ge si-hitachi c. - nrc.gov · si-hitachi ge hitachi nuclear energy james c. kinsey vice president,...

Si-HITACHIGE Hitachi Nuclear Energy

James C. KinseyVice President, ESBWR Licensing

PO Box 780 M/C A-55Wilmington, NC 28402-0780USA

T 910 675 5057F 910 362 5057

MFN 07-695 Docket No. 52-010

December 21, 2007

U.S. Nuclear Regulatory CommissionDocument Control DeskWashington, D.C. 20555-0001

Subject: Response to Portion of NRC Request for AdditionalInformation Letter No. 101 Related to ESBWR DesignCertification Application - Containment Systems-RAI Numbers 6.2-174, 6.2-175, and 6.2-176

Enclosure 1 contains the GE Hitachi Nuclear Energy (GEH) response to thesubject NRC RAIs transmitted via the Reference 1 letter.

If you have any questions or require additional information, please contact me.

Sincerely,

(mes C. KinseyVice President, ESBWR Licensing

MFN 07-695 of 2

Reference:

1. MFN 07-357, Letter from U.S. Nuclear Regulatory Commission to RobertE. Brown, Request for Additional Information Letter No. 101 Related toESBWR Design Certification Application, June 21, 2007

Enclosure:

1. MFN 07-695 - Response to Portion of NRC Request for AdditionalInformation Letter No. 101 Related to ESBWR Design CertificationApplication - Containment Systems - RAI Numbers 6.2-174, 6.2-175,and 6.2-176

cc: AE Cubbage USNRC (with enclosures)GB Stramback GEH/San Jose (with enclosures)RE Brown GEHlWilmington (with enclosures)eDRF RAI 6.2-174: 0000-0071-4892

RAIs 6.2-175 and 6.2-176: 0000-0071-4892R1

Enclosure 1

MFN 07-695

Response to Portion of NRC Request forAdditional Information Letter No. 101

Related to ESBWR Design Certification Application

Containment Systems

RAI Numbers 6.2-174, 6.2-175, and 6.2-176

MFN 07-695Enclosure 1 Page 1 of 12

NRC RAI 6.2-174:

DCD, Tier 2, Revision 3, Table 6.2-6 lists the RPV nominal water level as "NWL."However, NWL is not defined in the Global Abbreviations and Acronyms List, and itsvalue is not given in DCD Tier 2. Please define NWL in the Global Abbreviations andAcronyms List and provide its value in the DCD.

GEH Response:

The abbreviation "NWL" stands for "Normal Water Level." During normal operation, thewater level is controlled within the range between Level 4 (low level alarm) and Level 7(high level alarm) setpoints through the feedwater and level control system. This isfurther discussed in DCD Tier 2, Subsection 4D.1.5, Stability Performance DuringAQOs. NWL is fixed at 20720 mm for better driving head and more advantageous ratioof saturated water to two-phase mixture. DCD Tier 2, Global Abbreviations andAcronyms List, will be revised as requested to add this abbreviation, and the value forNWL will be provided in DCD Tier 2, Tables 6.2-6 and 15.2-1.

DCD Impact:

DCD Tier 2, Global Abbreviations and Acronyms List, will be revised to add "NWL -Normal Water Level." DCD Tier 2, Tables 6.2-6 and 15.2-1, will be.revised as shown inthe attached markup.


2rAIU2AT aev. Uu.9Bx Desgp Cmkd Dwclw 2

Table 6.2-6

Plant Isitial Cosiftims Comidered in tde Cantaknnat DMA Caes

N& Plant Parameter Nminal Vale Bundiag Valmn

1 RPVPow7 100% 102%

2 WW iveln mndity 100% 100%

3 PCC pool leve 4,8in 4.Sm

4 KPCpool teI znX 433-C (10-F) 43.3C(10-F)

5 DW Pmsme 101..3 kPa (147 pai) 110.3kPa(16.Opla)

6 DW Tmepumate 46.11C(115-1) 46.1C (115F)

7 WW Preme 101.3 kPa (14.7 psia) 110.3 kPa (16.0 pain)

8 jWW Tempemare 43.3-C (110-F) 43.3-C (110F)

