Text

Attachment 5 to W3Fl-2004-0073, Additional Information Regarding EPU Spent Fuel Pool Cooling Analysis
	ML042440429
Person / Time
Site:	Waterford
Issue date:	02/02/2004
From:	; Entergy Nuclear South, Entergy Operations
To:	; Office of Nuclear Reactor Regulation
References
	W3F1-2004-0073
	Download: ML042440429 (40)
	v • d • e

Attachment 5 To W3Fl-2004-0073 Additional Information Regarding EPU Spent Fuel Pool Cooling Analysis

rDRN No.

03- /4'40 Pages.2 3R, "CALCULATION Init. Doc.: ER-W3-2001-1149-000 Superseded DRN:

NIA COVER PAGE 03 Pending/lICN Required Ol As-Built/No ICN Required calculation Immediately incorporate/No ICN Required 0 Calculation Change OReason For Pending Status: (ER, T.S., Change, etc.)

ER-W3-2001-1149-000 (4"CALCULATION NO:

ECS96-003

"'REVISION:

0

"'TITLE: Spent Fuel Pool Heat Loads for a Full Spent Fuel Pool and SFP Cask Storage Aroa mSystem: Spent Fuel Pool t'Component No:

"'Safety Code:

'"Calc Code: (ANO/GGNS Only) 0 Yes E No E Quality

("'10CFR50.59 Review

"'Structure: (ANO Only) 0 Addressed In ER-W3-2001-1149-009 Bldg.

El Attached Room El No LBD Impact Coordinates:_

'"R-Type: F'1lt3 1 6 3. q ° Org. Code: (ANO/GGNS Only)

"Keywords: spent fuel pool, fuel pool heat exchanger, fuel discharge, fuel assemblies, decay heat, decay heat loads 4'e'(Print Name/Signature/Date) t"'n(Print Name/Signature/Date)

C'l(Print Name/Signature/Date)

Responsible Engineer El Design Verifier SupervisorlApproval 0 Reviewer Comments Attached E O Checker Comments Attached El

Reasonableness Review per DC-126, Sect. 5.8 (Rev. 0)

0 2DRN No.

03-i4'yP Pages ra s

(')CALCULATION Init. Doc.: ER-W3-2001-1149-000 Superseded DRN:

N/A COVER PAGE 0

PendinglCN Required E]

As-Bullt/No ICN Required j Calculatlon El Immediately IncorporatelNo ICN Required 0 Calculation Change 13Reason For Pending Status: (ER, T.S., Change, etc.)

ER-W3-2001-1149-000 (4)CALCULATION NO:

ECS96-003

()REVISION:

0

(")TITLE: Spent Fuel Pool Heat Loads for a Full Spent Fuel Pool and SFP Cask Storage Area

'r)System: Spent Fuel Pool f'1Component No:

(9)Safety Code:

(10'Calc Code: (ANOIGGNS Only) 0 Yes E No

[E Quality (1"0CFR50.59 Review (2)Structure: (ANO Only) 0 Addressed In ER-W3-2001-1149-009 Bldg.

O Attached Room El No LBD Impact Coordinates:

")R-Type:64 3

.2 4

a l

.0Org.

Code: (ANO/GGNS Only)

'5)Keywords: spent fuel pool, fuel pool heat exchanger, fuel discharge, fuel assemblies, decay heat, decay heat loads IM Don Haun d/SA xZ 1

Warrene Cox Cl6)(Print Name/Signature/Date) l "7(Print Name/Slgnature/Date) l (8)(Print Name/Signature/Date)

Responsible Engineer l

Design Verifier Supervisor/Approval l

Reviewer Comments Attached O l l Checker Comments Attached Ol

CALCULATION CALCULATION NO:

ECS96-003 REFERENCE SHEET lREVISION:

0

1.

DRNs INCORPORATED: None IL.

RELATIONSHIPS: (7 total)

Document No.

Sht Rev DRN Document No.

Sht Rev DRN INPUTS:

ECM98-022 I

A N/A ECM98-067 1

A N/A OUTPUTS:

MNQ9-9 1

4 03-729 MNQ9-65 1

1 03-728 MN9Q9-17 1

2 03-727 MNQ9-3 1

2 03-726 RF-005-001 0

9 Note I Note 1: Refer to ER-W3-2001-1149-000 Ill.

CROSS

REFERENCES:

(4 total)

1. NEAD Letter, DE-96100005, "Waterford 3 Fuel Performance Summary, January 5, 1996.

2.

USNRC Branch Technical Position Paper ASB 9-2, "Residual Decay Energy for Light Water Reactors for Long Term Cooling."

3.

CWTR3-03-160, "Transmittal of Watcrford-3 3716 MWt Uprate Task 2.1 Deliverables", dated October 15, 2003

4.

P05.13 IV.

SOFTWARE USED:

Title:

MicroSoft Excel Version/Release:

97 SR2 Disk/CD No. NA

Title:

N/A Version/Release:

N/A Disk/CD No. NA DISKICDS INCLUDED:

Title:

NIA Version/Release N/A Disk/CD No. NA.

V.

OTHER CHANGES: None

DESIGN VERIFICATION RECORD Pago I

of 2

Document Number ECS6-003 Revision DRN 03-1440 METHOD aw I-;s Verification methods to be used:

X Design Review Qualificatlon Testing Alternate Calculations DOCUMENT(S) REVIEWED: (Attach Additional Sheet(s), If needed)

Document Number Revision ar, 1.

Document Title ECS96-003 DRN 03-A4 SDent Fuel Pool Heat Load for a Full SDent Fuel Pool and SFP Cask Storage Area

SUMMARY

OF REVIEW: (Attach Additional Sheet(s). If needed)

The review verified the Input and assumptions, as well as, methodology used to determine the bounding additional decay heat loads on the Waterrord 3 spent fuel pool due to the core power Increase to 3716 MWL Design Verification Completed By Warren Cox (Enercon) KZSxv-Date:

It / e' Comment Resolutions Accepted By NIA Date:

Engineering Supervisor Ralph Schwartzbeck

-Enercn)

a.

,Date:

-9A,, I IV

/

/I

DESIGN VERIFICATION RECORD Page 2

of 2

Lrc I' Document Number ECS96-003 Revision DRN 03-1440 CN-T l ClACPT I INITMD CMTICOMMENT RESOLUTIONYI AT

.0 None All comments and questions were resolved without requiring documentation.

WATERFORD 3 ENGINEERING E

ntIt y

GENERAL COMPUTATION SHEET CALC. NO.:

ECS96-003 PAGE:

I REF TABLE OF CONTENTS Page No.

TABLE OF CONTENTS.............................

I LIST OF EFFECTIVE PAGES...........................

II 1.0 Purpose..........................

1 2.0 References..........................

1 3.0 Method..........................

1 4.0 Input Criteria and Assumptions..........................

3 5.0 Results Summary..........................

4 6.0 Calculations..........................

6

.5.-

WATERFORD 3 ENGINEERING GENERAL COMPUTATION SHEET CALC. NO.: ECS96-003 PAGE ii LIST OF EFFECTIVE PAGES PAGE REVISION DRN 03-1440 Calculation 1-7 Attachments:

1 2

3 4

5 1-5 1-5 1-2 1-4 1-2 DRN 03-1440 DRN 03-1440 DRN 03-1440 DRN 03-1440 DRN 03-1440 REVISION DESCRIPTION OF AFFECTED NO.

REVISION PAGES 0

Original Issue All Change 1 Changed the calculation to support DC-3465.

All DRN 03-Changed the calculation to support a 15 day outage, an 18 All 1440 month fuel cycle and a core uprate to 3716 MWt. This Is a complete re-write of the calculation and thus, no revision bars will be used. Attachments I and 11 have been replaced by Attachments 1-5. Decay heat loads are calculated using ASB 9-2 methodoligy.

WATERFORD 3 DESIGN ENGINEERING ktet Y GENERAL COMPUTATION SHEET CAMC. NO.

ECS96-003 PAGE I

OF 7

1.0 Purpose

This calculation evaluates the spent fuel pool (SFP) heat load (decay heat), for use in calculations MN(Q)-9-3. "Ultimate Heat Sink Study" and MN(Q)9-9, "Wet Cooling Tower Losses During LOCA" at various times after shutdown for the following storage conditions:

SFP contains a total of 1,849 spent fuel assemblies (FA) with 1,792 previously stored assemblies plus 108 assemblies discharged during the last outage.

