Text

Supplement to Amendment Request NPF-38-249 Extended Power Uprate
	ML043270472
Person / Time
Site:	Waterford
Issue date:	11/16/2004
From:	Dodds R; Entergy Nuclear South, Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NPF-38-249, W3F1-2004-0117
	Download: ML043270472 (54)
	v • d • e

-- Entergy Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Tel 504 739 6379 Fax 504 739 6698 rdodds~entergy.com R.A. (Al) Dodds, III Drector. Nuclear Safety Assurance Waterford 3 W3Fl-2004-0117 November 16, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

REFERENCES:

Supplement to Amendment Request NPF-38-249 Extended Power Uprate Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

1. Entergy Letter dated November 13, 2003, "License Amendment Request NPF-38-249 Extended Power Uprate"

2. Entergy Letter dated October 29, 2004, "Supplement to Amendment Request NPF-38-249 Extended Power Uprate"

3. Entergy Letter dated August 25, 2004, "Supplement to Amendment Request NPF-38-249 Extended Power Uprate"

4. Entergy Letter dated July 14, 2004, "Supplement to Amendment Request NPF-38-249 Extended Power Uprate"

Dear Sir or Madam:

By letter (Reference 1) Entergy Operations, Inc. (Entergy) proposed a change to the Waterford Steam Electric Station, Unit 3 (Waterford 3) Operating License and Technical Specifications to increase the unit's rated thermal power level from 3441 megawatts thermal (MWt) to 3716 MWt. By letter (Reference 2) Entergy supplemented the proposed change to revise the volumes of emergency diesel generator fuel oil required by Technical Specifications 3.8.1.1 and 3.8.1.2 to support extended power uprate.

On November 9, 2004, Entergy and members of your staff held a call to discuss the proposed change to Technical Specification 3.8.1.1 and 3.8.1.2. As a result of the call, one item was determined to need a formal response. Entergy's response is contained in Attachment 1.

Additionally, a marked-up Technical Specification Bases page is provided, for information only, in Attachment 2.

Additionally, in Attachment 5 to Reference 3, Entergy submitted additional information regarding spent fuel pool cooling analysis. This information has subsequently been revised and the revised information is provided in Attachment 3.

The no significant hazards consideration included in References 2 and 4 are not affected by any information contained in this supplemental letter. There are no new commitments contained in this letter.

ADDI

W3Fl-2004-0117 Page 2 of 3 If you have any questions or require additional information, please contact D. Bryan Miller at 504-739-6692.

I declare under penalty of perjury that the foregoing is true and correct. Executed on November 16, 2004.

Sincerely, RAD/DBM/cbh Attachments:

1. Supplemental Information Related to Emergency Diesel Generator Fuel Oil

2. Revised Markup of Technical Specification Bases Pages

3. Additional Information Regarding EPU Spent Fuel Pool Cooling Analysis

W3Fl-2004-0117 Page 3 of 3 cc:

Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Nageswaran Kalyanam MS O-7D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445

Attachment I To W3FI-2004-01 17 Supplemental Information Related to Emergency Diesel Generator Fuel Oil to W3Fl-2004-01 17 Page 1 of 1 Supplemental Information Related to Emergency Diesel Generator Fuel Oil In the Entergy Operations, Inc. (Entergy) letter dated October 29, 2004, Entergy proposed to revise the volumes of emergency diesel generator (DG) fuel oil required by Waterford Steam Electric Station, Unit 3 (Waterford 3) Technical Specifications 3.8.1.1 and 3.8.1.2 to support extended power uprate (EPU) operation. Specifically, 38,760 gallons is being changed to 39,300 gallons and 38,000 gallons is being changed to 37,000 gallons.

As described in the October 29, 2004 submittal, the proposed volume of 39,300 gallons useable will provide the DG with a post-EPU seven day supply of fuel oil based on the load dependent method for calculating stored fuel oil. Also, as described in the October 29, 2004 submittal, the proposed volume of 37,000 gallons useable will provide the DG with a five day supply of fuel oil based on full continuous load (4400kW) of the DG. It should also be noted that 37,000 gallons useable will provide the DG with greater than a six day supply of fuel oil post-EPU based on the load dependent method for calculating stored fuel oil consistent with a bases for the NRC's approval of Amendment 92. Calculations indicate that the DG can operate for approximately 6 days and 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months on 37,000 gallons of fuel oil based on the load dependent method for calculating stored fuel oil.

To W3FI-2004-0117 Markup of Technical Specification Bases Pages (for information only) to W3Fl-2004-01 17 Page 1 of 2 314.8 ELECTRICAL POWER SYSTEMS BASES 314,8.1. 3/4.8.2. and 3/4.8.3 A.C. SOURCES. D.C SOURCES. AND ONSITE POWER DISTRIBUTION SYSTEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for (1) the safe shutdown of the facility and (2) the mitigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of HAG eneral Design Criterion 17 of Appendix A to 10 CFR Part 50.

-The Lmiting Condition for Operation (LCO) ensures that each diesel generator storage tank c tains fueliof a sufficient volume to operate each diesel generator for a period of 7 days.

uuv ebased on the time-dependent loads of the diesel genera followingoss of offsite power and a design bases accident and Includes the capacity to power the engineered safety features in conformance with Regulatory Guile 1.137 October 1979 The minimum onsite stored fuel oil Is sufficient to operate the diesel generator for a period nger than the time to replenish the onsite supply from the outside sources discuss FSAR 9.5.4.2.

I An additional provision is included in the LCO whicK allow the diesel generators to remain operable when their 7 day fuel oil supply Is not available. This provision is acceptable on the basis that replacement fuel oil is onsite within the first 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after falling below the 7 day supply.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety analyses and are based upon maintaining at least one redundant set of onsite A.C. and D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. source. When one diesel generator is inoperable to perform either preplanned maintenance (both preventive and corrective) or unplanned corrective maintenance work, the allowed-outage-time (AOT) can be extended from 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to 10 days. if a temporary emergency diesel generator (TEDG) Is verified available and aligned for backup operation to the permanent plant EDG removed from service. The TEDG will be available prior to removing the permanent plant EDG from service for the extended preplanned maintenance work or prior to exceeding the 72-hour AOT for the extended unplanned corrective maintenance work. A Configuration Risk Management Program (CRMP) is implemented to assess risk of this activity when applying this ACTION. The TEDG availability is verified by: (1) starting the TEDG and verifying proper operation; (2) verifying 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months onsite fuel supply; and (3) ensuring the TEDG is aligned to supply power through a 4.16 kV non-safety bus to the 4.16kV safety bus. A status check for TEDG availability will also be performed at least once every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following the initial TEDG availability verification. The status check shall consists of: (1) verifying the TEDG equipment is mechanically and electrically ready for manual operation; (2) verifying 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months onsite fuel supply; and (3) ensuring the TEDG is aligned to supply power through a 4.16 kV non-safety bus to the 4.16 kV safety bus. If the TEDG becomes unavailable during the 10 day AOT and cannot be restored to available status, the EDG AOT reverts back to 72-hours. The WATERFORD - UNIT 3 B 314 8-1 AMENDMENT NO. 92, -66 to W3F1-2004-0117 Page 2 of 2 Bases Inserts Insert #1 The LCO limit of 39,300 gallons useable corresponds to a level of 96.41% in the fuel oil storage tank. This useable volume is sufficient to operate the diesel generator for 7 days...

Insert #2 To account for instrument uncertainty at least 97.86% indicated level is maintained in the fuel oil storage tank to assure that 39,300 usable gallons are available.

Insert #3

... provided that at least a 6 day supply of fuel oil is available.

Insert #4 The LCO limit of 37,000 gallons useable corresponds to a level of 90.76% in the fuel oil storage tank. This useable volume is sufficient to operate the diesel generator for 5 days based on the full continuous load (4400kW) of the diesel generator and is sufficient to operate the diesel generator for greater than 6 days based on the time dependent loads of the diesel generator following a loss of offsite power and a design basis accident. To account for instrument uncertainty at least 92.21 % indicated level is maintained in the fuel oil storage tank to assure that 37,000 usable gallons are available.

To W3F1-2004-0117 Additional Information Regarding EPU Spent Fuel Pool Cooling Analysis

DRN No.

04-1679 Page(s) 45 CALCULATION (2) Initiating Doc.:

ER-W3-2001-1149-000 COVER PAGE 0

DRN Superseded: 03-1440 El DRNs Voided:

El Calculation SupersededNoided:

El As-BuiltNo ICN Required 0

Pending/lCN Required (Verify current status in IDEAS)

Cl CALCULATION (3)

Reason For Pending Status: (ER, T.S., Change, etc.)

