Letter Sequence Acceptance Review |
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MONTHYEARLR-N20-0010, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2020-04-24024 April 2020 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology Project stage: Request ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping Project stage: Request ML20302A2012020-10-22022 October 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 - Acceptance Review (L-2020-LLA-0219) Project stage: Acceptance Review ML20338A5422020-12-0303 December 2020 Proposed License Amendment Request, Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis Project stage: Request ML20346A1032020-12-11011 December 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 LBB LAR - Acceptance Review (L-2020-LLA-0255) Project stage: Acceptance Review ML20364A0172020-12-28028 December 2020 NRR E-mail Capture - Surry Power Station, Units 1 and 2 AST LAR - Acceptance Review (L-2020-LLA-0258) Project stage: Acceptance Review ML21084A2732021-03-24024 March 2021 License Amendment Request - Application of Leak-Before-Break Methodology to Reactor Coolant System Branch Piping - Response to Request for Additional Information and Clarification Project stage: Response to RAI ML21127A1362021-05-13013 May 2021 May 13, 2021 NRC Pre-Submittal Meeting - Surry Power Station New Fuel Storage and Spent Fuel Pool Criticality Analysis Proposed License Amendment Request Project stage: Meeting ML21133A4212021-05-13013 May 2021 Response to NRC Request for Additional Information Regarding Proposed License Amendment Request Update of LOCA Alternative Source Term Dose Analysis Project stage: Response to RAI ML21270A0232021-07-0707 July 2021 State of Virginia Notification of Pending Amendment Issuance Ref: Surry Power Station, Units 1 and 2 - Request to Revise Technical Specifications 2.1.A.1.b Project stage: Other ML21175A1852021-08-20020 August 2021 Issuance of Amendment Nos. 304 and 304 Leak-Before-Break for Pressurizer Surge, Residual Heat Removal, Safety Injection Accumulator, Reactor Coolant System Bypass and Safety Injection Lines Project stage: Approval ML21272A0622021-09-28028 September 2021 NRR E-mail Capture - (External_Sender) Surry Fuel Melt Safety Limit (SL) LAR Question Project stage: Other ML21277A0652021-09-30030 September 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer Project stage: Request ML21286A7372021-10-13013 October 2021 Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR Project stage: Request ML21292A3022021-10-19019 October 2021 Response to Question on License Amendment Request to Revise Reactor Core Safety Limit Project stage: Request ML21294A3382021-10-21021 October 2021 Proposed Amendment to Relocate Unit Staff Qualification Requirements from Technical Specifications to Nuclear Facility Quality . Project stage: Request ML21188A1742021-10-26026 October 2021 Issuance of Amendment Nos. 305 and 305 Revised Reactor Core Safety Limit to Reflect Topical Report WCAP-177642-P-A, Revision 1 Project stage: Approval ML21307A4302021-11-0909 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Surry Post LOCA Buffer Change Project stage: Acceptance Review ML21253A0632021-11-19019 November 2021 Issuance of Amendment Nos. 306 and 306 to Update of the Loss of Coolant Accident Alternate Source Term Dose Analysis Project stage: Approval ML21326A1502021-11-22022 November 2021 NRR E-mail Capture - Acceptance Review for Relocation of Unit Staff Requirements to the QAPD LAR (L-2021-LLA-0195) Project stage: Acceptance Review ML21334A1692021-11-29029 November 2021 Proposed License Amendment Request Removal of Refueling Water Chemical Additional Tank and Replacement of Containment Buffer Supplemental Information Project stage: Supplement ML21340A1642021-12-0606 December 2021 Acceptance of Requested Licensing Action Amendment Project stage: Acceptance Review ML22004A2872022-01-14014 January 2022 Technical Specification Section 3.4.A.4 Change of Post Loss-of-Coolant Accident Chemical Buffer Audit Plan Project stage: Other ML22077A0542022-03-18018 March 2022 Change in Engineering Hours Estimate Surry Ph Buffer LAR Acceptance Project stage: Approval ML22089A0092022-04-13013 April 2022 Regulatory Audit Summary Related to the License Amendment Request to Change Loss-Of-Coolant Accident Chemical Buffer Project stage: Other ML22153A1352022-06-0202 June 2022 Proposed License Amendment Request (LAR) - Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Additional Information Project stage: Response to RAI ML22164A9252022-06-13013 June 2022 Page Substitutions to ADAMS Accession Number ML21294A338 Project stage: Request ML22164A8532022-06-13013 June 2022 Proposed License Amendment Request Removal of Refueling Water Chemical Addition Tank and Replacement of Containment Sump Buffer - Response to Request for Confirmation Project stage: Request ML22095A1072022-07-11011 July 2022 Issuance of Amendment Nos. 120, 344, & 284, 293 & 276, & 307 & 307 to Relocate Requirements to the QAPD Project stage: Approval ML22193A2952022-08-26026 August 2022 Issuance of Amendment Nos. 308 and 308 License Amendment Request for Removal of the Refueling Water Chemical Addition Tank and Containment Sump, Ph Buffer Change and Safety Evaluation Project stage: Approval ML22250A6672022-10-12012 October 2022 Correction to Issuance of Amendment Nos. 304 (EPID L-2020-LLA-0255), 305 (EPID L-2020-LLA-0219) 306 (EPID L-2020-LLA-0258), 307 (EPID L-2021-LLA-0195) and 308 Project stage: Approval 2021-12-06
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[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50 Request for Additional Information (RAI)
MONTHYEARML21307A4302021-11-0909 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Action Surry Post LOCA Buffer Change 2021-11-09
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Text
November 9, 2021 Mr. Daniel G. Stoddard Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
SURRY POWER STATION, UNITS 1 AND 2 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF PROPOSED LICENSE AMENDMENT REQUEST - REMOVAL OF REFUELING WATER CHEMICAL ADDITION TANK AND REPLACEMENT OF CONTAINMENT SUMP BUFFER (EPID L-2021-LLA-0179)
Dear Mr. Stoddard:
By letter dated September 30, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21277A065), Dominion Energy Virginia submitted a license amendment request for Surry Power Station, Units, 1 and 2 (Surry). The proposed amendment would revise the Surry TSs to eliminate the Refueling Water Chemical Addition Tank (CAT) and allow the use of sodium tetraborate decahydrate (NaTB) to replace sodium hydroxide (NaOH) as a chemical additive (buffer) for containment sump pH control following a loss-of-coolant accident (LOCA). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an application for an amendment to a license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has completed the acceptance review of the proposed amendments in accordance with Office of Nuclear Reactor Regulation (NRR) Office Instruction LIC-109, Revision 3 Acceptance Review Procedures for Licensing Basis Changes, dated July 20, 2020 (ADAMS Accession No. ML ML20036C829), and determined that additional information is needed for the NRC to begin its detailed technical review. The enclosure to this letter delineates the information needed for the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements for the protection of public health and safety and the environment.