SFP contains a total of 1,849 spent fuel assemblies (FA) with 1,684 previously stored assemblies plus 217 assemblies discharged during the last outage.

SFP & SFP cask storage area contain a total of 2,104 spent fuel assemblies (FA) with 2,008 previously stored assemblies plus 108 assemblies discharged during the last outage.

SFP & SFP cask storage pit contain a total of 2,104 spent fuel assemblies (FA) with 1,900 previously stored assemblies plus 217 assemblies discharged during the last outage.

The decay heat loads are calculated at 3 (72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ), 5 (120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months ), 7 (168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months ), 10 (240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months ), 15 days (360 hours0.00417 days 0.1 hours 5.952381e-4 weeks 1.3698e-4 months ) and 1 month (720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months ) after reactor shutdown.

This calculation also provides updated Spent Fuel Pool Cooling Capability for.5 of Refueling Procedure RF-005-001.

2.0

References:

1. Calculation EC-M98-022, Rev 0, CN-1, Thermal - Hydraulic Analysis of Waterford 3 Spent Fuel Pool"

2. USNRC Branch Technical Position ASB 9-2, Residual Decay Energy for Light-Water Reactors for Long-Term Cooling Rev 2 - July 1981

3. NEAD Letter, DE-96/00005, Waterford 3 Fuel Performance Summary, January 15, 1996.

4. Calculation EC-M98-067, Rev 0, CN-1, "Limiting Thermal-Hydraulic Analysis of Waterford 3 Spent Fuel Pool"

3.0 Method

Ref. 1 provides a thermal-hydraulic analysis of the Waterford 3 Spent Fuel Pool cooling system after the Installation of HOLTEC high density fuel storage racks and a proposed core thermal power uprate to 3661.2 MWt. Appendix L to Ref. I extends the results of the original analysis to confirm that the calculated heat loads on the SFP

is WATERFORD 3 DESIGN ENGINEERING

.L11UX15 GENERAL COMPUTATION SHEET CALC. NO.

ECS96-DO03 PAGE 2

OF 7

cooling system bound the heat loads associated with a 3716 MWt core power uprate.

An Excel spreadsheet was developed In Appendix L that summarizes refueling offloads to the SFP and calculates the decay heat contributions from each offload to the total heat load on the SFP cooling system. Decay heat loads for stored fuel are calculated In accordance with the equations provided in Ref. 2. A time dependent decay power fraction is calculated for each refueling discharge to the SFP and to the SFP cask storage area. These power fractions are then used to calculate power generation factors that relate decay powerof the spent fuel to average full power rating of an Individual fuel assembly. These power factors can then be summed for each specific core power rating and then the totals converted from power ratings In Kw to heat rates In Btulhr. The heat rates are then added to establish a total heat rate contribution for all tho previously stored offloads.

Because these offloads have storage times that are counted in years since reactor shutdown, the sum of their respective heat loads Is called the background decay heat load and Is treated as a constant during the thermal evaluation of the most recent refueling offloads impact on the cooling system.

The total decay heat load on the cooling system for the SFP or the SFP/ SFP cask storage area Is then the sum of the background decay heat load from the previous refueling discharges plus the decay heat load from the current refueling discharge.

Decay heat is a strong function of time after reactor shutdown. Thus the heat load contribution from the current or latest offload dominates the total heat load on the cooling system. Total decay heat loads for the most recent discharge are reported at 3, 5, 7, 10, 15 days and I month after shutdown to illustrate the rapid decline in decay heat over time.

The decay power fractions that ultimately determine the decay heat loads of the spent fuel assemblies are calculated In accordance with the equations in Ref. 2 and are generated In Attachment 3 of this calculation. The two critical dependent variables In these equations are the cumulative reactor operating time of the fuel assemblies and the time after reactor shutdown. The fission product decay term in the decay energy calculation includes an uncertainty factor K. A typographical error In the application of the uncertainty factor K In Ref. 2 for fission product decay calculation has been corrected in the power fraction calculations in Attachment 3. When calculating decay power fractions per Attachment 3 the following Input data was used:

Fuel assemblies have a cumulative operating time of 4.5 years.

Refuelings are performed on an 18 month cycle.

Power fractions for the most recent offload at 3, 5, 7, 10, 15 days and Imonth after reactor shutdown.

is WATERFORD 3 DESIGN ENGINEERING

.LteUX5 GENERAL COMPUTATION SHEET CALC. NO.

ECS96.003 PAGE 3

OF 7

4.0 Input Criteria And Assumptions:

The Important Input parameters to this calculation are the number of fuel assemblies discharged at each refueling outage, the power level of the core for the discharged assemblies, the cumulative storage times for each of the previous offloads and the respective times after reactor shutdown for determining the decay heat loads for the current refueling offload. The Excel spreadsheet format developed In Ref. I is used to capture all the required Input data and then to calculate the decay heat loads. has the spreadsheets generated for a partial core offload of 108 assemblies to the SFP and for a full core offload to the SFP. Attachment 2 has comparable spreadsheets for a partial core offload of 108 spent assemblies to the SFP/SFP Cask Storage Area and for a full core offload to the SFP/SFP Cask Storage Area. The prime difference between the two attachments is In the overall storage capacity available. In Attachment 1 the SFP has a total storage capacity of 1,849 assemblies with the HOLTEC high density storage racks. The number of previously stored fuel assemblies Is adjusted between the partial core oMoad event and the full core offload event to ensure that the total number of stored assemblies Is close to 1,849. In Attachment 2 the SFPISFP Cask Storage Area has a total storage area of 2,104 assemblies with the HOLTEC high density storage racks In place.

The Excel spreadsheets In Attachments I and 2 consist of eleven columns of data.

The first seven columns all relate to refueling offloads. They Indicate the number of assemblies offloaded during a particular refueling outage, the core power level associated with the discharged fuel, the cumulative number of assemblies placed In storage after the offload and the years since discharge for each offload. The storage times In the column labeled 'Years Since Discharge* Index by 18 month Increments as each subsequent offload is transferred to the SFP.

Historical data Is provided for refueling cycles I through 11 for the 3390 MWt core. Offload estimates of 92 spent assemblies are assumed for cycles 12 and 13 for the 3441 MWt core. Offloads of 108 spent fuel assemblies per discharge are assumed for each refueling outage after the 3716 MWt uprate is implemented. The number of cycles that Is Included In a given spreadsheet is dependent upon the storage capacity of the SFP or the SFP/SFP Cask Storage Area. is based on decay heat loads due to a full SFP. is based on a full SFP and Cask Storage Area. The number of spent assemblies used In the decay heat load calculations exceeds the actual storage capacity of the SFP or the SFP/SFP Cask Storage Area to provide some conservatism to the total heat loads being reported.

Columns 8 thru 10 are used to calculate the decay heat contribution of the discharged assemblies. The column headed Power Fractions Based on ASB 9-2 provides the decay heat fraction based on the time value since the fuel was discharged from the

WATERFORD 3 DESIGN ENGINEERING JUe 5

GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 4

OF 7

reactor. The actual values are taken from Attachment 3. The power fraction is then multiplied by the number of assemblies in a given offload to obtain a Power Generation Factor which are listed in column 8. All the power generation factors associated with a specific core power level are then total In column 9. The decay heat load from all of the spent fuel assembly discharges from a given core power level Is then the product of the sum of the power generation factors In column 9 and the average full power rating of an Individual fuel assembly at the given core power rating.

As an example 2 (core power factors for the 3390 MWt assemblies) x (3390 MW/217

.core assemblies) gives the heat load In MW for all the stored assemblies from the 3390 MW core design. The actual decay heat of an Individual spent fuel assembly Is a strong function of the assembly's power fraction In the core, especially during Its last cycle. Since the discharged assemblies in an offload will have much lower power ratings compared to the core average, this method for determining decay heat load is very conservative, and over estimates the decay heat load for a normal refueling outage but not a full core off-load.

A summary of the assumptions used to generate the decay heat loads in Attachments I and 2 are as follows:

all refueling outages are performed on an 18 month fuel cycle core power level is 3390 MWt for cycles I thru 11 core power level Is 3441MWt for cycles 12 and 13

core power uprate to 3716 MWt power level Impacts cycles 14 and beyond calculations of decay heat loads Include a 2% uncertainty on the power level of the 3390 MWt core assemblies and a 0.5% uncertainty on the 3441 and 3716 MWt core assemblies decay power fractions In accordance with ASB 9-2 are used to calculate the decay heat load for refueling offloads that comprise the background heat load (see attachment 3)

All power fractions include a "K" uncertainty factor of 0.1 In the fission product decay term.

