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MONTHYEARML0701601892006-12-19019 December 2006 12/19/2006, Viewgraphs from Meeting with Wolf Creek Generating Station to Discuss License Renewal Process and Environmental Scoping Project stage: Meeting ML0701201212006-12-19019 December 2006 Transcript of Wolf Creek Nuclear Generating Station Environmental Scoping Meeting, 12/19/2006, Page 1-22 Project stage: Request ML0701201142006-12-19019 December 2006 Environmental Scoping Public Meeting Evening Session Transcripts Project stage: Request ML0701803672007-01-11011 January 2007 Operating Corporation - Response to Request for Additional Information Regarding the Review of the License Renewal Application Project stage: Response to RAI ML0701704732007-01-19019 January 2007 12/19/2006 Summary of Public Meetings Related to the Review of the Wolf Creek Generating Station License Renewal Application Project stage: Meeting ML0702405542007-02-0707 February 2007 Request for Additional Information Regarding Severe Accident Mitigation Alternatives for Wolf Creek Generating Station Project stage: RAI ML0702305462007-02-21021 February 2007 Environmental Site Audit Regarding Wolf Creek Generating Station License Renewal Application Project stage: Other ML0722505722007-03-14014 March 2007 Meeting Minute Notes Captured by Bob Dover (Earth Tech) on March 13-14, 2007 During Wolf Creek Environmental Site Audit Project stage: Request ML0708511882007-04-0909 April 2007 Request for Additional Information Regarding the Environmental Site Audit Conducted at Wolf Creek Generating Station During the Week of March 16, 2007 Project stage: RAI ML0710802612007-04-18018 April 2007 E-mail Dated 4/18/07 - Lorrie Bell (Wolf Creek Nuclear Operating Corporation) to Christian Jacobs (NRC) Regarding Response to Questions Posed by NRC During March 20, 2007 Telecon Project stage: Request ML0712700402007-04-27027 April 2007 Administrative Procedure AP 07B-003, Revision 6, Offsite Dose Calculation Manual. Project stage: Request ML0710300772007-04-27027 April 2007 Summary of Site Audit Related to the Review of the License Renewal Application for Wolf Creek Generating Station, Unit 1 Project stage: Approval ML0708505382007-05-0101 May 2007 Issuance of Environmental Scoping Summary Report Associated with the Staff'S Review of the Application by Wolf Creek Nuclear Operating License for Wolf Creek Generating Station Project stage: Approval ML0724202502007-06-21021 June 2007 Summary of Phone Conversation Conducted Between John Szeligowski (Earth Tech) and Larry Holloway (Kansas Corporation Commission) on June 21, 2007 Regarding Alternatives Analysis for WCGS EIS Project stage: Request ML0718401902007-06-26026 June 2007 Response to NRC Request for Follow-up Information Regarding Severe Accident Mitigation Alternatives, Related to License Renewal Application Project stage: Request ML0718401882007-06-26026 June 2007 Response to NRC Requests for Follow-up Information Regarding Severe Accident Mitigation Alternatives for Wolf Creek Generating Station License Renewal Application Project stage: Other ML0720003122007-07-13013 July 2007 Summary of Impact to Wolf Creek License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Error Project stage: Other ML0723404432007-08-15015 August 2007 Summary of the Impact to Wolf Creek Generating Station License Renewal Application Severe Accident Mitigation Alternatives Analysis Due to Computer Program Errors Project stage: Other ML0722204792007-09-18018 September 2007 Notice of Availability of the Draft Plant-Specific Supplement 32 to the GEIS Regarding Wolf Creek Generating Station, Unit 1 (FRN) Project stage: Draft Other ML0722204492007-09-18018 September 2007 Letter from NRC to Wolf Creek Nuclear Operating Corporation Project stage: Other Press Release-IV-07-036, - NRC to Hold Public Meetings on Draft Environmental Impact Statement for Wolf Creek License Renewal Application2007-09-19019 September 2007 