ML18017A860
| ML18017A860 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/10/1998 |
| From: | Rhex Edwards, Lundy J CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML18017A859 | List: |
| References | |
| SF-0040, SF-0040-R00, NUDOCS 9909100159 | |
| Download: ML18017A860 (79) | |
Text
ENCLOSURE 2 to SERIAL: HNP-99-129 SHEARON HARRIS NUCLEARPOWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO NRC REQUEST FOR ADDITIONALINFORMATION REGARDING THE LICENSE AMENDMENTREQUEST TO INCREASE FUEL STORAGE CAPACITY Calculation SF-0040 Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis
@09<00<S9 eeOe03 PDR ADQCK 05000400 P
Title/A royal Sheet SYSTEM//
4065 CALC. TYPE Mechanical CAROLINAPOWER 8. LIGHTCOMPANY SF 0040 (CALCULATION8) ll FOR.
S ent Fuel Pools C and D Activation Pro'ect Thermal-H draulic Anal sis (TITLEINCLUDINGSTRUCTURE/SYSTEM/COMPONENT)
FOR SHEARON HARRIS NUCLEARPOWER PLANT X NUCLEARENGINEERING DEPARTMENT QUALITYCLASS XA Q B Q C Q D Q E REV NO.
RESPONSIBLE ENGINEER Pg DESIGN VERIFIEDBY APPROVED BY Q ENGINEERING REVIEWBY RESPONSIBLE SUPERVISOR DATE DATE DATE REASON FOR CHANGE REASON FOR CHANGE
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040
~e i"32 Rcv. 0 File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis List ofEffcctivc Pages PAGE PAGE PAGE I
ll Ill 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 A
Attachments B
C D
Fi G
H I
J K
L N
0 P
Q S
T U
V IV X
Y z
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SI'-0040 Pg iiol 32 Rcv0 File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table of Contents Section LIST OF EFFECTIVE PAGES TABLEOF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 ENGINEERING ANALYSISSOFTWARE 4.0 CALCULATION
5.0 CONCLUSION
S
~Pa e
32 Attacluncnts Subject Calculation SF-0040, Revision 0, PROTO-FLO'Model Modifications for the HNP Component Cooling Water System Rev 2 Calculation SF-0040, Revision 0, CCWS Alignment Summary Total Pages 77 D
Calculation SF-0040, Revision 0, Evaluation ofMinimumRHR Heat Exchanger CCW Flow Requirements for Design Basis Accident Conditions Calculation SF-0040, Revision 0, Evaluation ofMaxhnum RHR Heat Exchanger CCW Flow Requirements for Design Basis Accident Conditions Calculation SF-0040, Revision 0, Evaluation ofMinimum SFP Heat Exchanger CCW Flow Requirements for Various Operating Conditions Calculation SF-0040, Revision 0, Rcbalance CCW System Flow Distribution For LOCA: Sump Recirculation (RHR Only) Alignment Calculation SF-0040, Revision 0, Dcterminc MinimumCCW Heat Exchanger Service Water Flow During LOCA: Sump Recirculation (RHR Only) Alignment Calculation SF-0040, Revision 0, Rebalancc CCW System Flow Distribution for Minimum CCW Pump Developed Head Calculation SF-0040, Revision 0, Evaluation ofCCW System Normal System Alignment Hydraulic Performance Calculation SI'-0040, Revision 0, Evaluation ofCCW System Dual Train Hot Shutdown (350F) System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Single Train Hot Shutdown (350F) System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Refueling Core Shuffle System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Refueling Normal Full Core OIIload System Aligrunent Hydraulic Pcrformancc 17 34 34 14 19 37 35 40 35 33 39
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Attachments N
0 U
V W
Y AA BB CC DD Subject Calculation Sl'-0040, Revision 0, Evaluation ofCCW System Refueling Abnormal Full Core Offload System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System LOCA-Safety Injection Phase Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System LOCA-Containment Sump Recirculation (RHR Only) Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System LOCA-Containment Sump Recirculation (RHR and SFP) Alignment Hydraulic Performance Calculation SI'-0040, Revision 0, Evaluation ofCCW System Normal System Alignment Thermal Performance Calculation SI'-0040, Revision 0, Evaluation ofCCW System Dual Train Hot Shutdown (350F) System Alignment Thermal Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Single Train Hot Shutdown (350F) System Alignment Thermal Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Refueling Core Shuffle System Alignment Thermal Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Refueling Normal Full Core Offload System Alignment Thermal Pcrformancc Calculation SI'-0040, Revision 0, Evaluation ofCCW System Refueling Abnormal Full Core Offload System Alignment Thermal Pcrformancc Calculation Sl'-0040, Revision 0, Evaluation ofCCW System LOCA-Safety Injection Phase Alignment Thermal Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System LOCA-Containment Sump Recirculation (RHR Only) Aligtunent Thermal Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System LOCA-Containment Sump Recirculation (RHR and SFP) Alignment Thermal Performance Calculation SF-0040, Revision 0, Evaluation ofUHS Thermal Margins Calculation SF-0040, Revision 0, Evaluation ofShort Term Transient Fuel Pool Temperature Response During HNP Cooldown Operations Calculation SF-0040, Revision 0, Design Vcriflcation Records Calculation SF-0040, Revision 0, Evaluation ofCCW System Plant Startup Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation ofCCW System Plant Startup Alignment Thermal Performance Total Pages 41 18 25 32 33 30 30 31 32 33 18 27 4
68 28 36 33
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: Sl'-0040 Pg 1 or 32 Rcv0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 1.0 PURPOSE The purpose ofthis calculation is to document the thermal hydraulic capacity of the Component Cooling Water System (CCWS) to support the activation ofSpent Fuel Pools C and D at CP&L's Harris Nuclear Plant (HNP).
This calculation is only valid for Spent Fuel Pool C and D heat loads up to 1.0 MBTU/hrand does not consider the effect of potential increases in core thermal power due to the Steam Generator Replaccmcnt/Power Upratc Project.
2.0 REFERENCES
(1)
Harris Nuclear Plant Calculation CC-0039 Revision 0, Development of Component Cooling Water System PROTO-FLO Thermal-Hydraulic Model (2)
Harris Nuclear Plant Calculation SW-0088 Revision 0, Development of Emergency Service Water System PROTO-FLO Thermal-Hydraulic Model (3)
Harris Nuclear Plant Calculation HNP-M/MECH-1011 Revision 2, Pump Degradation Limits for ESW, CCW &ESCW, dated 5/10/97 (4)
Stone &Webster Feasibility Study for Pool Cooling and Clean-Up of Harris Nuclear Plant Spent Fuel Pools C &D, Revision 0, prcparcd 10/6/97 (5)
Preliminary Harris Nuclear Plant Drawing CAR 2166-G-412 Rcv 11, dated 10/6/97 (6)
Preliminary Harris Nuclear Plant Drawing CAR 2165-G-255 Rev 16, dated 4/4/97 (7)
Preliminary Harris Nuclear Plant Drawing CAR 2165-G-127 Rev 15, dated 10/4/97 (8)
Crane Tcclmical Paper 410, 1988 Crane Company (9)
Harris Nuclear Plant Calculation NSSS-38 Revision 2, RHR Heat Exchanger and Pump Cooler Cooling Water Outlet Temperatures, dated 4/30/97 (10)
Harris Nuclear Plant Engineering Service Request 9700536 Rev 0, Emergency Service Water System-FSAR Table 9.2.1-5 Supporting Documentation, dated 10/16/97 (11)
Harris Nuclear Plant Engineering Service Request 9600126 Rev 0, Spent Fuel Pool Cooling System, dated 3/5/97 (12)
Harris Nuclear Plant Final Safety Analysis Rcport Section 9.2.2 Component Cooling System Table 9.2.2-3 Amendment No. 35 (Superseded by RAF 2160)
(13)
Harris Nuclear Plant Design Basis Document, Component Cooling Water System, DBD-131 Revision 6, dated 6/19/97
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 Pg 2 or 32
~0 File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis (14)
Harris Nuclear Plant Calculation CC-0038 Revision 0, CCW Heat Exchanger Performance During Post-Accident Recirc Alignment, dated 4/21/97 (15)
Harris Nuclear Plant Calculation SW-0085 Revision 0, Ultimate Heat Sink Analysis, dated 1/6/96 (16)
Harris Nuclear Plant Calculation CC-0037 Revision 2, CCW Flow Rates for Various Valve Alignments, dated 4/8/97 (17)
Reactor Coolant Pumps, Technical Manual VM-MRF (18)
Harris Nuclear Plant Design Basis Document, Service Water System - Traveling Screens and Screen Wash System - Waste Processing Building Cooling Water System, DBD-128, Revision 6, dated 6/18/97 (19)
Harris Nuclear Plant Teclinical Specification Section 3/4.7.5 Ultimate Heat Sink, Tech Spec Interpretation 95-03 (20)
Harris Nuclear Plant Calculation SW-0078 Revision 4, ESW System Performance Evaluation, dated 6/11/96 (21)
Harris Nuclear Plant Calculation HNP-M/MECH-1008, Revised Containment Analysis for an Increase
- in the InitialTemperature from 120'F to 135'F Revision 1, dated 4/8/97 (22)
Harris Nuclear Plant Calculation CC-0020, Revision I, Component Cooling Water System Performance, dated 9/3/96 (23)
Meeting Minutes of 11/25/97 Meeting Bctwecn CP&Land Proto-Power Corporation (24)
Harris Nuclear Plant Engineering Service Request - Action Item, ESR 9500442 Revision 0 Ale, dated'8/11/97 (25)
Harris Nuclear Plant, Final Safety Analysis rcport Amendment no. 45 p. 5.4.7-10I, "Boration and Inventory Control" (26)
Harris Nuclear Plant Calculation HNP-F/NFSA-0026 Revision 0, Maximum Decay Heat Load for Spent Fuel Pools A, B &C Through the End ofYear 2001, dated 4/16/98 (27)
Not Used.
(28)
CP&L-Harris Nuclear Plant Letter 10003481-Model-00, Estimated Impact of Power Uprate, dated Novcmbcr 6, 1997 (29)
Harris Nuclear Plant Calculation SW-0080 Revision 5, ESW Flow Rcquircmcnts Based on Reservoir Level, dated 5/2/97
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CALCULATIONSHEET i'g 3 or 32 Fflc:
Rcv 0 Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis (30)
Harris Nuclear Plant Operating Procedure OP-145, Section 8.9 (31)
Harris Nuclear Plant Final Safety Analysis Rcport Table 9.2.1-7, Amendment 15 (32)
Westinghouse letter CQL-290, dated 6/5/79 (33)
Harris Nuclear Plant Engineering Service Request 9700272 Revision 0, dated 5/6/97 (34)
Harris Nuclear Plant Calculation 9-FHB-2 Revision 1, Fuel Handling BuildingAirConditioning System, dated 5/24/86 (35)
Harris Nuclear Plant Enginccring Scrvicc request 9700252 Revision 0, Evaluation ofEPT-174 Data, dated 4/7/97 3.0 ENGINEERING ANALYSISSOI'TWARE This calculation was performed using PROTO-FLO'3.04 and PROTO-IQP 3.02.
The default PROTO-FLO'database, CCW2.DBD (dated 10/14/98, Size 800KB) is included in Attacliment (A).
4.0 CALCULATION Rcfcrence (1) was used as a starting point for the analysis of thc CCWS system to determine therinal and hydraulic margins.
The default bcnclunarkcd PROTO-FLO'database, CCW.DBD, was modified to create a new PROTO-FLO'default database, CCW2.DBD, which incorporates tlic proposed CCWS tie-ins for the fuel pool C and D heat exchangcrs as well as other modifications defined in Table 1. Case aligiunents for:
Startup Operations (A CCWS Train Operating)
Normal Operations (A CCWS Train Operating)
Hot Shutdown at 350'F (A and B CCWS Trains Operating, Split),
Safe Shutdown at 350'F (A CCWS Train Operating, Single Failure),
Refueling: Core Shuffle (A CCWS Train Operating, Single Failure),
Refueling: Full Core Offload (A CCWS Train Operating, Single Failure),
Refueling: Abnorinal Full Core Offload (Aand B CCWS Trains Operating, Split),
LOCA: Safety Injection Phase (A CCWS Train Operating),
LOCA: Containmcnt Sump Recirculation with CCWS Noncsscntial Hcadcr Isolated [Recirc(a)]
(A CCWS Train Operating, Single Failure) and LOCA: Containment Sump Recirculation with Limited Fuel Pool Cooling [Rccirc(b)]
(A CCWS Train Operating, Single Failure).
werc dcvclopcd to capture all thc major CCWS systcin operating conditions.
All heat exchanger therinal models use design fouling factors rather than IST results to cnsurc that design basis conditions can be met even with extrcme fouling conditions.
CCW pump degradation to the 10% IST limit, Reference (3), was included for the flowmargin portion ofthis analysis.
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 rs 4 of 3g Rcv0 File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table I ModiTicd CCWS Pipe'Sections Pipe Section G4 85 41/53/60/G4 Node0001 Node0026 Fixed I/Fixcd2 105 121 Pump l Pump2 Pump3 314 300-319 900-905 27/28/29 SFP Hx D 33 20 43 Scrvicc BRS Supply BRSEC BRSEC LOCAlsolatc Prcssure In-linc Node Delctcd Nodes RIIR Pmp B Clr AHXlsol FP I/FP2 DummySFPCPump BRS Evap Cooler Degraded Pump 1 DcgradcdPump2 Degraded Pump3 TEMPI Proposed CCWS Tic-Ins to FP Hx C and D Fuel Pools A/B and C/D P IIsolate Fixed lteat Load DischXTic SuctXTic XSLD IIX Modilication Replaced MiscKof 1100 with MiscK~I8.11 from Reference (22)
Adjusted ICC-356 to 24.17% Open Adjusted ICC-353 to 0.75% Open Adjusted ICC-363 to 20.56% Open Added isolation valve to simulate COL direction to assume the BRS Skid is abandoned inplace.
Added isolation valve to simulate COLdirection to assume the BRS Skid is abandoned inplacc.
Added simulation valve for LOCA case alignments, References (12) and (13)
Changed to in-linc pressure node to climinatc bypass flowthrough thc Surge Tank which is not consistent with actual CCWS operation Eliminated Surge Tank nodes and lines to properly model CCWS and eliminate recirculating flow through thc Surge Tank Corrcctcd Heat Load Tag Added SFP Hx A Isolation Valve Added simulated I'uel pool cooling pumps Added simulated fuel pool cooling pump curves calibrated to 3750 gpm pcr Reference (II)
Deleted fixed heat load pcr Assumption 4.1.12 Added 10% TDIIDcgradcd CCW Pump Curve Added 10% TDH Degraded CCW Pump Curve Added 10% TDH Degraded CCW Pump Curve Added TEMP I Isolation Valve to Enhance Computational Stability Additions arc denoted by Altxx. Sec Attachment A Added simulation for tuel pools A/B and C/D to provide fuel pool ctluilibriumtemperature as a function offuel pool heat load.
Added Pumpl Isolation valves with Cv~l000000 to allow for Pump2 (B Train) Operation Changed SFP Hx D to a lixed heat load to improve computational cflicicncy at low CCWS flowrates and light FP C/D heat load.
Added gate valve with Cv 1000000 to simulate split CCW train ops, Rcferencc (30)
Added gate valve with Cv 1000000 to simulate split CGA train ops, Rcfercncc (30)
Added Simulation Isolation Valve with Cv~l00000 to isolate thc Excess Letdown Heat Exchanger Only
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Pg 5 oc32 Rcv 0 Project No.:
CALCULATIONSHEET File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 4.1 Bases and Assumptions 4.1.1 Case alignments which specify a single CCWS train operation assume the use ofthe "A"train as CCW Pump A delivers slightly less total developed head and therefore is the least hydraulically capable CCW pump.
4.1.2 All CCWS cooled heat exchangcrs usc design fouling factors.
This assumption is unconservative when analyzing the performance of individual heat exchangers but is conservative and realistic in terms of overall CCWS thermal performance as the CCW heat exchanger fouling factor significantly exceeds the other CCWS cooled heat exchangers and limits thc heat rejection capability of the CCWS. The tube plugging for the CCW heat exchanger is also assumed to be 0% as the design CCW heat exchanger tubesidc fouling factor of0.00176 hr-sqft-'F/BTU significantly (50.4 percent) exceeds the current worst case trended tubeside fouling factor, Reference (35), of0.00117 hr-sqft-'F/BTU thus the assumption ofadditional CCW heat exchanger degradation from tube failures would bc overly conscrvativc, given the excessive design fouling factor.
4.1.3 4.>.4 CVCS flow to the letdown heat exchanger is assumed to be at design Letdown flow conditions of 120 gpm pcr CPEcL direction, Reference (23).
Both RHR pumps and oil coolers are assumed to be operating and rejecting heat whenever the RHR system is activated for conservatism cxccpt for single CCW train failure cases which include Safe Shutdown (350'F),
Refuel-Core Shuffle, Refuel-Normal Full Core Offload and all LOCA cases.
4.1.5 The minimum ESWS flow to the CCW heat exchangers is 8500 gpm.
4.1.6 A maximum ESWS supply temperature to the CCW heat exchangcrs is assumed to be 95'F, Refercncc (13).
4.1.7 For the purposes ofthis analysis, Spent Fuel Pool heat exchangers A and D are in operation. It is assumed that the hydraulic resistance of CCWS piping to and from Spent Fuel Pool heat exchangcrs B and C are equivalent to Spent Fuel Pool heat exchanger A and D supply and return piping.
4.1.8 A maximum CCWS supply temperature of 105'F is assumed to be applicable during all operating modes except for Hot and Safe Shutdown Cases and LOCA: Containment Sump Recirculation Cases, Reference (13).
4.1.9 A maximum CCWS supply temperature of 120'F is assumed for all CCWS system lineups other than those identified in Assumption 4.1.8.
Reference (13) states that thc CCWS is designed for a maximum tcmpcraturc of 120'F (for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) which is based on the maximum permissible temperature to the reactor coolant pumps.
A review of the reactor coolant pump tcchnical manual, Reference (17), with thc cognizant plant engineer shows that there is no explicit time limitation on operation of the reactor coolant pumps with thermal barrier cooling in excess of 105'F so long as RCS temperature is less than 400'F.
Therefore, it is assumed that the statement of "approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />" is descriptive in that the CCWS supply temperature is only expected to be in excess of 105'F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during plant cooldown operations.
4.1.10 The reactor coolant pumps are assumed to be secured during Safe Shutdown, Refueling Operations and LOCA:Rccirc cases.
Thc CCWS flow is assumed to be supplied to the RCPs, for thc Safe Shutdown and
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CAROLINAPOWER &LIGHTCOMPANY Calculation ID: SF-0040 i's 6 <32 i~~0 Project No.:
CALCULATIONSHEET File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Refueling operations
- cases, even though they are not rejecting heat to the CCWS.
This assumption is conservative in terms ofCCWS flowmargins.
4.1.11 The heat load from the Gross Fuel Failure Detector (GFFD) and the Primary Sample Coolers are considered to be transient relative to the total steady state CCWS heat load and are assumed to be negligible for a steady state system thermal-hydraulic calculation pcr discussions with HNP System Engineering.
4.1.12 The CCWS alignments assume that thc Boron Rccovcry Skid is abandoned in place and does not require heat removal or CCWS flow, per CP&L System Engineering direction, Reference (23).
4.1.13 Analytical thermal uncertainty on overall CCWS heat transfer is assumed to be inherent and included in individual shell and tube heat cxchangcr models which werc devclopcd from manufacturer data sheets.
4.1.14 Letdown heat cxchangcr operation is NOT required during Safe Shutdown conditions as boration capacity is rcquircd to bc maintained by the Boric Acid Tank, the Boric Acid Transfer Pumps, the Refueling Water Storage Tank and the Centrifugal Charging Pumps, Rcferencc (25).
4.1.15 CCW trains 'A'nd 'B're split whenever both RHR heat exchangers are in service, Reference (30), with thc nonessential header assumed to be aligned to the 'A'CWtrain.
4.1.16 CCWS flow to the letdown heat exchanger is set to 610 gpm (575 gpm, Reference (12) + 6% hydraulic uncertainty, Reference (1)) for the purposes ofestablishing a hydraulic design basis for the CCW system.
4.1.17 It is assumed that this calculation is only valid for Spent Fuel Pool C and D heat loads less than 1.0 MBTU/1ir.
4.1.18 The thermal effect of the HNP Power Uprate project increased core thermal rating is not accounted for in this calculation.
4.1.19 Excess letdown heat exchanger process side parameters are only specified for the plant Startup case alignment when maximum letdown system capacity is required. Excess letdown heat exchanger CCWS flowis maintained for all alignments except for the LOCA:Recirc (RHR Only) and LOCA:Recirc (RHR and SFP) alignments during which the excess letdown heat exchanger is isolated by the Phase A containmcnt isolation signal.
