Attachment 5 to W3Fl-2004-0073, 'Additional Information ... · 1. NEAD Letter, DE-96100005,...

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 Doc.: ER-W3-2001-1149-000 Superseded DRN: NIA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 RequiredOl 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 YesE 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 EO Checker

Comments Attached El

* Reasonableness Review perDC-126, Sect. 5.8 (Rev. 0)

02DRN No. 03- i4'yP Pages ra s

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 Doc.: ER-W3-2001-1149-000 Superseded DRN: N/A

COVER PAGE 0 PendinglCN RequiredE] 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 : 4a | .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 xZ1 Warrene Cox

Cl6)(Print Name/Signature/Date) | "7(Print Name/Slgnature/Date) | (8)(Print Name/Signature/Date)

Responsible Engineer | Design Verifier Supervisor/Approval

| Reviewer Comments Attached O

| l Checker

Comments Attached Ol

CALCULATION CALCULATION NO: ECS96-003

REFERENCE SHEET |REVISION: 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, 20034. 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 ReviewQualificatlon TestingAlternate 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 FullSDent Fuel Pool and SFP Cask StorageArea

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

The review verified the Input and assumptions, as well as, methodology used to determine the boundingadditional decay heat loads on the Waterrord 3 spent fuel pool due to the core power Increase to 3716MWL

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, , IIV

/ /I

DESIGN VERIFICATION RECORD

Page 2 of 2Lrc I'

Document Number ECS96-003 Revision DRN 03-1440

CN- T | C|ACPT I INITMDCMTICOMMENT RESOLUTIONYI AT

.0

None All comments and questions wereresolved without requiringdocumentation.

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 03-1440Calculation 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 All1440 month fuel cycle and a core uprate to 3716 MWt. This Is a

complete re-write of the calculation and thus, no revisionbars will be used. Attachments I and 11 have been replacedby Attachments 1-5. Decay heat loads are calculated usingASB 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 incalculations MN(Q)-9-3. "Ultimate Heat Sink Study" and MN(Q)9-9, "Wet CoolingTower Losses During LOCA" at various times after shutdown for the following storageconditions:

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

* SFP contains a total of 1,849 spent fuel assemblies (FA) with 1,684 previouslystored 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 thelast outage.

* SFP & SFP cask storage pit contain a total of 2,104 spent fuel assemblies (FA) with1,900 previously stored assemblies plus 217 assemblies discharged during the lastoutage.

The decay heat loads are calculated at 3 (72 hours), 5 (120 hours), 7 (168 hours), 10(240 hours), 15 days (360 hours) and 1 month (720 hours) after reactor shutdown.

This calculation also provides updated Spent Fuel Pool Cooling Capability forAttachment 9.5 of Refueling Procedure RF-005-001.

2.0 References:

1. Calculation EC-M98-022, Rev 0, CN-1, Thermal - Hydraulic Analysis of Waterford3 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 ofWaterford 3 Spent Fuel Pool"

