|
|
(One intermediate revision by the same user not shown) |
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:February 28, 2008 | | {{#Wiki_filter:February 28, 2008 Mr. Terry Garrett Vice President, Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 |
| | |
| Mr. Terry Garrett Vice President, Engineering | |
| | |
| Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION |
|
| |
|
| ==Dear Mr. Garrett:== | | ==Dear Mr. Garrett:== |
|
| |
|
| By letter dated September 27, 2006, Wolf Creek Nuclear Operating Corporation (WCNOC) submitted an application pursuant to 10 CFR Part 54, to renew the operating license NPF-42 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. Further requests for additional information may be issued in the future. | | By letter dated September 27, 2006, Wolf Creek Nuclear Operating Corporation (WCNOC) submitted an application pursuant to 10 CFR Part 54, to renew the operating license NPF-42 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. Further requests for additional information may be issued in the future. |
| | | Items in the enclosure were discussed with Ms. Lorrie Bell; and a mutually agreeable date for the response is within 30 days from the date of this letter or no later than April 1, 2008. If you have any questions, please contact me at 301-415-3617 or by e-mail at TXT1@nrc.gov. |
| Items in the enclosure were discussed with Ms. Lorrie Bell; and a mutually agreeable date for the response is within 30 days from the date of this letter or no later than April 1, 2008. If you have any questions, please contact me at 301-415-3617 or by e-mail at TXT1@nrc.gov. Sincerely, /RA/ Tam Tran, Project Manager Project Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482 | | Sincerely, |
| | /RA/ |
| | Tam Tran, Project Manager Project Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
|
| |
|
| As Stated | | As Stated cc w/encl: See next page |
|
| |
|
| cc w/encl: See next page
| | ML080530067 OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR NAME YEdmonds T. Tran L. Lund DATE 02/27/08 02/27/08 02/28/08 |
|
| |
|
| ML080530067 OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR NAME YEdmonds T. Tran L. Lund DATE 02/27/08 02/27/08 02/28/08 WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION Metal Fatigue Analyses
| | WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION Metal Fatigue Analyses Follow-up RAI for 4.3-1 The applicants responses provided in letters dated October 3, and 17, 2007, did not address the staffs concerns as stated in RAI 4.3-1. The October 3, 2007, letter stated that 1D transfer functions were developed for HL surge line nozzle and the charging nozzles in the vicinity of the nozzle to pipe welds. It went on to state that the development of the transfer functions takes full advantage of the local geometry and symmetry. However, the staff finds no axis of symmetry at the nozzle corners. Further, at the nozzle to pipe welds, the loading is not symmetric if thermal stratification is present. Therefore, the validity of transfer functions developed by using 1-D peak stress is not applicable at these locations. In order to enable the staff to make a determination on this issue, the applicant is requested to perform an environmentally-assisted fatigue analysis and provide results to the NRC Staff of a 3-D finite element analysis using an industry-accepted computer code, such as ANSYS. The analysis should cover nozzle corners with geometrical discontinuities and at locations where thermal stratification loading is significant. This analysis shall follow the rules of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III, Subsection NB-3200, requiring the use of six stress components to define the stress state and determine the alternating stress intensities. |
| | | Follow-up RAI for 4.3-3 Wolf Creek Generating Stations (WCGS) commitment closure letter (ET 08-007), dated January 25, 2008, does not address the following commitments on Page 14 of the October 3, 2007, letter (ET 07-0046): |