U
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CAROLINAPOWER &LIGHTCOMPANY Calculation ID: SF-0040 Ps 7 of32 Rcv0 Project No.:
CALCULATIONSHEET File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 4.2 CCATS Alignments The baseline CCWS alignments were developed based on Reference (12) defined lineups with the exception of the excess letdown heat exchanger.
Thermal and hydraulic margins for the CCWS are not compared to the values in Reference (12). Rather, all margin comparisons are to either design data sheet'alues or to infcrrcd flow and heat load values from other design basis documents or calculated values provided herein. Allalignments assume the operation of one or two CCW trains, consistent with plant operating requirements.
For Safe Shutdown, single failure Refueling operations and LOCA case alignments, the CCW "A"cooling train is considcrcd to be in operation. Table 2 summarizes each operating CCWS lineup.
Table 2 Major CCAVS Alignments Normal Modo 1
@4 hrs (350F)
ILI)4 hrs (350F)
If3 Coro Normal Full Abnormal Full Shuftto Coro Ofaoad Coro Oftteod (Mode 6)
(Mode 6)
(Mode 6)
Safety Irt)ection Phaso Sump Recirc with Sump Redro Essential Header withUmited Only SFP Cooring mp RHR Hx 8 RHR Pmp A RHR HxA BRS: Orst Cir 8RS: Evap Ctr Vent Flow R
THx Seal Water Hx FPHxA FPHx8 RCP A RCP 8 SFP Hx C SFPHxo GFFD Sample Coolers Flow Only Flow 2 (sp4t)
Flow Onty Singlo Failure Flow Single Singlo Failure ofO'ailure of
'8'CW Train CCW Tain 2 (split)
GFFO and Sample Codes Isdated 8y S Signet
, FcHuro.
Conlalnment Isdated (RCPs, XSLO Hx, RCOT Hx Secured). Only RHR Loads I
O'CW Single Failure. All I4enessenthl Loads Isotatod Except forSFP Hxs Alloperating lineups use the benclunarkcd CCW pump curves for thc thermal margin analysis and the IST program 10 percent degraded pump curves for the flowmargin analysis.
CCW flow to thc cooled components for normal operations is consistent with the bcnchmarkcd values ofRcfcrcnce (1).
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 i'c 8 <32 R~0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis The thermal conditions applied in each CCWS alignment are the design values included in Reference (I) and summarized in Table 3, except where specifically noted.
The RHR heat exchanger flow for all cooldown conditions is based on maintaining the CCWS supply temperature at the design basis limitof 120'F at an RHR heat exchanger inlet tempcraturc consistent with the lineup up to a maximum RHR system flow rate of 4500 gpm, which is the RHR pump runout limit, Reference (28). The RHR heat exchanger inlet temperature is specified to be consistent with the corresponding Reactor Coolant System temperature for that condition.
The RHR heat exchanger conditions for post LOCA containment sump recirculation operations arc those identiflcd in References (9) and (14).
The RHR pump oil cooler heat loads are applied for each lineup in which RHR system operation is indicated, Table 2.
The thermal-hydraulic conditions of the spent fuel pools are based on the estimated heat load which would occur immediately prior and following the refueling outage in the Year 2000 at a Spent Fuel Pool Cooling (SFPC) system mass flow rate of 1.88E6 ibm/lu', Reference (11), which conservatively results a speciTied SFPC volumetric flow rate of 3750 gpm. Table 4 summarizes thc assumed heat loads for Spent Fuel Pools A/B and C/D as well as the applicable dates as the limiting heat load for each CCW system alignment does not necessarily corrcspond to operations at thc completion ofthc Year 2000 outage.
Refueling case alignment maximum heat loads are identified in Reference (26) for the Normal Full Core Offload scenario.
An estimate of Core Shuffle and Abnormal Full Core Offload scenario heat loads is performed to satisfy the analysis requirements ofNUREG-0800.
The base heat load for fuel pool A/B is estimated as follows:
Normal Full Core Offload (RFO7)
Fuel Pool A/9 Base Heat Load (RFO7)
Calculated Refueling Heat Load (RFO7)
Specified fuel pool A/B and C Heat Load Fuel Pool C Heat Load Refueling Heat Load Estimated Fuel Pool A/B Base Ht Load
[Reference (11)]
[Rcfcrcnce (11)]
= 35.06 MBTU/lir
= 5.16 MBTU/lir
= 29.9 MBTU/lir
= 44.13 MBTU/lu
[Attaclunent 5 ofRefcrcnce (26)]
~ 0.9957 MBTU/lu
[Attachment 8 ofReference (26)]
= 29.9 MBTU/hr
= 13.23 MBTU/lu;use 13.3 MBTU/lirfor conservatism.
The Core Shuffle refueling alignment heat load of25.0 MBTU/hris estimated as follows:
Fuel Pool A/B Base Heat Load As of9/26/2001 = 13.3 MBTU/lir Fuel Pool A/B Core Shuffle Heat Load = 11.68 MBTU/lu 16.84 -5.16 MBTU/lu [Reference (11)]
Fuel Pool A/B Core Shuffle Total Heat Load As of9/26/2001 = 13.3 + 11.68 25 MBTU/lu Thc maximum Abnormal Full Core Offload alignment heat load of44.1 MBTU/hris estimated as follows:
Fuel Pool A/B Base Heat Load As of9/26/2001 13.3 MBTU/lu Fuel Pool A/B Abnormal Full Core Offload Heat Load 30.71 MBTU/hr= 35.87 -5.16 MBTU/hr[Reference (11)]
Fuel Pool A/B Abnomial Full Core Offload Total Heat Load As of9/26/2001 = 13.3+ 30.71 44.1 MBTU/hr These heat loads do not include the effect ofany change in HNP core thermal power rating.
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CAROLINAPOWER 86 LIGHTCOMPANY Calculation ID: SF-0040 Pg 9 of 32 ReY0 Project No.:
CALCULATIONSHEET File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 3 Summary of CCIVS Operating Alignment Thermal Boundary Conditions Alignnient RHR Pump B iuIRHxB Units Heat Load (BTU/hr)
Flow (gpm) I Tin ('F)
Staitup Normal Mode I N/A IlotS/D (350+F)
Safe S/D (350'F) 70,000 650/
350
@4 his
@4 hrs Refuel (Mode 6)
Core Shume N/A N/A Reluel (Mode 6)
Full Omo d Abnormal Sl 70,000 Rccirc (RHR) 0/
140 Refuel LOCA LOCA (hlode 6)
Recirc (RIIRand SFP)
Reference Calc NSSS-38 R2 Gale NSS&38 R2/CC-0038 RO RHR Puny A Hea( Load (DTUnir) 70000 70000 70000 70000 Calc NSSS-38 R2 RHR Hx A BRS: Dist Ctr BRS: Eiup Clr BRS: Vair Cond Letdown Hx XSLD Hx RCDT Hx Scat Water Hx SFP HxA SFP Hxn RCP A Flow (gpm) I Tin ('F)
Iles( Load IBTUnir)
Heat Load (BTU/hr)
Heat Load (BTU/br)
Flow (gpm) I Tin ('F)
Flow (gpm) I Tin ('F)
Flow (gpni) I Tin ('F)
Flow(gpni) I Tin ('F)
Heat Load (DTUnir)
Heat Load (BTUnir)
Heat Load (BTUnir)
380 120/
380 24.8/$ 60 N/A 89.12/
180 89.12/
180 N/A N/A 367000 3G7000 128.1/
128.1/
138.5 138.$
15200000 15200000 650/3 SO 800/350 0/140 N/A N/A N/A N/A N/A N/A 120/
350 N/A N/A N/A 89.12/
180 89.12/
180 89.12/
180 N/A N/A N/A 3G7000 128.1/
128.1/
128.1/
138.$
138.5 138.$
13500000 13500000 25000000 0/140 N/A 89.12/
180 128.1/
138.5 31780000 N/A N/A N/A N/A N/A N/A 120/
380 N/A N/A 89.12/
180 128.1/
138.$
89.12/
180 128.1/
138.5 31780000 15200000 0
N/A 0
3G7000 0/140 N/A 3903/244.1 3903/209 15200000 N/A Calc NSSS.38 R2/CC-0038 RO Ass~ DRS Sh'd Abandoned Inplace Assume! BRS Skid Abandoned Inphec Assumal DRS Skid Abandoned Inphce Design CVCS Flow at RCS Tanp Spec Sheet in VM-MRK Spec Shcct in VM-MRK Spec Sheet in VM-MRK Estimated from Rcfaence (26)
I/3 ofWEC CQI 5361 6/5/79 Value RCP B RCP C SFP IixC Heat Load (DTUnir)
'eat Load (DTUnir)
Heat Load (DTUnir),
N/A N/A 367000 367000 3G7000 3G7000 367000 367000 N/A N/A 0
367000 0
367000 N/A '/A
" N/A I/3 ofWEC CQI 5361 6/5/79 Value I/3 ofWEC CQI S361 6/5/79 Value Secured SFP lixD Heat Load (DTU/hr) 1000000 N/A 1000000 1000000 1000000 1000000 1000000 Estimated from Rcfcrencc (2G)
GFFD Sanyle Coolers Fuel Pool A/B Heat Load (BTU/hr) liest Load (DTU/hr)
Heat Load NTUnir)
N/A N/A N/A 15200000 15200000 13500000 13500000 25000000 N/A 31780000 N/A N/A N/A N/A 0
31780000 15200000 15200000 15200000 Es(imatcd I'rom Refcrencc (26) 0 Assumed Negligible.
Ht Load ~ 0.24 MBTU/hr Assumed Negligil>le Due to Tnnsicnt Load Fuel Pool C/D Heat Load (DTU/hr) 1000000 1000000 1000000 1000000 1000000 1000000 1000000 1000000 Estimated from Refcrencc (26)
CCW Trains No Operating Split(I/I)
I I
Split(l/I)
I Split(l/0)
Split(l/0)
Consistent with ODD-131
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Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 4 Summary ofSpent Fuel Pool A/8 Heat Loads for Various CCW System Alignments Alignment As ofDate Ccw Temperature Limit('F)
SFP A/B SFP A/II Temp Heat Load Limit('F) (MIITU/hr)
Normal Hot S/D (350)
Safe S/D(350'F)
Refuel~re Shume Rcfucl-Normal Full Core Omoad (I)
Refuel-Abnormal Full Core Omoad (I)
LOCA-Safety Injection LOCA-Recirc (RHR Only)
LOCA-Recirc (RHR/SFP) 10/22/2001 9/15/2001 9/I5/2001 9/22/2001 9/22/2001 9/22/2001 10/22/2001 10/22/2001 10/22/2001 105 120 120 105 105 105 105 120 120 137 137 137 137 137 137 137 137 137 15.2 13.5 13.5 25.0 31.78 31.78 15.2 15.2 15.2 Notes: 1)
Assumes that 265.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> have elapsed since reactor shutdown to rcducc core decay heat to within thc heat removal capacity ofthc SFP heat exchangers.
4.3 Evaluation ofMinimumRHR Heat Exchanger CCWS Floav The post-modiTication CCW flow balance evaluated in this analysis maintains a maximum design CCW teruperaiure of 120'F, while considering the addition of 1.0 MBTU/lirto the C and D Spent Fuel Pools, 6 percent modeling uncertainty per Reference (I), and a RHR heat exchanger UA value which is modeled to change with fluid properties.
The licensing basis previous to this calculation is based on an assumed RHR heat cxchan cr UA of 1.635E6 BTU/Iir-'F, derived from the design RHR heat exchanger overall heat transfer coefficient of382 BTU/lu-sqft-'F which is in turn based on an RHR heat exchanger inlet temperature of 139'F and the overall heat transfer surface area of4280 sqft. However, during the initial phase ofcontainmcnt sump recirculation, the RHR tube side inlet temperature rises to 244.1'F, which increases thc calculated overall heat transfer coefficient to 421.2 BTU/lu-'F due to thc change in the RHR heat cxchangcr tube side fluid viscosity.
These conditions would tend to increase heat transfer tluough the RHR heat exchanger and increase CCW systein supply temperatures above the maximum CCW supply tcmpcraturc of 120'F for the given limiting conditions of minimum CCW heat exchanger Service Water flow and maximum Service Water supply temperature.
Two ch;rnges are prescribed herein to address the heat loads and conditions above in the post-modification CCW fl<<w balance.
First, the minimum specified CCWS flowto the RHR heat cxchangcr must be reduced to a level corisistent with heat rejection value of 111.1 MBTU/hr, consistent with Refcrcnce (9). An analysis of RHR he:it exchanger thermal performance, Attachment (C), was performed to determine the minimum shell side liow rate at 120'F shell side inlet temperature, 244.1'F tube side inlet tcmpcrature and 1.846E6 Ibm/lir urbe side flow rate, consistent with Rcfcrcncc (21). This analysis shows that a minimum CCWS flow rate of
'4874 gpin at 120'F is required at the beginning ofthe sump recirculation phase.
The spcciTied CCWS flow to the Rllk heat exchanger under these conditions, assuming 6 pcrccnt modeling uncertainty consistent with
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CAROLINAPOWER Sc LIGHTCOMPANY Calculation ID: SF-0040 P<, 11 oi'32 i<cv0 Project No.:
CALCULATIONSHEET File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Reference (1), is 5166 gpm or approximately 5200 gpm. As the containment sump tcmperaturc decreases, thc minimum required CCWS flowalso decreases, as shown in Figure 1 ofAttaclunent (C), based on maintaining a maximum RHR heat exchanger tube side outlet tcmperaturc of 180'F, Rcfcrcnec (21). The CCWS was initially rebalanced using thc CCWS PROTO-FLO'model in the LOCA:Recirc (RHR Only) alignment, Attacliment (F), with a 10 percent degraded CCW pump curve, by adjusting ICC-146 to 47.9 pcrccnt open.
When the nominal CCW pump curve is applied to thc previously balanced CCWS, CCWS fiow to thc RHR heat exchanger increases to approximately 5440 gpm resulting in an increased MIRheat exchanger heat duty of 118 MBTU/1ir. The increased MMheat exchanger heat duty results in an cxccssive CCWS supply temperature which cannot be maintained below 120'F, given 8250 gpm ESWS flow to the CCW heat cxchangcr.
Holding the position of 1CC-146 (or 1CC-166) constant, the specified ESWS flow to the CCW heat cxchangcr was increased to 8500 gpm which results in a CCW heat exchanger outlet temperature of 120'F, Attacluncnt (G),
consistent with the original assumption used in setting the minimum CCWS flow to the MK.heat exchanger, docurnentcd in Attaclunent (D).
Therefore, a reduction in the minimum specified RHR heat exchanger CCWS fiow to 5200 gpm from thc original 5600 gpm specification and an increase in the minimum specified CCW heat exchanger ESWS fiow to 8500 gpm from the original 8250 gpm are necessary to meet all the thermal-hydraulic assumptions which are used in the HNP Contaiiunent Analysis, Rcfcrence (21). A minimum specified ESWS flowof8500 gpm to the CCW heat exchangcrs was verified to be within the capacity ofthe current ESWS system, Reference (20), even considering the most limitingESWS single failure ofa MCC 1B35-SB feeder brcakcr failure, Rcfercnce (29).
.Evaluation ofMaximum RHR Heat Exchanger CCWS Flow An evaluation was performed, using the RHR heat cxchangcr PROTO-H3V" model devclopcd in Rcfcrencc (1),
to estimate the maximum CCWS flow rate which could be accommodated during the initial phase of contaiiunent sump recirculation.
This analysis shows that a maxiinum CCWS flowof 5220 gpm is attainablc for a CCW heat cxchangcr ESWS flowof8250 gpm and a maximum CCWS flowof5440 gpm is attainable for an ESWS flowof 8500 gpm in order to maintain a CCWS supply temperature of 120'F.
Given that the MM heat exchanger tlirottle valves (1CC-146 and 1CC-166) arc set on thc basis of maintaining a minimum CCWS fiow rate under all hydraulic conditions, including modeling uncertainty and CCW pump degradation limits, when the CCWS is in thc LOCA recirculation alignment, there willbc cxccss flow to thc RHR heat exchanger, approximately 5440 gpm total, Attaclunent (D). The thermal cffcct ofthe excess RHR heat exchanger flowcan be mitigated with an increase in the minimum ESWS flowto thc CCW heat exchanger of250 gpm.
4.5 Evaluation ofMinimum Spent Fuel Pool Heat Exchanger CCATS Flow An evaluation of thc minimum thermally required CCWS fiow to thc Spent Fuel Pool heat cxchangers was performed by generating heat duty versus CCWS flow for all combinations of design CCWS supply temperatures and SFP temperature limits. This analysis is performed using the PROTO-HX model dcvclopcd in Reference (1) and assumes 5 percent tube plugging and design fouling factors.
CCWS design supply temperatures of 105'F for normal and refueling system aligrunents and 120'F for cooldown and LOCA:Recirculation alignments are used in thc analysis. A maximum SFP tcmpcrature limit of 137'F for all fuel pool operations is also assumed.
Figure 1 and Table 5 summarize and Attaclimcnt (E) documents the results ofthis analysis.
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CAROLINAPOWER &LIGHTCOMPANY Calculation ID: SF-0040 Ps lg of 3P Re" 0 Project No.:
CALDJLATIONSHEET File:
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Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 35 Figure I SFP Hx Duty at a Given CCW Flow Rate 30
~
25 20 0
15 X
o 10 0
5 0 ts ssump ons:
Design Fouling Factor u 0 001049 hr. sqft F/aTV 5% Tube Ptugging 3000 CCW Flow (gpm)
FP emp~137F, empt t20F CI FP Temp ~137F.CCWTempu105F Table 5 Minimum SFP Heat Exchanger CCW Flow Requirentents Alignment Normal Hot S/D (350F)
As of Date 10/22/2001 9/1 5/2001 1200 2800 1272 2968 60 125 SFP Hx NB SFP Hx NB SFP Hx C/D Thermal Flow Minimum
- Thermal Flow Requirement Flow (1)
Requirement (gpm)
(gpm)
(gpm)
SFP Hx C/D Minimum Flow (1)
(gpm) 63.6 132.5 Safe S/D(350F)
Refuel-Core Shuffle 9/1 5/2001 9/22/2001 2800 2800 2968 2968 125 132.5 Refuel-Normal Full Core Offload (2) 9/22/2001 Refuel-Abnormal Full Core Offload (2) 9/22/2001 5400 5400 5400 (3) 5400 (3) 60 60 63.6 63.6 LOCA-Safety Injection LOCA-Recirc (RHR Only)
LOCA-Recirc (RHR/SFP) 10/22/2001 10/22/2001 10/22/2001 1200 3830 1272 4059.8 60 125 63.6 132.5 Note 1: Minimum Heat Exchanger Flow Includes 6% Hydraulic Uncertainty Per CP8L HNP Calculation CC4039 Revision 0 Note 2:
Assumes Sufficient Decay Time to Reach 31.78 MBTU/hr(265.36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> after S/D)
Note 3: SFP Hx NB Max Flow is 5400 gpm per design data sheet which should not be exceeded to ensure flow induced tube vibration problems do not occur.
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CAROLINAPOWER 8c LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 Pi', 13 or 32 Rcv0 Fflc:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 4.6 CCWS Hydraulic Mat gins In order to accommodate the changes in the CCWS load flow requirements identified above, the CCWS PROTO-FLO'model was rcbalanccd.
Based on previous analysis, it was determined that the most limiting CCWS alignment is thc Hot S/D (350F) 'A'CWTrain with thc Nonessential header case in which the CCW pump dcvclops the least head due to the maximum CCWS flow rcquircments.
Therefore, thc CCWS was rcbalanccd using thc Hot S/D (350F) alignment, thc 10 percent degraded CCW pump curve and minimum CCWS flows to each load with the exception of the tuIR heat cxchangcrs which werc balanced in the LOCA:Recirc (tuW Only) alignment. The results ofthis analysis arc documcntcd in Attachments (F) and (H).
The resulting changes in tluottlc valve position or miscellaneous loss coefficients arc shown in Table 6. It is noted that the SFP heat exchanger C/D tluottlc valves, AltV-15 and AltV-11, are heavily tlirottled and will require a suitably sized bypass line with a smaller tlirottlc valve in order to achieve acceptable tlirottling characteristics.
This modification to thc CCWS return line from SFP heat exchangcrs is a design detail which willhave to bc resolved at a later date by the cognizant design organization.
