ML20002D166
| ML20002D166 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/23/1966 |
| From: | Haueter R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Morris P, James Shea US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101190611 | |
| Download: ML20002D166 (3) | |
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s CONSUMERS POWER COMPANY 10j h'(f] {}s Id-/Sg TVX NR 529 I-PARNALL ROAD OFFICE TWX $8T TST-1985 gACCPZ[
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JACKSON MICNISAN 9-15-66 4-55 PM N
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TO - DR. PETER A R0PRIS' DIRECTOR DIVISION OF REACTOR LICENSING UNITED STATES ATOMIC ENERGY COMMISSION O
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/j, ATTENTION - RR. JAMES SNEA AS A RESULT OF SUR 8EPTEMBER 9' 1966 MEETING WITH MEM9ERS t
OF TOUP STAFF REGARDING OUR REQUEST FOR CHANGES TO THE BIG ROCK POINI TECHNICAL $PECIFICATIONS' DATED JULY 29' 1966' AND FURTHER SUPPORTING INFORMATION TRANSMITTED BY TWX ON AUGUST 16' 1966 AND SEPTEMBER 8' 1966' THE FOLLOVING ADDITIONAL INFORMATION IS SUBMITTED.
1.
REACTOR KINETICS FOR GRAVITY ROD DROP AT NOT STANDBY 186 DER C FROM 10 To MINUS 6 TIMES RATED POWER -
t SELTA RCD PEAK ENTHALPT*
CAL /GM 1.5 111 l
E.C 505 1
2."
366 5.0 420 5.5 4T5 4.0 550 4.5 S8S ROD'WORTNS AT TME N!'8MER END SF TNIS RANGE ARE NOT CONSIDERED CREDIBLE.
2.
VESSEL DAMARE PARAMETERS CALCULATED USING 40 MILLISECOND TIME CONSTANT FOR 400 CAL /GM FUIL AND DECREASING FOR NIGHER INTMALPIES.
[!
MAXIEUR p
MARIMUM
- PEAK ENTNALPY' - : VESSEL VERTICAL CAL /SN
.- NOVEMENT' FT VESSEL STRAIN
- PERCENT e,.
.,.p 4
.i 9O.1T' ' '
4 490 549
$90 p S.58 1.1 TME POSSIBLE PRIMARY SYSTEM RUPTSRE LIMITS ARE S.S FEET WESSEL ROVEMENT AND 15 PERCENT VESSEL STR41N, Y. ~ YEIBMT FUEL AT OR ABOVI' INDICATED ENTMALPT FOR VARIOUS M, L..,.EAK RI{MALFI26 J4.EJSLLSNSmu -.
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l
A
.-.m rEAK ENThn2PY ABOVE 425 CAL /GM ABOVE 280 CAL /GM AB0VE 220 CAL /G,1 CAL /GM
/ PROMPT RUPTURE /
/ FULLY MOLTEN /
/ START MELTING /
450 3 LB 460 LB 1080 LB 490 30 460 1450 540 100 TSO 1810 590 210 1130 2480 RM ALL THE ABO 4
ALL THE ABOVE RESULTS ARE FOR HOT STANDBY.
ALTHOUGH THE COLD CONDITION ACCIDENT RESULTS IN A GREATER PEAK ENTHALPY' THE AVAILABILITY OF TKE LARGE COLD WATER HEAT SINK REDUCES THE SEVERITY TO LESS THAN THAT OF THE HOT STANDBY CASE.
5.
THE FLUX DEPRESSION IN THE C' ENTER OF A BWR FUEL ROD IS 5 TO 10 PERCENT ' MINIMUM / AVERAGE AS COMPARED 70 ABOUT A FACTOR OF 4 FOR TEEAT 15 PERCENT ENRICHED RODS' AS STATED BY ANL.
IN A BWR TRANSIENT OF 425 CAL /GM' THE TEMPERATURE PROFILE ACROSS THE UO2 IS ESSENTI ALLY UNIFORM UP TO THE TIME OF FAILURE.
THEREFORE* ALL THE UO2 IS AT THE SAME CONDITION - MOLTEN AND PARTIALLY VAPORIZED.
~
TECHNICAL JUDGMENT INDICATES THAT THE POWDER HAS AGGLOMERATED WHEN lTHE FUEL BECOMES FULLY MOLTEN AT ABOUT 280 CAL /GM.
6.
THE TWO THIN CLAD FUEL'SUNDLES HAVE A PROMPT RUPTURE THRESHOLD ABOUT 1 PERCENT LOWER THAN THE STANDARD BUNDLES.
THIS IS NEGLIBLE IN ITS EFFECTS.
7.
REGARDING THE TRE AT POVDER FUEL TESTS -
A - PRESSURE TRACES DO NOT INDICATE PREMATURE UO2 EXPULSION FROM GAS-FILLED POWDER FUEL' AND B - ANALYSIS SHOWN ABOVE IS BASED ON HEAT TRANSFER TIME CONSTANT CONSISTANT WITH CBSERVED PARTICLE SIZE AND CAPSULE PRESSURE RISE RATE FOR POWDER FUEL.
THE AB0VE CALCULATIONS ARE QUITE CONSERVATIVE SINCE No CREDIT HAS BEEN TAKEN FOR THE ENERGY ABSORPTION WITHIN THE THERMAL SHIELD AND CORE STRUCTURE OR FOR THI REACTOR VESSEL SUPPORTS.
If IS OUR OPINION THA! A DROP OF THE R0D OF HIGHEST POSSIBLE WORTH WOULD NOT BESULT IN RUPTURE OF THE PRIMARY SYSTEM' EVEN ASSUMING THAT THE f
PRESENT TREAT EXPERIMENT DATA ON POVDER FUEL IS COMPLETELT VALID j
FOR A POWER REACTOR.
11 R. L. MAUETER ASSISTANT ELECTRIC PRODUCTION SUPT - NUCLEAR END DH
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