D. Stoddard In order to make the application complete, the NRC staff requests that Dominion Energy Virginia supplement the application to address the information requested above within working 13 days of the date of this letter which is November 30, 2021.
If the information responsive to the NRC staffs request is not received within 13 working days of the date of this letter, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its activities associated with the application under EPID No. L-2021-LLA-0179. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence. If any information requested in the enclosure is available in other correspondence on the docket (e.g., seismic, Generic Letter 2004-02, etc.), please indicate where the NRC can find this related information. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staffs detailed technical review by separate correspondence.
The information requested and associated time frame in this letter were discussed with Mr.
Gary Miller of your staff on November 9, 2021.
If you have any questions, please contact me at (301) 415-5136.
Sincerely,
/RA/
John Klos, Project Manager Plant Licensing Branch 2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-280, 50-281
Enclosure:
Supplemental Information Needed cc: Listserv
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST FOR REMOVAL OF REFUELING WATER CHEMICAL ADDITION TANK AND REPLACEMENT OF CONTAINMENT SUMP BUFFER DOMINION ENERGY VIRGINIA SURRY, UNIT NOS. 1 AND 2 DOCKET NO(S). 50-280, 50-281
- 1. A description of how the NaTB (sodium tetraborate decahydrate) will be stored, such as the number of baskets, size, detailed x-y-z location, and how they are designed to contain the NaTB while allowing access for the water to dissolve the NaTB.
- 2. A summary of the post-LOCA borated water sources, with a description of the boron concentrations evaluated.
- 3. A summary of the sources of other acids and bases included in the post-LOCA pH calculation, and reference to how they were calculated.
- 4. A description of the methodology and results for calculating pH and the required NaTB quantity, or the associated analysis.
- 5. For each case considered, a description of how input values and ranges were selected for the water and chemicals used in the calculations (e.g., water, boron, NaTB, and other applicable acids and bases).
- 6. An explanation for how the mass of NaTB would be measured in order to meet the proposed requirement in Technical Specification 3.4.A.4.
- 7. A description of the test that will be performed to verify that the NaTB in the baskets provides adequate pH adjustment, according to the proposed sampling test #4 in the license amendment submission, Table 4.1-2B, Minimum Frequencies for Sampling Tests.
- 8. Proposed revisions to Final Safety Analysis Report Sections such as 6.1 (General Description), 6.2.3.3 (Chemical Additives), and 6.3.1 (Spray System), which describe the use and characteristics of sodium hydroxide as the chemical additive and are used to derive the proposed TS in accordance with Title 10 Code of Federal Regulations Section 50.36.
- 9. A reference to the current GL 2004-02, Potential Impact of Debris Blockage On Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, chemical effects assessment of record for Surry Units 1 and 2 that supports the license amendments statement of reducing chemical precipitate and discussion, as appropriate, describing how this change may affect post-LOCA sump volumes.
- 10. General structural arrangement drawing(s) of the new containment chemical baskets documenting the basket support structure, including basket weight and basket design details.
- 11. Objective evidence (e.g., data, calculations, etc.) to support the statement in the license amendment that The design loads for the baskets are generated by combining the unfactored load effects of dead loading, chemical pressure loading, and seismic loading[the] baskets were evaluated to maintain their structural integrity during a Design Basis Earthquake event concurrent with post LOCA elevated temperature conditions. This information should indicate the applicable design code applied, Enclosure
applicable design loads, load combinations used for the design, a summary of computed stresses, and margins showing the structural integrity of the baskets.
- 12. A discussion on the high energy lines in the vicinity of the baskets, and how the baskets are protected from HELB effects (jet impingement and pipe whip) is not included.
ML21307A430 *by email OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DNRL/NCSG/BC*
NAME John Klos KGoldstein SBloom DATE 11/3/2021 11/04/2021 11/3/2021 OFFICE NRR/DEX/ESEB/BC* NRR/DEX/EMIB/BC* NRR/DORL/DD*
NAME JColaccino ITseng CCarusone DATE 11/3/2021 11/3/2021 11/3/2021 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JKlos DATE 11/4/2021 11/9/2021