ML20209E770
| ML20209E770 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 06/14/1999 |
| From: | Johnson W COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20209E743 | List: |
| References | |
| 22S-B-110X-0068, 22S-B-110X-0068-R00, 22S-B-110X-68, 22S-B-110X-68-R, NUDOCS 9907150147 | |
| Download: ML20209E770 (26) | |
Text
Attachment 3 Calculation Number 22S-B-110X-0068 Determination of the Heat Load for Assemblies F50D and Z33A June 14,1999 77S7*idelPs87 des i F PDR QQ071 Sol'O
CALCULATION TITLE PAGE Calculation No.: 22S-B-110X-0068 DESCRIPTION CODE: N00 DISCIPLINE CODE: N Z :.ON NUCLEAR STATION SYSTEM CODE: SF TITLE: Determination of the Ileat Load for Assemblies F50D and Z33A
@ Safety Related O Augmented Quality 0 Non-Safety Related IEFERENCE NUMBERS Type Number Type Number PROG ORIGEN2.1 AEDV NPNT&R PROJ 10436-003
' COMPONENT EPN: DOCUMENT NUMBERS:
EPN Compt Type Doc Type /Sub Type Document Number REMARKS:
REY. REVISING A PPROVED NO. ' ORGANIZATION DATE PRJNT/yIGN ,,
O S&L W.J. Johnson / [j/ f-119g I
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l CALCULATION NO. 22S-B-110X. 068 PAGE NO.: 2 l
REVISION SUMMARIES l REV: 0 REVISION
SUMMARY
OriginalIssue. Affected Pages: 1 to 12, A1 to A7, Bl to B1, and Cl to C5 ELECTRONIC CALCULATION DATA FILES:
l (Program Name, Version, File name ext / size /date/ hour /: min)
ORIGEN2.1 F50D.OUT / 653949 / 6/4/99 /16 / :47, ORIGEN2.1 Z33 A.OUT / 629783 / 6/4/99 /16 / :48 Prepared by: D.L. Marsh }k d/ IN1 Print / Sign Date Reviewed by: A.G. Klazura / O. [ % [- /4/'- f f Print / Sign # Date Type of Review
@ Detailed Alternate O Test Supplemental Revies Required YES (NEP-12-05 documentation attached) [R156 Supervisor Md/ //
UU AN Y AbbUMI'llVNb IN 1111b LALLULA iIUN KLQUIRL LA1LK V LKitILA ilVN U Y L5 @ NO Tracked by:
REV:
REVISION
SUMMARY
ELECTRONIC cal,CULATION DATA FILES:
(Program Name, Version, File name ext / size /date/ hour /: min)
Prepared by: ,
Print / Sign Date l l
Reviewed by:
Print / Sign Date Type of Review Detailed Alternate O Test YES (NEP-12-05 documentation attached)
NO Supplemental Review Required Supervisor l UU ANY AbbUMi'llVNb AN 1111b LALLULAllVN KLQUlKt LAILK V LKitiLAllVN U Y bb O NO Tracked by:
The reviewer's signature indicates compliance with S&L procedure SOP-0402 and the ve $$ication of, a following items: correctness of math for manually prepared calculations, appropriateness ofinput data, appropriatene assumptions, and appropriateness of the calculation method.
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COMMONWEALTil EDISON COMPANY l
l . CALCULATION TABLE OF CONTENTS PROJECT # 10436-003 CALCULATION NO. 22S-B-110X-0068 REV.NO.O PAGE NO. 3 l SUB-PAGE NO.
! SECTION PAGE NO.
Calculation Title Page 1 Revision Summaries 2 l
Calculation Table of Contents 3 i
1.0 Purpose / Objective 4 l
2.0 Methodology and Acceptance Criteria 4 3.0 Assumptions / Engineering Judgement 5 4.0 Designinputs 5 i
4.1 Unit I and Unit 2 Cycle Characteristics 5 l
4.2 Unit 1 and Unit 2 Fuel Assembly Characteristics 5 7
5.0 Refereners 7
l 6.0 Calculations 7.0 Summary and Conclusions 11
! Attachments A. ORIGEN2.1 Input Al to A7 l
l B. ORIGEN2.1 Output (Microfiche) Blto B1 C. NDITNFM9900121 C1 to C5 l
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COMMONWEALTil EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 4 1.0 Purpose / Objective The purpose of 6is calculation is to determine the hottest spent fuel assembly in terms of thermal output and the resulting heat load from the hottest spent fuel assembly in the spent fuel pool. This is accomplished by using Zion specific fuel assembly information as input to the computer code, ORIGEN2.1 (Reference 5.1). The two fuel assemblies chosen out of the nine fuel assemblies considered for this calculation are F50D and Z33A. These fuel assemblies were chosen based on the fact that they have the highest total bumup and shortest cooling period.
2.0 Methodology and Acceptance Criteria The computer code ORIGEN2.1 is used to calculate the heat load in units of Watts /MTU for the hottest spent fuel assembly in the spent fuel pool. Based upon a review of the nine fuel assembly characteristics presented in Tables 1,2, and 3, the fuel assemblies chosen for this calculation are F50D and Z33A because these assemblies have the highest total burnup and shortest cooling time which results in the highest heat loads. The highest total burnup is used instead of the highest burnup in the final cycle because the long lived nuclides and daughters contribute most to the heat load and the inventories associated with these long lived nuclides and daughters are directly pportional to the total burnup. ORIGEN2.1 has been qualified under Sargent & Lundy's QA procedure and therefore validation of this code is not required in this calculation.
