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{{#Wiki_filter:NRC FORM 699 | {{#Wiki_filter:NRC FORM 699 U.S. NUCLEAR REGULATORY COMMISSION (12-2020) | ||
CONVERSATION RECORD NAME OF PERSON(S)/TITLE CONTACTED OR IN CONTACT WITH YOU | CONVERSATION RECORD | ||
02/08/2023 | |||
E-MAIL ADDRESS | NAME OF PERSON(S)/TITLE CONTACTED OR IN CONTACT WITH YOU DATE OF CONTACT TYPE OF CONVERSATION Brian Cupp, Andrew McNeil, TVA Licensing, et. al. 02/08/2023 (see below) E-MAIL TELEPHONE E-MAIL ADDRESS TELEPHONE NUMBER INCOMING | ||
Tennessee Valley Authority (TVA), Sequoyah Nuclear 07200034 Plant LICENSE NAME AND NUMBER(S) | |||
Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Docket Nos: 50-327, 50-328, and EPID No: L-2022-LLE-0027 72-034 SUBJECT Clarification call with TVA regarding its August 4, 2022 exemption request (ADAMS Accession No. ML22216A078) for Sequoyah Nuclear Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI) | MS Teams Call Link Sent by NRC Teams Call OUTGOING | ||
ORGANIZATION DOCKET NUMBER(S) | |||
Tennessee Valley Authority (TVA), Sequoyah Nuclear 07200034 Plant | |||
LICENSE NAME AND NUMBER(S) MAIL CONTROL NUMBER(S) | |||
Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Docket Nos: 50-327, 50-328, and EPID No: L-2022-LLE-0027 72-034 | |||
SUBJECT Clarification call with TVA regarding its August 4, 2022 exemption request (ADAMS Accession No. ML22216A078) for Sequoyah Nuclear Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI) | |||
==SUMMARY== | ==SUMMARY== | ||
AND ACTION REQUIRED (IF ANY) | AND ACTION REQUIRED (IF ANY) | ||
SUBJECT Exemption request for deviating from various 10 CFR 72 non-destructive examination compliance requirements related to Sequoyah Nuclear Plant (SQN) ISFSI dated August 4, 2022 | SUBJECT Exemption request for deviating from various 10 CFR 72 non-destructive examination compliance requirements related to Sequoyah Nuclear Plant (SQN) ISFSI dated August 4, 2022 | ||
==SUMMARY== | ==SUMMARY== | ||
On February 8, 2023, the NRC staff held a call with TVA representatives to discuss certain portions of TVA's November 18, 2022 (ML22318A147) response to the staff's December 19, 2022 (ML22353A066) r equest for supplemental information (RSI) pertaining to SQN's August 4, 2022 (ML22216A078) exemption request. See continuation page. No NRC staff decision, neither technical nor regulatory in nature, was made at the call. | |||
As a result of the discussion, the staff indicated that it plans to provide followup questions via email to support additional clarity in order to allow TVA/SQN to respond in writing. TVA personnel expressed that it agreed with the staff's proposed plan. TVA/SQN was given an opportunity to review and comment on this summary. | |||
PARTICIPANTS NRC/NMSS: Omar Khan, Juan Lopez, Darrell Dunn, Sujit Samaddar,Tilda Liu TVA/SQN: Brian Cupp, Andrew McNeil, William Whitener Holtec (contractor/vendor to TVA/SQN): Chuck Bullard, Kyle Trotter, Anveshan Bommareddi, Vaughn Curcio, Robert Tindal | |||
NAME OF PERSON DOCUMENTING CONVERSATION Tilda Liu, NMSS/DFM/STLB | |||
SIGNATURE AND DATE | |||
Add 1 Continuation Page Delete 1 Continuation Page | |||
NRC Form 699 (12-2020) Page 1 of 2 NRC FORM 699 (12-2020) U.S. NUCLEAR REGULATORY COMMISSION CONVERSATION RECORD (continued) | |||
LICENSE NAME AND NUMBER(S) MAIL CONTROL NUMBER(S) | |||
LICENSE NAME AND NUMBER(S) | |||
Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Docket Nos: 50-327, 50-328, and EPID No: L-2022-LLE-0027 72-034 | Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Docket Nos: 50-327, 50-328, and EPID No: L-2022-LLE-0027 72-034 | ||
