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:	Veronica Rodriguez NRC/NRR/ADRO/DLR/RLRB
To:	Wolf Creek
rodriguez v m
References
Download: ML071220212 (9)

Text

May 6, 2007 LICENSEE: Wolf Creek Nuclear Operating Corporation FACILITY:

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 APPLICATION The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear Operating Corporation held a telephone conference call on April 06, 2007, to discuss and clarify the staffs 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 staffs D-RAIs. provides a listing of the participants and Enclosure 2 contains a listing of the D-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 Regulation Docket No. 50-482

Enclosures:

1. List of Participants

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

ML071220212 OFFICE PM:RLRB:DLR LA:DLR BC:RLRB:DLR NAME VRodríguez SFigueroa RAuluck DATE 05/4/07 05/4/07 05/6/07 TELEPHONE CONFERENCE CALL WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS APRIL 06, 2007 PARTICIPANTS AFFILIATIONS Verónica M. Rodríguez U.S. Nuclear Regulatory Commission (NRC)

John Ma NRC Zuhan Xi NRC Lorrie Bell Wolf Creek Nuclear Operating Corporation (WCNOC)

Charlie Medenciy WCNOC Zarif Botros WCNOC Eric Blocher Strategic Teaming and Resource Sharing Alliance (STARS)

Paul Crawley STARS Donald Stevens STARS Gary Warner STARS James Johnson STARS DRAFT REQUESTS FOR ADDITIONAL INFORMATION WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION APRIL 06, 2007 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of Wolf Creek Nuclear 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 2.4-1 LRA Section 2.4.9 states that structural features are provided to protect safety-related components 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 a formal RAI.

D-RAI 2.4-2 LRA Section 2.4.10 states that there is a wooden H-frame structure within each of the two transmission 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 a formal RAI.

D-RAI 2.4-3 The staff requests that the applicant clarify if the component type structural steel described in LRA 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 a formal RAI.

D-RAI 2.4-4 The staff requests that the applicant clarify if the component type structural steel described in LRA 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 response to RAI 2.3.3.14-2 submitted for the fire protection system. Therefore, this question is withdrawn and will not be sent as a formal RAI.

AGING MANAGEMENT PROGRAMS Concrete Containment Tendon Prestress D-RAI B.3.3-1 LRA Section B.3.3 states that procedures which list surveillance tendons will be extended to include random samples for the 40, 45, 50, and 55 year surveillances. The staff requests that the 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 a formal RAI.

D-RAI B.3.3-2 LRA Section B.3.3 states that Procedures will be enhanced to explicitly require a regression analysis 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 each tendon group after every surveillance (2) Discuss the difference between the current procedures and requirements and the enhanced procedures 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 difference between the current methods and the enhanced ones Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.

TIME-LIMITED AGING ANALYSIS Concrete Containment Tendon Prestress Analysis D-RAI 4.5-1 LRA Table 4.5-2 indicates that two tendon types, dome hoop and cylinder hoop, are combined into 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 a formal RAI.

D-RAI 4.5-2 LRA Table 3.5-2 states that the seven horizontal tendons forces at the first year surveillance were 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 a formal RAI.

D-RAI 4.5-3 LRA Figure 4.5-1, Note 4, states that The surveillance program predicted force lines were calculated 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 a formal RAI.

D-RAI 4.5-4 Based 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 a formal RAI.

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

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 APPLICATION HARD COPY DLR RF E-MAIL:

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Wolf Creek Generating Station cc:

Jay Silberg, Esq.

Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027 Office of the Governor State of Kansas Topeka, KS 66612 Attorney General 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6th Street Burlington, KS 66839 Thomas A. Conley, Section Chief Radiation and Asbestos Control Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 8201 NRC Road Steedman, MO 65077-1032 Kevin J. Moles, Manager Regulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Lorrie I. Bell, Project Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708