5.0 Results Summary:

The following table provides the total decay heat for a full SFP at 3, 5, 7, 10, 15 and 30 days after reactor shutdown. The decay heat values are based on the storage capacity of the SFP being limited to 1,849 assemblies with the high capacity HOLTEC storage racks in place. For the partial core offload of 108 assemblies the background decay heat is based on 1,792 previously stored assemblies from 19 fuel cycles. For

WATERFORD 3 DESIGN ENGINEERING GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 5

OF 7

the full core offload of 217 assemblies the background decay heat is based on 1,684 previously stored assemblies from 18 fuel cycles.

Time After Shutdown (days) 3 5

7 10 15 30 Decay Heat (106 Btulhr) 108 Assembly Discharge 32.73 27.46 24.55 22.06 19.73 15.98 Decay Heat (106 Btulhr)

Full Core Discharge 59.79 49.21 43.36 38.36 33.66 26.14

- The following table provides the total decay heat for a full SFP & SFP Cask Storage Area at 3, 5, 7, 10, 15 and 30 days after reactor shutdown. The decay heat values are based on the storage capacity of the SFP & SFP Cask Storage area being limited to 2,104 assemblies with the high capacity HOLTEC storage racks In place. For the partial core offload of 108 assemblies the background decay heat Is based on 2,008 previously stored assemblies from 21 fuel cycles. For the full core offload of 217 assemblies the background decay heat is based on 1,900 previously stored assemblies from 20 fuel cycles.

Timo After Shutdown (days) 3 5

7 10 15 30 Decay Heat (108 Btu/hr) 108 Assembly Discharge 33.17 27.91 24.99 22.51 20.17 16.42 Decay Heat (106 Btu/hr)

Full Core Discharge 60.24 49.67 43.81 38.82 33.12 26.59

to WATERFORD 3 DESIGN ENGINEERING hLJIt Iy GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 6

OF 7 provides an update to the offloading data provided in Attachment 9.5 of Refueling Procedure RF-005-001. The changes result from new estimates on spent fuel decay heat loads due to corrections to the power fraction equations in ASB 9-2 and SFP heat exchanger heat duty limits from Ref. 4. Revised CCW temperature requirements to support a full core offload are also reported. The CCW temperature requirements reflect updated SFP HX performance predictions from Ref. 1. provides updated shutdown offloading times If the Backup SFP HX Is used to handle the decay heat loads from a partial core offload or a full core offload after the 3716 MWt uprate.

6.0 Calculations

The total decay heat is calculated for the SFP containing approximately 1849 spent fuel assemblies with either a partial core offload of 108 assemblies or a full core discharge of 217 assemblies as the last refueling outage, for 3, 5, 7, 10, 15 and 30 days after shutdown. This calculation Is then repeated for the SFP containing 1849 assemblies and the SFP Cask Storage Area containing and additional 255 spent assemblies (2104 total assemblies). Decay heats are reported at 3, 5, 7, 10, 15 and 30 days after shutdown. The decay power fractions for the refueling cycles forming the background decay heats as well as the values used at 3, 5, 7, 10, 15 and 30 days after shutdown were taken from an Excel spreadsheet based on the equations In ASB 9-2. A copy of the Excel spreadsheet and resulting power fractions is provided as. The power fraction terms all include a K uncertainty factor of 0.1 in the fission product docay term as specified In the Standard Review Plan, NUREG-0800.

The time to boiling, for the SFP containing a total of 1849 fuel assemblies, based on:

(1) Initial pool temperature of 1200F, (2) minimum water level above the fuel assemblies and (3) 15 days after plant shutdown with 108 recently discharged fuel assemblies (19.73 x106 Btulhr total decay heat) Is calculated below. The SFP water volume which is based on minimum required water level of 23 ft above the fuel assemblies Is calculated In Rof. 3. The not volume (Ref. 3, page 73) Is 33,700 fte.

The use of this volume In the boiling time calculation Is conservative following the SFP reracking (performed prior to refuel 9) because: (1) the volume of the new HOLTEC storage racks is less than the volume of the Wachter racks used In Ref. 3. (2) as part of the reracking Gate #1 (which separates the SFP from the Cask Storage Pit ) is administratively prevented from being Installed (following the reracking fuel will also be stored In the Cask Storage Pit and Installing Gate #1 would Isolate this fuel from the intake and discharge of the Spent Fuel Pool Cooling System. There is therefore more water volume In the SFP following the reracking and this volume Is Increased once the Cask Storage Pit Is placed Into service.

WATERFORD 3 DESIGN ENGINEERING

.L11(IJ5 GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 7

OF 7

The time to boiling:

t(hr) = M(lbm) x Cp(Btu/lbm,0F) x AT(0F) I Q(Btu/hr) where:

M: mass of water in SFP (Ibm)

Cp: heat capacity of water = 1.0 (Btu/lbm,F0) for the temperature range of Interest 0: decay heat rate (Btu/hr)

M = 33,700 ft5 x 61.7 (Ibm/ft) = 2.079 x 106 Ibm t(hr) = 2.079x10 Ibm x 1 (Btu/lbm,F0) x (212-120) (F) / 19.73x10O (Btulhr) t(hr) = 9.7 hrs The time to boiling, for the SFP/SFP Cask Storage Pit containing a total of 2104 fuel assemblies, based on: (1) initial pool temperature of 1200F, (2) minimum water level above the fuel assemblies and (3) 15 days after plant shutdown with 108 discharged assemblies (20.17x106 Btu/hr total decay heat) Is calculated below. The SFP water volume which is based on minimum required water level of 23 ft above the fuel assemblies derived from Appendix E of Ref. 1. Appendix E page E-2 provides the following expression for the thermal Inertia of the SFP and Cask Storage Pit.

Pool thermal Inertia = [0.547

19,665.8 + 27, 844.8]

61.09 = 2.35 x IQ6 Btu/hr The terms in the bracket represent the total volume of water In the SFP/SFP Cask Storage pit. The term 27,844.8 Is the volume in cubic feet of water above the storage racks and the term 0.547*19665.8 Is the volume of water In the rack structure. The total volume of water in cubic feet is thus 38,602 fle. Substituting this into the equations above gives M = 38,602 ft3 x 61.7 (Ibmlft3) = 2.38 x 10 Ibm t(hr) = 2.38x108 Ibm x I (Btu/lbm,F0) x (212-120) / 20.17x1 06 (Btulhr) t(hr) = 10.86 hrs

at WATERFORD 3 DESIGN ENGINEERING ahteW1 GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003, Attachment I PAGE 1

OF 3

The following Excel spreadsheet calculates the decay heat load contribution for each refueling outage from RF cycle I to RF cycle 20. The following assumptions were made In developing this spreadsheet:

1. The nominal core power level for cycles I thru 11 is 3390 MWL

2. The nominal core power level for cycles 12 and 13 Is 3441 MWt

3. The power uprate to 3716 MWt impacts the spent fuel assemblies starting with Cycle 14.

4. The number of spent assemblies offloaded for cycles 1 thru 11 represents historical plant data.

5. Offloads for Cycles 12 and 13 are assumed values.

6. The maximum number of spent fuel assemblies discharged after the uprate to 3716 MWt Is 108 spent fuel assemblies per outage.

7. Decay power fractions are based on ASB 9-2. All power fraction calculations Include a K term with a value of 0.1 In the fission decay term.

B. Power level uncertainty factors are applied to all decay heat calculations. A 2% uncertainty factor is applied to the 3390 MWt core and a 0.5% uncertainty factor is applied to the 3441 and 3716 MWt cores.

The values In the column labeled 'Non Dim Power Gen Factor' are the product of the number of assemblies discharged In a cycle multiplied by the power fraction value for that particular cycle.

The decay heat spreadsheet Is patterned after the master version In calculation EC-M98-022 Appendix L. Long term decay times are adjusted based on the number of refueling outages required to fill the respective storage capacity being evaluated. In this attachment, spent fuel storage Is limited tol849 assemblies.

ECS96-003, Attachment I Page 2 of 5 Decay Heat Load Due to Full SFP Partial Core Offload SFP Capacity Limited to 1849 Assemblies CYCLE Assemblies Cumulative Years Since Non Dim Power Sum of Power EFPY Discharged Fuel Pool Discharge Gen. Factor Power Gen Fractions

(# assys x P.F.)

