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| : 1. Section 5 (top of page 4) of the relief request states that the techniques described inSections I-2000 and I-3000 of Code Case N-729-1 were validated in the Westinghouse report, WCAP-16589-P, Revision 0, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: | | : 1. Section 5 (top of page 4) of the relief request states that the techniques described inSections I-2000 and I-3000 of Code Case N-729-1 were validated in the Westinghouse report, WCAP-16589-P, Revision 0, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: |
| Wolf Creek," August 2006. | | Wolf Creek," August 2006. |
| (1) Describe the validation process (e.g., how the validation was performed andwhat parameters were reviewed).
| | (1) Describe the validation process (e.g., how the validation was performed andwhat parameters were reviewed). |
| (2) Section 5.2 of the relief request states that the fracture mechanics analysis in WCAP-16589-P does not fully meet the requirements stated in I-3200(a) Method 1 of Code Case N-729-1 because the analysis used the crack growth formula in EPRI MRP-55.
| | (2) Section 5.2 of the relief request states that the fracture mechanics analysis in WCAP-16589-P does not fully meet the requirements stated in I-3200(a) Method 1 of Code Case N-729-1 because the analysis used the crack growth formula in EPRI MRP-55. |
| Subarticle I-3200(a)(6) requires the use of crack growth rate fromAppendix O of the ASME Code, Section XI, 2004 edition. | | Subarticle I-3200(a)(6) requires the use of crack growth rate fromAppendix O of the ASME Code, Section XI, 2004 edition. |
| Clarify why the WCAP-16589-P does not fully meet the requirements of I-3200(a) of Code Case N-729-1 in terms of the crack growth formula. | | Clarify why the WCAP-16589-P does not fully meet the requirements of I-3200(a) of Code Case N-729-1 in terms of the crack growth formula. |
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| Their configuration poseschallenges to achieve the required examination coverage. | | Their configuration poseschallenges to achieve the required examination coverage. |
| However, the licensee onlyasks relief for penetration nozzle numbers 77 and 78 because these two penetration nozzles could not achieve the required coverage. | | However, the licensee onlyasks relief for penetration nozzle numbers 77 and 78 because these two penetration nozzles could not achieve the required coverage. |
| (1) Provide the examination coverage (the distance) for penetration nozzle numbers 74, 75, and 76.
| | (1) Provide the examination coverage (the distance) for penetration nozzle numbers 74, 75, and 76. |
| (2) Discuss why nozzle numbers 74, 75, and 76 are able to meet the required coverage but not nozzle numbers 77 and 78 if they all have the same configuration.
| | (2) Discuss why nozzle numbers 74, 75, and 76 are able to meet the required coverage but not nozzle numbers 77 and 78 if they all have the same configuration. |
| : 3. Section 5.3 of the relief request states that the radiation levels under the reactor vesselhead are estimated to be 10,000 millirem (mRem)/hr at the bottom of the control rod drive mechanism (CRDM) nozzles resulting in an exposure of approximately 2500 mRem per | | : 3. Section 5.3 of the relief request states that the radiation levels under the reactor vesselhead are estimated to be 10,000 millirem (mRem)/hr at the bottom of the control rod drive mechanism (CRDM) nozzles resulting in an exposure of approximately 2500 mRem per |
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| The licensee stated that the reactor vessel headconfiguration at Seabrook Station is similar to that at Wolf Creek. | | The licensee stated that the reactor vessel headconfiguration at Seabrook Station is similar to that at Wolf Creek. |
| At Seabrook Station,radiation levels under the reactor vessel head were measured during their previous inspection in 2006 and ranged from 7000 mRem/hr to 10,000 mRem/hr at the bottom of the CRDM nozzles. | | At Seabrook Station,radiation levels under the reactor vessel head were measured during their previous inspection in 2006 and ranged from 7000 mRem/hr to 10,000 mRem/hr at the bottom of the CRDM nozzles. |
| (1) Explain why Wolf Creek does not have its own plant-specific radioactive dose rates measured at the bottom of the CRDM nozzles from the examinations performed in 2006.
