ML20140D557

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Rev 1 to Decay Heat & Heatup Rate Analyses for Connecticut Yankee Sfp
ML20140D557
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 04/14/1997
From: Rosenbaum E
HOLTEC INTERNATIONAL
To:
Shared Package
ML20140D536 List:
References
SFP-97-1575-DY, SFP-97-1575-DY-R01, SFP-97-1575-DY-R1, NUDOCS 9706100415
Download: ML20140D557 (44)
v • d • e


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Holtec Center,555 Uncoln Dnve West, Martton, NJ 08053 t._

HOLTEC Telephone (609) 797-0900 lNTERNATIONAL Page 3 of 46 4

CALCULATION No.

SFP-97-1575 DY REVISION No.

Rev.1 i

3 4

i DECAY REAT AND REATUP RATE ANALYSES FOR THE CONNECTICUT i

YANKEE SFP i

FOR i

NUSCO i

i 1

i Holtec Report No: HI-971677 i

1 i

Holtec Project No: 70121 i

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Report Category: A 1

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Report Class : SAFETY RELATED 3

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9706100415 970530 PDR ADOCK 05000213 4

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C bI LJ Holtre Catntar,555 Uncoln Drivs West, Mrrtton, NJ 08053 HOLTEC Telechone (609) 797- 0900 INTERNATIONAL Page 4 of 46 i

l CALCULATION No. SFP-97-1575 DY I

REVIEW AND CERTIFICATION LOG REVISION No.

Rm1 l

DOCUMENT NAME :

DECAY HEAT AND HEATUP RATE ANALYSES FOR THE l

CONNECTICUT YANKEE SFP HOLTEC DOCUMENTl.D. NUMBER :

971677 l

HOLTEC PROJECT NUMBER :

70121 CUSTOMER / CLIENT:

NUSCO REVISION BLOCK

REVISION, AUTHOR &

REVIEWER & -

QA & DATE APPROVED &

DIST.

MBER I

DATE DATE DATE ORIGINAL M b ' "" d

[A O ' M V

J rN Q Q

$'bd C

  • N C/ 'f" c

L41 8 v l O 7,, v erufW kll M

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c REVISION 1 g'

REVISION 2 REVISION 3 REVISION 4 REVISION 5 REVISION 6 This document conforms to the requirements of the design specification and the applicable sections of the goveming codes.

Note : Signatures and printed names required in the review block.

A revision of this document will be ordered by the Project Manager and carried out if any ofits contents is materially affected during evolution of this project. The determination as to the need for revision will be made by the Project Manager with input from others, as deemed necessary by him.

I Must be Project Manager or his designee.

x Distribution : C:

Client M:

Designated Manufacturer F:

Florida Office i

      • Report category on the cover page indicates the contractual status of this document as ***

I A = to be submitted to client for approval I = for client's information N = not submitted externally THE REVISION CONTROL OF THIS DOCUMENT IS BY A"

SUMMARY

OF REVISIONS LOG" PLACED BEFORE THE TEXT OF THE REPORT.

Pase 5 of 46 CALCULATION No. SFP-97-1575-DY REVISION No.

Rev.I

SUMMARY

OF REVISIONS REVISION 0: Revision 0 contains the following sections and pages.

Title Page 1

Review and Certification Log 1

l Sumrnary of Revisions 1

Table of Contents 1

Section 1.0 1

Section 2.0 1

l Section 3.0 1

Section 4.0 1

Section 5.0 2

Section 6.0 2

l Section 7.0 1

Section 8.0 1

l Tables 2 tables (4 pages)

Graphs 2

i Appendix A 5

i Appendix B 3

j Appendix C 3

l Appendix D 7

Appendix E 3

l Appendix F

  • 5
  • Note: Appendix F is for internal Holtec use only, and is therefore not distributed.

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Holtec Report HI-971677 Holtec Project 70121 I

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Page 6 or46 CALCULATION No.

5 FP 1575.QY REVISION No.

Rev.t l

SUMMARY

OF REVISIONS (continued) l l

REVISION 1: The following changes are incorporated into this revision.

l

. Inserted a new assumption 3 into Section 4.0. Subsequent assumptions renumbered.

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. Modified Cycle 1 Fuel Decay Heat Analysis Sections 6.4 and 7.4. Added Table 3 and Graph 3.

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  • Added note to pages D-6 and E-3 about internal date representation.

. Updated Appendix F to include newer Cycle 1 Fuel Decay Heat Analysis.

l Revision 1 contains the following sections and pages.

j Title Page 1

Review and Certification Log 1

Summary of Revisions 2

Table of Contents 1

Section 1.0 1

Section 2.0 1

Section 3.0 1

Section 4.0 1

Section 5.0 2

Section 6.0 2

Section 7.0 1

Section 8.0 1

Tables 3 tables (5 pages)

Graphs 3

Appendix A 5

Appendix B 3

Appendix C 3

Appendix D 7

Appendix E 3

Appendix F

  • 5
  • Note: Appendix F is for internal Holtec use only, and is therefore not distributed.

Holtec Report HI-971677 Holtec Project 70121 0

.___m.

Page 7 of 46 CALCULATION No. SFP-97-1575.DY REVISION No.

Rev.1 l

l TABLE OF CONTENTS l

~SSL Iills Eage.$

l 1.0 Introduction 1

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2.0 Methodology 2

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3.0 Acceptance Criteria 3

4.0 Assumptions 4

l 5.0 Input Data 5

l 6.0 Calculations 7

7.0.

Results and Conclusions 9

8.0 References 10 Tables f

Graphs

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Appendix A l

Appendix B Appendix C Appendix D l

Appendix E Appendix F *

  • Note: Appendix F is for internal Holtec use only, and is therefore not distributed.

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-Holtec Project 70121 l

Holtec Report HI-971677

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Page 3 of 46 CALCULATION No.

SFP-97 1575-Dv, REVISION No.

Rev.I

1.0 INTRODUCTION

The Connecticut Yankee (CY) plant is a pressurized water reactor (PWR) nuclear power plant, located in Haddam Neck Connecticut. The CY facility is currently entering the decommissioning phase ofits operating life. While the decommissioning process is carried out and plant systems are downgraded and removed, adequste cooling and radiation shielding for the spent fuel assemblies stored in the plant's spent fuel pool (SFP) must still be provided.

It has been shown that the SFP ' structure is capable of withstanding the appropriate design basis thermal and structural loadings [1]. Therefore, the most credible scenario which could threaten the security of the stored fuel in the SFP is a loss of forced cooling. The stored fuel assemblies generate heat as a result of the continuing radioactive decay of the contained fissile materials.

Following a loss of forced cooling, only passive means of heat rejection will be available to reject the decay heat load. If the available passive heat rejection mechanisms are not sufficient to remove all of the generated decay heat, the temperature of the SFP will rise. If the decay heat load is large enough, bulk SFP boiling may occur.

