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| | number = ML17112A040 | | | number = ML17112A040 |
| | issue date = 04/20/2017 | | | issue date = 04/20/2017 |
| | title = Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING | | | title = 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 |
| | author name = Hon A | | | author name = Hon A |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Hon, Andrew Sent: Thursday, April 20, 2017 7:33 AM To: Hess, Thomas A (tahess@tva.gov) | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Hon, Andrew Sent: Thursday, April 20, 2017 7:33 AM To: Hess, Thomas A (tahess@tva.gov) |
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| ==Subject:== | | ==Subject:== |
| SEQUOYAH NUCLEAR STATION, UNIT 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LAR FOR TECHNI CAL SPECIFICATION 3.8.1, "AC SOURCES-OPERATING,"By letter dated May 26, 2016 (Agencywide Document s Access and Management System (ADAMS) Accession No. ML16148A175), Tennessee Valley Authority (TVA, the licensee) requested a revision to the Operating Licenses for the Sequoyah Nuclear Plant (SQN), Units 1 and 2. The proposed change would correct a non-conservatism in technical specification 3.8.1, "AC Sources-Operating," acceptance criterion for the diesel generator (DG) steady-state frequency range in Surveillance Requirements 3.8.1.2, 3.8.1.7, 3.8.1.9, 3.8.1.11, 3.8.1.12, 3.8.1.15, and 3.8.1.18. | | SEQUOYAH NUCLEAR STATION, UNIT 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LAR FOR TECHNICAL SPECIFICATION 3.8.1, AC SOURCES-OPERATING, By letter dated May 26, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16148A175), Tennessee Valley Authority (TVA, the licensee) requested a revision to the Operating Licenses for the Sequoyah Nuclear Plant (SQN), Units 1 and 2. The proposed change would correct a non-conservatism in technical specification 3.8.1, AC Sources-Operating, acceptance criterion for the diesel generator (DG) steady-state frequency range in Surveillance Requirements 3.8.1.2, 3.8.1.7, 3.8.1.9, 3.8.1.11, 3.8.1.12, 3.8.1.15, and 3.8.1.18. |
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| 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 April 19, 2017. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response by May 12, 2017 to this request for additional information (RAI). | | 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 April 19, 2017. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response by May 12, 2017 to this request for additional information (RAI). |
| 2The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effectiv e 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.
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| Docket Nos. 50-327 and 50-328 RAI-1 On page E8 of 20 of the LAR, the licensee provided an equation to calculate motor speed change as a function of torque. With this equation, the licensee cited a reference to topical report (TR) WCAP-17308, "Treatment of Diesel Generator Technical Specification Frequ ency and Voltage Tolerances." WCAP-17308 is still under NRC staff review and is not an approved TR. Unapproved guidance may be used as the basis for a proposed change, however, the licensee must supply all information necessary (i.e., plant-specific justification and technical basis) to support the change.
| | The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs 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. |
| | Docket Nos. 50-327 and 50-328 |
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| Please clarify the licensee's reliance on the unapproved TR referenced in the LAR for the equation discussed above, and any other portions of the LAR. Additionally, provide the relevant technical basis, as necessary. | | ===RAI-1=== |
| RAI-2 On page E12 of 20 of the LAR, the licensee stated that the DG load would increase by 4% as result of the DG operating at upper end of voltage (7260 V) and frequency (60.2 Hz, proposed change) steady-state ranges. The nominal DG loading values were not provided. Also, it appears that the 4% increase was calculated in consideration for the motor loads only.
