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| | number = ML051160316 | | | number = ML051160316 |
| | issue date = 04/27/2005 | | | issue date = 04/27/2005 |
| | title = Memo, Facsimile Transmission of Draft RAI (TAC MC4225 and MC4226) | | | title = Memo, Facsimile Transmission of Draft RAI |
| | author name = Gratton C | | | author name = Gratton C |
| | author affiliation = NRC/NRR/DLPM/LPD2 | | | author affiliation = NRC/NRR/DLPM/LPD2 |
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| | page count = 6 | | | page count = 6 |
| | project = TAC:MC4225, TAC:MC4226 | | | project = TAC:MC4225, TAC:MC4226 |
| | stage = Draft RAI | | | stage = Draft Other |
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| : 3. Revised 11/30/2004 RAI sent 3/24/2005 | | : 3. Revised 11/30/2004 RAI sent 3/24/2005 |
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| ML051160316 NRR-106 OFFICE PM/PD2-1 LA/PD2-1 NAME CGratton CHawes DATE 04/27/05 04/27/05 | | ML051160316 NRR-106 OFFICE PM/PD2-1 LA/PD2-1 NAME CGratton CHawes DATE 04/27/05 04/27/05 DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST SPENT FUEL RACK CRITICALITY ANALYSES VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425 |
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| DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST SPENT FUEL RACK CRITICALITY ANALYSES VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425 | |
| : 1. On page 20 of attachment 5 to your submittal, you stated that the Boral replacement Phase I racks were manufactured with new Boral plates and the Phase II racks were manufactured with both new and reclaimed Boral plates. The NRC staff requests the licensee to answer the following questions: | | : 1. On page 20 of attachment 5 to your submittal, you stated that the Boral replacement Phase I racks were manufactured with new Boral plates and the Phase II racks were manufactured with both new and reclaimed Boral plates. The NRC staff requests the licensee to answer the following questions: |
| : a. Explain the difference between what is consider a new and what is consider a reclaimed Boral plate. | | : a. Explain the difference between what is consider a new and what is consider a reclaimed Boral plate. |
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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 ML21154A2772021-07-20020 July 2021 Summary of a Public Meeting with Southern Nuclear Operating Company on May 27, 2021 ML21194A0402021-07-20020 July 2021 Summary of June 24, 2021 Public Meeting with SNC 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 ML20216A6252020-08-10010 August 2020 Summary of a Public Meeting with Southern Nuclear Operating Company on July 30, 2020 ML20216A6362020-08-10010 August 2020 Summary of a Public Meeting with Southern Nuclear Operating Company on July 23, 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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A1572024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley and Vogtle 1 and 2 - Alternative Request for Pressurizer Welds (L-2024-LLR-0047) ML24290A1552024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572 ML24289A2002024-10-15015 October 2024 NRR E-mail Capture - for Your Action - RAI - Proposed License Amendment Request (LAR) for Vogtle Electric Generating Plant, Units 3 and 4 TS 3.7.6 Action E and SR 3.7.6.5 (L-2024-LLA-0083) ML24199A1592024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information - Vogtle 3 and 4 - Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Report ML24100A7842024-04-0909 April 2024 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle, Units 3 and 4 - Alternative Request for Explosively Actuated Valves (L-2023-LLR-0016) ML24072A3982024-03-12012 March 2024 NRR E-mail Capture - for Your Action - Second Round Request for Additional Information (RAI) - Vogtle, Unit 1 - SG Tube Inspection Report - 1R24 (L-2023-LRO-0067) ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23342A0802023-12-0808 December 2023 NRR E-mail Capture - Request for Additional Information (RAI) - Vogtle, Unit 1 - Review of SG Tube Inspection Report for Refueling Outage 24 (L-2023-LRO-0067) ML23279A2082023-10-0505 October 2023 Issuance of Formal RAIs - Vogtle, Units 1 and 2 - Proposed LAR and Proposed Alternative Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23248A3482023-09-0505 September 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 6 - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23188A1512023-08-0909 August 2023 Round 2 RAIs for LAR 22-002 TS 3.8.3 Inverters-Operating, Completion Time Extension ML23200A0112023-07-18018 July 2023 Document Request for Vogtle Unit 3 RP Inspection ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23193A7832023-07-12012 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23065A0612023-03-0303 March 