| Follow-up RAI for 4.3-1 The applicant's responses provided in letters dated October 3, and 17, 2007, did not address the staff's concerns as stated in RAI 4.3-1. The October 3, 2007, letter stated that 1D transfer functions were developed for HL surge line nozzle and the charging nozzles in the vicinity of the nozzle to pipe welds. It went on to state that the development of the transfer functions takes full advantage of the local geometry and symmetry. However, the staff finds no axis of symmetry at the nozzle corners. Further, at the nozzle to pipe welds, the loading is not symmetric if thermal stratification is present. Therefore, the validity of transfer functions developed by using "1-D peak stress" is not applicable at these locations. In order to enable the staff to make a | | (1) Since WCGS implemented the modified operating procedure (MOP) prior to 1995, it is reasonable to suspect that heat-ups during PERIOD1 would have more insurge/outsurge cycles than PERIOD2. WCNOC agrees with this assertion, and will commit to updating the baseline to account for this factor. The baseline will be increased based on the expected number of additional insurge/outsurge cycles that would be accumulated in a pre-MOP environment. |
| | | (2) In a follow-up discussion, the reviewers further noted that the cumulative usage factors back-projection did not consider the relative severity of charging and letdown transients. |
| determination on this issue, the applicant is requested to perform an environmentally-assisted fatigue analysis and provide results to the NRC Staff of a 3-D finite element analysis using an industry-accepted computer code, such as ANSYS. The analysis should cover nozzle corners with geometrical discontinuities and at locations where thermal stratification loading is significant. This analysis shall follow the rules of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III, Subsection NB-3200, requiring the use of six stress components to define the stress state and determine the alternating stress intensities. | | However, in the revised baseline, Wolf Creek will explicitly consider the differential contribution of fatigue for each category of charging event. |
| | The January 25, 2008, letter did not close commitments made by WCGS in the October 3, 2007, letter as quoted above. Please provide additional calculations and discussions to address the committed actions regarding the additional insurge/outsurge cycles and the differential contribution of fatigue for each category of charging event. |
|
| |
|
| Follow-up RAI for 4.3-3
| | Letter to Wolf Creek from T. Tran, dated February 28, 2008 DISTRIBUTION: |
| | |
| Wolf Creek Generating Station's (WCGS) commitment closure letter (ET 08-007), dated January 25, 2008, does not address the following commitments on Page 14 of the October 3, 2007, letter (ET 07-0046):
| |
| (1) Since WCGS implemented the modified operating procedure (MOP) prior to 1995, it is reasonable to suspect that heat-ups during PERIOD1 would have more insurge/outsurge cycles than PERIOD2. WCNOC agrees with this assertion, and will commit to updating the baseline to account for this factor. The baseline will be increased based on the expected number of additional insurge/outsurge cycles that would be accumulated in a pre-MOP environment.
| |
| (2) In a follow-up discussion, the reviewers further noted that the cumulative usage factors back-projection did not consider the relative severity of charging and letdown transients. - However, in the revised baseline, Wolf Creek will explicitly consider the differential contribution of fatigue for each category of charging event.
| |
| The January 25, 2008, letter did not close commitments made by WCGS in the October 3, 2007, letter as quoted above. Please provide additional calculations and discussions to address the committed actions regarding the additional insurge/outsurge cycles and the differential contribution of fatigue for each category of charging event.
