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Category:Memoranda
MONTHYEARML24122C6202024-05-0101 May 2024 Public Meeting Summary - 2023 Annual Assessment Meeting Vogtle Electric Generating Plant, Units 1, 2, 3, and 4 Docket Nos.. 50-424, 50-424, 52-025, and 52-026 Meeting Number 20240471 ML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ML23303A2032023-11-0101 November 2023 October 24, 2023, Summary of Comment Gathering Public Meeting on Lessons Learned from the ITAAC Hearing Process for Vogtle Units 3 and 4 ML22348A0862023-07-25025 July 2023 Finding in Accordance with 10 CFR 52.103(G) That All Acceptance Criteria Are Met for Vogtle Electric Generating Plant, Unit 4 ML23115A0382023-05-0909 May 2023 Summary of Readiness Group Public Meeting on April 20, 2023 ML23115A0662023-05-0101 May 2023 Summary of Public Meeting with Southern Nuclear Operating Company to Have Presubmittal Meeting for Vogtle Electric Generating Plant, Unit 4 IR 05000424/20040252023-04-28028 April 2023 Public Meeting Summary - Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 5000424, 5000425, 5200025, 5200026, Meeting Number 20230375 ML22214B4882023-02-0808 February 2023 Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 4 ML22355A0322023-01-0303 January 2023 Revised Charter for the Vogtle Readiness Group to Oversee the Transition to Operations for Vogtle Units 3 and 4 ML22334A0812022-12-0101 December 2022 Update to Targeted Inspections, Tests, Analysis, and Acceptance Criteria for Vogtle Electric Generating Plant Unit 4 ML22322A1672022-11-28028 November 2022 Summary of 11/15/2022 Public Meeting on Lessons Learned ML22237A0782022-08-0505 August 2022 American Nuclear Insurers, Notification of Change in the Number of Power Reactors in the Secondary Financial Protection (SFP) Program ML20290A2812022-08-0101 August 2022 103g - Final Memorandum ML22123A0652022-05-0202 May 2022 Public Meeting Summary Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 50-424, 50-425, 52-025, 52-026, Meeting Number 20220330 ML21337A0032021-12-0707 December 2021 Summary of Vogtle Readiness Group Public Meeting on December 2, 2021 ML21322A1502021-12-0202 December 2021 Summary of November 10, 2021 Public Meeting with Southern Nuclear Operating Company ML21316A0692021-11-22022 November 2021 November 4, 2021 Summary of Public Meeting with Southern Nuclear Operating Company ML21280A2962021-10-22022 October 2021 Replacement of Page 2 to Letter Dated June 30, 2020, Titled License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions (EPID L-2020-LLA0150) ML21230A0102021-08-24024 August 2021 Summary of Public Meeting with Southern Nuclear Operating Company on August 12, 2021 ML21194A0402021-07-20020 July 2021 Summary of June 24, 2021 Public Meeting with SNC ML21154A2772021-07-20020 July 2021 Summary of a Public Meeting with Southern Nuclear Operating Company on May 27, 2021 ML21190A0622021-07-16016 July 2021 Summary of July 8 2021 Public Meeting to Discuss Late-Filed Allegation Process for Vogtle Electric Generating Plant Units 3 and 4 ML21194A0392021-07-16016 July 2021 July 8, 2021 Summary of Public Meeting with Southern Nuclear Operating Company ML21124A2032021-05-0606 May 2021 ASME Alternative ALT-16 Pre-submittal Meeting Summary 4-29-21 ML21123A1432021-05-0505 May 2021 April 22, 2021, Summary of a Public Meeting with Southern Nuclear Operating Company ML20318A2422020-12-18018 December 2020 .72 50.73 Applicability Memo ML20351A2822020-12-10010 December 2020 Summary of Public Meeting with Southern Nuclear Operating Co ML20318A2412020-11-18018 November 2020 Summary of Public Meeting with Southern Nuclear Operating Company, to Discuss Topic Regarding Vogtle Electric Generating Plant, Unit 4: ITAAC Post Closure Notification for ITAAC Index Number 344 ML20303A0422020-11-0505 November 2020 Summary of October 22, 2020 Public Meeting with Southern Nuclear Operating Company NL-20-1262, Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion2020-10-30030 October 2020 Submission of Proposed Alternative to Submitting Vogtle Unit 2 Inservice Inspection Summary Report within 90 Days of Outage Completion ML20296A2432020-10-15015 October 2020 Summary of 10-15-20 Public Meeting with Southern Nuclear Operating Company ML20283A4652020-10-15015 October 2020 Summary of Public Meeting on October 8, 2020 with Southern Nuclear Operating Company ML20279A5202020-10-0707 October 2020 October 1, 2020, Summary of Public Meeting with Southern Nuclear Operating Company ML20183A0902020-09-24024 September 2020 Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 3 ML20262G9882020-09-22022 September 2020 September 17, 2020 Summary of Public Meeting with Southern Nuclear Operating Company ML20248H3292020-09-10010 September 2020 Meeting Summary for September 3, 2020 Public Meeting with Southern Nuclear Operating Company ML20247J4812020-09-10010 September 2020 Summary for August 27, 2020 Public Meeting with Southern Nuclear Operating Company ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ML20216A6362020-08-10010 August 2020 Summary of a Public Meeting with Southern Nuclear Operating Company on July 23, 2020 ML20216A6252020-08-10010 August 2020 Summary of a