==SUMMARY== | ==SUMMARY== | ||
AND ACTION REQUIRED (IF ANY) (Continued) | AND ACTION REQUIRED (IF ANY) (Continued) | ||
Staff Follow-up to TVA's Response to RSI Related to August 4, 2022, Sequoyah ISFSI Exemption Request* | Staff Follow-up to TVA's Response to RSI Related to August 4, 2022, Sequoyah ISFSI Exemption Request* | ||
DRAFT Material Discipline | DRAFT | ||
Material Discipline | |||
: 1. Confirm whether 100% of all repairs were performed from the outside diameter of the multipurpose canister (MPC). [RSI-M1, RSI-M2] | : 1. Confirm whether 100% of all repairs were performed from the outside diameter of the multipurpose canister (MPC). [RSI-M1, RSI-M2] | ||
: 2. Repair 1 -- specify the location of the lack of fusion (LOF) (i.e., root/back-weld, root face, or sidewall of the weld joint). [RSI-M1] | : 2. Repair 1 -- specify the location of the lack of fusion (LOF) (i.e., root/back-weld, root face, or sidewall of the weld joint). [RSI-M1] | ||
: 3. Repair 2 -- specify the location of the LOF (i.e., root/back-weld, root face, or sidewall of the weld joint). | : 3. Repair 2 -- specify the location of the LOF (i.e., root/back-weld, root face, or sidewall of the weld joint). | ||
[RSI-M2] | [RSI-M2] | ||
Note: As the second iteration of radiographic testing (RT) identified 0.327 inches of LOF within the view of 0-1 for weld no. 21, located approximately 4 to 14 inches from the bottom of the MPC baseplate, explain and/or justify how the defect removal via excavation caused the repair area extend into the adjacent view 1-2, which is approximately 8.5 to 25 inches from the bottom of the baseplate for the total length of the excavation shown in Figure 5 as 16.5 inches. | Note: As the second iteration of radiographic testing (RT) identified 0.327 inches of LOF within the view of 0-1 for weld no. 21, located approximately 4 to 14 inches from the bottom of the MPC baseplate, explain and/or justify how the defect removal via excavation caused the repair area extend into the adjacent view 1-2, which is approximately 8.5 to 25 inches from the bottom of the baseplate for the total length of the excavation shown in Figure 5 as 16.5 inches. | ||
: 4. Specify the location of the 7.5 inches section with the missing RT. [RSI-M1, RSI-M2] | : 4. Specify the location of the 7.5 inches section with the missing RT. [RSI-M1, RSI-M2] | ||
Structural Discipline The staff noted that the RSI response did not include sufficient information in demonstrating how the local membrane plus primary bending stress remains acceptable after considering the reduction factor established for the exemption request. [RSI-S3] | |||
Note: Section 1.5 of Holtec RRTI-3087-007, Revision 2, evaluates only the primary membrane stress for the shell and does not address the local membrane plus primary bending stress and its resulting safety factor. The staff notes that | Structural Discipline | ||
The staff noted that the RSI response did not include sufficient information in demonstrating how the local membrane plus primary bending stress remains acceptable after considering the reduction factor established for the exemption request. [RSI-S3] | |||
Note: Section 1.5 of Holtec RRTI-3087-007, Revision 2, evaluates only the primary membrane stress for the shell and does not address the local membrane plus primary bending stress and its resulting safety factor. The staff notes that Section1.5.2 in analysis No. HI 2094418, Revision 20, Structural Calculation Package for HISTORM FW System," evaluates both the primary membrane stress AND the local membrane plus primary bending stress for the shell. | |||