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 14 - Vogtle - AST, TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML23006A0882023-01-0606 January 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - Accident Source Term (Ast), TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML22348A0332022-12-13013 December 2022 NRR E-mail Capture - for Your Action - RAI - Vogtle, Unit 2 - Steam Generator Tube Inspection Report (L-2022-LRO-0120) ML22192A1042022-08-0101 August 2022 Acceptance of Requested Licensing Action Amendment Request Application to Allow Use of Lead Test Assemblies for Accident Tolerant Fuel with Request for Additional Information ML22157A0902022-06-0606 June 2022 NRR E-mail Capture - RAIs - Vogtle, Unit 1 - Refueling Outage (RFO) 1R23 Steam Generator (SG) Tube Inspection Report ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML22026A3942022-01-26026 January 2022 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21350A1032021-12-16016 December 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21321A3762021-11-15015 November 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21033B1072021-02-0202 February 2021 NRR E-mail Capture - RAI - Vogtle Unit 1 - SG Report (L-2020-LRO-0059) ML20338A1512020-12-0303 December 2020 NRR E-mail Capture - RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20325A0432020-11-20020 November 2020 NRR E-mail Capture - for Your Review - Draft RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20297A3052020-10-22022 October 2020 NRR E-mail Capture - RAIs for Vogtle Relief Request - EPRI Report (L-2020-LLR-0109) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML19263A6432019-09-19019 September 2019 NRR E-mail Capture - RAI - Vogtle End State License Amendment Request (LAR) to Revise the Technical Specifications (Tss) for Vogtle, Units 1 and 2 (L-2019-LLA-0148) ML19156A1872019-06-0505 June 2019 NRR E-mail Capture - Request for Additional Information (RAI) for Vogtle Unit 2 Core Operating Limits Report, Cycle 21 ML19105B1632019-04-15015 April 2019 NRR E-mail Capture - Request for Additional Information (RAI) for Voglte TSTF-412 Adoption LAR (L-2018-LLA-0731) ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18236A4452018-08-30030 August 2018 Review of Response to RAI License Amendment Request for Approval to Utilize the Tornado Missile Risk Evaluator to Analyze Tornado Missile Protection Non-Conformances ML18227A0222018-08-15015 August 2018 Notification of Inspection and Request for Information ML18225A3362018-08-13013 August 2018 NRR E-mail Capture - Request for Additional Information Regarding Relief Request VEGP-ISI-RR-03 ML18197A0602018-07-13013 July 2018 Us NRC Final RAI No. 1 for Vogtle 3 and 4 LAR-18-015, Fire Protection System Non-Safety Cable Spray Removal ML18197A1882018-07-13013 July 2018 Us NRC Final Request for Additional Information (Final RAI) No. 4 on Vogtle LAR-17-024, Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes ML18197A1052018-07-13013 July 2018 Us NRC Final Request for Additional Information (Final RAI) No. 1 on Vogtle 3 and 4 LAR-17-043, Containment Pressure Analysis ML18192C0782018-07-11011 July 2018 RAI (LAR 18-009) - Vogtle Electric Generating Plant, Unit 3 and 4 ML18192B7692018-07-11011 July 2018 Us NRC Draft Request for Additional Information (Draft RAI) No. 4 on Vogtle LAR-17-024, Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes ML18136A4972018-06-0101 June 2018 Request for Additional Information, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18109A1152018-05-0101 May 2018 Request for Additional Information ML18079A9572018-03-28028 March 2018 Request for Additional Information Incorporate Seismic Probabilistic Risk Assessment Into the 10 CFR 50.69 Categorization Process (CAC Nos. MF9861 and MF9862; EPID L-2017-LLA-0248) ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18030B0622018-02-0808 February 2018 Request for Additional Information Reverse Technical Specification 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MG0240, MG0241; EPID L-2017-LLA-0295) 2024-07-17
[Table view] |
Text
April 27, 2005 MEMORANDUM TO: John A. Nakoski, 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 facsimiles containing questions to Mr. Jack Stringfellow of the Southern Nuclear Operating Company on November 30 2004 (Attachment 1), February 11, 2005 (Attachment 2), and March 24, 2005 (Attachment 3). The requests for additional information (RAIs) supported conference calls with the licensee regarding their application dated August 13, 2004. The February 17 call discussed the February 11, 2005, RAI, the February 22 call discussed the November 30, 2004, RAI, and the April 7, 2005, call was held to ensure the scope and breadth of the responses was clear. The licensees application proposed to supplant the previous spent fuel pool rack criticality analysis with updated criticality calculations.
