|
|
| (10 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML16041A022 | | | number = ML16041A022 |
| | issue date = 02/25/2016 | | | issue date = 02/25/2016 |
| | title = Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) | | | title = Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate |
| | author name = Saba F E | | | author name = Saba F |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
| | addressee name = Shea J W | | | addressee name = Shea J |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000259, 05000260, 05000296 | | | docket = 05000259, 05000260, 05000296 |
| | license number = DPR-033, DPR-052, DPR-068 | | | license number = DPR-033, DPR-052, DPR-068 |
| | contact person = Saba F E, NRR/DORL/LPLII-2 | | | contact person = Saba F, NRR/DORL/LPLII-2 |
| | case reference number = CAC MF6741, CAC MF6742, CAC MF6743 | | | case reference number = CAC MF6741, CAC MF6742, CAC MF6743 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 7 | | | page count = 7 |
| | project = CAC:MF6741, CAC:MF6742, CAC:MF6743 | | | project = CAC:MF6741, CAC:MF6742, CAC:MF6743 |
| | stage = | | | stage = RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 February 25, 2016 SUBJECT: BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF6741, MF6742, AND MF6743) Dear Mr. Shea: By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15282A 152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML 15317 A361, ML 15351A 113, and ML 15355A413, respectively), Tennessee Valley Authority (TVA or the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatts thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On February 2, 2016, the NRC staff forwarded, by electronic mail, a draft of the staff's request for additional information (RAI) to TVA. On February 9, 2015, TVA informed the NRC staff that no clarification call is needed. The official questions are found in the enclosed RAI. This request was discussed with Mr. Daniel Green of your staff, and it was agreed that TVA would respond by March 25, 2016. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 25, 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 |
| J. Shea -2 -If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov. Docket Nos. 50-259, 50-260, and 50-296 Enclosure: Request for Additional Information cc w/enclosure: Distribution via Listserv Sincerely, --Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15282A 152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML 15317 A361, ML 15351A 113, and ML 15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt. The U.S. Nuclear Regulatory Commission (NRC) staff from the Office of Nuclear Reactor Regulation (NRR), Division of Risk Assessment, Fire Protection Branch (AFPB), reviewed the LAR and its supplements. The NRC staff determined that the following information is needed to complete their review. AFPB-Reguest for Additional Information (RAil 1 The NRC staff notes that LAR Attachment 6 to the Safety Analysis Report (SAR) for BFN, Units 1, 2, and 3, Extended Power Uprate (EPU), NEDC-33860P, 1 Revision 0, September 2015, Section 2.5.1.4, "Fire Protection," states that, "The transition to NFPA 805 is currently under NRC staff review, and TVA anticipates its approval prior to implementation [of] EPU operation. Accordingly, the fire protection analysis described in this section is based on the NFPA 805 implementation ... " On October 10, 2015, the NRC issued a license amendment for BFN, Units 1, 2, and 3, to incorporate National Fire Protection Association (NFPA) 805 fire protection licensing basis in accordance with Title 10 of Code of Federal Regulations (10 CFR), Section 50.48(c). The amendment approved the transition of the licensee's fire protection program to a risk-informed, performance-based program based on the 2001 Edition of NFPA 805. The staff requests that the licensee provide a supplement to LAR Attachment 6 to the SAR for BFN Units 1, 2, and 3, 1 This document is marked "Proprietary" (non-publicly available information) in TVA letter dated September 21, 2015. All contents of this document should be handled in accordance with the NRC guidance of handling Sensitive Unclassified Non-Safeguards Information (SUNSI). Enclosure | | |
| -2 -EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4, "Fire Protection," consistent with the approved NFPA 805 licensing basis. AFPB-RAI 2 Attachment 1 to Matrix 5, "Supplemental Fire Protection Review Criteria, Plant Systems," of NRR RS-001, Revision 0, "Review Standard for Extended Power Uprates" (ADAMS Accession No. ML033640024) states: Power uprates typically result in increases in decay heat generation following plant trips. These increases in decay heat usually do not affect the elements of a fire protection program related to ( 1) administrative controls, (2) fire suppression and detection systems, (3) fire barriers, (4) fire protection responsibilities of plant personnel, and (5) procedures and resources necessary for the repair of systems required to achieve and maintain cold shutdown. In addition, an increase in decay heat will usually not result in an increase in the potential for a radiological release resulting from a fire. However, the