Regulatory Guide 3.54
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| Issue date: | 01/31/1999 |
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U.S. NUCLEAR REGULATORY COMMISSION Revision 1 January 1999 REGULATORY GUIDE
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 3.54 (Draft was issued as DG-301 0)
SPENT FUEL HEAT GENERATION IN AN INDEPENDENT
SPENT FUEL STORAGE INSTALLATION
A. INTRODUCTION
This regulatory guide presents a method acceptable to the Nuclear Regulatory Commission In 10 CFR Part 72, "Licensing Requirements for the (NRC) staff for calculating heat generation rates for Independent Storage of Spent Nuclear Fuel and High use as design, input for an independent spent fuel Level Radioactive Waste," paragraph (h)(1) of Section storage installation. The original guide, issued in
72.122, "Overall Requirements," requires that spent September 1984, was based on validated analyses fuel cladding be protected during storage against performed for pressurized-water reactors (PWRs),
degradation that leads to gross ruptures or the fuel must and boiling-water reactors (BWRs) were considered be otherwise confined such that degradation of the fuel only as a simple conservative extension of the PWR
during storage will not pose operational safety data base. In this revision, the procedure for problems with respect to its removal from storage. It determining heat generation rates for both PWRs and K>j has been shown that, under certain environmental BWRs is based on analyses of each reactor type using conditions, high storage temperatures can cause calculational methods that have been validated against degradation and gross rupture of the fuel rods to occur measured heat generation data from PWR and BWR
very rapidly. It is necessary to know what storage assemblies.
temperatures are anticipated during the life of the storage installation and that these temperatures will not This revision presents a methodology that is significantly degrade the cladding to a point that causes simpler and is therefore expected to be more useful to gross ruptures. The temperature in an independent spent applicants and reviewers.
fuel storage installation is a function of the heat generated by the stored fuel assemblies. The spent fuel This regulatory guide contains no information storage system is required by 10 CFR 72.128(a)(4) to be collection requirements and therefore is not subject to designed with a heat removal capability consistent with the requirements of the Paperwork Reduction Act of its importance to safety. 1980 (44 U.S.C. 3501 et seq.).
USNRC REGULATORY GUIDES The guides are Issued ki the following ten broad divisions:
Regulatory Guides awe Issued to describe and make available to the public such infomia tion as methods acceptable to the NRC staff for implementing specific parts of the 1. Power Reactors 6. Products Commission's regulations, techniques used by the staff In evaluating specific problems or 2. Research and Test reactors 7. Transportation postulated accidents, and data needed by the NRC staff in its review of applications for & Fuels and Materials Facitltes 8. Occupational Health permits and licenses. Regulatory guides are not substitutes for regulations. and compli- 4. Environmental and Siting 9. Antitrust and Financial Review ance with them Is not required. Methods and solutions different from those set out In the 5. Materials and Plant Protection 10. General guides will be acceptable iNthey provide a basis for the findings requisite to the Issuance of continuance of a permit or license by the Commission.
Single copies of regulatory guides may be obtained free of charge by writing the Reproduc This guide was issued after consideration of comments received from the public. Corn- tion and Distribution Services Section, Office of the Chief Information Officer. U.S. Nuclear ments and suggestions for Inprovements In these guides are encouraged at al times, and Regulatory Commission. Washington, DC 20555-0001; or by fax at (310)415-2289;,or by guides will be revised, as appropriate, to accommodate comments and to reflect new infor- e-mail to DISTRIBUTION@NRC.GOV.
mation or experience.
Issued guides may also be purchased from the National Technical Information Service on Written comments may be submitted to the Rules and Directives Branch, ADM, U.S. Nuclear a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Regulatory Commission, Washington, DC 20555-0001. Royal Road. Springfield, VA 22161.
J
B. DISCUSSION
S - percentage safety factor applied to decay heat rates, Plab The methodology of NUREG/CR-5625 1 is Tc - cooling time of an assembly, in years appropriate for computing the heat generation rates of T1 - cycle time of last cycle before discharge, in days fuel assemblies from light-water-cooled power Te-1 - cycle time of next-to-last cycle, in days reactors as a function of burnup, specific power, and T - cycle time of ith reactor operating cycle, decay time. The computed heat generation results are including downtime for all but last cycle of used in the next section in a procedure for determining assembly history, in days heat generation rates for PWR and BWR assemblies. 7r. - reactor residence time of assembly, from first loading to shutdown for discharge, in days Calculations of decay heat have been verified by f7 - last-cycle short cooling time modification factor comparison with the existing data base of experimen f'7 - next-to-last cycle short cooling time factor tally measured decay heat rates for PWR and BWR fe - 23SJ initial enrichment modification factor spent fuel. The range of parameter values in the fp - excess power adjustment factor procedure is considered to lie in the mainstream of p - heat generation rate of spent fuel assembly, typical burnup, specific power, enrichment, and W/kgU
cooling time. A detailed example is shown in Appendix A.
C. REGULATORY POSITION
The following terms and units have been used in The following method for determining heat this guide. generation rates of reactor spent fuel assemblies is acceptable to the NRC staff. There may be fuel TERMS AND UNITS USED IN GUIDE assemblies with characteristics that are sufficiently outside the mainstream of typical operations that they Be - bumup in last cycle, MWd/kgU need a separate computation of the heat generation Be-. - burnup in next-to-last cycle, MWd/kgU rate. A discussion of the characteristics of assumed Bi - fuel bumup increase for cycle i, MWd/kgU typical reactor operations is given in Appendix B.
Btot - total bumup of discharged fuel, MWd/kgU
E, - initial fuel enrichment, wt-% 235U The first part of this section contains the P - specific power of fuel as in Equations 2 and 3, definitions and derivations, as used in this guide, of kW/kgU parameters needed in the determination of the heat P*n - average cumulative specific power during 80% generation rate of a fuel assembly. The second part uptime, kW/kgU contains the procedure used in deriving the final heat Paoe-l - average cumulative specific power (at 80%) rate of an assembly. Although allowance has been through cycle e-1, the next-to-last cycle made to use simple adjustment factors for cases that are Pe - fuel-specific power during the last cycle e somewhat atypical, many cases will probably not Pe-* - fuel-specific power during cycle e-1, the next require any adjustment of the table heat rate other than to-last cycle the safety factor.
PL, PH - lower and higher values of specific power that bracket the specific power value of Pav, Heat generation rate tables for actinides, fission Plab - heat generation rate that is obtained from the products, and light elements are given in Appendix C
table by interpolation between the lower and for informational purposes only. They are not used higher bracketing values directly in this guide's method for determining heat Pyu* - final heat generation rate determined by rates.
applying all adjustment factors, followed by the safety factor to the value Ptb 1. DEFINITIONS AND DERIVATIONS
TL, TH - lower and higher time values in a table that OF PARAMETERS
bracket the cooling time of interest, Tc The following definitions and derivations of
'Technical Support for a ProposedDecay Heat Guide Using SAS2H/ parameters of the spent fuel assembly are used in the ORIGEN-S Data, NUREG/CR-5625 (ORNL-6698), September 1994. procedure in this guide.
Copies are available for inspection or copying for a fee from the NRC
Public Document Room at 2120 L Street NW., Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; 1.1 Heat Generation Rate (p)
telephone (202) 634-3273; fax (202) 634-3343. Copies may be purchased at current rates from the U.S. Government Printing Office, P.O. Box
37082, Washington, DC 20402-9328 [telephone (202) 512-1800]; or from The heat generation rate of the spent fuel assembly the National Technical Information Service by writing NTIS at Port Royal is the recoverable thermal energy (from radioactive Road, Springfield, VA 22161. decay) of the assembly per unit time per unit fuel mass.
3.54-2
The units for heat generation rate used in this guide are The technical basis for these characteristics is watts per kilogram U (W/kgU), where U is the initial presented in NUREG/CR-5625.
uranium loaded. Heat generation rate has also been The specific power of cycle i, or e (last cycle), in referred to as decay heat rate, afterbeat, or afterheat power. kW/kgU, using bumup in MWd/kgU, is determined by:
1000B
1.2 Cycle and Cycle Times (T,) P = 10.8ThBfor i < e (Equation 2)
A cycle of the operating history for a fuel assembly 10.0B= for I = e is, with one exception, the duration between the time criticality is obtained for the initially loaded or reloaded reactor to the time at which the next reloaded core becomes critical. The exception is for the last The average specific power over the entire cycle, in which the cycle ends with the last reactor operating history of a fuel assembly, using the same shutdown before discharge of the assembly. T.denotes units as in Equation 2, is determined by:
the elapsed time during cycle i for the assembly.
Specifically, the first and last cycles are denoted by i =
s (for start) and i = e (for end), respectively. T , the P.. PIW.
= lOOOB,*-I (Equation 3)
total residence time of the assembly, is the sum of all T.+o.8 *l.E T,
T, for i = s through e, inclusive. Except for the last cycle for an assembly, the cycle times include the downtimes during reload. Cycle times, in this guide, are in days. The average specific power through the next-to last cycle is used in applying the adjustment factor for
1.3 Fuel Burnup of the Assembly (B, and B,) short cooling time (see Regulatory Position 2.2). This parameter is determined by:
The fuel burnup of cycle i, Be, is the recoverable thermal energy per unit fuel mass during the cycle in units of megawatt days per metric ton (tonne) initial 1000 (Bw, - B,) (Equation 4)
uranium (MWd/tU), or in the SI unitse of mass used in 0- --
0(T,,- T,)
~ this guide, megawatt days per kilogram U (MWd/
kgU). Bi is the best maximum estimate of the fuel assembly bumup during cycle i. B,o, is the total Note that BM, and P,, as derived here, are used in operating history burnup: determining the heat generation rate with this guide.
