|
|
(11 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML15105A525 | | | number = ML15105A525 |
| | issue date = 04/15/2015 | | | issue date = 04/15/2015 |
| | title = 2015/04/15 NRR E-mail Capture - Final Rai'S MF2549 WBN, U1 Csst License Amendment Request | | | title = NRR E-mail Capture - Final Rai'S MF2549 WBN, U1 Csst License Amendment Request |
| | author name = Minarik A J | | | author name = Minarik A |
| | author affiliation = NRC/NRR/DORL/LPWB | | | author affiliation = NRC/NRR/DORL/LPWB |
| | addressee name = Arent G | | | addressee name = Arent G |
Line 14: |
Line 14: |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MF2549 | | | project = TAC:MF2549 |
| | | stage = Other |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Minarik, AnthonySent:Wednesday, April 15, 2015 3:17 PMTo:Arent, Gordon (garent@tva.gov)Cc:Bryan, Robert H Jr (rhbryan@tva.gov); Matharu, Gurcharan; Zimmerman, Jacob; Quichocho, JessieSubject:Final RAI's MF2549 WBN, U1 CSST License Amendment RequestAttachments:REQUEST FOR ADDITIONAL INFORMATION CSST MF2549 (4-15-2015).docxMr. Arent By letter dated August 1, 2013, the Tennessee Valley Authority (TVA) submitted an application for license amendment to revise the Technical Specifications for Watts Bar Nuclear Plant (WBN) Unit 1. These changes to the WBN Unit 1 Technical Specifications, would revise the Limiting Conditions for Operation related to alternating current sources while operating. You supplemented this request as recently as January 29, 2015. | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Minarik, Anthony Sent: Wednesday, April 15, 2015 3:17 PM To: Arent, Gordon (garent@tva.gov) |
| | Cc: Bryan, Robert H Jr (rhbryan@tva.gov); Matharu, Gurcharan; Zimmerman, Jacob; Quichocho, Jessie |
| | |
| | ==Subject:== |
| | Final RAI's MF2549 WBN, U1 CSST License Amendment Request Attachments: REQUEST FOR ADDITIONAL INFORMATION CSST MF2549 (4-15-2015).docx Mr. Arent By letter dated August 1, 2013, the Tennessee Valley Authority (TVA) submitted an application for license amendment to revise the Technical Specifications for Watts Bar Nuclear Plant (WBN) Unit 1. These changes to the WBN Unit 1 Technical Specifications, would revise the Limiting Conditions for Operation related to alternating current sources while operating. You supplemented this request as recently as January 29, 2015. |
| 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 attached to this e-mail. The proposed questions were provided to your staff on March 31, 2015, and TVA has agreed to provide a response to this information by April 30, 2015. | | 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 attached to this e-mail. The proposed questions were provided to your staff on March 31, 2015, and TVA has agreed to provide a response to this information by April 30, 2015. |
| Thank you for your time and attention in this matter, | | Thank you for your time and attention in this matter, Anthony Minarik 301-415-6185 Office of Nuclear Reactor Regulation (NRR) |
| | |
| Anthony Minarik 301-415-6185 Office of Nuclear Reactor Regulation (NRR) | |
| Division of Operating Reactor Licensing (DORL) | | Division of Operating Reactor Licensing (DORL) |
