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| | number = ML090620146 | | | number = ML090620146 |
| | issue date = 03/27/2009 | | | issue date = 03/27/2009 |
| | title = Wolf Creek Generating Station - Request for Additional Information Relief Request 13R-06, Alternatives to Requirements of ASME Code, Section Xi for Class 1 Piping Welds Examined from Inside the Reactor Vessel | | | title = Request for Additional Information Relief Request 13R-06, Alternatives to Requirements of ASME Code, Section XI for Class 1 Piping Welds Examined from Inside the Reactor Vessel |
| | author name = Singal B K | | | author name = Singal B |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = Muench R A | | | addressee name = Muench R |
| | addressee affiliation = Wolf Creek Nuclear Operating Corp | | | addressee affiliation = Wolf Creek Nuclear Operating Corp |
| | docket = 05000482 | | | docket = 05000482 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 r1arch 27, 2009 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 WOLF CREEK GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST 13R-06, ALTERNATIVE TO THE EXAMINATION REQUIREMENTS OF ASME SECTION XI FOR CLASS 1 PIPING WELDS EXAMINED FROM THE INSIDE OF THE REACTOR VESSEL (TAC NO. MD9658) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 r1arch 27, 2009 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839 |
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| | ==SUBJECT:== |
| | WOLF CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST 13R-06, ALTERNATIVE TO THE EXAMINATION REQUIREMENTS OF ASME SECTION XI FOR CLASS 1 PIPING WELDS EXAMINED FROM THE INSIDE OF THE REACTOR VESSEL (TAC NO. MD9658) |
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| ==Dear Mr. Muench:== | | ==Dear Mr. Muench:== |
| By letter dated September 16, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML082670891), Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI requirements. | | |
| The licensee proposed an alternative to the depth sizing requirements of ASME Code Cases N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," and N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface," for the third 1 O-year inservice inspection interval at Wolf Creek Generating Station. Based on its review, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete the evaluation for the above request for relief. The NRC staff's request for additional information (RAI) is contained in the enclosure to this letter. These RAts were sent to Ms. Diane Hooper of WCNOC via e-mail on February 23, 2009 and discussed with WCNOC staff on March 5, 2009. Ms. Hooper agreed that WCNOC will provide its RAI response within 30 days from the date of issuance of this letter. | | By letter dated September 16, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML082670891), Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI requirements. The licensee proposed an alternative to the depth sizing requirements of ASME Code Cases N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," and N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface," for the third 1O-year inservice inspection interval at Wolf Creek Generating Station. |
| R. Muench -2 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for the NRC staff to complete its review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | Based on its review, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete the evaluation for the above request for relief. |
| Sincerely, i l b, Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 | | The NRC staff's request for additional information (RAI) is contained in the enclosure to this letter. These RAts were sent to Ms. Diane Hooper of WCNOC via e-mail on February 23, 2009 and discussed with WCNOC staff on March 5, 2009. Ms. Hooper agreed that WCNOC will provide its RAI response within 30 days from the date of issuance of this letter. |
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| | R. Muench -2 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for the NRC staff to complete its review and contribute toward the NRC's goal of efficient and effective use of staff resources. |
| | Sincerely, b~ \L0~~ i l b, ~~ |
| | Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482 |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 13R-06 WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 By letter dated September 16, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML082670891), Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI requirements. | | As stated cc w/encl: Distribution via Listserv |
| WCNOC proposed an alternative to the depth sizing error requirements of ASME Code Cases N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," and N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface," for the third 1 O-year inservice inspection interval at Wolf Creek Generating Station (WCGS). Since 2004, the Energy Power Research Institute
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| -Performance Demonstration Initiative (PDI) representatives and U.S. Nuclear Regulatory Commission (NRC) staff have actively discussed the ASME Code requirements for depth sizing flaws in piping. At the December 2 and 3, 2008, public meeting with PDI and industry representatives, the NRC staff gave a presentation titled, "NRC Perspectives on Inside Diameter Pipe Examinations Depth Sizing Root Mean Square Error," (ADAMS Accession Nos. ML090760523 and ML090760528). The presentation identified potential issues with the current qualification test specimens and suggested that surface flatness issues as a possible hindrance in the qualification process. Securing the appropriate test specimens and acquiring appropriate qualifications may be impractical for WCNOC prior to the next refueling outage. Based on its review of the WCNOC's submittal, the NRC staff has determined that the following additional information is required to complete an evaluation for impracticality.
