ML20095G936
| ML20095G936 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/16/1984 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20095G918 | List: |
| References | |
| EPIP-4226, NUDOCS 8408280262 | |
| Download: ML20095G936 (26) | |
Text
{{#Wiki_filter:. . . 9 E.J. Mroczka 8-25-83 Form Approved by Station Superintendent Effective Date STATION PROCEDURE COVER SHEET { A. IDENTIFICATION Number EPIP 4226 Rev. 0 Title UNIT 3 COR2 DAMAGE ESTIMATE PROCEDURE Prepared By Mari J. Jaworsky B. REVIEW I have reviewed the above procedure and have found it to be satisfactory. TITLE SIGNATURE DATE DEPARTMENT HEAD nOIN%L _ q.a-#
\ f%Cdniatl Esinew E, ,/~- 7lTlk'y
- a y i- -
C. UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED: (Significant chan e in procedure method or scope ( asdescribedinFkAR) (If yes, document in PORC/50RC meeting minutes) YES [ ] N0 [O ENVIRONMENTAL IMPACT act) YES[] NO kJ (Adverse environmental imp /50RC ineeting minutes) (Ifyes,documentinPORC D. PROCEDURE REQUIRES 4 GAG /50RC REVIEW YES [X] NO [ ] E. POE/SORC APPF.0 VAL POR&/SORC Meeting Number ?# 2 4 - F. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below: P hv' ~ldOk urective uate stauoysermefuytsuperintendent SF-301 Rev. 6 L isRS!"8n"as8% E PDR
-3,
^ "
- EPIP 4226 Page 1 R v. 0
. (- LWIT 3 CORE DAMAGE ESTIMATE PROCEDURE PAGE NO. EFF. REV.
1-25 0
.(
j Responsible Individual Radiological Services Supervisor Title { L e e'
^
EPIP 4226 Page 2 Rtv. 0
- 1. '0BJECTIVE To provide a methodology to determine the extent of core damage under accident conditions. -
- 2. DISCUSSION 2.1 Accident Description 2.1.1 Clad Damage 2.1.1.1 An increasing potential for inadequate core cooling exists.
2.1.1.2 Loose part indication is observed. 2.1.1.3 No significant overheating has been observed at this point. 2.1.2 Fuel Overheating 2.1.2.1 The fuel is suspected to be at least partially uncovered for a period of time greater than a few minutes. 2.1.2.2 Loss of inventory in the pressurizer is ( 2.1.2.3 observed. Hot leg temperatures are increasing. 2.1.2.4 Voiding in the core is detected (use of picoameter across readout of in-core instrumentation in control room). 2.1.2.5 Ex-core countrate increasing (occurs when uncovered core is no longer shielded by water). 2.1.2.6 High in-core thermocouple readings are observed. 2.1.2.7 Fuel clad oxidation is detected by excess hydrogen in the containment (>\%). 2.1.3 Fuel Meltdown 2.1.3.1 The core has been uncovered for an appreciable period of time. 2.1.3.2 In-core thermocouples are off-scale. L U ,
.. s:
.. EPIP 4226 Page 3 Rev. 0
- m. .
2.1.3.3 In-core and ex-core instrumentation display erratic readings. 2.1.3.4 In-core-flux detectors cannot be moved properly (not normally expected to be - done). 2.2 ' Isotopic Analysis
- 2. 2.1 - Most of the noble gases will be seen in containment air samples unless the break has not occurred inside the containment, e.g. a Steam Generator Tube Rupture.
2.2.2 The appearance of noble gases and iodines in either containment gas or Reactor Coolant Sample without the presence of other fission products is a fair indication of clad damage and perhaps some degree of fuel overheat.