In ORIGEN2.1, the PWRUE model is used to represent the Zion fuel cycle. The cross section libraries used by ORIGEN2.1 are PWRUE. LIB for neutrons and GXUO2BRM. LIB for photons.
PWRUE is an ORIGEN2.1 reactor model designed to use 4.2 wt. % U-235 fuel in a wholly uranium-enriched three cycle PWR to achieve an extended burnup of 50,000 MWD /MTlHM, which is the closest model ORIGEN2.1 has in comparison with the Zion fuel assembly characteristics.
(Reference 5.3, Page xiii) There are two ORIGEN runs used in this calculation which represent fuel assemblies F50D and Z33A. This is done because before the runs were made it was uncertain as to wh.ich fuel assembly would have the highest heat load. The cycle numbers used for fuel assembly F50D are Z1Cl3, ZlC14, and ZlCl S. The characteristics of these cycles are listed in Table 1 and
- 2. Each cycle was further broken down into 10 burnup intervals with the same average power in ORIGEN2.1. The cycle numbers used for fuel assembly Z33A are Z2Cl2, Z2Cl3, and Z2C14.
The characteristics of these cycles are also listed in Tables 1 and 2. Each cycle was further broken down into 10 burnup intervals with the same average power in ORIGEN2.1.
There is not an acceptance criteria for this calculation because the purpose of the calculation is only to determine the hottest fuel assembly in the spent fuel pool and the resulting heat load from the hottest fuel assembly.
l REVISION NO. O L
COMMONWEALTil EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 5 3.0 Assumptions / Engineering Judgments 3.1 The activation products resulting from the irradiation of the fuel assembly hardware have a negligible contribution to the heat load. Thus, only the actinides and daughters and the fission products resulting from the irradiation of the uranium fuel are considered in the calculation of the heat load from the hottest fuel assembly.
4.0 Design Inputs 4.1 Unit 1 and Unit 2 Cycle Characteristics The cycle characteristic for fuel assemblies from Unit I and Unit 2 are listed in Tables 1 and 2.
The cycle characteristics presented in Tables 1 and 2 were obtained from Reference 5.2. The fuel assemblies from Unit I are F10C, F14C, F48C, F50D, and F70D. The fuel assemblies from Unit 2 are Z10A, Zl7A, Z24A, and Z33A. The length and shutdown date for each cycle are listed in Table 1. The bumup and region for all nine of these fuel assemblies for each cycle are listed in Table 2.
4.2 Unit 1 and Unit 2 Fuel Assembly Characteristics The fuel assembly characteristics from Unit I and Unit 2 are listed in Table 3. The fuel assembly characteristics presented in Table 3 were obtained from Reference 5.2. These characteristics include the region, the amount of metric tons of uranium per assembly, the enrichment of U-235, and the compositions (units of kg/MTU) for U-234, U-235, U-236, and U-238.
REVISION NO. O
I COMMONWEALTII EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 6 Table 1. Length and Shutdown Date for each Cycle 3 Cycle No. Length, days Shutdown Date Z1C13 434 10/2I/93 Z1C14 527 09/09/95 Z1C15 432 02/21/97 Z2C12 823 11/30/92 Z2C13 683 01/06/95 Z2C14 519 09/19/96 j Table 2. Region and Burnup for Fuel Assemblies per Cycle j l
Unit 1 Total Burnup (MWD /MTU)
Assembly ID Region ZlCl3 ZlC14 ZlC15 F10C 15B 14545 23501 36762 i 24137 37272 l F14C 15B 15190 F48C 15B 18424 24412 36254 F50D 15A 18448 35020 46894 F70D 15A 15228 30583 43388 Unit 2 Total Burnup (MWD /MTU) (
Assembly ID Region Z2C12 Z2C13 Z2Cl4 l Z10A 14A 13377 25203 43138 Zl7A 14A 13308 24873 42868 Z24A 14A 13374 25129 43017 14A 22559 31069 47734 Z33A Table 3. Unit 1 and Unit 2 Fuel Assembly Characteristics Region 15A 15B 14A MTU/ Assembly 0.460 0.460 0.462 3.604 3.200 3.618 Enrichment (w/o)
Composition (kg/MTU)
U-234: 0.314 0.272 0.305 U-235: 36.041 32.000 36.179 U-236: 0.038 0.041 0.050 U-238: 963.61 967.69 963.466 I
! REVISION NO. O l
F COMMONWEALTH EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 7 5.0 References 5.1 ORIGEN2.1," Isotope Generation and Depletion Code," S&L Program Number 03.7.533-2.1, Revision 0.
l 5.2 NDIT No. NFM9900121, " Zion Spent Fuel Pool Data," Seq. No. O. (Information supported by )
Calc. No. 22N-0-110M-0058 and nuclear design report NFSR-0097) 5.3 ORNL/TM-11018," Standard- and Extended-Burnup PWR and BWR Reactor Models for the i ORIGEN2 Computer Code," December,1989, Prepared by Oak Ridge National Laboratory for the US Department of Energy, Office of Civilian Radioactive Waste Management.
