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| number = ML12076A165
| number = ML12076A165
| issue date = 01/11/2012
| issue date = 01/11/2012
| title = 01/11/2012 Meeting Slides - Harris Realistic LBLOCA Question Response Meeting
| title = Meeting Slides - Harris Realistic LBLOCA Question Response Meeting
| author name =  
| author name =  
| author affiliation = Progress Energy Carolinas, Inc
| author affiliation = Progress Energy Carolinas, Inc
| addressee name = Billoch-Colon A T
| addressee name = Billoch-Colon A
| addressee affiliation = NRC/NRR/DORL/LPLII-2
| addressee affiliation = NRC/NRR/DORL/LPLII-2
| docket = 05000400
| docket = 05000400
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:* Introductions
* Introductions
* Overview of Status
* Overview of Status
* Response to Individual questions from December 13th Meeting
* Response to Individual questions from December 13th Meeting
* Schedule
* Schedule
* Concluding Remarks Harris M5 RLBLOCA questions -NRC Meeting p.2 Progress Energy Progress
* Concluding Remarks Harris M5 RLBLOCA questions - NRC Meeting p.2 ~ Progress Energy
* Mike
 
* John
Progress Energy
* Dave
* Mike Blom
* Dean AREVA
* John Caves
* Bob
* Dave Corlett
* Bert
* Dean Tibbitts AREVA
* Mireille
* Bob Baxter
* Nithian
* Bert Dunn
* Gayle Harris M5 RLBLOCA questions -NRC Meeting p. 3 Progress Energy Cycle 18 Feed Assembly Zircaloy 4 M5 Clad LBLOCA Method EMF-2087 ANP-3011 based on EMF-2103 PCT 2081 OF 1919 OF Transient 7% <3% Oxidation Safety Analysis 2958 2958 Core Power (MW) Harris M5 RLBLOCA questions -NRC Meetingp.4 Progress Energy Appendix K 2958 Zircaloy 4 2081 7.0 EMF-2103 Best 2993 Zircaloy4 1887 2.02 Rev 0 Estimate EMF-2103, i 2958 1930 11.95 Rev 0 + Estimate Trans Pkg Best 2958 M5 1919 2.94 Estimate Harris M5 RLBLOCA questions -NRC Meeting p.5 L Progress Energy Additional Sensitivity Cases Run (Response to Question 1) Discussions of Questions 2 to 6 and responses prepared Harris M5 RLBLOCA questions -NRC Meeting
* Mireille Cortes
* p.6 Progress Energy
* Nithian Nithianandan
* Characterize droplet shattering without modeling the fuel Show the sensitivity of the fuel relocation to fuel relocation packing factor Consider including a range of packing factors 30 -80% Utilize the Harris Nuclear Plant (HNP) limiting-peak clad temperature (PCT) case Harris M5 RLBLOCA questions -NRC Meetingp. 7 Progress Energy*
* Gayle Elliott (IQ~            Harris M5 RLBLOCA questions - NRC Meeting
co. Q.
: p. 3 ~ Progress Energy
----Question #1 Expand Sensitivity Study Table 1: 0.5 Packing Fraction Cases with Hot Assembly Rupture Harris M5 RLBLOCA questions -NRC Meeting p.9 Progress Energy Question #1 Expand Sensitivity cont'd Table 2: 0.6 Packing Fraction Cases with Hot Assembly Rupture Harris M5 RlBlOCA questions -NRC Meeting p.1 0 Progress Energy
 