Press Release-IV-07-036 - NRC to Hold Public Meetings on Draft Environmental Impact Statement for Wolf Creek License Renewal Application Project stage: Request ML0724201492007-09-20020 September 2007 Letter from NRC to Us Fish & Wildlife Service Biological Assessment for License Renewal of Wolf Creek Generating Station Project stage: Other ML0728202872007-09-24024 September 2007 Comment (1) of Jim Hays, on Behalf of Kansas Dept. of Wildlife & Parks Regarding Supplement 32 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Wolf Creek, Unit 1 Project stage: Supplement ML0725400262007-09-30030 September 2007 NUREG-1437, Suppl 32, Dfc, Generic Environmental Impact Statement for the License Renewal of Nuclear Plants: Regarding Wolf Creek Generating Station, Draft for Comment. Project stage: Draft Other ML0732403112007-11-0808 November 2007 Draft EIS Wolf Creek Public Meeting: Afternoon Project stage: Request ML0732402882007-11-0808 November 2007 Official Transcript of Draft EIS Wolf Creek Generating Station Public Meeting: Evening Session on November 8, 2007 in Burlington, Kansas. Pages 1 - 15 Project stage: Request ML0809501772008-05-0808 May 2008 Notice of Availability of the Final Plant-Specific Supplement 32 to the Generic Environmental Impact Statement for Licence Renewal of Nuclear Plants Regarding Wolf Creek Generating Station Project stage: Other ML0812807492008-05-0808 May 2008 Notice of Availability of the Final Plant-Specific Supplement 32 to the Generic Environmental Impact Statement for Licence Renewal of Nuclear Plants Regarding Wolf Creek Generating Station (TAC MD3182) - FRN Project stage: Other ML0812606082008-05-31031 May 2008 NUREG-1437, Supp No. 32, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Final Report Project stage: Acceptance Review ML0810602772008-06-0606 June 2008 Final Supplement 32 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Wolf Creek Generating Station Nuclear Power Plant Project stage: Other 2007-06-21
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Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[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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Text
February 7, 2007 Mr. Terry J. Garrett Vice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR WOLF CREEK GENERATING STATION (TAC NO. MD3182)
Dear Mr. Garrett:
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Severe Accident Mitigation Alternatives (SAMA) analysis submitted by Wolf Creek Nuclear Operating Corporation, in support of its application for license renewal for the Wolf Creek Generating Station, and has identified areas where additional information is needed to complete its review.
Enclosed is the staffs request for additional information (RAI).
We request that you provide your responses to these questions within 60 days of the date of this letter, in accordance with the license renewal review schedule. If you have any questions, please contact me at 301-415-3874 or via email at cjj@nrc.gov.
Sincerely,
/RA/
Christian Jacobs, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
As stated cc w/encl: See next page
February 7, 2007 Mr. Terry J. Garrett Vice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR WOLF CREEK GENERATING STATION (TAC NO. MD3182)
Dear Mr. Garrett:
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the Severe Accident Mitigation Alternatives (SAMA) analysis submitted by Wolf Creek Nuclear Operating Corporation, in support of its application for license renewal for the Wolf Creek Generating Station, and has identified areas where additional information is needed to complete its review.
Enclosed is the staffs request for additional information (RAI).
We request that you provide your responses to these questions within 60 days of the date of this letter, in accordance with the license renewal review schedule. If you have any questions, please contact me at 301-415-3874 or via email at cjj@nrc.gov.
