ML20031E110

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Slide Presentation from 810923 Meeting Re General Design Considerations & plant-specific Design Features
ML20031E110
Person / Time
Site: Clinch River
Issue date: 09/29/1981
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20031E108 List:
References
NUDOCS 8110150101
Download: ML20031E110 (95)
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{{#Wiki_filter:- l ENCLOSURE 2 ~ j >g LMFBR AND CRBRP 10 OVERVIEW

  • O I

ig NUCLEAR REGULATORY COMMISSION His BETHESDA, MARYLAND i WEDNESDAY, SEPTEMBER 23, 1981 l AGENDA l

  • INTRODUCTION J. L. LONGENECKER i
  • LMFBR DESIGN CONSIDERATIONS P. W. DICKSON
  • CRBRP DESIGN FEATURES j

- REACTOR AND HEAT TRANSPORT SYSTEMS P. W. DidKSON - ACCIDENT MITIGATION FEATURES G.H.CLARE I - AUXILIARY SYSTEMS G.H.CLARE

  • CONCLUSION J.L.LONGENECKER

1 ~ CRBRP PROJECT OR.GANIZATION ~ r___________________________________________________-_______, l l 1 l l PROJECT DEPARTMENT TENNESSEE l$ i MANAGEMENT OF VALLEY l CORPORATION ENERGY AUTHORITY l$ ,a l l 1 c_. 1 I< 1 1 I l I 1 u_____________________________ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.a WESTINGHOUSE l STONE AND WEBSTER ELECTRIC ENGINEERS & BURNS AND ROE, INC. CONTRACTORS CORPORATION l (OAK RIDGE, TN) l l 4 i ATOMICS WESTINGHOUSE GENERAL ELECTRIC INTERNATIONAL (WALTZ MILL, PA) ) 1 etewumeie

\\ 4 NRC REGULATORY GUIDANCE ~ IS CONSIDERED IN THE CRBRP DESIGN l PROCESS l l l

  • 10 CFR 50; APPENDICES A*, E, G, H, I, J
  • REGULATORY GUIDES; DIV.1, 5,8
  • POST-TMI GUIDANCE; NUREG 0718
  • STANDARD REVIEW PLAN; BRANCH TECHNICAL POSIT,10NS
  • CRBRP GENERAL DESIGN CRITERIA PROVIDED BY 4RC i

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9-81-PO2538-3

~ LMFBR AND CRBRP OVERVIEW BRIEFING FOR THE NUCLEAR REGULATORY esas COMMISSION LMFBR DESIGN CONSIDERATIONS l PRESENTED BY DR. PAUL W. DICKSON l TECHNICAL DIRECTOR, CRBRP PROJECT WESTINGHOUSE l ADVANCED REACTORS DIVISION I SEPTEMBER 23,1981 t... -. i

a _,,u ---Am e --4-- aa--i -h-- 0 4 .~ l S E O N LLI w aw W ct 5w q A o o W LLI E CD ~ s

i GOAL: BREED WELL 'l l j FAST SPECTRUM l Pu/U FUEL i LIQUID METAL SMALL NUCLEAR i COOLANT CROSS-SECTIONS t i I t S $1 WL2$04 2

i ) LIQUID METAL COOLANT I I I I I I I LARGE REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW EXPANSION l WITH BY WITH MELTI.NG BOILING TRANSFER SPECIFIC COEFFI-0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 2 CIENT 1 n i i 1 ....o....

1 SODIUM PARAMETERS VS WATER PARAMETERS I SODIUM WATER (1000 F) (600 F) l I Btu ) THERMAL CONDUCTIVITY 32.6 0.29 i ( hr-ft Fj [ Btu h HEAT CAPACITY 0.30 '1.51 ( Lb-F ) l I Lb h

  • VISCOSITY 0.54 0.21 l

(ft-hr ) I Lb ) 51.4 42.4 DENSITY ( ft 3 ) l I 9 81 WL2520-47

I LlOUID METAL COOLANT I I I I I I I REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW LARGE l WITH BY WITH MELTING BOILING TRANSFER SPECIFIC EXPANSION 0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT COEFFI-2 2 CIENT p-..._.!_-_ LEAK INERT Na/H 0 l THERMAL l 2 CELL j MARGIN l DETEC-ATMOS-REACTION LINERS l BEYOND l TORS PHERE SYSTEM l DESIGN l i l BASIS L-_---_____al COMPLEX IN REACTION ^ SYSTEMS DIATE i CELLS ACCOM-MODATION SUPPORT i l HIGH l INTEGRITY r STEAM GENERATOR ,i ... - ~. I

LIQUID METAL COOLANT I I I I I I I LARGE REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW EXPANSION WITH BY WITH MELTING BOILING TRANSFER SPECIFIC CO F1-0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 2 E I I INTERMEDIATE INERT HEAT ATMOS-TRANSPORT PHERE NEUTRON GENERATION INSPECTION yg IN CONCRETE IN CEls.S AND MAINTENANCE CONTAIN N PRIMARY GOAL: COMPLICATIONS GOAL: STRAIGHT PULL USE FFTF SPARE HEAD l l ( REFUELING l N ACHIN DEGRADATION OF TRIPLE FAILED FUEL MONilORS ROTATING AND EX-VESSEL PLUG HEAD NEUTRON SIGNALS i OAL: F--~~~~~--~~ ~~~-~~~--- ~~ LIMITED VESSEL l GOAL: PENETRATIONS I ,20' REACTOR BELOW OUTLET l VESSEL NOZZEL EX-VESSEL SOURCE RANGE FLUX MONITORS e

l LIQUID METAL COOLANT i I I I I I I I l LARGE REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW EXPANSION l WITH BY WITH MELTING BOILING TRANSFER SPECIFIC COEFF1-l 0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 2 CIENT I j COLD TRAPS MAINTAIN PURITY I l I ^ AC ENTAL lODIN I ^ FlELEASE .a ->m. t i

1 i j LIQUID METAL COOLANT i l I I I I I l l REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW LARGE WITH BY WITH MELTING BOILING TRANSFER SPECIFIC EXPANSION 0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT COEFFI-2 2 CIENT I I I I HIGH MINIMUM REO.FOR TRACE TEMP. OPERATING CONTIN-HEATERS REFUELING TEMPS. UOOS FLOW I CORG COM-PONENTS STORED i PREHEATED l EX-VESSEL STORAGE TANK l i

i LIQUID METAL COOLANT I I I l l l 1 REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW EXPANS Giv WITH BY WITH MELTING BOILING TRANSFER SPECIFIC COEFFI-0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 2 CIENT l ~ i i [ HIGH "ZERO" PRESSURE I OPERATING SYSTEM TEMPS. HIGH TURBINE EFFICIENCY i l i (

4 i { LIQUID METAL COOLANT ^ i I I I i l I I REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW LARGE EXPANSION i WITH BY WITH MELTING BOILING TRANSFER SPECIFIC I COEFF1-O & H2O NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 CIENT 1 MINIMUM HIGH l OPERATING I OPERATING I l TEMPS. TEMPS. 2 l j THERM-HIGH ALLY TURBINE PROGRAMD EFFICIENCY STARTUP I i MINIMUM j TURBINE INLET I TEMPS. i VARIABLE SPEEDS l PUMP I

4 I j LIQUID METAL COOLANT i I I I I I I 1 l LARGE I HEACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW EXPANSION WITH BY WITH MELTING BOILING TRANSFER SPECIFIC COEFFI-0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 2 CIENT l l I "ZERO" INERTED CELL PRESSURE l CELLS LINERS SYSTEM t I l NO PHASE l f CHANGE l j 1> I I LOW PRESSURE l CONTAINMENT i i i ..om i. 4 i

b l I \\ ) L; QUID METAL COOLANT I I I I I l I l LARGE REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW EXPANSION l i WITH BY WITH MELTING BOILING TRANSFER SPECIFIC COEFF1-0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT 2 2 CIENT 1 1 I i I HIGH LARGE AT's OPERATING RAPID AT's TEMPS. I 1 1 SMALLER HEATED

i CORES PLANT SMALLER CELLS i

COMPO-I NENTS CELL COOLING REO. i l l l l l l 1

l L l LIQUID METAL COOLANT I I I I I I I i REACTS ACTIVATED COMBINES HIGH 'l HIGH HIGH HEAT . LOW LARGE l WITH BY WITH MELTING BOILING TRANSFER SPECIFIC EXPANSION 0&HO NEUTRONS HALOGENS POINT POINT CAPABILITY HEAT COEFFI-2 2 CIENT l [ l II "ZERO" l PRESSURE LARGE AT's i SYSTEM RAPID AT's i l NO PHAFC I I CHANGE WITH ENHANCED LEAKS NATURAL CIRCULA-l 1, TION i GUARD i VESSEL CONCEPT j i l I I PRIMARY VESSELS " TOTALLY" l SUPPORTED AT TOP, I GUARD VESSELS PASSIVE j i l SUPPORTED AT EMERGENCY BOTTOM COOLING

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= LIQUID METAL COOLANT I I I I I I I l REACTS ACTIVATED COMBINES HIGH HIGH HIGH HEAT LOW LARGE WITH BY WITH MELTING BOILING TRANSFER SPEC!FIC EXPANSION 0 & H2O NEUTRONS H.ALOGENS POINT POINT CAPABILITY HEAT COEFFI-2 i CIENT "ZERO HIGH PRESSURE OPERATING LARGE AT's SYSTEM TEMPS. RAPID AT's I I "^ STRUCTURAL CHANGE MATERIALS' WITH DEGRADATION LEAKS I GUARD REQM'NT FOR VESSEL LOW THERMAL CONCEPT INERTIA IN STRUCTURES Pfi' MARY VESSELS THIN WALL SUPPORTED AT TOP, GUARD VESSELS VESSELS, PIPES, SUPPORTED AT COMPONENTS, BOTTOM USE OF LINERS I SEISMIC DESIGN IS j ~~~~ IMPORTANT

I FAST SPECTRUM Pu/U FUEL i l l 1 ^" LIQUID METAL COOLANT C SS SEC ON I I l LARGE ALLOWS HIGH HIGH HEAT LOW EXPANSION WIDER BOILING TRANSFER SPECIFIC C E F1-CHO C F POINT CAPABILITY HEAT CE R ALS I G LARGE AT's ~ { OPERAllNG l RAPID AT's TEMPS. I STRUCTURAL MATERIALS' DEGRADATION i, I l SSao4 SS316 INCONEL l

Y S T LI EDAV FEI R P I TRT ELU IL EC HEN I EMTA I I RI AE G UR FU L I O MR H B CS T I Y O B N Y S T V G I D WI N E TI E I E O R L CW D LS B AS E BN E ERAO ~ R NONS l F O RfO N U P B M i l L L U F E R L O L O R E T L

LW C U LRTS A

E F AEND O D I PU M BOO E G S/ MCR E S u R T UC P B S N Na A B F / SN O RI A T C E

  1. L E I

C S-US NS O R D C YE LHL H C E l GI U RF IHN E I

i i l GOAL: BREED WELL j 4 i I i FAST SPECTRUM Pu/U FUEL i d E I I I l LIQUID SMALL t METAL NUCLEAR COOLANT CROSS-SECTIONS I i I HIGH HEAT lilGHLY i HIGH ENRICHED TRANSFER l (AT t CAPABILITY FUEL I SMAL L i COOLANT VOLUME I FRACTION i, i I I E I POSITIVE FERTILE " FUEL ** LOW FUEL VOID ELEMENTS AS DOPPLER COEFFICIENT WELL AS FISSILE i I I n 7-j TWO I POTENTIAL 3 ] DUCTED CONTROL lFOR ENERGETIC l FUEL ROD l CORE SYSTEMS E DISRUPTION I u--------- a l h i a ..e,,,,

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LMFBR AND CRBRP OVERVIEW l BRIEFING FOR THE i NUCLEAR REGULATORY COMMISSION l REACTOR AND HEAT TRANSPORT SYSTEMS PRESENTED BY I DR. PAUL W. DICKSON TECHNICAL DIRECTOR, CRBRP PROJECT WESTINGHOUSE ADVANCED REACTORS DIVISION I l SEPTEMBER 23,1981

1 i CRBRP PLANT PARAMETERS I THERMAL POWER, MW 975 GROSS ELECTRICAL POWER, MW 380 i GROSS EFFICIENCY, % 39 l DESIGN LIFE, YEARS 30 REFUELING INTERVAL, MONTHS 12 PRIMARY PUMP DEVELOPED HEAD, FT Na 450 i AVERAGE BURNUP GOAL, MWD /kg l I EQUILIBRIUM CORE 80 I INITIAL CORE 50 i i i i i 9 81 PO403-8-4

..a. 7.. - -....rp . 9, ._. i I i l OVERALL REACTOR SYSTEM REQUIREMENTS i The CRBRP shall have the capability to be safely shutdown and be maintained in a safe condition for all design events 1 Overall breeding ratio 1.2 minimum Thermal Hydrualic Structural l - ~ ~ ~ - - ' Design Values Design i ~- 1 Total reactor power 975 MWt l Reactor inlet temperature 730 F 775 F I Reactor mixed mean outlet 995 F 1015*F t I temperature l l l l l I 'm e i.r .- 'l roi l ! ' r l n. ' l ' !,. 99). '1 !; e ', .,-l e.i i-l I ' r' il' ' i } 8 i ,i k r. cn

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  • 1% TD g

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(57 IN.)

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t 1 1 l l I l l l CRBRP HEAT TRANSPORT SYSTEM i 1 PURPOSE e TRANSPORT REACTOR GENERATED HEAT TO THE STEAM GENERATOR SYSTEM l 0 PROVIDE SUPERHEATED STEAM TO THE j TURBINE O PROVIDE SHUTDOWN DECAY HEAT REMOVAL CAPABILITY e PROVIDE FOR ISOLATION OF PRIMARY SYSTEM RADIOACTIVITY I 1 )

1 HEAT TRANSPORT SYSTEM THERMAL HYDRAULIC DESIGN CONDITIONS THERMALPOWER 975 MWt PRIMARY SYSTEM 0 HOT LEG TEMP 995 F COLD LEG TEMP 7300F FLOW (EACH LOOP) 13.82 x 106 LB/HR (33,700 GPM) MAX. HEAD 450 FT INTERMEDI ATE SYSTEM HOT LEG TEMP 9360F COLD LEG TEMP 6510F FLOW (EACH LOOP) 12.78 x 106 LB/HR MAX. HEAD 367 FT l STEAM /FEEDWATER SYSTEM TURBINE THROTTLE TEMP 9000F TURBINE THROTTLE PRES. 1465 PSI A STEAM FLOW (EACH LOOP) 1.11 x 106 LB/HR FEEDWATER TEMP 4680F ,_n, -.e- -- ...e. _,,n.,_, _~, y,- 7m-,,-_._ ,_v,,w-,- -. -.,. ,,nn.

t ~ 4 l CRBRP HTS SCHEMATIC i { PRIMARY l INTERMEDIATE STEAM GENERATOR - i i SYSTEM 8 SYSTEM i SYSTEM I n . _ TO TURSINE ~ " " ~ THROTTLE = I SUPERHEATER f -g STEAM DRUM PRIMARY ^ - N ( pFEEDWATER-PUMP l c, ON: INLET i o n IHX 1 STEAM DRUM EVAPORATOR CONTINUOUS CHECK EVAPORATOR DRAIN VALVE 13 v"= Ij yoH oi: REACTOR VESSELPM FLOW I INTER I ~ ~Q-b, i =V' i METER I PUMP i RECIRCULATION i i PUMP 1 I I I t I 9

LNCONTAINMENT PHTS LAYOUT AND ARRANGEMENT l INTERMEDIATE NTERMEDIATE HOT LEG g COLD LEG g - r... , u. 2 5, , ;/ +~ kf, PRNARY COLD iia =,~Em i) ~ I 4' l - :.%/ PRR*ARY= A- ~ j

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NOZZLE LEVEL PROBES 93 l 4 I) A HYDROSTATIC OUTLET NOZZLE ) BEARINGS INLET NOZZLE c,wm>i.i . -,.. ~.,, _ -..

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s t* LMFBR AND CRBRP OVERVIEW l BRIEFING FOR THE NUCLEAR REGULATORY COMMISSION l ACCIDENT MITIGATION FEATURES i PRESENTED BY GEORGE H. CLARE LICENSING MANAGER, CRBRP PROJECT WESTINGHOUSE ADVANCED REACTORS DIVISION SEPTEMBER 23,1981 I

w. y

~ PLANT SYSTEMS ARE PROVIDED TO MITIGATE POSTULATED ACCIDENTS \\

  • REACTOR SHUTDOWN SYSTEM i
  • SHUTDOWN HEAT REMOVAL SYSTEM
  • CONTAINMENT SYSTEM
  • LIQUID METAL FIRE MITIGATION SYSTEMS
  • SODIUM WATER REACTION PRESSURE RELIEF SYSTEM l

I l 4 m'. 941-WL2520-1

l THE REACTOR SHUTDOWN SYSTEM ASSURES CORE COOLABILITY FOLLOWING l ALL DESIGN BASIS ACCIDENTS l

  • PREVENTS CLADDING MELTING
  • PREVENTS SODIUM BOILING I

l [ j FOR MORE FREQUENT EVENTS, THE RSS MINIMlZES DAMAGE TO CLADDING AND PLANT COMPONENTS. r l l ll ~ l j en ene seas serein in

l ~ i ~ ~ I CRBR SHUTDOWN SYSTEMS s SECONDARY RSS PRIMARr RSS I I'dI"" II'* Pruswa SENSORS rhison chambers ion Chem 6,, I Discretc Components Istograted Circuit Direct Coupled I Ll;ht isolated LOGIC General Coincidence Local Coincidence t \\ solenoid volve m screm sroeners ELECTRIC / MECHANICAL INTERFACE i I I sellast l ...iDL ROD DRIVE MECliANISM ~ Rollw Nut 1 1 g -((# l Complient Screm Rod ys laside Stiff Strutwel g Member l ll

I

~ Latch I Pressure Assist Hydraulic Hex Duct Circuler Duct l Partially laserted Out of Core v l $w h,[,o, -~ De92 74 k' l } /

1 I 1 i i i ^ l l gi Primey ~i Secondary, e, s ~ i i 3-[ @h, 0 j ~ i ..... 3 } I' i i Stator Solenoid

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i H r, i ' ' k*"n[*"*'"- (e ~ Collapsible 9 a ' ~ ~ " ~ h'**f***'

4. i SYSTEMS COMPAR150NCONTROL ROD F " "*' ""

~" ( ~ j Spr na l.._.._._.__. ) ) Jd / g Driveline ~ l Dashpot 2 g Coupilng I Scram Latch l 1 ~ Nsl9 hDamper Control F'.A J I - - Control R'od 9

  • ... u: II 3 gp;.-

1 g pr. ..i t I _;..,e.' ~ ~ ~ lston ( Pin Bundle .. Pin Bundle h I ~ P ""k r.. i g,, _ g ;.. s 3 e

  • P mm

.I .es l:, e e* i- - E E e 1 5 b h $ $*&

l CRBRP SHUTDOWN HEAT REM' OVAL SYSTEMS l AIR PACC 1 g i aK WEW Na REACTOR CONDENSER COOLING PHTS IHTS' SGS AIR LOOP LOOP VESSEL FEEDWATER TOWER I i J AFWS 1 f t 2 LOOPS 2 PUMPS 3 LOOPS 3 PUMPS E

THE PREFERRED SHUTDOWN HEAT ~ REMOVAL PATH USES NORMALLY OPERATING SYSTEMS l

  • CAPABLE AND REDUNDANT
  • CONTINUOUSLY OPERATING
  • SELF MONITORING
  • PASSIVE I

l STANDBY SYSTEMS ARE UTILIZED WHERE APPROPRIATE i e

i -l l EMERGENCY HEAT SINKS AND POWER l i SUPPLIES ARE PROVIDED TO MITIGATE LOSS l OF MAIN CONDENSER, MAIN FEEDWATER l AND OFFSITE POWER i

  • POWER VENT VALVES
  • REDUNDANT l
  • AIR COOLED CONDENSERS
  • SEPARATE I
  • AUXILIARY FEEDWATER SYSTEM ~
  • SEISMIC CATEGORY I i

l

  • DIESEL GENERATORS
  • CLASS 1E
  • ASME SECTION lli j

l l-

i l I. DIVERSITY PROVIDED IN POWER SOURCES AND IN PATH FOR HEAT REMOVAL FROM l PRIMARY SODIUM I l FEATURE DIVERSE TO l

  • DIVERSE POWER SUPPLY
  • DIESEL GENERATORS 4

l

  • TURBINE DRIVEN AUXILIARY
  • MOTOR DRIVEN AUXILIARY l

FEEDWATER PUMP FEED PUMPS

  • DIRECT HEAT REMOVAL SERVICE
  • IHTS/SGS/SGAHRS l

l l t i l I l

i CRBRP NORMAL DECAY HEAT REMOVAL PATH ~ ________, TURBINE GENER ATOR r l ~ t INTERMEDIATE V ( m SUPERHEATER dBYPASS N HEAT TRANSPORT i l SYSTEM VALVE - COOLING i ~ - CONDENSER - TOWER l T REACTOR ] ((STEAM DRUM]i f VESSEL l 4 e ~ j ( ) i ^ ) llHX l V pg,gggy O h POW MON I ~ hMOTOR i HEAT l TRANSPORT j SYSTEM EVAPORATERS RECIRCULATION PUMP (2) C V WPICAL OF 3 j 1 w.

? l l CRBRP STEAM GENERATOR AUXa..lARY l HEAT REMOVAL SYSTEM 1 PROTECTED ~ f VENT AIR-COOLED VENT CONDENSER FROM CONDENSATE TO c TORAGE TANK ATMOSPHERE -$ f ] LOOP 3-TO h OUTLET ATMOSPHERE [ STEAM S Qg Fj gLOOP2 WATER l d ISOLATION STORAGE j VALVE g .A TANK TO TURBINE +-- -C s, j SUPERHEATERlN A' 4..M. LOOP 3 TURBINE-DRIVEN PUMP STEAM DRUM I~~- y 7 yfjOR-2 LOOP 2 j DRIVEN I I x 3 i I PUMP oJ e = EVAPORATORS g i t. = m-h k.a,,o., T MOTOR- . RECIRCULATION DRIVEN I PUMP PUMP AUXILIARY FEEDWATER a PUMPS I 3 l V i I TYPICAL OF 3 LOOPS l DS9 WLRBI

-l i l CRBRP DIRECT HEAT REMOVAL SERVICE AIR BLAST j' HEAT o j l EXCHANGERS ,i' ll-l 1 2 l 4 FAN FAN N REACTOR l ' PUMP VESSEL NaK 2 i N= l PUMP ) =q,3 { [ E =u OVERFLOW -oo-MAKEUP t HEAT EXCHANGER u PUMPS e Ii OVERFLOW VESSEL

i j CRBRP OVERALL LAYOUT l (PLAN VIEW) l 740FT CONTROL SUILDING PLANT SERVICE BulLDING CONTROL / DIESELGENERATOR BUILDING ROOM / / INTERMEDIAi5 g / INTERMEDIATE PUMP NERATORS P OVERFLOW TANK f gSUPERHEATERl1PERCELU [/ ff-STEAM DRUM FUEL HANDLING CELL DECONTAMINATION FACILITY NEW-FUEL 1 DEAERATOR / M O LOOP 1 TURBINE GENERATOR ~ 1 g o enII e i l. GFnMiilipams "2 . FT ~ TURBINE GENERATOR ^

  • I*

4 g E E BUILDING 7 g h =* g* EX-VESSEL REACTOR STORAGETANK I 9 CONTAINMENT] I' DIRECTHEAT ~ OVALSERVICE CONFINEMENT M BA INTERMEDIATE gHO AN SPORT f NS SYSTEM SYSTEM g c l ll e i l REACTOR SERVICE REACTOR CONTAINMENT STEAM GENERATOR i BUILDING BUILDING BUILDING

i ~ i NO OPERATOR ACTION IS REQUIRED I l TO MITIGATE LOSS OF OFFSITE POWER l

  • REACTOR AND TURBINE TRIP 5
  • DIESEL GENERATORS START f

l

  • STEAM GENERATOR SYSTEM ISOLATES FROM MAIN FEEDWATER j

AND CONDENSER

  • POWER VENT VALVES DUMP STEAM
  • AUXILIARY FEEDWATER PUMPS START AUTOMATICALLY i

I

  • PACC FANS START AUTOMATICALLY
  • PHTS AND IHTS PUMP PONY MOTORS ENGAGE l
  • EVEN IF LOOP PIPING, OR DIESEL GENERATORS, OR ALL l

PHTS/lHTS PUMPS FAIL, NO OPERATOR ACTION IS REQUIRED i i i l l

SODIUM FIRE CHARACTERISTICS " SPRAY FIRES" RESULT FROM LEAKS IN MODERATELY PRESSURIZED SYSTEMS i DROPLETS TRANSFER HEAT TO GAS ~ j DROPLETS REACT WITH AVAILABLE OXYGEN l DENSE AEROSOL IS PRODUCED (~100%) " POOL FIRES" FORM WHEN SODIUM ACCUMULATES ON FLOORS HEAT TRANSFER FROM POOL SURFACE TO GAS i SURFACE REACTS WITH AVAILABLE OXYGEN DENSE AEROSOL IS PRODUCED (~25%) l l il s.

-l l LEAKS IN CRBRP LIQUID METAL SYSTEM PIPING WOULD DEVELOP SLOWLY AND BE DETECTED PRIOR TO SIGNIFICANT SPILLAGE l

  • LOW PRESSURE SYSTEM i

l I

  • PIPING TOUGHNESS
  • SLOW FATIGUE CRACK GROWTH
  • EXTREMELY SENSITIVE LEAK DETECTORS d

l l l l l h 1

CRBRP CELL LINERS, CATCH PANS AND FIRE SUPPRESSION DECKS ARE ENGINEERED SAFETY FEATURES I 1 o CELL LINERS AND CATCH PANS FUNCTION TO PRECLUDE i SODIUM / CONCRETE REACTION, THEREBY PREVENTING GENERATION OF l HYDROGEN o FIRE SUPPRESSION DECKS FUNCTION TO TERMINATE RESIDUAL SODIUM t BURNING o THESE FEATURES DO NOT FUNCTION TO CONTAIN RADIONUCLlDES l o APPROPRIATE CRITERIA ARE SPECIFIED l l i i l

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CRBRP CATCH PAN SYSTEM FOR AIR-FILLED CELLS STRUCTURAL CONCRETE l di.Odk i' STEEL GRATING fy.*gt 0.dfd:- !,a e a e a a a e a u a s qm a m a m a s a a a FIRE l cSy T SODIUM FLOW UPPRESSION VENT i DECK } f n n nn F n n k.F nn F n ) L J l J lJ l J l J l J l I i J l J >J l J l J l = INSULATING A' b !l l ~ l PANEL G ES__ l ll ll DRAINS 1-1/2 DIA. 3/8 IN. WELDED STEEL i ] AIR GAP i [j d / CATCH PAN PLATE (STAGGERED) // 5h.[g* STRUCTURAL CONCRETE

\\ l THE CRBRP CONTAINMENT SYSTEM MUST ACCOMMdDATE A WIDE RANGE OF CONDITIONS l , i;

  • COVER GAS LEAKS i

l i

  • SODIUM LEAKS AND FIRES 4
  • SITE SUITABillTY SOURCE TERM
  • CRITERlON SMALL FRACTION OF 10CFR100 l
  • e i

9 81-W12520-14 .s

i ~ t i CRBRP CONTAINMENT SYSTEM ~ }H 1 d 1 CONCRETE CONFINEMENT STRUCTURE RECIRCULATING. ANNULUS u FILTRATION INSTRUMENTATION SYSTEM OOO 1 / 0 ~ ~ = STEEL CONTAINMENT I= VESSEL 1 CIS SENSOR (3) CIS VALVES RE ~ / ..__I A 1NSULATION l_ 7 ~ i CIS LOGIC g CIS SENSOR (3) l l 6--------- TRAIN #1 I 1 I t l INERTED I CIS LOGIC CELL - ~ " ~ ~ ~ ~ - ~ ~ ~ ' TRAIN #2, / CONTROL ROOM CELL LINER e A 9 8; WL25JD 87

i l ACCIDENTS IN THE CRBRP CONTAINMENT l WOULD DEVELOP SLOWLY l l

  • ATMOSPHERIC PRESSURE SYSTEMS I:

l

  • SODIUM WELL BELOW ITS BOILING POINT
  • INERTED AND LINED CELLS MINIMlZE SODIUM BURNING i

l 1 i 1 i l

  • s i

\\ l i t e l

l 1 i.( THE CONTAINMENT ISOLATION SYSTEM i l WILL ACT TO CONTAIN ALL DESIGN BASIS l EVENTS; OPERATOR ACTION MAY BE i l REQUIRED TO ISOLATE LEAKING AUXILIARY SYSTEMS 'l i l

  • RADIONUCLIDE RELEASE t

l REDUNDANT INSTRUMENTATION DETECTS

  • REDUNDANT LDGIC TRIPS
  • REDUNDANT VALVES ISOLATE "OPEN" PROCESS LINES INSTRUMENTATION WOULD DETECT LEAKAGE OF " CLOSED" PROCESS LINES I
  • OPERATORS CAN CLOSE VALVES FROM THE CONTROL ROOM l[

I 1 I

m. g_

THE CRBRP DESIGN INCLUDES FEATURES TO ~ ~. 4 MITIGATE A BROAD SPECTRUM OF STEAM GENERATOR LEAKS l

f' 2
  • LEAK DETECTION l

SMALL LEAKS (CRACK) l!