5.4 Baumeister, et. al.," Mark's Standard Handbook for Mechanical Engineers," Eighth Edition.
l 6.0 Calculations As stated in the Methodology and Acceptance Criteria section of this calculation, only fuel assemblies F50D and Z33A are considered because these fuel assemblies have the highest burnup and the shortest cooling period. Table 1 lists the number of days in each cycle as well as the shutdown date for each cycle. With this information, the beginning date for each cycle is calculated by subtracting the number of days in each cycle from the shutdown date. As an example, the beginning date for cycle ZlCl3 is calculated in Equation 6-1. The beginning dates for each cycle are listed in Table 4.
BOCncu = 10/21/93 - 434 days = 08/13/92 6-1 With the beginning and ending date for each cycle known, the number of days in the cooling period between the cycles is calculated by subtracting the end of cycle date of the previous cycle from the beginning of cycle date for the current cycle. As an example, the number of days in the cooling period between cycles ZlCl3 and ZlC14 is calculated in Equation 6-2. The number of days between the rest of the cycles are listed in Table 4. (Note: In Table 4, cycle Z1R13 is the cooling cycle between cycles Z1Cl3 and ZlCl4, etc.)
7.1R13 = 03/31/94 - 10/21/93 = 161 days 6-2 Table 2 lise the cumulative bumup for each cycle. The burnup per cycle is calculated by subtracting the cumulative burnup of the previous cycle from the cumulative burnup of the current cycle. As an example the burnup for fuel assembly F50D from cycle ZlC14 is calculated in Equation 6-3. The burnup per cycle for all of the cycles is listed in Table 5.
6-3 BurnuPacu = 35020 MWD /MTU - 18448 M~WD/MTU = 16572 MWD /MTU I
l REVISION NO. O
1 COMMONWEALTil EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 8 Once the burnup per cycle for each cycle is calculated, the specific power averaged over each cycle is calculated by dividing the burnup per cycle by the number of days in the cycle. As an example the specific power for fuel assembly F50D from cycle ZlCl3 is calculated in Equation 6-4. The specific power for the rest of the cycles for both fuel assemblies F50D and Z33A is listed in Table 5.
S.P.tsoornou zici3 = 18448 MWD /MTU / 434 Days = 42.50691 MW/MTU 6-4 The heat loads for both fuel assemblies F50D and Z33A are calculated for the following dates:
- 1) 02/28/97 l i
- 2) 12/31/97
- 3) 12/31/98
- 4) 04/30/99 l
- 5) 06/30/99 l
- 6) 09/30/99
- 7) 11/30/99
- 8) 12/31/99
- 9) 04/30/00 The final shutdown dates for F50D and Z33A are 02/21/97 and 09/19/96, respectively. The number of days from the fmal shutdown date to the first heat load calculation date (02/28/97) for F50D and Z33A are calculated in Equations 6-5 and 6-6, respectively.
C.P. r5on = 02/28/97 - 02/21/97 = 7 days 6-5 C.P. z333 = 02/28/97 - 09/19/96 = 162 days 6-6 The number of days between each heat load calculation date and 02/28/97 are calculated in Equations 6-7 through 6-14.
D.P. i = 12/31/97 - 02/28/97 = 306 days 6-7 D.P.2 = 12/31/98 - 02/28/97 = 671 days 6-8 D.P.3 = 04/30/99 - 02/28/97 = 791 days 6-9 D.P., = 06/30/99 - 02/28/97 = 852 days 6-10 D.P.3 = 09/30/99 - 02/28/97 = 944 days 6-11 D.P.6 = 11/30/99 - 02/28/97 = 1005 days 6-12 REVISION NO. O
COMMONWEALTH EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 9 D.P., = 12/31/99 - 02/28/97 = 1036 days 6-13 D.P., = 04/30/00 - 02/28/97 = 1157 days 6-14 The ORIGEN2.1 output units are Watts /MTU. The conversion factors which are applied t the output of ORIGEN2.1 to convert the units from Watts /MTU to Btu /Ilr./ Assembly are as follows:
1 Watt = 1 J/s (Reference 5.4, Pg.1-33) .
1 J = 9.47817E-04 Btu (Reference 5.4, Pg.1-34) 3600 second = 1 Hour 0.460 MTU/ Assembly for F50D 0.462 MTU/ Assembly for Z33A As an example, for fuel assembly F50D on 02/28/99, the total heat load (sum of Actinides and Daughters and Fission Products) from the output of ORIGEN2.1 is 8.230E+04 Watts /MTU. This is
' converted to Btu /hr/ Assembly in Equation 6.'l-15.
8.230E + 04 Watts ,1,.,. sec.) , 9.47817E - 04 Btu ,3600sec. ,0.460 MTU =1.292E + 05 Btu /hr/ Ass.
