ML20002C953
| ML20002C953 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/04/1964 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Boyd R, Doan R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101150344 | |
| Download: ML20002C953 (13) | |
Text
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G ilNC0HG DR R. L D0AN DIRECTOR OF REACTOR LICENSING
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ATOMIC ENERGY COMMISSION WASHINGTON DC g gg3 4 p i 9 4; AUGUST 4,1954MkO5)N FROM CONSUMERS POWER COMPANY a g a 4n re s
ATTENTION MR ROGE'R S BOYD dilecopy A - IN RESPONSE TO ITEM 1 OF CHANGE No.2 TO THE BIG ROCK POINT TECHNICALP SPECIFICATIONS, DOCKET 50-155, AS TRANSMITTED BY YOUR TW7 0F JULY 22, 1964, THE INFORMATION AND EhAULUATION OF THE SOURCE OPTIMIZATION
' TESTS RECENTLY COMPLETED ON THE 44 BUNDLE CONFIGUATION IS AS FOLLOWS '
1.
THE CORE CONFIGURATION DECIDED UPON AS THE MOST DESIRABLE FOR MEETING STARTUP ANI) MSIBILITY REQUIREMENTS, WHILE STILL YIELDING A POWER DISTRIBUTION AND PEAKING FACTORS COMPATIBLE WITH OPERATION AT 60 KW-L, IS A SKEWED CORE WITH FUEL IN THE FOLLOWING LOCATIONS -
R0W 58 - POSITIONS 02 TO 07 ROW 57 - POSITIONS 01 TO 08 ROW TY - POSITIONS 01 TO 08 L
e ROW 55-POSITIONS b1 TO ' O
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s ROW 54 - POSITIONS 01'TO 05 4f, ROW 53 - POSITIONS 02 TO 07.
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2.
THE SOURCE POSITIONS SELECTED TO YIELD ADEQUATE START-UP COUNT RATES AND SIGNAL TO NOISE RATIOS ARE 01-58 AND 08-58.
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3.
WITH THE ABOVE CORE CONFIGURATION AND SOURCE POSITIONS, THE ALL-RODS /
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DilNCONG og AUGUST 5,1964
, 9/25 AM CHAP'.EVOII, MICHIGAN N
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DIRECTOR OF REACTOR LICENSING g
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ATOMIC ENERGY COMMISSION VASHINGTON DC "O
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ATTENTION MR ROGER S BOYD REFERENCE TO TWX SENT AUGUST 4,1964 FROM CONSUMERS POWER COMPANY PLEASE MAKE THE FOLLOWING CORRECTIONS-SECTION A PART 1 ROW 7 SHOULD READ ROW 56 - POSITE0NS 01 TO PI SECTIONA PART 4 LINE $ SHOULD BE INSERTED AND READS V
F.C. NO.1 IS A CONVENTIONAL FISSION COUNTER INSTALLED Ih A DUMKER CHAMBER SECTION A PART 4 SECOND SECTION OF TAkt.E COLUMN HEADINGS SHOULD READ NO.5 NO.6 XE NO.7 ETC 8
SECTION A PART 5 PARA *,RAPH 6 LINE 3 SHOULD READ 84 BUNDLE CORE. CORRECTING FOR, ETC t
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SECTI0'4 'J MISCELLANEOUS ITEMS PART 1 LINE 10 SHOULD READ OF C' EFFICIENT AT THAT POINT OF -0.005 i ~0/-4/ PER DEGREE F.
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-IN READING ON CHANNEL 6 WAS APPROXIMAT 3.5 WITH A SIGNAL-TO-NOISEE QT RATIO OF GREATER THAN 4.
CHANNEL 7 READ APPROXIMATELY 4.0 WITH A XQIKVNAL-TO-NOISE RATIO OF GREATER THAN 4.0.
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4.
THE INSTRUMENT READINGS TAKEN DURING THE APPROACH TO CRITIC 4L ARE LISTED BELOW.
IT SHOULD BE NOTED THAT INSTRUMENT NO. 15A IS THE SPECIAL IN-CORE FISSION COUNTER CURRENTLY INSTALLED AS'PART OF IN-CORE PROBE NO.15, LOCATED BETWEEN CORE POSITIONS 08-55,a I U'UG,
r-s ',-i09-55 08-Q AND 09-54.
