ML18017A860

Rev 0 to Spent Fuel Pools C & D Activation Project Thermal- Hydraulic Analysis.

ML18017A860
Person / Time
Site:	Harris
Issue date:	11/10/1998
From:	Rhex Edwards, Lundy J CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18017A859	List: ML18017A858 ML18017A860 ML18017A861
References
SF-0040, SF-0040-R00, NUDOCS 9909100159
Download: ML18017A860 (79)

Text

ENCLOSURE 2 to SERIAL: HNP-99-129 SHEARON HARRIS NUCLEAR POWER 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 PDR

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 (TITLE INCLUDING STRUCTURE/SYSTEM/COMPONENT)

FOR SHEARON HARRIS NUCLEAR POWER PLANT X NUCLEAR ENGINEERING DEPARTMENT QUALITYCLASS XA QB QC QD QE REV RESPONSIBLE Pg DESIGN VERIFIED BY APPROVED BY NO. ENGINEER Q ENGINEERING REVIEW BY RESPONSIBLE SUPERVISOR DATE DATE DATE REASON FOR CHANGE REASON FOR CHANGE

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CAROLINAPOWER & LIGHT COMPANY Calculation ID: SF-0040 Jeff Lundy Checked by: Date: ~e i "32 Rcv.

0 CALCULATIONSHEET File:

Project No.:

Project

Title:

Spent Fuel Pools C and D Activation Project Calculation

Title:

Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis List of Effcctivc Pages PAGE PAGE PAGE I 28 B ll 29 C Ill 30 D 1 31 2 32 Fi 3 G 4 H 5 I 6 J 7 K 8 L 9

10 N 11 0 12 P 13 Q 14 15 S 16 T 17 U 18 V 19 IV 20 X 21 Y 22 z 23 AA 24 BB 25 CC 26 Attachments DD 27 A EiEi

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CAROLINAPOWER & LIGHTCOMPANY Calculation ID: SI'-0040 Jeff Lundy Checked by: Date: Pg ii ol 32 Rcv0 CALCULATIONSHEET File:

Project No.:

Project

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 ~Pa e LIST OF EFFECTIVE PAGES TABLE OF CONTENTS 1.0 PURPOSE

2.0 REFERENCES

3.0 ENGINEERING ANALYSISSOFTWARE 4.0 CALCULATION

5.0 CONCLUSION

S 32 Attacluncnts Subject Total Pages Calculation SF-0040, Revision 0, PROTO-FLO' Model Modifications for 77 the HNP Component Cooling Water System Rev 2 Calculation SF-0040, Revision 0, CCWS Alignment Summary Calculation SF-0040, Revision 0, Evaluation of Minimum RHR Heat 17 Exchanger CCW Flow Requirements for Design Basis Accident Conditions D Calculation SF-0040, Revision 0, Evaluation of Maxhnum RHR Heat 34 Exchanger CCW Flow Requirements for Design Basis Accident Conditions Calculation SF-0040, Revision 0, Evaluation of Minimum SFP Heat 34 Exchanger CCW Flow Requirements for Various Operating Conditions Calculation SF-0040, Revision 0, Rcbalance CCW System Flow 14 Distribution For LOCA: Sump Recirculation (RHR Only) Alignment Calculation SF-0040, Revision 0, Dcterminc Minimum CCW Heat 19 Exchanger Service Water Flow During LOCA: Sump Recirculation (RHR Only) Alignment Calculation SF-0040, Revision 0, Rebalancc CCW System Flow 37 Distribution for Minimum CCW Pump Developed Head Calculation SF-0040, Revision 0, Evaluation of CCW System Normal 35 System Alignment Hydraulic Performance Calculation SI'-0040, Revision 0, Evaluation of CCW System Dual Train 40 Hot Shutdown (350F) System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation of CCW System Single Train 35 Hot Shutdown (350F) System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation of CCW System Refueling 33 Core Shuffle System Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation of CCW System Refueling 39 Normal Full Core OIIload System Aligrunent Hydraulic Pcrformancc

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CAROLINAPOWER & LIGHTCOMPANY Calculation ID: SF-0040 Jeff Lundy Checked by: Date: ~~

iii'r 32 R~0 CALCULATIONSHEET Ffle:

Project No.:

Project

Title:

Spent Fuel Pools C and D Activation Project Calculation

Title:

Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Attachments Subject Total Pages N Calculation Sl'-0040, Revision 0, Evaluation of CCW System Refueling 41 Abnormal Full Core Offload System Alignment Hydraulic Performance 0 Calculation SF-0040, Revision 0, Evaluation of CCW System LOCA-Safety Injection Phase Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation of CCW System LOCA- 18 Containment Sump Recirculation (RHR Only) Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation of CCW System LOCA- 25 Containment Sump Recirculation (RHR and SFP) Alignment Hydraulic Performance Calculation SI'-0040, Revision 0, Evaluation of CCW System Normal 32 System Alignment Thermal Performance Calculation SI'-0040, Revision 0, Evaluation of CCW System Dual Train 33 Hot Shutdown (350F) System Alignment Thermal Performance Calculation SF-0040, Revision 0, Evaluation of CCW System Single Train 30 Hot Shutdown (350F) System Alignment Thermal Performance U Calculation SF-0040, Revision 0, Evaluation of CCW System Refueling 30 Core Shuffle System Alignment Thermal Performance V Calculation SF-0040, Revision 0, Evaluation of CCW System Refueling 31 Normal Full Core Offload System Alignment Thermal Pcrformancc W Calculation SI'-0040, Revision 0, Evaluation of CCW System Refueling 32 Abnormal Full Core Offload System Alignment Thermal Pcrformancc Calculation Sl'-0040, Revision 0, Evaluation of CCW System LOCA-Safety 33 Injection Phase Alignment Thermal Performance Y Calculation SF-0040, Revision 0, Evaluation of CCW System LOCA- 18 Containment Sump Recirculation (RHR Only) Aligtunent Thermal Performance Calculation SF-0040, Revision 0, Evaluation of CCW System LOCA- 27 Containment Sump Recirculation (RHR and SFP) Alignment Thermal Performance AA Calculation SF-0040, Revision 0, Evaluation of UHS Thermal Margins 4 BB Calculation SF-0040, Revision 0, Evaluation of Short Term Transient Fuel 68 Pool Temperature Response During HNP Cooldown Operations CC Calculation SF-0040, Revision 0, Design Vcriflcation Records 28 DD Calculation SF-0040, Revision 0, Evaluation of CCW System Plant Startup 36 Alignment Hydraulic Performance Calculation SF-0040, Revision 0, Evaluation of CCW System Plant Startup 33 Alignment Thermal Performance

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CAROLINAPOWER & LIGHTCOMPANY Calculation ID: Sl'-0040 Jeff Lundy Checked by: Date: Pg or Rcv0 1 32 CALCULATIONSHEET File:

Project No.:

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 of this calculation is to document the thermal hydraulic capacity of the Component Cooling Water System (CCWS) to support the activation of Spent 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/hr and 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

Computed by: Date: Calculation ID: SF-0040 Jeff Lundy CAROLINAPOWER & LIGHTCOMPANY Checked by: Date: Pg 2 or 32 ~0 CALCULATIONSHEET File:

Project No.:

Project

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 Initial Temperature 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&L and 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 of Year 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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CAROLINAPOWER Ec LIGHTCOMPANY Calculation ID: SF'-0040 Jeff Lundy Chcckcd by: Date: i'g 3 or 32 Rcv 0

CALCULATIONSHEET Fflc:

Project No.:

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 Building Air Conditioning System, dated 5/24/86 (35) Harris Nuclear Plant Enginccring Scrvicc request 9700252 Revision 0, Evaluation of EPT-174 Data, dated 4/7/97 3.0 ENGINEERING ANALYSIS SOI'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 (A and 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 flow margin portion of this analysis.

Computed by: Date: Calculation ID: SF-0040 Jeff Lundy CAROLINAPOWER & LIGHT COMPANY Checked by: Date: rs 4 of 3g Rcv0 CALCULATIONSHEET File:

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Project

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 Scrvicc Modilication G4 BRS Supply Replaced MiscK of 1100 with MiscK~I8.11 from Reference (22)

Adjusted ICC-356 to 24.17% Open Adjusted I CC-353 to 0.75% Open Adjusted ICC-363 to 20.56% Open BRSEC Added isolation valve to simulate COL direction to assume the BRS Skid is abandoned inplace.

85 BRSEC Added isolation valve to simulate COL direction to assume the BRS Skid is abandoned inplacc.

41/53/60/G4 LOCAlsolatc Added simulation valve for LOCA case alignments, References (12) and (13)

Node0001 Prcssure In-linc Node Changed to in-linc pressure node to climinatc Node0026 bypass flow through thc Surge Tank which is not consistent with actual CCWS operation Fixed I/Fixcd2 Delctcd Nodes Eliminated Surge Tank nodes and lines to properly model CCWS and eliminate recirculating flow through thc Surge Tank 105 RIIR Pmp B Clr Corrcctcd Heat Load Tag 121 AHXlsol Added SFP Hx A Isolation Valve FP I/FP2 Added simulated I'uel pool cooling pumps DummySFPCPump Added simulated fuel pool cooling pump curves calibrated to 3750 gpm pcr Reference (I I)

BRS Evap Cooler Deleted fixed heat load pcr Assumption 4.1.12 Pump l Degraded Pump 1 Added 10% TDII Dcgradcd CCW Pump Curve Pump2 DcgradcdPump2 Added 10% TDH Degraded CCW Pump Curve Pump3 Degraded Pump3 Added 10% TDH Degraded CCW Pump Curve 314 TEMPI Added TEMP I Isolation Valve to Enhance Computational Stability 300-319 Proposed CCWS Tic-Ins to Additions arc denoted by Altxx. Sec Attachment A FP Hx C and D 900-905 Fuel Pools A/B and C/D Added simulation for tuel pools A/B and C/D to provide fuel pool ctluilibrium temperature as a function of fuel pool heat load.

27/28/29 P I Isolate Added Pumpl Isolation valves with Cv~l000000 to allow for Pump2 (B Train) Operation SFP Hx D Fixed l teat Load Changed SFP Hx D to a lixed heat load to improve computational cflicicncy at low CCWS flow rates and light FP C/D heat load.

