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| | issue date = 09/01/2006 | | | issue date = 09/01/2006 |
| | title = RAI, EPU Round 9 (TS-431) | | | title = RAI, EPU Round 9 (TS-431) |
| | author name = Chernoff M H | | | author name = Chernoff M |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
| | addressee name = Singer K W | | | addressee name = Singer K |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000259 | | | docket = 05000259 |
| | license number = DPR-033 | | | license number = DPR-033 |
| | contact person = Chernoff M H, NRR/DORL, 415-4041 | | | contact person = Chernoff M, NRR/DORL, 415-4041 |
| | case reference number = TAC MC3812 | | | case reference number = TAC MC3812 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:September 1, 2006Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | | {{#Wiki_filter:September 1, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION FOR EXTENDED POWER UPRATE - ROUND 9 (TS-431) (TAC NO. MC3812) | | BROWNS FERRY NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 9 (TS-431) |
| | (TAC NO. MC3812) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| By letter dated June 28, 2004, as supplemented by letters dated August 23, 2004, February 23,April 25, June 6, and December 19, 2005, February 1 and 28, March 7, 9, 23, and 31, April 13, May 5 and 11, June 12, 15, 23 and 27, and July 6, 21, 24, 26, and 31, and August 416, and 18, 2006, Tennessee Valley Authority (TVA, the licensee) submitted an amendmentrequest for Browns Ferry Nuclear Plant, Unit 1. The proposed amendment would change the Unit 1 operating license to increase the maximum authorized power level from 3293 to 3952 megawatts thermal. This change represents an increase of approximately 20 percent above the current maximum authorized power level for Unit 1. The proposed amendment would also change the Unit 1 licensing bases and associated Technical Specifications to credit 3 pounds per square inch gauge (psig) for containment accident pressure following a loss-of-coolant accident and increase the reactor steam dome pressure by 30 psig. A response to the enclosed Request for Additional Information is needed before the NuclearRegulatory Commission staff can complete the review. These requests were provided in draft from to your staff by e-mail and discussed on August 8-11, 2006. In discussions with your staff it was agreed that a response would be provided by September 15, 2006. If you have any questions, please contact me at (301) 415-4041.Sincerely,/RA by EBrown for/Margaret H. Chernoff, Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-259 | | By letter dated June 28, 2004, as supplemented by letters dated August 23, 2004, February 23, April 25, June 6, and December 19, 2005, February 1 and 28, March 7, 9, 23, and 31, April 13, May 5 and 11, June 12, 15, 23 and 27, and July 6, 21, 24, 26, and 31, and August 4 16, and 18, 2006, Tennessee Valley Authority (TVA, the licensee) submitted an amendment request for Browns Ferry Nuclear Plant, Unit 1. The proposed amendment would change the Unit 1 operating license to increase the maximum authorized power level from 3293 to 3952 megawatts thermal. This change represents an increase of approximately 20 percent above the current maximum authorized power level for Unit 1. The proposed amendment would also change the Unit 1 licensing bases and associated Technical Specifications to credit 3 pounds per square inch gauge (psig) for containment accident pressure following a loss-of-coolant accident and increase the reactor steam dome pressure by 30 psig. |
| | A response to the enclosed Request for Additional Information is needed before the Nuclear Regulatory Commission staff can complete the review. These requests were provided in draft from to your staff by e-mail and discussed on August 8-11, 2006. In discussions with your staff it was agreed that a response would be provided by September 15, 2006. |
| | If you have any questions, please contact me at (301) 415-4041. |
| | Sincerely, |
| | /RA by EBrown for/ |
| | Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information | | Request for Additional Information cc w/enclosure: See next page |
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| cc w/enclosure: See next page
| | ML062350360 NRR-106 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA DSS/SBWB NAME EBrown EBrown for BClayton JWermeil by memo MChernoff DATE 9/ 01 /06 09/01/06 09/01/06 8/16/06 OFFICE APLA/BC DSS/ACVB LPL2-2/BC NAME MRubin by memo TMartin by memo LRaghavan DATE 8/31/06 8/22/06 09/01/06 |