Table 6 Estimated Cliangc in CCXVS Throttle Valve Positions and RCP Linc Miscellaneous Loss Coefficient Service TlirottleValve Old Position/Misc K New Position/Misc K RHR Heat Exchanger A RHR Heat Exchanger B RCDT Heat Exchanger XSLD Heat Exchanger SFP Heat Exchanger A(B)
SFP Heat Exchanger D(C)
RCP A Upper 13caring Cooler RCP A Lower Bearing Cooler RCP AThermal Barrier RCP B Upper Bearing Cooler RCP B Lower Bearing Cooler RCP B Thermal Barrier RCP C Upper 13caring Cooler RCP C Lower Bearing Cooler RCP C Thcrrnal Barrier 1CC-146 ICC-166 1CC-187 ICC-197 1CC-382(398)
AltV-15(11) 1CC-258 1CC-264 1CC-224 1CC-273 1CC-279 1CC-235 ICC-284 ICC-290 1CC-246 49.24 % Open 49.24 % Open 8.85 % Open 12.91% Open 34.35 % Open Not Installed 194.00 90000 510.00 211.00 30584.00 320.00 206.00 80610.00 404.00 48.61 % Open 47.91 % Open 41.98 % Open 80.23% Open 27.94% Open 2.03 % Open 14.14 11971 58.28 14.14 11971 58.28 14.14 11965 52.87 The hydraulic niargins for thc CCWS werc evaluated utilizing thc system throttle valve positions documented in Attaclunents (F) and (H) and degrading the operating CCW pump curves by 10 percent of thc total developed head, Reference (3). Tlic cffcct of the letdown heat cxchangcr was simulated by changing ICC-TCV-337 to a flowcontrol valve with a setpoint of610 gpm pcr Assumption 4.1.16, the spccificd letdown heat exchanger CCWS flow rate under non-startup conditions with hydraulic uncertainty.
For thc plant Startup case alignment, 1CC-TCV-337 was rcstorcd to a tcmpcraturc control valve with a sefpoint of 120'F.
ESWS flow to the operating CCW heat cxchangers was set to 8500 gprn at 95'F. The resulting CCWS flows were tabulated and reduced by 6 percent to account for rnodcling and iristrumcnt uncertainty as established in Reference (I).
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CAROLINAPOWER Sc LIGHTCOMPANY Calculation ID: SF-0040 Pg 14 of 32 Rcv0 Project No.:
CALCULATIONSHEET Fflc:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis This process is repeated for each of the major CCWS system lineups with the results documented in Attacluncnts (I) through (Q) and summarized in Tables 7a through 7j.
Minimum CCWS flow requirements in Tables 7a through 7j to cooled components are established from design data sheet values, Reference (1), for all components except for the RHR Pump Coolers, Reference (9), the RHR heat exchangers, Section 4.3, the Letdown heat exchanger, Reference (31), and thc Spent Fuel Pool heat exchangers, Section 4.5.
The Hot Shutdown (350F) and Safe Shutdown (350F) RHR heat exchanger minimum CCW flow limits were dctcrmincd, Attachments (J) and (K), by using the MIRheat exchanger PROTO-IDV" model, Rcfcrcncc (I), to meet a heat duty of 118.9 MBTU/lu and 177.76 MBTU/hrwith the maximum RHR pump flowof4500 gpm at an RCS temperature of350'F. The Hot Shutdown case required heat duty of 118.9 MBTU/Ie is detcrmincd as follows:
RCS Sensible Heat Removal Decay Heat 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after S/D RCP Heat (3 Pumps Operating)
Total Heat Removal Required or
= 66.96 MBTU/hr
[Table 9.2.1-7 ofRcferencc (31)]
= 110.8 MBTU/hr
[Table 9.2.1-7 ofReference (31)]
= 60 MBTU/hr
[Reference (32)]
237.76 MBTU/luwith 2 RHIVCCW trains in operation
= 118.9 MBTU/ln.pcr RHR heat exchanger The Safe Shutdown case RHR heat exchanger rcquircd heat duty of 177.76 MBTU/hr is taken from Table 9.2.1-7 of Reference (31).
The minimum required CCW fiow to the RHR heat exchanger, assuming design fouling factors and 120'F CCW supply temperature is 1300 gpm and 2560 gpm per operating heat exchanger for the Hot Shutdown and Safe Shutdown cases, rcspectivcly.
The LOCA: Recirc (RHR and SFP) case represents maintaining CCWS flow to both the Spent Fuel Pool and RHR heat cxchangers.
It is assumed that the operators do not adjust flow to the Spent Fuel Pool heat exchanger in order to maintain RHR heat exchanger flow as the estimated CCWS flow to the RHR heat cxchangers exceeds the thermally required CCWS flow of 2250 gpm for a containment sump temperature of 209'F, Attachment (C), to maintain a 180'F RHR heat exchanger outlet temperature, Reference (21).
When the containment sump temperature reaches 209'F, the CCWS fiow to the RHR heat exchanger is 4450 gpm, Attachment (Z). The worst case CCWS flow to the RHR heat exchanger at the point ofbringing the Spent Fuel Pool heat exchangers online is 4430 gpm with a corresponding heat removal of 80.53 MBTU/hr, consistent with Reference (14).
The results of this analysis, Tables 7a through 7j, show that sufflcient CCWS flow is available to cooled components under most major system alignments, given the 10% IST pump degradation limits assumed by Refcrencc (3), with thc exception of the Spent Fuel Pool heat exchanger A (or B) under the LOCA:
Recirculation (RHR and SFP) alignment and the nonessential header loads under thc Refuel-Normal (or
.Abnormal)
Full Core Offload case.
Evaluation of the system thermal analysis results during the LOCA:Recirculation (RHR and SFP) alignment, Attachment (Z), shows that thc steady state equilibrium tcmperaturc of fuel pool A/B does not exceed 136'F, even with the assumptions of 10% percent degraded CCWS flow, minimum ESWS fiowof8500 gpm to the CCW heat cxchangers, usc ofdesign fouling factors for all heat exchangers and design (maximum) Ultimate Heat Sink temperature of95'F. Acceptable fuel pool A/B temperature indicates that the minimum specified CCWS flows to the Spent Fuel Pool heat cxchangcrs are very
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Spent Fuel Pools C and D Activation Project Calculation
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Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis conservative and that acceptable operation ofthc Spent Fuel Pool heat exchangers under limitingconditions can be achieved.
These results demonstrate that the redistribution ofCCWS flow is adequate for the limitingCCW pump developed head.
For thc Refuel-Normal and Abnormal Full Core Offload cases in which a single failure ofthc '8'CW train or when thc CCW trains are split, insufficient CCW flow is provided to the SFP heat exchanger A (or 8), thc Seal Water heat cxchangcr and the RCDT heat cxchangcr for the limiting hydraulic case of 10% dcgradcd CCW pump curve operation.
A separate heat exchanger performance analysis was done for each heat exchanger assuming all other thermal conditions were specified as design values except for the CCW flow and supply temperature, documented in Attacluncnts (M) and (N). Thc results ofthis analysis indicates that the SFP Hx A (or 8) can just accommodate an assumed full core offload heat load of 31.7 MBTU/hrat design SFPC thermal conditions, thcreforc thc negative CCW flow margin is acceptable under these extreme thermal-hydraulic conditions.
The results of the Seal Water heat exchanger performance analysis show that thc estimated heat duty is 3.1 percent less than the design heat duty but this is judged to be acccptablc as the reactor coolant pumps arc not operating during refueling operations and the seal injection supply tetnpcrature only rises from 115.0 to 115.7'I'.
The results of the RCDT heat exchanger performance analysis show that thc estimated heat duty is 0.9 pcrccnt less than the design heat duty of the heat exchanger, resulting in an increase in RCDT heat exchanger outlet temperature from 130.0 to 130.5'F. It is considered that this small increase in RCDT heat outlet temperature is acceptable as RCS temperature is less than 140'F during this operating mode while the design RCDT heat exchanger inlet tempcraturc is 180'F.
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Title:
Spent Fuel Pools C and D Activation Project Calculation
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Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7a Summary of CCWS Flow Margins Normal Ops Section 105 Component RHR Pump B Calculated Flow (gpm) 6.9 W!Ih 6%
Uncertaint 6.5 Min Flow
( pm)
Flow Margin (%)
30%
108 115 112 66 80 73 61 45 44 98 91 203 205 208 207 209 214 212 215 304 305 Node 0401 Node0028 5 and 28 RHRHx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Barrier RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Barrier SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 36 36.9 1158 318 303 308 3613 N/A 6.7 51.6 194.2 51.6 194.2 6.7 51.6 N/A 160.9 14 160 6887 34.0 6.6 34.8 0.0 0.0 0.0 1092.5 300.0 285.8 290.6 3408.5 N/A 183.2 6.3 48.7 183.2 6.3 48.7 183.2 6.3 48.7 151.8 6497.2 575 247 225 230 1200 150 40 150 40 150 40 59 14 160 3305 N/A 32%
N/A N/A N/A N/A 90%
21%
27%
26%
184%
22%
26%
22%
22%
26%
22%
22%
26%
22%
157%
Specified Specified 97%
Notes RHR Hx Outlet Isolation Valves are Shut LD HX Flow is set based on maintaining 120F LD Outlet Temp.
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Spent Fuel Pools C and D Activation Project Calculation
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Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7b Summary of CCKVS Flow Margins Hot S/D (350F)
Section Component Calculated Flow (gpm)
With 6%
Uncertainty Min Flow (gpm)
Flow Margin (%)
105 108 115 112 66 80 73 45 44 54 98 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 5 and 28 RHR Pump B RHRHx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP Hx A SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Barrier RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Bamer RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Bamer SFP Kx C SFP Hx D GFFD Sampte Cooters Total CCWS Flow Operating CCW Train 7.2 5199 5.6 3983 610 262 249.5 253.9 2980.3 160 5.5 42.5 5.5 42.5 160 5.5 42.5 N/A
'i32.7 14 160 14529.3 A/B Split 6.8 4904.7 5.3 3757.5 0.0 0.0 0.0 575.5 247.2 235.4 239.5 2811.6 150.9 5.2 40.1 150.9 5.2 40.1 150.9 5.2 40.1 125.2 13706.9 1300 1300 575 247 225 230 2800 40 150 40 150 40 125 14 160 7571 A/B Split 36%
277%
6%
189%
N/A N/A
'/A 0%
0%
5%
4 0%
N/A 1%
4 0
1%
4%
0%
1%
4%
0%
N/A 0%
Specified Specified 81%
Notes LD Hx Flow Limited to a 575 GPM Nominal Value Defined in FSAR
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 Ps I8 or32 Rcv0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7c
. Summary ofCCAVS Flow Margins Safe S/D (350F)
Section Component Calculated Flow (gpm)
With 6%
Uncertainty Min Flow (gpm)
Flow Margin (%)
105 108 115 112 66 80 73 61 45 44 54 98 91 204 203 205 208 207 209 214 212 215 304 305 Node 0401 Node0028 5 and 28 RHR Pump B RHR Hx B RHR Pump A RHR Hx A BRS: Dist Cir BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Barrier RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Bamer RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Barrier SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 5.8 4119 271.6 258.8 263.5 3096 165.9 5.7 44.1 165.9 5.7 44.1 165.9 5.7 44.1 N/A 137.9 160 9003 0.0 0.0 5.5 3885.8 0.0 0.0 0.0 0.0 256.2 244.2 248.6 2920.8 156.5 5.4 41.6 156.5 5.4 41.6 156.5 5.4 41.6 130.1 8493.4 2560 247 225 230 2800 150 40 150 40 40 125 14 160 6951 9%
52%
N/A N/A N/A N/A 4
9%
8%
4 N/A 4%
8%
4 4%
8%
4%
4%
8%
4%
N/A 4%
Specified Specified 22%
Notes a) RCPs are secured but CCWS flowis maintained.
b) Letdown secured c) 'B'CW Train Single Failure
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: Sl'-0040 tg l9 <<r3g Rcv0 File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7d Summary of CCWS I<'lowMargins Section Component Calculated Flow (gpm)
Refuel - Core Shuffle With 6%
Min Flow (gpm)
Flow Margin (%)
Uncertainty 105 108 115 112 66 80 73 61 45 44 98 91 RHR Pump B RHR Hx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Hx B 5.8 4125 272 259.3 3103 0.0 0.0 5.5 3891.5 0.0 0.0 0.0 0.0 256.6 244.6 249.1 2927.4 247 225 230 2900 N/A N/A N/A N/A N/A N/A N/A N/A 4%
9%
8%
1%
N/A 204 RCP A Upper Oil Cooler 166.3 156.9 150 5%
203 RCP A Lower Oil Cooler 5.7 5.4 8%
205 RCP AThermal Barrier 44.1 41.6 40 4%
208 RCP B Upper Oil Cooler 166.3 156.9 150 5%
207 209 214 RCP B Lower Oil Cooler 5.7 RCP B Thermal Barrier 44.1 RCP C Upper Oil Cooler 166.3 5.4 41.6 156.9 40
'50 8%
4%
5%
212 RCP C Lower Oil Cooler 5.7 5.4 8%
215 304 RCP C Thermal Barrier 44.1 SFP Hx C 41.6 40 4%
N/A 305 Node0401 Node0028 5 and 28 SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 138.2 14 8997.6 130.4 8488.3 59 14 160 4420 121%
Specified Specified 92%
Notes a) RCPs are secured but CCWS flowis maintained.
b) 'B'CW Train Single Failure c) No min flowis defined for the RHR hx as RPV is defueled
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 t'g 20 or 32 aa 0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7e Sumnmry of CCWS Flow Margins Refuel - Normal Core Offload Section Component Calculated Flow (gpm)
VNth 6%
Uncertainty Min Flow Flow (gpm)
Margin (%)
105 108 115 112 66 80 73 45 44 98 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 Sand 28 RHR Pump B RHR Hx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Bamer RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Bamer SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 4.9 3470 224 213.8 217.1 5325.9 137.1 4.7 36.3 137.1 4.7 36.3 137.1 4.7 36.3 N/A 110.6 14 160 10285 A
0.0 0.0 4.6 3273.6 0.0 0.0 0.0 0.0 211.3 201.7 204.8 5024.4 129.3 4,4 34.2 129.3 4,4 34.2 129.3 4,4 104.3 150.9 9702.8 225 230 5400 60 14 160 6089 N/A N/A N/A N/A N/A N/A N/A 10%
11%
-7%
N/A NIA N/A NIA NIA N/A N/A N/A N/A N/A N/A 74%
Specified Specified 59%
Notes a) RCPs are secured but CCWS flowis maintained.
b) 'B'CW Train Single Failure c) No min flowis defined for the RHR hx as RPV is defueled d) SFP A/B hx CCW set to 5400 gpm e) RCDT, Seal Wtr Hx and SFP A/B Hx performance exceeds the design requirements f) No min flowIs defined for XSLD Hx as LD is secured
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 t'4 2l "I32 Re 0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7f Summary of CCIVS Flow Margins Refuel - Abnormal Core Offload Section Component Calculated Flow (gpm)
With 6%
Uncertainty MinFlow(gpm) FlowMargin(%)
105 108 115 112 66 80 73 61 45 44 54
'8 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 5 and 28 RHR Pump B RHRHx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP Hx A SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Bamer RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Barrier SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 7.2 5213 4.9 3470.3 224.1 213.8 217.1 5326 137.1 4.7 36.3 137.1 4.7 36.3 137.1 4.7 36.4 110.6 14 160 15505.2 6.8 4917.9 4.6 3273.9 0.0 0.0 0.0 0.0 211.4 201.7 204.8 5024.5 129.3 4.4 34.2 129.3 4.4 129.3 4.4 34.3 104.3 14627.5 225 230 5400 59 14 160 6098 36%
N/A 8%
N/A N/A N/A N/A N/A N/A 10%
-11%
-7%
N/A N/A N/A N/A N/A NIA N/A NIA NIA N/A 77%
Specified Specified 140%
Notes a) RCPs are secured but CCWS is maintained.
b) No min flowis defined for the RHR hx as RPV is defueled c) SFP A/B hx CCW set to 5400 gpm d) RCDT, Seal Wtr Hx and SFP A/B Hx performance exceeds the design requiroments e) No min flowis defined for XSLD Hx as LD is secured
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"2Z"32 Rc<<0 Project No.:
CALCULATIONSHEET File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7g Summary of CCWS I<lowMargins LOCA - Safety Injection Section Component Calculated Flow (gpm)
With 6%
Uncertainty Min Flow (gpm)
Flow Margin
(%)
105 108 115 112 66 80 73 61 45 44 98 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 Sand 28 RHR Pump B RHR Hx B RHR Pump A RHRHxA BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP Hx A SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Barrier RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Barrier SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 6.9 36.3 37.1 1145 321 305.8 310.5 3641.6 196.1 6.7 52.1 196.1 6.7 52.1 196.1 6.7 52.1 N/A 162.2 6746 6.5 34.2 6.6 35.0 0.0 0.0 0.0 1080.2 302.8 288.5 292.9 3435.5 185.0 6.3 49.2 185.0 6.3 49.2 185.0 6.3 49.2 153.0 0.0 0.0 6364.2 575 247 225 230 1200 150 40 40 40 "0
59 3131 30%
N/A 32%
N/A N/A N/A N/A 88%
23%
28%
27%
186%
N/A 23%
26%
23%
23%
26%
23%
23%
26%
23%
N/A 15g Isolated Isolated 103%
Notes a) System configuration is immediately after 'S'ignal
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040
's 23'2
"'"0 File:
Project
Title:
Spent I'uel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7h Summary of CCWS Floav Margins LOCA-Sump Recirc (RHR Only)
Section Component Calculated Flow (gpm)
With 6%
Uncertainty Min Flow (gpm)
Flow Margin (%)
105 108 115 112 66 80 73 61 45 44 54 98 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 5 and 28 RHR Pump B RHR Hx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Kx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Barrier RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Barrier SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train Notes 7.3 51930'.0 0.0 6.9 4881.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4874 N/A N/A 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 N/A N/A 5238 A (Split) 4923.7 4879 A (Split) a) Only operator action is splitting CCW Trains N/A N/A 37%
0%
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
~ NIA N/A N/A N/A Isolated Isolated 1%
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 s24o 32
~ 0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7i Summary of CCAVS Flow Margins LOCA-Sump Recirc (RHR/SFP)
Section Component Calculated Flow (gpm)
VNth 6%
Uncertainty Min Flow (gpm)
Flow Margin
(%)
105 108 115 112 66 80 73 61 45 44 54 98 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 Sand 28 RHR Pump B RHR Hx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Hx B RCP A Upper Oil Cooler RCP A Lower Oil Cooler RCP AThermal Barrier RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooler RCP C Lower Oil Cooler RCP C Thermal Bamer SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train 6.3 4472 3381.5 N/A 150.6 8038 A (Split) 0.0 0.0 5.9 4203.7 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3178.6 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 N/A 141.6 7555.7 2250 0.
3830 125 6210 A (Sptit)
N/A N/A 18%
87%
-17%
N/A NIA NIA N/A NIA N/A NIA N/A N/A N/A N/A 13%
Isolated Isolated 22%
Notes a) Operators manually bring SFP hxs online by opening upslream isolation valves
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 Pg 25 ol32 Rcv0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7j Summary of CCWS Flosv Margins Section Component Calculated Flow (gpm)
Startup Ops With 6%
Min Flow (gpm)
Flow Margin (%)
Uncertainty 105 108 115 112 66 80 73 61 45 44 98 91 204 203 205 208 207 209 214 212 215 304 305 Node0401 Node0028 5 and 28 RHR Pump B RHRHx B RHR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP HxA SFP Hx B RCP A Upper Oil Cooter RCP A Lower Oil Cooter RCP AThermal Bamer RCP B Upper Oil Cooler RCP B Lower Oil Cooler RCP B Thermal Barrier RCP C Upper Oil Cooter RCP C Lower Oil Cooler RCP C Thermal Bamer SFP Hx C SFP Hx D GFFD Sample Coolers Total CCWS Flow Operating CCW Train Notes 6.9 35.9 6.9 36.7 1250 317.4 301.6 306.8 3597.4 N/A 193.4 6.7 51.4 193A 6.7 51.4 193.4 6.7 51.4 6.5 33.9 6.5 34.6 0.0 0.0 0.0 1179.2 299.4'84.5 289.4 3393.8 N/A 182.5 6.3 48.5 182.5 6.3 48.5 182.5 6.3 48.5 1100 247 225 230 1200 150 40 40 150 40 160.2 14 160 6958 A
151.1 6564.2 59 14 160 3830 RHR Hx Outlet Isolation Valves are Shut 30%
N/A 30%
N/A N/A N/A N/A 7%
21%
26%
26%
183%
N/A 22%
26%
21%
22%
26%
21%
22%
26%
21%
N/A 156%
Specified Specified 71%
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CAROLINAPOWER &LIGHTCOMPANY Calculation ID: SF-0040 Pg 2g of 32 Rev0 Project No.:
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Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 4.7 Estimate of CCWS Thermal Performance The design basis thermal performance of the CCWS was developed by setting thc CCWS system thermal boundary conditions to the values defined in Table 3. A steady state thermal-hydraulic balance ofthe CCWS was performed using PROTO-FLO'3.04.
For case alignments in which RHR system flow can vary (notably Cooldown and Refueling alignments), RHR heat exchanger tube side flow is adjusted (up to a maximum of4500 gpm) to maintain CCWS supply temperatures at approximately 120'F, consistent with Refcrencc (13). The ESWS flow conditions are assumed to be at the maximum design temperature of 95'F and the minimum design flow of 8500 gpm, Reference (20), and the CCWS supply temperature is either 105'F or 120'F, depending on the system alignment, Rcfercncc (13).
Long term steady state spent fuel pool equilibrium temperatures'are estimated from thc PROTO-FLO'and PROTO-HX~ results.