Factors Based on ASB 9-2 Cycle Nom EOC No.

Power Date (MWO 1

3390 11/26/88 2

3390 04101188 3

3390 09/23189 4

3390 03115/91 5

3390 09/20/92 6

3300 03/04/94 7

3390 09122195 8

3390 04/11/97 9

3390 0210S/93 10 3390 09115100 11 3390 03/15102 12 3441 09/15/03 13 3441 03115/05 14 3716 09115/06 15 3716 03/15108 16 3715 09/15109 17 3718 03/15111 18 3716 0911512 19 3716 03/15/14 20 3716 09/15/15 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 92 84 84 84 84 92 96 84 92 92 76 92 02 108 108 108 108 108 108 108 92 178 260 344 428 520 e16 700 792 884 960 1052 1144 1252 1360 1468 1576 1684 1792 1900 29 27.5 26 24.5 22.92 21.1 19.5 18 16.5 15 13.5 12 10.5 9

7.5 6

4.5 3

1.5 72 hrs 99 hrs 106 hrs 120 hrs 168 hrs 184 hrs 240 hrs 360 hrs 720 hrs 0.002941737 3.197540E-05 0.002784055 3.314351E-05 0.002885761 3.435430E-05 0.002991182 3.560931E-05 0.003108393 3.698087E-05 0.003553627 3.662638E-05 0.003852801 4.013335E-05 0.003494358 4.159950E-05 0.003966972 4.311926E-05 0.004111919 4.469477E-05 0.003520982 0.0372098 4.B32871E-05 0.004418388 4.802595E-05 0.004581581 0.0990000 4.97998QE-05 0.005583343 5.169762E-05 0.005821709 5.390471E-05 0.006173838 5.716516E-05 0.006964770 6.448881E-05 0.009516738 8.811793E-05 0.019901933 0.0539623 1.842772E-04 Heat Load per Assy Btu/hr 1,705 1,767 1,832 1,899 1.972 2.059 2.140 2.218 2,299 Z383 2.470 2,561 2.911 3.022 3.150 3.341 3,769 5,150 10,770 249.143 218.137 211.780 200.653 173.818 167,469 150.910 129,362 94.852 0.460384118 0.403087995 0.391341308 0.370780526 0.321192409 0.309461029 0.278861811 0.239044167 0.17527449 4.262816E-03 3.732296E-03 3.623531E-03 3A33153E-03 2.974004E-03 2.865380E-03 2.582054E-03 2.213372E-03 1.622912E-03

ECS96-003, Attachment I Page 3 of 5 Background decay heat load due to 19 previous refueling offloads 5,683,149 Btulhr Where the background decay heat load Is calculated as follows Background heat load a 0.0372098133900001.023413/217+0.009-3441000 1.005 3413 217+.0.0539623 3716000-1.005 3413/217 Decay heat due to partial core offload at times Indicated This Is the 3 day lRmiting heat value assuming all assembles offloaded at one lime This Is the heat load at completion of oflIad assumlhg a start time 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reactor shutdown and a maximum of 4 assemblies per hour transferred to storage Approximate time Men pool reaches maximum bulk temperature for 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months hold before fuel transfer Is Initiated 72 hrs 99 hrs 106 hrs 27,045,032 23,679,200 Btuthr Btu3hr 22,989,147 Btu/hr 120 hrs 168 hrs 184 hrs Approximate time when pool reaches peak temperature for a 7 day hold prior to all Jel being discharged 21,781,314 18,868.285 18,179,131 16,381,596 14,042,528 10,296,411 Btu/hr Btulhr Btulhr Btu/hr Bth/hr Btulhr 240 hrs 360 hrs 720 hrs Where decay heat due to partial core offload equals Non Dim Power Gen Factor at time

373500034131217 Example at 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months partial decay heat load = 0.460384118-3735000134131217 = 27,045,032 Total Decay Heat Loads at times Indicated equals partial heat load plus background heat load 72 Irs 32,728,181 Btu/hr 99 hrs 29,362,349 Btu/hr 108 Irs 28,672,296 Btu/hr 120 hrs 27,464,463 Btuhr 168 hrs 24,551,434 Btuhr 184 hrs 23,862,280 Btu~hr 240 hrs 22,064,745 Btuihr 360 trs 19,725,677 Btu/hr 720 Irs 15,979,560 Btulhr

ECS96-003, Attachment 1 Page 4 of 5 Decay Heat Load Due to Full SFP Full Core Offload SFP Capacity Limited to 1849 Assemblies Cycle Nom EOC No.

Power Date (MWt) 1 3390 1126/86 2

3390 04101188 3

3390 09123/89 4

3390 03/15/91 5

3390 09/20/92 6

3390 03/04/94 7

3390 09/2295 8

3390 04/11/97 9

3390 02/05/99 10 3390 09115100 11 3390 03115/02 12 3441 09/15103 13 3441 03/15105 14 3716 09/15/08 15 3718 03/15/08 16 3716 09115109 17 3716 03115/11 18 3716 09115112 19 3716 03115/14 CYCLE Assemblies EFPY Discharged 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 92 84 84 84 84 92 96 84 92 92 73 92 92 108 108 108 108 108 Cumulative Fuel Pool 92 176 280 344 428 520 616 700 792 884 960 1052 1144 1252 1360 1468 1576 1684 Years Since Discharge 27.5 26 24.5 22.92 21.1 19.5 18 16.5 15 13.5 12 10.5 9

7.5 6

4.5 3

1.5 Non Dim Power Sum of Power Gen. Factor Power Gen Fractions

(# assys x P. F.)

Factors Based on ASB 9-2 0.003049203 3.314351E-05 0.002885781 3.435430E.05 0.002991182 3.560931E-05 0.003106393 3.698087E-05 0.003244818 3.862638E-05 0.003692268 4.013335E-05 0.003993552 4.159950E-05 0.003622018 4.311926E-05 0.004111919 4.469477E-05 0.004262242 4.632871E-05 0.003849973 0.0386091 4.8025952-05 0.004581581 4.979980E-05 0.004756181 0.0093378 5.169762E-05 0.005821709 5.390471E-05 0.006173838 5.716516E-05 0.006964770 8.448881E-05 0.00951673e 8.811793E-05 0.019901933 0.0483790 1.842772E-04 Heat Load per Assy Btu/hr 1,767 1.832 1,899 1,972 2.059 2,140 2,218 2.299 2.383 2,470 2,561 2.695 2,798 3,150 3.341 3,769 5,150 10.770 249,143 196.275 200.653 173.818 150.910 129,382 94,852

(

4.5 217 1901 72 hrs 126.25 hrs 120 firs 168 hlr 240 hlr 360 hrs 0.925031051 0.728739120 7.449942E-01 6.453588E-01 5.603057E-01 4.803017E-01 4.262816E-03 3.358245E-03 3.433153E-03 2.974004E-03 2.582054E-03 2.213372E-03 1.622912E-03 720 hrs 3.521719E-91

ECS96-003, Attachment 1 Page 5 of 5

- Background decay heat load due to 18 previous refueling loads 5,449,634 Btulhr Where decay heat load Is calculated by the folowing expression Heat load = 0.0386091-3390000 1.02-3413/217+0.0093378 344100061.005 3413127+0.0483793735000 3413/217 Full core offload decay heat load at times Indicated This Is 3 day llmliing heat vaue assuming all assembies offloaded at one time This is total time to offload full core starting at 72 hrs after shutdown and transferring 4 assembnles/hr 72 hrs 126.25 hrs 120 his 168 hrs 240 hrs 360 hrs 720 irs 54,340,480 Blu/hr 42,809,410 Btuthr 43,764,307 37,911,277 32,914,873 28,215,080 20,688,159 Btuihr Bbu/r Obtul Stulhr BtuLft Decay heat duo to ful core offload Is calculated by Heat Load = Non Dim Power Gen Factor 373500

3413/217 Total Decay Heat Load due to Full Core Offload at time 72 irs 120.25 i7S 120 h's 168 hrs 240 Irs 360 hrs 720 irs 59,790,114 48,259,044 49,213,941 43,360,911 38,364,507 33,664,714 26,137,793 BATur Bhu/hr Btulhr Bhu/hr atuihr Btu/hr Btulhr

AM' WATERFORD 3 DESIGN ENGINEERING DEdfeg GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003, PAGE i

OF 5

The following Excel spreadsheet calculates the decay heat load contribution for each refueling outage from RF cycle I to RF cycle 22.

