ML20215F300
| ML20215F300 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/31/1985 |
| From: | HOUSTON LIGHTING & POWER CO. |
| To: | |
| Shared Package | |
| ML20215F286 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 0PEP02-ZG-0007, PEP2-ZG-7, NUDOCS 8610160149 | |
| Download: ML20215F300 (41) | |
Text
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i b 1 HOUSTON LIGHTING AND POWER COMPANY SOUTH TEXAS PROJECT ELF (IRIC GENERATING STATION L .NT PROCEDURES MANUAL
" C. A. D. ...I. N. E..A,, D...M...A.TI A A.
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DIVISION PROCEDURE NON-SAFETY RELATED Coolant Activity and Radionuclide Trend for OPEPO2-ZG-OOO7 Failed Fuel Rev. O Page 1 of 41 APPROVED: / N h M- N TEC})dIkAL SUPPORT MANAGER DAT'E APPROVED DATE EFFECTIVE This procedure is not described in the FSAR.
1.0 Purpose and Scope
The purpose of this procedure is to provide instructions and guidelines for the following:
1.1 Trending of RTS radionuclide activities during normal at-power conditionsfcfthepredictionoffailedfueloccurrences.
1.2 Estimating th amount'of failed fuel during normal operating conditions.
1.3 Estimating the amount of failed fuel during post-accident conditions.
2.0 Prerecuisites 2.1 Plant power history for at least the previous 30 days is available.
3.0 Precautions 3.1 The numberts obtained by using this procedure are rough estimates, at best. Retsults of this procedure cannot be used to describe or infer the exact type and amount of fuel damage.
3.2 All equations quoted in this procedure are based on equilibrium full power iodine. Iodine spiking phenomena following transient operations may provide false fuel damage estimates.
8610160149 861009 PDR ADOCK 00000498 .
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I Coolant Activity and Rad 2nuclide Trend for OPEP02-ZG-0007 Failed 1331 Rev. O Page 2 of 41 4.0 RCS Radiornelide/ Failed Fuel Trend 4.1 Perform the following, ensuring that the sample required in Step ,
4.1.1 is taken at approximately the same time that the data required in Step 4.1.2 is recorded.
4.1.1 Request from chemical Analysis the specific activities (p Ci/gn), measured from the Reactor Coolant System (RCS), of the isotopes listed on Data Sheet 1.
4.1.2 Complete Section 2.0 of Data Sheet 1.
4.2 Record the specific activities determined in Step 4.1.1 onto Data Sheet 1.
4.3 Using Addeadum 1 and available plant power history data, determine the Power Correction Factor, X, for each isotope listed on Data Sheet 1. Record these values onto Data Sheet 1, Section 1.0.
4.4 If the activity values obtained in Step 4.1.1 have been decay corrected to the time of sampling, record the value "1.0" in all entries in the " Decay Correction Factor, Y" column on Data Sheet 1.
Otherwise, calculate and record on Data Sheet 1 the Decay Correction Factor, Y, for each isotope on Data Sheet 1 using the information in Addendum 2 and the data recorded per Step 4.1.2.
4.5 Using the equation presented in Data Sheet 1 Section 1.0, calculate .
f the Adjusted Specific Activity for each isotope listed on Data Sheet 1. Record these values on Data Sheet 1.
4.6 Using the equation presented in Data Sheet 1 Section 1.0, calculate the I-131/I-133 Ratio. Record this value on Data Sheet 1.
NOTE For the purposes of this procedure, " Base-line Specific Activity" is defined as the value determined by Reactor Performance Section to be the current normal operating specific activity present in the RCS for a given isotope.
4.7 Obtain from Reactor Performance Section and record on Data Sheet 1 the latest base-line specific activity data for each isotope listed on Data Sheet 1.
i *
. l Coolant Activity and Radionuclide Trend for OPEPO2-ZG-DOO7 Failed Fuel Rev. O Pcge 3 of 41 l
NOTE .
If reactor power has varied greater than +.5%
from the time-average power value within the past 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />, iodine spiking phenomena may occur which will provide false fuel failure indication for iodine isotopes.
4.8 If any Adjusted Specific Activity exceeds its base-line value, fuel failure may have occurred. Notify the Reactor Performance Supervisor and the Chemical Analysis Supervisor and proceed to Step 5.0. If no Adjusted Specific Activity exceeds its base-line value, proceed to Step 7.0.
5.0 Normal Operations Failed Fuel Estimates NOTE The failed fuel estimate equations used in this determination are based on operational experience data from M PWR plants. The results obtained from this section are at best rough estimates only, but should provide information concerning the general trends of fuel failure.
5.1 Using the Adjusted Specific Activity for I-131 recorded on Data Sheet 1, complete Data Sheet 2.
5.2 Inform the Reactor Performance Supervisor of the failed fuel estimates determined in Step 5.2.
5.3 Proceed to Step 7.0.
6.0 Estimation of Failed Fuel Durine Post-Accident Cor.dition; 6.1 If Qualified Display Processing System (QDPS) indications have shown core uncovery (Reactor Vessel Level < 0) or if core uncovery is suspected to have occurred, then proceed to Step 6.2. Otherwise, proceed to Step 6.11.
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Cpolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 4 of 41 6.2 Perform the following, ensuring that the samples required in Step 6.2.1 are taken at approximately the same time that the data required in Step 6.2.2 is recorded. ,
6.2.1 Request from Chemical Analysis the specific activities (p Ci/gn), measured from the RCS, Containment Sump and Containment Atmosphere; of the isotopes listed on Data Sheet 3, Section 1.0. Record these values on Data Sheet 3.
6.2.2 Complete Section 2.0 of Data Sheet 3. Addendum 7 provides appropriate data retrieval locations.
6.3 Using Addendum 1 and available plant power history data, determine the Power Correction Factor, X, for each of the isotopes listed on Data Sheet 3. Record these values on Data Sheet 3, Section 1.0.