| | (1) Explain why Wolf Creek does not have its own plant-specific radioactive dose rates measured at the bottom of the CRDM nozzles from the examinations performed in 2006. |
| (2) Discuss whether the radiation dose will be measured at thebottom of the CRDM nozzles to confirm the estimation of 10,000 mRem/hour during the upcoming examination scheduled for February 2013.
| | (2) Discuss whether the radiation dose will be measured at thebottom of the CRDM nozzles to confirm the estimation of 10,000 mRem/hour during the upcoming examination scheduled for February 2013. |
| If not, provide justificationand hardship. | | If not, provide justificationand hardship. |
| : 4. Provide the end date of the third 10-year inservice inspection interval. | | : 4. Provide the end date of the third 10-year inservice inspection interval. |
| : 5. Section 5.2 of the relief request states that the flaw tolerance chart demonstrates that apostulated through-wall flaw at the bottom edge of the proposed alternative examination zone will not grow to the toe of the J-groove weld within an inspection interval of four refueling cycles.(1) Provide the as-designed (i.e., as-analyzed) and as-built dimensions of the J-groove weld. | | : 5. Section 5.2 of the relief request states that the flaw tolerance chart demonstrates that apostulated through-wall flaw at the bottom edge of the proposed alternative examination zone will not grow to the toe of the J-groove weld within an inspection interval of four refueling cycles.(1) Provide the as-designed (i.e., as-analyzed) and as-built dimensions of the J-groove weld. |
| (2) Discuss whether the flaw evaluation in WCAP-16589-P is based on the as-designed or as-built J-groove weld dimensions.
| | (2) Discuss whether the flaw evaluation in WCAP-16589-P is based on the as-designed or as-built J-groove weld dimensions. |
| If the flaw evaluation was based onthe as-designed dimensions, demonstrate that it bounds the flaw evaluation of the as-built dimension.}} | | If the flaw evaluation was based onthe as-designed dimensions, demonstrate that it bounds the flaw evaluation of the as-built dimension.}} |
Letter Sequence RAI |
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MONTHYEARET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2012-07-0202 July 2012 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds Project stage: Other ML12216A0272012-08-0303 August 2012 Acceptance Review Email, Relief Request I3R-07 from ASME Code Case N-7229 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML12248A0802012-09-0404 September 2012 Email, Request for Additional Information, Relief Request I3R-07 from ASME Code Case N-729-1 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval Project stage: RAI ET 12-0024, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2012-10-15015 October 2012 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds Project stage: Response to RAI ML12353A2412013-01-0404 January 2013 Relief Request I3R-07 from ASME Code Case N-729-1 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval Project stage: Other 2012-08-03
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Category:E-Mail
MONTHYEARML23360A1562023-12-26026 December 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise the Ventilation Filter Testing Program in Technical Specifications ML23166A0622023-06-15015 June 2023 NRR E-mail Capture - Acceptance Review - Wolf Creek Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded post-tensioning System Components ML23090A1042023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML23090A0072023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Relief for Follow-Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface ML23080A0652023-03-21021 March 2023 NRR E-mail Capture - Wolf Creek Generating Station Evacuation Time Estimate Analysis Review ML23026A0222023-01-25025 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ML23009A4082023-01-0909 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise TS to Adopt Technical Specification Task Force (TSTF)-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22361A0052022-12-27027 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 ML22251A1312022-09-0808 September 2022 NRR E-mail Capture - Acceptance Review - Wolf Creek Request for Deviation from Fire Protection Program Requirements to Allow Use of Portable Lighting ML22215A2742022-08-0202 August 2022 Inservice Inspection Request for Information ML22208A1322022-07-27027 July 2022 NRR E-mail Capture - Wolf Creek Table of Contents LAR ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22131A0522022-05-11011 