--------------------Question #1 Expanded Sensitivity cont'd Table 3: 0.7 Packing Fraction Cases with Hot Assembly Rupture Harris M5 RLBLOCA questions -NRC Meeting* p. 11 Progress Energy
Cycle 18 Feed Assembly             Zircaloy 4                   M5 Clad LBLOCA Method             EMF-2087               ANP-3011 based on EMF-2103 PCT                         2081 OF                   1919 OF Transient                       7%                     <3%
: c.
Oxidation Safety Analysis               2958                     2958 Core Power (MW)
Histogram of PCT with Droplet Shattering Activated -0.7 Packing Harris M5 RLBLOCA questions -NRC Meeting* p.13 Progress Energy I l"""-Ll) I C1.) 1 I (/) co u III::tI ......--E Q. (/) t:c: '';; Q)0 Q) a. :2!: (/) C1.) z C1.) I III t: :J 0 ...., '';; IIIco Q) :::::I a. C1.) 0E u ....JC1.) aJ...., ....J c::tn It)c: :2!:.-III'C ''::: "C n:J:r:co-CJ C1.) I :J...., a. :J
~          Harris M5 RLBLOCA questions - NRC Meeting p.4 ~ Progress Energy
--------------------Question #1 Maximum Packing Factor [PF] Considerations PBF -Power Burst Facility Only 1 gamma scanning data point at 80% packing fraction and it is at 30% strain Data results are in question due to material movement during the handling of the test rods Micrographies measurement is more accurate compared to gamma scanning PBF micrographic data shows 70% PF for rupture strain below 50% AREVA estimates 45% PF for strains near 70% Harris M5 RLBLOCA questions -NRC Meeting p.15 Energy
 
----------------------Question #1 Maximum PF Considerations conl'd Packing Fraction vs. Rupture Strain Note: The balloonBalloon filling rate (0/0) by relocated fragments filling rate is interpreted as packing* fraction, 80 ......... --___0 ClI 0 r e. . ..... ----....0 o &sect; --..._-. ..... '';:;
Appendix K       2958               Zircaloy 4 2081   7.0 EMF-2103   Best             2993               Zircaloy4 1887   2.02 Rev 0       Estimate EMF-2103, i Best            2958                           1930   11.95 Rev 0 +     Estimate Trans Pkg ANP-3011    Best             2958               M5         1919   2.94 Estimate Harris M5 RLBLOCA questions - NRC Meeting p.5 L Progress Energy
* 50 LL. 40 o PBF/LOC-gammascanning:i
                                                                  ~
* PBF/LOC-micrographies 30
* Additional Sensitivity Cases Run (Response to Question 1)
* FR Upper bound IRSN sensitivity calculation 20 IRSN reference calculation 10. __ Packing Factor Needed for Equal Heat Fluxes: 1/(1 +*) o 20 30 40 50 60 70 80 Ballooning (%) Harris M5 RlBlOCA questions -NRC Meeting p.16 Progress Energy FR-2 (E-5) 61.5% Test maximized rupture strain and had very small rupture opening Halden IFA-92 GWd 650.4 --.......-------------.--Halden IFA-,r Not measured, but --90 GWd as similar to 650.4 (N EA report) Halden Test No relocation (no strain) 60GWd IFA-650.10 Harris M5 RLBLOCA questions -NRC Meetingp.17 Progress Energy Studsvik Tests -Provide results for burn-ups at 70 GWd, show no fuel in the ruptured region as it was all lost out of the rupture KfK/FR2 Tests -Only rod E5 showed a PF of 61.5%. During the swelling and rupture of the rod, the cladding expanded to make a seal around the 10 of the container tube, thus invalidating any other results Harris M5 RLBLOCA questions -NRC Meeting p.18 Progress Energy Q. I/) r::: o '';:; I/) Q) ::::s C" <C (,) o ...J III ...J 0::: It) I/) 'E ctJ J:
* Discussions of Questions 2 to 6 refined and responses prepared
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*~          Harris M5 RLBLOCA questions - NRC Meeting p.6 ~ Progress Energy
'""'"N . a..
* Characterize droplet shattering model without modeling the fuel relocation
50%, as in ANP-3011 P, is an appropriate PF based on the Halden test results, which are the most reliable information available
* Show the sensitivity of the fuel relocation to fuel relocation packing factor
* 70% PF is an upper limit (based on older PBF for the strain range seen in the HNP plant Sensitivity study concludes base case is conservative and no bias is proposed (with droplet shattering) Harris M5 RLBLOCA questions -NRC Meeting p.22 Progress Energy 
* Consider including a range of packing factors 30 - 80%
-----Question #2 Droplet Shattering Model Address whether droplet shattering is calculated on all flow blockage (non-vertical) surfaces in the S-RELAP5 calculation. If not, provide the flow blockage surfaces which are assumed to cause droplet shattering. Harris M5 RLBLOCA questions -NRC Meetingp.23 Progress Energy* 
* Utilize the Harris Nuclear Plant (HNP) limiting-peak clad temperature (PCT) case
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Question #1 Expand Sensitivity Study Table 1: 0.5 Packing Fraction Cases with Hot Assembly Rupture Harris M5 RLBLOCA questions - NRC Meeting p.9 ~ Progress Energy
 
