HNP-12-028, Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028

Realistic LBLOCA Question Response Meeting Handout, Enclosure 3 to HNP-12-028

ML12073A293
Person / Time
Site:	Harris
Issue date:	01/11/2012
From:	NGG Holdings, Progress Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
HNP-12-028, TAC ME6999
Download: ML12073A293 (49)

Text

HNP-12-028 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63 License Amendment Request for Revision to Technical Specification Core Operating Limits Report References for Realistic Large Break LOCA Analysis TAC NO. ME6999 Request for Withholding of Proprietary Information Enclosure 3 Harris Realistic LBLOCA Question Response Meeting Handout (Non-Proprietary)

HarsRelsi LBOA Qusto Rsone etig January 11, 2012 Rockville, MD

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AREVAI Think Fleet . .. . . . . . a & . P m..

• Introductions

• Overview of Status

• Response to Individual questions from December 13th Meeting Schedule Concluding Remarks

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Patiipnt Progress Energy

" Mike Blom

• John Caves

• Dave Corlett

• Dean Tibbitts AREVA

• Bob Baxter

• Bert Dunn

• Mireille Cortes

• Nithian Nithianandan

• Gayle Elliott Harris M5 RLBLOCA questions - NRC Meeting p.3

PG Reoa Sm r

-urn Feed Assembly Zircaloy 4 Cyl 18 M5 Clad LBLOCA Method EMF-2087 AN P-30 11 based on EMF-2103 PCT 2081 OF 1919 OF Transient 7% <3%

Oxidation Safety Analysis 2958 2958 Core Power (MW) mv'o,

"- Harris M5 RLBLOCA questions - NRC Meeting p.4 Q Progrs Energ

• OC Hitr Method Method Core Clad Trnin Type Power Local*

(MW)

EMF-2103 Best 2993 Zircaloy 4 1887 2.02 Rev 0 Estimate ANP-3011 Best 2958 M5 1919 2.94 Estimate MNA.,.~ Harris M5 RLBLOCA questions - NRC Meeting p.5 Voms~eg

Ovrve of Qusto Respons

" Additional Sensitivity Cases Run (Response to Question 1)

• Discussions of Questions 2 to 6 refined and responses prepared Ch.,,10'. ý-, Harris M5 RLBLOCA questions - NRC Meeting p.6 Q rlgrSSE_ rg

• 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 -- NRCc Meeting p.7 a Po En

Qusin#

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Qusto #1 Exan Sesiivt Std Table 1: 0.5 Packing Fraction Cases with Hot Assembly Rupture M 0""'. Harris M5 RLBLOCA questions - NRC Meeting p.9 Q PrMrmssnEnrg

Exan Sestvt cont Table 2: 0.6 Packing Fraction Cases with Hot Assembly Rupture M r. ," Harris M5 RLBLOCA questions - NRC Meeting p.10 Q2ProgressEner

Quetio #1 Exane gao Sestvt* S Table 3: 0.7 Packing Fraction Cases with Hot Assembly Rupture Harris M5 RLBLOCA questions - NRC Meeting p.11 ProgressEnergy

• uso a#a ae stvt gtd to umar gfExagde Harris M5 RLBLOCA questions - NRC Meeting p.12 Q2PmressEmngy

Qesto #1 S St' Histogram of PCT with Droplet Shattering Activated - 0.7 Packing Fraction

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Qusto #1

• St' Rupture node cladding temperature response for limiting Case-57 INCA

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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 a gressEwney

Qusto #1 Max um PF Cosdrain S S Packing Fraction vs. Rupture Strain Note: The balloon Balloon filling rate (%)by relocated fragments filling rate is

• %A - - interpreted as packing fraction.

80 70 0 0Ca1-.... _ ...