6.4 If the activity values obtained from Chemical Analysis have been decay corrected to the time of sampling, record the value "1.0" in all entries in the " Decay Correction Factor, Y" column on Data Sheet 3. Otherwise, calculate and record on Data Sheet 3 the Decay Correction Factor, Y, for each isotope on Data Sheet 3 using the information in Addendum 2 and the data recorded per Step 6.2.2.
6.5 Using Addendum 3 and the data recorded in Step 6.2.2, determine the Pressure-Temperature Correction Factor, Z, for the Containment Atmosphere isotopes listed on Data Sheet 3. Record these values on Data Sheet 3, Section 1,.0.
6.6 Using the appropriate equations presented in Data Sheet 3, Section 1.0, calculate the Adjusted Specific Activity for each isotope listed on Data Sheet 3. Record these values on Data Chect 3.
6.7 Using the information on Addendum 4 and the appropriate data recorded on Data Sheet 3, complete Data Sheet 4.
6.8 Using the data recorded on Data Sheet 4 and the guidelines in Addendum 5, complete Data Sheet 5 which will provide percent fuel melt and percent fuel overtemperature estimates.
6.9 Using the data recorded on Data Sheet 4 and the guidelines in Addendum 6 complete Data Sheet 6 which will provide percent fuel overtemperature and percent clad damage estimates.
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. i ggglant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 5 of 41 6.10 Proceed to Step 7.0.
NOTE The following steps in Section 6.0 should be performed only if QDPS indications have shown no core uncovery (Reactor Vessel Level > 0) or in the judgement of the Test Coordinator and the Shift Supervisor, no fuel melt has occurred.
6.11 Perform Steps 6.2 through 6.7 and Step 6.9.
l 7.0 Acceptance Criteria None ,
8.0 Documentation NOTE If this procedure'was performed under normal operating conditions, only the documentation in Steps 8.1 and 8.2 is required. Otherwise, only the documentation in Steps 8.3 through 8.6 is required.
i 8.1 OPEP02-ZA-0007-1 Normal Operations Radionuclide Trend Data Sheet.
8.2 OPEP02-ZG-0007-2 Normal Operations Failed Fuel Estimate Based on I-131 Activity.
8.3 OPEP02-ZG-0007-3 Post-Accident Specific Activity Determination.
8.4 OPEP02-ZG-0007-4 Post-Accident Gross Activity Determination.
g, 8.5 OPEP02-ZG-0007-5 Percent Fuel Overtemperature and Percent Fuel Melt Estimate.
8.6 OPEP02-ZG-0007-6 Percent Clad Damage and Percent Fuel Overtemperature Estimates.
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, s-l Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 6 of 41 9.0 References 9.1 Westinghouse Owners Group "Postaccident Core Damage Assessment .
Methodology", Rev. 2 November 1984.
9.2 Bechtel Calculation No. 2N109MC5410," NPSH For Containment Spray Pumps During Recirculation", 2/23/83.
9.3 Bechtel Calculation No. 2N129MC5037," RWST Verification & Level Setpoints", 9/4/82.
9.4 STPEGS FSAR Section 6.2.2.2.3, Amendment 38.
9.5 STPEGS FSAR Table 6.3-1, Amendment 51.
9.6 STPEGS FSAR Section 6.3.2.2, Amendment 49.
9.7 STPEGS P&ID 5N129F05013, Rev. 5, " Safety Injection System".
9.8 STPEGS P&ID 5N129F05014 Rev. 5, " Safety Injection System".
9.9 STPEGS P&ID 5N129F05015, Rev. 5, " Safety Injection System".
9.10 STPEGS P&ID 5N129F05016, Rev. 4, " Safety Injection System".
9.11 STPEGS PGID SR149F05001, Rev. 5, "RCS Primary Coolant Loop".
9.12 STPEGS P&ID 5R149F05003, Rev.'3, "RCS Pressurizer".
9.13 STPEGS P&ID 5Z329200045, Rev. 3, " Primary Sampling System".
10.0 Attachments 10.1 Addendum 1 - Determination of Power Correction Factor, X.
i 10.2 Addendum 2 - Determination of Decay Correction Factor, Y.
10.3 Addendum 3 - Determination of Pressure - Temperature Correction Factor, Z.
10.4 Addendum 4 - Determination of Sump Water Volume.
10.5 Addendum 5 - Estimation of Percent Fuel Overtemperature and Percent Fuel Melt.
10.6 Addendum 6 - Estimation of Percent Clad Damage and Percent Fuel Overtemperature.
10.7 Addendum 7 - Post-Accident Data Retrieval Locations.
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 7 of 41 10.8 Figure 1 - Power Correction Factor for I-131 Based on Average Power During Operation.
10.9 Figure 2 - Relationship of Percent Clad Damage With Percent Core Inventory Released of I-131.
10.10 Figure 3 - Relationship of Percent Clad Damage With Percent Core Inventory Released of I-131 With Spiking.
10.11 Figure 4 - Relationship of Percent Clad Damage With Percent Core Inventory Released of I-132.
10.12 Figure 5 - Relationship of Percent Clad Damage With Percent Core Inventory Released of I-133.
10.13 Figure 6-RelationshipofPercentCladDamagehithPercentCore j Inventory Released of I-135.
10.14 Figure 7 - Relationship of Percent Clad Damage With Percent Core Inventory Released of Kr-87.
10.15 Figure 8 - Relationship of Percent Clad Damage Witt Percent Core Inventory Released of Xe-131m.
10.16 Figure 9 - Relationship of Percent Clad Damage With Percent Core Inventory Released of Xe-133.
10.17 Figure 10 - Relationship of Pe'rcent Fuel Overtemperature With Percent Core Inventory Released of Xe, Kr, I, or Cs.
10.18 Figure 11 - Relationship of Percent Fuel Overtemperature With Percent Lore Inventory xeleased of Ba-140.
10.19 Data Sheet 1 - Normal Operations Radionuclide Trend Data Sheet.
10.20 Data Sheet 2 - Normal Operations Failed Fuel Estimate Based on I-131 Activity. ,
i 10.21 Data Sheet 3 - Post-Accident Specific Activity Determination. ;
i 10.22 Data Sheet 4 - Post-Accident Gross Activity Determination.
I 10.23 Data Sheet 5 - Percent Fuel Overtemperature and Percent Fuel Melt l Estimate.
10.24 Data Sheet 6 - Percent Clad Damage and Percent Fuel Overtemperature Estimates.
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Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 8 of 41 ADDENDUM 1 I
DETERMINATION OF POWER CORRECTION FACTOR. X (Page 1 of 3) .
The Power Correction Factor, X, may be determined by one of the following methods, whichever is more appropriate. Isotopic decay constants may be found at the end of this addendum.
Method 1 Case I: For isotopes Rb-88, I-132, I-133, I-135 If reactor power has not varied by more than i 10% from the time-average value for at least 4 days prior to sampling, use the following equation:
X = % Steady-State (time-averace) power for prior 4 days 100 Case II: For isotopes I-131, Xe-131m, Xe-133, Ba-140 If reactor power has not varied by more than i 10% from the time-average value for at least 30 days prior to sampling, use the following equation:
X = % Steady-State (time-average) power for prior 30 days 100 F
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Coolant Activity arisLRadionuclide Trend for OPEPO2-ZG-OOO7 Failed Fuel Rev. O Page 9 of 41 ADDENDUM 1 DETERMINATION OF POWEE CORRECTION FACTOR. X (Page 2 of 3) .
Method 2 For all isotopes except Cs-134, Cs-137 For cases with transient power history in which the power has varied greater than + 10% of the time-average value prior to shutdown, use the following formula X=
-1 t 1o P (1 - e g )) e g) t 100 where, .
P = Percent power during operating period t .
t = Operating period (in days) at power P where power does not vary greater than + 10% from the timedaverage value (P ).
t = Time between end or period j and time of sampling (or shutdown, J as appropriate) in days.
= Decay constant of isotope i, in inverse days. See chart below for values of 1.
l Isotope l l l DecayConstant,1,{)l (Inverse days, d l l 1 I l I-131 I O.0862 l l I-132 1 7.2652 l l I-133 l O.7998 l l I-135 l 2.5263 l l Xe-131m l 0.0581 l l Xe-133 1 0.1320 _l
-4 lCs-134 l . 2e,7 x 1o l l 1 l l Cs-137 l 6.2944 x 10" l l l l l Ba-140 l 0.0542 l l Rb-88 l 0.0123 l
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 10 of 41 ADDENDUM 1 DETERMINATION OF POWER CORRECTION FACTOR. X (Page 3 of 3) .
Method 3 For Cs-134 only:
Determine X for Cs-134 using the information on Figure 1.
For Cs-137 only:
X = Total Current Cumulative Core Burnuo (EFPD)
Total Design Expected Cumulative Core Burnup (EFPD)
For Present Cycle Example: ,
The core has three regions of fuel with burnups as follows:
Region 1 (Thrice burned) - 400 EFPD current cumulative Region 2 (Twice burned) - 250 EFPD current enaulative Region 3 (Once burned) - 100 EFPD current cumulative The design expected burnup for each region is as follows:
Region 1 - 450 EFPD Region 2 - 300 EFPD Region 3 - 150 EFPD Therefore 400 + 250 + 100
= 0.83 450 + 300 + 150
. e goolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 11 of 41 ADDENDUM 2 DETERMINATION OF DECAY CORRECTION FACTOR. Y (Page 1 of 1) .
The Decay Correction Factor, Y, for each isotope may be determined using the following equation.
Y=e t 1.t >
where, A = Decay constant for isotope i. Refer to the table below for valuesofk.
a t = Time in seconds between Time of Sampling and Time of Sample Analysis (recorded on Data Sheet 1) l ll Isotope ll (inverse Decay Constant,1 seconds, s , ) l l l l
~
l I-131 l 9.98 x 10 l l 1 l l I-132 l 8.408 x 10~
l 1 l l I-133 l 9.26 x 10" l I I
~
l I-135 l 2.92 x 10 l l l l Xe-131m l 6.725 x 10~ l l 1 I Xe-133 l 1.528 x 10~ l l l l l Cs-134 l
- l l Cs-137 l
- l Ba-140 l 6.273 x 10" l l l l Rb-88 l 1.424 x 10~ l l l l
- Assume Y = 1 for these isotopes
Coolant Activity and Radionuclide Trend for OPEPO2-ZG-OOO7 Failed Fuel Rev. O Page 12 of 41 ADDENDUM 3 DETERMINATION OF PRESSURE - TEMPERATURE CORRECTION FACTOR. Z .
(Page 1 of 1)
The Pressure-Temperature-Correction Factor, Z, may be determined using the following equation.
Z= P2 (T + 460)
P (T2 + 460) where, = P = Containment Atmosphere Sample Pressure, psig T = Containment Atmosphere Sample Temperature, F, P = Containment Atmosphere Pressure, psig T = Containment Atmosphere Temperature, F 2
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1 1
Coolant Activity and Radionuclide Trend for OPEPO2-ZG-0007 Failed Fuel Rev. O Page 13 of 41 ADDENDUM 4 DETERMINATION OF SUMP WATER VOLUME (Page 1 of 1) .
1.0 Estimation of Containment Sump Water Mass The mass of water in the containment sump may be approximated by totaling the water mass released by the Accumulators and the RWST. Use the equations below to determine these values.
% Water level prior -
% water level
[M CC]i to accident at time of sampl .(4.1165 x 10 ) gm 7
- 1 ,
100 where, M = mass (in grams) of water CC J i released by Accumulator i.
% water level prior to accident g
. . are values for Accumulator
% water level at i recorded on Data Sheet 3
, time of sample
. ., e -
M = ae ee prior % water level RWST 9 j to accident , ,at time of sample i .(1.2482 x 10 ) gm 100 where, M "*' ' ** * **** Y RWST "
" If"
% water levt:1 prior
, to accident are values for RWST
% water level at 1 recorded on Data Sheet 3 time of sample
. .y l
l l
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Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 14 of 41 ADDENDUM 5 ESTIMATION OF PERCENT FUEL OVERTEMPERATURE AND PERCENT FUEL MELT ,
(Page 1 of'4)
An estimation of Percent Fuel Overtemperature and Percent Fuel Melt may be made by comparing the relative activity ratios of Cs-137 and Ba-140.
Using the guidelines below will develop a plot of Percent Fuel Overtemperature vs. Percent Fuel Melt for the two isotopes. The intersection of the plots for each isotope will provide a best estimate percentage of each type of damage with the area underneath the curves representing all other possible combinations of damage (based on available data).
1.0 Calculation of Bounding Values .
Cesium 137 D = a ss Ac W hy 137 (Ci) -
1.2 x 10 (Ci) where, D = % of total core inventory of Cs-137 released (T'otal Gross Activity] = value for Cs-137 recorded on Data Sheet 4
Coolant Activity and Radionuclide Trend for OPEPO2-ZG-0007 Failed Fuel Rev. O
, Page 15 of 41 ADDENDUM 5 ESTIMATION OF PERCENT FUEL vyrati rni krATURE AND PERCENT FUEL MELT (Page 2 of 4) 137 " 137 x 100 %
52.0 137 137 x 100 %
89.0 where, FOT * " "" *** ** "" ** ** # " "#*
137 "
conditions assuming all Cs-137 release was due to fuel overtemperature FM y37 = % Fuel which would have experienced fuel melt assuming all Cs-137 release was due to fuel melt Barium 140 D " '*
140 "
, (91) ,
2.0 x 10 where, D = % Of total Core inventory of Ba-140 released
[ Total Gross' Activity] = value for Ba-140 recorded on Data Sheet 4 140 " 140 x 100 %
0.15
. =
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 16 of 41 ADDENDUM 5 ESTIMATION OF PERCENT FUEL OVERTEMPERATURE AND PERCENT FUEL MELT .
(Page 3 of 4) 140 " 140 x 100 %
24.0 where, FOT = % Fuel which would have experienced fuel overtemperature assuming all Ba-140 release was due to Fuel overtemperature FM = % Fuel which would have experienced fuel melt assuming all Ba-140 release was due to fuel melt 2.0 Plotting of Data 2.1 Cesium Data
- a. Plot, on Data Sheet 5. the FOT value determined in Section 1.0 above along the "% Ne1 Overtemperature" axis.
- b. Plot, on Data Sheet 5, the FM * "" ***" " * "
- above along the "% Fuel Melt"137 axis.
- c. Draw a s'traight line between both points plotted above and label the line "Cs-137".
2.2 Barium Data
- a. Plot, on Data Sheet 5, the FOT value determined in Section 1.0 above along the "% bel Overtemperature" axis.
- b. Plot, on Data Sheet 5, the FM value determined in Section 1.0 above along the "% Fuel Melt" bis.
- c. Draw a straight line between both points plotted above and label the line "Ba-140".
! 3.0 Data Interpretation 3.1 Draw a straight horizontal line from the intersection of the "Ba-140" and "Cs-137" curves on Data Sheet 5 to the "% Fuel Overtemperature" axis. The intersection of this line and the axis yields the best estimate % fuel overtemperature value.
Coolant Activity and Radionuclide Trend for OPEPO2-ZG-0007 Failed Fuel Rev. O Page 17 of 41 ADDENDUM S l
ESTIMATION OF PERCENT FUEL OVERTEMPERATURE AND PERCENT FUEL MELT ,
(Page 4 of 4) 3.3 The area underneath the "Ba-140" and "Cs-137" curves represents all the possible combinations of fuel melt and overtemperature based on available data.
3.2 Draw a straight vertical line from the intersection of the "Ba-140" and "Cs-137" curves on Data Sheet 5 to the "% Fuel Melt" axis. The intersection of this line and the axis yields the best estimate %
fuel melt value.
1
. =
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 l Failed Fuel Rev. O '
Page 18 of 41 ADDENDUM 6 ESTIMATION OF PERCENT CT.An DAMAGE AND PERCENT FUEL OVERTEMPERATURE ,
(Page 1 of 2)
The following methodology is used to estimate Percent Clad Damage and Percent Fuel Overtemperature.
1.0 Core Inventory Releases CIR = x 100 %
(Core Inventory]
where, CIR = % Core Inventory Released for isotope J.
[ Total Gross Activity, Ci] = value recorded on Data Sheet 4.
(Core Inventory] = Total available inventory (Ci) of isotope i.
Refer to. table below.
l Isotope l [ Core Inventory, Ci] l l 1 l l I-131 l 1.1(8) l l I-132 l 1.7(8) l l I-133 l 2.3(B) l l I-135 l 2.1(8) l l Kv-87 l 4.7(7) l l Xe-131m l 7.4(5) l l Xe-133 l 2.3(8) l l Rb-88 1 6.7(7) l l Cs-134 1 2.7(7) l l Cs-137 l 1.2(7) l l Ba-140 l 2.O(8) l h
I Coolant Activity and Radionuclide Trend for OPEP02-Z3-0007 Failed Fuel Rev. O Page 19 of 41 ADDENDUM 6 ESTIMATION OF PERCENT CLAD DAMAGE AND PERCENT FUEL OVERTEMPERATURE .
(Page 2 of 2) 2.0 Comparison of the CIR values calculated in the previous section to the information presented in Figures 2 through 12 will result in % fuel failure estimates based on the activity of each isotope. The chart below related the appropriate Figures to be used for each isotope.
l Isotope l % Clad Damage l % Fuel Overtemperature l l l Estimate l Estimate l l l Firure No. I Firure No. l l I-131 l 2* l 10 l l I-132 l 4 l 10 l l I-133 1 5 l 10 l l I-135 l 6 l 10 l l Kr-87 l 7 l 10 ___l l Xe-131m l 8 l 10 l l Cs-134 l l 10 l l Cs-137 l 10 l l Bu-140 l- 11 l
- If iodine spiking phenomena are suspected to have occurred, use Figure 3.
