ML060050022

2006/03/02-Vermont Yankee, License Amendment 229 Regarding Extended Power Uprate

ML060050022
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/02/2006
From:	Richard Ennis Plant Licensing Branch III-2
To:	Kansler M Entergy Nuclear Operations
Ennis R B, NRR/DLPM, 415-1420
Shared Package
ML060050024	List: ML060050022 ML060050028 ML060390107
References
%dam200606, TAC MC0761
Download: ML060050022 (16)

Text

March 2, 2006Mr. Michael KanslerPresident Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: EXTENDED POWER UPRATE (TAC NO. MC0761)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 229 to Facility Operating LicenseNo. DPR-28 for the Vermont Yankee Nuclear Power Station (VYNPS), in response to your application dated September 10, 2003, as supplemented by letters dated October 1, andOctober 28 (2 letters), 2003; January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters),October 5, October 7 (2 letters), December 8, and December 9, 2004; February 24, March 10, March 24, March 31, April 5, April 22, June 2, August 1, August 4, September 10,September 14, September 18, September 28, October 17, October 21 (2 letters), October 26,October 29, November 2, November 22, and December 2, 2005; January 10, and February 22, 2006. The amendment increases the maximum authorized power level for VYNPS from 1593megawatts thermal (MWt) to 1912 MWt, which is an increase of approximately 20 percent. The increase in power level is considered an extended power uprate (EPU). The amendment includes revisions to the VYNPS Operating License and Technical Specifications that arenecessary to implement the EPU.The related Safety Evaluation (SE) has been determined to contain proprietary informationpursuant to Title 10 of the Code of Federal Regulations, Section 2.390. Accordingly, the NRCstaff has prepared a redacted, publicly-available, non-proprietary version of the SE. Copies of the proprietary and non-proprietary versions of the SE are enclosed.

M. Kansler- 2 -A copy of the "Notice of Issuance of Amendment to Facility Operating License and FinalDetermination of No Significant Hazards Consideration," which is being forwarded to the Office of the Federal Register for publication, is also enclosed.Sincerely,/RA/Richard B. Ennis, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-271

Enclosures:

1. Amendment No. 229 to License No. DPR-28 2. Non-proprietary SE

3. Proprietary SE

4. Noticecc w/encls 1, 2, and 4: See next page M. Kansler- 2 -A copy of the "Notice of Issuance of Amendment to Facility Operating License and FinalDetermination of No Significant Hazards Consideration," which is being forwarded to the Office of the Federal Register for publication, is also enclosed.Sincerely,/RA/Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-271

Enclosures:

1. Amendment No. 229 to License No. DPR-28 2. Non-proprietary SE

3. Proprietary SE

4. Noticecc w/encls 1, 2, and 4: See next pageDISTRIBUTION: See next pageAccession Nos.

Package: ML060050024 Cover letter, Amendment, and Notice: ML060050022 License and TS pages: ML060390107 Non-proprietary SE: ML060050028 Proprietary SE: ML060050051*Cover letter onlyOFFICELPL1-2/PM CMTech Editor*LPL1-1/LAOGCNAMEREnnisHChangSLittleSTurkDATE2/27/061/5/062/27/062/28/06OFFICELPL1-2/BCDORL/DNRR/DNAMEDRobertsCHaneyJDyerDATE3/1/063/1/063/2/06The following provided safety evaluation input by memos dated**OFFICEEEIB-A/SCEEIB-B/SCEMCB-A/SCEMCB-B/SCEMCB-C/SCNAMEEMarinosRJenkinsSCoffinTChanLLundDATE**9/27/047/1/04, 12/15/05,9/29/0411/24/048/9/049/9/04OFFICEEMEB/SCIPSB-A/SCIPSB/BCIROB-B/SCSPLB-A/SC(A)NAMEKManolyDThatcherTQuayDTrimbleSJonesDATE**9/30/059/29/0511/10/041/24/059/30/05OFFICESPLB-B/SCSPSB-A/SCSPSB-C/SCSRXB-A/SCNAMESWeerakkodyMRubinRDennigFAkstulewiczDATE**7/31/0410/3/0510/4/04, 10/6/04,9/30/05 9/30/05,10/11/05OFFICIAL RECORD COPY Distribution for letter dated: March 2, 2006

SUBJECT:

VERMONT YANKEE NUCLEAR POWER STATION - ISSUANCE OF AMENDMENT RE: EXTENDED POWER UPRATE (TAC NO. MC0761)DISTRIBUTION

PUBLIC LPL1-2 Reading JDyer RBorchardt BSheron BBoger CHaney CHolden EHackett DRoberts REnnis JShea CRaynor SLittle TAlexion QNguyen OGC ACRS GHill (2)

CAnderson, RGN I STurk, OGC VBucci, OIG HGarg NTrehan APal BElliot RDavis KParczewski TScarbrough PSekerak CWu RPettis RPedersen JCai JBongarra DReddy RGallucci MStutzke RLobel HWalker MHart MRazzaque ZAbdullahi GThomas LWard THuang Vermont Yankee Nuclear Power Station cc:

Regional Administrator, Region IU. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415Mr. David R. LewisPillsbury, Winthrop, Shaw, Pittman, LLP 2300 N Street, N.W.

Washington, DC 20037-1128Mr. David O'Brien, CommissionerVermont Department of Public Service 112 State Street Montpelier, VT 05620-2601Mr. James Volz, ChairmanPublic Service Board State of Vermont 112 State Street Montpelier, VT 05620-2701Chairman, Board of Selectmen Town of Vernon P.O. Box 116 Vernon, VT 05354-0116Operating Experience CoordinatorVermont Yankee Nuclear Power Station 320 Governor Hunt Road Vernon, VT 05354G. Dana Bisbee, Esq.Deputy Attorney General 33 Capitol Street Concord, NH 03301-6937Chief, Safety Unit Office of the Attorney General One Ashburton Place, 19th Floor Boston, MA 02108Ms. Carla A. White, RRPT, CHPRadiological Health Vermont Department of Health P.O. Box 70, Drawer #43 108 Cherry Street Burlington, VT 05402-0070Mr. James M. DeVincentisManager, Licensing Vermont Yankee Nuclear Power Station P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500Resident InspectorVermont Yankee Nuclear Power Station U. S. Nuclear Regulatory Commission

P.O. Box 176 Vernon, VT 05354Director, Massachusetts Emergency Management Agency ATTN: James Muckerheide 400 Worcester Rd.

Framingham, MA 01702-5399Jonathan M. Block, Esq.Main Street

P.O. Box 566 Putney, VT 05346-0566Mr. John F. McCannDirector, Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Gary J. TaylorChief Executive Officer Entergy Operations 1340 Echelon Parkway Jackson, MS 39213 Vermont Yankee Nuclear Power Station cc:

Mr. John T. HerronSr. VP and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Oscar LimpiasVice President, Engineering Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Christopher SchwarzVice President, Operations Support Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColombDirector of Oversight Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Travis C. McCulloughAssistant General Counsel Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Jay K. ThayerSite Vice President Entergy Nuclear Operations, Inc.

Vermont Yankee Nuclear Power Station P.O. Box 0500 185 Old Ferry Road Brattleboro, VT 05302-0500Mr. James H. Sniezek5486 Nithsdale Drive Salisbury, MD 21801Ms. Stacey M. LousteauTreasury Department Entergy Services, Inc.