9 Suppheim pool Teamp 4330C(I (110F 43.3-C (110-F)

10 GDCS pool tnWamure 46 IC (115-F) 46.1C (115"F)

11 Suremimpaoo level 5.45m 5.50m

12 GDCSpoolleveI 6.60m 6.6Dm

13 DW relative humidity 20% 20%

14 RPFVpmm 7.17 MIN (1040 pea) 7.274 MP (1055 p$a

15 RFV Waer Level NWL NWL+0.3m

"NWL = Namm Wam L.evel (9 e 15-2-1)


2A48M2 RAw. 06ESBr Duig CealfdlDumani 2

Table 15.2-1

IW ParmetMs, Initi Cosdisus and Assmpih Used hi AOO ad hIrequnt

Event Aalys

Parameter Val2e

MS1V Closure Prfole usd to Botud Mz Chume Tmr a100% open 0.0100% opm 0.61% open 1.70%5 ope 3.0

High Flx Trp, % NB,, 125.0Seno Time Candut 0.03

TSV Clame Sam Ponitim of 2 or mnoe TSV, % opm e5TUp Tune delay,1 0.06

TCV Fadt Cl•ure Scuu Tnip, s 0.08

High lrem Scma, MPaG (pug) 7.619(1105)kninmm cram delay, s 0.7

High SW esi Pool Tepatme Saam tip, OC (MF), 48.9(120)Mazxnnm Ddoy Tihe, s 1.05

HEi SWupeasim Pool Tinpenure FAPCS achatii, PC (MF) 43.3(110)

Vensllel Up (above Iantia vemd)Level 9 -(LI), m (in) 2239 (81.5)Level a- •SMM0) 21.899(961.1)Level 7 - (I), m (in), h•uh level alarm 20.83(220.3)Naal Wier Level, M (in) 20.72(315.7)Level 4- (L4), m (in), low level aliam 20.60(311.2)Level 3 - 0.3), m (in) 19.73 (778.7)Level2 - (.2), m (in) 16.05 (631.9)Leve I - (LI), m(in) 11.50 (452.3)Level 0.5 - (L..5) m (in) .45 (332.7)

APIM Smoldaed m~araul Powe TripScra, %NBR 115T,,, Cansiea s 7

Total Stmmnline VoAune, m3 (f1V) 135(4767)

CR]D Hya Sysm . - cqaity, m3 fl (ffm). 235.1(1035)Opaciy ikgs (M900u= ) fr 99 kg/rn dasity 64.6 (0.513)(61.1 hu/f)_


NRC RAI 6.2-175:

DCD, Tier 2, Revision 3, does not describe a chronology of progression of aloss-of-coolant accident (LOCA), how it affects the containment and its systems, andhow containment systems operate to mitigate the consequences of a LOCA. Pleaseadd this information to the DCD Section 6.2.1.1.3.

GEH Response:

A new DCD Tier 2, Appendix 6E, will be added to DCD Tier 2, Chapter 6, describing thechronology of progression of a loss-of-coolant accident (LOCA). In addition, a sentencewill be added at the end of DCD Tier 2, Subsections 6.2.1.1.3.4 and 6.2.1.1.3.5 to referto the new Appendix 6E Subsections 6.E.1 and 6E.2 for the details of the FeedwaterLine Break LOCA and Main Steam Line Break LOCA bounding containment responses,respectively.

DCD Impact:

DCD Tier 2, Subsections 6.2.1.1.3.4 and 6.2.1.1.3.5 will be revised, and a new DCDTier 2, Appendix 6E, will be added to DCD Tier 2, Chapter 6, as shown in the attachedmarkup.


6.2.1.1.3.4 Feedwater Line Break - Bounding Analysis

[DCD Tier 2, Subsection 6.2.1.1.3.4, Last Paragraph]

Figures 6.2-13al through 6.2-13d3 show the pressure, temperature, PCCS and DW and GDCSairspace pressure responses for this analysis. Table 6.2-5 summarizes the results of thiscalculation. The calculated maximum drywell pressure during the 72 hours following a LOCAfor the bounding case is below the containment design pressure. The detailed discussion on thechronology of progression of the Feedwater Line Break Bounding case is given in Appendix 6E,Subsection 6.E. 1.


6.2.1.1.3.5 Main Steam Line Break - Bounding Analysis

[DCD Tier 2, Subsection 6.2.1.1.3.5, Last Paragraph]

Figures 6.2-14al through 6.2-14d3 show the pressure, temperature, PCCS and DW and GDCSairspace pressure responses for this analysis. Table 6.2-5 summarizes the results of thiscalculation. The calculated maximum drywell pressure during the 72 hours following a LOCAfor the bounding case is below the containment design pressure. The detailed discussion on thechronology of progression of the Main Steam Line Break Bounding case is given inAppendix 6E, Subsection 6.E.2.