  • MANUAL WATER DUMP h
  • IHTS EXPANSION TANK RUPTURE DISC '

INTERMEDIATE LEAKS

  • MANUAL WATER DUMP p

(FRACTION OF A TUBE) l I

  • MAIN RUPTURE DISCS

{ LARGE LEAKS l

  • AUTOMATIC WATER DUMP p (EQUIVALENT TO SEVERAL TUBES)

I l I i SODIUM WATER REACTION PRESSURE RELIEF SYSTEM (SW.RPRS) l ll

a= 1 r CRBRP SODIUM WATER REACTION l PRESSURE RELIEF SYSTEM i j i RUPTURE DISC VENT DUYURE DISCS 1 TO SODIUM (3 SETS) T ~ IGNITER l DUMP TANK l Fl i IHTS EXPANSION __ RUPTURE TANK DISC l EVAPORATOR 1 l l WATER ' -M - - - -l- - -- ->.- - - - -[_-#.. _--,- - -9 T ~- l DUMP l TANK l l l + 1 h LEAK DETECTOR ~ [ REACTION PRODUCTS IHTS PIPING SEPARATOR TANK ff

WATER / STEAM PIPING i

l 9 et gutM3B N =_g

a a APPROACH Hypothetical core disruptive accidents (HCDA's) are not design j i basis accidents l Design features prevent initiation of HCDA's Prudent margins beyond the design base incorporated to further l reduce public risk j e Structural margin beyond the design' base (SMBDB), l Thermal margin beyond the design base (TMBDB) t i h 3488-41

1 i -l l L I LMFBR AND CRBRP OVERVIEW BRIEFING FOR THE .l l l NUCLEAR REGULATORY asisas l COMMISSION L AUXILIARY SYSTEMS i, PRESENTED BY I GEORGE H. CLARE LICENSING MANAGER, CRBRP PROJECT WESTINGHOUSE ADVANCED REACTORS DIVISION SEPTEMBER 23,1981 8

l AUXILIARY LIQUID METAL SYSTEM i ) ^^ 1 I f o SAFETY FUNCTIONS - COOL SPENT FUEL; 2 FORCED LOOPS,1 NATURAL CIRCULATION LOOP l ,1 l - EMERGENCY REACTOR DECAY HEAT REMOVAL; DHRS - MAINTAIN REACTOR COOLANT BOUNDARY o GTHER FUNCTIONS l - MAINTAIN NORMAL REACTOR VESSEL SODIUM LEVEL - REMOVE IMPURITIES - FILL AND DRAIN l t

CRBRP i AUXILIARY LIQUID METAL SYSTEMS SGB RCB RS8 a i S rm i .ea.. j oo 4 f ~ 'Y.,y ..C 'y ww, c } EVST d !!.I~ ' {' i. 7m RV "3 I V Y - M i 5.$ g lf si @s!?..lQ:. R s.) ( ) I 3 g.. / / \\ e EVST COOLING e PRI. SODIUM PURIF. eel. SODIUM e IHTSSODIUM i M IMPURITY SODIUM PURIF. i RV LEVEL CONTROL FILIJDRAIN PURIF. MONITORING e I M P U r.1T Y RV DECAY T. e IMPURITYf MONITOR MONITOR REMOVAL j Rockwellintemational e IMPURITY MONITOR 77(812)68-138 % se % I \\ ~

O 1 REACTOR REFUELING SYSTEM FUNCTIONS THE REACTOR REFUELING SYSTEMS CONSIST OF EQUIPMENT AND FACILITIESTO ACCOMPLISH THE FOLLOWING: s

  • REACTOR REFUELING a REMOVAL OF IRRADI ATED CORE ASSEMBLIES FROM THE REACTOR CORE iO SPENT FUEL STORAGE OUTSIDE THE REACTOR VESSEL a ONE-FOR ONE REPLACEMENT 01-IRRADi ATED CORE ASSEMBLIES IN THE REACTOR CORE WITH NEW CORE ASSEMBLIES i

a POSITIVE MECHANICAL IDENTIFICATION OF EACH CORE ASSEMBLY PRIOR TO REMOVAL AND INSERTION INTO THE REACTOR CORE 4 e NEW FUEL RECEIPT a REMOVAL OF NEW CORE ASSEMBLIES FROM SHIPPING CONTAINERS a INSPECTION OF NEW CORE ASSEMBLIES FOR SHIPPING DAMAGE AND POSITIVE VISUAL AND MECHANICAL IDENTIFICATION s INERTING AND PREHEATING OF NEW CORE ASSEMBLIES a INSERTION OF NEW CORE ASSEMBLIES INTO SODIUM PRIOR TO REACTOR SHUTDOWN FOR REFUELING e SPENT FUEL SHIPPING e RADIOACTIVE DECAY OF HIGHER THERMAL-POWERED IRRADIATED CORE ASSEMBLIES TO ACCEPTABLE LEVELS FOR SHIPPING a REMOVAL OF CORE ASSEMBLIES FROM SODIUM AND DRIP-DRY a EXTERNAL EXAMINATION OF SELECTED CORE ASSEMBLIES IF DESIRF ) TO ASSESS DEMONSTRATION PLANT PERFORMANCE a POSITIVE VISUAL AND MECHANICAL IDENTIFICATION OF CORE ASSEMBLIES BEFORE SHIPPING e LOADING OF CORE ASSEMBLIES INTO SPENT FUEL SHIPPING CASK 4 I ~

N, l i \\ l s ec z i~ I r _"k i l Z-e 33 7 I WW d ~ "3 F l EM i my E &) ""w Mwwmwcv - ww-w ww e- -,n-n-mw-m-- - - - - - - - - - - - - - - - - _ _ _

i INERT GAS SYSTEMS l RAPS: RADIOACTIVE ARGON PROCESSING SYSTEM l RECIRCULATES PRIMARY COOLANT SYSTEM COVER GAS CONTINUOUSLY REMOVES FISSION FRODUCT GASES FROM COVER GAS CAPS: CELL ATMOSPHERE PROCESSING SYSTEM - MONITORS INERTED CELL ATMOSPHERES - PROCESSES CONTA.MINATED CELL ATMOSPHERES l l - PROCESSES EFFLUENT FROM RAPS APU: ATMOSPHERE PURlFICATION UNIT l l - REMOVES WATER VAPOR AND OXYGEN FROM FUEL HANDLING CELL ATMOSPHERE ARGON DISTRIBUTION NITROGEN DISTRIBUTION t I ~. 9-81-WL2520-57

4 l FAILED FUEL MONITORING SYSTEM 1 i ASSURES DETECTION AND TERMINATION OF LOCAL FUEL FAILURES .p DELAYED NEUTRON DETECTORS l. I ~

  • SENSE FUEL EXPOSURE TO SODIUM l

l l sp.wusam

~ i l l FAILED FUEL MONITORING SYSTEM FACILITATES FUEL MANAGEMENT BV DETECTING AND LOCATING j FISSION GAS LEAKS COVER GAS MONITORING SYSTEM