MTU 1 Watt 1J 1hr. Assembly l
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I REVISION NO. O
l COMMONWEALTil EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 10 Table 4. Beginning and End of Cycle Dates for each Cycle Cycle No. Days Beginning of Cycle End of Cycle l Z1C13 434 08/l3/92 10/21/93 Z1R13 161 10/21/93 03/31/94 l Z1Cl4 527 03/31/94 09/09/95 ZlR14 99 09/09/95 12/17/95 ZlC15 432 12/17/95 02/21/97 Z2C12 823 08/30/90 11/30/92 ,
Z2R12 84 11/30/92 02/22/93
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Z2Cl3 683 02/22/93 01/06/95 i I
Z2R13 103 01/06/95 04/19/95 Z2C14 519 04/19/95 09/19/96 1
Table 5. Burnup and Specific Power for each Cycle I
F50D Cumulative Burnup, Cycle Burnup, Specific Power, Cycle MWD /MTU MWD /MTU MW/MTU Z1Cl3 18448 18448 42.50691 l Z1Cl4 35020 16572 31.44592 (
I Z1C15 46894 11874 27.48611 _
Z33A I
Cumulative Bumup, Cycle Burnup, Specific Power, Cycle MWD /MTU MWD /MTU MW/MTU Z2Cl2 22559 22559 27.41069 31069 8510 12.45974 Z2C13 47734 16665 32.10983 Z2C14 f
REVISION NO. O
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> COMMONWEALTH EDISON COMPANY CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. 11 7.0 Summary and Conclusions The results of the 1. cat load for fuel assemblies F50D and Z33A are presented in Tables 6 and 7, respectively. The heat load from the actinides and daughters and the fission products resulting from
- the irradiation of the uranium fuel are summed to yield a total heat load for each of the decay dates L listed. Based on these results, the hottest fuel assembly in terms of thermal output is F50D The calculated heat loads from fuel assembly F50D on 06/30/99 and 09/30/99 are 8.561E+03 Btu /hr and 7.748E+03 Btu /hr, respectively.
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REVISION NO. O t
COMMONWEALTH EDISON COMPANY PROJECT NO. 10436-003 PAGE NO. 12 FINAL j CALCULATION NO. 22S-B-110X-0068 Table 6. Heat Load for Fuel Assembly F50D Actinides and D'aughters, Fission Products, Total, Watts Total, Decay Dates Watts per Assembly Watts per Assembly per Assembly Btu /hr./Assm.
1.083E+04 7.147E+04 8.230E+04 1.292E+05 02/28/97 1.632E+03 1.101E+04 1.264E+04 1.984E+04 12/31/97 8.302E+02 5.989E+03 6.819E+03 1.070E+04 12/31/98 7.429E+02 5.113E+03 5.856E+03 9.191E+03 04/30/99 7.126E+02 4.742E+03 5.455E+03 8.561E+03 06/30/99 6.792E+02 4.257E+03 4.936E+03 7.748E+03 09/30/99 6.631E+02 3.979E+03 4.642E+03 7.286E+03 11/30/99 6.562E+02 3.849E+03 4.505E+03 7.071E+03 12/31/99 6.363E+02 3.405E+03 4.041 E+03 6.343E+03 04/30/00 Table 7. Heat Load for Fuel Assembly Z33A Actinides and Daughters, Fission Products, Total, Watts Total, Decay Dates Watts per Assembly Watts per Assembly per Assembly Btu /hr./Assm.
3.182E+03 1,793E+04 2.111E+04 3.328E+04 02/28/97 8.357E+03 9.711E+03 1.531E+04 12/31/97 1.354E+03 8.097E+02 4.969E+03 5.779E+03 9.110E+03 12/31/98 7.498E+02 4.310E+03 5.060E+03 7.976E+03 04/30/99 _
7.289E+02 4.027E+03 4.756E+03 7.497E+03 06/30/99 7.056E402 3.656E+03 4.362E+03 6.876E+03 09/30/99 6.942E+02 3.441E+03 4.135E+03 6.519E+03 11/30/99 6.893E+02 3.341E+03 4.030E+03 6.353E+03 12/31/99 6.749E+02 2.996E+03 3.671E+03 5.787E+03 04/30/00 l
REVISION NO. O
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COMMONWEALTil EDISON COMPANY PROJECT NO. 10436-003 PAGE NO. A1 CALCULATION NO. 22S-B-110X-0068 Attachment A. ORIGEN2.1 Input l
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There were two ORIGEN2.1 cases used in this calculation. The purpose of these two cases was to
- 1) determine the hottest fuel assembly based on thermal output and 2) determine the heat load of the I hottest fuel assembly. The two fuel assemblies considered in this calculation were chosen to be F50D and Z33A based on the fact that these two assemblies have the highest burnup and the shortest cooling period. The ORIGEN2.1 input decks for both cases are listed below.
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REVISION NO. 0 1
FL L j s COMMONWEALTH EDISON COMPANY CALCULATION No. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. A2 F50D.INP I
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-1 RDA . CALC NO. 22S-B-110X-0068, REV. O, DETERMINATION OF THE HEAT LOAD FOR ASSEMBLIES F50D AND 233A' RDA Use default fractional Tecovery values as given by first three records.
