LD-90-060, 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:
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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.
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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
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,
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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)...
o.
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
- l containment).-
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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).
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)..
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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.[
g M wyd
[ /Feedi and bleed on System 80+ can' )pe~
. delay'ed for-up o.30 minutes followin'g dry out 60 min,tes).
- b _(versu y.
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The system 80+ l control-room pressure,
boundary will' include fans _and-filters-(versus excluding _.HVAC equipment).
/
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
-l"
_ 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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