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| =Text= | | =Text= |
| {{#Wiki_filter:From: Sent: To: Cc: | | {{#Wiki_filter:From: Hon, Andrew Sent: Thursday, February 19, 2015 11:21 AM To: Shea, Joseph W Owshea@tva.gov) |
| | Cc: Sallman, Ahsan; Helton, Shana; Hess, Thomas A (tahess@tva.gov) |
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| ==Subject:== | | ==Subject:== |
| ADAMSAccessionNumber:
| | SEQUOYAH NUCLEAR STATION, UNIT 1- REQUEST FOR ADDITIONAL INFORMATION RELATED TOLAR to Ice Condendser Inc Mass Tech Spec. |
| Mr. Joseph W. Shea Hon, Andrew Thursday, February 19, 2015 11:21 AM Shea, Joseph W Owshea@tva.gov)
| | ADAMSAccessionNumber: ML15050A096 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 6A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801 |
| Sallman, Ahsan; Helton, Shana; Hess, Thomas A (tahess@tva.gov)
| |
| SEQUOYAH NUCLEAR STATION, UNIT 1-REQUEST FOR ADDITIONAL INFORMATION RELATED TOLAR to Ice Condendser Inc Mass Tech Spec. ML15050A096 Vice President, Nuclear Licensing Tennessee Valley Authority 6A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2,-REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION ON ICE CONDENSER ICE MASS (TAC NOS. MF2446 AND MF2447) | | SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2,- REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION ON ICE CONDENSER ICE MASS (TAC NOS. MF2446 AND MF2447) |
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| ==Dear Mr. Shea:== | | ==Dear Mr. Shea:== |
| In a letter dated July 3, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML13199A281) (Reference 1), Tennessee Valley Authority (TVA or the licensee) requested an amendment to Operating Licenses (OLs) DPR-77 and DPR-79 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively, in the form of changes to the Technical Specifications (TSs). TVA supplemented Reference 1 by letter dated February 13, 2014 (Reference 2). The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed below. The proposed questions were discussed by telephone with your staff on February 18, 2015. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response by March 31, 2015 to this request for additional information (RAI). 1 The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | |
| Please note that if you do not respond to this request by the agreed-upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If circumstances result in the need to revise the agreed upon response date, please contact me at (301) 415-8480 or via e-mail Andrew.Hon@nrc.gov. | | In a letter dated July 3, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML13199A281) (Reference 1), Tennessee Valley Authority (TVA or the licensee) requested an amendment to Operating Licenses (OLs) DPR-77 and DPR-79 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively, in the form of changes to the Technical Specifications (TSs). TVA supplemented Reference 1 by letter dated February 13, 2014 (Reference 2). |
| Docket Nos. 50-327 and 50-328 Accession No. ML15050A096 Sincerely, RIA Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 2
| | The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed below. The proposed questions were discussed by telephone with your staff on February 18, 2015. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response by March 31, 2015 to this request for additional information (RAI). |
| SCVB-RAl-9 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO CHANGE TO TECHNICAL SPECIFICATION TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (WBN), UNIT 1 AND UNIT 2 DOCKET NOS. 50-327 AND 50-328 In UFSAR Section 6.2.1.3.4, under heading "Containment Pressure Calculation", the ice temperature used in the containment pressure calculation as per assumption (10) is 15°F. On the other hand, Surveillance Requirement (SR) 4.6.5.1a states: "At least once per 12 hours by verifying that the maximum ice bed temperature is less than or equal to 27°F." The ice bed temperature is a key parameter for the ice condenser performance for pressure suppression, i.e., assuming a lower ice bed temperature for the long term pressure response is less conservative than using a higher temperature.