Question #1 Expand Sensitivity cont'd
            --~--.--
Table 2: 0.6 Packing Fraction Cases with Hot Assembly Rupture
                                                                ,,~
Harris M5 RlBlOCA questions - NRC Meeting p.1 0 Progress Energy
 
Question #1 Expanded Sensitivity cont'd
- - - - --   - ~~--       - -                                 - - - - -- - -          -  -  -
Table 3: 0.7 Packing Fraction Cases with Hot Assembly Rupture
  * ~                  Harris M5 RLBLOCA questions - NRC Meeting
: p. 11     ~ Progress Energy
 
c.*
Histogram of PCT with Droplet Shattering Activated - 0.7 Packing Fraction
*~                Harris M5 RLBLOCA questions - NRC Meeting p.13 ~ Progress Energy
 
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Question #1 Maximum Packing Factor [PF] Considerations PBF - Power Burst Facility
* Only 1 gamma scanning data point at 80%
packing fraction and it is at 30% strain
* Data results are in question due to material movement during the handling of the test rods
* Micrographies measurement is more accurate compared to gamma scanning
* PBF micrographic data shows 70% PF for rupture strain below 50%
* AREVA estimates 45% PF for strains near 70%
  ~                    Harris M5 RLBLOCA questions - NRC Meeting
(~
: p. 15 ~, Progress Energy
 
Question #1 Maximum PF Considerations conl'd Packing Fraction vs. Rupture Strain Note: The balloon Balloon filling rate (0/0) by relocated fragments                           filling rate is interpreted as packing 90'
* r ..
fraction, 80 .........e- - ___0
      &sect; 60 70                    o ClI 0
                                                      .                   0
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* FR-2
                - Upper bound
                ~ IRSN sensitivity calculation 20 IRSN reference calculation
: 10. __ Packing Factor Needed for Equal Heat Fluxes: 1/(1 + )
o 20        30          40          50     60        70              80 Ballooning (%)
Harris M5 RlBlOCA questions - NRC Meeting p.16  ~ Progress Energy
 
FR-2 (E-5)                          61.5%                                I Test maximized rupture strain and had very small rupture opening Halden IFA-                        53%                                   92 GWd 650.4 Halden IFA-                     ,r  Not measured, but observed            -- 90 GWd 650.9                              as similar to 650.4 (N EA report)
Halden Test                        No relocation (no strain)              60GWd IFA-650.10
~                                Harris M5 RLBLOCA questions - NRC Meeting p.17 ~ Progress Energy
* Studsvik Tests - Provide results for burn-ups at 70 GWd, show no fuel in the ruptured region as it was all lost out of the rupture
* KfK/FR2 Tests - Only rod E5 showed a PF of 61.5%. During the swelling and rupture of the rod, the cladding expanded to make a seal around the 10 of the container tube, thus invalidating any other results Harris M5 RLBLOCA questions - NRC Meeting p.18 ~ Progress Energy
 
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* 50%, as in ANP-3011 P, is an appropriate PF based on the Halden test results, which are the most reliable information available
* 70% PF is an upper limit (based on older PBF data) for the strain range seen in the HNP plant cases
* Sensitivity study concludes base case is conservative and no bias is proposed (with droplet shattering)
                                                              ~
Harris M5 RLBLOCA questions - NRC Meeting p.22 ~ Progress Energy
 
Question #2 Droplet Shattering Model Address whether droplet shattering is calculated on all flow blockage (non-vertical) surfaces in the S-RELAP5 calculation. If not, provide the flow blockage surfaces which are assumed to cause droplet shattering.
  ~
Harris M5 RLBLOCA questions - NRC Meeting p.23 ~ Progress Energy
 
