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{{#Wiki_filter:November 8, 2022 | {{#Wiki_filter:November 8, 2022 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc. | ||
3535 Colonnade Parkway Birmingham, AL 35243 | |||
Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc. | |||
3535 Colonnade Parkway Birmingham, AL 35243 | |||
==SUBJECT:== | ==SUBJECT:== | ||
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - AUDIT AGENDA AND TOPICS IN SUPPORT OF REVIEW OF THE APPLICATION TO ALLOW USE OF LEAD TEST ASSEMBLIES FOR ACCIDENT-TOLERANT FUEL (EPID L-2022-LLA-0097) | VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - AUDIT AGENDA AND TOPICS IN SUPPORT OF REVIEW OF THE APPLICATION TO ALLOW USE OF LEAD TEST ASSEMBLIES FOR ACCIDENT-TOLERANT FUEL (EPID L-2022-LLA-0097) | ||
==Dear Ms. Gayheart:== | ==Dear Ms. Gayheart:== | ||
By {{letter dated|date=June 30, 2022|text=letter dated June 30, 2022}} (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22181B156), Southern Nuclear Operating Company submitted a license amendment request (LAR) for Vogtle Electric Generating Plant, Units 1 and 2. The proposed license amendment request (LAR) would allow the use of lead test assemblies for accident-tolerant fuel. | By {{letter dated|date=June 30, 2022|text=letter dated June 30, 2022}} (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22181B156), Southern Nuclear Operating Company submitted a license amendment request (LAR) for Vogtle Electric Generating Plant, Units 1 and 2. The proposed license amendment request (LAR) would allow the use of lead test assemblies for accident-tolerant fuel. | ||
On October 7, 2022 (ML22103A253), the U.S. Nuclear Regulatory Commission (NRC) staff issued an audit plan that conveyed intent to conduct a regulatory audit to support its review of the subject LAR. In the audit plan, the NRC staff requested an electronic portal setup and provided a list of documents to be added to the portal. | On October 7, 2022 (ML22103A253), the U.S. Nuclear Regulatory Commission (NRC) staff issued an audit plan that conveyed intent to conduct a regulatory audit to support its review of the subject LAR. In the audit plan, the NRC staff requested an electronic portal setup and provided a list of documents to be added to the portal. | ||
The NRC staff has performed a review of the licensees submittal dated June 30, 2022, and developed a list of audit topics. The proposed date for the audit is from Tuesday, December 6, 2022, through Thursday, December 8, 2022. The proposed agenda for the audit is provided as, and the list of Audit topics is provided as Enclosure 2 to this letter. | |||
The NRC staff has performed a review of the licensees submittal dated June 30, 2022, and developed a list of audit topics. The proposed date for the audit is from Tuesday, December 6, 2022, through Thursday, December 8, 2022. The proposed agenda for the audit is provided as, and the list of Audit topics is provided as Enclosure 2 to this letter. | |||
If you have any questions, please contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov. | If you have any questions, please contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov. | ||
Sincerely, | |||
Sincerely, | /RA/ | ||
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425 | |||
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
Docket Nos. 50-424 and 50-425 | |||
==Enclosures:== | ==Enclosures:== | ||
: 1. Audit Agenda | : 1. Audit Agenda | ||
: 2. Audit Topics | : 2. Audit Topics cc: Listserv | ||
cc: Listserv | |||
AUDIT AGENDA Day 1 - Tuesday, December 6, 2022 9:00 a.m. to 12:00 p.m. eastern standard time (EST) | |||
Entrance Meeting o Opening comments by U.S. Nuclear Regulatory Commission (NRC) and Southern Nuclear Operating Company (SNC, the licensee) o Introductions and logistics Discussion related to Probabilistic Risk Assessment (PRA) - PRA Oversight Branch (APOB) | Entrance Meeting o Opening comments by U.S. Nuclear Regulatory Commission (NRC) and Southern Nuclear Operating Company (SNC, the licensee) o Introductions and logistics Discussion related to Probabilistic Risk Assessment (PRA) - PRA Oversight Branch (APOB) | ||
