ML070930685
| ML070930685 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/10/2007 |
| From: | Veronica Rodriguez NRC/NRR/ADRO/DLR/RLRB |
| To: | Garrett T Wolf Creek |
| rodriguez v m, ADRO/DLR/RLRB, 415-3703 | |
| References | |
| Download: ML070930685 (7) | |
Text
April 10, 2007 Mr. Terry J. Garrett Vice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION
Dear Mr. Garrett:
By letter dated September 27, 2006, Wolf Creek Nuclear Operating Corporation submitted an application pursuant to 10 CFR Part 54, to renew the operating license for Wolf Creek Generating Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Lorrie Bell, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3703 or e-mail VMR1@nrc.gov.
Sincerely,
/RA/
Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
Requests for Additional Information cc w/encl: See next page
ML070930685 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME SFigueroa VRodríguez RAuluck DATE 04/05/07 04/09/07 04/10/07
Enclosure WOLF CREEK GENERATING STATION (WCGS), UNIT 1 LICENSE RENEWAL APPLICATION (LRA)
REQUEST FOR ADDITIONAL INFORMATION (RAI)
SCOPING AND SCREENING RESULTS Scoping and Screening Results: Structures 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.
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.
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.
AGING MANAGEMENT PROGRAMS Concrete Containment Tendon Prestress 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.
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 TIME-LIMITED AGING ANALYSIS Concrete Containment Tendon Prestress Analysis 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.
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.
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.
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.
Letter to T. Garrett, from V. Rodriguez, dated April 10, 2007 DISTRIBUTION:
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION HARD COPY DLR RF E-MAIL:
PUBLIC RWeisman GGalletti SSmith (srs3)
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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