. 2.2.3 Iodine could be found in both the reactor coolant and containment air samples, depending on the accident scenario and on the physical and chemical form of the release. If both samples are available, then the
- total iodine released can be determined from both samples. However, iodine should not be used as the sole ~means of determining an estimate of core damage since it is difficult to determine the extent to which iodine will plate-out on containment walls and other surfaces and on piping walls. Also, spiking due to power excursions can lead to inaccurate ,
results in this analysis. 2.2.4 If core temperatures are below 2,300 *F or if-the core has not been at least partially uncovered for an appreciable amount of time, then no significant quantity of cesiums (i.e., >30% of the inventory) should be found. (It should be noted that core thermocouples may not show an accurate indication of actual core temperatures.) Therefore, the presence of an appreciable amount of cesium will be indicative , L W
. e - EPIP 4226 Pagm 4 Rzv. 0 of a fuel overheat situation. The amount of hydrogen in the sample (s) will serve as a confirmation. It
. should also be noted that just as in the case of iodines, the cesiums from both containment air and reactor coolant samples should be taken together. 2.2.5 Nearly complete release of noble gases, iodines, and cesium from extensively damaged fuel clad is expected even if fuel temperatures remain below the melting point. 2.2.6 As the fuel temperature increases (and fuel melting is suspected to have occurred), the likelihood of finding significant quantities above the baseli'ne of other core solids (Groups 4 to 8 in Table 6) increases. However, these fission products will not be found in reactor coolant samples unless the core has been covered and a recirculation mode has been established. Many of the fission products and most of the actinides which occur as refractory oxides are released only in { relatively small amounts even at elevated tempera-tures. However, if damaged fuel pellets are rewetted some of the more refractory radioactive material will be leached out. 2.2.7 Significant releases of tellurium, ruthenium and more refractory materials will occur only if the temperature approaches the fuel melting point (5,200 'F). However, the presence of ruthenium and tellurium does not " prove" melting, but their absence in long-term sampling analysis is a good indicator that melt has not occurred. 2.2.8 A fixed inventory of radioisotopes exists within the fuel pellet, assuming equilibrium conditions have been reached. The relative ratios of the isotopes which have reached equilibrium can be considered a constant value. The distribution of isotopes in the gap are not in the same proportion {
r EPIP 4226 Page 5 Rev. 0 ( as in the fuel pellet. This is due to the differing diffusion rates from-the pellet to the gap for each of the isotopes. In an accident situation, the ratios of the isotopic activities obtained from the PASS sample can be compared to the ratios in Table
- 8. If the ratios from the PASS sample are higher than the gap activity ratios, then this can be indicative of more severe failures, e.g. fuel overheat or even melt.
2.2.9 If conflicting data exist, then all indications involved should be reanalyzed.
- 3. INSTRUCTIONS 3.1 A "first-cut" estimate of the extent of core damage can be obtained by using the containment high range monitors as given in Drywell/ Containment Curie Level Estimation EPIP 4212. The percent inventory of noble gases released, divided by 100, can
.( be used as " FREI." in Part III.6, Table 3 for noble gases.
3.2 Samples will be obtained using EPIP 4224, Unit 3 Reactor Coolant Post-Accident Sampling, and EPIP 4225, Unit 3 Containment Air Post-Accident Sampling. 3.3 Samples will be analyzed using EPIP 4224 and EPIP 4225 for the gamma spectrum and hydrogen analysis. The results must be decay-corrected to the time of reactor shutdown. Half-lives of selected isotopes are given in Table 7. 3.4 The results from both reactor coolant and containment air samples should be used for this analysis whenever possible and if appropriate. 3.5 The sampling point to be utilized to draw a sample will be determined using Table 1. 3.6 The Plant Parameter Sheet (Table 2) should be completed to the extent possible using EPIP 4219 "MP3 NESS" available on TS0's in the Control Room, TSC, and E0F or directly from the Control Room. 3.7 A dilution and pressure and temperature correction will be ( performed using Part I of Table 3.
~'
3 EPIP 4226 Page 6 R:v. 0 3.8 A baseline subtraction should be performed unless baseline
-{ activity concentrations are negligible compared to accident activity concentrations.