licensee's application should confirm that these elements are not impacted by the extended power uprate. The NRC staff notes that LAR Attachment 6 to SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program," specifically addresses items (1) through (4) above. The staff requests that the licensee provide statements to address item (5) and a statement confirming no increase in the potential for a radiological release resulting from a fire. AFPB-RAI 3 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program,'' states: The higher decay heat associated with EPU results in higher heat input into the suppression pool which, without mitigation, will result in higher suppression pool temperatures. The higher decay heat may also result in lower vessel water levels or higher Peak Cladding Temperatures (PCTs), depending on the plant-specific analysis basis. As a result of these effects, fire suppression and detection systems, operator response time, peak clad temperature (PCT), and suppression pool temperature need to be addressed. The staff requests the licensee verify that additional heat in the plant environment from the EPU will not: a. Impact any required operator manual actions (referred to as recovery actions per NFPA 805 licensing basis) being performed at their designated time (including, e.g., verifying that under EPU conditions, recovery actions and repairs required to demonstrate the availability of a success path to achieve the nuclear safety
| | ==SUBJECT:== |
| -3 -performance criteria are feasible and have been evaluated for the additional risk due to their use), or b. Require any new recovery actions due to additional heat in the plant environment to maintain the plant in safe and stable conditions. AFPB-RAI 4 The staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program," states that, " ... Other EPU modifications will be assessed and assured not to adversely affect the ability to achieve and maintain the fuel in a safe and stable condition in the event of a fire ... " Further, Section 2.11.1.2.2, "Fire Safe Shutdown (FSS) Events," states: Attachment 47 of the EPU LAR provides a listing and discussion of the modifications planned for EPU. The effect of these modifications on the Browns Ferry Fire Protection Program will be evaluated, in accordance with TVA's configuration change process, prior to EPU implementation. Per the process, these modifications will be evaluated to assure the changes do not affect the approved Fire Protection Program and will not adversely affect the ability to achieve and maintain safe shutdown in accordance with the current Browns Ferry license conditions and procedures ... The NRC staff notes that modifications associated with the EPU have not yet been completed to address the impact on the fire protection program. The staff requests that the licensee discuss how the results of plant modifications would impact the fire protection program and the plant's compliance with the fire protection program licensing basis (10 CFR 50.48(c)). AFPB-RAI 5 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program," states: Original NFP 805 analyses were performed at EPU conditions and therefore operator action times cannot be compared to CL TP [current licensed thermal power] conditions. To ensure that PCT remains less than the acceptance criterion in the most limiting scenario, one LPCI pump must be manually aligned for injection within 20 minutes ... The staff requests the licensee provide a technical justification for the 20-minute time for the operator to perform the actions to align LPCI pump injection. Include discussion of the original time margin without CL TP conditions (i.e., what was assumed for the NFPA 805 analyses) and why the 20-minute assumption is deemed adequate.
| | BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF6741, MF6742, AND MF6743) |
| -4 -AFPB-RAI 6 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.2, "Fire Event," states: The results of Case 4, and the evaluations in Section 2.6.5.2, FUSAR [Fuel Uprate Safety Analysis Report] Section 2.5.1.4, and LAR Attachment 39, demonstrate that the peak fuel cladding temperature, vessel water level, and suppression pool temperature meet the acceptance criteria and the time available for the operators to perform the necessary actions is sufficient. Therefore, EPU has no adverse effect on the ability of the systems and personnel to mitigate the effects of a fire event and satisfies the requirement of achieving and maintaining the fuel in a safe and stable condition in the event of a fire. The staff requests the licensee confirm that the above analysis cases at EPU conditions meet the NFPA 805 licensing basis to achieve and maintain the fuel in a safe and stable condition in the event of a fire. AFPB-RAI 7 Some plants credit aspects of their fire protection system for other than fire protection activities (e.g., utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems). If BFN, Units 1, 2, and 3, credits its fire protection system in this way, identify the specific situations and discuss to what extent, if any, the EPU affects these "non-fire-protection" aspects of the plant fire protection system.