  • DETECTS AND CHARACTERIZES DISCRETE FISSION GAS LEAK EVENTS j

FAILED FUEL LOCATION ' SYSTEM I [

  • CONCENTRATES AND ANALYZES TAG GASSES TO IDENTIFY

[ FAILED ASSEMBLIES i l I 9 81 WL2520 41

l. i i 1 ) I 1 DELAYED NEUTRON MONITORING SYSTEM i i 818 ft 0 in. LEVEL j ID \\ {yE(%gg, l l "g p j. T O PREAMPLIFIEM SECTION A-A .'gCONCRETE 5 .4 4. w l s CABLE l A . $ g,,. ~ i DETECTOR O OETECTOR SOURCE } THIMBLE THIMBLE IHX REAUTOR e e bd INSULATION GRAPHITE V \\ _ / m.p y. l

  • * *:V y

i N r 5 l i,:.',:.' / i .::.6 0 Call 8 RAT 10N B i / / ~ ' NEUTRON s 50I

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/' f = AD' y g } NEUTRON y g .,Y l d@.::.' L E AD.*.".~."'..'. DETECTOR ~ ~ i l PRIMARY SODIUM SECTION B-B PUMP y i PIPE SHIELD MODERATOR q f ASSEMBLY I @,C""*"' sww i.a O

l l i LIQUID METAL / GAS LEAK DETECTION SYSTEM e FUNCTION l i i i e CONTINUOUS MONITORING OF LIQUID METAL SYSTEMS FOR LEAKAGE INTO SURROUNDING GAS SPACES 1 l i l e DETECTION (WITH LOCATION INFORMATION) OF SMALL LEAKS PRIOR 1 TO SIGNIFICANT CORROSION OR CRACK PROPOGATION i 1 e DETECTION OF LARGER LEAKS PRIOR TO SIGNIFICANT LOSS OF LIQUID l METAL INVENTORY OR ONSET OF SIGNIFICANT ECONOMIC DAMAGE.. ll 31-AU19-924 l tases,sys==e creup

) i j j 4 8 2 el l l l i; i. 4 i O3 e ) f/ 5 w E R E i H P \\ Sf G O r N M k l I IP TI N A jJ T AP _w, N T E R j H E L O L NF \\ E g S I I C AN D T ^' T MA C G R N T TM E NI OLP/ v I EE TM AA DT L S S t /E U S KY P S A N lPI G 'f AS j EN L L S LR O OO S I sT OC AT RE G A ET AE T D ES ON SE T E V - D LM R r A AU kU 09 G LL TR AE l' E T CN g Q-OA MS LP jr N f e j DI R I E U E G Q T N AA h H d I I D C = L = E X H ME mE M de R T .m e n O E A O T n e d E R N n n H ir a I T l _ 9 a. c L n O I e R s k d u c s TL o e N, g KEN, y l R A O LDP C gy _! !;l 'I l1l l i! ,I l I

l l ,t l ~ s T .T N E .u C ) R 0 RN oU s 0 .o D p U 4 O OLs ( C M R0a 0A s R oP 9 n 0 E O N n u 08R N Ot E 8 O 8 .A T O Ro p ITo O C S E o 3 I T AE T R uT As R S I LS ~ A O .C O T L A*+ T E S UO sM/ SP T U C .E C D R EE Y S uT N E LT N 1 T gLA O I S 0 E W OL E I y ,CP G T D O 4 L

  • f A

A e

  • . k D *,T E

Fi4 N T Z H L S L I T B A R N O N t A A G O E V O O E\\ H C T M E I TA \\A M I e C T E b E HF \\ I L OI R U C $/H s T 1 T E 0 A D Q 0 e E y 8 E H gg S g y d T g t gy, p E g ,g gp g D K A L E A L R IT R A L NaO O E EnT T sa Ru s j C Ao/ Esp S CM T E s s te P es Pep A M IRi IP E T L oPN NI D A A, O R Na k G SO L I E T O H R Ea S / s N D O sa4,j R O L L n uT R LwC r E A I rJ /* ~ A E A T g, /" NE T m\\ E R NS D R E Il E E a T T L s E C M I u T M .[M A P g T G NN P N O D D I L C G T O G = I G U D s U L L Q M P e I E L L T R l. O P R. u J

L

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l!!ljlf; ji l

3

Il l

} l .LIQUID METAL / GAS LEAK DETECTION SYSTEM i BREAKDOWN OF DETECTOR QUANTITIES.. i i l DIFFERENTI AL SODIUM l PRESSURE IONIZATION CABLE CONTACT i s REACTOR AND 2 3 i GUARD VESSEL 3 PRIMARY HEAT TRANSFER SYSTEM 30 6 12 4 INTERMEDIATE HEAT TRANSFER SYSTEM 73 6 27 l STEAM GENERATOR 12 21 30 AUXILIARY SYSTEMS 6 38 29 157 l TOTAL 124 46 71 214 l l 1-H Rockwellintemettonal l Enwgy SM Greg 81.AU19-921 N l r.. i

FUNCTIONAL DESCRIPTION ~ l l o THE PIPING AND EQUIPMENT ELECTRICAL AND CONTROL SYSTEM PROVIDES ELECTRICAL HEATERS, HEATER POWER CONTROLLERS AND RELATED TEMPERATURE MEASURING AND CONTROLLING INSTRUMENTATION AND EQUIPMENT REQUIRED FOR - PREHEATING OF COMPONENTS AND PIPING PRIOR TO SODIUM FILL - HEATING OF SODIUM FILLED COMPONENTS AND PIPING FROM l REFUELING CONDITIONS TO AND DURING PLANT POWER OPERATION 4 i; l HOLDING TEMPERATURES OF COMPONENTS AND PIPING AT SPECIFIED - SE U N ALLY HEATIN SECTIONS OF SODIUM FILLED COMPONENTS l AND PIPING IN WHICH THE SODIUM HAS BEEN ALLOWED TO FREEZE \\ i l u I 9-81 WL2520 58

j l TUBULAR TRACE HEATER i HEATER CONFIGURATION ON l (TYPICAL ASSEMBLY) PIPE OR COMPOhiENT OUTER i SHEATH- .e.yN.#,P-.' $h h $ s t,c p.- l T ~ A "*:-1. ;.f0 f hV:.,j.. A*pp,:.:p 4 ,a;.* c..M. .. s, .x rs x. e i it ':.y. !!- sk. INS LATIONf l&y*/WC s.. . ?, 5 i-. o .k 'E:j.S'ds[i. Iih'@: '%?,e<,W.5 i:.s&; e M.$- h: i[hll!. .?./ . !I l 5 M N NN l I I V w.1 i v c k+ :.v a a e w. ' M,9htiM.. d h; -i +. ?g> %. N,..,I.,N.c '.'.N6'$.. i j p'.ge,)N.. 't:ff,,h.'e. 1 J MOUNTING CLIP [l f;7. b@.#,.. . f. 4 SEAL PLATES

