Letter Sequence RAI |
|---|
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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, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, 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
|
MONTHYEARML0631104352006-11-0707 November 2006
Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes
Project stage: Request
05000260/LER-2007-001, Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test2007-03-0202 March 2007
Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test
Project stage: Request
ML0711300782007-04-18018 April 2007
Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Supplemental Response to Requests for Additional Information (RAI)
Project stage: Supplement
ML0711503662007-04-24024 April 2007
Units 1, 2, & 3 - Fire Protection Program - Post-Fire Operator Manual Actions
Project stage: Request
ML0711503712007-04-24024 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
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
ML0721303752007-07-31031 July 2007
CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz
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
05000259/LER-2007-005, Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank2007-08-0808 August 2007
Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank
Project stage: Request
ML0723602572007-08-21021 August 2007
Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Limit Curves
Project stage: Request
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
05000296/LER-2007-003, Leak in an ASME Class I Code Reactor Pressure Boundary Pipe2007-11-21021 November 2007
Leak in an ASME Class I Code Reactor Pressure Boundary Pipe
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
(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
ML0804304462008-02-11011 February 2008
Notification of Potential Part 21 Report Power Supply Unit Is Limited at Elevated Temperatures
Project stage: Request
ML0803503812008-02-14014 February 2008
Summary of Meeting with Tennessee Valley Authority - on Extended Power Uprate Review
Project stage: Meeting
ML0806501012008-02-21021 February 2008
Response to Round 16 Request for Additional Information SRXB-73
Project stage: Request
ML0805302562008-02-21021 February 2008
Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments
Project stage: Other
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
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
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
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
ML0812804712008-05-0202 May 2008
Request for Additional Information for Extended Power Uprate - Round 17
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
2007-07-05
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 28, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 110'1 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1, REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE - ROUND 26 (TAC NO. MD5262) (TS-431)
Dear Mr. Swafford:
By letter dated June 28,2004, the Tennessee Valley Authority (TVA, the licensee) submitted an amendment request for Browns Ferry Nuclear Plant (BFN), Unit 1, as supplemented by letters dated August 23, 2004, February 23, April 25, June 6, December 19, 2005, February 1 and 28, March 7,9,23, and 31, April 13, May 5,15, and 16, June 15, 23, and 27, July 6,21,26, and 31, August 4,16,18, and 31, September 1,15, and 22, October 3,5, and 13, November 7, December 1, 5, 11, and 21, 2006, January 31, February 16 and 26, April 6, 18, and 24, July 27, September 24, November 15 and 21, December 14,2007, January 25 and 31, February 11 and 21, March 6, April 4 and 9, May 1, June 3, 12, and 16, August 15, September 2 and 19, October 3,17, and 31, November 11 and 14, December 15, 2008, January 9, 16, and 23, February 18 and 24, March 11, 12, and 27, April 3, 10,21, and 29, and May 7 and 29, 2009.
The proposed amendment would change the BFN operating license for Unit 1 to increase the maximum authorized power level by approximately 14 percent.
A response to the enclosed Request for Additional Information (RAI) is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. Gordon Arent of your staff on August 31,2009, and it was agreed that TVA would respond within 30 days of issuance of this letter.
P. Swafford
- 2 If you have any questions, please contact me at (301) 415-2315.
Sincerely Ira!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
RAI cc w/enclosure: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION EXTENDED POWER UPRATE ROUND 26 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-259, AND 50-260 EMCB (Units 1 and 2 Only) 81.187.
During a recent inspection at Browns Ferry Nuclear Plant (BFN) from April 20-24, 2009 [See Inspection Report (IR) 50-259(260)(296)/2009-007] the response to a significant fire was reviewed. Based on this review and information provided in support of the BFN extended power uprate (EPU) review, it is the Nuclear Regulatory Commission (NRC) staff's understanding that upon detection of a significant fire the reactor operators would first enter the emergency operating instructions (EOls). From there the operators may stay in the EOls or subsequently enter the safe shutdown instructions (SSls), if the conditions for entry are satisfied.
Observations by the inspection staff of a simulated significant fire
[IR 50-259(260)(296)/2009-007] indicated the possibility that, at the time of entry into the SSls, the suppression pool temperature may be greater than the initial suppression pool temperature of 95 degrees Fahrenheit (degrees F) assumed in the net positive suction head (NPSH) Appendix R analyses due to the discharge of steam from the reactor vessel to the suppression pool.
Explain how this sequence of events is consistent with the timing assumed in the Appendix R Fire analyses provided in a letter dated March 12, 2009, to demonstrate adequate NPSH for the residual heat removal (RHR) pump credited with cooling the suppression pool and the core. Also, justify the use of an initial suppression pool temperature of 95 degrees F, if entry into the SSls is not made at the time of reactor trip. Address how a higher initial suppression pool temperature (the suppression pool
- 2 temperature at entry into the SSls) will affect the peak suppression pool temperature and the timing of assumed operator actions (manually opening the main steam relief valves and terminating the cooling of the containment fan coolers).
82.188.
Provide detailed justification for each fire area that demonstrates that during a significant fire spurious actuations of containment isolation valves or maloperation of other systems or components will not result in loss of containment integrity.
83.189.
The March 12, 2009, letter to the NRC revising the BFN Appendix R Fire NPSH analyses assumes a required NPSH value corresponding to a 3-percent head loss.
By definition, the RHR pump will be operating with a level of cavitation greater than the level of cavitation assumed in previous Appendix R analyses. Provide an explanation why the RHR pump can be expected to perform its safety function at the 3-percent head loss value of required NPSH.
.. ML092370020 NRR-088 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA SCVB/BC LPL2-2/BC NAME SLingam EBrown BClayton HWalker orRDennig w/ comments TBoyce (MVaaler for)
DATE 08/24/09 08/26/09 08/24/09 08/26/09 08/28/09