| | |
| J. Shea -2 -If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov. Sincerely, IRA/ Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 Enclosure: Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-2 R/F RidsNrrDorllpl2-2 BFNEPU Resource ADAMS A ccess1on N o.: Nlqbal, NRR RidsNrrLABClayton RidsACRS_MailCTR RidsNrrDorlDpr ML 16041A022 OFFICE N RR/DORL/LPLI 1-2/PM N RR/DORL/LPLI 1-2/LA NAME FSaba BClavton (LRonewicz for) DATE 2/18/2016 2/18/2016 OFFICE NRR/DORL/LPLI 1-2/BC NRR/DORL/LPLI 1-2/PM NAME BBeasley FSaba DATE 2/24/2016 2/25/2016 OFFICIAL RECORD COPY RidsRgn2MailCenter RidsNrrPMBrownsFerry RidsNrrDraAfpb *b 1y memo NRR/DRA/AFPB/BC* AKlein 2/2/2016 | | ==Dear Mr. Shea:== |
| }} | | |
| | By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA or the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatts thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On February 2, 2016, the NRC staff forwarded, by electronic mail, a draft of the staff's request for additional information (RAI) to TVA. On February 9, 2015, TVA informed the NRC staff that no clarification call is needed. The official questions are found in the enclosed RAI. This request was discussed with Mr. Daniel Green of your staff, and it was agreed that TVA would respond by March 25, 2016. |
| | |
| | J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov. |
| | Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/enclosure: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt. |
| | The U.S. Nuclear Regulatory Commission (NRC) staff from the Office of Nuclear Reactor Regulation (NRR), Division of Risk Assessment, Fire Protection Branch (AFPB), reviewed the LAR and its supplements. The NRC staff determined that the following information is needed to complete their review. |
| | AFPB-Reguest for Additional Information (RAil 1 The NRC staff notes that LAR Attachment 6 to the Safety Analysis Report (SAR) for BFN, Units 1, 2, and 3, Extended Power Uprate (EPU), NEDC-33860P, 1 Revision 0, September 2015, Section 2.5.1.4, "Fire Protection," states that, "The transition to NFPA 805 is currently under NRC staff review, and TVA anticipates its approval prior to implementation [of] EPU operation. |
| | Accordingly, the fire protection analysis described in this section is based on the NFPA 805 implementation ... " |
| | On October 10, 2015, the NRC issued a license amendment for BFN, Units 1, 2, and 3, to incorporate National Fire Protection Association (NFPA) 805 fire protection licensing basis in accordance with Title 10 of Code of Federal Regulations (10 CFR), Section 50.48(c). The amendment approved the transition of the licensee's fire protection program to a risk-informed, performance-based program based on the 2001 Edition of NFPA 805. The staff requests that the licensee provide a supplement to LAR Attachment 6 to the SAR for BFN Units 1, 2, and 3, 1 |
| | This document is marked "Proprietary" (non-publicly available information) in TVA letter dated September 21, 2015. |
| | All contents of this document should be handled in accordance with the NRC guidance of handling Sensitive Unclassified Non-Safeguards Information (SUNSI). |
| | Enclosure |
| | |
| | EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4, "Fire Protection," consistent with the approved NFPA 805 licensing basis. |
| | AFPB-RAI 2 to Matrix 5, "Supplemental Fire Protection Review Criteria, Plant Systems," of NRR RS-001, Revision 0, "Review Standard for Extended Power Uprates" (ADAMS Accession No. ML033640024) states: |
| | Power uprates typically result in increases in decay heat generation following plant trips. These increases in decay heat usually do not affect the elements of a fire protection program related to ( 1) administrative controls, (2) fire suppression and detection systems, (3) fire barriers, (4) fire protection responsibilities of plant personnel, and (5) procedures and resources necessary for the repair of systems required to achieve and maintain cold shutdown. In addition, an increase in decay heat will usually not result in an increase in the potential for a radiological release resulting from a fire. However, the licensee's application should confirm that these elements are not impacted by the extended power uprate. |
| | The NRC staff notes that LAR Attachment 6 to SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program," |
| | specifically addresses items (1) through (4) above. The staff requests that the licensee provide statements to address item (5) and a statement confirming no increase in the potential for a radiological release resulting from a fire. |
| | AFPB-RAI 3 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program,'' |
| | states: |
| | The higher decay heat associated with EPU results in higher heat input into the suppression pool which, without mitigation, will result in higher suppression pool temperatures. The higher decay heat may also result in lower vessel water levels or higher Peak Cladding Temperatures (PCTs), depending on the plant-specific analysis basis. As a result of these effects, fire suppression and detection systems, operator response time, peak clad temperature (PCT), and suppression pool temperature need to be addressed. |
| | The staff requests the licensee verify that additional heat in the plant environment from the EPU will not: |
| | : a. Impact any required operator manual actions (referred to as recovery actions per NFPA 805 licensing basis) being performed at their designated time (including, e.g., verifying that under EPU conditions, recovery actions and repairs required to demonstrate the availability of a success path to achieve the nuclear safety |
| | |
| | performance criteria are feasible and have been evaluated for the additional risk due to their use), or |
| | : b. Require any new recovery actions due to additional heat in the plant environment to maintain the plant in safe and stable conditions. |
| | AFPB-RAI 4 The staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program," |