3.9 A density correction will be performed on Reactor Coolant samples using Tables 3 and 4. 3.10 The total curies released, percent of core inventory released, and type of release will be determined using Table 3 in conjunction with Tables 5 and 6. 3.11 As an additional confirmatory piece of information, a ratio of each of the noble gases to Xe133 activity and each of the iodines to I131 will have to be determined. Once these ratios are obtained they will be compared against the fuel pellet activity ratios and the gap activity ratios in Table 8. A choice will have to be made in Table 3, Part III regarding which ratios the post-accident values are most similar to. 3.12 This information will be reported to the Manager of Radiological Dose Assessment (MRDA).
- 4. TABLES Table Title P_ ate 1 Post-Accident Sampling Points 7 2 MP-3 Plant Parameters 8 3 Calculation of Core Damage 9 4 Density Correction Factors. 16 5 Fission Product Inventory for MP-3 at Shutdown 17 6 Release Fractions for Various Types of Core Damage 21 7 Half-Lives of Selected Isotopes 23 8 Isotopic Activity Ratios 24 MJJ:jle
.L
0 D EPIP 4226 P;g2 7 D' - Rev. O. s Table 1 POST ACCIDENT SAMPLING POINTS Sampling Point Limitations .
- 1. Loop A Hot Leg Break should not be upstream of the sampling point.
.2. Loop C Hot Leg Break should not be upstream of the sampling point.
- 3. Containment Sump via System should be in operation and sump recirculation actuation signal should be Containment Spray System in effect prior to sampling.
(To be verified).
- 4. Containment Air Sampling may not need to be performed for an isotopic analysis if indications are
- that a release to the containment atmosphere has not occurred, e.g. steam generator tube rupture. (Please note there are two samping points available since the hydrogen recombiner intake lines are used and this system is redundant. They are located more than 90 feet apart.)
w-,m-
+
EPIP 4226 Paga 8 Rsv. 0 Table 2 MP-3 Plant Parameters Time of Sampling:
- 1. Time of reactor shutdown: . ...........
- 2. a. Refueling Water Storage Tank (RWST) Level . . % capacity (Initial)
% capacity (at time of sampling)
(Circle One)
- b. Accumulator Tank 1 Isolation Valve ..... Open/ Closed Tank 2 Isolation Valve ..... Open/ Closed Tank 3 Isolation Valve ..... Open/ Closed
( Tank 4 Isolation Valve . ... . Open/ Closed
- 3. Emergency Cooling Systems: . ........... Yes No WhichT Recire mode: Yes No
- 4. Containment Hi-Range Monitor Reading: ...... a) R/hr b) R/hr "First Cut" Damage Estimate (From EPIP 4212): % Inventory Released
- 5. Containment: . . . . . . . . . . . Pressure psig Temperature 'F
- 6. Reactor Coolant Temperature (average): . . ... . *F
- 7. Reactor Coolant Pressure . . . . . . . . . . . . . Psig
M. r p p ', .:' EPIP 4226 .Page 9 Rev. 0-Table 3 DATA SHEET FOR CORE DAMAGE ESTIMATE Part I , Icitope
- 1. a) C mRC
= measured activity concentration in Reactor Coolant in uCi/cc = uCi/cc b) C -= measured activity concentration in Containment Atmosphere in uCi/cc = uCi/cc
- 2. DECAY CORRECTION (If the half-life of an isotope is much longer than the time since shutdown, this step can be eliminated. Therefore, the value for C and C will be placed in C RC
# air, 88 8PPropriate).
mRC mair t = time since reactor shutdown to time of sampling = (1) hrs (Table 2, #1) A = (0.692/Tg ) = (0.692/ hrs) (Table 7) A = (2) hrs 1 a) =C dC exP[At] Reactor Coolant: C RC C RC
= pCi/cc x exp [(2) hrs 1 x (1) hrs]
C I'* b) Containment Air: C = C, exp[At] C.**#
= pCi/cc x exp [(2) hrs 1 x (1) hrs]
(#1b above) C. = pCi/cc air
g Q -
/'*% EPIP 4226 Rev. O Pcae. Y , ,
Table 3 DATA SHEET FOR CORE DAMAGE ESTIMATE (Cont'd) l
~P.;rt 1 l .
l
- 3. DL = Dilution correction = (Reactor Coolant Sample) .