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Page 122 of ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis" states, In the present model, the rupture blockage ratio [which is correlated to the number of droplets to yield a maximum atomization factor], 8, is taken from the swelling and rupture correlation.
Page 122 of ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis" states, In the present model, the rupture blockage ratio [which is correlated to the number of droplets to yield a maximum atomization factor], 8, is taken from the swelling and rupture correlation.
* Address whether droplet shattering is calculated only against the hot pin rupture, or the additional flow blockage areas (i.e., balloon/burst regions, spacer grids, etc.) assumed to be present upstream of the hot pin rupture location.
* Address whether droplet shattering is calculated only against the hot pin rupture, or the additional flow blockage areas (i.e., balloon/burst regions, spacer grids, etc.) assumed to be present upstream of the hot pin rupture location.
* If the additional flow blockage areas are not based on pre-transient core geometry, discuss how the locations and sizes of flow blockages are distributed. Harris M5 RLBLOCA questions -NRC Meeting p.25 ",. Progress Energy CD N. a. C') c: CI> CI> U 0::: 2 "N. Q.
* If the additional flow blockage areas are not based on pre-transient core geometry, discuss how the locations and sizes of flow blockages are distributed.
co N . Q.
(N~                    Harris M5 RLBLOCA questions - NRC Meeting     ",. Progress Energy p.25 ~
On page 123 of ANP-3011 (P), it is stated, It can be seen that the code predicted the peak cladding temperature variation well. The data is so tightly clustered that the degree of agreement is difficult to ascertain. Please tabulate the data to provide a more quantitative indication. Address how well the S-RELAP5 modification predicted the data. Harris M5 RLBLOCA questions -NRC Meeting p.29 Progress Energy
 
