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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement
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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 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 ML20296A6232020-10-22022 October 2020 Request for NRC Approval to Apply Leak-Before-Break Methodology to Reactor Coolant System Branch Piping Project stage: Request 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 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 ML22164A9252022-06-13013 June 2022 Page Substitutions to ADAMS Accession Number ML21294A338 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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Text
From:
gary.d.miller@dominionenergy.com Sent:
Tuesday, September 28, 2021 3:29 PM To:
Klos, John
Subject:
[External_Sender] Surry Fuel Melt Safety Limit (SL) LAR Question
- John, Per our discussion this morning regarding the update of the UFSAR as a result of the Fuel Melt Safety Limit (SL) LAR, an UFSAR update is not required as a result of the revision of the SL. As noted in Attachment 1, page 3 of 10, of the LAR discussion of the change:
The peak fuel centerline temperature SL is independent of the PAD5 methodology (Reference 2). The current licensing basis safety analyses use the existing SL 2.1.A.1.b for fuel melt as an acceptance criterion as required by the current methodology. Thus, Dominion Energy Virginia will continue to meet the existing SL when using its current licensing basis safety analyses even with the implementation of the proposed SL. Since the existing SL for peak fuel centerline temperature is more restrictive than the proposed limit, the current licensing basis safety analyses remain conservative with respect to the proposed SL.
Consequently, since we will continue to use the existing, more restrictive, SL, a UFSAR change is not necessary. However, the UFSAR Chapter 14 safety analysis will be reviewed and updated as required to address the implementation of PAD 5. The non-LOCA analyses of record updates are part of the PAD 5 implementation which is planned in 2022.
Note that this approach is consistent with the NRC SER for Turkey Point dated August 15, 2019, TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 -
ISSUANCE OF AMENDMENT NOS. 288 AND 282 REGARDING REVISED REACTOR CORE SAFETY LIMIT TO REFLECT TOPICAL REPORT WCAP-17642-P-A, REVISION 1 (EPID L-2018-LLA-0120), [ML19031C891]
which states:
As previously discussed, the peak fuel centerline temperature SL is independent of the PADS methodology. Therefore, the NRC staff reviewed the proposed SL to ensure that it is supported by the current licensing basis safety analyses. The current licensing basis safety analyses use the existing SL 2.1.1.b for fuel melt as an acceptance criterion as required by the current methodology. Thus, the licensee will continue to be required to meet the existing SL when using its current licensing basis safety analyses even with the implementation of the proposed SL. Since the existing SL for peak fuel centerline temperature is more restrictive than the proposed limit, the current licensing basis safety analyses will remain conservative to the proposed SL Thus, the staff determined that the proposed limit is acceptable with the Turkey Point current licensing basis.
Please advise if you have any further questions.
Gary D. Miller Consulting Engineer - Corporate Licensing Nuclear Regulatory Affairs Dominion Energy, Inc.
(804) 273-2771 CONFIDENTIALITY NOTICE: This electronic message contains information which may be legally confidential and or privileged and does not in any case represent a firm ENERGY COMMODITY bid or offer relating thereto which binds the sender without an additional express written confirmation to that effect. The information is intended solely for the individual or entity named above and access by anyone else is unauthorized. If you are not the intended recipient, any disclosure, copying, distribution, or use of the contents of this information is prohibited and may be unlawful. If you have received this electronic transmission in error, please reply immediately to the sender that you have received the message in error, and delete it. Thank you.
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Subject:
[External_Sender] Surry Fuel Melt Safety Limit (SL) LAR Question Sent Date:
9/28/2021 3:29:14 PM Received Date:
9/28/2021 3:29:24 PM From:
gary.d.miller@dominionenergy.com Created By:
gary.d.miller@dominionenergy.com Recipients:
"Klos, John" <John.Klos@nrc.gov>
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