LD-90-060, Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per

Forwards Proposed Changes to Sys 80+ Licensing Review Basis Document,Per

ML20059J189
Person / Time
Site:	05000470
Issue date:	08/28/1990
From:	Erin Kennedy ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Wambach T Office of Nuclear Reactor Regulation
References
PROJECT-675A LD-90-060, LD-90-60, NUDOCS 9009190208
Download: ML20059J189 (8)

Text

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ABB -

ASEA BROWN DOVERI '- ]

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~ August 28, 1990'  !

! LD-90-060: J

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' Project No. 675

-- I t 'Mr.-ThomasLV.:Wambach~ -;

! Project Manager '

Office.of Nuclear Reactor. Regulation U. S. Nuclear Regulatory Commission-Attn: Document-Control. Desk- ..;

Washington, DC .20555 >

Subject:

Licensing Review Basis forlthe- i system 80+" Standard Design- '

t

Reference:

Letter LD-90-005, A. E. Scherer~(C-E) tof i R. Singh = (NRC) , dated January - 22, 1990,  ;

4

Dear Mr.-Wambach:

t Enclosed are proposed changes to, the System: 80+" Liscensing -

Review Basis document (submitted:by the reference letter) which we expect to-include in the next revision. We are providing this information.at this timeito facilitate your..

review. If.you have:any questions on'theLenclosed; revisions, please callLme'or_Mr. S. E. Ritterbusch at'(203), ,

285-5206.

g

-Very;truly yours,;

COMBUSTION-LEN EERING,LINC.

l E. H.oKennedy.

Manager.

Nuclear Systems-Licensing h

EHK:lw Enclosure. As Stated l

f cc: C. Miller (NRC) 3 W.-- Miller -(NRC) d F. Ross'(DOE-Germantown) '.

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ABB Combustion Engineering Nuclear Power Ol i i

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l -- Comtustum Engneenno. Inc. 1000 Prospect Hdt Road Telephone (203) 688-1911. -- I

l. Post Office Box 500 Fax (203) 285-0512

! 9009190208 900828 wnesor cmnectat oc09s.0600 . TWex 99297 COMBEN WSOR ,

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675A PDC s .

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. o- For hydr . generation a ontrol inside'c nment,:

l ass extent of meta ter reaction (7 .and the sum - j al able hydrogen entration(13% differe han those:  : I L ecified by 10 C 50,34(f):(LR8 Sed) on 7s,15 li ,

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The requirements for requesting exemptions from current; regulations- l (10 CFR 50.12) willibe applied where appropriate.

'1.2.2 Desian Feathre: and Method's which nav Involve Ouestions of Commission y.. 4 Poliev l a ,

1 o_ The need for,L and. formulation of, a goal for expected ]

con?,ainment performance (Section 6.5.3)-

-o ~ Thedegree'towhich,Lifany,.newdesign.featuresarerequired .

'to improve protection against. sabotage (Section 7.2)=

o The degree to_which, if any,-newl design. features arel required -

for improved fire-protection (Section 7.9)'

s o The-degree to which realistic source terms can ~be' used for PRA and: severe accident evaluations (Section _7.12) f

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o Whether there is za need for containment' vendng'capatiility for severe accident mitigation beyond that. required by-current .

regulations (Section.7.16) a l 0 Whether proposed design' features'for prevention _and mitigation; l- of degraded core' conditions are adequate (Section-7.21) '

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- 7.13' Doeratina Basis Earthauake-1 The NRC st'aff agrees that the 0BE should not'necessarily control thei design'of safety systems,.which now occurs when t.he criteria of 10 CFR, Part 100, Appendix A, are applied.. The_ System 80+: design will be consistent with the EPRI:ALWR Requirements Doctment with f respect to definition of OBE, SSE,t and. analysis methodology. It is g expected that the OBE wl11 be less than'one-half of:the SSE, which I is a departure from 10 CFR, Part'100, Appendix A. 'The NRC staff _ j will-review the OBE design basis'and.will consider C-E's request to' decouple the OBE from the SSE, subject to Commission approval.

.I 7.14 Tvoe C Containment Leak Rate  !

Containment leakage is acknowledged by the NRC staff as' being a function of containment pressure. This. pressure dependence will be j reflected in predictions of leak ratg forihe System'80+ L containment. TNg Pgm M gg'T R kg g4 4 -]

es i stN sy4Neam &Q 7.15 Hydroaen Generation j- . . . /o C.FRIe"=8,M en,F g, J o, i

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C-E will provide info ation to-just'ify a system + con;a' design consistent with 'he EPRI ALWR RequiYements Document and NRC : Y

'" a staff review thereof. i... ' E :t':- ' . . /. _ ; _ l _ _ ; '. '. . . . : . n - 1

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7.16 Severe Accident Containment Vents fi c e .. m __..- "-' $e System M + containment design ' . ' _lr +he s wr-a+.a n a n cy '

capability to add containntentAvent4ar.:

g a~ ruture time. This' approach ~!

is in compliance with 50.34(f)(3)(iv). ' NRC! staff. will;revie'w System :

80+ severe accident-issues including containment overpressure; analysis and, subject 'to Commission approval, will determine if' j there~isaneed":b:;_.!containmentven Me= d eggp gggggg

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has a dual' containment system. The steel containment _-pressure boundary is. :s surrounded by a concrete shield building, with ~an annului in between. Such : ,

a design presents; no significant- probless'to the addition of a'large. ,

(three-foot diameter) containment penetration in the future.. Therefore, (

. the System 80+ design has' r

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,.y Regarding EPRI requirements directed at improved plant performance and operation;(and;not required for, regulatory compiiance), C-E 'has-' .