----------------Question #4 Benchmark to SR Data cont'd An Excel spreadsheet that contained blockage Test 61607 data has been placed in PGN FTP site for NRC to retrieve for further evaluation Figures 6-14 and 6-15 in ANP-3011 P show S-RELAP5 conservatively predicted PCT compared to blockage test data for the FLECHT-SEASET and REBEKA-6 tests Additional FLECHT-SEASET test benchmarks, 61509 and 61607, are presented on the next two slides COBRA-TF (NUREG/CR-4166) modeled all expected dimensional flow phenomena at rupture location, including flow diversion The figures show that S-RELAP5 conservatively predicts cladding response compared to the COBRA-TF results Harris M5 RLBLOCA questions -NRC Meetingp.30 Progress Energy M. c..
CD N   .
N M. a.
a.
Comparative data demonstrate the global effects of the droplet shattering phenomena; however, the correlation as implemented discriminates between large and small droplets and the behavioral differences between the two. Validate droplet size distribution as implemented in model. Explain how the Sugimoto/Murao correlation applies to the scenario in which it is applied. Harris M5 RLBLOCA questions -NRC Meetingp.33 Progress Energy M a.
C')
Question #6 Droplet shattering impacts on Heat ----_.-------Explain how droplet shattering model incorporates the following droplet-dependent heat transfer effects: Inter-phase heat transfer Fluid-structural interactions including cladding, balloon, and spacer heat transfer to coolant Validate heat transfer modeling for these separate effects Harris M5 RLBLOCA questions -NRC Meetingp.35 Progress Energy (0 M. Q.
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00 M. Co 100 90 bur5t rod quench (mm) grid 4 i f! A....." 80 70 60 11k 50 grid 5 !30 20 10 . o 0 -30 , 0 30 60 I I 90 \.. R 120 150 R 180 135 $ 210 210 270 -I 300 time fsl no. 29 40V I93.5:5.1I sequence '7":{(V 1800 1850 \1910' burst 1950 2050 2150 ZZZ REBEKA-6 Test: Rupture rod cladding temp. & pin j -ltDI burst plane t1 t2 t] t, Fig. 7 quenching of burst claddLngs (schemat:lc) 1000 900 I? 800 i700 600 SOD .r 0400:a 300 200 100 a Harris M5 RLBLOCA questions -NRC Meeting* p.39 Progress Energy Ia)(ial level: 21 oomIDJ REBEKA-7 Maximum blockage...., 70 % .. GI:ltoX. E cv +J 900 600 700 600 soo 400 300 200 100 0 01 c "'0 o o--o t , : Upstream of 90 BO 70 60 to 50 ..c Near .. QI 40... rupture --+----tII11i30'" cu '" 00oO('X-nx)O... 20a. max. flow blockage: -70 %10 0 r0 30 60 90 120 150 180 210 240 time. s axjallevel: 1810mm Harris M5 RLBLOCA questions -NRC Meeting* p.40 Progress Energy FEBA Tests 1000 r.--------------, n loa 'L 8110 600III t :!Do LEVEL 2.112 ... 410 i".1 0, I 800 III .. c I... :lOll mo 400 2,12 m 114 in.1 HOG Ol: o 13101 ;:;; II: !I tOO :: ...* 0' 71100 CI 1110 2011 300 400 \ TIME t-;I 1700 { illIG ..!) II:toO " III bIIICIfJ .. =-] 100 FL.OODING RATE .. Q,038 ....._ it,I m.JHeJ 'InssuPIlE .. I.AD W. 1,$' pwi,1 SERIE$ II: TEIiT 2Z!1 .. CftlD U AOE fMI lII"'ILOCKfD !WNDLE D CLADOtN(II . "'0 1(1 ; 2.az .. [ao ... 1 lilESTZH
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* GRID SPACERS . " OCKE:D BI1NOl E t3 X l FlOOSl ILOCKAG! ... , ILEVEL 1.02111 i80 ir'l.1 BLOC:K.wlE IllAT.O 80'" t t t to BYPA&.I 6 BLOCK.ED 00000 + SLlEi'll': lao0 00X UNDERNEATtoil 00 ""0 Upstream of Harris M5 RLBLOCA questions -NRC Meetingp.41 Progress Energy
~
* Droplet shatter model is implemented in a conservative manner Benchmarking demonstrates that sensitivity study model provides conservative predictions ". Harris M5 RlBlOCA questions -NRC Meeting p.42 Progress Energy'. 'h ,;Ii F__ _
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Best estimate to upper bound packing factor is 50% to 70% The response of PCT over a range of PF shows a smooth response to changes AREVA's sensitivity method has been successfully benchmarked against applicable research AREV A's treatment of the SRR phenomenon is applied in a conservative manner within ANP-3011 A PCT of 1919 from base case is therefore defensible Harris M5 RLBLOCA questions -NRC Meetingp.43 Progress Energy Discussion of questions received on January 10th , 2012. Harris M5 RlBlOCA questions -NRC Meetingp.44 L Progress Energy
2
 
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On page 123 of ANP-3011 (P), it is stated, It can be seen that the code predicted the peak cladding temperature variation well. The data is so tightly clustered that the degree of agreement is difficult to ascertain. Please tabulate the data to provide a more quantitative indication.
Address how well the S-RELAP5 modification predicted the data.
Harris M5 RLBLOCA questions - NRC Meeting p.29 ~ Progress Energy
 
Question #4 Benchmark to SR Data cont'd
* An Excel spreadsheet that contained blockage Test 61607 data has been placed in PGN FTP site for NRC to retrieve for further evaluation
* Figures 6-14 and 6-15 in ANP-3011 P show S-RELAP5 conservatively predicted PCT compared to blockage test data for the FLECHT-SEASET and REBEKA-6 tests
* Additional FLECHT-SEASET test benchmarks, 61509 and 61607, are presented on the next two slides
* COBRA-TF (NUREG/CR-4166) modeled all expected multi dimensional flow phenomena at rupture location, including flow diversion
* The figures show that S-RELAP5 conservatively predicts cladding response compared to the COBRA-TF results
  .~                    Harris M5 RLBLOCA questions - NRC Meeting p.30       ~ Progress Energy
 
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Comparative data demonstrate the global effects of the droplet shattering phenomena; however, the correlation as implemented discriminates between large and small droplets and the behavioral differences between the two. Validate droplet size distribution as implemented in model. Explain how the Sugimoto/Murao correlation applies to the scenario in which it is applied.
(N~              Harris M5 RLBLOCA questions - NRC Meeting p.33 ~ Progress Energy
 
~
M a.
 