C 60 ARF 0

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50 0O 40 o PBFILOC-gamma'scanning 0r

• PBFILOC-micrographies 30 A FR-2 Upper bound 20 IRSN sensitivity calculation

' IRSN reference calculation 10 - - Packing FactorNeeded for Equal Heat Fluxes: 1/(1+C) 0 20 30 40 50 60 70 80 Ballooning (%)

IAO

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Qusto #1 Max u C SFnieatin S S S a Masue PFI C m et Halden IFA- 53% 92 GWd 650.4 Halden Test No relocation (no strain) 60 GWd IFA-650.1 0 M 0", "ý, Harris M5 RLBLOCA questions - NRC Meeting p.17 ~mrs~eg

• 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 ID of the container tube, thus invalidating any other results eA'_Harris M5 RIB LOCA questions - NRC Meeting p.18Nk' Progr=s Energ

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Qusto #1 N Rutr Stra i v s.

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Qusto #1 e S

• Harris M5 RLBLOCA questions - NRC Meeting p.21 Pwr Esmn

• 50%, as in ANP-301 1P, 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 0 Sensitivity study concludes base case is conservative and no bias is proposed (with droplet shattering)

Harris M5 RLBLOCA questions - NRC Meeting p.22 Prnlu* Energ

Qusto #2 Drpe S attrn Moe 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.

M0."-, Harris M5 RLBLOCA questions - NRC Meeting p.23 a ProgressE

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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], C, 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.

Harris M5 RLBLOCA questions - NRC Meeting P.25 jrMg Energy

Qusto #3

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Qusto #4 Becmr to Swl/utr [SR Dat 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 Prg Energ

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" 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-301 1P 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 Progess Energ

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Qusto #5 Appiato of0 Sugmt/ a correlation 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 Meeting p.33 P/g Energ

Qusto #5 Applica0i0 ofSuio/Mro CSorrelato

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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 M 0"... Harris M5 RLBLOCA questions - NRC Meeting p.35 & Prorss Energy

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Qusto #6a contS REBEKA-6 Test: Rupture rod cladding temp. & pin pressure I

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plane tj1 t2 N3 4 time '4  ; ti t2 t3 ti Frg. 7 Premature quenching of burnt Zircaloy claddLnge (schematic) quench Tr--

I000 100. burst start of flodng sequenc 9 00o SO- rod no. burst Is 700- 70- (4) 19, 600 , so- 2),19' 1500 50 '2 400- 40 5 undetformed' 300-0 30- 93.5s rod no. 54 100 - !0, 135 s 0-30 60 90 120 150 10O 210 240 270 300 HIMe (a)

Harris M5 RLBLOCA questions - NRC Meeting p.39 r2mgs=nrg

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axial level: 2100mm I 900 Boo 700 600 500 E 400 300 REBEKA-7 Results: 200 100 0

90 Maximum blockage - 70 % 80 70 60

,. 50 40 30 20 0.

10 0

0 30 60 90 120 150 180 210 240 time, s

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Qusto #6

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FEBA Tests Results FLOO1UNOG RATE T AM mine (IS mJmaW urn Pmsmm: - we W si -

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Upstream of blockage Harris M5 RLBLOCA questions - NRC Meeting p.41

• Progress Eiergy

° 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 Pr* gEsswEnefr

Coclsin

• 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

• AREVA's treatment of the SRR phenomenon is applied in a conservative manner within ANP-301 1

• A PCT of 1919 from base case is therefore defensible M 0".." Harris M5 RLBLOCA questions - NRC Meeting p.43 Q roress=Energ

Ne Soun of Questin Discussion of questions received on January 10th, 201 2.

Harris M5 RLBLOCA questions - NRC Meeting p.44 PrgressnEnMry

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 m 0",, ý,

- Harris M5 RLBLOCA questions - NRC Meeting p.45 EmssEnerg

Suplmna Slies S upplemental Slides Harris M5 RLBLOCA questions - NRC Meeting p.46 Q Press Eneg

Suplmeta Slde Qusto #5 Harris M5 RLBLOCA questions - NRC Meeting p. 47 Progress Eerg

Supemna Slde Question#

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