| | states that, " ... Other EPU modifications will be assessed and assured not to adversely affect the ability to achieve and maintain the fuel in a safe and stable condition in the event of a fire ... " |
| | Further, Section 2.11.1.2.2, "Fire Safe Shutdown (FSS) Events," states: |
| | Attachment 47 of the EPU LAR provides a listing and discussion of the modifications planned for EPU. The effect of these modifications on the Browns Ferry Fire Protection Program will be evaluated, in accordance with TVA's configuration change process, prior to EPU implementation. Per the process, these modifications will be evaluated to assure the changes do not affect the approved Fire Protection Program and will not adversely affect the ability to achieve and maintain safe shutdown in accordance with the current Browns Ferry license conditions and procedures ... |
| | The NRC staff notes that modifications associated with the EPU have not yet been completed to address the impact on the fire protection program. The staff requests that the licensee discuss how the results of plant modifications would impact the fire protection program and the plant's compliance with the fire protection program licensing basis (10 CFR 50.48(c)). |
| | AFPB-RAI 5 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program," |
| | states: |
| | Original NFP 805 analyses were performed at EPU conditions and therefore operator action times cannot be compared to CLTP [current licensed thermal power] conditions. To ensure that PCT remains less than the acceptance criterion in the most limiting scenario, one LPCI pump must be manually aligned for injection within 20 minutes ... |
| | The staff requests the licensee provide a technical justification for the 20-minute time for the operator to perform the actions to align LPCI pump injection. Include discussion of the original time margin without CLTP conditions (i.e., what was assumed for the NFPA 805 analyses) and why the 20-minute assumption is deemed adequate. |
| | |
| | AFPB-RAI 6 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.2, "Fire Event," states: |
| | The results of Case 4, and the evaluations in Section 2.6.5.2, FUSAR [Fuel Uprate Safety Analysis Report] Section 2.5.1.4, and LAR Attachment 39, demonstrate that the peak fuel cladding temperature, vessel water level, and suppression pool temperature meet the acceptance criteria and the time available for the operators to perform the necessary actions is sufficient. |
| | Therefore, EPU has no adverse effect on the ability of the systems and personnel to mitigate the effects of a fire event and satisfies the requirement of achieving and maintaining the fuel in a safe and stable condition in the event of a fire. |
| | The staff requests the licensee confirm that the above analysis cases at EPU conditions meet the NFPA 805 licensing basis to achieve and maintain the fuel in a safe and stable condition in the event of a fire. |
| | AFPB-RAI 7 Some plants credit aspects of their fire protection system for other than fire protection activities (e.g., utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems). If BFN, Units 1, 2, and 3, credits its fire protection system in this way, identify the specific situations and discuss to what extent, if any, the EPU affects these "non-fire-protection" aspects of the plant fire protection system. |
| | |
| | J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov. |
| | Sincerely, IRA/ |
| | Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION: |
| | PUBLIC Nlqbal, NRR RidsRgn2MailCenter LPL2-2 R/F RidsNrrLABClayton RidsNrrPMBrownsFerry RidsNrrDorllpl2-2 RidsACRS_MailCTR RidsNrrDraAfpb BFNEPU Resource RidsNrrDorlDpr ADAMS A ccess1on N o.: ML16041A022 *b1y memo OFFICE N RR/DORL/LPLI 1-2/PM N RR/DORL/LPLI 1-2/LA NRR/DRA/AFPB/BC* |
| | NAME FSaba BClavton (LRonewicz for) AKlein DATE 2/18/2016 2/18/2016 2/2/2016 OFFICE NRR/DORL/LPLI 1-2/BC NRR/DORL/LPLI 1-2/PM NAME BBeasley FSaba DATE 2/24/2016 2/25/2016 OFFICIAL RECORD COPY}} |
Letter Sequence RAI |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting
Results
Other: CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate, CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report, CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports, CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report, ML16085A301, ML16105A441, ML16168A026, ML16176A316
|
MONTHYEARML15282A2352015-09-21021 September 2015
RHR Heat Exchange K-values Utilities in EPU Containment Analyses
Project stage: Request
ML15282A1812015-09-21021 September 2015
Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7
Project stage: Request
ML15282A1522015-09-21021 September 2015
Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate
Project stage: Request
CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information
Project stage: Supplement
CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7
Project stage: Supplement
CNL-15-261, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information2015-12-18018 December 2015
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information
Project stage: Supplement
ML16032A0442016-02-0101 February 2016
FWS to NRC, Updated List of Threatened and Endangered Species that May Occur in Your Proposed Project Location for Browns Ferry EPU
Project stage: Request
ML16041A3072016-02-18018 February 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16041A0222016-02-25025 February 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16040A2322016-02-25025 February 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16049A4632016-02-29029 February 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
CNL-16-045, Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information2016-03-0909 March 2016
Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information
Project stage: Supplement
ML16062A0722016-03-15015 March 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
CNL-16-048, Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)2016-03-24024 March 2016
Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)
Project stage: Supplement
ML16084A3202016-03-25025 March 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