In order to quantify the effects of a loss of forced cooling event on the CY SFP during the decommissioning process, the decay heat load and corresponding maximum heatup rate are calculated over this time period. The SFP decay heat load will continually reduce over the decommissioning period. The SFP heatup rate is proportional to the net decay heat load and will therefore decrease over time.

Thus, as the decay heat load reduces so to does the maximum heatup rate.

The results of these evaluations provide a conservative picture of the potential consequences on the SFP of and the time available for recovery from, a postulated loss of forced cooling. These i

results can then be'used to assist decommissioning schedule planning and emergency recovery procedures development, to ensure that the safety and integrity of the stored fuel is not threatened.

Holtec Report HI-971677 Holtec Project 70121 page1 G

Page 9 of 46 CALCULATION No. SFP-97-1575.DY REVISION No.

Rev.I 2.0 METHODOLOGY 2.1 Decay Heat Load Calculations Decay heat load calculations are performed using the ORIGEN-2 program [2] as incorporated into the Holtec QA Validated computer program LONGOR v1.0 [3]. The use of this method,

)

which considers the actual initial Um enrichment and burnup for each discharge batch, results in an accurate decay heat load determination. In order to provide the most accurate determination of the total decay heat load in the CY SFP, these calculations were performed using the actual-historic discharge schedule. The initial Um enrichment and burnup for each assembly is averaged for each discharge batch, and the evaluations are performed using the batch average values.

2.2 Heatup Rate Calculations i

The heatup rate of a SFP, following a loss of forced cooling, is a function of the net heat load in the SFP and the total SFP thermal capacity. This function is given in the following equation:

.AT _ Qow, Ar C,7 i

l where:

AT/At is the heatup rate ( F/hr)

Qoeca is the decay heat input (Btu /hr)

Csn> is the SFP thermal capacity (Btu /*F) l l

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l Holtec Report HI-971677 Holtec Project'70121 page 2 x

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l Page 10 of 46 CALCULATION No. SFP-97-I $75-DY REVISION No.

Rev.1 3.0 ACCEPTANCE CRITERIA l

The analyses documented in this report are a purely analytical study. As such, no explicit i

acceptance criteria are applied to any of the presented work.

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Page 11 of 46 CALCULATION No SFP-971575 DY REVISION No.

IDv.1 4.0 ASSUMPTIONS P:veral conservative assumptions are required to perform the analyses documented in this report.

These assumptions and correspondingjustifications are presented below.

1.

Any beneficial cooling effects which arise due to evaporation of the SFP water are conservatively neglected. This conservatively maxmuzes the resulting heatup rates.

2.

The thermal capacity of the SFP is based on the net water volume only. This assumption 1

conservatively reduces the total thermal capacity, which subsequently results in maximized heatup rates.

3.

The thermal capacity calculation assumes that the fuel assemblies are composed entirely of the material of construction with the lowest density, namely zircaloy. This conservatively maximizes the volume of water displaced, thereby minimizin' the net water volume.

g 4.

The batch average enrichment and burnup are used for decay heat load analyses. While differences in the decay heat generation rate from individual assemblies may affect local temperature analyses, they have no effect on the bulk SFP temperatures.

5.

Slight differences in the uranium weight of fuel assemblies in the SFP are neglected. The decay heat generation of a fuel assembly is not radically affected by minor changes in the uranium weight. The decay heat calculations are conservatively based on the largest uranium weight for the fuel assembly types in a given discharge batch.

6.

Decay heat loads for dates that fall between explicitly calculated data points are linearly interpolated. Because the decay heat curve, governed by exponential decay, is always concave up, a linear interpolation will always conservatively overpredict the actual temperature by a small amount.

Holtec Report HI-971677 Holtec Project 70121 page 4 m

Pace 12 of 46

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CALCULATION No. SFP.97-1575-DY REVISION No.

Rev.1 5.0 INPUT DATA Input data and references required for the SFP thermal capacity calculation are defined within that calculation. A list of all other required input parameters is included below.

Reactor Type: PWR, from [4]

Reactor Thermal Power: 1,825 MW(t), from [5]

Core Size: 157 assemblies, from [5]

Bounding Fuel Uranium Weight (cycles 2-18): 412.125 kg, from [6]

Bounding Fuel Uranium Weight (cycle 19): 363.810 kg, from [7]

Fuel Discharge Schedule: see below, from [4), [7] and [8]

Evaluation Start Date: January 1,1997, from [9]

Evaluation End Date: December 31,2015, from [9]

Discharge Date

  1. of Assemblies Avg. Enrichment Avg. Burnup April 16,1971 23 3.020 26500 June 10,1972 53 3.233 30800 July 8,1973 55 2.953 27300 May 17,1975 48 4.000 32900 May 18,1976 53 3.654 30600 October 15,1977 52 3.654 33400 January 27,1979 48 3.974 32700 May 3,1980 53 3.981 34300 September 26,1981 53 3.989 33900 January 22,1983 49 3.994 33900 August 1,1984 53 3.990 35300 January 4,1986 56 3.981 33800 July 18,1987 53 3.981 33900 September 2,1989 55 3.402 32400 October 17,1991 53 3.997 34600 May 15,1993 53 3.987 33400 January 28,1995 53 4.000 34900 Holtec Report HI-971677 Holtec Project 70121 page 5 0

Page 13 of 46 CALCULATION No. SFP.97-1575-DY REVISION No.

Rev.1 July 22,1996 52 3.600 40400 l

52 3.600 27900 l

53 4.200 14400 l

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Page 14 of 46 l

CALCULATION No. _SEP-97-1575-DY REVISION No.

Rev.I 6.0 CALCULATIONS 6.1 SFP Thermal Capacity Calculation The total thermal capacity of the SFP, subject to the assumptions listed in Section 4.0, is calculated using version 6.0+ of the Mathcad electronic scratchpad. This calculation is included in Appendix B, on pages B-2 through B-3.

6.2 Decay Heat Load Calculations As described in Section 2.1, the total decay heat load in the SFP is calculated using the LONGOR v1.0 program. The decay heat is calculated, based on the fuel inventory presented in Section 5.0, on the following dates:

  • The first day of every month in 1997

. Every January 1" and July 1" from 1998 through 2006

. Every January 1" from 2007 through 2016 Calculating the decay heat load for each date requires a separate LONGOR evaluation, for a total of forty (40) evaluations. A list of the LONGOR input and results files is included in Appendix C l

on pages C-2 and C-3. The LONGOR input and results files are included in Appendix F.

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l A benchmark cornparison between ORIGEN-2 calculated decay heat load values and the highly conservative Branch Technical Position ASB 9-2 (10] is included in this report in Appendix D.

6.3 -

SFP Heatup Rate Calculations

)

In the absence of evaporation, the net heat load in the SFP is equal to the decay heat load. The SFP heatup rate for the forty dates evaluated in Section 6.2 is calculated as des'cribed in Section a

Holte;c Report HI-971677 Holtec Project 70121 page 7 l

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Page iS of 46 CALCULATION No. __SEP-97-lAli DX REVISION No.

