Text

Enclosure 2, Browns Ferry, Units 1, 2 & 3 - Calculation MDQ099920060011, Revision 1, Transient Npsh/Containment Pressure Evaluation of RHR and Core Spray Pumps.
	ML062510382
Person / Time
Site:	Browns Ferry
Issue date:	08/21/2006
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	TAC MC3743, TAC MC3744, TAC MC3812 MDQ099920060011, Rev 1
	Download: ML062510382 (56)
	v • d • e

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 TECHNICAL SPECIFICATIONS (TS) CHANGES TS-431 AND TS-418 -

EXTENDED POWER UPRATE (EPU) - REPLACEMENT DOCUMENTATION (TAC NOS. MC3812, MC3743, AND MC3744)

CALCULATION MDQ099920060011, REVISION 1, "TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS" This enclosure provides TVA Calculation MDQ099920060011, Rev. 1, "Transient NPSH/Containment Pressure Evaluation of RHR and Core Spray Pumps."

The revised calculation utilizes the revised Appendix R results from TVA Calculation MDQ0999970046, Rev. 10 (Enclosure 1).

Additionally, this calculation revision corrects an anomaly which existed at the two hour time point in the Appendix R wetwell pressure response and provides improved modeling of the values for required NPSH as a function of time (step function changed to continuous function) for the Appendix R event. The revised Appendix R results are shown in Figures 7.14 and 7.15.

TVAN CALCULATION COVERSHEETICCRIS UPDATE Page 1 REV 0 EDMS/RIMS NO. EDMS TPE i EDMS ACCESSION NO WA foraREV. 0) calculations(nuclear) NA R14 *- oO8 07106 Catc Tile:

TRANSIENT NPSHICONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS iAL I UE PLA BRANCH NUMBE CUR R CURRENT ON NUC BFN MED MDQ099920060011 0 APPLICABILITY NEW CN NUC Entire 0I

-...-...,- Selected pages 03 No cCRIS Changes 0L ACTION NEW DELETE Q SUPERSEDE 0 OCRIS UPDATE ONLY [0 (For calc revision, CORIS REVISION RENAM 0 DUPUCATE 0 (Verifier Approval Signatures Not been reviewed and no E Required) CCRIS changes required)

UNITS 001 002003 N

SYSNEMS 1064 074 075 APPUCABLE DESIGN DOCUMENT(S) 7 CLASSIFICATION tAI E gUAIT SUl HNVR.IFE SPECIAL REQUIREMENTS, DESIGN OUTPUT I SAtT and/or ISFSI RCLAED2 ELATED (ifyes, ASUP IO ANIRLMTN O AflA"IENT I SARtQoQAFECED~ER Ye 0NR. a yes) Yes 19No [I YesO0NoO 1 Yesfl3 No PREPARER ID PREPARER PHONE NO PREPARING ORG (BRANCH) VflER~IFICAIN NEW MEHOD OF ANALYSIS William A. Eberly 423-751-8222 MNE 13 Yes I _ III DesignReview [] No PREPARER SIGNATURE - DATE CHECKER SIGNAPJUiE /- DATE VERFIER SIGNATURE DIo SIGTU ATE "PROBLEWABSTRACT The purpose of this calculation is to determine the Net Positive Suction Head (NPSH) available to the Core Spray (CS) and Residual Heat Removal (RHR) pumps as a function of time after postulated accident and operational transient events in accordance with Regulatory Guide (RG) 1.82. The available NPSH Is compared to the required NPSH for the respective pumps to demonstrate that adequate margins exist to ensure that the RHR and CS pumps perform their intended design safety functions. The containment pressure necessary to preclude pump cavitation is also determined. This calculation provides graphical representations of the sequences to support responses to Round 6 Requests for Additional Information (RAI) In support of BFN Units 1, 2 and 3 Extended Power Uprate (EPU) license amendment requests (TS-418 and TS-431).

The results presented In Table 6.2-1 on page 21 show that adequate NPSH margins exist for each event scenario analyzed. The minimum margins, maximum required containment (wetwell) overpressure, and the duration for required overpressure credit are presented in this table.

Acceptable results for the Appendix R event are based on assumed operator action at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to Isolate all drywell coolers (see UNVERIFIED ASSUMPTION, Appendix R Assumption 6 on page 18).

MICROFICHEEFICHE Yes'b NO E FICHE NUMBER(S) o LOAD INTO EDMS AND DESTROY 0 LOAD INTO EDMS AND RETURN CALCULATION TO CALCULATION UBRARY. ADDRESS: SAB 1A-BFN LOAD INTO EDMS AND RETURN CALCULATION TO:

TVA 40632 107-20051 Page I df2 NEDP-2-1 [07-W20051

"VAN CALCULATION COVERSHEETICCRIS UPDATE p'age 2 CALC ID TYPE ORG PLANT BRANCH NUMBER I REV I ICN NUC BFN MEB MD0099920060011I II I

ALTERNATE CALCULATION IDENTIFICATION BLDG ROOM ELEV COORD/AZIM FIRM Print Report Yes 0 01 TVA CATEGORIES NA KEY NOUNS (A-add, D-delete)

ACTION KEY NOUN AID KEY NOUN A PUMP A RHR A POOL A CS A ATWS A NPSH A DBA A SBO A LOCA A APPENDIX R CROSS-REFERENCES (A-add, C-change, D-delete)

ACTION XREF XREF XREF XREF XREF XREF (A/C/D) CODE TYPE PLANT BRANCH NUMBER REV A P CN BFN MEB MDQ0999970046 RIO A P CN BFN MEB MDQ0023980143 R2 A P CN BFN MEB MDQ0064920353 R1 A P VD BFN MEB VTD-P160-0030 R6 A S CN BFN NTB NDQ0999920116 R20 A P VD BFN MEB GE-ER1-AEP-06-334 (W79-060803-001)

A P VD BFN MEB VPF2647-10-1 A P VD BFN NTB C1320503-6924 R2 A P VD BFN MEB GE-ER1-AEP-06-340 (W79-060811-002)

CCRIS ONLY UPDATES:

Following are required only when making keyword/cross reference CCRIS u ates and page 1 of form NEDP-2-1 Is not included:

PREPARER SIGNATURE DATE CHECKER SIGNATURE DATE PREPARER PHONE NO. EDMS ACCESSION NO.

TVA 40532 [07-20061 Page 2 of 2 NEDP-2-1 [07-08-2005]

Paae 3 TVAN CALCULATION RECORD OF REVISION I

CALCULATION IDENTIFIER MDQO09920060011 Title TRANSIENT NPSHICONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Revision DESCRIPTION OF REVISION No.

0 Initial Issue Total Number of Pages = 54 (including attachments)

The SAR and ISFSI SAR have been reviewed by J.D. Wolcott and this revision of the calculation does not affect SAR sections 6.1. 6.2. 6.3. 6.4. 6.5. 14.5 and 14.6 and does not affect any ISFSI SAR sections.

Tech Specs and ISFSI CoC have been reviewed and determined not to be affected.

The calculation reflects parameters/values associated with the Implementation of Extended Power Uprate (EPU) as well as the use of containment over-pressure credit where needed for calculating NPSH margins.

I This revision is a complete replacement for the previous revision and incorporates the additional Appendix R case with RHR pump flow rate of 9000 gpm consistent with Revision 10 of predecessor calculation MDQ0999970046. This revision also incorporates revised Appendix R containment response data by GE which corrects a minor error in the wetwell pressure transient at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months due to an error Inthe initial condition specified for the wetwell heat sinks at the start of the second phase of the analysis with coolers off at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Total Number of Pages = 55 (including attachments)

The SAR and ISFSI SAR have been reviewed by and this revision of the calculation does not aff A sections 61 6.2 6.3, 6.4 6.5. 14.5 and 14.6 and does not affect any ISFSI SAR sections.

Tech Specs and ISFSI CoC have been reviewed and determined not to be affected.

The calculation reflects parameters/values associated with the implementation of Extended Power Uprate (EPU) as well as the use of containment over-pressure credit where needed for calculating NPSH margins.

Page 1 of 1 NEDP-2-2 [12-04.2000]

I TVA [12-2000]

40709 [12-2000]

TVA 40709 Page I1of 1 NEDP-2-2 [12-04-2000]

Page 4 TVAN CALCULATION TABLE OF CONTENTS Calculation Identifier: MDQ099920060011 I Revision: i TABLE OF CONTENTS SECTION TITLE PAGE Coversheet ........................................................................................................ 1 TVAN Calculation CCRIS Update ................................................................. 2 Revision Log ..................................................................................................... 3 Table of Contents ............................................................................................ 4 Design Verification (Independent Review) ..................................................... 5 Computer Input File Storage Information Sheet ............................................. 6 1.0 Purpose ............................................................................................................ 7 2.0 References ........................................................................................................ 7 3.0 Design input data ............................................................................................ 8 4.0 Assumptions ................................................................................................... 9 5.0 Requirements/Limiting Conditions ................................................................. 9 6.0 Computations and Analysis ............................................................................. 10 7.0 Supporting Graphics ........................................................................................ 22 8.0 Summary of Results ........................................................................................ . 34 9.0 Conclusions ...................................................................................................... 34 Appendices A RHR Heat Exchanger K-Factor Evaluation ................................................... (4 pages)

B Recirculation Pump M otor Heat Load .......................................................... (4 pages)

C Excel Spreadsheet Calculations ..................................................................... (3 pages)

Attachments I Sulzer Pumps Required NPSH Charts ............................................................ (3 pages) 2 Drywell Cooler Data ....................................................................................... (7 pages)

Total Pages 55 TVA 40710 [12-2000] Page 1 of I NEDP-2-3 [12-04-2000]

Page 5 TVAN CALCULATION VERIFICATION FORM Calculation Identifier Revision I MDQ099920060011 Method of verification used:

1. Design Review

2. Alternate Calculation El Verifier Julie Jarvis/Bechtel Date

3. Qualification Test __

Comments:

This calculation was verified using the design review method to verify that the methodology, design inputs, assumptions, computations, and results of this analysis are technically accurate, adequate, complete and in accordance with Regulatory Guide 1.82.

The design review was performed in accordance with NEDP-5, Document Design Review.

The Excel spreadsheets were reviewed to confirm that the plotted results and calculated NPSH/containment pressure margins for the different accident and operational transient events are reasonable compared to the inputs. The calculation provides adequate explanations and justifications. Therefore, the reviewer finds this calculation to be acceptable for its intended safety related purpose NEDP-2-4 [07-09-2001]

Page 1 of 1 40533 [07-2001]

TVA WA [07-20011 Page I of I NEDP-2-4 [07-M20011

Page 6 TVAN COMPUTER INPUT FILE STORAGE INFORMATION SHEET Document MDQ099920060011 Rev. I Plant: BFN

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS El Electronic storage of the input files for this calculation is not required. Comments:

[ Input files for this calculation have been stored electronically and sufficient identifying information is provided below for each input file. (Any retrieved file requires re-verification of its contents before use.)

i - Prpertis icrosft Iterne Exporer rovied byT.. il rpris-Mcosf nentEpoe po ide yT.. F Genieral PceRbeWS ISeciiy I Folder Fied InlIPNbisWed General PIoj~ei3 I SecmriJ Folders Filed In Publshed FILEKEEPER PUBUCNUCLFEAR iv R1LEKEEPER PUBUC.NUC1EAR Documqen rotles Ivowe Document Properties IVakieI Plant F Pat1 BFN Dmcnerd Meritifier 3M Docwsert kdentiier 13DB639 Domimert Type IFIL Document Type IFLE hbated Date Inbated Date l2DO60804 Key ees DOCVT EMBEDDED SPREADSHET 0 Key leas EXCEL SPRlEADSHEET FILES9 EqA rt Name WR8 CS .M' Eq.*oent Nae IRHR &CS KIMPS vernnIVakie Prpertes VersionProperties IJ Valae Fle Name ICOWTAN~BT OVBEFtRESSUREJ1 z Fie Nam ICONTAMENT OVERPRESIJRE4zi i

Dcanrt Date Document Dae __________________

'S1i(yWM=d)

Resp Org RespOg JEFN E8TS

( K )I He*

L 0 Microfiche/eFiche TVA 40535 [12-20001 Page 1 of 1 NEDP-2-6 [12-04-20001

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 7

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS

1.0 Purpose

The purpose of this calculation is to determine the Net Positive Suction Head (NPSH) available to the Core Spray (CS) and Residual Heat Removal (RHR) pumps as a function of time after postulated accident and operational transient events in accordance with Regulatory Guide (RG) 1.82. The calculation specifically addresses the recirculation pump suction DBA-LOCA, Station Blackout (SBO), Appendix R (APP R), and Anticipated Transient Without Scram (ATWS) events.

The available NPSH is compared to the required NPSH for the respective pumps to demonstrate that adequate margins exist to ensure that the RHR and CS pumps perform their intended design safety functions. The containment pressure necessary to preclude pump cavitation is also determined. This calculation evaluates maximum pump flow rates, operation of drywell coolers, and containment sprays with minimum or maximum cooling water temperature and provides graphical representations of the sequences to support responses to Round 6 Requests for Additional Information (RAI) relative to BFN Units 1, 2 and 3 Extended Power Uprate (EPU) license amendment requests (TS-418 and TS-431).

2.0

References:

2.1 TVA Calculation MDQ0999970046, Revision 10 2.2 GE-ERI-AEP-06-334, GE Responses to NRC Request for Additional Information - ACVB-37 and Draft TVA Letter, W79-060803-001 2.3 Sulzer Pumps (US) Inc. Document No: E12.5.1267 Rev 0, NPSH Transient Review RHR and Core Spray Pumps, 7/11/2006 2.4 TVA Calculation MDQ0023980143, Revision 2 (for RHR HX K-factor method) 2.5 TVA Vendor Datasheet for Aerofin Drywell Coolers, VPF2647-10-1 (see Attachment 2) 2.6 PROTOHX Version 4.00 QA software for heat exchanger performance analysis 2.7 Browns Ferry Nuclear Plant (BFN) - Units 2 And 3 - Proposed Technical Specifications (TS)

Change TS - 418 - Request For License Amendment Extended Power Uprate (EPU) Operation 2.8 Browns Ferry Nuclear Plant (BFN) - Unit I- Proposed Technical Specifications (TS) Change TS - 431 - Request For License Amendment - Extended Power Uprate (EPU) Operation ***

2.9 NRC Requests for Additional Information for EPU - RAI 6, June 26, 2006 Unit 1 and Units 2 and 3 letters from Eva A. Brown to Karl W. Singer ***

2.10 Heat Exchanger Specification Sheet, Perfex Corporation, vendor manual VTM-P 160-0010 (VTD-P 160-0030, R6) 2.11 TVA Calculation MDQ0064920353, Revision 1 2.12 C1320503-6924, Revision 2, BFN EPU Containment Overpressure (COP) Credit Risk Assessment 2.13 TVA Calculation NDQ0999920116, Revision 20, Appendix R Manual Action Requirements

- - Information Only reference, not specifically cited in calculation for design input

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 -FPage: 8

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 2.14 EPU FTR T0400 RI, Containment System Response 2.15 Browns Ferry EOI-1, RPV Control, R 1I (Unit 2), R8 (Unit 3) 2.16 Browns Ferry EOI-2, Primary Containment Control, R9 (Unit 2), R7 (Unit 3) 2.17 EPU FTR T06 11 RO, Appendix R Fire Protection 2.18 EPU FTR T0903 RO, Station Blackout 2.19 GE-ER1-AEP-06-340, W79-060811-002 3.0 Design Input Data:

3.1 Pump Flow Rates - Maximum flow rates Iler num. are determined from Ref 2.1 as follows:

Short Term post DBA-LOCA RHR pump flow rate to the broken recirc loop = 11,500 gpm RHR pump flow rate to the intact recirc loop = 10,500 gpm CS pump flow rate = 4125 gpm Long Term post DBA-LOCA RHR pump flow rate = 6500 gpm CS pump flow rate = 3125 gpm Station Blackout (SBO) RHR pump flow rate = 6500 gpm Appendix R (APP R) RHR pump flow rate = 9000 gpm Anticipated Transient Without Scram (ATWS) RHR pump flow rate = 6500 gpm 3.2 Pump suction hydraulic losses and available NPSH without overpressure are determined for specified state point conditions from Tables 6, 10, and 13 of Ref. 2.1 3.3 Containment transient response parameters (suppression pool temperature, wetwell pressure, etc.) are obtained from Ref 2.2 and Ref 2.14 3.4 RHR and CS pump required NPSH as functions of flow rate and operating duration are obtained from the charts on pages 8 & 9 of Ref 2.3.

3.5 Initial suppression pool volume of 122,940 ft3 (TS Minimum with Drywell-to-Wetwell operating pressure differential) from MDQ0064920353, Rev. 1 (Ref. 2.11) 3.6 RHRSW maximum temperature of 92'F based upon highest recorded temperature during study for C1320503-6924, Rev. 2 (Ref 2.12) 3.7 RHR heat exchanger K value of 227 BTU/sec-°F per RHR heat exchanger based upon RHRSW temperature of 92°F (see Appendix A) 3.8 For other inputs used in the GE containment analyses, see Ref. 2.2

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 9

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS

4.0 Assumptions

4.1 For events involving containment spray cooling, the minimum service water temperature is assumed to be 32F. Technical Justification: This limiting temperature condition conservatively maximizes the depressurization of the containment following containment spray cooling initiation.

4.2 For events involving containment spray cooling (LOCA and SBO), the static head in the suppression pool is reduced by the equivalent amount of water that would be required to flood the drywell floor holdup volume to the elevation of the downcomer pipe invert. Technical Justification: The drywell holdup volume will accumulate spillage from the break in the event of a LOCA and containment spray water following spray initiation after a LOCA or SBO. It is conservative for the NPSH computations to assume that this inventory is deducted from the initial pool inventory at the onset of the event scenario.

4.3 It is assumed that no makeup is provided from the condensate storage tank (CST). Technical Justification: Although the HPCIIRCIC systems would initially take suction from the CST to maintain reactor water level, compensating for coolant volume shrinkage during cooldown, this inventory of relatively cool water would reduce the pool temperature response and increase the pool level and pump suction static head. It is conservative to neglect this makeup source.

4.4 UNVERIFIED ASSUMPTION - see Section 6.2.3, Appendix R, Assumption 6.

5.0 Requirements/Limiting Conditions:

There are no operational requirements / limiting conditions for operation established by this analysis.

The action sequences and timing are consistent with the current Emergency Operating Instructions and Technical Specifications relative to reactor and containment control and initiation of suppression pool cooling and containment sprays.

Calculation No. MDQ099920060011 Rev: 1 I Plant: BFN Unit 0 Page: 10

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 6.0 Computations and Analyses:

6.1 Methodology The NPSH available is determined from the following standard equation for pumps with flooded suctions:

NPSHa = Hstatic + 144/p(Pww - Pvapor) - Hf Where: Hstatic = water static head from the pool surface to the pump impeller centerline, ft Pww = the containment wetwell pressure, psia Pvapor = the water saturation pressure at the respective pool temperature, 3

psia p = the density of the water at the respective pool temperature, Ibm/ft Hf = the suction piping and strainer frictional head loss at the respective flow rate, fR The available NPSH without credit for containment pressure is determined in Ref. 2.1 at specified pool temperature conditions (initial pump start, maximum pool temperature, and end of required overpressure credit period) and flow rates for each event. The TVA MultiFlow hydraulic flow balance software is employed in Ref. 2.1 to determine the suction head loss, Hf including the strainer head loss reflecting the appropriate debris loading for cases subject to post-accident debris generation (LOCA).

GE determined the containment response for each event using the Browns Ferry SHEX model (Ref 2.2) which provides the containment pressure and temperature transient conditions. To maximize suppression pool temperature and minimize containment pressure the mechanistic, non-equilibrium model of the mass and energy exchange between the pool surface and the wetwell atmosphere is applied in the subject NPSH analyses.

Sulzer Pumps evaluated the Browns Ferry RHR and CS pumps and provided charts of the required pump NPSH as a function of the flow rate and operational period in Ref 2.3 (see Attachment 1). The values for required NPSH are obtained from these charts by interpolation when necessary. Required NPSH values are selected for operating periods which bound the specific transient characteristic. For example, the APP R event is analyzed with one RHR pump operating at 9000 gpm and the following required NPSH values are applied:

RJ-R Operating Flow Rate Time NPSHr gpm hours ft 9000 0-8 22.4-24.7 9000 8-12 24.7-25.6 9000 12-24 25.6-26.9 9000 24-100 26.9-34.6 For the APP R event, the NPSH requirement is incorporated as a continuous time variant function. For all other cases, the reqirement is applied as a step function for bounding operating periods.

Calculation No. MDQ09992006001 Rev: I Plant: BFN Unit 0 Page: 11

Subject:

I TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS These parameters are input into a Microsoft EXCEL spreadsheet to calculate the available NPSH versus time for each event scenario. The steady-state NPSHa value from Ref. 2.1 is adjusted in the spreadsheet by replacing the steady-state vapor pressure and wetwell pressure with the transient vapor pressure and wetwell pressure, Pww. Available NPSH declines with increasing temperature. Therefore, the steady-state hydraulic calculations performed for the peak suppression pool temperature conditions are the base values in this analysis. No adjustment is made to the frictional and static head terms for the minor increase in fluid specific gravity at lower temperature conditions. The resulting transient available NPSHa is then compared to the required NPSHr to determine the margin available. Finally, the minimum containment pressure necessary to preclude pump cavitation is determined.

6.2 Analysis This calculation analyzes the following event sequences to determine the NPSH available to the RHR and CS pumps as a function of time after the respective events:

Loss of Coolant Accident (LOCA) - Short Term

Loss of Coolant Accident (LOCA) - Long Term

Anticipated Transient Without Scram (ATWS)

Appendix R

Station Blackout (SBO)

For each scenario, input parameters for this calculation are chosen from appropriate containment pressure/temperature models, flow models, available NPSH values and vendor supplied required NPSH information.

The spreadsheets for each event are documented in Appendix C and are identified as follows:

EPU RAI 6 LOCA.xls

EPURAI_6_ATWS.xls

EPURAI_6_APPR.xls and EPURAI_6_APPRGE_Rl.xls

EPURAI_6_SBO.xls Pertinent parameters (i.e. suppression pool temperatures, containment pressures and subject pump required containment pressures) are plotted to provide graphic representations of the time history of these events. The graphs for each case are included in Section 7 of this calculation.

The event-specific boundary conditions and assumptions are described in the following sections.

- IM FCalculation No. MD0099920060011 I Rev: I I Plant: BFN Unit 0 IPage: 12 I

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 6.2.1 Loss of Coolant Accident (LOCA) - Short Term (ST)

The limiting design basis loss of coolant accident (LOCA), instantaneous double-ended rupture of one of the recirculation pump suction lines is postulated. The containment response is predicted with the SHEX code based on the following inputs and assumptions:

LOCA Containment Analysis Key Inputs Iem fParameter Value

1. Reactor Power 102% of EPU power 4031 MWt

2. Reactor Steam Dome Pressure 1055 psia

3. Decay Heat Decay heat used in the SHEX analysis is based on 102% of ANS 5.1-1979 decay heat with 2-sigma uncertainty adder

4. Initial Suppression Pool volume corresponding 121,500 ft3 to minimum suppression pool level

5. Initial Drywell Volume 159,000 ft3

6. Initial Wetwell Airspace Volume 129,300 ft3

7. Initial Drywell Pressure 15.5 psia

8. Initial Drywell Temperature 150°F

9. Initial Drywell Relative Humidity 100%

10. Initial Wetwell Pressure 14.4 psia

11. Initial Wetwell Temperature 95 0 F

12. Initial Suppression Pool Temperature 95 0F

13. Initial Wetwell Relative Humidity 100%

14. Ultimate Heat Sink/RHR Service Water 950 F Temperature

15. RHR Heat Exchanger (HX) K value (per loop) 223 Btu/sec-°F

16. Number of RHR Loops (1 RHR pump & 1 RHR 4 HX per RHR loop)

17. RHR Mode of Operation LPCI and Pool Cooling

18. Number of Drywell Coolers 0 (unavailable following LOOP)

19. Heat Loads Modeled Yes

20. Heat Sinks in Drywell, Wetwell and Yes Suppression Pool Modeled

21. Leakage from the primary containment 2%/day

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 13

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Pertinent Equipment Status:

" Two RHR Pumps at 11,500 gpm each (broken loop)

" Two RHR Pumps at 10,500 gpm each (intact loop)

" Four Core Spray Pumps at 4,125 gpm each

" No Containment Sprays in short term LOCA-ST Assumptions:

1. The suppression pool is assumed to be initially at minimum technical specification level.

Justification - This minimizes the static head contribution to the available NPSH.

2. The suppression pool is assumed to be initially at maximum technical specification temperature.

Justification - This maximizes the temperature transient which minimizes the available NPSH.

3. Maximum drywell relative humidity and temperature are assumed. Justification - This minimizes the initial mass of non-condensable nitrogen in the containment and thus minimizes the transient pressure response.

4. Pumps start automatically and operate with wide open discharge valves with no operator intervention. Justification - No operator actions are credited within the first ten minutes.

5. Pumps operate on their pump curves above their design flow rates (no throttling). Justification -

NPSH required increases and NPSH available decreases with flow rate so it is conservative to consider maximum flow rates.

6. Maximum suction strainer pressure drop is assumed, consistent with maximum debris loading.

Justification - Maximum pressure drop is conservative for prediction of minimum NPSH available.

The time-history graphs of NPSH, containment pressure, and suppression pool temperature are presented in Section 7.

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 14

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Loss of Coolant Accident (LOCA) - Long Term The LOCA-LT is the continuation of the LOCA-ST scenario from 10 minutes until suppression pool temperature is reduced and containment overpressure credit is no longer required for adequate NPSH.

The limiting long-term LOCA scenario assumes loss of offsite power and single active failure of one division of emergency AC power, providing one train of safety equipment for accident mitigation.

Pertinent Equipment Status:

" Two RHR Pumps at 6,500 gpm each

" Two Core Spray Pumps at 3125 gpm each

" Containment Spray cooling mode initiated at 10 minutes LOCA-LT Assumptions:

1. Pumps are assumed to operate at their design flow rates under operator control.

Justification- Emergency Operating Instruction (EOI) entry conditions for initiation of containment sprays are satisfied for this event and the operators will respond accordingly.

2. RHRSW is assumed to be supplied to the RHR heat exchangers at either 32°F or 95'F (two extremes are analyzed to determine the limiting case). Justification - Cold cooling water minimizes the containment spray temperature and produces the most rapid reduction in containment overpressure. Maximum cooling water temperature produces the maximum pool temperature response.

The time-history graphs of NPSH, containment pressure, and suppression pool temperature are presented in Section 7.

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 15

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 6.2.2 Anticipated Transient Without Scram (ATWS)

For Browns Ferry, the limiting ATWS events are the Main Steam Isolation Valve Closure (MSIVC) and Pressure Regulator Failure-Open (PRFO). The containment response for these events is very similar, therefore the MSIVC event is selected for the NPSH evaluation.

ATWS Containment Analysis Key Inputs

__Item .Parameter Value

1. Reactor Power 100% of EPU power 3952 MWt

2. Reactor Steam Dome Pressure 1050 psia

3. Decay Heat Decay heat prior to reactor depressurization used in the ODYN analysis is based on the May-Witt model.

Decay heat used in the SHEX analysis after reactor depressurization is initiated is based on nominal ANS 5.1-1979 decay heat (i.e., with no uncertainty adder).

4. Initial Suppression Pool volume corresponding 122,940 ft3 to minimum suppression pool level

5. Initial Drywell Volume 171,000 ft3

6. Initial Wetwell Airspace Volume 127,860 ft3

7. Initial Drywell Pressure 15.5 psia

8. Initial Drywell Temperature 150OF

9. Initial Drywell Relative Humidity 50%

10. Initial Wetwell Pressure 14.4 psia

11. Initial Wetwell Temperature 95 0 F

12. Initial Wetwell Relative Humidity 100%

13. Initial Suppression Pool Temperature 95 0 F

14. Ultimate Heat Sink/RHR Service Water 92 0 F Temperature

15. RHR Heat Exchanger (HX) K value (per loop) 227 Btu/sec-0 F

16. Number of RHR Loops (1 RHR pump & 1 RHR 4 HX per RHR loop)

17. RHR Mode of Operation Pool Cooling

18. Number of Drywell Coolers 10

19. Heat Loads Modeled Yes

20. Heat Sinks in Drywell, Wetwell and Yes Suppression Pool Modeled

21. Leakage from the primary containment 2%/day

I I.. I.s. - I LCalculation No.

Subject:

MDQ099920060011 Kev: 1 I lant: BWN unitu I rage: 16 -I TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Pertinent Equipment Status:

Four RHR Pumps at 6,500 gpm each in Suppression Pool Cooling Mode

" All ten drywell air coolers remain in service ATWS Assumptions:

1. Initial Drywell Relative Humidity is 50%. Justification - Drywell RH normally ranges from 20%

to 40% without coolant system leakage. The maximum value of 50% RH is selected to minimize the mass of non-condensable nitrogen in the drywell and thereby minimize the containment pressure response.

2. The operator initiates the Automatic Depressurization System (ADS) at the Heat Capacity Temperature Limit (HCTL) at approximately 20 minutes. Justification - The suppression pool temperature reaches the EOI-2 HCTL before reactor shutdown and RCS depressurization is required by.EOI-2 (SP/T-7).

3. Assume the operator uses the FW system to maintain water level after depressurization to replace HPCI when below HPCI isolation pressure. Justification - EOI-1 (RC/L-4)

4. Both RHR trains (2 RHR pumps and HXs per train) are aligned in pool cooling mode.

Justification - This is consistent with EOI-2 (SP/T-7)

5. The drywell coolers (and drywell heat loads) are modeled. It is assumed that all 10 drywell coolers are operating. Justification - Operating all 10 coolers minimizes containment pressure.

6. There is no leakage from the primary system to the drywell. Justification - This assumption minimizes drywell pressure.

The ATWS containment response analysis is conducted in two parts corresponding to the period from event initiation until reactor depressurization and the period subsequent to depressurization. The first phase of the transient is modeled with the Browns Ferry ODYN model which determines the reactor power response and MSRV flow which is input to the SHEX containment model to determine the initial suppression pool temperature increase to the HCTL (180F). At that point the RCS is depressurized and, the SHEX containment code with a shutdown power curve is utilized to determine the long term, post-depressurization response.

Time-history graphs of NPSH, containment pressure, and suppression pool temperature are presented in Section 7.

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 17

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 6.2.3 Appendix R (Fire Safe Shutdown)

The limiting APP R event for containment response, previously identified and analyzed in EPU Task Report 0611 (Ref. 2.17) as APP R Case I postulates the following:

S No spurious operation of plant equipment.

S Depressurization begins at 25 minutes using three main steam relief valves (MSRVs).

S One RHR pump aligned in the Low Pressure Coolant Injection (LPCI) mode, one RHR heat exchanger, and one RHR service water (RHRSW) pump is initiated at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months GE re-analyzed this event with their approved SHEX containment code utilizing the following inputs and assumptions:

hiiim P0aramete - Value

1. Reactor Power 100% of EPU power 3952 MWt

2. Reactor Steam Dome Pressure 1055 psia

3. Decay Heat Decay heat used in the SHEX analysis is based on nominal ANS 5.1-1979 decay heat (i.e., with no uncertainty adder).

4. Initial Suppression Pool volume corresponding 122,940 ft3 to minimum suppression pool level

5. Initial Drywell Volume 171,000 ft3

6. Initial Wetwell Airspace Volume 127,860 ft3

7. Initial Drywell Pressure 15.5 psia

8. Initial Drywell Temperature 150°F

9. Initial Drywell Relative Humidity 50%

10. Initial Wetwell Pressure 14.4 psia

11. Initial Wetwell Temperature 95 0 F

12. Initial Wetwell Relative Humidity 100%

13. Initial Suppression Pool Temperature 95°F

14. Ultimate Heat Sink/RHR Service Water 92 0 F Temperature

15. RHR Heat Exchanger (HX) K value (per loop) 227 Btu/sec-°F

16. Number of RHR Loops (1 RHR pump & 1 RHR 1 HX per RHR loop)

17. RHR Mode of Operation 9400 gpm in LPCI mode until RCS depressurization, then 6000 gpm in Alternate Shutdown Cooling mode

18. Number of Drywell Coolers 10 for first 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , then isolated

19. Heat Loads Modeled Yes

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 18

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS

20. Heat Sinks in Drywell, Wetwell and Yes Suppression Pool Modeled

21. Leakage from the primary containment 2%/day Pertinent Equipment Status:

One RHR Pump in ASDC mode at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

6,000 gpm assumed for minimum heat removal (Ref. Attachment 2)

9,000 gpm assumed for maximum required NPSH

Ten Drywell Coolers continue operation until isolated by operator action at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months APP R Assumptions:

1. Initial Drywell Relative Humidity is 50%. Justification - Drywell RH normally ranges from 20%

to 40% without coolant system leakage. The maximum value of 50% RH is selected to minimize the mass of non-condensable nitrogen in the drywell and thereby minimize the containment pressure response.

2. RHRSW Temperature of 92°F. Justification - Based upon highest recorded temperature during study for C1320503-6924, Rev. 2 (Ref. 2.12)

3. RHR heat exchanger K value of 227 BTU/sec-0 F per RHR heat exchanger. Justification - Based upon using RHRSW Temperature of 92*F (see Appendix A).

4. Use initial suppression pool volume of 122,940 ft (TS Minimum with Drywell-to-Wetwell operating pressure differential). Justification - MDQ0064920353, Rev. 1 (Ref. 2.11)

5. Pump is running on its pump curve above its design flow rate (no throttling). Justification -

NPSH required increases and NPSH available decreases with flow rate so it is conservative to consider maximum flow rates.

6. It is assumed that the unit operators isolate all drywell coolers at 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the start of the fire event based on the recognition that the reduction in drywell pressure by the coolers and the pool temperature increase due to the MSRV discharge are challenging the available NPSH to the RHR pump(s). Justification - This is an UNVERIFIED ASSUMPTION which will be resolved with the subsequent revision of the Appendix R Manual Actions Requirements calculation (Ref. 2.13) which is listed as a successor document to this calculation in CCRIS.

Time-history graphs of NPSH, containment pressure, and suppression pool temperature are presented in Section 7.

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 -FPage: 19

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 6.2.4 Station Blackout (SBO)

The Station Blackout event sequence defimed in EPU Task Report 0903 was re-analyzed by GE with the approved SHEX code methodology. Inputs and assumptions consistent with RG 1.82 to maximize pool temperature and minimize containment pressure were applied as follows:

" Unit trips when SBO occurs with automatic initiation of RCIC/HPCI systems to provide initial level control.

" Initial pressure control by automatic MSRVs operation.

" Operator action taken at one hour to control depressurization by cycling MSRVs while level control is maintained automatically by RCIC system.

" Coping duration is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Item Parameter

....... .Value

1. Reactor Power 100% of EPU power 3952 MWt

2. Reactor Steam Dome Pressure 1055 psia

3. Decay Heat Decay heat used in the SHEX analysis is based on nominal ANS 5.1-1979 decay heat (i.e., with no uncertainty adder).

