ML062230063
| ML062230063 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/04/2006 |
| From: | Eberly W Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TVA-BFN-TS-418, TVA-BFN-TS-431 MDQ099920060011, Rev 0 | |
| Download: ML062230063 (54) | |
Text
TVAN CALCULATION COVERSHEET/CCRIS UPDATE Page 1 REV 0 EDMS/RIMS NO. EDMS TYPE: EDMS ACCESSION NO INIA for REV, 0)
INA I calculations(nuclear)
Calc
Title:
TRANSIENT NPSWCONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS CLC ID n 2M NUMBER CUR REV DMUEW CURRENT CN NUC REVISION APPLICABILITY NEW CN NUC BFN MEB MDQ099920060011 SeEntire calg 0 Selected Pages E3
,.i,,No CCRIS Changes [3 ACTION NEW I DELETE [I SUPERSEDE 0 CCRIS UPDATE ONLY [0 (For calc revision, CCRIS REVISION r- RENAM [3 DUPLICATE 0 (Verifier Approval Signatures Not been reviewed and no E Required) CCRIS changes required) 001 002 003 064 074 075 DCN,EDCN/A APPLICABLE DESIGN DOCUMENT(S) CLASSIFICATION N/A LSAFET UNVERIFIED SPECIAL REQUIREMENTS DESIGN OUTPU SAR/TS and/or ISFSI RUA=o- RELATED? Of yes, ASSUMPTIQN AND/OR UMITING CONQnN? ATTACHMENT2 SAR/CoC AFFECTED R= Yes) Yes 0 No0 Yes0El No 0 Yes'0 No 0
. Yes NNorII Yes 0 No 10 PREPARER ID PREPARER PHONE NO PREPARING ORG (BRANCH) VERIFICATIO NEW METHOD OF ANALYSIS William A. Eberly 423-751-8222 MNE MIiiQ 0 Yes Design Review [] No 0
PREP RER SIGNATURE " DATE CHECKER SI3gNA *E DATE
_________I__ , Eý4 L8/-o VERIFIER SIGNATURE V p) 0 10 DATE APPVAL S1GNWTURE DATE
.. U& ,- /I- ,1.
0 - "_ W_,/_,
STATEMENT OF PROBLEM/ABSTRACT
/
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 InTable 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to Isolate all drywell coolers (see UNVERIFIED ASSUMPTION, Appendix R Assumption 6 on page 18).
MICROFICHE/EFICHE Yes 0 No I FICHE NUMBER(S, LOAD
- INTO EDMS AND DESTROY
[ LOAD INTO EDMS AND RETURN CALCULATION TO CALCULATION UBRARY. ADDRESS: SAB 1A-BFN 0 LOAD INTO EDMS AND RETURN CALCULATION TO:
TVA 40632 [07-20051 Page I of 2 NEDP-2-1 [07-M20061
TVAN CALCULATION COVERSHEETICCRIS UPDATE P'age 2 CALC ID TYPE ORG PLANT BRANCH NI IMRFR I I=V NUMBE )age ICN NUC BFN MEB MDQ099920060011I 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 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 (AIC/D) CODE TYPE PLANT BRANCH NUMBER REV A P CN BFN MEB MDQ0999970046 R9 A P CN BFN MEB MDQ0023980143 R2 A P CN BFN MEB MD00064920353 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 CCRIS ONLY UPDATES:
Following are required only when making keyword/cross reference CCRIS updates and page I of form NEDP-2-1 is not included:
PREPARER SIGNATURE DATE CHECKER SIGNATURE DATE PREPARER PHONE NO. EDMS ACCESSION NO.
TVA 40532 [07-2005] Page v
2 of 2 NEDP-2-1 [07-08-20051
Page 3 TVAN CALCULATION RECORD OF REVISION CALCULATION IDENTIFIER 'MO0099920060011 Title TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Revision " , DESCRIPTION OF REVISION
_-No.
0 Initial Issue Total Number of Pages =64 (Including attachments)
The SAR and ISFSI SAR haVe been reviewed by 0,.)- L1 6 ('-"
and this revision of the calculation does not affect SAR sections 6.1.6.2.6.3. 6.4.6.5. 14.5 and j4.6 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.
Pageloti NEDP4-2 (12.04-2000]
TVA WA [1 2.2000]
40709 112-20001 Page I of I ,NEDPý12-211i2-04-20001 1
Page 4 TVAN CALCULATION TABLE OF CONTENTS Calculation Identifier: MDQ099920060011 Revision: o TABLE OF CONTENTS SECTION TITLE PAGE Coversheet ........................................................................................................ I 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 Requirem ents/Lim iting Conditions ................................................................ 9 6.0 Com putations and Analysis ............................................................................. 10 7.0 Supporting Graphics ....................................................................................... 22 8.0 Sum mary of Results ........................................................................................ 34 9.0 Conclusions ...................................................................................................... 34 Appendices A RHR Heat Exchanger K-Factor Evaluation (4 pages) ....................................
B Recirculation Pump Motor Heat Load (4 pages) ...........................................
C Excel Spreadsheet Calculations (3 pages) .................................................
Attachments 1 Sulzer Pumps Required NPSH Charts (2 pages) ............................................
2 Dryw ell Cooler D ata (7 pages) ........................................................................
Total Pages 54 TVA 40710 [12-20001 Page 1 of I NEDP-2-3 [12-04-2000]
Paae 5 WAN CALCULATION VERIFICATION FORM Calculation Identifier Revision 0 MDQ099920060011 Method of verification used: I
- 1. Deslgn Revwew': .
- 2. Alternate Calculation ' Verifier J arvs/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 NEPD-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 (07-09-2001J 40533 [07-20011 WA TVA 40533107-20011 Page 1 Page of 1 I of I NEOP-2-4107-09-20011
Page 6 TVAN COMPUTER INPUT FILE STORAGE INFORMATION SHEET Document MDQ099920060011 Rev. 0 Plant: BFN
Subject:
TRANSIENT NPSHICONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Electronic storage of the input files for this calculation is not required. Comments:
0 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.)