2EMWUF, l2R ]l. 06ESBWE Dasp Camrd DimDlcriw 2

6E. TRACG LOCA CONTAINMENT RESPONSE ANALYSIS

TMe chrnology ofprogies ofFeedwat Line BRek (FW* B) LOCA (Bounding CM) mdMa Stem Line Bnmek (MSLB) LOCA (Bauuding Cane) amtinmmt respmm a disuedin detail inhis senuhzL

9LL Feedwater Lime Break LOCA (D6=d&M Caue)

Foflwi to postulated FWLB LOCA, tdo DIywell premoe imcreses apdl leadi& to wtecleain of tfim puieamaiicCnaunust Coabling Systet (FCCS) id main vents- The Drywellpomur iucase is bemuauted at around 70 secads (FiguM 6.2-13.2), wme mua of thenon-condemble (NC) gses i tem Drywel omualus imu bee purged into the Wetwell(Figure 6.2-136).

As dhown in Figure 6.2-13a2, the peak DyweUll IesaUe is a 313 kPa (46.1 p•Wi) at347 seconsk jxiar to &em (kvufty-Dnven Cooling System (GDCS) &lo inititri shwitly afkarthi opening of the dessunzlion valves (DFVs) C•able 6.2-7d). Iis pek pesum ia belowthe desig pnssure of 4137 kPa (60 puO) wilh a Iag nurgin. The GDCS flow initiates atappxmmnad tly 513 seconds. The suzooled IDCS wvak continues fiwing io the vssel,minces the seming Amn the mactur premuxe vsse (R ) mid the D Rywe presure. Atapp.r. Inugooy 300 the Drywdil pressue drops below the Wweiwd preimne, causing theopenin of tim vauiim Wrekess and alloing some NC pses to flow buck io the DTywLConseqently, the syten rmoures drop to a value of applnimutely 260 kPa (Figu 62-1363).

Figures 6.2-13d1 tmhu 6-2-13d3 slow tim NC gas essules in the Dywell anuIns tieDrymell head gs spma, md the GDCS pool gs pace. Figue 6-2-3d3 shows tiat most of theNC gams in tim Dxyvml minauhis w purged inti tim Wetwell within 100 seconds At axinnd

00M seconk, m NC gases flows back to e Dywell amnma (Figure 6-2-13d0) Am teopening of the vacmm imnbkes.

Subomequmly, decay hea overcames the sudbcooling in the GDCS water and steaningreu s(at -13B0 second, IFigur 6.2-1303). lTe remarytims of RPV staigo causes the Drywellpemuere to mease agai stating firm 130 secnds The Drywed piessure i•edes thelong-term peak of 339 kPa (49 psis) at 72 hour (Figre 6.2-13al).

Afer 10M mecus, the Drywell pmssure is hige r tahe Wetwell prlem. The PCCS mnvethe wem nmd NC gs miizte fAmn the Dywl md purges Mhe NC gae into tim WetwdlMad of the NC gmes tt ratummed to the Dryw•ll aninhas because ofvamm bmaker pae purged back iat the Wetwell in approxinmaly 3 hous (gue 6.2-13d1).

Figue 62-13cl cmnuyes the total heat nmval by tmo PCCS witl the dMcay heat Alar •imfErt 6 hours, the PCCS is able to remave all the decay hest with smu magin to go&re Fromthis point an, all the dcy beat geerated by the com is trnferd to tie Iolatiom Cimdmnser(IC)Passive Coutainnuet Cooliag (PCC) poos, which are lcted outside of tie catainant


DSOWR Dep Cftrd Dumwmmr 2

Figite 61-13b1 through 6-2-13b3 dmo the Dzywei gS t~ayuhtume Wetwell gSu inperfaturmad uaffmsmon. pool imirfce tempemban. As hown in Figin6-2-13b2, the Drywelft~aabxm eache a maxmum of 17C at appnmzuamfy 350 meconhL By the end of

72 horn the Drywel temahm atue maintained at 138 7"C, well below the DzUell desigtompeniture of 171C (340F). Whie h Wetwell ps tuzyerature miius below the Wetwelltinzymzle design hiit of 121.1-C (2.0'F) in 72 booms.