Thc temperature and heat duty constraints for the CCWS are all satisfied with the current design basis assumptions with thc exception of the Startup case alignment in which the CCW supply temperature of 105.1'F slightly cxcceds the design vaue of 105.0'F.
Thc slight increase in CCW supply temperature is considered to bc acceptable as the following conditions would not occur simultaneously:
The CCW heat exchanger model assumes design fouling when trcndcd fouling indicates at least 50 percent margin in the fouling factor.
The CCW heat exchanger Service Water supply conditions of 8500 gpm and 95'F represent thc worst case conditions associated with the limiting single active failure of the 1MCC-1B35-SB feeder brcakcr with the ESW system operating on the Main Reservoir at the minimum design basis level of205.7 feet.
Maximum letdown flow is assumed on the CVCS side of the Letdown heat exchanger simultaneously with operation ofthe Excess Letdown heat exchanger at it's design CVCS side conditions.
Attachments (R) through (Z) and Attachment (EE) document and Tables 8a and 8b summarize the results of this analysis.
4.8 Estimate ofTransient Spent I<'uel Pool Thermal Performance An estimate ofthe short term transient thermal performance, Attacluncnt (BB), ofthe spent fuel pools was performed to determine the maximum bulk fuel pool temperature during plant cooldown operations.
The transient analysis calculates the bulk fuel pool temperature in 15 minute increments using an estimated fuel pool decay curve correlation, estimated fuel pool heat exchanger thermal performance correlation developed from several PROTO-HX'runs, only accounting for the water volume ofthe fuel pool and neglecting changes in the water thermal properties.
Fuel pool heatup thermal transients are calculated from:
.VENT P'i
~FuelPool
~SFPHx Equation (1) where:
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CAROLINAPOWER &LIGHTCOMPANY Calculation ID: SF-0040 Pg 27 ol 32 RcY0 Project No.:
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Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis p=Pool Water Density (ibm/cuft) at temperature T;
C>
Pool Water Specific Heat (BTU/ibm/F) at temperature T;
V=Pool Water Volume (cu.A)
T; = Pool Water Bulk Temperature (I') at time t; T;+1= Pool Water Bulk Temperature (F) at time i;+1 J, Mlpo I DecayHI(li')
<Srplrx =f(Ti)
Discretizing the pool heat up rate term:
dT T
1 T
d/
E.+1-r
~
Equation (2)
Solving for T at the i+I time step results in:
(
T.+ i+1 r.(~
i+i= i
~ (gFeelPeol
<<SPPHxj p Cp.V Equation (3)
Equation (3) is solved at each time step using the updated decay heat and Spent Fuel Pool heat exchanger correlations described below.
The decay heat correlation for Fuel Pools A/8 and C are conservatively estimated from Attaclunents 5 and 8 of Reference (26) as follows.
Thc Fuel Pool A/8 decay heat correlation is calculated by subtracting the values in for Fuel Pool C from the values in Attachment 5 for Fuel Pools A/8 and C. This data is then curve fit, as shown in Figures 1 and 2 ofAttaclunent (88), to a generalized decay curve using TableCurve'.
The Fuel Pool decay heat curves of Reference (26) must be adjusted to represent the decay heat generated from the previous refueling (RFO9) which would bc rcprescntative of thc fuel pool inventory during thc plant cooldown prior to refueling outage 10. This calculation assumes that the basic decay heat correlation is conservatively representative of the fuel pool inventory after RFO9 as the decay heat curves from Reference (2G) are for thc last RPV defucling prior to the Power Uprate outage oflate 2001 (RFO10). Thc decay time bctwccn RFO9 and RFO10 is calculated to be 519 days (4/15/2000 to 9/22/2001) from Attachment 3 of Refcrcncc (2G). Thc adjusted curves are used as input into an Excel spreadsheet for calculating the transient thermal performance of thc spent fuel pools during the plant cooldown prior to RFO10 The Spent Fuel Pool heat exchanger performance correlation is developed by using the Spent Fuel Pool heat exchanger PROTO-HX'model developed in Reference (I) at the minimum CCW flows and maximum CCW supply temperatures identified in Attachment (E). The Fuel Pool Cooling Sys'tcm inlet tcmpcraturc to the SFP heat exchanger is varied to calculate a corresponding heat removal rate for the SFP heat exchanger.
Thcsc runs, attached, arc then curve fit using
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CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SF-0040 Pg 2g ot32 RcY0 File:
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis TableCurve'to develop a correlation of heat removal capacity versus fuel pool outlet (SFP Hx inlet) temperature.
These correlations are input into the fuel pool thermal transient sprcadshect.
It is conservatively assumed that the fuel pools are at the maximum temperature limitof 105'1', Reference (33), prior to the thermal transient. It is also assuincd that CCWS supply temperature is a step change to 120'F at the beginning ofthe cooldown for an RCS temperature of 350'F.
The CCWS supply temperature is maintained at 120'F throughout thc cooldown transient.
This analysis also assumes no operator action with respect to the fuel pools during the plant cooldown.
The thermal transient for Spent Fuel Pools A/8, summarized in Table 1 of Attachment (88), shows that 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />, Reference (13), after the start of the plant cooldown, the fuel pool A/8 temperature is 135.7'F which is less than the administrative temperature limitof 137'F. Table 2 ofAttachment (BB) shows that fuel pool C willnot exceed 113.8'F which is less than the administrative limitof 137'F and less than the 126'F, assumed for design basis HVACconditions in Reference (34).
Therefore, it is concluded that acccptablc spent fuel pool temperatures will be maintained even during a plant cooldown from 350'F to 200'F when elevated CCWS supply temperatures arc likely to occur, although the fuel pool A/8 and C temperatures are bounded by the refueling cases in which the maximum steady state bulk pool temperature of 13G.3'F and 122.0'F for fuel pools A/8 and C, respectively.
The Fuel Handling Building (FHB) design basis HVAC analysis, Refercncc (34), shows that four installed air handler cooling coils are sufficient to maintain ambient conditions of 80'F dry bulb temperature and 70 percent Relative Humidity.
Tile as-built FHB HVAC system only includes three air handler cooling coils, which is justified in Attachment G ofReference (34). A thermal transient analysis ofSpent Fuel Pool C was performed to establish thc bulk pool temperature at the completion of fuel handling (39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br />), Reference (11), in order to reduce the conservatism in Reference (34). This analysis assumes a step change in CCWS supply temperature to 105'F at thc minimum CCWS flow rate defined in Tables 7d through 7f and that Spent Fuel Pool C is at the maximum allowable normal operating temperature of 105'F, Reference (33); These thermal conditions are assumed to be maintained tliroughout the transient even though the CCWS supply temperature will decrease afler 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> as the decay heat generated by the recently discharged fuel assemblies in Spent Fuel Pool A/8 is decreasing due to longer decay times.
The transient fuel pool C temperature is estimated to be 113.8'F at 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> after commencing fuel handling in the A/8 fuel pools which are also assumed to be at the administrative temperature limitof 137'F.
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Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 8a Summary of CCWS Steady-State Thermal Capacity Load RHR Pump B RHRHx B Units Heat Load BTU/hr Heat Load BTU/hr Startup Normal Mode 1 Hot S/D (350F) 71926000 Alignment Safo S/D (350F)
Refcrenco Calo NSSS~ R2 Calculated RKR Pump A RHR Hx A BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLO Hx RCDT Hx Seal Water Hx SFP Hx A SFP HxB RCP A Heat Load BTU/hr Heat Load BTU/hr Heat Load BTU/tu Heat Load BTU/hr Heat Load TU/hr Heat Load TU/hr Heat Load BTU/hr Heat Load BTU/hr KeatLoad BTU/hr Heat Load 8TU/hr Heat Load 8TU/hr Heat Load BTU/hr 15827000 15827000 2386000 2428000 1626000 1689000 15345000 15343000 367000 67817000 12536000 1871000 881000 13683000 367000 70000 Cate NSSSQG R2 81098000 Calculated Assumed BRS Skid Abandoned ln taco Assumed BRS Skid Abandoned ln lace Assumed BRS Skid Abandoned In tace Catculated Calculated 1890000 Calcutated 898000 Calculated 13680000 Calculated Secured 1/3 of WEC CQL4361 6/5/79 Valuo RCP B RCP C SFP HxC Heat Load TU/hr Heat Load BTU/hr Heat Load BTU/hr 367000 3G7000 367000 367000 367000 367000 0
1/3 of WEC CQL4361 6/5/79 Valuo 1/3 of WEC CQL~t 6/5/79 Valuo Sccurcd SFP Hx 0 GFFO Samplo Coolers CCW Trains CCW Hx Ht Out CCW Su Tem Design CCW Supply Tcm Heat Load BTU/hr Heat Load BTU/hr HeatLoad BTU/hr No Operating 8TU/hr (F) 1000000 1000000 105.1 105 103.8 105 42,913,000 36,852,000 2 (Split) 171,612,748 119.6/110.5 1000000 Fixed Consistent w/DBD-131 Calculated @ Node0011 Consistent w/ DBD-131 119.4 99.528.000 Calculated ESW Flow (Design)
Design Basis ESW Inlet Tcm Fuel Pool A/BTemp Fuel Pool A/BTemp Lfmt Fuel Pool C/O Temp Fuel Pool C/0 Temp Limit (gpm)
(F)
(F)
(F)
(F)
(F) 95 122.3 137.0 117.2 137.0 95 121.0 137.0 115.8 137.0 95 13G.O 137.0 134.0 137.0 137.0 133.3 137.0
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Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 8b Summary of CCXVS Steady-State Thernial Capacity Refuel Refuet Refuel LOCA LOCA Load RHR Pump B RHR Hx B RHR Pump A RKR HXA BRS: Dist Clr BRS: Evap Clr BRS: Vent Cond Letdown Hx XSLD Hx RCDT Hx Seal Water Hx SFP Hx A SFP Hx B RCP A
'I RCP B Units Meal Load BTU/lu Heal Load BTUhu Heat Load BTU/hr Heat Load BTU/hr Heat Load TU/hr Heat Load 8TU/hr Heat Load BTU/hr Heat Load BTU/hr Heat Load 8TU/hr Heat Load BTU/hr HeatLoad BTU/hr Keat Load BTU/lu
'eal Load BTU/hr Heat Load BTU/hr Heat Load BTU/hr Coro Shuffle 2394000 1673000 25271000 Full Offload Abnormal 70000 2249000 2248000 1498000 1497000 32121000 32122000 SI 15827000 2437000 1701000 15341000 Recirc (A)
Recirc (B) 70000 118077000 81336000 Refercnco Cato NSSS48 R2 Copulated Calo NSSS~ R2 Calculated Assumed 8RS Skid Abandoned In laco Assumed BRS Skid Abandoned In co Assumed BRS Stdd Abandoned ln taco Calculated Calculated Calculated Calculated Securod 1/3 ofWEC CQL4361 6/5/79 Valuo 1/3 ofWEC CQL~1 6/5/79 Valuo RCP C SFP Hx C SFP Hx D GFFD Heat Load BTU/hr HeatLoad BTUhu Keat Load BTU/hr Keel Load BTU/hr 1000000 1000000 367000 0
1/3 of WEC CQL<361 6/5/79 Valuo Secured Fixed Sampto Coolers CCW Trains CCW Hx KtDu HcalLoad 8TU/hr No Operating BTU/hr 31.258.000 0
2 (Split) 38.239.000 38.388.629 Split (1/I)
Split (I/1) 188.153.000 97,728,000 Consistent w/DBD-131 Calculated CCWSu I Tem Design CCW Supply Temp ESW Flow (Design)
Design Basis ESW Inlet Tem Fuel Pool A/B Temp Fuel Pool A/B Temp Umt Fuel Pool C/D Temp Fuel Pool C/D Temp Umit (F)
(gpm)
(F)
(F)
(F)
(F)
(F) 102.8 105 95 132.9 137.0 116.9 137.0 104.8 105 95 136.4 137.0 122.5 137.0 104.8/95.0 105 95 136,4 137.0 122.5 137.0 103.6 105 95 120.8 137.0 115.5 137.0 120.0 95 Isolated 137.0 Isolated 137.0 118.4 135.9 137.0 131.8 137.0 Calculated Node0011 Consistent w/ DBD-131
Computed by:
Jeff Lundy Checked by:
Date:
Date:
CAROLINAPOWER &LIGHTCOMPANY Calculation ID: SF-0040 Pg 3 I or 32 Rcv 0 Project No.:
CALCULATIONSHEET Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis 4.9 ESWS Hydraulic Margins Assumption 4.1.5 is critical to this analysis.
Table 14 of Rcfcrence (20) shows that thc minimum available ESWS flow to the CCW heat exchangers is 8797 gpm, including 4 percent ESWS model uncertainty and a single active failure, when operating on the Main Reservoir at the minimum design basis reservoir level. As the worst case calculated single failure flow exceeds the assumed minimum ESWS flow to the CCW heat exchangers, the assumption ofa minimum CCW heat exchanger flowof8500 gpm is considered to bc valid and achievable.
4.10 ESWS Ultimate Heat Sink Margins An evaluation of the available thermal and reservoir level margins was performed, Attachment (AA). The current UHS analysis of record, Reference (15), evaluated the time dependent effect of a design basis LOCA, given worst case historical mctcorological conditions of 9+1 days.
Reference (15) documents a means of evaluating the overall energy balance of thc HNP main and auxiliary reservoirs.
The results from Reference (15) are that the worst case UHS tcmperaturc is 94.2'F which occurs approximately 30 days after a design basis LOCA. The design temperature ofthe UHS is currently specified as 95'F, Reference (19).
The thermal margin ofthe UHS is defined as the difference between the heat rejected from the reservoir at the design temperature and the heat rejection at thc maximum estimated water temperature.
Using thc UHS heat loss relationship developed in Rcfcrcnce (15) and neglecting the thermal capacitance ofthe auxiliary rcscrvoir, it was determined, Attachment (AA),that the change in surface heat fluxwas 6.3 BTU/hr-'F-sq.fl
(-3.9 BTU/hr-sqft at 95'F and -10.2 BTU/hr-sqft at 94.2'F) due to a change in the reservoir surface temperature from 94.2'F to 95.0'F.
The change in heat flux accounts for changes in tlic convcctivc and evaporative heat fluxes which are a direct function of the reservoir surface temperature.
The change in the surface heat flux results in a change in the heat rejection capability of 85.17 MBTU/hr, given a reservoir surface" area of 1.3519E7 square feet at 249.6 fcct, Reference (15).
The activation of Spent Fuel Pools C and D results in an increase in CCWS and ESWS heat load of approximately 1.0 MBTU/hr, Reference (26). The availablc thermal margin of the Ultimate Heat Sink is 85. 17 MBTU/lu. The change in Ultimate Heat Sink peak tempcraturc is less than 0.01'F, Attachment (AA). It is concluded that the activation of Spent Fuel Pools C and D are within the current thermal capacity of the Ultimate Heat Sink and have a negligible impact on the design Ultimate Heat Sink temperature.
Reference (15) also evaluated the impact of a design basis LOCA on reservoir levels 30 days after the event which resulted in the Tcchnical Specification minimum UHS level rcquircments.
The reservoir temperature used in thc Reference (15) analysis was 95'F for conservatism in order to maximize thc surface evaporation rate.
Based on these considerations, the current UHS level requirements are not impacted so long as UHS thermal margin is available.
Computed by:
Jeff Lundy Checked by:
Project No.:
Date:
Date:
CAROLINAPOWER &LIGHTCOMPANY CALCULATIONSHEET Calculation ID: SI'-0040 Pg 32 of 32 Rev0 File:
Project
Title:
Spent Fuel Pools C and D Activation Project Calculation
Title:
Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis
5.0 CONCLUSION
S This analysis documents the estimated thermal and hydraulic margins in the CCW system, the ESW system and the UHS. It is concluded that sufficient thermal and hydraulic margins exist in the CCW and ESW systems to support the proposed CCWS tie-in for the Fuel Pool C/D heat cxchangers up to a maximum fuel pool C heat load of 1.0 MBTU/lu. It is further concluded that the availablc thermal margin in thc Ultimate Heat Sink is sufficient to accommodate the added Fuel Pool C/D heat load of 1.0 MBTU/hr which willhave a negligible impact on the design Ultimate Heat Sink temperature or level.
KNCj OSURE 4 to SKMAL: HNP-99-129 SHEARON HARRIS NUCLEARPOWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 RESPONSE TO NRC REQUEST FOR ADDITIONALINFORMATION REGARDING THE LICENSE AMENDMENTREQUEST TO INCREASE FUEL STORAGE CAPACITY Attachment Z to Calculation SF-0040 Evaluation of CCW System LOCA-Containment Sump Recirculation (RHR and SFP) Alignment Thermal Performance
ATTACHMENTZ TO CALCULATIONSF-0040, REVISION 0, EVALUATIONOF CCWV SYSTEM LOCA-CONTAINMENT SUMP RECIRCULATION(RHR ANDSFP) ALIGNMENT THERMALPERFORMANCE CP&L Calc ID: SP-0040
Attachment:
Z Rev: 0 Page 1 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 1
Carolina Power and Light - G:BCPL>HARRIS<SFPMOD>CCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Calculation Summary Report LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Utility:
Plant:
System:
Version:
Fluid:
Case Alignment:
Carolina Power and Light Harris Nuclear Plant Component Cooling Water System Revision 2 Fresh Water LOCA: Recirc (RHR and SFP Cooling)
System was NOT Balanced to Balancing Parameters Calculation was completed:
06-08-1998 16:38 Pressure Tolerance Sum of Flows Tolerance:
Friction Factor Tolerance:
Fixed Flow Tolerance:
Pressure Control Tolerance:
Temperature Tolerance:
0.0000100 0.0100000 0.0000010 0.0001000 0.0010000 0.0050000 Calculation
Description:
Revision 0:
Added Throttle Valves and Thermal Models. See CC-0039 Rev 0 dated 10/15/97 Revision 1:
Added alignments for Normal Ops, Hot Shutdown (350F), Cold Shutdown (200F),
Safe Shutdown (350F), Safe Shutdown (200F), 1/3 Core ShuNe Refueling, Full Core ONoad Refueling, Abnormal Full Core ONoad, LOCA (Sl/Recirculation Phases)
Added SWEC proposed CCW tie-in for SFP Hxs C and D.
Added Simulated Fuel Pool Cooling Systems for Fuel Pools A/B and C/D to provide pool equilibrium temperatures.
Additional nodes and valves are designed by Altxxx tags.
SFP Hx C and D models are equivalent to SFP Hx A and B models.
Determined RHR Flow = 3903 gpm (1.846E6 Ibm/hr) at 244.1F during Post LOCA Recirculation per HNP Gale NSSS-38 Rev 2 dtd 4/30/97.
Assume Sl Signal Isolates GFFD and Sample Coolers and starts B CCW Pump.
Phase A Containment Isolation signal isolates XSLD and RCDT heat exchangers.
Phase B Containment Isolation signal isolates RCP supply and return headers.
Added TEMP1 simulation valve to eliminate low flow instability problem. This does not effect the results but signficantly improves the model computational efficiency.
Assume Post LOCA Recirc:
CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 2 of 41
A SFP Hx CCW flow throttled as necessary to maintain RHR Hx Flow above 5600 gpm.
Added LOCA Isolate simulation valve to model.
Deleted MiscK = 1100 in Pipe Section 64. Balanced each BRS heat exchanger to measured values.
Throttle valve positions are:
1CC-356 = 24.17%
1CC-353 = 0.75%
1CC-363 = 20.56%
Assumes BRS Skid is Abandoned ln Place Per Direction from CCW System Engineer at CPBL meeting on 11/25/97.
Added BRSEC Isolation Valve to Pipe Sections 64 and 85. Deleted BRS Skid Heat Loads from all alignments.
Added 10% Degraded CCW Pump Curves Per HNP Gale HNP-M/MECH-1011 Rev 2 dtd 5/10/97.
Eliminated flow recirculation through the expansion tank by changing Node0001 to an in-line pressure node with applied pressures of 42.04 psia. Changed Node0025 to a free flow node.
Deleted nodes Fixed1 and Fixed2 and pipe sections 1 and 26.
This change is necessary to eliminate inaccuracies in the system thermal balance.
Revision 2:
Changed Node00026 to In-line Pressure Node for Split System Ops with an applied pressure of 42.04 psia.
Added CCW Suction and Discharge Header Cross Tie Isolation Valves to Simulate Split CCW Trains when Both RHR Hxs are operating per OP145 Section 8.9 Rebalanced CCWS for SFP C/D Activation as of 12/2001.