The following assumptions wore made In developing this spreadsheet:

1. The nominal core power level for cycles 1 thru 11 is 3390 MWt.

2. The nominal core power level for cycles 12 and 13 Is 3441 MWI

3. The power uprate to 3716 MWt Impacts the spent fuel assemblies starting with cycle 14.

4. The number of spent assemblies offloaded for cycles I thru 11 represents historical plant data

5. Offloads for cycles 12 and 13 are assumed values.

6. The number of spent fuel assemblies discharged after the uprate to 3716 MWt Is a maximum of 108 assemblies per outage.

7. Decay power fractions are based on ASB 9-2. All power fraction calculations Include the K factor with a value of 0.1 In the fission decay term.

8. Power level uncertainty factors are applied to ar decay heat calculations. A 2% uncertainty Is applied to the 3390 MWt core and a 0.5% uncertainty Is applied to the 3441 and 3716 MWt cores.

The values In the column labeled 'Non Dim Power Gen Factor' are the product of the number of assemblies discharged In a cycle multiplied by the power fraction value for that particular cycle. The decay heat spreadsheet Is patterned after the master version in calculation EC-M98-022 Appendix L Long term decay times are adjusted based on the number of refueling outages required to fill the respective storage capacity being evaluated. In this attachment spent fuel assemblies are stored In the SFP & Cask Storage area. The total storage capacity Is limited to 2104 spent assemblies.

ECS96-003, Attachment 2 Page 2 of 5 Decay Heat Load Due to Full SFP & Cask Storage Area Partial Core Offload SFP Capacity Limited to 2104 Assemblies Cycle No.

Nom EOC Date CYCLE Power EFPY (MWt)

Assemblies Discharged Cumulative Fuel Years Since Non Dim Power Sum of Power Fractions Heat Load per Pool Discharge Gen. Facto Power Gen Based on ASB 9-2 Assy Btulhr

(# assys x P. F.)

Factors 1

3390 11/26/86 2

3390 04101188 3

3390 09/23/89 4

3390 03/15/91 5

3390 09120/92 a

3390 03104/94 7

3390 09/22/95 8

3390 04111/97 9

3390 0205M9 10 3390 09115100 11 3390 03/15/02 12 3441 09115103 13 3441 03115105 14 3716 09/15/06 15 3716 03/15/08 16 3718 09/15/09 17 3716 03/15/11 18 3716 09/15112 19 3716 03/15/14 20 3716 09115/15 21 3716 03/15117 4.5 92 4.5 84 4.5 84 4.5 84 4.5 84 4.5 92 4.5 96 4.5 84 4.5 92 4.5 92 4.5 76 4.5 92 4.5 92 4.5 108 4.5 108 4.5 108 4.5 108 4.5 108 4.5 108 4.5 108 4.5 108 92 176 260 344 428 520 616 700 792 884 960 1052 1144 1252 1360 14B8 1576 1684 1792 1900 2008 32 30.5 29 27.5 26

.24.5 22.92 21.1 19.5 18 18.5 15 13.5 12 10.5 9

7.5 6

4.5 3

1.5 2.738034E403 2.591271E403 2.685934E403 2.784055E403 0.002885761 0.003276057 0.03550164 0.003244616 3.f92268E403 0.003827154 0.003277064 0.0345524 0.004111919 0.004262242 0.0083742 0.005186803 0.005378378 0.005583343 0.005821709 0.006173838 0.006964770 0.0095f6736 0.019901933 0.0645275 2.976124E-05 3.08484BE-O5 3.197540E-05 3.314351E.05 3A35430E-05 3.560931E-05 3.698087E-05 3.862638E-05 4.013335E-05 4.159950E-05 4.311926E-05 4.469477E-05 4.632871E-05 4.802595E05 4.979980E-05 5.169762E-05 5.390471E405 5.716516E-05 B.443861E-05 8.811793E-05 1.842772E-04 1,587 1,645 1.705 1,787 1.832 1.899 1,972 2,059 2.140 2,218 2,299 2,383 2,708 2,807 2,911 3,022 3.150 3.341 3,769 5,150 10,770

ECS96-003, Attachment 2 Page 3 of 5 22 3716 09115118 4.5 103 210 72hrs 0.460384118 0.004262816 99 Ivs 0.403087995 0.003732296 120 hrs 0.370780526 0.003433153 168hrs 0.321192409 0.002974004 240 hrn 0.278861811 0.002582054 360 hrs 0239044167 0.002213372 720 hrs 0.17527449 0.001022912 Background decay heat load due to 21 previous refuellng loads 6,124,808 Bbithr Where heat load = 0.03455243390000'1.02?3413/217+0.0083742r34410001.0053413t217 + 0.0645275-37180001.005 3413/217 Decay heat due to partial core offload at times Indicated 72 hrs 27,045,032 Btu/hr 99 hrs 23,679.200 Bbtuhr 120 hrs 21,781.314 Btu/hr 168 hrs 18,868,285 8tulhr 240 hrs 16,381,596 Bfthn 360 hrs 14,042,528 Bhfthr 720 hrs 10,296,411 Btulhr Where heat load = Non Dim Power Gen Factor' 3735030

3413/217 Total Decay Heat Load due to Partial Core Offload at times Indicated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 33,169,840 Btu/hr 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months 27,905,122 Btultr 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months 24,993,093 Bhft 240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months 22,505,404 Btu/hr 360 hours0.00417 days 0.1 hours 5.952381e-4 weeks 1.3698e-4 months 20,167,336 Buflt 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 16,421,219 BtuflT

ECS96-003, Attachment 2 Page 4 of 5 Decay Heat Load Due to Full SFP & Cask Storage Area Full Core Offload Capacity Limited to 2104 Assemblies CYCLE Assemblies Cumulative Fuel Years Since Non Dim Power Sum of Power Fractions Heat Load per EFPY Discharged Pool Discharge Gen. Factor Power Gen Based on ASB 9.2 Assy Btulhr

(# assys x P. F.)

Factors Cycle No Nom EOC Date I

Power (Mt) 1 3390 11126/88 2

3390 04101188 3

3390 09123/89 4

3390 03115/91 5

3390 09120/92 6

3390 03t04/94 7

3390 09122/95 8

3390 04111/97 9

3390 02/05/99 10 3390 09/15/00 11 3390 03t15/02 12 3441 09115/03 13 3441 03/15105 14 3718 09/15/06 15 3718 03115108 18 3716 09115/09 17 3718 03/15/11 18 3718 09/15/12 19 3716 03115/14 20 3718 09115/15 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 92 84 84 84 84 92 96 84 92 92 78 92 92 108 108 108 108 108 108 108 92 176 260 344 428 520 818 700 792 884 960 1052 1144 1252 1360 1468 1576 1684 1792 1900 30.5 29 27.5 28 24.5 22.92 21.1 19.5 18 16.5 15 13.5 12 10.5 9

7.5 8

4.5 3

1.5 2.838058E-03 2.685934E-03 2.784055E-03 2.885761E-03 2.991182E-03 3A02240E403 3.708132E-03 3.371201E-03 3.827154E-03 3.9se972.E03 3.396802E-03 0.0358575 4.262242E-03 4.418388E-03 0.0086808 5.378378E-03 5.583343E-03 5.821709E-03 6.173838E-03 8.984770E-03 0.009518736 1.990193E-02 0.0593407 3.084846E-05 3.197540E-05 3.314351 E-05 3.435430E-05 3.560931E-05 3.698087E-05 3.882638E-05 4.013335E-05 4.159950E-05 4.311926E-05 4.4e9477E-05 4.S32871E-05 4.802595E-05 4.979980E-05 5.169762E-05 5.390471E-05 5.718516E-05 6.448861E-05 8.811793E-05 1.842772E-04 1,845 1,705 1,787 1.832 1.899 1,972 2.059 2,140 2,218 2.299 2.383 2.470 2.807 2,911 3.022 3,150 3.341 3,769 5,150 10,770