Question #6 Droplet shattering impacts on Heat Transfer Explain how droplet shattering model incorporates the following droplet-dependent heat transfer effects:
* Inter-phase heat transfer
* Fluid-structural interactions including cladding, balloon, and spacer heat transfer to coolant
* Validate heat transfer modeling for these separate effects
  ~                  Harris M5 RLBLOCA questions - NRC Meeting p.35 ~ Progress Energy
 
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                                                                                                  - I 100                                                                   $
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                              -30      0      30 60    90    120    150  180  210  210
*~                                  Harris M5 RLBLOCA questions - NRC Meeting p.39       ~ Progress Energy
 
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                                  ~ 600 GI    700
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                                                            ~
: Upstream of rupture 0
90 Maximum blockage...., 70 %                  BO                           (3000000 C)OOO( -~O 70 00 o (lX-)O 60                           OOOC)C~O cx)cx)O~jO to
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*~
                                                                                      ~
Harris M5 RLBLOCA questions - NRC Meeting p.40 ~            Progress Energy
 
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~                                          Harris M5 RLBLOCA questions - NRC Meeting p.41 ~ Progress Energy
* Droplet shatter model is implemented in a conservative manner
* Benchmarking demonstrates that sensitivity study model provides conservative predictions "Ir.p-                                                  .        ~~
  ~.':J
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Harris M5 RlBlOCA questions - NRC Meeting p.42 Progress Energy
* Best estimate to upper bound packing factor is 50% to 70%
* The response of PCT over a range of PF shows a smooth response to changes
* AREVA's sensitivity method has been successfully benchmarked against applicable research
* AREV A's treatment of the SRR phenomenon is applied in a conservative manner within ANP-3011
* A PCT of 1919 from base case is therefore defensible
~                Harris M5 RLBLOCA questions - NRC Meeting      ~
p.43 ~ Progress Energy
 
Discussion of questions received on January 10th , 2012.
~              Harris M5 RlBlOCA questions - NRC Meeting p.44 L Progress Energy
                                                              ~
* Progress Energy will docket the responses
* Progress Energy will docket the responses
* Projected docket date is January 20, 2012
* Projected docket date is January 20, 2012
* Target date for new round of questions to docketed is the week of February 13th Harris M5 RLBLOCA questions -NRC Meeting p.45 Progress Energy
* Target date for new round of questions to be docketed is the week of February 13th
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Latest revision as of 11:10, 10 March 2020

Meeting Slides - Harris Realistic LBLOCA Question Response Meeting
ML12076A165
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/11/2012
From:
Progress Energy Carolinas
To: Billoch-Colon A
Plant Licensing Branch II
Billoch-Colon, Araceli
Shared Package
ML12076A140 List:
References
TAC ME6999
Download: ML12076A165 (48)


Text

  • Introductions
  • Overview of Status
  • Response to Individual questions from December 13th Meeting
  • Schedule
  • Concluding Remarks Harris M5 RLBLOCA questions - NRC Meeting p.2 ~ Progress Energy

Progress Energy

  • Mike Blom
  • John Caves
  • Dave Corlett
  • Dean Tibbitts AREVA
  • Bob Baxter
  • Bert Dunn
  • Mireille Cortes
  • Nithian Nithianandan
  • Gayle Elliott (IQ~ Harris M5 RLBLOCA questions - NRC Meeting
p. 3 ~ Progress Energy

Cycle 18 Feed Assembly Zircaloy 4 M5 Clad LBLOCA Method EMF-2087 ANP-3011 based on EMF-2103 PCT 2081 OF 1919 OF Transient 7% <3%

Oxidation Safety Analysis 2958 2958 Core Power (MW)

~ Harris M5 RLBLOCA questions - NRC Meeting p.4 ~ Progress Energy

Appendix K 2958 Zircaloy 4 2081 7.0 EMF-2103 Best 2993 Zircaloy4 1887 2.02 Rev 0 Estimate EMF-2103, i Best 2958 1930 11.95 Rev 0 + Estimate Trans Pkg ANP-3011 Best 2958 M5 1919 2.94 Estimate Harris M5 RLBLOCA questions - NRC Meeting p.5 L Progress Energy

