|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:From: gary.d.miller@dominionenergy.com To: Klos, John |
| | |
| | ==Subject:== |
| | [External_Sender] Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR Date: Wednesday, October 13, 2021 3:17:05 PM |
| | : John, In addition to the information provided below and as a result of the clarification call between Dominion Energy and the NRC this afternoon, this email is provided to identify an additional implementation plan item associated with the Surry Power Station Units 1 and 2 License Amendment Request to revise the TS 2.1.A.1.b safety limit for fuel melt. Specifically, UFSAR section 3.4.1.1 will be revised as part of the implementation plan for the license amendments following their issuance to include the revised fuel melt safety limit and its technical basis. Furthermore, the UFSAR will be reviewed and additional UFSAR changes will be implemented, if required, to reflect the revised fuel melt safety limit. |
| | If you have any questions or require additional information, please do not hesitate to ask. |
| | Respectfully, Gary D. Miller Consulting Engineer - Corporate Licensing Nuclear Regulatory Affairs Dominion Energy, Inc. |
| | (804) 273-2771 From: Gary D Miller (Services - 6) |
| | Sent: Tuesday, September 28, 2021 3:29 PM To: Klos, John <John.Klos@nrc.gov> |
| | |
| | ==Subject:== |
| | 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.}} |
Latest revision as of 14:34, 18 January 2022
Letter Sequence Request |
---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance, Acceptance, Acceptance
- Supplement
|
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
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML24213A2602024-07-31031 July 2024 Request for Additional Information LAR to Support Implementation of Framatome Gaia Fuel ML24116A0112024-04-25025 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-13 Regarding Steam Generator Channel Head Drain Modification ML24116A2822024-04-25025 April 2024 Acceptance of Requested Licensing Action: Surry TS Change Section 3.8 Containment Temperature and Pressure Requirements and Surveillances ML24115A2622024-04-24024 April 2024 Acceptance Review Determination for Proposed Alternative Request IR-4-14 Regarding Pressurizer and Steam Generator Pressure-Retaining Welds and Full-Penetration Welded Nozzles ML24114A3192024-04-23023 April 2024 Acceptance Review Determination LAR to Extend Inspection Interval for Reactor Coolant Pump Flywheels (TSTF-421) Using the CLIIP ML24113A2502024-04-22022 April 2024 Request for Additional Information (e-mail 4/22/2024) License Renewal Commitment for Aging Management Program of Alloy 600 Components ML24107A9112024-04-15015 April 2024 NRC to Fws, Follow-up on Request for Concurrence for North Anna SLR ML24107A9122024-04-11011 April 2024 Fws to NRC, Follow-up on Request for Concurrence for North Anna SLR ML24102A0682024-04-10010 April 2024 IST (z)(2) Hardship RR V-1 RCS Cold Leg, Lh Safety Injection Check Valves ML24092A1082024-04-0101 April 2024 3R22 RFO ISI Owners Activity Report Extension - NRC Staff Acknowledgement Email (4/1/2024) ML24087A0102024-03-26026 March 2024 NRR E-mail Capture - Verbal Relief for North Anna Unit 1 - (ASME Code), Section XI, Subsection IWB-2430 ML24087A0112024-03-23023 March 2024 NRR E-mail Capture - Draft RAIs for Reactor Coolant Pump (RCP) Relief Request (L-2024-LLR-0022) ML24075A1762024-03-15015 March 2024 Email, Acceptance of Requested Licensing Action: Surry TSTF-577, Rev. 1 ML24144A2432024-03-0808 March 2024 002 Radiation Safety Baseline Inspection Information Request ML24065A3112024-03-0505 March 2024 Request for Additional Information (Redacted) (03/05/2025 E-mail from R. Guzman to S. Sinha) Framatome Gaia Fuel LOCA LAR ML24065A2532024-03-0505 March 2024 RAI Issuance Surry RR IST P-1 P-2 ML24058A2322024-02-27027 February 2024 2/27/2024 E-mail from S. Sinha to R. Guzman P-8 Instrument Uncertainty in Support of LAR Framatome Gaia Fuel ML24107B1562024-02-20020 February 2024 Cherokee Nation E.Toombs Na Removal Request ML24044A2462024-02-0606 February 2024 001 Radiation Safety Baseline Inspection Information Request ML24032A4702024-02-0101 February 2024 Change in Estimated Review Schedule Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC ML24024A0202024-01-24024 January 2024 Correction to Safety Evaluation Associated Wit Amendment No. 288 - Revision to Applicability Term for RCS Heat-Up and Cooldown Pressure-Temperature Limitations Figures ML24024A2452024-01-24024 January 2024 1/24/2024 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in SE for Amendment No. 288 - Revision to Applicability Term for RCS Heatup and Cooldown Pressure-Temperature Limitations Figures ML23320A1122024-01-18018 January 2024 NRC to Fws, Concurrence with Endangered Species Act Determinations for North Anna Power Station, Units 1 and 2, Subsequent License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML23355A2722023-12-21021 December 2023 NRR E-mail Capture - Schedule Revision for Emergency Preparedness Staff Augmentation