ECS96-003, Attachment 2 Page 5 of 5 21 3716 03115117 4.5 217 2117 72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 360 hrs 720 hrs 9.250311E-O0 7.287391E-01 7.449942E-01 6.453588E-01 5.603057E-01 4.803017E-01 3.521719E-01 4.282816E-03 1.7131109 3.358245E-03 3.433153E-03 2.974004E-03 2.582054E-03 2.213372E-03 1.622912E-03 249.143 196,275 200,653 173,818 150,910 129,362 94,852 Background decay heat load due to 20 previous refueling loads 5,907.794 Btulhr Where heat load = 0.03585753390000-1.0213413f217+0.00868068344100011.005'3413t217+0.059340r37160001.00534131217 Decay heat due to full core offload at times IndIcated 72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 300 hrs 720 hrs Where heat load = Non DIm Power Gen Factor ' 3718000r1.005 ' 3413 1 217 Total Decay Heat Load due to Full Core Offload at times Indicated 72 hrs 126.25 Na 120 ars 168 hrs 240 hrs 360 hNs 720 hrs 54,334,370 Btu/hr 42,804,596 Btu/tr 43,759,386 Btulr 37,907,014 Btulhr 32,911,172 Btuhir 28,211,907 Btu/hr 20,6E5,833 Btuft 60,242,163 Btu/hr 48,71Z390 Btu/hr 49,667,179 Bbftur 43.814,807 Btu/lr 38,818,9B5 Btul-r 34,119,701 Btulrr 26,593,627 Btufr

ECS96-003, ATrACHMENT 3 Page 1 of 2 Surnio0 Sun An an PIP,(-,T. + %)

PIPA(.... j Pipe (TO.t.)

P(U.239)IP.

P(N.-239YPO 5.18086-04 1.0361sE-01 0.003327838 0.66556757i PIPO (T..rJ

(1 + K)( P/PI (-..)

- PIN (C.-. -. + t 3.0907E.03 for T.

428+E05 s.

7.1 059E-95 Hevy Metal Decay Hat Term 3.5494E404 H"vy etal Decay Heat Ternm 3.445676E.03 Total Fraction of Operating Power P Spent Fuel Pool Decay Power Fractions to-141912000 see 4.28E+0 Scs t*+"-

142340400 Sam 1

2 3

4 6

8 7

9 9 10 11 0.598 185 3.1 3.87 Z33 1.29 0.482 0.328 017 0.0865 0.114 1.772 0.5774 0.08743 0.008214 0.0004739 0.0000481 0.000005344 5.716E407 1.03SE-07 2.959608 7.585E-10 0.0000E+00 0.00OOE400 0

0 a

a 0 1.51872E-36 8.70100S 0.001281834 0.102333108 0

0 a

0 1.878648 1.4504E-0 0.048814018 0.258759ss2 0.1828200 0.085410416 0.11396M283 whem K

.2 Wor decay tkne s thanw iP ene and K

.1 for decay times between ile and i0 sec sea and per Stnd Review Plan K -O.1 fora lbng tem storap caWaons lower Fractio Term Tlne ltlh 1 W O.1 3 days 4.262818E-03 5 day 3.433153E-03 7 days 2.974004E-03 10 days 2.5820D4E-03 15 days 2.213372E-03 30 days 1.e22912E-03 0 days 1.10!361E-03 90 days 8.74056E-04 t year Z824211E-04 1.5 yeas 1.842772E-04 2 yeats 1.34846oE-04

2. years 1.059989E-04 3 years 8.81 1793E-05 3.5 years 7.67374sE-05 4 yeas

.938270E-05 4.5 yews

.Us8881E-0t Long Term Storage Value, used In Ec-396-003 The (yews)

Power Fracion 33.3 2.8850OE-05 32 2.97812E45 30.5 3.084846E-05 29 3.1975406E05 27.5 3.3143SE1605 26 3.435430E-05 24.5 3.580931E.05 22.92 3.698087E605 21.1 3.882638E-05 19.5 4.013335605 18 4.159950.E05 18.5 4.311926E45 15 4.4u9477E-05 13.5 4.832571E605 Short Term Storge Values used In EC49640(3 Tlne (hotr)

Power Fradbn 72 4282818E.03 80 4.08446OE-03 88 3.924993E403 98 3.782063E03 99 3.732298E03 104 3.853801E603 108 3.S9422e6.3 112 3.537816603 126.25 3.3582456E-03 120 3.433153E603 131 3.304947E-03 141 3.20191SE603 1e8 Z974004E-03 184 Z865380.E03 240 2.582054E-03 360 2.213372E-03 720 1.622912E-03

ECS96-003, ATTACHMENT 3 Page 2 of 2 Tim.

wfthK.0.1 5 yes 6.118300E-05 6 yeas 5.716516E-05 7 years 5.480254E.05 a years 5.310269E-05 9 years 6.169762E-05 10 years 5.041414E-05 15 years 4.469477E-0S 20 years 3.915621E-05 T1A (years)

Power Frcion 12 4.SM2595E.05 10.5 4.979980E.5 9

5,169782E5CS 7.5 5.39047IE-C5 8

5.71651SE-C5 4.5 6.4e861E-05 3

8.811793E6-5 1.5 1.542772E-04 shortTeml Storage Values For use In evluating hourly change In dey heat durtag partal o89oad 73 74 75 78 77 78 79 80 e1 82 83 84 855 88 87 88 89 90 91 92 93 94 95 98 97 98 99 100 101 102 103 104 105 106 107 108 Power Fracin 0.0042394 0.0042163 0.0041935 0.0041711 0.0041490 o.O04127 0.0041057 0.0040844 0.0040835 0.0040429 0.0040221 0.0040025 0.0039827 0.0039632 0.0039440 0.0039250 0.0039083 0.0038878 0.0038698 0.0038518 0.0038339 0.0038164 0.0037991 0.0037821 0.0037653 0.0037487 0.0037323 0.0037181 0.0037002 0.0036845 0.0038889 0.0036538 0.0038385 0.0036235 0.0036088 0.0035942

ECS96-003, ATTACHMENT 4

> Page I of 4 Calculations Performed in Support of RF-005-001 Attachment 9.5 Purpose Use SFP HX single failure decay heat lmit of 29 x 10' Btu/hr determined In calculation EC-M98-067 to update the maximum number of spent fuel assemblies that can be transferred to the SFP at times Indicated In RF-005-00l Attachment 9.5.

Maximum background decay heat from 2008 previously stored assemblies 6,124,808 Btu/hr From attachment 2 Core Rating MWt Partial Core Offloading LUmits Currently In RF-005-0O1 Max Number of Max Authorized Assys w new Time after Non Dim EFPY Number of PFs & heat Shutdown; Power Gen Factor Assys limit of 29E06 Btufhr Heat load due to offload (Btulhr)

SFP & Cask Storage Area decay heat calculation -

Power Fraction Total Heat per ASB 9-2 Load Cycle 22 (Corrected K Offload (Btuthr) factor) 3716 4.5 79 72 hrs 91 Where Power Gen Factor = Number of Asserrblios

Power Fraction Heat load= Power Gen Factor* 3735000 34131217 Total heat load = heat load due to offload + background decay heat load 82 80 hrs 0.336762458 0.387916247 0.334924861 0.388022704 0.333624366 0.388574262 0.332821578 0.385770465 0.328824082 0.387281696 19,782,940 22,787,943 19,674,991 22,794,197 19,598,594 22,826,598 19,551,435 22,661,890 19,316,604 2Z750,667 0.004262810 25,907,748 28,912,751 0.004084450 25,799,799 28,919,005 0.003924993 25,723,402 28,951,406 0.003782063 25,676,243 28,788,898 0.003653601 25,441,412 28,875,475 85 88 hrs 88 96 hrs 102 90 104 hrs 106

ECS96-003, ATTACHMENT 4 Page 2 of 4 93 112 hrs 110 108 120 hrs 0.329016877 19,327,930 0.389159747 22,860,992 0.370780528 21,781,314 0.387946291 22,789,708 0.356934305 20,967,925 0.386878831 22,715,252 0.003537816 25,452,738 28,985,800 0.003433153 27,906,122 28,914,516 0.003304947 27,092,733 28,840,060 113 108 131 hrs 117

ECS96-003, ATTACHMENT 4 Page 3 of 4 Full core offload of 217 assemblies Operating Conditions: Fuel Pool Primary Heat Exchanger In-Service Spent Fuel Pool Pump Flow' 3,650 gpm Component Cooling Water Flow= 5,000 gpm Component Cooling Water Temperature 90°F Total Amount of Fuel Assemblies Transferred - 217 Core Number of Time After Decay Heat Power Fraction Total Decay Rating EFPY Assemblies In Shutdown Power Gen Factor of Offload per ASB 8-2 with Heat Load MWt Offload (hours)

(Btulhr) corrected K term (Btulhr) 3716 4.5 217 72 0.925031051 54.340.480 0.004262816 60,455,288 The total decay heat load of a full core offload at 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months afterreactor shutdown, 60,465,288 Btulhr, exceeds the SFP primary heat exchanger heat duty limitof 52.47 x l0Btulhrcalculated In EC-M98-022,Appendix K. Thisheatdutylimitof52.47x ia0 Btu/hris based onthe operating conditions specified above along with a heat exchanger effectiveness (hi) of 0.3249 at 115F. In order to not violate the heat duty limit of 52.47 x 10a Btulhr, the number of spent assemblies that can be transfered to the pool must be controlled. The following tabulation give the maximum number of spent assembles that can be stored in the SFP at the specified Ume after reactor shutdown and not violate the heat duty Imit of 52.47 x 10 6 Btulhr.