33 DischXTic Added gate valve with Cv 1000000 to simulate split CCW train ops, Rcferencc (30) 20 SuctXTic Added gate valve with Cv 1000000 to simulate split CGA train ops, Rcfercncc (30) 43 XSLD I IX Added Simulation Isolation Valve with Cv~l00000 to isolate thc Excess Letdown Heat Exchanger Only

Computed by: Date: Calculation ID: SF-0040 Jeff Lundy CAROLINAPOWER & LIGHTCOMPANY Checked by: Date: Pg 5 oc32 Rcv 0

CALCULATIONSHEET File:

Project No.:

Project

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 of the "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 of 0.00176 hr-sqft-'F/BTU significantly (50.4 percent) exceeds the current worst case trended tubeside fouling factor, Reference (35), of 0.00117 hr-sqft-'F/BTU thus the assumption of additional CCW heat exchanger degradation from tube failures would bc overly conscrvativc, given the excessive design fouling factor.

4.1.3 CVCS flow to the letdown heat exchanger is assumed to be at design Letdown flow conditions of 120 gpm pcr CPEcL direction, Reference (23).

4.>.4 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 of this 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

Computed. by: Date: Calculation ID: SF-0040 Jeff Lundy CAROLINAPOWER & LIGHT COMPANY Checked by: Date: i's 6 <32 i~~0 CALCULATIONSHEET File:

Project No.:

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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 Refueling operations cases, even though they are not rejecting heat to the CCWS. This assumption is conservative in terms of CCWS flow margins.

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'CW train.

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 of establishing 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 flow is 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 Jeff Lundy Checked by: Date: Ps 7 of 32 Rcv0 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 4.2 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. All alignments 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 If3 Coro Normal Full Abnormal Full Safety Sump Recirc with Sump Redro ILI) 4 hrs Modo 1 @4 hrs (350F) Shuftto Coro Ofaoad Coro Oftteod Irt)ection Essential Header with Umited (350F)

(Mode 6) (Mode 6) (Mode 6) Phaso Only SFP Cooring mp RHR Hx 8 RHR Pmp A RHR Hx A Flow BRS: Orst Cir 8RS: Evap Ctr Vent R THx Seal Water Hx FPHxA FPHx8 RCP A RCP 8 Flow Onty Flow SFP Hx C SFPHxo GFFD Sample Coolers Flow Only F low 2 (sp4t) 2 (split)

GFFO

, FcHuro. O'CW Single and Conlalnment Failure. All Single Singlo Sample Singlo Isdated (RCPs, I4enessenthl Failure of O'ailure of Codes Failure '8'CW XSLO Hx, RCOT Loads Isotatod Train CCW Tain Isdated Hx Secured). Only Except for SFP 8y S RHR Loads Hxs Signet I

All operating lineups use the benclunarkcd CCW pump curves for thc thermal margin analysis and the IST program 10 percent degraded pump curves for the flow margin analysis. CCW flow to thc cooled components for normal operations is consistent with the bcnchmarkcd values of Rcfcrcnce (1).

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CAROLINAPOWER & LIGHTCOMPANY Calculation ID: SF-0040 Jeff Lundy Checked by: Date: i'c <32 R~0 8

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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 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 limit of 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 of thc 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 of NUREG-0800.

The base heat load for fuel pool A/B is estimated as follows:

Normal Full Core Offload (RFO7) = 35.06 MBTU/lir [Reference (11)]

Fuel Pool A/9 Base Heat Load (RFO7) = 5.16 MBTU/lir [Rcfcrcnce (11)]

Calculated Refueling Heat Load (RFO7) = 29.9 MBTU/lir Specified fuel pool A/B and C Heat Load = 44.13 MBTU/lu [Attaclunent 5 of Refcrcnce (26)]

Fuel Pool C Heat Load ~ 0.9957 MBTU/lu [Attachment 8 of Reference (26)]

Refueling Heat Load = 29.9 MBTU/hr Estimated Fuel Pool A/B Base Ht Load = 13.23 MBTU/lu; use 13.3 MBTU/lirfor conservatism.

The Core Shuffle refueling alignment heat load of 25.0 MBTU/hr is estimated as follows:

Fuel Pool A/B Base Heat Load As of 9/26/2001 = 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 of 9/26/2001 = 13.3 + 11.68 25 MBTU/lu Thc maximum Abnormal Full Core Offload alignment heat load of 44.1 MBTU/hr is estimated as follows:

Fuel Pool A/B Base Heat Load As of 9/26/2001 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 of 9/26/2001 = 13.3+ 30.71 44.1 MBTU/hr These heat loads do not include the effect of any change in HNP core thermal power rating.

Computed by: Date:

CAROLINAPOWER 86 LIGHTCOMPANY Calculation ID: SF-0040 Jeff Lundy Checked by: Date: Pg 9 of 32 ReY0 CALCULATIONSHEET File:

Project No.:

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 Staitup Normal Ilot S/D Safe S/D Refuel Reluel Refuel LOCA LOCA (350+F) (350'F) (Mode 6) (Mode 6) (hlode 6)

Units Mode I @4 his @4 hrs Core Full Abnormal Sl Rccirc Recirc Reference Shume Omo d (RHR) (RIIR and SFP)

RHR Pump B Heat Load 70,000 N/A 70,000 Calc NSSS-38 R2 (BTU/hr) iuIRHx B Flow (gpm) I N/A 650/ N/A 0/ Gale NSS&38 R2/CC-Tin ('F) 350 140 0038 RO RHR Puny A Hea( Load 70000 70000 70000 70000 Calc NSSS-38 R2 (DTUnir)

RHR Hx A Flow (gpm) I N/A 650/3 SO 800/350 0/140 0/140 0/140 N/A 3903/244.1 3903/209 Calc NSSS.38 R2/CC-Tin ('F) 0038 RO BRS: Dist Ctr Iles( Load N/A N/A N/A N/A N/A Ass~ DRS Sh'd IBTUnir) Abandoned Inplace BRS: Eiup Clr Heat Load NIA N/A N/A N/A N/A Assume! BRS Skid (BTU/hr) Abandoned Inphec BRS: Vair Cond Heat Load NIA NIA N/A N/A N/A N/A N/A Assumal DRS Skid (BTU/br) Abandoned Inphce Letdown Hx Flow (gpm) I 120/ 120/ 120/ 120/ Design CVCS Flow at Tin ('F) 380 380 350 380 RCS Tanp XSLD Hx Flow (gpm) I 24.8/$ 60 N/A N/A N/A N/A N/A N/A N/A Spec Sheet in VM-Tin ('F) MRK RCDT Hx Flow (gpni) I 89.12/ 89.12/ 89.12/ 89.12/ 89.12/ 89.12/ 89.12/ 89.12/ Spec Shcct in VM-Tin ('F) 180 180 180 180 180 180 180 180 MRK Scat Water Hx Flow(gpni) I 128.1/ 128.1/ 128.1/ 128.1/ 128.1/ 128.1/ 128.1/ 128.1/ Spec Sheet in VM-Tin ('F) 138.5 138.$ 138.$ 138.5 138.$ 138.5 138.$ 138.5 MRK SFP HxA Heat Load 15200000 15200000 13500000 13500000 25000000 31780000 31780000 15200000 0 15200000 Estimated from (DTUnir) Rcfaence (26)

SFP Hxn Heat Load N/A N/A N/A N/A N/A N/A N/A (BTUnir)

RCP A Heat Load 367000 3G7000 3G7000 0 3G7000 I/3 of WEC CQI (BTUnir) 5361 6/5/79 Value RCP B Heat Load 367000 367000 367000 0 367000 I/3 of WEC CQI (DTUnir) 5361 6/5/79 Value RCP C Load 367000 0 367000 I/3 of WEC CQI

'eat 3G7000 3G7000 SFP Iix C (DTUnir)

Heat Load N/A N/A N/A N/A N/A '/A "

N/A S361 6/5/79 Value Secured (DTUnir),

SFP lix D Heat Load 1000000 1000000 1000000 1000000 1000000 1000000 Estimated from (DTU/hr) N/A Rcfcrencc (2G)

GFFD Heat Load N/A N/A N/A N/A N/A N/A 0 Assumed Negligible.

(BTU/hr) Ht Load ~ 0.24 MBTU/hr Sanyle Coolers liest Load N/A N/A 0 Assumed Negligil>le (DTU/hr) Due to Tnnsicnt Load Fuel Pool A/B Heat Load 15200000 15200000 13500000 13500000 25000000 31780000 31780000 15200000 15200000 15200000 Es(imatcd I'rom NTUnir) Refcrencc (26)

Fuel Pool C/D Heat Load 1000000 1000000 1000000 1000000 1000000 1000000 1000000 1000000 Estimated from (DTU/hr) 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 Thermal-Hydraulic Analysis Table 4 Summary of Spent Fuel Pool A/8 Heat Loads for Various CCW System Alignments Alignment As of Date Ccw SFP A/B SFP A/II Temperature Temp Heat Load Limit ('F) Limit ('F) (MIITU/hr)

Normal 10/22/2001 105 137 15.2 Hot S/D (350) 9/15/2001 120 137 13.5 Safe S/D(350'F) 9/I 5/2001 120 137 13.5 Refuel~re Shume 9/22/2001 105 137 25.0 Rcfucl-Normal Full Core Omoad (I) 9/22/2001 105 137 31.78 Refuel-Abnormal Full Core Omoad (I) 9/22/2001 105 137 31.78 LOCA-Safety Injection 10/22/2001 105 137 15.2 LOCA-Recirc (RHR Only) 10/22/2001 120 137 15.2 LOCA-Recirc (RHR/SFP) 10/22/2001 120 137 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 of thc SFP heat exchangers.

4.3 Evaluation of Minimum RHR 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/lir to 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 of 382 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 of 4280 sqft. However, during the initial phase of containmcnt 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 flow to 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 of the 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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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 flow also decreases, as shown in Figure 1 of Attaclunent (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 MIR heat exchanger heat duty of 118 MBTU/1ir. The increased MM heat 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 flow of 8500 gpm to the CCW heat exchangcrs was verified to be within the capacity of the current ESWS system, Reference (20), even considering the most limiting ESWS single failure of a MCC 1B35-SB feeder brcakcr failure, Rcfercnce (29).

.Evaluation of Maximum 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 flow of 5220 gpm is attainablc for a CCW heat cxchangcr ESWS flow of 8250 gpm and a maximum CCWS flow of 5440 gpm is attainable for an ESWS flow of 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 will bc cxccss flow to thc RHR heat exchanger, approximately 5440 gpm total, Attaclunent (D). The thermal cffcct of the excess RHR heat exchanger flow can be mitigated with an increase in the minimum ESWS flow to thc CCW heat exchanger of 250 gpm.

4.5 Evaluation of Minimum 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 of this analysis.

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Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Figure I SFP Hx Duty at a Given CCW Flow Rate 35 30

~ 25 20 0

15 X

o 10 0

5 FP emp~137F, empt t20F CI FP Temp ~137F.CCWTempu105F 0 ts 3000 ssump ons:

Design Fouling Factor u 0 001049 hr. sqft F/aTV CCW Flow (gpm) 5% Tube Ptugging Table 5 Minimum SFP Heat Exchanger CCW Flow Requirentents SFP Hx NB SFP Hx NB SFP Hx C/D SFP Hx C/D Thermal Flow Minimum -

Thermal Flow Minimum Requirement Flow (1) Requirement Flow (1)

Alignment As of Date (gpm) (gpm) (gpm) (gpm)

Normal 10/22/2001 1200 1272 60 63.6 Hot S/D (350F) 9/1 5/2001 2800 2968 125 132.5 Safe S/D(350F) 9/1 5/2001 2800 2968 125 132.5 Refuel-Core Shuffle 9/22/2001 2800 2968 Refuel-Normal Full Core Offload (2) 9/22/2001 5400 5400 (3) 60 63.6 Refuel-Abnormal Full Core Offload (2) 9/22/2001 5400 5400 (3) 60 63.6 LOCA-Safety Injection 10/22/2001 1200 1272 60 63.6 LOCA-Recirc (RHR Only) 10/22/2001 LOCA-Recirc (RHR/SFP) 10/22/2001 3830 4059.8 125 132.5 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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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'CW Train 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 of this 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 Tlirottle Valve Old Position/Misc K New Position/Misc K RHR Heat Exchanger A 1CC-146 49.24 % Open 48.61 % Open RHR Heat Exchanger B ICC-166 49.24 % Open 47.91 % Open RCDT Heat Exchanger 1CC-187 8.85 % Open 41.98 % Open XSLD Heat Exchanger ICC-197 12.91% Open 80.23% Open SFP Heat Exchanger A(B) 1CC-382(398) 34.35 % Open 27.94% Open SFP Heat Exchanger D(C) AltV-15(11) Not Installed 2.03 % Open RCP A Upper 13caring Cooler 1CC-258 194.00 14.14 RCP A Lower Bearing Cooler 1CC-264 90000 11971 RCP A Thermal Barrier 1CC-224 510.00 58.28 RCP B Upper Bearing Cooler 1CC-273 211.00 14.14 RCP B Lower Bearing Cooler 1CC-279 30584.00 11971 RCP B Thermal Barrier 1CC-235 320.00 58.28 RCP C Upper 13caring Cooler ICC-284 206.00 14.14 RCP C Lower Bearing Cooler ICC-290 80610.00 11965 RCP C Thcrrnal Barrier 1CC-246 404.00 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 flow control valve with a setpoint of 610 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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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 MIR heat exchanger PROTO-IDV" model, Rcfcrcncc (I), to meet a heat duty of 118.9 MBTU/lu and 177.76 MBTU/hr with the maximum RHR pump flow of 4500 gpm at an RCS temperature of 350'F. The Hot Shutdown case required heat duty of 118.9 MBTU/Ie is detcrmincd as follows:

RCS Sensible Heat Removal = 66.96 MBTU/hr [Table 9.2.1-7 of Rcferencc (31)]

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 = 110.8 MBTU/hr [Table 9.2.1-7 of Reference (31)]

RCP Heat (3 Pumps Operating) = 60 MBTU/hr [Reference (32)]

Total Heat Removal Required 237.76 MBTU/lu with 2 RHIVCCW trains in operation or = 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 of bringing 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 fiow of 8500 gpm to the CCW heat cxchangers, usc of design fouling factors for all heat exchangers and design (maximum) Ultimate Heat Sink temperature of 95'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 Thermal-Hydraulic Analysis conservative and that acceptable operation of thc Spent Fuel Pool heat exchangers under limiting conditions can be achieved. These results demonstrate that the redistribution of CCWS flow is adequate for the limiting CCW pump developed head.

For thc Refuel-Normal and Abnormal Full Core Offload cases in which a single failure of thc '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 of this analysis indicates that the SFP Hx A (or 8) can just accommodate an assumed full core offload heat load of 31.7 MBTU/hr at 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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Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7a Summary of CCWS Flow Margins Normal Ops Section Component Calculated Flow W!Ih 6% Min Flow Flow Margin (%)

(gpm) Uncertaint ( pm) 105 RHR Pump B 6.9 6.5 30%

108 RHRHx B 36 34.0 N/A 115 RHR Pump A 6.6 32%

112 RHR Hx A 36.9 34.8 N/A 66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 1158 1092.5 575 90%

45 XSLD Hx 318 300.0 247 21%

44 RCDT Hx 303 285.8 225 27%

Seal Water Hx 308 290.6 230 26%

98 SFP HxA 3613 3408.5 1200 184%

91 SFP Hx B N/A N/A RCP A Upper Oil Cooler 183.2 150 22%

203 RCP A Lower Oil Cooler 6.7 6.3 26%

205 RCP A Thermal Barrier 51.6 48.7 40 22%

208 RCP B Upper Oil Cooler 194.2 183.2 150 22%

207 RCP B Lower Oil Cooler 6.3 26%

209 RCP B Thermal Barrier 51.6 48.7 40 22%

214 RCP C Upper Oil Cooler 194.2 183.2 150 22%

212 RCP C Lower Oil Cooler 6.7 6.3 26%

215 RCP C Thermal Barrier 51.6 48.7 40 22%

304 SFP Hx C N/A 305 SFP Hx D 160.9 151.8 59 157%

Node 0401 GFFD 14 14 Specified Node0028 Sample Coolers 160 160 Specified 5 and 28 Total CCWS Flow 6887 6497.2 3305 97%

Operating CCW Train 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 Thermal-Hydraulic Analysis Table 7b Summary of CCKVS Flow Margins Hot S/D (350F)

Section Component Calculated With 6% Min Flow (gpm) Flow Margin (%)

Flow (gpm) Uncertainty 105 RHR Pump B 7.2 6.8 36%

108 RHRHx B 5199 4904.7 1300 277%

115 RHR Pump A 5.6 5.3 6%

112 RHR Hx A 3983 3757.5 1300 189%

66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A

'/A 73 BRS: Vent Cond 0.0 Letdown Hx 610 575.5 575 0%

45 XSLD Hx 262 247.2 247 0%

44 RCDT Hx 249.5 235.4 225 5%

54 Seal Water Hx 253.9 239.5 230 4 98 SFP Hx A 2980.3 2811.6 2800 0%

91 SFP Hx B N/A 204 RCP A Upper Oil Cooler 160 150.9 1%

203 RCP A Lower Oil Cooler 5.5 5.2 4 205 RCP A Thermal Barrier 42.5 40.1 40 0 208 RCP B Upper Oil Cooler 150.9 150 1%

207 RCP B Lower Oil Cooler 5.5 5.2 4%

209 RCP B Thermal Bamer 42.5 40.1 40 0%

214 RCP C Upper Oil Cooler 160 150.9 150 1%

212 RCP C Lower Oil Cooler 5.5 5.2 4%

215 RCP C Thermal Bamer 42.5 40.1 40 0%

304 SFP Kx C N/A N/A 305 SFP Hx D 'i32.7 125.2 125 0%

Node0401 GFFD 14 14 Specified Node0028 Sampte Cooters 160 160 Specified 5 and 28 Total CCWS Flow 14529.3 13706.9 7571 81%

Operating CCW Train A/B Split A/B Split Notes LD Hx Flow Limited to a 575 GPM Nominal Value Defined in FSAR

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Spent Fuel Pools C and D Activation Project Thermal-Hydraulic Analysis Table 7c

. Summary of CCAVS Flow Margins Safe S/D (350F)

Section Component Calculated Flow With 6% Min Flow (g pm) Flow Margin (%)

(gpm) Uncertainty 105 RHR Pump B 0.0 108 RHR Hx B 0.0 115 RHR Pump A 5.8 5.5 9%

112 RHR Hx A 4119 3885.8 2560 52%

66 BRS: Dist Cir 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 0.0 N/A 45 XSLD Hx 271.6 256.2 247 4 44 RCDT Hx 258.8 244.2 225 9%

54 Seal Water Hx 263.5 248.6 230 8%

98 SFP HxA 3096 2920.8 2800 4 91 SFP Hx B N/A 204 RCP A Upper Oil Cooler 165.9 156.5 150 4%

203 RCP A Lower Oil Cooler 5.7 5.4 8%

205 RCP A Thermal Barrier 44.1 41.6 40 4 208 RCP B Upper Oil Cooler 165.9 156.5 150 4%

207 RCP B Lower Oil Cooler 5.7 5.4 8%

209 RCP B Thermal Bamer 44.1 41.6 40 4%

214 RCP C Upper Oil Cooler 165.9 156.5 4%

212 RCP C Lower Oil Cooler 5.7 5.4 8%

215 RCP C Thermal Barrier 44.1 41.6 40 4%

304 SFP Hx C N/A N/A 305 SFP Hx D 137.9 130.1 125 4%

Node 0401 GFFD 14 Specified Nod e0028 Sample Coolers 160 160 Specified 5 and 28 Total CCWS Flow 9003 8493.4 6951 22%

Operating CCW Train a) RCPs are secured but CCWS flow is maintained.

Notes b) Letdown secured c) 'B'CW Train Single Failure

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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 7d Summary of CCWS I<'low Margins Refuel - Core Shuffle Section Component Calculated With 6% Min Flow (gpm) Flow Margin (%)

Flow Uncertainty (gpm) 105 RHR Pump B 0.0 N/A 108 RHR Hx B 0.0 N/A 115 RHR Pump A 5.8 5.5 N/A 112 RHR Hx A 4125 3891.5 N/A 66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 0.0 N/A 45 XSLD Hx 272 256.6 247 4%

44 RCDT Hx 259.3 244.6 225 9%

Seal Water Hx 249.1 230 8%

98 SFP HxA 3103 2927.4 2900 1%

91 SFP Hx B 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 A Thermal Barrier 44.1 41.6 40 4%

208 RCP B Upper Oil Cooler 166.3 156.9 150 5%

207 RCP B Lower Oil Cooler 5.7 5.4 8%

209 RCP B Thermal Barrier 44.1 41.6 40 4%

214 RCP C Upper Oil Cooler 166.3 156.9 '50 5%

212 RCP C Lower Oil Cooler 5.7 5.4 8%

215 RCP C Thermal Barrier 44.1 41.6 40 4%

304 SFP Hx C N/A 305 SFP Hx D 138.2 130.4 59 121%

Node0401 GFFD 14 14 Specified Node0028 Sample Coolers 160 Specified 5 and 28 Total CCWS Flow 8997.6 8488.3 4420 92%

Operating CCW Train a) RCPs are secured but CCWS flow is maintained.