CNL-16-055, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information2016-03-28028 March 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information
Project stage: Supplement
ML16089A1372016-03-29029 March 2016
NRR E-mail Capture - Correction to Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16064A2862016-04-0404 April 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16091A0712016-04-0707 April 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16085A3012016-04-11011 April 2016
Regulatory Audit Plans for April 19 - 21, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request
Project stage: Other
ML16085A0792016-04-14014 April 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16102A3392016-04-14014 April 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
CNL-16-069, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information2016-04-14014 April 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information
Project stage: Supplement
ML16104A2452016-04-20020 April 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016
for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information
Project stage: Supplement
ML16105A4412016-04-27027 April 2016
Regulatory Audit Plan for May 10-11, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request
Project stage: Other
CNL-16-079, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information2016-05-11011 May 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information
Project stage: Supplement
ML16124A9322016-05-12012 May 2016
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16125A4232016-05-19019 May 2016
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate2016-05-26026 May 2016
Update on Progress of Facility Modifications for MSIV Leak Rate
Project stage: Other
CNL-16-091, Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendment2016-05-27027 May 2016
Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendments
Project stage: Response to RAI
CNL-16-094, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information2016-06-0909 June 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information
Project stage: Supplement
ML16146A6352016-06-13013 June 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16161A0642016-06-15015 June 2016
Notice of Forthcoming Closed Meeting with Tennessee Valley Authority and Its Consultant, GEH, Regarding Steam Dryers Structural Adequacy for Browns Ferry Units 1, 2 & 3 Extended Power Uprate (EPU) License Amendment Request (LAR)
Project stage: Meeting
CNL-16-093, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information2016-06-17017 June 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information
Project stage: Supplement
ML16154A5442016-06-21021 June 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
ML16168A0262016-06-23023 June 2016
Summary Report for the April 19 to 21, 2016 Audit in Support of Replacement Steam Dryer Review Associated to Extended Power Uprate License Amendment Request (CAC Nos. MF6741, MF6742, and MF6743)
Project stage: Other
CNL-16-105, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information2016-06-24024 June 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information
Project stage: Supplement
ML16125A4062016-07-0606 July 2016
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16127A6092016-07-0606 July 2016
NRC Letter Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16125A0842016-07-0707 July 2016
Approval for Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16130A6002016-07-0707 July 2016
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16173A0262016-07-0707 July 2016
Approval for Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML16176A3162016-07-11011 July 2016
Summary Report for the May 3 to May 5, 2016 Audit in Support Containment Accident Pressure Associated to Extended Power Uprate License Amendment Request
Project stage: Other
CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016
Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates
Project stage: Supplement
CNL-16-119, Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers2016-07-13013 July 2016
Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers
Project stage: Supplement
ML16193A4602016-07-21021 July 2016
June 23, 2016, Summary of Closed Meeting with Tennessee Valley Authority Regarding the Structural Adequacy of Steam Dryers for Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (MF6741, MF6742
Project stage: Meeting
ML16194A2292016-07-21021 July 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
Project stage: RAI
CNL-16-116, Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 252016-07-27027 July 2016
Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 25
Project stage: Supplement
CNL-16-118, Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 272016-07-29029 July 2016
Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 27
Project stage: Supplement
2016-04-07
[Table View] |
|
|---|
Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024
Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
ML24023A2802024-01-23023 January 2024
Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump
CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions
ML24016A3042024-01-16016 January 2024
Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024
Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47
ML24022A1732024-01-0303 January 2024
Receipt and Availability of the Subsequent License Renewal Application
ML23319A1992024-01-0303 January 2024
Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves
ML23355A2062023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23348A3942023-12-14014 December 2023
Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
IR 05000259/20230102023-12-11011 December 2023
Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010
ML23335A0722023-12-0101 December 2023
Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump
ML23334A2492023-11-30030 November 2023
Site Emergency Plan Implementing Procedure Revision
CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023
Submittal of Fifth 10-Year Interval Inservice Testing Program Plan
