ML071220212

Summary of Telephone Conference Call Held on 03/06/07, Between the NRC and Wolf Creek Nuclear Operating Corporation, Concerning Draft RAIs Pertaining to the Wolf Creek, Unit 1, License Renewal Application

ML071220212
Person / Time
Site:	Wolf Creek
Issue date:	05/06/2007
From:	Rodriguez V M NRC/NRR/ADRO/DLR/RLRB
To:	Wolf Creek
rodriguez v m
References
Download: ML071220212 (9)

Text

May 6, 2007LICENSEE: Wolf Creek Nuclear Operating CorporationFACILITY:Wolf Creek Generating Station, Unit 1

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 06, 2007,BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATIONThe U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation held a telephone conference call on April 06, 2007, to discuss and clarify the staff's draft requests for additional information (D-RAIs) concerning the Wolf Creek Generating Station, Unit 1, license renewal application. The telephone conference call was useful in clarifying the intent of the staff's D-RAIs.Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of theD-RAIs discussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary.

/RA/Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-482

Enclosures:

1. List of Participants

2. List of Draft Requests for Additional Informationcc w/encls: See next page

ML071220212 OFFICEPM:RLRB:DLRLA:DLRBC:RLRB:DLRNAMEVRodríguezSFigueroaRAuluck DATE05/4/0705/4/0705/6/07 TELEPHONE CONFERENCE CALLWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONLIST OF PARTICIPANTSAPRIL 06, 2007PARTICIPANTSAFFILIATIONSVerónica M. RodríguezU.S. Nuclear Regulatory Commission (NRC)John MaNRC Zuhan XiNRC Lorrie BellWolf Creek Nuclear Operating Corporation (WCNOC)

Charlie MedenciyWCNOC Zarif BotrosWCNOC Eric BlocherStrategic Teaming and Resource Sharing Alliance (STARS)

Paul CrawleySTARS Donald StevensSTARS Gary WarnerSTARS James JohnsonSTARS DRAFT REQUESTS FOR ADDITIONAL INFORMATIONWOLF CREEK GENERATING STATION, UNIT 1LICENSE RENEWAL APPLICATIONAPRIL 06, 2007The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf CreekNuclear Operating Corporation held a telephone conference call on April 06, 2007, to discuss and clarify the following draft requests for additional information (D-RAIs) concerning the Wolf Creek Generating Station (WCGS), Unit 1, license renewal application (LRA). SCOPING AND SCREENING RESULTS Scoping and Screening Results: Structures D-RAI 2.4-1LRA Section 2.4.9 states that structural features are provided to protect safety-relatedcomponents from flooding. The staff requests that the applicant identify these structural features, which are used to protect safety-related components from flooding, and discuss whether they should be within the scope of license renewal.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.4-2LRA Section 2.4.10 states that there is a wooden H-frame structure within each of the twotransmission power lines. However, LRA Table 2.4-10 does not list the wooden H-frame as a structure within the scope of license renewal. The staff requests that the applicant justify its exclusion from the scope of license renewal. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.4-3The staff requests that the applicant clarify if the component type structural steel described inLRA Table 2.4-13 include the trash rack and stop log slots, guideways for the traveling water screens, and walls. If not, the staff requests that the applicant explain and justify its response. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.4-4The staff requests that the applicant clarify if the component type structural steel described inLRA Table 2.4-14 include the traveling screens. If not, the staff requests that the applicant explain and justify its response. Discussion: The applicant stated that the traveling screens will be addressed in its responseto RAI 2.3.3.14-2 submitted for the fire protection system. Therefore, this question is withdrawnand will not be sent as a formal RAI.AGING MANAGEMENT PROGRAMSConcrete Containment Tendon Prestress D-RAI B.3.3-1LRA Section B.3.3 states that procedures which list surveillance tendons will be extended toinclude random samples for the 40, 45, 50, and 55 year surveillances.