Rev.I 2.2. This division is performed using the Excel spreadsheet program. The Excel worksheet for this calculation is included in Appendix E, on pages E-2 through E-3.

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6.4.

Cycle 1 Fuel Decay Heat Effects Evaluation The fuel assemblies discharged at the end of Cycle 1 are currently not stored in the SFP. The l

thermal-hydraulic effects of returning the Cycle 1 fuel assemblies to the SFP is qualitatively evaluated in this section.

i The per assembly decay heat input of the Cycle 1 fuel assemblies will be less than the corresponding value for the Cycle 2 assemblies, due to the longer decay period. From the LONGOR results files, the decay heat contribution of the 23 assemblies discharged at the end of Cycle 2 can be determined. The per assembly decay heat load for Cycle 2 assemblies is therefore:

Q,, = 0*'"

23 Per reference [6], a. total of 76 fuel assemblies have been shipped offsite. The total decay heat i

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contribution of these 76 assemblies at Cycle 2 per assembly conditions would be:

~

Qu = 76 x Q,,

Note that because of its longer decay period the actual total heat load would be less than this f

value.

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Page 16 of 46 1

CALCULATION No, SFP 971575.DY REVISION No.

Rev.1

)

7.0 RESULTS AND CONCLUSIONS 7.1 SFP Thermal Capacity Calculation i

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The total thermal capacity of the SFP is determined to be 2.285x10' Btu / F. As postulated in j

Section 4.0, this thermal capacity includes the water only, and conservatively neglects the thermal l

capacity of the racks, fuel, liner and concrete structure.

}

7.2 Decay Heat Load Calculations The decay heat load on the dates examined are presented numerically in Table 1 and ' graphically in Graph 1. As stated in Section 4.0, decay heat loads on intermediate dates are conservatively linearly interpolated between calculated values.

7.3 SFP Heatup Rate Calculations The SFP heatup rate on the dates examined are presented numerically in Table 2 and graphica))y in Graph 2.

Heatup rates on intermediate dates can be conservatively linearly interpolated between calculated values.

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7.4 Cycle 1 Fuel Decay Heat Effects Evaluation

. i As calculated in Section 6.4, the decay heat contribution of the Cycle 1 fuel assemblies, should they be returned to CY in the future, would be a relatively small fraction of the total deciy heat load. These results are presented numerically in Table 3 and graphically in Graph 3. Subject to l

the many conservative assumptions listed in Section 4.0, this negligible decay heat increase would have no appreciable effect on the results of the analyses documented in this report.

i Holtec Report HI-971677 Holtec Project 70121 page 9 he

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CALCULATION No. _ SIP-97-I$75-DX REVISION No.

Rev.I

8.0 REFERENCES

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[1]

" Calculation Package - Structural Qualification of the Spent Fuel Pool at Connecticut l

Yankee", Holtec Report HI-941226, Revision 1.

(

[2]

A.G. Croff, "ORIGEN2 - A Revised and Updated Version of the Oak Ridge Isotope l

Generation and Depletion Code," ORNL-5621, Oak Ridge National Laboratory,1980.

[3]

"QA Documentation for LONGOR v1.0", Holtec Report HI-951' 90, Revision 0.

3 l

[4]

Haddam Neck Plant Updated Final Safety Analysis Report (USFSAR) l

[5]

NUSCO/CY Specification SP-ME-909, " Technical Specification for Purchase of Spent Fuel Racks for Haddam Neck Nuclear Power Plant Spent Fuel Pool", Revision 1, 3/22/94.

[6]

Memorandum from J. J. Parillo to E. Mullarkey, " Additional Fuel Data for Connecticut Yankee Rerack", NE-94-F-305, 6/20/94.

[7]

Memorandum from J. Hartzell to E. Mullarkey, " Connecticut Yankee Discharged Fuel Data for Decay Heat Load Analysis", NE-97-F-008,1/10/97.

[8]

Facsimile from E. Mullarkey to E. Rosenbaum, " Connecticut Yankee Operating History -

Operating Landmarks", transmitted on 1/14/97.

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[9]

NUSCO Purchase Requisition # 02014688.

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[10]

USNRC Branch Technical Position ASB 9-2, " Residual Decay Energy for Light Water' l

Reactors for Long Term Cooling", Revision 2, July 1981.

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Page 18 of 46 CALCULATION No. SFP-97-1575-DY REVISION No.

Rev.1 Table 1 l

Connecticut Yankee SFP Decay Heat Load for 1/1/1997 - 1/1/2016 1019 Total Stored Assemblies (Computer Code LONGOR) l i

Date SFP Decay Heat Load (Btu /hr)

January 1,1997 4,759,102 February 1,1997 4,327,231 March 1,1997 3,986,898 April 1,1997 3,712,612 May 1,1997 3,486,114 June 1,1907 3,298,303 July 1,1997 3,138,888 August 1,1997 3,002,399 September 1,1997 2,880,626 October 1,1997 2,773,193 November 1,1997 2,676,575 December 1,1997 2,589,608 January 1,1998 2,509,618 July 1,1998 2,145,186 January 1,1999 1,902,143 July 1,1999 1,733,032 1

January 1,2000 1,611,378 July 1,2000 1,522,712 January 1,2001 1,455,651 July 1,2001 1,404,009 January 1,2002 1,363,043 July 1,2002 1,329,764 January 1,2003 1,301,812 j

July 1,2003 1,277,966 January 1,2004 1,257,001 July 1,2004 1,233,424 i

Holtec Report HI-971677 Holtec Project 70121 U

Page 19 of 46 CALCULATION No. S FP-97-1575-DY rUiVISION No.

Rev.1 l

January 1,2005 1,221,400 July 1,2005 1,205,904 January 1,2006 1,191,409 July 1,2006 1,177,752 January 1,2007 1,164,836 January 1,2008 1,140,660 January 1,2009 1,118,311 January 1,2010 1,097,302 January 1,2011 1,077,269 January 1,2012 1,058,159 January 1,2013 1,039,732 January 1,2014 1,021,889 January 1,2015 1,004,665 January 1,2016 987,903 Holtec Report HI-971677 Holtec Project 70121

Y$4ju}ri CALCULATION No.

SFP-97 157$-DY REVISION No.

Rev.1 i

Table 2 Connecticut Yankee SFP Hestup Rate for 1/1/1997 - 1/1/2016 No Evaporative or Forced Cooling Available Date SFP Heatup Rate ('F/hr)

January 1,1997 2.11 February 1,1997 1.92 March 1,1997 1.76 April 1,1997 1.64 May 1,1997 1.54 June 1,1997 1,46 July 1,1997 1.39 August 1,1997 1.33 i

September 1,1997 1.28 October 1,1997 1.23 November 1,1997 1.18 j

December 1,1997 1.15 January 1,1998 1.11 July 1,1998 0.95 January 1,1999 0.84 July 1,1999 0.77 January 1,2000 0.71 j

July 1,2000 0.67 January 1,2001 0.64 i

July 1,2001 0.62 January 1,2002 0.60 July 1,2002 0.59 January 1,2003 0.58 July 1,2003 0.57 January 1,2004 0.56 July 1,2004 0.55 January 1,2005 0.54 l

Holtec Report HI-971677 Holtec Project 70121

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CALCULATION No. SFP-97-1575-DY REVISION No.