639 Loyola Avenue New Orleans, LA 70113Mr. Raymond ShadisNew England Coalition Post Office Box 98 Edgecomb, ME 04556Mr. James P. MatteauExecutive Director Windham Regional Commission 139 Main Street, Suite 505 Brattleboro, VT 05301Mr. William K. ShermanVermont Department of Public Service 112 State Street Drawer 20 Montpelier, VT 05620-2601Mr. Michael D. Lyster5931 Barclay Lane Naples, FL 34110-7306Ms. Charlene D. FaisonManager, Licensing 440 Hamilton Avenue White Plains, NY 10601 ENTERGY NUCLEAR VERMONT YAN KEE, LLCAND ENTERGY NUCLEAR OPERATIONS, INC.DOCKET NO. 50-271VERMONT YANKEE NUCLEAR POWER STATIONAMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 229License No. DPR-281.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment filed by Entergy Nuclear Vermont Yankee, LLCand Entergy Nuclear Operations, Inc. (the licensee) on September 10, 2003, as supplemented by letters dated October 1, and October 28 (2 letters), 2003; January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2letters), October 5, October 7 (2 letters), December 8, and December 9, 2004; February 24, March 10, March 24, March 31, April 5, April 22, June 2, August 1,August 4, September 10, September 14, September 18, September 28,October 17, October 21 (2 letters), October 26, October 29, November 2, November 22, and December 2, 2005; January 10, and February 22, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance: (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment, and paragraph 3.B of FacilityOperating License No. DPR-28 is hereby amended to read as follows:(B)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 229, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.In addition, the license is amended to revise paragraph 3.A of Facility Operating LicenseNo. DPR-28 to reflect the new maximum licensed reactor core power level of 1912 megawatts thermal. The licensee is also amended to add new license conditions 3.K, 3.L, and 3.M as follows:K. Minimum Critical Power RatioWhen operating at thermal power greater than 1593 megawatts thermal, the safety limitminimum critical power ratio (SLMCPR) shall be established by adding 0.02 to the cycle-specific SLMCPR value calculated using the NRC-approved methodologiesdocumented in General Electric Licensing Topical Report NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," as amended, and documented in the Core Operating Limits Report. L. Transient Testing1.During the extended power uprate (EPU) power ascension test program and prior toexceeding 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> of plant operation at the nominal full EPU reactor power level, with feedwater and condensate flow rates stabilized at approximately the EPU fullpower level, Entergy Nuclear Operations, Inc. shall confirm through performance of transient testing that the loss of one condensate pump will not result in a completeloss of reactor feedwater. 2.Within 30 days at nominal full-power operation following successful performance ofthe test in (1) above, through performance of additional transient testing and/or analysis of the results of the testing conducted in (1) above, confirm that the loss ofone reactor feedwater pump will not result in a reactor trip.M. Potential Adverse Flow EffectsThis license condition provides for monitoring, evaluating, and taking prompt action inresponse to potential adverse flow effects as a result of power uprate operation on plant structures, systems, and components (including verifying the continued structuralintegrity of the steam dryer).1.The following requirements are placed on operation of the facility above the originallicensed thermal power (OLTP) level of 1593 megawatts thermal (MWt): a.Entergy Nuclear Operations, Inc. shall monitor hourly the 32 main steam line(MSL) strain gages during power ascension above 1593 MWt for increasing pressure fluctuations in the steam lines.b.Entergy Nuclear Operations, Inc. shall hold the facility for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 105%,110%, and 115% of OLTP to collect data from the 32 MSL strain gages required by Condition M.1.a, conduct plant inspections and walkdowns, and evaluate steam dryer performance based on these data; shall provide the evaluation to the NRC staff by facsimile or electronic transmission to the NRC project manager upon completion of the evaluation; and shall not increase power above each hold point until 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC project manager confirms receipt ofthe transmission.c.If any frequency peak from the MSL strain gage data exceeds the limit curveestablished by Entergy Nuclear Operations, Inc. and submitted to the NRC staffprior to operation above OLTP, Entergy Nuclear Operations, Inc. shall return the facility to a power level at which the limit curve is not exceeded. Entergy NuclearOperations, Inc. shall resolve the uncertainties in the steam dryer analysis, document the continued structural integrity of the steam dryer, and provide thatdocumentation to the NRC staff by facsimile or electronic transmission to the NRC project manager prior to further increases in reactor power.d.In addition to evaluating the MSL strain gage data, Entergy Nuclear Operations,Inc. shall monitor reactor pressure vessel water level instrumentation or MSL piping accelerometers on an hourly basis during power ascension above OLTP.

If resonance frequencies are identified as increasing above nominal levels inproportion to strain gage instrumentation data, Entergy Nuclear Operations, Inc.shall stop power ascension, document the continued structural integrity of thesteam dryer, and provide that documentation to the NRC staff by facsimile orelectronic transmission to the NRC project manager prior to further increases inreactor power.e.Following start-up testing, Entergy Nuclear Operations, Inc. shall resolve theuncertainties in the steam dryer analysis and provide that resolution to the NRC staff by facsimile or electronic transmission to the NRC project manager. If theuncertainties are not resolved within 90 days of issuance of the license amendment authorizing operation at 1912 MWt, Entergy Nuclear Operations, Inc. shall return the facility to OLTP.2.As described in Entergy Nuclear Operations, Inc. letter BVY 05-084 datedSeptember 14, 2005, Entergy Nuclear Operations, Inc. shall implement the followingactions:a.Prior to operation above OLTP, Entergy Nuclear Operations, Inc. shall install 32additional strain gages on the main steam piping and shall enhance the data acquisition system in order to reduce the measurement uncertainty associatedwith the acoustic circuit model (ACM). b.In the event that acoustic signals are identified that challenge the limit curveduring power ascension above OLTP, Entergy Nuclear Operations, Inc. shall evaluate dryer loads and re-establish the limit curve based on the new strain gage data, and shall perform a frequency-specific assessment of ACM uncertainty at the acoustic signal frequency. c.After reaching 120% of OLTP, Entergy Nuclear Operations, Inc. shall obtainmeasurements from the MSL strain gages and establish the steam dryer flow-induced vibration load fatigue margin for the facility, update the dryer stressreport, and re-establish the steam dryer monitoring plan (SDMP) limit curve with the updated ACM load definition and revised instrument uncertainty, which willbe provided to the NRC staff. d.During power ascension above OLTP, if an engineering evaluation is required inaccordance with the SDMP, Entergy Nuclear Operations, Inc. shall perform the structural analysis to address frequency uncertainties up to

