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| {{#Wiki_filter:July 05, 2007Mr. William R. CampbellChief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | | {{#Wiki_filter:July 05, 2007 Mr. William R. Campbell 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, UNITS 1, 2 AND 3 - REQUEST FORADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 13 (TS-431-S AND TS-418) (TAC NOS. MD5262, MD5263, AND MD5264) | | BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 13 (TS-431-S AND TS-418) (TAC NOS. MD5262, MD5263, AND MD5264) |
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| ==Dear Mr. Campbell:== | | ==Dear Mr. Campbell:== |
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| By letters dated June 28 and 25, 2004, the Tennessee Valley Authority (TVA, the licensee)submitted amendment requests for Browns Ferry Nuclear Plant (BFN), Units 1, 2 and 3, 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, July 6, 21, 24, 26, and 31, December 1, 5, 11 and 21, 2006, January 31, February 16, and 26, and April 6, 18 and 24, 2007. The proposed amendments would change the BFN operating licenses for Units 1, 2 and 3 toincrease the maximum authorized power level by approximately 15 percent. In a letter dated November 7, 2006, TVA reported changes in the modeling used to determine compliance with emergency core cooling system requirements. The enclosed Request for Additional Information is related to this submittal.A response to the enclosed Request for Additional Information is needed before the NuclearRegulatory Commission staff can complete the review. This request was discussed with Mr. David Langley of your staff on June 4, 2007, and it was agreed that TVA would respond within 30 days of issuance of this letter.If you have any questions, please contact me at (301) 415-2315.Sincerely,/RA/Eva A. Brown, Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-259, 50-260 and 50-296 | | By letters dated June 28 and 25, 2004, the Tennessee Valley Authority (TVA, the licensee) submitted amendment requests for Browns Ferry Nuclear Plant (BFN), Units 1, 2 and 3, 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, July 6, 21, 24, 26, and 31, December 1, 5, 11 and 21, 2006, January 31, February 16, and 26, and April 6, 18 and 24, 2007. |
| | The proposed amendments would change the BFN operating licenses for Units 1, 2 and 3 to increase the maximum authorized power level by approximately 15 percent. In a letter dated November 7, 2006, TVA reported changes in the modeling used to determine compliance with emergency core cooling system requirements. The enclosed Request for Additional Information is related to this submittal. |
| | A response to the enclosed Request for Additional Information is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. David Langley of your staff on June 4, 2007, and it was agreed that TVA would respond within 30 days of issuance of this letter. |
| | If you have any questions, please contact me at (301) 415-2315. |
| | Sincerely, |
| | /RA/ |
| | Eva A. Brown, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260 and 50-296 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/enclosure: See next page | | Request for Additional Information cc w/enclosure: See next page |
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| ML071780190 NRR-088 OFFICELPL2-2/PMLPL2-2/LADSS/SBWB/BCDRA/APLA/BCLPL2-2/BC NAMEEBrownBClaytonGCranston MRubinTBoyce DATE07 / 05 /0707 / 02 /0707 / 05 /07 06 / 29 /07 07/ 05 /07 Letter to William R. Campbell, Jr. from Eva A. Brown dated July 5, 2007 | | ML071780190 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA DSS/SBWB/BC DRA/APLA/BC LPL2-2/BC NAME EBrown BClayton GCranston MRubin TBoyce DATE 07 / 05 /07 07 / 02 /07 07 / 05 /07 06 / 29 /07 07/ 05 /07 |
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| | Letter to William R. Campbell, Jr. from Eva A. Brown dated July 5, 2007 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FORADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 13 (TS-431-S AND TS-418) (TAC NOS. MD5262, MD5263 AND MD5264) DISTRIBUTION: | | BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 13 (TS-431-S AND TS-418) (TAC NOS. MD5262, MD5263 AND MD5264) |
| | DISTRIBUTION: |
| PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown RidsNrrLABClayton (Hard Copy) | | PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown RidsNrrLABClayton (Hard Copy) |
| RidsNrrDorlDpr RidsNrrDssSbwb (GCranston) | | RidsNrrDorlDpr RidsNrrDssSbwb (GCranston) |
| RidsNrrDraApla (MRubin) | | RidsNrrDraApla (MRubin) |
| RidsNrrPMTAlexion RidsAcrsAcnwMailCenter RidsOgcRp THuang MRazzaque TNakanishi LWard MLobel MStutzke EnclosureREQUEST FOR ADDITIONAL INFORMATIONEXTENDED POWER UPRATETENNESSEE VALLEY AUTHORITYBROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3DOCKET NOS. 50-259 , 50-260 AND 50-296 APLA28./30.Confirm that the following success criteria were used to estimate the risk relatedto the containment overpressure (COP) credit:InitiatorInjectionNPSHLarge Break Lossof coolant Accident (LLOCA)1 core spray (CS)pump or1 Low PressureCore Injection (LPCI) pump3 or 4 residual heat removal (RHR) pumps/heatexchanges (H/Xs) aligned to spent fuel pool cooling (SPC) or2 RHR pumps/HXs aligned to SPC and favorableplant conditions (initial SP volume at 123,500 ft 3 ,river water temperature at 85 degrees F, torus water temperature less than or equal to 86 degrees F) or2 pumps/HXs aligned to SPC and containmentintegrity (COP credit)Note: 1 pump/HX aligned to SPC andcontainment integrity (COP credit) will not provideadequate NPSH to the low pressure emergency core cooling system (ECCS) pumps during LLOCAsAnticipatedTransient Without Scram (ATWS) | | RidsNrrPMTAlexion RidsAcrsAcnwMailCenter RidsOgcRp THuang MRazzaque TNakanishi LWard MLobel MStutzke |
| | |
| orStation Blackout (SBO) (upon AC power recovery after 4 hours)1 CS pump or1 LPCI pumpcontainment integrity (COP credit)Note: Does not depend on the number of RHRpumps/HXs aligned to SPC Other transients1 CS pump or1 LPCI pump2 or more RHR pumps/HXs aligned to SPC or1 pump/HX aligned to SPC and containmentintegrity (COP credit)29./31.Describe any interlocks or procedural prohibitions that preclude the simultaneousopening of the LPCI valves, SPC valves, and/or drywell spray valves in the same RHR subsystem. 30./32.The licensee has made a commitment to terminate drywell cooling within two ofentry into the Appendix R fire safe shutdown operating procedures. Address how this commitment was considered during development of the probabilistic risk
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| assessment (PRA) success criteria.31./33.The SPC mode is manually aligned by the operator. Describe how the operatordecides the number of RHR pumps/HXs to align to SPC. Address whether it is credible (e.g., within procedural guidance) that the operator would actually align three or four RHR pumps/HXs to SPC.32./34.Determine if there is a significant statistical correlation between the suppressionpool water level, river water temperature, and/or torus water temperature. 33./35.Discuss whether it is possible to eliminate or substantially reduce the need forthe COP credit by maximizing the suppression pool water level, minimizing the initial torus water temperature and/or reducing the amount of power uprate.34./36.Provide the approximate high confidence of low probability of failure (HCLPF) ofthe Browns Ferry containment structure (including considerations of personnel access or equipment hatches, penetrations, etc.). 35./37.Discuss whether the fire risk evaluation contained in the IPEEE addressesspurious actuations (hot shorts) of the containment isolation valves or the need for the COP credit. If not, address the change in risk considering COP and submit a summary of the updated results.36./37.Discuss when and how the peer review for the Unit 1 PRA was conducted(identify the participants, describe what methods were used, etc.), and submit the peer review report. Indicate which comments may significantly affect the PRA results, insights, and conclusions concerning the proposed EPU. Also, discuss the plans and timetable to resolve comments and revise the PRA model. 37./38.Explain how COP credit maintains the defense-in-depth concept providedSection 2.2.1.1 of Regulatory guide 1.174. Specifically address each of the seven bulleted items with particular emphasis on the fifth item (independence of barriers is not degraded). SBWB(Unit 1 Only)67.Discuss whether the 3-D MONICORE core monitoring system is based onTGBLA06/PANAC11 methods.68.The 50 megawatt thermal/million pounds mass/hour (MWt/Mlbm/hr) limit establishes thegeneric envelope for General Electric neutronic methods nodal, bundle and axial power distribution uncertainties. Discuss whether the core thermal power to core flow ratio for the Unit 1 extended power uprate will remain below 50 MWt/Mlbm/hr at any statepoint in the allowed operating domain limit. 69.Discuss whether the plant specific R-factor calculation at a bundle level was performedconsistent with lattice axial void conditions expected for the hot channel operating state. 70.The presence of bypass voiding at the low-flow conditions where instabilities are likelycan result in calibration errors. Discuss whether these calibration errors were accounted for when determining the setpoints for the detect and suppress long term methodology.(Units 2 and 3 Only) 82.Provide the reference and/or description of the models governing counter-current flow(CCFL) at the exit to the hot bundle/core. Also identify the reference that describes the validation (separate effects and integral test data comparisons) of the CCFL limit model governing top down cooling in rod bundles. 83.Provide the vapor and liquid hot bundle exit velocities versus time for the 0.05 ft 2 breakspresented in the April 18, 2007, SBWB-64 Supplement response.84.Provide the axial power shapes used in the calculations provided in the April 18, 2007,request for additional information response.
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| William R. Campbell, Jr.BROWNS FERRY NUCLEAR PLANTTennessee Valley Authority cc:Mr. Ashok S. Bhatnagar
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| Senior Vice President Nuclear Generation Development and Construction Tennessee Valley Authority
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| 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Preston D. Swafford Senior Vice President Nuclear Support Tennessee Valley Authority
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| 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Walter M. Justice II Interim Vice President Nuclear Engineering & Technical Services Tennessee Valley Authority
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| 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 35609General CounselTennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902Mr. John C. Fornicola, General ManagerNuclear Assurance Tennessee Valley Authority
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| 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 2000Decatur, AL 35609Mr. Robert G. Jones, General Manager Browns 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.
| | REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 DOCKET NOS. 50-259 , 50-260 AND 50-296 APLA 28./30. Confirm that the following success criteria were used to estimate the risk related to the containment overpressure (COP) credit: |
| Suite 23T85 Atlanta, GA 30303-8931 Ms. Beth A. Wetzel, ManagerCorporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. William D. Crouch, ManagerLicensing 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
| | Initiator Injection NPSH Large Break Loss 1 core spray (CS) 3 or 4 residual heat removal (RHR) pumps/heat of coolant pump exchanges (H/Xs) aligned to spent fuel pool Accident (LLOCA) cooling (SPC) or or 1 Low Pressure Core Injection 2 RHR pumps/HXs aligned to SPC and favorable (LPCI) pump plant conditions (initial SP volume at 123,500 ft3, river water temperature at 85 degrees F, torus water temperature less than or equal to 86 degrees F) or 2 pumps/HXs aligned to SPC and containment integrity (COP credit) |
| | Note: 1 pump/HX aligned to SPC and containment integrity (COP credit) will not provide adequate NPSH to the low pressure emergency core cooling system (ECCS) pumps during LLOCAs Anticipated 1 CS pump containment integrity (COP credit) |
| | Transient Without Scram (ATWS) or Note: Does not depend on the number of RHR or pumps/HXs aligned to SPC Station Blackout 1 LPCI pump (SBO) (upon AC power recovery after 4 hours) |
| | Enclosure |
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| Athens, AL 35611-6970State Health OfficerAlabama Dept. of Public Health RSA Tower - Administration
| | Other transients 1 CS pump 2 or more RHR pumps/HXs aligned to SPC or or 1 LPCI pump 1 pump/HX aligned to SPC and containment integrity (COP credit) 29./31. Describe any interlocks or procedural prohibitions that preclude the simultaneous opening of the LPCI valves, SPC valves, and/or drywell spray valves in the same RHR subsystem. |
| | 30./32. The licensee has made a commitment to terminate drywell cooling within two of entry into the Appendix R fire safe shutdown operating procedures. Address how this commitment was considered during development of the probabilistic risk assessment (PRA) success criteria. |
| | 31./33. The SPC mode is manually aligned by the operator. Describe how the operator decides the number of RHR pumps/HXs to align to SPC. Address whether it is credible (e.g., within procedural guidance) that the operator would actually align three or four RHR pumps/HXs to SPC. |
| | 32./34. Determine if there is a significant statistical correlation between the suppression pool water level, river water temperature, and/or torus water temperature. |
| | 33./35. Discuss whether it is possible to eliminate or substantially reduce the need for the COP credit by maximizing the suppression pool water level, minimizing the initial torus water temperature and/or reducing the amount of power uprate. |
| | 34./36. Provide the approximate high confidence of low probability of failure (HCLPF) of the Browns Ferry containment structure (including considerations of personnel access or equipment hatches, penetrations, etc.). |
| | 35./37. Discuss whether the fire risk evaluation contained in the IPEEE addresses spurious actuations (hot shorts) of the containment isolation valves or the need for the COP credit. If not, address the change in risk considering COP and submit a summary of the updated results. |
| | 36./37. Discuss when and how the peer review for the Unit 1 PRA was conducted (identify the participants, describe what methods were used, etc.), and submit the peer review report. Indicate which comments may significantly affect the PRA results, insights, and conclusions concerning the proposed EPU. Also, discuss the plans and timetable to resolve comments and revise the PRA model. |
| | 37./38. Explain how COP credit maintains the defense-in-depth concept provided Section 2.2.1.1 of Regulatory guide 1.174. Specifically address each of the seven bulleted items with particular emphasis on the fifth item (independence of barriers is not degraded). |
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| Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017ChairmanLimestone County Commission 310 West Washington Street
| | SBWB (Unit 1 Only) |
| | : 67. Discuss whether the 3-D MONICORE core monitoring system is based on TGBLA06/PANAC11 methods. |
| | : 68. The 50 megawatt thermal/million pounds mass/hour (MWt/Mlbm/hr) limit establishes the generic envelope for General Electric neutronic methods nodal, bundle and axial power distribution uncertainties. Discuss whether the core thermal power to core flow ratio for the Unit 1 extended power uprate will remain below 50 MWt/Mlbm/hr at any statepoint in the allowed operating domain limit. |
| | : 69. Discuss whether the plant specific R-factor calculation at a bundle level was performed consistent with lattice axial void conditions expected for the hot channel operating state. |
| | : 70. The presence of bypass voiding at the low-flow conditions where instabilities are likely can result in calibration errors. Discuss whether these calibration errors were accounted for when determining the setpoints for the detect and suppress long term methodology. |
| | (Units 2 and 3 Only) |
| | : 82. Provide the reference and/or description of the models governing counter-current flow (CCFL) at the exit to the hot bundle/core. Also identify the reference that describes the validation (separate effects and integral test data comparisons) of the CCFL limit model governing top down cooling in rod bundles. |
| | : 83. Provide the vapor and liquid hot bundle exit velocities versus time for the 0.05 ft2 breaks presented in the April 18, 2007, SBWB-64 Supplement response. |
| | : 84. Provide the axial power shapes used in the calculations provided in the April 18, 2007, request for additional information response. |
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| Athens, AL 35611Mr. Robert H. Bryan, Jr., General ManagerLicensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801}} | | William R. Campbell, Jr. BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc: |
| | Mr. Ashok S. Bhatnagar Decatur, AL 35609 Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Generation Development Browns Ferry Site Operations and Construction Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Decatur, AL 35609 Chattanooga, TN 37402-2801 Mr. Larry S. Mellen Mr. Preston D. Swafford Browns Ferry Unit 1 Project Engineer Senior Vice President Division of Reactor Projects, Branch 6 Nuclear Support U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW. |
| | 6A Lookout Place Suite 23T85 1101 Market Street Atlanta, GA 30303-8931 Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Mr. Walter M. Justice II Corporate Nuclear Licensing Interim Vice President and Industry Affairs Nuclear Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority 4X Blue Ridge 6A Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. William D. Crouch, Manager Brian OGrady, Site Vice President Licensing and Industry Affairs Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 P.O. Box 2000 Decatur, AL 35609 Decatur, AL 35609 General Counsel Senior Resident Inspector Tennessee Valley Authority U.S. Nuclear Regulatory Commission ET 11A Browns Ferry Nuclear Plant 400 West Summit Hill Drive 10833 Shaw Road Knoxville, TN 37902 Athens, AL 35611-6970 Mr. John C. Fornicola, General Manager State Health Officer Nuclear Assurance Alabama Dept. of Public Health Tennessee Valley Authority RSA Tower - Administration 6A Lookout Place Suite 1552 1101 Market Street P.O. Box 303017 Chattanooga, TN 37402-2801 Montgomery, AL 36130-3017 Mr. Bruce Aukland, Plant Manager Chairman Browns Ferry Nuclear Plant Limestone County Commission Tennessee Valley Authority 310 West Washington Street P.O. Box 2000 Athens, AL 35611 Decatur, AL 35609 Mr. Robert H. Bryan, Jr., General Manager Mr. Masoud Bajestani, Vice President Licensing and Industry Affairs Browns Ferry Unit 1 Restart Tennessee Valley Authority Browns Ferry Nuclear Plant 4X Blue Ridge Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801}} |
Letter Sequence RAI |
|---|
|
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, Request, Request
- Acceptance...
- 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, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML070370281, ML073100027, ML073510180, ML080360067, ML080430700, ML080500171, ML080530256, ML081010450, ML081010451, ML081120502, ML081700294, ML081720078, ML081760295, ML082040065, ML082050462, ML082100425, ML082810470, ML083120308, ML083240224, ML083250083, ML090130718, ML090340528, ML090720951, ML090760630, ML091320366, ML092020345, ML092430520, ML092440518, ML092460495, ML092460496, ML092460497, ML092460498, ML092460500, ML092540483, ML092680057, ML12319A076, ML13044A498
|
MONTHYEARML0711503712007-04-24024 April 2007
Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Evaluations
Project stage: Request
ML0712905652007-05-16016 May 2007
Withholding Information from Public Disclosure, Response to Nuclear Regulatory Commission (NRC) Request for Additional Information - Round 12 for Browns Ferry EPU: Supplemental to SBWB-64
Project stage: RAI
ML0716303492007-06-15015 June 2007
Meeting with the Tennessee Valley Authority Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2 and 3, Steam Dryer Review
Project stage: Meeting
ML0718700242007-07-0303 July 2007
Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 - Supplement 1
Project stage: Request
ML0717801902007-07-0505 July 2007
Request for Additional Information for Extended Power Uprate - Round 13 (TS-431 and TS-418 (TAC Nos. MD5262, MD5263, and MD5264)
Project stage: RAI
ML0719004762007-07-10010 July 2007
Meeting with the Tennessee Valley Authority (TVA) Concerning the Pending ACRS Meeting on the Browns Ferry Extended Power Uprate
Project stage: Meeting
ML0721501562007-07-18018 July 2007
Slides from Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation
Project stage: Meeting
ML0721303712007-07-27027 July 2007
Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations
Project stage: Request
ML0721400442007-08-0808 August 2007
Summary of Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation
Project stage: Meeting
ML0724805472007-08-31031 August 2007
Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure
Project stage: Request
ML0727606602007-10-0909 October 2007
Request for Additional Information for Extended Power Uprate - Round 14 (TS-418)
Project stage: RAI
ML0728902372007-10-18018 October 2007
Request for Withholding Information from Public Disclosure Concerning Round 13 Request for Additional Information for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263 and MD5264)
Project stage: RAI
ML0729603112007-10-22022 October 2007
Technical Specification (TS) Changes TS-431 & TS-418, Extended Power Uprate - EPU Large Transient Testing
Project stage: Request
ML0731000272007-11-0909 November 2007
Request for Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418-S)
Project stage: Other
ML0732303482007-11-15015 November 2007
Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure APLA-35/37
Project stage: Request
ML0733304832007-11-21021 November 2007
Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Preliminary Findings on Steam Dryer Stress Analysis
Project stage: Request
ML0735101802007-12-14014 December 2007
Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Schedule Regarding Analysis for Steam Dryers
Project stage: Other
ML0734607572007-12-19019 December 2007
Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac No. MD5262, MD5263 and MD5264)
Project stage: Withholding Request Acceptance
ML0735400102008-01-25025 January 2008
Summary of Meeting with Tennessee Valley Authority on Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264), Browns Ferry Units 1, 2, and 3
Project stage: Meeting
ML0801504182008-01-25025 January 2008
Plants, Units 1, 2, and 3 - (Public Version) - Summary of December 10, 2007 Meeting with TVA on Steam Dryer Portion of the Extended Power Uprate Review
Project stage: Meeting
ML0803205212008-01-25025 January 2008
Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) Response to Round 15 Request for Additional Information (RAI) - APLA-38/40, SRXB-71, and SRXB-72
Project stage: Request
ML0803600672008-01-25025 January 2008
Steam Dryer RAI 15 Status, Slides
Project stage: Other
ML0802501652008-01-30030 January 2008
Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263, and MD5264)
Project stage: Withholding Request Acceptance
ML0803805602008-01-31031 January 2008
Technical Specifications (TS) Change TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 Request for Additional Information (RAI) Regarding Steam Dryer Analyses
Project stage: Request
ML0804307002008-02-11011 February 2008
Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Schedule Regarding EPU
Project stage: Other
ML0803503812008-02-14014 February 2008