Notes b) 'B'CW Train Single Failure c) No min flow is defined for the RHR hx as RPV is defueled

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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 7e Sumnmry of CCWS Flow Margins Refuel - Normal Core Offload Section Component Calculated Flow VNth 6% Min Flow Flow (gpm) Uncertainty (gpm) Margin (%)

105 RHR Pump B 0.0 N/A 108 RHR Hx B 0.0 N/A 115 RHR Pump A 4.9 4.6 112 RHR Hx A 3470 3273.6 N/A 66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 73 BRS: Vent Cond 0.0 N/A Letdown Hx 0.0 N/A 45 XSLD Hx 224 211.3 N/A 44 RCDT Hx 213.8 201.7 225 10%

Seal Water Hx 217.1 204.8 230 11%

98 SFP HxA 5325.9 5024.4 5400 -7%

91 SFP Hx B N/A 204 RCP A Upper Oil Cooler 137.1 129.3 NIA 203 RCP A Lower Oil Cooler 4.7 4,4 N/A 205 RCP A Thermal Bamer 36.3 34.2 NIA 208 RCP B Upper Oil Cooler 137.1 129.3 NIA 207 RCP B Lower Oil Cooler 4.7 4,4 N/A 209 RCP B Thermal Barrier 36.3 34.2 N/A 214 RCP C Upper Oil Cooler 137.1 129.3 N/A 212 RCP C Lower Oil Cooler 4.7 4,4 N/A 215 RCP C Thermal Bamer 36.3 N/A 304 SFP Hx C N/A N/A 305 SFP Hx D 110.6 104.3 60 74%

Node0401 GFFD 14 14 Specified Node0028 Sample Coolers 160 150.9 160 Specified Sand 28 Total CCWS Flow 10285 9702.8 6089 59%

Operating CCW Train A a) RCPs are secured but CCWS flow is maintained.

b) 'B'CW Train Single Failure c) No min flow is defined for the RHR hx as RPV is defueled Notes 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 flow Is defined for XSLD Hx as LD is secured

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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 7f Summary of CCIVS Flow Margins Refuel - Abnormal Core Offload Section Component Calculated Flow With 6% MinFlow(gpm) FlowMargin(%)

(gpm) Uncertainty 105 RHR Pump B 7.2 6.8 36%

108 RHRHx B 5213 4917.9 N/A 115 RHR Pump A 4.9 4.6 8%

112 RHR Hx A 3470.3 3273.9 N/A 66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 0.0 N/A 45 XSLD Hx 224.1 211.4 N/A 44 RCDT Hx 213.8 201.7 225 10%

54 Seal Water Hx 217.1 204.8 230 -11%

'8 SFP Hx A 5326 5024.5 5400 -7%

91 SFP Hx B N/A 204 RCP A Upper Oil Cooler 137.1 129.3 N/A 203 RCP A Lower Oil Cooler 4.7 4.4 N/A 205 RCP A Thermal Bamer 36.3 34.2 N/A 208 RCP B Upper Oil Cooler 137.1 129.3 N/A 207 RCP B Lower Oil Cooler 4.7 4.4 NIA 209 RCP B Thermal Barrier 36.3 N/A 214 RCP C Upper Oil Cooler 137.1 129.3 212 RCP C Lower Oil Cooler 4.7 4.4 NIA 215 RCP C Thermal Barrier 36.4 34.3 NIA 304 SFP Hx C N/A 305 SFP Hx D 110.6 104.3 59 77%

Node0401 GFFD 14 14 Specified Node0028 Sample Coolers 160 160 Specified 5 and 28 Total CCWS Flow 15505.2 14627.5 6098 140%

Operating CCW Train a) RCPs are secured but CCWS is maintained.

b) No min flow is defined for the RHR hx as RPV is defueled c) SFP A/B hx CCW set to 5400 gpm Notes d) RCDT, Seal Wtr Hx and SFP A/B Hx performance exceeds the design requiroments e) No min flow is defined for XSLD Hx as LD is secured

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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 7g Summary of CCWS I<low Margins LOCA - Safety Injection Section Component Calculated Flow With 6% Min Flow (gpm) Flow Margin (gpm) Uncertainty (%)

105 RHR Pump B 6.9 6.5 30%

108 RHR Hx B 36.3 34.2 N/A 115 RHR Pump A 6.6 32%

112 RHRHxA 37.1 35.0 N/A 66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 1145 1080.2 575 88%

45 XSLD Hx 321 302.8 247 23%

44 RCDT Hx 305.8 288.5 225 28%

Seal Water Hx 310.5 292.9 230 27%

98 SFP Hx A 3641.6 3435.5 1200 186%

91 SFP Hx B N/A 204 RCP A Upper Oil Cooler 196.1 185.0 150 23%

203 RCP A Lower Oil Cooler 6.7 6.3 26%

205 RCP A Thermal Barrier 52.1 49.2 40 23%

208 RCP B Upper Oil Cooler 196.1 185.0 23%

207 RCP B Lower Oil Cooler 6.7 6.3 26%

209 RCP B Thermal Barrier 52.1 49.2 40 23%

214 RCP C Upper Oil Cooler 196.1 185.0 23%

212 RCP C Lower Oil Cooler 6.7 6.3 26%

215 RCP C Thermal Barrier 52.1 49.2 40 23%

304 SFP Hx C N/A "0 N/A 305 SFP Hx D 162.2 153.0 59 15g Node0401 GFFD 0.0 Isolated Node0028 Sample Coolers 0.0 Isolated Sand 28 Total CCWS Flow 6746 6364.2 3131 103%

Operating CCW Train Notes a) System configuration is immediately after 'S'ignal

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Spent I'uel Pools C and D Activation Project Calculation

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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 With 6% Min Flow Flow Margin (%)

(gpm) Uncertainty (gpm) 105 RHR Pump B N/A 108 RHR Hx B 0.0 N/A 115 RHR Pump A 7.3 6.9 37%

0'.0 112 RHR Hx A 5193 4881.4 4874 0%

66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 0.0 N/A 45 XSLD Hx 0.0 N/A 44 RCDT Hx 0.0 N/A 54 Seal Water Hx 0.0 98 SFP HxA 0.0 N/A 91 SFP Kx B 204 RCP A Upper Oil Cooler 0.0 N/A 203 RCP A Lower Oil Cooler 0.0 N/A 205 RCP A Thermal Barrier 0.0 N/A 208 RCP B Upper Oil Cooler 0.0 N/A 207 RCP B Lower Oil Cooler 0.0 209 RCP B Thermal Barrier 0.0 N/A 214 RCP C Upper Oil Cooler 0.0 ~ NIA 212 RCP C Lower Oil Cooler 0.0 N/A 215 RCP C Thermal Barrier 0.0 304 SFP Hx C N/A N/A N/A 305 SFP Hx D N/A N/A N/A Node0401 GFFD Isolated Node0028 Sample Coolers Isolated 5 and 28 Total CCWS Flow 5238 4923.7 4879 1%

Operating CCW Train A (Split) A (Split)

Notes a) Only operator action is splitting CCW Trains

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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 7i Summary of CCAVS Flow Margins LOCA - Sump Recirc (RHR/SFP)

Section Component Calculated VNth 6% Min Flow (gpm) Flow Margin Flow (gpm) Uncertainty (%)

105 RHR Pump B 0.0 N/A 108 RHR Hx B 0.0 N/A 115 RHR Pump A 6.3 5.9 18%

112 RHR Hx A 4472 4203.7 2250 87%

66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 NIA 61 Letdown Hx 0.0 NIA 45 XSLD Hx 0.0 N/A 44 RCDT Hx 0.0 NIA 54 Seal Water Hx 0.0 0. N/A 98 SFP HxA 3381.5 3178.6 3830 -17%

91 SFP Hx B N/A 204 RCP A Upper Oil Cooler 0.0 NIA 203 RCP A Lower Oil Cooler 0.0 NIA 205 RCP A Thermal Barrier 0.0 N/A 208 RCP B Upper Oil Cooler 0.0 NIA 207 RCP B Lower Oil Cooler 0.0 N/A 209 RCP B Thermal Barrier 0.0 NIA 214 RCP C Upper Oil Cooler 0.0 N/A 212 RCP C Lower Oil Cooler 0.0 N/A 215 RCP C Thermal Bamer 0.0 N/A 304 SFP Hx C N/A N/A N/A 305 SFP Hx D 150.6 141.6 125 13%

Node0401 GFFD Isolated Node0028 Sample Coolers Isolated Sand 28 Total CCWS Flow 8038 7555.7 6210 22%

Operating CCW Train A (Split) A (Sptit) a) Operators manually bring SFP hxs online by opening Notes upslream isolation valves

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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 7j Summary of CCWS Flosv Margins Startup Ops Section Component Calculated Flow With 6% Min Flow (gpm) Flow Margin (%)

(gpm) Uncertainty 105 RHR Pump B 6.9 6.5 30%

108 RHRHx B 35.9 33.9 N/A 115 RHR Pump A 6.9 6.5 30%

112 RHR Hx A 36.7 34.6 N/A 66 BRS: Dist Clr 0.0 N/A 80 BRS: Evap Clr 0.0 N/A 73 BRS: Vent Cond 0.0 N/A 61 Letdown Hx 1250 1179.2 1100 7%

45 XSLD Hx 317.4 247 21%

299.4'84.5 44 RCDT Hx 301.6 225 26%

Seal Water Hx 306.8 289.4 230 26%

98 SFP HxA 3597.4 3393.8 1200 183%

91 SFP Hx B N/A N/A N/A 204 RCP A Upper Oil Cooter 193.4 182.5 150 22%

203 RCP A Lower Oil Cooter 6.7 6.3 26%

205 RCP A Thermal Bamer 51.4 48.5 40 21%

208 RCP B Upper Oil Cooler 193A 182.5 22%

207 RCP B Lower Oil Cooler 6.7 6.3 26%

209 RCP B Thermal Barrier 51.4 48.5 40 21%

214 RCP C Upper Oil Cooter 193.4 182.5 150 22%

212 RCP C Lower Oil Cooler 6.7 6.3 26%

215 RCP C Thermal Bamer 51.4 48.5 40 21%

304 SFP Hx C N/A 305 SFP Hx D 160.2 151.1 59 156%

Nod e0401 GFFD 14 14 Specified Node0028 Sample Coolers 160 160 Specified 5 and 28 Total CCWS Flow 6958 6564.2 3830 71%

Operating CCW Train A Notes RHR Hx Outlet Isolation Valves are Shut

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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 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 of the 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 of 4500 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 of 205.7 feet.