| |
| Letter to Wolf Creek from T. Tran, dated February 28, 2008 DISTRIBUTION | |
| : | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION HARD COPY: DLR R/F E-MAIL: PUBLIC SSmith (srs3) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION HARD COPY: |
| | | DLR R/F E-MAIL: |
| SDuraiswamy RidsNrrDlr RidsNrrDlrRlra | | PUBLIC SSmith (srs3) |
| | | SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes |
| RidsNrrDlrRlrb | | ------------- |
| | | JDonohew GPick, RIV SCochrum, RIV CLong, RIV SRay VGoel |
| RidsNrrDlrRlrc | |
| | |
| RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe | |
| | |
| RidsNrrDeEemb | |
| | |
| RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter | |
| | |
| RidsNrrAdes | |
| | |
| ------------- | |
| | |
| JDonohew GPick, RIV SCochrum, RIV | |
| | |
| CLong, RIV | |
| | |
| SRay VGoel 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 PO 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. 10 th Avenue, 2nd Floor Topeka, KS 66612-1597
| |
| | |
| County Clerk Coffey County Courthouse
| |
| | |
| 110 South 6 th 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 PO Box 411 Burlington, KS 66839
| |
| | |
| Supervisor Licensing
| |
| | |
| Wolf Creek Nuclear Operating Corporation PO 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 PO Box 411 Burlington, KS 66839 Lorrie I. Bell, Project Manager
| |
| | |
| Wolf Creek Nuclear Operating Corporation PO Box 411 Burlington, KS 66839 Mr. Gordon A. Clefton Nuclear Energy Institute
| |
|
| |
|
| 1776 I Street, NW, Suite 400 Washington, DC 20006-3708}} | | Wolf Creek Generating Station cc: |
| | Jay Silberg, Esq. Supervisor Licensing Pillsbury Winthrop Shaw Pittman, LLP Wolf Creek Nuclear Operating Corporation 2300 N Street, NW PO Box 411 Washington, DC 20037 Burlington, KS 66839 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 611 Ryan Plaza Drive, Suite 400 8201 NRC Road Arlington, TX 76011-7005 Steedman, MO 65077-1032 Senior Resident Inspector Kevin J. Moles, Manager U.S. Nuclear Regulatory Commission Regulatory Affairs PO Box 311 Wolf Creek Nuclear Operating Corporation Burlington, KS 66839 PO Box 411 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission Lorrie I. Bell, Project Manager 1500 SW Arrowhead Road Wolf Creek Nuclear Operating Corporation Topeka, KS 66604-4027 PO Box 411 Burlington, KS 66839 Office of the Governor State of Kansas Mr. Gordon A. Clefton Topeka, KS 66612 Nuclear Energy Institute 1776 I Street, NW, Suite 400 Attorney General Washington, DC 20006-3708 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 PO Box 411 Burlington, KS 66839}} |
|
---|
Category:Letter
MONTHYEARML24352A0322024-12-17017 December 2024 Notification of Post Approval Site Inspection for License Renewal and Request for Information IR 05000482/20240142024-12-17017 December 2024 Comprehensive Engineering Team Inspection Report 05000482/2024014 05000482/LER-2024-002-01, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-12-11011 December 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve IR 05000482/20244022024-12-0505 December 2024 Security Baseline Inspection Report 05000482/2024402 ML24337A0132024-12-0202 December 2024 Cycle 27 Core Operating Limits Report, Revision 1 ML24306A2192024-11-0101 November 2024 Results of the Steam Generator Tube Inservice Inspection During the 26th Refueling Outage to Reflect TSTF-577 Reporting Requirements IR 05000482/20240032024-11-0101 November 2024 Integrated Inspection Report 05000482/2024003 IR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications 2024-09-06
[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 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 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 ML18074A3102018-04-0606 April 2018 Request for Additional Information License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning System (CAC No. MF9961; EPID L-2017-LLA-0262) 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 2022-06-29
[Table view] |
Text
February 28, 2008 Mr. Terry Garrett Vice President, Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION
Dear Mr. Garrett:
By letter dated September 27, 2006, Wolf Creek Nuclear Operating Corporation (WCNOC) submitted an application pursuant to 10 CFR Part 54, to renew the operating license NPF-42 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. Further requests for additional information may be issued in the future.
Items in the enclosure were discussed with Ms. Lorrie Bell; and a mutually agreeable date for the response is within 30 days from the date of this letter or no later than April 1, 2008. If you have any questions, please contact me at 301-415-3617 or by e-mail at TXT1@nrc.gov.
