ML12320A481
| ML12320A481 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/15/2012 |
| From: | Tennessee Valley Authority |
| To: | Ellen Brown Plant Licensing Branch II |
| Brown, Eva A. | |
| References | |
| Download: ML12320A481 (16) | |
Text
N l
Browns Ferry Nuclear Plant Nuclear Browns Ferry XM Fuel Transition Update November 15, 2012
Agenda Nuclear
- Review June Meeting Highlights g
g g
- LAR Overview and Status
- Review schedule
- Future EPU issues 2
June Meeting Summary Nuclear
- TVA desires to transition to ATRIUM-10 XM fuel
- Industry proven design
- Approved for Brunswick (similar plant)
- XM design is compliant with ANF-89-98(P)(A)
- NRC audited XM compliance documentation in November 2010
- LAR will be for all three Browns Ferry units
- First targeted XM reloads by unit
- Unit 2 spring 2015, Unit 3 spring 2016, Unit 1 fall 2016
- Transition work will use Unit 2 cycle 19 as the basis for review
- Will demonstrate transition from current ATRIUM-10 fuel to XM fuel
- Will demonstrate application of several additional methods to BFN
- Transition cores will only contain AREVA fuel types
- No multi vendor core issues
- TVA requesting approval for current power level only 3
q g pp p
y
June Meeting Summary (cont)
Nuclear
- Implementation requires use of additional AREVA methods
- RODEX4
- SAFLIM-3D
- ACE
- The additional methods will be added to TS 5 6 5 b The additional methods will be added to TS 5.6.5.b
- Application of existing AREVA methods in TS 5.6.5.b to Browns Ferry has received extensive NRC review C
h d di 2008
- NRC methods audit August 2008
- Unit 1 ATRIUM-10 LAR
- NRC requested thermal conductivity degradation be addressed in the LAR 4
June Meeting Summary (cont)
Nuclear
- Supplement with additional information pp
- Application of the three additional methodologies to Browns Ferry
- Address thermal conductivity degradation issue
- Address ACE K factor issue (plant specific supplement) ill i l d i
h S f
i 2
- SAFLIM-3D based 5
LAR Overview and Status Nuclear
- Submittal Tech Spec change number assigned: TS-478
- Transition work essentially complete y
p
- All reports except Reload Safety Report received
- Reports being docketed for TS-478 (similar to TS-473)
- Bundle mechanical design report (ANP-3150) g p
(
)
- Thermal hydraulic compatibility report (ANP-3082)
- Fuel cycle design report (ANP-3145)
- Reload safety analysis report (ANP-3167)
- LOCA break spectrum report (ANP-3152)
- LOCA analysis uses revised core spray modeling method
- Licensing methods compendium (ANP-2637) - revised RAI report (ANP 2860) supplemental
- RAI report (ANP-2860) - supplemental
- RAI report
- Prior RAIs in ANP-2860 screened along with Brunswick RAIs Questions impacted by fuel type changes screened in 6
- Questions impacted by fuel type changes screened in
- Updated responses included in the supplement
LAR Overview and Status (cont)
Nuclear
- Additional reports being docketed
- Fuel rod thermal mechanical report (ANP-3159) p
(
)
- Equilibrium fuel cycle design report (ANP-3148)
- SLMCPR analysis report
- SAFLIM 3-D based
- Conductivity degradation report (ANP-3170)
- BFN specific ACE supplement (ANP-3140)
- Approved ACE methodology has a known issue
- Axial averaging process for K factor
- Generic ACE supplement still under review by NRC pp y
- Tech Spec markups for TS 5.6.5.b will reflect the BFN specific supplement
TS-478
LAR Overview and Status (cont)
Nuclear Thermal conductivity degradation issue
- RODEX2 still used for transient and LOCA analyses y
- Legacy ATRIUM-10 fuel will still utilize this method for thermal-mechanical evaluations
- RODEX4 addresses conductivity degradation U
d f th l
h i
l l
ti f
XM f l
- Used for thermal-mechanical evaluations for XM fuel
- A BFN evaluation report has been prepared (ANP-3170)
- Report address impacts of conductivity degradation on:
- Overpressure events
- Stability
- Fire protection events 8
LAR Overview and Status (cont)
Nuclear LAR License Commitment
- Brunswick SER for use of RODEX4 raised an issue
- NRC had concerns over oxide thickness
- 130 micron limit in the topical report