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| Flaw Depth Sizing Alternative Page 1 of the application identified welds as either Category B-F or Category B-J. Please provide representative sketches of the configurations and identify the weld and base material (carbon steel, stainless steel, Inconel, etc). Include in the sketches the impediments that are preventing the Code-required examinations. Page 4 of the application indicates that these welds were examined during fourteenth refueling outage (RF14). If the vendor being used for the welds in this request is the same vendor that was used for RF14, please provide a discussion on the vendor's efforts to satisfy the Code-required root mean square error (RMSE) since RF14. The Electric Power Research Institute (EPRI) -PDI identified a surface roughness criterion of 1/32-inch gap beneath the transducer for ultrasonic testing (UT) examinations.
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| The inside diameter (ID) surface roughness of many of PDl's test specimens used for ID performance demonstrations are outside this standard.
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| Having test specimens with an acceptable ID surface provides an
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| -2 opportunity for qualifying to the Code-required 0.125-inch RMSE. The availability of test specimens with acceptable ID surfaces is the responsibility of the entity desiring to use these test specimens in their performance demonstrations.
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| Please discuss the vendor's depth sizing RMSE capabilities when using test specimens made with acceptable ID surfaces. The PDI program test specimens contain ID surface roughness that existed in the field prior to utilities implementing risk-informed inservice inspection (RI lSI) programs.
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| These test specimens normally exceed the 1/32-inch gap between the transducer and surface that PDI determined as acceptable for UT examination.
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| For RI lSI programs, the ID surfaces should be conducive to UT examinations.
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| In the event that a flaw is detected, please discuss your efforts to provide a surface roughness that supports a vendor's 0.125-inch RMSE qualifications.
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| Flaw Detection Alternative During RF14, the NRC granted WCNDC a similar relief on these welds in a letter dated December 27,2006 (ADAMS Accession No. ML063470082).
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| The relief was based on a partial UT examination combined with a supplemental eddy current testing examination and visual examination.
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| In the WCNDC letter dated September 16, 2008, no visual examination is included in the proposed alternative.
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| Please clarify if a visual examination is to be performed and, if not, please detail how the same level of safety will be accomplished.
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| Enclosure R. Muench -2 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for the NRC staff to complete its review and contribute toward the NRC's goal of efficient and effective use of staff resources.
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| Sincerely, /RN Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
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| ==Enclosure:==
| | REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 13R-06 WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 By letter dated September 16, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML082670891), Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI requirements. WCNOC proposed an alternative to the depth sizing error requirements of ASME Code Cases N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," and N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface," for the third 1O-year inservice inspection interval at Wolf Creek Generating Station (WCGS). |
| | Since 2004, the Energy Power Research Institute - Performance Demonstration Initiative (PDI) representatives and U.S. Nuclear Regulatory Commission (NRC) staff have actively discussed the ASME Code requirements for depth sizing flaws in piping. At the December 2 and 3, 2008, public meeting with PDI and industry representatives, the NRC staff gave a presentation titled, "NRC Perspectives on Inside Diameter Pipe Examinations Depth Sizing Root Mean Square Error," (ADAMS Accession Nos. ML090760523 and ML090760528). The presentation identified potential issues with the current qualification test specimens and suggested that surface flatness issues as a possible hindrance in the qualification process. Securing the appropriate test specimens and acquiring appropriate qualifications may be impractical for WCNOC prior to the next refueling outage. |