3.0 Method:

Ref. 1 provides a thermal-hydraulic analysis of the Waterford 3 Spent Fuel Poolcooling system after the Installation of HOLTEC high density fuel storage racks and aproposed core thermal power uprate to 3661.2 MWt. Appendix L to Ref. I extendsthe 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 refuelingoffloads to the SFP and calculates the decay heat contributions from each offload tothe total heat load on the SFP cooling system. Decay heat loads for stored fuel arecalculated In accordance with the equations provided in Ref. 2. A time dependentdecay power fraction is calculated for each refueling discharge to the SFP and to theSFP cask storage area. These power fractions are then used to calculate powergeneration factors that relate decay powerof the spent fuel to average full powerrating of an Individual fuel assembly. These power factors can then be summed foreach specific core power rating and then the totals converted from power ratings InKw to heat rates In Btulhr. The heat rates are then added to establish a total heat ratecontribution for all tho previously stored offloads. Because these offloads havestorage times that are counted in years since reactor shutdown, the sum of theirrespective heat loads Is called the background decay heat load and Is treated as aconstant during the thermal evaluation of the most recent refueling offloads impact onthe cooling system.The total decay heat load on the cooling system for the SFP or the SFP/ SFP caskstorage area Is then the sum of the background decay heat load from the previousrefueling 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 loadcontribution from the current or latest offload dominates the total heat load on thecooling system. Total decay heat loads for the most recent discharge are reported at3, 5, 7, 10, 15 days and I month after shutdown to illustrate the rapid decline in decayheat over time.The decay power fractions that ultimately determine the decay heat loads of the spentfuel assemblies are calculated In accordance with the equations in Ref. 2 and aregenerated In Attachment 3 of this calculation. The two critical dependent variables Inthese equations are the cumulative reactor operating time of the fuel assemblies andthe time after reactor shutdown. The fission product decay term in the decay energycalculation includes an uncertainty factor K. A typographical error In the application ofthe uncertainty factor K In Ref. 2 for fission product decay calculation has beencorrected in the power fraction calculations in Attachment 3. When calculating decaypower 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 assembliesdischarged at each refueling outage, the power level of the core for the dischargedassemblies, the cumulative storage times for each of the previous offloads and therespective times after reactor shutdown for determining the decay heat loads for thecurrent refueling offload. The Excel spreadsheet format developed In Ref. I is used tocapture all the required Input data and then to calculate the decay heat loads.Attachment 1 has the spreadsheets generated for a partial core offload of 108assemblies to the SFP and for a full core offload to the SFP. Attachment 2 hascomparable spreadsheets for a partial core offload of 108 spent assemblies to theSFP/SFP Cask Storage Area and for a full core offload to the SFP/SFP Cask StorageArea. The prime difference between the two attachments is In the overall storagecapacity available. In Attachment 1 the SFP has a total storage capacity of 1,849assemblies with the HOLTEC high density storage racks. The number of previouslystored fuel assemblies Is adjusted between the partial core oMoad event and the fullcore offload event to ensure that the total number of stored assemblies Is close to1,849. In Attachment 2 the SFPISFP Cask Storage Area has a total storage area of2,104 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 ofassemblies offloaded during a particular refueling outage, the core power levelassociated with the discharged fuel, the cumulative number of assemblies placed Instorage after the offload and the years since discharge for each offload. The storagetimes In the column labeled 'Years Since Discharge* Index by 18 month Increments aseach subsequent offload is transferred to the SFP. Historical data Is provided forrefueling cycles I through 11 for the 3390 MWt core. Offload estimates of 92 spentassemblies are assumed for cycles 12 and 13 for the 3441 MWt core. Offloads of 108spent fuel assemblies per discharge are assumed for each refueling outage after the3716 MWt uprate is implemented. The number of cycles that Is Included In a givenspreadsheet is dependent upon the storage capacity of the SFP or the SFP/SFP CaskStorage Area. Attachment 1 is based on decay heat loads due to a full SFP.Attachment 2 is based on a full SFP and Cask Storage Area. The number of spentassemblies used In the decay heat load calculations exceeds the actual storagecapacity of the SFP or the SFP/SFP Cask Storage Area to provide someconservatism to the total heat loads being reported.

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


... 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 thenmultiplied by the number of assemblies in a given offload to obtain a PowerGeneration Factor which are listed in column 8. All the power generation factorsassociated with a specific core power level are then total In column 9. The decay heatload from all of the spent fuel assembly discharges from a given core power level Isthen the product of the sum of the power generation factors In column 9 and theaverage 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 the3390 MW core design. The actual decay heat of an Individual spent fuel assembly Isa strong function of the assembly's power fraction In the core, especially during Its lastcycle. Since the discharged assemblies in an offload will have much lower powerratings compared to the core average, this method for determining decay heat load isvery conservative, and over estimates the decay heat load for a normal refuelingoutage but not a full core off-load.A summary of the assumptions used to generate the decay heat loads in AttachmentsI 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 3716MWt core assemblies

* decay power fractions In accordance with ASB 9-2 are used to calculate the decayheat load for refueling offloads that comprise the background heat load (seeattachment 3)

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

5.0 Results Summary:The following table provides the total decay heat for a full SFP at 3, 5, 7, 10, 15 and30 days after reactor shutdown. The decay heat values are based on the storagecapacity of the SFP being limited to 1,849 assemblies with the high capacity HOLTECstorage racks in place. For the partial core offload of 108 assemblies the backgrounddecay heat is based on 1,792 previously stored assemblies from 19 fuel cycles. For


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 1,684previously stored assemblies from 18 fuel cycles.