Summary of Meeting with Tennessee Valley Authority - on Extended Power Uprate Review
Project stage: Meeting
ML0805302562008-02-21021 February 2008
Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments
Project stage: Other
ML0806501012008-02-21021 February 2008
Response to Round 16 Request for Additional Information SRXB-73
Project stage: Request
ML0804506472008-02-27027 February 2008
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML0803506982008-02-29029 February 2008
Request for Additional Information for Extended Power Uprate - Round 16 (TS-431 and TS-418) (TACs MD5262, MD5263, MD5264)
Project stage: RAI
ML0807104982008-03-0606 March 2008
(BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90
Project stage: Request
ML0811205102008-03-20020 March 2008
Summary of March 20, 2008, Meeting with Tennessee Valley Authority Regarding Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264) - Slides
Project stage: Meeting
ML0810104512008-04-0404 April 2008
Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) BFN Steam Monitoring Plan
Project stage: Other
ML0810104502008-04-0404 April 2008
(BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 and Round 16 Requests for Additional Information (RAI) Regarding Steam Dryer Analyses
Project stage: Other
ML0817602952008-04-0909 April 2008
Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Confirmation of Commitment Completions
Project stage: Other
ML0811205022008-04-16016 April 2008
CDI Incoming Letter Dated April 16, 2008 Regarding NRC Presentation Entitled, Tennessee Valley Authority Browns Ferry Nuclear Plant - Extended Power Uprate Steam Dryers.
Project stage: Other
ML0811302312008-04-17017 April 2008
Public Slides - Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review,
Project stage: Meeting
ML0811200332008-04-30030 April 2008
Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Withholding Information from Public Disclosure for Round 15 Fuels Responses
Project stage: Withholding Request Acceptance
ML0812806272008-05-0101 May 2008
Technical Specifications Change TS-418, Extended Power Uprate Supplemental Response to Round 16 Request for Additional Information - SRXB-87 & SRXB-89
Project stage: Supplement
ML0813502222008-05-0202 May 2008
Request for Additional Information for Extended Power Uprate - Round 17 (TS-431 and TS-410)
Project stage: RAI
ML0805001712008-05-0202 May 2008
- Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418)
Project stage: Other
ML0812804712008-05-0202 May 2008
Request for Additional Information for Extended Power Uprate - Round 17
Project stage: RAI
ML0813602912008-05-22022 May 2008
Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review
Project stage: Meeting
ML0815805532008-05-22022 May 2008
Summary of 5/22/08 Meeting Regarding Containment Overpressure Portion of the Extended Power Uprate Review - Browns Ferry - Handouts
Project stage: Meeting
ML0810604452008-06-0202 June 2008
Request for Withholding Information from Public Disclosure for Partial Round 13 Responses (Tacs. MD5262, MD5263 and MD5264)
Project stage: Withholding Request Acceptance
ML0810606162008-06-0202 June 2008
Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant
Project stage: Withholding Request Acceptance
ML0810607222008-06-0202 June 2008
Request for Withholding Information from Public Disclosure for Partial Response to Round 13
Project stage: Withholding Request Acceptance
ML0816403252008-06-0303 June 2008
Units 2 & 3 - Technical Specifications Change TS-418 - Extended Power Uprate - Supplemental Response to Round 16 Request for Additional Information - SRXB-88
Project stage: Supplement
ML0812607122008-06-0505 June 2008
Summary of Meeting with TVA Steam Dryer Portion of the Extended Power Uprate Review
Project stage: Meeting
ML0817002942008-06-12012 June 2008
Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to ACRS Conclusions and Recommendations Regarding Containment Overpressure Credit
Project stage: Other
2008-01-30
[Table View] |
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Category:Letter
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[Table view] |
Text
July 05, 2007 Mr. William R. Campbell 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, UNITS 1, 2 AND 3 - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 13 (TS-431-S AND TS-418) (TAC NOS. MD5262, MD5263, AND MD5264)
Dear Mr. Campbell:
By letters dated June 28 and 25, 2004, the Tennessee Valley Authority (TVA, the licensee) submitted amendment requests for Browns Ferry Nuclear Plant (BFN), Units 1, 2 and 3, 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, July 6, 21, 24, 26, and 31, December 1, 5, 11 and 21, 2006, January 31, February 16, and 26, and April 6, 18 and 24, 2007.