! = 1 if accounted for previously. (Use DL=1 if uncertain).
- 4. DC = Density correction = (Table 4) (Reactor Coolant Sample)
Sample Temperature 'F Reactor Coolant Average Temperature = 'F (#6, Table 2)
- 5. Vol*RC = Volume of Reactor Coolant in cc =-(1) 3.31 x 10sec (yg a Steam Generator Tube Rupture has occurred, an estimate will have to be made regarding the amount of Reactor Coolant left inside the primary system; in other words, only a portion of the above amount will be used for this calcu-lation).-
*The total volume of Reactor Coolant used.will be determined by which emergency cooling systems are used, if-any, and what source of cooling water is used for these systems.
- a. Total RWST water used = ( % initial capacity - % at time of sampling) x 1,206,556 gal /100 (See #2a, Table 2) i
= gal x 3785 cc/ gal l
= (2) cc-
- b. The amount of water volume added from the accumulator tanks can be calculated by determining how many, if any, of the tanks have been used for emergency cooling. This can be done by referring to section 2b on Table 2. Also, Reactor Coolant pressure has to be below 600 psig (see Table 2, #7). Therefore:
7
- The amount of water volume added from the accumulator tanks in cc = 2.69 x 10 cc x Number of Valves Opened (Table 2, #2b)
= (3) cc
*If uncertain about how many valves have been opened, then assume all four have opened if the Reactor Coolant pressure is below 600 psig (see Table 2, #7). -
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EPIP.4226 ;Page'I D, . . . '
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- l 5 ,_ , y,,, e j-3, -
t Table 3 '-
- . t i
DATA SEET FOR CORE DAMAGE ESTIMTE (Cost'd) z, r
# 'r ' ;Part I ,. , %. ,
n, , , 3(- l' , N-
\ ) !] ,,
, / .. ,< - -
,, .s .
, , c.
Tots 1A'c1[.(1) . cc , + (2) ', , cc + (S) .' cc = \; s. dy , e-
+
- 6. Vol air ' . . =Volume of, Containment. Air~ = 6.5' x 10:ece, -
k 3 ( 5 .
- ,\
i , . 1 l . . s
- .7. K = pressure Etemperature. correction of a, gas sample = 1 if previously accounted for.
\T/. '
,j l .t i f 5
\ .
g \
,y (; .} - [g '3 ,
= P,T,/P,T ,otherwise. ,.' ,
t
- +
, 3 t
l7 P ,='costainment presssure (psig)~ 14.7 psia ,
\ ti 3 t, - .
A .1 -
\s - '
\
l- ' P3=* c psig (#5 of Table 2) + 14.7 psia = . ia. l . . , ,
>g, /
c< g ., s , .g . s. .- .
** 'T l P,9 sample pressure (psi,5) M h.7 poia 1
l
\ , , 4. -
T, = temperature of sample + 459'F T, = * *F + 459'F = 'R
*Use 70*F if actual temperature is not kaava.
i T ,= containment temperature *F + 459'T i l l l
_ .) b O _EPIP 4226 Page . Rev. 0
- .j l
Table 3 i l DATA SMEET FOR CORE DAMAGE ESTIMATE (Cont'd) 1 Part I Tc = *F (#5 of Table 2) + 459'T = *R i PT = P,T,/P,Tc =( psia x *R)/( psia x 'R) PT =
, 8. Cg , = Curies of Isotops in core in Curies (obtained free Table 5) = Ci I
i l 1 l 1
C' O EPIP 4226 Pcg2 O , .. R:v. O Table 3. , CALCULATION OF FRACTION OF INVENTORY RELEASED Pr.rt II
. . Isatcpe-
'~
! a. Reactor Coolant ' i ; i .