| | 1 |
| For a conservative containment pressure calculation, please justify using a conservative assumption of ice temperature of 15°F instead of 27°F. SCVB-RAl-10 In UFSAR Section 6.2.1.3.4, under heading "Containment Pressure Calculation", the input assumption (10) for containment pressure calculation states the initial containment air temperature of 100°F in the lower volume and dead-ended volumes, and 85°F in the upper volume. On the other hand, TS 3.6.1.5 states that the maximum values of 105°F in the upper volume and 125°F in the lower volume shall be maintained. | | |
| By sensitivity analyses, please justify these temperatures in the UFSAR would maximize the peak containment transient pressure compared to the transient pressure obtained by using the initial TS maximum values. REFERENCES | | The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Please note that if you do not respond to this request by the agreed-upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If circumstances result in the need to revise the agreed upon response date, please contact me at (301) 415-8480 or via e-mail Andrew.Hon@nrc.gov. |
| : 1. Letter from TVA to NRC dated July 3, 2013, "Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)", (ADAMS Accession Number ML13199A281) | | Sincerely, RIA Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 Accession No. ML15050A096 2 |
| : 2. Letter from TV A to NRC dated February 13, 2014, "Response to NRC Request for Additional Information Regarding Sequoyah Nuclear Plant (SQN), Units 1 and 2 -Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)(TAC Nos. MF2446 and MF2447)", (ADAMS Accession Number ML14045A290) 3}} | | |
| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO CHANGE TO TECHNICAL SPECIFICATION TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (WBN), UNIT 1 AND UNIT 2 DOCKET NOS. 50-327 AND 50-328 SCVB-RAl-9 In UFSAR Section 6.2.1.3.4, under heading "Containment Pressure Calculation", the ice temperature used in the containment pressure calculation as per assumption (10) is 15°F. On the other hand, Surveillance Requirement (SR) 4.6.5.1a states: |
| | "At least once per 12 hours by verifying that the maximum ice bed temperature is less than or equal to 27°F." |
| | The ice bed temperature is a key parameter for the ice condenser performance for pressure suppression, i.e., |
| | assuming a lower ice bed temperature for the long term pressure response is less conservative than using a higher temperature. For a conservative containment pressure calculation, please justify using a non-conservative assumption of ice temperature of 15°F instead of 27°F. |
| | SCVB-RAl-10 In UFSAR Section 6.2.1.3.4, under heading "Containment Pressure Calculation", the input assumption (10) for containment pressure calculation states the initial containment air temperature of 100°F in the lower volume and dead-ended volumes, and 85°F in the upper volume. On the other hand, TS 3.6.1.5 states that the maximum values of 105°F in the upper volume and 125°F in the lower volume shall be maintained. |
| | By sensitivity analyses, please justify these temperatures in the UFSAR would maximize the peak containment transient pressure compared to the transient pressure obtained by using the initial TS maximum values. |
| | REFERENCES |
| | : 1. Letter from TVA to NRC dated July 3, 2013, "Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)", (ADAMS Accession Number ML13199A281) |
| | : 2. Letter from TVA to NRC dated February 13, 2014, "Response to NRC Request for Additional Information Regarding Sequoyah Nuclear Plant (SQN), Units 1 and 2 -Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)(TAC Nos. MF2446 and MF2447)", (ADAMS Accession Number ML14045A290) 3}} |
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Category:E-Mail
MONTHYEARML24281A0072024-10-0202 October 2024 NRR E-mail Capture - Acceptance Review Results for the Sequoyah License Amendment Request to Modify the FHA Analysis, Tech Spec TS 3.9.4 and Tech Spec 3.3.6 (L-2024-LLA-0117) ML24177A1412024-06-11011 June 2024 NRR E-mail Capture - Audit Plan Related to Review of the Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, LAR to Revise Technical Specification Table 3.3.2-1 Function 5 ML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24128A1802024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review for Sequoyah License Amendment Request to Modify TS 3.8.1 and TS 3.8.2 (L-2024-LLA-0047) ML24123A0882024-05-0202 May 2024 NRR E-mail Capture - Correction Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24122B4872024-04-30030 April 2024 NRR E-mail Capture - Acceptance Review Results for the Browns Ferry, Sequoyah, and Watts Bar License Amendment Request to Revise TS 5.4.1 or 5.7.1 (L-2024-LLA-0039) ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24074A4252024-03-14014 March 2024 NRR E-mail Capture - Sequoyah Hydrologic Analysis License Amendment Request - Notification of Change to Estimated Completion and Hours ML24059A4052024-02-28028 February 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-02 ML24053A0302024-02-21021 February 2024 NRR E-mail Capture - Request for Steam Generator (SG) Tube Inspection Call for Sequoyah, Unit 1 ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML24036A0132024-01-23023 January 2024 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar Nuclear Plants, License Amendment Request to Revise TS Table 3.3.2-1, Function 5, Turbine Trip and Feedwater Isolation ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23236A2562023-08-24024 August 2023 NRR E-mail Capture - Acceptance Review Results for the Sequoyah and Watts Bar License Amendment Request to Adopt TSTF-567 (L-2023-LLA-0106) ML23165A2862023-06-14014 June 2023 Tennessee Multi-Sector Permit (Tmsp), 2023 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, SW-17, SW-18, SW-19, and SW-21 ML23072A0722023-03-10010 March 2023 NRR E-mail Capture - (External_Sender) State Consultation - Sequoyah Nuclear Plant, Units 1 and 2; and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML23058A1312023-02-27027 February 2023 FW: TVA Intentions on EA-22-129 ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23046A3552023-02-15015 February 2023 Annual Water Withdrawal Report 2022 ML23019A3442023-01-19019 January 2023 Tennessee