| | Based on its review of the WCNOC's submittal, the NRC staff has determined that the following additional information is required to complete an evaluation for impracticality. |
| | Flaw Depth Sizing Alternative |
| | : 1. Page 1 of the application identified welds as either Category B-F or Category B-J. Please provide representative sketches of the configurations and identify the weld and base material (carbon steel, stainless steel, Inconel, etc). Include in the sketches the impediments that are preventing the Code-required examinations. |
| | : 2. Page 4 of the application indicates that these welds were examined during fourteenth refueling outage (RF14). If the vendor being used for the welds in this request is the same vendor that was used for RF14, please provide a discussion on the vendor's efforts to satisfy the Code-required root mean square error (RMSE) since RF14. |
| | : 3. The Electric Power Research Institute (EPRI) - PDI identified a surface roughness criterion of 1/32-inch gap beneath the transducer for ultrasonic testing (UT) examinations. The inside diameter (ID) surface roughness of many of PDl's test specimens used for ID performance demonstrations are outside this standard. Having test specimens with an acceptable ID surface provides an |
| | |
| | -2 opportunity for qualifying to the Code-required 0.125-inch RMSE. The availability of test specimens with acceptable ID surfaces is the responsibility of the entity desiring to use these test specimens in their performance demonstrations. |
| | Please discuss the vendor's depth sizing RMSE capabilities when using test specimens made with acceptable ID surfaces. |
| | : 4. The PDI program test specimens contain ID surface roughness that existed in the field prior to utilities implementing risk-informed inservice inspection (RI lSI) programs. These test specimens normally exceed the 1/32-inch gap between the transducer and surface that PDI determined as acceptable for UT examination. For RI lSI programs, the ID surfaces should be conducive to UT examinations. In the event that a flaw is detected, please discuss your efforts to provide a surface roughness that supports a vendor's 0.125-inch RMSE qualifications. |
| | Flaw Detection Alternative During RF14, the NRC granted WCNDC a similar relief on these welds in a letter dated December 27,2006 (ADAMS Accession No. ML063470082). The relief was based on a partial UT examination combined with a supplemental eddy current testing examination and visual examination. In the WCNDC letter dated September 16, 2008, no visual examination is included in the proposed alternative. Please clarify if a visual examination is to be performed and, if not, please detail how the same level of safety will be accomplished. |
| | Enclosure |
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| As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
| | * .. ML090620146 *Memo dated 2/20/09 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlCPNB NRRlLPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt TChan' MMarkley BSingal DATE 3/9/09 3/9/09 2/20/09 3/26/09 3/27/09}} |
| PUBLIC RidsNrrDorlLpl4 Resource RidsRgn4MailCenter Resource LPLIV r/f RidsNrrPMWolfCreek Resource MAudrain, NRR/DCI RidsAcrsAcnw_MailCTR Resource RidsNrrLAJBurkhardt Resource RidsNrrDciCsgb Resource RidsOgcRp Resource ADAMS Accession No*.. ML090620146
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| *Memo dated 2/20/09 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlCPNB NRRlLPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt TChan' MMarkley BSingal DATE 3/9/09 3/9/09 2/20/09 3/26/09 3/27/09 OFFICIAL RECORD COPY}} | |
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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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 r1arch 27, 2009 Mr. Rick A. Muench President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST 13R-06, ALTERNATIVE TO THE EXAMINATION REQUIREMENTS OF ASME SECTION XI FOR CLASS 1 PIPING WELDS EXAMINED FROM THE INSIDE OF THE REACTOR VESSEL (TAC NO. MD9658)
Dear Mr. Muench:
By letter dated September 16, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML082670891), Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements. The licensee proposed an alternative to the depth sizing requirements of ASME Code Cases N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," and N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface," for the third 1O-year inservice inspection interval at Wolf Creek Generating Station.
Based on its review, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is required to complete the evaluation for the above request for relief.
The NRC staff's request for additional information (RAI) is contained in the enclosure to this letter. These RAts were sent to Ms. Diane Hooper of WCNOC via e-mail on February 23, 2009 and discussed with WCNOC staff on March 5, 2009. Ms. Hooper agreed that WCNOC will provide its RAI response within 30 days from the date of issuance of this letter.
R. Muench -2 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for the NRC staff to complete its review and contribute toward the NRC's goal of efficient and effective use of staff resources.