| | On page E8 of 20 of the LAR, the licensee provided an equation to calculate motor speed change as a function of torque. With this equation, the licensee cited a reference to topical report (TR) WCAP-17308, Treatment of Diesel Generator Technical Specification Frequency and Voltage Tolerances. WCAP-17308 is still under NRC staff review and is not an approved TR. Unapproved guidance may be used as the basis for a proposed change, however, the licensee must supply all information necessary (i.e., plant-specific justification and technical basis) to support the change. |
| | Please clarify the licensees reliance on the unapproved TR referenced in the LAR for the equation discussed above, and any other portions of the LAR. Additionally, provide the relevant technical basis, as necessary. |
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| Please provide the following details on DG loading: a) The change in KW and KVA loading of the DG, showing consideration for the effects on both motor loads and non-motor loads (e.g. heaters) to the total DG load values, b) Maximum postulated loading (KW and KVA) of the DG, if the major pumps are potentially operating at run-out conditions at the onset of an event, c) At nominal voltage and frequency: the maximum postulated, worst-case loading (KW and KVA) for steady-state operation, d) At the upper range voltage and frequency: the maximum postulated, worst-case loading (KW and KVA) for steady-state operation, and e) The DG loading compared to the DG rating (minimum margin) for the loading conditions in b), c), and d) above. | | ===RAI-2=== |
| | On page E12 of 20 of the LAR, the licensee stated that the DG load would increase by 4% as result of the DG operating at upper end of voltage (7260 V) and frequency (60.2 Hz, proposed change) steady-state ranges. |
| | The nominal DG loading values were not provided. Also, it appears that the 4% increase was calculated in consideration for the motor loads only. |
| | Please provide the following details on DG loading: |
| | a) The change in KW and KVA loading of the DG, showing consideration for the effects on both motor loads and non-motor loads (e.g. heaters) to the total DG load values, b) Maximum postulated loading (KW and KVA) of the DG, if the major pumps are potentially operating at run-out conditions at the onset of an event, c) At nominal voltage and frequency: the maximum postulated, worst-case loading (KW and KVA) for steady-state operation, d) At the upper range voltage and frequency: the maximum postulated, worst-case loading (KW and KVA) for steady-state operation, and e) The DG loading compared to the DG rating (minimum margin) for the loading conditions in b), c), and d) above. |
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| Hearing Identifier: NRR_PMDA Email Number: 3455 Mail Envelope Properties (Andrew.Hon@nrc.gov20170420073300) | | Hearing Identifier: NRR_PMDA Email Number: 3455 Mail Envelope Properties (Andrew.Hon@nrc.gov20170420073300) |
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| ==Subject:== | | ==Subject:== |
| SEQUOYAH NUCLEAR STATION, UNIT 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LAR FOR TECHNICAL SPECIFICATION 3.8.1, "AC SOURCES-OPERATING," | | SEQUOYAH NUCLEAR STATION, UNIT 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LAR FOR TECHNICAL SPECIFICATION 3.8.1, AC SOURCES-OPERATING, Sent Date: 4/20/2017 7:33:00 AM Received Date: 4/20/2017 7:33:00 AM From: Hon, Andrew Created By: Andrew.Hon@nrc.gov Recipients: |
| Sent Date: 4/20/2017 7:33:00 AM Received Date: 4/20/2017 7:33:00 AM From: Hon, Andrew Created By: Andrew.Hon@nrc.gov | | "Hess, Thomas A (tahess@tva.gov)" <tahess@tva.gov> |
| | | Tracking Status: None Post Office: |
| Recipients: "Hess, Thomas A (tahess@tva.gov)" <tahess@tva.gov> Tracking Status: None Post Office: Files Size Date & Time MESSAGE 3655 4/20/2017 7:33:00 AM | | Files Size Date & Time MESSAGE 3655 4/20/2017 7:33:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | | Recipients Received:}} |
| Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:}} | |
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Category:E-Mail
MONTHYEARML24177A1412024-06-11011 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) ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 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) ML23058A1312023-02-27027 February 2023 FW: TVA Intentions on EA-22-129 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 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 ML23026A0282023-01-12012 January 2023 001 Radiation Safety Baseline Inspection Information Request 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) 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) 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 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - 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 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 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 