Coolant Activity and'Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 20 of 41 ADDENDUM 7 POST-ACCIDENT DATA RETRIEVAL LOCATIONS (Page 1 of 1) ,
i Parameter l Location (s)/ Description Containment Atmosphere: l Pressure l QDPS, CP018 (PR-0934)
Temperature l ODPS. CPOO2 (TI-9681)
Containment Atmosphere l Sample l
. Pressure l Obtain from Chemical Analysis personnel Temperature l Obtain from Chemical Analysis personnel RCS: l Tavg l QDPS. CP005 (TI-0412A/0422A/0432A/0442A)
Pressure l ODPS. CPOO4 (TI-0445/0456/0457/0458) 4 RWST Imvel l ODPS. CP001 (LI-0931/0932)
- Accumulator Level: l ,
A l ERF/ DADS, CPOO1 (LI-0950/0951)
B l ERF/ DADS, CP001 (LI-0952/0953)
C l Fer/nAnR. CP001 (LI-0954/0955)
Containment Emergency l Water Level (Wide Dance) l0DPS. CPOIS (LR-3925) i I
I
Coolant Activity ardlg.ionuclide Trend for OPEPO2-ZG-DOO7 Failed Fuel Rev. O Page 21 of 41 FIGURE 1 POWER CORRECTION FACTOR FOR CS-134 BASED ON AVERAGE POVER DURING OPERATION
- C C
.C.e m E CE
- w W W E 2 2 "E C C C C =
m Ch. Ch. >=
4 M M N m C to C w e r% 44"J &
=
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C E C ll3 i C C
- =
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lp= W
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- . >== to U
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. A %C O
. .C w O W 2 I
- C p-
. = a a y p= U V 4 6
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. IB .
- a> M U
w 2
K C
C U C
. N CC W
3 C
3 . 4 a
h I .
4
- fB ft t -
C r% u3 10 w.
C. Cn. CO. . m. N.
. C.
~ C C C C C C C CD, C 'O
- v- =
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m ewg
- -~m-, -- - , - - ~w r-
. +
s Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O
- Page 22 of 41 t l FIGURE 2 DFT.ATIONSHIP OF PERCENT CT.An DAMAGE WITH PERCENT CORE inve.n10RY pyr. RASED OF I-131 ,
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Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 23 of 41 FIGURE 3 RELATIONSHIP OF PERCENT CLAD DAMAGE WITH PERCENT CORE INVENTORY RELEASED OF I-131 WITH SPIKING .
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. /
^ / / \
M / 4 / i w .01 .. / b .. ;
f
.007 5i s e' Ygt 5i i
.. # / . 1 0e
.005 .. ,e ,/ .. j
.. s ' ..
T en
.003 ..
s s' sds ..
.002 ' '
w u
s o -
.00 ..
,/ ..
T> 7 0-4 : .
5 5 0-4 : ::
E "J.0-4 a
'> 2 0-4 .. -
1 30.4 ..
- 7. 0 :: . .
5 0-5 ::
3 0-5 .. .
2 0-5 .. .
.0-5 . .:
n n e . . . . . . . . . . .
" " " " 2 4 6 d 44- 2 R .R 2 8 -
Clad Damage (5)
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 24 of 41 FIGURE 4 RELATIONSHIP OF PERCENT CLAD DAMAGE WITH PERCENT CORE INVENTORY PFr.FASED OF I-132 .
0.8 ..
0T :: ,
j{
.05
/ '.
sf ..
.03 .. .
/ .
.02 ..
,/ ..
/
- 01 #
- j ; ,,
007 :: / ::
.. / --
.005 .. / r
/
- 003
. p ,/ --
. / / ..
/ /
002 j 7
w
/
I" .001 . /
/ / ::
2 T.0-4 :
/ / -
h 5 0-4 / 9 p '
3.0-4 .. ,' } ,/ .
5 2*0-4 .. / , .,
c / /
~ / /
N I.0-4
.' /
/ .
O T.0-5 ::
.. /
/ ;;
5.0-5 .
,/ .
/
3.0-5 . e . ..
/
2 0=5 '
. / -
/
l.0-5 - -
a= N ipe . . . . .- '. . . . . .
- M. A. N M a .a M A O RR
- * == O O o o o - M u 8 CladDamage(5) 4 eg
,,nn,,r..e,, .-,,,,n , , - , , . , , , , - , ,
l Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O l Page 25 of 41 FIGURE 5 m -ATIONSHIP OF PERCENT CLAD DAMAGE 1 WITH PERCENT CORE Invrn10RY RELEASED OF I-133 .
l 1
. , ,,, , y qp 07 :: - i.
05 ..
03 ..
02 .. . . ,'.-
/
/
01 :: f
.07 / ::
/ .-
.05 .. / : .-
.. / ..
.03 ..
/ ..
/
.02 ..
/ .-
H /
s ,/
.01 /
3 .007
' f E .005 :: * / ::
s /
'l* ..
V<sO - '
a: .003 .. / .
a
{ .002 ..
s
,/ f,' /
.001
./ %/ /
,$ :: f ::
,5 ,7 0-4 :: ,' .r ' 'i s.0-4 :: /
/
/ .-
2 / .-
3 3 0-4
. .' f 2 0-4 ..
s' ..
.s'
.W' t.0-4 .. ,e ::
7.0-5 :: -
.. s -
5 0-5 . .s . .
3.0-5 ..
2 0-5 .
10 -
- n. ,,; . e., . . .
n n . e, u...o o
o o o o o 2 wi .a. -
Clad Damage (1) g(_, _ _ _ . , , _ _ , , _ _, ._, , , _ , , , , , , _ _, __
Coolant Activity and Radionucl'de i Trend for OPEPO2-ZG-OOO7 Failed Fuel Rev. O Page 26 of 41 FIGURE 6 RELATIONSHIP OF PERCENT CLAD DAMAGE WITH PERCENT CORE inym.n1vPY PFT. FARED OF I-135 . i l
1 - - . -
o.7 j-:
0.5 :: -
~
o.3 ..
o.2 ..