Rev.1 July 1,2005 0.53 January 1,2006 0.53 July 1,2006 0.52 l

January 1,2007 0.52 January 1,2008 0.50 January 1,2009 0.50 January 1,2010 0.49 January 1,2011 0.48 January 1,2012 0.47 January 1,2013 0.46 January 1,2014 0.45 January 1,2015 0.44 January 1,2016 0.44 l

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Page 22 of 46 CALCULATION No. SFP-97.L511-DX REVISION No.

Rev.1 Table 3 Connecticut Yankee SFP Decay Heat Load for 1/1/1997 - 1/1/2016 Current Inventory + Cycle 1 Assemblies Date Total Heat Load (Btu /hr)

Cycle 1 Fuel Heat (Btu /hr)

January 1,1997 4,827,069 67,967 January 1,1998 2,576,505 66,887 January 1,1999 1,967,982 65,839 January 1,2000 1,676,193 64,815 January 1,2001 1,519,471 63,820 January 1,2002 1,425,878 62,835 January 1,2003 1,363,686 61,874 January 1,2004 1,317,946 60,945 January 1,2005 1,281,423 60,023 January 1,2006 1,250,537 59,128 January 1,2007 1,223,085 58,249 January 1,2008 1,198,053 57,393 January 1,2009 1,174,872 56,561 January 1,2010

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1,153,040 55,738 January 1,2011 1,132,204 54,935 January 1,2012 1,112,304 54,145 January 1,2013 1,093,107 53,375 January 1,2014 1,074,504 52,615 January 1,2015 1,056,543 51,878 January 1,2016 1,039,054 51,151 l

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Holtec Report HI-971677 Holtec Project 70121 l

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1og Connecticut Yankee SFP Decay Heat Load for 1/1/1997 - 1/1/2016 1019 Total Stored Assemblies m

(Computer Code LONGOR) 5,000,000 x

i 4,500,000 -

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4,000,000 ---

c 3,500,000 -

ba p 3,000,000 --

3a j 2,500,000 -

z A 2,000,000 --

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3 Connecticut Yankee SFP Heatup Rate for 1/1/1997 - 1/1/2016 n

xg No Evaporative or Forced Cooling Available oa 2.5 B

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I Connecticut Yankee SFP Decay Heat Load for 1/1/1997 - 1/1/2016 o

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5,000,000

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Page 26 of 46 CALCULATION No. S FP-97-1575-DY REVISION No.

Rev.I Appendix A Holtec QA Approved Computer Program List l

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Holtec Report HI-971677 Holtec Project.70121 J

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CALCULATION No. SFP-97 1575-DY

[

REVISION No.

Rev.I 1

l Rt.vistum 4: MAML,111, im HOLTEC APPROVED COMPUTER PROGRAM LIST l

CODE Computer PROGRAM VERSION USED Environment l

CASMO-3 4.4,4.7 i

KENO-SA (INCLUDES 2.3 l

WORKER AND NITAWL) l i

ANSYS 5.0, 5.0A, 5.1, 5.2, 5.3 l

l MCNP 4A I

l l

SCANS 1A l

AC-XPERT 1.12 AIRCOOL 5.01E, 5.01F, 5.02G, 5.11H, 5.21, 6.1 AIRSYS 1.03 1

ANYSHEET 1.3

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AVESPC 1.0 AXISOL 1.0 BOXEQ 1.0 BULKTEM 2.0 CANISTER 1.0 CELLDAN 4.3 CHANBP6.TRU 1.0 i

CONPRO 1.0 CORRE.FOR f.3 CROSSTIE.FOR 1.0 DECAY 1.4 DYNARACK (also known 1.5 thru 1.13 inclusive as DYNAMO XXXX) l l

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l Holtec Report Hi-971677 Holtec ?roject 70121

r Page 23 of 46 CALCULATION No. S FP-97-1575.DY REVISION No.

Rev.1 i

REVISION 2: MARCH 1,1997 HOLTEC APPROVED COMPUTER PROGRAM LIST I

1 CODE Computer i

PROGRAM VERSION USED Environment DYNA-2D HI-95 1

FLANGE 2.0 l

J FLUENT

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4.3, 4.32 I

l

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SFMR2 1.1 ST-XPERT 2.01 l_

STATICD.FOR 1.0 l

l STER 3.12B, 3.22 A, 3.22C, 3.24D, 3.3E, 4.12, 5.04 l

TBOIL 1.7,1.6 THERPOOL

.1.2,1.2A TUBVIB 2.0 UBAX 1.0 UFLOW.FOR 1.0 VIB1DOF 1.0 i

VMCHANGE.FOR 1.4,1.3 BOUND.FOR 1.0 MAXDISP.FOR 1.2 SFMR2A.FOR 1.0 PD16 1.1,1.0 SPG16 1.0 FIMPACT

'?

1.0 MAXDIS16 1.0 j

PREDYNAl 1.5,1.4 j.

GENEQ.FOR

, 1.3 l

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Page 29 of 46 CALCULAT!ON No. _.SFP-971575-DY REVISION No.

Rev.1 l

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REVISION 2: MARCH 1,1997 HOLTEC APPROVED COMPUTER PROGRAM LIST CODE Computer PROGRAM VERSION USED Environment HEATER 1.0 l

HEXTEM 1.0 i

HEXTRAN 1.2 HYSYST 1.01 IBP.DAT 1.0 INSYST 2.01 LONGOR 1.0 1.0 DOS / Win LNSMTH2.FOR 1.0 LUINVS.F 1.0 MASSINV.FOR 1.5 MR2.FOR 1.4 through 1.9 MR216.FOV 1.0 MRPLOT.FOR 1.2 j

MR2 POST PROCESSORS 2.0 MSREFINE.FOR 1.3 MULPOOLD 1.4,1.3 MULTil.FOR

'I.3,1.4,1.5 ONEPOOL 1.4, 1.4.1, 1.5 PIPE PLUS 5.04-3H LS-DYNA 3D 936 PREMULT2.FOR 1.0 PREMULT8.FOR 1.0 PRESPRG8.FOR 1.0 Holtec Report HI-971677 A-4 nnte,c penicc, vo i, t

Page 30 of 46 CALCULATION No.

SFP.97 1571.[gr REVISION No.

Rev.1 l

REVISION 2: MARCH 1,1WI HOLTEC APPROVED COMPUTER PROGRAM LIST PROGRAM VERSION CODE Computer USED Environment SACS 1.0 SCALE (SAS2H AND 4.3 ORIGEN-S MODULES)

TRIEL 2.0 i

WORKING MODEL 3.0 SIFATIG 1.0 DYNAPOST 1.0 ORIGEN 2 (2.1), S NOTES:

1.

XXXX = ALPHANUMERIC COMBINATION 2.