4. Initial Suppression Pool volume corresponding 121,500 ft3 to minimum suppression pool level

5. Initial Drywell Volume 171,000 Wt 3

6. Initial Wetwell Airspace Volume 129,300 ft3

7. Initial Drywell Pressure 15.5 psia

8. Initial Drywell Temperature 150OF

9. Initial Drywell Relative Humidity 100%

10. Initial Wetwell Pressure 14.4 psia

11. Initial Wetwell Temperature 95 0 F Initial Wetwell Relative Humidity 100%

12. Initial Suppression Pool Temperature 95 0 F

13. Ultimate Heat Sink/RHR Service Water 95 0 F and 32 0 F Temperature

14. RHR Heat Exchanger (HX) K value (per loop) 223 Btu/sec-0 F

15. Number of RHR Loops (1 RHR pump & 1 RHR 2 HIX per RHR loop)

16. RHR Mode of Operation Containment Spray Cooling mode at 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

17. Number of Drywell Coolers 0, unavailable due to SBO

18. Heat Loads Modeled Yes

19. Heat Sinks in Drywell, Wetwell and Yes Suppression Pool Modeled

20. Leakage from the primary containment 2%/day

Calculation No. MDQ099920060011 I Rev: 1 I Plant: BFN Unit 0 I Page: 20

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Pertinent Equipment Status:

" Two RHR Pumps initiated in Containment Spray Mode at 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

" Containment heat removal is based on assumed 5850 gpm each pump (Ref 2.18)

" NPSH is evaluated assuming 6500 gpm each pump Assumptions:

1. Containment spray and suppression pool cooling at 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Justification - The analysis demonstrates that the E0I entry conditions for containment spray are met at the end of the coping period when power is restored.

Two SBO cases are analyzed to demonstrate the sensitivity of the available NPSH to the extremes of spray water temperature (i.e., RHRSW water temperature).

Time-history graphs of NPSH, containment pressure, and suppression pool temperature are presented in Section 7.

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 21

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Table 6.2

SUMMARY

OF NPSH AND CONTAINMENT PRESSURE MARGINS

SUMMARY

OF NPSH RESULTS MAXIMUM MINIMUM DURATION MINIMUM REQUIRED CONTAINMENT OF MINIMUM REQUIRED NPSH CONTAINMENT PRESSURE REQUIRED CASE PUMP FLOW NPSHA NPSH MARGIN PRESSURE MARGIN COP GPM FT FT FT PSIA PSI CS 4125 26.5 25.5 1.0 16.4 0.4 9 min.

LOCA-ST RHR-IL 10500 29.4 25.5 3.9 15.2 1.6 5 min.

RHR-BL 11500 26.4 28.4 -2.0 17.7 -0.9 10 min.

LOCA-LT CS 3125 35.1 24.5 10.6 12.6 4.5 0 SPRAYS, 32F RHRSW RHR 6500 38.5 23 15.6 9.8 6.6 0 LOCA-LT CS 3125 36.3 29 7.3 17.4 3.1 22.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months SPRAYS, 95F RHRSW RHR 6500 39.8 23 16.8 13.4 7.1 0 A'WS ALL DW COOLERS RHR 6500 24.3 21.5 2.8 16.3 1.2 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months APP R ALL DW COOLERS RHR 7200 11.8 24.1 -12.3 27.5 -6.8 NA APP R NO DW COOLERS RHR 7200 32.6 22.4 10.2 23.3 2.6 71 hours8.217593e-4 days 0.0197 hours 1.173942e-4 weeks 2.70155e-5 months APP R DW COOLERS FOR 2HRS RHR 9000 26.9 23 3.9 24 1.6 69 hours7.986111e-4 days 0.0192 hours 1.140873e-4 weeks 2.62545e-5 months SBO SPRAYS, 32F RHRSW RHR 6500 27.6 21.5 6.1 15.6 2.5 0.6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SBO SPRAYS, 95F RHRSW RHR 6500 32.2 21.5 10.7 15.8 4.5 1.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 22

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 7.0 Supporting Graphics:

Calculation No. MDQ099920060011 Rev: 1 Plant: BFN Unit 0 Page: 23

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.2 ST LOCA MAXIMUM RHR AND CS FLOW RATES I

161E 0 100 200 300 400 500 600 Thne (second&)

Suppression Pool Temperature 0 Wetwell Pressure

- - - Atmospheric Pressure it-RHR Pump Broken Loop Containment Pressure Required

-w- RHR Pump LPCI Loop Containment Pressure Required - CS Pump Containment Pressure Required Figure 7.3 ST LOCA CS PUMP 4125 GPM 90 s0 70 X 60

NPSHa

~50 _____ ACTUA

h-NPSHa NO COP

-NPSHr

-4 0 100 200 300 400 500 600 700 TIME, SEC

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 24

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.4 ST LOCA RHR 10500 GPM 90 so 70

60

NPSHa 150 ACTUAL

-&- NPSHa

_ _ _ _NO COP z40 -NPSHr 30 ____-

20 25.5-i_ _ _

10 0

0 100 200 300 400 500 600 700 TIMN , SEC Figure 7.5 ST LOCA RHR 11500 GPM 90 so 70-I NPSHa 5____ ACTUAL z-*-- NPSHa NO COP z 4NPSHr 0 100 200 300 400 500 600 700 TIME, SEC

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 J'Page: 25

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.6 LT LOCA 95F SPRAYS I160 16j 15 0 4 8 12 16 20 24 Time (hours)

- Suppression Pool Temperature r Wetwe7l Pressure

--- Atmospheric Pressure --W-RHR Pump Containment Pressure Required CS PumpnContainment Pressure Reoulred Figure 7.7 LT LOCA 32F SPRAYS SI.

0 1 2 3 4 5 6 7 8 9 TIME, HOURS Suppression Pool Temperature a Containment Pressure Atmospheric Pressure -i- RHR Pump Containment Pressure Required

[ CS Pump Containment Pressure Required

IAlr~mlntinn No. MD0O99920060011 Rev: I Plant: BFN Unit 0 Page: 26

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.8 LT LOCA CS 3125 GPM, 95F SPRAYS 100 90 80 70 60

NPSHa ACTUAL 50--

"f 5 NPSHa NO COP z NPSHr 40 30

'o 216 20 24 TIME, HOURS Figure 7.9 LT LOCA CS 3125 GPM, 32F SPRAYS 100 90 so 70 607 - NPSHa ACTUAL X!

22 so NO COP

-NPSHr Anl 3 4 5 6 7 8 TIME. HOURS

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 27

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.10 LT LOCA RHR 6500 GPM, 95F SPRAYS 100 go 70 60

NPSHa ACTUAL

-o -A-- NPSHa tNO COP Z mNPSHr 40 -

0.3 00_

20 0

4 8 12 16 20 24 TIME, HOURS Figure 7.11 LT LOCA RHR 6500 GPM, 32F SPRAYS 100 go 80 70 60 # NPSHa ACTUAL 50 -a- NPSHa NO COP z NPSHr 0 3E4 5 6 9 TIME, HOURS

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 28

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.12 ATWS 10 0W COOLERS, BALANCED PERFORMANCE 250 50 45 SP Temp 35 c 150 -30_

, -25 ==

...=.

IL100 20.

50 -10 5

0 -0 0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5 6 TIE, HOURS

- Suppression Pool Temperature - DWTEMP F

-e Wetwef Pressure Atmospheric Pressure W-- RHR Pump Containment Pressure Required - DW PRESS PSIA Figure 7.13 ATWS 6500 GPM, 10 DW COOLERS AS2-RAIATWS-DWC2 50 45 40 35

NPSHa ACTUAL

£30 --a- NPSHa NO GOP

-NPS~tr 251.

20

\

0 0 '

15 10 0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5 6 TIME, HOURS

Calculation No. MDQO99920060011iRv ln:BF nt0 Pg:2

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.14 APP R 10 DW COOLERS, 100% RH 9000 GPM, COOLERS OFF AFTER 2 HRS 2 40 ..... .. .. ... . .. ... .. . .... ... .. . ... . . .. . .. . .... . .. . .. .. ......... .... . ... .. . . ... . .. . . ... . .. . . .... . .... . . .. . .. ... . . . . . . . . ..... .. ..

.. ..... 40 Suppression Pool Temperature 220___ 35 200 30______

a 180 _25 U) 160 RR Pump Requi We20 140 ---- A mosp enci'ressure-- --------- ------ 15 120 10 100 -5 0 3 6 9 12 15 18 21 24 27 30 33 36 39 42 45 48 51 54 57 60 TIME, HOURS Suppression Pool Temperature

Wetwell Pressure - -Atmospheric Pressure -*--RHR Pump Required Wetwell Pressure I Figure 7.15 APP R 9000 GPM, 10 DW COOLERS COOLERS OFF AFTER 2 HRS 50 45 40 NPSHa 35 ACTUAL

-- NPSHa 30 i ACTU~AL g,,,.,7.7w,0wwNPS- NPSHr 25 NPS.- NPSHa z NO COP 2/ NPSH Margin 10 -- - ari 3.9 28 32 36 40 44 48 52 56 60 64 TIME, HOURS

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 30

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure7.16 APP R 10 DW COOLERS, 100% RH 240 30 230 28 220 26 210 24 2002 S190 20 I S180 18 170 16 160 14 150 12 140 10 0 4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 64 TIME, HOURS

-Suppression Pool Temperature -- Containment Pressure

- Aknospheric Pressure --*--RHR Pump C~ontainrnent Pressure Required

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 31

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure7.18 APP R NO DW COOLERS 230 28 220 -26 210 24 Wa 200 .22~

190 180 .18 A.1 170

-- -- -- -- __________ 16 160 150- 12 1~----I IV 140 5, V 0 8 16 24 32 40 48 56 64 72 80 88 96 104 112 120 128 136 144 TME, HOURS Sups Pood Temperature --- Cnwtainent Pressure Sirosheric Pressure --- RHRPupContainentPressurrRequirede

Calculation No. MDQ099920060011 Rev: 1 Plant: BFN Unit 0 Page: 32

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure7.20 SBO 95F SPRAY AT 4 HOURS 30~

160 0 4 6 8 Time (hours)

- Suppression Pool Temperature -0 Wetwe? Pressure -- - Abtospheric Pressure ---- RHR Pump Containmerft Pressure Required Figure7.21 SBO 32F SPRAY AT 4 HOURS 220 s0 200 40 180 30 1160 20 140.

120 10 100 0 0 2 4 6 Tbe (hours)

I- Suppression Pool Temperature -- Wetwell Pressure - - - Abmospheric Pressure W-

-RHR Pump Containment Pressure Required

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 33

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure7.22 SBO 6500 GPM, 95F SPRAYS AT 4 HOURS 250 200

________50 0 NPSHs 150s ~ ACTUAL

--- NPSH-

_NO COP

_________NPSHr NNW100 -SPTEMP DEG F 22-23

-150 0 4 8 12 16 20 24 TIrE. HOURS Figure7.23 SBO 6500 GPM, 32F SPRAYS AT 4 HOURS 250 200

ONPSHa

-150 ACTUAL r NO COP

-NPSHr 100 10 -SP TEMP DIEGF 0 8 12 16 20 24 TIME, HOURS

Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: 34

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 8.0 Summary of Results:

The case parameters and results are presented in Table 6.2-1 (page 21) and in Figures 7.2 through 7.23.

9.0

Conclusions:

Analyses determining the Net Positive Suction Head (NPSH) available to the Core Spray (CS) and Residual Heat Removal (RHR) pumps as a function of time after postulated accident and operational transient events in accordance with Regulatory Guide (RG) 1.82 have been performed.

The calculations are performed at EPU bounding conditions specifically for the recirculation pump suction DBA-LOCA, Anticipated Transient Without Scram (ATWS), Appendix R (APP R), and Station Blackout (SBO) events.

This calculation evaluates maximum pump flow rates, operation of drywell coolers, and containment sprays with minimum or maximum cooling water temperature and provides graphical representations of the sequences to support responses to Round 6 Requests for Additional Information (RAI) relative to BFN Units 1, 2 and 3 Extended Power Uprate (EPU) license amendment requests (TS-418 and TS-43 1).

Comparison of the available NPSH to the required NPSH for the respective pumps demonstrates that adequate margins exist to ensure that the RHR and CS pumps perform their intended design safety functions. The containment overpressure necessary to preclude pump cavitation and the duration for the required COP credit are determined for each event as summarized in Table 6.2-1 (page 21).

Specific conclusions are:

The small deficiency (-2 ft) for the RHR pumps discharging to the broken loop in the LOCA-ST case is considered acceptable on the basis of the short (<10 min.) duration involved.

" Maximum spray temperature produces the maximum duration for the wetwell overpressure requirement as indicated by comparison of the two LOCA-LT cases for 32F and 95F RHRSW.

" The case which results in the minimum available NPSH margin is the ATWS event which reflects a minimum margin of 2.8 ft for a short duration of approximately one hour. This is a consequence of the conservative power input included in the ATWS model.

" A small margin is also predicted for the Appendix R event (3.9 ft). This event requires operator action to isolate the drywell coolers within the first two hours of the event scenario.

" The maximum duration for required wetwell overpressure is determined by the Appendix R event with coolers isolated at two hours.

" Continued operation of drywell coolers for events which do not involve LOCA break flow or drywell sprays (ATWS and Appendix R) minimizes the containment pressure and NPSH margins for those cases.

APPENDIX A Calculation No. MDQ099920060011 Rev: I I Plant: BFN Unit 0 Page: Al of 4

Subject:

TRANSIENT NPSHICONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 1.0 Purpose The purpose of this Appendix is to calculate the heat exchanger K-factor per RHR heat exchanger required to transfer the design basis heat loads for the applicable PRA event sequences described in Section 6 of the main calculation. The result of this calculation serves as input to containment analysis that is used in the main calculation to provide time histories of the event sequences.

2.0 References 2.1 TVA Calculation MDQ0023980143, Revision 2 - RHR Heat Exchanger Tube Plugging Analysis For Power Uprate (RIMS W78030630006) 2.2 Textbook entitled Fundamentals of Heat and Mass Transfer by Frank P. Incropera and David P.

DeWitt, John Wiley & Sons, 3 d Edition 2.3 Power Uprate Evaluation Report for the Tennessee Valley Authority, Browns Ferry Units 2 and 3, Primary Containment System," General Electric Design Record File GE-NE-B13-01866-4, Rev 1, July 1998, (RIMS W79 980716 001) 3.0 Design Input Data 3.9 TVA Calculation MDQ0023980143, Revision 2 - RHR Heat Exchanger Tube Plugging Analysis For Power Uprate (RIMS W78030630006) 4.0 Documentation of Assumptions 4.1 RHRSW Temperature of 92°F. Justification - Based upon highest recorded temperature during study for C1320503-6924, Rev. 2 4.2 Suppression Pool Temperature of 187.3°F. Justification - reference 2.3.

4.3 RHRSW flow is 4000 gpm per pump. Justification - reference 2.1 4.4 RHR flow is 6500 gpm per pump. Justification - reference 2.1 5.0 Special RequirementslLimiting Conditions None.

6.0 Computations and Analysis 6.1 Methodology This Appendix uses an RHR heat exchanger model developed for reference 2.1. This model is an Excel spreadsheet application that uses known heat exchanger parameters and accepted standard engineering formulas to solve for unknown parameters. The accuracy of this model was confirmed previously (reference 2.1).

The major equation deals with heat exchanger effectiveness as a function of the overall heat transfer coefficient, the effective heat transfer area, the minimum mass flow-heat capacity product, and the heat capacity ratio. The effectiveness for a single shell pass, two tube pass CES type heat exchanger is given by reference 2.2, as follows:

APPENDIX A Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: A2 of 4

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS c=2,[I+CR+[(I+CRey)o." l+e-NTU[{'+ct") ("n 1 where:

E = heat exchanger effectiveness CR = heat capacity ratio

= Cmin/Cmax Cmin = minimum mass flow rate times fluid heat capacity product, Btu/hr-°F Cmax = maximum mass flow rate times fluid heat capacity product, Btu/hr-°F NTU = number of transfer units

= UAICmin U = overall heat transfer coefficient, Btu/hr-ft2-OF 2

A = effective heat transfer area, ft This equation along with others shown in reference 2.1, were programmed in an Excel spreadsheet and solved in the following sequence: (Note all equation references come from reference 2.1)

1. To determine the heat exchanger performance at any flow condition, the inside and outside fluid film resistance terms are calculated with Eqns 3 & 4 respectively.

2. The new overall heat transfer coefficient, U is determined from Eqn 2.

3. The effective heat transfer area is found from Eqn 5 for the assumed tube plugging percentage (for this appendix 1.5% is used).

4. The mass flow rates and heat capacity rates are found from Eqns 6 & 7.

5. The effectiveness is determined from Eqn 1

6. From the effectiveness and minimum heat capacity rate, the K-factor is calculated.

The Excel spreadsheet is presented in Table 1.

6.2 Analysis Using the accepted model, the following parameters were evaluated:

RHRSW Temperature = 92-F.

Suppression Pool Temperature = 187.3 0 F RHRSW flow = 4000 gpm per pump.

RHR flow = 6500 gpm per pump.

The spreadsheet solves for heat exchanger K-factor as indicated in Table 1.

APPENDIX A Calculation No. MDQ099920060011 Rev: 1 1 Plant: BFN Unit 0 Page: A3 of 4 Subject TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS

. .l.!......

. i . . ...

.. .I..

...... .. . .1.*. . ...... .. . *. _, ] ... .......* .... . . . . . ..............

itabl 1 r t ...........

. . .... -- ... ---... I -- -- -----.. .... .........-............... .... ... 4. ....

I- -q SK&Qas function of RHR Temp. at fixed Tp% and RHRSW condltlons -

'CONTAINMENT SPRAY DESIGN CASE ! Shell rhr Tube0w 1.11)l

-h Tub ___ - . 44__in 0.005 -- 0.002357 Au - . . - . .l .......-oC .....-

low. gpmn F 10000 4500 _ ... . ! .. . .. . ~~~.

r~ .... .. .. . . . . .. . . .. . .

1*veal s 20.02648 55

- Ibm/sec 1388.913

.- 625.0109 - ------- .. i...........

.....- GPM 1 - i SW F)1i - a ___ --

1 Trhr = - RHR Flow T STswFow Sw Cmln 'bmax itotal

/hdo/d)t-/ho . Rio . U EPS K IRHRSW '-TP_ Aeff - - Tautrhr -

Ib.

I..

b - F- . .. . . . . . . . . .. . .. -t ... .. ... otal, gpm i% 1Btu/hr 120.893.7808. ...... 95!

- --.1-553.1059 4000 553.1059! 893*.4.7 0000942 .D667- 0.0488k2 204.8619 0.4042621 3.5% 5M*-1*7.-6 .57801 60734 2 0 1 3 1 4 45. 7 11 3.4 800~ 7 4 1 --S.f103',

800014.5728071

-6107.341 28173554.3' 121.22091 109.14921

' 8 140 - 95] -4000553.1059 553.1059 888-9081 0.000942- 0.00067j 0-0048_ I 204.8519- 0.40411 223.5098. 72417190.9 80=00 4.567286071j6107.34 36208595.4 128.6812 113.184 10 886.2171 95 4000, 553.1059 553.1059 886.217 0.000942 0.0006671 0.004882i 204.8519 _0.403928i 223.41361 88471794.3 160 883.3883!