0 DRN ER-W3-2001-1149-000 (4) Calculation No: ECS96-003 1(5) Revision: 0 (6)

Title:

Spent Fuel Pool Heat Loads for a Full Spent Fuel Pool and SFP Cask Storage Area (7) System(s): FHS, FS, CC, SI (8) Component/Equipment identifier:

(9) Safety Code:

(10) Calc Code:

Various 0 Yes (ANOIGGNS Only)

El Quality El No (20)Study Calc El Yes 0D No (10) IOCFR50.59 Review:

(12) Structure: (Optional) 0 Addressed in ER-W3-2001-1140-009 Bldg.

l Elev.

El Attached Room Wall El No LBD Impact Coordinates:

(13) R-Type: B13.40 (14) Org. Code: (ANO/GGNS/RBS Only)

(15) Keywords: Spent Fuel Pool, Decay Heat Load, CCW Heat (19) Topical Codes: (ANO Only)

Exchanger, Ultimate Heat Sink, Fuel Pool Cooling, Component Cooling System, Fuel Pool Cooling Heat Exchanger, 3716 MWt, EPU REVIEWS (16) Name/Signature/Date (17) Name/Signat a

(18) Name/Signature/Date N/A I

/

I Responsible Engineer Design Verifier up isor pproval 0

Reviewer*,

El Checker (Only As-Built DRNs included in Revision)

El Comments Attached El Comments Attached

Reasonableness Review per DC-126 Section 5.8

(1) DRN No.

04-1679 Page(s)

CALCULATION (2)

Initiating Doc.:

ER-W3-2001-1149-000 COVER PAGE Z DRN Superseded: DRN 03-1440 E1 DRNs Voided:

El Calculation SupersededNoided:

O As-Bullt/No ICN Required 0 PendingIlCN Required (Verify current status In IDEAS)

O CALCULATION (3)

Reason For Pending Status: (ER, T.S., Change. etc.)

0 DRN ER-W3-2001-1149-000 (4) Calculation No: ECS96-003

.1 '5 Revision: 0 (6)

Title:

Spent Fuel Pool Heat Loads for a Full Spent Fuel Pool and SFP Cask Storage Area (7) System(s): FHS, FS, ><DC,

,jS, (8) Component/Equipment Identifier:

(9) Safety Code:

(10)

Calc Code:

[yes (ANO/GGNS Only)

El Quality Ea No (20)Study Calc El Yes 0D No (11) I0CFR50.59 Review:

(12) Structure: (optional) 0 Addressed in ER-W3-2001-1149-009 Bldg.

l Elev.

o Attached Room Wall a No LBD Impact Coordinates:

(13) R-Type:

(14)W f13 40 jj,?1°

(

Org. Code: (ANO/GGNS/RBS Only)

(15) Keywords: Spent Fuel Pool, becay Heat Load, CCW Heat (19) Topical Codes: (ANO Only)

Exchanger, Ultimate Heat Sink, Fuel Pool Cooling, Component Cooling System, Fuel Pool Cooling Heat Exchanger REVIEWS (16) Name/Signature/Date

( n Name/Signature/Date (18) Name/Signature/Date Michael Caldwell /

10/14/04 Jeff Famsworth I 10/14/04

CZAtRwr, Z. dCHc H 5-G Responsible Engineer 0

Design Verifier Supervisor/Approval

[3 Reviewer El Checker (Only As-Built DRNs Included In Revision)

El Comments Attached El Comments Attached

CALCULATION CALCULATION NO:

ECS96-003 REFERENCE SHEET REVISION:

0

1.

DRNs INCORPORATED:

None II.

RELATIONSHIPS:

Sht Rev Input Output Impact DRN/ Tracking No.

Doc Doc YIN

1. ECM98-022 1

0 ED El N

2. ECM98-067 1

0 0

El N

3. MNQ9-3 1

2 El Y

03-726

4. MNQ9-9 1

4 El 0

Y 03-729

5. RF-005-001 0

9 El 0

Y ER-W3-2001-1149-009 I11.

CROSS

REFERENCES:

1. NEAD Letter, DE-96/00005, 'Waterford 3 Fuel Performance Summary,' January 5, 1996

2.

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

3.

NUREG-0800, -Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants"

4.

Technical Specification Bases 5.6.4

5. CWTR3-04-214, 'Transmittal of Waterford-3 3716 MWt Uprate Task 2.1 and New l&C Deliverables" October 15, 2004

6.

P05.13 IV.

SOFTWARE USED:

Title:

Microsoft Excel Version/Release:

97 SR-2 Disk/CD No.: N/A DISK/CDS INCLUDED:

Title:

N/A Version/Release:

N/A Disk/CD No.: N/A V.

OTHER CHANGES:

None

DESIGN VERIFICATION RECORD PAGE 1 OF 2 methods to be used:

Design Review Qualification Testing Alternate Calculations Revision Document Title 0

Spent Fuel Pool Heat Loads for a Full Spent Fuel Pool and SFP Cask Storage Area

=.

i Verification Completed By, IComment Resolutions Accepted By

DESIGN VERIFICATION RECORD PAGE 2 OF 2 DocumentNumber DRN 04-1679 (ECS96-003)

Revision N/A MNT ACPTI INIT/

NO.

COMMENT RESOLUTION IYIN DATE Minor editorial comments resolved.

WATERFORD 3 ENGINEERING Entergy 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............................

2 3.0 Method............................

2 4.0 Input Criteria and Assumptions............................

3 5.0 Results Summary............................................................................6 6.0 Calculations.....................................................................................7

WATERFORD 3 ENGINEERING efgy' GENERAL COMPUTATION SHEET CALC. NO.: ECS96-003 PAGE ii LIST OF EFFECTIVE PAGES PAGE REVISION Calculation 1-8 DRN 04-1679 Attachments:

1 1-5 DRN 04-1679 2

1-5 DRN 04-1679 3

1-2 DRN 04-1679 4

1-4 DRN 04-1679 5

1-2 DRN 04-1679 6

1-5 DRN 04-1679 REVISION DESCRIPTION OF AFFECTED NO.

REVISION PAGES 0

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

All DRN 04-Changed the calculation to support a 15 day outage, an 18 All 1679 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 1-6. Decay heat loads are calculated using ASB 9-2 methodology.

Changed to clarify purpose and to increase offloaded fuel assemblies to conservatively bound Technical Specification maximum assembly capacity of 2398 fuel assemblies. Time to boil analyses are removed since these analyses are contained in ECM98-022 and ECM98-067. Document is repaginated.

I%

WATERFORD 3 DESIGN ENGINEERING

-- I-7h t GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 1

OF 8

1.0 Purpose

This calculation has two distinct purposes.

One is to evaluate the spent fuel pool cooling loads on the Ultimate Heat Sink based upon the physical storage limitations of the spent fuel pool and cask storage area (2104 assemblies). The other purpose is to evaluate the decay heat loads in the spent fuel pool for refueling and fuel storage management.

1.

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.

2.

This calculation provides updated Spent Fuel Pool Cooling Capability for.5 of Refueling Procedure RF-005-001. 2332 previously offloaded assemblies are assumed for the partial core offload, and 2224 previously offloaded assemblies are assumed for the full core offload.

This analysis bounds the number of assemblies as discussed in Technical Specification Bases 5.6.4.

For both purposes, 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 I month (720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months ) after reactor shutdown.

WATERFORD 3 DESIGN ENGINEERING terw GENERAL COMPUTATION SHEET CALC. NO.

ECS96"03 PAGE 2

OF e

2.0

References:

1. Calculation EC-M98-022, Rev 0, "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, "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. 1 extends the results of the original analysis to confirm that the calculated heat loads on the SFP 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 power of 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 Btu/hr. The heat rates are then added to establish a total heat rate contribution for all the 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 1 month after shutdown to illustrate the rapid decline in decay heat over time.

WATERFORD 3 DESIGN ENGINEERING Enterd GENERAL COMPUTATION SHEET CALC. NO.

ECS96S003 PAGE 3

OF 8

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 I month after reactor shutdown.

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. 1 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 I 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 offload 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 SFP/SFP Cask Storage Area has a total storage area of 2,104 assemblies with the HOLTEC high density storage racks in place. Attachments 1 and 2 are used to determine the inputs to the Ultimate Heat Sink analyses, calculations MN(Q)-9-3, "Ultimate Heat Sink Study" and MN(Q)-9-9, 'Wet Cooling Tower Losses During LOCA". Attachments 4, 5, and 6 are used to develop the inputs to RF-005-001.

The Excel spreadsheets In Attachments 1, 2 and 6 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

WATERFORD 3 DESIGN ENGINEERING

~Entery GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 4

OF 8

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 1 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. Attachment 6 provides a yet more conservative analysis, assuming the SFP and Cask Storage Area are full, and partial and full core offloads are then added. The number of assemblies assumed in fully bounds the Technical Specification Bases 5.6.4 maximum number of assemblies (2398).