Figure -l c• mpares the watin leveli in the Dzyw mel innsm and suppwsion pool IeTDywemf =mA= water leel Am due to ti he ae flow dischage imm the RN3 and the brokenfeedwua piw gm. In qWyoxi gmuey 10 h4i sAm t Daywolorl s unwatur buv rehes the

qimiqullkimaelevation of 9 metL. At this elevatis, the Drywell amoum hister~ level UiapInI ly 3 1m s below bhe qdlover bholsw , hot wam in The Drywell amamin wlemain an the DayweRl ad not ente into the botama of the supreson pool via the Viaover

Fime &2 smhws &e GDCS pool Imel Me waD m level dmop below L33 (F.gd 61-7) ip I, uiIly 4hmbom afler the iito of GDCS fiow. This crw es a botorm lanye .f-NC. Ts

spaewhich is appimmumbl 6 -um below ie coan•udma pies & he MtNC gas •ma siedin the top two level "L and 135) awe purged to minimal values ina Ew, laura, thiough thie

4L4 ana Stea Lin Break OCA (Bounding Cam)

Followng the postuated LOCN , the DUwel poe imaimmssed bpy leading to Peri ofthe FCCS and mai vests. The coutainumat prome respoome of the DqAyel Wetwell andRV are dhow in Figure 61-14al through 6-2-14a3. During the Winiia blow&,wn plume, theNC pmse in the upper reguom of the Daywel am cleared rapidly to the Wetwel thragh thermiveinrta as shown by the Dtyweil mnd aDCS pa premium m Fnmm 6-14d2 amd 6-2-14d3iue D.ywe- prelsTe sptt to tumn moud mad decreae at b em 17930 mdcar afu f Aleh

UDCS thim initiats as show in Figur 6-2-14a3- The GDCS flow Mll Se reactor vesse to theelevation of the bivk, mod tan spill ib the Drywkl T1hea bed nfe 1 rca 6 hring theGDCS cooling pesund is dumactiezed by cizidmutirm of s~in the vamiel aod Daywel At

ound 550 meok, vacuumnlnueker opeoiug occr as the sen rhxi dofs vloff rtningsomme of NC gase bark to the DiywelL Subsequaunly, decy heat ovecoums the uabcolnahg ofthe GDCS Wilk mod simoming remem. The Dsywell Fxmie L rims wil fow is esablishedthraoug the PCCS, wheme azadenutle fromGo OCXS is recydled back main &e vesse tIog vie

GCpool intdie DrywaL It take approzinuei 11 ham s diite NC gaon to be --druthe CDCS gas space mod 23 hmns fim the Drywel m show in. Figue 6-2-14d1- Me long-trn,(72 hours) response of the cmutainment presarre is dhown. in Fqgur 61-,14a1. The Dywellpremure levels off at arounid 4 hour mid increase ina gudhralpaoe. The peak Drywell pressurereaches 334 kPa (55.8 psa) at the mad of 72 hans, but rmaimnn below the design promnue of414 kPa (60 pam).

Due to the pumesnce NC gases the effectwivus of condommticali hbut trausr i the PCCS asimpaired for the fiast 23 hours, as show by the PCCS hedt ruzarv vame decay heat inFigur 62-14cl. The Vpie in the heat removal fi the time between 17 mid 28 bans indlicate


21GA66M 11m. 06EMDWR Deig CaOtrdDacume rw 2

the peiod wherethe PCC head removal knilioruiily exees h demy heat readfing in a dropi the Dywall pinemo below the Wetweil psnemm This leka to a tympoy cansaim ofshmm, flow I Due PFCC& Sbaeqtamdy the vacmn IkIn qpm, mm WC mei -= retemuedto &th D1ywel, and e POCS hMet keg moval rate mie s a steam flow fimo the Dryweirmmumi. For the first 23 e the d ht eyb the & CCS het h nndval cmag.city. 11Mafter h NC sam ame pjurd from the GDCS and Drywal g qes sw, the PCC hea removalcapa"t nalchesth doeiacy had- Hloweer, at stil carno iremov raiatio he&*g gueratd inthe cme HBm, both fle Drywall and Wetw&ll immres conimie to rm n contimnlly oathe 724.ur period.