EPID No.: L-2022-LLE-0027 Docket No. 72-034 | EPID No.: L-2022-LLE-0027 Docket No. 72-034 | ||
* By {{letter dated|date=August 4, 2022|text=letter dated August 4, 2022}} (ML22216A078), Tennessee Valley Authority (TVA) submitted an exemption request for the Sequoyah Nuclear Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI), requesting deviation from the conditions of the NRC Certificate of Compliance (CoC) No. | * By {{letter dated|date=August 4, 2022|text=letter dated August 4, 2022}} (ML22216A078), Tennessee Valley Authority (TVA) submitted an exemption request for the Sequoyah Nuclear Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI), requesting deviation from the conditions of the NRC Certificate of Compliance (CoC) No. | ||
1032, Amendment No. 3 (ML17214A039), Appendix B, Section 3.3, "Codes and Standards." By {{letter dated|date=November 18, 2022|text=letter dated November 18, 2022}} (ML22318A147), the NRC staff provided a request for supplemental information (RSI) to TVA as part of the acceptance review process. By {{letter dated|date=December 19, 2022|text=letter dated December 19, 2022}} (ML22353A066), TVA provided its response to NRC's RSI. | 1032, Amendment No. 3 (ML17214A039), Appendix B, Section 3.3, "Codes and Standards." By {{letter dated|date=November 18, 2022|text=letter dated November 18, 2022}} (ML22318A147), the NRC staff provided a request for supplemental information (RSI) to TVA as part of the acceptance review process. By {{letter dated|date=December 19, 2022|text=letter dated December 19, 2022}} (ML22353A066), TVA provided its response to NRC's RSI. | ||
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NRC Form 699 (12-2020) Page 2 of 2}} | |||
Latest revision as of 07:23, 15 November 2024
| ML23047A295 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/08/2023 |
| From: | Tilda Liu Storage and Transportation Licensing Branch |
| To: | Cupp B, Mcneil A Tennessee Valley Authority |
| References | |
| EPID L-2022-LLE-0027 | |
| Download: ML23047A295 (2) | |
Text
NRC FORM 699 U.S. NUCLEAR REGULATORY COMMISSION (12-2020)
CONVERSATION RECORD
NAME OF PERSON(S)/TITLE CONTACTED OR IN CONTACT WITH YOU DATE OF CONTACT TYPE OF CONVERSATION Brian Cupp, Andrew McNeil, TVA Licensing, et. al. 02/08/2023 (see below) E-MAIL TELEPHONE E-MAIL ADDRESS TELEPHONE NUMBER INCOMING
MS Teams Call Link Sent by NRC Teams Call OUTGOING
ORGANIZATION DOCKET NUMBER(S)
Tennessee Valley Authority (TVA), Sequoyah Nuclear 07200034 Plant
LICENSE NAME AND NUMBER(S) MAIL CONTROL NUMBER(S)
Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Docket Nos: 50-327, 50-328, and EPID No: L-2022-LLE-0027 72-034
SUBJECT Clarification call with TVA regarding its August 4, 2022 exemption request (ADAMS Accession No. ML22216A078) for Sequoyah Nuclear Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI)
SUMMARY
AND ACTION REQUIRED (IF ANY)
SUBJECT Exemption request for deviating from various 10 CFR 72 non-destructive examination compliance requirements related to Sequoyah Nuclear Plant (SQN) ISFSI dated August 4, 2022
SUMMARY
On February 8, 2023, the NRC staff held a call with TVA representatives to discuss certain portions of TVA's November 18, 2022 (ML22318A147) response to the staff's December 19, 2022 (ML22353A066) r equest for supplemental information (RSI) pertaining to SQN's August 4, 2022 (ML22216A078) exemption request. See continuation page. No NRC staff decision, neither technical nor regulatory in nature, was made at the call.