RHR/CS TRANSIENT NPSH EVALUATION I oorurentutJwuncI 0 Microfiche/eFiche TVA 40535 [12-2000] Page 1 of I NEDP-2-6 [12-04-20001
Calculation No. MDQ099920060011 Rev: 0 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 9 2.2 GE-ER1-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 1- 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-P160-0010 (VTD-P160-0030, 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: 0 Plant: BFN Unit 0 Page: 8
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 2.14 EPU FTR T0400 R1, Containment System Response 2.15 Browns Ferry EOI-I, 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 T061 1 RO, Appendix R Fire Protection 2.18 EPU FTR T0903 RO, Station Blackout 3.0 Design Input Data:
3.1 Pump Flow Rates - Maximum flow rates per pump are determined from Ref2.1 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 = 7200 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: 0 1 Plant: BFN Unit 0 Page: 9
Subject:
TRANSIENT NPSHICONTAINMENT 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 HPCI!RCIC 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: 0 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, psia p = the density of the water at the respective pool temperature, lbm/ft3 Hf = the suction piping and strainer frictional head loss at the respective flow rate, ft 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 7200 gpm and the following required NPSH values are applied:
RHR Operating Flow Rate Time NPSHr gpm hours ft 7200 0-8 22.4 7200 8-24 24 7200 24-72 31.3 These parameters are input into a Microsoft V 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,
Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 Page: 11
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 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
- 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:
S EPURAI_6_LOCA.xls S EPURAI_6_ATWS.xls 0 EPU RAI 6 APPR.xls 0 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.
Calculation No. MDQ099920060011 Rev: 0 Plant: BFN Unit 0 Page: 12
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
- 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 121,500 fW3
- 4. Initial Suppression Pool volume corresponding to minimum suppression pool level 159,000 fW3
- 5. Initial Drywell Volume 129,300 fW3
- 6. Initial Wetwell Airspace Volume
- 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 950 F
- 12. Initial Suppression Pool Temperature 950 F
- 13. Initial Wetwell Relative Humidity 100%
- 14. Ultimate Heat Sink/RHR Service Water 95 0 F Temperature
- 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 12%/day
Calculation No. MDQ099920060011 Rev: 0 1 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.
I I- - - --- -- I LCalculation No. MDQ099920060011 I Rev: 0 I Plant: BFN Unit 0 I Page: 14 -2
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 32TF or 95 0 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: 0i 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
- 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 fts
- 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 950 F
- 12. Initial Wetwell Relative Humidity 100%
- 13. Initial Suppression Pool Temperature 95 0 F I
- 14. Ultimate Heat Sink/RHR Service Water 920 F Temperature ,
- 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
Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 Page: 16
Subject:
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-l (RC/L-4)
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: 0 1 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 1 postulates the following:
" No spurious operation of plant equipment.
" Depressurization begins at 25 minutes using three main steam relief valves (MSRVs).
" 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> GE re-analyzed this event with their approved SHEX containment code utilizing the following inputs and assumptions:
_______ Paaie ~Valuew
- 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 ft
- 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 950 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
- 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then isolated
- 19. Heat Loads Modeled Yes
Calculation No. MDQ099920060011 Rev: 0 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
- 6,000 gpm assumed for minimum heat removal (Ref. Attachment 2)
- 7,200 gpm assumed for maximum required NPSH
- Ten Drywell Coolers continue operation until isolated by operator action at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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-*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 ft3 (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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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: 0 Plant: BFN Unit 0 Page: 19
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 6.2.4 Station Blackout (SBO)
The Station Blackout event sequence defined 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 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 ft3 129,300 Wt 3
- 6. Initial Wetwell Airspace Volume
- 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 Initial Wetwell Relative Humidity 100%
- 12. Initial Suppression Pool Temperature 95 0 F
- 13. Ultimate Heat Sink/RHR Service Water 950 F and 320F Temperature
- 16. RHR Mode of Operation Containment Spray Cooling mode at 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- 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. MDQ09992006001o Rev: 0 Plant: BFN Unit 0 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
" 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Justification - The analysis demonstrates that the EOI 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: 0 FPlant: BFN Unit 0 TPage: 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 Cs 3125 35.1 24.5 10.6 12.6 4.5 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> SPRAYS, 95F RHRSW RHR 6500 39.8 23 16.8 13.4 7.1 0 ATWS ALL DW COOLERS RHR 6500 24.3 21.5 2.8 16.3 1.2 1.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 <br />0.0197 hours <br />1.173942e-4 weeks <br />2.70155e-5 months <br /> APP R DW COOLERS FOR 2HRS RHR 7200 25.7 22.4 3.3 23.0 1.4 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> SBO SPRAYS, 32F RHRSW RHR 6500 27.6 21.5 6.1 15.6 2.5 0.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SBO SPRAYS, 95F RHRSW RHR 6500 32.2 21.5 10.7 15.8 4.5 1.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
Calculation No. MDQ099920060011 Rev: 0 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: 0 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 160 22 150 20 140 18 130- 1621 0 11 11 11 11, 1, 1
- 10 0 100 200 300 400 500 600 Time (seconds)
Suppression Pool Temperature -.- Wetwell Pressure
- - - Atmospheric Pressure X--RHR Pump Broken Loop Containment Pressure Required
-- RHR Pump LPCI Loop Containment Pressure Required --9--CS Pump Containment Pressure Required Figure 7.3 ST LOCA CS PUMP 4125 GPM
- NPIa
________ACTUAL
- ~ NPSHa NO COP
-NPI 0 100 200 300 400 500 600 700 TIME, SEC
Calculation No. MDQ099920060011 Rev: 0 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 80 - --
70 -
60
- NPSHa 501 ACTUAL Z
TIE NPSHC
- -NO COP 4011 NPSWr ftwom 301-30 0 100 200 300 400 500 600 700 TIME, SEC Figure 7.5 ST LOCA RHR 11500 GPM 90 70N 60
- NPSH~a 50 ___ EACTUAL
-h--NPSHa NO COP z40 -NPS~r 0 100 200 300 400 500 500 700 TIME, SEC
Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 Page: 25
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.6 LT LOCA 95F SPRAYS 200 190 180 170 I
1160 16 1 IL I150 I.