| Watts Bar Special Projects Branch (LPWB) | | Watts Bar Special Projects Branch (LPWB) |
| Normal Hours: 0600-1545: Mon-Fri | | Normal Hours: |
| | 0600-1545: Mon-Fri 1 |
|
| |
|
| Hearing Identifier: NRR_PMDA Email Number: 2001 Mail Envelope Properties (Anthony.Minarik@nrc.gov20150415151700) | | Hearing Identifier: NRR_PMDA Email Number: 2001 Mail Envelope Properties (Anthony.Minarik@nrc.gov20150415151700) |
|
| |
|
| ==Subject:== | | ==Subject:== |
| Final RAI's MF2549 WBN, U1 CSST License Amendment Request Sent Date: 4/15/2015 3:17:03 PM Received Date: 4/15/2015 3:17:00 PM From: Minarik, Anthony Created By: Anthony.Minarik@nrc.gov Recipients: "Bryan, Robert H Jr (rhbryan@tva.gov)" <rhbryan@tva.gov> Tracking Status: None "Matharu, Gurcharan" <Gurcharan.Matharu@nrc.gov> | | Final RAI's MF2549 WBN, U1 CSST License Amendment Request Sent Date: 4/15/2015 3:17:03 PM Received Date: 4/15/2015 3:17:00 PM From: Minarik, Anthony Created By: Anthony.Minarik@nrc.gov Recipients: |
| Tracking Status: None "Zimmerman, Jacob" <Jacob.Zimmerman@nrc.gov> Tracking Status: None "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov> Tracking Status: None "Arent, Gordon (garent@tva.gov)" <garent@tva.gov> | | "Bryan, Robert H Jr (rhbryan@tva.gov)" <rhbryan@tva.gov> |
| Tracking Status: None Post Office: Files Size Date & Time MESSAGE 1146 4/15/2015 3:17:00 PM REQUEST FOR ADDITIONAL INFORMATION CSST MF2549 (4-15-2015).docx 29608 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | Tracking Status: None "Matharu, Gurcharan" <Gurcharan.Matharu@nrc.gov> |
| ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION REGARDING OFFSITE POWER AVAILABILITY REQUIREMENTS WATTS BAR NUCLEAR PLANT UNIT 1 TAC NO. MF2549 The following questions were developed as a result of the staff's review of the licensee's revised license amendment request (LAR) submitted by letter dated January 29, 2015. The revised LAR proposes to change Technical Specification (TS) Surveillance Requirement (SR) 3.8.1.8 and modify the current licensing basis as described in the Updated Final Safety Analysis Report (UFSAR). This wouldallow thelicensee to use Common Station Service Transformers (CSSTs) A and B as offsite power source for an indefinite time in lieu of CSST C or D. 1. The current licensing basis of the plant has the offsite power sources with the capability to power each of the Shutdown Boards 1A-A and 1B-B from CSSTs C and D. For compliance with General Design Criterion 17, each shutdown board has an immediately available normal source, CSST C for 1 A-A and CSST D for 1 B-B and an automatic transfer to the alternate source CSST D for 1A-A and CSST C for 1 B-B. CSSTs A or B, when used as offsite power circuits for extended duration, do not have similar flexibility or capability.
| | Tracking Status: None "Zimmerman, Jacob" <Jacob.Zimmerman@nrc.gov> |
| 10CFR 50.36 requires Limiting conditions for operation (LCO) to be specified whenremedial actionsare permitted by the TS to restore the plant to full compliance. In view of the reduction in defense in depth from the current TS (i.e., when CSST A or B is used as a GDC 17 power source), please provide details on proposed duration (LCO) when using the maintenance feeds through CSSTs A or B in lieu of CSSTs C or D.