As a result of the discussion, the staff indicated that it plans to provide followup questions via email to support additional clarity in order to allow TVA/SQN to respond in writing. TVA personnel expressed that it agreed with the staff's proposed plan. TVA/SQN was given an opportunity to review and comment on this summary.
PARTICIPANTS NRC/NMSS: Omar Khan, Juan Lopez, Darrell Dunn, Sujit Samaddar,Tilda Liu TVA/SQN: Brian Cupp, Andrew McNeil, William Whitener Holtec (contractor/vendor to TVA/SQN): Chuck Bullard, Kyle Trotter, Anveshan Bommareddi, Vaughn Curcio, Robert Tindal
NAME OF PERSON DOCUMENTING CONVERSATION Tilda Liu, NMSS/DFM/STLB
SIGNATURE AND DATE
Add 1 Continuation Page Delete 1 Continuation Page
NRC Form 699 (12-2020) Page 1 of 2 NRC FORM 699 (12-2020) U.S. NUCLEAR REGULATORY COMMISSION CONVERSATION RECORD (continued)
LICENSE NAME AND NUMBER(S) MAIL CONTROL NUMBER(S)
Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation; Docket Nos: 50-327, 50-328, and EPID No: L-2022-LLE-0027 72-034
SUMMARY
AND ACTION REQUIRED (IF ANY) (Continued)
Staff Follow-up to TVA's Response to RSI Related to August 4, 2022, Sequoyah ISFSI Exemption Request*
DRAFT
Material Discipline
- 1. Confirm whether 100% of all repairs were performed from the outside diameter of the multipurpose canister (MPC). [RSI-M1, RSI-M2]
- 2. Repair 1 -- specify the location of the lack of fusion (LOF) (i.e., root/back-weld, root face, or sidewall of the weld joint). [RSI-M1]
- 3. Repair 2 -- specify the location of the LOF (i.e., root/back-weld, root face, or sidewall of the weld joint).
[RSI-M2]
Note: As the second iteration of radiographic testing (RT) identified 0.327 inches of LOF within the view of 0-1 for weld no. 21, located approximately 4 to 14 inches from the bottom of the MPC baseplate, explain and/or justify how the defect removal via excavation caused the repair area extend into the adjacent view 1-2, which is approximately 8.5 to 25 inches from the bottom of the baseplate for the total length of the excavation shown in Figure 5 as 16.5 inches.
- 4. Specify the location of the 7.5 inches section with the missing RT. [RSI-M1, RSI-M2]
Structural Discipline
The staff noted that the RSI response did not include sufficient information in demonstrating how the local membrane plus primary bending stress remains acceptable after considering the reduction factor established for the exemption request. [RSI-S3]
Note: Section 1.5 of Holtec RRTI-3087-007, Revision 2, evaluates only the primary membrane stress for the shell and does not address the local membrane plus primary bending stress and its resulting safety factor. The staff notes that Section1.5.2 in analysis No. HI 2094418, Revision 20, Structural Calculation Package for HISTORM FW System," evaluates both the primary membrane stress AND the local membrane plus primary bending stress for the shell.
EPID No.: L-2022-LLE-0027 Docket No.72-034
- By letter dated August 4, 2022 (ML22216A078), Tennessee Valley Authority (TVA) submitted an exemption request for the Sequoyah Nuclear Plant (SQN) Independent Spent Fuel Storage Installation (ISFSI), requesting deviation from the conditions of the NRC Certificate of Compliance (CoC) No.
1032, Amendment No. 3 (ML17214A039), Appendix B, Section 3.3, "Codes and Standards." By letter dated November 18, 2022 (ML22318A147), the NRC staff provided a request for supplemental information (RSI) to TVA as part of the acceptance review process. By letter dated December 19, 2022 (ML22353A066), TVA provided its response to NRC's RSI.
Add 2nd Continuation Page Delete 2nd Continuation Page
NRC Form 699 (12-2020) Page 2 of 2