+/-10% and assurethat peak responses that fall within this uncertainty band are addressed. e.Entergy Nuclear Operations, Inc. shall revise the SDMP to reflect long-termmonitoring of plant parameters potentially indicative of steam dryer failure; to reflect consistency of the facility's steam dryer inspection program with GeneralElectric Services Information Letter 644, Revision 1; and to identify the NRC Project Manager for the facility as the point of contact for providing SDMPinformation during power ascension. f.Entergy Nuclear Operations, Inc. shall submit the final extended power uprate(EPU) steam dryer load definition for the facility to the NRC upon completion ofthe power ascension test program. g.Entergy Nuclear Operations, Inc. shall submit the flow-induced vibration relatedportions of the EPU startup test procedure to the NRC, including methodologyfor updating the limit curve, prior to initial power ascension above OLTP.3.Entergy Nuclear Operations, Inc. shall prepare the EPU startup test procedure toinclude the (a) stress limit curve to be applied for evaluating steam dryer performance; (b) specific hold points and their duration during EPU power ascension; (c) activities to be accomplished during hold points; (d) plant parameters to be monitored; (e) inspections and walkdowns to be conducted for steam, feedwater, and condensate systems and components during the hold points; (f)methods to be used to trend plant parameters; (g) acceptance criteria for monitoring and trending plant parameters, and conducting the walkdowns and inspections; (h) actions to be taken if acceptance criteria are not satisfied; and (i) verification of the completion of commitments and planned actions specified in its application and all supplements to the application in support of the EPU license amendment request pertaining to the steam dryer prior to power increase above OLTP. Entergy Nuclear Operations, Inc. shall provide the related EPU startup test procedure sections to the NRC by facsimile or electronic transmission to the NRC project manager prior toincreasing power above OLTP. 4.When operating above OLTP, the operating limits, required actions, andsurveillances specified in the SDMP shall be met. The following key attributes of the SDMP shall not be made less restrictive without prior NRC approval:a.During initial power ascension testing above OLTP, each test plateau incrementshall be approximately 80 MWt;b.Level 1 performance criteria; and c.The methodology for establishing the stress spectra used for the Level 1 andLevel 2 performance criteria.Changes to other aspects of the SDMP may be made in accordance with theguidance of NEI 99-04.5.During each of the three scheduled refueling outages (beginning with the spring2007 refueling outage), a visual inspection shall be conducted of all accessible, susceptible locations of the steam dryer, including flaws left "as is" and modifications.6.The results of the visual inspections of the steam dryer conducted during the threescheduled refueling outages (beginning with the spring 2007 refueling outage) shall be reported to the NRC staff within 60 days following startup from the respectiverefueling outage. The results of the SDMP shall be submitted to the NRC staff in areport within 60 days following the completion of all EPU power ascension testing.7.The requirements of paragraph 4 above for meeting the SDMP shall beimplemented upon issuance of the EPU license amendment and shall continue until the completion of one full operating cycle at EPU. If an unacceptable structural flaw(due to fatigue) is detected during the subsequent visual inspection of the steam dryer, the requirements of paragraph 4 shall extend another full operating cycle untilthe visual inspection standard of no new flaws/flaw growth based on visual inspection is satisfied.8.This license condition shall expire upon satisfaction of the requirements inparagraphs 5, 6, and 7 provided that a visual inspection of the steam dryer does not reveal any new unacceptable flaw or unacceptable flaw growth that is due to fatigue. 3.This license amendment is effective as of its date of issuance and shall be implementedwithin 120 days.FOR THE NUCLEAR REGULATORY COMMISSION