- Concerns that significant oxide spalling could occur at these levels
- Available AREVA fuel data shows no concerns up to 85 microns
- Brunswick committed to restricting calculated oxide to 85 microns when using RODEX4
- TVA will comply with this same reduced limit
- Browns Ferry LAR contains a commitment to this effect 9
LAR Overview and Status (cont)
Nuclear Other Emerging Issues Addressed in RAI Process
- Upcoming Regulation and SRP revision p
g g
- Plant specific responses needed to address emerging concerns
- No Regulation/SRP in place to provide final criteria for evaluation
- Approved methods are not in place yet to address all emerging issues
- Potential for understanding of phenomena, NRC focus of concern, and methods of evaluation to evolve over time NRC T F
l t th t i
RIA i ill b
- NRC Top Fuel paper suggests that emerging RIA issues will be addressed in RAI process (Paul Clifford)
If an existing licensee voluntarily seeks a license amendment or change and (1) the NRC staffs consideration of the request involves a regulatory issue directly relevant to RIA and (2) the specific subject matter of this new guidance is an essential consideration in the staffs determination of the acceptability of the licensees request, then the staff may request that the licensee either follow the new guidance or provide an equivalent alternative process that demonstrates compliance with the underlying NRC regulatory requirements 10 the underlying NRC regulatory requirements.
LAR Overview and Status (cont)
Nuclear Reactivity Insertion Accident
- RIA Criteria that will be supported by LAR
- Show the current radiological source evaluation bounds the number of rods failed based on peak radial average fuel enthalpy rise criteria of 170 cal/g (high cladding based on peak radial average fuel enthalpy rise criteria of 170 cal/g (high cladding temperature failure criteria for zero power conditions)
- Show that interim criteria for core coolability of 230 cal/g peak average fuel enthalpy rise is met e t a py se s et
- Compliance with other underlying NRC regulatory requirements will be demonstrated as requested during RAI process 11
LAR Overview and Status (cont)
Nuclear
- Technical Specifications
- All three units will have changes to TS 5.6.5.b g
- Remove reference to ANF-524PA (SAFLIM2)
- Add reference to ANP-10307PA (SAFLIM-3D)
- Add reference to BAW-10247PA (RODEX4)
- Add reference to ANP 10298PA (ACE for XM)
- Add reference to ANP-10298PA (ACE for XM)
- Unit 2 will also have a change to TS 2.1.1.1 (SLMCPR) g
(
)
- 0.02 reduction from current Unit 2 SLMCPR values
- Conservatively selected relative to SAFLIM-3D calculated values
- TVA is choosing not to pursue all the margin SAFLIM 3D can provide
- TVA is choosing not to pursue all the margin SAFLIM-3D can provide
- Intention is to make the new SLMCPR cycle independent
- TVA will request a change for Units 1 and 3 as part of the normal reload cycle process for first XM use at those units 12
LAR Overview and Status (cont)
Nuclear
- Technical Specification Bases changes
- All three units TS Bases will be modified
- B 2.1.1 Reactor Core SLs
- B 3.2.1 APLHGR
- B 3 2 2 MCPR
- B 3.2.2 MCPR
- References in these Bases will be updated to reflect new methods
- Modify discussion of low power SL to reflect new CPR correlation
- UFSAR changes will be made under 10CFR50.59 process 13
Schedule Nuclear
- Target date for LAR submittal
- January 2013
- SER need date
- End of February 2014 y
- Need date is tied to reload design and fuel fabrication milestones for Unit 2 cycle 19 14
Future EPU Issues Nuclear
- EPU versus XM timing
- First XM application (unit 2 cycle 19) not targeted for EPU pp
(
y
)
g
- 2016 reloads are potential EPU cycles
- Unit 3 cycle 18
- Unit 1 cycle 12
- Potential for concurrent EPU and XM intro in these two cycles
- TVA views this as acceptable under the ELTR process
- Information docketed for EPU does not consider XM
- Only GE14 and ATRIUM-10 considered
- Meeting needed to discuss how to supplement EPU LAR to account for XM fuel 15
Nuclear Discussion 16