140 130 0 4 8 12 I6 20 24 Time (hours)
- Suppression Pool Temperature F r Wetwell Pressure
- - - Atmospheric Pressure X-RHR Pump Containment Pressure Required
- CS Pump Containment Pressure Required Figure 7.7 LT LOCA 32F SPRAYS 200 40 19D 35 180 30 170 -25 S 160 -20i 150 .15 140 - 10 130 5 120 0 0 1 2 3 4 5 6 7 8 9 TIME, HOURS Suppression Pool Temperature --- Containment Pressure
- Atmospheric Pressure KudRHR Pump Containment Pressure Required
ý-4--CS PureD Containment Pressure Reouired
Calculation No. MDQ099920060011 Rev: 0 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 a- NPSI~a No COP Z _NPSHr 40
- 30 - 9
-24.5-10 0
0 4 8 12 16 20 24 TIME, HOURS Figure 7.9 LT LOCA CS 3125 GPM, 32F SPRAYS 100 90 80 70 60 *NPSHa ACTUAL z50 -a- NPSHa NO COP z -NPSHr 30 - -
,- - - - -24.5 - ,
20 10o_
0 1 2 3 4 5 6 7 8 9 TIME, HOURS
Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 Page: 27
Subject:
TRANSIENT NPSHICONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.10 LT LOCA RHR 6500 GPM, 95F SPRAYS 100 80 70 60
- NPSHa ACTUAL
_50_ &-- NPSHa NO COP z ,mw NP S Hr 203-20 ____
10 i 0 4 8 12 16 20 24 lIME, HOURS Figure 7.11 LT LOCA RHR 6500 GPM, 32F SPRAYS 100 ____
90 70 0 NPSHa t *ACTUAL
- e50 _______ ANPSHs No COP
-NPSHr 40 ____
30 __
2021.
0 1 2 3 4 5 6 7 8 9 TIME, HOURS
I Calculation No. MDQ099920060011 Rev: 0 Plant: BFN Unit 0 Page: 28
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.12 ATWS 10 DW COOLERS, BALANCED PERFORMANCE 250 50 SP Tamp C 150 DWTmp 50 0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5 6 TIME, HOURS
- Suppression Pool Temperature --- DWTEMP F
- Wetwell Pressure Atmospheric Pressure
-(--RHR Pumo Containment Pressure Reauired - DW PRESS PSIA Figure 7.13 ATWS 6500 GPM, 10 DW COOLERS AS2RAIATWSDWC2
~ E NPSHa ACTUAL NPSHa NO OOP
-NPS:Hrr 0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5 5.5 6 TIME, HOURS
Calculation No. MDQ09992006001 Rev: 0 Plant: BFN Unit 0 Page: 29
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS Figure 7.14 APP R 10 DW COOLERS, 100% RH Coolers Off After 2 Hr 30 26 I10 181 14
- 10 a t6 24 32 40 48 56 64 72 Time (hours) 1- Suppression Pool Temperature --- Wetwell Pressure - - - Atmospheric Pressure --- RHR Pump Containment Pressure Required[
Figure 7.15 APP R 7200 GPM, 10 DW COOLERS Coolers Off After 2 Hrs
- NPSHa ACTUAL
- NPSHa NO COP
_NPSFWt 0 4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 64 TIME, HOURS
Calculation No. MDQ099920060011 Rev: 0 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 M I w
190 20 180 -18 1 14 0 4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 64 TIME, HOURS
- Suppression Pool Temperature --- Containment Pressure Atmospheric Pressure w RHR Pump Containment Pressure Required Figure7.17 APP R 7200 GPM, 10 DW COOLERS 50 40 0
- NPSHa Iz 2.11JACTUAL
£20 -. 1110 NPSHa z -NPSHr 10-01 0 10 20 30 40 50 60 TIME, HOURS
Calculation No. MDQ099920060011 Rev: 0 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 240* 30 230 .28 220 .26 210 *24 190 -209 170 *16 -
150 -12 140 10 0 8 16 24 32 40 48 56 64 72 W0 88 96 104 112 120 128 136 144 TIME,HOURS
- Suppression Pool Temperature -. -Containment Pressure SAtmospheric Pressure -- XRHR PumnpContainnmerd Pres,,sure Reqiuiredi Figure7.19 APP R 7200 GPM, NO DW COOLERS ACTU:AL z -NPISHr NPSHa
-*-NPSHa F *- '0 NOCOP 0 8 16 24 32 40 48 56 64 72 80 88 96 104 112 120 128 136 144 l1ME. HOURS
-Calculation No. MD0099920060011 Rev: 0 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 50 16
.20 0 4 a Time (hours)
- Suppression Pool Temperture --- Wetwel Pressure - - - AtmosDheric Pressure -N-- RHR PumD Containment Pressure Reouired Figure7.21 SBO 32F SPRAY AT 4 HOURS 50 20 10 0 2 4 6 Time (hours)
I- Suppression Pool Temperature -f-- Wetwell Pressure - - - Atmospheric Pressure --- X- RHR Pump Containment Pressure Required I
Calculation No. MDQ099920060011 Rev: 0 1 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
- NPSHa 150 E ACTUAL
-&- NPSHa
_NOCOP
-NPSHr S100 -SPTEMP DEGF 0 4 8 12 16 20 24 TIME, HOURS Figure7.23 SBO 6500 GPM, 32F SPRAYS AT 4 HOURS
- NPSHa ACTUAL
--A- NPSHa NO COP
-NPSHr SP TEMP DEG F TWE, HOURS I
Calculation No. MDQ099920060011 Rev: 0 Plant: BFN Unit 0 Page: 34
Subject:
TRANSIENT NPSHICONTAINMENT 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 (3.3 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: 0 1 Plant: BFN Unit 0 Page: Al 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 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, 3rd 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 C1 320503-6924, Rev. 2 4.2 Suppression Pool Temperature of 187.4°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: 0 1 Plant: BFN Unit 0 1 Page: A2 of 4
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS e=2* +CR + [(I+ C'R2 Y1 m[].[1+]. (Eqn 1)
I 1-e NU(C~-jJ where:
9 = 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-0 F NTU = number of transfer units
= UA/Cmin U = overall heat transfer coefficient, Btu/hr-ft 2 -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 0F.
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 I Calculation No. MDQ099920060011 I Rev: 0 1Plant: BFN Unit 0 1 Page: A3 of 41
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS f !ef _:::::(:* 1 !iiiiL K&Q as function of RHR Temp. at fixed TP% and RHRSW conditions
-t i IIFI
. .l ... .. .. .
. I iiiii i 71i!!!i:!ffiiZ
....... fluid roe ioulig "Fes- 0.0005 Tube sw 0.0023 I
I subf@a6 0.0160W 0.016043 metal rae 0.000473 Flwgp 10000 4500 total mes 0.004645
.38.1 Ib.e 625.010....
_qi __ U ow.fiI 215.285253
-- I6500 GPM,-
rI.....O4P
-~ L~n A C I t
... .t. r .....
inlr Ilbm/sec ý! )F ..................