CF&LCalc ID: SF-0040
Attachment:
Z Rev:
0 Page 3 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:BCPL>HARRIS>SFPMOD>CCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Calculation Summary Report LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Summary of Flagged Conditions for Current Calculation Page 3 Pipe:116.00 Node0106 - Node0104 Pipe:120.00 Node0212 - Node0210 Pipe:121.00 Node0212 - Node0214 Pipe:312.00 AltN7-AltN10 Pipe:901.00 FP3 - FP1 DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible CP&L Calc ID: SF-0040
Attachment:
Z Rev. 0 Page 4 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL>HARRIS>SFPMOD>CCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0E-4 PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 1
Pipe:
2.00 ID =
12.000 Flow =
4,473.01 Vel =
12.690 Turbulent f= 0.0133 Reynold's Number = 2.6502E+06 N1: Node0001
'* Press=
41.98 Elev= 247.00 Flow= 0.00 N2: Node0002 Press=
39.67 Elev= 250.62 Flow= 0.00 Pipe:
3.00 ID =
17.250 Flow =
8,099.73 Vel =
11.120 Turbulent f = 0.0125 Reynold's Number = 3.1832E+06 N1: Node0002 Press=
39.67 Elev= 250.62 Flow= 0.00 N2: Node0003 Press=
38.99 Elev= 250.75 Flow= 0.00 Pipe: 4.00 ID =
17.250 Flow =
8,099.73 Vel =
11.120 Turbulent f = 0.0125 Reynold's Number = 3.1832E+06 N1: Node0003 Press=
38.99 Elev= 250.75 Flow= 0.00 N2: Node0004 Press=
42.74 Elev= 238.72 Flow= 0.00 Temp=
154.20 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
142.04 Pipe:
5.00 ID =
15.250 Flow =
8,099.73 N1: Node0004 Press=
42.74 N2: Node0005 Press=
123.88 NPSHA = 93.00 Elev= 238.72 Flow= 0.00 Elev= 238.59 Flow= 0.00 Temp=
142.04 Temp=
142.04 Pipe:
6.00 ID =
17.250 Flow =
8,099.73 Vel =
11.120 Turbulent f = 0.0125 Reynold's Number = 3.1832E+06 N1: Node0005 Press=
123.88 Elev= 238.59 Flow= 0.00 N2: Node0006 Press=
118.12 Elev= 248.30 Flow= 0.00 Pipe:
7.00 ID =
17.250 Flow =
8,099.73 Vel =
11.120 Turbulent f = 0.0125 Reynold's Number = 3.1832E+06 N1: Node0006 Press=
118.12 Elev= 248.30 Flow= 0.00 N2: Node0007 Press=
116.24 Elev= 250.63 Flow= 0.00 Pipe:
8.00 ID =
17.250 Flow =
8,099.73 Vel =
11.120 Turbulent f = 0.0125 Reynold's Number = 3.1832E+06 N1: Node0007 Press=
116.24 Elev= 250.63 Flow= 0.00 N2: Node0008 Press=
117.97 Elev= 245.00 Flow= 0.00 Pipe:
9.00 ID =
23.250 Flow =
8,072.11 Vel = 6.100 Turbulent f = 0.0122 Reynold's Number = 2.1309E+06 N1: Node0008 Press=
117.97 Elev= 245.00 Flow= 0.00 N2: Node0009 Press=
112.42 Elev= 244.67 Flow= 0.00 Pipe:
10.00 ID =
17.250 Flow =
8,046.97 Vel =
11.048 Turbulent f= 0.0126 Reynold's Number = 2.5717E+06 N1: Node0009 Press=
112A2 Elev= 244.67 Flow= 0.00 N2: Node0010 Press=
106.90 Elev= 250.69 Flow= 0.00 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
142.04 Temp=
118.02 Temp=
118.02 Temp=
118.02 l! Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%% Pressure Below Vapor Pressure
'l2 Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 5 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 I
I
~l
~
~~
I
~~
~
~
~
~
I Carolina Power and Light - G:BCPL)HARRIS>SFPMOD>CCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 2 Pipe:
11.00 ID =
17.250 Flow =
3,611.25 Vel = 4.958 Turbulent f = 0.0132 Reynold's Number = 1.1541E+06 N1: Node0010 Press=
106.90 Elev= 250.69 Flow= 0.00 N2: Node0011 Press=
106.74 Elev= 250.71 Flow= 0.00 Pipe:
19.00 ID =
17.250 Flow =
3,627.09 Vel = 4.980 Turbulent f = 0.0131 Reynold's Number = 1.3411E+06 N1: Node0028 Press=
39.71 Elev= 250.62 Flow= 0.00 N2: Node0002 Press=
39.67 Elev= 250.62 Flow= 0.00 Pipe:
21.00 ID =
17.250 Flow =
3,619.68 Vel = 4.969 Turbulent f = 0.0132 Reynold's Number = 1.2556E+06 N1: Node0027 Press=
40.04 Elev= 250.70 Flow= 0.00 N2: Node0028 Press=
39.71 Elev= 250.62 Flow= 0.00 Pipe:
22.00 ID =
19.250 Flow =
3,619.68 Vei =
3.991 Turbulent f = 0.0131 Reynold's Number = 1.1251E+06 N1: Node0306 Press=
40.14 Elev= 250.68 Flow= 0.00 N2: Node0030 Press=
40.09 Elev= 250.68 Flow= 0.00 Pipe:
35.00 ID =
19.250 Flow =
3,611.25 Vel =
3.981 Turbulent f = 0.0132 Reynold's Number = 1.0342E+06 N1: Node0024 Press=
106.65 Elev=
250.71 Flow= 0.00 N2: Node0301 Press=
106.59 Elev= 250.67 Flow= 0.00 Pipe:
37.00 ID =
12.000 Flow =
4,435.72 Vel =
12.584 Turbulent f = 0.0134 Reynold's Number = 2.0378E+06 N1: Node0010 Press=
106.90 Elev= 250.69 Flow= 0.00 N2: Node0101 Press=
107.05 Elev= 246.97 Flow= 0.00 Pipe:
38.00 ID =
19.250 Flow =
3,611.25 Vel =
3.981 Turbulent f = 0.0132 Reynold's Number = 1.0342E+06 Ni: Node0011 Press=
106.74 Elev= 250.71 Flow= 0.00 N2: Node0024 Press=
106.65 Elev= 250.71 Flow= 0.00 Pipe:
51.00 ID =
19.250 Flow =
3,619.68 Vel =
3.991 Turbulent f= 0.0131 Reynold's Number = 1.1251E+06 N1: Node0030 Press=
40.09 Elev= 250.68 Flow= 0.00 N2: Node0027 Press=
40.04 Elev= 250.70 Flow= 0.00 Pipe:
52.00 ID =
19.250 Flow =
3,611.25 Vel =
3.981 Turbulent f = 0.0132 Reynold's Number = 1.0342E+06 N1: Node0301 Press=
106.59 Elev= 250.67 Flow= 0.00 N2: Node0307 Press=
107.22 Elev= 248.81 Flow= 0.00 Temp=
118.02 Temp=
118.02 Temp=
127.10 Temp=
142.04 Temp=
127.10 Temp=
127.10 Temp=
127.10 Temp=
127.10 Temp=
118.02 Temp=
118.02 Temp=
118.02 Temp=
118.02 Temp=
118.02 Temp=
118.02 Temp=
127.10 Temp=
127.10 Temp=
118.02 Temp=
118.02 II Reverse Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
/o'/o Pressure Below Vapor Pressure V2 Temperature Outside Fluid Property Range PO NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev:
0 Page 6 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial 5PFL-0000 Carolina Power and Light - G:BCPL)HARRIS<SFPMOD>CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EC PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
'age3 Pipe:
59.00 ID =
19.250 Flow=
3,619.68 Vel =
3.991 Turbulent f = 0.0131 Reynold's Number = 1.1251E+06 N1: Node0310 Press=
41.13 Elev= 248.83 Flow= 0.00 N2: Node0306 Press=
40.14 Elev= 250.68 Flow= 0.00 Pipe:
63.00 ID =
19.250 Flow =
3,611.25 Vel =
3.981 Turbulent f = 0.0132 Reynold's Number = 1.0342E+06 Ni: Node0307 Press=
107.22 Elev=
248.81 Flow= 0.00 N2: Node0311 Press=
107.16 Elev= 248.83 Flow= 0.00 Pipe:
86.00 ID =
19.250 Flow =
3,619.68 Vel =
3.991 Turbulent f = 0.0131 Reynold's Number = 1.1251E+06 Ni: Node0328 Press=
41.91 Elev=
247.31 Flow= 0.00 N2: Node0310 Press=
41.13 Elev= 248.83 Flow= 0.00 Pipe:
87.00 ID =
17.250 Flow =
3,619.68 Vel = 4.969 Turbulent f = 0.0132 Reynold's Number = 1.2556E+06 N1: AltN12 Press=
42.07 Elev= 247.36 Flow= 0.00 N2: Node0328 Press=
41.91 Elev=
247.31 Flow= 0.00 Temp=
127.10 Temp=
127.10 Temp=
118.02 Temp=
118.02 Temp=
127.10 Temp=
127.10 Temp=
127.10 Temp=
127.10 Pipe:
88.00 ID =
17.250 Flow =
3,611.25 Vel = 4.958 Turbulent f= 0.0132 Reynold's Number = 1.1541E+06 N1: Node0311 Press=
107.16 Elev= 248.83 Flow= 0.00 N2: AltN1 Press=
108.20 Elev= 245.34 Flow= 0.00 Pipe:
96.00 ID =
13.250 Flow=
3,449.64 Vel = 8.027 Turbulent f= 0.0134 Reynold's Number = 1.5554E+06 N1: Node0210 Press=
46.83 Elev= 238.01 Flow= 0.00 N2: Node0211 Press=
46.72 Elev= 238.09 Flow= 0.00 Pipe:
97.00 ID =
13.250 Flow =
3,465.21 Vel = 8.063 Turbulent f = 0.0134 Reynold's Number = 1.5624E+06 N1: Node0209 Press=
103.27 Elev= 243.48 Flow= 0.00 N2: Node0212 Press=
102.01 Elev= 237.99 Flow= 0.00 Pipe:
98.00 ID =
13.250 Flow =
3,461.18 Vel = 8.054 Turbulent f = 0.0134 Reynold's Number = 1.5000E+06 N1: Node0208 Press=
108.38 Elev= 243.58 Flow= 0.00 N2: Node0209 Press=
103.27 Elev= 243.48 Flow= 0.00 Pipe:
99.00 ID =
13.250 Flow =
3,457.30 Vel = 8.045 Turbulent f = 0.0135 Reynold's Number = 1.4385E+06 N1: Node0207 Press=
107.64 Elev= 245.33 Flow=
0.00 N2: Node0208 Press=
108.38 Elev= 243.58 Flow= 0.00 Temp=
118.02 Temp=
118.02 Temp=
126.93 Temp=
126.93 Temp=
126.93 Temp=
126.93 Temp=
118.02 Temp=
126.93 Temp=
118.02 Temp=
118.02
!! Reverso Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
/o/o Pressure Below Vapor Pressure
'?'? Temperature Outside Fluid Property Range
¹4 NPSHA less than NPSHR
&8 Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 7 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:ECPLIHARRIStSFPMOD'tCCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 4 Pipe:
100.00 ID =
13.250 Flow =
3,457.30 Vel = 8.045 Turbulent f = 0.0135 Reynold's Number = 1.4385E+06 N1: Node0201 Press=
107.93 Elev= 245.33 Flow= 0.00 N2: Node0207 Press=
107.64 Elev= 245.33 Flow= 0.00 Pipe:
111.00 ID =
12.000 Flow =
4,429.48 Vel =
12.566 Turbulent f = 0.0134 Reynold's Number = 2.0349E+06 N1: Node0101 Press=
107.05 Elev= 246.97 Flow= 0.00 N2: Node0102 Press=
97.40 Elev= 262.35 Flow= 0.00 Pipe:
112.00 ID =
17.250 Flow=
4,450.86 Vel =
6.111 Turbulent f= 0.0129 Reynold's Number = 1.6670E+06 N1: Node0102 Press=
97.40 Elev= 262.35 Flow= 0.00 N2: Node0103 Press=
89.88 Elev=.243.78 Flow= 0.00 Pipe:
113.00 ID =
12.000 Flow =
4,449.32 Vel =
12.623 Turbulent f = 0.0133 Reynold's Number = 2.7605E+06 N1: Node0115 Press=
88.24 Elev= 243.81 Flow= 0.00 N2: Node0116 Press=
48.66 Elev= 244.98 Flow= 0.00 Temp=
118.02 Temp=
1'18.02 Temp=
118.02 Temp=
118.02 Temp=
118.02 Temp=
154.22 Temp=
154.22 Temp=
154.22 Pipe:
114.00 ID =
2.067 Flow =
6.24 Vel = 0.597 Turbulent f = 0.0286 Reynold's Number = 1.6648E+04 N1: Node0101 Press=
107.05 Elev= 246.97 Flow= 0.00 N2: Node0105 Press=
128.04 Elev=
197.53 Flow= 0.00 Temp=
118.02 Temp=
118.02 Pipe:
115.00 ID =
0.824 Flow =
6.26 Vel = 3.767 Turbulent f= 0.0268 Reynold's Number = 4.6345E+04 N1: Node0105 Press=
128.04 Elev=
197.53 Flow= 0.00 N2: Node0106 Press=
126.95 Elev=
198.68 Flow= 0.00 Pipe:
116.00 ID= 2.067 Flow=
6.29 Vel= 0.602 Turbulent f = 0.0272 Reynold's Number = 2.1528E+04 N1: Node0106 Press=
126.95 Elev=
198.68 Flow= 0.00 N2: Node0104 Press=
42.54 Elev= 247.00 Flow= 0.00 Temp=
118.02 Temp=
140.62 Temp=
140.62 Temp=
154.20 Pipe:
117.00 ID =
12.000 Flow =
4,481.53 Vel =
12.714 Turbulent f = 0.0133 Reynold's Number = 2.7801E+06 N1: Node0104 Press=
42.54 Elev= 247.00 Flow= 0.00 N2: Node0001
- Press=
41.98 Elev= 247.00 Flow= 0.00 Pipe:
120.00 ID =
13.250 Flow =
3,449.64 Vel = 8.027 Turbulent f = 0.0134 Reynold's Number = 1.5554E+06 N1: Node0212 Press=
102.01 Elev= 237.99 Flow= 0.00 N2: Node0210 Press=
46.83 Elev= 238.01 Flow= 0.00 Temp=
154.20 Temp=
154.20 Temp=
126.93 Temp=
126.93
!! Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%% Pressure Betow Vapor Pressure
'?? Temperature Outside Fiuid Property Range
¹¹ NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 8 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:<CPL'tHARRIStSFPMOD'tCCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EQ PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 5 Pipe:
121.00 ID =
0.824 Flow=
15.57 Vel =
9.367 Turbulent f = 0.0250 Reynold's Number = 1.1288E+05 N1: Node0212 Press=
102.01 Elev= 237.99 Flow= 0.00 N2: Node0214 Press=
47.79 Elev= 236.74 Flow= 0.00 Pipe:
123.00 ID=
1.049 Flow=
15.57 Vel= 5.780 Turbulent f = 0.0242 Reynold's Number = 8.8665E+04 N1: Node0214 Press=
47.79 Elev= 236.74 Flow= 0.00 N2: Node0215 Press=
47.60 Elev= 236.74 Flow= 0.00 Temp=
126.93 Temp=
126.93 Temp=
126.93 Temp=
126.93 Pipe:
124.00 ID =
1.049 Flow= -15.57 Vel = -5.780 Turbulent f= 0.0242 Reynold's Number = 8.8665E+04 N1: Node0211 Press=
46.72 Elev= 238.09 Flow= 0.00 N2: Node0215 Press=
47.60 Elev= 236.74 Flow= 0.00 Pipe:
125.00 ID =
13.250 Flow=
3,465.21 Vel = 8.063 Turbulent f = 0.0134 Reynold'umber = 1.5624E+06 N1: Node0211 Press=
46.72 Elev= 238.09 Flow= 0.00 N2: Node0206 Press=
46.52 Elev= 238.09 Flow= 0.00 Temp=
126.93 Temp=
126.93 Temp=
126.93 Temp=
126.93 Pipe:
130.00 ID =
12.000 Flow =
4,475.25 Vel =
12.696 Turbulent f = 0.0133 Reynold's Number = 2.7766E+06 N1: Node0103 Press=
89.88 Elev= 243.78 Flow= 0.00 N2: Node0115 Press=
88.24
~
Elev=
243.81 Flow= 0.00 Pipe:
131.00 ID =
12.000 Flow =
4,475.24 Vel =
12.696 Turbulent f = 0.0133 Reynold's Number = 2.7764E+06 N1: Node0116 Press=
48.66 Elev= 244.98 Flow= 0.00 N2: Node0104 Press=
42.54 Elev= 247.00 Flow= 0.00 Pipe:
133.00 ID =
1.049 Flow =
25.94 Vel = 9.630 Turbulent f = 0.0232 Reynold's Number = 1.8410E+05 N1: Node0115 Press=
88.24 Elev= 243.81 Flow= 0.00 N2: Node0116 Press=
48.66 Elev= 244.98 Flow= 0.00 Pipe:
300.00 ID =
17.250 Flow =
153.95 Vel =
0.211 Turbulent f = 0.0213 Reynold's Number = 4.9199E+04 Press=
108.20 Elev= 245.34 Flow= 0.00 Press=
108.20 Elev= 245.34 Flow= 0.00 Pipe:
301.00 ID =
17.250 Flow =
153.95 Vel =
0.211 Turbulent f = 0.0213 Reynold's Number = 4.9199E+04 Press=
108.20 Elev= 245.34 Flow= 0.00 Press=
108.20 Elev= 245.34 Flow= 0.00 Temp=
154.22 Temp=
154.22 Temp=
154.22 Temp=
154.20 Temp=
154.22 Temp=
154.22 Temp=
118.02 Temp=
118.02 Temp=
118.02 Temp=
118.02 l! Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%% Pressure Below Vapor Pressure
'?? Temperaturo Outside Fluid Property Range
¹¹ NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 9 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL>HARRIS>SFPMOD>CCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence:
Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EQ PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 6 N1: AltN5 N2: AltN7 Pipe:
305.00 ID =
13.250 Flow=
154.20 Vel = 0.359 Turbulent f = 0.0201 Reynold's Number = 6.8100E+04 Press=
108.20 Elev= 245.34 Flow= 0.00 Press=
108.19 Elev= 245.34 Flow= 0.00 Temp=
118.02 Temp=
131.13 N1: AltN5 N2: AltN3 Pipe:
306.00 ID =
13.250 Flow= -153.95 Vel = -0.358 Turbulent f = 0.0203 Reynold's Number = 6.4052E+04 Press=
108.20 Elev= 245.34 Flow= 0.00 Press=
108.20 Elev= 245.34 Flow= 0.00 Temp=
118.02 Temp=
118.02 Pipe:
310.00 ID =
13.250 Flow =
154.47 Vel = 0.359 Turbulent f= 0.0199 Reynold's Number = 7.2229E+04 N1: AltN10 Press=
43.08 Elev= 245.00 Flow= 0.00 N2: AltN11 Press=
43.08 Elev= 245.00 Flow= 0.00 Pipe:
311.00 ID =
17.250 Flow =
154.39 Vel = 0.212 Turbulent f= 0.0209 Reynold's Number = 5.4500E+04 Press=
43.08 Elev= 245.00 Flow= 0.00 Press=
42.07 Elev= 247.36 Flow= 0.00 Temp=
131.13 Temp=
131.13 Temp=
131.13 Temp=
127.10 Pipe:
312.00 ID =
13.250 Flow =
154.47 Vel = 0.359 Turbulent f= 0.0199 Reynold's Number = 7.2229E+04 N1: AitN7 Press=
108.19 Elev= 245.34 Flow= 0.00 N2: AltN10 Press=
43.08 Elev= 245.00 Flow= 0.00 Pipe:
315.00 ID=
13.250 Flow=
3,465.29 Vel= 8.064 Turbulent f = 0.0135 Reynold's Number = 1.5637E+06 N1: Node0206 Press=
46.52 Elev= 238.09 Flow= 0.00 N2: AltN12 Press=
42.07 Elev= 247.36 Flow= 0.00 Temp=
131.13 Temp=
131.13 Temp=
126.93 Temp=
127.10 Pipe:
319.00 ID =
17.250 Flow =
3,457.30 Vel = 4.747 Turbulent f= 0.0134 Reynold's Number = 1.1049E+06 Press=
108.20 Elev= 245.34 Flow= 0.00 Press=
107.93 Elev= 245.33 Flow= 0.00 Temp=
118.02 Temp=
118.02 Pipe:
900.00 ID =
9.750 Flow =
3,749.84 NPSHA = 228.10 N1: FP1
- Press=
100.00 Elev= 0.00 Flow= 0.00 N2: FP2 Press=
228.18 Elev= 0.00 Flow= 0.00 Temp=
135.68 Temp=
127.47 Pipe:
901.00 ID =
17.124 Flow =
3,749.84 Vel =
5.224 Turbulent f = 0.0132 Reynold's Number = 1.3619E+06 N1: FP3 Press=
228.18 Elev= 0.00 Flow= 0.00 N2: FP1
- Press=
100.00 Elev= 0.00 Flow= 0.00 Temp=
127.47 Temp=
135.68 II Reverse Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
%% Pressure Below Vapor Pressure YE Temperature Outside Fluid Property Range
¹¹ NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 10 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:>CPL<HARRIS>SFPMOD>CCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 7 Pipe:
902.00 ID= 9.750 Flow=
3,745.67 Vel=
16.097 Turbulent f= 0.0140 Reynold's Number = 2.3061E+06 Press=
228.18 Elev= 0.00 Flow= 0.00 Press=
228.18 Elev= 0.00 Flow= 0.00 Temp=
127.47 Temp=
127.47 ll Reverso Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
%% Pressure Below Vapor Pressure
'?'P Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR 8 8 Flow Past End of Pump Curve CP8t:L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 11 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - GACPLFHARRISLSFPMODLCCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Pump Status Report LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 1
Pump Name Pump Name Pump Name Pump Name Manufacturer Model Manufacturer:
Model:
Pump2 Drawings:
Pump Status:
OFF Speed (RPM>:
Hydraulic Horsepower:
Pump Impeller Datum (ft)
Pump Suction Temperature ('F NPSH Curve:
NONE NPSH Available:
Head (ft):
Flow (gpm):
Inlet Node Elevation (ft):238.74 NPSH Required:
Manufacturer:
Model:
Pump3 Drawings:
Pump Status:
OFF Speed (RPM):
Hydraulic Horsepower:
Pump Impeller Datum (ft)
Pump Suction Temperature ('F NPSH Curve:
NONE NPSH Available:
Head (ft):
Flow (gpm):