Sincerely, b~ \L0~~ i l b, ~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-482
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 13R-06 WOLF CREEK NUCLEAR OPERATING CORPORATION DOCKET NO. 50-482 By letter dated September 16, 2008 (Agencywide Document Access and Management System (ADAMS) Accession No. ML082670891), Wolf Creek Nuclear Operating Corporation (WCNOC) requested relief from certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements. WCNOC proposed an alternative to the depth sizing error requirements of ASME Code Cases N-695, "Qualification Requirements for Dissimilar Metal Piping Welds," and N-696, "Qualification Requirements for Appendix VIII Piping Examinations Conducted From the Inside Surface," for the third 1O-year inservice inspection interval at Wolf Creek Generating Station (WCGS).
Since 2004, the Energy Power Research Institute - Performance Demonstration Initiative (PDI) representatives and U.S. Nuclear Regulatory Commission (NRC) staff have actively discussed the ASME Code requirements for depth sizing flaws in piping. At the December 2 and 3, 2008, public meeting with PDI and industry representatives, the NRC staff gave a presentation titled, "NRC Perspectives on Inside Diameter Pipe Examinations Depth Sizing Root Mean Square Error," (ADAMS Accession Nos. ML090760523 and ML090760528). The presentation identified potential issues with the current qualification test specimens and suggested that surface flatness issues as a possible hindrance in the qualification process. Securing the appropriate test specimens and acquiring appropriate qualifications may be impractical for WCNOC prior to the next refueling outage.
Based on its review of the WCNOC's submittal, the NRC staff has determined that the following additional information is required to complete an evaluation for impracticality.
Flaw Depth Sizing Alternative
- 1. Page 1 of the application identified welds as either Category B-F or Category B-J. Please provide representative sketches of the configurations and identify the weld and base material (carbon steel, stainless steel, Inconel, etc). Include in the sketches the impediments that are preventing the Code-required examinations.
- 2. Page 4 of the application indicates that these welds were examined during fourteenth refueling outage (RF14). If the vendor being used for the welds in this request is the same vendor that was used for RF14, please provide a discussion on the vendor's efforts to satisfy the Code-required root mean square error (RMSE) since RF14.
- 3. The Electric Power Research Institute (EPRI) - PDI identified a surface roughness criterion of 1/32-inch gap beneath the transducer for ultrasonic testing (UT) examinations. The inside diameter (ID) surface roughness of many of PDl's test specimens used for ID performance demonstrations are outside this standard. Having test specimens with an acceptable ID surface provides an
-2 opportunity for qualifying to the Code-required 0.125-inch RMSE. The availability of test specimens with acceptable ID surfaces is the responsibility of the entity desiring to use these test specimens in their performance demonstrations.
Please discuss the vendor's depth sizing RMSE capabilities when using test specimens made with acceptable ID surfaces.
- 4. The PDI program test specimens contain ID surface roughness that existed in the field prior to utilities implementing risk-informed inservice inspection (RI lSI) programs. These test specimens normally exceed the 1/32-inch gap between the transducer and surface that PDI determined as acceptable for UT examination. For RI lSI programs, the ID surfaces should be conducive to UT examinations. In the event that a flaw is detected, please discuss your efforts to provide a surface roughness that supports a vendor's 0.125-inch RMSE qualifications.
Flaw Detection Alternative During RF14, the NRC granted WCNDC a similar relief on these welds in a letter dated December 27,2006 (ADAMS Accession No. ML063470082). The relief was based on a partial UT examination combined with a supplemental eddy current testing examination and visual examination. In the WCNDC letter dated September 16, 2008, no visual examination is included in the proposed alternative. Please clarify if a visual examination is to be performed and, if not, please detail how the same level of safety will be accomplished.
Enclosure
- .. ML090620146 *Memo dated 2/20/09 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlCPNB NRRlLPL4/BC NRR/LPL4/PM NAME BSingal JBurkhardt TChan' MMarkley BSingal DATE 3/9/09 3/9/09 2/20/09 3/26/09 3/27/09