Sincerely,
/RA/
Christian Jacobs, Project Manager Environmental Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION: See next page Adams Accession No: ML070240554 OFFICE LA:DLR PM:DLR:REBB GS:DLR:REBB BC:DLR:REBB NAME SFigueroa CJacobs VRodriguez RFranovich DATE 1/31/07 2/5/07 2/5/07 2/7/07 OFFICIAL RECORD COPY
Letter to T. Garrett from C. Jacobs Dated February 7, 2007
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING SEVERE ACCIDENT MITIGATION ALTERNATIVES FOR WOLF CREEK GENERATING STATION (TAC NO. MD3182)
DISTRIBUTION:
HARD COPY:
DLR R/F E-MAIL:
P.T. Kuo (RidsNrrDlr)
M. Rubin (RidsNrrDraApla)
R. Franovich (RidsNrrDlrRebb)
E. Benner (RidsNrrDlrReba)
B. Palla R. Schaaf C. Jacobs A. Williamson bobbie.hurley@earthtech.com V. Rodriguez J. Donohew V. Dricks S. Cochrum RidsOGCMailRoom DLR/REBB DLR/REBA VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV
Request for Additional Information (RAI)
Regarding the Analysis of Severe Accident Mitigation Alternatives (SAMAs) for the Wolf Creek Generating Station (WCGS)
- 1. Provide the following information regarding the development of the WCGS probabilistic safety analysis (PSA) used for the SAMA analysis, i.e., the 2002 Update:
- a. Sections F.2.3 and F.2.4 of the environmental report (ER) provide a description of the 1998 and 2002 PSA model changes. For each PSA update, identify which changes had the greatest impact on the core damage frequency (CDF) (e.g., the top five changes).
- b. In Table F.2.2 of the ER, several of the facts and observations (F&Os) have outstanding items or improvements that are underway (e.g., L2-1, QU-9, TH-1, TH-6, and TH-7). Describe the impact of each of these remaining items on the SAMA evaluation. Additionally, for F&O TH-1, which addressed the misuse of Modular Accident Analysis Program (MAAP) 3.0B, describe the plant-specific thermal hydraulic analyses that are of concern and the meaning of the phrase The impact to the WCGS PSA model has been bounded.
- c. Section F.2.7 of the ER states that the Wolf Creek Nuclear Operating Corporation (WCNOC) engineering design process contains procedural screening questions to identify changes with potential impact to the PSA model.
List the changes either implemented or pending following the 2002 PSA update, and discuss their impact on the SAMA evaluation.
- d. The internal flood CDF from the individual plant examination (IPE) is 4.5E-6/y, whereas the updated internal flood analysis is said to have a CDF of 2.5E-6/y.
Provide the following information regarding the internal flood analysis:
- i. a description of the peer review that was performed on the updated flooding analysis, and ii. a description of Scenario 3 (FL3), which was used for screening internal flood related SAMAs from further consideration.
- 2. Provide the following information relative to the Level 2 analysis:
- a. In its evaluation of the IPE, the U.S. Nuclear Regulatory Commission (NRC) indicated that re-analysis of several steam generator tube rupture (SGTR)-initiated sequences using the MAAP code led to the conclusion that core damage was not possible for these sequences within the 24-hour mission time and that the elimination of these SGTR sequences is a weakness of the IPE submittal. Also, the baseline release category frequency table in Section F.2.8 ENCLOSURE
of the ER shows a SGTR contribution to large early release frequency (LERF) of 1.65E-7, which is less than 20 percent of the SGTR CDF contribution. Clarify whether this concern has been addressed in the PSA model used for the SAMA analysis. If this observation is still applicable, explain how it impacts the SAMA evaluation.
- b. In the August 30, 1995, letter responding to NRC RAIs on the IPE, the response to Question 26 discusses the impact of induced SGTRs. Describe the treatment of induced SGTRs in the 2002 Update PSA, and whether SAMAs to address these sequences were considered.
- c. Section F.2.8 of the ER indicates that Release Category A (no containment failure within mission time), was grouped with Release Category S (no containment failure). This treatment is non-conservative since sequences in Release Category A would lead to containment failure after 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Provide an assessment of the impact on the SAMA analysis if the sequences in Release Category A were alternatively assigned to Release Category K (late containment failure).
- d. Justify the assumption in Section F.2.8 of the ER that the conditional probabilities from the original IPE can be used to obtain the non-LERF release categories, and why this approach was used in lieu of rebinning non-LERF sequences using the IPE MAAP runs.
