ML20126E220
| ML20126E220 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/18/1969 |
| From: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Morris P, Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101150391 | |
| Download: ML20126E220 (8) | |
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DR P A MORRIS, DIRIOTOR g-EIVISION OF RIACTOR LICIN3ING gg US ATO::IO I!:IRGY C0!:!:I53 ION WA3"INGTON D C i
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i DA3ED ON DISCUSSIONS WITM YOUR STAFF, WE ARE SUPPLYING THE FOLLOUING 00RRIOTIONS AND ADDITI0t?AL INFORMATION TO OUR PROPO3ED
?>APGI t:0 17 TO TE TICHNICAL SPICIFICATIONS OT LICEN3E DPR-6 ZIK, DOCKIT NO 50-155, ISSUID TO CONSUf:ZR3 POWER COMPANY Off MAY 1,1964 TOR TVI SIG RO K POINT f;UCLEAR PLANT.
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!:0TI 7 IN TABLE Trot
- 3ECTION 5.1.5 SHOULD READ "UO2-PUO2 4
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TUEL ROD STAOK DEN 3ITY VILL VARY FROM 74-92 PERCINT THEORETI-f CAL SY U ING ANNULAR, DI3uED, OR NONDI3HID PELLETS IN SELECTED j
RODS."
T"E LOWER VALUE DERIVES FR0!' TWE PELLET WITH AN 0.2 ID T
"0LI I'18 FIRCINT PELLET VO UI:I/ WITM TUE AS OCI ATED WORST
/H DOCUMENT CONTAINS TOLERANCES, t M"-
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THE TWO PUO2-UO4 RODS PER BUNDLE WILL BE INSERTED INTO TFE E-G BUNDLES FOR NEXT CYCLE OPERATION. HOWEVER, WE WISH TO RESERVE TVE CAPABILITY OF MOVING SOME OR ALL OF THESE TO E FUEL BUNDLES IN THE FUTURE. BECAUSE OF THE RAPID RATE OF PLUTONIUM BURNUP, TFE PUO2-UO2 RODS WOULD BE COMPATIBLE WITH THE FUEL RODS IN THE I FUEL BUNDLES AFTER A CYCLEiOF OPERATIO!.1. CONSE0UENTLY, WE VISH TO NOTE AN ERROR IN OUR PREVIOUS SUBMITTAL ON' TABLE 5.1.5, A SUPIRSCRIPT 7 SHOULD BE PLACED IN TFE RELOAD E. COLUMN AFTER THE STACKED DENSITY VALUES OF "90-95," PELLET," AS WAS DONE IN TME RELOAD E-G COLUMN.
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J ADDITIONAL INFORMATION t
1.
PP 4 AND 5, SECTION II.E.1 AND II.E.2 - THERE APPEARS TO BE AN IN00NSISTENCY IN TFE CORRELATION OF FUEL TEMPERATURE AND LINIAR " EAT GENERATION R ATE, EG, P 4,17.8 KV/FT EGUALS 1500-1600 DEGREES C, BUT ON P 5,10.6 KW/FT EGUALS 1500 DEGRETS C.
T"E FRTR FUEL RODS, WHICH CONTAINED COLD PRESSED AND SINTERED UC2-FUO2 pef.LETS, OPERATED AT 17.8 KW/FT AND ONLY HAD A SLIGHT AMOU!..OrICUIAXEDGRAINGROWTH,WHICHWOULDMEkNTHATTHEPEAK CENTER TEMFERATURE VAS ABOUT 1500-1600 DEGREES C. HOWEVER, THE PRECICTED CENTIR TEMPERATURE FOR THIS FUEL WAS ABOUT 2000 DIGREIS C, AND THUS SHOULD HAVE MAD MUCH MORE GRAIN GROWTH. THERITORE, TFI FUEL APPARENTLY OPERATED AT A LOWER ' CENTER TEMPIRATURE THAN WAS EXPECTED. THE ACTUAL OPERATION WOULD POSSIBLY INDICATE HIGHER TIRMAL CONDUCTIVITY THAN EXPECTED FOR UO2. THUS, SAFETY-WISE, USE OF THE UC2 CONDUCTIVITY VALUES IS CONSERVATIVE.
TVE SA% TON UO2-PUO2 SINTERED PELLET FUEL RODS, DESCRIBED IN SECTION II.E.2, HAD A SLIGHT AMOUNT OF EQUI AXED GRAIN GROWTH U"!CH WAS CONSISTENT WITH AN EXPECTED CENTER TEMPERATURI 0F ABOUT 1500 DEGREES C FOR A FUEL R0D OPERATING AT 10.7 KW/FT.
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2.
HOW MANY PUO2-UO2' RODS WERE IRRAb1 ATED IN PRTR.
' THREE SINTERID FELLET U02-QUO 2 FUEL RODS WERE IRRADI ATED IN PRTR. TWO RODS ARE STILL UNpIR TEST AND ONI RCD WAS REMOVID FOR POST-IRRADIATION EXAMINATION.
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WHAT IS THE LOGIC OF THE CHOICE Of THE VOLUME OF THE CENTRAL 9,
VOIB IN THE ANNULAR PELLETS.
THE 0.1* HOLE SIZE A NULAR PELLET WILL l'ELT AT ABOUT 22 KW/TT AND TH$' PELLET WITH THE ABOUT 0.2" HOLE SIIE WILL MILT AT ABOUT 2S KiJ/TT. ALTHOUGH THE FUEL RODS WILL NOT REACH THESE POWER LIVILS IN BIG ROCK, IRRADI ATION Of THE PELLET CONFIGURATIONS WILL YIELD RESULTS OF TUEL WHICH MAY BE USETUL TOR THE DESIGN OF TUTURE HIGH SPE0ITIC POWIR REACTORS.
4.
HOW DOES THE ADDITION OF PU ATTICT THE CALCULATED DOSES AT THE SITE BOUNDARY.
THE BONE DOSE IS SHOUN IN THE' BIG ROCK POINT /THSR,/ SEC 13, P 29, TO BI ALWAYS LESS THAN 0.1 REM ON ALL CONDITIOf!A OT. EXPOSURE TIME, LOCATION AND DITTUSION REGIME.
THE PLUTONIUM IS A NON-VOLATILE SOLID. TOR RELEASE OT t:0N-l VOLATILIS, THE TUEL MUST VAPORIZE. !!ONE '0F THE EXPERIMENTAL
'LUT0NIUM ROD 3 IS CALCULATED TO VAPORIII AS A RESULT OF THE POSTULATED.C21 DELTA X ROD DROP ACCIDEf!T, NOR IS THERE CAL-CULATED TO BE ANY VAPORIZATION IN TC CASE OT A COMPLETE CORI
!:ELT DOWN. THUS, THERE IS NO DOSE INCREASE DUE TO THE EXPERI-MINTAL PU. HO'.'IVIR, A CONSERVATIVE APPROACH WOULD INDICATE A l
SITE BOUNDARY DOSE INCREASE IN THE SAME PROPORTION AS THE PU ItlVINTORY INCREASE. AS SHOWN IN THE ANSWER TO CUESTION 5, THE II:PERIt'. ENTAL PU WILL CONSTITUTE A MAXIMUM OT 4 PERCENT OF THE l-CORE PU INVENTORY. AS PU ACCOUNTS FOR ABOUT 25 PERCENT OF THE DOSI DUE TO N0!!-VOLATILE SOLIDS AT THE SITE BOUNDARY, THE TOTAL DOSE DUE TO NON-VOLATILE SOLIDS WOULD BE CONSERVATIVELY INCREASED A MAXIMUM OF 1 PERCENT. THE DOSE AT THE SITE BOUNDARY IS STILL THEN, CALCULATED TO BE LESS THAN '.1 REM.
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V"AT IS T!!I RILATION OF THE PU ADDED TO THE CORE WITH EXISTING IN-CORI PU ItiVENTORY.
3 THE PLUTONIUM CONTENT IS DL' AILED AT THE BEGINNING OF CYCLE
/BOC/ AND IND OF CYCLE /EOCi CONDITIONS, WHICH ARE THE EXTREMES.
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.l ISOTOPE EOC 6 B00 7 TUEL EXCEPT PUO2-UO2 RODS PUO2-UO2 RODS TOTAL 3
3 3
3 10 GM 10 GM 10 GM 10 GM 4
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3 PU-240 7.
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PU-241 2.
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.2 TOTAL 40.4 22.09
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AS CAN BE SIEN THE BOC 7 PLUTONIUM DUE TO THE EXPERIMENTAL RODS CONSTITUTES APPRO :IMATILY 4 PERCENT OF THE TOTAL CORE PLUT0NIUN. AT e
THE E00 6, A TYPICAL EOC CONCENTRATION, THE ADDED PLUT0NIUM WOULD CONSTITUTE ABOUT 2.3 PERCENT OF THE TOTAL CORE PLUTONIUM. THE PROPORTION WILL BE EVEN LESS AT IOC 7 BECAUSE THE EXPERIMENTAL PLUTONIUM WILL HAVE BEEN FISSIONED CONSIDERABLY, AS NOTED IN THE ANSUER TO QUESTION 3 ABOVE. THUS, IT IS SEEN THAT THE EXPERIMENTAL PLUTONIUM VILL CONSTITUTE A MAXI, MUM OT 4 PERCENT OF THE TOTAL PU INVENTORY AT BOC 7 AND REDUCE TO LESS TFAN 2.3 PERCENT AT THE EOC 7, WITM TURTHER REDUCTION EACH SUCCEIDING CYCLE.
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WHAT ALPHA DETICTORS WILL BE AVAILABLE AT BRP TOR PU DETECTION.
'VE PLAN TO MAVE ALPHA-CAMMA SCINTILLATION COUNTER, IBERLINI INSTRUMENT CORPORAT10N, PORTABLE MODEL PAC-ISAGA, ON HAND DURING ALL OPERATION 3. THIS INSTRUt:ENT VILL HAVE BEEN RECENTLY CALI-
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BRATED, AND WILL HAVE A RANGE FROM 200 TO 2 X 10 TO THE NEGATIVE 6 COUNTS PER MINUTE, AND AURAL AND VISUAL READOUT.
c ALSO AVAILABLE WILL 'BE A GAS TLOW PROPORTIONAL foUNTER.WHICH CAN f
DETECT ALPVA RADI ATION. AIR, WATER AND SMIARS ARE NOW ROUTINILY TAKIN TOR DETECTION OT ALPHA CONTAMINATION AROUND THE PLANT.
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WHAT SPECI AL TUEL HANDLING PRECAUTIONS WILL BE TAKIN WITH PU TUEL INTACT. WITH PU TUEL FAILED.
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SEALEDJ LEAK-CHICKED AND CLEANED TUEL RODS BEARING PUO2 WILL BE MANDLID IN A MANt!IR SIMILAR TO UO2 RODS. NORMAL PRACTICE AT GE IS TO CLEAN THE RODS TO A SMEARABLE ALPHA CollTAMINATION LE VEL OF LESS THdN 200 D/M, WHICH IS LESS JTAN THE AEC LIMIT OT 500 D/M. THE T0XIC NATURE OF PLUTONIUM, IT INGESTED, MAKES IT MAN-DATORY THAT PLUT0tJIUM-BEARING TUEL RODS BE HANDLED WITH CAUTION TO PREVINT ANY MECHANICAL DAMAGE WHICH MAY EXPOSE THE TUEL. TO
!:It IMIZE THE POSSIBILIT. OF DAMAGE, EXPERIENCED GE PERSONNEL WILL REMOVE THE FUEL RODS TROM THE SHIPPING CONTAINERS. THESE SAME PERSot:NEL VILL BE AVAILABLE FOR ALL hat:DLING AND LOADING OPER-ATIONS. SUITABLE ASSAULT MASKS /1/ AND ALPHA COUNTING INSTRUMENTA-TION WILL BE AVAILABLE AT ALL TTMES DURING THESE OPERATIONS.
THE RODS WILL BE SHIPPED IN ONE OR TWO RA-1A CONTAINERS. THE RODS WILL BE I"DIVIDUALLY SEALED Irl PLASTIC, TVIN GROUPS OF RODS VILL BI SIALED It! PIPES /2R CONTAINERS /, WHICH, It! TURN, ARE PLACED It!
THI SHIPPI!!G C0!! TAI!!IR. AT THE BIG ROCK POINT SITE, THE PIPE lit!ER VILL BE OPE!!ED A!!D CHECKED TOR CONTAMIt!ATION. RODS WILL BE RI!:0VID TRO:: THE PIPE lit!ER, Of!E AT A TIME, AND CARRIED TO THE NEW TUIL STORAGE ARIA L' HIRE 16 E-G BUt:DLES HAVE BEEN PLACED. THE PLASTIC SLEEVE WILL BE OPEt:ED, A CONTAMIt:ATION CHECK MADE, AND THE SLEIVE RE!:0VID TROM THE ROD. EACH ROD WILL BE SMEARED AS IT IS REM 0' ED V
TROM THE PLASTIC SLEEVI. SMIARABLE Cot!TAMINATI0t1 IN EXCESS OT 2C0 C/M VILL BE CAUSE TO REBAG THE ROD. THE RODS VILL THEN BE It1SPECTID VISUALLY Af!D LOADED INTO THE REMOVABLE ROD POSITI0 tis.
Iti THE EXTREMELY UNLIKELY EVENT THAT AN UNIRRADIATED PUO2-UC2 ROD IS IROPPID AND BROKTM OPEN, THE TOLLOVING PROCEDURE WOULD BE TOLLOWED-1.
T:'I REACTOR CONTAIt!!:IrlT BUILDING WOULD BE EVACUATED.
2.
RI-INTRY WITH ASSAULT MASKS VOULD BE MADE AND ALL PIECES LOCATED AND BAGGID..
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fEcoffTAMIt!ATION OF ANY SMEARABLE ALPHA CONTAMINATI0f! WOULD BE PERFORMED UNTIL THE COUNT WAS LESS THAN 500 D/M.