  • g,.

fg [:34 r~l INTER SFEATH' @ U i .y$hbi-N' N ;{R.'hi iD POWER LEAD- -- Y -S SpgE OR GROUND LEAD 8 2 COMPONENT CERAMIC -"I TO METAL SEAL)$g ..EM. 4 FIBERGLASS SLEEVE Ft9 HEATER HEATER MOUNTING SUPPORT,TYP .50i.005 DIA. 4 J) BAND I, g. z 5 / // __,, PIPE OR N i+ HEATER SHEATH k-- - \\ COMPONENT fl g1l WALL i ' T L L,,. C L. 4 W. . S 35 WL25tt 5

t EMERGENCY POWER SUPPLIES I o THREE (3) CLASS 1E SOURCES PROVIDE POWER FOR FORCED FLOW DECAY HEAT REMOVAL - DIESEL GENERATOR A - DIESEL GENERATOR B - DIVERSE (BATTERY) POWER SUPPLY o IBC BATTERY SUPPLIES AND TURBINE DRIVEN AFWP CAN SUPPORT NATURAL CIRCULATION DECAY HEAT REMOVAL 1 o FOUR (4) SEPARATE GRID CONNECTIONS WILL DECREASE RELIANCE ON ON-SITE SOURCES t ^ h! 81 WL2520-54

} l AUXILIARY COOLING SYSTEMS 1 o MO SEPARATE AND INDEPENDENT TRAINS PROVIDE COOLING TO ESSENTIAL EQUIPMENT i EMERGENCY COOLING TOWERS [- - EMERGENCY PLANT SERVICE WATER SYSTEM f I - EMERGENCY CHILLED WATER SYSTEM - RECIRCULATING GAS COOLING SYSTEM o A SEPARATE VENTILATION SYSTEM PROVIDES OUTSIDE AIR COOLING TO EACH HTS LOOP IN THE STEAM GENERATOR BUILDING f l } j i* l l ii 1 we %9() rp,

l l RADWASTE SYSTEM l GASEOUS WASTES ARE PROCESSED BY RAPS AND CAPS l

  • LIQUID AND SOLID WASTES ARE PROCESSED BY CONVENTIONAL SYSTEMS LIQUID VOLUMES ARE A SMALL FRACTION OF TYPICAL VOLUMES FOR j

LWRS i l l i i i b l \\ l ~. t 81 WL2520-56

l CRBRP IS BENEFITING FROM A WIDE RANGING DEVELOPMENT PROGRAM i i i

  • REACTOR SHUTDOWN SYSTEMS
  • SHUTDOWN HEAT REMOVAL SYSTEMS i
  • CORE COMPONENTS

(% j = SODIUM-WATER REACTION PROTECTION SYSTEM

  • MAIN HEAT TRANSPORT SYSTEM COMPONENTS
  • REACTIVITY CHARACTERISTICS
  • FLUX MONITORING

= SPENT FUEL COOLING

  • EVENTS BEYOND THE DESIGN BASE (DEGRADED CORE EVENTS) l l

I 9-81-PG.538-4 i

1 4 l I q EVOLUTION OF THE LMFBR i CRBRP i l FFTF SEFOR 1969 EBR-Il 1963 l b FERMI 1963 bl HALLAM 1962 i l b.SRE 1957 4 I b EBR-1 1951 4 l l 1950 1960 1970 1980 1990 2000 t I 9 28 W1476 79 0

l CRBRP IS BENEFITING FROM FFTF l

  • EXPERIENCE IN DESIGN AND CONSTRUCTION; CONTRACTOR l

REPRESENTATIVES ARE LOCATED AT HEDL. l INDIVIDUALS WITH FFTF EXPERIENCE ARE PART OF THE CRBRP PROJECT e l OPERATING EXPERIENCE AND TEST DATA WILL BE UTILIZED REACTOR COMPONENTS AND MATERIALS HEAT TRANSPORT SYSTEMS INSTRUMENTATION AND CONTROL SYSTEMS REACTOR SHUTDOWN SYSTEM REFUELING SYSTEM j AUXILIARY SYSTEMS i 'l e 9-81-PO2538-5

s I a t -w : I 1 i THE REACTOR AND PLANT SYSTEM CONCEPTS UTILIZED IN CRBRP 1 CAN SUPPORT RELIABLE PLANT OPERATION

  • A VARIETY OF APPROPRIATE SYSTEM CONCEPTS ARE EMPLOYED IN CRBRP TO MITIGATE A BROAD SPECTRUM OF ACCIDENTS

-l l i l j I 9-81-WL2520-31

September 29, 1981 Distribution

hk File bcc: Applicant Service List Local PDR CRBR File NSIC TERA TIC E. Case D. Eisenhut R. Vollmer R. Mattson S. Hanauer

[ 'yh \\* ' I I $7 T. Murley J. P. Knight q e P,\\fI,5 W. Johnston /$y/ @ ; u L,i l L. ) I D. Muller 6 19gja d P. Check '1 W. Kreger ?" 001 L. Rubenstein \\ u.s.rr$*il3%Y"" 7 2 F. Schroeder 40'Igjlro(A M. Ernst I ACRS (16) / g l OI&E (3) ~ l S. Treby (OELD) l J. LeDoux, I&E l V. Moore l B. Grimes ) C. Thomas P. Leech R. Stark W. H. Foster R.. Woodruff B. Morris I&E Region II ED0 List of Attendees l l l}}

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