18087.24 F 956 5

_ 00053.10159 553.1059~

4000 553.1059 531059 883.3883 0.00ý094.21 8077.2241 6,06M09 0.067 .08 0.0006871 00482 24819 0.59! _ 0.403741 223.3112! 104509632 30403337136530069 8000 4.572807 --61-07.3-4 1422M85.89 8000 4.572807t 61 07.34 522650481.8 4 .58122 143.58313, 121.2159 187.3~ 874.817 95, 4000 531953.0 874.817F 000942 0 000667j 0048 0 .403331 23 4374 --

~~~-

8000i 4.5728071 6107.34174178-720 183.8483 -132-.2538 158.38361 129.28371

_03V8~044 227 860.7125 92 4000 553 ,4209 8607125 0.00000667 i200004882' 204.8519 0.409859 226.8245i 220473396 8000: i.5t -3041 1102366981 1914233! 147.309

.... l ....... ..... *... . .. ..

APPENDIX A Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: A4 of 4

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 7.0 Supporting Graphics None.

8.0 Summary of Results This calculation establishes that the heat exchanger K-factor per RHR heat exchanger that is required to transfer the design basis heat loads for the applicable event sequences is 227 BTU/sec-°F.

9.0 Conclusions The heat exchanger K-factor derived by this Appendix was conservatively derived and is reasonable and expected with consideration with the inputs. The result of this calculation will serve as conservative input to containment analysis that will be used for main calculation.

APPENDIX B Calculation No. MDQ099920060011 Rev: I Plant: BFN Unit 0 Page: B1 of 4

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 1.0 Purpose The purpose of this Appendix is to calculate the heat load rate contribution of the reactor water recirculation pump motors to the containment. The result of this calculation serves as input to containment analysis that is used in the main calculation to provide time histories of the event sequences.

2.0 References 2.1 Cameron Hydraulic Data - 19 uhEdition.

3.0 Design Input Data 3.1 Rated horsepower of the reactor water recirculation pump motors is 8657 hp per page B3 of this Appendix.

3.2 The efficiency of the reactor water recirculation pump motors is 96.1% per page B4 of this Appendix.

4.0 Documentation of Assumptions 4.1 All horsepower lost due to inefficiencies is converted to heat that warms the drywell. Justification

- This will provide the most containment heat lost due to pump motor contribution at the time of the ATWS and Appendix R events to predict conservative drywell cooler performance.

4.2 Two Recirculation pumps are running at 100% rated flow. Justification - This will provide the most containment heat lost due to pump motor contribution at the time of the ATWS and Appendix R events to predict conservative drywell cooler performance.

5.0 Special Requirements/LImiting Conditions None.

6.0 Computations and Analysis 6.1 Methodology This Appendix takes the rated horsepower of the reactor water recirculation pump motors and determines how much horsepower is lost due to inefficiencies. The lost horsepower is converted to heat rate using standard conversion factors.

6.2 Analysis Efficiency loss = (100% - Efficiency)/1 00, thus Efficiency loss = (100% - 96.1%)/100 Efficiency loss = 0.039 The per pump horsepower loss is given by Horsepower loss/pump = (Efficiency loss) x (rated horsepower)

Horsepower loss/pump = (0.039) x (8657 hp) = 337.623 hp

APPENDIX B Calculation No. MDQ099920060011 Rev: I I Plant: BFN Unit 0 ] Page: B2 of 4

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS The horsepower lost for two pumps = 337.623 x 2 = 675.246 hp Converting to a heat rate (Btu/sec):

(675.246 hp) x (42.43 Btu/min) x (1 min/60 sec) = 477.5 Btu/sec 7.0 Supporting Graphics None.

8.0 Summary of Results This calculation establishes that the heat load rate contribution to the containment for the reactor water recirculation pump motors is 477.5 Btu/sec.

9.0 Conclusions The heat load rate contribution of the reactor recirculation pump motors as determined by Appendix was conservatively derived and is reasonable and expected with consideration with the inputs. The result of this calculation will provide the most containment heat lost due to pump motor contribution at the time of the ATWS and Appendix R events to predict conservative drywell cooler performance. The cooler performance will serve as conservative input to containment analysis that will be used for main calculation to provide time e histories of the event sequences.

10.0 Attachments None

APPENDIX B I Calculation No. MDQ099920060011 I Rev: I Plant: BFN Unit 0 1 Page: B3 of 4

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS GE Industrial Systems

GE Motors - DATA SHEET - Custom 800 (R)

SQUIRREL CAGE MOTOR CUSTOMER TWA BROWNS FERRY/IGE NUCLEAR CUSTOMER ORDER 00001704 01343/431005962 GE MODEL 291R610 DESIGN KC899R240B SO 288003412880035 RI :132-1.619702M3 OTY :11 SERLALN : 2880000421288000043 POWER 8657 HP TYPE :KV POLES : 04 FRAME : 8300 VOLTAGE 3965 V ENCLOSURE COOLING ODP FREQUENCY : 56.6 Hz SERVICE FACTOR :1.00 CLASS 8 RISE PHASES : 03 INSULATION CLASS : F (POLYSEAL)

TEMPERATURE RISE : 73C I TC 0 SF 1.0 TEMPERATURE CLASS :B DRIVEN LOAD : PUMP MAX ALTITUDE : 3300 It LOAD WK2 REF.TO MOTOR SHAFT :12872 Lbft AMB. TEMP. (MIN/MAX) -18/57 C Calculated Performance RATED RPM :1682 NEMA STARTING CODE :E RATED CURRENT :1066 A LOCKED ROTOR CURRENT : 570%

RATED TORQUE : 26960 LbFt LOCKED ROTOR TORQUE :60%

RATED KVA : 7383 PULL UP TORQUE : 60%

STATOR CONNECTION :Y BREAKDOWN TORQUE :175%

MIN. STG .VOLTAGE : 90%V COUPUNG TYPE : FIXED ()

TIME RATING : CONT ARRANGEMENT Vt - SOUD SHAFT ROTATION : COW FROM TOP TOTAL WEIGHT (calculate) : 40000 Lb ROTOR WK2 (caicuated) :15700 LbIF MAX BRG.VIBR. [pk] : .12 n/ecc BEARING TYPE : SLEEVE (')

BRG LUBRICJ(UPPERUWER) : OILIOIL END PLAY :0.01 In STATOR RESIST. @ 25C : 0.0139 Ohms L-L LOCKED ROTOR TIME (100% V)

COLD :208 XIR RATIO :38.700 (NEMAMGI-20.43) HOT: 158 OPEN CIRC. TIME CONSTANT : 2.6680 9 NUMBER OF STARTS OUTLINE NUMBER : M88D100134 COLD :2 INSTRUCTION BOOK : LATER HOT :1 STATOR I ROTOR (SLOTS) :96/110 NOTES VIBRATION UMITS BASED ON MOTOR RUNNING UNCOUPLED AND WITH BEARING TEMPERATURE STABILIZED IN STIFF BASE

() PROVIDED BY CUSTOMER.

(') UP THRUST BRG -JV 15" M) DOWN THRUST BRG - JV IT 112

(*) UPPER SLEEVE GUIDE SRG - r (TAPERED LAND)

(M)LOWER SLEEVE GUIDE BRG - 10" SERVICE FACTOR @ CLASS F RISE (LATER)

SH I OF2 PREPARED BY OSVALDO AKIRA APPROVED 1 0o6-30.2,o9 640-200BI__EV:_06DS2880034 IREV:06 I

APPENDIX B Calculation No. MDQ099920060011iRev: I Plant: BFN Unit 0 Page: B4 of 4

Subject:

A TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS GE IndustdaM Systems IS GE Motors - DATA SHEET - CuTomsR (S SOUIRREL CAGE MOTOR MODEL: 291R610 SO: 288003412880035 RI: 132-1-6167/02/03 Calcidated Peformance NO Load 19 100 0.91 96.1 1066 75 0.91 96.0 801 so 0.90 95.4 51 ACCESSORIES TESTS 6 STATOR THERMOCOUPLE COPPER CONSTANTAN-T AIR GAP MEASUREMENTS 12 HEATER 3600W- 3 PH DC HIGH POTENTIAL TEST I VIBRATION DETECTOR - R. SHAWN 366-A7 HEAT RUN STATOR AND BEARINGS (DUAL FREO) AT REDUCED LOAD 4 BRG THERMOCOUPLE-COPPER CONST-DOUBLE

HIGH POTENTIAL TEST INSULATION RESISTANCE TO GRD NO LOAD TEST NOISE POLARIZATION INDEX (BEFORE VP1 AND FINAL ASSY)

POWER FACTOR TIP-UP TEST NOTES STATOR CORE TEST TORQUE & STARTING CURRENT EQUIVALENT RATING: WINDING RESISTANCE (BEFORE VPI; FINAL) 9177 HP - 4200 V - 1066 A - 1787 rpm - 60 Hz PHASE SURGE TEST (BEFORE VPI; FINAL)

AC HIPOT (BEFORE VPI AND FINAL ASSY; FNAL)

STATOR THERMOCOUPLE LOCATION SPRAY TEST TC SLOT PHASE TC SLOT PHASE SH-AFT VOLTAGE

I #1 A #7 #25 A (SPARE) LOCKED ROTOR TEST AT REDUCED VOLTAGE 02 a9 C #8 a33 B (SPARE) ROTOR THERMAL STABIULTY TEST (COLD AND HOT 03 #17. B #9 #41 C(SPARE) . VIBRATION MEASUREMENTS) a 4 #49 A BEARING INSULATION RESISTANCE TEST a5 a57 C SHAFT CRITICAL SPEED TEST (COAST DOWN) as6 a6 B SPEED / TORQUE AND SPEED i CURRENT REED FRED TEST REVISIONS

[1] AccoMn to customer comments.

[2] Accorcng to cutomer comments.

(41 Accordlng to customer comments.

[4] AccodmIng to customer comments.

SH2OF2 PREPAREDBY : OSVALDO AKIRA APPROVED : DS2880034 06o-30-2006 IREV: 06

APPENDIX C Calculation No. MDQ099920060011 Rev: I I Plant: BFN Unit 0 Page: C1 of 3

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Excel Spreadsheet Computations The spreadsheets used to develop the transient available NPSH curves and required containment pressure curves are setup with the GE transient containment parameters in the left hand columns, followed by three columns listing the atmospheric pressure, pool vapor pressure, and temperature dependent conversion factor for converting pressure to water head. The remaining columns to the right list the steady state NPSH case input in a block in rows 2-6 and the adjusted transient parameters below that for each pump considered for the subject event. An extract of the LOCA spreadsheet is presented on the following page and is typical of the other files.

The spreadsheet files identified as follows for each event are stored electronically as indicated on page 6:

EPURAI_6_LOCA.xls

" EPURAI_6_ATWS.xls

EPURAI_6_APPR.xls and EPURAI_6_APPRGERl.xls

" EPURAI_6_SBO.xls

APPENDIX C Calculation No. MD0099920060011 Rev: 1 1 Plant: BFN Unit 0 Page: C2 of 3 Subject TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS A IL I I a H . U N [0 a I u I~~~~~=0 - - -1Nf1~__ am --- Ma __ -

44 IOF-to9m~ 46408.40 I22466.I _____ 187.1 __

LMmt fEVVVT%'WF 54 OA.W L8mtwm ff5r,

____ _____ft I" eREOP4 -

W0 DATA rlV. 6W7r32.1_XF LI "_&IM I 9 -PPAN MN x Mpd S933S 347 23 2,1.5 0+ 7s2