Sincerely,
/RA/
Tam Tran, Project Manager Project Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
As Stated cc w/encl: See next page
ML080530067 OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR NAME YEdmonds T. Tran L. Lund DATE 02/27/08 02/27/08 02/28/08
WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION Metal Fatigue Analyses Follow-up RAI for 4.3-1 The applicants responses provided in letters dated October 3, and 17, 2007, did not address the staffs concerns as stated in RAI 4.3-1. The October 3, 2007, letter stated that 1D transfer functions were developed for HL surge line nozzle and the charging nozzles in the vicinity of the nozzle to pipe welds. It went on to state that the development of the transfer functions takes full advantage of the local geometry and symmetry. However, the staff finds no axis of symmetry at the nozzle corners. Further, at the nozzle to pipe welds, the loading is not symmetric if thermal stratification is present. Therefore, the validity of transfer functions developed by using 1-D peak stress is not applicable at these locations. In order to enable the staff to make a determination on this issue, the applicant is requested to perform an environmentally-assisted fatigue analysis and provide results to the NRC Staff of a 3-D finite element analysis using an industry-accepted computer code, such as ANSYS. The analysis should cover nozzle corners with geometrical discontinuities and at locations where thermal stratification loading is significant. This analysis shall follow the rules of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section III, Subsection NB-3200, requiring the use of six stress components to define the stress state and determine the alternating stress intensities.
Follow-up RAI for 4.3-3 Wolf Creek Generating Stations (WCGS) commitment closure letter (ET 08-007), dated January 25, 2008, does not address the following commitments on Page 14 of the October 3, 2007, letter (ET 07-0046):
(1) Since WCGS implemented the modified operating procedure (MOP) prior to 1995, it is reasonable to suspect that heat-ups during PERIOD1 would have more insurge/outsurge cycles than PERIOD2. WCNOC agrees with this assertion, and will commit to updating the baseline to account for this factor. The baseline will be increased based on the expected number of additional insurge/outsurge cycles that would be accumulated in a pre-MOP environment.
(2) In a follow-up discussion, the reviewers further noted that the cumulative usage factors back-projection did not consider the relative severity of charging and letdown transients.
However, in the revised baseline, Wolf Creek will explicitly consider the differential contribution of fatigue for each category of charging event.
The January 25, 2008, letter did not close commitments made by WCGS in the October 3, 2007, letter as quoted above. Please provide additional calculations and discussions to address the committed actions regarding the additional insurge/outsurge cycles and the differential contribution of fatigue for each category of charging event.
Letter to Wolf Creek from T. Tran, dated February 28, 2008 DISTRIBUTION:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, LICENSE RENEWAL APPLICATION HARD COPY:
DLR R/F E-MAIL:
PUBLIC SSmith (srs3)
SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDci RidsNrrDra RidsNrrDe RidsNrrDeEemb RidsNrrDeEeeb RidsNrrDss RidsOgcMailCenter RidsNrrAdes
JDonohew GPick, RIV SCochrum, RIV CLong, RIV SRay VGoel
Wolf Creek Generating Station cc:
Jay Silberg, Esq. Supervisor Licensing Pillsbury Winthrop Shaw Pittman, LLP Wolf Creek Nuclear Operating Corporation 2300 N Street, NW PO Box 411 Washington, DC 20037 Burlington, KS 66839 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 611 Ryan Plaza Drive, Suite 400 8201 NRC Road Arlington, TX 76011-7005 Steedman, MO 65077-1032 Senior Resident Inspector Kevin J. Moles, Manager U.S. Nuclear Regulatory Commission Regulatory Affairs PO Box 311 Wolf Creek Nuclear Operating Corporation Burlington, KS 66839 PO Box 411 Burlington, KS 66839 Chief Engineer, Utilities Division Kansas Corporation Commission Lorrie I. Bell, Project Manager 1500 SW Arrowhead Road Wolf Creek Nuclear Operating Corporation Topeka, KS 66604-4027 PO Box 411 Burlington, KS 66839 Office of the Governor State of Kansas Mr. Gordon A. Clefton Topeka, KS 66612 Nuclear Energy Institute 1776 I Street, NW, Suite 400 Attorney General Washington, DC 20006-3708 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 PO Box 411 Burlington, KS 66839