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Category:Note to File incl Telcon Record
MONTHYEARML0807304422008-04-15015 April 2008 03/12/2008 - Summary of Conference Call Between NRC Staff and WCNOC- Clarification of a Certain Masonry Wall of the Turbine Building Documented in the Safety Evaluation Report with Open Items for Wolf Creek Generating Station License Renewa ML0716202012007-07-0606 July 2007 Summary of Telephone Conference Call Held on May 24, 2007, Between the NRC and Wolf Creek Nuclear Operating Corporation Concerning the Analysis of Service Accident Mitigation Alternatives Pertaining to the Wolf Creek Generating Station, Uni ML0712402692007-05-22022 May 2007 Summary of Telephone Conference Call Held on March 20, 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, Uni ML0712201912007-05-0707 May 2007 Summary of Telephone Conference Call Held on March 7, 2007, Between the NRC and Wolf Creek Nuclear Operating Corporation, Concerning Draft RAIs Pertaining to the Wolf Creek Generating Station, Unit 1, License Renewal Application ML0712202122007-05-0606 May 2007 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 ML0306400162003-03-0505 March 2003 Memo Teleconference on Relief Request No. 12R-23 for Wolf Creek 2008-04-15
[Table view] Category:Verbal Comm
MONTHYEARML0807304422008-04-15015 April 2008 03/12/2008 - Summary of Conference Call Between NRC Staff and WCNOC- Clarification of a Certain Masonry Wall of the Turbine Building Documented in the Safety Evaluation Report with Open Items for Wolf Creek Generating Station License Renewa ML0716202012007-07-0606 July 2007 Summary of Telephone Conference Call Held on May 24, 2007, Between the NRC and Wolf Creek Nuclear Operating Corporation Concerning the Analysis of Service Accident Mitigation Alternatives Pertaining to the Wolf Creek Generating Station, Uni ML0712402692007-05-22022 May 2007 Summary of Telephone Conference Call Held on March 20, 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, Uni ML0712201912007-05-0707 May 2007 Summary of Telephone Conference Call Held on March 7, 2007, Between the NRC and Wolf Creek Nuclear Operating Corporation, Concerning Draft RAIs Pertaining to the Wolf Creek Generating Station, Unit 1, License Renewal Application ML0712202122007-05-0606 May 2007 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 ML0306400162003-03-0505 March 2003 Memo Teleconference on Relief Request No. 12R-23 for Wolf Creek 2008-04-15
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22361A0052022-12-27027 December 2022 NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements ML22321A2662022-11-16016 November 2022 January 2023 Emergency Preparedness Program Inspection - Request for Information ML22307A1372022-11-0202 November 2022 August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information ML22249A2552022-06-29029 June 2022 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000482/2022012 ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22055A1142022-02-23023 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time ML22045A4512022-02-14014 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling ML22025A3612022-01-21021 January 2022 PI&R RFI Final ML21327A2602021-11-23023 November 2021 NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21271A1952021-09-28028 September 2021 E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021 ML21253A0902021-09-23023 September 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment and Regulatory Exemption for a Risk-Informed Approach to Address GSI-191 (EPIDs L-2021-LLA- 0152 and L-2021-LLE-0039) ML21221A1282021-08-0505 August 2021 NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise ML21132A1032021-05-12012 May 2021 Document Request List, Paperwork Reduction Act Statement ML20302A4782020-10-28028 October 2020 OPC R1 Request for Information ML20262A7512020-09-17017 September 2020 NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425 ML20195A2712020-07-13013 July 2020 Generation Station - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2020012) and Request for Information ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19346E6052019-11-0404 November 2019 Target Set Request for Information for Week of November 4, 2019 ML19224A5242019-08-12012 August 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5 ML18304A1052018-11-0505 November 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML18282A6402018-10-0909 October 2018 NRR E-mail Capture - Request for Additional Information - Wolf Creek Generating Station License Amendment Request for Revision to the Emergency Plan ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses ML18207A4332018-07-24024 July 2018 NRR E-mail Capture - (External_Sender) Draft Request for Additional Information Relief Request from ASME Code N-666-1 Alternate Repair of Essential Service Water Piping Wolf Creek Generating Station, Unit 1 EPID No.:L-2018-LLR-0101 ML18116A6132018-04-25025 April 2018 Operating Corporation - Notification of Inspection (NRC Inspection Report 05000482/2018002) and Request for Information ML17331A1782017-12-0404 December 2017 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML17291A7102017-10-17017 October 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17265A0142017-09-21021 September 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses ML17170A3152017-06-19019 June 2017 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2017008) and Request for Information ML17166A0382017-06-14014 June 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17052A0282017-02-15015 February 2017 NRR E-mail Capture - Wolf Creek Generating Station - Official EAL RAIs ML16319A4282016-11-14014 November 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Requests 13R-14 and 13R-15 ML16300A2662016-10-21021 October 2016 Request for Additional Information - Relief Request I3R-13 Regarding Weld Examination Coverage IR 05000482/20160022016-08-0303 August 2016 NRC Integrated Inspection Report 05000482/2016002 ML16110A3722016-04-25025 April 2016 Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16020A1392016-01-15015 January 2016 Notification of NRC Component Design Bases Inspection (05000482/2016007) and Initial Request for Information ML15135A4862015-05-14014 May 2015 Wc 2015007 17T RFI ML15082A0052015-03-27027 March 2015 Request for Additional Information, Round 2, Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15079A0762015-03-23023 March 2015 Request for Additional Information, Round 2, Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML15040A6252015-02-10010 February 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14323A5742014-12-0404 December 2014 Request for Additional Information, License Amendment Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in USAR ML14230A7572014-08-21021 August 2014 Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML14206A0122014-08-0101 August 2014 Request for Additional Information, Relief Requests I3R-08, RPV Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14197A3362014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval ML14148A3872014-06-0202 June 2014 Request for Additional Information Related to Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML14111A1002014-04-30030 April 2014 Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14083A4002014-04-0303 April 2014 Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14058A0882014-03-0505 March 2014 Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14027A1622014-01-28028 January 2014 Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term 2022-06-29
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May 6, 2007LICENSEE: Wolf Creek Nuclear Operating CorporationFACILITY:Wolf Creek Generating Station, Unit 1
SUBJECT:
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:
SUBJECT:
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)
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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