Inlet Node Elevation (ft):238.73 NPSH Required:
Model:
Manufacturer FP1 Drawings:
Pump Status:
DummySFPCPump Speed (RPM):
Flow (gpm):
3,749.84 Hydraulic Horsepower:
280.42 Pump Impeller Datum (ft)
Pump Suction Temperature ('F 135.68 NPSH Curve: 'ONE NPSH Available:
228.10 NPSH Required:
Head (ft):
300.01 Inlet Node Elevation (ft):
Pump1 Drawings:
Pump Status:
Pump1DegradedCurve Speed (RPM):
Flow (gpm):
8,099.73 Head (ft):
190.36 Hydraulic Horsepower:
383.20 Pump Impeller Datum (ft)
Inlet Node Elevation (ft):238.72 Pump Suction Temperature ('F 142.04 NPSH Curve:
NONE NPSH Available:
93.00 NPSH Required:
CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 12 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial IIIIPFL-0000 Carolina Power and Light - G:<CPL)HARRIS>SFPMOD<CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Pump Status Report LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 2 Manufacturer:
Model:
Head (ft):
Flow (gpm):
Inlet Node Elevation (ft):
NPSH Required:
Pump Name:
FP2 Drawings:
Pump Status:
OFF Speed (RPM):
Hydraulic Horsepower:
Pump Impeller Datum (ft)
Pump Suction Temperature ('F NPSH Curve:
NONE NPSH Available:
COL Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 13 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL'tHARRIS'tSFPMOD'tCCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Manual Valve Line-Up Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 1
Tag ValveType Position Actual **
1CC-146 1CC-155 1CC-166 1CC-187 1CC-197 1CC-323 1CC-353 1CC-356 1CC-363 1CC-382 1CC-398 A RHR OUTLET AHXlsol AitV1 AitV10 Altv11 AitV12 AitV13 AitV14 AitV15 AitV2 AitV4 AitV5 AltV6 AltV7 AltV8 AitV9 B SFPC HX BRSEC BRSEC CCW B/C SUCT CCW PUMP B/C Closed Closed DischXTie LOCA Isolate LOCA Isolate LOCA Isolate LOCA Isolate P1lsolate P1lsoiate RCP IN RCP OUT RHR A BYPASS RHR B BYPASS RHR B OUTLET SFPC HX FD Butterfly Globe Butterfly Globe Globe Globe Globe Globe Butterfly Butterfly Butterfly Gate Gate Gate Butterfly Butterfly Gate Gate Butterfly Butterfly Butterfly Gate Gate Butterfly Butterfly Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate 0
47 91%
3.93%
48.61%
41.98%
12.90%
41.32%
0 75%
24.17%
20.56%
28.42%
28.42%
100.00%
100 00%
0.00%
0.00%
2 09%
0.00%
P PP%
100 00%
2.09%
100.00%
ppp 0.00%
100.00%
0.00%
100.00%
100.00%
P PP%
0.00%
P PP%
0.00%
P PP%
P PP%
P P0%
ppp P PP%
0.00%
P PP%
ppp 0.00%
ppp P PP%
P PP%
1PP PP P PP%
P PP%
P PP%
- 'ctual Position for Partially Open Check Valves CF&LCalc ID: SF-0040
Attachment:
Z Rev:
0 Page 14 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:BCPL)HARRIS>SFPMODtCCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Manual Valve Line-Up Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EQ PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 2 Tag ValveType Position Actual **
SuctionXTie TEMP1 XSLD HX Gate Gate Gate P PP%
P PP%
P PP%
- 'ctual Position for Partially Open Check Valves CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 15 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:ttCPL>HARRIS<SFPMOD>CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 1
ag:
is oo er ype:
ixe ea oa Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr a us 1,000,000.00BTU/hr CP&L Calo ID: SF-0040
Attachment:
Z Rev: 0 Page 16 of 41 FIX'Tag: BRS~vap Cooner I
ype:
axe ea Loa~X Status: 0 Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr FIIITag: BRS Veen Conrnt XTyype:
'rxedTl~ea Loaol FIXStatus:
Ol Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr Fl~ag: CCWTtxA FIX'Type:
SWe u e XSt~aus: On/tnFlowPat Mfr: Westinghouse Model: 64-396 Dwgs: Spec Sht AH-CC-657 Tube Fluid: Fresh Water Shell Fluid: Fresh Water Shell Flow = 8,072.11 Shell Temperatures
= 142.04'F - 118.02'F Tube Flow = 8,500.00 Tube Temperatures
= 95.00'F - 117.82'F 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 5.9840 ft"2, Design Shell Velocity = 3.400 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft*2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 33.00 ft, K = 26.00 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 3,668 of 3,663 Tubes Active UTubes = No Effective Area = 23,341.00 ft"2 Area Factor = 0.9821 Fouling = 0.0000 (inside) 0.0025 (outside)
Hoff= 0.5906 LMTD= 23.6137 LMTDCorrections FF = 0.8063 Fb = 1.0000 Heat Load =
96,923,543.72BTU/hr UOverall = 218.09 BTU/hr/ft"2/'~ag:
CCSIFRxB FIX Type:
SMe u e Mfr: Westinghouse Model: 640396 Dwgs: Spec Sht AH-CC-657 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 5.9840 ftA2, Design Shell Velocity = 3.400 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 33.00 ft, K = 26.00 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 3,668 of 3,668 Tubes Active UTubes = No Effective Area = 23,341.00 ft"2 Area Factor = 0.9821 Fouling = 0.0000 (inside) 0.0025 (outside)
Hoff= 0.5892 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F Mfr:
Model:
Dwgs:
System Fluid: Fresh Water Tube Flow = 3,749.84 Tube Temperatures
127.47'F - 135.68'F Heat Load
15,200,000.00BTU/hr RXTaag:
uelPnoOC1D ype:
rxe ea oa~XB&aus:
On FRonrn Ffouwsat Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:ECPLEHARRIS)SFPMODtiCCNCCW2.PDB - Revision 2 Harris Nuclear Plant-Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-S Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EQ PCV=1.0E-3 Temperature=S.OE-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 2 aus:
n o in ow a
Dwgs: Dwgf/5428 Rev 1 Shell Fluid: Fresh Water ype:
ixe ea oa Model:
Dwgs Dwgs ICrag: RCPSTIIermBaarl ype:
rxe ea
~oa RX S&aus 0
Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr ag:
x ype:
e u e Mfr: Joseph Oat Model: 22-165/BFU Tube Fluid: Fresh Water 1 Shells, 1 Shell Passes, 8 Tube Passes Shell Min Area = 0.6460 ft"2, Design Shell Velocity = 3.800 ft/s, Shell Diameter = 0.000 Baffle Info: Spacing = 0.000 in, Thickness = 0.500 in, Area = 25.210 ft"2, K = 9.400 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 28.03 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 142 of 142 Tubes Active UTubes = Yes Effective Area = 780.00 ft"2 Area Factor = 0.9981 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.7164 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F RXTag: RCD x
X S&aus:
OnnriloOin Flow Oat Mfr: Atlas Model: 12-144/BEU Dwgs: Spec Sht RC-632 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 4 Tube Passes Shell Min Area = 0.0960 ft"2, Design Shell Velocity = 5.186 ft/s, Shell Diameter = 0.000 Baffle Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 24.32 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 40 of 40 Tubes Active UTubes = Yes Effective Area = 189.00 ft*2 Area Factor = 0.9895 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.7104 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F RICTag: RCPaCwWr31rCIrrl ype:
rxe ea oacalX SIaaus: 0 Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr Fl ag:
a pr iTCr a us:
Mfr:
System Fluid:
Heat Load =
0.00BTU/hr FIK1ag:
RCPSCwWryrIC~r ype:
rxe ea oa a us:
Mfr:
Model:
System Fluid:
Heat Load =
0.00BTU/hr R
CP&L Cate ID: SF-0040
Attachment:
Z Rev: 0 Page 17 of 41
06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL)HARRIS>SFPMOD>CCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition)
Page 3 pr i
r ype:
ixe Model:
ag:
Mfr:
System Fluid:
Heat Load =
0.00BTU/hr FIX~ag: RCpcCwr01rClrrr ype:
ixe Mfr:
Model:
System Fluid:
Heat Load =
0.00BTU/hr ea oa ea oa Dwgs:
a us:
cgreece: 0 Dwgs:
Model:
Dwgs:
ype:
ixe ea oa Model:
Tube Temperatures
= 118.02'F - 140.62'F 70,000.00BTU/hr CP6Q. Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 18 of 41 RX'Tag: RCPcThermgaarl Mfr:
System Fluid:
Heat Load =
O.OOBTU/hr FIX Tag: RCPcoprOtIC r
~raaue:
0 Mfr:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr X S&aus:
On / in Flow Pat Mfr: Joseph Oats Model: RS-628/BEU Dwgs: 5443 and 5444 Tube Fluid: Fresh Water Shell Fluid: Fresh Water Shell Flow = 4,450.86 Shell Temperatures
= 118.02'F - 154.22'F Tube Flow = 3,903.00 Tube Temperatures
= 209.00'F - 167.89'F 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 1.4120 ft"2, Design Shell Velocity = 8.830 ft/s, Shell Diametei = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 76.97 ft, K = 9.40 Tube Pitch = 0.9688 in Tube Pitch Type = Triangular 592 of 592 Tubes Active UTubes = Yes Effective Area = 4,280.00 ft"2 Area Factor = 0.4784 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.4741 LMTD= 52.2863 LMTDCorrections FF = 0.9015 Fb = 1.0000 Heat Load =
80,528,980.48BTU/hr UOverall = 399.16 BTU/hr/ft"2/'fr:
Jospeh Oats Model: RS-628 Dwgs: 5443 and 5444 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 1.4120 ft"2, Design Shell Velocity = 8.830 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 76.97 ft, K = 9.40 Tube Pitch = 0.9688 in Tube Pitch Type = Triangular 592 of 592 Tubes Active UTubes = Yes Effective Area = 4,280.00 ft*2 Area Factor = 0.4784 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.4741 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
O.OOBTU/hr UOverall = 0.00 BTU/hr/ft"2/'F RXTag: RFIR Pmp KC r Mfr:
Model:
Dwgs:
System Fluid: Fresh Water Tube Flow = 6.26 Heat Load =
Carolina Power and Light - G."BCPL>HARRIS>SFPMOD)CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition) a us ag:
Mfr:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr BXTag: SeeaW~rx ype: WerS~ueB X S~aus:
On/igoTin Flow Pal Illp r
Mfr: Altas Model: 20-128/BEU Dwgs: SW-627 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 8 Tube Passes Shell Min Area = 0.1530 ft"2, Design Shell Velocity = 3.375 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 21.82 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 110 of 110 Tubes Active UTubes =Yes Effective Area = 460.00 ft"2 Area Factor = 0.9761 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.6951 LMTD = 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F HXTag: SFP~xA HXTyype: "WelirTugeelX Sfalus:
On lin FloOwal Mfr: Yuba Model: 39-285/CEN Dwgs: EA1ABCD Tube Fluid: Fresh Water Shell Fluid: Fresh Water Shell Flow = 3,461.18 Shell Temperatures
= 118.02 F - 126.92'F Tube Flow = 3,749.84 Tube Temperatures
= 135.68'F - 127.47'F 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 3.1870 ft"2, Design Shell Velocity = 0.000 ft/s, Shell Diameter = 39.000 BaNe Info: Spacing = 11.830 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.569 in, Dout = 0.625 in, Length = 23.75 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 1,324 of 1,324 Tubes Active UTubes = No Effective Area = 5,065.00 ft"2 Area Factor = 0.9844 Fouling = 0.0005 (inside) 0.0005 (outside)
Hoff= 0.9624 LMTD= 9.1006 LMTDCorrections FF = 0.8298 Fb = 1.0000 Heat Load =
15,397,323.23BTU/hr UOverall = 402.54 BTU/hr/ft"2/'~ag:
SFP Hxsy laaus:
On I Ho~nloaw'al Mfr: Yuba Model: 39-285/CEN Dwgs: EA-1ABCD Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 3.1870 ft"2, Design Shell Velocity = 0.000 ft/s, Shell Diameter = 39.000 BaNe Info: Spacing = 11.830 in, Thickness = 0.000 in, Area = 0.000 ft*2, K = 0.000 Tubes: Din = 0.569 in, Dout = 0.625 in, Length = 23.75 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 1,324 of 1,324 Tubes Active UTubes = No Effective Area = 5,065.00 ft"2 Area Factor = 0.9844 Fouling = 0.0005 (inside) 0.0005 (outside)
Hoff= 0.9624 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
UOverall = 0.00 BTU/hr/ft"2/'F 0.00BTU/hr 06.08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 4 CP&L Calc ID: SF-0040
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Carolina Power and Light - G:BCPL>HARRIStSFPMOD>CCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EA PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Min Flow Condition) aus:
n o in ow a
Dwgs: EA1ABCD Shell Fluid: Fresh Water ype:
e u e Model: 39-285/CEN ag:
x Mfr: Yuba Tube Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 3.1870 ft*2, Design Shell Velocity = 0.000 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.569 in, Dout = 0.625 in, Length = 23.75 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 1,324 of 1,324 Tubes Active UTubes = No Effective Area = 5,065.00 ft"2 Area Factor = 0.9844 Fouling = 0.0005 (inside) 0.0005 (outside)
Hoff= 0.9624 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F 06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 5 Mfr: Yuba Model: 39-825/CEN Dwgs: EA1ABCD System Fluid:
Shell Flow = 154.20 Shell Temperatures
118.02'F - 131.13'F Heat Load
1,000,000.00BTU/hr RX~ag: xsCD Flx 'lxYype: sWerr~u6eel X Sfatus:
On fNoHn F~ow ath Mfr: Atlas Model: 8-137/BEU Dwgs: Spec Sht EL-626 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 4 Tube Passes Shell Min Area = 0.1430 ft"2, Design Shell Velocity = 3.838 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.500 in, Area = 1.880 ft"2, K = 9.400 Tubes: Din = 0.495 in, Dout = 0.625 in, Length = 23.06 ft, K = 9.40 Tube Pitch = 0.8125 in Tube Pitch Type = Triangular 24 of 24 Tubes Active UTubes = Yes Effective Area = 90.00 ft"2 Area Factor = 0.9939 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.7159 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F CP8cL Calc ID: SF-0040
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06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 1
Carolina Power and Light - G:BCPL>HARRISLSFPMOD<CCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Calculation Summary Report LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Utility:
Plant:
System:
Version:
Fluid:
Case Alignment:
Carolina Power and Light Harris Nuclear Plant Component Cooling Water System Revision 2 Fresh Water LOCA: Recirc (RHR and SFP Cooling)
System was NOT Balanced to Balancing Parameters Calculation was completed:
06-08-1 998 16:41 Pressure Tolerance Sum of Flows Tolerance:
Friction Factor Tolerance:
Fixed Flow Tolerance:
Pressure Control Tolerance:
Temperature Tolerance:
0.0000100 0.0100000 0.0000010 0.0001000 0.0010000 0.0050000 Calculation
Description:
Revision 0:
Added Throttle Valves and Thermal Models. See CC-0039 Rev 0 dated 10/15/97 Revision 1:
Added alignments for Normal Ops, Hot Shutdown (350F), Cold Shutdown (200F),
Safe Shutdown (350F), Safe Shutdown (200F), 1/3 Core Shuffle Refueling, Full Core Offload Refueling, Abnormal Full Core Offload, LOCA (Sl/Recirculation Phases)
Added SWEC proposed CCW tie-in for SFP Hxs C and D.
Added Simulated Fuel Pool Cooling Systems for Fuel Pools A/B and C/D to provide pool equilibrium temperatures.
Additional nodes and valves are designed by Altxxx tags.
SFP Hx C and D models are equivalent to SFP Hx A and B models.
Determined RHR Flow = 3903 gpm (1.846E6 Ibm/hr) at 244.1F during Post LOCA Recirculation per HNP Gale NSSS-38 Rev 2 dtd 4/30/97.
Assume SI Signal Isolates GFFD and Sample Coolers and starts B CCW Pump.
Phase A Containment Isolation signal isolates XSLD and RCDT heat exchangers.
Phase B Containment Isolation signal isolates RCP supply and return headers.
Added TEMP1 simulation valve to eliminate low flow instability problem. This does not effect the results but signficantly improves the model computational efficiency.
Assume Post LOCA Recirc:
COL Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 21 of 41
A SFP Hx CCW flow throttled as necessary to maintain RHR Hx Flow above 5600 gpm.
Added LOCA Isolate simulation valve to model.
Deleted MiscK = 1100 in Pipe Section 64. Balanced each BRS heat exchanger to measured values.
Throttle valve positions are:
1CC-356 = 24.17%
1CC-353 = 0.75%
1CC-363 = 20.56%
Assumes BRS Skid is Abandoned In Place Per Direction from CCW System Engineer at CPBL meeting on 11/25/97. Added BRSEC Isolation Valve to Pipe Sections 64 and 85. Deleted BRS Skid Heat Loads from all alignments.
Added 10% Degraded CCW Pump Curves Per HNP Gale HNP-M/MECH-1011 Rev 2 dtd 5/10/97.
Eliminated flow recirculation through the expansion tank by changing Node0001 to an in-line pressure node with applied pressures of 42.04 psia. Changed Node0025 to a free flow node.
Deleted nodes Fixed1 and Fixed2 and pipe sections 1 and 26.
This change is necessary to eliminate inaccuracies in the system thermal balance.
Revision 2:
Changed Node00026 to In-line Pressure Node for Split System Ops with an applied pressure of 42.04 psia.
Added CCW Suction and Discharge Header Cross Tie Isolation Valves to Simulate Split CCW Trains when Both RHR Hxs are operating per OP145 Section 8.9 Rebalanced CCWS for SFP C/D Activation as of 12/2001.