>\ >; y T tal Curies in' Reactor Coolant = A RC CRC.zDyxDCxVo1 RC -
1 'uCi/cc x x. J x' ./ cc x 1 Ci {
-AR 'C =' (#2a ,' Pa rt I)
(#3, Part I) '(#4, Part I) (TS, Part 1) 10*uci i , i
~Ci <
ARC = 3
- b. Containment Air , _
\' J' l' . f Total. Curies in Containment air = Aair = C,g, x PT x1Volair i A'.**# =( uci/cc) x x cc x 1 Ci (#2b, Part I) (#7, Part I) , (#6, Part I) 106 uci
.s A. = Ci
- air I c. Fraction Release .
Fraction of Core Inventory Released =,FREL * (b'RC.+:Aair)I INV 4 Ci + Ci)/ Ci FREI' = ( (#8, Part I) [
- y. -
REL - (FREL f r a n ble gas can be compared with #4 of Table 2, i.e., % Inventory Released from EPIP 4212.) 5
- EPIP 4226_ Paga 14 .
Rev. 0 - Table 3 CORE DAMAGE ESTIMATE . P Part III
- Isstepe
- 1. The release fraction, FREL, btain in Part II of this attachment,_will be compared against the values in Table 6.
, 2. The first step is to determine the " group" to which the isotope belongs. For example, 1135 belongs in group 2 (rated
- by relative volatility), Halogens. Cs134 belongs in group 3, Alkali Metals.
1 j 3. Once the group to which the isotope belongs has been found, the range of release fractions can be determined using the same table. For example, if FREL = 0.25 for I135, then the range is 0.20 to 0.50 under " fuel overheating" since 0.25 - falls within that range.
- 4. The higher number of the range will be used to determine the extent of core damage. For example
Isotope 1135 FREL = 0.25 Isotope Group 2 Type !!alogens Type of Damage Fuel overheating Release Fraction Range 0.20 to 0.50 F comp
= fraction used for comparison = 0.50 REL/Fcomp = 0.25/0.50 = .50 Fraction of fuel overheating = F = F l Comments: Up to 50% percent of the fuel has . experienced overheating.
- 5. It is important to remember this kind of determination must be both quantitative and qualitative since in a situation where core degradation can, or has, occurred, conflicting data can exist. Section 2.1 contains an operational description of the various states of core degradation. A qualitative description of what the isotopic analysis can indicate is given in Section 2.2. These should be referred before a final decision is made regarding the extent of
]'
core damage. i l 1
(-s. /**\ EPIP 4226 Peg 2 15 . '. Rzv. 0 . Table 3 CORE DAMAGE ESTIMATE (Cont'd) Part III
- 6. Please note that although the table in Table 6 gives discrete limits to each type of core damage, in reality no one state exists alone. In other words, if it is calculated that extensive clad damage (e.g., 90%) has occurred, then a portion of the fuel is probably experiencing overheating, and perhaps localized melting of fuel has also occurred.
~
F = Isotope = REL Isotope Group Type Type of Damage
- Release Fraction Range F = fraction used for comparison =
,,p 4
Fraction of =F=F REL! comp * ! From Table 8 the isotope ratios are comparable to: Cap Activity / Fuel Pellet Activity.
; (Circle One) 4 5
0 i 4 e
[ ' 0 1 e g P c-6 e e 2 t t '2 a a 40 D D
'P I v P;
ER
)
d
't n y o b y C b
( d e d E m e T r v 3 A o o M f r e r p b- l b I T S P e A p a E T E G A M A D E R O C s b t n e m I m I o I C t r a P e f llfl l
,* EPIP 4226 Page 18 Rev. O Table 5 FISSION PRODUCT INVENTORY FOR MP-3 AT SHUTDOWN .