1 RDA RDA Provide a title for the Core I calculations.
RDA- '
TIT Eion Unit 1 Decay' Heat Calculation for SFP assembly F500 RDA i RDA' -Storage vector -1 = One metric tonne initial heavy metal. From 21C13 RDA- region 15A data, average initial enrichment 3.604 RDA w/o U-235. Average fuel load is 0.460 MTU per RDA assembly RDA RDA Assembly F500 total cycle assembly RDA burnup burnup power RDA days MWD /MTU MWD /MTU MW/MTU RDA' E1C13 '434 18448 18448 42.50691
.RDA 21R13 161 0 0 0.00 RDA 21C14 527 35020 16572 31.44592 RDA 21R14 .99 0 0 0.00
-RDA 21C15 432 46894 11874 27.48611 RDA shutdown 1012 0 0 0.00. (thru 11/30/99)
RDA RDA RDA Read data library for U-235 enriched uranium oxide PWR fuel. Use PWR RDA extended, updated libraries. Input data on unit 9,
! RDA. . .
! LIB 0 1'2 3 . 604 605 606 9 0 0 1 39 RDA t RDA Read no bremstraalung photon library. Put data on unit 10.
! RDA PHO 101 102 103 10 RDA-RDA. Read in the composition for fresh 3.604 w/o fuel.
RDA INP -1 1 4*0 RDA Print out power tables for actinides and fission products. j RDA J
! RDA OPTF 8*8 7 19*8 OPTA 4*8 .7 3*8 7 19*8 l OPTL 28*8 RDA j
'RDA Provide unit basis information card.
RDA I BAS Eion Unit 1 Cycle 13, Burnup to 18.448 GWD/HTU RDA RDA Move fuel composition to output vector 1 and burn fuel.
RDA-MOV -1 1 0 1.0-RDA ,
RDA Burnup Cycle 21C13 / 21R13 RDA BUP IRP 43.4- '42.50691 1 2 4 2
! IRP- 86.8 42.50691 2 3 4 0 i IRP 130.2 42.50691 3 4 4.0 j
IRP 173.6 42.50691 4 5 4 0
'IRP 217.0 42.50691 5. 6 4 0 l IRP 260.4 42.50691 6 7 4 0 i .IRP 303.8 42.50691 7 8 4 0 l IRP- 347.2 42.50691 8 9 4 0
. IRP 390.6 42.50691 9 10 4 0 IRP 434.0 42.50691 10 11 4 0 ,
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.DEC 595.0 -11 12 4 0 BUP RDA RDA Print out tables.
REVISION NO. O L
l COMMONWEALTH EDISON COMPANY i CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. A3 RDA HED 1 *BOC Z1C13 l HED 11 *EOC Z1C13 HED 12 *Z1R13 OUT 12 1 0 0 RDA RDA Provide unit basis information card.
RDA l BAS Zion Unit 1 Cycle 14, Burnup to 35.020 GWD/MTU J RDA RDA Move fuel composition to output vector 1 and burn fuel.
RDA MOV 12 1 0 1.0 RDA RDA Burnup Cycle Z1C14 / Z1R14 RDA BUP IRP 52.7 31.44592 1 2 4 2 IRP 105.4 31.44592 2 3 4 0 IRP 158.1 31.44592 3 4 4 0 IRP 210.8 31.44592 4 5 4 0 IRP 263.5 31.44592 5 6 4 0 IRP 316.2 31.44592 6 7 4 0 IRP 368.9 31.44592 7 8 4 0 IRP 421.6 31.44592 8 9 4 0 IRP 474.3 31.44592 9 10 4 0 IRP 527.0 31.44592 10 11 4 0 CEC 626.0 11 12 4 0 BUP RDA RDA Print out tables.
RDA HED 1 *BOC Z1C14 HED 11 *EOC 21C14
'HED 12 *Z1R14 OUT 12 1 0 0 RDA RDA Provide unit basis information card.
RDA BAS Zion Unit 1 Cycle 15, Burnup to 46.894 GWD/MTU RDA RDA Move fuel composition to output vector 1 and burn fuel.
RDA MOV 12 1 0 1.0 RDA RDA Burnup Cycle Z1C15 / shutdown RDA BUP IRP 43.2 27.48611 1 2 4 2 IRP 86.4 27.48611 2 3 4 0 IRP 129.6 27.48611 3 4 4 0 IRP 172.8 27.48611 4 5 4 0 IRP 216.0 27.48611 5 6 4 0 IRP 259.2 27.48611 6 7 4 0 IRP 302.4 27.48611 7 8 4 0 IRP 345.6 27.48611 8 9 4 0 IRP 388.8 27.48611 9 10 4 0 IRP 432.0 27.48611 10 11 4 0 DEC 439.0 11 12 4 0 BUP RDA RDA Print out tables.
RDA HED 1 *BOC 21C15 HED 11 *EOC 21C15 HED 12 *2/28/97 OUT 12 1 0 0 l PIA l
RDA Provide unit basis information card.
RDA BAS Zion Unit 1 shutdown date - 2/21/97 .
RDA RDA Move fuel composition to output vector 1 and burn fuel.
I i REVISION NO. 0 l
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COMMONWEALTil EDISON COMPANY !
