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MONTHYEARWO 18-0031, Inservice Inspection (ISI) Program Relief Request from the Requirements of American Society of Mechanical Engineers (ASME) Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12018-07-23023 July 2018 Inservice Inspection (ISI) Program Relief Request from the Requirements of American Society of Mechanical Engineers (ASME) Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 Project stage: Request 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 Project stage: Draft Request ML18334A0132018-12-12012 December 2018 Request for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-666-1 Project stage: Approval 2018-07-23
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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
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Text
NRR-DMPSPEm Resource From: Sweet Sheryl A <shsweet@WCNOC.com>
Sent: Tuesday, July 24, 2018 2:22 PM To: Singal, Balwant Cc: Taylor, Nick; Tsao, John
Subject:
[External_Sender] FW: Wolf Creek Relief Request Please see below:
From: Meredith David B Sent: Tuesday, July 24, 2018 1:15 PM To: Sweet Sheryl A; Isch Jeffrey R; Hafenstine Cynthia R; Rudeen Jim K Cc: Mand Daljit S; Herrman Paul J; Knust Jason B; Hinterweger Kyle A; Barraza Alan J
Subject:
RE: Wolf Creek Relief Request Additions to the new statements includes.
- Thanks, Dave Meredith, PE Design Engineering ext. 8498 From: Meredith David B Sent: Tuesday, July 24, 2018 11:05 AM To: Sweet Sheryl A; Isch Jeffrey R; Hafenstine Cynthia R; Rudeen Jim K Cc: Mand Daljit S; Herrman Paul J; Knust Jason B; Hinterweger Kyle A; Barraza Alan J
Subject:
RE: Wolf Creek Relief Request Provided are the responses for the NRC questions. Attached is the sketch requested by the NRC.
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 DOCKET NO. 50-482
- 1. Discuss why Section 3, Applicable Code Requirement, does not include ASME Code,Section XI, IWA-4000 as the applicable code requirement in addition to Code Case N-666-1. Specifically, IWA IWA-4611.1(a) states, "Defects shall be removed in Accordance with IWA-4422.1. A defect is considered removed when it has been reduced to an acceptable size." The NRC staff notes that based on the regulatory path, relief should be requested from the primary requirement i.e., ASME Code,Section XI, IWA-4000. Code Case N-666-1 is a secondary requirement to perform the weld overlay repair.
WCNOC Response: Section 2 of the Request will include relief form IWA-4000, of the ASME Code,Section XI.
1
- 2. Code Case N-666-1 has drawings of a typical socket weld. However, provide drawings (hand sketch is acceptable) of the socket weld and associated drain line at Wolf Creek (how the socket weld joins the drain line to the main pipe).
WCNOC Response: Drawing/sketches of the current configuration, the proposed weld overlay, and the adjacent pipe wall as-found and minimum wall thickness.
- 3. Discuss why there is no date on the top of the cover letter of the submittal. Also on the cover letter, 10 CFR 50.55(z)(2) should be 10 CFR 50.55a(z)(2).
WCNOC Response: The letter will include the dates and correct the reference to 10 CFR 50.55a(z)(2).
- 4. Under the Degradation Mechanism section of the relief request the licensee stated that it is most likely that the corrosion initiated the flaw and reduced the wall thickness to a point where fatigue propagated the flaw through wall Code Case N-666-1 is only applicable to piping with the vibration fatigue degradation mechanism. Because corrosion is a potential degradation mechanism as discussed in the relief request, discuss whether relief will also be requested for the use of Code Case N-666-1 on a pipe having corrosion degradation mechanism in addition to the relief from the carbon content provision.
WCNOC Response:
From N-666-1, Paragraph 1(d), it states in part, Prior to performing a repair, the Owner shall verify that the pipe base material adjacent to the socket weld requiring overlay meets the required minimum wall thickness. The intent of this requirement is that the Owner verifies that the pipe wall thickness where the overlay will be applied is not less than the minimum required wall thickness. Ultrasonic examination was performed on the piping starting at the toe of the socket weld and extending to the downstream valve EGV0029. The as-found wall thickness no less than 0.157 in and the calculated minimum required wall thickness is 0.143 in. The piping location where the weld overlay will be installed is greater than the minimum required wall thickness.
In addition, this requirement is applicable to the piping not within the socket fitting since a through wall flaw at the toe of the socket weld the pipe wall thickness is zero. In addition, for a fatigue crack, the crack length may extend nearly full circumference before penetrating through wall. Thus, the remaining piping in the socket may provide minimal or no load carrying capacity.
From the radiograph there appears to be corrosion of the connecting piping within the socket fitting, including the socket weld, but not of the socket. Since vibration is present in the connection, once the material thickness in the socket weld was sufficiently reduced, a crack may have initiated and propagated through the reaming weld. This aligns with the Reply stating that the Code Case is applicable to cracked or leaking socket welds resulting from vibration fatigue.
In addition, WCNOC requests relief from N-666-1:
- 1) Paragraph 1(d), specifically the pipe wall thickness within the socket welded coupling is unknown.
- 2) Paragraph 2(a), specifically the failure mechanism is a result of vibration fatigue.
- 5. The Examination and Testing section (Page 8) of the relief request states that walk downs will be used to identify leakage post installation Discuss the frequency of the walkdowns.
WCNOC Response: Walk downs will completed at least once per 12-hour shift to identify potential leakage post repair.
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- 6. Paragraph 2(b) of N-666-1 states that If review of the design, operating history, and changes to the piping system indicates that the current system configuration has not been changed for one or more fuel cycles, the weld overlay shall be acceptable until the next refueling outage, if no action is taken to reduce the vibration to acceptable levels. If corrective action is taken that reduces the vibration to acceptable levels, the weld overlay shall be acceptable for the remaining life of the piping system. If the time to failure of the original socket weld was less than one fuel cycle, corrective action that reduces the vibration to acceptable levels must be taken.
Vibration acceptance standards shall be in accordance with ASME-OMb-S/G-2002, Part 3 (a) Discuss whether the proposed weld overlay will be a permanent repair or temporary repair to the next refueling outage.
(b) If the proposed alternative is a permanent repair, discuss the corrective action as specified in paragraph 2(b) above.
WCNOC Response: The weld overlay will be removed from service prior to the end of refueling outage 23, scheduled for the fall of 2019. The socket weld connection will be reworked/repaired to meet the requirements of the ASME Code.
- 7. The Duration of Proposed Alternative Section of the relief request states that the duration for the proposed activity is though refueling outage 23 scheduled for the fall of 2019. Clarify whether this means that the weld overlay will be removed and the socket weld will be repaired in accordance with the ASME Code in the fall of 2019 WCNOC Response: See response to question 6.
From: Meredith David B Sent: Tuesday, July 24, 2018 10:49 AM To: Sweet Sheryl A; Isch Jeffrey R; Hafenstine Cynthia R; Rudeen Jim K; Mand Daljit S; Herrman Paul J; Knust Jason B; Hinterweger Kyle A; Barraza Alan J
Subject:
RE: Wolf Creek Relief Request Importance: High Answers to the NRC questions below in red. Please review and let me know if there are any changes/additions.
- Thanks, Dave Meredith, PE Design Engineering ext. 8498 From: Sweet Sheryl A Sent: Tuesday, July 24, 2018 7:53 AM To: Mccoy Jaime H Cc: Isch Jeffrey R; Carlson Eric D; East Tim F; Stucker Bill J; Greenfield Tyler N; Edwards James L; Hafenstine Cynthia R; Rudeen Jim K; Meredith David B; Mand Daljit S; Gholson David M; Herrman Paul J; Knust Jason B; Hinterweger Kyle A; Barraza Alan J
Subject:
FW: Wolf Creek Relief Request RAIs from Balwant:
3
From: Singal, Balwant [1]
Sent: Tuesday, July 24, 2018 7:47 AM To: Sweet Sheryl A; Rudeen Jim K Cc: Hafenstine Cynthia R; Pascarelli, Robert; Tsao, John; Ruffin, Steve; Taylor, Nick
Subject:
Wolf Creek Relief Request
- Sheryl, Following are the Draft RAI questions the NRC staff would like to discuss with your staff during the call at 9:30 AM.
Thanks.
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 DOCKET NO. 50-482
- 1. Discuss why Section 3, Applicable Code Requirement, does not include ASME Code,Section XI, IWA-4000 as the applicable code requirement in addition to Code Case N-666-1. Specifically, IWA IWA-4611.1(a) states, "Defects shall be removed in Accordance with IWA-4422.1. A defect is considered removed when it has been reduced to an acceptable size." The NRC staff notes that based on the regulatory path, relief should be requested from the primary requirement i.e., ASME Code,Section XI, IWA-4000. Code Case N-666-1 is a secondary requirement to perform the weld overlay repair.
WCNOC Response: Section 2 of the Request will include relief form IWA-4000, of the ASME Code,Section XI.
- 2. Code Case N-666-1 has drawings of a typical socket weld. However, provide drawings (hand sketch is acceptable) of the socket weld and associated drain line at Wolf Creek (how the socket weld joins the drain line to the main pipe).
WCNOC Response: Drawing/sketches of the current configuration, the proposed weld overlay, and the adjacent pipe wall as-fond and minimum wall thickness.
- 3. Discuss why there is no date on the top of the cover letter of the submittal. Also on the cover letter, 10 CFR 50.55(z)(2) should be 10 CFR 50.55a(z)(2).
WCNOC Response: The letter will include the dates and correct the reference to 10 CFR 50.55a(z)(2).
- 4. Under the Degradation Mechanism section of the relief request the licensee stated that it is most likely that the corrosion initiated the flaw and reduced the wall thickness to a point where fatigue propagated the flaw through wall Code Case N-666-1 is only applicable to piping with the vibration fatigue degradation mechanism. Because corrosion is a potential degradation mechanism as discussed in the relief request, discuss whether relief will also be requested for the use of Code Case N-666-1 on a pipe having corrosion degradation mechanism in addition to the relief from the carbon content provision.
WCNOC Response:
From N-666-1, Paragraph 1(d), it states in part, Prior to performing a repair, the Owner shall verify that the pipe base material adjacent to the socket weld requiring overlay meets the required minimum wall thickness. The intent of this requirement is that the Owner verifies that the pipe wall thickness where the overlay will be applied is not less than the minimum require wall thickness. Ultrasonic examination was performed on the piping starting at the toe of the socket weld and extending to the downstream 4
valve EGV0029. The as-found wall thickness is 0.157 in and the calculated minimum required wall thickness is 0.143 in. The piping location when the weld overlay will be installed is greater than the minimum required wall thickness.
In addition, this requirement is applicable to the piping not within the socket fitting since a through wall flaw at the toe of the socket weld the pipe wall thickness is zero. In addition, for a fatigue crack, the crack length may extend nearly full circumference before penetrating through wall. Thus, the remaining piping in the socket may provide minimal or no load carrying capacity.
From the radiograph there appears to be corrosion of the connecting piping within the socket fitting, including the socket weld, but not of the socket. Since vibration is present in the connection, once the material thickness in the socket weld was sufficiently reduced, a crack may have initiated and propagated through the reaming weld. This aligns with the Reply stating that he Case is applicable to cracked or leaking socket welds resulting from vibration fatigue.
- 5. The Examination and Testing section (Page 8) of the relief request states that walk downs will be used to identify leakage post installation Discuss the frequency of the walkdowns.
WCNOC Response: Walk downs will completed at least once per shift to identify leakage post.
- 6. Paragraph 2(b) of N-666-1 states that If review of the design, operating history, and changes to the piping system indicates that the current system configuration has not been changed for one or more fuel cycles, the weld overlay shall be acceptable until the next refueling outage, if no action is taken to reduce the vibration to acceptable levels. If corrective action is taken that reduces the vibration to acceptable levels, the weld overlay shall be acceptable for the remaining life of the piping system. If the time to failure of the original socket weld was less than one fuel cycle, corrective action that reduces the vibration to acceptable levels must be taken.
Vibration acceptance standards shall be in accordance with ASME-OMb-S/G-2002, Part 3 (a) Discuss whether the proposed weld overlay will be a permanent repair or temporary repair to the next refueling outage.
(b) If the proposed alternative is a permanent repair, discuss the corrective action as specified in paragraph 2(b) above.
WCNOC Response: The weld overlay will be removed from service prior to the end of refueling outage 23, scheduled for the fall of 2019. The socket weld connection will be reworked/repaired to meet the requirements of the ASME Code.
- 7. The Duration of Proposed Alternative Section of the relief request states that the duration for the proposed activity is though refueling outage 23 scheduled for the fall of 2019. Clarify whether this means that the weld overlay will be removed and the socket weld will be repaired in accordance with the ASME Code in the fall of 2019 WCNOC Response: See response to question 6.
Balwant K. Singal Senior Project Manager (Diablo Canyon and Wolf Creek)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222 5
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[External_Sender] FW: Wolf Creek Relief Request Sent Date: 7/24/2018 2:21:41 PM Received Date: 7/24/2018 2:22:03 PM From: Sweet Sheryl A Created By: shsweet@WCNOC.com Recipients:
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Tracking Status: None "Singal, Balwant" <Balwant.Singal@nrc.gov>
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