3 F. O. T.1, I3 1 T.'2TIO.L 5'~ 33TN COUNTER IU3TALIZI IN AND INSERTED IN CORE POSITION 08-51-DURING THIS CRITICAL APPROACH AND READING OUT IN THE C0f1 TROL ROOM.
RTs3XXIIXERKXMXXIMIIIKEXXREYIIIEXXXXEXIXXXX5X2 LINE NO.
RODS WITHDRAUN INITI,sL REVISED h0.1 NO.2 NO.3 NO.4 K/EST/
K/EST/
X10/-i X10/-7 X10/-7 1
ALL RODS FULLY ALL INSERTED 0.906 RO.9044 10 20 3
2 A4,A5,B5,B6 READINGS C 6,D 1,D 6,E 1 LESS THAN 3
E2,E5,E6,F2, F3,F4,Fi 10/-5/
FULLY WITH l
DRAWN 0.924 0.9224 5
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3 ABOVE PLUS A3,E3 FULLY WITHDRAWN 0.952 EINEXX 0.9508 7
25 3
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4 ABOVE PLUS 9/
B4,D2 FULLY WITHDRAWN 0.977 0.9756 6
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5 ABOVE PLUS-C1 AT NOTCH 09, C5 AT 8
24 3
NOTCH 10 0.990 6
ABOVE PLUS EXXXIXME C',C5 FULLY 1
WITHDRAWN 1.001 0.9992 10 19 3
7 ABOVE PLUS A2,E4 AT 04.
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13 20 3
8 ABOVE PLUS A2,E4 AT 05 18 20 10 9
ADOVE PLUS A2 AT NOTCH 05 E4 AT NOTCH 06 1.0007
/ALL CHANIELS ON SCALE AND
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RISING INCLUDING CHANNELS 4 AND 5/
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NO.7 15A F.C. ?!0.1 I
X10/-5 k1 2
3.5 4.0 5/ APPROX /
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2.2 14 4
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5 2.2 22/18&
26/16&
2 60 220 6
2.0 2S&
65&
530 520 7
1.3 45&
150&
1800 8
1.3 130&
650&
7600 6500 9
NOTE LAST LINE OF 2100&
SECTION K 1
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&- INDICATES RECORDER READINGS.ON CHANNELS 6 AND 7.
' Ut! STARRED CHANNEL 6 AND 7 DATA ARE SCA',ER DATA.
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EVAUATION OF THE ABOVE DATA TAKEN PRIOR TO AND DURINC THE APPROACH TO CRITICAL INDICATES THE ADEQUACY OF THE SOURCE LOCATIONS AND THE SELECTED CONTROL ROD WITH-DRAWAL SEQUENCE.
FOR EXAMPLE, THE SOURCE LOCATIONS 0158,0858 P'ROVIDE A FULLY SHUTDOWN COUNT RATE IN THE STARTUP CHANNELS IN EXCESS OF 3 COUNTS /SEC WITH A SIGNAL-TO XX553X -NOISE RATIO IN EXCESS OF 3/1.
THE SELECTION OF 0158 WAS MADE TO IMPROVE THE VISIBILITY OF C5NTROL ROD WITHDRAWALS.'BY CHANNEL NO.7 THE SECOND SOURCE WAS LOCATED AT 0858 RATHER THAN 0853 IN ORDER TO OBTAIN A SUFFICIENT COUNT RATE ON CNANNEL NO THE VISIBILITY OF CONTROL ROD WITHDRAWAL FOR THE SELECTED ROD SEQUENCE IS EXCELLENT.
TYPICAL PERCENTAGE CHANGES IN STARTUP CHANNEL READINGS FOR PREDICTED CHANGES IN CORE REACTIVITIY ARE AS FOLLOWS -
D KEFF CHANGE IN CH 6 CHANGE IN CH 7 0.952 TO 0.97 5 PER CENT 100 PER CENT 0.9'7 TO 0.98 10
'85
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0.98 TO 0.99 22 75 0.99 TO 0.995 11 61 IT CAN BE SEEN THAT CHANNEL 7 SHOWS VERY GOOD RESPONSES TO INCREASES IN CORE REACTIVITY ABOVE KEFF APPROXIMATELY 0.95.
BECAUSE OF THE LESS FAVORABLE GEOMETRY OF THE SOURCE CLOSEST TO CHANNEL 6, THAT CHANNELS RESPONSE TO CONTROL ROD WITHDRAWAL IS CONSISTENT BUT NOT AS GREAT.
THE ACTUAL CORE MULTIPLICATION WAS FOUND TO BE APPROXIMATELY 0.16 PER CENT LESS THAN PREDICTED, CORRECTING FOR THIS WOULD SLIGHTLY j
DECREASE THE EXPECTED RESPONSE FROM THE STARTUP CHANNELS._
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h THE PIC0 AMMETERS WERE FOUND TO OVdLAP THE STARTUP CHANNEL CHANilELS NO.1 AND NO.3 WERE READING 2 AFID
' APPROXIMATELY TWO DECADES.
3 TIMES THEIR SHUTDOW!! BASE READING WITH THE REACTOR SUBCRITIC CONTROL RODS A-2 A!!D E-4 AT NOTCH 05.
REFER TO LItlE 8 0F DATA.
UPON PULLIllG THE NEXT NOTCH ON ROD E-4, CHAllNEL NO.2 GAVE A CLEAR INDICATION OF POWER LEVEL RESPONSE AT A POWER LEVEL APPROXIMATELY 2 TO 3 T AT PRIOR TO PULLINC THE NOTCH.
PICO NO.3 READ 10 X 10/-7 PER CENT POWER FOR THE SUBCRITICAL COR WITH A-2 AND E-4 AT 05.
THIS SCALE WAS CALIBRATTJ FOR THE OPERATING CORRECTING FOR DIFFERENCES IN WATER DENSITY AND CORE BUNDLE CORE.
POUER DISTRIBUTION THIS CALIBRATION IS EXPECTED TO BE UITHIN A FA PF FIVE OF THE CORRICT VALUE FOR THE 44 BUTIDLE CORE.
THE IN-CORE STARTUP MONITOR,15A, SHOWED GOOD RESPONSE THROUGHOUT T:I STARTUP SEQUENCE.
ITS LOCATibt! WAS REASONABLY CLOSE TO FISSION CHAMBER No.1 WHICH Ues IN THE WATER REFLECTOR.
THE RELATIVE RESPONSE OF THE IN-CORE AND O'JT-OF-CORE FISSION CHAMBERS CA!! BE SEEN FROM T DATA TO BE REA50tlABLY CONSTANT.
SMALL CHA!!GES - LESS THAN 25 PERCENT -
IN COUNT RATE ON THE IN-343 WERE DIIFICULT TO OBSERVE UNTIL THE COUN RATE WAS ABOUT ONE DECADE ABOVE THE FULLY SHUT DOUN CUNT RATE OF EVEN BITTER RESPONSES WULD BE EXPECTED FROM A MORI CENTRAL 5 CPS.
LOCATED IN-CIRE.
FROM THE ABOVE DATA AND EVAUATION, CONSUMERS POWER COMPANY CONCLUDE THAT THE SOURCE POSITINS, ROD PATTERN AND VISIBILITY ARE ADEOUATE FOR START-UP AND OPERATION OF THIS 44 BUNDLE CORE. VE REQtTEST YOUR j
CONCURRENCE.
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BM MISCELLANIOUS ITEMS -
DISCUSSIONS WITH YOUR STAFF HAVE PROMFYED FURTHER INFORMATI0fl ON
.SEVERAL ITEMS NOT CONNECTED WITH -A-ABOVE.
- 1.
THE ANALYSIS ASSO CIATED WITH OUR REQUESTED ITEM t10.20 AS CONTAIt!ED N OUR SUBMITTAL OF MAY 21,1964, STATES THAT THE ?EMPERATURE COEFFICIEt!T
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FOR THE 84 BUNDLE CORE WILL BE MEASURED AND IS EXPECTED TO SHOU A
.SLIGHTLY HIGHER TURF!-AROUt!D TEMPERATURE THAN THAT OF PREVIOUS CORES.
THESE MEASUREMEtiTS HAVE BEEN MADE ON THE 84 BUNDLE CORE AND THIS A'!ALYSIS CAN BE MADE MORE CURRENT.
THE INITIAL TEST OF THE 74-BUt!DLE CORE INDICATED A TEMPERATURE COEFFICIENT OF ZERO AT 93F.
THE RATE-0F-CHANCE OF THE COEFFICIENT AT 93F WAS -0.005 X 10/-4/ PER DIGREE F.
THE 84-BUt!DLE INITI AL TURNOVER POINT WAS 127F WITH A RATE-OFZ-
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C/ 4/ PER DEGREE F.