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 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 X(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

a^

WATERFORD 3 DESIGN ENGINEERING EntevVy GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 5

OF 8

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 3441and 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 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 Decay Heat (10 6 Btu/hr)

Decay Heat (10" Btu/hr)

Shutdown (days) 108 Assembly Discharge Full Core Discharqe 3

32.73 59.79 5

27.46 49.21 7

24.55 43.36 10 22.06 38.36 15 19.73 33.66 30 15.98 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

WATERFORD 3 DESIGN ENGINEERING Entergy GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 6

OF 8

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. This analysis provides the conclusions for Purpose 1, which is to provide input to the Ultimate Heat Sink analysis.

Time After Decay Heat (106 Btu/hr)

Decay Heat (106 Btu/hr)

Shutdown (days) 108 Assembly Discharge Full Core Discharge 3

33.17 60.24 5

27.91 49.67 7

24.99 43.81 10 22.51 38.82 15 20.17 33.12 30 16.42 26.59 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, with an additional full or partial core current offload. This evaluation conservatively bounds the physical capacity of these areas (2104 assemblies). For the partial core offload of 108 assemblies the background decay heat is based on 2,332 previously stored assemblies from 24 fuel cycles. For the full core offload of 217 assemblies the background decay heat is based on 2224 previously stored assemblies from 23 fuel cycles. The total number of assemblies analyzed for the full core offload (2441) and the partial core offload (2440) exceeds the maximum storage capacity of the spent fuel pool, cask storage area, and refueling canal as defined by Technical Specification 5.6.4 (2398 assemblies). The refueling canal is only used during the final offload, and has a maximum capacity of 294 assemblies. This data is taken from Attachment 6, and (along with Attachments 4 and 5) is used to provide input to RF-005-001.

WATERFORD 3 DESIGN ENGINEERING MEnterU GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 7

OF 8

Time After Decay Heat (10e Btu/hr)

Decay Heat (108 Btu/hr)

Shutdown (days) 108 Assembly Discharge Full Core Discharge 3

33.81 60.88 5

28.54 50.30 7

25.63 44.45 10 23.14 39.45 15 20.81 34.75 30 17.06 27.23 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 is detailed in Attachment 1. 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).

This is detailed in Attachment 2. 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

TT WATERFORD 3 DESIGN ENGINEERING

-EnteLi GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003 PAGE 8

OF 8

fission product decay term as specified in the Standard Review Plan, NUREG-0800. provides a similar analysis assuming 2332 previously offloaded assemblies for the partial core discharge case, and 2224 previously offloaded assemblies for the full core discharge case.

nt WATERFORD 3 DESIGN ENGINEERING GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003, Attachment I PAGE 1

OF 5

The following Excel spreadsheet calculates the decay heat load contribution for each refueling outage from RF cycle 1 to RF cycle 20. The following assumptions were 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 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.

8. 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 to1849 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 Nom EOC No.

Power Date (MWt)

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

(# assys x P.F.)

Factors Based on ASB 9-2 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 3390 11/26/86 3390 04/01/88 3390 09/23/89 3390 03/15/91 3390 09/20/92 3390 03/04/94 3390 09/22/95 3390 04/11/97 3390 02/05/99 3390 09/15100 3390 03/15/02 3441 09/15/03 3441 03/15/05 3716 09/15/06 3716 03/15/08 3716 09115109 3716 03/15/11 3716 09/15/12 3716 03/15/14 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 92 108 108 108 108 108 108 108 92 176 260 344 428 520 616 700 792 884 960 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 168hrs 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 3.560931 E05 0.003106393 3.698087E-05 0.003553627 3.862638E-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 4.632871 E-05 0.004418388 4.802595E-05 0.004581581 0.0090000 4.979980E-05 0.005583343 5.169762E-05 0.005821709 5.390471E-05 0.006173838 5.716516E-05 0.006964770 6.448861 E-05 0.009516736 8.811793E-05 0.019901933 0.0539623 1.842772E-04 Heat Load per Assy Btulhr 1,705 1,767 1,832 1,899 1,972 2,059 2,140 2,218 2,299 2,383 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 3.623531 E-03 3.433153E-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 Btu/hr Where the background decay heat load Is calculated as follows Background heat load = 0.03720983390000'1.02-34131217+0.009-344100011.005134131217+.0.0539623'37160001.005'3413/217 Decay heat due to partial core offload at times Indicated This is the 3 day limiting heat value assuming all assemblies offioaded at one time This is the heat load at completion of offload assuming 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 when 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 Approximate time when pool reaches peak temperature for a 7 day hold prior to all fuel being discharged 72 hrs 99 hrs 106 hrs 120 hrs 168 hrs 184 hrs 240 hrs 360 hrs 720 hrs 27,045,032 Btuthr 23,679,200 Btuihr 22,989,147 Btu/hr 21,781,314 18,868,285 18,179,131 16,381,596 14,042,528 10,296,411 Btulhr Btullhr Btulhr Btulhr Btulhr Btuthr Where decay heat due to partial core offload equals Non Dim Power Gen Factor at time

3735000-34131217 Example at 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months partial decay heat load = 0.460384118*37350003413/217 = 27,045,032 Total Decay Heat Loads at times Indicated equals partial heat load plus background heat load 72 hrs 99 hrs 106 hrs 120 hrs 168 hrs 184 hrs 240 hrs 360 hrs 720 hrs 32,728,181 29,362,349 28,672,296 27,464,463 24,551,434 23,862,280 22,064,745 19,725,677 15,979,560 Btulhr Bltuhr 13tuthr Btu/hr Btuthr Btulhr Btu/hr Btu/hr Btuthr

ECS96-003, Attachment I 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)

CYCLE Assemblies Cumulative EFPY Discharged Fuel Pool Years Since Discharge 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 3390 11126/86 3390 04101188 3390 09123189 3390 03115191 3390 09/20192 3390 03/04194 3390 09122/95 3390 04/11197 3390 02/05/99 3390 09/15100 3390 03115102 3441 09115103 3441 03/15105 3716 09115106 3716 03115108 3716 09115/09 3716 03/15/11 3716 09115/12 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 92 108 108 108 108 108 217 92 176 260 344 428 520 616 700 792 884 960 1052 1144 1252 1360 1468 1576 1684 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 3.314351 E-05 0.002885761 3.435430E-05 0.002991182 3.560931 E-05 0.003106393 3.698087E-05 0.003244616 3.862638E-05 0.003892268 4.013335E-05 0.003993552 4.1 59950E-05 0.003622018 4.311926E-05 0.004111919 4.469477E-05 0.004262242 4.632871E-05 0.003649973 0.0386091 4.802595E-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 6.448861E-05 0.009516736 8.811793E-05 0.019901933 0.0483790 1.842772E-04 Heat Load por Assy Btulhr 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 10,770 249,143 196,275 200,653 173,818 150,910 129,362 94,852 19 3716 03/15/14 1901 72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 360 hrs 720 hrs 0.925031051 0.728739120 7.449942E-01 6.453588E-01 5.603057E-01 4.803017E-01 3.521719E-01 4.262816E-03 3.358245E-03 3.433153E-03 2.974004E-03 2.582054E-03 2.213372E-03 1.622912E-03

ECS96-003, Attachment I Page 5 of 5 Background decay heat load due to 18 previous refueling loads 5,449,634 Btu/hr Where decay heat load is calculated by the following expression Heat load = 0.0386091 3390000*1.02'34131217+0.009337834410001.00534131217+0.048379'3735000*34131217 Full core offload decay heat load at times Indicated This is 3 day Omiting heat value assuming all assemblies offloaded at one time This Is total time to offload full core starting at 72 hrs after shutdown and transferring 4 assemblies/hr 72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 360 hrs 720 hrs 54,340,480 Btulhr 42,809,410 Btulhr 43,764,307 37,911,277 32,914,873 28,215,080 20,688,159 Btuhrn Btulhr Btu/hr Btulhr Btulhr Decay heat due to full core offload Is calculated by Heat Load = Non Dim Power Gen Factor

3735000

3413/217 Total Decay Heat Load due to Full Core Offload at time 72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 360 hrs 720 hrs 59,790,114 48,259,044 49,213,941 43,360,911 38,364,507 33,664,714 26,137,793 Btuthr Btulhr Stuthr Btuthr Btulhr Btulhr Btuthr

WATERFORD 3 DESIGN ENGINEERING

-Entery GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003, PAGE 1

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 were made in developing this spreadsheet:

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

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 I thru II 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 all 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.

Cycle No.

Nom EOC Date I

Power (MWM) 3390 11126186 3390 04101/88 3390 09/23/89 3390 03/15/91 3390 09120/92 3390 03/04194 3390 09/295 3390 04/111/97 3390 02/05199 3390 09115/00 3390 0315/02 3441 09115/03 3441 03/15/Q5 3718 09115/00 3718 03115/08 3716 09115M09 3716 03/15/11 3716 09/15/12 3716 03115Y14 3716 09/15115 371B 03115117 ECS96-003, Attachment 2 Page 2 of 5 Decay Heat Load Duo to Full SFP & Cask Storage Area Partial Core Offload SFP 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. Facto Power Gen Based on ASB 9-2 Assy Btu/hr (9 assys x P. F.)

Factors 4.5 92 92 32 2.738034E-03 2.976124E-05 1.587 4.5 84 176 30.5 2.591271E-03 3.084848E-05 1,845 4.5 84 260 29 2.685934E-03 3.197540E-05 1,705 4.5 84 344 27.5 2.784055E-03 3.314351E-05 1,767 4.6 84 428 26 0.002885781 3.435430E-05 1,832 4.5 92 520 24.5 0.003276057 3.660931E-05 1,8S9 4.5 98 618 2292 0.003550164 3.598087E-05 1,972 4.5 84 700 21.1 0.00324461B 3.882384-05 2,059 4.5 92 792 19.5 3.6922688-03 4.013335E-05 Z,140 4.5 92 884 18 0.003827154 4.159950E-05 2.218 4.5 76 960 16.5 0.003277064 0.0345524 4.311928E-05 2,299 4.5 92 1052 15 0.004111919 4A69477E-05 Z,383 4.5 92 1144 13.5 0.004262242 0.0083742 4.632871E-05 2708 4.5 108 1252 12 0.005186803 4.802595E-05 2,807 4.5 108 1360 10.5 0.005378378 4.970980E-05 Z911 4.5 108 1468 9

0.005583343 5.169762E-05 3,022 4.5 108 1578 7.5 0.005821709 5.390471E-05 3,150 4.5 108 1684 0.006173838 5.716516E-05 3.341 4.5 108 1792 4.5 0.008964770 6.448861E-05 3,769 4.5 108 1900 3

0.009516736 8.811793E-05 5,150 4.5 108 2008 1.5 0.019901933 0.0645275 1.842772E-04 10,770

ECS96-003, Attachment 2 Page 3 of 5 22 3716 09/15118 4.5 108 2116 72 hrs 0.460384118 0.004262818 99 hrs 0.403087995 0.003732296 120 hrs 0.37078052B 0.003433153 168 hrs 0.321192409 0.002974004 240 hnr 0.278881811 0.002582054 380 hrs 0.239044167 0.002213372 720 his 0.17527449 0.001822912 Background decay heat load due to 21 previous refueling loads 6,124,808 Bthr Mare heat load = 0.03455243390000'1.02h34131217+0.00837423441000h1.005*34131217 + 0.0645275-3716000'1.005*3413/217 Decay heat due to partial core offload at times Indicated 72 hrs 27,045,032 BShfhr 99 hrs 23,679,200 Bhtftw 120 hrs 21,781,314 Btuihr 168 hra 18,868,285 BUhr 240 hnr 16,381,596 Btuhr 360 hrs 14,04ZS28 Bihr 720 hrs 10,296,411 BLfhr Where heat load = Non Dim Power Gen Factor 3735000

34131217 Total Decay Heat Load due to Partial Core Offload at times Indicated 72 houbs 33,169,840 Btuhr 120 hours0.00139 days 0.0333 hours 1.984127e-4 weeks 4.566e-5 months 27,905,122 Bkluft 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months 24,993,093 Bh/hr 240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months 22,506,404 Bhuftr 360 hours0.00417 days 0.1 hours 5.952381e-4 weeks 1.3698e-4 months 20,167,336 BbuJhr 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 18,421,219 Btu/hr

ECS96.003, Attachment 2 Pago 4 of 5 Decay Heat Load Due to Full SFP & Cask Storage Area Full Core Offload Capacity Limited to 2104 Assemblies Cycle No Nom EOC Date CYCLE Power EFPY (MM) 1 3390 11/268 4.5 2

3390 04ta/88 4.5 3

3390 09123189 4.5 4

3390 03115/91 4.5 5

3390 09/20/92 4.5 6

3390 03104/94 4.5 7

3390 09t22195 4.5 8

3390 04111/97 4.5 9

3390 a2/05/99 4.5 10 3390 09/15/00 4.5 11 3390 03/15102 4.5 12 3441 09115/03 4.5 13 3441 03/15105 4.5 14 3716 09115/08 4.5 15 3718 015108 4.5 16 3716 09/1SJ09 4.5 17 3715 03t15/11 4.5 18 3718 09/15112 4.5 19 3710 03115114 4.5 20 3718 09/15/15 4.5 Assemblies Cumulative Fuel Years Since Non Dim Power Sum of Power Fractions Heat Load per Discharged Pool D1scharge Gen. Factor Power Gen Based on ASB 9-2 Assy Btuthr

(# assys x P. F.)

Factors 92 84 84 84 84 92 96 84 92 92 78 92 92 108 108 108 108 108 108 10B 92 176 260 344 428 520 616 700 792 884 9B0 1052 1144 1252 1360 14B8 1578 1684 1792 1900 30.5 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 2.8380S8E-03 2.685934E-03 2.784055E-03 2.885761E-03 2.991182E-03 3.402240E-03 3.708132E-03 3.371201E-03 3.827154E-03 3.966972E-03 3.396802E-03 0.0358575 4.262242E-03 4.41B388E-03 0.0086806 5.378378E-03 5.58334E-03 5.821709E-03 6.173838E-03 6.904770E-03 0.009516736 1.990193E-02 0.0593407 3.084848E-05 1.645 3.197540E-05 1.705 3.314351E-05 1,767 3A35430E-05 1.832 3.560931E-05 1,899 3.698087E-05 1.972 3.862638E-05 2059 4.013335E-05 2,140 4.1599s50E-05 2,218 4.311926E-05 2.299 4.469477-E05 2,383 4.632871E-05 2,470 4.80259SE-05 2,B07 4.97998OE-05 2.911 5.169762E-05 3,022 5.390471E-05 3,150 5.716516E-05 3,341 6.448861E-05 3,769 8.811793E-05 5,150 1.B42772E-04 10,770

ECS96-003, Attachment 2 Page 5 of 5 21 3718 03/15f17 4.5 217 2117 72 hts 128.25 his 120 hrs 168 hrs 240 hrs 360 hrs 720 h"s 9.250311E-01 7.287391E-01 1.7131109 7.449942E-01 8.453588E-01 5.603057E-01 4.803017E-01 3.521719E-01 4.26281 E-03 3.358245E-03 3.433153E-03 2.974004E-03 2.582054E-03 2.213372E-03 1.622912E-03 249,143 106,275 200,653 173,818 150,910 129,362 94,852 Background decay heat load due to 20 previous refueling loads 5,907.794 Btfthr Where heat load = 0.0358575 3390000 1.02 3413 217+0.0086806*3441000'1.005'34131217+0.0593407371(8000o1.005-3413217 Decay heat due to full core offload at times Indicated 72 hns 126.25 hns 120 hns 163 hns 240 hrs 360 hrs 720 hrs 54,334,370 Btulhr 42,804,B98 Bhzfr 43,759,388 BMA/hr 37,907,014 Bhlhr 32,911,172 Btu/hr 28,211,907 Otu/hr 20,685,833 BUthr heat load = Non Dim Power Gen Fador 3716000 1.005

3413/217 Total Decay Heat Load due to Full Core Offload at times Indicated 72 hrs 12625 hrs 120 his 168 hrs 240 hrs 360 his 720 hrs 60,242,163 Btuf/l 48,712,390 Bltuhr 49,667,179 Btu/hr 43,814,807 BtUlhr 38,818,965 Btuhr 34,119,701 B/hr 26,593,627 Btulhr

ECS6-003, ATTACHMENT 3 Page 1 of 2 Spent Fuel Pool Decay Power Fractlons

t.

141912000 secs

t.

8.10E405 sacs 10+1s 142722000 sacs 1

2 3

4 5

6 7

8 9

10 11 0.598 1.65 3.1 3.87 2.33 1.29 0.452 0.328 0.17 0.0885 0.114 1.772 0.5774 0.06743 0.006214 0.0004739 0.0000481 O.0O05344 5.716E-07 1.036E-07 2.959E-08 7.585E-10 SumMOO Sum An an PlP,(*,4 + t.

5.1785E-04 1.03571E-01 PIP,(-. t*

0.00283B156 0.567231145 o.OOOE6+00 O.OOOOE+00 0

0 0

0 121948E-36 6.4413E-08 0.00126744 0.10230349 0

4.566E-167 1.5490E-17 0.0060D9168 0.206441609 0.1563164 0.08445142 0.11392998 PIPO(tt.

P(U-239YP, P(Nr.239)/Po PIlP (TtJ"(1

+ K)( P/Pg("t)- P/Po (-, tlo,j) where K.2fordecaytmnes less ttan 10' s*cs and K-.lfordecaytiebehween0'andl0sec 2.550tE-03 fort,-

8.10E+05 secs nd per Standard Review Plan K 0.1 for all 1ag term siorage calcuatmna 3.0184E-178 Heavy Mel Decy Heat Term 9.6106E-05 Heavy Metal Decay Heat Term Z646741 E03 Total Fracion o Opemkg Power Power Fraction Term Tlme Vtth K " 0.1 Long Term Storage Short Term Storage 3 days 4.262S164-03 Values used In EC-S9603 Values used In EC.SSS-003 5 days 3.433153E-03 7 days Z9740U4E-3 Thne (years)

Pwer Fraction Tbne (hors)

Power Fraction 10 days 2.582054E-03 3S.3 2.68523E-05 72 4.262816E-03 15 day 2.213372E-03 35 2.770039E-05 80 4.084450E-03 30 days 1,622912E-03 34.8 2.78332E-05 88 3.924993E-3 60 days 1.105381E-03 33.5 2.87123E-05 96 3.782063E-a 90 da" 8.748586E-04 33.3 2.885004-05 99 3.732296Z-03 32 2.97612E-05 104 3.653601E-03 1 year 2.824211E-04 30.5 3.084846E-05 108 3.594228E-03 1.5 years 1.842772E-04 29 3.197540E-05 112 3.53781BE-03 2 yeas 1.3484B0E-04 27.5 3.314351E-05 126.25 3.358245E-03 2.5 years 1.059989E-04 28 3.435430E-05 120 3.433153E-3 3 years 8.811793E-05 25.92 3.442010E-05 131 3.304947E-03 3.5 years 7.873748E-05 24.5 3.580931E45 132 3.294102E-03 4 years 6.93827CE0-0 24.42 3.56775E-05 141 3.201919E-03 4.5 yeas 8.4488B1E-05 24.1 3.59517E-5 188 2.974004E-03 2Z92 3.698087E-05 184 2.885380E-03 22.8 3.7265E-05 195 2.799367E-03 22.5 3.73543E-05 240 2.5820544-03 21.1 3.862638E-OS 380 2.213372E43 21 3.87189E-05 720 1.622912E-03 19.5 4.013335E-05 220 2.669831E403 18 4.159950-05 225 2.646741E-03 18.5 4.311926E-05 15 4.4694T7E-05 13.5 4.832871E-05 Short Term Storage Values For use In evaluating hourly

ECS96-003, ATTACHMENT 3 Page 2 of 2 nnme wlth K - 0.1 5 yeaws 6.118300E-05 6 yews 5.71851EE-05 7 years 5.4802542-05 8 yere 5.310939E-05 9 years 5.169762E-05 10yers 5.041414E-05 15 yews:

4.489477E-O5 20 yew:

3.9S5B21E-05 Time er) Power Fractilon 12 4.802595E-05 10.5 4.979SS0E-05 9

5.169762E-05 7.5 5.390471E-05 6

5.716516E-05 4.5 6.4488B1E-05 3

8.811793E-05 1.5 1.842772E204 change In decay heat during partial offload hats Power Fraction 73 0.0042394 74 0.0042163 75 0.0041935 76 0.0041711 77 0.0041490 78 0.0041272 79 0.0041057 80 0.0040844 81 0.0040635 82 0.0040429 83 0.0040228 84 0.0040025 85 0.0039827 86 0.0039832 87 0.0039440 8s 0.0039250 89 0.0039063 90 0.0038878 91 0.003889B 92 0.0038516 93 0.0038339 94 0,0038164 95 0.0037991 96 0.003721 97 0.0037853 98 0.0037487 99 0.0037323 100 0.0037161 101 0.0037002 102 0.0036845 103 0.0036689 104 0.0036536 105 0.0036385 10B 0.0038235 107 0.0038088 108 0.0035942 116 0.0034842 124 0.0033848 128 0.0033383

ECS96-003, ATTACHMENT 4 Page 1 of 4 Calculations Performed in Support of RF-005-001 Attachment 9.5 Purpose Use SFP HX single failure decay heat limit of 29 x Id0 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-005-001 Attachment 9.5.

Maximum background decay heat from 2332 previously stored assemblies 6,762,518 Btulhr From Attachment 6 SFP & Cask Storage Area decay heat calculation Core Rating MWt Partial Core Offloading UImits Currently in RF-005-001 Max Number of Max Authorized Assys w new Time after Non Dim EFPY Number of PFs & heat Shutdownr, Power Gen Factor Assys limit of 29E06 Q#12lhr Heat load due to offload (Btulhr)

Power Fraction per ASB 9-2 (Corrected K factor)

Total Heat Load Cycle 22 Offload (Btumhr) 3716 4.5 79 72 hrs 0.336762456 0.3751278 19,782,940 22.036.692 0.004262816 26,545.458 28,799,210 88 Where Power Gen Factor = Number of Assemblies

Power Fraction Heat load = Power Gen Factor

3735000

3413 1 217 Total heat load = heat load due to offload + background decay heat load 82 80 hrs 92 85 88 hrs 96 0.334924861 0.375769356 0.333624366 0.376799284 0.332821578 0.378206338 0.328824082 0.376320893 19,674,991 22,074,380 19,598,594 22,134,883 19,551,435 22,217,540 19,316,604 22,106,780 0.004084450 26,437,509 28,836,898 0.003924993 26,361,112 28,897,401 0.003782063 26,313,953 28,980,058 0.003653601 26,079,122 28,869,298 88 96 hrs 100 90 104 hrs 103

ECS96-003, ATTACHMENT 4 Page 2 of 4 93 112 hrs 106 108 120 hrs 0.329016877 19,327,930 0.375008483 22,029,683 0.370780526 21,781,314 0.377646832 22,184,672 0.356934305 20,967,925 0.376763989 22,132,810 0.003537816 26,090,448 28,792,201 0.003433153 28,543,832 28,947,190 0.003304947 27,730,443 28,895,328 110 108 131 hrs 114

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 a 3,650 gpm.

Component Cooling Water Flow = 5,000 gpm Component Cooling Water Temperature 90°F Total Amount of Fuel Assemblies Transferred - 217 Maximum background decay heat from 2224 previously stored assemblies 6,539,675 Btulhr (From Attachment 6)

Core Number of Time After Decay Heat Power Fraction Total Decay Rating EFPY Assemblies in Shutdown Power Gen Factor of Offload per ASS 9-2 with Heat Load MWt Offload (hours)

(Btuthr) corrected K term (Btulhr) 3716 4.5 217 72 0.925031051 54,340.480 0.004262816 60,880,155 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 after reactor shutdown, 60,880,155 Btulhr, exceeds the SFP primary heat exchanger heat duty limit of 52.47 x 10" Btulhr calculated in EC-M98-022, Appendix K. The original maximum Holtec decay heat load was 51,873,480 Btulhr. Appendix L to ECM98-022 shows a new decay heat load of 48,669,323. In order to ensure that the original analyes remain bounding, the total decay heat load as determined in Appendix L of ECM98-022 will be considered the maximum heat duty. In order to not violate the heat duty limit of 48.67 x 1 ltBtulhr, the number of spent assemblies that can be transfered to the pool must be controlled. The following tabulation gives the maximum number of spent assemblies that can be stored in the SFP at the specified time after reactor shutdown and not violate the heat duty limit of 48.67 x 1I& Btu/hr.

168 72 0.716153072 42,070,049 0.004262816 48,609,724 171 76 0.713259117 41,900,045 0.004171106 48,439,721 175 80 0.714778666 41,989,310 0.00408445 48,528,986 179 84 0.716450077 42,087,497 0.004002514 48,627,172 182 88 0.714348643 41,964,049 0.003924993 48,503,724 186 92 0.716397168 42,084,388 0.003851598 48,624,064 189 96 0.714809979 41,991,150 0.003782063 48,530,825 192 100 0.713499174 41,914,147 0.003716142 48,453,823 196 104 0.716105778 42,067,271 0.003653601 48,606,946 197 106 0.713835534 41,933,907 0.003623531 48,473,582 199 108 0.715250975 42,017,056 0.003594226 48,556,731

ECS96-003, ATTACHMENT 4 Page 4 of 4 202 112 205 116 208 120 211 124 0.714638807 41,981,094 0.714257545 41,958,697 0.714095829 41,949,197 0.714142678 41,951,950 0.71438749 41,966,331 0.714820041 41,991,741 0.820707754 48,212,061 0.003433153 0.003384562 48,488,873 48,491,625 0.003537816 48,520,770 0.003484183 48,498,373 214 128 217 132 0.003338259 48,506,006 0.003294102 48,531,416 0.003782063 54,751,736 217 96 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 I tf Btu/hr and the total decay heat load is 54.75 x I CP tulhr. 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 flow to the heat exchanger at 5,000 gpm at S86 F.