/RA/J. E. Dyer, DirectorOffice of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: March 2, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 229FACILITY OPERATING LICENSE NO. DPR-28DOCKET NO. 50-271Replace the following pages of the Facility Operating License and Appendix A TechnicalSpecifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.Facility Operating LicenseRemoveInsert 33 99---10

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---13Technical SpecificationsRemoveInsert 33 66 771010 1212 1313 1414 1515 1717 2121 2424 3030 8383 9090 9292 9494 9797 9898135135 136136 137137 138138 142142 224224 225225 226226 228228 7590-01-P U.S. NUCLEAR REGULATORY COMMISSIONENTERGY NUCLEAR VERMONT YANKEE, LLC ANDENTERGY NUCLEAR OPERATIONS, INC.DOCKET NO. 50-271NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSEAND FINAL DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONThe U.S. Nuclear Regulatory Commission (Commission) has issued Amendment No. 229 to Facility Operating License No. DPR-28, issued to Entergy Nuclear Vermont Yankee,LLC and Entergy Nuclear Operations, Inc. (the licensee), which revised the Technical Specifications (TSs) and License for operation of the Vermont Yankee Nuclear Power Station(VYNPS) located in Windham County, Vermont. The amendment was effective as of the date of its issuance.The amendment increases the maximum authorized power level for VYNPS from1593 megawatts thermal (MWt) to 1912 MWt, which is an increase of approximately 20 percent. The increase in power level is considered an extended power uprate. The application for the amendment complies with the standards and requirements of theAtomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.

The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.The Commission published a "Notice of Consideration of Issuance of Amendment toFacility Operating License and Opportunity for a Hearing" related to this action in the FEDERALREGISTER on July 1, 2004 (69 FR 39976). This Notice provided 60 days for the public to request a hearing. On August 30, 2004, the Vermont Department of Public Service and theNew England Coalition filed requests for hearing in connection with the proposed amendment.

By Order dated November 22, 2004, the Atomic Safety and Licensing Board (ASLB) granted those hearing requests and by Order dated December 16, 2004, the ASLB issued its decision to conduct a hearing using the procedures in 10 CFR Part 2, Subpart L, "Informal Hearing Procedures for NRC Adjudications."The Commission published a "Notice of Consideration of Issuance of Amendment toFacility Operating License and Proposed No Significant Hazards Consideration Determination" related to this action in the FEDERAL REGISTER on January 11, 2006 (71 FR 1744). This Notice provided 30 days for public comment. The Commission received comments on the proposed no significant hazards consideration as discussed below. Under its regulations, the Commission may issue and make an amendment immediatelyeffective, notwithstanding the pendency before it of a request for a hearing from any person, in advance of the holding and completion of any required hearing, where it has determined that no significant hazards consideration is involved.The Commission has applied the standards of 10 CFR 50.92 and has made a finaldetermination that the amendment involves no significant hazards consideration. Publiccomments received on the proposed no significant hazards consideration determination wereconsidered in making the final determination. The basis for this determination is contained inthe Safety Evaluation related to this action. Accordingly, as described above, the amendment has been issued and made immediately effective and any hearing will be held after issuance.The Commission published an Environmental Assessment related to the action in theFEDERAL REGISTER on January 27, 2006 (71 FR 4614). Based on the Environmental Assessment, the Commission concluded that the action will not have a significant effect on the quality of the human environment. Accordingly, the Commission determined not to prepare anenvironmental impact statement for the proposed action.For further details with respect to this action, see the application for amendment datedSeptember 10, 2003, as supplemented by letters dated October 1, and October 28 (2 letters),2003; January 31 (2 letters), March 4, May 19, July 2, July 27, July 30, August 12, August 25, September 14, September 15, September 23, September 30 (2 letters), October 5, October 7(2 letters), December 8, and December 9, 2004; February 24, March 10, March 24, March 31, April 5, April 22, June 2, August 1, August 4, September 10, September 14, September 18,September 28, October 17, October 21 (2 letters), October 26, October 29, November 2,November 22, and December 2, 2005; January 10, and February 22, 2006, which is available for public inspection at the Commission's PDR, located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available recordswill be accessible electronically from the Agencywide Documents Access and ManagementSystem's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site,http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS orwho encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail topdr@nrc.gov.

Dated at Rockville, Maryland, this 2nd day of March, 2006. FOR THE NUCLEAR REGULATORY COMMISSION/RA/Richard B. Ennis, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation