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EPID:L-2017-LLE-0029, Package: First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15 (CAC No. 001028, Docket No. 72-58, EPID L-2017-LLE-0029) (Approved, Closed) |
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MONTHYEARML18100A1882013-04-11011 April 2013 Enclosure 7 - Procedure 12751-MNGP-QP-9.201, Revision 0, Visual Weld Examination Project stage: Other ML18100A1852013-04-11011 April 2013 Enclosure 6 - Procedure 12751-MNGP-OPS-01, Revision 0, Spent Fuel Cask Welding: 61BT/BTH Nuhoms Canisters Project stage: Other ML18100A1912014-01-30030 January 2014 Enclosure 9 - Structural Integrity Associates, Inc. Report 130415.402, Revision 0, Review of Trivis Inc. Welding Procedures Used for Field Welds on the Transnuclear Nuhoms 61BTH Type 1 & 2 Transportable Canister for BWR Fuel Project stage: Other ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records Project stage: Other ML18065A5482018-03-0606 March 2018 EnclosuRAI-1 (non-proprietary) (Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15) Project stage: RAI ML18065A5452018-03-0606 March 2018 Package: First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15 (CAC No. 001028, Docket No. 72-58, EPID L-2017-LLE-0029) Project stage: Request ML18065A5462018-03-0606 March 2018 Letter to T. J. O'Connor First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 Through 15 (CAC No. 001028, Docket No. 72-58, EPID L-2017-LLE-0029) Project stage: RAI ML18100A1932018-04-0505 April 2018 Enclosure 13 - Tn Americas LLC Calculation 11042-0207, Revision 1, Nuhoms 61BTH Type 1 DSC Itcp and Otcp Maximum Weld Flaw Evaluation Project stage: Other L-MT-18-013, Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 152018-04-0505 April 2018 Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 Project stage: Response to RAI ML18121A2502018-05-0101 May 2018 Package: 05/01/2018, E-Mail from C. Jacobs/Dsfm to S. Jurek Monticello Exemption: NRC Clarification Questions on RAI#1 Responses Project stage: Request L-MT-18-034, Supplement to Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 (CAC No. 001028, EPID L-2017-LLE-00292018-05-31031 May 2018 Supplement to Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (Dscs) 11 Through 15 (CAC No. 001028, EPID L-2017-LLE-0029 Project stage: Supplement ML18248A1212018-09-13013 September 2018 Federal Register Notice: Exemption; Issuance - Xcel Energy, Monticello Nuclear Generating Plant Independent Spent Fuel Storage Installation Project stage: Other ML18262A3782018-09-20020 September 2018 Letter to T.O'Connor Exemption from Certain Provisions of 10 CFR 72.212 and 72.214 - Storage Standardized Nuhoms Dry Shielded Canisters 11-15 at Monticello Nuclear Generating Plant Isfsi(Cac No.001028, Dockets 72-58 and 50-263, EPID L-2017- Project stage: Approval 2018-04-05
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Category:Letter type:L
MONTHYEARL-MT-24-038, Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI2024-10-15015 October 2024 Subsequent License Renewal Application Response to Request for Additional Information - 3rd Round RAI L-MT-24-025, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2024-09-26026 September 2024 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-MT-24-029, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI2024-09-13013 September 2024 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information-Supplement to Set 1 Part 2 and Response to 2ci Round RAI L-MT-24-028, Response to RCI for RR-017 ISI Impracticality2024-08-28028 August 2024 Response to RCI for RR-017 ISI Impracticality L-MT-24-022, – Preparation and Scheduling of Operator Licensing Examinations2024-07-0909 July 2024 – Preparation and Scheduling of Operator Licensing Examinations L-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024 Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-24-017, Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-01602024-06-0404 June 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 (EPID-L-2023-LLA-0160 L-MT-24-015, Response to Request for Additional Information - Alternative Request VR-09 for OMN-172024-05-16016 May 2024 Response to Request for Additional Information - Alternative Request VR-09 for OMN-17 L-MT-24-013, 2023 Annual Radiological Environmental Operating Report2024-05-14014 May 2024 2023 Annual Radiological Environmental Operating Report L-MT-24-016, 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2024-05-0808 May 2024 2023 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-24-002, Submittal of Revision 41 to the Updated Safety Analysis Report2024-04-17017 April 2024 Submittal of Revision 41 to the Updated Safety Analysis Report L-MT-24-004, Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP)2024-04-17017 April 2024 Submittal of 10 CFR 72.48 Report for Monticello Nuclear Generating Plant (MNGP) L-MT-24-006, Subsequent License Renewal Application Annual Update 1 and Supplement 92024-02-29029 February 2024 Subsequent License Renewal Application Annual Update 1 and Supplement 9 L-MT-24-007, Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval2024-02-15015 February 2024 Response to NRC Request for Additional Information on Proposed Inservice Inspection Alternative RR-002 for the Sixth Ten-Year ISI Interval L-MT-24-001, 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval2024-01-30030 January 2024 10 CFR 50.55a Request RR-017 - Inservice Inspection (ISI) Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval L-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-053, Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch2023-12-0404 December 2023 Condition Prohibited by Technical Specifications Due to Inoperable Main Steam Line Low Pressure Isolation Switch L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases 2024-09-26
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2807 West County Road 75 Monticello, MN 55362 (l Xcel Energy*
RESPONSIBLE BY NATURE ~
800.895.4999 xcelenergy.com May 31, 2018 L-MT-18-034 10 CFR 72.7 ATTN: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Independent Spent Fuel Storage Installation Docket No. 72-58 Supplement to Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (DSCs) 11 through 15 (CAC No. 001028, EPID L-2017-LLE-0029)
References:
- 1) NSPM letter to NRC, Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (DSCs) 11 through 15, dated October 18, 2017 (ADAMS Accession No. ML17296A205)
- 2) NRC letter to NSPM, First Request for Additional Information for Review of Exemption Request for Five Nonconforming Dry Shielded Canisters 11 through 15 (CAC No. 001028, Docket No. 72-58, EPID L-2017-LLE-0029),
dated March 6, 2018 (ADAMS Accession No. ML18065A545)
- 3) NSPM letter to NRC, Response to Request for Additional Information Regarding Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (DSCs) 11 through 15 (CAC No.
001028, EPID L-2017-LLE-0029), dated April 5, 2018 (ADAMS Accession No. ML18100A183)
- 4) NRC email to NSPM, Monticello Exemption: NRC Clarification Questions on RAI #1 Responses, dated May 1, 2018 (ADAMS Accession No. ML18121A250)
- 5) NRC Conversation Record, Clarification Call with Xcel Energy (XE) on RAI #1 Response in Regard to Monticello Exemption Request for DSCs 11-15, dated May 14, 2018 (ADAMS Accession No. ML18134A323)
Document Control Desk Page 2 In accordance with 10 CFR 72.7, Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, requested in Reference 1, a permanent exemption from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i),
10 CFR 72.212(b)(11), and 10 CFR 72.214 for five NU HOMS Dry Shielded Canisters (DSCs),
designated DSCs 11-15, due to nonconforming dye penetrant (PT) examinations performed during the loading campaign that started in September 2013 at the Monticello Nuclear Generating Plant (MNGP). In Reference 2, the NRC provided a Request for Additional Information (RAI) regarding NSPM's application in Reference 1. NSPM provided its response to the RAI in Reference 3.
Subsequent to NSPM's RAI response, the NRC provided clarifying questions in Reference 4.
On May 10, NSPM held a teleconference with members of the NRC staff to discuss the NRC's clarifying questions (Reference 5). During the teleconference, NSPM agreed to provide supplemental information for its RAI response provided in Reference 3. The enclosure to this letter provides supplemental information for NSPM's response to RAls M-4, M-5, and M-6.
If additional information is required, please contact Mr. Shane Jurek at (612) 330-5788.
Summary of Commitments w commitments and no revisions to existing commitments.
Connor ice President and Chief Nuclear Officer rn States Power Company - Minnesota Enclosure cc: Administrator, Region Ill, USNRC NMSS Project Manager, USNRC NRR Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC
L-MT-18-034 NSPM Enclosure SUPPLEMENTAL INFORMATION EXEMPTION REQUEST FOR NONCONFORMING DYE PENETRANT EXAMINATIONS OF DRY SHIELDED CANISTERS (DSCS) 11 THROUGH 15 On October 18, 2017, Northern States Power Company, a Minnesota corporation (NSPM),
doing business as Xcel Energy, submitted a request for a permanent exemption for the Monticello Nuclear Generating Plant (MNGP). Specifically, NSPM requested a permanent exemption from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3),
10 CFR 72.212(b)(5)(i), 10 CFR 72.212(b)(11), and 10 CFR 72.214 for five NUHOMS Dry Shielded Canisters (DSCs), designated DSCs 11-15, due to nonconforming dye penetrant (PT) examinations performed during the loading campaign that started in September 2013. By letter dated March 6, 2018, the NRC provided a request for additional information (RAI). NSPM provided its response to the RAI in a letter dated April 5, 2018. Subsequently, the NRC provided clarifying questions regarding NSPMs response to five of the nine questions.
On May 10, 2018, NSPM held a teleconference with members of the NRC staff to discuss the clarifying questions. During the teleconference, NSPM agreed to provide supplemental information regarding its responses to RAIs M-4, M-5, and M-6. The requested information is provided below.
RAI M-4 Requested Information NSPM agreed to supplement the RAI M-4 response to clarify rework vs. repair or conditioning for DSC 12, specifically in regards to layers 2a and 2c. In addition NRC staff had a follow-up question requesting NSPM to describe what is a hot pass in Enclosure 8 of the response to RAI M-4. NSPM agreed to include the description of a hot pass in their supplemental response.
NSPM Response The 1st pass or 1(Root) discussed in Enclosure 3 to the exemption request (Reference 1),
Structural Integrity Associates, Inc. Report 700388.401, Revision 1, Evaluation of the Welds on DSC 11-15, for DSC-12, as well as the other canisters, refers to the root pass. A nondestructive examination (NDE) is required after the root pass is completed. Weld head video records for the DSC-12 outer top cover plate (OTCP) provided evidence indicating that light grinding had been performed on the top surface of the root pass prior to the NDE inspection. Light grinding and cleaning of the root pass surface prior to inspection is commonplace to facilitate and improve the NDE inspection. The root pass inspection result for the DSC-12 OTCP was reported as satisfactory; thus, no post-NDE repairs were performed on the root pass.
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L-MT-18-034 NSPM Enclosure The weld head video records for the OTCP of DSC-12 show a second layer deposited in five separate segments or strips each of variable lengths. These strips are identified 2 strip, 2a, 2b, 2c, and 2d. The tabulated results for each of these strips were reported in Enclosure 3 to Reference 1. The deposit conditions previously described as blow-through or blow-out related to 2 strip and 2c are more appropriately described as a weld deposit crater, because the bottoms of both craters are visible in the weld head video records. This observation establishes that the underlying root pass was not breeched. The first crater developed while shutting down the 2_strip segment, and the second crater event during the shutdown of the 2c segment. The reason(s) for shutting down the weld progression was not documented.
Both craters were reworked by rewelding over the discontinuity location with the addition of weld filler metal. It is noted that rework is not a post-NDE defect repair as defined by Section 8.10 of the 12751-MNGP-OPS-01 welding procedure.
A review of the weld head video information shows that a limited surface area of the 2 strip weld deposit needed to be smoothed to facilitate improved weldability over that surface. This was the grinding referred to in the segment 2a notes. Segment 2a was approximately 1 inch long. The rework cited in the comments on segment 2a involved repositioning the welding arc closer to the lid side to improve the weld deposit distribution and to eliminate the crater that formed when welding was stopped on segment 2 strip. These activities are rework of in-process welds.
Hot pass is welding jargon, typically used by welders and/or pipe fitters when referring to the weld layer placed on top of the root pass (root layer). In the context of the report, hot pass is used to designate the second layer weld that was completed in conformance with the approved welding procedure.
RAI M-5 Requested Information NSPM agreed to supplement RAI M-5 response to provide clarifying language for the inconsistent use of repairs versus rework or conditioning of welds. NSPM can address each instance of apparent inconsistent use, or provide a high level clarification that generically cleans up what was intended to be said.
NSPM Response The usage of the term repair was, in fact, referring to in-process rework or conditioning performed in accordance with Section 8.8 and 8.9 of the Spent Fuel Cask- 61BT/BTH NUHOMS Canister Welding Procedure 12751-MNGP-OPS-01, Rev 0. No post NDE defect repairs were required. A discussion of the differences between In-process Repair and Post NDE Repair of Defects follow:
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L-MT-18-034 NSPM Enclosure In-Process Repair (rework):
Repair activities performed during welding are identified as in-process repairs, and because they are performed prior to performing acceptance NDE, they are properly considered rework. Rework typically is conducted at the discretion of the welding operator to correct undesirable welding surface conditions that can be assessed visually prior to NDE. In-process rework may involve welding and/or surface conditioning by metal removal methods such as grinding, filing, sanding, etc. Rework was conducted in accordance with Sections 8.8 and 8.9 of the Spent Fuel Cask -61BT/BTH NUHOMS Canisters Welding Procedure 12751-MNGP-OPS-01, Rev 0.
Post NDE Repair of Defects:
All rejectable and non-rejectable indications discovered during NDE must be recorded according to the inspection procedures. All indications determined to be defects must be repaired. Section 8.10 of the Spent Fuel Cask -61BT/BTH NUHOMS Canisters 12751-MNGP-OPS-01, Rev 0 welding procedure describes two types of weld repairs - major and minor. Minor weld repairs require only surface conditioning of the weld area, whereas major repairs require defect removal with the addition of weld metal. These repairs require post-repair inspection to determine acceptability for meeting acceptance criteria.
No unacceptable NDE results were identified and thus no repairs were required in accordance with Section 8.10 of procedure 12751-MNGP-OPS-01. These results were consistent with the lack of any observed post-NDE repair activities in the general area videos records.
RAI M-6 Requested Information SIA previously had technical difficulties viewing the general area video of DSC 12. However, during this call, NRC became aware that NSPM revisited the historical video files and was able to resolve the technical difficulties enabling NSPM subject matter experts to review the general area video for DSC 12. NSPM agreed to provide a summary of the restored video to NRC as a supplemental response to RAI M-6.
NSPM Response The general area video of DSC 12 inner top cover plate (ITCP) welding was reviewed by NSPM. The area observations during this welding focused on the operation of the gas tungsten arc welding (GTAW) welder as well as any follow-up corrective actions (e.g., grinding, weld buildup). The details of the area observations for DSC 12 ITCP welding evolution are outlined in Table 1.
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L-MT-18-034 NSPM Enclosure Table 1 - DSC 12 ITCP Welding Area Observations Cask Time Time Date Activity Notes Plate Start End ITCP 9/13/2013 1st Pass 9:15:52 10:29:41 GTAW machine was stopped and started once. Manual weld buildup.
2nd Pass 13:35:31 14:48:55 GTAW machine was stopped and started once. Manual weld buildup.
SIA has reviewed the DSC-12 results in Table 1 and compared them to similar ITCP records for DSC-13 and DSC-16 previously reported. The results are considered consistent with the general welding area observations reviewed for the other canister ITCP closure welds regarding duration and activities performed.
References
- 1. NSPM letter to NRC, Exemption Request for Nonconforming Dye Penetrant Examinations of Dry Shielded Canisters (DSCs) 11 through 15, dated October 18, 2017 (ADAMS Accession No. ML17296A205)
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