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)

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ABB ASEA BROWN DOVERI '-

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~ August 28, 1990' LD-90-060:

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' Project No. 675

'Mr.-ThomasLV.:Wambach~

t 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 f

Enclosure.

As Stated l

cc:

C. Miller (NRC) 3 W.-- Miller -(NRC) d F. Ross'(DOE-Germantown) 3 ABB Combustion Engineering Nuclear Power Ol n n.,,, -

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Comtustum Engneenno. Inc.

1000 Prospect Hdt Road Telephone (203) 688-1911.

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Post Office Box 500 Fax (203) 285-0512 9009190208 900828 wnesor cmnectat oc09s.0600

. TWex 99297 COMBEN WSOR PDR PROJ 675A PDC l

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. 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:

50,34(f):(LR8 Sed) on 7s,15 L

ecified by 10 C li

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

'1.2.2 Desian Feathre: and Method's which nav Involve Ouestions of Commission 4

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

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con?,ainment performance (Section 6.5.3)-

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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)'

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

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Whether there is za need for containment' vendng'capatiility for o

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-.

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- de a nd,8 I tael C-E will provide info ation to-just'ify a system

+ con;a' design consistent with 'he EPRI ALWR RequiYements Document and NRC :

Ya staff review thereof.

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7.16 Severe Accident Containment Vents fi

__..- "-' $e System M + containment design '. ' _lr +he c e.. m s

wr-a+.a n a n cy '

capability to add containntentAvent4ar.: a~ ruture time. This' approach

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g 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

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INSERT A ik

~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,

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. 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 i

which deviate from EPRI requirements is,provided:belowL System 80+ reactor coolant 'hottleg temperature will be reduced l

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

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

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System 80+ steam generators.will have' handholes at' the. bottom,.

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

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System 80+ Control Element Drive Mechanisms will not have -

anti-ejection latches.

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i The System.80+ Emergency Feediater: System will havb:a!

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cross-connect between the twooindependent. trains.

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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 l

ruerene -ntn _ar w 4 3

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

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signal. on pressure rate-of-change.

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

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. 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

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

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. operating floor level (versus grade level).

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ecfety. _ analysis ; will - be:

Im completedL using-. thel conservative.-

l source' _ term of, TID 14844 (versus ; an-EPRI-proposed

" realistic":

term)

source j i

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/.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 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 30 seconds).

-load sequence time.is 20 seconds (ver i

-j system 80+ minimum Ldiesel-start : and 3

sus 40 seconds).

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'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)..

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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).

h 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

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-(versus'normally' operating).

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The replacement of.systsa 80+ praecur-

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' 'izeri heateri sleeves requires-cutting

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

EMM.[

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[ /Feedi and bleed on System 80+ can' )pe~

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

spatially 1 dedicated L display Land con-

'l trol Jwith compact work stations- (ver-m sus exclusive - use'- of redundant, - com-1

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_ pact work stations).

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System 80+- point-to-point communica -

N.

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

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

.but outsidej the Main control Room: area:

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

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ea).

System 80+

usesi separate standby-

)

socrce transformers for

invertersc (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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