PROJECT NO. 10436-003 PAGE NO. A4 CALCULATION NO. 22S-B-110X-0068 RDA MOV 12 1 0 1.0 RDA RDA Desey after shutdown RDA BUP DEC 306.0 1 2 4 2 DEC 671.0 2 3 4 0 DEC 791.0 3 4 4 0 DEC 852.0 4 5 4 0 DEC 944.0 5 6 4 0 DEC 1005.0 6 7 4 0 DEC 1036.0 7 8 4 0 DEC 1157.0 8 9 4 0 BUP i RDA I RDA Print out tables.
RDA HED 1 *2/28/97 HED 2 *12/31/97 HED 3 *12/31/98 HED 4 *4/30/99 HED 5 *6/30/99 HED 6 '9/30/99 HED 7 *11/30/99 HED 8 *12/31/99 HED 9 *4/30/00 OUT 9 1 0 0 END 2 922340 314.0 922350 36041.0 922360 38.0 922300 963610.0 0 0.0 0
l REVISION NO. O
COMMONWEALTH EDISON COMPANY t
CALCULATION NO. 22S-B-110X-0068 PROJECT NO. 10436 003 PAGE NO. A5 l .
Z33A.INP 7
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-1 l RDA, CALC No. 22S-B-110X-0068, REV. 0, . DETERMINATION OF THE HEAT LOAD FOR ASSEMBLIES F50D AND Z33A RDA Use default fractional recovery values as given by first three records.
RDA RDA Provide a title for the Core I calculations.
RDA TIT Zion Unit 2 Decay Heat Calculation for SFP assembly 233A RDA .
RDA Storage sector -1 = One metric tonne initial heavy metal. From Z2C12 RDA region 14A data, average initial enrichment 3.618 RDA w/o U-235. Pverage fuel load is 0.462 MTU per RDA assembly RDA RDA Assembly 233A total cycle assembly RDA burnup burnup power RDA days MWD /MTU ~ MWD /MTU MW/MTU ,
22559 -27.41069- l RDA 22C12 823 22559 i RDA Z2R12 84 0 0 0.00 RDA. 22C13 -683 31069 8510 12.45974 RDA Z2R13 103 0' O 0.00 RDA 22C14 519 47734- 16665 32.10983 RDA shutdown 1167 0 'O 0.00 (thru 11/30/99)
RDA RDA. .
RDA Read data library for U-235 enriched uranium oxide PWR fuel. Use PWR RDA extended, updated libraries. Input data on unit.9.
RDA . .
LIB- -0 1 2 3 604 605- 606 9 0 0 1 39 .
RDA .
1 RDA~ Read no bremstraalung photon library. Put data on unit 10.
RDA PHO 101 102 103 10 RDA- .
RDA.- Read in the composition for fresh 3.618 w/o fuel.
~RDA INP ' -1 1 4*0.
RDA RDA Print out power tables for actinides and fission products.
RDA OPTF B'8 7 19*8 OPTA- 4*8 7 3*8 7 19*8 OPTL- 28*8 RDA RDA Provide unit basis information card.
RDA BAS Zion Unit 2 Cycle 12, Burnup to 22.559 GWD/MTU RDA RDA Move fuel composition to output vector 1 and burn fuel.
RDA 0.462 MTU/ ASSEMBLY IN REGION 14A RDA MOV _ -1 1 0 1.0-RDA RDA Burnup Cycle 22C12 / 22R12 RDA BUP IRP 82.3 27.41069 1 2 4 2 IRP 164.6 27.41069 2 3 4 0 IRP 246.9 27.41069 3 4 4 0 IRP 329.2 27.41069 4 5 4 0 IRP 411.5 27.41069 5 6 4 0
- 1RP 493.8 27,41069 6 7 4 0 IRP 576.1 27.41069 7 8 4 0
. I RP 058.4 27.41069- 8 9 4 0
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CALCULATION NO. 22S-B-110X-0068 PROJECT NO.10436-003 PAGE NO. A6 RDh - Print cut taoles.
-RDA-i -i HED 1 *BOC F2C12 ii HED _11. *EOC 22C12 HED 12 - *E2R12 OUT 12 1-0 0
-RDA-l"
.RDA Provide unit basis information card.
'RDA BAS Zion Unit 2 Cycle 13, Burnup to 31.069 GWD/MTU RDA j.
RDA1 . Move fuel composition to output vector 1 and burn fuel.
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- RDA
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MOV 12 .1' 0 ..1.0 RDA -
RDA' Burnup Cycle 22C13 /'22R13 RDA BUP IRP 68.3 ' 12.45974 1 2 4 2 IRP -136.6 12.45974 2 3 4 0-IRP 204.9 12.45974 3' 4 4 0.
IRP ! 273.2 12.45974 4 5 4 IRP, 341.5 .12.45924 5 6.4 0 IRP 409.8 12.45974 6 7L4 0 IRP 478.1 12.45974 7 8 4 0 IRP 546.4 12.45974 8 9 4. O r;IRP 614.7 12.45974 9 10 -4 0 IRP 683.0. 12.45974 10 11 40.
- f. ,786.0 11 12' 4 0 DEC BUP RDA- 7/
RDA Print out tables. '
RDA HED 1 *BOC 22C13 HED 11 *EOC E2C13
~HED 12
- E2 R13 OUT- 12 1 0 0.
. RDA .
RDA'. Provide unit basis information card.
RDA
' BAS Elon Unit 2 Cycle 14, Burnup to 47.734 GWD/HTU HDA RDA Move fuel composition to output vector 1.and burn fuel.