~

  • Additional Sensitivity Cases Run (Response to Question 1)
  • Discussions of Questions 2 to 6 refined and responses prepared
  • ~ Harris M5 RLBLOCA questions - NRC Meeting p.6 ~ Progress Energy
  • Characterize droplet shattering model without modeling the fuel relocation
  • Show the sensitivity of the fuel relocation to fuel relocation packing factor
  • Consider including a range of packing factors 30 - 80%
  • Utilize the Harris Nuclear Plant (HNP) limiting-peak clad temperature (PCT) case

~

Harris M5 RLBLOCA questions - NRC Meeting

(~

p. 7 ~ Progress Energy

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Question #1 Expand Sensitivity Study Table 1: 0.5 Packing Fraction Cases with Hot Assembly Rupture Harris M5 RLBLOCA questions - NRC Meeting p.9 ~ Progress Energy

Question #1 Expand Sensitivity cont'd

--~--.--

Table 2: 0.6 Packing Fraction Cases with Hot Assembly Rupture

,,~

Harris M5 RlBlOCA questions - NRC Meeting p.1 0 ~ Progress Energy

Question #1 Expanded Sensitivity cont'd

- - - - -- - ~~-- - - - - - - -- - - - - -

Table 3: 0.7 Packing Fraction Cases with Hot Assembly Rupture

  • ~ Harris M5 RLBLOCA questions - NRC Meeting
p. 11 ~ Progress Energy

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Histogram of PCT with Droplet Shattering Activated - 0.7 Packing Fraction

  • ~ Harris M5 RLBLOCA questions - NRC Meeting p.13 ~ Progress Energy

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Question #1 Maximum Packing Factor [PF] Considerations PBF - Power Burst Facility

  • Only 1 gamma scanning data point at 80%

packing fraction and it is at 30% strain

  • Data results are in question due to material movement during the handling of the test rods
  • Micrographies measurement is more accurate compared to gamma scanning
  • PBF micrographic data shows 70% PF for rupture strain below 50%
  • AREVA estimates 45% PF for strains near 70%

~ Harris M5 RLBLOCA questions - NRC Meeting

(~

p. 15 ~, Progress Energy

Question #1 Maximum PF Considerations conl'd Packing Fraction vs. Rupture Strain Note: The balloon Balloon filling rate (0/0) by relocated fragments filling rate is interpreted as packing 90'

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~ IRSN sensitivity calculation 20 IRSN reference calculation

10. __ Packing Factor Needed for Equal Heat Fluxes: 1/(1 + )

o 20 30 40 50 60 70 80 Ballooning (%)

Harris M5 RlBlOCA questions - NRC Meeting p.16 ~ Progress Energy

FR-2 (E-5) 61.5% I Test maximized rupture strain and had very small rupture opening Halden IFA- 53% 92 GWd 650.4 Halden IFA- ,r Not measured, but observed -- 90 GWd 650.9 as similar to 650.4 (N EA report)

Halden Test No relocation (no strain) 60GWd IFA-650.10

~ Harris M5 RLBLOCA questions - NRC Meeting p.17 ~ Progress Energy

  • Studsvik Tests - Provide results for burn-ups at 70 GWd, show no fuel in the ruptured region as it was all lost out of the rupture
  • KfK/FR2 Tests - Only rod E5 showed a PF of 61.5%. During the swelling and rupture of the rod, the cladding expanded to make a seal around the 10 of the container tube, thus invalidating any other results Harris M5 RLBLOCA questions - NRC Meeting p.18 ~ Progress Energy

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  • 50%, as in ANP-3011 P, is an appropriate PF based on the Halden test results, which are the most reliable information available
  • 70% PF is an upper limit (based on older PBF data) for the strain range seen in the HNP plant cases
  • Sensitivity study concludes base case is conservative and no bias is proposed (with droplet shattering)

~

Harris M5 RLBLOCA questions - NRC Meeting p.22 ~ Progress Energy

Question #2 Droplet Shattering Model Address whether droplet shattering is calculated on all flow blockage (non-vertical) surfaces in the S-RELAP5 calculation. If not, provide the flow blockage surfaces which are assumed to cause droplet shattering.