Discussion related to plant systems - Containment and Plant Systems (SCPB) | Discussion related to plant systems - Containment and Plant Systems (SCPB) 1:00 p.m. to 4:00 p.m. EST Discussion related to (1) Cladding Emissivity, (2) ADOPT pellets and AXIOM cladding, (3) | ||
1:00 p.m. to 4:00 p.m. EST | |||
Discussion related to (1) Cladding Emissivity, (2) ADOPT pellets and AXIOM cladding, (3) | |||
Effects of lead test assemblies on co-resident fuel, and (4) Peaking Factors - Nuclear Methods and Fuel Analysis (SFNB) | Effects of lead test assemblies on co-resident fuel, and (4) Peaking Factors - Nuclear Methods and Fuel Analysis (SFNB) | ||
Summary of the day1 | Summary of the day1 Day 2 - Wednesday, December 7, 2022 9:00 a.m. to 12:00 p.m. EST Summary of previous day and review open items Discussion and questions on the Criticality Safety Analyses of the accident-tolerant fuel/increased enriched fuel (SFNB) o How does doping the fuel assemblies affect enrichment? | ||
Day 2 - Wednesday, December 7, 2022 | |||
9:00 a.m. to 12:00 p.m. EST | |||
Summary of previous day and review open items Discussion and questions on the Criticality Safety Analyses of the accident-tolerant fuel/increased enriched fuel (SFNB) o How does doping the fuel assemblies affect enrichment? | |||
o Why arent IFBA used in ADOPT fuel rods? | o Why arent IFBA used in ADOPT fuel rods? | ||
o Are the LTAs over or under moderated? | o Are the LTAs over or under moderated? | ||
| Line 76: | Line 48: | ||
o Walk through the differences between the NFSR AOR in ELV-00511 (ML20244D557) Application for amends to Licenses NPF-68 and NPF-81, revising Tech Spec 5.3.1 to change max enrichment to 4.55 weight percent U-235. And the analysis done for the NFSR for the LTA storage in CN-WFE-02-100. | o Walk through the differences between the NFSR AOR in ELV-00511 (ML20244D557) Application for amends to Licenses NPF-68 and NPF-81, revising Tech Spec 5.3.1 to change max enrichment to 4.55 weight percent U-235. And the analysis done for the NFSR for the LTA storage in CN-WFE-02-100. | ||
o Walk through the differences between the SFP AOR in CN-WFE-02-100 and the analysis done for the SFP All-Cell LTA storage in CN-CRIT-VOG-003. | o Walk through the differences between the SFP AOR in CN-WFE-02-100 and the analysis done for the SFP All-Cell LTA storage in CN-CRIT-VOG-003. | ||
1:00 p.m. to 4:00 p.m. EST Discussion related to the supporting analysis to reach the submittal conclusions for the Rod Ejection Accident - Nuclear Systems Performance Branch (SNSB) | |||
Summary of the day1 1 If discussion topics are completed early, additional discussions for the day may be on the next days agenda items. | |||
Day 3 - Thursday, December 8, 2022 9:00 a.m. to 12:00 p.m. EST Summary of previous day and review open items Discussion of topics related to radiation and dose - Radiation Protection and Consequence Branch (ARCB) | |||
Discussion of proposed technical specification changes - Technical Specifications Branch (STSB) 1:00 p.m. to 4:00 p.m. EST Follow up on any remaining or new open action items Technical summary meeting with SNCs audit team | |||
AUDIT TOPICS By {{letter dated|date=June 30, 2022|text=letter dated June 30, 2022}} (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22181B156), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) for Vogtle Electric Generating Plant, Units 1 and 2. The proposed LAR would allow the use of lead test assemblies (LTAs) for accident-tolerant fuel (ATF). | |||
By {{letter dated|date=June 30, 2022|text=letter dated June 30, 2022}} (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22181B156), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request ( | |||
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the LAR and provided the following topics to discuss during the audit. | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the LAR and provided the following topics to discuss during the audit. | ||