Figure 6-2-14b tmh gh 62-14b3 how the MDywell, Wetwell and sqpwsimi pood s qwetempaahze respuases at varieow elevatiam Whtilly, all ele-vatid s hiea up doe to lu maim vewand brin discharge After the main, d cae, only the upper levels we impacted by the PCCSvant dizchazgeý flue Drywell gas tunperatiue peaks at 170.26C immediately following theblow&,wu. which is slghtly below the Orywe desig lempanture of 171-C (34"F) due toadiabc camupmuby the tam dichwgi fin th blui In &a long tam (72 hew) tetaiemperae emiinm below 171T. While th WdswelR gs tom.npeame remains below theWetwell temperature design limit of 121-1-C 0150'F) in 72 hawm.

Figm W-3 cofmpere the mwukmb leml &th Drywell anunlus anl suppnesmon, pooL 11w

=rwl amnauuh withe level Tise due to the break flow dischaWe fini flu mm dmm Iue~a pi~ui Mme Drywell somilo water level will remnain in the low Drywall mdi not M

adto the bottm of the suWmusim pool via the ValloverhWas.

Forf MISLB the DCS pool level, (F ige E-4) dops to the elevatmm of the IJIVsanmdstyabove 133 (Figur 6-2-1). As no psa - is tAwA below [133, gas umane I I md intle top twolevels ([.34 said 1L35) we pnpgd to mimminm values in a few boundws tiaug cooue ctuion pqMes11uintl 60 '1 (or 120nz) of the initil ICS coldwater 461C (11M"F muwuan insiide

theGDCSpook Th hot PCCS coudaatemimeswiththe cold GDCS poo wat•r. TIeteaqnatme of te GDCS water njected b Ilue RFV. i lower tan tIhat of the FWLB. A p tionof the decay hea is used to heat up th imcuug colder GDX waler, which isshown inFVow 6-2-1463 as flu diffuace betwnim due decay hedatMe the tota PCCS coalmohnpower. R hires -pmmid 60 hews to bring the muuxtue terpuatmbe to qpim y950C.

Both the wltia blowdown adl the womug aupissamm pool heat up M lerger in dle MSLB &hathe FWLB, hlich leads to highe pool water I tay at and hihe nzaxsia paoolwaftelevel, and mmlerf Wetwel gos space vohuinu. All thime effects resuth in NgheDryweR pawssieintdhe MSLB tdan FWLB.


2SAW61ZUF 1ra. U.ai CamwAW DecnwIrm 2

wwioam

U

Li I- 41

I~~i K-t II.4-4.-4.-4-4-4-4-4-I-IA KI mvmwbI

* ~ I I I'p j-----------.1.~ - ~I 4 ~ I - * - - - - - - -

Fimge v-1L FWL (BMadig) •DryuA a mnd S s l. Lelah (72 irs)

NowUOXOM o

a, -* -. -. -. - - - -.

I -be,

I

'ft

I1k- j m•4-,4gm-~h

~a f ~ ~ ~4 * I I I = 1' = I - I - I -

IF T & I I12 is if 00 is a is 6

m"6

Figur E-2. FWLB (Boundig) GDCS Pod Lmeve (72i)


IEMU2W Itm- .D1ism CamkdDmcmmriw 2

,VuW --

a'~ 1L1LK-$,''-4-4-4-4-4-4-4-4-iS

I * I - = = = =

4 1~ = - 1 =1 I - ~..q -ws~ f4

* - ---- I - ---- --- I -0 6 Is so so :. a 1 0 0 so a636 1

•Fgu E&. lIL (Eu&rg Dryd Auusm m a" Smim ftd Imk (7 )

tII

a I-

" -L M2 -ý GM

t- - - - --

*

4 i 3 6 6 3 6 3

Foue E4.ML (umtEg GDC FelLw 7 s


NRC RAI 6.2-176:

DCD, Tier 2, Revision 3, many figures incorrectly refer to noncondensible gas as 'Air".Staff notes Figures 6.2-9, 6.2-10, 6.2-11, 6.2-12,-6.2-13, and 6.2-14 all refer to "...GDCSAir Pressures." Please revise.

GEH Response:

All captions for DCD Tier 2, Figures 6.2-9, 6.2-10, 6.2-11, 6.2-12, 6.2-13, and 6.2-14 willbe changed from "GDCS Air Pressures" to "GDCS NC Gas Pressures" as requested.

DCD Impact:

DCD Tier 2, Figures 6.2-9, 6.2-10, 6.2-11, 6.2-12, 6.2-13, and 6.2-14, will be revised asdescribed in the above response.

ge si-hitachi c. - nrc.gov · si-hitachi ge hitachi nuclear energy james c. kinsey vice president,...

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