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{{#Wiki_filter:.5ni Transition to Framatome ANP Fuel Carolina Power & Light-Company Brunswick Steam Electric Plant, Units 1 and 27 ___ -___March 10, 2006 Nuclear I Generation I Group I2 Progress Energy Meeting Agenda* Purpose* Background
{{#Wiki_filter:. 5ni Transition to Framatome ANP Fuel Carolina Power & Light-Company Brunswick Steam Electric Plant, Units 1 and 2 77, ,' 7                                                  W E  ___ - ___
March 10, 2006 Nuclear IGeneration IGroup                  I2 Progress Energy
 
Meeting Agenda
* Purpose
* Background
* Transition approach P Licensing o Analysis o Methodology
* Transition approach P Licensing o Analysis o Methodology
* Licensing submittals and schedule* Summary b2 .Progress Energy Purpose* Describe the transition process from GNF to Framatome ANP fuel supply* Communicate transition plan* Discuss licensing activities and schedule i A*b U3 Progress Energy 3  
* Licensing submittals and schedule
* Summary b2     .                     Progress Energy
 
Purpose
* Describe the transition process from GNF to Framatome ANP fuel supply
* Communicate transition plan
* Discuss licensing activities and schedule i
U3 Progress Energy A*b   3


===Background===
===Background===
Fuel supplier change.Progress Energy fuel bid.Proposals requested Summer 2004.) Bids received Winter 2004.Framatome ANP awarded Brunswick fuel supply Fall 2005.Transition to FANP fuel supply March 2008 A%&5 Progress Energy 4
Fuel supplier change
. Progress Energy fuel bid
    . Proposals requested Summer 2004.
    ) Bids received Winter 2004
. Framatome ANP awarded Brunswick fuel supply Fall 2005
. Transition to FANP fuel supply March 2008 A%     4
                                      &5 Progress Energy


===Background===
===
GE14 11 Ills In. I I RI Iffimm= pS 11 Key Features* 1Ox10 lattice* Large central water rods (2)is14 nprt lanrgth rodz (~2/3 lonrgth* 8 spacers* Debris filter lower tie plate 179 kgU i Extensive operating experience 5 @ Progress Energy  
Background===
GE14                     11Ills In.
II RI       Iffimm= pS jm 11 Key Features
* 1Ox10 lattice
* Large central water rods (2) is14 nprt lanrgth rodz (~2/3 lonrgth
* 8 spacers
* Debris filter lower tie plate 179 kgU i Extensive operating experience 5                                 @   Progress Energy


===Background===
===
ATRIUM-1 0 Key Features* 1 Ox1 0 lattice* Square internal water channel 8nr pa nr lengt rods(rI3I le/ "ngth)%J J LA I i I ,II LIII J %.,: K O*8 8spacers*Debris filter lower tie plate*178 kgU* Extensive operating experience 6 ~ Progress Energy  
Background===
ATRIUM-1 0 Key Features
* 1Ox1 0 lattice
* Square internal water channel 8nr pa           lengt rods(rI3I nr                  le/"ngth)
            *8 8spacers
                %J J LA I I filter
              *Debris        ,II   LIII i J tie plate lower
                                        %.,:     K O
              *178 kgU
* Extensive operating experience 6     ~                                   Progress Energy


===Background===
===Background===
Brunswick Plant* 24 month fuel cycles* Extended power uprate to 120% of original license o Unit 1 Cycle 15; Spring 2004 i Unit 2 Cycle 17; Spring 2005* Current licensing basis fuel designs o GE13 9x9* GE14 10x1O (full core in each unit)* ATRIUMŽ-10 lead use assemblies Unit 2 Cycle 14* Transition to Framatome ANP ATRIUMTM-10 o Unit 1 Cycle 17; March 2008 o Unit 2 Cycle 19; March 2009 (j 7 -gB Progress Energy  
Brunswick Plant
* 24 month fuel cycles
* Extended power uprate to 120% of original license o Unit 1 Cycle 15; Spring 2004 i Unit 2 Cycle 17; Spring 2005
* Current licensing basis fuel designs o GE13 9x9
* GE14 10x1O (full core in each unit)
* ATRIUM'-10 lead use assemblies Unit 2 Cycle 14
* Transition to Framatome ANP ATRIUMTM-10 o Unit 1 Cycle 17; March 2008 o Unit 2 Cycle 19; March 2009 (j       7                                 -gB Progress Energy