....... 1/ho Rtotal_ U EPS K atotal Btu/hr RHRSW TP Aleff q____ ~4~h Tot.w Ibmlsec 40262891.4 otal, gpm Stufhr I 121893.7808 95 553.1059 893.78Wi 0.000942 0.0106466i 23682 4.572807 6107.34...
- 20131445.71 113.74341 105.1103 130j 891.4327( 95 4000 55.1059 0.000667 0.404122 553.1059 891.43271 O.(942 0.004882 223.5996 56347108.6 800C
( .
6107.341 28173554.31 121.22091 109.1492 56A059 0.000667 204.851S ........ -- - - 4.v' i i . .. -.. -..... ..
1407 88.981.. . 9 553.1059 888.90811 0.000942 0.004882 0.4041 223.5098 4.572807
- tt.U *O00. f 1I 24.851 6107/ . tlflI 4000 553.1059 0.000667 0.00488211111111-11...... 0.4632 223.4136 88471794.3 800 '.34 44235897.11 136.13461 117.2159 553.1059 0.004882 160 88.683 180~ 877.2 294 95 9
4000 5 01531059 _ K]
883.36831 0.000942 877.22941 0.000942
- 0. ........ 82_
6 . 0.0.....8._
800C 6107.341 52254815.8 143.56831 121.2431 0.000667
.531059 0.004882 204.851S 136530069 *"f *.=____ -- .( ........................
187.31 8 74 8 7 800C 4.572810 68265034.41 1SU.3831 12g.2837 0.403178 22,3' 6107.34 741787201 163.84631 132.2536 11,016..000-66v 8015 1 0 00 0942 00048821
.8.. 204 [ ..
.. 22.8 .2.4.5 .. 220473396. 800x 6304 110236698 191.4233 147.3309
APPENDIX A Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 1 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.
SI iI~
II I I I
APPENDIX B Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 1 Page: BI 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 th Edition.
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 RequlrementslLimlting 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 Efficiencyloss = (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: 0 1 Plant: BFN Unit 0 1 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 B
APPENDIX Rev: 0 1 Plant: BFN Unit 0 I Calculation No. MDQ099920060011 1 Page: B3 of 4
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS GE Industrial Systems
- -GEMotors - DATA SHEET - custom aooo R SQUIRREL CAGE MOTOR CUSTOMER 'IVA BROWNS FERRY/ GE NUCLEAR CUSTOMER ORDER 00001704 013431431005962 GE MODEL 291R610 DESIGN KC899R240B SO : 2880034/2880035 RI :132-14187/02/03 OTY :1l1 SERIAL : 2880000421288=0043 POWER 8657 HP TYPE :KV POLES : 04 FRAME : 8800 VOLTAGE : 3965 V ENCLOSURE / COOLING : ODP FREQUENCY : 56.6 Hz SERVICE FACTOR :1.0 @ CLASS B RISE PHASES : 03 INSULATION CLASS F (POLYSEAL)
TEMPERATURE RISE :73=C /TO@ SF1.0 TEMPERATURE CLASS :B DRIVEN LOAD : PUMP MAX. ALTITUDE : 3300 ft LOAD WK2 REF.TO MOTOR SHAFT :12872 LbftI AMB. TEMP. (MINIMAX) -18/57 C Calculated Performanoe RATED RPM :1682 NEMA STARTING CODE :E RATED CURRENT :10566A LOCKED ROTOR CURRENT : 570%
RATED TORQUE : 26960 LbR LOCKED ROTOR TORQUE :60%
RATED KVA : 7383 PULL UP TORQUE : 60%
STATOR CONNECTION :Y BREAKDOWN TORQUE :175%
MIN. STG .VOLTAGE : 90% V COUPLING TYPE : FIXED (')
TIME RATING : CONT ARRANGEMENT : Vt - SOUD SHAFT ROTATION : CCW FROM TOP TOTAL WEIGHT (calckuated) : 40000 Lb ROTOR WK2 (calculated) :15700 Lbf2 MAX. BRG.VIBFL pk] : .12 lrnSec BEARING TYPE :SLEEVE (M)
BRO WBRIC(UPPER WER) : OIL/OIL END PLAY : 0.01 In STATOR RESIST. @ 25C : 0.0139 Ohms L-L LOCKED ROTOR TIME (100% V)
COLD: 20s XIR RATIO : 38.700 (NEMAMG1-20.43) HOT: 15s OPEN CIRC. TIME CONSTANT : 2.6680 s NUMBER OF STARTS OUTLINE NUMBER : M88D100134 COLD :2 INSTRUCTION BOOK : LATER HOT: 1 STATOR/ROTOR (SLOTS) :96/110 NOTES ,
VIBRATION UMITS BASED ON MOTOR RUNNING UNCOUPLED AND WITH BEARING TEMPERATURE STABIUZED IN STIFF BASE.
(A)PROVIDED BY CUSTOMER.
(M) UP THRUST RG - JV I5" M DOWN THRUST BRG- JV 15 1I2 (M)UPPER SLEEVE GUIDE BRG -8' (TAPERED LAND)
M")LOWER SLEEVE GUIDE RG SERVICE FACTOR @ CLASS F RISE (LATER)
SH 1 OF2 PREPARED BY : OSVALDO AK]RA APPROVED I DS2880034
APPENDIX B I Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 1 Page: B4 of 4
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS GE Industrlal Systems GE Motors - DATA SHEET- custom aoo (MT SQUIRREL CAGE MOTOR MODEL: 291R610 SO: 2880034/2880035 RI: 132-1-6167102/03 Calculated Performance No Load i 159 100 0.91 96.1 1066 75 0.91 9610 801 so 0.90 95.4 543 ACCESSORIES TESTS 6 STATOR THERMOCOUPLE COPPER CONSTANTAN-T AIR GAP MEASUREMENTS 12 HEATER 3600W - 3 PH DC HIGH POTENTIAL TEST I VIBRATION DETECTOR - R. SHAW # 68-A7 HEAT RUN STATOR AND BEARINGS (DUAL FREQ) AT REDUCED LOAD 4 SRG THERMOCOUPLE-COPPER CONST-DOUBLE'T HIGH POTENTIAL TEST INSULATION RESISTANCE TO GRD NO LOAD TEST NOISE POLARIZATION INDEX (BEFORE VPi 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 - I066 A - 1787 rpm - 60 Hz PHASE SURGE TEST (BEFORE VPI; FINAL)
AC HIPOT (BEFORE VPI AND FINAL ASSY; FINAL)
STATOR THERMOCOUPLE LOCATION SPRAY TEST TC SLOT PHASE TC SLOT PHASE SHAFT VOLTAGE
- 1 #1 A #7 #25 A (SPARE) LOCKED ROTOR TEST AT REDUCED VOLTAGE
- 2 #9 C #8 #33 B (SPARE) ROTOR THERMAL STABILITY TEST (COLD AND HOT
- 3 #17. B #9 #41 C(SPARE) . VIBRATION MEASUREMENT)
- 4 #49 A BEARING INSULATION RESISTANCE TEST
- 5 #167 C SHAFT CRITICAL SPEED TEST (COAST DOWN N6 165 B SPEED I TORQUE AND SPEED tCURRENT REED FREQ TEST REVISIONS
[1 Aocosdng to customer comments.