- e. Explain why the total release frequency (3.16E-5/y) is higher than the CDF (2.98E-5/y).
- 3. Provide the following information with regard to the treatment and inclusion of external events in the SAMA analysis:
- a. State the version of the PSA that was used to support the initial fire analysis.
- b. In Section F.5.1.6.1 of the ER, a list of PSA topics that prevent the effective comparison of the CDF between the internal events PSA and the fire PSA is provided. These topics appeared to be derived from NEI 05-01, and are provided as general statements rather than specific arguments applicable to the WCGS Fire Model. State how these assumptions apply to the WCGS Fire Model.
- c. Explain the scope, changes and peer review associated with the fire re-analysis, including the date of the analysis and peer reviews, relative to the fire individual plant examination of eternal events (IPEEE). Provide a comparison between the contributions to CDF for significant fire areas between the fire re-analysis and the fire IPEEE.
- d. The potential enhancement identified in the IPEEE to increase seismic ruggedness for the eight electrical cabinets that have a 0.20g peak ground acceleration (PGA) high confidence in low probability of failure (HCLPF) is indicated as not implemented on the basis that the HCLPF value is acceptable
for reduced scope plants (Sections F.5.1.5 and F.5.1.6.2.2 of the ER). Provide additional justification as to why SAMAs to address this item would not be cost beneficial.
- 4. For the MACCS analyses population projection to year 2040, confirm that the growth rates used for the projection assumed a constant growth rate. Additionally, the population sensitivity analysis in Section F.7.3.2 of the ER states that the baseline population was for the year 2045, yet Section F.3.1 of the ER states that the population was projected to the year 2040. Clarify this discrepancy.
- 5. In Section F.5.1.4 of the ER, six potential improvements are listed from the IPE. The third improvement is listed as not implemented and states that the risk reduction worth (RRW) for the related operator action is 1.001. Yet, the IPE safety evaluation report implies that crediting this improvement would decrease the CDF by 19 percent.
Describe the PSA model changes since the IPE that have reduced this RRW.
- 6. Provide the following with regard to the Phase II cost-benefit evaluations:
- a. For SAMA 1, provide the following information:
- i. a characterization of the sequences that were assumed to be impacted by the SAMA (i.e., SBOS02 through SBOS32).
ii. an explanation why the mitigation of station blackout sequences does not result in the elimination of a larger percentage of early containment failure and containment isolation failure (CIF), since for SAMA 3, the removal of the dual division emergency diesel generator (EDG) and emergency service water failure was assumed to result in removal of all of the cutsets in the CIF release category. Given that a similar concern may apply to SAMA 14, confirm that the explanation provided for SAMA 1 is also relevant to SAMA 14.
- b. For SAMA 2, provide the following information:
- i. an explanation of the difference between the actions taken during extended EDG completion time (CT) and those included in SAMA 2, including the ability to black start under EDG CT conditions without the SAMA 2 modifications.
ii. a cost-benefit evaluation similar to that of other SAMAs for maintaining the extended EDG CT actions 24/7, as an alternative to SAMA 2.
iii. a list of the top contributors to the 0.294 failure of the Sharpe Station to deliver power to the WCGS that is used in SAMA 2, and confirmation that there are no cost-beneficial SAMAs that could reduce these contributions.
- c. Provide the basis for the assumed 5E-2 failure probability to cross-connect used in assessing the benefit of SAMA 3.
- d. Provide the basis for the values used in the determination of break isolation failure probabilities used in assessing the benefit of SAMA 4.
- e. For SAMAs 6 and 7, the ER states that the importance of the associated common cause failure is artificially inflated in the WCGS PSA. The analysis, therefore, gives credit to the ability of operators to manually initiate (SAMA 6) or manually align (SAMA 7) recirculation mode, among other credited operator actions. Clarify whether the credit that is taken in SAMAs 6 and 7 for operator actions are proceduralized, trained upon and/or represent current operational practices (the disposition of the initiating event INIT-VLO in Table F.5-1 of the ER implies that operating procedures and training to initiate injection already exist). If not proceduralized, evaluate the cost-benefit of each of these SAMAs for adding the appropriate procedural guidance.