Also, for cooling times <7 years, Pe is used in an Btot-=iB i=5 (Equation 1) adjustment formula. The method applied here accommodates storing a fuel assembly outside the reactor during one or two cycles and returning it to the
1.4 Specific Power of the Fuel (P.,P,, P,,, and P,,.,) reactor. Then, B, = 0 may be set for all intermediate storage cycles. If the cooling time is short (i.e., _10
Specific power has a unique meaning in this guide. years), the results derived here may be excessively The reason for developing this definition is to take into high for cases in which the fuel was temporarily account the differences between the actual operating discharged. Other evaluation methods that include the history of the assembly and that used in the incorporation of storage cycles in the power history computation of the tabulated heat generation rates. may be preferable.
The calculational model applied an uptime (time at power) of 80% of the cycle time in all except the last 1.5 Assembly Cooling Time (7T)
cycle (of the discharged fuel assembly), which had no downtime. The definition of specific power, used here, The cooling time, T, of an assembly is the time has two basic characteristics. First, when the actual elapsed from the last downtine of the reactor prior to uptime experienced by the assembly exceeds the 80% its discharge (at end of T) to the time at which the heat applied in the SAS2H/ORIGEN-S calculations, the generation rate is desired. Cooling times, in this guide, heat rate derived by the guide procedure maintains are in years.
equivalent accuracies within 1%. Second, when the actual uptime experienced is lower than the 80% 1.6 Assembly Initial Fuel Enrichment (E,)
applied in the calculations, the heat rate is reduced.
The initial enrichment, E, of the fuel assembly is
2 35
2 The International System of Units. considered to be the average weight percent U in the
3.54-3
uranium when it is first loaded into the reactor. Heat generation rates vary with initial enrichment for fuel P PL + -L)PLp (Equation 5)
having the same burnup and specific power; the heat rate increases with lower enrichment. If the enrichment is different from that used in the
- 'c.alculations at a given burnup'and specific power, a PH - PB. (Equation 6)
P PL + PH-PL (Bt -EBL)
correction factor is applied.
2. DETERMINATION OF HEAT
BELT
GENERATION RATES
P. [-;- (to- rL (Equation 7)
Directions for determining the heat generation rates of light-water-reactor (LWR) fuel assemblies from Tables 1 through 8 are given in this section. First, a heat Where PL and PH represent the tabulated or rate, p,, is found by interpolation from Tables 1 through interpolated heat rates at the appropriate parameter
3 or Tables 5 through 7. Next, a safety factor and all the limits corresponding to the L and H index. If applied in necessary adjustment factors are applied to determine the sequence given above, Equation 5 would need to be the final heat generation rate, P .- There are three used four times to obtain p values that correspond to B.
adjustment factors (see Regulatory Pj,4ons 2.2 to 2.4) and B at valups of T and T,. A mini-table. of four p plus a safety factor (see Regulatory Position 2.5) that are valuesat4P is now available to interpolate burnup and applied in computing the final heat generation rate, Pp.,, cooling time. Equation 6 would then be applied to fromp.,. In many cases, the adjustment factors are unity obtain two values of p at TL and TH. One fmal and thus are not needed. An alternative to these interpolation of these two p values (at P, and B,o,)
directions is the use of the light-water-reactor afterheat using Equation 7 is needed to calculate the final p, rate calculation (LWRARC) code on a personal value corresponding to P , B , and T. The optional computer; the code is referred to in Regulatory Position Lagrangian interpolation scheme offered by the
2.7. This code evaluates pt andpn using the data and LWRARC code is also considered an acceptable procedures established in this guide. method for interpolating the decay heat data.
2.1 Computing Heat Rate Provided by Tables If P. or B,, falls below the minimum table value range, the minimum table-specific power or burnup, Tables 1 through 3 are for BWR fuel, and Tables 5 respectively, may be used conservativel
y. If P
through 7 are forPWR fuel. .The heat rates in each table exceefls the maximum table value, the table with the pertain to a single average specific poWaand are listed maximum-specific power (Table 3 for BWR fuel and as a function of total bumup and cooling time. After Table 7 for PWR fuel) may be used in addition to the determining P , B., and T as above, select the next adjustment factor, fp, described in Regulatory lower (L-index) and next higher (H-index) heat rate Position 2.3.
values from the tables so that:
The tables should not be applied if B, exceeds the P* P *v ePH maximum burnup in the tables, or if T is less than the BL*SB,. *5BHf minimum (1 year). If T exceeds the maximum (110
and years) cooling time of the tables, the 1 10-year value is TL*T *TI acceptable, although it may be too conservative.
Compute pb, the heat generation rate, at P , B., 2.2 Short Cooling Time Factorsf7 andf'7 and T, by proper interpolation between the tabuated values of heat rates at the lower and higher parameter The heat rates presented in Tables 1 through 3 and limits. A linear interpolation should-beused between Tables 5 through 7 were computed from operating heat rates for either burnup or specific power histories in which a constant specific power and an interpolations. In computing the heat rate at T, the uptime of 80% of the cycle time were applied.
interpolation should be logarithmic in heat rate and Expected variations from these assumptions cause linear in cooling time. Specifically, the interpolation only minor changes (51 %) in decay heat rates beyond formulas for interpolating in specific power, burnup, approximately 7 years of cooling. However, if the and cooling time are, respectively, specific power near the end of the operating history is
3.54-4
Table I
BWR Spent Fuel Heat Generation Rates, Watts Per Kilogram U, for Specific Power = 12 kW/kgU
Cooling Fuel Burnup, MWd/kgU
Time,
20 25 30 35 40 45 Years
4.147 4.676 5.121 5.609 6.064 6.531
1.0
3.132 3.574 3.955 4.370 4.760 5.163
1.4
2.249 2.610 2.933 3.281 3.616 3.960
2.0
1.592 1.893 2.174 2.472 2.764 3.065
2.8
4.0 1.111 1.363 1.608 1.865 2.121 2.384
5.0 0.919 1.146 1.371 1.606 1.844 2.087
7.0 0.745 0.943 1.142 1.349 1.562 1.778
0.645 0.819 0.996 1.180 1.369 1.561
10.0
15.0 0.569 0.721 0.876 1.037 1.202 1.370
20.0 0.518 0.656 0.795 0.940 1.088 1.240
0.477 0.603 0.729 0.861 0.995 1.132
25.0
30.0 0.441 0.556 0.672 0.792 0.914 1.039
40.0 0.380 0.478 0.576 0.678 0.781 0.886
50.0 0.331 0.416 0.499 0.587 0.674 0.764
60.0 0.292 0.365 0.438 0.513 0.589 0.666
70.0 0.259 0.324 0.387 0.454 0.520 0.587
80.0 0.233 0.291 0.347 0.405 0.464 0.523
90.0 0.212 0.263 0.313 0.365 0.418 0.470
100.0 0.194 0.241 0.286 0.333 0.380 0.427
110.0 0.179 0.222 0.263 0.306 0.348 0.391
3.54-5 I . .1
Table 2 BWR Spent Fuel Heat Generation Rates, Watts Per Kilogram U, for Specific Power = 20 kW/kgU
Cooling Fuel Bumup, MWd/kgU
Time, Years 20 25 30 35 40 45
1.0 5.548 6.266 6.841 7.455 8.000 8.571
1.4 4.097 4.687 5.173 5.690 6.159 6.647
2.0 2.853 3.316 3.718 4.142 4.540 4.950
2.8 1.929 2.296 2.631 2.982 3.324 3.673
4.0 1.262 1.549 1.827 2.117 2.410 2.705
5.0 1.001 1.251 1.501 1.760 2.024 2.292
7.0 0.776 0.985 1.199 1.420 1.650 1.882
10.0 0.658 0.838 1.023 1.215 1.413 1.616
15.0 0.576 0.731 0.890 1.056 1.227 1.403
20.0 0.523 0.663 0.805 0.954 1.107 1.263
25.0 0.480 0.608 0.737 0.871 1.009 1.150
30.0 0.444 0.560 0.678 0.800 0.925 1.053
40.0 0.382 0.481 0.579 0.682 0.786 0.893
50.0 0.332 0.417 0.501 0.588 0.677 0.767
60.0 0.292 0.365 0.438 0.513 0.589 0.666
70.0 0.259 0.324 0.386 0.452 0.518 0.585
80.0 0.233 0.290 0.345 0.403 0.460 0.519
90.0 0.211 0.262 0.311 0.362 0.413 0.465
100.0 0.193 0.239 0.283 0.329 0.375 0.421
110.0 0.178 0.220 0.260 0.302 0.343 0.385 Q1
3.54-6
Table 3 BWR Spent Fuel Heat Generation Rates, Watts Per Kilogram U, for Specific Power = 30 kW/kgU
Cooling Fuel Bumup, MWd/kgU
Time, Years 20 25 30 35 40 45
1.0 6.809 7.786 8.551 9.337 10.010 10.706
1.4 4.939 5.721 6.357 7.006 7.579 8.169
2.0 3.368 3.958 4.463 4.979 5.453 5.938
2.8 2.211 2.651 3.050 3.460 3.855 4.256
4.0 1.381 1.705 2.016 2.339 2.663 2.991
5.0 1.063 1.335 1.605 1.885 2.172 2.462
7.0 0.797 1.015 1.239 1.471 1.713 1.958
10.0 0.666 0.850 1.039 1.237 1.443 1.653
-15.0 0.579 0.737 0.898 1.067 1.242 1.422
20.0 0.525 0.667 0.811 0.962 1.117 1.276
25.0 0.482 0.611 0.741 0.877 1.017 1.160
30.0 0.445 0.563 0.681 0.805 0.931 1.061
40.0 0.382 0.482 0.581 0.685 0.790 0.898
50.0 0.332 0.418 0.502 0.589 0.678 0.769
60.0 0.292 0.366 0.438 0.513 0.589 0.666
70.0 0.259 0.323 0.386 0.451 0.517 0.584
80.0 0.232 0.289 0.344 0.401 0.459 0.517
90.0 0.210 0.261 0.310 0.361 0.411 0.463
100.0 0.192 0.238 0.282 0.327 0.372 0.418
110.0 0.177 0.219 0.259 0.300 0.340 0.382 Table 4 BWR Enrichments for'Burnups In Tables Fuel Burnup, Average Initial MWd/kgU Enrichment, wt-% U-235
20 1.9
25 2.3
30 2.7
35 3.1
40 3.4
45 3.8
3.54-7
Table 5 PWR Spent Fuel Heat Generation Rates, Watts Per Kilogram U, for Specific Power = 18 kW/kgU
Cooling Fuel Burnup, MWd/kgU
Time, Years 25 30 35 40 45 50
1.0 5.946 6.574 7.086 7.662 8.176 8.773
1.4 4.485 5.009 5.448 5.938 6.382 6.894
2.0 3.208 3.632 4.004 4.411 4.793 5.223
2.8 2.253 2.601 2.921 3.263 3.595 3.962
4.0 1.551 1.835 2.108 2.398 2.685 2.997
5.0 1.268 1,520 1.769 2.030 2.294 2.576
7.0 1.008 1.223 1.439 1.666 1.897 2.143
10.0 0.858 1.044 1.232 1.430 1.633 1.847
15.0 0.744 0.905 1.068 1.239 1.414 1.599
20.0 0.672 0.816 0.963 1.116 1.272 1.437
25.0 0.615 0.746 0.879 1.018 1.159 1.308
30.0 0.566 0.686 0.808 0.934 1.063 1.197
40.0 0.487 0.588 0.690 0.797 0.904 1.017
50.0 0.423 0.510 0.597 0.688 0.780 0.875
60.0 0.372 0.447 0.522 0.601 0.680 0.762
70.0 0.330 0.396 0.462 0.530 0.599 0.670
80.0 0.296 0.355 0.413 0.473 0.534 0.596
90.0 0.268 0.321 0.372 0.426 0.480 0.536
100.0 0.245 0.293 0.339 0.387 0.436 0.486
110.0 0.226 0.270 0.312 0.356 0.399 0.445
3.54-8
Table 6 PWR Spent Fuel Heat Generation Rates, Watts Per Kilogram U, for Specific Power = 28 kW/kgU
Cooling Fuel Bumup, MWd/kgU
Time,
25 30 35 40 45 50
Years
7.559 8.390 9.055 9.776 10.400 11.120
1.0
5.593 6.273 6.836 7.441 7.978 8.593
1.4
2.0 3.900 4.432 4.894 5.385 5.838 6.346
2.641 3.054 3.435 3.835 4.220 4.642
2.8
1.724 2.043 2.352 2.675 2.999 3.346
4.0
5.0 1.363 1.637 1.911 2.195 2.486 2.793
1.045 1.271 1.500 1.740 1.987 2.248
7.0
0.873 1.064 1.261 1.465 1.677 1.900
10.0
0.752 0.915 1.083 1.257 1.438 1.627
15.0
20.0 0.677 0.823 0.973 1.128 1.289 1.457
25.0 0.619 0.751 0.886 1.027 1.171 1.322
30.0 0.569 0.690 0.813 0.941 1.072 1.208
40.0 0.488 0.590 0.693 0.800 0.909 1.023
50.0 0.424 0.511 0.599 0.689 0.782 0.877
60.0 0.372 0.447 0.523 0.601 0.680 0.762
70.0 0.330 0.396 0.461 0.529 0.598 0.668
80.0 .0.295 0.354 0.411 0.471 0.531 0.593
90.0 0.267 0.319 0.371 0.424 0.477 0.531
100.0 0.244 0.291 0.337 0.385 0.432 0.481
0.225 0.268 0.310 0.352 0.396 0.440
110.0
3.54-9
Table 7 PWR Spent Fuel Heat Generation Rates, Watts Per Kilogram U, for Specific Power = 40 kW/kgU
Cooling Fuel Burnup, MWd/kgU
Time, Years 25 30 35 40 45 50
1.0 8.946 10.050 10.900 11.820 12.580 13.466
1.4 6.514 7.400 8.111 8.863 9.514 10.254
2.0 4.462 5.129 5.692 6.284 6.821 7.418
2.8 2.947 3441 3.884 4.346 4.787 5.267
4.0 1.853 2.212 2.554 2.910 3.265 3.647
5.0 1.429 1,728 2.021 2.327 2.639 2.970
7.0 1.067 1.304 1.543 1.793 2.052 2.325
10.0 0.881 1.078 1.278 1.488 1.705 1.936
15.0 0.754 0.921 1.091 1.268 1.452 1.645
20.0 0.678 0.827 0.978 1.136 1.298 1.469
25.0 0.619 0.754 0.890 1.032 1.178 1.331
30.0 0.570 0.693 0.816 0.945 1.077 1.215
40.0 0.488 0.592 0.695 0.803 0.912 K)
1.026
50.0 0.423 0.512 0.599 0.691 0.783 0.879
60.0 0.371 0.448 0.522 0.601 0.680 0.762
70.0 0.329 0.396 0.461 0.529 0.597 0.668
80.0 0.294 0.353 0.410 0.470 0.530 0.592
90.0 0.266 0.319 0.369 0.422 0.475 0.530
100.0 0.243 0.290 0.336 0.383 0.430 0.479
110.0 0.224 0.267 0.308 0.351 0.393 0.437 K)j
3.54-10
Table 8 PWR Enrichments for Burnups in Tables Fuel Burnup, Average Initial MWd/kgU Enrichment, wt-% U-235
25 2.4
30 2.8
35 3.2
40 3.6
45 3,9
50 4.2 It can be observed that there are upper limits to R
significantly different from the average specific and R'in Equations 8 and 10. It is recommended to not power, P ,*, p, 1 needs to be adjusted if T < 7. The "usethe decay heat values of this guide if any of the ratios Pf and P/P are, respectively, used to following conditions occur:
determine the adjustmenatictorsf 7 andf'> The factors reduce the heat rate pb, if the corresponding ratio is less if the if T < 10 years andP/Pw> 1.3, than 1 and increase the heat rate p,.,
1. The formulas for if 10 years < T < 15 years and P/P > 1.7, corresponding ratio is greater than if T < 10 years and P,,fý,., > 1.6 the factors are below.
A = when T, > 7 years or e = s Although it is safe to use the procedures in this (i.e., I cycle only) guide, the heat rate values forp* may be excessively high when f 7 = 1 + 0.35RI1/ -when 0s R s 0.3 f = I + 0.25RIT' when -0.3 s R < 0 T < 7 years and P/P* < 0.6, f= 1 - 0.075/T, when R < - 0.3 (Equation 8) T 5 7 years and Pe-/P.. < 0.4.
2.3 The Excess Power Adjustment Factorf, where R= PW -
a--p (Equation 9) The maximum specific power, P , used to generate the data in Tables 1 through 3 a Tables 5 through 7 is 40 kW/kgU for a PWR and 30 kWikgU for a BWR. If P , the average cumulative specific power, f7 =1 when TC > 7 years or is more than 35% higher than P,. (i.e., 54 kW/kgU for PWR fuel and 40.5 kW/kgU for BWR fuel), the guide e<3 should not be used. When 1 < P,,P.. < 1.35, the r' = I +0.lOR'/.[T when0"f R' c0.6 guide can still be used, but an excess power adjustment f = I +0.08 R'IT when - 0.5 : R' < 0 factor, f , must be applied. The excess power adjustment factor is
- 0.04/TC
when R' < - 0.5 (Equation 10)
JC =
Fo= vP.,/P.mx (Equation 12)
where P,, (Equation 11)
R' PC-, -1 For P* *; P30 =,
Pawx,- I fP =1
3.54-11
2.4 The Enrichment Factorf 2.5 Safety Factor S
The decay heat rates of Tables 1 through 3 and Before obtaining the final heat rate pa, an Tables 5 through 7 were calculated using initial appropriate estimate of a percentage safety factor S
enrichments of Tables 4 and 8. The enrichment factorf.
is used to adjust the value p . for the actual initial should be determined. Evaluations of uncertainties enrichment of the assembly E . o calculatef , the data performed as part of this project indicate that the safety in Tables 4 (BWR) or 8 (PWk) should be interpolated factor should vary with burnup and cooling time.
linearly to obtain the enrichment value E.a that corresponds to the assembly burnup, B . IfE/E. < 0.6, For BWR assemblies: (Equation 14)
the NRC staff recommends not using &is guide. When E/E* Ž 0.6, set the enrichment factor as follows: S= 6.4 + 0.15 (Bw - 20) + 0.044 (T,- 1)
.f= +0.01[a + b(T - d)][l - EIE,4] For PWR assemblies: (Equation 15)
when E!E,Ab< 1.5, S = 6.2 + 0.06 (Bw - 25) + 0.050 (T - 1)
f,=1 - 0.005 [a + b(T- d) (Euation3) The purpose of deriving spent fuel heat generation rates is usually to apply the heat rates in the when E/Eab > 1.5, computation of the temperatures for storage systems.