ML23331A2532023-11-27027 November 2023
Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions
CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML23325A1102023-11-21021 November 2023
Anchor Darling Double Disc Gate Valve Commitment Revision
ML23320A2542023-11-16016 November 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
IR 05000259/20230032023-11-13013 November 2023
Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003
IR 05000259/20230402023-11-0202 November 2023
Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter
ML23292A2532023-10-18018 October 2023
BFN 2024-301, Corporate Notification Letter (210-day Ltr)
ML23282A0022023-10-0606 October 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
ML23278A0122023-10-0505 October 2023
Updated Final Safety Analysis Report, Amendment 30
ML23271A1702023-09-28028 September 2023
Site Emergency Plan Implementing Procedure Revision
ML23270A0702023-09-26026 September 2023
SLRA Pre-Application Meeting Summary 09-13-2023
ML23257A1232023-09-22022 September 2023
Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315
CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision
ML23263B1042023-09-20020 September 2023
Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64
IR 05000259/20230052023-08-29029 August 2023
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005
ML23233A0432023-08-18018 August 2023
Enforcement Action EA-22-122 Inspection Readiness Notification
ML23219A1542023-08-17017 August 2023
Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program
ML23228A1642023-08-16016 August 2023
Site Emergency Plan Implementing Procedure Revision
ML23228A0202023-08-15015 August 2023
(BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
IR 05000259/20230022023-08-10010 August 2023
Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001
ML23192A4472023-07-31031 July 2023
Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information
CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023
Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills
ML23171A8862023-07-24024 July 2023
Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML23201A2182023-07-20020 July 2023
Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299)
ML23159A2552023-07-20020 July 2023
Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles
ML23199A3072023-07-18018 July 2023
Site Emergency Plan Implementing Procedure Revision
CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023
Tennessee Valley Authority - Radiological Emergency Plan Revisions
IR 05000259/20233012023-07-18018 July 2023
NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301
2024-02-01
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23332A0042023-11-27027 November 2023
NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47
ML23243A9892023-08-29029 August 2023
Inspection Information Request
ML23124A0082023-05-0303 May 2023
NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3
ML23041A0022023-02-0909 February 2023
NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025)
ML22299A0292022-10-26026 October 2022
NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage
ML22292A2722022-10-19019 October 2022
NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3
ML22208A2172022-07-15015 July 2022
NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081)
ML22174A2722022-06-24024 June 2022
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML22168A0802022-06-17017 June 2022
NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie
ML22160A4742022-06-0303 June 2022
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel
ML22168A0392022-05-13013 May 2022
NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie
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
ML22047A1612022-02-16016 February 2022
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3
ML22025A4132022-01-25025 January 2022
RP Inspection Doc Request
ML21343A4232021-12-0909 December 2021
Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI)
ML21173A1042021-06-21021 June 2021
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to TS 3.8.6
ML21041A5422021-02-10010 February 2021
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt 10 CFR 50.69
ML21041A5432021-02-0505 February 2021
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Draft Request for Additional Information Regarding 10 CFR 50.69 LAR
ML21026A1652021-01-26026 January 2021
Document Request for Browns Ferry Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-02
ML20296A3782020-10-22022 October 2020
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Incorporate TMRE
ML20297A3012020-10-22022 October 2020
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Request to Adopt TSTF-425
ML20294A3762020-09-23023 September 2020
NRR E-mail Capture - Draft Request for Additional Information - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Adopt TSTF-425
ML20266G4472020-09-22022 September 2020
Notification of Inspection and Request for Information
ML20224A4732020-08-11011 August 2020
Requalification Program Inspection Browns Ferry Nuclear
ML20195B1302020-07-13013 July 2020
NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Regarding Alternative Request No. 0-ISI-47
ML20149K3212020-05-27027 May 2020
RP Inspection Document Request, Browns Ferry 2020-003
ML20254A3032020-05-13013 May 2020
Request for Supporting Information for the Browns Ferry, Units 1, 2, and 3 Seismic Probabilistic Risk Assessment Audit Review
ML20054B8592020-02-20020 February 2020
Emergency Preparedness Program Inspection Request for Information
ML20014E6552020-01-14014 January 2020
01 RP Inspection Document Request
ML19196A0752019-07-12012 July 2019
NRR E-mail Capture - Final RAIs Browns Ferry Nuclear, Units 1, 2, 3 - Application to Revise Technical Specifications to Adopt TSTF-542 Revision 2, Reactor Pressure Vessel Water Inventory Control
ML19116A0712019-06-0303 June 2019
Request for Additional Information Related Resubmittal of Proposed Alternative Request No. 1-ISI-27 for the Period of Extended Operation
ML18331A5442018-12-0606 December 2018
Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary)