THIS IS IN GOOD AGREEMENT WITH THE EXPECTED CHANGE IN COEFFICIE!!T FROM THE 74-BUNDLE TO THE 84 BUNDLE LOADING.
2.
DETECTOR 15A REFERRID TO IN -A-ABOVE IS A SPECI AL HI-SEi!SITIVITY FISSION COUNTER REPLACING ONE REGULAR FISSION CHAMBER ON It!-CORE STRING
!?JMBER 15.
COMPARISON OF REGULAR FISSION CHAMBER AND HI-set!SITIVITYP TYPE IS AS FOLLOWS WITH PHYSICAL DIMENSIONS BEING APPROXIMATELY THE SAME.
REGULAR DETECTOR IS USED WITH TRANSISTORIZED DC AMPLIEIER.
3PIC-IAL DETECTOR IS USED WIT SPECIAL ESXXX EXPERIMENTAL TRANSISTORIZED PULSE CIRCUITS.
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REGULAR HI-SENSITIVITY.
LINING U/3/0/895PERCENTPLUS SAME ENRICHED PRESSURE SEAL LAVA GLANDS CERAMIC i
FILLING GAS 1 ATMOS. N2 200 PSIG AGRott OPERATING VOLTAGE 100 VPC IEXMEXERXXXX 500 VDC
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NEUTR0!! SENSITIVITY 3 X 10-18 AMPS /NV 10/-4 CPS /NV ENVIRONMENTAL 650 F 1000 F It!TERMAL CABLE STAINLESS STEEL CONDUCTOR NICKEL CONDUCTORS, AND SHEATH, COAX, WITH ALUMINA TRIAX, QUARTZ INSULATION FIBER INSULATION NEUTRON PULSE UNDETECTADLE '
3 - 6 VOLTS
!!EIGHT FROM CURRENT FULSE AMPLIFIER 3.
SUMMARY
DATA FROM THE HAZARDS ANALYSIS OF THE 60 KW/L CORE HAVE IIIAIX PREVIOUSLY BEEN PRESENTED IN AMENDMENT 14.
FOR THE PURPOSE
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OF IIIAIXEIXEX DETAILING THE EXTENSIVE HAZARDS ANALYSES WHICH UERE PERFORMED, AND SUMMARIZED IN AMENDMENT 14, ADDITIONAL INFORMATION
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IS PRESENTED BELOW.
IN EVALUATING THE Ed2ARDS ASSOCIATED WITH THE OPERATION OF THE O KW/L-CORE REFERENCE IS MADE TO THOEXXX-THOSE STUDIES PRESENTED IN THE FINAL HAZARDS SLP.: MARY REPORT SECTION 12, TOGETHER WITH PERTINENT
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.s AME!!DMENTS THERETO.' THESE STUDIES WERE MAD' E FOR THE MOST SEVERE p
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EXPECTED C0tJDITION OF THE IBG ROCK POItk PLANT, I.E., 240 MWT AT 1500 PSI A WITH THE 84 BUt!DLE CORE - APPROXIMATELY 45 KW/L.
AT LOWER,T6TAL POWER LEVELS AND LOVER PRESSURES, ALMOS,T ALL ACCIDENT CASES ARE LESS SEVERE THAN THOSE CITED, EVEN THOUGH POWER DENISTY IS GREATER.
SO'ME EXCEPTIONS ARE DISCUSSED LATER.
THE FOLLOWIt!G FACTORS CONTRIBUTE TO THIS SITUATION-1 THE MORE SERIOUS POSTULATED ACCIDErlTS DEPEND FOR THEIR SEVERITY UPot! A!:0Ut1T OF TOTAL ENERGY STORED Irl THE REACTOR PRIMARY SYSTEM.
THE 60 KW/L TESTS WILL BE RUN AT 165 MWT AND 1050 PSIA.
IN SOME I!!STA!!CES, THE HIGHER, POWER DENSIFY DOES SLIG$'TLY SPEED UP THE X TRAIT! 0F EVENTS DURIllG THE POSTULATED ACCIDEtJT, BUT NOT TO AtJY DEGREE THAT L'00LD INVALIDATE THE At!ALYSES PRESENTED IN THE THSR.