: 1. Explain the supporting analysis to reach the submittal conclusions for the Rod Ejection Accident. | : 1. Explain the supporting analysis to reach the submittal conclusions for the Rod Ejection Accident. | ||
| Line 108: | Line 63: | ||
: d. How do the LTAs impact the SFP ITC/MTC, if separated and if collocated? | : d. How do the LTAs impact the SFP ITC/MTC, if separated and if collocated? | ||
: e. Walk through the differences between the NFSR AOR in ELV-00511 (ML20244D557) Application for amends to Licenses NPF-68 and NPF-81, revising Tech Spec 5.3.1 to change max enrichment to 4.55 weight percent U-235. And the analysis done for the NFSR for the LTA storage in CN-WFE-02-100. | : e. Walk through the differences between the NFSR AOR in ELV-00511 (ML20244D557) Application for amends to Licenses NPF-68 and NPF-81, revising Tech Spec 5.3.1 to change max enrichment to 4.55 weight percent U-235. And the analysis done for the NFSR for the LTA storage in CN-WFE-02-100. | ||
: f. Walk through the differences between the SFP AOR in CN-WFE-02-100 and the analysis done for the SFP All-Cell LTA storage in CN-CRIT-VOG-003. | : f. | ||
Walk through the differences between the SFP AOR in CN-WFE-02-100 and the analysis done for the SFP All-Cell LTA storage in CN-CRIT-VOG-003. | |||
: 4. Cladding Emissivity | : 4. Cladding Emissivity | ||
: 5. ADOPT pellets and AXIOM cladding | : 5. ADOPT pellets and AXIOM cladding | ||
| Line 115: | Line 71: | ||
: 8. Plant Systems | : 8. Plant Systems | ||
: 9. Radiation and Dose | : 9. Radiation and Dose | ||
: 10. Technical Specifications | : 10. Technical Specifications | ||
ML22279B053 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/SFNB/BC NRR/DSS/SNSB/BC (A) | ML22279B053 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/SFNB/BC NRR/DSS/SNSB/BC (A) | ||
NAME JLamb KGoldstein (KEntz for) SKrepel DWoodyatt DATE 10/6/2022 10/31/2022 10/24/2022 10/24/2022 OFFICE NRR/DSS/SCPB/BC NRR/DSS/STSB/BC NRR/DRA/APOB/BC NRR/DRA/ARCB/BC NAME BWittick VCusumano AZoulis KHsueh DATE 10/24/2022 10/24/2022 10/24/2022 10/28/2022 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 11/7/2022 11/8/2022}} | NAME JLamb KGoldstein (KEntz for) | ||
SKrepel DWoodyatt DATE 10/6/2022 10/31/2022 10/24/2022 10/24/2022 OFFICE NRR/DSS/SCPB/BC NRR/DSS/STSB/BC NRR/DRA/APOB/BC NRR/DRA/ARCB/BC NAME BWittick VCusumano AZoulis KHsueh DATE 10/24/2022 10/24/2022 10/24/2022 10/28/2022 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 11/7/2022 11/8/2022}} | |||
Latest revision as of 15:25, 27 November 2024
| ML22279B053 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/08/2022 |
| From: | John Lamb Plant Licensing Branch II |
| To: | Gayheart C Southern Nuclear Operating Co |
| Lamb, J. | |
| References | |
| EPID L-2022-LLA-0097 | |
| Download: ML22279B053 (1) | |
Text
November 8, 2022 Ms. Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - AUDIT AGENDA AND TOPICS IN SUPPORT OF REVIEW OF THE APPLICATION TO ALLOW USE OF LEAD TEST ASSEMBLIES FOR ACCIDENT-TOLERANT FUEL (EPID L-2022-LLA-0097)
Dear Ms. Gayheart:
By letter dated June 30, 2022 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22181B156), Southern Nuclear Operating Company submitted a license amendment request (LAR) for Vogtle Electric Generating Plant, Units 1 and 2. The proposed license amendment request (LAR) would allow the use of lead test assemblies for accident-tolerant fuel.
On October 7, 2022 (ML22103A253), the U.S. Nuclear Regulatory Commission (NRC) staff issued an audit plan that conveyed intent to conduct a regulatory audit to support its review of the subject LAR. In the audit plan, the NRC staff requested an electronic portal setup and provided a list of documents to be added to the portal.
The NRC staff has performed a review of the licensees submittal dated June 30, 2022, and developed a list of audit topics. The proposed date for the audit is from Tuesday, December 6, 2022, through Thursday, December 8, 2022. The proposed agenda for the audit is provided as, and the list of Audit topics is provided as Enclosure 2 to this letter.
If you have any questions, please contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov.