[2] Accordlng to custom comments.
(31Accordlng to customer comments.
[41 According to customer comments.
(81AccordIng to customer comments.
[6] Accoiding to customer comments.
SH2 OF2 PREPARED BY OSVALDO AKIRA APPROVED : DS280034 08-30-2006e REV : 06
APPENDIX C Calculation No. MDQ099920060011 Rev: 0 1 Plant: BFN Unit 0 1 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:
- EPU RAI_6_ATWS.xls
" EPURAI_6_SBO.xls
APPENDIX C Calculation No. MDQ09920060011 Rev: 0 1 Plant: BFN Unit 0 1 Page: C2 of 3
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS I-9
. I"..II="I..
HCN.xm MA Ir F-ft Ilr-I old' &p1mme. Ap =fl!
O.1J HFOft am COMM.
Amum. I It "
Mpg*%
1 *0 =W Cft PmJ 43~
p176 z'slI a
I 3s I
-al
APPENDIX C Calculation No. MDQ099920060011 ICRev: 0 1 Plant: BFN Unit 0 1 Page: C3 of 3 APPENDIX
Subject:
TRANSIENT NPSH/CONTAINMENT PRESSURE EVALUATION OF RHR AND CORE SPRAY PUMPS 2 .1J K L M 0 P 0 - R 8 T U 4 __ _ __ _ _ _ _ _ _ F ¶ 7.3_ _ _ _ _ _ _
6 __mm____ 4 14.38 24ap~ 1
- - 4021 4 00:1 4?4P10150) p,10 Ei01 -!!T1:T152 NPS41a PVAP SP 14psl4 CREDIT HOIPS& CwtLPmats, Rgqd Coaftftms" o PSIA Paib,PSIA - -lbo ACTUAL I PSI mOcoCOPti 101
-WQ mans" Do61
___ ..fte v10I 4A _ _____.144 1 ___ 0 40b5-4 00.1 1 ______ 40100 ___ 14 lo-EPo-01041. _$1"10 12 ___ 11 - 1441 I __=00 1 45I =00 1 1 ______ 41 1 ____ 14Ai4P1-Q1.11L11 -011I-811 12___ 11 ____14.4 144 12 . 2 05
__~~
-521 51221A I55 1124012 N______ 144(1Q,01jn,2 JM__ .121 1 =____ 12 "0112412___
14 ____ 4114 ___ A 4.4 14 14 ___ 14 0 -S 21.5 ______ 144414____ 14.4-4PI44014W1&14 140t14 _ _
15 1 4A W__ .144% w150) - _ 0)-.104W"58S15- 5 21, _____ 401 ___ - 14,.4 Pl-15)l1 015 415 ______SI 106__ =0Wi 410 1 1A4 10 05-s11 - -5.M41 M210
______1841041 -___14-Pl"IOWL81) 18,18 aW_
=1 117)--
H__ 14.4 --- +00SWIi~7j7__ ____
is__ ___ 14A =14 1tet8.0 $."a1 0 WOMS818-215 =11-8___
-kill-als_ 141 (P10-01814L18 I"01841 ___
to ____ t9--- 14.4_ 14f+$s-J 0W-s 11"4211.6 1410-10 ____ 141 P1-Mi 14wit.
_____ 10410"16 20 ___= ___14.4 -144 20A ___ 505.(0-5220 S =50W 210 =N132.020 144
_________"2~ -__ 42"-20
-W-20 I 21___ 1I(12) ___ 14.4 1144 ý 1.0 __ 050os-522 %0 500521 4 50530-5221-M1.5 _____ 11__ 14. P 1-2 I 40 1-S21 _
23 ____413)__ 14A 14 2.a 3 5050- !4 2105 14223-= ___ 14_41P23,23fL.23 xS023.823 -
4 __24 4vk M___1A =144*f 24.0 4 40 42n_ 2105 ______ A24424 ___ 14.Ep24424 40244S24 _
-pll.(~~~ 1 0 (00Sl 14 _9H_
27_n _ P 4127) __ 14.4 =1 b4*(27.o) __ 5-27 45 55 .2-so =5512105 -1427427 ___ 14A JP27-027¶&27 02.7427 25 420"3 ___ 14.4 1 %Iq(42 - - = 00 JSCM64LI304121.5__
- ____ -14.4(00s1 31 32
-~"all11____
z___
4321 14A 14A4
=144 1te31.0) 3.
5050. 5050 5.131 405
=505 04.32 1 0 1-521 5 __________
0W50 3-8.2 21I.
441131-Q 2-032 11
.___ ~PSI-O31L31 4314S31 __
-N2____ ____ 14A P3-$2=032-22_ _
33 *_PIW.H33) __ _ 14A e(43 "1 _ 0{OS 08 4I 34 ____ - 413 Ar -144 41W34.0 _ _____
30
- 41*(30 HW 1_14A4 1__4A
=1
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4 $,$0G*
215 ____ =1H35-035____
14.4 4P354301-M3 4035-S30 _
-215 ______ 1 3043 ___ 14.1 IP103& 14U 40203"30 _
37 413 ___7 __114. .4 37.0 ___ =703 00$651$7S40 =7 -50 . 00-.74 21A ______=47-37 2 14-44P3747l
-___ -5037-S37 ___ ___
39 - 10___14.4 =144% p32.03 ___~o 05355- 421 _ ___=1430,039 ___ 14,4jP30430YLL0 40G30.830 __ _
40~~~~ 440 - ___ 144p(1 4 .0) __ 45+ 25______ .40____ 14 P4401.4 H41i 04.40___ __
_ -14 10 -"M+SS-J1- 4152 _____ 414 ___ 1.P101 4 0101___ ___
143 14.4___ .1"404 = 3&__ s1.1~444v144 215 ___
40 - - 444 14.4 14. 0 __=00 5-20 004 5-.4 2014000___=41~44044 004 __
ATTACHMENT 1 Calculation No. MDQ099920060011 I Rev: 0 Plant: BFN Unit 0 Page: 1 of 2
!SULZER Traa27-t - ow a.UI 41I iso i~ 71 Oporulng Hours V1i July 14- 2006
ATTACHMENT I Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 1 Page: 2 of 2 IJuly
!SULZER 11. 2006 SUZ RTransdnt 3wim Pwistm (USI hu II
-NPSHReltiew E12.5,1267 D.01 CA 1 10 100-, 1000 00 rD z
z.
Operating Hours 9 15 July 14. 2006
ATTACHMENT 2 Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 1 Page: 1 of 7 D*2G11 cC~fON2'1 AfR RBCCW LATENT 1Cccs 10 OCOILS 10 CLS foCOU FLOW. INLET OULET FLOW. RIBCON RCCW SENSH.E HT. CONODENATE. SEI HT,"LELATENT HT, TOTAL HT, CONDENSATE CARE ACFU T.-W3 T-DB RNIl GPM IN OUT KT,BTUIMIE 5rW3 LOAIR "TUfSEC BTUGEC BiLVEC LDWSc DE'4GW 102 q= 1446 '115 i C '27 2 102 129. 692 0 m % 1647987 :20r
- g1 12445 i it. 4 2274 10 12.3 s8666 D mCO lC c6z0 221 19=02 U446 113 43 '27 4 102 I2._4 661042 14318 14.76 16.4 -ZI *66 Z.4 1 1I2 5 '17.1
- 446 -c 2714 102 11.4 W0662 221840 235L92 1427 6W8 204 1.6 3 19t= 'A4 5 '311 2 74
-2 i10 122.47 25M94 12743*6 1.10 5; 3w 42 3m66 2 1!C c-- 144 263 12 1274 102 13C,1 l14gXC 21026M2 21676 31 384 6160 ý 6 1202 .3!Z7 'C6,1 SC 1774 w6 t:A,3 62016 72C29 74.%6 14:J6 20C i64 111 7 1IN= I2M7 1269 122 1274 A 9 121.6 37SW 163863 '742.9% 3132 4698 8079 4.8 RAI-&1 IMN 180 1152 40 IVA 13 110. 8036 254w 260 32 71 19w OUT7 RM-6.2 "am 1i 1185 45 1274 I 112.45 41011M 1S 20., ow 543 2230.
RAO4, lim 180 a216 50 127A la 114&16 562257 3 38,172 1534 139 2802 IMO
ATTACHMENT 2 Calculation No. MDQ09992006001 I Rev: 0 Plant: BFN Unit 0 Page: 2 of 7 v7-26-OOv1:1659 PROTO-HX 4.01 by Proto-Fower Corporatio (SNt*THX-1027) Pe 1 TVA Cacuation Rqxpt for BFN2CCL-070-740 - Dqywell Air Cooler 15G,F5RH, EPURM6 INIALcOND1rDN Cakulation Specifications Costa Inlet Tempeu Method Was Used Etrpolation Was to User Specified Conditions Design Fouling Facbrs Were Used Test Data Data Date Air Flow (acm)
Air DryBulb Temp In()
Air Dy Bulb Temp Out(MF)
ReAtive Humidity In (%)
Reative Humidity Out Wet Bulb Temp InF)
Wet Bulb Temp Out ('F)
Amuospheric Presur QDSia)
Tube Flow (gpym)
Tube Temp Ik ('F)
Tube Temp Out (TF)
Condesate Tempture ()
Extrapolation Data Tube Flow (gpm) 127.40 Air Flow (acfin) 19,000.00 Tube lnet Temp (-F) 100.00 Ai nlet Temp (-F) 150.00 Inlet Retive Humidity () 50.00 Inlet Wet Bulb Temp ('F 0.00 AtmoVhic PArue. (pOia) 15500
'*AkMmsVeiaciy (LbmIu*), TDdbe bmdVekociy (franc);Ak Dncaxat InlT ,OderPs enies atAvrge T
ATTACHMENT 2 Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 1 Page: 3 of 7 o7-26-200d 17:1t9 PROTO-HX 4.01 by Proto-Power Corporation (SMkTHX-102T) Pw 2 WA CalculationReport for BFN2CCL-070-740 - Drywell Air Cooler 15F, 50%RH, EPURAI 6DINT1ALCOND1TION Extrapolation Calculation Summary Air-Side Tube-Side Mass Flow (bni'r) 68,5034 63,353.58 Tube-Side hi (BTU/hrf*-rF) 0.00 Jnlet Temperature M 150.00 100.00 j Factor 0.0000 Outlet Temperature (7') 121-53 114.16 Air-Side ho (BTU/br-ff-F) 0.00 Inlet Specific Humidity Tube WallmResistace (hr---F/BTUr 000016250 Outlet Specific Humidity Overall Fouling (hr-12-'F1BTU) 0.00412059 U Overall (T hr-f-'F)
Effective Area (if) 2,046.63 LMTD 0.00 Total Heat Trmnsfenied (BTU/br) 922,338 Surface Effectiveness (Eta) 0.o0oo Senuble Heat Transfend (BTU/lr) 552,067 Latent Heat Transferred (BTU/br) 370,265 Heat to Condensate (BTUfhr) 26,889 Extrapolation Calculation for Row 1(Dry)
Air-Side Tube-Side 1
Mass Flow (ibmU ) 63,.50.34 63,353-59 Tube-Side hi (BTU b-'-°F) 1,801.20 Inlet Tempenature (MF) 150.00 111.80 j Factor 0.0103 Outlet Temperature (MF) 142.29 114.16 Air-Side ho (BTU/hr-f-oF) 15.46 Inlet Specific Humidty 0 08483g Tube Wall Resistance (br-Ife-F/BTIJ 0.00016250 Outlet Specific H~imdity 008483 Overall Fouling 0zr-ftF/BTU) 0.00412059 Average Temp ('F) 146.14 112.9785 Skin Tempemtue (CF) 116.29 114.9949 U OveraU (BTU/hr-fr-*F) 13.29 V) *** 5.047.79 6264I5 Effective Area (if) 341.11 Renola's Number 1.849- 42,497 LMTD 33.01 Pra;ndNumber 0.7253 3.9144 Total Heat Transfmed (BTU~Ir) 149,618 Bulk Vise Ma -thr) 0.0491 1.4407 Skin Visc Obm/*-r) 0.0000 1A125 Surface Effectiveness (Eta 0.9743 Density (ftm ) 0.0612 61.8172 Sensible Heat Transferred (BTU/hr) 149,618 Cp (BTU -bm'F) 01402 0.9988 Latent Heat Transfered (BTU/hr)