Isotopes Curies Kr 83M 1.26+07* *1.26x10 Kr 85M 2.45+07 Kr 85 9.89+05 Kr 87 4.09+07 Kr 88 6.14+07 Kr 89 7.50+07 Kr 90 8.53+07 Kr 91 6.48+07 Xe 131M 6.00+05 Xe 133M 6.67+06 Xe 133 1.38+08 Xe 135M 3.31+07 Xe 135 2.53+07 Xe 137 1.67+08 Xe 138 1.60+08 Xe 139 1.33+08 Xe.140 8.87+07 ( Xe 141 Br 84 3.41+07 1.84+07 Br 85 2.29+07 Br 86 3.37+07 Br 87 4.09+07 Br 88 5.12+07 Br 89 5.12+07 Br 90 5.12+07 I 131 9.21+07 I 132 1.30+08 I 133 1.88+08 I 134 2.01+08 I 135 1.74+08 I 136 9.55+07 I 137 1.16+08 I 138 7.16+07 I 139 3.75+07 I 140 1.60+07 Se 84 1.81+07 Se 85 2.15+07 Se 86 2.59+07 Se 87 2.25+07 L
- - --- , _ , , - - , - - e- n. ., ~ , - .--,.ne-.m - - , . - -- -
~
EPIP 4226 Page 17 Rev. O Table 4 DENSITY CORRECTION FACTORS Reactor Coolant Average Temperature Sample Temperature 'F
'F- 60 70 80 90 100 100 . 994 .995 . 996 . 998 1.0
.987 150 . 981 .982 . 983 . 985 200 . 964 .965 . 966 . 968 .970 250 . 943 .944 . 945 . 947 .949 300 . 919 .920 . 921 . 923 .924 350 . 891 .892 . 894 . 895 .897
-400 . 860 .861 . 862 . 864 .865 450 . 825 .826 . 827 . 828 .830 500 . 785 .786 . 787 . 788 .790 l
( 550 560 737 727
.738
.727 739 728 740 729
.742
.731 570 . 716 .716 . 717 . 718 .720 580 . 704 .705 . 706 . 707 .708 590 . 691 .692 . 693 . 694 .696 600 . 679 .679 . 680 . 681 .683 t
610 . 665 .666 . 667 . 668 .669 . 620 . 651 .651 . 652 . 653 .654 630 . 635 .636 . 637 . 638 .639 640 . 618 .619 . 620 . 621 ~ .622 650 . 600 .600 . 601 . 602 .603 660 . 580 .580 . 581 . 582 .583 670 . 556 .557 . 558 . 559 .560
.532
,-{ 680 . 529 .529 . 530 . 531 690 . 494 .494 . 495 . 496 .497 700 . 437 .438 . 438 . 439 .440 n - ,, w ,m --.--w----,,~ - ~ v- , - - , . . - . s--e ,w-s ,-----n,-,., ,-ye,---,n ---,e --,wew e
o EPIP 4226 Page 19 R:v. O Table 5 FISSION PRODUCT INVENTORY FOR MP-3 AT SHUTDOWN (Cont'd)
-( Isotopes Curies i .
Rb 88 6.14+07 Rb 89 7.84+07 Rb 90 1.02+08 Rb 91 1.02+08 Sr'89 8.19+07 Sr 91 1.02+08
- Sr 92 1.12+08 Sr 93 1.30+08 Sr 94 1.33+08 Y 91M 6.20+07 Y 91 1.06+08
- Y 92 1.13+08 Y 93 1.33+08 Y 94 1.40+08 Y 95 1.50+08 Y 96 1.43+0S Y 99 3.75+07 Zr 95 1.54+08