===Background===
===
Background===
Core monitoring
Core monitoring
* PPX-ll in use since 1994* PPX-lll upgrade prior to fuel transition i CASMO-4*uO" R 0U BR__ N -B* iviiIROUK3UN-B2
* PPX-ll in use since 1994
* PPX-lll upgrade prior to fuel transition i CASMO-4
* iviiIROUK3UN-B2
      *uO" R 0U BR__ -
N B
* Benchmark past cycles o EPUR operation o Methodology uncertainty validation
* Benchmark past cycles o EPUR operation o Methodology uncertainty validation
* Implementation under 50.59 8 A ProgsEnergy Transition to ATRIUM T m-10 Fuel , .- ._ -* Licensing approach* Analysis approach*eApproved methodologies A%&O .Progress Energy 9 Licensing Approach* Minimize changes to the current plant licensing basis* ATRIUMTM-1 0 fuel evaluated in accordance with 1 0 CFR 50.59* Technical Specification changes o Update references to NRC-approved methods i LHGR operating limit addition o SLMCPR, scram speed option changes o Remove vendor-specific criticality analysis methods (k-infinity)
* Implementation under 50.59 8                               A ProgsEnergy
P Design features update* Cycle specific submittals
 
* COLR* SLMCPR o 50.46 annual report o Periodic FSAR updates k 10 § Progress Energy Licensing Approach MELLLA+* MELLLA+ separate from fuel transition
Transition to ATRIUMT m-10 Fuel
* Reload analyses will bound MELLLA+* Operation contingent upon additional
                  , .- . _ -
*" LO% Wf LO AV N -I 'f* MELLLA+ (NEDO-33006-P, Rev. 1)i Stability (ANP-1 0262)license* Schedule determined by methodology and approval review A%Progress Energy 11 Analysis approach __* Review all event analyses identified in FSAR* Disposition analyses as: o Not impacted by the change in fuel design^ Bounded by the UouiSquences of another event-Potentially limiting* Analyze potentially limiting events with NRC approved Framatome ANP methodology
* Licensing approach
* Current licensing basis retained for events not impacted by the change in fuel design (Gb 12 Progress Energy Approved Methodologies COLR TS References  
* Analysis approach
-Mechanical Analysis* XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.* XN-NF-85-67(P)(A), Ge Exxon Nurc1laqr 1 kt Pum neric Mechanical Design p BWR Reload Fut!L for* EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model* ANF-89-98(P)(A), Generic Mechanical Design for BWR Fuel Designs Criteria Aib w Progress Energy 13 Approved Methodologies COLR TS References  
*eApproved methodologies A%&   9 O .Progress Energy
-Neutronic Analysis XN-NF-80-19(P)CA)
 
Volume 1, Exxon Nuclear Methodology for oiling Water Reactors -Neutronic Methods for Design and Analysis.* XN-NF-80-1 9(P)(A) Volume 4, Exxon Nuclear.Methodoinn\/
Licensing Approach
for Boiling W\Aater Reactors:
* Minimize changes to the current plant licensing basis
Applcation of the ENU O/Aethodology to BWR Reloads.* EMF-2158(P)(A),,-Siemens Power Corporation Methodology for Boilinq Water Reactors:
* ATRIUMTM-1 0 fuel evaluated in accordance with 10 CFR 50.59
Evaluation and Validation of CAS 0-4/MICROBURN-B2.
* Technical Specification changes o Update references to NRC-approved methods i LHGR operating limit addition o SLMCPR, scram speed option changes o Remove vendor-specific criticality analysis methods (k-infinity)
o XN-NF-80-19(P)(A)
P Design features update
Volume 3, Exxon Nuclear Methodology for boiling Water Reactors THERMEX: Thermal Limits Methocology Summary Description G 14 .Progress Energy Approved Methodologies COLR TS References  
* Cycle specific submittals
-Transient Analysis o XN-NF-84-105(P)(A)
* COLR
Volume 1, XCOBRA-T:
* SLMCPR o 50.46 annual report o Periodic FSAR updates k     10                                               § Progress Energy
A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis.o ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.P ANF-913(P)(A)
 