The proposed amendments would change the BFN operating licenses for Units 1, 2 and 3 to increase the maximum authorized power level by approximately 15 percent. In a letter dated November 7, 2006, TVA reported changes in the modeling used to determine compliance with emergency core cooling system requirements. The enclosed Request for Additional Information is related to this submittal.
A response to the enclosed Request for Additional Information is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. David Langley of your staff on June 4, 2007, and it was agreed that TVA would respond within 30 days of issuance of this letter.
If you have any questions, please contact me at (301) 415-2315.
Sincerely,
/RA/
Eva A. Brown, Project Manager Plant Licensing Branch II-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: See next page
ML071780190 NRR-088 OFFICE LPL2-2/PM LPL2-2/LA DSS/SBWB/BC DRA/APLA/BC LPL2-2/BC NAME EBrown BClayton GCranston MRubin TBoyce DATE 07 / 05 /07 07 / 02 /07 07 / 05 /07 06 / 29 /07 07/ 05 /07
Letter to William R. Campbell, Jr. from Eva A. Brown dated July 5, 2007
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 13 (TS-431-S AND TS-418) (TAC NOS. MD5262, MD5263 AND MD5264)
DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown RidsNrrLABClayton (Hard Copy)
RidsNrrDorlDpr RidsNrrDssSbwb (GCranston)
RidsNrrDraApla (MRubin)
RidsNrrPMTAlexion RidsAcrsAcnwMailCenter RidsOgcRp THuang MRazzaque TNakanishi LWard MLobel MStutzke
REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 DOCKET NOS. 50-259 , 50-260 AND 50-296 APLA 28./30. Confirm that the following success criteria were used to estimate the risk related to the containment overpressure (COP) credit:
Initiator Injection NPSH Large Break Loss 1 core spray (CS) 3 or 4 residual heat removal (RHR) pumps/heat of coolant pump exchanges (H/Xs) aligned to spent fuel pool Accident (LLOCA) cooling (SPC) or or 1 Low Pressure Core Injection 2 RHR pumps/HXs aligned to SPC and favorable (LPCI) pump plant conditions (initial SP volume at 123,500 ft3, river water temperature at 85 degrees F, torus water temperature less than or equal to 86 degrees F) or 2 pumps/HXs aligned to SPC and containment integrity (COP credit)
Note: 1 pump/HX aligned to SPC and containment integrity (COP credit) will not provide adequate NPSH to the low pressure emergency core cooling system (ECCS) pumps during LLOCAs Anticipated 1 CS pump containment integrity (COP credit)
Transient Without Scram (ATWS) or Note: Does not depend on the number of RHR or pumps/HXs aligned to SPC Station Blackout 1 LPCI pump (SBO) (upon AC power recovery after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Enclosure
Other transients 1 CS pump 2 or more RHR pumps/HXs aligned to SPC or or 1 LPCI pump 1 pump/HX aligned to SPC and containment integrity (COP credit) 29./31. Describe any interlocks or procedural prohibitions that preclude the simultaneous opening of the LPCI valves, SPC valves, and/or drywell spray valves in the same RHR subsystem.
30./32. The licensee has made a commitment to terminate drywell cooling within two of entry into the Appendix R fire safe shutdown operating procedures. Address how this commitment was considered during development of the probabilistic risk assessment (PRA) success criteria.
31./33. The SPC mode is manually aligned by the operator. Describe how the operator decides the number of RHR pumps/HXs to align to SPC. Address whether it is credible (e.g., within procedural guidance) that the operator would actually align three or four RHR pumps/HXs to SPC.
32./34. Determine if there is a significant statistical correlation between the suppression pool water level, river water temperature, and/or torus water temperature.
33./35. Discuss whether it is possible to eliminate or substantially reduce the need for the COP credit by maximizing the suppression pool water level, minimizing the initial torus water temperature and/or reducing the amount of power uprate.
34./36. Provide the approximate high confidence of low probability of failure (HCLPF) of the Browns Ferry containment structure (including considerations of personnel access or equipment hatches, penetrations, etc.).
