 2003. License Renewal Application (LRA), Appendix A, Section A,1.25 and Appendix B, Section B.l.25 Parent Action Tracking Number 101562.34 25

Program Action Tracking File Exelon," Action Tracking Number Nuclear 101562.34 - Quad Cities ATI # 101562.34 B.1.25 Buried Pipina and Tanks Inspection Introduction Appendix A and B of the Dresden/Quad Cities License Renewal Application (D/QC LRA) identify all activities that are credited for aging management of passive, long-lived components and structures within the scope of license renewal. Specifically, section A.1.25 of Appendix A a~ section B.1.25 of AppendiX B describe aging management activiti > aging management activities credited for components credited for components exposed to soil and/or groundwater. This action tracking file documents those activities credited as part of the exposed to soil and/or groundwater. Buried Piping and Tanks Inspection aging management program (AMP) that has been credited for the aging management of component external surfaces exposed to a soil and groundwater environment. The aging mechanisms and aging effects associated with those component external surfaces falling within the scope of license renewal exposed to a soil and groundwater environment is contained in Aging Management Report (AMR), MOB, External Environments. This AMR along with the license renewal application can be found in the electronic data management system (EDMS) for reference. The scope of components included in the Buried Piping and Tanks Inspection AMP activities include buried ferrous portions of the diesel fuel oil systems and storage tanks, fire protection system piping, circulating water (ultimate heat sink) system

piping, condensate/CCST system
piping, and

--;7 buried ferrous portions of the demineralized water system piping. It also includes buried mechanical joint rubber gaskets contained in the fire protection piping. The ferrouS diesel fuel oil systems and components are constructed from the materials included in the following aging mechanism listing, and are subject to a "Loss of Material" aging effect. Rubber storage tanks, fire protection mechanical joint materials are subject to a "Change in Material Properties" aging effect. system piping, circulating water Material Aging Mechanism (ultimate heat sink) system Carbon steel General corrosion, pitting corrosion, crevice corrosion piping, condensate/CCST and MIG system piping, and Cast iron General corrosion, pitting corrosion, crevice corrosion, MIC and selective leaching demineralized water system (B.1.24, Selective Leaching of Materials, is utilized in conjunction with 8.1.25 to address piping. It also includes buried selective leaching) mechanical joint rubber gaskets Ductile iron General corrosion, pitting corrosion, crevice corrosion and MIC contained in the fire protection Stainless steel Pitting corrosion, crevice corrosion piping. and MIC Rubber Elastomer degradation and loss of resiliency 26

Program Action Tracking File Exelon'M At Quad Cities, yard excavation activities to date have not uncovered buried piping or tanks due to their locations and depths of the specific routings. Since inspections during periodic uncovering of buried components cannot solely be relied upon for providing effective degradation aging management, other inspection and testing activity license renewal commitments have been credited. The Buried Piping and Tanks Inspection AMP activities provide for managing the "Loss of Material" (for both ferrous and asbestos concrete) and the "Change in Material Properties" aging effects through the use of piping and component coatings and wrappings. periodic inspections,

7 and pressure testing.

Commitments Exelon has committed to implement a Buried Piping and Tanks Inspection AMP that is consistent with the program described in Section XI.M34 of NUREG 1801, Generic Aging Lessons Learned Report, dated April 2001 with the following one exception: NUREG-1801 indicates that buried piping and tanks are inspected when they are excavated during maintenance. NUREG-1801 also indicates that because the inspection frequency is plant-specific and also depends on plant operating experience, the inspection frequency requires I i I further evaluation. ~ns of Quad Cities buried components uncovered due to main nanca cannot be relied upon as the sale method for providing effective aging management because uncovering of piping or tanks during maintenance is not likely. Therefore, the Quad Cities AMP as enhanced includes the use of piping and component coatings and wrappings, periodic pressure testing, buried tank leakage checks, inspections of buried tank internal surfaces, and inspections of the ground above buried tanks and piping. It also includes a one-time internal UT inspection of one buried 51eel tank, and a one-time visual inspection of the external surface of a buried piping section. The following Buried Piping and Tanks Inspection AMP activities, sorted by coatings and wrappings, periodic inspections, and pressure testing. comprise the commitments for this AMP: Coatings and Wrappings Coatings and wrappings on buried ferrous piping and tanks perform a mitigative function by preventing metal contact with the aggressive soil/groundwater. All buried carbon steel piping at Quad Cities was in the past, and will continue to be, coated prior to installation or after maintenance. This determination is based upon two facts: 1) The original and current installation specifications applicable for Quad Cities buried piping (R-2329 and R-4411, Section1501.10) require an external coating on buried carbon steel piping, and 2) There has been no failure history at Quad Cities of buried carbon steel piping attributed to the absence of an external coating on the piping. Nuclear managing the "Loss of Material" (for both ferrous and asbestos concrete) and the "Change in Material Properties" aging effects through the use of piping and component coatings and wrappings, periodic inspections, and pressure testing. Coatings and Wrappings 27