- o. . s s ,
.oT :: /
.os :: .s "
s ""
s'
.os .,
s'
.o2 .. -
- s s
5 .ol ..
/ .,
.oor --
e s::
7 .005
- s - s ..
.. s s ::
g .. s
/
- .cos ..
.E
{
002
.001 s'
s
/
g/
9's' s
e .. s -
8 7 0-4 li %g ' .,
l s' s ii
.E 5.o-4 ::
s s
s s
s' - -
5 3.6-4
., s s -
/ /
0 2 0-4
. .s /
s .
/
- 1 0-4 . . .
T.o-5 3.
.s - --
5.o-5 :: ,,- .
3.o-5 .
- ~
2 0-5 ..
l.o-5 ... .- .
~ n* n m s. . . . . . . . . . . .
- * *
- an= N n M A.O o o o o o o 2 2
.o ~ 8 Clad Damage (5) l l
4 Coolant Activity and Radionuclide Trend for OPEPO2-ZG-OOO7 Failed Fuel Rev. O Page 27 of 41 EIGHEELI RELATIONSHIP OF PERCENT CLAD DAMAGE WITH PERCENT CORE INVENTORY RELEASED OF Kr-87 ,
01 ..
.07 .: . . :"
.05 .
.03 ..
.02 ..
f t.
/
/
.01 .. ./ ..
- /
.007
.. / '~
.005 / ..
j .
.003 .. / ..
/
Q w
.002 . . .
/
/-
s
/ /
/ /
a .001 ..
/
g ..
' / ::
- 7 0-4 :: /
e ..
ac 5.0-4 . /. / ..
- h ..
/ -
/ ..
u / *y o 3.0-4 .. / f
$, 2.0-4 .. s s' -
,/ ..
c s s
- # /
p ,
s '
E o
I.0-4 ..
. s
/
s
/ .-
U T.0-5
. l 5.0-5 p' .. !
a s .. :
,m 3 0-5 ..
.. l i
2 0-5 . .
l l
i 1 0-5 ,
l i
. . . . . . . . . . . i
, . n. n. e.
e o
- n. n n m u a o n
o n,
o o n *. g <
1 o o o ,
. CladDamage(1) l
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 28 of 41 FIGURE 8 RELATIONSHIP OF PERCENT CLAD DAMAGE WITH PERCENT CORE InvrnrORY DFLEASED OF Xe-131m .
- i. . . .
o.1 .. .
o.s . .
i o.s .. ,
f.
/
o.2 ..
/ --
/
- / .
/
n o.s .. / ..
.me -
/ -
1 .or :: * -
- / .-
- / ..
g .os ..
/ ..
2" s --
/
.os ..
f --
a o
.02 ..
% /.-
es
/ /
3- /
~
a / -
f* s
< pet f v
t o
.on ..
s' /
/ --
=-
..oor
.oos
.- %d -
,/
/ .
.________as' s
.cos . .. \
.002 .. -
,,o, . . ..... . . . .
~
N " n%o
- 4 i sid ff f ~4 $
o o o .a .
CladDamage(5) l 1
1
a .
l Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 29 of 41 FIGURE 9 DPTATIONSHIP OF PERCENT CLAD DAMAGE WITH PERCENT CORE invr nrQEY DFr.FASED OF Xe-133 .
- 3. . .
~'
0.7 ..
~~
05 ..
0.3 ..
02 . .
, /..
y
. /
/
01 .. .
/ ,,
j .
.07 :: -
/ ::
.. . ./ ..
g .05 .. / ..
w
/ ..
T 03 . . / ..
$ /.
/
g .02 ..
f ..
/ .
- D / /
g'.0s .. q&, ,' ..
- J// -
/ ::
.E 00T ., y
/
.. . / -
r
,e#,*,,' g40
.005 .. / ..
u -e
. /
y .
- ,'g.
.00, . f *,. ...
__,==** .
.001 Y Y W W T '
d l ew
- n. .' s., n.. * . . . . . . . . . .
D. O o .o o
. ew n a n. o e o o os. o to n a o-CladDamage(5)
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 30 of 41 FIGURE 10 RELATIONSHIP OF PERCENT FUEL OVERTEMPERATURE WITH PERCENT CORE INVENTORY RELEASED OF Xe. Kr. I . or Cs -
100- . - - - - - - .
702: ::
/. .
- 50. . '
/ *
.. / ..
~
/ /
30-- . / / ~~
.: / /
m
./ /
20- . / / ~~
/ /
/ /
/ /
/ /
10 .,, . / /
.. / / ::
/ / ,,
"g* 5% . p+}p / +pp+/ ..
g .. . '. . / / ..
/
/-./ ',
g 3 .
/
/ 4. t , .,,
/ . , ,
h / / '
g 2- . . '/ / -
~
c ,/ ,/ ..
. =
> / ' /
' '" / / '
~ .
1~ . ./ ./ ..
Q3 ==
/ / ..
o y 0. i- -
f
/
se ., ..
05 . /
==
/ -
A 03 .
01 .
j . . .
0.1 - . . . . . . . .
~ N Yb an s. o o o o o o
= N P') to >. o t ' -
. Fuel Overtemperature (%)
l- .. . . - . . . - - . . _ , - - , - - - - - - - . - - - - - - - . . ,.-.,,.. -- ---- - --.- , - - - - - - - - - - - , - - - - - - - , - - - - - - -
Coolant t.ctivity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 31 of 41 FIGURE 11 RELATIONSHIP OF PERCENT FUEL OVERTEMPERATURE WITH PERCENT CORE INVENTORY RELEASP.'.D OF Ba-140 e 3 . . . . . .. . . . . .
o.t o.s . l r-o.3 . J.? ..
t o.2 . . .
s s
- s s
o.L... t / ..
s ..