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| ML062350360 NRR-106OFFICELPL2-2/PMLPL2-2/PMLPL2-2/LADSS/SBWBNAMEEBrownEBrown forMChernoffBClaytonJWermeil by memoDATE9/ 01 /0609/01/0609/01/068/16/06OFFICEAPLA/BCDSS/ACVBLPL2-2/BCNAMEMRubin by memoTMartin by memoLRaghavanDATE8/31/068/22/0609/01/06
| | ==SUBJECT:== |
| | BROWNS FERRY NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 9 (TS-431) |
| | (TAC NO. MC3812) |
| | Dated: September 1, 2006 DISTRIBUTION: |
| | PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrLACGoldstein RidsNrrPMMChernoff RidsNrrPMEBrown RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn2MailCenter RidsNrrDorl (CHolden) |
| | RidsNrrDorlDpr TAlexion GCranston GThomas THuang ZAbdullahi RLobel MStutzke SLaur RDennig RGoel |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 APLA |
| | : 25. In various correspondence the NRC staff has noted different values for the suppression pool (SP) bulk temperature limit: |
| | : a. Section 4.8.6.2, Page 4.8-4 of the updated final safety analyses report (UFSAR) states a limit of 177 degrees Fahrenheit (EF), based on an analysis of the torus attached piping. |
| | : b. The limit of 177 EF was used in the previous 5 percent power uprate for Units 2 and 3 (ADAMS Accession No. ML042670045). |
| | : c. The draft Unit 1 Fire Protection Program Report (ADAMS Accession No. ML060620424) provides various limits as follows: |
| | : i. Page 301- The design limit is 281 EF. |
| | ii. Page 309 - The residual heat removal (RHR) pump seals were rated for 160 EF, but have been re-evaluated for 215 EF. |
| | : d. Table 4-1 of Enclosure 4 of the submittals dated June 28 and 25, 2004, uses the 281 EF limit. Provide the correct SP bulk temperature limit for evaluating the proposed containment accident pressure (CAP) credit. |
| | : 26. Analysis (e.g., the August 4, 2006, submittal) indicates that containment accident pressure (CAP) credit is required to ensure adequate net positive suction head (NPSH) to the RHR pumps during an Appendix R scenario. The NRC staff understands that CAP credit is required for the pre-EPU [extended power uprate] plant as well as for the post-EPU plant. The Fire Protection Program Report defines the Appendix R scenario as a fire that results in a total loss of high-pressure makeup sources (feedwater (FW), |
| | high pressure coolant injection, and reactor core isolation cooling), followed by manual depressurization using three S/RVs and operation of one RHR pump and its associated heat exchanger in low pressure coolant injection (LPCI) mode (i.e., no suppression pool cooling(SPC)). |
| | For transient initiating events (e.g., loss of FW), the probabilistic risk assessment (PRA) credits manual depressurization using the S/RVs and use of either core spray (CS) or LPCI, along with SPC, upon the failure of all high-pressure makeup sources. The PRA also includes sequences initiated by transient events that lead to multiple stuck-open S/RVs (e.g., loss of FW and subsequent MSIV closure, which causes the S/RVs to Enclosure |
| | |
| | open, followed by subsequent failure of the S/RVs to reclose). The previous risk evaluation of the proposed CAP credit does not address these types of accident sequences. |
| | Provide a risk evaluation of the proposed CAP credit that includes the increase in core-damage frequency and, large early release frequency due to sequences that are initiated by transient events that lead to either (a) manual depressurization via the S/RVs and use of CS or LPCI upon the total loss of high-pressure makeup sources, and (b) sequences that are initiated by transient events that lead to multiple stuck-open S/RVs. |
| | ACVB |
| | : 62. The August 4, 2006, response to Request for Additional Information (RAI) Risk Assessment Containment & Ventilation Branch (ACVB) 37/35 states that, for the CS pump, the operator is instructed to maintain flow less than 4000 gallons per minute (gpm) and within the NPSH limit curves. However, for determining adequate NPSH, it is assumed that the operator would reduce flow in response to the NPSH limit curves, but not less than 3125 gpm. |
| | It appears that at a flow rate of 4000 gpm and the peak calculated suppression pool temperature, the pumps are in the acceptable region of the Emergency Operating Instruction NPSH limit curves. Therefore, explain what prompts the operator to reduce flow to 3125 gpm. If the operator can operate acceptably at 4000 gpm, address why shouldnt this more conservative flow rate be used in the NPSH analyses. |
| | : 63. In the July 21, 2006, response to RAI Probabilistic Risk Assessment Licensing Branch A (APLA) 24/26, five fire areas are described. For those fire areas for which the safety analysis depends on RHR pumps (control room and turbine building), 2 RHR pumps are said to be available. Address why only one RHR pump is credited for the Appendix R analyses and NPSH analyses. |
| | : 64. Enclosure 4 of the August 4, 2006, letter contains Calculation MDQ099920060011, Transient NPSH/ Containment Pressure Evaluation of RHR and CS Pumps. For the short term loss-of-coolant accident response, Figure 7.5 of Calculation MDQ099920060011 shows that the wetwell pressure required is less than the wetwell pressure available for the RHR pumps pumping into the broken recirculation loop. |
| | TVA indicated this was acceptable based on RHR pump tests reported in Enclosure 2 to a May 21, 1976 TVA letter to the NRC. A margin of 9 feet was shown to be available in these tests relative to the required NPSH based on a 3 percent head drop. |
| | (i) Provide the margin between the lowest NPSH value of the cavitation tests reported in the May 21, 1976 letter and the reduced required NPSH values used in Tennessee Valley Authority (TVA) Calculation MDQ099920060011. |
| | (ii) Discuss the difference between the required NPSH and the available NPSH at 600 seconds. |
| | (iii) Describe how the required NPSH value of 28.4 ft in Figure 7.5 of Calculation |
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| ==SUBJECT:==
| | MDQ099920060011 was obtained. |
| BROWNS FERRY NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION FOR EXTENDED POWER UPRATE - ROUND 9 (TS-431) (TAC NO. MC3812) Dated: September 1, 2006 DISTRIBUTION
| | : 65. Table 10-2 of Enclosure 4 to the June 28, 2004, submittal, NEDC-33101P, DRF 0000-0010-9439, Browns Ferry Unit 1 Safety Analysis Report for Extended Power Uprate (PUSAR), shows that the peak drywell air temperature due to a steam line break (336 °F) exceeds the containment shell design temperature limit (281 °F). Verify that the shell temperature itself remains below the 281 °F design limit. |
| :PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrLACGoldstein RidsNrrPMMChernoff RidsNrrPMEBrown RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn2MailCenterRidsNrrDorl (CHolden)
| | : 66. Provide the maximum RHR and core spray pump seal temperatures. If less than the calculated peak suppression pool temperatures, address why this is acceptable. |
| RidsNrrDorlDpr TAlexion GCranston GThomas THuang ZAbdullahi RLobel MStutzke SLaur RDennig RGoel EnclosureREQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATETENNESSEE VALLEY AUTHORITYBROWNS FERRY NUCLEAR PLANT, UNIT 1DOCKET NO. 50-259 APLA25.In various correspondence the NRC staff has noted different values for the suppressionpool (SP) bulk temperature limit:a.Section 4.8.6.2, Page 4.8-4 of the updated final safety analyses report (UFSAR)states a limit of 177 degrees Fahrenheit (F), based on an analysis of the torusattached piping.b.The limit of 177 F was used in the previous 5 percent power uprate for Units 2and 3 (ADAMS Accession No. ML042670045).c.The draft Unit 1 Fire Protection Program Report (ADAMS AccessionNo. ML060620424) provides various limits as follows:i.Page 301- The design limit is 281 F.ii.Page 309 - The residual heat removal (RHR) pump seals were rated for 160 F, but have been re-evaluated for 215 F.d.Table 4-1 of Enclosure 4 of the submittals dated June 28 and 25, 2004, uses the 281 F limit. Provide the correct SP bulk temperature limit for evaluating theproposed containment accident pressure (CAP) credit. 26.Analysis (e.g., the August 4, 2006, submittal) indicates that containment accidentpressure (CAP) credit is required to ensure adequate net positive suction head (NPSH) to the RHR pumps during an Appendix R scenario. The NRC staff understands thatCAP credit is required for the pre-EPU [extended power uprate] plant as well as for the post-EPU plant. The Fire Protection Program Report defines the Appendix R scenario as a fire that results in a total loss of high-pressure makeup sources (feedwater (FW),
| | : 67. Provide the maximum acceptable temperature of the piping attached to the torus. If less than the maximum suppression pool water temperature, address why is this acceptable. |
| high pressure coolant injection, and reactor core isolation cooling), followed by manual depressurization using three S/RVs and operation of one RHR pump and its associatedheat exchanger in low pressure coolant injection (LPCI) mode (i.e., no suppression pool cooling(SPC)). For transient initiating events (e.g., loss of FW), the probabilistic risk assessment (PRA)credits manual depressurization using the S/RVs and use of either core spray (CS) or LPCI, along with SPC, upon the failure of all high-pressure makeup sources. The PRA also includes sequences initiated by transient events that lead to multiple stuck-open S/RVs (e.g., loss of FW and subsequent MSIV closure, which causes the S/RVs to open, followed by subsequent failure of the S/RVs to reclose). The previous riskevaluation of the proposed CAP credit does not address these types of accident sequences. Provide a risk evaluation of the proposed CAP credit that includes the increase incore-damage frequency and, large early release frequency due to sequences that are initiated by transient events that lead to either (a) manual depressurization via the S/RVsand use of CS or LPCI upon the total loss of high-pressure makeup sources, and (b) sequences that are initiated by transient events that lead to multiple stuck-openS/RVs.ACVB62.The August 4, 2006, response to Request for Additional Information (RAI) RiskAssessment Containment & Ventilation Branch (ACVB) 37/35 states that, for the CSpump, the operator is instructed to maintain flow less than 4000 gallons per minute (gpm) and within the NPSH limit curves. However, for determining adequate NPSH, it is assumed that the operator would reduce flow in response to the NPSH limit curves, but not less than 3125 gpm.It appears that at a flow rate of 4000 gpm and the peak calculated suppression pooltemperature, the pumps are in the acceptable region of the Emergency OperatingInstruction NPSH limit curves. Therefore, explain what prompts the operator to reduce flow to 3125 gpm. If the operator can operate acceptably at 4000 gpm, address why shouldn't this more conservative flow rate be used in the NPSH analyses.63.In the July 21, 2006, response to RAI Probabilistic Risk Assessment Licensing Branch A(APLA) 24/26, five fire areas are described. For those fire areas for which the safety analysis depends on RHR pumps (control room and turbine building), 2 RHR pumps aresaid to be available. Address why only one RHR pump is credited for the Appendix Ranalyses and NPSH analyses.64.Enclosure 4 of the August 4, 2006, letter contains Calculation MDQ099920060011,Transient NPSH/ Containment Pressure Evaluation of RHR and CS Pumps. For theshort term loss-of-coolant accident response, Figure 7.5 of Calculation MDQ099920060011 shows that the wetwell pressure required is less than the wetwell pressure available for the RHR pumps pumping into the broken recirculation l oop. TVA indicated this was acceptable based on RHR pump tests reported in Enclosure 2 toa May 21, 1976 TVA letter to the NRC. A margin of 9 feet was shown to be available inthese tests relative to the required NPSH based on a 3 percent head drop. (i) Provide the margin between the lowest NPSH value of the cavitation tests reported inthe May 21, 1976 letter and the reduced required NPSH values used in Tennessee Valley Authority (TVA) Calculation MDQ099920060011.(ii) Discuss the difference between the required NPSH and the available NPSH at600 seconds.(iii) Describe how the required NPSH value of 28.4 ft in Figure 7.5 of Calculation MDQ099920060011 was obtained.65.Table 10-2 of Enclosure 4 to the June 28, 2004, submittal, NEDC-33101P,DRF 0000-0010-9439, Browns Ferry Unit 1 Safety Analysis Report for Extended Power Uprate (PUSAR), shows that the peak drywell air temperature due to a steam line break (336 °F) exceeds the containment shell design temperature limit (281 °F). Verify that the shell temperature itself remains below the 281 °F design limit.66.Provide the maximum RHR and core spray pump seal temperatures. If less than thecalculated peak suppression pool temperatures, address why this is acceptable.67.Provide the maximum acceptable temperature of the piping attached to the torus. If lessthan the maximum suppression pool water temperature, address why is this acceptable.SBWB49.Provide the head flow curves used in the limiting large break loss-of-coolant accidentanalyses (battery failure case). The curves should include the head flow curve for one low pressure core spray and one low pressure coolant injection pump discharging into each recirculation line. Also, provide the limiting axial power shape used in this limiting break.
| | SBWB |
| Mr. Karl W. SingerBROWNS FERRY NUCLEAR PLANTTennessee Valley Authority
| | : 49. Provide the head flow curves used in the limiting large break loss-of-coolant accident analyses (battery failure case). The curves should include the head flow curve for one low pressure core spray and one low pressure coolant injection pump discharging into each recirculation line. Also, provide the limiting axial power shape used in this limiting break. |
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| cc: | | Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc: |
| Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Brian O'Grady, Site Vice PresidentBrowns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Robert J. Beecken, Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 General CounselTennessee Valley Authority ET 11A 400 West Summit Hill DriveKnoxville, TN 37902Mr. John C. Fornicola, ManagerNuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Bruce Aukland, Plant ManagerBrowns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Masoud Bajestani, Vice PresidentBrowns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Robert G. Jones, General ManagerBrowns Ferry Site Operations Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Mr. Larry S. MellenBrowns Ferry Unit 1 Project Engineer Division of Reactor Projects, Branch 6 U.S. Nuclear Regulatory Commission 61 Forsyth Street, SW. | | Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW. |
| Suite 23T85 Atlanta, GA 30303-8931 Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. William D. Crouch, M anagerLicensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609Senior Resident InspectorU.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970State Health OfficerAlabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017ChairmanLimestone County Commission 310 West Washington Street Athens, AL 35611}} | | Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Mr. Glenn W. Morris, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Robert J. Beecken, Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, Manager 10833 Shaw Road Nuclear Assurance and Licensing Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609}} |
Letter Sequence RAI |
|---|
TAC:MC3812, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- 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, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML041980222, ML042370100, ML050590036, ML051150191, ML051160036, ML051320148, ML051430036, ML051570381, ML051660602, ML052290397, ML060530185, ML060670304, ML060680586, ML060680590, ML060680596, ML060680599, ML060720253, ML060720272, ML060720273, ML060720281, ML060720293, ML060720295, ML060720298, ML060720303, ML060720354, ML060880464, ML060880469, ML061040217, ML061660002, ML061770163, ML061840027, ML061910705, ML062050056, ML062090482, ML062090555, ML062120411, ML062130163, ML062130343, ML062200277, ML062210102, ML062220647, ML062270240, ML062360160, ML062400472, ML062510022, ML062510371, ML062510374, ML062510382, ML062510385, ML062620064... further results
|
MONTHYEARML0607202531975-05-23023 May 1975
May 23, 1975 - Final Summary Report Unit 2 Startup
Project stage: Other
ML0606805861975-05-23023 May 1975
May 23, 1975 - Final Summary Report Startup, Enclosure 4
Project stage: Other
ML0607202721977-05-0909 May 1977
May 9, 1977 - Final Summary Report Unit 3 Startup
Project stage: Other
ML0606805901977-05-0909 May 1977
May 9, 1977 - Final Summary Report Startup, Enclosure 5
Project stage: Other
ML0607202731992-11-30030 November 1992
a Guide for Environmental and Best Management Practices for Tennessee Valley Authority Transmission Construction and Maintenance Activities
Project stage: Other
ML0607202982001-03-13013 March 2001
Environmental Assessment Bear Creek Reservoirs Land Management Plan
Project stage: Other
ML0607202952001-03-31031 March 2001
Bear Creek Reservoirs Land Management Plan, Resource Stewardship Bear Creek Watershed
Project stage: Other
ML0606805992001-03-31031 March 2001
Bear Creek Reservoirs Land Management Plan
Project stage: Other
ML0419802222004-07-0909 July 2004
Technical Specification 436 - Increased Main Steam Isolation Valve Leakage Rate Limits and Exemption from 10CFR50, Appendix J
Project stage: Other
ML0423701002004-08-23023 August 2004
Browns Ferry, Ltr, Framatome Proprietary Review
Project stage: Other
ML0423708492004-08-23023 August 2004
(BFN) - Unit 1- Proposed Technical, Specifications (TS) Change TS - 431 - Request for License Amendment - Extended Power Uprate (EPU) Operation Probabilistic Safety Assessment (PSA) Update
Project stage: Request
ML0429202832004-11-18018 November 2004
Ltr, Results of Acceptance Review for Extended Power Uprate
Project stage: Acceptance Review
ML0431004762004-11-18018 November 2004
Ltr, Results of Acceptance Review for EPU
Project stage: Acceptance Review
ML0433701792004-12-29029 December 2004
RAI Re Extended Power Uprate
Project stage: RAI
ML0434400452004-12-30030 December 2004
RAI, Extended Power Uprate
Project stage: RAI
ML0500303612005-01-0606 January 2005
Ltr, Request for Information for Status of Amendment (Tac No. MC1330, MC1427, MC2305, MC3812, MC4070, MC4071, MC4072, MC4161, MC3743, MC3744)
Project stage: RAI
ML0505900362005-02-16016 February 2005
Enclosure 2, 02/01/2005 Conference Call with TVA Presentation Slides on TS Changes Using Method 3 for Interim Solution
Project stage: Other
ML0505601502005-02-23023 February 2005
Response to NRC Acceptance Review Letter and Request for Additional Information Related to Technical Specifications Change No. TS-431 - Request for Extended Power Uprate Operation
Project stage: Request
ML0505603372005-02-23023 February 2005
(BFN) - Response to Nrc'S Acceptance Review Letter and Request for Additional Information Related to Technical Specifications Change No. TS-418 - Request for Extended Power Uprate Operation (Tac Nos MC3743 and MC3744)
Project stage: Request
ML0607202932005-02-28028 February 2005
Hydrothermal Modeling of Browns Ferry Nuclear Plant with Units 1, 2, and 3 at Extended Power Uprate
Project stage: Other
ML0606805962005-02-28028 February 2005
Hydrothermal Modeling of Browns Ferry with Units 1, 2, and 3 at Extended Power Uprate
Project stage: Other
ML0511501912005-04-19019 April 2005
Enclosure 3, Ltr, Licensing Action Status and Interdependencies
Project stage: Other
ML0511702442005-04-25025 April 2005
(BFN) - Unit 1 - Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS-431 - Request for Extended Power Uprate Operation
Project stage: Request
ML0511702422005-04-25025 April 2005
(BFN) - Units 2, and 3 - Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS-418 - Request for Extended Power Uprate Operation
Project stage: Request
ML0514300362005-05-20020 May 2005
Response to Nrc'S Letter on Licensing Action Status and Interdependencies,
Project stage: Other
ML0513201462005-05-27027 May 2005
EPU Acceptance Review Results to Increase Maximum Authorized Power Level (TAC No. MC3743, MC3744) (TS-418)
Project stage: Acceptance Review
ML0515802492005-06-0606 June 2005
Response to Nrc'S Request for Additional Information Related to Technical Specifications (TS) Change No. TS - 431 - Request for License Amendment Extended Power Uprate (EPU) Operation
Project stage: Request
ML0516403912005-06-0606 June 2005
Response to Technical Specifications (TS) Change No. TS-418 - Request for License Amendment - Extended Power Uprate (EPU) Operation
Project stage: Request
ML0517902372005-06-24024 June 2005
Part 21 Notification - Critical Power Determination for G314 and GE12 Fuel with Zircaloy Spacers, 06/24/2005
Project stage: Request
ML0513201482005-06-29029 June 2005
Ltr., Ind FRN Facility Operating License for EPU and Opportunity for a Hearing
Project stage: Other
ML0515703812005-06-29029 June 2005
Fanp, Withholding Information from Public (TACs MC3743, MC3744)
Project stage: Other
ML0516606022005-06-29029 June 2005
Ltr., Withholding Public Disclosure for GE Company (TACs MC3743, MC3744)
Project stage: Other
ML0511600362005-07-0101 July 2005
Notice of Consideration of Issuance of Amendment and Notice of Opportunity for a Hearing Regarding Extended Power Uprate (Tac No. MC3743, MC3744)
Project stage: Other
ML0518703902005-07-0707 July 2005
06/08/05, Meeting Summary with TVA and Framatome Regarding Fuel Analysis Methodology, Enclosure 2, Framatome Presentation
Project stage: Meeting
ML0520706042005-07-26026 July 2005
Notice of Meeting with Tennessee Valley Authority (TVA) BFN Units 1, 2, and 3, and Sequoyah Units 1 and 2 on Resolution of Instrument Setpoint Concerns
Project stage: Meeting
ML0524204912005-08-23023 August 2005
Ltr., GE Request for Withholding Information from Public on Steam Dryer Analysis for EPU Conditions
Project stage: Withholding Request Acceptance
ML0522901442005-09-0202 September 2005
Summary of Meeting with the Tennessee Valley Authority Regarding Plant-Specific Resolution of Instrument Setpoint Concerns
Project stage: Meeting
ML0522903972005-09-0202 September 2005
TVA Handout Method 3 Issue BFN Proposed Resolution
Project stage: Other
ML0524303412005-10-0303 October 2005
RAI, Extended Power Uprate (TS-431) (Tac No. MC3812)
Project stage: RAI
ML0525104462005-10-0303 October 2005
Request for Additional Information Regarding Extended Power Uprate
Project stage: RAI
ML0535601862005-12-19019 December 2005
Response to NRC Round 2 Request for Additional Information Related to Technical Specifications Change No. TS-418-Request for Extended Power Uprate Operation
Project stage: Request
ML0535601942005-12-19019 December 2005
Response to NRC Round 2 Requests for Additional Information Related to Technical Specifications Change No. TS-431 - Request for Extended Power Uprate Operation
Project stage: Request
ML0535601202005-12-22022 December 2005
Request for Additional Information, Information Concerning Extended Power Uprate
Project stage: RAI
ML0535601772005-12-22022 December 2005
Request for Additional Information, Concerning Extended Power Uprate
Project stage: RAI
ML0535703412006-01-19019 January 2006
Revised Schedule for Response to Extended Power Uprate Requests for Additional Information
Project stage: RAI
ML0614502612006-02-0101 February 2006
Response to NRC Request EMEB-B.6 from NRC Round 2 Requests for Additional Information Related to Technical Specification (TS) Change No. TS-431- Request for Extended Power Uprate.