K (BlTJthr-eft-) 0.0163 0.3676 Heat to Condensate (BT/h)
Relative Humidity In (C.) 50.00 Relative Humidity Out (%/) 60-67
- R~ynod& )&-b- Owmi&d Iange afEqu ztmAffh-Wfl~iy
'**Air m-ssvelociyW (L nxi), Tage F) dve tyft&ýuc) AkDemsntyxtnkeT. OtherPnpeniesxmAvepT
ATTACHMENT 2 Calculation No. MDQ099920060011 I Rev: 0 1 Plant: BFN Unit 0 1 Page: 4 of 7 01.26-,26 17:-i&6 PROTO-HX 4.01 by Prato-FPwer Corporation (SN#PHX-1027) Pw 3 TVA Calculation Report for BFN2CCL,070-740 - Drywell Air Cooler iMF, 5MOA EPUIAI 6 IN*7IAL Ca ITION Extrapolation Calculation for Row 2(Dry)
Air-Side Tube-Side Mass Flow (Ibmolk) 68,85034 63,353-58 Tube-Side hi (BTU/hr-fl-t F) 1,779-92 Inlet Temperature (MF) 14229 109.79 j Factor 0.0103 Outlet TemperatUre ('F) 135.75 111.0 Air-Side ho (BTU/hr-ft.*F) 15.40 Inlet Specif Humidity 0.084938 Tube WallResistae (hr-fi-'F/BTU, 0.00016250 Outlet Specific Humidity 0.084&38 OverallFouling (hr-fl-'FIBTU) 0.00412058 Average Temp ("F) 139.02 110.7941 Skin Temperature ('F) 114.12 112.5236 U Overall (BTU/hr-W-OF) 13.24 v c *** 5.047.79 6.2613 Effective Area (i') 341.11 Number 1.m- 41,586 LMTD 28.09 Prandtl Number 0.7259 4.0087 Total Heat Tranferred (BTU~hr) 126,815 Bulk Visc (ibmt-hr) 0.0487 1.4723 Skin Visc (lbm/ft-hr) 0.0000 1.4472 Surface Effectiveness (Eta) 0.9744 Ds (lwr 0.0618 61.87 Sensible Heat Transfed (BTU/br)15 T/m-k"F) 01402 0_9988 Latent Heat Transferred (BTU/br)
K (BTUJhr-ft-'F) 0.0161 03668 Heat to Condensate (BTU/Ir)
Relative Hmduky () 60.67 Relative Himidity Out (%) 71.82
'q Ra&ua z *- m &Ru p OfEtptioAnra) .y Extrapolation Calculation for Row 3(Dxy)
Air-Side Tube-Side Mass Flow (bmir) 68,9"034 63,353-58 Tube-Side hi (BTU/h-1.fr-MF) 1,761.82 Inlet Temperature (MF) 135.75 108.09 j Factor 0.0102 Outlet Temperature (MF) 130.20 109.79 Air-Side ho (BTU/hr4-*wF) 15-35 Inlet Specifc Hmidity 0.04838 Tube Wall Resistane (hr f -OF/BTU, 0.00016250 Outlet Sped Hudty 0.0848 Overall Foling (hrf--v'F/BTIJ) 0.00412058 Average Temp (M) 132.97 108.9416 Skin Temperature ) 111.78 110.4243 U Overall (BTUbnr-W.OF) 13.19 Vdcitv *** 5.047.79 62587 Efkctm Are (fe) 341.11 11's Number 1.880"' 40,819 LMTD 23.92 Prannd Number 0.7264 4.0917 Total Heat Tanseed (BTU4ir) 107,615 Bulk Vise (lim/nfi-hr) 0.0483 1.4999 Skin Visc (lbn/ft-r) 0.0000 1.4777 Surface Effectiveness (Eta) 0-9745 Denity (bmf) 0.0624 61.8749 Sensible Heat Transferred (BTU/br) 107,615 Cp (BTUbmý:F) O.24O2 0.9985 Latent Heat Transferred (BTU/hr)
K J/by-ft-'F) 0.0160 0.3662 Heat to Cmdensate (BTU/br)
Relative Humidity In C%) 718.2 Relative Hfumidity Out ('/.) 83.16
" Ray4ds& N ut=& Kni afBqpiim Applcability Vlocty J~mliS9,I~e I
'~'AirMas dVelocay sec) Aff Density a aTOtherPwpezresatAveageT
-t
ATTACHMENT 2 Calculation No. MDQ099920060011 I Rev: 0 Plant: BFN Unit 0 Page: 5 of 7
- 7-26-,O 17:1639 PROTO-HX 4.01 by Froto-Power Corporation (SN#ITHX-1027) P] 4 TVA Calculation Repo for BFN2CCI070-740- D-ywell Air Cooler U1F, 50%RH, 33 RKI 6 IDITJALCMOnK Exrapolation Calculation for Row 4(Dry)
Air-Side Tube-Side Mass Flow obmnhr) 6 50.34 63,353.58 Tube-Side hi (BTU/br-fl'-'I) 1,74640 Inlet Temperature (MF) 130.20 106.65 j Factor 0.0102 Outlet Temperature MF) 125-49 108-09 Air-Side ho (BTU/hr-f-oF) 15-31 Inlet Specific Hmidity 0.084838 Tube Wall-Resistae (hr-f'-`F/BTUQ 0.00016250 Outlet Specific Humidity 0-084838 Overall Fouling (hr-ifi-F1BTU') 0.00412058 Average Temp ('F) 127.14 1073689 Skin Tem=erare ('F) 109.79 108.6395 U Overall (BhU -JP.Wfl-F) 13.15 Velocity 5.047-79 62565 Effective Am (Wf) 341-11 Reyiows Number 1.93** 40,171 LMTD 2038 Pant uber 0-7268 4.1643 Total Heat Transferred (BTU/hr) 91,416 Bulk Vise (Ibm, t-hr) 0.0480 1-5241 Skim Visc ( -inft-br) o.oooo 1-5045 Surfac Effectiveness (Eta) 0-9746 "De~y (Run/) 0.0629 61.896 Sensible Heat Transfemed (BTU/Hr) 91,416 M tUbm=.'F) 02402 0.9989 Latent Heat Transerred (BTU/hr)