XD.
EXPERIENCE WITH SINTERED UO2-PUO2 FUEL PELLETS HAS SHOWN THAT ESSENTIALLY, NONE OF TFE PLUT0aIA BECOMES AIRBOR'NEj $0 GROSS
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C0!!TAMINATION INSIDE THE C0flTAINMENT WOULD NOT OCCUR.
ONCE THE RODS HAVE BEEN IRRADI ATED, FAILED PLUTONIUM RODS WILL i
BI TREATED IN A t'ANNER IDENTICAL WITH UO2 RODS. THE DIFFERENCE IN PLUTONIUM CONCENTRATION IN THE RODS IS NOT SIGNIFICANT IN THE j
PHYSIOLOGICAL SENSE AFTER A FEW THOUSAND VWD/T. A GREAT DIAL OF EXPIRIENCE WITH IRRADIATED PLUTONIUM FUEL R0D HANDLING IN THE MANNIR DESCRIBED HAS BEEN ACCUMULATED AT THE PRTR, HOWEVER, REACTOR WATER AND WASTE DISCHARGE WHICH ARE ROUTINILY ANALYZED FOR RADI0 ISOTOPES VILL BE FURTHER ANALYZED FOR ALPHA CONTAMINATION, f
AND FOR A CHANGE IN FISSION PRODUCT CONTENT.
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/1/ MIME SATITY APPLI At!CE /XXXXX /MS A/ "CLEARVUE" MASK UITH t
ULTRA FILTER CARTRIDGE.
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8.
VFAT'ARE PLUTONIUM TOLERANCES IN REACTOR WATER.
ALTFOUGH NOT NECESSARILY AN UPPER LIMIT FROM A SAFETY STANDPOINT, IT IS DESIRABLE To LIMIT THE BIOLOGICAL SIGNIFICANCE OF PLUTONIUM IN THE PRIMARY SYSTEM WATER TO BE LESS THAN TFAT FROM THE BETA AND CA:'MA IMITTIt:G FISSION PRODUCTS. ON THIS BASIS, THE PLUTONIUM Ill UC/ML/ SHOULD BE KEPT AT A FACTOR OF 100-1000 LESS THAN THE j
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l TYPICAL 0.1 TO 1 UC/ML TOTAL WATER ACTIVITY IN THE PRESENCE OF FUEL FAILURIS, f.ICENSE LIMITS FOR BRP ARE 35 UC/ML FOR HALOCEN ACTIVITY. TPUS, THE PLUT0NIUM COULD BE TOLERATED AT LEVELS OF ABOUT 10 TO THE f:ECATIVE 3 UC/ML, OR EVEN HIGHER.
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EXPERIENCE AT 3 OILING VATER REACTORS VITH SUBSTAt:TIAL FUEL FAILURES HAS SHOVN PLUTONIUM CONIEt7 IN THE VATER OF ONLY
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2 T.10 TO THE NEGATIVE 6 UC/ML.
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-f-EVIt! WITH PLUT0NIhl. Cot!CEt!TRATIONS IN THE fur AS MUCH AS A FACTOR 07*10 HIGNER THAt1 THAT PREVIOUSLY EXPERIENCED, THERE IS VERY LITTLE LIKELIHOOD OF APPROACHIt!G THE 10 TO THE NEGATIVE 3.
VALUE.
' ' THE COW CONCE!!TRATIONS OF PLUTONIUM RESULT FROM BOTH THE WATER CLEAT!UP SYSTEM WHICH GIVES PLUTot!IUM IN THE WATER A!( EFFECTIVE
. HALF-LIFE OF ONLY ABOUT FOUR HOURS AS WELL AS THE LOV SOLUBILITY OF THE PLUT0tlIUM. THE MAJORITY OF PLUTot!IUM IN THE WATER APPEARS TO COME FROM DECAY OF NEPTUNIUM IN THE WATER RATHER THAN DIRECTLY i
FROM THE FUEL.
IF YOU HAVE NEED FOR ADDITIONAL DISCUSSION, PLEASE DONT HISITATE TO CALL.
GERALD J WALKE.
SUPERVISORY ENGIllIER CONSUT.ERS POWER COMPANY 9
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Jackson, Michigan (c rc1d J. Walke)
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CC:
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To:
Dr. Peter A. Morris 1
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ACTION NECESSARY O
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NO ACTION KCESSARY O coa *arwr cLt.ssir.:
PCST OFFICE FtL.E CODE:
U aco. e 50-155 acrenaco to are neCrivro ev mre E'fWX"Wapply%g*eertections & add'1 info to the proposed Change No. 17 to the Tech Specs of Lie DPR-6.....
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" Ult'fRIE1JIION:
1-Reg File 1-occ 2-compliance
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