Program Action Tracking File Exelon,. Periodic Inspections 'Periodic inspections of buried piping and tanks to manage the effects of corrosion are performed when the opportunity arises. Inspections are performed utilizing procedures SA AA-117, Excavation, Trenching, and Shoring, and ER-MW 450, Structures Monitoring, whenever said components are excavated during station yard area maintenance or general yard excavations to detect coating or base metal degradation (AT Nos. 101562.34.11, 101562.34.13). 'Periodic inspections of the inside of buried tanks will be performed. Quad Cities procedure QCMPM 6600-03, Diesel Oil storage Tank Cleaning, and predefines 15839-02, 23085 03 direct the cleaning and visual inspection of the inside surfaces of the fuel oil storage tanks. These visual inspections will also detect thru-wall degradation penetrating from the exterior surfaces of the tanks (AT Nos. 101562.34.01,101562.34.08,101562.34.10). "A one-time UT inspection of the internals of one buried fuel oil storage tank to detect loss of material will be performed utilizing work order 592920. In addition to verifying the effectiveness of the current fuel oil chemistry control program, it will also identify wall thinning caused by a lOSS of material originating from the exterior surfaces of the tan1"--'....LlO<--f 101562.34.06). of the ground above buried commodities are performed, utilizing procedure ER-MW-450, Structures Monitoring, for indications of below-ground seepage or ground settling (AT No. 101562.34.13). A one-lime inspection of a section of buried ductile iron fire protection piping, Including a mechanical joint, will be performed, if determined to be necessary (see NOTE below). The inspection will examine the piping surface for coating and base metal degradation, and the mechanical joint for evidence of minor leakage or other indications of a lack of joint integrity (AT Nos. 101562.34.05, 101562.34.14). NOTE This inspection is only required if excavation inspections as specified in AT Nos. 101562.34.11,101562.34.13 above do not occur prior to 12/14/10 (Two years priorlo the expiration of both Quad Cities Units 1 & 2 current term licenses). Pressure Testing Periodic pressure testing of buried cooling water piping is accomplished utilizing lSI pressure testing of Class 3 buried cooling water piping, performed in accordance with ER-AA-330 001, Section XI Pressure Testing. The rate of pressure loss or change-in-flow between the ends of the buried components is utilized as the VT-2 visual examination for the buried piping and components (AT No. 101562.34.12). Nuclear --;;;r Periodic Inspections ~ Pressure Testing 28

ACRS License Renewal Subcommittee Dresden and Quad Cities Nuclear Power Station License Renewal Application Safety Evaluation Report with Open Items April 14, 2004 TJ Kim Kimberley Corp Senior Project Manager Project Manager

Overview Exelon submitted its application for Dresden and Quad Cities by letter dated January 3, 2003 General Electric BWR/type 3 reactor,. Mark I containment generates 2957 megawatt thermal at both Dresden and Quad Cities generates 850 and 855 megawatt electrical at Dresden and Quad Cities, respectively Location of Stations Dresden is on the Illinois and Kankakee Rivers in Grundy County, Illinois. Quad Cities is on the Mississippi River 3 miles north of Cordova, Rock Island County, Illinois. April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 2

Overview continued Current licenses expire Dresden Unit 2 - December 22, 2009 Dresden Unit 3 - January 12, 2011 Quad Cities Units 1 & 2-December 14, 2012 Request license renewal through December 22, 2029 for Dresden Unit 2 January 12, 2031 for Dresden Unit 3 December 14, 2032 for Quad Cities Units 1 &2 Application implemented the generic aging lessons learned (GALL) process April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 3