~

Harris M5 RLBLOCA questions - NRC Meeting p.23 ~ Progress Energy

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Page 122 of ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis" states, In the present model, the rupture blockage ratio [which is correlated to the number of droplets to yield a maximum atomization factor], 8, is taken from the swelling and rupture correlation.

  • Address whether droplet shattering is calculated only against the hot pin rupture, or the additional flow blockage areas (i.e., balloon/burst regions, spacer grids, etc.) assumed to be present upstream of the hot pin rupture location.
  • If the additional flow blockage areas are not based on pre-transient core geometry, discuss how the locations and sizes of flow blockages are distributed.

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On page 123 of ANP-3011 (P), it is stated, It can be seen that the code predicted the peak cladding temperature variation well. The data is so tightly clustered that the degree of agreement is difficult to ascertain. Please tabulate the data to provide a more quantitative indication.

Address how well the S-RELAP5 modification predicted the data.

Harris M5 RLBLOCA questions - NRC Meeting p.29 ~ Progress Energy

Question #4 Benchmark to SR Data cont'd

  • An Excel spreadsheet that contained blockage Test 61607 data has been placed in PGN FTP site for NRC to retrieve for further evaluation
  • Figures 6-14 and 6-15 in ANP-3011 P show S-RELAP5 conservatively predicted PCT compared to blockage test data for the FLECHT-SEASET and REBEKA-6 tests
  • Additional FLECHT-SEASET test benchmarks, 61509 and 61607, are presented on the next two slides
  • COBRA-TF (NUREG/CR-4166) modeled all expected multi dimensional flow phenomena at rupture location, including flow diversion
  • The figures show that S-RELAP5 conservatively predicts cladding response compared to the COBRA-TF results

.~ Harris M5 RLBLOCA questions - NRC Meeting p.30 ~ Progress Energy

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Comparative data demonstrate the global effects of the droplet shattering phenomena; however, the correlation as implemented discriminates between large and small droplets and the behavioral differences between the two. Validate droplet size distribution as implemented in model. Explain how the Sugimoto/Murao correlation applies to the scenario in which it is applied.

(N~ Harris M5 RLBLOCA questions - NRC Meeting p.33 ~ Progress Energy

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Question #6 Droplet shattering impacts on Heat Transfer Explain how droplet shattering model incorporates the following droplet-dependent heat transfer effects:

  • Inter-phase heat transfer
  • Fluid-structural interactions including cladding, balloon, and spacer heat transfer to coolant
  • Validate heat transfer modeling for these separate effects

~ Harris M5 RLBLOCA questions - NRC Meeting p.35 ~ Progress Energy

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  • ~ Harris M5 RLBLOCA questions - NRC Meeting p.39 ~ Progress Energy

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Harris M5 RLBLOCA questions - NRC Meeting p.40 ~ Progress Energy

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~ Harris M5 RLBLOCA questions - NRC Meeting p.41 ~ Progress Energy

  • Droplet shatter model is implemented in a conservative manner
  • Benchmarking demonstrates that sensitivity study model provides conservative predictions "Ir.p- . ~~

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Harris M5 RlBlOCA questions - NRC Meeting p.42 ~ Progress Energy

  • Best estimate to upper bound packing factor is 50% to 70%
  • The response of PCT over a range of PF shows a smooth response to changes
  • AREVA's sensitivity method has been successfully benchmarked against applicable research
  • AREV A's treatment of the SRR phenomenon is applied in a conservative manner within ANP-3011
  • A PCT of 1919 from base case is therefore defensible

~ Harris M5 RLBLOCA questions - NRC Meeting ~

p.43 ~ Progress Energy

Discussion of questions received on January 10th , 2012.

~ Harris M5 RlBlOCA questions - NRC Meeting p.44 L Progress Energy

~

  • Progress Energy will docket the responses
  • Projected docket date is January 20, 2012
  • Target date for new round of questions to be docketed is the week of February 13th

~,..

Harris M5 RLBLOCA questions - NRC Meeting p.45 ~ Progress Energy

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