A preferred engineering practice may be to calculate the temperatures prior to application of a final safety where the parameters a, b, and d vary with reactor type, factor. This practice is acceptable ifS is accounted for Ee Eab, and K'. These variables are defined in Tables 9 in the more comprehensive safety factors applied to the and 10. calculated temperatures.
Table 9 Enrichment Factor Parameter Values for BWR Assemblies Parameter Parameter Value in Equation
13 E /E,, < 1 E,/E;b> 1
<40
- 1* T>40 1 TK 15 K >15 a 5.7 5.7 0.6 0.6 b -0.525 0.184 -0.72 0.06 d 40 40 15 15 Table 10
Enrichment Factor Parameter Values for PWR Assemblies Parameter Parameter value in Equation EIE *1 EIE
13 E ab s tab >1
1l<T<540 T>40 1<T<K20 T >20
a 4.8 4.8 1.8 1.8 b -0.6 0.133 -0.51 0.033 d 40 1 40 20 20
3.54-12
2.6 Final Heat Generation Rate Evaluation help messages and verification dialog boxes. The menus may be used with either a keyboard or a mouse.
The equation for converting p,*, determined in The code printout (one page per case) contains the Regulatory Position 2.1, to the final heat generation input data, the computed safety and adjustment factors, rate of the assembly, is and the interpolated and final computed decay heat rates. The output file may be printed, observed on a pft = (1 + 0.0S)f7 f 7 ffp," (Equation 16) monitor, or saved. Input cases may be saved, retrieved, duplicated, or stacked in the input file.
where fI f;. f, f,, and S are determined by the procedures given in Regulatory Positions 2.2 The LWRARC code may be requested from the through 2.5. Radiation Safety Information Computational Center (RSICC).
2.7 Heat Rate Evaluation by LWRARC Code Radiation Safety Information The LWRARC (light-water-reactor afterheat rate Computational Center calculation) code is an MS-DOS PC program that Oak Ridge National Laboratory performs the calculations in this guide. The only input P.O. Box 2008 for cases in which the cooling time exceeds 15 years Oak Ridge, TN 37831-6362 are Be T,,, E., and T. Additionally, the short cooling Telephone: (423)574-6176 time factors require B' and T* of the last and next-to-last FAX: (423)574-6182 cycles. The code features a pull-down menu system Electronic Mail: PDCm1+/-gox with data entry screens containing context-sensitive
3.54-13
APPENDIX A
SAMPLE CASE USING HEAT GENERATION RATE TABLES
A BWR fuel assembly with an average fuel T = 1240 - 940 = 300 d enrichment of 2.6 wt-% 235U was in the reactor for four cycles. Determine its final heat generation rate with Be = 26,300 - 20,900 = 5,400 kWd/kgU
safety factors, using the method in this guide, at 4.2 years cooling time. Adequate details of the operating p = (26,300 - 20,900)/300 = 18.00 kW/kgU
history associated with the fuel assembly are shown in Table A.1. T 1 = 940 - 630 = 310 d Table A.1 Sample Case Operating History Relative Time from Startup of Fuel, Days Accumulated Burnup Fuel (Best Maximum Estimate),
Cycle Cycle Startup Cycle Shutdown MWd/kgU
1 0 300 8.1
2 340 590 14.7
3 630 910 20.9
4 940 1240 26.3 Note that the output of the LWRARC code for this B,_l = 20,900 - 14,700 = 6,200 kWd/kgU
case is shown in the first case of Appendix B of NUREG/CR-5625.1 P., = 6,200/[0.8(310)] = 25.0 kW/kgU
Using Regulatory Position 1 P .a.1 = 20,900/[0.8(940)] = 27.793 kW/kgU
The following were given in the sample case (see Paw = 26,300/[300 + 0.8 (940)] = 25.00 kW/kgU
Regulatory Position 1 for definitions):
T = 1240d Using Regulatory Position 2 B,, = 26.30 MWd/kgU P~b should be determined from P , B.0 and T, as described in Regulatory Position 2.1. First, select the T= 4.2 y nearest heat rate values in Tables 2 and 3 for the
235 following limits:
E = 2.6 wt-% U
Compute T B, P ,T, P PP,,and P from PL = 20<Pa< 30
fiPH
Regulatory Position 1 and Equations 2 through 4. BE = 2 5 :< B,.5B.Y 30
'Technical Support for a Proposed Decay Heat Guide Using SAS2H/
OPJGEN-S Data, NUREBG/CR-5625 (ORNL-6698), September 1994.
T f=4 Tr : 5 Copies are available for inspection or copying for a fee from the NRC
Public Document Room at 2120 L Street NW, Washington, DC; the Next, use the prescribed interpolation procedure PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; for computing p. bfrom the tabular data. Although the telephone (202) 634-3273; fax (202) 634-3343. Copies may be purchased at current rates from the U.S. Government Printing Office, P.O. Box order is optional, the example here interpolates
37082, Washington, DC 20402-9328 [telephone (202) 5 12-1800]; or from between specific powers, burnups, and then cooling the National Technical Information Service by writing NTIS at Port Royal times. Denote the heat rate, p, as a function of Road, Springfield, VA 22161.
specific power, bumup, and cooling time byp(P,B,T). K)j
3.54-14
The table values at PI. and P,, for BL, and T. are With the value for p,, the formulas of Regulatory P(P'v BL, TL) = p(20,25,4) = 1.549 Positions 2.2 through 2.6 can be used to determinepr,.
Since T < 7 y, use Equations 8 through 11 to calculate p(P1 , BL, TL) = p(3 0, 2 5 ,4 ) = 1.705 the short cooling time factors:
First, interpolate the above heat rates to P. using R = P1P - 1 = (18/25) - 1 0.902=8 p(Pf,25,4) = p(20,25,4) + F [p(30,25,4) f7 I + [0.25(-0.28)]/4.2 = 0.983
- p(20,25,4)]
where R'= P .,IPo.- I =-O.lO005 F = (Pý. - PL Y(PH -PL) = 0-5 f = 1 + [0.08(-0.1005)]/4.2 = 0.998 The result at p(P ,25,4) is Since P < P. = P ., the excess power factor, f., is p(P ,25,4) = 1.549 + 0.5 (1.705 - 1.549) unity. Interpolating Table 4 enrichments to obtain the
= 1.627 enrichment associated with the burnup yields The other three values at P* are computed with a E,1 = 2.3 + (2.7 - 2.3)(26.3 - 25)/(30 - 25)
similar method: = 2.404 p(P ,30,4) = 1.827 + 0.5 (2.016 - 1.827)
- 1.9215 The enrichment factor, f, is then calculated using Equation 13:
p(P ,25,5) = 1.293 p(P.,30,5) = 1.553 f = I + 0.01 (8.376)(1 - 2.6/2.404) = 0.993 because E > E1 These are heat rates at the burnup and time limits.
Second, interpolate each of the above pairs of The safety factor, S, for a BWR is given in Equation 14:
heat rates to Bo, from the values at BL and B.:
S = 6.4 + 0.15 (26.3 - 20) + 0.044 (4.2 - 1)
FR = (B,,- Bi )/(BH- BL) = 0. 2 6 = 7.49%
p(PaBot,4) = 1.627 + 0.26 (1.9215 - 1.627)
= 1.7036 Then, using Equation 16, p(PwB,,,5) = 1.3606 Pfjmt = (1 + 0.01 S)f 7f' 7fffpl, Third, compute the heat rate at T from the above values at TL and TH by an interpolation that is with the above adjustment factors and p, yields logarithmic in heat rate and linear in time:
Pa = 1.0749 x 0.983 x 0.998 x I x 0.993 x 1.629 FT = (T -TL )(TH-TL) = 0.2
= 1.0749 x 1.587 = 1.706 W/kgU
log[p(P,*BdT)] = log 1.7036 + 0.2 (log 1.3606 - log 1.7036)
=0.2118 Thus, the final heat generation rate, including the safety factor, of the given fuel assembly is
2 1.706 W/kgU.
