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Category:E-Mail
MONTHYEARML24309A0552024-11-0101 November 2024 NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5 ML24304A3752024-10-29029 October 2024 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) to Revise Watts Bar Updated Final Safety Analysis Report (UFSAR) for Hydrologic Analysis ML24274A2762024-09-24024 September 2024 Email from K.Green to S.Hughes, Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, Hydrologic LAR to Revise the UFSAR ML24260A0322024-09-10010 September 2024 NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5 ML24215A3152024-07-24024 July 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-276-A, Revision 2 TS 3.8.1, AC Sources 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 ML24157A3152024-06-0303 June 2024 2024 Sequoyah Commercial Grade Dedication Inspection Information Request ML24155A1372024-05-29029 May 2024 Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate ML24156A0062024-05-22022 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Recapture Low-Power Testing Time ML24130A0132024-05-0707 May 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.11 for MCR Chiller Completion Time 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) ML24082A0662024-04-17017 April 2024 Email to Stuart Rymer on Exemption Decision for Watts Bar ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24082A0682024-04-10010 April 2024 Email to Stuart Rymer Re_ Availability of EA-FONSI for Watts Bar ML24100A8392024-04-0909 April 2024 Response from State of Tn Regarding Review of Environmental Assessment for Watts Bar Exemption Request ML24100A8402024-04-0808 April 2024 Email to State of Tn Requesting Review of Environmental Assessment for Watts Bar Exemption Request ML24071A0982024-03-0707 March 2024 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate ML24058A0962024-02-26026 February 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant License Amendment Request to Revise UFSAR for Hydrologic Analysis ML24047A2792024-02-15015 February 2024 RAI Related to the Exemption Request for 10 CFR 37.11 ML24045A0312024-02-14014 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML24033A0562024-02-0101 February 2024 NRR E-mail Capture - Correction Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Adopt TSTF-427-A, Revision 2 Regarding Degraded Barriers 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 ML24022A2592024-01-22022 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Unit 1, License Amendment Request to Revise TS LCO 3.8.2 to Remove Note C-S Diesel Generator ML24016A0762024-01-16016 January 2024 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Request to Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications ML23347A0642023-12-13013 December 2023 12-13-23 Email from Kimberly Green to Wells, Russell, Subject: Results of NRC SUNSI Review of Watts Bar Nuclear Plant Dual-Unit UFSAR, Amendment 5 ML23334A0932023-11-28028 November 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Surveillance Requirement 3.9.5.1 to Reduce RHR Flow Rate During Mode 6 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) ML23254A2872023-09-11011 September 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise TS Table 1.1-1 Re Number of Required Rvh Closure Bolts 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) ML23191A8672023-07-10010 July 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23150A2472023-05-25025 May 2023 NRR E-mail Capture - Audit Plan Related to Review of the Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23116A1492023-04-21021 April 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML23075A0032023-03-13013 March 2023 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1, 2, and 3, License Amendment Request to Revise TS 3.7.11, Required Actions A.1 and E.1 Footnotes Re Date for the Modification 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) ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request 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) ML22356A2982022-12-22022 December 2022 Email Response to Letter, Dated November 22, 2022 Regarding Watts Bar Integrated Inspection Report ML22353A0812022-12-15015 December 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Alternative Request WBN-2-ISI-01 Regarding Examination of Upper Head Injection Nozzle Dissimilar Metal Piping Butt Welds 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) 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 ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22166A4292022-06-0606 June 2022 NRR E-mail Capture - LAR to Adopt TSTF-577 2024-09-24
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NRR-PMDAPEm Resource From: Quichocho, Jessie Sent: Wednesday, May 07, 2014 5:23 PM To: Lingam, Siva
Subject:
FW: FYI: Watts Bar Unit 2 - Open Items 23 & 26 Attachments: WATTS BAR UNIT 2 Action Items 23 EEEB Input.docx Fyi Jessie Quichocho, Chief Plant Licensing Branch LPL II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-0209 From: Zimmerman, Jacob Sent: Wednesday, May 07, 2014 2:45 PM To: Poole, Justin Cc: Quichocho, Jessie; Matharu, Gurcharan
Subject:
FYI: Watts Bar Unit 2 - Open Items 23 & 26 Justin Attached is the EEEB write-up closing out the Open Items 23 & 26 for Watts Bar Unit 2 licensing review.
If you have any comments or questions, please contact Singh Matharu.