185 72 0.788620942 46,327,137 0.004262816 52.451,945 189 76 0.788339024 46,310,576 0.004171106 52,435,384 193 80 0.788298757 46,308,211 0.00408445 52,433,019 197 84 0.788495336 46,319,759 0.004002514 52,444,567 200 88 0.784998509 46,114,339 0.003924993 52,239,147 204 92 0.785725926 46,157,071 0.003851598 52,281,879 208 96 0.786669184 46.212,482 0.003782063 52,337,290 212 100 0.787822004 46,280,204 0.003716142 52,405,012 215 104 0.785524195 46,145,221 0.003653601 52,270,029 217 106 0.786306146 46,191,158 0.0036235 52,315,964 217 120 0.744994206 43,764,307 0.003433153 49,889,115

ECS96-003, ATTACHMENT 4 Page 4 of 4 Note: Based on SFP heat exchanger performance predictions from page K-3 of EC-M98-022, the spent fuel pool biuk temperature could be maintained at 155' F with a total decay heat load of 60.47 x 106 Btu/hr, the heat toad of a full core offload 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reactor shutdown, but It would require 5,000 gpm of CCW flow at 80 F and 3,650 gpm of fuel pool water cooling water flow. Under these operating conditions the heat exchanger's heat removal ruinn.ehv Is nmdictarri tn he fin-m x 1 no Rhitnhr.

217 96 0.820707754 48.212,061 0.003782063 54,336,869 At 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after shutdown, the full core offload heat load Is 48.21 x 106 Btulhr and the total decay heat load Is 54.34 x 106 Btulhr. In order to maintain the SFP bulk pool temperature at 1550 F, fuel pool cooling water flow must be maintained at 3,650 gpm and the CCW low to the heat exchanger at 5,000 gpm at' 8r F.

217 120 0.744994206 43,764,307 0.003433153 49,889,115 At 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months after reactor shutdown, the total decay heat load for a full core offload transferred to the SPF Is 49.89 x 108 Btulhr. Assuming 3,650 gpm of fuel pool cooling water flow and 5,000 gpm of CCW flow, the CCW Inlet temperature to the HX can be as high as 93 F and the bulk pool temperature can be manitalned at 1550 F. If the CCW Inlet temperature to the heat exchanger Increases to 1050 F. the full core offload would have to be delayed to 220 hours0.00255 days 0.0611 hours 3.637566e-4 weeks 8.371e-5 months after reactor shutdown In orderto maintain the bulk pool temperature at 155' F andnotviolatethe heat exchanger heat duty flmit of 40.40 x 10' Btulhr specified in Appendix K of EC-9198-022.

217 220 0.579353412 34,033,822 0.002669831 40,158,830

ECS96-003, ATTACHMENT 5 Page 1 of 2 Backup HX Heat Duty Calculations Maximum heat duty of Backup HX 15.4 x 106 Btu/hr per ECM98-022.

Determine decay time before Backup HX can handle heat load from partial core offload 108 assembles from 3716 MIt uprate ECM98-022 App L 2116 assemblies In storage heat load 6,335,446 Btulhr ECS96003 2008 assemblies in storage heat load 6,124,808 Btu/hr Establish maximum decay heat load from partial core ofiload by subtracting above background decay heats from heat duty ECM98-022 2116 assemblies In storage 9,064,554 Btulhr ECS96-003 2008 assemblies In storage 9,275,192 Btulhr Using the following equation determine the power fraction needed to obtain decay heat load Heat load = 108 (PF)

3735000 3413 /217 Power Fraction = heat load 1(3735000*3413/217)

ECM98-022 with 2118 previously stored assemblies (PF) =

0.001428748 Use equations In Attachment 3 and Iterate time after shutdown to obtain the required PF value Ts PF 915 hrs 0.001428093 Total Decay heat load = 108 '0.001428093 3735000 '3413/217=

9,060,400 15,395,848 Btulhr ECS96-003 with 2008 previously stored assemblies (PF) =

0.001461948 PF 877 hre 0.001461648 Decay heat load = 108* 0.001461648 3735000 "3413/217=

9,273,287 15,398,095 Btu/hr

ECS96-003, ATTACHMENT 5 Page2of2 Full core offload of 217 assemblies Determine decay time before SFP Backup HX can handle heat bad from a full core offload Maximum heat duty on heat exchanger ECM9-022 with 2116 previously stored assemblies ECS96-003 with 2008 previously stored assemb1les 1 5.4 x 106 Btulhr 9,064,554 Btulhr 9,275,192 Btu~hr Allowable decay heat load due to offload Allowable decay heat load due to offload Heat load = 217 *(PF)' 3735000

34131217 = (PF) 3735000

3413 ECM98-022 (PF) =

0.000711082 required Ts PF 3013 hrs 0.000711013 125.5 days after shutdown Decay beat load = 0.000711013

3735000

3413 =

Core Offload 9,063,679 Total 15,399,124 Btulhr ECS96-003 (PF) =

0.000727606 required PF

-2915 hrs 0.00072873 121.5 days after shutdown Core Offload 9,264,030 Total 15,388,838 Btu/hr Decay heat load = 0.00072673

3735000

3413 =

Technical Review Comments:

ECS9-003 DRN 03-

, SFP Heat Loads Entergy Technical Review Comments Document Calculation No.

Rev.

Subjectrltle:

Spent Fuel Pool Heat Loads Number _IECS96 00 DRN 03-???

O Document Type: Calculation Special Notes or Instructions Comment Section/

Technical Comments Response/Resolutlon Number Page No.

title Calculation no longer applies to 1088 Spent Fuel Assemblies.

Concur. Will chane title to remove '1088 Spent Fuel AssenbUes Therefore, revise title to the original title of 'Spent Fuel Pool and substitute "for a Full Spent Fuel Pool and SF? Cask Storage Heat Loadsm A

2 general Why is this calculation needed?

Ihis calculation was apparently developed to provide limiting heat What is the Interaction of this calculation with the HOLTEC loads for the Ultimate Heat Sink Study and for Wet Cooling Tower calculations ECM98-022 and ECM98-07 Losses During a LOCA calculations The initial issue looked at a

.fMl storage pool with 1088 spent asserblies. This revision updates the calculation to provide heat loads at3, 5,7,10,15 and 30 days after shutdown for a full SFP and for the SFPJSFP Cask Storage Area. The HOLTEC calculation EC-M98-022 gives sinilar data but is based an mne conservative assumption of background decay beat loads. The intent cf EC-M98M022 was to show that the cooling system could handle dtermal loads beyond the physical storage capacity of the SFP ard SFP Cask Area. Ihe stated intent of EC-M98-067 was to dctenmlne the most limiting conditio for removing SFP hat loads assuming a different single ailure uthan the one adopted inEC-M98-022. Calculution M98-022 assumes the loss of the most efficient FP cooling pump as its single failure EC-M98.067 assumes loss of an electrical bus that not only takes out a FP cooling pump but also reduces CCW flow to the SFP HX to 2768 gpm from the 5000 gpm assumed in EC-M98q22. With the reduction in CCW flow, the heat load in the SFP nnast be kept below 29xl0' Btufr to prevent from exceeding the pool bulk temperaturc limit of 140F.

3 6.0 What is end use of this calculation? Time to boil would be The heat loads reported in this calculation are used in support of reduced If computed at the conditoins of higher decay heat the Ultimate Heat Sink Study MN(Q) 9-3 and Wet Cooling Tower associated with shorter times after shutdown than 15 days.