Sincerely,
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425
Enclosures:
- 1. Audit Agenda
- 2. Audit Topics cc: Listserv
AUDIT AGENDA Day 1 - Tuesday, December 6, 2022 9:00 a.m. to 12:00 p.m. eastern standard time (EST)
Entrance Meeting o Opening comments by U.S. Nuclear Regulatory Commission (NRC) and Southern Nuclear Operating Company (SNC, the licensee) o Introductions and logistics Discussion related to Probabilistic Risk Assessment (PRA) - PRA Oversight Branch (APOB)
Discussion related to plant systems - Containment and Plant Systems (SCPB) 1:00 p.m. to 4:00 p.m. EST Discussion related to (1) Cladding Emissivity, (2) ADOPT pellets and AXIOM cladding, (3)
Effects of lead test assemblies on co-resident fuel, and (4) Peaking Factors - Nuclear Methods and Fuel Analysis (SFNB)
Summary of the day1 Day 2 - Wednesday, December 7, 2022 9:00 a.m. to 12:00 p.m. EST Summary of previous day and review open items Discussion and questions on the Criticality Safety Analyses of the accident-tolerant fuel/increased enriched fuel (SFNB) o How does doping the fuel assemblies affect enrichment?
o Why arent IFBA used in ADOPT fuel rods?
o Are the LTAs over or under moderated?
o How do the LTAs impact the SFP ITC/MTC, if separated and if collocated?
o Walk through the differences between the NFSR AOR in ELV-00511 (ML20244D557) Application for amends to Licenses NPF-68 and NPF-81, revising Tech Spec 5.3.1 to change max enrichment to 4.55 weight percent U-235. And the analysis done for the NFSR for the LTA storage in CN-WFE-02-100.
o Walk through the differences between the SFP AOR in CN-WFE-02-100 and the analysis done for the SFP All-Cell LTA storage in CN-CRIT-VOG-003.
1:00 p.m. to 4:00 p.m. EST Discussion related to the supporting analysis to reach the submittal conclusions for the Rod Ejection Accident - Nuclear Systems Performance Branch (SNSB)
Summary of the day1 1 If discussion topics are completed early, additional discussions for the day may be on the next days agenda items.
Day 3 - Thursday, December 8, 2022 9:00 a.m. to 12:00 p.m. EST Summary of previous day and review open items Discussion of topics related to radiation and dose - Radiation Protection and Consequence Branch (ARCB)
Discussion of proposed technical specification changes - Technical Specifications Branch (STSB) 1:00 p.m. to 4:00 p.m. EST Follow up on any remaining or new open action items Technical summary meeting with SNCs audit team
AUDIT TOPICS By letter dated June 30, 2022 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML22181B156), Southern Nuclear Operating Company (SNC, the licensee) submitted a license amendment request (LAR) for Vogtle Electric Generating Plant, Units 1 and 2. The proposed LAR would allow the use of lead test assemblies (LTAs) for accident-tolerant fuel (ATF).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the LAR and provided the following topics to discuss during the audit.
- 1. Explain the supporting analysis to reach the submittal conclusions for the Rod Ejection Accident.
- 2. Explain the supporting analysis/technical reasoning to reach the submittal conclusion that there is no impact on unfavorable exposure time in the anticipated transient without scram (ATWS) PRA model and that there is no change in time to core damage for other significant accident sequences.
- 3. Criticality Safety Analyses of the ATF/Increased Enriched Fuel
- a. How does doping the fuel assemblies affect enrichment?
- b. Why arent IFBA used in ADOPT fuel rods?
- c. Are the LTAs over or under moderated?
- e. Walk through the differences between the NFSR AOR in ELV-00511 (ML20244D557) Application for amends to Licenses NPF-68 and NPF-81, revising Tech Spec 5.3.1 to change max enrichment to 4.55 weight percent U-235. And the analysis done for the NFSR for the LTA storage in CN-WFE-02-100.
- f.
Walk through the differences between the SFP AOR in CN-WFE-02-100 and the analysis done for the SFP All-Cell LTA storage in CN-CRIT-VOG-003.
- 4. Cladding Emissivity
- 5. ADOPT pellets and AXIOM cladding
- 6. Effects of LTAs on co-resident fuel
- 7. Peaking Factors
- 8. Plant Systems
- 9. Radiation and Dose
- 10. Technical Specifications
ML22279B053 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DSS/SFNB/BC NRR/DSS/SNSB/BC (A)
NAME JLamb KGoldstein (KEntz for)
SKrepel DWoodyatt DATE 10/6/2022 10/31/2022 10/24/2022 10/24/2022 OFFICE NRR/DSS/SCPB/BC NRR/DSS/STSB/BC NRR/DRA/APOB/BC NRR/DRA/ARCB/BC NAME BWittick VCusumano AZoulis KHsueh DATE 10/24/2022 10/24/2022 10/24/2022 10/28/2022 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 11/7/2022 11/8/2022