Public Meeting with Southern Nuclear Operating Company on July 30, 2020 ML20205L4312020-07-29029 July 2020 Summary of a Public Meeting with Southern Nuclear Operating Company to Discuss Inspections, Tests, Analyses and Acceptance Criteria Nos. 375 and 216 ML20178A1302020-07-15015 July 2020 Memorandum Transmitting Safety Evaluation Regarding Welded Reinforcement Bar Splices at Vogtle Electric Generating Plant Units 3 and 4 ML20190A0182020-07-0808 July 2020 Summary of Meeting Regarding the Vogtle Readiness Group ML20168A3352020-06-26026 June 2020 Summary of June 11, 2020 Public Meeting with Southern Nuclear Operating Company ML20150A0092020-06-0202 June 2020 Summary of May 28, 2020 Public Meeting with Southern Nuclear Operating Company ML20154K7272020-06-0202 June 2020 EOC Meeting Summary ML20141L6182020-06-0101 June 2020 Summary of May 14, 2020 Public Meeting with Southern Nuclear Operating Company ML20141L6982020-05-26026 May 2020 Audit Report for Vogtle Electric Generating Plant Unit 3 LAR 20-001: Auxiliary Building Wall 11 Seismic Gap Requirements ML20133K1062020-05-15015 May 2020 Audit Plan for Vogtle Electric Generating Plant Units 3 and 4, Request for License Amendment: Core Makeup Tank Boron Concentration Requirements (LAR 20-004) 2024-05-01
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August 29, 2005 MEMORANDUM TO: Evangelos Marinos, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Christopher Gratton, Sr. Project Manager, Section 1 /RA/
Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
VOGTLE ELECTRIC GENERATING STATION, UNITS 1 AND 2 -
FACSIMILE TRANSMISSION OF DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MC4225 AND MC4226)
The Nuclear Regulatory Commission (NRC) staff transmitted the attached facsimile containing questions to Mr. Jack Stringfellow of the Southern Nuclear Operating Company on June 16, 2005. The request for additional information supported a June 30, 2005, conference call with the licensee regarding their application dated August 13, 2004. The licensees application proposed to supplant the previous spent fuel pool rack criticality analysis with updated criticality calculations.
This memorandum and the attached questions do not convey or represent an NRC staff position regarding the licensees request.
Docket Nos. 50-424 and 50-425 Attachments: 1. Request for Additional Information sent 6/16/2005
ML052380434 NRR-106 OFFICE PM/PD2-1 LA/PD2-1 NAME CGratton CHawes DATE 8/29/05 8/29/05 DRAFT SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION (RAI)
SPENT FUEL POOL RACK CRITICALITY ANALYSIS SOUTHERN NUCLEAR OPERATING COMPANY (SNC)
VOGTLE ELECTRIC GENERATING PLANT (VEGP), UNITS I AND 2 DOCKET NUMBERS: 50-424 AND 50-425
- 1. Regarding calculation X6CKA.01, dated 9/25/97, the results for both methods demonstrate that the criticality assumption is bounded by the manufacturing specifications of both types of panels, but it is not clear to the staff whether manufacturing tolerances were factored into the calculations. Please discuss whether manufacturing tolerances were factored into the B-10 areal density calculations.
- 2. In your response to RAI No.1b (ML051260207), you stated that Maine Yankee (MY) had implemented a surveillance procedure once per cycle which involved drag testing and visual inspection of the cells to monitor for signs of bulging. Given that blistering is now known to occur in the Boral panels, does VEGP have any surveillance procedures in place, and if not, does it plan to implement any surveillance procedures similar to those at MY to monitor the potential for bulging and blistering (via drag testing, visual inspection or any other method)?
- 3. In your response to RAI No. 3 (ML051260207), you named some of the conservatisms that would offset the effects of blistering on reactivity. Two of the conservatisms were that the B-10 content is uniformly reduced by 10 percent and that the limiting flux trap size is modeled. Regarding the B-10 content conservatism, the staff is not clear whether this 10 percent reduction is taken from the value of 0.0238 g/cm2 or if it is already included in this value. With respect to the modeling of the flux trap size, it is not clear to the staff what this entails. Is this assumption meant to take into account the effects of blistering on reactivity?
- 4. In your response to RAI No. 3 (ML051260207), you stated that SNC continues to monitor issues regarding the application of Boral in spent fuel racks through its Operating Experience and Corrective Actions Program and through the internal operating experience at one of its other plants that has a Boral surveillance program.
The staff would like more information regarding the use of Boral in the other SNC plant; for example:
- a. How long has the Boral been in use there?
- b. What kind of tests are performed and how often have the coupons been tested?
- c. Is the coupon environment (fuel exposure) similar to that of VEGP?
ATTACHMENT
In addition, the staff would like to confirm that VEGP has the proper material certification documentation from MY for any testing and a discussion of the results performed to the Boral prior to their installation in VEGP.