| | Tracking Status: None "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov> |
| : 2. In case of a loss of offsite power (LOOP) event, the onsite power sources are required to connect to the safety busses. In order to recover from a LOOP or a station blackout (SBO) event, the offsite power sources have to be restored to the safety busses. The current TS surveillances validate the capability to parallel the onsite and offsite sources for successful transfer between the two sources through CSSTs C and D. To demonstrate operability of a power source, the licensee has to perform periodic surveillances in their required power source alignment to comply with the requirements of 10 CFR 50.36. The current TS proposal to use CSST A or B as GDC 17 sources does not appear to have TS surveillances to validate a similar capability. Please provide information on surveillances that will be performed to demonstrate the operability of the circuits between the switchyard and the safety busses through CSST A or B. 3. Please confirm that the components in the circuits associated with CSSTs A and B, 161kV switchyard and the safety busses will be subjected to the requirements of the Maintenance Rule as applicable under 10CFR50.65 "Requirements for monitoring the effectiveness of maintenance at nuclear power plants." 4. Assuming that CSST A or B is being used as an offsite power source for the safety buses with both WBN units operating at full power, the sequence of events following an accident signal in one unit could be reactor trip, turbine trip and a delayed generator trip depending on the coast down time of the generator. The safety buses will have accident loads block loaded while the generator in coast down. After the generator trip, the safety busses will be
| | Tracking Status: None "Arent, Gordon (garent@tva.gov)" <garent@tva.gov> |
| - 2 - transferred to the CSST A or depending on the selected source. Please provide the following information: i. A summary of analyses performed to demonstrate the consequences of this sequence of events on the accident analyses. ii. Details or referenced information in the licensing basis documenting the adequacy of this design as related to accident analyses. iii. Summary of electrical system analyses performed with the grid at minimum allowablevoltage and simultaneous restart or reacceleration of all safety related and non-safety related loads,assuming a design basis accident in one unit and simultaneous orderly shutdown of the other unit. 5. Since the operation of non-safety related circuit breakers related with offsite power sources is critical for separation and restoration of power from the switchyard, plant designs incorporate redundant trip coils and closing coils powered from reliable DC sources. Please confirm if the circuit breakers associated with CSSTs A and B and offsite power source have similar design features.
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 1146 4/15/2015 3:17:00 PM REQUEST FOR ADDITIONAL INFORMATION CSST MF2549 (4-15-2015).docx 29608 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
|
| |
|
| }} | | REQUEST FOR ADDITIONAL INFORMATION REGARDING OFFSITE POWER AVAILABILITY REQUIREMENTS WATTS BAR NUCLEAR PLANT UNIT 1 TAC NO. MF2549 The following questions were developed as a result of the staffs review of the licensees revised license amendment request (LAR) submitted by letter dated January 29, 2015. The revised LAR proposes to change Technical Specification (TS) Surveillance Requirement (SR) 3.8.1.8 and modify the current licensing basis as described in the Updated Final Safety Analysis Report (UFSAR). This wouldallow thelicensee to use Common Station Service Transformers (CSSTs) |
| | A and B as offsite power source for an indefinite time in lieu of CSST C or D. |
| | : 1. The current licensing basis of the plant has the offsite power sources with the capability to power each of the Shutdown Boards 1A-A and 1B-B from CSSTs C and D. For compliance with General Design Criterion 17, each shutdown board has an immediately available normal source, CSST C for 1 A-A and CSST D for 1 B-B and an automatic transfer to the alternate source CSST D for 1A-A and CSST C for 1 B-B. CSSTs A or B, when used as offsite power circuits for extended duration, do not have similar flexibility or capability. |
| | 10CFR 50.36 requires Limiting conditions for operation (LCO) to be specified whenremedial actionsare permitted by the TS to restore the plant to full compliance. In view of the reduction in defense in depth from the current TS (i.e., when CSST A or B is used as a GDC 17 power source), please provide details on proposed duration (LCO) when using the maintenance feeds through CSSTs A or B in lieu of CSSTs C or D. |
| | : 2. In case of a loss of offsite power (LOOP) event, the onsite power sources are required to connect to the safety busses. In order to recover from a LOOP or a station blackout (SBO) event, the offsite power sources have to be restored to the safety busses. The current TS surveillances validate the capability to parallel the onsite and offsite sources for successful transfer between the two sources through CSSTs C and D. To demonstrate operability of a power source, the licensee has to perform periodic surveillances in their required power source alignment to comply with the requirements of 10 CFR 50.36. The current TS proposal to use CSST A or B as GDC 17 sources does not appear to have TS surveillances to validate a similar capability. Please provide information on surveillances that will be performed to demonstrate the operability of the circuits between the switchyard and the safety busses through CSST A or B. |