The staff requests thatthe applicant discuss the differences between these enhanced procedures and the current procedures.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI B.3.3-2LRA Section B.3.3 states that "Procedures will be enhanced to explicitly require a regressionanalysis for each tendon group after every surveillance; and to invoke and describe regression analysis methods used to construct the lift-off trend lines, including the use of individual tendon data in accordance with Information Notice (IN) 99-10, "Degradation of Prestressing Tendon Systems in Prestressed Concrete Containments." The staff requests that the applicant address the following: (1)Describe the enhanced procedures and requirements of the regression analysis for eachtendon group after every surveillance(2)Discuss the difference between the current procedures and requirements and the enhancedprocedures and requirements to be used during the period of extended operation (3)Describe the analysis methods used to construct the lift-off trend lines, and the differencebetween the current methods and the enhanced onesDiscussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. TIME-LIMITED AGING ANALYSISConcrete Containment Tendon Prestress AnalysisD-RAI 4.5-1LRA Table 4.5-2 indicates that two tendon types, dome hoop and cylinder hoop, are combinedinto one horizontal hoop group. The total number of examined tendons for these two types was seven for the first, third, and fifth year surveillance, and three for the tenth, fifteenth, and twentieth year surveillance. Two dome hoop tendons were inspected at the first and third year surveillance; however, no dome hoop tendon was inspected after the third year surveillance.

ASME Code Section XI, Subsection IWL-2520, "Examination of Unbonded Post-Tensioning Systems", states that tendons on dome and cylinder shall be characterized into two different tendon types because of their geometry and position in the containment. In addition, Subsection IWL-2520 states that the minimum number of surveillance tendons is four for each type of tendons for the first, third, and fifth year surveillance, and three for the tenth, fifteenth, and twentieth year surveillance. The staff requests that the applicant justify this deviation from the ASME Code requirements.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 4.5-2LRA Table 3.5-2 states that the seven horizontal tendons forces at the first year surveillancewere 1358.0 kips, 1359.0 kips, 1381.0 kips, 1409.0 kips, 1348.0 kips, 1422.0 kips, and 1387.0 kips. The average value of these seven tendons force is 1380.6 kips, which is different from the value of 1416.0 kips shown on LRA Figure 4.5-1. The staff requests that the applicant explain this discrepancy.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 4.5-3LRA Figure 4.5-1, Note 4, states that "The surveillance program predicted force lines werecalculated per wire. The values plotted here assume 170 wires per tendon. Some tendons have fewer due to failure to meet acceptance criteria at installation, or due to removal for surveillance testing." If the numbers of wires in a tendon is less than 170 due to failure to meet acceptance criteria at installation, or due to removal for surveillance testing, the predicted magnitude of force of that tendon based on the assumption of 170 wires would be higher than it should have been. Therefore, the staff requests that the applicant provide its basis for using the assumed 170 wires per tendon instead of using the actual numbers of wires per tendon to calculate the tendon force.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 4.5-4Based on the discussion of RAIs 4.5-2 and 4.5-3, the staff requests that the applicant establish a new trend line in LRA Figure 4.5-1 with actual prestressed tendon force. The trend line points should be calculated based on the actual number of wires multiplied by the lift-off-wire force.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.

Memo to Wolf Creek Nuclear Operation Corp, from V. Rodriguez dated May 06, 2007DISTRIBUTION:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON APRIL 06, 2007,BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND WOLF CREEK NUCLEAR OPERATING CORPORATION, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATIONHARD COPY DLR RF E-MAIL:PUBLICRWeisman SSmith (srs3)

SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb

RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb

RidsNrrDss RidsOgcMailCenter RidsNrrAdes

---

VRodriguez

CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV Wolf Creek Generating Station cc:Jay Silberg, Esq.Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839Chief Engineer, Utilities DivisionKansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027Office of the GovernorState of Kansas Topeka, KS 66612Attorney General120 S.W. 10 th Avenue, 2 nd FloorTopeka, KS 66612-1597County ClerkCoffey County Courthouse 110 South 6 th StreetBurlington, KS 66839Thomas A. Conley, Section ChiefRadiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366Vice President Operations/Plant ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Supervisor LicensingWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839U.S. Nuclear Regulatory CommissionResident Inspectors Office/Callaway Plant

8201 NRC Road Steedman, MO 65077-1032Kevin J. Moles, ManagerRegulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Lorrie I. Bell, Project ManagerWolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708