. .or: ..
- s s
s s-:
01 . .
s
/ ,s ..
, ,s ..
3 01 . -
s s ..
s s a s a *o2 .
y / ,/ . ..
- 9 '
=
e cm
.0L .
s.
' #s '#s s /
s
. s s x .002.- s .
u o
.. .s ..
.w .001 . *
,s ,
g .. s s .:. ..
> .cos ' ,s ..
~
a . /
/ /
. .002.' ,s . ..
o s v s s
.00L . s .
. .s ..
~~
l 7 0-C .
5 0-4 . -
. l 3 0-4 . - ..
I i
2.0-4 . ..
1.o=4 .
n- n - m u a a a a a a
- n n m n a
.* .. =
s.
6 Fuel Ove'rtemperature .c
~**~ ume,-=,ee. .,en e
)
f Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 i Failed Fuel Rev. O Page 32 of 41 DATA SHEET 1 NORMAL OPERATIONS RADIONUCLIDE TREND DATA SHEET -
I OPEPO2-ZG-0007-1 (Page 1 of 1) 1.0 Isotopic Activities 4
lItotopel Specific l Power Correction l Decay Correction l Adjusted Specific l Base-line l l l Activity l Factor, X l Factor, I l Activity l Specific Activity l l l ( AA Ci/eml l I (ACCi/en) I (AACi/en) l l I-131 1 I I I I l l I-132 I I I I I l l I-133 I I I I 1 l l I-13s 1 I I I I l lre-131ml I I I I l lre-133 I I I I l l 1
l Rb-sa I I I I l l (Adjusted Specific Activity] = (Specific Activity) . X . Y I-131/I-133 Ratio = II-131 Adinated Specific Activitvl
! (I-133 Adjusted Specific Activity]
I-131/I-133 Ratio =
2.0 Procedure' Data Sample Time /Date Time of Sample Analysis Reactor Power at Sample Time %
(CPOOS, NI-0041B/00428/004?d/0044B) l RCS Pressure at Sample Time psig (CPOO4, PI-0455/0456/0457/0458)
RCS Tavg at Sample Time (CPOOS, TI-0412A/0422A/0432A/0442A)
Completed by Test Coordinator Time /Date V rified by Time /Date This FORM, when completed, shall be retained for 5 (five) years.
l I
Coolant Activity and D=dionuclide Trend for OPEPO2-ZG-OOO7 Failed Fuel Rev. O Page 33 of 41 DATA SHEET 2 l
! EORMAL OPERATIONS FAILED FUEL ESTIMATE BASED OR I-131 ACTIVITY -
i OPEP02-2G-DOO7-2 (Page 1 of 1)
Using the Adjusted Specific Activity value for I-131 recorded on Data Sheet 1, the following equations can be used to estimate the extent of failed fuel damage 1.0 Number of Failed Fuel Pins (Maximum Expected and Best Estimate) 4 Adjusted Specific Activity ( pCi/gn) for I-131 ,
~
3.5 x 10 p Ci/gm
= pins 2.0 Number of Failed Fuel Pins (Minimum Expected)
Adjusted Specific Activity (p Ci/gn) for I-131
=
~
, 4.9 x 10 pCi/gm
= pins 3.0 Percent Failed Fuel (Maximum Expected and Best Estimate)
Adjusted Specific Activity (pci/gn) for I-131 1.8 /eci/gm
= % Failed Fuel f
4.0 Percent Failed Fuel (Minimum Expected)
Adjusted Specific Activity (/A ci/gn) for I-131 2.5 /Aci/gm
= % Failed Fuel
]
Completed by __
Test Coordinator Time /Date Verified by Time /Date
, This FOkM, when completed, shall be retained for 5 (five) years.
i Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 34 of 41 DATA SHEET 3 POST-ACCIDENT SPECIFIC ACTIVITY DETERMINATION OPEP02-ZG-0007-3 -
(Page 1 of 2) 1.0 RCS Sample l Isotope l Specific l Power Correction l Decay Correction l Adjusted Specific l l l Activity l Factor, X l Factor, Y l Activity l l(paci/eml I I (/4C1/en) l I-131 I I I I l l I-132 l l l l l l I-133 l l l l l l I-13s l I I I l
l Rb-se i I I I l lCs-134 I I I I l lCs-137 l l l l l lBa-140 i l l l l Adjusted Specific Activity = Specific Activity . X . Y ( Ci/ga)
Containment Sump Sample l Isotope l Specific l Power Correction l Decay Correction l Adjusted Specific l l l Activity l Factor, X l Factor, Y l Activity l l l( AA ci/eml l l (/Aci/rm) l l I-131 l l l l l l I-132 l l l l l l I-133 l l l l l l I-135 l l l l [
l Rb-se I l I I lCs-134 l l l l lCs-137 1 l l I lBa-140 l l l l Adjusted Specific Activity = Specific Activity . X . Y (faci /ga)
This FORM, when completed, shall be retained for the life of the plant.
i
. e ... Coolant Activity and Dadinnnelide Trend for CPEP02-ZG-0007 Failed Fuel Rev. O Page 35 of 41 DATA SHEET 3 POST-ACCIDENT SPECIFIC ACTIVITY DETERMINATION OPEP02-ZG-0007-3 (Page 2 of 2) 1.0 Containment Atmosphere Sample l Isotope l Specific l Power l Decay l Press.-Temp.l Adjust Specific l l l Activity l Correction l Correction l Correction l Activity l l l( #Ci/ccll Factor X l Factor Y l Factor Z l Luci/cc) l l Kr-87 l l l l l l lXe-131ml l l l l l l Xe-1331 l l l l l Adjusted Specific Activity = Specific Activity . X . Y . Z 2.0 Sampling Data Approximate Time /Date of Accident / ;
Time of Sample Containment Atmosphere Conditions at Time of Sample:
Pressure psig Temperature F Containment Atmosphere Sample Conditions at Time of Sample:
Pressure psig Temperature F RCS Conditions at Time of Sample:
Tavg F Pressure psig RWST and Accumulators at Time of Samples l l RWST l Accumulator l l l l A l B l C l
% Water Level prior to l l l l l accident l l l l l l % Water Level prior to l l l l l H sample l l l l l Containment Emergency Water Level (Wide Range) at Time of Samples feet completed by Test Coordinator Time /Date Verified by Time /Date
f e.