Maximum letdown flow is assumed on the CVCS side of the Letdown heat exchanger simultaneously with operation of the 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 of Transient Spent I<'uel Pool Thermal Performance An estimate of the short term transient thermal performance, Attacluncnt (BB), of the 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 of the fuel pool and neglecting changes in the water thermal properties.

'i Fuel pool heatup thermal transients are calculated from:

P .VENT ~FuelPool ~SFPHx Equation (1) where:

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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 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 Equation (2) d/ E.+1-r ~

Solving for T at the i+I time step results in:

i+1 r .(~ (

i+i=T.+ i

< ~ (gFeelPeol <<SPPHxj Equation (3) p Cp.V 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 of Attaclunent (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 of late 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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Spent Fuel Pools C and D Activation Project Calculation

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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 limit of 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 of the 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 limit of 137'F. Table 2 of Attachment (BB) shows that fuel pool C will not exceed 113.8'F which is less than the administrative limit of 137'F and less than the 126'F, assumed for design basis HVAC conditions 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 of Reference (34). A thermal transient analysis of Spent 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 limit of 137'F.

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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 8a Summary of CCWS Steady-State Thermal Capacity Alignment Startup Normal Hot S/D (350F) Safo S/D (350F)

Load Units Mode 1 Refcrenco RHR Pump B Heat Load Calo NSSS~ R2 BTU/hr RHRHx B Heat Load 71926000 Calculated BTU/hr RKR Pump A Heat Load 70000 Cate NSSSQG R2 BTU/hr RHR Hx A Heat Load 67817000 81098000 Calculated BTU/hr BRS: Dist Clr Heat Load Assumed BRS Skid Abandoned BTU/tu ln taco BRS: Evap Clr Heat Load Assumed BRS Skid Abandoned BTU/hr ln lace BRS: Vent Cond Heat Load Assumed BRS Skid Abandoned TU/hr In tace Letdown Hx Heat Load 15827000 15827000 12536000 Catculated TU/hr XSLO Hx Heat Load Calculated BTU/hr RCDT Hx Heat Load 2386000 2428000 1871000 1890000 Calcutated BTU/hr Seal Water Hx KeatLoad 1626000 1689000 881000 898000 Calculated BTU/hr SFP Hx A Heat Load 15345000 15343000 13683000 13680000 Calculated 8TU/hr SFP HxB Heat Load Secured 8TU/hr RCP A Heat Load 367000 367000 1/3 of WEC CQL4361 6/5/79 Valuo BTU/hr RCP B Heat Load 367000 367000 367000 0 1/3 of WEC CQL4361 6/5/79 Valuo TU/hr RCP C Heat Load 3G7000 367000 367000 1/3 of WEC CQL~t 6/5/79 Valuo BTU/hr SFP HxC Heat Load Sccurcd BTU/hr SFP Hx 0 Heat Load 1000000 1000000 1000000 Fixed BTU/hr GFFO Heat Load BTU/hr Samplo Coolers HeatLoad BTU/hr CCW Trains No Operating 2 (Split) Consistent w/DBD-131 CCW Hx Ht Out 8TU/hr 42,913,000 36,852,000 171,612,748 99.528.000 Calculated CCW Su Tem 105.1 103.8 119.6/110.5 119.4 Calculated @ Node0011 Design CCW Supply (F) 105 105 Consistent w/ DBD-131 Tcm ESW Flow (Design) (gpm)

Design Basis ESW Inlet (F) 95 95 95 Tcm Fuel Pool A/B Temp (F) 122.3 121.0 13G.O Fuel Pool A/B Temp Lfmt (F) 137.0 137.0 137.0 137.0 Fuel Pool C/O Temp (F) 117.2 115.8 134.0 133.3 Fuel Pool C/0 Temp Limit (F) 137.0 137.0 137.0 137.0

Date:

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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 8b Summary of CCXVS Steady-State Thernial Capacity Refuel Refuet Refuel LOCA LOCA Load Units Coro Shuffle Full Offload Abnormal SI Recirc (A) Recirc (B) Refercnco RHR Pump B Meal Load Cato NSSS48 R2 BTU/lu RHR Hx B Heal Load Copulated BTUhu RHR Pump A Heat Load 70000 70000 Calo NSSS~ R2 BTU/hr RKR HXA Heat Load 118077000 81336000 Calculated BTU/hr BRS: Dist Clr Heat Load Assumed 8RS Skid TU/hr Abandoned In laco BRS: Evap Clr Heat Load Assumed BRS Skid 8TU/hr Abandoned In co BRS: Vent Cond Heat Load Assumed BRS Stdd BTU/hr Abandoned ln taco Letdown Hx Heat Load 15827000 Calculated BTU/hr XSLD Hx Heat Load Calculated 8TU/hr RCDT Hx Heat Load 2394000 2249000 2248000 2437000 BTU/hr Seal Water Hx HeatLoad 1673000 1498000 1497000 1701000 Calculated BTU/hr SFP Hx A Keat Load 25271000 32121000 32122000 15341000 Calculated BTU/lu SFP Hx B 'eal Load Securod BTU/hr RCP A Heat Load 1/3 of WEC CQL4361 6/5/79

'I BTU/hr Valuo RCP B Heat Load 1/3 of WEC CQL~1 6/5/79 BTU/hr Valuo RCP C Heat Load 367000 0 1/3 of WEC CQL<361 6/5/79 BTU/hr Valuo SFP Hx C HeatLoad Secured BTUhu SFP Hx D Keat Load 1000000 1000000 Fixed BTU/hr GFFD Keel Load BTU/hr Sampto Coolers HcalLoad 0 8TU/hr CCW Trains No Operating 2 (Split) Split (1/I) Split (I/1) Consistent w/DBD-131 CCW Hx Kt Du BTU/hr 31.258.000 38.239.000 38.388.629 188.153.000 97,728,000 Calculated CCWSu I Tem 102.8 104.8 104.8/95.0 103.6 120.0 118.4 Calculated Node0011 Design CCW Supply (F) 105 105 105 105 Consistent w/ DBD-131 Temp ESW Flow (Design) (gpm)

Design Basis ESW Inlet (F) 95 95 95 95 95 Tem Fuel Pool A/B Temp (F) 132.9 136.4 136,4 120.8 Isolated 135.9 Fuel Pool A/B Temp (F) 137.0 137.0 137.0 137.0 137.0 137.0 Umt Fuel Pool C/D Temp (F) 116.9 122.5 122.5 115.5 Isolated 131.8 Fuel Pool C/D Temp (F) 137.0 137.0 137.0 137.0 137.0 137.0 Umit

Computed by: Date: Calculation ID: SF-0040 Jeff Lundy CAROLINAPOWER & LIGHTCOMPANY Checked by: Date: Pg 3I or 32 Rcv 0

CALCULATIONSHEET Project No.:

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 of a minimum CCW heat exchanger flow of 8500 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 of the UHS is currently specified as 95'F, Reference (19).

The thermal margin of the 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 of the auxiliary rcscrvoir, it was determined, Attachment (AA), that the change in surface heat flux was 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: Date:

CAROLINAPOWER & LIGHT COMPANY Calculation ID: SI'-0040 Jeff Lundy Checked by: Date: Pg 32 of 32 Rev0 CALCULATIONSHEET File:

Project No.:

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 will have a negligible impact on the design Ultimate Heat Sink temperature or level.

KNCj OSURE 4 to SKMAL: HNP-99-129 SHEARON HARRIS NUCLEAR POWER 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 AND SFP) 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: Carolina Power and Light Plant: Harris Nuclear Plant System: Component Cooling Water System Version: Revision 2 Fluid: Fresh Water Case Alignment: LOCA: Recirc (RHR and SFP Cooling)

System was NOT Balanced to Balancing Parameters Calculation was completed: 06-08-1998 16:38 Pressure Tolerance 0.0000100 Sum of Flows Tolerance: 0.0100000 Friction Factor Tolerance: 0.0000010 Fixed Flow Tolerance: 0.0001000 Pressure Control Tolerance: 0.0010000 Temperature Tolerance: 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&L Calc 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 Page 3 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 Pipe:116.00 Node0106 - Node0104 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:120.00 Node0212 - Node0210 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:121.00 Node0212 - Node0214 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:312.00 AltN7 - AltN10 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:901.00 FP3 - FP1 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 Page 1 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)

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 Temp= 154.20 N2: Node0002 Press= 39.67 Elev= 250.62 Flow= 0.00 Temp= 142.04 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 Temp= 142.04 N2: Node0003 Press= 38.99 Elev= 250.75 Flow= 0.00 Temp= 142.04 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 Temp= 142.04 N2: Node0004 Press= 42.74 Elev= 238.72 Flow= 0.00 Temp= 142.04 Pipe: 5.00 ID = 15.250 Flow = 8,099.73 NPSHA = 93.00 N1: Node0004 Press= 42.74 Elev= 238.72 Flow= 0.00 Temp= 142.04 N2: Node0005 Press= 123.88 Elev= 238.59 Flow= 0.00 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 Temp= 142.04 N2: Node0006 Press= 118.12 Elev= 248.30 Flow= 0.00 Temp= 142.04 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 Temp= 142.04 N2: Node0007 Press= 116.24 Elev= 250.63 Flow= 0.00 Temp= 142.04 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 Temp= 142.04 N2: Node0008 Press= 117.97 Elev= 245.00 Flow= 0.00 Temp= 142.04 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 Temp= 142.04 N2: Node0009 Press= 112.42 Elev= 244.67 Flow= 0.00 Temp= 118.02 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 Temp= 118.02 N2: Node0010 Press= 106.90 Elev= 250.69 Flow= 0.00 Temp= 118.02 l! Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Below Vapor Pressure

Attachment:

Z

'l2 Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR Rev: 0 Page 5 of 41

&& Flow Past End of Pump Curve

I I 06-08-1998 16:38

~l PROTO-FLO I 3.04 by Proto-Power Corporation - Serial ¹PFL-0000

~ Page 2 Carolina Power and Light -I 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)