- f. For SAMA 13, the ER states that installation of a portable fuel oil pump was considered, but gaining access to the fuel oil tanks at WCGS requires a crane and about 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of work. Evaluate the cost-benefit associated with installing a manual fuel oil transfer pump in parallel (but valved out) with the current fuel oil transfer pump, or some other alternative that would not require access to the fuel oil tanks.
- g. For SAMA 15, provide the following information:
- i. a more detailed description of the modifications for Cases 1 and 2, sufficient to understand what is included in the cost estimate, and ii. the basis for the assumption that the fire events comprise 85 percent of the external events risk, since this equates to a fire risk of 2.6E-5 (3E-5 x 0.85) and implies a fire risk much higher than the conservative fire CDF of 5.9E-6/y.
- h. For SAMA 16, provide the bases for the 0.1 failure probability of the operator to diagnose and realign the component cooling water (CCW) system to take advantage of a CCW cross-tie.
- i. The ER states that cost-beneficial SAMAs 4 (Case 2), 5, and 13 should all be considered for implementation, but is vague regarding WCNOCs intentions for SAMAs 1, 2, 3, and 14. While recommendations are stated for implementing combinations of these remaining SAMAs, Section F.8 of the ER is unclear about specifically which of these SAMAs WCNOC plans to implement and which are planned for continued consideration. Specifically indicate whether each of these SAMAs will be considered for implementation. Note that Section 4.20 of the ER states that only six potentially cost-beneficial SAMAs exist, while the SAMA analysis conclusions identify seven. Clarify this discrepancy.
- 7. For certain SAMAs considered in the ER, there may be lower-cost alternatives that could achieve much of the risk reduction at a lower cost. In this regard, discuss whether any lower-cost alternatives to those Phase II SAMAs considered in the ER would be viable and potentially cost-beneficial. Evaluate the following SAMAs (previously found to
be potentially cost-beneficial at other plants), or indicate if the particular SAMA has already been considered. If the latter, indicate whether the SAMA has been implemented or has been determined to not be cost-beneficial at WCGS:
- a. Use portable generator to extend the coping time in loss of AC power events (to power selected instrumentation and DC power to the turbine-driven auxiliary feedwater pump).
- b. Provide alternate DC feeds (using a portable generator) to panels supplied only by DC bus.
- c. Add an alternate AC source to the site as an alternative to Sharpe Station.
Wolf Creek Generating Station cc:
Jay Silberg, Esq. Vice President Operations/Plant Manager Pillsbury Winthrop Shaw Pittman, LLP Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P.O. Box 411 Washington, DC 20037 Burlington, KS 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 400 P.O. Box 411 Arlington, TX 76011-7005 Burlington, KS 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant P.O. Box 311 8201 NRC Road Burlington, KS 66839 Steedman, MO 65077-1032 Chief Engineer, Utilities Division Kevin J. Moles, Manager Kansas Corporation Commission Regulatory Affairs 1500 SW Arrowhead Road Wolf Creek Nuclear Operating Corporation Topeka, KS 66604-4027 P.O. Box 411 Burlington, KS 66839 Office of the Governor State of Kansas Lorrie I. Bell, Project Manager Topeka, KS 66612 Wolf Creek Nuclear Operating Corporation P.O. Box 411 Attorney General Burlington, KS 66839 120 S.W. 10th Avenue, 2nd Floor Topeka, KS 66612-1597 Mr. James Ross Nuclear Energy Institute County Clerk 1776 I Street, NW, Suite 400 Coffey County Courthouse Washington, DC 20006-3708 110 South 6th Street Burlington, KS 66839 Ms. Valerie Williams, Branch Director Coffey County Library Thomas A. Conley, Section Chief Burlington Branch Radiation and Asbestos Control 410 Juniatta St.
Kansas Department of Health Burlington, KS 66839 and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366