During the February 17, 2004, call, it was determined that the responses to questions 1 and 2 of the February 11, 2005, RAI resided in material already docketed, which was contained in the application, or was not needed to arrive at a safety conclusion. Therefore, the NRC staff determined that no response was necessary. The NRC staff clarified what information was needed for questions 3a, 3b, and 4. The NRC staff transmitted a revised RAI, enclosed in this noted-to-file as Attachment 3, on March 24, 2005. No other changes to any RAI was deemed necessary based on the conference calls. The NRC staff agreed that responses could be consolidated, as necessary. The licensee also agreed to provide a description of axial reactivity effects as part of their overall response.
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 11/30/2004
- 2. Request for Additional Information sent 2/11/2005
- 3. Revised 11/30/2004 RAI sent 3/24/2005
ML051160316 NRR-106 OFFICE PM/PD2-1 LA/PD2-1 NAME CGratton CHawes DATE 04/27/05 04/27/05 DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST SPENT FUEL RACK CRITICALITY ANALYSES VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425
- 1. On page 20 of attachment 5 to your submittal, you stated that the Boral replacement Phase I racks were manufactured with new Boral plates and the Phase II racks were manufactured with both new and reclaimed Boral plates. The NRC staff requests the licensee to answer the following questions:
- a. Explain the difference between what is consider a new and what is consider a reclaimed Boral plate.
- b. The licensee stated that the boral replacement racks were originally constructed for the Main Yankee spent fuel pool (SFP). Please clarify if these racks were ever used in the Maine Yankee SFP. If the racks were used, then clarify if the racks were checked to ascertain the physical state of the racks and tested for any degradation (e.g, blistering, etc.) prior to installation in the Vogtle SFP.
- c. Was the B-10 content verified prior to installation? Is it the same amount for both the new and reclaimed plates?
- d. Are there any manufacturing or material differences between these types of plates? If there are differences, explain how these differences are accounted for in the expected performance of Boral.
- 2. On page 8 of attachment 5 to your submittal, you stated that for conservatism, all of the Vogtle, Unit 1 storage cells were simulated with the dimensions associated with the thickest (0.2 inches) Boral plates. The staff believes that instead of using the reclaimed plates, more conservatism would be introduce by using the new plates, which have a thickness of 0.081 inches. Please explain how would more conservatism be introduced in the computer model by using the thickest Boral plates.
- 3. Recently, incidents of Boral blistering have been reported and the impact on the expected performance of this material is not yet known. The NRC staff requests the licensee to explain if a Boral coupon surveillance program is in place to monitor Boral degradation. The licensee should include a complete description of its program (see below). If a program does not currently exists, the NRC staff requests the licensee to implement a coupon surveillance program to ensure consistent material performance.
This program should monitor the physical and chemical properties of Boral over time and should include the following:
Attachment 1
I. A description of the coupons used (e.g., from the same lot as the panels).
II. The technique for measuring the initial Boron-10 (B-10) content of the coupons.
III. Frequency of coupon removal and its justification.
IV. Tests to be performed on the coupons (e.g., weight and dimension measurement (length, width and thickness), and B-10 content.
In addition, the licensee should discuss the impact it would have on the analyses should the coupons reveal a change in material performance from that assumed in the analyses.
DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST SPENT FUEL RACK CRITICALITY ANALYSES VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425
- 1. The vendor for the rack analysis stated that the methodology proposed in the application dated August 13, 2004, would not be used again. Please explain the basis for basing your application on this methodology.