GENERAL PURPOSES UTILITY CODES (MATHCAD, EXCEL, ETC.)

MAYBE USED ANYTIME.

I Holtec Report Hi-971677 Holtec Project 70121 A-5 m

Page 31 of 46 CALCULATION No.

SFP-97 1 $73.Dy REVISION No.

Rev.I l

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Appendix B SFP Thermal Capacity Calculation i

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Page 32 of 46 CALCULATION No.

SFP-97 1575-DY REVISION No.

Rev.1 The purpose of this calculation is to determine the thermal capacity of the SFP at Connecticut Yankee's Haddam Neck Plant with a post-Cycle 19 SNF inventory. The thermal capacity is determined by calculating a bounding net water volume of the SFP at the low water level, and multiplying by the appropriate spec:6c heat capacity.

REFERENCES

[1] Holtec Drawing 1367. " Survey Elevations for Spent Fuel Storage Racks", Revision 0.

[2] Holtec Drawing 1368, " Pool Layout Drawing", Revision 2.

[3] NUSCO/CY F.4cification SP-ME-909," Technical Specification for Purchase of Spent Fuel Racks for Haddam Neck Nuclear Power Plant Spent Fuel Pool", Revision 1,3/22/94.

[4] Memo NE-97-F-008 from J. Hartzell to E. Mullarkey, dated 1/10/97.

[5] Avallone and Baumeister," Marks' Standard Handbook for Mechanical Engineers",9th Edition.

[6] Rust, J.H.," Nuclear Power Plant Engineering", Haralson Publishing Company,1979.

[7] "ASME Steam Tables", American Society of Mechanical Engineers,3rd Edition,1977.

DEFINE INPUT PARAMETEBE D g := 396 in SFP Depth, from [1]

p Ldp := 437.68 in SFP Length, from [2]

W g := 428.57 in SFP Width, from [2]

p M racks :: 480500-lb Total Mass of Racks, from [2] and [3]

M fuel := 1500 lb Total Fuel Assembly Weight, from [3]

Nfuel := 1020 Number of Stored Fuel Assemblies, from [4]

50lI Density of Stainless Steel, from [5]

p 3, ::

ft' g:=4095 Density of Zircaloy, from [6]

p ft' p, :: 59.8I Density of Water @ 212 F, from [7]

ft' Cp := 0.998 Specific Heat of Water @ 100 F, from [7]

l lb R l

CALCULATE TOTAL SFP VOLUME i

V g = 4.29910 ft' 4

V g :: D4.L4.wdp p

p I

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Page 33 of 46 CALCULATION No.

SFP-97 1575-Q1 REVISION No.

Rev 1 CALCULATE TOTAL VOLUME OCCUPIED BY RACKS V,:= Mracks' V = 959.082 ff n

Pu CALCULATE TOTAL VOLUME OCCUPlED BY FUEL Vgg := N gg M gg 1 Vgg - 3,741 103.f9 P zr CALCULATE THE NET WATER VOLUME AND MASS V w := V4 V, V 91 V = 3.82910' 19 w

M, := Vwpw M, = 2.29 10' lb l

CALCULATE THE WATER THERMAL CAPACITY j

C := M Cp C = 2.285 10' BW w

l R

4 l

t l

l l

l l

l Holtec Report HI-971677 Holtec Project 70121 B-3

... ~

~ - -.. - -... - ~.. -.. ~ -. - -.

.... ~....... ~.. -.... ~ ~... -

. =.

l Page 34 of 46 CALCULATION No. SFP.97 1575.DY REVISION No.

Rev.1 l:

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- Appendix C l

LONGOR Input, Output and Results Files l

t for 1

' Decay Heat Lead Calculations 1

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(

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1 I

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1 4

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1-I I

Holtec Report HI-971677 Holtec Project 70121 page C-1 1

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Page 35 of 46 CALCULATION No, SFP-97-1575-DY REVISION No.

Rev.1 I

Volume in drive F is VOL1 Directory of Fa\\ ANALYSIS \\EROSENBA\\70121\\ ANALYSES \\HEATLOAD APR97 IN 1,009 01-14-97 12:25p APR97 RES 1,686 01-14-97 1:47p AUG97 IN 1,009 01-14-97 12:26p AUG97 RES 1,686 01-14-97 2:16p DEC97 IN 1,009 01-14-97 12:27p DEC97 RES 1,686 01-14-97 2:55p FEB97 IN 1,009 01-14-97 12:24p FEB97 RES 1,686 01-14-97 1:20p JAN00 IN 1,009 01-15-97 8:26a JAN00 RES 1,686 01-15-97 9:02a JAN01 IN 1,009 01-15-97 8:26a JAN01 RES 1,686 01-15-97 9:18a JANO2 IN 1,009 01-15-97 8:27a JANO2 RES 1,686 01-15-97 9:33a JANO3 IN 1,009 01-15-97 8:27a JANO3 RES 1,686 01-15-97 10:31a JAN04 IN 1,009 01-15-97 8:28a JAN04 RES 1,686 01-15-97 10:45a JAN05 IN 1,009 01-15-97 8:28a JANOS RES 1,686 01-15-97 10:58a JAN06 IN 1,009 01-15-97 8:29a l

JAN06 RES 1,686 01-15-97 11:12a JAN07 IN 1,009 01-15-97 8:29a JAN07 RES 1,686 01-15-97 11:26a JANOS IN 1,009 02-13-97 11:53a JAN08 RES 1,686 02-13-97 12:09p JAN09 RES 1,686 02-13-97 12:15p I

JAN09 IN 1,009 02-13-97 11:53a JAN10 RES 1,686 02-13-97 12:23p JAN10 IN 1,009 02-13-97 11:53a JAN11 RES 1,686 02-13-97 12:30p JAN11 IN 1,009 02-13-97 11:54a JAN12 RES 1,686 02-13-97 12:37p JAN12 IN 1,009 02-13-97 11:54a JAN13 RES 1,686 02-13-97 12:51p JAN13 IN 1,009 02-13-97 11:54a JAN14 RES 1,686 02-13-97 12:44p JAN14 IN 1,009 02-13-97 11:54a JAN15 RES 1,686 02-13-97 1:01p JAN15 IN 1,009 02-13-97 11:54a JAN16 RES 1,686 02-13-97 1:10p JAN16 IN 1,009 02-13-97 11:54a JAN97 IN 1,009 01-14-97 12:22p JAN97 RES 1,686 01-14-97 1:13p JAN98 IN 1,009 01-14-97 12:27p JAN98 RES 1,686 01-14-97 3:03p JAN99 IN 1,009 01-15-97 8:25a JAN99 RES 1,686 01-15-97 8:49a JULOO IN 1,009 01-15-97 8:26a JULOO RES 1,686 01-15-97 9:11a JULO1 IN 1,009 01-15-97 8:26a JULO1 RES 1,686 01-15-97 9:26a H0ltec Report HI-971677 Holtec Project 70121 page C-2 l

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Page 36 of 46 CALCULATION No. SFP-97-1575-DY REVISION No.

