Letter Sequence Other |
|---|
|
Results
Other: ML090330363, ML090770162, ML101160152, ML101160154, ML101160155, ML101160164, ML101160181, ML101160183, ML101160184, ML101160210, ML101160211, ML101160515
|
MONTHYEARML0903304642009-01-28028 January 2009 Slides/Viewgraphs NRC Meeting - White Flint Regarding Browns Ferry Plant, Unit 1 Areva Fuel Transition Project stage: Meeting ML0903303632009-03-23023 March 2009 Loading Bleu Fuel in Browns Ferry, Unit 1 - Slides/Handouts - TVA Project stage: Other ML0907801812009-03-23023 March 2009 Summary of Meeting with the Tennessee Valley Authority Regarding Proposed Fuel Transition Amendment for Browns Ferry Nuclear Plant, Unit 1 Project stage: Meeting ML0907701622009-06-0303 June 2009 TVA, Presentation Slides for Browns Ferry, Unit 1 Project stage: Other ML0915205452009-06-0303 June 2009 Summary of Meeting with the Tennessee Valley Authority Regarding Proposed Fuel Transition Amendment Project stage: Meeting ML1011601542009-06-30030 June 2009 ANP-2821(NP), Revision 0, Browns Ferry Unit 1 Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies (105% Oltp) Project stage: Other ML1011601522009-09-30030 September 2009 ANP-2859(NP), Revision 0, Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design (105% Oltp) Project stage: Other ML1011602102009-10-0606 October 2009 51-9121503-002, Engineering Information Record, Responses to NRC Comments Regarding Browns Ferry Unit 1 Proposed Fuel Transition Amendment Project stage: Other 05000296/LER-2009-001, Regarding Reactor Scram Due to Loss of Condensate Booster Pumps2009-10-23023 October 2009 Regarding Reactor Scram Due to Loss of Condensate Booster Pumps Project stage: Request ML1011605162009-10-31031 October 2009 Part 1: Previous NRC Requests for Additional Information Matrix and Text, Part 2: Browns Ferry Unit 1 - Summary of Response to Request for Additional Information, ANP-2860(NP), Rev. 2, Browns Ferry Unit 1 - Summary of Responses to Requests Project stage: Response to RAI ML1011605152009-10-31031 October 2009 ANP-2638NP, Revision 2, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions Project stage: Other ML1011601642009-11-30030 November 2009 ANP-2877NP, Revision 0, Mechanical Design Report for Browns Ferry Unit 1 Reload BFR1-9 ATRIUM-10 Fuel Assemblies (105% Oltp) Project stage: Other ML0935613962009-12-23023 December 2009 Nonacceptance of Utilization of Areva Fuel and Associated Analysis Methodologies. (TAC ME2451) (TS-467) Project stage: Acceptance Review ML1011601812010-01-31031 January 2010 GNF 0000-0111-8036-R0-NP, GE14 Fuel Thermal-Mechanical Information Project stage: Other ML1011601842010-01-31031 January 2010 NEDO-32484, Revision 7, Browns Ferry Nuclear Plant Units 1, 2, and 3 SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis Project stage: Other ML1005412492010-02-25025 February 2010 Withdrawal of an Amendment Request to Utilization of Areva Fuel and Associated Analysis Methodologies Project stage: Withdrawal ML1011601552010-03-31031 March 2010 ANP-2863(NP), Revision 1, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp Project stage: Other ML1011601832010-03-31031 March 2010 ANP-2908(NP), Revision 0, Browns Ferry Units 1, 2, and 3 105% OLTP LOCA Break Spectrum Analysis Project stage: Other ML1011602112010-03-31031 March 2010 ANP-2637, Revision 3, Boiling Water Reactor Licensing Methodology Compendium Project stage: Other ML1011602992010-04-16016 April 2010 Affidavit of Alan B. Meginnis Regarding Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request Project stage: Supplement ML1011601532010-04-16016 April 2010 Supplemental Information for Technical Specification Change TS-473 - Areva Fuel Transition Amendment Request Project stage: Supplement ML1011601852010-04-30030 April 2010 NEDO-32484, Supplement 1, Revision 0, Browns Ferry Nuclear Plant Unit 1 Supplementary Report Regarding ECCS-LOCA Additional Single Failure Evaluation at Current Licensed Thermal Power Project stage: Supplement 2009-06-03
[Table View] |
Text
--
Z JJ
()
S:S:
~
CD
~
CD
('")
~
- r ::J
-L to 0)1 I\\)~
8~
COeD 11-
- J OJ
...., o
- E
- J en
- i~
tu....,
- J en'<
r-+
o >>
- J CD <
tu 11 c::
CD
(J) c 0
3 Q.)-
""C Q.)
("")
Q.) "
(Q CD 0 <
CD ;:
CD
~
(J)
C 0
3 Q.)-
en
("")
- r CD
- a.
c -
CD C
""C
- a.
Q.)
CD CO>
CD
- J
- a.
Q)
en c
cr 3
Ol en o
- r.
eo
- a.
c CD C
-c
- a.
Ol eo
Revised Schedule
- January 28 meeting - NRC requested that the submittal schedule be reviewed to determine best possible dates
- Areva and TVA have agreed on approach to improve schedule
- Preliminary core design work will be eliminated
- Final core design has commenced using best available energy plan estimate for current cycle
- TVA review time for selected reload inputs and analyses will be accelerated
Revised Schedule (cant)
- Areva will deliver all reload documentation needed to support submittal by 10/23/09
- TVA will require time to prepare final submittal package and complete internal reviews and approvals
- TVA will commit to a submittal date of 12/11/09
en c
c 3
Dl
-c Dl o
="
Dl co CD o
CD
~
CD
~
LAR Contents LAR will be a complete package No supplemental information planned to be submitted
- Will include the following reports:
Thermal Hydraulic Design Report Mechanical Design Report ANP-2637 (BWR Licensing Methodology Compendium)
Fuel Cycle Design Report Reload Safety Report
- Will not submit the LOCA break spectrum report Will provide justification as to unit 1 applicability
- Will include the following Tech Spec related changes:
SLMCPR Tech Spec (if required)
Tech Spec 5.6.5 update to add Areva analytical methods Tech Spec Bases page changes
LAR Contents (cant)
- LAR will also address the eleven items requested by NRC in the draft Summary of Information Request
- Request NRC formally issue final as soon as possible
- LAR will address the prior BFN 2/3 fuel related EPU RAls
- Will also address the RAls from the Brunswick transition