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TRANSIEtlTS It! t1EUTRON FLUX FOR SYSTEM TYPE ACCIDEtJTS ARE LARGELY EPXXX DEPEllDENT ON RATE OF CHAtJGE OF PRESSURE, WHICH IS ALMOST DIRECTLY PROPORTIONAL TO STEAM FLOW RATE.
SINCE THIS IS A FUt!CTI0t1 0F TOTAL POWER OUTPUT IRRESPECTIVE OF CORE SIZE, YPXXX O KW/L AT A LOUER TOTAL CORE POWER IS A LESS HAZARDOUS C0tIDITION THAN THOSE CASES ALREADY DOCUMEllTED.
3 SINCE RATE OF CHAT GE OF PRESSURE EXERTS ITS IMPACT O!! CORE RESD0!!SE LARGELY THROUGH THE TRANSIENT VOID MECHANISM, THE ARGUA ICHT IN ITEM 1 DEPENDS ON THE TRAt!SIENT VOID COEFFICIENT OF REAC-FOR iHE 240 MWT, 84 BUNDLE CORE, THIS COEFFICIEtJT IS TIVITY.
GIVE!! AS 7.4 CEf1TS PER PERCEtJT VOID.
THE CORRESPONDING CALUCAXXX CALCULATED VALUE.FOR THE 60 KW/L CORE IS ESSENTI ALLY THE SAME,
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SUCrHIIFTHAT~SIMIMR PNSSURE TRANSIENTS YIELD SIM2LAR REACTIVITY 1
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FOUR SPECIFIC CASES UERE PREVIOUSLY EVALUATED At!D REPORTED Ill AMENDME!!T NO.14 IN TABLE VIII.
Ill THESE PfRTICULAR CASES THE AGXXX ARGUME!!T5 CITED ABOVE PLAY A ROLE,'BUT THE HIGH POWER DErlSITY CORE IN OXXXXX3INEXUESIKXE SOME I!JSTAtlCES RESPONDS TO A SOMEUHAT GREATER DEGREE THAN THE CORRESP0tJDING 240 MWT CORE.
1.
Ill THE CASE OF GENERATOR TRIP THE NEUTRoll FLUX RESPO!!SE S SIMILAR, THE PRESSURE RISE IS HIGHER FOR THE SMALL CORE, A!!D 50 IS THE PEAK HEAT FLUX.
t:0!!E ARE SIGt!IFICANT TRAt!SIEt:TS.
2.
THE TURBINE TRIP UITH HIGH FLUX SCRAM RESULTS I!! A SLIGHTLY CREATER PRE 3SURE RISE UITH THE SMALL CORE, THOUGH RELATIVELY It!3IG!!IFICAtlT.
3.
FOR THE TURBI!!E TRIP UITE HIGH PRESSURE SCRAM, THOUGH THE PRESSURE PEAK IS LOUER, BOTH !!IUTRoll FLUX ATID MAXIMUM HEAT FLUX ARE SLIGHXXX SLIG1!TLY HIGHER thall FOR THE REFEREtJCE 240 ffUT CASE, AdAIN EITH NO SIGt3IFICANT DIFFEREi!CE.
0 4.
UITH l'AIN STEAM SHUT 0FF A!!D 1:0 SCRAM, ALL VARIABLES RESPOUD LESS F0h THE HIGH POWER DENSITY CORE, AtlD HEf!CE ARE SAFE.
Ai!OTHER CASE UHICH WARREMTS ME!1 TION IN THE REACTOR RISER RUPTURE.
I!! THIS ACCIDEt:T THE MAJOR C0t1CERN, DUE TO IllCREASE CORE FLOW, IS THE POSSIBILITY OF THE FUEL BUNDLE LIFTING FROM THE CHAtitlEL.
ANY CORE, TFEREFORE', LESS THAN 56 BUtJDLES IN !!UtdBER WILL HAVE EACH BUNDLE LOCKED IN PLACE BY A SPECIAL HOLD DOUN DEVICE.
THIS APPLIES TO THE 60 KU/L CORE AS WELL', PRECLUDI!!G THE LIFTING OF THE FUEL IN -- -" _ ~ _.
THE - EVENT OF TFIS ACCIDENT.
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STABILITY TESTS PERFORMED TO DATE AT CONDITI0 tis OF CORE POWER At!D VOIDS MOST NEARLY SIMULATING THE EXPECTED 60 KV/L OPERATION I!!DICATE VERY GOOD DYNAMIC STABILITY OF THE REACTOR.