ML18317A1642018-11-20020 November 2018
Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary
ML18263A1412018-09-11011 September 2018
NRR E-mail Capture - Browns Ferry Unit 1: RAI Associated with Relief Request 1-ISI-28
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)
ML18108A1872018-04-18018 April 2018
Information Request for the Cyber-Security Baseline Security Inspection, Notification to Perform Inspection 05000259/2018411, 05000260/2018411, and 05000296/2018411
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)
ML17216A0062017-08-18018 August 2017
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to LAR to Revise Modifications and Implementations Related to NFPA 805 for Fire Protection for Light Water Reactor Generating Plants (CAC Nos. MF9814-MF9816)
ML17163A0502017-06-0808 June 2017
NRR E-mail Capture - RAI for Browns Ferry RR 3-ISI-28 CAC No. MF9257
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)
ML16288A0182016-10-27027 October 2016
Browns Ferry Nuclear Plant, Units 2 and 3 - RAI Related to Relief Request for the Use of Alternatives to Certain American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section XI Requirements (CAC Nos. MF7795 and MF7796)
ML16236A0732016-08-31031 August 2016
Request for Additional Information Related to License Amendment Request to Add New Technical Specification 3.3.8.3
ML16203A0272016-07-25025 July 2016
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (CAC Nos. MF6738, MF6739, and MF6740)
ML16187A2932016-07-21021 July 2016
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743)
ML16194A2292016-07-21021 July 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
ML16154A5442016-06-21021 June 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
ML16146A6352016-06-13013 June 2016
Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
ML16145A1582016-06-0303 June 2016
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SBPB-RAI 4) (CAC Nos. MF6741, MF6742, and MF6743)
ML16144A6452016-06-0303 June 2016
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Non-proprietary Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (EMCB-RAI)
ML16119A1332016-05-0606 May 2016
Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (SNPB-RAI) (CAC Nos. MF6741, MF6742, and MF6743)
2023-08-29
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 25, 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF6741, MF6742, AND MF6743)
Dear Mr. Shea:
By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA or the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatts thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On February 2, 2016, the NRC staff forwarded, by electronic mail, a draft of the staff's request for additional information (RAI) to TVA. On February 9, 2015, TVA informed the NRC staff that no clarification call is needed. The official questions are found in the enclosed RAI. This request was discussed with Mr. Daniel Green of your staff, and it was agreed that TVA would respond by March 25, 2016.
J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.
The U.S. Nuclear Regulatory Commission (NRC) staff from the Office of Nuclear Reactor Regulation (NRR), Division of Risk Assessment, Fire Protection Branch (AFPB), reviewed the LAR and its supplements. The NRC staff determined that the following information is needed to complete their review.
AFPB-Reguest for Additional Information (RAil 1 The NRC staff notes that LAR Attachment 6 to the Safety Analysis Report (SAR) for BFN, Units 1, 2, and 3, Extended Power Uprate (EPU), NEDC-33860P, 1 Revision 0, September 2015, Section 2.5.1.4, "Fire Protection," states that, "The transition to NFPA 805 is currently under NRC staff review, and TVA anticipates its approval prior to implementation [of] EPU operation.
Accordingly, the fire protection analysis described in this section is based on the NFPA 805 implementation ... "
On October 10, 2015, the NRC issued a license amendment for BFN, Units 1, 2, and 3, to incorporate National Fire Protection Association (NFPA) 805 fire protection licensing basis in accordance with Title 10 of Code of Federal Regulations (10 CFR), Section 50.48(c). The amendment approved the transition of the licensee's fire protection program to a risk-informed, performance-based program based on the 2001 Edition of NFPA 805. The staff requests that the licensee provide a supplement to LAR Attachment 6 to the SAR for BFN Units 1, 2, and 3, 1
This document is marked "Proprietary" (non-publicly available information) in TVA letter dated September 21, 2015.
All contents of this document should be handled in accordance with the NRC guidance of handling Sensitive Unclassified Non-Safeguards Information (SUNSI).
Enclosure
EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4, "Fire Protection," consistent with the approved NFPA 805 licensing basis.
AFPB-RAI 2 to Matrix 5, "Supplemental Fire Protection Review Criteria, Plant Systems," of NRR RS-001, Revision 0, "Review Standard for Extended Power Uprates" (ADAMS Accession No. ML033640024) states:
Power uprates typically result in increases in decay heat generation following plant trips. These increases in decay heat usually do not affect the elements of a fire protection program related to ( 1) administrative controls, (2) fire suppression and detection systems, (3) fire barriers, (4) fire protection responsibilities of plant personnel, and (5) procedures and resources necessary for the repair of systems required to achieve and maintain cold shutdown. In addition, an increase in decay heat will usually not result in an increase in the potential for a radiological release resulting from a fire. However, the licensee's application should confirm that these elements are not impacted by the extended power uprate.
The NRC staff notes that LAR Attachment 6 to SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program,"
specifically addresses items (1) through (4) above. The staff requests that the licensee provide statements to address item (5) and a statement confirming no increase in the potential for a radiological release resulting from a fire.