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 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 ML22095A0182022-04-0404 April 2022 NRR E-mail Capture - Sequoyah Nuclear Plant - Acceptance of Request for Alternative - Pressure Isolation Valve Leakage ISTC-3630 (L-2022-LLR-0034) ML22125A1422022-03-22022 March 2022 1 and 2 - March 22, 2022 e-mail - Sequoyah TSTF-505 LAR Supplemental Information ML22075A0942022-03-16016 March 2022 NRR E-mail Capture - Acceptance Review for Sequoyah Units 1 and 2 - LAR to Use of Fire and Seismic PRAs to Modify Approved 10 CFR 50.69 Categorization Process ML22046A2742022-02-15015 February 2022 NRR E-mail Capture - Audit Question (Snsb 02) for Sequoyah Units 1 and 2 LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) ML22047A0552022-02-15015 February 2022 Annual Water Withdrawal Report 2021 ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22035A0182022-02-0303 February 2022 NRR E-mail Capture - Audit Questions (Eeb follow-up) for Sequoyah Units 1 and 2 LAR to Adopt TSTF-505, Revision 2 (L-2021-LLA-0145) 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) ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 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 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 ML14318A8052014-11-12012 November 2014 Requalification Program Inspection - Sequoyah Nuclear Plant 2024-05-31
[Table view] |
Text
NRR-PMDAPEm Resource From: Hon, Andrew Sent: Thursday, April 20, 2017 7:33 AM To: Hess, Thomas A (tahess@tva.gov)
Subject:
SEQUOYAH NUCLEAR STATION, UNIT 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LAR FOR TECHNICAL SPECIFICATION 3.8.1, AC SOURCES-OPERATING, By letter dated May 26, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16148A175), Tennessee Valley Authority (TVA, the licensee) requested a revision to the Operating Licenses for the Sequoyah Nuclear Plant (SQN), Units 1 and 2. The proposed change would correct a non-conservatism in technical specification 3.8.1, AC Sources-Operating, acceptance criterion for the diesel generator (DG) steady-state frequency range in Surveillance Requirements 3.8.1.2, 3.8.1.7, 3.8.1.9, 3.8.1.11, 3.8.1.12, 3.8.1.15, and 3.8.1.18.
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 April 19, 2017. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response by May 12, 2017 to this request for additional information (RAI).
1
The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs 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.
Docket Nos. 50-327 and 50-328
RAI-1
On page E8 of 20 of the LAR, the licensee provided an equation to calculate motor speed change as a function of torque. With this equation, the licensee cited a reference to topical report (TR) WCAP-17308, Treatment of Diesel Generator Technical Specification Frequency and Voltage Tolerances. WCAP-17308 is still under NRC staff review and is not an approved TR. Unapproved guidance may be used as the basis for a proposed change, however, the licensee must supply all information necessary (i.e., plant-specific justification and technical basis) to support the change.
Please clarify the licensees reliance on the unapproved TR referenced in the LAR for the equation discussed above, and any other portions of the LAR. Additionally, provide the relevant technical basis, as necessary.
RAI-2
On page E12 of 20 of the LAR, the licensee stated that the DG load would increase by 4% as result of the DG operating at upper end of voltage (7260 V) and frequency (60.2 Hz, proposed change) steady-state ranges.
The nominal DG loading values were not provided. Also, it appears that the 4% increase was calculated in consideration for the motor loads only.
Please provide the following details on DG loading:
a) The change in KW and KVA loading of the DG, showing consideration for the effects on both motor loads and non-motor loads (e.g. heaters) to the total DG load values, b) Maximum postulated loading (KW and KVA) of the DG, if the major pumps are potentially operating at run-out conditions at the onset of an event, c) At nominal voltage and frequency: the maximum postulated, worst-case loading (KW and KVA) for steady-state operation, d) At the upper range voltage and frequency: the maximum postulated, worst-case loading (KW and KVA) for steady-state operation, and e) The DG loading compared to the DG rating (minimum margin) for the loading conditions in b), c), and d) above.
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Hearing Identifier: NRR_PMDA Email Number: 3455 Mail Envelope Properties (Andrew.Hon@nrc.gov20170420073300)
Subject:
SEQUOYAH NUCLEAR STATION, UNIT 1 & 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LAR FOR TECHNICAL SPECIFICATION 3.8.1, AC SOURCES-OPERATING, Sent Date: 4/20/2017 7:33:00 AM Received Date: 4/20/2017 7:33:00 AM From: Hon, Andrew Created By: Andrew.Hon@nrc.gov Recipients:
"Hess, Thomas A (tahess@tva.gov)" <tahess@tva.gov>
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