Time After

Shutdown (days)

3

5

7

10

1530

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 StorageArea at 3, 5, 7, 10, 15 and 30 days after reactor shutdown. The decay heat values arebased on the storage capacity of the SFP & SFP Cask Storage area being limited to2,104 assemblies with the high capacity HOLTEC storage racks In place. For thepartial core offload of 108 assemblies the background decay heat Is based on 2,008previously stored assemblies from 21 fuel cycles. For the full core offload of 217assemblies the background decay heat is based on 1,900 previously stored assembliesfrom 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

Attachment 4 provides an update to the offloading data provided in Attachment 9.5 ofRefueling Procedure RF-005-001. The changes result from new estimates on spentfuel decay heat loads due to corrections to the power fraction equations in ASB 9-2and SFP heat exchanger heat duty limits from Ref. 4. Revised CCW temperaturerequirements to support a full core offload are also reported. The CCW temperaturerequirements reflect updated SFP HX performance predictions from Ref. 1.

Attachment 5 provides updated shutdown offloading times If the Backup SFP HX Isused to handle the decay heat loads from a partial core offload or a full core offloadafter the 3716 MWt uprate.

6.0 Calculations:

The total decay heat is calculated for the SFP containing approximately 1849 spentfuel assemblies with either a partial core offload of 108 assemblies or a full coredischarge of 217 assemblies as the last refueling outage, for 3, 5, 7, 10, 15 and 30days after shutdown. This calculation Is then repeated for the SFP containing 1849assemblies and the SFP Cask Storage Area containing and additional 255 spentassemblies (2104 total assemblies). Decay heats are reported at 3, 5, 7, 10, 15 and30 days after shutdown. The decay power fractions for the refueling cycles formingthe background decay heats as well as the values used at 3, 5, 7, 10, 15 and 30 daysafter shutdown were taken from an Excel spreadsheet based on the equations In ASB9-2. A copy of the Excel spreadsheet and resulting power fractions is provided asAttachment 3. The power fraction terms all include a K uncertainty factor of 0.1 in thefission 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 fuelassemblies and (3) 15 days after plant shutdown with 108 recently discharged fuelassemblies (19.73 x106 Btulhr total decay heat) Is calculated below. The SFP watervolume which is based on minimum required water level of 23 ft above the fuelassemblies 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 SFPreracking (performed prior to refuel 9) because: (1) the volume of the new HOLTECstorage racks is less than the volume of the Wachter racks used In Ref. 3. (2) as partof the reracking Gate #1 (which separates the SFP from the Cask Storage Pit ) isadministratively prevented from being Installed (following the reracking fuel will also bestored In the Cask Storage Pit and Installing Gate #1 would Isolate this fuel from theintake and discharge of the Spent Fuel Pool Cooling System. There is therefore morewater volume In the SFP following the reracking and this volume Is Increased once theCask 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 fuelassemblies, based on: (1) initial pool temperature of 1200F, (2) minimum water levelabove the fuel assemblies and (3) 15 days after plant shutdown with 108 dischargedassemblies (20.17x106 Btu/hr total decay heat) Is calculated below. The SFP watervolume which is based on minimum required water level of 23 ft above the fuelassemblies derived from Appendix E of Ref. 1. Appendix E page E-2 provides thefollowing 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 CaskStorage pit. The term 27,844.8 Is the volume in cubic feet of water above the storageracks and the term 0.547*19665.8 Is the volume of water In the rack structure. Thetotal volume of water in cubic feet is thus 38,602 fle. Substituting this into theequations 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 ENGINEERINGahteW1 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 refuelingoutage from RF cycle I to RF cycle 20. The following assumptions were made In developing thisspreadsheet:

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 plantdata.

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 Is108 spent fuel assemblies per outage.

7. Decay power fractions are based on ASB 9-2. All power fraction calculations Include a Kterm 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% uncertaintyfactor is applied to the 3390 MWt core and a 0.5% uncertainty factor is applied to the 3441and 3716 MWt cores.

The values In the column labeled 'Non Dim Power Gen Factor' are the product of the number ofassemblies 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-M98-022Appendix L. Long term decay times are adjusted based on the number of refueling outagesrequired to fill the respective storage capacity being evaluated. In this attachment, spent fuelstorage Is limited tol849 assemblies.

ECS96-003, Attachment IPage 2 of 5

Decay Heat Load Due to Full SFPPartial Core Offload

SFP Capacity Limited to 1849 Assemblies

CYCLE Assemblies Cumulative Years Since Non Dim Power Sum of PowerEFPY Discharged Fuel Pool Discharge Gen. Factor Power Gen Fractions

(# assys x P.F.) Factors Based on ASB9-2

Cycle Nom EOCNo. Power Date

(MWO

1 3390 11/26/882 3390 041011883 3390 09/231894 3390 03115/915 3390 09/20/926 3300 03/04/947 3390 091221958 3390 04/11/979 3390 0210S/9310 3390 0911510011 3390 03/1510212 3441 09/15/0313 3441 03115/0514 3716 09115/0615 3716 03/1510816 3715 09/1510917 3718 03/1511118 3716 091151219 3716 03/15/14

20 3716 09/15/15

4.54.54.54.54.54.54.54.54.54.54.54.54.54.54.54.5

4.54.54.5

4.5

92

848484849296849292769202

108108108108108108

108

92178260344428520

e16

70079288496010521144125213601468157616841792

1900

2927.526

24.522.9221.1

19.518

16.515

13.512

10.59

7.56

4.53

1.5

72 hrs99 hrs

106 hrs120 hrs

168 hrs

184 hrs240 hrs360 hrs720 hrs

0.002941737 3.197540E-050.002784055 3.314351E-050.002885761 3.435430E-050.002991182 3.560931E-050.003108393 3.698087E-050.003553627 3.662638E-050.003852801 4.013335E-050.003494358 4.159950E-050.003966972 4.311926E-050.004111919 4.469477E-050.003520982 0.0372098 4.B32871E-050.004418388 4.802595E-050.004581581 0.0990000 4.97998QE-050.005583343 5.169762E-050.005821709 5.390471E-050.006173838 5.716516E-050.006964770 6.448881E-050.009516738 8.811793E-050.019901933 0.0539623 1.842772E-04

Heat Loadper AssyBtu/hr

1,7051,7671,8321,8991.9722.0592.1402.2182,299Z3832.4702,5612.9113.0223.1503.3413,7695,150

10,770

249.143218.137211.780200.653

173.818167,469150.910129,36294.852

0.4603841180.4030879950.3913413080.3707805260.3211924090.3094610290.2788618110.239044167

0.17527449

4.262816E-033.732296E-033.623531E-033A33153E-032.974004E-032.865380E-032.582054E-032.213372E-03

1.622912E-03

ECS96-003, Attachment IPage 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 hours afterreactor shutdown and a maximum of 4 assemblies per hour transferred to storage

Approximate time Men pool reaches maximum bulk temperaturefor 72 hour 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 hrs168 hrs184 hrsApproximate time when pool reaches peak temperature for a 7 day hold

prior to all Jel being discharged

21,781,31418,868.28518,179,131

16,381,59614,042,52810,296,411

Btu/hrBtulhrBtulhr

Btu/hrBth/hrBtulhr

240 hrs360 hrs720 hrs

Where decay heat due to partial core offload equals

Non Dim Power Gen Factor at time * 373500034131217

Example at 72 hours 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/hr108 Irs 28,672,296 Btu/hr120 hrs 27,464,463 Btuhr

168 hrs 24,551,434 Btuhr184 hrs 23,862,280 Btu~hr240 hrs 22,064,745 Btuihr360 trs 19,725,677 Btu/hr

720 Irs 15,979,560 Btulhr

ECS96-003, Attachment 1Page 4 of 5

Decay Heat Load Due to Full SFPFull Core Offload


Cycle Nom EOCNo. Power Date

(MWt)

1 3390 1126/862 3390 04101188

3 3390 09123/894 3390 03/15/915 3390 09/20/92

6 3390 03/04/947 3390 09/2295

8 3390 04/11/979 3390 02/05/9910 3390 0911510011 3390 03115/0212 3441 09/1510313 3441 03/1510514 3716 09/15/0815 3718 03/15/0816 3716 0911510917 3716 03115/1118 3716 09115112

19 3716 03115/14

CYCLE AssembliesEFPY Discharged

4.5

4.54.5

4.5

4.54.5

4.5

4.5

4.5

4.54.5

4.5

4.5

4.5

4.5

4.54.54.5

92

8484

848492

9684

92

92

7392

92

108

108

108108108

CumulativeFuel Pool

92176280

344428520

616700792884

9601052

114412521360146815761684

YearsSince

Discharge

27.526

24.522.9221.119.5

18

16.515

13.5

1210.59

7.56

4.531.5

Non Dim Power Sum of PowerGen. Factor Power Gen Fractions

(# assys x P. F.) Factors Based onASB 9-2

0.003049203 3.314351E-050.002885781 3.435430E.050.002991182 3.560931E-050.003106393 3.698087E-050.003244818 3.862638E-050.003692268 4.013335E-050.003993552 4.159950E-050.003622018 4.311926E-050.004111919 4.469477E-050.004262242 4.632871E-050.003849973 0.0386091 4.8025952-050.004581581 4.979980E-050.004756181 0.0093378 5.169762E-050.005821709 5.390471E-050.006173838 5.716516E-050.006964770 8.448881E-050.00951673e 8.811793E-050.019901933 0.0483790 1.842772E-04

Heat Loadper Assy

Btu/hr

1,7671.8321,8991,9722.0592,1402,2182.2992.3832,4702,5612.6952,7983,1503.3413,7695,150

10.770

249,143196.275200.653173.818150.910129,38294,852

(

4.5 217 1901 72 hrs

126.25 hrs120 firs

168 hlr240 hlr

360 hrs

0.925031051

0.728739120

7.449942E-016.453588E-01

5.603057E-01

4.803017E-01

4.262816E-03

3.358245E-03

3.433153E-03

2.974004E-03

2.582054E-032.213372E-031.622912E-03720 hrs 3.521719E-91


- 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 timeThis is total time to offload full core starting at 72 hrs after shutdownand transferring 4 assembnles/hr

72 hrs126.25 hrs

120 his168 hrs240 hrs360 hrs720 irs

54,340,480 Blu/hr42,809,410 Btuthr

43,764,30737,911,27732,914,87328,215,08020,688,159

BtuihrBbu/rObtulStulhrBtuLft

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 time72 irs

120.25 i7S120 h's168 hrs240 Irs360 hrs720 irs

59,790,11448,259,04449,213,94143,360,91138,364,50733,664,71426,137,793

BATurBhu/hrBtulhrBhu/hratuihrBtu/hrBtulhr

AM' WATERFORD 3 DESIGN ENGINEERING

DEdfeg GENERAL COMPUTATION SHEET

CALC. NO. ECS96-003,Attachment 2

PAGE i OF 5

The following Excel spreadsheet calculates the decay heat load contribution for each refueling outagefrom 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 of108 assemblies per outage.

7. Decay power fractions are based on ASB 9-2. All power fraction calculations Include the K factorwith 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 Isapplied to the 3390 MWt core and a 0.5% uncertainty Is applied to the 3441 and 3716 MWtcores.

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


Decay Heat Load Due to Full SFP & Cask Storage Area

Partial Core Offload


Cycle No. Nom EOC Date CYCLEPower EFPY(MWt)

AssembliesDischarged

Cumulative Fuel Years Since Non Dim Power Sum of Power Fractions Heat Load perPool 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


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 hours 33,169,840 Btu/hr

120 hours 27,905,122 Btultr

168 hours 24,993,093 Bhft

240 hours 22,505,404 Btu/hr

360 hours 20,167,336 Buflt

720 hours 16,421,219 BtuflT


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 perEFPY Discharged Pool Discharge Gen. Factor Power Gen Based on ASB 9.2 Assy Btulhr

(# assys x P. F.) Factors

Cycle No Nom EOC Date IPower(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


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 3Page 1 of 2

Surnio0 Sun Anan

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 10 110.598 185 3.1 3.87 Z33 1.29 0.482 0.328 017 0.0865 0.1141.772 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 secsea and per Stnd Review Plan K -O.1 fora lbng tem storap caWaons

lower Fractio Term

Tlne ltlh 1 W O.13 days 4.262818E-035 day 3.433153E-03

7 days 2.974004E-0310 days 2.5820D4E-0315 days 2.213372E-0330 days 1.e22912E-030 days 1.10!361E-03

90 days 8.74056E-04

t year Z824211E-041.5 yeas 1.842772E-042 yeats 1.34846oE-04

2. years 1.059989E-043 years 8.81 1793E-05

3.5 years 7.67374sE-054 yeas .938270E-05

4.5 yews .Us8881E-0t

Long Term StorageValue, used In Ec-396-003

The (yews) Power Fracion33.3 2.8850OE-0532 2.97812E45

30.5 3.084846E-0529 3.1975406E05

27.5 3.3143SE160526 3.435430E-05

24.5 3.580931E.0522.92 3.698087E60521.1 3.882638E-0519.5 4.01333560518 4.159950.E05

18.5 4.311926E4515 4.4u9477E-05

13.5 4.832571E605

Short Term StorgeValues used In EC49640(3

Tlne (hotr) Power Fradbn72 4282818E.0380 4.08446OE-0388 3.924993E40398 3.782063E0399 3.732298E03