Times License Amendment Request ML23326A0132023-11-22022 November 2023 Acceptance Review Determination LAR to Support Implementation of Framatome Gaia Fuel ML23318A0952023-11-14014 November 2023 Request for Additional Information (E-mail Dated 11/14/2023) LAR to Revise TSs Related to Framatome Gaia Fuel ML23317A0732023-11-13013 November 2023 Acceptance Review Determination - License Amendment Request Modification of TS SR 4.3.6.a ML23318A1172023-11-13013 November 2023 NRR E-mail Capture - Formal Issuance of RAIs for North Anna Technical Support Center (TSC) License Amendment Request (LAR) (L-2023-LLA-0006) ML23312A2962023-11-0808 November 2023 Email - Surry Relief Request Acceptance Review Results; Surry Unit 1 and 2 IST P-3 P-4 Pumps ML23312A2022023-11-0808 November 2023 Relief Request Acceptance Review Results; IST Impracticality P-1 P-2 RHR Containment Pumps ML23297A2312023-10-24024 October 2023 E-mail to File - Summary of September 13, 2023, Meeting with Dominion to Discuss Proposed LAR to Support Cycle Reloads Using Framatome Gaia Fuel ML23283A3262023-10-10010 October 2023 Update Acceptance Review Status Surry TS Change Apply RG 1.97, Rev 3 Instrumentation to Lhsi ML23265A2302023-09-22022 September 2023 Acceptance Review Determination - License Amendment Request Revision to TS Design Features Section to Remove the Nine Mile Point Unit 3 Nuclear Project, LLC 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 ML23255A2772023-09-12012 September 2023 Acceptance of Requested Licensing Action: Surry TS Change, Lhsi Indication and Instrumentation ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23258A0552023-08-31031 August 2023 Setup of Online Reference Portal and Audit Plan for the NRC Staff'S Review of LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies (08/31/2023 e-mail) ML23219A1602023-08-0707 August 2023 003 Radiation Safety Baseline Inspection Information Request ML23199A2832023-07-18018 July 2023 Request for Additional Information (E-mail Dated 7/18/2023) LAR to Revise the Pressure-Temperature Limits ML23193A9552023-07-12012 July 2023 NRR E-mail Capture - Acceptance Review for VC Summer and Surry Relief Request (L-2023-LLR-0029) ML23187A1122023-07-0606 July 2023 TSC Relocation LAR RAIs ML23172A0752023-06-21021 June 2023 Acceptance Review Determination LAR to Revise TSs for Reactor Core Safety Limits, Fuel Assemblies, and COLR Related to Framatome Gaia Fuel ML23171B0522023-06-20020 June 2023 NRR E-mail Capture - RAI for Review of Appendix F to DOM-NAF-2-P (Redacted) ML23145A0042023-05-25025 May 2023 Acceptance Review Determination LAR to Use Framatome Small Break and Realistic Large Break LOCA Methodologies ML23145A0052023-05-25025 May 2023 Acceptance Review Determination Exemption to Use Framatome Gaia Fuel Assemblies Containing Fuel Rods Fabricated with M5 Fuel Rod Cladding ML23115A3022023-04-24024 April 2023 4/24/2023 E-mail from R.Guzman to S.Sinha - Acknowledgement of Error in Issuance of Amendments Adoption of TSTF-359, Increase Flexibility in Mode Restraints ML23107A2212023-04-10010 April 2023 Amendment Turbine Building Wind Load Basis Reclassification License Amendment Request - State Consultation No Comment ML23089A1882023-03-29029 March 2023 Request for Additional Information (E-mail Dated 3/29/2023) Spring 2022 Steam Generator Tube Inspection Report ML23075A0232023-03-15015 March 2023 NRR E-mail Capture - RAI - License Amend Req (LAR) to Revise Tech Spec (Ts) 3.6.8 Limiting Condition for Operation to Remove Refueling Water Chemical Addition Tank and Replace the Containment Sump Buffer North Anna, 1 and 2 (L-2022-LLA-0162 ML23068A0242023-03-0808 March 2023 RAI Issuance Fuel Handling Trolley LAR 2024-07-31
[Table view] |
Text
From: gary.d.miller@dominionenergy.com To: Klos, John
Subject:
[External_Sender] Additional Element Included in the Implementation Plan for the Surry Fuel Melt Safety Limit (SL) LAR Date: Wednesday, October 13, 2021 3:17:05 PM
- John, In addition to the information provided below and as a result of the clarification call between Dominion Energy and the NRC this afternoon, this email is provided to identify an additional implementation plan item associated with the Surry Power Station Units 1 and 2 License Amendment Request to revise the TS 2.1.A.1.b safety limit for fuel melt. Specifically, UFSAR section 3.4.1.1 will be revised as part of the implementation plan for the license amendments following their issuance to include the revised fuel melt safety limit and its technical basis. Furthermore, the UFSAR will be reviewed and additional UFSAR changes will be implemented, if required, to reflect the revised fuel melt safety limit.
If you have any questions or require additional information, please do not hesitate to ask.
Respectfully, Gary D. Miller Consulting Engineer - Corporate Licensing Nuclear Regulatory Affairs Dominion Energy, Inc.
(804) 273-2771 From: Gary D Miller (Services - 6)
Sent: Tuesday, September 28, 2021 3:29 PM To: Klos, John <John.Klos@nrc.gov>
Subject:
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.