217

120 0.744994206 43,764,307 0.003433153 50,303,982 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 SFP Is 50.30 x 1i6 Btuthr. 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 92 F and the bulk pool temperature can be maintained at 155 F. If the CCW inlet temperature to the heat exchanger increases to 105 F, the full core offload would have to be delayed to 225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months after reactor shutdown in order to maintain the bulk pool temperature at 155. F and not violate the heat exchanger heat duty limit of4O.40 x 106 Btulhr specified In Appendix K of EC-M98-022.

217 225 0.574342773 33,739,475 2.646741E-03 40,279,150

ECS96-003, ATTACHMENT 5 Page 1 of 2 Backup HX Heat Duty Calculations Maximum heat duty of Backup HX 16.65xI06 Btu/hr per EC-M98-067 at a CCW inlet temperature of 90 degrees.

Determine decay time before Backup HX can handle heat load from partial core offload 108 assemblies from 3716 MWt uprate EC-S96-003 2332 assemblies in storage heat load 6,762,518 Btu/hr Establish maximum decay heat load from partial core offload by subtracting above background decay heats from heat duty EC-S96-003 2332 assemblies in storage 9,887,482 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 / (108*3735000 *3413 / 217)

(PF) =

0.001558 (required)

Use equations in Attachment 3 and iterate time after shutdown to obtain the required PF value To PF 779 hrs 0.001557634 Decay heat load = 108

0.001625235

3735000

3413 /217 =

9,882,262 16,644,780 Btulhr

ECS96-003, ATTACHMENT 5 Page 2 of 2 Full core offload of 217 assemblies Determine decay time before SFP Backup HX can handle heat load from a full core offload ECS96-003 2224 assemblies in storage heat load 6,539,675 Btu/hr Maximum heat duty on heat exchanger 16.65x106 Btulhr EC-S96-003 with 2224 previously stored assemblies 10,110,325 Btulhr Allowable decay heat load due to offload Heat load = 217 * (PF)

3735000

3413 /217 = (PF) "3735000

3413 EC-S96-0()3 (PF) = 0.000793119 reqi TX Nhounl PF 2545 0.000792363 106.0 days after shutdown Decay heat load = 0.000792363

3735000

3413 =

uired Core Offload Total 10,100,693 16,640,368 Btu/hr

T===!-

WATERFORD 3 DESIGN ENGINEERING

~~Enters GENERAL COMPUTATION SHEET CALC. NO.

ECS96-003, PAGE 1

OF 5

The following Excel spreadsheet calculates the decay heat load contribution for partial and full core offloads for refueling outages from RF cycle 1 to RF cycle 24.

The following assumptions were made in developing this spreadsheet:

1. The nominal core power level for cycles 1 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 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 all 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 for the partial core offload, and also In the refueling canal for the full core offload. For the partial core offload, 2332 assemblies from 24 previous offloads are conservatively assumed to be stored in the spent fuel pool and the cask storage pit. Thus, the total number of analyzed assemblies (2440) for the partial core offload conservatively exceeds the actual storage capacity of these areas (2104 assemblies).

For the full core offload, the total number of assemblies analyzed for the full core offload exceeds the maximum storage capacity of the spent fuel pool, cask storage pit, and refueling canal of 2398 assemblies as discussed In the Technical Specification Bases 5.6.4.

2224 assemblies from 23 previous refuelings are assumed to exist prior to the full core offload of 217 assemblies.

ECS96-003, ATTACHMENT 6 Page 2 of 5 Decay Heat Load for 3716 Uprate Starting with Cycle 14 Offload Full Final Core Offload (Full Spent Fuel Pool, Full Cask Storage Pit, Full Refueling Canal)

(Maximum Storage Limit Is 2398 assemblies)

Cycle Nom No.

Power (MWt)

I 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 24 24 24 24 3390 3390 3390 3390 3390 3390 3390 3390 3390 3390 3390 3441 3441 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 EOC Date CYCLE Assemblies Cumulative Years Non Dim Power Sum of Power Power Heat Load per EFPY Discharged Fuol Pool Since Gen. Factor Gen Factors Fractions Assy Btufhr Discharge (# assys x P. F.)

Based on ASB 9-2 11126/1986 4.5 92 92 34.8 0.0025606570174 2.78332E-05 1,514 4/1/1988 4.5 84 176 33.5 0.0024118357211 2.87123E-05 1,562 9123/1989 4.5 84 260 32 0.0024999437999 2.97612E-05 1,619 3/15/1991 4.5 84 344 30.5 0.0025912706026 3.08485E-05 1,678 9/20/1992 4.5 84 428 29 0.0026859337143 3.19754E-05 1,739 3/4/1994 4.5 92 520 27.5 0.0030492031124 3.31435E-05 1,802 9/2211995 4.5 96 616 26 0.0032980123888 3.43543E-05 1,868 4/11/1997 4.5 84 700 24.42 0.0029969115580 3.56775E-05 1,940 2/5/1999 4.5 92 792 22.6 0.0034283824632 3.7265E-05 2,027 9/15/2000 4.5 92 884 21 0.0035621371334 3.87189E-05 2,106 3/15/2002 4.5 76 960 19.5 0.0030501343509 0.03213 4.01333E-05 2,183 9/15/2003 4.5 92 1052 18 0.0038271537674 4.15995E-05 2,263 3/15/2005 4.5 92 1144 16.5 0.0039669721971 0.00779 4.31193E-05 2,345 9/15/2006 4.5 108 1252 15 0.0048270348389 4.46948E-05 2,626 3/15/2008 4.5 108 1360 13.5 0.0050035012051 4.63287E-05 2,722 9/15/2009 4.5 108 1468 12 0.0051868030633 4.80260E-05 2,821 3/15/2011 4.5 108 1576 10.5 0.0053783778692 4.97998E-05 2,925 9/15/2012 4.5 108 1684 9

0.0055833430659 5.16976E-05 3,037 3/15/2014 4.5 108 1792 7.5 0.0058217091435 5.39047E-05 3,167 9/15/2015 4.5 108 1900 6

0.0061738376927 5.71652E-05 3,358 3/15/2017 4.5 108 2008 4.5 0.0069647701761 6.44886E-05 3,788 9/15/2018 4.5 108 2116 3

0.0095167359157 8.81179E-05 5,176 3/15/2020 4.5 108 2224 1.5 0.0199019331311 0.07436 1.84277E-04 10,825 9/15/2021 4.5 217 2441 72 hrs 0.9250310510919 4.26282E-03 250,417 9/15/2021 4.5 217 2441 126.25 hrs 0.7287391203056 3.35824E-03 197,278 9/15/2021 4.5 217 2441 120 hrs 0.7449942057444 3.43315E-03 201,679 9/15/2021 4.5 217 2441 168 hrs 0.6453588210186 2.97400E-03 174,706 9/15/2021 4.5 217 2441 240 hrs 0.5603056751525 2.58205E-03 151,681

ECS96-003, ATTACHMENT 6 Page 3 of 5 24 24 3716 9115/2021 3716 9115/2021 4.5 4.5 217 217 2441 2441 360 hrs 0.4803017061314 720 hrs 0.3521718920632 2.21337E-03 1.62291 E-03 130,023 95,337 Background heat load due to 23 previous refueling loads 6,539,675 Btu/hr heat load = 0.03213*3457800*3413/217 + 0.00779*3458200*3413/217 + 0.07436*3735000*3413/217 Heat load due to full core offload Cycle 24 at time t=:

72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 360 hrs 720 hrs 54,340,480 Btu/hr 42,809,410 Btulhr 43,764,307 Btu/hr 37,911,277 Btulhr 32,914,873 Btulhr 28,215,080 Btulhr 20,688,159 Btu/hr

where, heat load = Non Dim Power Gen Factor *3735000*3413/217 Total Decay Heat Load at time t=:

72 hrs 126.25 hrs 120 hrs 168 hrs 240 hrs 360 hrs 720 hrs 60,880,155 Btulhr 49,349,086 Btulhr 50,303,982 Btulhr 44,450,952 Btu/hr 39,454,548 Btu/hr 34,754,756 Btulhr 27,227,835 Btu/hr

ECS96-003, ATTACHMENT 6 Page 4 of 5 Decay Heat Load for 3716 Uprate Starting with Cycle 14 Offload Partial Core Offload (Full Spent Fuel Pool, Full Cask Storage Pit)

(Maximum Storage Limit is 2104 assemblies)

Cycle Nom No.

Power (MWt)

EOC Date CYCLE Assemblies Cumulative Years Non Dim Power Sum of Power Power Heat Load per EFPY Discharged Fuel Pool Since Gen. Factor Gen Factors Fractions Assy BtuThr Discharge (# assys x P. F.)