Volume 1, COTRANSA2:
Licensing Approach MELLLA+
A Computer Program for Boiling Water Reactor Transient Analyses.o ANF-1 358(P)(A), The Los's of Feedwater Heating Transient in Boiling Water Reactors.15 .Progress Energy d,&b Approved Methodologies COLR TS References  
* MELLLA+ separate from fuel transition
-CPR and LOCA P EMF-2209(P)(A), SPCB Critical Power Correlation o EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-I ROIdetI ILFue,.o EMF-2361 (P)(A), EXEM BWR-2000 ECCS Evaluation Model.o EMF-2292(P)(A), ATRIUMTM-10:
* Reload analyses will bound MELLLA+
Heat Transfer Coefficients.
* Operation contingent upon additional license
Appendix K Spray d,4 K3 Progress Energy 16 Licensing Submittals Schedule* TS amendment request o Submit January 2007 o Request approval by January 2008..ACPRP amendmeint reus I kilyy L-"I 5 .IVbI July I I, I IAE I II L I ,;L II2007U i Submit July 2007 o Request approval by January 2008 Ab Q Progress Energy 17 Summary.* Established ATRIUM-1 0 transition process O Browns Ferry (2004)0 Columbia Generating Station (2003)I River Bend and Grand Gulf (2001)* NRC-approved methodology will be used for the transition
    *" LO%
*'Progress Energy and Framatome ANP are committed to support the NRC's review 18 .Progress Energy}}
Wf LO AV N - I 'f
* MELLLA+ (NEDO-33006-P, Rev. 1) i Stability (ANP-1 0262)
* Schedule determined by methodology review and approval Progress Energy A%           11
 
Analysis approach               __
* Review all event analyses identified in FSAR
* Disposition analyses as:
o Not impacted by the change in fuel design
    ^ Bounded by the UouiSquences of another event
    - Potentially limiting
* Analyze potentially limiting events with NRC approved Framatome ANP methodology
* Current licensing basis retained for events not impacted by the change in fuel design (Gb     12                                       Progress Energy
 
Approved Methodologies COLR TS References - Mechanical Analysis
* XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.
* XN-NF-85-67(P)(A), Ge neric Mechanical Design for Exxon Nurc1laqr 1kt Pum p BWR Reload Fut!L
* EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model
* ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs Aib     13 w Progress Energy
 
Approved Methodologies COLR TS References         - Neutronic Analysis XN-NF-80-19(P)CA) Volume 1, Exxon Nuclear Methodology for oiling Water Reactors - Neutronic Methods for Design and Analysis.
* XN-NF-80-1 9(P)(A) Volume 4, Exxon Nuclear.
Methodoinn\/ for Boiling W\Aater Reactors: Applcation of the ENU O/Aethodology to BWR Reloads.
* EMF-2158(P)(A),,-Siemens Power Corporation Methodology for Boilinq Water Reactors: Evaluation and Validation of CAS 0-4/MICROBURN-B2.
o XN-NF-80-19(P)(A) Volume 3, Exxon Nuclear Methodology for boiling Water Reactors THERMEX:
Thermal Limits Methocology Summary Description G   14                                       . Progress Energy
 
Approved Methodologies COLR TS References - Transient Analysis o XN-NF-84-105(P)(A) Volume 1, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis.
o ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.
P ANF-913(P)(A) Volume 1, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses.
o ANF-1 358(P)(A), The Los's of Feedwater Heating Transient in Boiling Water Reactors.
d,&b  15               .                       Progress Energy
 