Ipb =p(PeB,,Td)=10°o = l.629W/kgU
3.54-15
APPENDgIXB
ACCEPTABILITY AND LIMITS OF THE GUIDE
-Inherent difficulties arise in attempting to prepare applied to correct for variations in power history that a heat rate guide that has appropriate safety factors, is differ from those used in the generation of the tables. For not excessively conservative, is easy to use, and example, the heat rate at 1 year is increased substantially applies to all commercial reactor spent fuel assemblies. if the power in the last cycle is twice the average power In the endeavor to increase the value of the guide to of the assembly. The limits on the conditions in licensees, the NRC staff made an effort to ensure that Regulatory Position 2.2 on ratios of cycle to average safe but not overly conservative heat rates were specific power are needed; first, to derive cooling time computed. The procedures and data recommended in adjustment factors that are valid, and second, to exclude the guide should be appropriate for most power reactor cases that are extremely atypical. Although these limits operations with only minor limitations in applicability. were determined so that the factors are safe, a reasonable degree of discretion should be used in the considerations In general, the guide should not be applied outside the of atypical assemblies-particularly with regard to their parameters of Tables 1 through 8. These restrictions, in power histories.
addition to certain limits on adjustment factors, are given in the text. The major table limits are summarized in Another variable that requires attention is the 59Co Table B.1. content of the clad and structural materials. Cobalt-59 Table B.1 Parameter Range for Applicability of the Regulatory Guide Parameter BWR PWR
T (year) 1-110 1-110
B, (MWd/kgU) 20-45 25-50
Pav (kW/kgU) 12-30 18-40
In using the guide, the lower limit on cooling time, is partly transformed to 6Co in the reactor and T, and the upper limit on burnup, B,.O, should never be subsequently contributes to the decay heat rate. The
59 extended. An adjustment factor, f , can be applied if Co content used in deriving the tables here should the specific power, P/', does not exceed the maximum apply only to assemblies containing Zircaloy-clad fuel value of the tables by more than 35%. Thus, if P is pins. The 6OCo contribution can become excessive for
59 greater than 54 kW/gU for PWR fuel or 40.5 kW/kgU Co contents found in stainless-steel-clad fuel pins.
for BWR fuel, the guide should not be applied. The Thus, the use of the guide for stainless-steel-clad minimum table value of specific power or bumup can assemblies should be limited to cooling times that be used for values below the table range; however, if exceed 20 years. Because 6Co has a 5.27-year half the real value is considerably less than the table life, the heat rate contribution from 6°Co is reduced by minimum, the heat rate derived can be excessively the factor of 13.9 in 20 years.
conservative. Also, the upper cooling time limit is conservative for longer cooling times. In addition to the parameters used here, decay heat rates are a function of other variables to a lesser degree.
In preparing generic depletion/decay analyses for Variations in moderator density (coolant pressure, specific applications, the most difficult condition to temperature) can change decay heat rates, although model is the power operating history of the assembly. calculations indicated that the expected differences Although a power history variation (other than the most (approximately 0.2% heat rate change per 1% change extreme) does not significantly change the decay heat in water density, during any of the first 30-year decay rate after a cooling time of approximately 7 years, it can times) are not sufficient to require additional have significant influence on the results in the first few years. Cooling time adjustment factors, f 7 and f '7,are corrections. The PWR decay heat rates in the tables were calculated for fuel assemblies containing water K)
3.54-16
total or individual nuclide decay heat rates with those holes. Computed decay heat rates .for assemblies determined by independent computational methods, containing burnable poison rods (BPRs) did not as well as comparisons of heat rate measurements change significantly (*1% during the first 30-year obtained for a variety of reactor spent fuel assemblies.
decay) from fuel assemblies containing water holes. Note from the equations that the safety factors increase with both burnup and cooling time. This Several conditions were considered in deriving increase in the safety factor is a result of the increased the safety factors (Equations 14 and 15) that were importance of the actinides to the decay heat with developed for use in the guide. Partial uncertainties increased burnup and cooling time together with the in the heat generation rates were computed for larger uncertainty in actinide predictions caused by selected cases by applying the known standard model approximations and limited experimental data.
deviations of half-lives, Q-values, and fission yields of all the fission product nuclides that make a Whenever the design or operating conditions for a significant contribution to decay heat rates. This spent fuel assembly exceed the parameter ranges calculation did not account for uncertainties in accepted in this guide, another well-qualified method contributions produced by the neutron absorption in of analysis that accounts for the exceptions should be nuclides in the reactor flux, or from variations in other used. A well-qualified method would be one that has a parameters. In addition to the standard deviations in technical basis that is validated against measured heat neutron cross sections, much of the uncertainty from rate data and has been demonstrated to provide neutron absorption arose from approximations in the conservative heat-rate estimates (i.e., per justified model used in the depletion analysis. In developing safety factors consistent with the measured data) for the safety factors, these more indirect uncertainties the extended design or operating conditions.
were determined from comparisons of the calculated
3.54-17
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Table C.3 BW . decay heat rates (W/kgU) of light elements, actinides, and fission products, for specific power , 12 kW/kgU, Set 3 Burnup = 40 lHd/kgU Coolinq Burnup 4 45 MHd/kgU