K (BT ~u/r-ft-4 F) 0.0159 03656 Heat to Condensate (BTU/lr)
Relative Humidity In (' 9 3-16 Relative Humidity Out CYh) 94-42
- 4 s N]- Oauf Rsu gAoonp o oow n zl. for ry)iy Extrapolation Calculaton for Row 5MDzy)
Air-Side Tube-Side Mas Flow Obmi~) 6%850.34 63,353_U Tube-Side hi (BTU/br-flr-F) 1,736.14 Inlet Temiperature M'F 125.49 106.00 j Factor 0.0102 Outlet Temperaure (M 12339 106.65 Air-Side ho (BTU/hr-fl1-F) 1528 Inlet Specifi Thinndity 0.084838 Tube Wall Resistance (hr-Wft-F/BTU 0.00016250 Outlet Specific Humdity 0.084838 Overall Fouling (r-w--w iTU) 0.00412058 Average Temp (T') 124.44 106-3245 Skin Temperature (M) 108.47 107-4529 U Overall (BThfr-fWt.F) 13-12 5.047.79 6.2550 Effective Ame (ft) 171.64 39.743 LMTD 18.09 PrandU Number 0.7271 42137 Total Heat Transferred (BTUfar) 40,753 Bulk Vis (Rn/ft.Ihr) 0.0478 1.5405 Skin Vis (IbmM-hr) 0.O000 1.5228 Surfa*ce Ffectiveness (Eta) 0.9746 Density (An/) 0.0629 61_9111 Sensi&e Heat T-ansferred (BTUihr) 40,753 Cp (BTUftbm-"') 0.2402 0.9989 Lateat Heat Tran*sfered (BTUhr)
K TUhr-f--*F) 0.0158 0.3652 Heat to Condensate (BTU/br)
Relative Humidity LIn(. 94.42 Relative Hunidity Out C(1) 100.00 "R~nl&NAb~rumd 0=& p aiR utm AFplkabi~Iy
-Ak Mass vejodzy(J~mu-, Tube iutd Veocity W-tiec AirDmnstyazhxtbdtr Otherk~rupiu st Aver T
ATTACHMENT 2 I Calculation No. MDQ099920060011 I o0 Plant: BFN Unit 0 1 Page: 6 of 7 o0-200o0 17m:ms PROTO-ZX 4.01 by Prato-Power Corporation (SNAlHX-1027) pw s TVA Calculation Repmt for BFN27CCL-740 - Drywell Air Cooler OF, W0%RKBPURAI 6INITIALCONDnIO Extrapolation Calculation for Row 5(Wet)
Air-Side Tube-Side Mass Flow (Obm*r) 68,85034 63,353.58 Tube-Side hi (BTU/br-r-Ok) 1,730.22 Inlet Temperature M 12339 104-12 j Factor 0.0102 Outlet Tenqmerature (7F) 122-12 106.00 Air-Side ho (BTU/ar-f1-*F) 75.22 Inlet Specific Huaidity 0.084838 Tube Wall Resistance hrr -F/BTLU, 000016250 Outlet Specific Hmnidity 0.083331 Overall Fouling (hrmf-'F/BTU) 0.00412051 Average TemopC ) 123.10 105.0625 Skin Temperature ('F) 111.17 108.6458 U Overall (BMfiUr-fF-OF) 41.70 Veloctyv *** 5.047.79 6.2533 Effective Area ( 169.47 Reynlaos Number 1.905" 39,228 LMTD 12.02 Prxnl Number 0.-7272 42746 Total Heat Tnafderred (ETU*hr) 127,362 Bulk Visc (bmfti-hr) 0.0477 15608 Skin Visc (lbmlft-hr) 0.0000 1-5044 Surface Effectivees (Eta) 0.8902 fljo (l ) 0.0633 61.92S2 Sensile Heat Tmsfrred (BTU/hi) 1O,997 Bt = F) 02402 0.9989 Latent Heat Transferred (BTU/br) 116,371 K (BTU/hr-fl-OF) 0.0158 0.3647 Heat to Cmdensate (BTUI-r) 85W Relative Humidity In (%) 100.00 Relative Humidity Out (%) 100.00 Rqh ads WNwutO~u&sd Razg ofEq-= oAV~I*-Wnliy Extrapolation Calculation for Row 6(Wet)
Air-Side Tube-Side Mas Flow (bmn4r) 698950.34 63,353.58 Tube-Side hi (BTUI/hr- -OF) 1,702.67 Inlet Temperature C'F) 122.82 100.01 j Factor 0.0102 Outlet Temperature (F) 121.53 104.12 Air-Side ho (BTU/Tru'*r-IF) 72.77 Inlet Specific Humidity 0.083331 Tube Wall Resistance (hr f-'-/BTUr 0.00016250 Outlet Specific Humidity 0.080042 Overall Fouling (hr-W-*F/BTU) 0.00412058 Average Temp M 122.17 102.0691 Skin Temperature ('F) 109-55 106.0385 U Overall (B¶fhr-t.'F) 40.80 5.047-79 6-2493 Effective Area (W') 341.11 RyodsNumber 1.907* 3s,015 LMTD 20.03 Pnmdt Number 0.7273 4.4250 Total Heat Transferred (BTU/br) 278,758 Bula Vise (HuMitur) 0.0476 1.6106 Skin Visc (lbmlft-hr) 0.0000 1.5451 Surface Effectiveness (Eta) 0.8932 Densit (IbmWf) 0.0638 61.9678 Senmible Heat Trxnferred (BTU/hr) 24,852 Cp (BTU/lbm-0F) 01402 0.9989 Latent Heat Tranferred,(ETUEhr) 253,893 K (BT~f=-ft-*F) 0.0157 0.3636 Heat to Condensate (BTU&b) 1 ,300 Relative Humidity In C%) 100.00 Relative Humidity Out C1.) 100.00
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ATTACHMENT 2 Calculation No. MDQ099920060011 I Rev: 0 Plant: BFN Unit 0 Page: 7 of 7
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