Letter Sequence Meeting |
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MONTHYEARPMNS20210790, Pre-Submittal Meeting - Proposed License Amendment Request for Alternate Source Term and TSTF-4902021-06-0909 June 2021
Pre-Submittal Meeting - Proposed License Amendment Request for Alternate Source Term and TSTF-490
Project stage: Meeting
ML21183A1512021-07-13013 July 2021
July 1, 2021, Summary of Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a Proposed LAR to Implement Alternate Source Term and TSTF-490 for Vogtle Electric Generating Plant, Units 1 and 2
Project stage: Meeting
ML21165A2762021-07-13013 July 2021
Pre-Submittal Meeting - Proposed License Amendment Request for Alternate Source Term and TSTF-490
Project stage: Request
ML21238A3842021-09-22022 September 2021
Correction to Summary of July 1, 2021, Public Meeting with Southern Nuclear Operating Company, Inc., Regarding a Proposed License Amendment Request to Implement Alternate Source Term and TSTF-490 for Vogt
Project stage: Meeting
2021-07-13
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Category:Letter
MONTHYEARML24032A0252024-02-0505 February 2024
NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009
ML24010A0712024-01-31031 January 2024
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Cyber Security Inspection Report 05200026/2024401 - Public
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Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report Enclosure 2, GAE-NRCD-RF-LR-000002 P-Attachment, Rev. 0
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Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants
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IR 05000424/20244032024-01-26026 January 2024
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Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report
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Voluntary Requests for Data, Information, And/Or Observation
ML23279A0042024-01-17017 January 2024
Amendment No. 194 to Remove Combined License Appendix C
NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024
Correction of Technical Specification Typographical Error
ML23341A2042024-01-12012 January 2024
Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021)
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Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021)
ML23317A2072023-12-22022 December 2023
Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448
ML23335A1222023-12-19019 December 2023
Safety Evaluation Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 (EPID L-2023-LRQ-0002) - Letter
ML23353A1702023-12-19019 December 2023
LAR-22-002, TS 3.8.3 Inverters Operating Completion Time Extension Letter
ML23310A2922023-12-0707 December 2023
Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007
ML23339A1812023-12-0707 December 2023
Correction Letter Regarding License Amendment Request: More Restrictive Action for Technical Specification 3.1.9
ML23338A2182023-12-0606 December 2023
Project Manager Reassignment
NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023
Request for Exemption from Security Event Notification Implementation
ML23289A1632023-11-28028 November 2023
Letter and Amendment 195 and 192 LAR-23-006R1 TS 3.1.9 More Restrictive Action
NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023
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Integrated Inspection Report 05200025/2023003
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Integrated Inspection Report 05200026/2023003
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NRC Initial Test Program and Operational Programs Integrated Inspection Report 052000/262023008
ML23268A0572023-11-0707 November 2023
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IR 05000424/20234022023-11-0606 November 2023
Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402
IR 05000424/20230032023-10-27027 October 2023
Integrated Inspection Report 05000424/2023003 and 05000425/2023003
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Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 0520026/2024401
ML23263A9852023-10-12012 October 2023
Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing
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ML23243B0252023-08-30030 August 2023
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IR 05000424/20230052023-08-29029 August 2023
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License Amendment Request: Remove Combined License Appendix C (LAR 23-008)
2024-02-05
[Table view] |
Text
September 22, 2021 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 - CORRECTION TO
SUMMARY
OF JULY 1, 2021, PUBLIC PRE-SUBMITTAL MEETING WITH SOUTHERN NUCLEAR OPERATING COMPANY, INC., REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO IMPLEMENT ALTERNATE SOURCE TERM AND TSTF-490 FOR VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (EPID L-2021-LRM-0059)
Dear Ms. Gayheart:
On July 1, 2021, an Observation Public Meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company, Inc. (SNC, the licensee). The purpose of the pre-submittal meeting was for SNC to describe its plan to submit a license amendment request (LAR) to implement alternate source term (AST) and Technical Specification Task Force (TSTF)-490-A, Deletion of E Bar Definition and Revision to RCS [Reactor Coolant System] Specific Activity Technical Specification [TS], for Vogtle Electric Generating Plant (Vogtle), Units 1 and 2).
On July 13, 2021 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML21183A151), a meeting summary was issued. There were 2 errors and 1 omission in the summary that are being corrected below.
First Error The meeting summary stated the following:
SNC stated it plans to submit to the NRC the mark-ups to TS pages and bases for the AST and TSTF-490 LAR for Vogtle, Units 1 and 2. SNC also said it plans to submit the full compliment of dose consequence analyses for the AST LAR for Vogtle, Units 1 and 2, as specified in [Regulatory Guide] RG 1.183 to support peak rod burn-ups up to < 62 gigawatt-days per metric ton uranium (GWD/MTU).
SNC said that it would submit the following dose analyses: (1) large break loss-of-coolant accident (LBLOCA), (2) fuel handling accident (FHA), (3) locked rotor accident (LRA), (4) control rod ejection (CRE), (5) steam generator tube rupture (SGTR), and (6) main steam-line break (MSLB).