- 2. The shortcomings of the Westinghouse methodology are alluded to on page E1-1 of Enclosure 1, namely, the axial shape bias and the reactivity equivalencing techniques.
The first of these is dealt with on page 29 of Enclosure 5. Section 3.3 discusses the modeling utilized to simulate the axial depletion. However, upon reading this section, it is apparent that axial depletion is not being performed, rather, the method appears to assume a uniform axial distribution. Does the methodology use a uniform axial distribution, and if so, why, when the majority of the industry depletes the assemblies using a number of axial zones?
- 3. a. In the second paragraph of Section 3.3 of attachment 5, reference is made to average moderator and temperature profiles utilized to perform spectral calculations. However, no basis was provided for these choices. Please provide the basis for these selections.
- b. In the third paragraph of Section 3.3, reference is made to the use of boron in all the DIT (Discrete Integral Transport) calculations. Were these calculations performed in compliance with NUREG-6683, A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage," September 2000.
- 4. It is not clear to the NRC staff where the subject of reactivity equivalencing is discussed and employed. If so, why is this practice being used when practically every other licensee and vendor has stopped using it. Please provide chapter and section pointing to this subject matter.
Attachment 2
DRAFT REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST SPENT FUEL RACK CRITICALITY ANALYSES VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-424 AND 50-425
- 1. On page 20 of attachment 5 to your submittal, you stated that the Boral replacement Phase I racks were manufactured with new Boral plates and the Phase II racks were manufactured with both new and reclaimed Boral plates. The staff requests the licensee to answer the following questions:
- a. Explain the difference between what is consider a new and what is consider a reclaimed Boral plate.
- b. The licensee stated that the Boral replacement racks were originally constructed for the Maine Yankee spent fuel pool (SFP). Please clarify if these racks were ever used in the Maine Yankee SFP. If the racks were used, then clarify if the racks were checked to ascertain the physical state of the racks and tested for any degradation (e.g., blistering, etc.)
prior to installation in the Vogtle SFP.
- c. Was the B-10 content verified prior to installation? Is it the same amount for both the new and reclaimed plates?
- d. Are there any manufacturing or material differences between these types of plates? If there are differences, the licensee should explain how these differences are accounted for in the expected performance of Boral.
- 2. On page 8 of attachment 5 to your submittal, you stated that for conservatism, all of the Vogtle, Unit 1 storage cells were simulated with the dimensions associated with the thickest (0.2 inches) Boral plates. The staff believes that instead of using the reclaimed plates, more conservatism would be introduce by using the new plates, which have a thickness of 0.081 inches. Please explain how would more conservatism would be introduced in the computer model by using the thickest Boral plates.
- 3. Recently, incidents of Boral blistering have been reported and the impact on the expected performance of this material is not yet known. The NRC staff requests the licensee to explain if a Boral coupon surveillance program is in place to monitor Boral degradation. The licensee should include a complete description of its program (see below). Discuss your plans to implement a coupon surveillance program to ensure consistent material performance. A coupon surveillance program should monitor the physical and chemical properties of Boral over time and should include the following:
I. A description of the coupons used (e.g., from the same lot as the panels).
II. The technique for measuring the initial Boron-10 (B-10) content of the coupons.
III. Frequency of coupon removal and its justification.
IV. Tests to be performed on the coupons (e.g., weight and dimension measurement: length, width and thickness), and B-10 content.
Attachment 3
In addition, the licensee should discuss the impact it would have on the analyses should the coupons reveal a change in material performance from that assumed in the analyses.
- 4. In your submittal dated November 20, 1997, an areal density of 0.0238 g/cm2 was assumed for the criticality analysis. In your submittal dated August 13, 2004, this same value is also assumed. Given that the racks have been exposed to radiation for many years at Maine Yankee and approximately 7 years at Vogtle; and tests have not been performed to verify the areal density of the panels prior to installation, provide the technical basis for the assumed areal density value and its continued use in the current criticality analysis. This justification should address Reference 4 of your November 20, 1997 submittal and industry experience.