Losses During a LOCA MN(Q) 9-9. The time to boil calculaticn is not really used since the FSAR currently references a time to boil value from EC-1M8-022. This value is based on a loss of forced cooling when the SFP temperature peaks aft a partial core offload. For a partial core oflload 7 days after reactor shutdown, HOLTEC predicts that the pool temperatre peaks at 132.6 F when cooling is lost. It then takes 6.8 hrs for the pool temperature to reach 21F. As past of the 3716 MWt upate evaluation this ecs9M3jn. 9115=3.12.'39 PM Pamn 1

Technical Review Comments:

ECS96-003 DRN 03-SFP Heat Loads loss of cooling system transient has be recalculated using decay heat loads for the 3716 MWt uprate. Ihe new calculation, draft Appendix M to EC-M98-422, predicts a starting temperature of 125.7 and a time period of 8.65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months for the pool to heat up to the boiling point.

4 5.0 Note that since fuel offload is not allowed per1S until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months The decay heat loads reported at 3 days aft reactor shutdown for and with a 4 assembly per hour assumed offload rate, full core a partial core offload and for a full core offload establish thermal discharge at 3 days after shutdown is not considered aedible.

limits for refueling oflIoading rates. In the case of dse partial core Similarly, 108 assemblies will not be discharged at 3 days after oMoad of 108 assemblies, all 108 assemblies could theoretically shutdown.

be offloaded without violating the design basis heat duty of How does consideration of these constraints impact this 33.73x10' Btuhr on the SFP DCX Consequently Waterford-3 calculation or downstream calculatfors?

could start refueling 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after shutdown and offload at rates in excess of 4 assemblies per hour witbout exceeding the heat duty design basis of the SFP HX. The additional decay heat resulting from offloading more than 4 assemblies perhour woud be traded off against the higher background decay beat term assumed in the HOLTEC analysis - 9.93x106 Btu/hr versus the 3716 uprate value of 634x10' Btahr. At 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after shutdown a fuel asembly frm the 3716 MWtcore will be generating approximately 249,000 Btlbr of decayheat. For the full core offload the calculated decay heat load of 60.47x10 Btc/.r exceeds the 50.41x105 design basis heat duty of the heat exchanger. This indicates that an offiloading rat limit exist Based on the results in Appendix L to EC-M98-022, the limiting rate exceeds the cuent limit of 4 assernblie perhourbut vwatthe actual limit is has not been evaluated as part of this analysis.

5 Attl What is logic for the times after shutdown considered In tis The 108 hour0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months 'time increment represents the time when the SFP calculation? Specifically, document the reason why 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months reached its peak bulk temperature for the partial core offlond in and 12625 hours are considered.

EC-M9-022. The design basis heat load for the SFP EX was takn at the 108 hour0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months icrement. All fuel assembly discharge was completed at the 101 hour0.00117 days 0.0281 hours 1.669974e-4 weeks 3.84305e-5 months increment Due to the thermal lag in the SFP bulk temperature the peak bulk temperature didn't occur until 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months later. The original guidelines for the 3716 uprate called for a partial discharge of 1 16 assemblies so the transfer would again be completed at 101 hours0.00117 days 0.0281 hours 1.669974e-4 weeks 3.84305e-5 months and the peak temperature would presumably occur at 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months . Now that the partial oftload is a

.nnsionnm of 108 assemblies, transfer will ie completed at 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months after shutdown and peak temperatures could occur at 106 hours0.00123 days 0.0294 hours 1.752645e-4 weeks 4.0333e-5 months after shutdomn. Since the 3 day heat load doesn't exceed the design basis heat duty of the SEP heat exchanger it really doesn't matter whether the beat load is reported at 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months , 106 hours0.00123 days 0.0294 hours 1.752645e-4 weeks 4.0333e-5 months or

___I 08 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . For the full core offload. it has already been stated that ecs98DO3_ps. 9/1 MOM, 12:39 P14 Page 2

Technical Review Comments:

ECS96.003 DRN 03-...., SFP Heat Loads the 3 day value exceeds the heat duty limt of the beat changer.

The 126.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months lime increment represents the completion of the full cote dischare and tiusrepresentsthenmiDmmheatloadon the SFI'DL.

0tt Sow *10 em M3-ps. 911 wo203. 1Z39 PM Page 3

~~Entery~

Technical Review Comments Document Rev. SubJocU1e:

Number EC-S96B003 0-1 Spent Fuel Pool Heat Loads for 1088 Spent Fuel Assemblies Document Type:

Spedal Notes or Instructions:

Enercon Calculation Comment Sectlonl Comment Response/Resolution Number Page No.

I Calc Cover Remove 1088 Spent Fuel assemblies from Title?

Concur, will change Title to remove 1088 Spent Fuel assemblies Page and substitute 'a Full Spent Fuel Pool and SFP CasL Storage Area!

2 Revision Indicate that this is a complete rewrite of the Calculation and Agree will indicate this is a complete rewrite of calculation and that Page that no revision bars will be used. Also indicate that no revision bars are used. Original Attachments I and II have been Attachments I and II have been replaced with decay heats load replaced by Attachment I -5. Decay heat loads are calculated calculations using ASB 9.2 methodology using ASB 9-2 methodology.

3 1.0 Actual discharge assemblies go through Cycles 1 through 11.

Concur. Calculation revised to show offload3 for Cycles I through Cycles 12 and 13 are expected ofiloads.

11 based on historical data. Number of assemblies in offloads 12 &

13 are expected quantities based on contacts with Westinghouse Windsor.

4 2.0 Why is EC-M9B-067 used as a reference?

Calculation EC-M98-067 was originally referenced because the power fraction values used in the draft version of this calculation were taken from Attachment 8.11 ofEC-M98-067. Subsequently zn error in applying the Kuncertainty in ASB 9-2 was discovered rendering the power fractions in BC-M98-067 overly conserative.

EC-M9867 is being deleted. Attachment 3 recalculates power fractions with updated formulas fronm ASB 9-2.

5 4.0 Adda core power of3390 for cycles I -1I in the bulleted Concur. Corepowerof3390 MWthasbeenincluded ibulleted section.

section on hInt Criteria and Assumption 6

6.0 The value of 38,602 ft3 is not a direct value from EC-M98-022.

The volume value was obtained fomn page E-2 Appendix B to BC.

Derive how this volune was determined.

ML°&2 The volue is calculated to obtain a thermal inertia value for the 5FF and cask storage ars The expression for the volume is

([0547

19,665.8 + 27,844.81. When this cxpression is reduced it gisves a volume value of 38,601.99 ft.

7 At 1 Insert a formula that was used to calculate the offload heat load Wi incorporate equation or heat load of offload, but spreadsheet is (i.e. similar to the background heat load formula given above) not really an attachuent to this calculation but a part of the main body. There are two attachmnents. The first gives the update equations forASB 9-2 and the values used in various uprate calculations. The second attachment gives values for RPF005-001.5 Pago I of 2

Att I What is the relevance of the 12625 hours?

This represents the time after shutdown when all 217 core assemblies have been offload for the full core offlond assuming discharge is initiated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after shutdown and 4 assemblies are transferred every hour.

Reviewed By.

Resolved By.

tD0L A1u,.

?7/V8a3 (Name/Date)

David Vlener 8129103 (Name/Date)

[onaid Hlj 9112/03 Department:

Phone:

Accepted By./

W3 - Design Engineerng 504J739-6686 (NameDate)

-/0

(°/ aK Pagem2f2 To W3FI-2004-0073 List of Regulatory Commitments

f to W3F11-2004-0073 Page 1 of 1 List of Regulatory Commitments The following table identifies those actions committed to by Entergy in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

TYPE (C eck one)

SCHEDULED ONE-CONTINUING COMPLETION REVISED COMMITMENT TIME COMPLIANCE DATE (If ACTION Required)

Revised technical specification mark-ups for X

9/30/04 technical specification pages 2-3, 3/4 3-19, and 3/4 3-20 will be provided in a future supplement to replace those previously provided.

/

ML042440429

Contents

Text

REFERENCES:

Title:

Title:

Title:

SUMMARY

1.0 Purpose

References:

3.0 Method

6.0 Calculations

Navigation menu

ML042440429

Text

REFERENCES:

Title:

Title:

Title:

SUMMARY

1.0 Purpose

References:

3.0 Method

6.0 Calculations

Navigation menu

Search