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 Temp= 118.02 N2: Node0011 Press= 106.74 Elev= 250.71 Flow= 0.00 Temp= 118.02 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 Temp= 127.10 N2: Node0002 Press= 39.67 Elev= 250.62 Flow= 0.00 Temp= 142.04 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 Temp= 127.10 N2: Node0028 Press= 39.71 Elev= 250.62 Flow= 0.00 Temp= 127.10 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 Temp= 127.10 N2: Node0030 Press= 40.09 Elev= 250.68 Flow= 0.00 Temp= 127.10 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 Temp= 118.02 N2: Node0301 Press= 106.59 Elev= 250.67 Flow= 0.00 Temp= 118.02 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 Temp= 118.02 N2: Node0101 Press= 107.05 Elev= 246.97 Flow= 0.00 Temp= 118.02 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 Temp= 118.02 N2: Node0024 Press= 106.65 Elev= 250.71 Flow= 0.00 Temp= 118.02 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 Temp= 127.10 N2: Node0027 Press= 40.04 Elev= 250.70 Flow= 0.00 Temp= 127.10 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 Temp= 118.02 N2: Node0307 Press= 107.22 Elev= 248.81 Flow= 0.00 Temp= 118.02 II Reverse Flow Thru Check Valve

++ Section Was Balanced Fixed Pressure CP&L Calc ID: SF-0040

/o'/o Pressure Below Vapor Pressure

Attachment:

Z V2 Temperature Outside Fluid Property Range PO NPSHA less than NPSHR Rev: 0 Page 6 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial 5PFL-0000 'age3 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)

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 Temp= 127.10 N2: Node0306 Press= 40.14 Elev= 250.68 Flow= 0.00 Temp= 127.10 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 Temp= 118.02 N2: Node0311 Press= 107.16 Elev= 248.83 Flow= 0.00 Temp= 118.02 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 Temp= 127.10 N2: Node0310 Press= 41.13 Elev= 248.83 Flow= 0.00 Temp= 127.10 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 Temp= 127.10 N2: Node0328 Press= 41.91 Elev= 247.31 Flow= 0.00 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 Temp= 118.02 N2: AltN1 Press= 108.20 Elev= 245.34 Flow= 0.00 Temp= 118.02 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 Temp= 126.93 N2: Node0211 Press= 46.72 Elev= 238.09 Flow= 0.00 Temp= 126.93 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 Temp= 126.93 N2: Node0212 Press= 102.01 Elev= 237.99 Flow= 0.00 Temp= 126.93 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 Temp= 118.02 N2: Node0209 Press= 103.27 Elev= 243.48 Flow= 0.00 Temp= 126.93 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 Temp= 118.02 N2: Node0208 Press= 108.38 Elev= 243.58 Flow= 0.00 Temp= 118.02

!! Reverso Flow Thru Check Valve

++ Section Was Balanced CP&L Calc ID: SF-0040

- Fixed Pressure

Attachment:

Z

/o/o Pressure Below Vapor Pressure

'?'? Temperature Outside Fluid Property Range Rev: 0 Page 7 of 41

¹4 NPSHA less than NPSHR

&8 Flow Past End of Pump Curve

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 4 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)

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 Temp= 118.02 N2: Node0207 Press= 107.64 Elev= 245.33 Flow= 0.00 Temp= 1'18.02 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 Temp= 118.02 N2: Node0102 Press= 97.40 Elev= 262.35 Flow= 0.00 Temp= 118.02 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 Temp= 118.02 N2: Node0103 Press= 89.88 Elev= .243.78 Flow= 0.00 Temp= 154.22 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 Temp= 154.22 N2: Node0116 Press= 48.66 Elev= 244.98 Flow= 0.00 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 Temp= 118.02 N2: Node0105 Press= 128.04 Elev= 197.53 Flow= 0.00 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 Temp= 118.02 N2: Node0106 Press= 126.95 Elev= 198.68 Flow= 0.00 Temp= 140.62 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 Temp= 140.62 N2: Node0104 Press= 42.54 Elev= 247.00 Flow= 0.00 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 Temp= 154.20 N2: Node0001 ** Press= 41.98 Elev= 247.00 Flow= 0.00 Temp= 154.20 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 Temp= 126.93 N2: Node0210 Press= 46.83 Elev= 238.01 Flow= 0.00 Temp= 126.93

!! Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Betow Vapor Pressure

Attachment:

Z

'?? Temperature Outside Fiuid Property Range

¹¹ NPSHA less than NPSHR Rev: 0 Page 8 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 5 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)

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 Temp= 126.93 N2: Node0214 Press= 47.79 Elev= 236.74 Flow= 0.00 Temp= 126.93 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 Temp= 126.93 N2: Node0215 Press= 47.60 Elev= 236.74 Flow= 0.00 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 Temp= 126.93 N2: Node0215 Press= 47.60 Elev= 236.74 Flow= 0.00 Temp= 126.93 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 Temp= 126.93 N2: Node0206 Press= 46.52 Elev= 238.09 Flow= 0.00 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 Temp= 154.22 N2: Node0115 Press= 88.24 ~ Elev= 243.81 Flow= 0.00 Temp= 154.22 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 Temp= 154.22 N2: Node0104 Press= 42.54 Elev= 247.00 Flow= 0.00 Temp= 154.20 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 Temp= 154.22 N2: Node0116 Press= 48.66 Elev= 244.98 Flow= 0.00 Temp= 154.22 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 Temp= 118.02 Press= 108.20 Elev= 245.34 Flow= 0.00 Temp= 118.02 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 Temp= 118.02 Press= 108.20 Elev= 245.34 Flow= 0.00 Temp= 118.02 l! Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Below Vapor Pressure

'?? Temperaturo Outside Fluid Property Range

Attachment:

Z

¹¹ NPSHA less than NPSHR Rev: 0 Page 9 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 6 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)

Pipe: 305.00 ID = 13.250 Flow= 154.20 Vel = 0.359 Turbulent f = 0.0201 Reynold's Number = 6.8100E+04 N1: AltN5 Press= 108.20 Elev= 245.34 Flow= 0.00 Temp= 118.02 N2: AltN7 Press= 108.19 Elev= 245.34 Flow= 0.00 Temp= 131.13 Pipe: 306.00 ID = 13.250 Flow= -153.95 Vel = -0.358 Turbulent f = 0.0203 Reynold's Number = 6.4052E+04 N1: AltN5 Press= 108.20 Elev= 245.34 Flow= 0.00 Temp= 118.02 N2: AltN3 Press= 108.20 Elev= 245.34 Flow= 0.00 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 Temp= 131.13 N2: AltN11 Press= 43.08 Elev= 245.00 Flow= 0.00 Temp= 131.13 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 Temp= 131.13 Press= 42.07 Elev= 247.36 Flow= 0.00 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 Temp= 131.13 N2: AltN10 Press= 43.08 Elev= 245.00 Flow= 0.00 Temp= 131.13 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 Temp= 126.93 N2: AltN12 Press= 42.07 Elev= 247.36 Flow= 0.00 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 Temp= 118.02 Press= 107.93 Elev= 245.33 Flow= 0.00 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 Temp= 135.68 N2: FP2 Press= 228.18 Elev= 0.00 Flow= 0.00 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 Temp= 127.47 N2: FP1 ** Press= 100.00 Elev= 0.00 Flow= 0.00 Temp= 135.68 II Reverse Flow Thru Check Valve

++ Section Was Balanced Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Below Vapor Pressure

Attachment:

Z YE Temperature Outside Fluid Property Range

¹¹ NPSHA less than NPSHR Rev: 0 Page 10 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 7 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)

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 Temp= 127.47 Press= 228.18 Elev= 0.00 Flow= 0.00 Temp= 127.47 ll Reverso Flow Thru Check Valve

- Fixed Pressure

++ Section Was Balanced CP8t:L Calc ID: SF-0040

%% Pressure Below Vapor Pressure

Attachment:

Z

'?'P Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR Rev: 0 Page 11 of 41 8 8 Flow Past End of Pump Curve

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 1 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)

Pump Name Pump1 Manufacturer Model 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:

Pump Name Pump2 Manufacturer: Model:

Drawings:

Pump Status: OFF Speed (RPM>: Flow (gpm): Head (ft):

Hydraulic Horsepower:

Pump Impeller Datum (ft) Inlet Node Elevation (ft): 238.74 Pump Suction Temperature ('F NPSH Curve: NONE NPSH Available: NPSH Required:

Pump Name Pump3 Manufacturer: Model:

Drawings:

Pump Status: OFF Speed (RPM): Flow (gpm): Head (ft):

Hydraulic Horsepower:

Pump Impeller Datum (ft) Inlet Node Elevation (ft): 238.73 Pump Suction Temperature ('F NPSH Curve: NONE NPSH Available: NPSH Required:

Pump Name FP1 Manufacturer Model:

Drawings:

Pump Status: DummySFPCPump Speed (RPM): Flow (gpm): 3,749.84 Head (ft): 300.01 Hydraulic Horsepower: 280.42 Pump Impeller Datum (ft) Inlet Node Elevation (ft):

Pump Suction Temperature ('F 135.68 NPSH Curve: 'ONE NPSH Available: 228.10 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 Page 2 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)

Pump Name: FP2 Manufacturer: Model:

Drawings:

Pump Status: OFF Speed (RPM): Flow (gpm): Head (ft):

Hydraulic Horsepower:

Pump Impeller Datum (ft) Inlet Node Elevation (ft):

Pump Suction Temperature ('F NPSH Curve: NONE NPSH Available: NPSH Required:

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 Page 1 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)

Tag Valve Type Position Actual **

0 1CC-146 Butterfly 47 91%

1CC-155 Globe 3.93%

1CC-166 Butterfly 48.61%

1CC-187 Globe 41.98%

1CC-197 Globe 12.90%

1CC-323 Globe 41.32%

1CC-353 Globe 0 75%

1CC-356 Globe 24.17%

1CC-363 Butterfly 20.56%

1CC-382 Butterfly 28.42%

1CC-398 Butterfly 28.42%

A RHR OUTLET Gate 100.00%

AHXlsol Gate 100 00%

AitV1 Gate 0.00%

AitV10 Butterfly 0.00%

Altv11 Butterfly 2 09%

AitV12 Gate 0.00%

AitV13 Gate P PP%

AitV14 Butterfly 100 00%

AitV15 Butterfly 2.09%

AitV2 Butterfly 100.00%

AitV4 Gate ppp AitV5 Gate 0.00%

AltV6 Butterfly 100.00%

AltV7 Butterfly 0.00%

AltV8 Gate 100.00%

AitV9 Gate 100.00%

B SFPC HX Gate P PP%

BRSEC Gate 0.00%

BRSEC Gate P PP%

CCW B/C SUCT Gate 0.00%

CCW PUMP B/C Gate P PP%

Closed Gate P PP%

Closed Gate P P0%

DischXTie Gate ppp LOCA Isolate Gate P PP%

LOCA Isolate Gate 0.00%

LOCA Isolate Gate P PP%

LOCA Isolate Gate ppp P1lsolate Gate 0.00%

P1lsoiate Gate ppp RCP IN Gate P PP%

RCP OUT Gate P PP%

RHR A BYPASS Gate 1PP PP RHR B BYPASS Gate P PP%

RHR B OUTLET Gate P PP%

SFPC HX FD Gate P PP%

• 'ctual Position CF&L Calc ID: SF-0040 for Partially Open Check Valves

Attachment:

Z Rev: 0 Page 14 of 41

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 2 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)

Tag Valve Type Position Actual **

SuctionXTie Gate P PP%

TEMP1 Gate P PP%

XSLD HX Gate 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 Page 1 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) ag: is oo er ype: ixe ea oa a us Mfr: Model: Dwgs:

System Fluid:

Heat Load = O.OOBTU/hr 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 FIX Status: 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 LMTD Corrections 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 LMTD Corrections 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 = 1,000,000.00BTU/hr CP&L Calo ID: SF-0040

Attachment:

Z Rev: 0 Page 16 of 41

06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 2 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) ag: x ype: e u e aus: n o in ow a Mfr: Joseph Oat Model: 22-165/BFU Dwgs: Dwgf/5428 Rev 1 Tube Fluid: Fresh Water Shell 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 LMTD Corrections 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 LMTD Corrections 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 ype: ixe ea oa a us:

Mfr: Model: Dwgs System Fluid:

Heat Load = 0.00BTU/hr FIK1ag: RCPSCwWryrIC~r ype: rxe ea oa a us:

Mfr: Model: Dwgs System Fluid:

Heat Load = 0.00BTU/hr RICrag: RCPSTIIermBaarl ype: rxe ea ~oa RX S&aus 0 Mfr: Model: Dwgs:

System Fluid:

Heat Load = O.OOBTU/hr 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 Page 3 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) ag: pr i r ype: ixe ea oa a us:

Mfr: Model: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr FIX~ag: RCpcCwr01rClrrr ype: ixe ea oa cgreece: 0 Mfr: Model: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr RX'Tag: RCPcThermgaarl Mfr: Model: Dwgs:

System Fluid:

Heat Load = O.OOBTU/hr FIX Tag: RCPcoprOtIC r ype: ixe ea oa ~raaue: 0 Mfr: Model: 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 LMTD Corrections 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 LMTD Corrections 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 Tube Temperatures = 118.02'F - 140.62'F Heat Load = 70,000.00BTU/hr CP6Q. Calc ID: SF-0040

Attachment:

Z Rev: 0 Page 18 of 41

06.08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 4 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) ag: Illp r a us Mfr: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr BXTag: SeeaW~rx ype: WerS~ueB X S~aus: On/igoTin Flow Pal 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 LMTD Corrections FF = 0.0000 Fb = 0.0000 Heat Load = 0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F HXTag: SFP~xA HXTyype: "WelirTugeel X 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 LMTD Corrections 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 LMTD Corrections 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

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06-08-1998 16:38 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 5 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) ag: x ype: e u e aus: n o in ow a Mfr: Yuba Model: 39-285/CEN Dwgs: EA1ABCD 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 = 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 LMTD Corrections FF = 0.0000 Fb = 0.0000 Heat Load = 0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F 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 f X Sfatus: On NoHn 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 LMTD Corrections 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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Z Rev: 0 Page 20 of 41

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: Carolina Power and Light Plant: Harris Nuclear Plant System: Component Cooling Water System Version: Revision 2 Fluid: Fresh Water Case Alignment: LOCA: Recirc (RHR and SFP Cooling)

System was NOT Balanced to Balancing Parameters Calculation was completed: 06-08-1 998 16:41 Pressure Tolerance 0.0000100 Sum of Flows Tolerance: 0.0100000 Friction Factor Tolerance: 0.0000010 Fixed Flow Tolerance: 0.0001000 Pressure Control Tolerance: 0.0010000 Temperature Tolerance: 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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Z Rev: 0 Page 22 of 41

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 3 Carolina 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 Pipe:116.00 Node0106- Node0104 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:120.00 Node0212 - Node0210 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:121.00 Node0212 - Node0214 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:312.00 AltN7 - AltN10 DP > 50% of Inlet Pressure Cavitation Flow Possible Pipe:901.00 FP3 - FP1 DP > 50% of Inlet Pressure Cavitation Flow Possible CP&L Calc ID: SF-0040

Attachment:

Z Rev: 0 Page 23 of 41

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 1 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)

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 Temp= 153.48 N2: Node0002 Press= 39.60 Elev= 250.62 Flow= 0.00 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 Temp= 141.66 N2: Node0003 Press= 38.88 Elev= 250.75 Flow= 0.00 Temp= 141.66 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 Temp= 141.66 N2: Node0004 Press= 42.52 Elev= 238.72 Flow= 0.00 Temp= 141.66 Pipe: 5.00 ID = 15.250 Flow = 8,417.93 NPSHA =92.54 N1: Node0004 Press= 42.52 Elev= 238.72 Flow= 0.00 Temp= 141.66 N2: Node0005 Press= 130.16 Elev= 238.59 Flow= 0.00 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 Temp= 141.66 N2: Node0006 Press= 124.27 Elev= 248.30 Flow= 0.00 Temp= 141.66 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 Temp= 141.66 N2: Node0007 Press= 122.31 Elev= 250.63 Flow= 0.00 Temp= 141.66 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 Temp= 141.66 N2: Node0008 Press= 123.99 Elev= 245.00 Flow= 0.00 Temp= 141.66 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 Temp= 141.66 N2: Node0009 Press= 117.99 Elev= 244.67 Flow= 0.00 Temp= 118.39 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 Temp= 118.39 N2: Node0010 Press= 112.23 Elev= 250.69 Flow= 0.00 Temp= 118.39 I! Reverse Flow Thru Check Valve

-++Fixed Section Was Balanced Pressure CP&L Calo ID: SF-0040

'/o'/o Pressure Below Vapor Pressure

'?? Temperature Outside Fluid Property Range

Attachment:

Z

¹¹ NPSHA less than NPSHR Rev: 0 Page 24 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 2 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)

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 Temp= 118.39 N2: Node0011 Press= 112.06 Elev= 250.71 Flow= 0.00 Temp= 118.39 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 Temp= 127.13 N2: Node0002 Press= 39.60 Elev= 250.62 Flow= 0.00 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 Temp= 127.13 N2: Node0028 Press= 39.65 Elev= 250.62 Flow= 0.00 Temp= 127.13 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 Temp= 127.13 N2: Node0030 Press= 40.06 Elev= 250.68 Flow= 0.00 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 Temp= 118.39 N2: Node0301 Press= 111.90 Elev= 2 0.67 Flow= 0.00 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 Temp= 118.39 N2: Node0101 Press= 112.27 Elev= 246.97 Flow= 0.00 Temp= 118.39 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 Temp= 118.39 N2: Node0024 Press= 111.96 Elev= 250.71 Flow= 0.00 Temp= 118.39 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 Temp= 127.13 N2: Node0027 Press= 40.01 Elev= 250.70 Flow= 0.00 Temp= 127.13 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 Temp= 118.39 N2: Node0307 Press= 112.51 Elev= 248.81 Flow= 0.00 Temp= 118.39 ll Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SP-0040

%% Pressure Below Vapor Pressuro

Attachment:

Z Y? Temperature Outside Fluid Property Range Nf NPSHA less than NPSHR Rev: 0 Page 25 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 3 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)

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 Temp= 127.13 N2: Node0306 Press= 40.12 Elev= 250.68 Flow= 0.00 Temp= 127.13 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 Temp= 118.39 N2: Node0311 Press= 112.45 Elev= 248.83 Flow= 0.00 Temp= 118.39 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 Temp= 127.13 N2: Node0310 Press= 41.12 Elev= 248.83 Flow= 0.00 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 Temp= 127.13 N2: Node0328 Press= 41.92 Elev= 247.31 Flow= 0.00 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 Temp= 118.39 N2: AltN1 Press= 113.46 Elev= 245.34 Flow= 0.00 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 Temp= 126.96 N2: Node0211 Press= 46.79 Elev= 238.09 Flow= 0.00 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 Temp= 126.96 N2: Node0212 Press= 106.52 Elev= 237.99 Flow= 0.00 Temp= 126.96 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 Temp= 118.39 N2: Node0209 Press= 108.07 Elev= 243.48 Flow= 0.00 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 Temp= 118.39 N2: Node0208 Press= 113.58 Elev= 243.58 Flow= 0.00 Temp= 118.39 Il Reverse Flow Thru Check Valve

++ Section Was Balanced Fixed Pressure CP&L Calc ID: SF-0040

/o%%d Pressure Below Vapor Pressure

Attachment:

Z 22 Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR Rev: 0 Page 26 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 4 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)

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 Temp= 118.39 N2: Node0207 Press= 112.84 Elev= 245.33 Flow= 0.00 Temp= 118.39 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 Temp= 118.39 N2: Node0102 Press= 102.37 Elev= 262.35 Flow= 0.00 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 Temp= 118.39 N2: Node0103 Press= 93.61 Elev= 243.78 Flow= 0.00 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 Temp= 153.50 N2: Node0116 Press= 49.13 Elev= 244.98 Flow= 0.00 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 Temp= 118.39 N2: Node0105 Press= 133.24 Elev= 197.53 Flow= 0.00 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 Temp= 118.39 N2: Node0106 Press= 132.10 Elev= 198.68 Flow= 0.00 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 Temp= 140.14 N2: Node0104 Press= 42.58 Elev= 247.00 Flow= 0.00 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 Temp= 153.48 N2: Node0001 ** Press= 41.98 Elev= 247.00 Flow= 0.00 Temp= 153.48 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 Temp= 126.96 N2: Node0210 Press= 46.91 Elev= 238.01 Flow= 0.00 Temp= 126.96 II Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Below Vapor Pressure

'?'? Temperature Outside Fluid Property Range

Attachment:

Z

¹¹ NPSHA less than NPSHR Rev: 0 Page 27 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 5 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)