Multi-Sector Permit (Tmsp), 2022 Annual Discharge Monitoring Report for Outfalls SW-1, SW-16, and SW-19 ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22348A0432022-11-28028 November 2022 NRR E-mail Capture - State Consultation - Sequoyah Nuclear Plant, Units 1 and 2, License Amendment Request to Modify the Approved 10 CFR 50.69 Categorization Process (L-2022-LLA-0033) ML22227A0712022-08-15015 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 (EPID L-2022-LLA-0103) - Corrected ML22227A0262022-08-12012 August 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah and Watts Bar License Amendment Request to Revise TS 3.4.12 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22196A0732022-07-15015 July 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - TSTF-505 RICT (L-2021-LLA-0145) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A0332022-06-17017 June 2022 NRR E-mail Capture - (External_Sender) State Notification for Sequoyah Units 1 and 2 Amendment Issuance - Reactor Trip System Instrumentation (L-2021-LLA-0200) ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22137A2692022-05-17017 May 2022 Notice of Termination, TNR192066, Gravel Lot Restoration Project ML22136A0182022-05-16016 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, Alternative Request RP-11 and Watts Bar Nuclear Plant, Units 1 and 2, Alternative Request IST-RR-9 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22132A1762022-05-12012 May 2022 Tennessee Multi-Sector Permit (Tmsp), 2021 Annual Discharge Monitoring Report for Outfalls SW-2, SW-3, SW-4, SW-6, SW-8, SW-9, and SW-13 ML22123A1812022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-577 2024-06-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283B0592018-10-10010 October 2018 NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18233A1942018-08-21021 August 2018 NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML17112A0402017-04-20020 April 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING ML17004A0612017-01-0404 January 2017 Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007) ML15194A3882015-07-13013 July 2015 Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec ML15175A2912015-06-24024 June 2015 E-mail Re. Request for Additional Information RR RP-07 ML15159B1642015-06-22022 June 2015 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482) ML15050A0962015-02-19019 February 2015 E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec ML15042A4702015-02-11011 February 2015 E-mail Re. Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink 2024-05-31
[Table view] |
Text
From: Hon, Andrew Sent: Thursday, February 19, 2015 11:21 AM To: Shea, Joseph W Owshea@tva.gov)
Cc: Sallman, Ahsan; Helton, Shana; Hess, Thomas A (tahess@tva.gov)
Subject:
SEQUOYAH NUCLEAR STATION, UNIT 1- REQUEST FOR ADDITIONAL INFORMATION RELATED TOLAR to Ice Condendser Inc Mass Tech Spec.
ADAMSAccessionNumber: ML15050A096 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 6A Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2,- REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION ON ICE CONDENSER ICE MASS (TAC NOS. MF2446 AND MF2447)
Dear Mr. Shea:
In a letter dated July 3, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML13199A281) (Reference 1), Tennessee Valley Authority (TVA or the licensee) requested an amendment to Operating Licenses (OLs) DPR-77 and DPR-79 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2, respectively, in the form of changes to the Technical Specifications (TSs). TVA supplemented Reference 1 by letter dated February 13, 2014 (Reference 2).
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed below. The proposed questions were discussed by telephone with your staff on February 18, 2015. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response by March 31, 2015 to this request for additional information (RAI).
1
The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. Please note that if you do not respond to this request by the agreed-upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If circumstances result in the need to revise the agreed upon response date, please contact me at (301) 415-8480 or via e-mail Andrew.Hon@nrc.gov.
Sincerely, RIA Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 Accession No. ML15050A096 2
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO CHANGE TO TECHNICAL SPECIFICATION TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (WBN), UNIT 1 AND UNIT 2 DOCKET NOS. 50-327 AND 50-328 SCVB-RAl-9 In UFSAR Section 6.2.1.3.4, under heading "Containment Pressure Calculation", the ice temperature used in the containment pressure calculation as per assumption (10) is 15°F. On the other hand, Surveillance Requirement (SR) 4.6.5.1a states:
"At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the maximum ice bed temperature is less than or equal to 27°F."
The ice bed temperature is a key parameter for the ice condenser performance for pressure suppression, i.e.,
assuming a lower ice bed temperature for the long term pressure response is less conservative than using a higher temperature. For a conservative containment pressure calculation, please justify using a non-conservative assumption of ice temperature of 15°F instead of 27°F.
SCVB-RAl-10 In UFSAR Section 6.2.1.3.4, under heading "Containment Pressure Calculation", the input assumption (10) for containment pressure calculation states the initial containment air temperature of 100°F in the lower volume and dead-ended volumes, and 85°F in the upper volume. On the other hand, TS 3.6.1.5 states that the maximum values of 105°F in the upper volume and 125°F in the lower volume shall be maintained.
By sensitivity analyses, please justify these temperatures in the UFSAR would maximize the peak containment transient pressure compared to the transient pressure obtained by using the initial TS maximum values.
REFERENCES
- 1. Letter from TVA to NRC dated July 3, 2013, "Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)", (ADAMS Accession Number ML13199A281)
- 2. Letter from TVA to NRC dated February 13, 2014, "Response to NRC Request for Additional Information Regarding Sequoyah Nuclear Plant (SQN), Units 1 and 2 -Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)(TAC Nos. MF2446 and MF2447)", (ADAMS Accession Number ML14045A290) 3