Eight~ E*Actinides Fis Prod years Light El Actinides Fis Prod
5.467E-02 1.008E#00 S.001E400 1.0 5.559E-02 1.186E400 5.2891400
4.027E-02 7.380[-01 4.00Z£*00 1.4 4.089E-OZ 8.S74E-01 4.2651400
3.390E-02 5.141E-01 3.0681*00 2.0 3.439E-02 6.255-01 3.300E*00
2.970E-OZ 4.1981-01 Z.31E500 Z.8 3.013E-0Z S.]75E-01 Z.S1E700
Z.4971-02 3.875E-01 1.709E#00 4.0 Z.533E-OZ 4.791E-01 1.850E+00
2.173E-02 3.8Z7E-03 1.440E*00 5.0 2.20SE-02 4.723E-01 1.593E+00
1.657E-02 3.8101-01 1.364E#00 7.0 1.681E-02 4.6751-01 1.293E+00
1.11ZE-02 3.797E-01 9.777E-01 10.0 1.129E-02 4.A6[E-01 1.067E.00
5.800E-03 3.760E-01 8.199E-01 15.0 S.89Z1-03 4.533E-01 9.1101-01
3.066E-03 3.7112-01 7.139E-01 20.0 3.1181-03 4.434E-01 7.930E-01
1.641E-03 3.653E-01 6.280E-01 Z3.0 1.671E-03 4.33ZE-01 6.973E-01
8.90SE-04 3.5901-01 5.54S.-01 30.0 9.086E-04 4.:29E-O: 6.1551-01
9.771E-04 3.4S6E-01 4.347E-01 40.0 2.841E-04 4.OZ9E-0]: 4.824E-01
9.697E-05 3.320E-01 3.4ZZ-01 SO.0 3.001E-04 3.840E-01 3.797E-01
4.118E-O5 3.1881-01 Z.701E-01 60.0 4.286E-OS 3.666E-01 2.996E-01
.Z501-0S 3.064E-01 2.134E-01 7C.0 Z.3571-0S 3.50SE-01 2.367[-01 I. ESE-GS Z.9481-01 1,688E-01 80.0 1.6291-OS 3.358E-01 1.8721-01
1.4ZZ1-OS 2.8401-01 1.33SE-01 90.0 1.307E-05 3.ZZ31-01 1.481E-01
1.0781-0S Z.739E-01 1.0S7E-01 100.0 1.13SE-0S 3.099E-01 1.17Z2-01
9.704E-06 Z.646E-01 8.36SE-02 110.0 1.0ZZE-OS 2.9851-01 9.979E-02 Table C.4 BWR decay kict rates (W/KggU) of light elements, actinides, and fission products, for specific power '20 kW/kgU, Set 1 Burnup a 20O ,Wd/kqgU Cooling Burnup a 25 ttd/,kgU
Time; ---des Light E1 Actinides Fis Prod years Light El Actinxdes Fis Prod
6.2811-02 2.957[-01 5.1901400 2.0 6.5731-02 4.366E-01 5.764E400
4.084E-02 t.036E-01 3.E53E*00 1.4 4.447E-01 3.012E-01 4.341E+00
3.278*-02 1.3981-01 2.680E100 2.0 3.60S5-02 t.0681-01 3.073F400
2.332E-02 1.119E-01 1.789E400 t.8 3.123E-02 1.648E-02 2.IOE400
Z.36ZE-02 1.0511-02 1.133E+00 4.0 2.60SE-02 1.5311-01 .1.370E+00
2.047E-02 1.064E-01 6.744E-01 5.0 2.2f6Z-02 1.536E-01 1.071E400
1.SSE-OZ 1.113E-01 6.493E-01 7.0 1.716E-02 1.58Z1-01 8.1013-01
1.03ZE-02 2.181E-01 5.29SE-02 10.0 1.14SE-02 1.646E-Cl 6.620E-01 S.299E-03 1.271E-01 4.431E-01 IS.0 5.905E-03 1.7301-01 S.SZIE-01
2.7481-03 1.337E-01 3.8646-01 20.0 3.081E-03 1.788E-01 4.610E-01
1.436E-03 1.384E-01 3.406E-01 25.0 1.6231-03 1.826E-01 4.2331-01
7.S70E-04 1.4161-01 3.0121-01 30.0 6.6401-04 1.849E-01 3.7431-01
2.182E-04 1.4SOE5-01 2.366E-01 40.0 2.S54E-04 1.865E-01 2.939E-01
6.936E-05 1.4561-01 1.86SE-01 S5.0 8.361E-OS 1.8S31-01 2.31SE-01
2.71ZE-OS 1.447E-01 1.473E-01 60.0 3.3ZZ-OS 1.826E-01 1.8281-01
1.4491-OS 1.42S1-01 1.164E-01 70.0 1.7481-OS 1.791E-01 1.44SE-01
1.027E-05 1.404E-401 9.2081-02 80.0 1.Z20E-OS 1.7531E-01 1.143E-01
8.5S1.-06 1.37E4-01 7.Z861-02 90.0 9.719E-06 1.713E-01 9.0401-02
7.6181-06 1.3SIE-01 S.767[-02 100.0 8.5191-06 1.673E-01 7.15S1E-O
6.966E-06 1.324E-01 4.5631-OZ 110.0 7.72ZE-06 1.6351-01 S.664E-02
3.54-19 I 1 .1
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Table C.7 BWR decay heat rates (W/kgU) of light elements, adtmudcs, and fission products, for specific power = 30 kW/kgU, Set 1 Burnup a 20 hWd/kgU Cooling Burnup = 25. II1d/kgU
_________________________ Time,* ______________
Lignt El Actinides Fis Prod years Light El Actinid
e. s FLs Prod
7.591E-02 ZSSE0-01 A.4,75E.00 1.0 5.104E-02 3.89ZE-01 7.316E#00
4.621E-O2 1.816E-01 4.?711EO0 1.4 S.0801-OZ 2.731E-01 S.397E100
3.S4IE-OZ 1.289E-01 3.203E+00 Z.0 3.970E-02 1.924E-01 3.726E*00
3.046E-02 1.0621-01 2.074E+00 2.8 3.405E-0Z 1.567E-01 Z.460E#00
Z.S29E-OZ I.0SZE-01 I.ZSSEO5 4.0 2.830E-02 ].472E-01 1.S291400
2.188E-02 1.0ZSE-01 9.384E-01 5.0 2.450E-02 14aZE-01 1.162E4+00
I.ASSE-02 1.079E-01 6.7Z,1-01 7.0 I.85SE-OZ 1.530E-01 6.438E-01
1.1001-0Z 1.148E-01 5.3981-01 10.0 I.Z35E-02 1.597E-01 6.776E-01
5.638E-03 1.241E-01 4.492-0a 15.0 4.356E-03 1.;841-01 5.619E-01 E.915E-03 1.308E-01 3.916E-03 20.0 3.309E-03 1.74SE-01 4.890E-01 I.SZZ-03 1.357E-01 3.430[-01 ZS.O 1.7381-03 1.786E-01 4.304E-01
8.003E-,04 I.391E-Z; :;z,:; 30.0 9.222-04 1.812E-01 3.804E-01
2.29OE-04 1.427E-01 2.396"1-01 40.0 2.701E-04 1.631E-01 2.986E-01
7.194E-.S 1.436E-01 1.88SE-01 50.0 8.718E-OS 1.8231-01 2.3SZ-01
2.749!-0S 1.4ZE1-01 1.491E-01 60.0 3.40ZE-OS 1.799E-01 1.857E-01
1.4S9E-0S 1.4111-01 1.179E-01 70.,0 1.764E-05 1.767E-01 1.4681-01
1.0Z91-0S 1.389E-01 9.3Z21-02 80.0 I.O3E-OS 1.7301-01 1.161]-01
6.S64E-06 1.3641-01 7.376E-0? 90.0 9.736E-06 1.493E-01 9.185E-02
7.435E-06 1.3381-01 5.838E-OZ 200.0 8.$391-06 1.63SE-01 7.2691-OZ
4.98U6-06 1.3121-01 4.622E-02 110.0 7.745E-06 1.615E-01 S,754E-02 Table C.8 BWR decay heat rates (W/kgU) of light elm*ents, actinides, and fission products, for specific power - 30 kW/kgU, Set 2 burnup 30 Wi'd/lkgU Coo ling Burnup a 35 IlWd/kgU
Time, I
LEht .E1 Actinides Frz rod yeats Light Il Actinides Fis Prod
8.SZE-02 5.349E-01 7.931E+00 1.0 8.934E-OZ 4.9451-01 8.5531*00
5.4S'E-02 5.7701-01 5.9251400 1.4 5.801E-02 4.93S1-01 6.4541*00
4.307E-02 2.4661-01 4.1531400 2.0 4.609E-0Z 3.SSE-01 4-5804E00
3.704E-02 Z.1701-01 2.796E100 2.6 3.971E-02 Z.8831-01 3.13ZE400
3.084E-0Z Z.OZ30-01 1.783100 4.0 3.3091-02 2.680E-01 2.038E400
2.67ZE-OZ 2.0Z1E-03 1.376E#00 5.0 Z.868E-02 9.664E-01 1.5901E00
2.OZS0-OZ Z.OSSE-01 1.013E*00 7.0 2.176E-02 2.68SE-01 1.181E100
1.331E-02Z .1121-01 6.144E-01 10.0 1.4531-0Z 2.7181-01 9.504E-01
6.976E-03 2.178--01 4.736E-01 IS.0 7.523E-03 2.7531-01 7.644E-01
3.6481-03 2.219E-01 S.SS-01 20.0 3.948E-03 2.7661-01 ;.811E-01
1.921E-03 Z.Z421-O1 5,1511-01 ZS.0 Z.0961-03 2.7631-01 5.9881-01
1.031E-03 Z.,S11-01 4.SSOE-01 30.0 1.1*26-03 z.7491-01 5.288E-01
3.076E-04 2.2401-01 3.569E-01 40.0 3.404E-04 2.697E-01 4.146E-01
1.014E-04 Z.2061-01 1.811E-01 SO0. 1.1381-04 2.629E-01 3.264E-01
4.00!1E-OS .1591-01 2.219E-01 40.0 4.SZ8-0S Z.SSS-1-01 2.576E-01 Z.056E-OS 2.1081-01 1.7S31-01 70.0 2.311E-05 2.479E-01 2.036E-01
1.3691-3S 2.054E-01 1.387E-01 60.0 1.S161-05 2.404E-01 1.6101-01
1.0851-OS 2.001E-01 1.097E-01 90.0 1.1541-OS 2.332E-01 1.2741-01
9.393E-06 1.949E-01 8.682E-02 100.0 I.0S1-0 Z.Z64E-01 1.0080-01
8.461E-06 1.900E-01 6 873E-02 110.0 9.099E-06 2.ZOE-01 7.979E-02
3.54-21
Table C.9 BWR decay heat rates (W/kgL) of light elements, actinides, and fission products, for specific power - 30 kW/kgU, Set 3 Durnup a 40 IlW/kgU Cooling EUinup x 45 tfldkjU
Light 91 Actinides Fl: Frod Time,#
years Light El Actinides Fiz Prod
9.37]1-02 0.8a0E-01 9.0291+00 1.0 9.716E-02 1.063E+00 9.546E100