Approved Methodologies COLR TS References - CPR and LOCA P EMF-2209(P)(A) , SPCB Critical Power Correlation o EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-I ROIdetI ILFue,.
o EMF-2361 (P)(A), EXEM BWR-2000 ECCS Evaluation Model.
o EMF-2292(P)(A), ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients.
K3 Progress Energy d,4     16
 
Licensing Submittals Schedule
* TS amendment request o Submit January 2007 o Request approval by January 2008
      ..ACPRP amendmeint         reus I       kilyy L-"I
: 5. IVbI   JulyI I, IAEI I II L   I   ,;L II2007U i Submit July 2007 o Request approval by January 2008 Ab     17 Q Progress Energy
 
Summary.
* Established ATRIUM-1 0 transition process OBrowns Ferry (2004) 0 Columbia Generating Station (2003)
I River Bend and Grand Gulf (2001)
* NRC-approved methodology will be used for the transition
*'Progress Energy and Framatome ANP are committed to support the NRC's review 18     .                         Progress Energy}}

Revision as of 21:56, 23 November 2019

03/10/2006, Meeting Handouts for Summary of Meeting W/Carolina Power & Light Regarding the Fuel Transition Process and Licensing Submittals for Brunswick, Units 1 & 2
ML060790305
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 03/10/2006
From:
Nuclear Generation Group, Progress Energy Co
To:
Carolina Power & Light Co, Office of Nuclear Reactor Regulation
Mozafari B, NRR/ADRO/DORL, 415-2020
Shared Package
ML061290361 List:
References
Download: ML060790305 (18)


Text

. 5ni Transition to Framatome ANP Fuel Carolina Power & Light-Company Brunswick Steam Electric Plant, Units 1 and 2 77, ,' 7 W E ___ - ___

March 10, 2006 Nuclear IGeneration IGroup I2 Progress Energy

Meeting Agenda

  • Purpose
  • Background
  • Transition approach P Licensing o Analysis o Methodology
  • Licensing submittals and schedule
  • Summary b2 . Progress Energy

Purpose

  • Describe the transition process from GNF to Framatome ANP fuel supply
  • Communicate transition plan
  • Discuss licensing activities and schedule i

U3 Progress Energy A*b 3

Background

Fuel supplier change

. Progress Energy fuel bid

. Proposals requested Summer 2004.

) Bids received Winter 2004

. Framatome ANP awarded Brunswick fuel supply Fall 2005

. Transition to FANP fuel supply March 2008 A% 4

&5 Progress Energy

=

Background===

GE14 11Ills In.

II RI Iffimm= pS jm 11 Key Features

  • 1Ox10 lattice
  • Large central water rods (2) is14 nprt lanrgth rodz (~2/3 lonrgth
  • 8 spacers
  • Debris filter lower tie plate 179 kgU i Extensive operating experience 5 @ Progress Energy

=

Background===

ATRIUM-1 0 Key Features

  • 1Ox1 0 lattice
  • Square internal water channel 8nr pa lengt rods(rI3I nr le/"ngth)
  • 8 8spacers

%J J LA I I filter

  • Debris ,II LIII i J tie plate lower

%.,: K O

  • 178 kgU
  • Extensive operating experience 6 ~ Progress Energy

Background

Brunswick Plant

  • 24 month fuel cycles
  • Extended power uprate to 120% of original license o Unit 1 Cycle 15; Spring 2004 i Unit 2 Cycle 17; Spring 2005
  • Current licensing basis fuel designs o GE13 9x9
  • GE14 10x1O (full core in each unit)
  • ATRIUM'-10 lead use assemblies Unit 2 Cycle 14
  • Transition to Framatome ANP ATRIUMTM-10 o Unit 1 Cycle 17; March 2008 o Unit 2 Cycle 19; March 2009 (j 7 -gB Progress Energy

=

Background===

Core monitoring

  • PPX-ll in use since 1994
  • PPX-lll upgrade prior to fuel transition i CASMO-4
  • iviiIROUK3UN-B2
  • uO" R 0U BR__ -