104 3.853801E603108 3.S9422e6.3112 3.537816603

126.25 3.3582456E-03120 3.433153E603131 3.304947E-03141 3.20191SE6031e8 Z974004E-03184 Z865380.E03240 2.582054E-03360 2.213372E-03720 1.622912E-03

ECS96-003, ATTACHMENT 3Page 2 of 2

Tim. wfthK.0.15 yes 6.118300E-056 yeas 5.716516E-057 years 5.480254E.05a years 5.310269E-059 years 6.169762E-05

10 years 5.041414E-0515 years 4.469477E-0S20 years 3.915621E-05

T1A (years) Power Frcion12 4.SM2595E.05

10.5 4.979980E.59 5,169782E5CS

7.5 5.39047IE-C58 5.71651SE-C5

4.5 6.4e861E-053 8.811793E6-5

1.5 1.542772E-04

shortTeml Storage ValuesFor use In evluating hourlychange In dey heat durtag partal o89oad

7374757877787980e18283848558887888990919293949598979899100101102103104105106107108

Power Fracin0.00423940.00421630.00419350.00417110.0041490o.O041270.00410570.00408440.00408350.00404290.00402210.00400250.00398270.00396320.00394400.00392500.00390830.00388780.00386980.00385180.00383390.00381640.00379910.00378210.00376530.00374870.00373230.00371810.00370020.00368450.00388890.00365380.00383850.00362350.00360880.0035942

ECS96-003, ATTACHMENT 4> Page I of 4

Calculations Performed in Support of RF-005-001 Attachment 9.5

PurposeUse SFP HX single failure decay heat lmit of 29 x 10' Btu/hr determined In calculation EC-M98-067 to update the maximum number ofspent 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

CoreRatingMWt

Partial Core Offloading LUmits Currently In RF-005-0O1

Max Number ofMax Authorized Assys w new Time after Non Dim

EFPY Number of PFs & heat Shutdown; Power Gen FactorAssys limit of 29E06

Btufhr

Heat loaddue tooffload(Btulhr)

SFP & Cask Storage Areadecay heat calculation -

Power Fraction Total Heatper ASB 9-2 Load Cycle 22(Corrected K Offload (Btuthr)

factor)

3716 4.5 79 72 hrs

91

WherePower Gen Factor = Number of Asserrblios * Power FractionHeat load= Power Gen Factor* 3735000 34131217Total 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


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


Full core offload of 217 assemblies

Operating Conditions: Fuel Pool Primary Heat Exchanger In-ServiceSpent Fuel Pool Pump Flow' 3,650 gpmComponent Cooling Water Flow= 5,000 gpmComponent Cooling Water Temperature 90°FTotal Amount of Fuel Assemblies Transferred - 217

Core Number of Time After Decay Heat Power Fraction Total DecayRating EFPY Assemblies In Shutdown Power Gen Factor of Offload per ASB 8-2 with Heat LoadMWt 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 hours afterreactor shutdown, 60,465,288 Btulhr, exceeds the SFP primary heat exchanger heat dutylimitof 52.47 x l0Btulhrcalculated In EC-M98-022,Appendix K. Thisheatdutylimitof52.47x ia0 Btu/hris based onthe operating conditions specifiedabove 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 spentassemblies that can be transfered to the pool must be controlled. The following tabulation give the maximum number of spent assembles that can be storedin 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


Note: Based on SFP heat exchanger performance predictions from page K-3 of EC-M98-022, the spent fuel pool biuk temperature could be maintainedat 155' F with a total decay heat load of 60.47 x 106 Btu/hr, the heat toad of a full core offload 72 hours after reactor shutdown, but It would require 5,000gpm 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 removalruinn.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 hours 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 theSFP 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 gpmat' 8r F.

217 120 0.744994206 43,764,307 0.003433153 49,889,115

At 120 hours 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 fuelpool 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 bemanitalned 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 hoursafter reactor shutdown In orderto maintain the bulk pool temperature at 155' F andnotviolatethe heat exchanger heat duty flmit of 40.40 x 10' Btulhrspecified in Appendix K of EC-9198-022.