35./37. Discuss whether the fire risk evaluation contained in the IPEEE addresses spurious actuations (hot shorts) of the containment isolation valves or the need for the COP credit. If not, address the change in risk considering COP and submit a summary of the updated results.
36./37. Discuss when and how the peer review for the Unit 1 PRA was conducted (identify the participants, describe what methods were used, etc.), and submit the peer review report. Indicate which comments may significantly affect the PRA results, insights, and conclusions concerning the proposed EPU. Also, discuss the plans and timetable to resolve comments and revise the PRA model.
37./38. Explain how COP credit maintains the defense-in-depth concept provided Section 2.2.1.1 of Regulatory guide 1.174. Specifically address each of the seven bulleted items with particular emphasis on the fifth item (independence of barriers is not degraded).
SBWB (Unit 1 Only)
- 67. Discuss whether the 3-D MONICORE core monitoring system is based on TGBLA06/PANAC11 methods.
- 68. The 50 megawatt thermal/million pounds mass/hour (MWt/Mlbm/hr) limit establishes the generic envelope for General Electric neutronic methods nodal, bundle and axial power distribution uncertainties. Discuss whether the core thermal power to core flow ratio for the Unit 1 extended power uprate will remain below 50 MWt/Mlbm/hr at any statepoint in the allowed operating domain limit.
- 69. Discuss whether the plant specific R-factor calculation at a bundle level was performed consistent with lattice axial void conditions expected for the hot channel operating state.
- 70. The presence of bypass voiding at the low-flow conditions where instabilities are likely can result in calibration errors. Discuss whether these calibration errors were accounted for when determining the setpoints for the detect and suppress long term methodology.
(Units 2 and 3 Only)
- 82. Provide the reference and/or description of the models governing counter-current flow (CCFL) at the exit to the hot bundle/core. Also identify the reference that describes the validation (separate effects and integral test data comparisons) of the CCFL limit model governing top down cooling in rod bundles.
- 83. Provide the vapor and liquid hot bundle exit velocities versus time for the 0.05 ft2 breaks presented in the April 18, 2007, SBWB-64 Supplement response.
- 84. Provide the axial power shapes used in the calculations provided in the April 18, 2007, request for additional information response.
William R. Campbell, Jr. BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar Decatur, AL 35609 Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Generation Development Browns Ferry Site Operations and Construction Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Decatur, AL 35609 Chattanooga, TN 37402-2801 Mr. Larry S. Mellen Mr. Preston D. Swafford Browns Ferry Unit 1 Project Engineer Senior Vice President Division of Reactor Projects, Branch 6 Nuclear Support U.S. Nuclear Regulatory Commission Tennessee Valley Authority 61 Forsyth Street, SW.
6A Lookout Place Suite 23T85 1101 Market Street Atlanta, GA 30303-8931 Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Mr. Walter M. Justice II Corporate Nuclear Licensing Interim Vice President and Industry Affairs Nuclear Engineering & Technical Services Tennessee Valley Authority Tennessee Valley Authority 4X Blue Ridge 6A Lookout Place 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 Mr. William D. Crouch, Manager Brian OGrady, Site Vice President Licensing and Industry Affairs Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 P.O. Box 2000 Decatur, AL 35609 Decatur, AL 35609 General Counsel Senior Resident Inspector Tennessee Valley Authority U.S. Nuclear Regulatory Commission ET 11A Browns Ferry Nuclear Plant 400 West Summit Hill Drive 10833 Shaw Road Knoxville, TN 37902 Athens, AL 35611-6970 Mr. John C. Fornicola, General Manager State Health Officer Nuclear Assurance Alabama Dept. of Public Health Tennessee Valley Authority RSA Tower - Administration 6A Lookout Place Suite 1552 1101 Market Street P.O. Box 303017 Chattanooga, TN 37402-2801 Montgomery, AL 36130-3017 Mr. Bruce Aukland, Plant Manager Chairman Browns Ferry Nuclear Plant Limestone County Commission Tennessee Valley Authority 310 West Washington Street P.O. Box 2000 Athens, AL 35611 Decatur, AL 35609 Mr. Robert H. Bryan, Jr., General Manager Mr. Masoud Bajestani, Vice President Licensing and Industry Affairs Browns Ferry Unit 1 Restart Tennessee Valley Authority Browns Ferry Nuclear Plant 4X Blue Ridge Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801