( Zr 97 Zr 08 Zr 99 1.57+08 1.54+08 1.40+08 Zr.100 1.09+08 Nb 95M 3.17+06 Nb 95 1.54+08 Nb 97M 1.55+08 Nb 97 1.57+08 Nb 93M 1.57+08 Nb 99M 5.80+07 Nb 99 1.54+08 Nb 100M 8.87+07 Nb 100 8.87+07 Mo 99 1.74+08 Mo 101 1.57+08 Mo 102 1.47+08 , Mo 103M 3.21+07 Mo 103 1.26+08 Mo 104 1.02+08 Tc 99M 1.54+08 Tc 100 1.57+07 Tc 101 1.57+08 . Tc 102M 1.50+08 Tc 103. 1.50+08 ,.( Tc 104 1.19+08 l l Li
1 E. .. EPIP 4226 Page 20 R v. O Table 5
** FISSION PRODUCT INVENTORY FOR MP-3 AT SHUTDOWN (Cont'd)
Isotopes Curies Tc 105 7.85+07 Tc 107 3.37+07 Tc 108 2.39+07 Ru 103 1.50+08 Ru 105 8.19+07 Ru 106 5.46+07 Ru 107 5.12+07 Ru 108 4.09+07 Ru 109 2.49+07 Rh 103M 1.47+08 Rh 104 6.14+07 Rh 105M 1.74+07 Rh 105 8.19+07 Rh 106 5.80+07 Rh 107 5.46+07 Rh 108 4.43+07 Rh 109 2.69+07 Pd 109 2.87+07 Sn 130 3.11+07 Sn 131 2.77+07 Sn 132 2.39+07 Sb 127 9.59+06 Sb 128M 1.40+07 Sb 129 3.07+07 Sb 130 4.43+07 Sb 131 7.50+07 Sb 132M 4.78+07-Sb 132 7.85+07 Sb 133 8.53+07 Sb 134 4.43+07 Sb 135 1.40+07 Te 127 1.23+06 Te 129 2.93+07 Te 131M 1.47+07 Te 131 8.19+07 Te 132 1.30+08 Te 133M 1.09+08 Te 133 8.19+07 Te 134 1.67+08 Te 135 8.53+07 Te 136- 3.41+07 4 E
,m-., ,o . - .-, , .-.__, , . , - - _ , -- . , - -n v
C .. c.- - - EPIP 4226 Page 21 Rsv. 0 Table 5 FISSION PRODUCT INVENTORY FOR MP-3 AT SHUTDOWN (Cont'd) (' Isotopes Curies Cs 134 1.83+07 Cs 137 1.13+07 Cs 138 1.71+08 Cs 139 1.67+08 Cs 140 1.54+08 Cs.141 1.16+08 Cs 142 7.16+07 Cs 143 3.41+07 Ba 139 1.71+08 Ba 140 1.64+08 Ba 141 1.57+08 Ba 142 1.33+08 Ba 143' 1.09+08 Ba 144 6.48+07 La 140 1.71+08 La 141 1.57+08 La 142 1.43+08 La 143 1.36+08 La 144 1.19+08 l Ce 141 1.57+08 Ce 143 1.40+08 Ce 144 1.19+08 Ce 145 9.55+07 Ce 146 7.50+07 Ce 147 5.12+07 Ce 148 2.97+07 Pr 142 -1.19+07 Pr 143 1.36+08 Pr 144 1.19+08 Pr 145 9.55+07 Pr 146 7.85+07 Pr 147 5.80+07 Pr 148 4.78+07 Pr 149 3.11+07 Nd.147 6.14+07 Nd 149 3.41+07 Nd 151 1.71+07 Pm 147 2.22+07 Pm 149 5.12+07 Pm 151 1.84t07 l Sm 153 3.03+07 ( En 156 1.64+07 I
~
L .l
. EPIP 4226 Pege 24
.. - Rzv. O a
. -* TABLE 7 HALF-LIVES OF SELECTED ISOTOPES ISOTOPE T g (HOURS)
Xe 133 129.6 Kr 85 90228 Kr 85m 4.5 Kr 87 1.27 I 131 193.7 I 132 2.30 I 133 20.8 I 134 0.875 I 135 6.7
.Cs 134 17870 Cs 137 262800 Cs 138 0.535 Te 132 78 Sr 91 9.7 Sr 92 2.7 Ba 140 307.2 Ru 103 948
( Mo 99 Ce 144 67 6840 La 140 40.3
. Zr '5 1560 Zr 3/ 17 L
l .
;a e
EPIP 4226 ' Pr.ga . =.
'Rav. 0 .