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


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 PF915 hrs 0.001428093

TotalDecay 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

PF877 hre 0.001461648

Decay heat load = 108* 0.001461648 3735000 "3413/217= 9,273,287 15,398,095 Btu/hr

ECS96-003, ATTACHMENT 5Page2of2

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 PF3013 hrs 0.000711013

125.5 days after shutdown

Decay beat load = 0.000711013 * 3735000 * 3413 =Core Offload9,063,679

Total15,399,124 Btulhr

ECS96-003 (PF) = 0.000727606 required

PF-2915 hrs 0.00072873

121.5 days after shutdown

Core Offload9,264,030

Total15,388,838 Btu/hrDecay heat load = 0.00072673 * 3735000 * 3413 =

Technical Review Comments:ECS9-003 DRN 03- , SFP Heat Loads

Entergy Technical Review CommentsDocument Calculation No. Rev. Subjectrltle: Spent Fuel Pool Heat LoadsNumber _IECS96 00 DRN 03-??? ODocument Type: Calculation Special Notes or Instructions _Comment Section/ Technical Comments Response/ResolutlonNumber Page No.

title Calculation no longer applies to 1088 Spent Fuel Assemblies. Concur. Will chane title to remove '1088 Spent Fuel AssenbUesTherefore, revise title to the original title of 'Spent Fuel Pool and substitute "for a Full Spent Fuel Pool and SF? Cask StorageHeat Loadsm A .

2 general Why is this calculation needed? Ihis calculation was apparently developed to provide limiting heatWhat is the Interaction of this calculation with the HOLTEC loads for the Ultimate Heat Sink Study and for Wet Cooling Towercalculations ECM98-022 and ECM98-07 Losses During a LOCA calculations The initial issue looked at a

.fMl storage pool with 1088 spent asserblies. This revisionupdates the calculation to provide heat loads at3, 5,7,10,15 and30 days after shutdown for a full SFP and for the SFPJSFP CaskStorage Area. The HOLTEC calculation EC-M98-022 givessinilar data but is based an mne conservative assumption ofbackground decay beat loads. The intent cf EC-M98M022 was toshow that the cooling system could handle dtermal loads beyondthe physical storage capacity of the SFP ard SFP Cask Area. Ihestated intent of EC-M98-067 was to dctenmlne the most limitingconditio for removing SFP hat loads assuming a different singleailure uthan the one adopted inEC-M98-022. Calculution -

M98-022 assumes the loss of the most efficient FP cooling pumpas its single failure EC-M98.067 assumes loss of an electrical busthat not only takes out a FP cooling pump but also reduces CCWflow to the SFP HX to 2768 gpm from the 5000 gpm assumed inEC-M98q22. With the reduction in CCW flow, the heat load inthe SFP nnast be kept below 29xl0' Btufr to prevent fromexceeding 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 ofreduced If computed at the conditoins of higher decay heat the Ultimate Heat Sink Study MN(Q) 9-3 and Wet Cooling Towerassociated 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 toboil value from EC-1M8-022. This value is based on a loss offorced cooling when the SFP temperature peaks aft a partial coreoffload. For a partial core oflload 7 days after reactor shutdown,HOLTEC predicts that the pool temperatre peaks at 132.6 Fwhen cooling is lost. It then takes 6.8 hrs for the pool temperature

__ __ __ __ __ to reach 21F. As past of the 3716 MWt upate evaluation thisecs9M3jn. 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 decayheat loads for the 3716 MWt uprate. Ihe new calculation, draftAppendix M to EC-M98-422, predicts a starting temperature of125.7 and a time period of 8.65 hours for the pool to heat up tothe boiling point.

4 5.0 Note that since fuel offload is not allowed per1S until 72 hours The decay heat loads reported at 3 days aft reactor shutdown forand with a 4 assembly per hour assumed offload rate, full core a partial core offload and for a full core offload establish thermaldischarge at 3 days after shutdown is not considered aedible. limits for refueling oflIoading rates. In the case of dse partial coreSimilarly, 108 assemblies will not be discharged at 3 days after oMoad of 108 assemblies, all 108 assemblies could theoreticallyshutdown. be offloaded without violating the design basis heat duty ofHow does consideration of these constraints impact this 33.73x10' Btuhr on the SFP DCX Consequently Waterford-3calculation or downstream calculatfors? could start refueling 72 hours after shutdown and offload at rates