Project stage: Request
ML0603207332006-02-0101 February 2006
Response to NRC Request EMEB-B.7 from NRC Round 2 Requests for Additional Information Related to Technical Specification (TS) Change No. TS-418 - Request for Extended Power Uprate
Project stage: Request
ML0603901352006-02-0808 February 2006
Forthcoming Meeting with Tennessee Valley Authority, to Discuss Various Topics Regarding Tva'S Extended Power Uprate Amendment Request for the Browns Ferry Nuclear Plant, Units 1 and 2 and 3
Project stage: Meeting
ML0607202812006-02-28028 February 2006
NEDO-33173, Applicability of GE Methods to Expanded Operating Domains.
Project stage: Other
ML0606203072006-02-28028 February 2006
Technical Specifications Change TS-418 - Response to Request for Additional Information SPSB-A.11 Regarding Extended Power Uprate - Credit for Net Positive Suction Head
Project stage: Response to RAI
2005-02-28
[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
September 1, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 9 (TS-431)
(TAC NO. MC3812)
Dear Mr. Singer:
By letter dated June 28, 2004, as supplemented by letters dated August 23, 2004, February 23, April 25, June 6, and December 19, 2005, February 1 and 28, March 7, 9, 23, and 31, April 13, May 5 and 11, June 12, 15, 23 and 27, and July 6, 21, 24, 26, and 31, and August 4 16, and 18, 2006, Tennessee Valley Authority (TVA, the licensee) submitted an amendment request for Browns Ferry Nuclear Plant, Unit 1. The proposed amendment would change the Unit 1 operating license to increase the maximum authorized power level from 3293 to 3952 megawatts thermal. This change represents an increase of approximately 20 percent above the current maximum authorized power level for Unit 1. The proposed amendment would also change the Unit 1 licensing bases and associated Technical Specifications to credit 3 pounds per square inch gauge (psig) for containment accident pressure following a loss-of-coolant accident and increase the reactor steam dome pressure by 30 psig.
A response to the enclosed Request for Additional Information is needed before the Nuclear Regulatory Commission staff can complete the review. These requests were provided in draft from to your staff by e-mail and discussed on August 8-11, 2006. In discussions with your staff it was agreed that a response would be provided by September 15, 2006.
If you have any questions, please contact me at (301) 415-4041.
Sincerely,
/RA by EBrown for/
Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML062350360 NRR-106 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA DSS/SBWB NAME EBrown EBrown for BClayton JWermeil by memo MChernoff DATE 9/ 01 /06 09/01/06 09/01/06 8/16/06 OFFICE APLA/BC DSS/ACVB LPL2-2/BC NAME MRubin by memo TMartin by memo LRaghavan DATE 8/31/06 8/22/06 09/01/06
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 9 (TS-431)
(TAC NO. MC3812)
Dated: September 1, 2006 DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrLACGoldstein RidsNrrPMMChernoff RidsNrrPMEBrown RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn2MailCenter RidsNrrDorl (CHolden)
RidsNrrDorlDpr TAlexion GCranston GThomas THuang ZAbdullahi RLobel MStutzke SLaur RDennig RGoel
REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 APLA
- 25. In various correspondence the NRC staff has noted different values for the suppression pool (SP) bulk temperature limit:
- a. Section 4.8.6.2, Page 4.8-4 of the updated final safety analyses report (UFSAR) states a limit of 177 degrees Fahrenheit (EF), based on an analysis of the torus attached piping.
- b. The limit of 177 EF was used in the previous 5 percent power uprate for Units 2 and 3 (ADAMS Accession No. ML042670045).
- c. The draft Unit 1 Fire Protection Program Report (ADAMS Accession No. ML060620424) provides various limits as follows:
- i. Page 301- The design limit is 281 EF.
ii. Page 309 - The residual heat removal (RHR) pump seals were rated for 160 EF, but have been re-evaluated for 215 EF.
- d. Table 4-1 of Enclosure 4 of the submittals dated June 28 and 25, 2004, uses the 281 EF limit. Provide the correct SP bulk temperature limit for evaluating the proposed containment accident pressure (CAP) credit.
- 26. Analysis (e.g., the August 4, 2006, submittal) indicates that containment accident pressure (CAP) credit is required to ensure adequate net positive suction head (NPSH) to the RHR pumps during an Appendix R scenario. The NRC staff understands that CAP credit is required for the pre-EPU [extended power uprate] plant as well as for the post-EPU plant. The Fire Protection Program Report defines the Appendix R scenario as a fire that results in a total loss of high-pressure makeup sources (feedwater (FW),
high pressure coolant injection, and reactor core isolation cooling), followed by manual depressurization using three S/RVs and operation of one RHR pump and its associated heat exchanger in low pressure coolant injection (LPCI) mode (i.e., no suppression pool cooling(SPC)).