w . Pqam "wt wt.

TIME 0WTOW PRS WW 2WALK aPTOW OF Pelm NP1 CREW Pu9u P~

MAP MINN" Pre68w HOURS TOM PSIA w TWA P F 1 PIA IPRA Cqvv ACTUAL I IP NO COP P"-*w KmgW F6 mfigbl

-3 IC I CL_

0.8 1 "A_ 2-23.-33-21 429 4V 49.=.2 415170 22 21. AC7J32 fJ7i 39 9-11 1-s 9 __ 0.07 17A4 SSAD 144AC 9S_(" "AD ..... I MGM" MA.23M9..4A, 3 AZ 489S4 2i-l 21 07M 607439 j3 C.21 _-1GC le6.73 ".4T I1. 3 14 WE, 0.81341 1.4A 4.4 3.9.46 . 4z6w6 21.5 22 773,9 .742-T* R I12 M C37 __ 233 .g*~i - 06108__IA!3 Sul... 611 AS2_TII~

.22146 42.93102 21.5 2&6.61141 S.177176 12., _

.c2246 a. 2S SA 211.13 17.16 121.1m 17.16 K23 6162 __ _4 23248 A 214832"eC12 -_17946f it 99 _

s 043218 CAS.6 27-2 219.13 15-33 131.12 15133 -9&31 LCLS823136 s. 2-32'532 - CE3742 451 4195c6 21.5 3290974 S9.1 13,S1 3

MC34.

!7 0.0113338 a.2 1...1 __0

_762 l 23

~I

_ I26.M. -~3 22.-01

--- 49 0.

OL35ca I 446c 14.57MS2 4 12 4z826 1.5 2 34J I 144C 4A 2-3.23744 - 63L971312 45-14475 &2.8.6WI 11.6 39071311 S6.9439 'S.54 is 15 32 6 -A 2-t2 23.14 17 .i 23.94 8 1.4.4 2 322... 21.. 4&3 I f,-21 7 "S to.

7 2I* -7 1 -'33.7: 213' 4.72 25.64 953 -6544& All '13V - 6 3811 4M12 42-8210 21.S 'A-381 &2IZ;72 _2.3A C.

__ -- -W 154.n2 27. R1.2 ___74 -A 742423324 469501, ¶Z33- S-33!. 3 22.72

-9r C.fFJ0 .9. 9. 287 337 5I~ 0.516144 1'4A 2321 iS7 o 4 .M1r.3 4.2. 7 21.6 651cs41 6.27fiai4 2645AS

'I .75 3357 -3 1 32 231.

____C.32 3232 12 -A7 323 24921 44.96173 416797' 214'S 62. 0492163.

Ms 26.99 S3.l3 3 9-!

I,_"_ 1AvC. 2S .31- 33.2-' 234ý32 33 4 . 1 S

ý- S13.63 .4& 2_323B31 9527M' &24 660, 21.S 6477' 23 S63 12 297..

2

. 7.46 41 12 288.92 33.2 251.- 33.&2 1077 8IA .' 659893 9 16 28 5 .C. 9' 41, 3+ --. 27"3 34A7 P.4 19 16 -6 2.26416 - 89792M3 AM I

2983 __

.3 .1C 27. 3424 _2775 1.31-- 3 4.11344. 21.5 8 83B9 6675' 9.

_ U .7T -A239 - . I i.s!! T * *&AA7

1. 61-9 -954 4.43 4656M lI _

0.0W40 ___0L . *Z - - . 1 316 279 1I - . - 172S937 SC 1.M. 2.384-8626 43211 A167 128 6090 12 0.01~c 72 2.6 27.719 4262 42.'3 76.4 6.62 122.0 37.M- 23ý 7.7,,.16.s 1 130.51

8. 3 - 1 92 5I"2 3 14.4 333582 1 2-36.3L 195i29369 91 4 2e 3' .737651E z21.5 ]

760 71-33961 6.527. 31. 63A ___

0..33 3800968__1.8 3576 A.

14 S 210.92. 37.24 223.41

'R.5232 37.8*-344 133722 37341 - 2X696 -4A 2-341634 929891 4,.6954a7 3.182C4 .. !. . 7168 46691 GY6. 3 3A13 All.

Mr0. 72A0. _ a, 34.-a .3 A6 --304.62 87.63 37 .33 223.8 I7 iz!132 8A

-S.93-12 '6192431 . 2231 4-. 9299969 . 1 3$6 39.31492 1.46.....

4ier 5CL-9L7 -21.62 .5_ 71-459769761 6 IA 3263 , _

.0 327 .5 3I e - 4"AD 1 ZZIC 3 ],4. 1 3.3 2,1226-2 %4* .3.3861 A 8,622. 3.S31 36 60.012 3.7.3 372 39.30 25 j72*

T2 229 -31 13234 - 2A=32933 &A4.9-35653143447 41.617i 3S.29993. 21.6 0.012202 39371 2-0.93 372A 223 43 37.337 131.3 2.426124 2-1437M 563161 41.24.62 33.3149.S 711.639 1.99 r.713153 G,96,61 3}31.6 U6

_0_ 3S. ,4 42 37'4- 17 s zw4. AA. 3417. 4 21.S 7 6 96, 7 .

20.f1 7 _ 3 Z 7.22 373 22351 37353? 133 3.. _ I"4 2341766 53033449 21A 1S7 634 936 I .AI_

3 0 45 7.7 40.51391343924W -na 66.13 37.3 ... 1 37.24. i3133.*- 2.4-Z 231 14A 2.41 1932111 414466fl-41 ME M34.3346 -

=A'14 21.6 1, 7.4 ,M1 32__m .

47 ms 6... 37a 2266.2=3~ 37.6S 22-LD 37.M 13.4.2 6132978 14A4 2.342657s 8"32222 3l 1&219% 21. _71.7223S 6.881661 31.52 O. 1 ___ 49. 3 _ _ __ 38. _ al " 68.9l 4 3"774 223

~ 37.33 . 13"3 _.2.92& S4 2-3417 3 3-SE t. 22A1 7141 6-79 31.822.&

31. 1I6 - .8 245 -, 1 33.8 ~ 6 ., ~ ~

APPENDIX C Calculation No. MDQ099920060011 Rev: I I Plant: BFN Unit 0 Page: C3 of 3

Subject:

TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS J-~ _________

K L

M N LT LUCAICae 3 0 P RHRI,_____C_____

_ _ _ _ _T

=_W Pw& 14A NPSHa At CREDIT ps __

SM N MIN MINMA M:N

- MININION1520) -M._NO10*-15 ) WMIN(FtP1O52W) MN 0"1} -MINNR11O:RI -MAX(S! 1O S1 -'2S 9 .IMNITD,:T11Z9l PVAP SP NpsHa CRE NPSfa Cant Pf*aut R.%d COPI.

SP 1A Plom PSRA r A,.J ATllUAL IOP I P"r hMh, NO NI WI NIAH -

sc!

ATTACHMENT I I Calculation No. MDQ099920060011 Rev: 0 1Plant: BFN Unit 0 1Page: 1 of 3 SULZER (U~hp~Transient SUILWPuimrn -NPSH R~niiew

1. E..2

.2006 I

I I

I 0.0'1 0.1 1 10 100 1000 Opwang IHour 9 15 July 14. 2006 Q,ol-

ATTACHMENT 1 Calculation No. MDQ099920060011 Rev: 0 [Plant: BFN Unit 0 Page: 2of3 SULZERJuly. 2006 SUZ RTransient NPSH Revitw E2516 D.01 C1 1 10 'm0 1000 ----

LL 0.01 01 10 100 1000 10000 Operating Hours 9 15 Juh' 14. 2006

ATTACHMENT I 1

I Calculation No. MDQ099920060011 ATTACHMENT I Rev: 0 1 Plant: BFN Unit 0 IPage: 3 of 3 1 TIME 6500 r Interpolated Values I SULZER RHR PUMP REQUIRED NPSH (DATA FROM SULZER REPORT FIG. 1) 7200 9000 10000 A

10000 B

0.01 21 21.40 22.43 23 8 21.5 22.40 24.71 26 12 22 23.00 25.57 27 27 24 23 24.10 26.93 28.5 28.5 32 23.7 24.84 27.77 29.4 29.4 100 30 31.30 34.64 36.5 36.5 8000 30 31.30 34.64 36.5 36.5 40 38 36 34 P 32

{ 30 z 28 26 24 22 20 0 8 16 24 32 40 48 56 64 72 80 88 96 TIME (HRS)

A 10000

6500

9000 )K 7200 Linear (10000) - Linear (6500)

ATTACHMENT 2 I Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 1 Page: 1 of 7 EFS43N C0NDTk44C RBCCW LATEWN 10 COILS 10 COILS 10 COILS 10 COILS FLOW, ILoET OULET FLOW, RBCCW RCCW SENSIBLE Kr, CONOENUATE SIISIBILE "T. LAEWIT KT, TOTAL NT. CONDENSLATE CASE ACFU T-00 T-O5 RH GPM IN OUTf HT, BTLiR BTU+IR LSA" 5TruSEC BTUISEC BTLCSEC LBWSEc DESGN% 1CM 1A445 tIS1 c i27 4 iO 1Z9.4 5%mm3 0 ZmO 1647 i647 2rco 4c, 2"74 IC 1M"3 5W665 a0 U.J 1630 0 1630 2.00 4 14=1 1445 126 43 1274 100 10..4 681042 14315 14.76 1614 4: 165, Z.14 1 13=1 '445 1171 51, 1274 100 111.4 5066 22-640 25.2 1427 W35 2043 2.66 3 19C U.445 '31 1 K 1274 10W 122.47 25OD94 127465 1313.60 59, 3w 423 3.6 2 190-x1'445 '36,3 1= 127A 102 132.11 1-49X- 2102M 2167.64 319 5641 6160 5.2 5 19=C 1337 -6 1 50 1274 9! 114.3 52019E 72r29 7416 1445 200 1645 2.21 7 19M[ M137 ' I1 2"74 95 121.8 137636 16M663 '742.5 3II 4,96 5079 4.14 ftdi V- 150 11573 40 12VA 15 11u 67'M 25438 26.22 71 133 no1' PA 2 I=~ 150 1185 45 127A 1T0 1124 om 19m 213 162 543 2234 am Rp na1911 150 1213 so TVA 15 114.16 550657 a1m 381.72 I34 102 283 1.0 Page i

( -,V-,-ý,

ATTACHMENT 2 Calculation No. MDQ099920060011 I Rev: 0 Plant: BFN Unit 0 Page: 2 of 7 07-26-200M 17.1639 PROTO-HX 4.01 by Proto-Power Corporation (SN EPX-1027) Pag I WA Calculation Report for BFN2CCL-070-740 - Drywell Air Cooler 3UOF, 50%RH, EPU RAI 6 fLIAL CONMT*lTrI Calculation Specifications Constant Wiet Temperte Method Was Used Extrapoltion Was to User Specified Conditions Design Fouling Factors Were Used Test Data Data Date Air Flmo (acfm)

Air Dry Bulb Temp In ('F)

Air Dry Bulb Temp Out (7F)

Relative Humidity In (%)

Relative Humidity Out (%)

Wet Bulb Temp In M Wet Bulb Temp Out (OF)

Atmospheric Pressure (psia)

Tube Flow (gpm)

Tube Temp In (TF)

Tube Temp Out (T)

Condensate Temperature ('F)

Extrapolation Data Tube Flow (gpm) 127.40 Air Flmo (acfmn) 19,000.00 Tube Inlet Temp (7F) 100.00 Air Inlet Temp (*F) 150.00 Inlet Relatihe Humidity (%) 50.00 Inlet Wet Bulb Temp ( 0.00 Atmopheric Pressure (psia) 15W00 04Air Mass Velocity (Lki~1zr"~, Tube Flmd Velociny (ft'sec)q Air Dmnity xt Julet T, Odser Prqpermes x Aer~ge T

ATTACHMENT 2 Calculation No. MDQ099920060011 i Rev: 0 Plant: BFN Unit 0 Page: 3 of 7 07-26-2C06 17.16:59 PROTO-EX 4.01 by Proto-Power Corporation (SNVPHX-l027) Age 2 TVA Calculation Report for BFN2CCL.070-740 -Drywell Air Cooley I.OF, 50%R, EU MAS 6 rMTIAL CONMZITION Extrapolation Calculation Summary Air-Side Tube-Side Mass Flow (Ibmrb) 68,850.34 63,353.58 Tube-Side hi (BTU/hr-ft'-'F) 0.00 Inlet Temperature (7F) 150.00 100.00 j Factor 0.0000 Outlet Temperature (F) 121.53 114.16 Air-Side ho (BTU/br-ff.°F) 0.00 Inlet Specific Humidity Tube Wall Resistance (hr.flt-'F/BTLU 0.00016250 Outlet Specific Humidity Oerall Fouling hr-.ft-.F/BTLU) 0.00412058 2

U Overall (BTU,1 -f-'F)

Effective Anea (r1) 2,046.63 l.lD 0.00 Total Heat Transferred (BTUinr) 922338 Surface Effectiveness (Eta) 0.0000 Sensible Heat Transfered (BTUIq) 552,067 Latent Heat Transfeed (BTU/br) 370,265 Heat to Condensate (BTUL r) 26,889 Extrapolation Calculation for Row l(Dry)

Air-Side Tube-Side Mass Flow (Ibmbr) 68,850.34 63,353.58 Tube-Side hi (BTUTJ.fFl.F) 1,801.20 Inlet Temperature (OF) 150.00 111.80 j Factor 0.0103 Outlet Temperature (*F) 142.29 114.16 Air-Side ho (BTUTJr-fle.°F) 15.46 Inlet Specific Humidity 0.084838 Tube Wall Resistance (hr-ft 'F/BTLrJ 0.00016250 Outlet Specific Humidity 0.084838 Overall Fouling (hr.ft.'.F/BTU) 0.00412058 Avernge Temp (OF) 146.14 112.9785 Skin Temperature (0F) 116.88 114.9949 U Overall (BTU *w-ft'.F) 13.29 Velocityt *** 5.047.79 6.2645 Effective Ama (fn) 341.11 Reynlffs Number 1.849,, 42,497 LMTD 33.01 Prandi Number 0.7253 3.9144 Total Heat Transferred (BTU/Ihr) 149,618 Bulk Visc (Ibm/ft-hr) 0.0491 1.4407 Skin Visc (Ibm/fl-) 0.0000 1.4125 Surface Effectiveness (Eta) 0.9743 De "(Ibm,') 0.0612 61.8172 Sensible Heat Transferred (BTU/hr) 149,618 Cp BTU/Ilbm.°F) 0.2402 0.9988 Latent Heat Transferred (BTU/hk)

K (BTU/br.ft-°F) 0.0163 0.3676 Heat to Condensate (BTUbr)

Relative Humidity In (%) 50.00 Relative Humidity Out (%) 60.67

0Reywols Number Outside Kane of Equsitkm Aplicability

4Air Mass Velocity (Lbmr~flc), Tube Fli Velocity (ft set); AirDenlsity atlziletT, Other Propernes at Awrale T

ATTACHMENT 2 I Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 1 Page: 4 of 7 1 07-26-2006 17.16359 PROTO-HX 4.01 by Pruto-Power Corporation (SNCPHX-1027) Pp.3 TVA Calcalation Report for BFN2CCL-070-740 - Drywell Air Cooler 130F, 50%R- EPU PAI 6 EMIAL CONDON" Extrapolation Calculation for Row 2(Dry)