| | : 3. Please confirm that the components in the circuits associated with CSSTs A and B, 161kV switchyard and the safety busses will be subjected to the requirements of the Maintenance Rule as applicable under 10CFR50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power plants. |
| | : 4. Assuming that CSST A or B is being used as an offsite power source for the safety buses with both WBN units operating at full power, the sequence of events following an accident signal in one unit could be reactor trip, turbine trip and a delayed generator trip depending on the coast down time of the generator. The safety buses will have accident loads block loaded while the generator in coast down. After the generator trip, the safety busses will be ENCLOSURE |
| | |
| | transferred to the CSST A or depending on the selected source. Please provide the following information: |
| | : i. A summary of analyses performed to demonstrate the consequences of this sequence of events on the accident analyses. |
| | ii. Details or referenced information in the licensing basis documenting the adequacy of this design as related to accident analyses. |
| | iii. Summary of electrical system analyses performed with the grid at minimum allowablevoltage and simultaneous restart or reacceleration of all safety related and non-safety related loads,assuming a design basis accident in one unit and simultaneous orderly shutdown of the other unit. |
| | : 5. Since the operation of non-safety related circuit breakers related with offsite power sources is critical for separation and restoration of power from the switchyard, plant designs incorporate redundant trip coils and closing coils powered from reliable DC sources. Please confirm if the circuit breakers associated with CSSTs A and B and offsite power source have similar design features.}} |
Letter Sequence Other |
---|
|
|
MONTHYEARML13220A1032013-08-0101 August 2013 Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02) Project stage: Request ML13260A2022013-09-17017 September 2013 Accepted for Review of Application to Modify Watts Bar Nuclear Plant Unit 1 Tech Spec Regarding AC Sources Project stage: Approval ML14056A5252014-02-26026 February 2014 E-mail, Request for Additional Information Regarding Application to Modify Technical Specifications Related to AC Sources-Operating Project stage: RAI CNL-14-015, Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02)2014-04-21021 April 2014 Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02) Project stage: Response to RAI ML14132A2432014-06-16016 June 2014 Summary of 4/24/214, Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2, Request for Additional Information Related to License Amendment to Modify AC Power Source Technical Specifications Project stage: RAI CNL-14-107, Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02)2015-01-29029 January 2015 Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02) Project stage: Response to RAI ML15090A6112015-03-31031 March 2015 NRR E-mail Capture - Watts Bar Unit 1 Draft RAIs for Csst License Amendment Request, TAC MF2549 Project stage: Draft RAI ML15105A5252015-04-15015 April 2015 NRR E-mail Capture - Final Rai'S MF2549 WBN, U1 Csst License Amendment Request Project stage: Other CNL-15-078, Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02)2015-06-12012 June 2015 Response to NRC Request for Additional Information Related to Application to Modify Technical Specifications Regarding AC Sources - Operating (TS-WBN-13-02) Project stage: Response to RAI ML15232A1162015-08-24024 August 2015 FRN Re. Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing Project stage: Other ML15232A1132015-08-24024 August 2015 LTR Re. Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing (TAC No. 2549) Project stage: Other ML15225A0942015-09-29029 September 2015 Issuance of Amendment Regarding Alternating Current Sources Project stage: Approval CNL-19-110, Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10)2019-12-17017 December 2019 Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10) Project stage: Request 2015-01-29
[Table View] |
|
---|
Category:E-Mail