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 36 of 41 DATA SHEET 4 POST-ACCIDENT GROSS ACTIVITY DETERMINATION OPEP02-ZG-0007-4 *
(Page 1 of 3) 1.0 Containment Sump Water Mass
[M ACC A *
" I"
[M C]B
[MACC1C " I" RWST
[ Containment Sump Water Mass) = [MACC A + ACC B ACC C RWST
[ Containment Sump Water Mass] = gm 2.0 Gross Activity (Use the equations given below the table to complete the table) ,
l l RCS l Containment Su=n l Containment Atmosphere l l l Adjusted l Gross l Adjusted l Gross l Adjusted ll Gross l l Isotope l Specific l Activity l Specific l Activity l Specific l Activity l l l Activity l l Activity l l Activity (
l l ( # Ci/en) l (Ci) l (# Ci/en) l (Ci) l (A C1/cc) (Ci) (
l I-131l l l l l l l I-132l l l l l l l!
I-133l l l l l l I-1351 l l l l l Rb-881 l l l l l l Cs-134I I I I l l l Cs-1371 l l l l l l Ba-1401 l 1 l Kr-87l
=[ ll l l l l l l lXe-131ml l l l l l l Xe-131 l l i
This FORM, when completed, shall be retained for the life of the plant.
- o Coolant Activity and Radionuclide Trend for OPEPO2-ZG-0007 Failed Fuel Rev. O Page 37 of 41 DATA SHEET 4 OPEPO2-ZG-0007-4 -
(Page 2 of 3)
RC.E:
Adjusted Specific
[ Gross Activity) , p,= , Activity (paCi/gn)g ,, p, x 259.61 Ci Containment Sump:
- j Adjusts Specific Containment Sump Activity (p Ci/gn) x Water Mass (gn)
(Gross Activity) , p,=
10, C1 1 x Containment Atmosphere
[ Gross Activity]g, djusted Specific x (1.008 x 10 ] Ci p,= Activity (/ACi/cc , p, 3.0 Total Gross Activity Use the table and corresponding eqdation below to determine the Total Gross Activity for each isotope.
l Isotope l Total Gross Activity. Ci l l I-131 l l l I-132 l l l I-133 l ll l I-135 l l Rb-88 l l l Cs-134 l l l Cs-137 l l l Ba-140 l l l Kr-87 l l l Xe-131m l l l Xe-133 l l
s o Coolant Activity and Radionuclide Trend fm OPEPO2-ZG-DOO7 Failed Fuel Rev. O Page 38 of 41 DATA SHEET 4 POST-ACCIDENT GROSS ACTIVITY DETERMINATION OPEPO2-ZG-DOO7-4 -
(Page 3 of 3)
. r -
[ Total Gross Activity (Ci)] , = Activity + Gross Activity ,
+ Containment Atmosphere ~l Gross Activity ,
Completed by Test Coordinator Time /Date Verified by Time /Date 1
I
. I
, s. o Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Puel Rev. O Page 39 of 41 DATA SHEET S PERCENT FUEL OVERTEMPERATURE AND PERCENT FUEL MELT ESTIMATE OPEPO2-ZG-0007-5
. (Page 1 of 2) 1.0 Bounding Values D = f s- core inventory released.
137 70T = % Fuel which would have experienced 137 overtemperature conditions assuming al Cs-137 release was due to fuel overtemperture.
FM = % Fuel which would have experienced melt 137 conditions all Cs-137 was due to fuel melt.
D = % of Ba-140 core inventory released.
40 FOT = % Fuel which would have experienced 140 overtemperature conditions assuming all Ba-140 release was due to fuel overtemperature.
FN 140
= ue u e e perienced melt conditions assuming all Ba-140 release was due to fuel melt.
2.0 Plotting of Data to
$0
$70-t 5*
l c <
> l C) 40 i
- u.
d: ae l
, ,.. .c...., , .9 i. .~~- l l
i O
o 1o ao 30 90 to 60 70 f0 To
%!. ruel tielt This FORM, when completed, shall be retained for the life of the plant.
<~
- O s
Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 40 of 41 DATA SHEET 5 PERCENT FUEL OVERTEMPERATURE AND PERCENT FUEL MELT ESTIMATE .
OPEP02-ZG-OOO7-5 (Page 2 of 2) 3.0 Data Interpretation From intersection of Cs-137 and Ba-140 curves:
Best Estimate % Fuel Overtemperature = %
Best Estimate % Fuel Melt = -
Completed by Test Coordinator Time /Date Verified by Time /Date 4
. e. o Coolant Activity and Radionuclide Trend for OPEP02-ZG-0007 Failed Fuel Rev. O Page 41 of 41 DATA nuwPT 6 PERf91rT Cr.An DAMAt:E AND PERCENT FUEL Ove.ad --EvaTURE ESTIMATES
- OPEPO2-ZG-DOO7-6 (Page 1 of 1)
Isotope l CIR I % Clad Failure I % Fuel Overtemperature l l l (%) l Estimate l l_ l Estimate l I l 1 1 I l
I 1 1-131 1 I i i l l l l
1
[. 1-132 I I I I t I I I
' I I l I-133 l : I l l l l l l+
l .
1-13s i I I 1
I I i _l l
l tr-s7 l l l
i l l l l
l l- xe-131m l l 1 l
I I 1
I l xe-133 l l
I l i I
(
I l cs-134 I I I l l l l l l cs-137 I l l e l
1 1 l I I l_ Ba-140 l l l I
l !
k Completed by Test Coordinator Time /Date I Verified by Time /Date 5,
ib o 5 l This FORM, when completed, shall be retained for the life of the plant. Y 1