IN ADDITION, PREVIOUS STABILITY TESTS HAVE SHOWN THE REACTOR TO BE MORE STABLE THAN PREDICTED BY ANALYTICAL METHODS.
STABILITY OF THE 60 KV/dL CORE IS PREDICTED TO BE GOODON THE BASIS OF BOTH, PREVIOUS TEST' EXPERIENCE AND ANALYTICAL. METHODS.
OtlE LAST ITEM TO BE DISCUSSED IS THE MAXIMUM CREDIBLE ACCIDENT UHEN OPERATING THE 60 KW/L CORE.
INSECTION130FTHEFHSR, FIGURE 13%2 13.1 AREILLUSTRATED THE TRANSIE!ITS FOR THE LARGE CORE.
REGARDLESS 0F CORE SIZE, THE NATURE OF THE SYSTEM RUPTURE RESULTS IN A RAPID LOSS OF COOLANT TO THE CORE.
THIS REQUIRES FROM 16 TO 20 SECONDS.
TO UNCOVER THE FUEL.
THE FAST INCREASE IN THE ENCLOSURE PRESSURE AND TE!:PERATURE DURING THIS TRANSIENT RESULTS IN ACTUATION OF THE ENCLOSURE SPRAY COOLING, WHICH HALTS THE FURTHER RISE OF THESE TWO VARIABLES BEFORE LOSS OF COOL,.NT TO THE FUEL.
AS THE CORE FUEL LOOXXX LOSES THIS COOLING THE FUEL AND CLADDING TEMPERATURES RISE.
SINCE THE 60 KV/L CORE FUEL OPERATES VITH PEAK HEAT FLUXES EORE THAN 25 PERCENT HIGHER THAN THE 240 MWT CORE, THE STO' RED ENERGY IN THE PEAK FUEL BUNDLES IS HIGHER, AS IS THE AVERAGE FUEL TEMPER ATURE.
THE FIRS 1 HIGH POWER D'ENSITY FUEL RODS TO REACH CLAD PERFORATION TENPERATURE VOULD DO SO APPROXIMATELY 2 SECONDS l
S00tlER THAN SHOWN FOR THE LOWER POWER DENSITY CASE.
ALTHOUGH THE FRACTIO!J OF RODS REACHING THIS LIMIT MAY BE SOMEWHAT HIGHER AT 60 KU/L, IT Is REFERENCED TO A CORE OF ONLY PALF THE SIZE.
THE TOTAL
!TdMBER OF RODS REACHING THIS CLAD PERFORMATION TEMPERATURE, THEREFORE, f
IS ESTIMATED TO BE LESS THAN IN THE ORIGItJAL CASE.
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THIS EARLIER PERFORMATION OF THE CLAD OF THESE FIRST RODS IS-NOT GREATLY SIGNIFICANT SINCE THE SPRAY COOLING EFFECT PRECEDES THIS THRESHOLD AND NO GREATER IMPACT IS FELT ON ENCOXXX ENCLOSURE PRESSURE OR TEMPERATURE.
THE TRANSIENT RESPONSE I# FIGURE 13.1 CAN, THERECXXX THEREFORE, CE CONSIDERED CONSERVATIVELY TYPICAL OF'THE 60 KW/L CORE, AS WELL AS OF THE FULL SIZE 84 BUNDLE CORE.
EXAliINING THESE CASES, WHICH ARE THE MOST SIGNIFICANT OF ALL-CASES OF CONCERN, IT IS SHOWN THAT THE Ei:PECTED OPERATION OF THE HIGH POWER DENSITY CORE IS NO MORE HA2ARDOUS THAN THE 240 MUT CORE.
SIGNED R L HAUETER ASSISTANT ELECTRIC PRODUCTION SUPERINTENDENT - NUCLEAR D!D OR GA VO 04/21412 AUG' DV O
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ACflON NECESSARY CONCURRENCE O
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NO ACilON NECE55Any O COMMEN1 Q
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DE5CairfiON- (Mvs Se Uadesemed)
REFERRED TO DATE RECEIVED gy DATE c1 rc.tmitting info and enluation of g8 3,g 3
he cource optisisation tests ncently cceleted on the 144 I
w/all extras-Fm ACTION 0 NYTe hN*rIcs[ g config*tgon Er.ctosvaEs' Dr. DOen = C880 0-I (correction thereto included)
,ft,g, g, Dr. Dryans 8-5 w/ info cy.
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