MONTHYEARML24022A2592024-01-22022 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 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) 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 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) 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 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 ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) ML22083A2372022-03-24024 March 2022 NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8 ML22081A2222022-03-22022 March 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 1, License Amendment Request to Revise Allowable Value for TS Table 3.3.2-1, Function 6.e(1) ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML22131A1902022-02-23023 February 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Unit 2, Request to Revise the Reactor Vessel Surveillance Capsule Withdrawal Schedule ML22046A0392022-02-15015 February 2022 NRR E-mail Capture - Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report 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 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22011A0382022-01-10010 January 2022 NRR E-mail Capture - Acceptance Review Results for Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-205-A, Rev. 3 and TSTF-563-A ML21306A2452021-11-0202 November 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21252A0912021-09-0909 September 2021 NRR E-mail Capture - Request for Comments on Proposed Issuance of Amendments to Watts Bar Nuclear Plant, Unit 2 - Revise Steam Generator Secondary Side Water Level ML21223A2592021-08-11011 August 2021 Affidavit - Prop Slides - Partially Closed Meeting with TVA Potential Watts Bar, Unit 2 Tube Locking LAR ML21221A2602021-08-0909 August 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary ML21215A1152021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21215A1142021-07-26026 July 2021 NRR E-mail Capture - (External_Sender) Correction to WBN Chiller Replacement LAR ML21197A0452021-07-15015 July 2021 WBN U1 Isi/Sgisi Request for Information (RFI) Letter ML21193A2422021-07-12012 July 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 2 Technical Specifications Related to Steam Generator Inspection/Repair Program Provisions ML21189A0202021-06-29029 June 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specifications 3.3.6 and 3.3.7 Re Radiation Monitor Redundant Unit of Measure 2024-01-22
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23166A1142023-06-15015 June 2023 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03 ML23067A2372023-03-0808 March 2023 WB_2023-02_RP_inspection_doc_request ML23030A3512023-01-25025 January 2023 Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information 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) 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 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 ML22115A1402022-04-25025 April 2022 NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017) ML22083A2372022-03-24024 March 2022 NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8 ML22056A3802022-02-25025 February 2022 Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02 ML21267A1392021-09-23023 September 2021 Document Request for Upcoming RP Inspection at Watts Bar ML21221A2602021-08-0909 August 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary ML21102A1312021-04-19019 April 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 ML21095A0422021-04-0202 April 2021 NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR ML21095A0402021-04-0202 April 2021 NRR E-mail Capture - Request for Additional Information Re Generic Letter 95-05 90-Day Report and LAR to Adjust Growth Rate for Thot (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21095A0412021-04-0101 April 2021 NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21095A0442021-04-0101 April 2021 NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026) ML21091A0772021-04-0101 April 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21095A0462021-03-22022 March 2021 NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Generic Letter 95-05 90-Day Report for Watts Bar Unit 2 ML21039A6402021-02-0808 February 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 1 Technical Specifications Related to Steam Generator Tube Inspection Frequency ML21012A2032021-01-11011 January 2021 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar UFSAR to Use Alternate Probability of Detection ML20350B5592020-12-15015 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Adopt Traveler TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML20338A3202020-12-0303 December 2020 Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information ML20322A4412020-11-17017 November 2020 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement ML20322A4392020-11-0505 November 2020 NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement ML20308A3512020-11-0202 November 2020 Request for Additional Information on WBN Request for Exemption from 10 CFR Part 73, Appendix B, Section VI for the Conduct of an Annual Force-on-Force Exercise (EPID L-2020-LLE-0165 (COVID-19)) ML20253A1782020-09-0909 September 2020 Emergency Preparedness Program Inspection Request for Information ML20266G4592020-08-14014 August 2020 Notification of Inspection and Request for Information ML20196L8622020-07-14014 July 2020 NRR E-mail Capture - Watts Bar Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Implement the Full Spectrum LOCA Methodology ML20086G4802020-03-26026 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) - Part 2 ML20085G3572020-03-25025 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML20084M1942020-03-24024 March 2020 NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML20083J3952020-03-12012 March 2020 NRR E-mail Capture - Draft Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) ML19340A6842019-12-0505 December 2019 NRR E-mail Capture - Request for Additional Information