N B

  • Benchmark past cycles o EPUR operation o Methodology uncertainty validation
  • Implementation under 50.59 8 A ProgsEnergy

Transition to ATRIUMT m-10 Fuel

, .- . _ -

  • Licensing approach
  • Analysis approach
  • eApproved methodologies A%& 9 O .Progress Energy

Licensing Approach

  • Minimize changes to the current plant licensing basis
  • Technical Specification changes o Update references to NRC-approved methods i LHGR operating limit addition o SLMCPR, scram speed option changes o Remove vendor-specific criticality analysis methods (k-infinity)

P Design features update

  • Cycle specific submittals
  • SLMCPR o 50.46 annual report o Periodic FSAR updates k 10 § Progress Energy

Licensing Approach MELLLA+

  • MELLLA+ separate from fuel transition
  • Reload analyses will bound MELLLA+
  • Operation contingent upon additional license
  • " LO%

Wf LO AV N - I 'f

  • Schedule determined by methodology review and approval Progress Energy A% 11

Analysis approach __

  • Review all event analyses identified in FSAR
  • Disposition analyses as:

o Not impacted by the change in fuel design

^ Bounded by the UouiSquences of another event

- Potentially limiting

  • Analyze potentially limiting events with NRC approved Framatome ANP methodology
  • Current licensing basis retained for events not impacted by the change in fuel design (Gb 12 Progress Energy

Approved Methodologies COLR TS References - Mechanical Analysis

  • XN-NF-81-58(P)(A), RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model.
  • XN-NF-85-67(P)(A), Ge neric Mechanical Design for Exxon Nurc1laqr 1kt Pum p BWR Reload Fut!L
  • EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model
  • ANF-89-98(P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs Aib 13 w Progress Energy

Approved Methodologies COLR TS References - Neutronic Analysis XN-NF-80-19(P)CA) Volume 1, Exxon Nuclear Methodology for oiling Water Reactors - Neutronic Methods for Design and Analysis.

  • XN-NF-80-1 9(P)(A) Volume 4, Exxon Nuclear.

Methodoinn\/ for Boiling W\Aater Reactors: Applcation of the ENU O/Aethodology to BWR Reloads.

  • EMF-2158(P)(A),,-Siemens Power Corporation Methodology for Boilinq Water Reactors: Evaluation and Validation of CAS 0-4/MICROBURN-B2.

o XN-NF-80-19(P)(A) Volume 3, Exxon Nuclear Methodology for boiling Water Reactors THERMEX:

Thermal Limits Methocology Summary Description G 14 . Progress Energy

Approved Methodologies COLR TS References - Transient Analysis o XN-NF-84-105(P)(A) Volume 1, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis.

o ANF-524(P)(A), ANF Critical Power Methodology for Boiling Water Reactors.

P ANF-913(P)(A) Volume 1, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses.

o ANF-1 358(P)(A), The Los's of Feedwater Heating Transient in Boiling Water Reactors.

d,&b 15 . Progress Energy

Approved Methodologies COLR TS References - CPR and LOCA P EMF-2209(P)(A) , SPCB Critical Power Correlation o EMF-2245(P)(A), Application of Siemens Power Corporation's Critical Power Correlations to Co-I ROIdetI ILFue,.

o EMF-2361 (P)(A), EXEM BWR-2000 ECCS Evaluation Model.

o EMF-2292(P)(A), ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients.

K3 Progress Energy d,4 16

Licensing Submittals Schedule

  • TS amendment request o Submit January 2007 o Request approval by January 2008

..ACPRP amendmeint reus I kilyy L-"I

5. IVbI JulyI I, IAEI I II L I ,;L II2007U i Submit July 2007 o Request approval by January 2008 Ab 17 Q Progress Energy

Summary.

  • Established ATRIUM-1 0 transition process OBrowns Ferry (2004) 0 Columbia Generating Station (2003)

I River Bend and Grand Gulf (2001)

  • NRC-approved methodology will be used for the transition
  • 'Progress Energy and Framatome ANP are committed to support the NRC's review 18 . Progress Energy