Table 6 , RELEASE FRACTIONS FOR VARIOUS TYPES OF CORE DAMAGE Suggested Isotope (s)g) Sample Relative Gap- Fuel - for Analysis Type Volatility Release (3) Overheating Meltdown-Xe133*,Kr85m Containment Air 1 0.010 0.12 0.50 ' Kr87,Kr85* (Reactor Coolant to to to if not depressur- 0.12 0.50 0.970 ized) I131*,1132,I133 Reactor Coolant 2 0.001 0.20 0.50 1134,I135 Containment Air to to to 0.200 0.50 0.983 Cs134*,Cs137* Reactor Coolant 0.004 0.30 0.380 Cs138 Containment Air 3 to to to O.30 0.50 0.855 Te132 Reactor 4 3 x 10- - 0.04 0.05 Coolant to to to 0.04 0.05 0.25
-9 Sr91,Sr92 Reactor 5 3 x 10 0.0004 0.02 Ba140* Coolant to to to 0.0004 0.02 0.20 Rul03*,Mo99 Reactor 6 ---
<0.01 0.01 Coolant to 0.10 Cel44*,La140 Reactor 7 ---
<0.001 0.001 Coolant to 0.01 Zr95*,Zr97 Reactor 8 ---
<0.001 0.001 Coolant to 0.01
*Long half-lived isotopes.
- EPIP 4226 Page 23 Rrv. O e
Table 6
-{ RELEASE FRACTIONS FOR VARIOUS TYPES OF CORE DAMAGE Notes (1) a. The isotopes listed reflect a best choice in terms of measurement and effect from ingrowth of daughter products. However, it should be noted that any short term sample will be difficult to analyze due to the large amount of short-lived isotopes in the sample. There may be many isotopes with similar peaks which will be difficult to distinguish one from another. Some isotopes may have peaks near the annhilation radiation (511 kev).
Also, Compton edges could lead to difficulties in the sample analysis.
- It is, therefore, recommended that confirming peaks be used in the isotopic analysis. Any other quantifying techniques, such as iodine cartridge analysis, if available, are also suggested.
- b. Isotopes with asterisks are those with longer half-lives, and therefore, will serve as a better basis for analysis in long term sampling.
(2) Fission product grouping with respect to their relative volatility.
-( GROUP FISSION PRODUCT TYPE f 1 Noble Gases (Xe, Kr) l 2 Halogens (I, Br) i 3 Alkali Metals (Cs, Rb) 4 Tellurium (Te, Se, Sb) 5 Alkaline Earths (Sr, Ba) 6 Noble Metals (Ru, Rh, Pd, Mo, Tc) 7 Rare Earths and Actinides (Y, La, Ce) 8 Refractory Oxides of Zr and Nb The categories of isotopes are grouped in' order of decreasing volatility.
(3) Gap releases are due to clad damage prior to fuel overheat. l l
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r~ EPIP 4226 Page 25. Rev. O i TABLE 8 ( ISOTOPIC ACTIVITY RATIOS Fuel Pellet Calculated Gap Activity Isotope Activity Ratio Ratio Ratio KR85M 0.11 0.022 KR87 G.22 0.022 KR88 0.29 0.045 Xe131M 0.004 0.004 Xe133 1.0 1.0 Xe133M 0.14 0.096 Xe135 0.19 0.051 1131 1.0 1.0 1132 1.5 0.17 1133 2.1 0.71 1135 1.9 0.39 Noble Gas Ratio = Noble Gas Isotope Inventory Xe-133 Inventory Iodine Ratio = I dine Isotope Inventory 1-131 Inventory l-Please Note: . The measured ratios of various nuclides found in reactor coolant during normal operation is a function of the amount of " tramp" uranium on fuel rod cladding, the number and size of " defects" (i.e. " pin holes"), and the location of the fuel rods containing the defects in the core. The ratios above are based on calculated values of relative'coacentrations in the feel or in the gap. The use of the above ratios for post accident damage. assessment is restricted to an attempt to differentiate between fuel overtemperature conditions and fuel cladding failure conditions. Thus the ratios derived here are not related to fuel defect levels-incurred during normal operation. L
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