For transient initiating events (e.g., loss of FW), the probabilistic risk assessment (PRA) credits manual depressurization using the S/RVs and use of either core spray (CS) or LPCI, along with SPC, upon the failure of all high-pressure makeup sources. The PRA also includes sequences initiated by transient events that lead to multiple stuck-open S/RVs (e.g., loss of FW and subsequent MSIV closure, which causes the S/RVs to Enclosure
open, followed by subsequent failure of the S/RVs to reclose). The previous risk evaluation of the proposed CAP credit does not address these types of accident sequences.
Provide a risk evaluation of the proposed CAP credit that includes the increase in core-damage frequency and, large early release frequency due to sequences that are initiated by transient events that lead to either (a) manual depressurization via the S/RVs and use of CS or LPCI upon the total loss of high-pressure makeup sources, and (b) sequences that are initiated by transient events that lead to multiple stuck-open S/RVs.
ACVB
- 62. The August 4, 2006, response to Request for Additional Information (RAI) Risk Assessment Containment & Ventilation Branch (ACVB) 37/35 states that, for the CS pump, the operator is instructed to maintain flow less than 4000 gallons per minute (gpm) and within the NPSH limit curves. However, for determining adequate NPSH, it is assumed that the operator would reduce flow in response to the NPSH limit curves, but not less than 3125 gpm.
It appears that at a flow rate of 4000 gpm and the peak calculated suppression pool temperature, the pumps are in the acceptable region of the Emergency Operating Instruction NPSH limit curves. Therefore, explain what prompts the operator to reduce flow to 3125 gpm. If the operator can operate acceptably at 4000 gpm, address why shouldnt this more conservative flow rate be used in the NPSH analyses.
- 63. In the July 21, 2006, response to RAI Probabilistic Risk Assessment Licensing Branch A (APLA) 24/26, five fire areas are described. For those fire areas for which the safety analysis depends on RHR pumps (control room and turbine building), 2 RHR pumps are said to be available. Address why only one RHR pump is credited for the Appendix R analyses and NPSH analyses.
- 64. Enclosure 4 of the August 4, 2006, letter contains Calculation MDQ099920060011, Transient NPSH/ Containment Pressure Evaluation of RHR and CS Pumps. For the short term loss-of-coolant accident response, Figure 7.5 of Calculation MDQ099920060011 shows that the wetwell pressure required is less than the wetwell pressure available for the RHR pumps pumping into the broken recirculation loop.
TVA indicated this was acceptable based on RHR pump tests reported in Enclosure 2 to a May 21, 1976 TVA letter to the NRC. A margin of 9 feet was shown to be available in these tests relative to the required NPSH based on a 3 percent head drop.
(i) Provide the margin between the lowest NPSH value of the cavitation tests reported in the May 21, 1976 letter and the reduced required NPSH values used in Tennessee Valley Authority (TVA) Calculation MDQ099920060011.
(ii) Discuss the difference between the required NPSH and the available NPSH at 600 seconds.
(iii) Describe how the required NPSH value of 28.4 ft in Figure 7.5 of Calculation
MDQ099920060011 was obtained.
- 65. Table 10-2 of Enclosure 4 to the June 28, 2004, submittal, NEDC-33101P, DRF 0000-0010-9439, Browns Ferry Unit 1 Safety Analysis Report for Extended Power Uprate (PUSAR), shows that the peak drywell air temperature due to a steam line break (336 °F) exceeds the containment shell design temperature limit (281 °F). Verify that the shell temperature itself remains below the 281 °F design limit.
- 66. Provide the maximum RHR and core spray pump seal temperatures. If less than the calculated peak suppression pool temperatures, address why this is acceptable.
- 67. Provide the maximum acceptable temperature of the piping attached to the torus. If less than the maximum suppression pool water temperature, address why is this acceptable.
SBWB
- 49. Provide the head flow curves used in the limiting large break loss-of-coolant accident analyses (battery failure case). The curves should include the head flow curve for one low pressure core spray and one low pressure coolant injection pump discharging into each recirculation line. Also, provide the limiting axial power shape used in this limiting break.
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW.
Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Mr. Glenn W. Morris, Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Robert J. Beecken, Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, Manager 10833 Shaw Road Nuclear Assurance and Licensing Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609