Air-Side Tube-Side MaNss Flow (Ibm,1r) 69,850.34 63,353.58 Tube-Side hi (BTU/hr-/W-MF) 1,779.92 Inlet Temperature (7) 142.29 109.79 j Factor 0.0103 Outlet Temperature (MF) 135.75 111.80 Air-Side ho (BTU/br-fe-°F) 15.40 Inlet Specific Humidity 0.0M438 Tube Wall Resistance (hr-ft'-°FABTU, 0.00016250 Outlet Specific Humidity 0.084839 O~vrall Fouling (hr.ft-.F/BTU) 0.00412059 Average Temp ("F) 139.02 110.7941 Skin Temperature (OF) 114.12 112.5236 U Overall (BTU/r-ift-'F) 13.24 Velocity *** 5.047.79 62613 Effective Area (fi5 341.11 Reynolffs Number 1.866** 41,586 LMID 28.09 Pranddl Number 0.7259 4.0087 Total Heat Transferred (BTUhr) 126,815 Bulk Visc (Ibmnft-hr) 0.0487 IA723 Skin Visc (IbmIft-b) 0.0000 1.4472 Surface Effectiveness (Eta) 0.9744 Density (Ibm.1ft') 0.0618 61.8487 Sensible Heat Transferred (BTU/ihr) 126,815 Cp (BTU/lbm-°F) 0.2402 0.9928 Latent Heat Transferred (BTU/hr)

K (BTUikr.ft-.F) 0.0161 0-3668 Heat to Condensate (BTU10)

Relative Humidity In (%) 60.67 Relative Humidity Out (C) 71.82 IepRolds Number Outside Rang ofEquaittm Apcirbility R

Extrapolation Calculation for Row 3(Dry)

Air-Side Tube-Side Mass Flm, (Ibm/hr) 68,950-34 63,353.58 Tube-Side hi (BTUJir-/t-hF) 1,761.82 Inlet Temperature (MF) 135.75 108.09 j Factor 0.0102 Outlet Temperature ("F) 130.20 109.79 Air-Side ho (BTU/hr-ft-°F) 1535 Inlet Specific Humidity 0.084838 Tube Wall Resistance hr*-fe-°F/BTU, 0.00016250 Outlet Specific Humidity 0.084839 Overall Fouling (hr-fl'-°F/BTU) 0.00412059 Average Temp ("F) 132.97 108.9416 Skin Temperature (F) 111.78 110.4243 U Overall (BTIE/-fe-°F) 13.19 Velocity*** 5.047.79 6.2587 Effective Area (ft-) 341.11 Reyzolffs Number l.820, 40,819 LMTD 23.92 Prandtl Number 0.7264 4.0917 Total Heat Trasferred (BTU/0r) 107,615 Bulk Visc (rbmnfi-hr) 0.0483 1.4999 Skin Visc (Ibmfl-ft-) 0.0D00 1.4777 Surface Effectiveness (Eta) 0.9745 Denity (Ibm,'fl') 0.0624 61.8749 Sensible Heat Transferred (BTU/hr) 107,615 Cp (BTUnlbm.-F) 0-2402 0.9988 Latent Heat Transferred (BTU/hr)

K (BTU/hr-fl-F) 0.0160 0.3662 Heat to Condensate (BTUhr)

Relative Humidity In (%) 71.82 Relative Humidity Out (%) 83.16 0R~eynolds Number Outside Range of Equisoz Apphcability

- 1. Air Mass Veloc*y (Lbmnzrf:-), Tube Fluid Velocity (f'sec) Air Denity at Iulet T, Other Properaes a Aeage T

A1-ACHMENT 2 Calculation No. MDQ099920060011 Rev: 0 Plant: BFN Unit 0 Page: 5 of 7 07-26-20M 17V16359 PROTO-HX 4.01 by Proto-Power Corporation (SNOPlHX-1027) P31e 4 IVA Calculation Report for BFN2CCL-070-740 - Drywell Air Cooler 1530, 50-Ra, EPU RAI 6 ICMAL CONDTON Extrapolation Calculation for Row 4(Dr')

Air-Side Tube-Side Mass Flow (Ibmlir) 68,150.34 63,353.58 Tube-Side hi (BTU/brf*T--F) 1,746.40 Inlet Tenmprare (M) 130.20 106.65 j Factor 0.0102 Outlet Temperature (MF) 125.49 108.09 Air-Side ho (BTU/r -ft-OF) 1531 Inlet Specific Humidity 0.084838 Tube Wall Resistance (hr-flF-F/BTUr, 0.00016250 Outlet Specific Humidity 0.084838 Overall Fouling hr-ift-"F/BTU) 0.00412058 Average Temp (M1) 127.84 107-3689 Skin Temperature (TF) 109.79 108.6395 U Overall (BTUjr.f-'F) 13.15 Velocity *** 1 5.047.79 6.2565 Effective Area (fW ) 341.11 Reynolas Number 1.893#* 40,171 LMTD 20.38 Prandtl Number 0.7268 4.1643 Total Heat Transferred (BTUMr) 91,416 Bulk Visc (Ibmlfl-hr) 0.0480 1-5241 Skin Visc (bmt-hr) 0.0000 1-5045 Surface Effectiveness (Eta) 0.9746 Densit-(lbm.ft') 0.0629 61.8968 Sensible Heat Transferred (BTU,%r) 91,416 Cp (BTU/lbm.7F) 0.2402 0.9989 Latent Heat Transferred (BTU/hr)

K (BTUtkr-fk-OF) 0.0159 0.3656 Heat to Condensate (BTUibr)

Relative Humidity In(%) 83.16 Relative Humidity Out (%) 94.42

"*Ranolds )'`uber Ouwside Ian- of Equao Atfhcability Extrapolation Calculation for Row 5(Dry)

Air-Side Tube-Side Mass Flow (Ibm/hr) 68,850.34 63,353.58 Tube-Side hi (BTU/hr-if'°"F) 1,736.14 Inlet Temperature ('F) 125.49 106.00 j Factor 0.0102 Outlet Temperature (F) 123.39 106.65 Air-Side ho (BTU/br-ft'-OF) 15.28 Inlet Specific Humidity 0.084838 Tube Wall Resistance (hr-W-°F/BTU: 0.00016250 Outlet Specific Humidity 0.094838 Overall Fouling (hr.ft.-F/BTU) 0.00412058 Average Temp (OF) 124.44 1063245 Skin Temperature (MF) 108.47 107.4529 U Overall (BTUIar-fV--F) 13.12 Velocity *** 5,047.79 6.2550 Effective Area (fn) 171.64 Reynol's Number 1-902,, 39,743 LMTD 18.09 Prand Number 0.7271 4.2137 Total Heat Transferred (BTU/hr) 40,753 Bulk Visc (lbmnfi-hr) 0.0478 1.5405 Skin Visc (Ibm,0fk-hr) 0.0000 1.5228 Surface Effectiveness (Eta) 0.9746 Densit (lbm.') 0.0629 61.9111 Sensible Heat Transferred (BTU/hr) 40,753 Cp (BTZU/lbm-F) 02402 0.9989 Latent Heat Transferred (BTU/br)

K (BTU/kr-ft-*F) 0.0158 0.3652 Heat to Condensate (BTU/hr)

Relative H-umidity In (1/) 94.42 Relative Humidity Out (%) 100.00

0Reaynolds Number Outside Ism.-e of Equsdon Apphcabihi,

0*Air Mass Velocity (Lbmtrfl') Tub F~ Veoct (fr'se4l Air Density at IWet T, Othe Propemtes st Asurap T

ATrACHMENT 2 I Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 I Page: 6 of 7 I 07-26-2W6 17:16:59 PROTO-HX 4.01 by Proto-Power Corporation (SNNLPHX-1027) P31 5 TVA Calculation Report for BF1N'2CCL-070-740 - Drywell Air Cooler ISOF, 5*4O., MERAI 6 TAL CONDITION Extrapolation Calculation for Row S(Wet)

Air-Side Tube-Side Mass Flow (Ibm-hr 68,850.34 63,353.58 Tube-Side hi (BTU,/r -fP-F) 1,730.22 Inlet Tempera*ure (M) 12339 104.12 j Factor 0.0102 Outlet Temperature (T) 122.82 106.00 Air-Side ho (BTU/r-ft. *F) 75.22 Inlet Specific Humidity 0.084838 Tube Wall Resistance (hr. f--F/BTU': 0.00016250 Outlet Specific Humidity 0.083331 Oeranl Fouling (hr.fl'-"F/BTU") 0.00412058 Average Temp (M) 123.10 105.0625 Skin Temperature (F) 111.87 108.6458 U Overal (BTU/hr-fP.9F) 41.70 Velocity *** 5.047.79 62533 Effective Amea (ft') 169.47 Reynolas Number 1-905"* 39,228 LMTD 13.02 Prandtl Number 0.7272 4.2746 Total Heat Transferred (BTU/hr) 127,362 Bulk Vise (Ibm'ft-br) 0.0477 1.3608 Skin Visc (In/ft-hr) 0.0000 1.5044 Surface Effectiveness (Eta) 0.8902 Densiy (lbmlfe') 0.0633 61.9282 Sensible Heat Transferred (BTU/hr) 10,997 Cp (BTUIbm-F) 0.2402 0.9989 Latent Heat Transfened (BTU/hr) 116,371 K (BTUhr-fk-`F) 0.0158 0-3647 Heat to Condensate (BTUur) 8,589 Relative Humidity In (%) 100.00 Relative Humidity Out (%) 100.00 "1Reynolds Number Outside Rasp ofEquzm Apbcability Extrapolation Calculation for Row 6(Wet)

Air-Side Tube-Side Mass Flow (lbmur) 68,850.34 63,353.58 Tube-Side hi (BTUrk-ftz'-F) 1,702.67 Inlet Temperature (F) 122.82 100.01 j Factor 0.0102 Outlet Temperature ('F) 121.53 104.12 Air-Side ho (BTU/br-ft-°F) 72.77 Inlet Specific Humidity 0.083331 Tube Wall Resistance (hr-fV-FiBTUL' 0.00016250 Outlet Specific Humidity 0.080042 Ovwall Fouling (hbrf'.F/BTU) 0.00412058 Average Temp (0F) 122.17 102.0681 Skin Tempernture (MF) 109.55 106.0385 U Overall (B-U~b.rft1 .F) 40.80 Veloci-V *** 5,047.79 62493 Effective Area (ft) 341.11 leynolffs Number 1.907*4 39,015 LMTD 20.03 Prmnd Number 0.7273 4.4250 Total Heat Transferred (BTU/hr) 278,758 Bulk Visc (Ibmft-hr) 0.0476 1.6106 Skin Visc ( -hnm br) 0.0000 1.5451 Surface Effectiness (Eta) 0.8932 Denity (lbmVft) 0.0638 61.9678 Sensible Heat Transfkrred (BTU'hr) 24,852 Cp (BTU/Ibm-°F) 02402 0.9989 Latent Heat Transferred (BTU/fr) 253,893 K (BTU/hr-ft-.F) 0.0157 03636 Heat to Condensate (BTU/br) 18,300 Relative Humidity In 100.00 Relative Humidify Out (%) 100.00 "Reynolds Number Outside Rxnge of Equation.A~ppliability 040Air bais Velocity (LmIm~rfl, Tube Mlid Velocity (ftsec), Air Density a Inlet T, Otber Propaems a AvwWa T

ATTACHMENT 2 Calculation No. MD0099920060011 I Rev: 0 1 Plant: BFN Unit 0 [ Page: 7 of 7

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v t e Letter Sequence Other
TAC:MC3743, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed) TAC:MC3744, (Approved, Closed) TAC:MC3812, Revise Containment Requirements During Handling Irradiated Fuel and Core Alterations (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance Supplement, Supplement, Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 19 September 2006 29 December 2004 30 December 2004 6 January 2005 3 October 2005 3 October 2005 22 December 2005 22 December 2005 19 January 2006 7 March 2006 25 May 2006 2 June 2006 26 June 2006 26 June 2006 19 July 2006 19 July 2006 8 August 2006 10 August 2006 7 August 2006 10 August 2006 1 September 2006 6 September 2006 1 September 2006 15 September 2006 21 September 2006 27 September 2006 20 December 2006 17 November 2006 17 November 2006 26 January 2007 Answers 28 February 2006 28 February 2006 23 March 2006 23 March 2006 31 March 2006 19 October 2006 Results Approval, Approval, Approval Other: ML041980222, ML042370100, ML050590036, ML051150191, ML051160036, ML051320148, ML051430036, ML051570381, ML051660602, ML052290397, ML060530185, ML060670304, ML060680586, ML060680590, ML060680596, ML060680599, ML060720253, ML060720272, ML060720273, ML060720281, ML060720293, ML060720295, ML060720298, ML060720303, ML060720354, ML060880464, ML060880469, ML061040217, ML061660002, ML061770163, ML061840027, ML061910705, ML062050056, ML062090482, ML062090555, ML062120411, ML062130163, ML062130343, ML062200277, ML062210102, ML062220647, ML062270240, ML062360160, ML062400472, ML062510022, ML062510371, ML062510374, ML062510382, ML062510385, ML062620064... further results
MONTHYEAR2005-02-28 [Table View]

ML062510382

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