CP&L Calc ID: SF-0040
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06-08-1998 16:41 Carolina PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Power and Light - G:BCPL)HARRIS'iSFPMODFCCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Calculation Summary Report LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Summary of Flagged Conditions for Current Calculation Page 3 Pipe:116.00 Node0106-Node0104 Pipe:120.00 Node0212 - Node0210 Pipe:121.00 Node0212 - Node0214 Pipe:312.00 AltN7 - AltN10 Pipe:901.00 FP3 - FP1 DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible DP > 50% of Inlet Pressure Cavitation Flow Possible CP&L Calc ID: SF-0040
Attachment:
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06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL)HARRIS)SFPMOD)CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Con ergence: Pressure=1.0E-5 Sum 0=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 1
Pipe: 2.00 ID =
12.000 Flow =
4,648.67 Vel =
13.188 Turbulent f = 0.0133 Reynold's Number = 2.7426E+06 N1: Node0001
- Press=
41.98 Elev= 247.00 Flow= 0.00 N2: Node0002 Press=
39.60 Elev= 250.62 Flow= 0.00 Temp=
153.48 Temp=
141.66 Pipe:
3.00 ID =
17.250 Flow =
8,417.93 Vel =
11.557 Turbulent f= 0.0125 Reynold's Number = 3.2981E+06 N1: Node0002 Press=
39.60 Elev= 250.62 Flow= 0.00 N2: Node0003 Press=
38.88 Elev= 250.75 Flow= 0.00 Pipe: 4.00 ID =
17.250 Flow =
8,417.93 Vel =
11.557 Turbulent f = 0.0125 Reynold's Number = 3.2981E+06 N1: Node0003 Press=
38.88 Elev= 250.75 Flow= 0.00 N2: Node0004 Press=
42.52 Elev= 238.72 Flow= 0.00 Temp=
141.66 Temp=
141.66 Temp=
141.66 Temp=
141.66 Pipe:
5.00 ID =
15.250 Flow =
8,417.93 N1: Node0004 Press=
42.52 N2: Node0005 Press=
130.16 NPSHA =92.54 Elev= 238.72 Flow= 0.00 Elev= 238.59 Flow= 0.00 Temp=
141.66 Temp=
141.66 pe:
6.00 ID =
17.250 Flow =
8,417.93 Vel =
11.557 Turbulent f = 0.0125 Reynold's Number = 3.2981E+06 N1: Node0005 Press=
130.16 Elev= 238.59 Flow= 0.00 N2: Node0006 Press=
124.27 Elev= 248.30 Flow= 0.00 Pipe:
7.00 ID =
17.250 Flow =
8,417.93 Vel =
11.557 Turbulent f = 0.0125 Reynold's Number = 3.2981E+06 N1: Node0006 Press=
124.27 Elev= 248.30 Flow= 0.00 N2: Node0007 Press=
122.31 Elev= 250.63 Flow= 0.00 Pipe:
8.00 ID =
17.250 Flow =
8,417.93 Vel =
11.557 Turbulent f = 0.0125 Reynold's Number = 3.2981E+06 N1: Node0007 Press=
122.31 Elev= 250.63 Flow= 0.00 N2: Node0008 Press=
123.99 Elev= 245.00 Flow= 0.00 Pipe:
9.00 ID =
23.250 Flow =
8,390.16 Vel =
6.341 Turbulent f = 0.0122 Reynold's Number = 2.2147E+06 N1: Node0008 Press=
123.99 Elev= 245.00 Flow= 0.00 N2: Node0009 Press=
117.99 Elev= 244.67 Flow= 0.00 Pipe:
10.00 ID =
17.250 Flow =
8,364.80 Vel =
11.484 Turbulent f = 0.0126 Reynold's Number = 2.6824E+06 N1: Node0009 Press=
117.99 Elev= 244.67 Flow= 0.00 N2: Node0010 Press=
112.23 Elev= 250.69 Flow= 0.00 Temp=
141.66 Temp=
141.66 Temp=
141.66 Temp=
141.66 Temp=
141.66 Temp=
141.66 Temp=
141.66 Temp=
118.39 Temp=
118.39 Temp=
118.39 I! Reverse Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
'/o'/o Pressure Below Vapor Pressure
'?? Temperature Outside Fluid Property Range
¹¹ NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calo ID: SF-0040
Attachment:
Z Rev: 0 Page 24 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:FCPLtHARRIS)SFPMOD>CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EC PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 2 Pipe:
11.00 ID =
17.250 Flow =
3,753.68 Vel =
5.153 Turbulent f = 0.0132 Reynold's Number = 1.2037E+06 Ni: Node0010 Press=
112.23 Elev= 250.69 Flow= 0.00 N2: Node0011 Press=
112.06 Elev=
250.71 Flow= 0.00 Pipe:
19.00 ID =
17.250 Flow =
3,769.62 Vel =
5.175 Turbulent f= 0.0131 Reynold's Number = 1.3918E+06 N1: Node0028 Press=
39.65 Elev= 250.62 Flow= 0.00 N2: Node0002 Press=
39.60 Elev= 250.62 Flow= 0.00 Temp=
118.39 Temp=
118.39 Temp=
127.13 Temp=
141.66 Pipe:
21.00 ID =
17.250 Flow =
3,762.13 Vel =
5.165 Turbulent f = 0.0131 Reynold's Number = 1.3053E+06 N1: Node0027 Press=
40.01 Elev= 250.70 Flow= 0.00 N2: Node0028 Press=
39.65 Elev= 250.62 Flow= 0.00 Pipe:
22.00 ID =
19.250 Flow =
3,762.13 Vel = 4.148 Turbulent f = 0.0131 Reynold's Number = 1.1697E+06 N1: Node0306 Press=
40.12 Elev= 250.68 Flow= 0.00 N2: Node0030 Press=
40.06 Elev= 250.68 Flow= 0.00 Temp=
127.13 Temp=
127.13 Temp=
127.13 Temp=
127.13 Pipe:
35.00 ID =
19.250 Flow =
3,753.68 Vel = 4.138 Turbulent f = 0.0132 Reynold's Number = 1.0787E+06 Ni: Node0024 Press=
111.96 Elev=
250.71 Flow= 0.00 N2: Node0301 Press=
111.90 Elev=
2 0.67 Flow= 0.00 Temp=
118.39 Temp=
118.39 Pipe:
37.00 ID =
12.000 Flow =
4,611.12 Vel =
13.082 Turbulent f = 0.0134 Reynold's Number = 2.1256E+06 N1: Node0010 Press=
112.23 Elev= 250.69 Flow= 0.00 N2: Node0101 Press=
112.27 Elev= 246.97 Flow= 0.00 Pipe:
38.00 ID =
19.250 Flow =
3,753.68 Vel = 4.138 Turbulent f = 0.0132 Reynold's Number = 1.0787E+06 N1: Node0011 Press=
112.06 Elev= 250.71 Flow= 0.00 N2: Node0024 Press=
111.96 Elev=
250.71 Flow= 0.00 Pipe:
51.00 ID =
19.250 Flow =
3,762.13 Vel = 4.148 Turbulent f = 0.0131 Reynold's Number = 1.1697E+06.
N1: Node0030 Press=
40.06 Elev= 250.68 Flow= 0.00 N2: Node0027 Press=
40.01 Elev= 250.70 Flow= 0.00 Pipe:
52.00 ID =
19.250 Flow =
3,753.68 Vel = 4.138 Turbulent f= 0.0132 Reynold's Number = 1.0787E+06 N1: Node0301 Press=
111.90 Elev= 250.67 Flow= 0.00 N2: Node0307 Press=
112.51 Elev= 248.81 Flow= 0.00 Temp=
118.39 Temp=
118.39 Temp=
118.39 Temp=
118.39 Temp=
127.13 Temp=
127.13 Temp=
118.39 Temp=
118.39 ll Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%% Pressure Below Vapor Pressuro Y? Temperature Outside Fluid Property Range NfNPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SP-0040
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06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:)CPL>HARRIS>SFPMOD<CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EA PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 3 Pipe:
59.00 ID =
19.250 Flow =
3,762.13 Vel = 4.148 Turbulent f= 0.0131 Reynold's Number = 1.1697E+06 N1: Node0310 Press=
41.12 Elev= 248.83 Flow= 0.00 N2: Node0306 Press=
40.12 Elev= 250.68 Flow= 0.00 Pipe:
63.00 ID =
19.250 Flow =
3,753.68 Vel = 4.138 Turbulent f= 0.0132 Reynold's Number = 1.0787E+06 N1: Node0307 Press=
112.51 Elev=
248.81 Flow= 0.00 N2: Node0311 Press=
112.45 Elev= 248.83 Flow= 0.00 Pipe:
86.00 ID =
19.250 Flow =
3,762.13 Vel = 4.148 Turbulent f= 0.0131 Reynold's Number = 1.1697E+06 N1: Node0328 Press=
41.92 Elev=
247.31 Flow= 0.00 N2: Node0310 Press=
41.12 Elev= 248.83 Flow= 0.00 Temp=
127.13 Temp=
127.13 Temp=
118.39 Temp=
118.39 Temp=
127.13 Temp=
127.13 Pipe:
87.00 ID =
17.250 Flow =
3,762.13 Vel = 5.165 Turbulent f= 0.0131 Reynold's Number = 1.3053E+06 N1: AltN12 Press=
42.09 Elev= 247.36 Flow= 0.00 N2: Node0328 Press=
41.92 Elev=
247.31 Flow= 0.00 Temp=
127.13 Temp=
127.13 Pipe:
88.00 ID =
17.250 Flow =
3,753.68 Vel = 5.153 Turbulent f= 0.0132 Reynold's Number = 1.2037E+06 N1: Node0311 Press=
112.45 Elev= 248.83 Flow= 0.00 N2: AltN1 Press=
113.46 Elev= 245.34 Flow= 0.00 Temp=
118.39 Temp=
118.39 Pipe:
96.00 ID =
13.250 Flow =
3,585.40 Vel = 8.343 Turbulent f= 0.0134 Reynold's Number = 1.6171E+06 N1: Node0210 Press=
46.91 Elev=
238.01 Flow= 0.00 N2: Node0211 Press=
46.79 Elev= 238.09 Flow= 0.00 Temp=
126.96 Temp=
126.96 Pipe:
97.00 ID =
13.250 Flow =
3,601.58 Vel =
8.381 Turbulent f = 0.0134 Reynold's Number = 1.6244E+06 N1: Node0209 Press=
108.07 Elev= 243.48 Flow= 0.00 N2: Node0212 Press=
106.52 Elev= 237.99 Flow= 0.00 Pipe:
98.00 ID =
13.250 Flow =
3,597.55 Vel =
8.371 Turbulent f= 0.0134 Reynold's Number = 1.5619E+06 N1: Node0208 Press=
113.58 Elev= 243.58 Flow= 0.00 N2: Node0209 Press=
108.07 Elev= 243.48 Flow= 0.00 Temp=
126.96 Temp=
126.96 Temp=
118.39 Temp=
126.96 Pipe:
99.00 ID =
13.250 Flow =
3,593.66 Vel = 8.362 Turbulent f= 0.0134 Reynold's Number = 1.5003E+06 N1: Node0207 Press=
112.84 Elev= 245.33 Flow= 0.00 N2: Node0208 Press=
113.58 Elev= 243.58 Flow= 0.00 Temp=
118.39 Temp=
118.39 Il Reverse Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
/o%%d Pressure Below Vapor Pressure 22 Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
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06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL>HARRIS)SFPMOD(CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=S.OE-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 4 Pipe:
100.00 ID =
13.250 Flow =
3,593.66 Vel = 8.362 Turbulent f= 0.0134 Reynold's Number = 1.5003E+06 Ni: Node0201 Press=
113.16 Elev= 245.33 Flow= 0.00 N2: Node0207 Press=
112.84 Elev= 245.33 Flow= 0.00 Pipe:
111.00 ID =
12.000 Flow =
4,604.63 Vel =
13.063 Turbulent f = 0.0134 Reynold's Number = 2.1226E+06 N1: Node0101 Press=
112.27 Elev= 246.97 Flow= 0.00 N2: Node0102 Press=
102.37 Elev= 262.35 Flow= 0.00 Temp=
118.39 Temp=
118.39 Temp=
118.39 Temp=
118.39 Pipe:
112.00 ID=
17.250 Flow=
4,626.21 Vel= 6.351 Turbulent f= 0.0129 Reynold's Number = 1.7302E+06 N1: Node0102 Press=
102.37 Elev= 262.35 Flow= 0.00 N2: Node0103 Press=
93.61 Elev= 243.78 Flow= 0.00 Temp=
118.39 Temp=
153.50 Pipe:
113.00 ID =
12.000 Flow =
4,623.78 Vel =
13.118 Turbulent f = 0.0133 Reynold's Number = 2.8534E+06 N1: Node0115 Press=
91.84 Elev=
243.81 Flow= 0.00 N2: Node0116 Press=
49.13 Elev= 244.98 Flow= 0.00 Temp=
153.50 Temp=
153.50 Pipe:
114.00 ID =
2.067 Flow =
6.49 Vel = 0.620 Turbulent f= 0.0284 Reynold's Number = 1.7363E+04 N1: Node0101 Press=
112.27 Elev= 246.97 Flow= 0.00 N2: Node0105 Press=
133.24 Elev=
197.53 Flow= 0.00 Temp=
118.39 Temp=
118.39 Pipe:
115.00 ID =
0.824 Flow =
6.51 Vel = 3.915 Turbulent f = 0.0267 Reynold's Number = 4.8140E+04 N1: Node0105 Press=
133.24 Elev=
197.53 Flow= 0.00 N2: Node0106 Press=
132.10 Elev=
198.68 Flow= 0.00 Temp=
118.39 Temp=
140.14 Pipe:
116.00 ID =
2.067 Flow =
6.54 Vel = 0.625 Turbulent f = 0.0270 Reynold's Number = 2.2266E+04 N1: Node0106 Press=
132.10 Elev=
198.68 Flow= 0.00 N2: Node0104 Press=
42.58 Elev= 247.00 Flow= 0.00 Temp=
140.14 Temp=
153.48 Pipe:
117.00 ID =
12.000 Flow=
4,657.26 Vel =
13.213 Turbulent f = 0.0133 Reynold's Number = 2.8737E+06 N1: Node0104 Press=
42.58 Elev= 247.00 Flow= 0.00 N2: Node0001
- Press=
41.98 Elev= 247.00 Flow= 0.00 Pipe:
120.00 ID =
13.250 Flow =
3,585.40 Vel =
8.343 Turbulent f = 0.0134 Reynold's Number = 1.6171E+06 N1: Node0212 Press=
106.52 Elev= 237.99 Flow= 0.00 N2: Node0210 Press=
46.91 Elev=
238.01 Flow= 0.00 Temp=
153.48 Temp=
153.48 Temp=
126.96 Temp=
126.96 II Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%% Pressure Below Vapor Pressure
'?'? Temperature Outside Fluid Property Range
¹¹ NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev:
0 Page 27 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:FCPLiHARRIStSFPMOD tCCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EQ PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 5 Pipe:
121.00 ID= 0.824 Flow=
16.18 Vel = 9.737 Turbulent f= 0.0250 Reynold's Number = 1.1736E+05 N1: Node0212 Press=
106.52 Elev= 237.99 Flow= 0.00 N2: Node0214 Press=
47.90 Elev= 236.74 Flow= 0.00 Pipe:
123.00 ID=
1.049 Flow=
16.18 Vel= 6.008 Turbulent f = 0.0242 Reynold's Number = 9.2187E+04 N1: Node0214 Press=
47.90 Elev= 236.74 Flow= 0.00 N2: Node0215 Press=
47.69 Elev= 236.74 Flow= 0.00 Pipe:
124.00 ID=
1.049 Flow= -16.18 Vel= -6.008 Turbulent f = 0.0242 Reynold's Number = 9.2187E+04 N1: Node0211 Press=
46.79 Elev= 238.09 Flow= 0.00 N2: Node0215 Press=
47.69 Elev= 236.74 Flow= 0.00 Pipe:
125.00 ID =
13.250 Flow =
3,601.58 Vel =
8.381 Turbulent f = 0.0134 Reynold's Number = 1.6244E+06 N1: Node0211 Press=
46.79 Elev= 238.09 Flow= 0.00 N2: Node0206 Press=
46.58 Elev= 238.09 Flow= 0.00 Pipe:
130.00 ID =
12.000 Flow =
4,650.74 Vel =
13.194 Turbulent f = 0.0133 Reynold's Number = 2.8701E+06 N1: Node0103 Press=
93.61 Elev= 243.78 Flow= 0.00 N2: Node0115 Press=
91.84 Elev=
243.81 Flow= 0.00 Pipe:
131.00 ID =
12.000 Flow =
4,650.72
'ei =
13.194 Turbulent f= 0.0133 Reynold's Number = 2.8699E+06 N1: Node0116 Press=
49.13 Elev= 244.98 Flow= 0.00 N2: Node0104 Press=
42.58 Elev= 247.00 Flow= 0.00 Pipe:
133.00 ID =
1.049 Flow =
26.96 Vel =
10.008 Turbulent f = 0.0232 Reynold's Number = 1.9031E+05 N1: Node0115 Press=
91.84 Elev= 243.81 Flow= 0.00 N2: Node0116 Press=
49.13 Elev= 244.98 Flow= 0.00 Temp=
126.96 Temp=
126.96 Temp=
126.96 Temp=
126.96 Temp=
126.96 Temp=
126.96 Temp=
126.96 Temp=
126.96 Temp=
153.50 Temp=
153.50 Temp=
153.50 Temp=
153.48 Temp=
153.50 Temp=
153.50 Pipe:
300.00 ID =
17.250 Flow =
160.02 Vel = 0.220 Turbulent f = 0.0211 Reynold's Number = 5.1315E+04 N1'itN1 Press=
113.46 Elev= 245.34 Flow= 0.00 N2: AltN2 Press=
113.46 Elev= 245.34 Flow= 0.00 Temp=
118.39 Temp=
118.39 Pipe: 301.00 ID =
17.250 Flow =
160.02 Vel = 0.220 Turbulent f = 0.0211 Reynold's Number = 5.1315E+04 N1: AltN2 Press=
113.46 Elev= 245.34 Flow= 0.00 N2: AltN3 Press=
113.46 Elev= 245.34 Flow= 0.00 Temp=
118.39 Temp=
118.39
!! Reverso Flow Thru Check Valve
++ Section Was Balanced
- Fixed Pressure
%% Pressure Below Vapor Pressuro
'?'? Temperature Outside Fluid Property Range fry NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 28 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:'tCPL>HARRISESFPMOD(CCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 6 Pipe:
305.00 ID =
13.250 Flow =
160.28 Vel = 0.373 Turbulent f = 0.0199 Reynold's Number = 7.0857E+04 N1: AltN5 Press=
113.45 Elev= 245.34 Flow= 0.00 N2: AltN7 Press=
113.45 Elev= 245.34 Flow= 0.00 Pipe:
306.00 ID=
13.250 Flow= -160.02 Vel= -0.372 Turbulent f = 0.0202 Reynold's Number = 6.6806E+04 N1: AltN5 Press=
113.45 Elev= 245.34 Flow= 0.00 N2: AltN3 Press=
113.46 Elev= 245.34 Flow= 0.00 Temp=
118.39 Temp=
131.00 Temp=
118.39 Temp=
118.39 Pipe:
310.00 ID =
13.250 Flow =
160.55 Vel =
0.374 Turbulent f= 0.0197 Reynold's Number = 7.4988E+04 N1: AltN10 Press=
43.10 Elev= 245.00 Flow= 0.00 N2: AltN11 Press=
43.09 Elev= 245.00 Flow= 0.00 Pipe:
311.00 ID =
17.250 Flow =
160.46 Vel =
0.220 Turbulent f = 0.0207 Reynold's Number = 5.6619E+04 N1: AitN11 Press=
43.09 Elev= 245.00 Flow= 0.00 N2: AIIN12 Press=
42.09 Elev= 247.36 Flow= 0.00 Pipe:
312.00 ID =
13.250 Flow =
160.55 Vel =
0.374 Turbulent f = 0.0197 Reynold's Number = 7.4988E+04 N1: AltN7 Press=
113.45 Elev= 245.34 Flow= 0.00 N2: AltN10 Press=
43.10 Elev= 245.00 Flow= 0.00 Pipe:
315.00 ID =
13.250 Flow=
3,601.67 Vel =
8.381 Turbulent f= 0.0135 Reynold's Number = 1.6256E+06 N1: Node0206 Press=
46.58 Elev= 238.09 Flow= 0.00 N2: AltN12 Press=
42.09 Elev= 247.36 Flow= 0.00 Pipe:
319.00 ID =
17.250 Flow=
3,593.66 Vel = 4.934 Turbulent f = 0.0134 Reynold's Number = 1.1524E+06 N1: AltN1 Press=
113.46 Elev= 245.34 Flow= 0.00 N2: Node0201 Press=
113.16 Elev= 245.33 Flow= 0.00 Temp=
131.00 Temp=
131.00 Temp=
131.00 Temp=
127.13 Temp=
131.00 Temp=
131.00 Temp=
126.96 Temp=
127.13 Temp=
118.39 Temp=
118.39 Pipe:
900.00 ID =
9.750 Flow =
3,749.84 NPSHA = 228.09 N1: FP1
- Press=
100.00 Elev= 0.00 Flow= 0.00 Temp=
135.78 N2: FP2 Press=
228.17 Elev= 0.00 Flow= 0.00 Temp=
127.57 Pipe: 901.00 ID =
17.124 Flow =
3,749.84 Vel =
5.224 Turbulent f = 0.0132 Reynold's Number = 1.3630E+06 N1: FP3 Press=
228.17 Elev=
0.00 Flow= 0.00 N2: FP1
- Press=
100.00 Elev= 0.00 Flow= 0.00 Temp=
127.57 Temp=
135.78 ll Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%%d%%d Pressure Below Vapor Pressure
'?2 Temperature Outside Fluid Property Range
¹¹ NPSHA less than NPSHR
&&Flow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 29 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL)HARRIS>SFPMOD<CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Combined Output Report Con ergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EA PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 7 N1: FP2 N2: FP3 Pipe:
902.00 ID= 9.750 Flow=
3,745.67 Vel=
16.097 Turbulent f = 0.0140 Reynold's Number = 2.3081E+06 Press=
228.17 Elev= 0.00 Flow= 0.00 Press=
228.17 Elev= 0.00 Flow= 0.00 Temp=
127.57 Temp=
127.57 II Reverse Flow Thru Check Valve
++ Section Was Balanced
" Fixed Pressure
%% Pressure Below Vapor Pressure
'2V Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR
&&Fiow Past End of Pump Curve CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 30 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:hCPLFHARRIS>SFPMODtCCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Pump Status Report LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 1
Pump Name Pump Name Pump Name Manufacturer Model:
Head (ft):
205.60 Inlet Node Elevation (ft):238.72 Pump2 Drawings:
Pump Status:
OFF Speed (RPM):
Hydraulic Horsepower:
Pump Impeller Datum (ft)
Pump Suction Temperature ('F NPSH Curve:
NONE NPSH Available:
Model:.