May 2022 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek Inservice Inspection Relief Request for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface 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 ML22026A4392022-01-26026 January 2022 NRR E-mail Capture - Wolf Creek Acceptance Review Results - Removal of TS Table of Contents (L-2022-LLA-0008) 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 ML21309A0332021-11-0505 November 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.8.1, AC Sources - Operating ML21307A4202021-11-0303 November 2021 NRR E-mail Capture - Acceptance Review - 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 ML21259A0652021-09-16016 September 2021 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek License Amendment and Exemption Requests Regarding 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 ML21189A0252021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Request Revision to the Emergency Plan Related to on-shift Staffing ML21230A3922021-05-19019 May 2021 May 19, 2021 Dricks Response to Gurdziel Letter Dated May 13, 2021 - August 17, 2021 ML21102A3342021-04-12012 April 2021 Email 4-12-21 RFI for In-Office Rvw of Recent RERP and a Related EPIP Change ML21064A0342021-03-0404 March 2021 NRR E-mail Capture - Wolf Creek Generating Station Upcoming Steam Generator Tube Inservice Inspection ML20353A2712020-12-18018 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML20349A3092020-12-14014 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Change to Owner Licensee Names ML20297A3022020-10-22022 October 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 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 ML20191A0222020-07-0606 July 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request in Support of Replacement Engineered Safety Features Transformers with Load Tap Changers ML20162A1642020-06-0909 June 2020 Email June 9, 2020 - RFI in Preparation for Wolf Creek EP Program Inspection ML20149K4272020-05-22022 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20132A3442020-05-11011 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19273A0232019-09-30030 September 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, ML19268B7172019-09-25025 September 2019 NRR E-mail Capture - Acceptance Review - Inservice Inspection (ISI) Program Relief Request to Use Code Case N-666-1 ML19261A2272019-09-18018 September 2019 NRR E-mail Capture - Regulatory Audit Plan - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 3.3.5 ML19255H3032019-09-12012 September 2019 NRR E-mail Capture - Acceptance Review - Relief Request I4R-07 to Utilize Code Case N-513-4 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 ML19274D2752019-07-31031 July 2019 Request for Information-IR 05000482 2019-004, Dated 7/31/2019 ML19203A2362019-07-19019 July 2019 LTR-19-0291 Tom Gurdziel, E-mail July 18, 2019, Confirmatory Order on Wolf Creek ML19112A1772019-04-22022 April 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ML19091A0362019-03-29029 March 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ML19065A0982019-03-0606 March 2019 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Revision to Technical Specifications to Adopt TSTF-529 ML19036A6832019-02-0505 February 2019 LTR-18-0498 - Email Response - Sheryl Sweet, Licensing Engineer, Wolf Creek Nuclear, E-mail Acronyms for NRC Personnel 2023-06-15
[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
[Table view] |
Text
From:Benney, Brian To:Wideman Steve G; Muilenburg William T Cc:Burkhardt, Janet; Chen, Qiao-Lynn
Subject:
ME9078 Request for Additional Iinformation (RAI)
Date:Tuesday, September 04, 2012 9:46:01 AMSeptember 4, 2012
Mr. Steve G. Wideman Wolf Creek Generating Station Wolf Creek Nuclear Operating Company
Dear Mr. Wideman:
By letter dated July 2, 2012 (Agencywide Documents Access and Management System Accession No. ML12193A559), the Wolf Creek Nuclear Operating Corporation (WCNOC) submitted Relief Request 13R-07, requesting relief from ASME Code Case N-729-1 for examination of Reactor Vessel Head Penetration welds.
The NRC staff has reviewed the information provided by WCNOC and determined that additional information is needed to complete its review. The request for additional information (RAI) is provided as an attachment to this e-mail. The staff is requesting a written response to the RAls no later than October 15, 2012.
Please contact me if you have a concern meeting the proposed schedule for responding to this request and/or if WCNOC would like to have a conference call to discuss the RAls.