chosen to' add'ress' selected' design attributes 11nfa manner thatL  ;

differ's' from specific EPRI requirements. -Such differences are based: j on C-E's own evaluation ~ of the desirability, effectiveness, and commercial; viability of L the feature as it pertains: specificallyLto' ths' System 80+ design. : A current' list of, System 80+ design features- 1 which deviate from EPRI requirements is,provided:belowL i System 80+ reactor coolant 'hottleg temperature will be reduced

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to 615'F (ve'rsus 600iF)... . , ,

o. Skirt-type supports will be. used for'the System 80+ pressu~rizer and steam. generators (versus, pedestal.or open-frame ~ supports). . q o System 80+ steam generators .will have' handholes at' the. bottom,.

tubesheet elevation of> the secondary side. (versus^ every U-tube) supportelevation).  !

I o System 80+ Control Element Drive Mechanisms will not have -

anti-ejection latches. _ j

i o' The System.80+ Emergency Feediater: System will havb:a! l cross-connect between the twooindependent. trains. 4

i o The System 80+ design will retain-redundant

feedwater.. isolation valves (versus a using the- feedwater controlLvalve fori .

4 isolation). '

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0 The Sy;t0: SO: 70ir, f00'dw0ter ;;0:p; WUl 50 .thdir.0 dridh .,

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p The-System 80+ design will not-includ'e the main steam isolationu

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signal. on pressure rate-of-change. ,

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o- The' System' 80+' design will include some pol vinyli choloride and:

. neoprene insulation.

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o The System:80+ design includes the Reactor Vessel. Level' -

Measurement' System. LCompliance with.the'EPRI-requirement'tol not have'such a system wouldLlead to'a' non-compliance with;10: q CFR50.34(f)(2)(xxviii)..

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o The' System 80+ design has a spherical (versus; cylindrical) steel- dual containment.

o The' System 80+ nuclear steam supply- system will not1 bet significantly offcet from the-centeriof the: containment due to

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, the enlarged workspace. provided-by:thelsphericaligeometry- of .

j the containment (versus a 15-70 foot offset'in a" cylindrical -l containment).-

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o The System 80+' containment equipment hatch will bec at thei

. operating floor level (versus grade level).

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-a D Syctem 80+. ecfety. _ analysis ; will - be:

completedL using- . thel conservative.-

source' _ term of, TID 14844 (versus ; an-l EPRI-proposed " realistic": source j term)

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M. /.SyJtem 80+ sa'fety analysis will demon-

strate that 10 CFR 100 limitsocan be mat . with a ' containment design leaks race' of 0.3 wt% per day (versus' O.5 Ub5 g ' System 80+ L will . employ. alloy 690 in the pressur '.zar heater sleeves-'and-,

instrument. _ wells. (versus. restricting ,

use to steam generator. tubes).- 1

$ For a -loss. of all feedwater core un-

!covery would occur-in. approx,imately 1 '

hour and 45 minutes without ~ operator action:(versus 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).

$.  : System- - 80+' _ containment: -purge' . valves require closure;inL15: seconds (versus i 30 seconds).

$._ system 80+ minimum Ldiesel- start : and

-load sequence time.is 20 seconds3 (ver i -j sus 40 seconds). -

1

'g The system 80+ design places only the, first stage of-low! pressure feedwater- ,

heaters'in the condenser neckf(versus '

l all. low pressureLheaters). ',

j- The System 80+ turbine ~exhnust to; ,

condenser inlet connection uses eitherS t a rubber flexible seal or. . a d';:2 N.

seal with spring -mounted condenser.

(versus fstainless steel' flexible'- i seal)..  ;

1' g system 80+ usesf6, stages of feedwater re-heating in_ the ! reference design-

't with the actuali number - to ~ be ' deter- -

mined;by the site. specific. heat bal--

ance (versus 7Sstages). -

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$ The System 80+ atmospheric' dump' valves' j

.are '

manua y operate _-(versus- pressure o actuated with variable setpoint)..

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g The third main feedwater pump and .;

booster pump ..are - normally :in standby l

[, -(versus'normally' operating).

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'J.x ' ;The replacement of.systsa 80+ praecur-

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'izeri heateri sleeves requires- cutting

.and velding (versus -no cutting,'or twalding).:

EMM.[ g M wyd

[ /Feedi . delay'ed and for-upbleed on System 80+ can' )pe~

o.30 minutes followin'g dry out 60 min,tes). .

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$. ~ The system 80+ l control- room pressure , ,

,-- boundary will' include fans _and-filters- ,.

(versus excluding _.HVAC equipment).

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The' System 80+t Advanced '. Controll Com-1 plex .(called: 'Nuplex 80+)2 . integrates.

spatially 1 dedicated L display Land con-trol Jwith compact work stations- (ver-m 'l sus exclusive - use'- of redundant, - com-1 -l

_ pact work stations).

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-$ System 80+- point-to-point communica - N. >

j tion 'is by sound - powered _ phones -(ver- 1 sus a wireless system).

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$ System 80+. arrangements locate kitchen- 1 and restroom.facilitiesJconvenient toj j

.but outsidej the Main control Room: area:

! -(versus inside' Main Control' Room-- ar = '>

l. ea). ..

$ System socrce 80+ usesi separate standby-transformers for ;invertersc

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(versuc common transformer). .

$ System 80+ interfaces doinotk require 4, separate switchyard E for. ' main - and . re- =

serve off site' L circuits: (versus sepa-rate'switchyards). ,

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