Rev.1 JULO2 IN 1,009 01-15-97 8:27a JULO2 RES 1,686 01-15-97 10:24a JULO3 IN 1,009 01-15-97 8:28a JULO3 RES 1,686 01-15-97 10:38a JULO4 IN 1,009 01-15-97 8:28a JULO4 RES 1,686 01-15-97 10:51a JULOS IN 1,009 01-15-97 8:29a JULOS RES 1,686 01-15-97 11:05a JULO6 IN 1,009 01-15-97 8:29a JULO6 RES 1,686 01-15-97 11:19a

-JUL97 IN 1,009 01-14-97 17:25p JUL97 RES 1,686 01-14-97 2:09p JUL98 IN 1,009 01-15-97 8:25a JUL98 RES 1,686 01-15-97 8:42a JUL99 IN 1,009 01-15-97 8:25a JUL99 RES 1,686 01-15-97 8:55a JUN97 IN 1,009 01-14-97 12:25p JUN97 RES 1,686 01-14-97 2:02p MAR 97 IN 1,009 01-14-97 12:24p MAR 97 RES 1,686 01-14-97 1:27p MAY97 IN 1,009 01-14-97 12:25p MAY97 RES 1,686 01-14-97 1:55p

)

NOV97 IN 1,009 01-14-97 12:27p NOV97 RES 1,686 01-14-97 2:48p I

OCT97 IN 1,009 01-14-97 12:27p OCT97 RES 1,686 01-14-97 2:31p SEP97 IN 1,009 01-14-97 12:26p SEP97 RES 1,686 01-14-97 2:41p 1

i Holtec Report HI-971677 Holtec Project 70121 page C-3 1

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Page 37 of 46 CALCULATION No. SFP-97 1575-DY REVISION No.

Rev.I l

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l Appendix D Decay Heat Calculation Benchmark Comparison between ORIGEN-2 and Branch Technical Position ASB 9-2 l

l.

Holtec Proicct 70121 Holtec Report HI-971677 page D-1

Pase 33 of 46 j

CALCULATION No.

SFP.97-1575-DY l

D.1 Introduction Licensing basis thermal-hydraulic analyses of the SFP have utilized the method of Branch Technical Position ASB 9-2 to determine decay heat loads. The ASB 9-2 correlations, which are basically curve-fit equations, are known to be highly conservctive. In the analyses documented in this report, the ORIGEN-2 code, as incorporated into Holtec's LONGOR program, is used to determine decay heat loads. The ORIGEN-2 code is an explicit isotope generation and depletion code, and is therefore more accurate than the approximations of ASB 9-2. In order to quantify the difference between the results of ORIGEN-2 and ASB 9-2, a comparison between the two methods is performed for the range of dates from January 1,1997 through January 1,2016.

D.2 Comparison Methodology The decay heat is evaluated using both the ORIGEN-2 and ASB 9-2 methods, at forty (40) dates between January 1,1997 and January 1,2016. The actual existing SFP inventory is used as input for both methods. Both numerical and graphical comparisons are performed.

D.3 Calculations The ORIGEN-2 based calculated decay heat results are extracted from the analyses in Section 6.2. The ASB 9-2 code, as incorporated into version 1.4 of the Holtec QA Validated DECAY program [D.1], is run with the same input data. The following DECAY input and results Sles are used in this evaluation.

Volume in drive F is VoL1 Directory of Fr\\ ANALYSIS \\ERoSENBA\\70121\\ ANALYSES \\ASB APR97 IN 172 02-14-97 10 : 41a-APR97 RES 3,880 02-14-97 10:57a AUG97 IN 174 02-14-97 10:42a AUG97 RES 3,880 02-14-97 10:58a l

DEC97 IN 176 02-14-97 10:43a DEC97 RES 3,880 02-14-97 10:58a FEB97 IN 175 02-14-97 10:41a l

FEB97 RES 3,880 02-14-97 10:57a l

Holtec Report HI-971677 Holtec Project 70121 page D-2

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Page 39 of 46 l

CALCULATION No. SFP.971575 DY f

REVISION No.

Rev.1 JAN00 IN 175 02-14-97 los44a JAN00 RES 3,880 02-14-97 11:00a JAN01 IN 175 02-14-97 10:45a JANO1 RES 3,880 02-14-97 11:00a JANO2 IN 175 02-14-97 10:49a JAN02 RES 3,880 02-14-97 11:01a JANO3 IN 175 02-14-97 10:50a JANO3 RES 3,880 02-14-97 11:01a JAN04 IN 175 02-14-97 10:50a JANO4 RES 3,880 02-14-97 11:01a JANOS IN 176 02-14-97 10:50a l

JANOF RES 3,880 02-14-97 11:02a I

JAN06 IN 176 02-14-97 10:52a JAN06 RES 3,880 02-14-97 11:02a-JAN07 IN 176 02-14-97 10:52a l

JAN07 RES 3,880 02-14-97 11:02a JAN08 RES 3,880 02-14-97 11:03a JAN08 IN 176 02-14-97 10:52a JAN09 RES 3,880 02-14-97 11:03a JAN09 IN 176 02-14-97 10:53a 4

JAN10 RES 3,880 02-14-97 11:03a JAN10 IN 176 02-14-97 10:53a JAN11 RES 3,880 02-14-97 11:03a JAN11 IN 176 02-14-97 10:53a l

JAN12 RES 3,880 02-14-97 11:03a JAN12 IN 176 02-14-97 10:53a JAN13 RES 3,880 02-14-97 11:03a JAN13 IN 176 02-14-97 10:53a i '

JAN14 RES 3,880 02-14-97 11:03a l

JAN14 IN 176 02-14-97 10:53a JAN15 RES 3,880 02-14-97 11:03a JAN15 IN 176 02-14-97 10:54a l

JAN16 RES 3,880 02-14-97 11:04a JAN16 IN 176 02-14-97 10:54a t

JAN97 IN 174 02-13-97 4:05p JAN97 RES 3,880 02-13-97 4:05p JAN98 IN 175 02-14-97 10:43a JAN98 RES 3,880 02-14-97 10:59a JAN99 IN 175 02-14-97 10:44a JAN99 RES 3,880 02-14-97 10:59a JULOO IN 172 02-14-97. 10:45a l

JULOO RES 3,880 02-14-97 11:00a JULO1 IN 172 02-14-97 10:49a JULO1 RES 3,880 02-14-97 11:00a JULO2 IN 172 02-14-97 10:49a JULO2

-AES 3,880 02-14-97 11:01a JULO3 IN 172 02-14-97 10:50a JULO3 RES 3,880 02-14-97 11:01a JULO4 IN 172 02-14-97 10:50a JULO4 RES 3,880 02-14-97 11:01a JULOS IN 173 02-14-97 10:51a JULOS RES 3,880 02-14-97 11:02a i

JULO6 IN 173 02-14-97 10:52a j'

JULO6 RES 3,880 02-14-97 11:02a

'JUL97 IN 172 02-14-97 10:42a f

Holtec Report HI-971677 Holtec Project 70121 l

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Page 40 of 46 CALCULATION No. SFP-97-1575.DY REVISION No.