Based on ASB 1

2 3

4 5

6 7

8 9

10 I1 12 13 14 15 16 17 18 19 20 21 22 23 24 25 25 25 25 25 3390 3390 3390 3390 3390 3390 3390 3390 3390 3390 3390 3441 3441 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 3716 11/26/1986 4/1/1988 9/23/1989 3/15/1991 9/20/1992 3/4/1994 9/22/1995 4/11/1997 2/5/1999 9/15/2000 3/15/2002 9/15/2003 3/15/2005 9/15/2006 3/15/2008 9115/2009 3/15/2011 9/15/2012 3/15/2014 9/15/2015 3/15/2017 9/15/2018 3/15/2020 9/15/2021 3/15/2023 3/15/2023 3/15/2023 3/15/2023 3/15/2023 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 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 92 108 108 108 108 108 108 108 108 108 108 108 108 108 108 108 108 92 176 260 344 428 520 616 700 792 884 960 1052 1144 1252 1360 1468 1576 1684 1792 1900 2008 2116 2224 2332 2440 2440 2440 2440 2440 36.3 0.0024704091606 35 0.0023268329256 33.5 0.0024118357211 32 0.0024999437999 30.5 0.0025912706026 29 0.0029417369252 27.5 0.0031817771608 25.92 0.0028912883322 24.1 0.0033075524487 22.5 0.0036922678984 21 0.0031615618079 19.5 0.0036922678984 18 0.0038271537674 16.5 0.0046568804053 15 0.0048270348389 13.5 0.0050035012051 12 0.0051868030633 10.5 0.0053783778692 9

0.0055833430659 7.5 0.0058217091435 6

0.0061738376927 4.5 0.0069647701761 3

0.0095167359157 1.5 0.0199019331311 72 hrs 0.4603841175941 99 hrs 0.4030879947696 106 hrs 0.3913413078857 120 hrs 0.3707805263613 168 hrs 0.3211924086175 9-2 2.68523E-05 1,460 2.77004E-05 1,506 2.87123E-05 1,562 2.97612E-05 1,619 3.08485E-05 1,678 3.19754E-05 1,739 3.31435E-05 1,802 3.44201 E-05 1.872 3.59517E-05 1,955 3.73543E-05 2,183 0.03148 3.87189E-05 2,262 4.01333E-05 2,183 0.00752 4.15995E-05 2,263 4.31193E-05 2,533 4.46948E-05 2,626 4.63287E-05 2,722 4.80260E-05 2,821 4.97998E-05 2,925 5.16976E-05 3,037 5.39047E-05 3,167 5.71652E-05 3,358 6.44886E-05 3,788 8.81179E-05 5,176 0.07901 1.84277E-04 10,825 4.26282E-03 250,417 3.73230E-03 219,252 3.62353E-03 212,862 3.43315E-03 201,679 2.97400E-03 174,706

ECS96-003, ATTACHMENT 6 Page 5 of 5 25 25 25 25 3716 3716 3716 3716 3/15/2023 3/15/2023 3/15/2023 3/15/2023 4.5 4.5 4.5 4.5 108 108 108 108 2440 2440 2440 2440 184 hrs 240 hrs 360 hrs 720 hrs 0.3094610294743 0.2788618106750 0.2390441671069 0.1752744900591 2.86538E-03 2.58205E-03 2.21337E-03 1.62291 E-03 168,325 151,681 130,023 95,337 Background heat load due to 24 previous refueling loads 6,762,518 Btu/hr heat load = 0.03148*3457800*3413/217 + 0.00752*3458200*3413/217 + 0.07901*3735000*34131217 Heat load due to full core offload Cycle 25 at time t=

where, heat load = Non Dim Power Gen Factor *3735000*34131217 Total Decay Heat Load at time t=

72hrs 99 hrs 106 hrs 120 hrs 168 hrs 184 hrs 240 hrs 360 hrs 720 hrs 72 hrs 99 hrs 106 hrs 120 hrs 168 hrs 184 hrs 240 hrs 360 hrs 720 hrs 27,045,032 Btu/hr 23,679,200 Btu/hr 22,989,147 Btulhr 21,781,314 Btu/hr 18,868,286 Btu/hr 18,179,131 Btu/hr 16,381,596 Btu/hr 14,042,528 Btulhr 10,296,411 Btu/hr 33,807,549 Btu/hr 30,441,718 Btu/hr 29,751,665 Btu/hr 28,543,832 Btu/hr 25,630,803 Btu/hr 24,941,649 Btu/hr 23,144,114 Btu/hr 20,805,046 Btu/hr 17,058,929 Btu/hr

'~'Entemoyx Technical Review Comments Document Rev.

SubjectrTtle:

Number EC-S96-003 (DRN 04-1679) 0-1 Spent Fuel Pool Heat Loads for 1088 Spent Fuel Assemblies Document.Type:

Special Notes or Instructions:

Enercon Calculation Comment Section!

Response/Resoution Number Page No.

l

_No comments Reviewed By:

Resolved By:

(Name/Date)

David Viener 10/14/04 (Name/Date)

Department:

Phone:

Accepted By:

W3 - Design Engineering 504-739-6686 (Name/Date)

//Ig

/

I I

Page Iof

TECHNICAL REVIEW COMMENTS FROM DRN 03-1440 (5 PAGES INCLUDED FOR REFERENCE)

Technical Review Comments:

ECS96-003 DRN 03-__. SFP Heat Loads Entergy Technical Review Comments Document Calculation No.

Rev. I SubJectitle: I Spent Fuel Pool Heat Load Number EC596M003 DNO03-7 0

Document Type:

Calculation Special Notes or Instructions.

Comment Sectiont Technical Comments Response/Resolutlon Number Page No.

I tile Calculallon no longer applies tD 1088 Spent Fuel Assemblies.

Conc=. Wichane tidt to remove '1088 Spent Fue AsehbLes lherefore,revise title to de original title of 'Spent uelPool and subste faFull SpentPFelPool and SF Ck Stongc HeatLoads" Arca.

igenrl Why is this calulation needed7 bis culation was appmildy developed to provide lmiting heat What is the fnteraction of this calculation with the HOLTEC loads for the UtiJte Heat Sink Study and for Wet Cooling Tower calculations ECg98-2 and ECM98-067?

Losses During a

LOCA calculatios The Initial issue looked at a fuil storage pool wiO loss spent assemblies. T revision updates de calculation to provide et lods at 3,5,7, 10, 15 and 30 days afe shutdown for a fdl SEP ard for the SFP/WSFP Cask Storage Area. TheROLTEC cluain EC-M9022 give simil. data bt based onroe contervative aumptio of bac.ground deay best loads. The ident of EMM9822 was to show that the cooling system could h l &xmil loads beyond tfe phys stoage capacity of the SFP and SFP Cask Are The stated innt ofECfM98-067 wras to dctermine the mod limiting condition forremoving SFP hbat loads ssuming a dient single failure than the or adopted inEC-M9S-022. Calculation EC-M9S-022 assame the loss of dte most effient FP cooling pump as Its sglte fai EC-M98067 Isnns loss ofan elecrical bus tat Da only taks out aFP cooling pumpbut also reduces CCW flow to he SFP HX to 2768 gm from th 5000 zpmnssmed in EC-M8-2 With the reduction ir CCW flow, the hest load in the SFP must be kept below 29cl0' Btu'ir to prevent from exceeding the pool bulk tenperature limit of 140 F.

3 6.0 What is end use of this calculation? Time to boll would be The hat loads reported in this calcuatiton are used in support of reduced if computed at the conditoins of higher deay heat the Uitimate Hest Sink Study MN(Q) 9-3 and Wet Cooling Tower associated with shorter times after shutdown thum 15 dcay.

Losses During a WCA MN(Q) 9-9. The dme to boil calculation is notreally used since the FSA w cady refaence a timc to boil value from EC-M98-022. T value is based on a loss of ftreed cooling when the SFP temperatura peash e a partial core offload For a partial core ofiload 7 days ate reactor shutdow, HOLTEC predicts that toe pool temperate pes at 132.6' F when eooling is lost It then tas 6.8 hn for the pool temperature to reack212F. As part of the 3716 MWtuprt evaluaion this ecsg=3-j)s. W15=3.12:39 PM PWO 1

Technical Review Comments:

ECS96-003 DRN 03-.__,

SFP Heat Loads l

loss of cooling system transient bah be recalculated using dcay ht loads for the 3716 MWtpte. Te bnew calculationdraft Appendix M to EGM9S-022, predicts a Starting tMperaM of 125.7'P and a time period of 8.65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months for Ihe pool to et up to fte boiling Point

4.