AFPB-RAI 3 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program,
states:
The higher decay heat associated with EPU results in higher heat input into the suppression pool which, without mitigation, will result in higher suppression pool temperatures. The higher decay heat may also result in lower vessel water levels or higher Peak Cladding Temperatures (PCTs), depending on the plant-specific analysis basis. As a result of these effects, fire suppression and detection systems, operator response time, peak clad temperature (PCT), and suppression pool temperature need to be addressed.
The staff requests the licensee verify that additional heat in the plant environment from the EPU will not:
- a. Impact any required operator manual actions (referred to as recovery actions per NFPA 805 licensing basis) being performed at their designated time (including, e.g., verifying that under EPU conditions, recovery actions and repairs required to demonstrate the availability of a success path to achieve the nuclear safety
performance criteria are feasible and have been evaluated for the additional risk due to their use), or
- b. Require any new recovery actions due to additional heat in the plant environment to maintain the plant in safe and stable conditions.
AFPB-RAI 4 The staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program,"
states that, " ... Other EPU modifications will be assessed and assured not to adversely affect the ability to achieve and maintain the fuel in a safe and stable condition in the event of a fire ... "
Further, Section 2.11.1.2.2, "Fire Safe Shutdown (FSS) Events," states:
Attachment 47 of the EPU LAR provides a listing and discussion of the modifications planned for EPU. The effect of these modifications on the Browns Ferry Fire Protection Program will be evaluated, in accordance with TVA's configuration change process, prior to EPU implementation. Per the process, these modifications will be evaluated to assure the changes do not affect the approved Fire Protection Program and will not adversely affect the ability to achieve and maintain safe shutdown in accordance with the current Browns Ferry license conditions and procedures ...
The NRC staff notes that modifications associated with the EPU have not yet been completed to address the impact on the fire protection program. The staff requests that the licensee discuss how the results of plant modifications would impact the fire protection program and the plant's compliance with the fire protection program licensing basis (10 CFR 50.48(c)).
AFPB-RAI 5 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.1, "Fire Protection Program,"
states:
Original NFP 805 analyses were performed at EPU conditions and therefore operator action times cannot be compared to CLTP [current licensed thermal power] conditions. To ensure that PCT remains less than the acceptance criterion in the most limiting scenario, one LPCI pump must be manually aligned for injection within 20 minutes ...
The staff requests the licensee provide a technical justification for the 20-minute time for the operator to perform the actions to align LPCI pump injection. Include discussion of the original time margin without CLTP conditions (i.e., what was assumed for the NFPA 805 analyses) and why the 20-minute assumption is deemed adequate.
AFPB-RAI 6 The NRC staff notes that LAR Attachment 6 to the SAR for BFN, Units 1, 2, and 3, EPU, NEDC-33860P, Revision 0, September 2015, Section 2.5.1.4.2, "Fire Event," states:
The results of Case 4, and the evaluations in Section 2.6.5.2, FUSAR [Fuel Uprate Safety Analysis Report] Section 2.5.1.4, and LAR Attachment 39, demonstrate that the peak fuel cladding temperature, vessel water level, and suppression pool temperature meet the acceptance criteria and the time available for the operators to perform the necessary actions is sufficient.
Therefore, EPU has no adverse effect on the ability of the systems and personnel to mitigate the effects of a fire event and satisfies the requirement of achieving and maintaining the fuel in a safe and stable condition in the event of a fire.
The staff requests the licensee confirm that the above analysis cases at EPU conditions meet the NFPA 805 licensing basis to achieve and maintain the fuel in a safe and stable condition in the event of a fire.
AFPB-RAI 7 Some plants credit aspects of their fire protection system for other than fire protection activities (e.g., utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems). If BFN, Units 1, 2, and 3, credits its fire protection system in this way, identify the specific situations and discuss to what extent, if any, the EPU affects these "non-fire-protection" aspects of the plant fire protection system.
J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, IRA/
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:
PUBLIC Nlqbal, NRR RidsRgn2MailCenter LPL2-2 R/F RidsNrrLABClayton RidsNrrPMBrownsFerry RidsNrrDorllpl2-2 RidsACRS_MailCTR RidsNrrDraAfpb BFNEPU Resource RidsNrrDorlDpr ADAMS A ccess1on N o.: ML16041A022 *b1y memo OFFICE N RR/DORL/LPLI 1-2/PM N RR/DORL/LPLI 1-2/LA NRR/DRA/AFPB/BC*
NAME FSaba BClavton (LRonewicz for) AKlein DATE 2/18/2016 2/18/2016 2/2/2016 OFFICE NRR/DORL/LPLI 1-2/BC NRR/DORL/LPLI 1-2/PM NAME BBeasley FSaba DATE 2/24/2016 2/25/2016 OFFICIAL RECORD COPY