Rav. I JUL97 RES 3,880 02-14-97 10:57a 172 02-14-97 10:44a JUL98 IN JUL98 RES 3,880 02-14-97 10:59a 172 02-14-97 10:44a JUL99 IN JUL99 RES 3,880 02-14-97 11:00a 172 02-14-97 10:41a JUN97 IN JUN97 RES 3,880 02-14-97 10:57a 172 02-14-97 10:41a MAR 97 IN MAR 97 RES 3,880 02-14-97 10:57a 171 s<2-14-97 10:41a MAY97 IN MAY97 RCS 3,880 02-14-97 10:57a 176 02-14-97 10:43a NoV97 IN NoV97 RES 3,880 02-14-97 10:50a 175 02-14-97 10:42a oCT97 IN oCT97 RES 3,880 02-14-97 10:58a 177 02-14-97 10:42a SEP97 IN SEP97 RES 3,880 02-14-97 10:58a The DECAY input and output files are included in Appendix F of this report.

The Excel The numeric comparison is performed using the Excel spreadsheet program.

worksheet for this comparison is included on pages D-S and D-6. A graphical comp presemed on page D-7.

D.4 References "QA Documentation for DECAY v1.4", HOltec Report HI-92830, Revision 1.

D.1 Holtec Project 70121 Holtec Report HI-971677 page D-4

. - - _._ - -.~..

~..-_-.

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Page 41 of 46 l

l CALCULATION No. SFP.97 1575.DY l

REVISION No.

Rev.1 l

ORIGEN2 ASB 9-2 ASB 9 2

% Diff Date Stu/hr Non-Dim Stu/hr 1/1/1997 4,759.102 0.17374 6.892,858 30.95604 Wod gg l/db 2/1/1997 4,327,231 0.16284 6,460,418 33.01933 3/1/1997 3,986,898 0.15387 6,104,547 34.6897 g n #58 4/1/1997 3,712,612 0.14643 5,809,377 36.09277 5/1/1997 3,486,114 0.14017 5,561,022 37.31163 C@

6/1/1997 3,298,303 0.13487 5,350,752 38.35815 l

7/1/1997 3,138,888 0.13032 5,170,238 39.2893 8/1/1997 3,002,399 0.12639 5,014,322 40.12353 9/1/1997 2,880,626 0.12296 4,878,242 40.94951 10/1/1997 2,773,193 0.11994 4,758,429 41.7204 11/1/1997 2,676,575 0.11726

-4,652,104 42 46528 12/1/1997 2,589,608 0.11486 4,556,888 43.17156 1/1/1998 2,509,618 0.11270 4,471,193 43.8714 l

7/1/1998 2,145,186 0.10320 4,094,296 47.60549 1/1/1999 1,902,143 0.09723 3,857,445 50.68905 l

7/1/1999 1,733,032 0.09318 3,696,768 53.12035 l

1/1/2006 1,611,378 0.09026 3,580,922 55.00103 r

l 7/1/2000 1,522,712 0.08806 3,493,640 56.41475 l

1/1/2001 1,455,651 0.08631 3,424,212 57.48946 l

7/1/2001 1,404,009 0.08484 3,365,892 58.28716 l

1/1/2002 1,303,043 0.08355 3,314,713 58.87901 l

7/1/2002 1,329,764 0.08238 3,268,295 59.31322 i

l 1/1/2003 1,301,812 0.08129 3,225,051 59.63438 7/1/2003 1,277,966 0.08026 3,184,188 59.86524 i

l 1/1/2004 1,257,001 0.07926 3,144,514 60.02559 l

7/1/2004 1,238,424 0.07829 3,106,031 60.12841 1/1/2005 1,221,400 0.07735 3,068,738 60.19862 l

7/1/2005 1,205,904 0.07642 3,031,842 60.22537 i

l 1/1/2006 1,191,409 0.07550

'!,995,342 60.22461 i

7/1/2006 1,177,752 0.07460 2,959,636 60.20619 1/1/2007 1,164,836 0.07371 2,924,327 60.16738 1/1/2008 1,140,660 0.07197 2,855,295 60.05107 1/1/2009 1,118,311 0.07027 2,787,850 59.88626 l

1/1/2010 1,097,302 0.06861 2,721,992 59.68755 1/1/2011 1,077,269 0.06699 2,657,722 59.46645 1/1/2012 1.058,159 0.06540 2,594,641 59.21752 1/1/2013 1,039,732 0.06386 2,533,544 58.96136 1/1/2014 1,021,889 0.06235 2,473,637 58.6888 1/1/2015 1,004,665 0.06088 2,415,317 58.40443 l

1/1/2016 987,903 0.05944 2,358,187 58.10754 l

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Page 42 of 46 CALCULATION No. SFP.97-1575-DY REVISION No.