C. Gayheart SNC informed the NRC staff that SNC will not submit TS mark-ups for the AST; SNC will only provide TS mark-ups for TSTF-490. Slide 4 of the SNC presentation indicated that SNC plans to submit the dose consequence analyses listed. However, SNC said that slide 4 (ADAMS Accession No. ML21172A131) contained an error and it should have read that SNC plans to update the dose consequence analyses listed. SNC has no plans to actually submit those analyses as part of the proposed LAR.
The correct paragraphs should read as follows:
SNC stated it plans to submit to the NRC the mark-ups to TS pages and bases for TSTF-490 LAR for Vogtle, Units 1 and 2. SNC also said it plans to update the dose consequence analyses listed below for the AST LAR for Vogtle, Units 1 and 2, as specified in RG 1.183 to support peak rod burn-ups up to < 62 gigawatt-days per metric ton uranium (GWD/MTU).
SNC said that it would update and not submit the following dose analyses: (1) large break loss-of-coolant accident (LBLOCA), (2) fuel handling accident (FHA),
(3) locked rotor accident (LRA), (4) control rod ejection (CRE), (5) steam generator tube rupture (SGTR), and (6) main steam-line break (MSLB).
Second Error The meeting summary stated the following:
Vogtle, Units 1 and 2, have 193 fuel assemblies in a 17-inch by 17-inch (17x17) array, and there are 264 fuel rods per assembly. The overall length of the fuel assembly is approximately 14 feet. So, 40-percent of the 264 fuel rods per assembly is approximately 105 fuel rods per assembly.
The NRC staff incorrectly stated the fuel assembly array and its length. The correct paragraph should read as follows:
Vogtle, Units 1 and 2, have 193 fuel assemblies in a 17 x17 array, and there are 264 fuel rods per assembly. The overall length of the fuel assembly is approximately 13.5 feet. So, 40-percent of the 264 fuel rods per assembly is approximately 105 fuel rods per assembly.
Omission The meeting summary stated the following paragraphs:
The NRC staff questioned what is the [linear heat generation rate] LHGR
[kilowatt per foot] kw/ft limit that SNC will request in the proposed LAR? SNC stated that the Vogtle, Units 1 and 2, LHGR kw/ft limit will be 7.5 kw/ft. SNC stated that other licensees have requested higher than 7.5 kw/ft. The NRC staff asked for SNC to provide the ADAMS Accession Nos. for those precedents.
C. Gayheart SNC stated that other licensees have requested up to 50-percent of the rods in an assembly be allowed to exceed the LHGR limit in footnote 11 in RG 1.183.
The NRC staff asked for SNC to provide the ADAMS Accession Nos. for those precedents.
The following are the revised paragraphs:
The NRC staff questioned what is the LHGR kw/ft limit that SNC will request in the proposed LAR? SNC stated that the Vogtle, Units 1 and 2, LHGR kw/ft limit will be 7.5 kw/ft. SNC stated that other licensees have requested higher than 7.5 kw/ft. The NRC staff asked for SNC to provide the ADAMS Accession Nos. for those precedents. SNC cited the letter to Wolf Creek, dated May 31, 2019 (ADAMS Accession No. ML19100A122), which cites LHGRs from 12.2 kw/ft at 35 GWD/MTU to 7.0 kw/ft at 65 GWD/MTU. SNC said other applicable precedents would be reviewed and provided to the NRC. The LHGR kw/ft will likely be 7.5 kw/ft; however, SNC did not commit to an actual value. Besides Wolf Creek cited above, other precedents that SNC stated that are consistent with its proposed LAR are (1) Kewaunee, dated March 8, 2007 (ADAMS Accession No. ML070430020), (2) Point Beach, Units 1 and 2, dated April 14, 2011 (ADAMS Accession No. ML110240054), (3) Indian Point, Unit 2, dated October 27, 2002 (ADAMS Accession No. ML042960007), and (4) Indian Point, Unit 3, dated March 22, 2005 (ADAMS Accession No. ML050750431).
SNC stated that other licensees have requested up to 50-percent of the rods in an assembly be allowed to exceed the LHGR limit in footnote 11 in RG 1.183.
The NRC staff asked for SNC to provide the ADAMS Accession Nos. for those precedents. SNC stated that Kewaunee had 50-percent of the rods in an assembly allowed to exceed the LHGR limit in footnote 11. SNC said that Indian Point, Units 2 and 3, and Point Beach, Units 1 and 2, had 100-percent of the rods in an assembly allowed to exceed the LHGR limit in footnote 11.
If you have any questions, please contact me at (301) 415-3100 or via email at John.Lamb@nrc.gov.
Sincerely,
/RA John G. Lamb, Sr. Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-424 and 50-425 cc: Listserv
ML21238A384 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DORL/LPL2-1/BC DORL/LPL2-1/PM NAME JLamb KGoldstein EMiller for MMarkley JLamb DATE 08/25/2021 08/30/2021 09/22/2021 09/22/2021