for WBN2 Request for One-Time Extension of Completion Time for TS 3.7.8 (L-2019-LLA-0020) ML19218A0302019-08-0505 August 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2 ML19218A0282019-07-25025 July 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Draft Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2 ML19186A4352019-07-0505 July 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Correction to Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69 ML19169A3592019-06-18018 June 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69 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 ML19106A0462019-04-15015 April 2019 NRR E-mail Capture - Watts BAR, Units 1 and 2 Request for Additional Informatin (RAI) Regarding Changes to Technical Specifications Sections 3.8.1, 3.8.7, 3.8.8, and 3.8.9 ML19071A3542019-03-0808 March 2019 NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request to Adopt TSTF-425 to Relocate Specific Surveillance Frequency Requirements to Licensee-Controlled Program ML18313A2202018-11-0707 November 2018 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML18282A6372018-10-0909 October 2018 NRR E-mail Capture - RAIs (Final) - LAR to Revise the Steam Generator Technical Specifications for Watts Bar Nuclear Plant, Unit 2 ML18270A2362018-09-26026 September 2018 NRR E-mail Capture - Watts Bar Units 1 and 2 RAIs - Modify TS 3.8.9 Completion Time for Inoperable 120V AC Vital Buses (L-2018-LLA-0050) ML18240A0702018-08-27027 August 2018 NRR E-mail Capture - RAI for Watts Bar Unit 2 Tpbars LAR and Watts Bar Units 1 and 2 LAR Related to Fuel Storage ML18199A1822018-07-17017 July 2018 NRR E-mail Capture - Request for Additional Information Regarding Watts Bar Unit 1 Extension of Surveillance Requirement Intervals ML18123A3942018-05-0303 May 2018 NRR E-mail Capture - Request for Additional Information Unit 2 Cycle 1 Steam Generator Tube Inspection Report 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) ML18031A6592018-02-0606 February 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1 and Technical Specifications Related to Fuel Storage ML18016A0112018-01-12012 January 2018 Draft Request for Additional Information Exigent Amendment Request for Inoperable Reactor Coolant Temperature Indication ML17226A0032017-08-11011 August 2017 NRR E-mail Capture - Watts Bar, Unit 1 - Final Request for Additional Information Concerning Request to Amend Turbine Trip Low Fluid Oil Pressure Reactor Protection System Trip Setpoint 2023-06-15
[Table view] |
Text
NRR-PMDAPEm Resource From: Minarik, Anthony Sent: Wednesday, April 15, 2015 3:17 PM To: Arent, Gordon (garent@tva.gov)
Cc: Bryan, Robert H Jr (rhbryan@tva.gov); Matharu, Gurcharan; Zimmerman, Jacob; Quichocho, Jessie
Subject:
Final RAI's MF2549 WBN, U1 CSST License Amendment Request Attachments: REQUEST FOR ADDITIONAL INFORMATION CSST MF2549 (4-15-2015).docx Mr. Arent By letter dated August 1, 2013, the Tennessee Valley Authority (TVA) submitted an application for license amendment to revise the Technical Specifications for Watts Bar Nuclear Plant (WBN) Unit 1. These changes to the WBN Unit 1 Technical Specifications, would revise the Limiting Conditions for Operation related to alternating current sources while operating. You supplemented this request as recently as January 29, 2015.
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 attached to this e-mail. The proposed questions were provided to your staff on March 31, 2015, and TVA has agreed to provide a response to this information by April 30, 2015.
Thank you for your time and attention in this matter, Anthony Minarik 301-415-6185 Office of Nuclear Reactor Regulation (NRR)
Division of Operating Reactor Licensing (DORL)
Watts Bar Special Projects Branch (LPWB)
Normal Hours:
0600-1545: Mon-Fri 1
Hearing Identifier: NRR_PMDA Email Number: 2001 Mail Envelope Properties (Anthony.Minarik@nrc.gov20150415151700)
Subject:
Final RAI's MF2549 WBN, U1 CSST License Amendment Request Sent Date: 4/15/2015 3:17:03 PM Received Date: 4/15/2015 3:17:00 PM From: Minarik, Anthony Created By: Anthony.Minarik@nrc.gov Recipients:
"Bryan, Robert H Jr (rhbryan@tva.gov)" <rhbryan@tva.gov>
Tracking Status: None "Matharu, Gurcharan" <Gurcharan.Matharu@nrc.gov>
Tracking Status: None "Zimmerman, Jacob" <Jacob.Zimmerman@nrc.gov>
Tracking Status: None "Quichocho, Jessie" <Jessie.Quichocho@nrc.gov>
Tracking Status: None "Arent, Gordon (garent@tva.gov)" <garent@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1146 4/15/2015 3:17:00 PM REQUEST FOR ADDITIONAL INFORMATION CSST MF2549 (4-15-2015).docx 29608 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION REGARDING OFFSITE POWER AVAILABILITY REQUIREMENTS WATTS BAR NUCLEAR PLANT UNIT 1 TAC NO. MF2549 The following questions were developed as a result of the staffs review of the licensees revised license amendment request (LAR) submitted by letter dated January 29, 2015. The revised LAR proposes to change Technical Specification (TS) Surveillance Requirement (SR) 3.8.1.8 and modify the current licensing basis as described in the Updated Final Safety Analysis Report (UFSAR). This wouldallow thelicensee to use Common Station Service Transformers (CSSTs)
A and B as offsite power source for an indefinite time in lieu of CSST C or D.