NRC Review Process 5 Open Items (1 resolved, 3 under review, 1 waiting applicant response) 16 Confirmatory Items (15 resolved, 1 under review) Brought into scope and subjected to AMR Several new systems and components 4 new AMPs April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 4

NRC Audits and Inspections Scoping and Screening Methodology Audit May 19-23, 2003 Scoping and Screening Inspection July 28 -- August 1, 2003 (Exelon Headquarters) Aging Management Program Audit October 7-8, 2003 Aging Management Review Inspection September 29 - October 3,2003 (Dresden) October 14-17, 2003 (Quad Cities) Optional Third Inspection March 15-17, 2004 April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 5

Section 2 - Structures & Components Subject to an AMR 2.1 - Seoping and Screening Methodology Describes methodology used to identify SSCs that are within the scope of the license renewal rule and subject to an AMR Staff audit determined that the applicant's methodology satisfies the rule 2 Open Items (1 waiting applicant response, 1 under staff review) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 6

Open Item 01-2.1-1 The staff identified that there was not sufficient basis for limiting consideration of fluid spray interactions to only those non-safety related SSCs located within 20 ft of an active safety related SSCs. Resolution - The applicant has decided not to take the 20 ft exception and has scoped in all systems and components. Applicant is still evaluating the systems and components to be scoped in with new methodology. April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 7

Open Item 01-50-237/03-04-01, 50-249/03-04-01, 50 254/03-04-01, and 50-266/03-04-01 The staff identified the need for clarification of the definition of an equivalent anchor as used to determine the extent of non-safety related attached to safety related systems that was included within the scope of license renewal. Resolution - Currently under review by NRR and Rill staff. April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 8

J Section 2 - Structures & Components Subject to an AMR continued ~~cE," Section 2.2 - Plant Level Scoping Results Staff reviewed Section 2.2 to determine if any systems, structures or commodities required to be within scope <were omitted. No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 9

r Section 2 - Structures & Components Subject to an AMR continue~ iX~,)i' f~:~1 Section 2.3 - Scoping and Screening of Mechanical Systems Includes the following systems: Reactor Vessel, Internals, and Reactor Coolant System Engineered Safety Features Systems Auxiliary Systems Steam and Power Conversion Systems No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 10

T Steam Dryers/EPU Steam dryers are generally not in scope for license renewal according to the rule. Staff has determined that Quad Cities and Dresden are unique among other operating SWRs. O* April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 11

Section 2 - Structures &Components Subject to an AMR continued Section 2.4 - Structures and Structural Components Describes structures and structural components Containment Other Structures (15) No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 12

Section 2 - Structures & Components Subject to an AMR continue~__,_,,",w__ $:~=~~:;~L~~~~~~~~~':,~~:~."*,~:',~::'""':<;"""""*~',>'v"""""'h:";"v,,,g~ Section 2.5 - Electrical and Instrumentation and Controls These components were evaluated on a plant-wide basis utilizing the "spaces" approach 3 commodity groups No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 13

Seoping and SereeningSummary Scoping and screening methodology is adequately described and justified in the LRA and satisfies the requirements of 10 CFR 54.21 (a)(2). Scoping and screening review results found that the SSCs within the scope of license renewal have been identified, as required by 10 CFR 54.4(a) and those subject to an AM R have been identified, as required by 10 CFR 54.21 (a)(1). April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 14

License Renewal Inspections Highlights: Scoping and Screening Inspection Aging Management Review Inspection Plant ROP April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 15

License Renewal Inspection oTt! Program Implementation_,,0'__"'" License Renewal Manual Chapter-MC2516 License Renewal Inspection Procedure-IP71 002 Site-specific inspection plan for each applicant Scheduled to support NRR's review Resources - regional inspection personnel April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 16

License Renewal Inspections Scoping and Screening Inspection Objective: to confirm that the applicant has included all appropriate SSCs in the scope of license renewal as requjred by the rule One week in length Conducted July 28 - August 1,2003 at Exelon Headquarters April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 17

License Renewal Inspections continued Scoping and Screening Inspection Results Scoping and screening process was successful in identifying those SSCs needing aging management review April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 18

License Renewal Inspections continued Aging Management Review Inspection Objective: to confirm that existing AMPs are managing current age related degradation Two weeks in length Conducted September 29 - October 3, 2003 at Dresden and October 14-17, 2003 at Quad Cities April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 19