B I tn I

4%

O.U Note that since fuel offload is not allowed per1 until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and with a 4 assembly per hour assumed offload rate, full core discharge at 3 days afltr shutdown Is not considered credible.

Similarly, 108 assemblies will not be discharged at 3 days after shutdown.

How does consideration of these constraints impact this calculation or downstreanm calculations?

The decay heat Loads reported at3 days after reactor shutdown for a partial core oioad and for a full core ofioad establs thermal Ihit for refueling offloadi°g rates. In de case of the partial core offload of lO assemblies, all 10 assemblies could theoretically be offlosded wivtrAt violating the design basis hest duty of 33.73xlO Btuhr ontihe SFP EDC Cosequently Waterford-3 could sdrt refueing 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months alier shutdown and offload at rates in excess of 4 assemblies per hour witdut exceeding the heat duty design bsis of the SPP I The additional decayheatresultng flmmoffmoadingsrvetha4asembles perour wd be raded offagiteigerbackg und decaybeat term umned inthe HOLTEC analysis - 9.93xl10 Btin/r versus the 3716 uprate value of 634xl0 Btn/br. At 7 hor afterhudown a assembly from the 3716 MWt core will be generating approximately 249,00OBtanhrofdecayheat Fortie full cor or oad, the calculted decay eat load of 6Q.47xlO Btuhr eeeds the 5OAxldesign bsis heat dutyofthehat eMxchnr. TIis indicate tat anofiloa g rate inmit exists. Based on the results in Appendix Lto EC-M98-022, the limting rate cxceeds tbe cur limit of 4 assemblies per bour but vwat the actual limit is tas not been evalnated as nut of ffi aIasIs I

5 AMt What is logk for the times aftershutdown considered in this calculation7 Specifically, document the reason why 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months and 126.25 hours2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months are consdered.

The 108 hour0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months time in r

t e time when fte SFP reached its peak bulk temprature for the partial core offload in EC-M9022. The design basis hWat load for the SF' EX was tAzn atthe 108 hour0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months incremeni All fuel assembly discarge was completed at the 101 ourincrement Due to tie themlalag in the SFP bulk temperature the peak bulk tempmature didn't occur until 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months later. The original guildeines for the 3716 uprate called for a partial discharge of 116 assemblies so dhe transfer would agan be completed at 101 hours0.00117 days 0.0281 hours 1.669974e-4 weeks 3.84305e-5 months and the peak temperatue would presumably occur at 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months . Now tat the partial offload is a mxlnmmof 108 assEmbl1es, transfer will be completed at 99 hours0.00115 days 0.0275 hours 1.636905e-4 weeks 3.76695e-5 months after shutdown and peak temperatres could occur at 106 hours0.00123 days 0.0294 hours 1.752645e-4 weeks 4.0333e-5 months after shutdown. Since tho 3 day het load doesn't exceed te design basis heat duty of the SFP beat exchger it really doesn't matter wheter th 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 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months . For the full coe offload ithas alrady been stated that ecegGOO3ps, Wt&Oa3. 1+/-39 PM Page 2 0=96M-ps. 91M=. 12:x PM PA;P 2

Technical Review Comments:

ECS96"003 DRN 03-

, SFP Heat Loads fth 3 day vlu exceeds the heat ty limit of te heat cxcbanM.

The 126.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months titn inciemeatrepresents te completion of te fill com diLbrge ard tn represent tie inaxum heat load an ft SFP ML The power fradion Excel spradsheet in Attchment 3 can be used to calclte a power fmctou and subsequent decy blu load at any time irementrot carently repoted in fs calculatio Reviewed By-.

Paul Sicard

) n Resolved By Donald Haun/mum (Name/Date) 19 August 2003 0-)

?

(Name/Date) 18Septembe;2003 19 /i$/3 Department:

Phoaet:

(504)

Accepted By.

Z 1

._Enterg__

/ Safety An a

l y

9_648 NameDate eC03_ps. 9115*00. 1239 PM Psne 3

~Enterie Technical Review Comments Document

_ReV.

SubJeclftle:

umnber EC-S96W G0-1 Spent Fuel Pool Heat Loads for 1088 Spent Fuel Assemblies Document Type:

Spedal Notes or Instrutlons Enercon Calculation Comment Section/

Comment ResponseResoluton Number Page No.

I Cale Cover lmove 1088 SpentFoel assemblies from Title?

Cmcur, will change te to remsve 1088 Spent Fuel assemblies pap and substitute -aFuU Spent Fuel Pool and SFP Cask Stoame Arcae 2

Revision Ildicate that this is a complete rite of tha Calculation id Agree will indicate, this is a complete rezite of calculation and tht Page thatno revisionbars will be used Also indicate that no revisonbars areused. Original Atchments and I hsvebeen Attacments I and l Ive been replaced with decay hebs load replaced by Atachmen1-5. Deay est loads are calculated calculations using ASB 9-2 methodology uig ASB 9-2 methodology.

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

Cancur. Calculation revised to show offloads for Cycles 1 through Cycles 12 and 13 are expected oflicads.

11 based on historical data. Nurbr of assemblies in ofloads 12 &

13 ae expected quantities based on contacts with Westinghouse Wfindsor.

4 2.0 Why is EC-M98-067 used as a refence?

Caculam EC-M98067 was originallyrefatncedbemuse th power fraction values used in tie draft version of this calculation were taken from Attachment 8.11 OfEC-M9067. Subsequently an enor in applying th Kiunertainty in ASB 9-2 was discovered rendering the power fiions in C-M98-067 overly conservative.

EC-M98-067 is being deletedi recalculates power fractions with updated firmilas fiom ABE 9-2.

5 4.0 Add a core power of3390 for cycles I -11 in the bulleted Concur. Corpowe of339oMWthasbeenincludedinbulleted section.

section on biput Citeria and Asmptions.

6 6.0 Ihe value of 38,602 f3 is not a direct value from ECM98-022.

The volume value was obtained from page B-2 Appaeni d to EC-Derive how this volume was deterinded.

M 9 The volume is calculated to obin a thermal inertia vaue for the SPF and cask stbrap ar.

The ezxression for lie volmne is

[0.547

19,665.8 + 27,844.8]. When this expression is reduced it gives avolunme value of 38,601.99 ft.

7 At. I Insert a forrala that was used to calculate the offload heat load

'Will icorpora equation or heat load of ofllosd, but spreadsheet is (i.e. similar to the background heat oad farmula given above) not really an attachment to this calculation but apart of the man body. There a two atchment The first gives the update equations for ASB 9-2 and the values used in various uprate calculations. The second attachmet gives values for RF-005-001

..5 Page l d2

8 At 1 What is the relvamnce of the 126125 hours?

Ts represents ffie time afrr shutdown when all 217 core usemblcs have been offload for te ffi l cre offlond assuming discharge is initiated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months afir shutdown snd 4 assemblies are

_ trsfased evmy hour.

Reviewed By.

Resolved By.

I

)LD v

_A ?r/

8A' (NamelDate)

David Viener 8129103 (Name/Date) ionald Hjun 9112103 Department Phone:

Accepted By.

W3-Design Engineering 1504 739-686 (Name/Date) 4/fV 01f/le Page 2 of 2

v t e Letter Sequence Supplement
TAC:MC1355, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting Questions 10 February 2004 28 January 2004 16 March 2004 24 March 2004 31 March 2004 8 April 2004 20 April 2004 26 March 2004 4 May 2004 21 June 2004 30 January 2004 18 February 2004 23 February 2004 2 March 2004 29 September 2004 29 October 2004 26 October 2004 Answers Results Approval, Approval, Approval, Approval Other: ML040300802, ML040631055, ML042520157, ML042670485, ML050870511, ML051090111, ML052290107, ML052800176, W3F1-2004-0076, To Amendment Request NPF-38-256, Alternate Source Term, W3F1-2004-0085, Schedule Clarification for Amendment Request NPF-38-249, Extended Power Uprate, W3F1-2004-0095, To Amendment Request NPF-38-256 Alternate Source Term, W3F1-2004-0101, To Amendment Request NPF-38-256, Alternate Source Term, Waterford Steam Electric Station, Unit 3
MONTHYEAR2004-03-04 [Table View]

W3F1-2004-0117, Supplement to Amendment Request NPF-38-249 Extended Power Uprate

Text

SUBJECT:

REFERENCES:

Dear Sir or Madam:

Title:

Title:

REFERENCES:

Title:

Title:

1.0 Purpose

References:

3.0 Method

6.0 Calculations

Navigation menu

W3F1-2004-0117, Supplement to Amendment Request NPF-38-249 Extended Power Uprate

Text

SUBJECT:

REFERENCES:

Dear Sir or Madam:

Title:

Title:

REFERENCES:

Title:

Title:

1.0 Purpose

References:

3.0 Method

6.0 Calculations

Navigation menu

Search