6.150E-02 6.345E-01 6.8831E00 1.4 6.41CE-02 7.7051-03 7.334E100
4.91ZE-02 4.590E-01 4.945E+00 2.0 5.132E-O S.651]-01 S.3221*00
4.241E-0! 3.780E-01 3.4351400 Z.8 4.435E-02 4.6941-01 3.742E#00
3.538E-0Z 3.5071-01 Z.Z77t1.00 +4.0 3.701E-02 4.3571-01 Z.3I8E400
3.0681-0Z 3.4701-03 1.7941400 3.0 3.2111-0Z 4.299E-10 2.0001+00
2.3291-0! 3.463E-01 1.3431100 7.0 2.4351-02 4.2641-01 1.507E+00
1.556E-02 3.4601-01 1.0811[00 10.0 1.6Z9E-OZ 4.2Z4E-O 1.214E+00
8.070E-03 3.441E-01 8.8991-01 135.0 8.4S57-03 4.1491-01 9.982z-o0
4.2431-03 3.407E-01 7.719E-01 20.0 4,.1,E-03 4.067E-01 8.6331-01 Z.2581-03 3.3631-01 6.7a3E-0o 25.0 2.3721-03 3.9801-03 7.6001-01 f.h6E-03 3.3131-01 5.9571-01 30.0 1.Z.BI-03 3.8921-01 6.707E-01
3.703E-04 3.2021-01 4.692E-01 40.0 3.9191-04 3.7189-01 s.Z,5-01
1.2481-04 3.0861-01 3.6931-01 S0.0 1.3ZS-04 3.ss31-01 4.1361-01
5.001E-05 2.9731-01 2.9141-01 60.0 5.3431-05 3.4001-01 3.2631-01
.5s51-0s z.8a66-o0 t.3031-01 70.0 2.7301-os 3.26oz-01 2.5781-01
1.i69-0s z.7651-o0 i.821-o1 80.0 1.7771-05 3.131E-01 2.0391-01
1.297e-05-2.671E-01 1.4411-01 90.0 1.3761-05 3.0141-01 1.613E-01
1.1E01-0s .5831-e0 1.1401-01 100.0 1.1731-05 2.9061-01 1.276E-01
9.9131-06 Z.501-01 .9.0241-02 110.0 2.04779-05 z.a86z-0, 1.oso0-o Table C. 10 PWR decay heat rates (W/AgU) of light eleancts, actinides, and fission products, for specific power =18 kW/kgU, Set 1 Burnup a .5 i1Wd/kgU Cooling Burnup a 30' tmlHd/kgU
Light E1 Times, Actinidis Fi: Prod years Light El Actinides FL: Prod
1.19EE-01 4.3771-01 5.359E100 1.0 1.269E-01 3.911E-01 5.855E+00
.06ZE-01 3.0021-01 4.0791+00 1.4 2.130E-01 4.091E-01 4.4871E00
9.S79E-02 2.04SE-01 2.9081.00 2.0 1.021E-01 Z.814E-01 3.249E100
8.aS!E-02 I.620E-01 t.0061+00 2.8 9.113E-02 2.241E-01 Z.Z86E100
7.2621-02 1.501E-01 1.3ZE8100 4.0 7.7421-02 2.0721-01 1.5501E00
6.3311-02 I.S15E-01 1.053E#00 5.5 6.771E-02 2.071E-01 1.2451#00
4.369E-02 1.5671-01 8.0311-01 7.0 3.1911-02 2.116E-01 9.5979-01
3.275E-02 1.641E-01 6.609E-01 10.0 3.49ZE-02 2.18ZE-0 7.9051-01
1.696S-01 1.7391E-01 5.30E-01 13.0 16808E-0! 2.2641-01 6.6001-01
8.806s-03 1.3071-01 C.8221-I1 zo.0 9.359E-03 2.315E-01 5.7.91[-01
4.5891-03 1.855E-01 4.Z47E-01 25.4 4.894E-03 2.351E-01 5.060E-01 z.4061-03 1.885E-01 3.7551-01 30.0 2.566E-03 2.3671-01 4.471E-01
6.8721-04 1.9101-01 2.9451-01 40.0 7.341E-04 2.366E-01 3.509E-01 Z.2351-04 1.9051-01 2.3Z39-01 50.0 2.399E-04 Z.3361-01 2.7641-01
9.681-05 1.8821[-01 .8341-01 60.0 1.0471-04 2.290E-01 2.182E-01
6.0719-05 1.849E-01 1.4501-01 70.0 6.6201-05 2.238E-01 1.724E-01
4.9121-05 1.812E-01 1.1471-01 80.0 3.3791[-OS 2.1831-01 1.3641E-01
4.4ZSE-05 1.77Z1-01 9.07ZE-02 90.0 4.8561-05 2.1271-01 1.079E-01
4.133E-05 1.7331-01 7.180E-02 100.0 4.5411-0S 2.0721-01 8.5391-02
3.904E-05 1.693E-01 3.684E-02 110.0 4.Z93E-0S Z.019E-01 6.759E-02
3.54-22
Table C. 11 PWR, decay heat rates (W/kgU) of light elements, actinides, and fission products, for specific power = 18 kW/klgU, Set 2 Burnup r 55 ItHd/kgU Cooling Burnup = '40 Wd/kgU
Fis Prod years Liqht E1 Actinides FLi Prod Light El ActInides
1.0 1.365E-01 9.35ZE-01 S.$901E0G
1.319E-01 7.60,ZE-01 6.194E+00 6.608E-01 5.155E+00
1.177E-01 5.305E-01 4.800E400 1.4 1.22S1-01
2.0 1.10SE-01 4.680E-01 3.8333100
1.064E-01 3.696E-01 3.5261400 3.7971-01 2.785E400
9.506E-0 z2.96SE-01 2.529E+00 2.8 9.870E-0Z
4.0 8.380E-0Z 3.507E-01 1.963E100
8.077[-0Z Z.734E-01 1.754** 00 3.476E-01 1.609E400
7.064E-0Z Z.721E-01 1.4Z6E+00 5.0 7.33SE-02
7.0 S.6Z3E-0Z 3.486E-01 1.2611+00
5.416E-OZ 1.7S:E-01 1.110E100 3.783E-02 3.506E-01 l.q04*E00
3.643E-02 2.798E-01 9.16Z1-01 10.0
15.0 1.959E-02 3.5Z-01 8.0670--1
1.587E-02 Zt.85 -01 7.640E-01 3.5151-01 7.540E-01
9.797E-03 2.879E-01 6.649E-01 ZO.0 1.01?E-02
2S.0 5.305E-03 3.49ZE-01 6.630E-01
5.108E-03 2.088E-01 S.aSOE-01 3.4571-01 56 ,*5-01
2.6601-03 Z. 8ZE-0% S.1671-01 30.0 2.784E-03
40.0 7.997E-04 3.367E-01 4.$9-01
7.683E-04 Z.8411-0 4.0SZE-01 3.264E-01 3.614E-01
2.521E-04 2.775T-01 3.191E-01 50.0 2.641E-04
60.0 1.1751-04 3.156E-01 Z.SSZE-01
1.II4E-04 2.705E-01 2.518E-01 3.049E-01 2.253E-01
7.1061-05 1[.628-01 1.9901-01 70.0 7.55SE-05
5.804E-05 t.$511-01 1.574E-01 60.0 6.201E-05 t.947E-01 1.782E-01
5.251E-05 2.4761-01 1.24SE-01 90.0 S.4211-05 2.609E-03 1.410E-01
4.916E-05 Z.A04E-01 9.8SE-OZ 100.0 5.2671-0S 2.7S81-01 1.116E-01
4.d5ZE-05 Z.3351-01 7.8011-0Z 110.0 4.9891-05 2.672E-01 8.831E-02 Table C.12 PWR decay heat rates (W/kgU) of light elements, actinides;
and fission products, for specific power- 18 kW/kgU, Set 3 Burnup a 45 MlLd/k"U CAo.Lin" Burnup s 50 ttHd/kVU
_"_ Time#, _e Light 11 Actinides Fls Prod years igUht E1 Acti*ndas Fis Prod
1.4101-01 1.144E+00 6.891E#00 1.0 1.4581-01 1.354E400 7.273E+40
1.264E-01 8.1801-01 5.438E100 1.4 1.308E-01 9.8Z41-01 5.781E00
1.144E-01 S.8831-01 4.0904E00 2.0 1.185E-01 7.198E-01 4.38S5*00
I.0ZZE-01 4.820E-01 3.)114E00 2.8 I.059E-01 5.973E-01 3.1591+00
8.6851-02 4.4541-01 2.153E1.0 4.0 6.996E-02 5.533E-.01 2.354E*00
7.597E-02 4.399E-01 1.7781+00 S.0 7.869E-02 5.4521-01 1.951E+00
S.824E-02 4.378E-01 1.4011.00 7.0 6.033E-02 S.393E-01 1.S43E*00
3.91GE-02 4.351E-01 1.158E+00 10.0 4.059E-O2 S.32ZE-01 1.2741*00
2.029E-02 4.31EE-01 9.428E-01 15.0 Z.102E-02 5.20OE-01 1.0581*00
1.054E-02 4.252E-01 8.367E-01 20.0 1.092E1-0 S.074E-01 9.187E-01
5.498E-03 4.181E-01 7.354E-01 Z5.0 5.6981-03 4.947E-01 8.072E-01 Z.887E-03 4.106E-01 6.491E-01 30.0 2.993E-03 4.8a1E-01.7.1Z21-01
8.3151-04 3.947E-01 5.0871-01 4,0.0 68.46E-04 4.58E-01 5.5791-01
2.766E-04 3.789E-01 4.004E-01 50.0 2.691E-04 4.3541-01 4.391E-01
.246E-04 3.636E-01 3.157E-01 60.0 1.3151-04 4.15.E-01 3.464E-01
5.104E-05 3.493E-01 2.496E-01 70.0 6.63ZE-05 3.944E-01 2.7371-01
6.684E-05 3.3601-01 1.574E-01 80.0 7.150E-05 3;.7971E-01 2.164E-01
6.0721-05 3.236E-01 1.562E-01 90.0 6.507E-0S 3.A3E-01 1.712E-01
5.4961-05 3.121E-01 1.236E-01 100.0 6.1081-OS 3.S0ZE-01 1.350E-01
5.3986-05 3.014E-01 9.-783-0Z 110.0 5.792E-OS 3.373E-01 1.073E-01
3.54-23
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Table C. 15 PWR decay heat rates (W/kgU) of light elemenrts, actinides, and fission products, for specific power - 28 kW/kgU, Set 3 Burnup a 45 hVJd/kgU Cooling Burnup = 50 hld/kgU
_______
_______ ______ Time, _ _ _ _ _ _ _ _ _ _ _
Light El A*tinides Fis- PFro years Light El Acti-nides Fis Pzod
1.690E-01 1.073E400 9.136E400 .0 1.767E-01 .1.282E400 9.661E400
1.493E-01 7.710E-01 7.058E#00 1.4 1.S651-01 9.334E-01 7.503E.00
1.344E-01 5.S8SE-01 S.1451.00 2.0 1.410E-01 4.8701-01 5.518[400