RDA:
MOV- 12 1 0 1.0
! RDA' RDA ..Burnop Cycle 12C14 /. shutdown RDA-
.BUP IRP - 51.9 32.10983 1 2.4.2 IRP .103.8 32.10983 2 3 4'O IRP- -155.7 32.10983 3- 4 4 0 IRP 207.6 32.10983 4 -5 4 0 IRP 259.5 32.10903 5 6 4 0 IRP :311.4 32.10983 6 7. 4. O IRP -363.3 32.10983. 7 8 4 0-
-IRP' 415.2 32.10983 8 9 4 0 IRP 467.1 32.10983 10 4 0 IRP 519.0 32.10983 10 11 -4 0 DEC 681.0 11 12 4 O BUP RDA
+- RDA. Print out tables. '
l . RDA-HED 1 *BOC E2C14 HED 11 *EOC 22C14
.'HED 12 '*2/28/97-OUT 12 10 0 RDA RDA ' Provide unit basis information card. j RDA j
BAS Zion Unit 2 shutdown date - 9/19/96 RDA1 1 1
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, COMMONWEALTH EDISON COMPANY CALCULATION NO. . 22S-B-110X-0%8 PROJECT NO.10436-003 PAGENO. A7 FINAL RDA . Move fuel composition to output vector 1 and burn fuel.
-^ RDA MOV- .12.1'O 1.0
-RDA RDA- Deacy after shutdown-
'RDA
.BUP ;
DEC 306.0' 1 '2.4-2
'DEC 671.0 2 3 ~' 4 0 DEC' 791.0 3 '4 '4 0 DEC 852.0- '4. 5 4 0-DEC- ' 944,0' 5 '6 4'O DEC :1005.0 6 7'4 0 DEC 1036.0 .71 '8 4 0 i DEC 1157.0 8! 9 4 0 i.
.BUP.
RDA BDA Print out tables.
,-' i RDA l' '
HED l '.
- 2/28/9'?
-I 'HED. 2 *12/31/97 _
, 'HED 3 '*12/31/98
^-
HED~ 4 *4/30/99 HED 5 *6/30/99 HED 6 *9/30/99' HED :7 *11/30/99-HED 8 *12/31/99 HED ' 9 *4/30/00 OUT 9-1 0 0 END 2 '922340' 305.0 922350 36179.0 922360 50.0 922380 '963466.0 0 0.0 0
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COMMONWEALTil EDISON COMPANY ,
CAL.CULATION NO. 22S-B-110X-0068 PROJECT NO. 10436-003 PAGE NO. B1 FINAL i Attachment B. ORIGEN2.1 Output (Microfiche)
This attachment contains the microfiche for the two ORIGEN2.1 cases. The microfiche labels for ,
both cases are as follows: !
l F50D.OUT l
l 22S-B-110X-0068 REV.0,ORIGEN2.103.7.533-2.1,F50D.OUT Z33A.OUT
)
22S-B-110X-0068 REV,0,ORIGEN2.103.7.533-2.1,Z33A.OUT ORIGEN21 Version 2.1 - Sargent & Lundy Program No. 03.7.533-2.1 User OLO647 on PC5614 Friday, June 4, 1999 Time: 13:26:11 Controlled Files:
Drive V: = SNLl\SYS3: \
Detailed list of controlled files omitted at user request.
End of Controlled File Information scope y
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g ,. ( j REVISION NO. O
l COMMONWEALTH EDISON COMPANY
! l CALCULATION NO. 22S-b-110X-0068 PROJECT NO. 10436-003 PAGE NO. Cl l
Attachment C. NDIT NFM9900121 This attachment contains NDIT NFM9900121 entitled " Zion Spent l'uel Pool Data." This NDIT l contains the information about the fuel cycles as well as the fuel assemblies from both Unit 1 and f l Unit 2 which are used in this calculation.
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4 REVISION NO. O i l
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, NUCLEAR FUEL MANAGEMENT DEPARTMENT NUCLEAR DESIGN INFORMATION TRANSMITTAL l @ SAFI FY RELATED Originating Organization NDIT No. NFM9900121
! O NON-SAFETY RELATED S NuclearFuelManagement Seq. No. -0 0 REGULATORYRELATED 0 other(specify) Page 1 of 4 1
Station Zion Unit N/A Cycle N/A Gencric To: Bob Peterson(S&L)
Subject Zion Spent Fuct Pool Data Jeffrey A.Dunlap ( N '
4 Preparcr P tu Date Annie W. Wong b [( k Reviewer Date I l Rcvicyslignaturey Haksoo Kim 9$
NF61 Group Lead NFM Group Lead's Bijnaturc Date [
Status oIInformation: @ wrified i O Unveriried I @ EngineeringJudgenunt blethod and Schedule of Verification for Unverified NDITs:
Description ofInibrmstlan: The attached data includes the initial composition and bumup data for fuel loaded in Zion Unit ! Cycle 13 and Zion Unli 2 Cycle 12. Fuct loaded during these cycles will have the highest bumup (thrice burns assemblies), and were most recendy removed t'mm the core (after ZlCIS and 22Cl4). ne assemblies included in this trarsmittal are those that arc expected to have the highest decay heat.
l and arc sclected based on highest total bumup and highest bumup during the most recent cycle (ZlC15 and Z2Cl4). Based on unverified sensitivity studies, it was determined that Unit I assembly F50D was the most limiting assembly for maximum decay heat generation.