in excess of 4 assemblies per hour witbout exceeding the heat dutydesign basis of the SFP HX. The additional decay heat resultingfrom offloading more than 4 assemblies perhour woud be tradedoff against the higher background decay beat term assumed in theHOLTEC analysis - 9.93x106 Btu/hr versus the 3716 uprate valueof 634x10' Btahr. At 72 hours after shutdown a fuel asemblyfrm the 3716 MWtcore will be generating approximately249,000 Btlbr of decayheat. For the full core offload thecalculated decay heat load of 60.47x10 Btc/.r exceeds the50.41x105 design basis heat duty of the heat exchanger. Thisindicates that an offiloading rat limit exist Based on the resultsin Appendix L to EC-M98-022, the limiting rate exceeds thecuent 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 hour'time increment represents the time when the SFP

calculation? Specifically, document the reason why 108 hours reached its peak bulk temperature for the partial core offlond inand 12625 hours are considered. EC-M9-022. The design basis heat load for the SFP EX was

takn at the 108 hour icrement. All fuel assembly discharge wascompleted at the 101 hour increment Due to the thermal lag in theSFP bulk temperature the peak bulk temperature didn't occur until7 hours later. The original guidelines for the 3716 uprate calledfor a partial discharge of 1 16 assemblies so the transfer wouldagain be completed at 101 hours and the peak temperature wouldpresumably occur at 108 hours. Now that the partial oftload is a.nnsionnm of 108 assemblies, transfer will ie completed at 99hours after shutdown and peak temperatures could occur at 106hours after shutdomn. Since the 3 day heat load doesn't exceed thedesign basis heat duty of the SEP heat exchanger it really doesn'tmatter whether the beat load is reported at 99 hours, 106 hours or

.________ .________ ___I 08 hours. 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 hour lime increment represents the completion of thefull cote dischare and tiusrepresentsthenmiDmmheatloadonthe 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/ResolutionNumber Page No. _

I Calc Cover Remove 1088 Spent Fuel assemblies from Title? Concur, will change Title to remove 1088 Spent Fuel assembliesPage 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 thatPage 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 calculatedcalculations 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 throughCycles 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 WestinghouseWindsor.

4 2.0 Why is EC-M9B-067 used as a reference? Calculation EC-M98-067 was originally referenced because thepower fraction values used in the draft version of this calculationwere taken from Attachment 8.11 ofEC-M98-067. Subsequently znerror in applying the Kuncertainty in ASB 9-2 was discoveredrendering the power fractions in BC-M98-067 overly conserative.EC-M9867 is being deleted. Attachment 3 recalculates powerfractions with updated formulas fronm ASB 9-2.

5 4.0 Adda core power of3390 for cycles I -1I in the bulleted Concur. Corepowerof3390 MWthasbeenincluded ibulletedsection. 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 updateequations forASB 9-2 and the values used in various upratecalculations. The second attachment gives values for RPF005-001Attachment 9.5

Pago I of 2

Att I What is the relevance of the 12625 hours? This represents the time after shutdown when all 217 coreassemblies have been offload for the full core offlond assumingdischarge is initiated 72 hours after shutdown and 4 assemblies aretransferred every hour.

Reviewed By. Resolved By. tD0L A1u,. ?7/V8a3(Name/Date) David Vlener 8129103 (Name/Date) [onaid Hlj 9112/03Department: Phone: Accepted By./

W3 - Design Engineerng 504J739-6686 (NameDate) -/0 (°/ aK

Pagem2f2

Attachment 6 To

W3FI-2004-0073

List of Regulatory Commitments

f

Attachment 6 toW3F11-2004-0073Page 1 of 1

List of Regulatory Commitments

The following table identifies those actions committed to by Entergy in this document. Anyother statements in this submittal are provided for information purposes and are notconsidered to be regulatory commitments.

TYPE(C eck one) SCHEDULED

ONE- CONTINUING COMPLETIONREVISED COMMITMENT TIME COMPLIANCE DATE (If

ACTION Required)Revised technical specification mark-ups for X 9/30/04technical specification pages 2-3, 3/4 3-19, and 3/43-20 will be provided in a future supplement toreplace those previously provided.

/

Attachment 5 to W3Fl-2004-0073, 'Additional Information ... · 1. NEAD Letter, DE-96100005,...

Documents

Transcript of Attachment 5 to W3Fl-2004-0073, 'Additional Information ... · 1. NEAD Letter, DE-96100005,...