1.199E-01 4.403E-01 3.640E#00 t.8 IA.281-01 5.7Z1E-01 3.944E400
1.01[]-01 4.267E-01 Z.4711[.00 4.0 1.068E-01 5.310E-01 2.708940u
8.90]E-02 4.211E-01 1.975E.00 5.0 9.341E-02 5.234]-01 2.1761E00
6.821E-02 4.202E-01 1.4991.00 7.0 7.1$8E-OZ 5.180£-01 1.658400
4.S87E-02 4.1899-01 1.221E.00 10.0 4..814-0Z 5.116E-01 1.340E+00
t.374E-OZ 4.151E-01 9.993E-01 1S.0 Z.492g-02 S.003E-0 1.10ZE400
1.233E-02 4.098E-01 8.666E-01 tO.0 I.Z.941-O 4.886E-01 9.521E-01
6.4AZ£-03 4.036E-nl 7 II-ln. 25.o 6.741E-03 4.766E-01 6.3871-01
3.366E-03 3.967E-01 6.719E-01 30.0 3.534E-03 4.6481-01 7.400E-01
9.603E-04 3.820]-01 S.2441-01 40.0 1.009E-03 4.4201-01 $.796E-01
3.114E-04 5.6721-01 4.143E-01 50.0 3.Z8SE-04 4.[091-o1 4.5601-01
1.341E-04 3.529E-01 3.269E-01 60.0 1.424E1-0 4.01(E-01 3.598E-01
8.388E-05 3.394E-01 t.S83E-01 70.0 8.954E-05 3.841E-01 2.8421-01
6.7641-OS 3.269E-01 2.0421-01 10.0 7.2641-05 3.681E-01 Z.Z47E-01
6.l12[-OS 3.15ZE-01 1.616E-01 90.0 6.563E105 3.5361-01 1.778E-01
5.T7ZE-05 3.044E-01 1.279E-01 100.0 6.146E-05 3.404E-01 1.407E-01
5.4M51-05 2.943E-01 I.0IZ-01 110.0 5.8231-OS 3.28ZE-01 1.114E-01 Table C. 16 PWR decay heat rates (W/kgU) of light elements, actinides, and fission products, for specific power - 40 kW/kgU, Set 1 Burnup a 25 'h1d/kgU ooling Burnup x 50 lHd/.kgU
_____________ ______ Tima, _ _ _ _ __ _ _ _ _ _
Light El Actinides FLl Perod years LIht El Actimides Fi: Prod
1.4851-01 3.419E-01 8.456E.00 1.0 1.607E-01 4.8001-01 9.4114E00
I.259 -01 Z.43SE-01 6.1451.00 1.4 1.374E-01 3.4201-01 6.92E1400
1.119g-01 1.754E-01 4.175E.00 1.0 .1.24-012.4591-4l 4.7611400
9.944E-02 1.4581-01 2.702E*10 Z.8 1.088]-01 t.0331-01 3.1291E00
8.428*-02 1.389E-01 1.630E4.00 4.0 9.225E-OZ 1.917E-01 1.9281.00
7.3651-02 1.406E-01 I.ZISE00 5.0 8.0611-02 3.9Z6E-01 1.4551*00
S. 41 -02 1.463E-01 8.646E-01 7.0 6.1751-02 1.977E-01 1.0451E00
3.7931-0Z 1.543E-01 6.8G6E-01 0.0 4.1521-02 2.0491-01 8.31SE-01
1.9631-02 1.6461-01 5.700E-01 31.0 2.1481-02 .2.140-01 6.859E-01
1.0191-02 1.721E-01 4.9601-01 0.0, 1.115E-02 2.2031-01 5.9601-01
5.304E-03 1.773E-01 4.367E-01 5.0o 5.805E-03 2.24Z-01 5.243E-01
2.776*-03 1.6081-01 3.859E-01 30.0 3.0381-03 2.2651-01 4.631E-01
7.6671-04 1.841E-01 3.030E-01 40.0 8.612E-04 2.2741-01 3.633E-01
2.50S5-04 1.84ZE-01 t.3871-01 50.0 2.7431-04 2.ZS3E-01 2.86Z-001
1.04Z1-04 1.8251-01 1. 88E-01 60.0 1.143E-04 2.M4161-01 .2*591-l
6.28e71-05 1.797E-01 1.489E-01 70.0 6.90Z1-05 2.2701-01 1.78SE-01
4.98SE-0S 1.764E-01 1.178E-01 80.0 S.4791-05 2.120E-01 1.41ZE-01
4.4591-05 1.7261-01 9.3201-02 90.0 4.905E-05 2.0701-01 1.117E-01
4.1SSE-OS 1.69Z1-01 7.376E-O 100.0 4.574E-05 Z.OZO-01 8.839E-02
3.9231-O5 1.456E-01 5.839E-02 110.0 4.32ZE-OS 1.97Z1-01 6.997E-02
3.54-25
Table C. 17 PWR decay heat rates (W/kgU) of light elements, actinides, and fission products, for specific power - 40 kW/kgU, Set 2 Btrnup = 35 t ld.kgU Cooling- Times Sunup a 40 WUCRlcgU
Light El Actinides Fixs Prod year: Light El Actinides Flu Prod
1.706E-01 6.341E-01 1.010E101 1.0 1.800E-01 7.998E-01 1.084E101
1.469E-03 4.S381-01 7.SOE.00 1.4 I.SS7E-1I 5.766E-01 8.1319#00
1.311E-01 3.277E-01 S.233E,00 2.0 1.393E-01 4.ZOIE-01 5.721E00
1:.1671-03 2.709E-01 3.4961*00 2.8 1.239E-01 3.4871-01 3.8731+00
9.891E-02 Z.S381-01 Z.Z011.00 4.0 1.0SIE-a 3.258E-01 2.4791400
8.644E-0Z 2.534E-01 1.6814E00 5.0 9.183E-02 3.2381-01 1.911E+00
6.6211-02 2.571E-01 1.zZ01.00 7.0 7.034E-0Z 3.Z571--03 1.397E100
4.45ZE-02 2.626E-01 9.7131-01 10.0 4.729E-02 3.Z87E-01-I.IIZE#00
2.304E-02 2.689E-01 7.990E-01 13.0 2.447E-02 3.3141-01 9.1251-01
1.195E-02 2.726E-03 6.9349-01 20.0 I.Z70E-02 3.318E-01 7.911E-01
6.2Z4E-03 2.743E-01 6.096E-03 25.0 6.612Z-03 3.306E-01 6.9511-01
3.Z$8E-03 2.74TE-0l 5.3821-01 30.0 3,4611-03 3.2811-01 6.136E-01
9.218E-04 Z.7171-01 4.220E-01 40.0 9.818E-04 3.Z071-01 4.8091-03
2.9461-04 2.665E-01 3.323E-01 50.0 3.134E-04 3.217E-01 3.786E-01
1.2301-04 2.601E-01 2.62*1-01 60.0 1.311E-04 3.022E-01 2.987E-01
7.449E-05 2.533E-03 2.07ZE-01 70.0 7.9601-OS 2.9271-01 2.360E-01
5.924E-05 2.464E-02 1.6391-03 80.0 6.3401-0S 2.8341-03 1.866E-01 S.310E-05 2.3941-01 1.2961-01 90.0 .68SE--05 2.746E-01 1.477E-01
4.956E-0S 2.331E-01 3.026E-01 100.0 S.313E-05 2.663E-01 1.169E-01
4.6361-os z.Z68E-01 8.1Zs1-02 110.0 3.0271-os Z.s58-01 9.249E-02 Table C. 18 PWR decay heat rates (W/kgU) of light elements, actinides, and fission products, for specific power - 40 kW/kgU, Set 3 BuRnup 2 45 fl*L/IgU CooJ0Lngr Time, burnup * 50 fl4/kgLU
Light E1 ActiniLdes el Prod years Light EL Actinzdes Fl* Prod
1.901E-01 9.994E-01 1.1399+01 1.0 2.001E-01 1.2061V,00
1.65ZE-01 7.266E-01 8.6ZZ1.00 1.0614OI
1.4 1.746E-01 6.8671-01 9.1931*00
1.480*-01 5.34S1-01 6.1381,00 2.0 1.651E-01 6.6121-01
1.3181-01 4.4601-01 4.209E#00 6.6001400
1.118E-01 z.8 1.394E-02 5.560E-01 4.57ZE100
4.157E-01 2.738st00 4.0 1.1821-01 5.184E-01 3.010E100
9.767E-02 4.1141-01 2.130E#00 3.0 1.033E-01 5.114E-01
7.482E-02 4.1021-01 2.367E100 Z.35SE100
7.0 7.9171-02 5.064E-01 1.7391400
3.030E-02 4.0921-01 1.Z46,Ot" 20.0 5.323:-02 5.003E-01
2.6031-02 4.0591-02 1.02.OVO 1.38ZE100
135.0 Z.7341-02 4.8961-01 3.1281400
1.3SIE-02 4.01CI-01 8.8351-01 20.0 1.4291-02 4.7831-01
7.034E-03 3.9511-01 7.75;E-01 9.7611-01
23.0 7.443E-03 4.6681-03 8.5681-01
3.682E-03 3.886E-01 6.8W6r-02 30.0 3.897E-03 4.5549-01
1.045E-03 3.7461-01 5.3631-01 7.5S7E-01
40.0 1.107E-03 44334E-01 5.918E-01
3.34SE-04 3.604E-01 4.ZZE-01 50.0 3.549E-04 4.130E-01
1.406E-04 3.466E-01-3.3301-01 4.657E-01
60.0 1.4971-04 3.9431-01 3.673E-03
8.S74E-05 3.336E-03 2.6311-01 70.0 9.166E-0S 3.773E-01
6.84SE-OS 3.ZIS1-02 2.0801-01 2.90ZE-01
80.0 7.336E-OS 3.6201-01 2.29SE-01
6.151E-OS 3.1031-01 1.6461-01 90.0 6.5961-oS 3.4801-03 S.749E-OS 2.9981-01 1.302E-01 1.81M1-01
100.0 6.161G-0S 3.351E-01 1.437E-01 S.44ZE-OS 2.90Z1-03 1.0311-01 110.0 3.841Z-03 3.234E-01 1.1371-01
3.54-26
Value /Impact Statement A Value/Impact Statement was published with Regulatory Guide 3.54 when it was issued in September 1994.
No changes are necessary, so a separate value/impact statement for this proposed Revision 1 has not been prepared.
A copy of the value/impact statement is available for inspection or copying for a fee in the Commission's Public Document Room at 2120 L Street NW., Washington, DC, under Regulatory Guide 3.54. The PDR's mailing address is the Mail Stop LL-6, Washington, DC 20555; telephone (202) 634-3273; fax (202) 634-3343.
K-I
3.54-27
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