- Thanks, Jake Jacob I. Zimmerman, Chief Electrical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission E-mail: Jacob.Zimmerman@nrc.gov l Office: (301) 415-1220 l NRC - One Mission - One Team 1
Hearing Identifier: NRR_PMDA Email Number: 1271 Mail Envelope Properties (2B99C8FC0E9CB14D9BAD822B6E7B17E02C5F3B4FD7)
Subject:
FW: FYI: Watts Bar Unit 2 - Open Items 23 & 26 Sent Date: 5/7/2014 5:23:17 PM Received Date: 5/7/2014 5:23:18 PM From: Quichocho, Jessie Created By: Jessie.Quichocho@nrc.gov Recipients:
"Lingam, Siva" <Siva.Lingam@nrc.gov>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 908 5/7/2014 5:23:18 PM WATTS BAR UNIT 2 Action Items 23 EEEB Input.docx 25005 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
WATTS BAR UNIT 2 ACTION ITEMS EEEB ITEM #23 Issue: Resolve whether or not TVAs reasoning for not upgrading the MSIV solenoid valves to Category I is a sound reason to the contrary, as specified in 10 CFR 50.49(i). (SSER 22, Section 3.11.2.2.1, pages 3-15)
Detailed
Description:
Main Steam Isolation Valves (MSIVs)
TVA stated that the original WBN Unit 2 MSIVs are qualified to NUREG-0588, Category II. TVA is refurbishing the MSIVs by replacing the missing subcomponents, including the solenoid valves, terminal blocks, and manufacturing wiring, with components of the same make, model, and type as supplied on the original purchase order. With the exception of the solenoid valves, the subcomponents will be qualified to NUREG-0588, Category I requirements. According to TVA, the solenoid valves cannot be upgraded because equivalent subcomponents qualified to NUREG-0588, Category I, requirements are not available. The NRC staff does not consider TVA's justification for not upgrading the MSIV solenoid valves to Category I, as specified in 10 CFR 50.49(1), to be a sound reason. Resolution of this issue is Open Item 23 (Appendix HH).
Resolution: By letter dated April 6, 2011, (ADAMS # ML110980637) TVA response to Request for Additional Information (RAI) stated that the MSIV solenoids would be upgraded to Cat I.
Based on this response, the staff considers this item to be resolved.
EEEB ITEM #26 Issue: For the scenario with an accident in one unit and concurrent shutdown of the second unit without offsite power, TVA stated that Unit 2 pre-operational testing will validate the diesel response to sequencing of loads on the Unit 2 emergency diesel generators (EDGs). The NRC staff will evaluate the status of this issue and will update the status of the EDG load response in a future SSER. (SSER 22, Section 8.1)
Detailed
Description:
By letter dated November 18, 2011, Watts Bar Nuclear Plant, Unit 2 -
Request for Additional Information Regarding Supplemental Safety Evaluation Report, the staff requested additional details on Open item 26. TVA updated its response by letter dated June 7, 2012 (ADAMS # ML12163A048). The questions were related to Emergency Diesel Generator (EDG) rating and loading criteria. Specifically the staff requested TVA to:
a) Explain the variations in the worst-case loading provided in different responses and provide a summary of current calculations depicting DG loading, including procedurally required loads that may be manually connected b) Provide verification or test documents from manufacturer or Appendix B qualified supplier of DG engine and DG generator certifying the 'hot, cold and step load' capabilities.
Resolution: In response to staff questions, TVA stated that the ongoing plant modifications and validation of calculation accuracies through the inspection process had resulted in adjustments to the EDG loading calculations. TVA attached excerpts from calculation #
EDQ00099920080014, Rev. 16 summarizing the results from the last update.
The licensee has evaluated the load carrying capability (steady-state running load) and margin available for the worst case EDG loading for two separate events. As stated in the Final Safety
Analysis Report (FSAR), load carrying capability is based on a 2-hour rating of 4840 kilowatt (kW) from 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and on a continuous rating of 4400 kW from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to the end. Table 1, provided in Attachment 1 to Calculation No. EDQ00099920080014, Rev. 16 depicts worst case EDG loading with available margin when serving loads during a loss of offsite power (LOOP) concurrent with a loss of coolant accident (LOCA). This table indicates that EDG 2B-B has the highest loading of 4,237.20 kilowatt (kW) which is less than the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rating of 4840 kW. The maximum steady state running load (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to end) is calculated to be 4093.66 kW for EDG 1A-A compared to nominal rating of 4400 kW. The other EDGs have lower loading for this event. to the Calculation provides details on each EDG loading with one unit in LOOP plus LOCA and the second unit in LOOP only. For the case of Unit 1 in LOOP/LOCA event and Unit 2 in a LOOP only condition, the licensee has concluded that EDG 1A-A has the maximum loading of 4220.51 kW for the first two hours and 4093.66 kW for the remaining duration. These loading are below the corresponding nominal and 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ratings of the EDGs. The other EDGs have lower loading for this event.
For the case of Unit 2 in LOOP/LOCA event and Unit 1 in a LOOP only condition, the licensee has concluded that EDG 2B-B has the maximum loading of 4237.2 kW for the first two hours and EDG 2A-A has 3975.57 kW for steady state operation beyond 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> . These loading are below the corresponding nominal and 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ratings of the EDGs. The other EDGs have lower loading for this event.
The licensee has also performed a sensitivity analyses for transient loading of the EDGs during motor starts. Based on the details provided in the referenced calculation, the staff finds that the EDGs at WBN units 1 and 2 are adequately rated to support safe shutdown of both units following an accident in one unit coupled with a LOOP at both units.
The licensee has indicated that the hot cold and step load capabilities of the EDGs were reviewed and concurred by MKW Power Systems, Inc., the Appendix B qualified supplier of EDG engine and generator for WBN. The licensee has used the higher rating(s) for motor starting analyses. The staff did not consider the additional spare margin available with these ratings as the nameplate ratings envelope the postulated steady state loadings.
Based on the responses provided by the licensee, staff considers open item #26 to be resolved.
Prepared BY: G. S. Matharu Reviewed By: Roy Mathew