Sincerely, Brian Benney, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission (301) 415-2767
Brian.Benney@nrc.gov
REQUEST FOR ADDITIONAL INFORMATIONREQUEST I3R-07EXAMINATION OF REACTOR VESSEL HEAD PENETRATION WELDSWOLF CREEK GENERATING STATION UNIT 1WOLF CREEK NUCLEAR OPERATING CORPORATIONDOCKET NUMBER 50-482
By letter dated July 2, 2012 (Agencywide Documents Access and Management System Accession No. ML12193A559), the Wolf Creek Nuclear Operating Corporation (the licensee) requested relief from certain requirements of the ASME Code, Code Case N-729-1, as conditioned in Title 10, Code of Federal Regulations, Part 50, paragraph 10 CFR 50.55a(g)(6)(ii)(D), for examination of reactor vessel head nozzle penetration welds at theWolf Creek Generating Station Unit 1.
To complete its review, the U.S. Nuclear RegulatoryCommission requests the following additional information.
- 1. Section 5 (top of page 4) of the relief request states that the techniques described inSections I-2000 and I-3000 of Code Case N-729-1 were validated in the Westinghouse report, WCAP-16589-P, Revision 0, "Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation:
Wolf Creek," August 2006.
(1) Describe the validation process (e.g., how the validation was performed andwhat parameters were reviewed).
(2) Section 5.2 of the relief request states that the fracture mechanics analysis in WCAP-16589-P does not fully meet the requirements stated in I-3200(a) Method 1 of Code Case N-729-1 because the analysis used the crack growth formula in EPRI MRP-55.
Subarticle I-3200(a)(6) requires the use of crack growth rate fromAppendix O of the ASME Code,Section XI, 2004 edition.
Clarify why the WCAP-16589-P does not fully meet the requirements of I-3200(a) of Code Case N-729-1 in terms of the crack growth formula.
- 2. Section 4 of the relief request states that penetration nozzle numbers 74 through 78have a threaded outside diameter and an internal taper.
Their configuration poseschallenges to achieve the required examination coverage.
However, the licensee onlyasks relief for penetration nozzle numbers 77 and 78 because these two penetration nozzles could not achieve the required coverage.
(1) Provide the examination coverage (the distance) for penetration nozzle numbers 74, 75, and 76.
(2) Discuss why nozzle numbers 74, 75, and 76 are able to meet the required coverage but not nozzle numbers 77 and 78 if they all have the same configuration.
- 3. Section 5.3 of the relief request states that the radiation levels under the reactor vesselhead are estimated to be 10,000 millirem (mRem)/hr at the bottom of the control rod drive mechanism (CRDM) nozzles resulting in an exposure of approximately 2500 mRem per
nozzle. Section 5.3 further states that these dose rates are consistent with dose ratesmeasured at the Seabrook Station during 2006, as reported in a Seabrook Station request for relief dated October 27, 2011.
The licensee stated that the reactor vessel headconfiguration at Seabrook Station is similar to that at Wolf Creek.
At Seabrook Station,radiation levels under the reactor vessel head were measured during their previous inspection in 2006 and ranged from 7000 mRem/hr to 10,000 mRem/hr at the bottom of the CRDM nozzles.
(1) Explain why Wolf Creek does not have its own plant-specific radioactive dose rates measured at the bottom of the CRDM nozzles from the examinations performed in 2006.
(2) Discuss whether the radiation dose will be measured at thebottom of the CRDM nozzles to confirm the estimation of 10,000 mRem/hour during the upcoming examination scheduled for February 2013.
If not, provide justificationand hardship.
- 4. Provide the end date of the third 10-year inservice inspection interval.
- 5. Section 5.2 of the relief request states that the flaw tolerance chart demonstrates that apostulated through-wall flaw at the bottom edge of the proposed alternative examination zone will not grow to the toe of the J-groove weld within an inspection interval of four refueling cycles.(1) Provide the as-designed (i.e., as-analyzed) and as-built dimensions of the J-groove weld.
(2) Discuss whether the flaw evaluation in WCAP-16589-P is based on the as-designed or as-built J-groove weld dimensions.
If the flaw evaluation was based onthe as-designed dimensions, demonstrate that it bounds the flaw evaluation of the as-built dimension.