License Renewal Inspections continued AMR Inspection Results Material condition of plant was being adequately maintained. No significant aging related issues were identified. Documentation was of good quality, detailed, and understandable. Third Optional Inspection conducted March 16 17, 2004. An additional follow Lpinspection will be conducted in May/June 2004 April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 20

Dresden 2 40/2003 Performance Summa Reactor Radiation Safeguards Safety Safety Initiating Mitigating Emergency Eventa Syatem.s P reparedneaa Performance Indicators L~st Modified:,J~nlJ~/y 23, 2004 April 14, 2004 ACRS Subcommittee Meeting 21 Dresden and Quad Cities

Dresden 3 40/2003 Performance Summa Reactor Radiation Safeguards Safety Safety [ I ~ i i Occupational Public Initiating Mitigating Barrier Emergency Physical Radiation Radiation Events ~ Systems Integrity Preparedness Protection Safety Safety Performance Indicators High Pressure Injection System Unavailability <<lV) Last Modified: Janl.Jary 23,2004 April 14, 2004 ACRS Subcommittee Meeting 22 Dresden and Quad Cities

Quad Cities 1 4Q/2003 Performance Summa Reactor Radiation Sa'feguards Sa'fety Safety Initiating IWtigating Barrier Emergency Events Systems Integrity Preparedness Performance Indicators Last Modified: JantJary 23, 2004 April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 23

Quad Cities 2 4Q/2003 Performance Summa Reactor Radiation Safeguards Safety Safety ~ Initiating M Mitigating Barrier Emergency Events Systems r-- Integrity Preparedness Performance Indicators Last Modified: JanlJary 23,2004 April 14, 2004 ACRS Subcommittee Meeting 24 Dresden and Quad Cities

Section 3 - Aging Management Review GALL divides systems and structures into 6 broad system/structural groups 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) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 25

Aging Management Programs Aging Management Programs 47 AMPs credited for license renewal 18 common AMPs 29 system/structural group-specific AMPs 18 AMPs consistent with GALUconsistent with enhancements 20 AMPS consistent with GALL, with exceptions 9 AMPS non GALL 4 new AMPs added - 3 system specific and 1 common 1 Open Item and 5 Confirmatory Items (aU resolved) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 26

AMP Audit Date of audit - October 7-8,2003 Auditors - 4 Project managers from license renewal, 1 Regional inspector and 5 Contractors Concluded AMPS were consistent with GALL except: Three AMPs were revised by making enhancements to the programs for review by the technical staff. The staff found them acceptable. April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 27

I Section 3 - Aging Management Review continued Section 3.1 - Reactor Vessel, Internals and Reactor Coolant Systems 5 Confirmatory Items (4 resolved and 1 under review) Section 3.2 - Engineered Safety Features System No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 28

Section 3 - Aging Management Review continued Section 3.3 & 3.4 - Auxiliary Systems & Power Conversion Systems 1 Open (AMP Open Item) and 2 Confirmatory Items (all items resolved) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 29

Open Items One-Time Inspection - Auxiliary System: Plant Heating System 01-8.1.23-2 The staff identified that additional information needs to be provid,ed on the environmental conditions and the operating experience in order to justify the use of a one time inspection, or provide periodic inspections for these components Resolution - Staff has received applicable information and is incorporating into the final SER. April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 30

Open Items continued One-Time Inspection - Steam and Power Conversion: Main Steam 01-8.1.23-2 continued The staff identified that additional information needs to be provided to justify the use of a one-time inspection. Resolution - Staff has received applicable information and is incorporating into the final SER. April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 31

Section 3 - Aging Management Review continued Section 3.5 - Containment, Structures, and Component Supports Containment structure 15 other structures 1 Open Item (under review) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 32

Open Item ASM E Section XI, Subsection IWF 01-3.5.2.3.2-1 The staff id*entified that the existing IWF program is not consistent with GALL in that it does not include the inspection of Class MC supports Resolution - Curre.ntly under review by NRR staff April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 33

Aging Management of In-Scope Inaccessible Concrete Aggressive Limit Dresden Quad Cities pH < 5.5 7-9 6.9 - 7.9 Chlorides > 500 ppm 5 - 30 ppm < 29 ppm Sulfates > 1500 ppm 10 - 30 ppm I < 24 ppm Periodic testing to verify chemistry remains nOfl aggressive Below grade soil/water environment noR wessive April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 34