Manufacturer:
Flow (gpm):
Head (ft):
Inlet Node Elevation (ft):238.74 NPSH Required:
Model:
Manufacturer:
Pump3 Drawings:
Pump Status:
OFF Speed (RPM):
Hydraulic Horsepower:
Pump Impeller Datum (ft)
Pump Suction Temperature ('F NPSH Curve:
NONE NPSH Available:
Head (ft):
Flow (gpm):
Inlet Node Elevation (ft):238.73 NPSH Required:
Pump1 Drawings:
Pump Status:
Design Pump1 Speed (RPM):
Flow (gpm):
8,417.93 Hydraulic Horsepower:
430.18 Pump Impeller Datum (ft)
Pump Suction Temperature ('F 141.66 NPSH Curve:
NONE NPSH Available:
92.54 NPSH Required:
Pump Name Model:
Head (ft):
300.01 Inlet Node Elevation (ft):
FP1 Manufacturer:
Drawings:
Pump Status:
DummySFPCPump Speed (RPM):
Flow (gpm):
3,749.84 Hydraulic Horsepower:
280.42 Pump Impeller Datum (ft)
Pump Suction Temperature ('F 135.78 NPSH Curve:
NONE NPSH Available:
228.09 NPSH Required:
i CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 31 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL)HARRIS>SFPMOD<CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Pump Status Report LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 2 Manufacturer:
Model:
Head (ft):
Flow (gpm):
Inlet Node Elevation (ft):
NPSH Required:
Pump Name:
FP2 Drawings:
Pump Status:
OFF Speed (RPM):
Hydraulic Horsepower:
Pump Impeller Datum (ft)
Pump Suction Temperature ('F NPSH Curve:
NONE NPSH Available:
CPEcL Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 32 of. 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:>CPL~IHARRIStSFPMOD>CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Manual Valve Line-Up Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 1
Tag ValveType Position Actual "*
1CC-146 1CC-155 1CC-166 1CC-187 1CC-197 1CC-323 1CC-353 1CC-356 1CC-363 1CC-382 1CC-398 A RHR OUTLET AHXlsol Altv1 Altv10 Altv11 Altv12 Altv13 Altv14 AltV15 Altv2 Altv4 Altvs Altv6 Altv7 Altvs Altv9 B SFPC HX BRSEC BRSEC CCW B/C SUCT CCW PUMP B/C Closed Closed DischXTie LOCA Isolate LOCA Isolate LOCA Isolate LOCA Isolate Pilsolate P1lsolate RCP IN RCP OUT RHR A BYPASS RHR B BYPASS RHR B OUTLET SFPC HX FD I
Butterfly Globe Butterfly Globe Globe Globe Globe Globe Butterfly Butterfly Butterfly Gate Gate Gate Butterfly Butterfly Gate Gate Butterfly Butterfly Butterfly Gate Gate Butterfly Butterfly Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate Gate 0
47 91%
3.93%
48.61%
41.98%
12.90%
41.32%
0.75%
24.17%
20.56%
28.42%
28.42%
100 00%
100 00%
0.00%
p pp 2.09%
0.00%
P PP%
100.00%
2.09%
100 00%
ppp P PP%
100.00%
P PP%
100.00%
100.00%
0.00%
ppp 0.00%
0.00%
P PP%
0.00%
P PP%
P PP%
0.00%
P PP%
0.00%
P PP%
0.00%
P PP%
P PP%
0.00%
100.00%
P PP%
0.00%
P PP%
- Actual Position for Partially Open Check Valves CP&1. Calc ID: SF-0040
Attachment:
Z Rev:
0 Page 33 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL>HARRIS>SFPMOD<CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Manual Valve Line-Up Report Convergence: Pressure=1.0E-S Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=S.OE-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 2 Tag ValveType Position Actual **
SuctionXTie TEMP1 XSLD HX Gate Gate Gate 0
0.00%
0.00%
P PP%
- 'ctual Position for Partially Open Check Valves c:
F-0040
Attachment:
Z Rev: 0 Page 34 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:(CPL>HARRISFSFPMOD)CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 1
ag:
Mfr:
System Fluid:
Heat Load =
is oo er a us:
ype:
ixe ea oa Model:
Dwgs:
0.00BTU/hr ype:
axe ea
~oa RX greens: 0 el:
Dwgs:
Dwgs 1,000,000.00BTU/hr CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 35 of 41 H~ag: HRS~vap Coo er Mfr:
Mod System Fluid:
Meat Load =
0.00BTU/hr Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr R~ag: ccyr x
ype:
We u e X glaaus:
On I in Floaw>al Mfr: Westinghouse Model: 64-396 Dwgs: Spec Sht AH-CC-657 Tube Fluid: Fresh Water Shell Fluid: Fresh Water Shell Flow = 8,390.16 Shell Temperatures
= 141.66'F - 118.38'F Tube Flow = 8,500.00 Tube Temperatures
= 95.00'F - 117.98'F 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 5.9840 ft"2, Design Shell Velocity = 3.400 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 33.00 ft, K = 26.00 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 3,668 of 3,668 Tubes Active UTubes = No Effective Area = 23,341.00 ft"2 Area Factor = 0.9821 Fouling = 0.0000 (inside) 0.0025 (outside)
Hoff= 0.5906 LMTD = 23.5321 LMTDCorrections FF = 0.8105 Fb = 1.0000 Heat Load =
97,598,063.99BTU/hr UOverall = 219.23 BTU/hr/ft'2/'~ag:
CC x
ype:
Me u e Mfr: Westinghouse Model: 640396 Dwgs: Spec Sht AH-CC-657 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 5.9840 ft"2, Design Shell Velocity = 3.400 ft/s, Shell Diameter = 0.000 Baffle Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 33.00 ft, K = 26.00 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 3,668 of 3,668 Tubes Active UTubes = No Effective Area = 23,341.00 ft"2 Area Factor = 0.9821 Fouling = 0.0000 (inside) 0.0025 (outside)
Moff= 0.5892 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
O.OOBTU/hr UOverall = 0.00 BTU/hr/ft"2/'F Mfr:
Model:
Dwgs:
System Fluid: Fresh Water Tube Flow = 3,749.84 Tube Temperatures
127.57'F - 135.78'F Heat Load
15,200,000.00BTU/hr Mfr:
Model:
System Fluid:
Heat Load =
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:BCPL>HARRISESFPMOD)CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-S Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 2 aus:
n o in ow a
Dwgs: Dwgftt5428 Rev 1 Shell Fluid: Fresh Water Sa us Heat Load =
0.00BTU/hr Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr ag:
x ype:
e u e Mfr: Joseph Oat Model: 22-165/BFU Tube Fluid: Fresh Water 1 Shells, 1 Shell Passes, 8 Tube Passes Shell Min Area = 0.6460 ft"2, Design Shell Velocity = 3.800 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.500 in, Area = 25.210 ft"2, K = 9.400 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 28.03 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 142 of 142 Tubes Active UTubes = Yes Effective Area = 780.00 ft"2 Area Factor = 0.9981 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.7164 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
O.OOBTU/hr Uoverall = 0.00 BTU/hr/ft~2/'F RXTag: RCD x
KTyype:
'Tel u e X Staaus:
n 'Movin FlosvVal Mfr: Atlas Model: 12-144/BEU Dwgs: Spec Sht RC-632 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 4 Tube Passes Shell Min Area = 0.0960 ft"2, Design Shell Velocity = 5.186 ft/s, Shell Diameter = 0.000 Baffle Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 24.32 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 40 of 40 Tubes Active UTubes = Yes Effective Area = 189.00 ft"2 Area Factor = 0.9895 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.7104 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr Uoverall = 0.00 BTU/hr/ft"2/'F Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr FIXTag: RCPaTharmgar R
ype:
ixe ea oa XS a us:
Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr Mfr:
Model:
Dwgs:
System Fluid:
R CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 36 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial 5PFL-0000 Carolina Power and Light - G:<CPL)HARRIS>SFPMOD'tCCVNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-S Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0'CV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 3 pr i
r ype:
ixe ea oa Model:
a us eat Load FIKSraius: 0 Dwgs:
CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 37 of 41 ag:
Mfr:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr Mfr:
Model:
System Fluid:
Heat Load =
O.OOBTU/hr HXTag: RCPc erm ar ype:
rxe ea Load RKStaaus: 0 Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
0.00BTU/hr RXTag: PICP'oeeprOiICtrrt ype:
ixe ea oa
~~aus:
0 Mfr:
Model:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr HXTag: RHR x
Kryypa
'Ke1 u e X Staaus:
On IIFlow Pal Mfr: Joseph Oats Model: RS-628/BEU Dwgs: 5443 and 5444 Tube Fluid: Fresh Water Shell Fluid: Fresh Water Shell Flow = 4,626.21 Shell Temperatures
= 118.39'F - 153.50'F Tube Flow = 3,903.00 Tube Temperatures
= 209.00'F - 167.54'F 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 1.4120 ft"2, Design Shell Velocity = 8.830 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 76.97 ft, K = 9.40 Tube Pitch = 0.9688 in Tube Pitch Type = Triangular 592 of 592 Tubes Active UTubes = Yes Effective Area = 4,280.00 ft"2 Area Factor = 0.4784 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.4741 LMTD= 52.2629 LMTDCorrections FF = 0.9037 Fb = 1.0000 Heat Load =
81,200,950.01BTU/hr UOverall = 401.68 BTU/hr/ft"2/'~ag:
RFI x
~ype:
Me u e KS&aus: Onnntonn Ffoawal Mfr: Jospeh Oats Model: RS-628 Dwgs: 5443 and 5444 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 1.4120 ft"2, Design Shell Velocity = 8.830 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 76.97 ft, K = 9.40 Tube Pitch = 0.9688 in Tube Pitch Type = Triangular 592 of 592 Tubes Active UTubes = Yes Effective Area = 4,280.00 ft"2 Area Factor = 0.4784 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.4741 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
O.OOBTU/hr UOverall = 0.00 BTU/hr/ft"2/'F H~ag: RHKPmp A C r ype:
ixe ea oa a us:
n in ow at Mfr:
Model:
Dwgs:
System Fluid: Fresh Water Tube Flow = 6.51 Tube Temperatures
118.39'F - 140.14'F Heat Load
70,000.00BTU/hr
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Carolina Power and Light - G:BCPL'tHARRIStSFPMOD<CCNCCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-5 Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0EQ PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 4 Illp r
ag:
Mfr:
Dwgs:
System Fluid:
Heat Load =
O.OOBTU/hr XType: SMe~uSeel XSIaaue:
On o in ow a
Mfr: Altas Model: 20-128/BEU Dwgs: SW-627 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 8 Tube Passes Shell Min Area = 0.1530 ft"2, Design Shell Velocity = 3.375 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.652 in, Dout = 0.750 in, Length = 21.82 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 110 of 110 Tubes Active UTubes = Yes Effective Area = 460.00 ft*2 Area Factor = 0.9761 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.6951 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F ype:
ixe ea oa Model:
a us "RXTag: Spp~x BXType: Shell u e X SÃaus:
O~nin FloOw'at Mfr: Yuba Model: 39-285/CEN Dwgs: EA1ABCD Tube Fluid: Fresh Water Shell Fluid: Fresh Water Shell Flow = 3,597.55 Shell Temperatures
= 118.39'F - 126.95'F Tube Flow = 3,749.84 Tube Temperatures
= 135.78'F - 127.57'F 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 3.1870 ft"2, Design Shell Velocity = 0.000 ft/s, Shell Diameter = 39.000 Baffle Info: Spacing = 11.830 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.569 in, Dout = 0.625 in, Length = 23.75 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 1,324 of 1,324 Tubes Active UTubes = No Effective Area = 5,065.00 ft"2 Area Factor = 0.9844 Fouling = 0.0005 (inside) 0.0005 (outside)
Hoff= 0.9624 LMTD= 9.0039 LMTDCorrections FF = 0.8333 Fb = 1.0000 Heat Load =
15,398,293.97BTU/hr UOverall =405.20 BTU/hr/ft"2/'~ag:
SFP RxB ype:
e u e XStatus:
On o in ow a
Mfr: Yuba Model: 39-285/CEN Dwgs: EA-1ABCD Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 3.1870 ft"2, Design Shell Velocity = 0.000 ft/s, Shell Diameter = 39.000 BaNe Info: Spacing = 11.830 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.569 in, Dout = 0.625 in, Length = 23.75 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 1,324 of 1,324 Tubes Active UTubes = No Effective Area = 5,065.00 ftA2 Area Factor = 0.9844 Fouling = 0.0005 (inside) 0.0005 (outside)
Hoff= 0.9624 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
O.OOBTU/hr UOverall = 0.00 BTU/hr/ft"2/'F CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 38 of 41
06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Carolina Power and Light - G:<CPL>HARRIS>SFPMOD>CCVACCW2.PDB - Revision 2 Harris Nuclear Plant - Component Cooling Water System Heat Exchanger Data Report Convergence: Pressure=1.0E-S Sum Q=1.0E-2 Friction=1.0E-6 FCV=1.0E-4 PCV=1.0E-3 Temperature=5.0E-3 LOCA-Recirc (RHR and SFP) A CCW Train (Nominal Flow Condition)
Page 5 aus:
n o in ow a
Dwgs: EA1ABCD Shell Fluid: Fresh Water ag:
x ype:
e u e Mfr: Yuba Model: 39-285/CEN Tube Fluid: Fresh Water 1 Shells, 1 Shell Passes, 2 Tube Passes Shell Min Area = 3.1870 ft"2, Design Shell Velocity = 0.000 ft/s, Shell Diameter = 0.000 BaNe Info: Spacing = 0.000 in, Thickness = 0.000 in, Area = 0.000 ft"2, K = 0.000 Tubes: Din = 0.569 in, Dout = 0.625 in, Length = 23.75 ft, K = 9.40 Tube Pitch = 0.9375 in Tube Pitch Type = Triangular 1,324'of 1,324 Tubes Active UTubes = No Effective Area = 5,065.00 ft"2 Area Factor = 0.9844 Fouling = 0.0005 (inside) 0.0005 (outside)
Hoff= 0.9624 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F H~ag: SFP FfxX3 Mfr: Yuba Model: 39-825/CEN Dwgs: EA1ABCD System Fluid:
Shell Flow = 160.28 Shell Temperatures
118.39'F - 131.00'F Heat Load
1,000,000.00BTU/hr RX~ag: XSCD FIx ype:
We u e Mfr: Atlas Model: 8-137/BEU Dwgs: Spec Sht EL-626 Tube Fluid: Fresh Water Shell Fluid: Fresh Water 1 Shells, 1 Shell Passes, 4 Tube Passes Shell Min Area = 0.1430 ft"2, Design Shell Velocity = 3.838 ft/s, Shell Diameter = 0.000 Baffle Info: Spacing = 0.000 in, Thickness = 0.500 in, Area = 1.880 ft"2, K = 9.400 Tubes: Din = 0.495 in, Dout = 0.625 in, Length = 23.06 ft, K = 9.40 Tube Pitch = 0.8125 in Tube Pitch Type = Triangular 24 of 24 Tubes Active UTubes = Yes Effective Area = 90.00 ft"2 Area Factor = 0.9939 Fouling = 0.0003 (inside) 0.0005 (outside)
Hoff= 0.7159 LMTD= 0.0000 LMTDCorrections FF = 0.0000 Fb = 0.0000 Heat Load =
0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F CP&L Calc ID: SF-0040
Attachment:
Z Rev: 0 Page 39 of 41
18:17:16 PROTO-HX 3.02 by Proto-Power Corporation (SNPPHX-0000)
Carolina Power and Light Calculation Report for Spent Fuel HX - Spent Fuel Pool Heat Exchanger 06/08/98 Calculation Specifications Constant Inlet Temperature Method Was Used Extrapolation Was to User Specified Conditions Design Fouling Factors Were Used Data Date Shell Flow (gpm)
Shell Temp In ('F)
Shell Temp Out ('F)
Tube Flow (gpm)
Tube Temp In ('F)
Tube Temp Out ('F)
Test Data Extrapolation Data Tube Flow (gpm)
Shell Flow (gpm)
Tube Inlet Temp ('F)
Shell Inlet Temp ('F)
Fouling Calculation Results 3,750.0 160.3 131.1 118.4 Shell Mass Flow (ibm/hr)
Tube Mass Flow (Ibm/hr)
Heat Transferred (BTU/hr)
LMTD Effective Area (ft')
Property Velocity (A/s)
Reynold's Number Prandtl Number Bulk Vise (ibm/ft.lu)
Skin Vise (Ibm/fthr)
Density (ibm/ft')
Cp (BTU/ibm'F)
K(BTU/hrft'F)
Shell-Side Tube-Side U Overall (BTU/hrft"F)
Shell-Side ho (BTU/hrft"F)
Tube-Side hi (BTU/hr ft"F) 1/Wall Rcsis (BTU/hrft"F)
LMTDCorrection Factor Overall Fouling (hr IP'F/BTU)
Shell Temp In ('F)
Shell Temp Out ('F)
Tav Shell ('F)
Shell Skin Temp ('F)
Tube Temp In ('F)
Tube Temp Out ('F)
Tav Tube ('F)
Tube Skin Temp ('F)
Extrapolation Calculation Results Shell Mass Flow (ibm/hr)
Tube Mass Flow (ibm/hr)
Heat Transferred (BTU/hr)
LMTD Effective Area (ft')
8.018E+4 1.876E+6 1.027 E+6 3.2 5,065.0 Overall Fouling (hr IP'F/BTU)
Shell-Side ho (BTU/lu"ft"F)
Tube-Side hi (BTU/hrft"F) 1/Wall Resis (BTU/hrft"F)
LMTDCorrection Factor U Overall (BTU/hr A"F) 0.001049 225.6 2,161.2 3,845.3 0.3994 160.0 Property Velocity (ft/s)
Reynold's Number Prandtl Number Bulk Vise (ibm/ft.hr)
Skin Vise (ibm/ft hr)
Density (ibm/ft')
Cp (BTU/ibm'F)
K(BTU/hrft'F)
Shell-Side 0.113 1.016E+03 3.468
$ 1.29
$ 1.24
$61.64
$ 1.00
$0.37 Tube-Side 7.244 6.238E+04
$3.26
$ 1.22
$ 1.23
$61.54
$ 1.00
$0.37
- Reynolds Number Outside Range of Equation Applicability
!! With Minimum Fouling Thc Test Heat Load Could Not Bc Achie Shell Temp In ("F) 118.4 Shell Temp Out ('F) 130.8 Tav Shell ('F) 124.6 Shell Skin Temp ('F) 129.0 Tube Temp In ('F) 131.1 Tube Temp Out ('F) 130.6 Tav Tube('F)
CP&LCalc ID: SF-00401308 Tube Skin Temp (%tachment: Z Rev: 0 Page 40 of 41
18:17:16 PROTO-HX 3.02 by Proto-Popover Corporation (SNPPHX-0000)
Carolina Power and Light Calculation Report for Spent Fuel HX - Spent Fuel Pool Heat Exchanger 06/08/98 Shell and Tube Heat Exchanger Input Parameters yl' Q~y, TBR Inlet Temperature Outlet Temperature Fouling Factor Shell-Side gpm
$358.00 0'P 105.00 QF 110.62 0.00050 Tube-Side 120.00 112.00 0.00050 Shell Fluid Name Tube Fluid Name Design Heat Transfer (BTU/hr)
Design Heat Trans Coeff (BTU/hr ft2'F)
Emprical Factor for Outside h Performance Factor (% Reduction)
Heat Exchanger Type Effective Area (A*2)
Area Factor Area Ratio Number ofShells per Unit Shell Minimum Area Shell Velocity (A/s)
Tube Pitch (in)
Tube Pitch Type Number ofTube Passes U-Tubes Total Number ofTubes Number ofActive Tubes Tube Length (A)
Tube Inside Diameter (in)
Tube Outside Diameter (in)
Tube Wall Conductivity (BTU/hrO')
Ds, Shell Inside Diameter (in)
Lbc, Central Baffle Spacing (in)
Lbi, Inlet Baffle Spacing (in)
Lbo, Outlet Baffle Spacing (in)
Dotl, Tube circle diameter (in)
Bh, Baffle cut height (in)
Lsb, Diametral difference between Baffle and Shell (in)
Ltb, Diametral difference between Tube and Baffle (in)
Nss, Number Sealing Strips Fresh Water Fresh Water 15,060,000
. 418.00 0.962424000 0.00 TEMA-E 5,065.00 0.984417230 1
3.187000000 0.000 0.9375 Triangular 2
No 1,324 1,324 23.75 0.569 0.625 9.40 39.000 11.830 0.000 0.000 0.000 0.000 0.000 0.000 0.000 CPS'alc ID: SF-0040
Attachment:
Z Rev: 0 Page 41 of 41