- 1. The current licensing basis of the plant has the offsite power sources with the capability to power each of the Shutdown Boards 1A-A and 1B-B from CSSTs C and D. For compliance with General Design Criterion 17, each shutdown board has an immediately available normal source, CSST C for 1 A-A and CSST D for 1 B-B and an automatic transfer to the alternate source CSST D for 1A-A and CSST C for 1 B-B. CSSTs A or B, when used as offsite power circuits for extended duration, do not have similar flexibility or capability.
10CFR 50.36 requires Limiting conditions for operation (LCO) to be specified whenremedial actionsare permitted by the TS to restore the plant to full compliance. In view of the reduction in defense in depth from the current TS (i.e., when CSST A or B is used as a GDC 17 power source), please provide details on proposed duration (LCO) when using the maintenance feeds through CSSTs A or B in lieu of CSSTs C or D.
- 2. In case of a loss of offsite power (LOOP) event, the onsite power sources are required to connect to the safety busses. In order to recover from a LOOP or a station blackout (SBO) event, the offsite power sources have to be restored to the safety busses. The current TS surveillances validate the capability to parallel the onsite and offsite sources for successful transfer between the two sources through CSSTs C and D. To demonstrate operability of a power source, the licensee has to perform periodic surveillances in their required power source alignment to comply with the requirements of 10 CFR 50.36. The current TS proposal to use CSST A or B as GDC 17 sources does not appear to have TS surveillances to validate a similar capability. Please provide information on surveillances that will be performed to demonstrate the operability of the circuits between the switchyard and the safety busses through CSST A or B.
- 3. Please confirm that the components in the circuits associated with CSSTs A and B, 161kV switchyard and the safety busses will be subjected to the requirements of the Maintenance Rule as applicable under 10CFR50.65 Requirements for monitoring the effectiveness of maintenance at nuclear power plants.
- 4. Assuming that CSST A or B is being used as an offsite power source for the safety buses with both WBN units operating at full power, the sequence of events following an accident signal in one unit could be reactor trip, turbine trip and a delayed generator trip depending on the coast down time of the generator. The safety buses will have accident loads block loaded while the generator in coast down. After the generator trip, the safety busses will be ENCLOSURE
transferred to the CSST A or depending on the selected source. Please provide the following information:
- i. A summary of analyses performed to demonstrate the consequences of this sequence of events on the accident analyses.
ii. Details or referenced information in the licensing basis documenting the adequacy of this design as related to accident analyses.
iii. Summary of electrical system analyses performed with the grid at minimum allowablevoltage and simultaneous restart or reacceleration of all safety related and non-safety related loads,assuming a design basis accident in one unit and simultaneous orderly shutdown of the other unit.
- 5. Since the operation of non-safety related circuit breakers related with offsite power sources is critical for separation and restoration of power from the switchyard, plant designs incorporate redundant trip coils and closing coils powered from reliable DC sources. Please confirm if the circuit breakers associated with CSSTs A and B and offsite power source have similar design features.