Section 3 - Aging Management Review continued Section 3.6 - Electrical and Instrumentation and Controls 3 Component commodity groups subject to AMR electrical cables and connections bus ducts high voltage transmission conductors and insulators No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 35

t Aging Management Review Summary ~:2~"""" ~ 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) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 36

Section 4 - Time-Limited Aging Analyses Reactor Vessel and Internals Neutron Embrittlement Metal Fatigue Environmental Qualification Loss of Prestress in Concrete Containment Tendons Fatigue of Primary Containment, Attached Piping and Components Other Plant-Specific TLAAS April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 37

Section 4 - TLAAs continued Section 4.2 - Reactor Vessel and Internals Neutron Embrittlement Seven analysis affected by irradiation embrittlement identified asTLAAs ~ Reactor Vessel USE Pressure-Temperature Limits 5 other neutron embrittlement related TLAAs 1 Open Item (under staff review) 4 Confirmatory Items (resolved) April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 38

~ Reactor Vessel Upper Shelf Energy (USE) Staff Calculated Staff Calculated USE (FT-LBS) USE (FT-LBS) Screening Criteria USE Dresden Quad Cities Reactor Vessel Beltline Material (FT-LBS) Unit 2 Unit 3 Unit 1 Unit 2 Limiting Beltline ~50 75 77 76 80 Plate Material Limiting Weld ~.35 (EMA)* 49 47 49 34**

  • EPRI Topical Report - 113596 demonstrated that welds with Charpy USE values of 35 ft-lbs can have margins of safety against fracture equivalent to those required by Appendix G, Section XI of the ASME Code; therefore acceptable.
    • Open Item - Plant specific equivalent margin analysis (EMA) is being prepared by the applicant for a weld with a Charpy USE less than 35 ft-Ibs.

April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 39

Pressure/Temperature Curves The applicant will submit P-T curves for the period of extended operation for approval before the current license expires Technical specificatio,ns will be updated as required by Appendix G of 10 CFR 50 April 14, 2004 ACRS Subcommittee Meeting-' Dresden and Quad Cities 40

,). Section 4 - TLAAs continued Section 4.3 - Metal Fatigue Reactor coolant system components at Dresden and Quad Cities designed to Class 1 of the ASME Code All components have projected cumulative usage factor (CUF) < 1.0 for the period of extended operation No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 41

~ Section 4 - TLAAs continued Section 4.4 - Environmental Qualification Applicant has adequately identified the TLAA for EO components Applicant's EO Program is consistent with GALL Staff concluded EO Program will continue to manage equipment in accordance with 10 CFR 50.49, and meets 10 CFR 54.21 (c)(1 )(i), (ii), and (iii) No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 42

Section 4 - TLAAs continued Section 4.6 - Fatigue of Primary Containment, Attached Piping, and Components The staff concludes that the TLAAs for this section remain valid or the effects of aging on the intended functions will be adequately managed for the extended period of operation. No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 43

It Section 4 - TLAAs continued Section 4.7 - Other Plant-Specific TLAAs Reactor Building Crane Load Cycles Metal Corrosion Crack Growth Calculation of a Postulated Flaw in the Heat Affected Zone of an Arc Strike in the Suppression Chamber Shell Radiation Degradation of Drywell Shell Expansion Gap PolyurethaneFoam High-Energy Line Break Postulation Based on Fatigue Cumulative Usage Factor All demonstrate that the TLAA has been projected to the end of the period of extended operation No Open or Confirmatory Items April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 44

TLAA Summary The applicant has identified the appropriate TLAAs and has demonstrated or is committed to demonstrate that the TLAAs: 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 April 14, 2004 ACRS Subcommittee Meeting Dresden and Quad Cities 45

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Staff Conclusions Pending the resolution of the 5 Open and 16. Confirmatory Items, 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 such that thereis reasonable assurance that activities will continue to be conducted in the renewal term in accordance with the current licensing basis The applicable requirements of 10 CFR Part 51 have been satisfied Matters raised under 10 CFR 2.758 have been addressed April 14, 2004 ACRS Subcommittee Meeting - Dresden and Quad Cities 46}}

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