Additional miscellencous Zion fuel building and spent fuel assembly data is provided in the NDIT l
Puriwe ofinformation Use in the calculation of the Zion peak assembly dceny heat in the spent fuct pool and the calculation of maximum cladding temperature for an smcovered spent fuel pool, l
l j Source ofInfonnation As described on annched slwols.
1 Supplemental Distribution: Mr.rk llandrick (S&L). WJ. Johnson (S&L), Don Marsh (S&L)
DG Cemral File l
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& k. fJe. W" % - la OY - Cb(cfr, Q+ v.O, fre.jed c ,. It>4%-003, & [3 l NUCLEAR FUEL MANAGEMENT DEPARTMENT NDIT No. NFM9900121 NUCLEAR DESIGN INFORMATION TRANSMITTAL Seq.No. O Page 2 0f 4 l
Unit 1 Data Burnup data taken from nuclear fuel data bank. Cycle and outage length data taken from ,
Zion calculation 22N-0-110M-0058. All other data taken from nuclear design report l NFSR-0097. .
Region 15A ISB MTU/ assembly 0.460 0.460 Enrichment (w/o) 3.604 3.200 Comnosition (ka/MTU) I U-234 0.314 0.272 U-235 36.041 32.000 U-236 0.038 0.041 U-238 963.61 967.69 l Total Bumup (MWD /MTU) !
assembly ID Region Z1C13 Z1C14 Z1C15 .
F10C 15B 14545 23501 30 /5'>. l F14C 16B 15190 24137 37272 F48C 168 18424 24412 36254 F500 15A 18448 35020 46894 F70D 16A 15228 30583 43388 Z1C13 length- 434 days Z1C13 shutdown date - 10/21/93 Z1C14 length - 527 days Z1C14 shutdown date - 9/9/95 Z1CIS length - 432 days 21 C15 (final) shutdown date - 2/21/97 l
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f \c blo 92 $ ~ O' llo K- CCM , Ve+ 0, PtcydlGo . 10 W -0c3,Ps$c dy NUCLEAR FUEL MANAGEMENT DEPARTMENT NDIT No. NFM9900121 NUCLEAR DESIGN INFORMATION TRANSMUTAL Seq No. O Page 3 of 4 Unit 2 Data Bumup data taken from nuclear fuel data bank. Cycle and outage length data taken from Zion calculation 22N-0-110M-0058. All other data taken from nuclear design report NFSR-0079.
Region 14A MTU/ assembly 0.462 Emichment (w/o) 3.618 Comoosition Om/MTU)
U-234 0.305 :
U-235 36.179 U-236 0.050 U-238 963.466 Total Bumup (MWD /MTU) assembly ID Region Z2C12 Z2C13 Z2C14 210A 14A 13377 25203 43138 217A 14A 13308 24873 42868 l 224A 14A 13374 25129 43017 233A 14A 22559 31069 47734 Z2Cl2 length - 823 days Z2C12 shutdown date - 11/30/92 Z2Cl3 length- 683 days Z2C13 shutdown date - 1/6/95 !
Z2Cl4 length - 519 days Z2C14 (final) shutdown date - 9/19/96
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(k lC blc d)6~ WilC X' COlob, Stv 0, ftojt'c / C 4h -&O 3, Vct *) f WYUS
, NUCLEAR FUEL MANAGEMENT DEPARTMENT NDIT No. NFM9900121 NUCLEAR DEsloN INFORMATloN TRANSMITTAL seq.No. ,0 Ps;;c 4 of 4 Miscellaneous Zion Fuel Building and Spent Fuel Pool Assembly Information e Zion Fuel Building HVA C Supply Air Temperature - 95 'F - The supply oiHVAC air is from Auxiliary Building Ventilation System is expected to be at ambient conditions of the Auxiliary Building. With no equipment running, this air temperature is expected to be below 95'F based on engineeringjudgement e Grid spacer Loss Coeficients - The grid spacer loss coefficients should be calculated based on an appropriate methodology taking into account the appropriate flow type (laminar / turbulent). Some guidance is given on p. 386 of" Nuclear Systems I, Thermal Hydraulic Fundamentals" by Neil E. Todreas and Mujid S. Kazami.
. Assembly Top and Bottom Nozzle Drawings - The appropriate assembly nozzle drawings, for the limiting fuel assemblies, discharged into the spent fuel pool are as follows:
Unit 1 Region 15 - 15x15 VANTAGE 5 w/o IFMs Top Nozzle - 1125E34 (3 sheets), Revision 19 Bottom Nozzle - 1125E22 (2 sheets), Revision 14 Unit 2 Region 14 - 15x15 OFA Top Nozzle - 1123E36 (2 sheets), Revision 22 Bottom Nozzle - 1541E27 (2 sheets), Revision 25 ,
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. SFF Total Decay Heat Generation - The attached calculation (PSA-Z-99-01,19 pages total), calculates the total decay heat generation in the pool to be 5.5 MBTU/hr.
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