Rev.1 OW"G O/3 v.s.,,f 3 & M ORIGEN2 ASB 9-2 ASB 9-2

% Diff Date Stu/hr Non-Dim Btu /hr 35431 4750102 0.17374

=1825000000*3.413*C3/157 =100*(D3-83)O3 35462 4EY231 0.16284

=1825000000*3.413*C4/157 =100*(D4-B4)/D4 4

35493 3986898 0.15387

=1825000000-3.413*C5/157 =100*(D5-BS)/D5 35521 3712612 0.14643

=1825000000*3.413*C6/157 =100*(D6-86)/D6 35551 3486114 0.14017

=1825000000*3.413*C7/157 =100*(D7-87)/D7 35582 3298303 0.13487

=1825000000*3.413*Co/157 =100*(D8-88)/D8 35612 3138888 0.13032

=1825000000*3.413*C9/157

=100*(D9-B9)/D9 l

35643 3002399 0.12639

=1825000000*3.413*C10/157 =100*(D10-B10)/D10 35674 2880626 0.12296

=1825000000*3.413*C11/157 =100*(D11-B11)/D11 35704 2773193 0.11994

=1825000000*3.413*C12/157 =100*(D12-B12)/D12 35735 2676575 0.11726

=1825000000*3.413*C13/157 =100*(D13-B13)/D13 l

35765 2589608 0.11486

=1825000000*3.413*C14/157 =100*(D14-B14)/D14 35796 2509618 0.1127

=1825000000*3.413*C15/157 =100*(D15-B15)/D15 l

35977 2145186 0.1032

=1825000000*3.413*C16/157 =100*(D16-B16)O16 l

36161 1902143 0.09723

=1825000000*3.413*C17/157 =100*(D17-B17)/D17 l

36342 1733032 0.09318

=1825000000*3 413*C18/157 =100*(D18-818)/D18 36526 1611378 0.00026

=1825000000*3.413*C19/157 =100*(D19-819)/019 36708 1522712 0.08806

=1825000000*3.413*C20/157 =100*(D20-820)m20 36892 1455651 0.08631

=1825000000*3.413*C21/157 =100*(D21-821)/D21 37073 1404009 0.08484

=1825000000*3.413*C22/157 =100*(D22-822)O22 37257 1363043 0.08355

=1825000000*3.413*C23/157 =100*(D23-823)O23 l

l 37438 1329764 0.08238

=1825000000*3.413*C24/157 =100*(D24-824)/D24 37622 1301812 0.08129

=1825000000*3.413*C25/157 =100*(D25 825)C25 j

37803 1277966 0.08026

=1825000000*3.413*C26/157 =100*(D26-826)/D26 37987 1257001 0.07926

=1825000000*3.413*C27/157 =100*(D27-B27)/D27 38169 1238424 0.07829

=1825000000*3.413*C28/157 =100*(D28-828)O28 38353 1221400 0.07735

=1825000000*3.413 C29/157 =100*(D29 829)m29 38534 1205904 0.07642

=1825000000-3.413*C30/157 = 100*(D30-B30)O30 38718 1191409 0.0755

=1825000000*3.413*C31/157 =100*(D31 B31)/D31 j

38899 1177752 0.0746

=1825000000*3.413*C32/157 =100*(D32-832)/D32 39083 1164836 0.07371

=1825000000*3.413*C33/157 =100*(033-833)/D33 39448 1140660 0.07197

=1825000000*3.413*C34/157 =100*(D34-B34)O34 39814 1118311 0.07027

=1825000000*3.413*C35/157 =100*(D35-835)/D35 40179 1097302 0.06881

=1825000000*3.413*C36/157 =100*(D36-B36)C36 40544 1077269 0.06699

=1825000000*3.413*C37/157 =100*(D37-837)/D37 40909 1058159 0.0654

=1825000000*3.413*C38/157 =100*(D38-838)/D38 41275 1039732 0.06386

=1825000000*3.413*C39/157 =10T(D39-839)C39 41640 1021889 0.06235

=1825000000*3.413*C40/157 =100*(D40-840)/D40 42005 1004665 0.06088

=1825000000*3.413*C41/157 =100*(D41-841)O41 42370 987902.6 0.05944

=1825000000*3.413*C42/157 =100*(D42-B42)C42 2l The first column in this worksheet is displaying the internal date representation for the evaluation dates. Each number is the number of days from Jan.1,1900 to the i

specified date.

I 1

Holtec Report HI-971677 D-6 Holtec Project 70121

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i-t Comparison of Calculated Decay Heat Load ORIGEN-2 vs. ASB 9-2 7,000,000 6,000,000 -

t 5

_ 5,000,000 --

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10/28/199 7/24/1998 4/19/2001 1/14/2004 10/10/200 72/2009 4/1/2012 12/27/201 9/22/2017 m[

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i Page 44 of 46 CALCULATION No. S FP 1575-DY REVISION No.

Rev.I Appendix E Excel Worksheets for Hentup Rate Calculations I

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Holtec Report HI-971677 Holtec Project 70121 page E-1

Page 45 of 46 CALCULATION No. SFP.97-1575-DY REVISION No.

Rev 1 Date Heat Load Heatup Rate (no evsp) f Stu/hr deg F/hr Q keet' N#gg pde W" Da[0-1/1/1997 4,759,102 2.10672953 2/1/1997 4,327,231 1.91555157 3/1/1997 3,986,898 1.76489509 4/1/1997 3,712,612 1.64347587 l

5/1/1997 3,486,114 1.54321116 6/1/1997 3,298,303 1.46007216 l

7/1/1997 3,138,888 1.38950332 i

8/1/1997 3,002,399 1.32908322 l

9/1/1997 2,880,626 1.27517751 10/1/1997 2,773,193 1.22761974 11/1/1997 2,676,575 1.18464949 l

12/1/1997 2,589,608 1.14635148 l

1/1/1998 2,509,618 1.11094201 7/1/1998 2,145,186 0.94961753 1/1/1999 1,902,143 0.84202877 I

7/1/1999 1,733,032 0.76716777 1/1/2000 1,611,378 0.71331474 7/1/2000 1,522,712 0.67406463 1/1/2001 1,455,651 0.64437849 7/1/2001 1,404,009 0.62151793 1/1/2002 1,363,043 0.60338336 7/1/2002 1,329,764 0.58865162 1/1/2003 1,301,812 0.576278 7/1/2003 1,277,966 0.565722 1/1/2004 1,257,001 0.55644135 7/1/2004 1,238,424 0.5482178 1/1/2005 1,221,400 0.54068172 7/1/2005 1,205,904 0.53382205 1/1/2006 1,191,409 0.52740549 7/1/2006 1,177,752 0.52135989 1/1/2007 1,164,836 0.51564232 1/1/2008 1,140,660 0.50494024 1/1/2009 1,118,311 0.49504692 1/1/2010 1,097,302 0.48574679 1/1/2011 1,077,269 0.47687871 1/1/2012 1,058,159 0.46841921 1/1/2013 1,039,732 0.46026206 1/1/2014 1,021,889 0.45236344 1/1/2015 1,004,665 0.44473882 1/1/2016 987,903 0:43731855 l

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Page 46 of 46 CALCULATION No, SFP-97 1 $75.DY REVISION No.

Rev.1 Date Heat Load Heatup Rate gyg p,,,y/qg (no evap)

Stu/hr deg F/hr gy gg 4 pf 35431 4759102

=B4/2259000 35462 4327231

=B5/2259000 35490 3986898

=B6/2259000 35521 3712612

=B7/2259000 35551 3486114

=B8/2259000 35582 3298303

=B9/2259000 35612 3138888

=B10/2259000 35643 3002399

=B11/2259000 35674 2880626

=B12/2259000 35704 2773193

=B13/2259000 35735 2676575

=B14/2259000 35765 2589608

=B15/2259000 i

35796 2509618

=B16/2259000 35977 2145186

=B17/2259000 36161 1902143

=B18/2259000 36342 1733032

=B19/2259000 36526 1611378

=B20/2259000 36708 1522712

=B21/2259000 36892 1455651

=B22/2259000 37073 1404009

=B23/2259000 37257 1363043

=B24/2259000 37438 1329764

=B25/2259000 a

37622 1301812

=B26/2259000 37803 1277966

=B27/2259000 37987 1257001

=B28/2259000 38169 1238424

=B29/2259000 38353 1221400

=B30/2259000 38534 1205904

=B31/2259000 38718 1191409

=B32/2259000 38899 1177752

=B33/2259000 39083 1164836

=B34/2259000 39448 1140660

=B35/2259000 39814 1118311

=B36/2259000 40179 1097302

=B37/2259000 40544 1077269

=B38/2259000 40909 1058159

=B39/2259000 41275 1039732

=B40/2259000 41640 1021889

=B41/2259000 42005 1004665

=B42/2259000 42370 987902.6

=B43/2259000 The first column in this worksheet is displaying the internal date representation for the evaluation dates. Each number is the number of days from Jan.1,1900 to the specified date.

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