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 Temp= 126.96 N2: Node0214 Press= 47.90 Elev= 236.74 Flow= 0.00 Temp= 126.96 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 Temp= 126.96 N2: Node0215 Press= 47.69 Elev= 236.74 Flow= 0.00 Temp= 126.96 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 Temp= 126.96 N2: Node0215 Press= 47.69 Elev= 236.74 Flow= 0.00 Temp= 126.96 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 Temp= 126.96 N2: Node0206 Press= 46.58 Elev= 238.09 Flow= 0.00 Temp= 126.96 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 Temp= 153.50 N2: Node0115 Press= 91.84 Elev= 243.81 Flow= 0.00 Temp= 153.50 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 Temp= 153.50 N2: Node0104 Press= 42.58 Elev= 247.00 Flow= 0.00 Temp= 153.48 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 Temp= 153.50 N2: Node0116 Press= 49.13 Elev= 244.98 Flow= 0.00 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 Temp= 118.39 N2: AltN2 Press= 113.46 Elev= 245.34 Flow= 0.00 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 Temp= 118.39 N2: AltN3 Press= 113.46 Elev= 245.34 Flow= 0.00 Temp= 118.39

!! Reverso Flow Thru Check Valve

++ Section Was Balanced Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Below Vapor Pressuro

Attachment:

Z

'?'? Temperature Outside Fluid Property Range fry NPSHA less than NPSHR Rev: 0 Page 28 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 6 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)

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 Temp= 118.39 N2: AltN7 Press= 113.45 Elev= 245.34 Flow= 0.00 Temp= 131.00 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 Temp= 118.39 N2: AltN3 Press= 113.46 Elev= 245.34 Flow= 0.00 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 Temp= 131.00 N2: AltN11 Press= 43.09 Elev= 245.00 Flow= 0.00 Temp= 131.00 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 Temp= 131.00 N2: AIIN12 Press= 42.09 Elev= 247.36 Flow= 0.00 Temp= 127.13 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 Temp= 131.00 N2: AltN10 Press= 43.10 Elev= 245.00 Flow= 0.00 Temp= 131.00 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 Temp= 126.96 N2: AltN12 Press= 42.09 Elev= 247.36 Flow= 0.00 Temp= 127.13 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 Temp= 118.39 N2: Node0201 Press= 113.16 Elev= 245.33 Flow= 0.00 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 Temp= 127.57 N2: FP1 **Press= 100.00 Elev= 0.00 Flow= 0.00 Temp= 135.78 ll Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SF-0040

%%d%%d Pressure Below Vapor Pressure

Attachment:

Z

'?2 Temperature Outside Fluid Property Range

¹¹ NPSHA less than NPSHR Rev: 0 Page 29 of 41

&& Flow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 7 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)

Pipe: 902.00 ID= 9.750 Flow= 3,745.67 Vel= 16.097 Turbulent f = 0.0140 Reynold's Number = 2.3081E+06 N1: FP2 Press= 228.17 Elev= 0.00 Flow= 0.00 Temp= 127.57 N2: FP3 Press= 228.17 Elev= 0.00 Flow= 0.00 Temp= 127.57 II Reverse Flow Thru Check Valve

++ Section Was Balanced

" Fixed Pressure CP&L Calc ID: SF-0040

%% Pressure Below Vapor Pressure

Attachment:

Z

'2V Temperature Outside Fluid Property Range ffffNPSHA less than NPSHR Rev: 0 Page 30 of 41

&& Fiow Past End of Pump Curve

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 1 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)

Pump Name Pump1 Manufacturer Model:

Drawings:

Pump Status: Design Pump1 Speed (RPM): Flow (gpm): 8,417.93 Head (ft): 205.60 Hydraulic Horsepower: 430.18 Pump Impeller Datum (ft) Inlet Node Elevation (ft): 238.72 Pump Suction Temperature ('F 141.66 NPSH Curve: NONE NPSH Available: 92.54 NPSH Required:

Pump Name Pump2 Manufacturer: Model:.

Drawings:

Pump Status: OFF Speed (RPM): Flow (gpm): Head (ft):

Hydraulic Horsepower:

Pump Impeller Datum (ft) Inlet Node Elevation (ft): 238.74 Pump Suction Temperature ('F NPSH Curve: NONE NPSH Available: NPSH Required:

Pump Name Pump3 Manufacturer: Model:

Drawings:

Pump Status: OFF Speed (RPM): Flow (gpm): Head (ft):

Hydraulic Horsepower:

Pump Impeller Datum (ft) Inlet Node Elevation (ft): 238.73 Pump Suction Temperature ('F NPSH Curve: NONE NPSH Available: NPSH Required:

Pump Name FP1 Manufacturer: Model:

Drawings:

Pump Status: DummySFPCPump Speed (RPM): Flow (gpm): 3,749.84 Head (ft): 300.01 Hydraulic Horsepower: 280.42 Pump Impeller Datum (ft) Inlet Node Elevation (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 Page 2 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)

Pump Name: FP2 Manufacturer: Model:

Drawings:

Pump Status: OFF Speed (RPM): Flow (gpm): Head (ft):

Hydraulic Horsepower:

Pump Impeller Datum (ft) Inlet Node Elevation (ft):

Pump Suction Temperature ('F NPSH Curve: NONE NPSH Available: NPSH Required:

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 Page 1 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)

Tag Valve Type Position Actual "*

I 0 1CC-146 Butterfly 47 91%

1CC-155 Globe 3.93%

1CC-166 Butterfly 48.61%

1CC-187 Globe 41.98%

1CC-197 Globe 12.90%

1CC-323 Globe 41.32%

1CC-353 Globe 0.75%

1CC-356 Globe 24.17%

1CC-363 Butterfly 20.56%

1CC-382 Butterfly 28.42%

1CC-398 Butterfly 28.42%

A RHR OUTLET Gate 100 00%

AHXlsol Gate 100 00%

Altv1 Gate 0.00%

Altv10 Butterfly p pp Altv11 Butterfly 2.09%

Altv12 Gate 0.00%

Altv13 Gate P PP%

Altv14 Butterfly 100.00%

AltV15 Butterfly 2.09%

Altv2 Butterfly 100 00%

Altv4 Gate ppp Altvs Gate P PP%

Altv6 Butterfly 100.00%

Altv7 Butterfly P PP%

Altvs Gate 100.00%

Altv9 Gate 100.00%

B SFPC HX Gate 0.00%

BRSEC Gate ppp BRSEC Gate 0.00%

CCW B/C SUCT Gate 0.00%

CCW PUMP B/C Gate P PP%

Closed Gate 0.00%

Closed Gate P PP%

DischXTie Gate P PP%

LOCA Isolate Gate 0.00%

LOCA Isolate Gate P PP%

LOCA Isolate Gate 0.00%

LOCA Isolate Gate P PP%

Pilsolate Gate 0.00%

P1lsolate Gate P PP%

RCP IN Gate P PP%

RCP OUT Gate 0.00%

RHR A BYPASS Gate 100.00%

RHR B BYPASS Gate P PP%

RHR B OUTLET Gate 0.00%

SFPC HX FD Gate 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 Page 2 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)

Tag Valve Type Position Actual **

0 SuctionXTie Gate 0.00%

TEMP1 Gate 0.00%

XSLD HX Gate P PP%

• 'ctual Position for Partially Open Check Valves

Attachment:

c:Z F-0040 Rev: 0 Page 34 of 41

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 1 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) ag: is oo er ype: ixe ea oa a us:

Mfr: Model: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr H~ag: HRS~vap Coo er ype: axe ea ~oa RX greens: 0 Mfr: Mod el: Dwgs:

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 LMTD Corrections 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 LMTD Corrections 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: Dwgs System Fluid:

Heat Load = 1,000,000.00BTU/hr CP&L Calc ID: SF-0040

Attachment:

Z Rev: 0 Page 35 of 41

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial ¹PFL-0000 Page 2 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) ag: x ype: e u e aus: n o in ow a Mfr: Joseph Oat Model: 22-165/BFU Dwgs: Dwgftt5428 Rev 1 Tube Fluid: Fresh Water Shell 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 LMTD Corrections 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 LMTD Corrections 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 Sa us Mfr: Model: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr R

Mfr: Model: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr 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 Page 3 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) ag: pr i r ype: ixe ea oa a us Mfr: Model: Dwgs:

System Fluid:

Heat Load = 0.00BTU/hr eat Load FIKSraius: 0 Mfr: Model: Dwgs:

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 I IFlow 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 LMTD Corrections 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 LMTD Corrections FF = 0.0000 Fb = 0.0000 Heat Load = O.OOBTU/hr UOverall = 0.00 BTU/hr/ft"2/'F H~ag: RHKPmp C r A 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 CP&L Calc ID: SF-0040

Attachment:

Z Rev: 0 Page 37 of 41

06-08-1998 16:41 PROTO-FLO 3.04 by Proto-Power Corporation - Serial PPFL-0000 Page 4 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) ag: Illp r ype: ixe ea oa a us Mfr: Model: 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 LMTD Corrections FF = 0.0000 Fb = 0.0000 Heat Load = 0.00BTU/hr UOverall = 0.00 BTU/hr/ft"2/'F "RX Tag: 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 LMTD Corrections 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 LMTD Corrections 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 Page 5 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) ag: x ype: e u e aus: n o in ow a Mfr: Yuba Model: 39-285/CEN Dwgs: EA1ABCD 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 = 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 LMTD Corrections 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 LMTD Corrections 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

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18:17:16 PROTO-HX 3.02 by Proto-Power Corporation (SNPPHX-0000) 06/08/98 Carolina Power and Light Calculation Report for Spent Fuel HX - Spent Fuel Pool Heat Exchanger Calculation Specifications Constant Inlet Temperature Method Was Used Extrapolation Was to User Specified Conditions Design Fouling Factors Were Used Test Data Extrapolation Data Data Date Tube Flow (gpm) 3,750.0 Shell Flow (gpm) Shell Flow (gpm) 160.3 Shell Temp In ('F) Tube Inlet Temp ('F) 131.1 Shell Temp Out ('F) Shell Inlet Temp ('F) 118.4 Tube Flow (gpm)

Tube Temp In ('F)

Tube Temp Out ('F)

Fouling Calculation Results Shell Mass Flow (ibm/hr) U Overall (BTU/hr ft"F)

Tube Mass Flow (Ibm/hr) Shell-Side ho (BTU/hr ft"F)

Tube-Side hi (BTU/hr ft"F)

Heat Transferred (BTU/hr) 1/Wall Rcsis (BTU/hr ft"F)

LMTD LMTD Correction Factor Effective Area (ft')

Overall Fouling (hr IP'F/BTU)

Property Shell-Side Tube-Side Velocity (A/s) Shell Temp In ('F)

Reynold's Number Shell Temp Out ('F)

Prandtl Number Tav Shell ('F)

Bulk Vise (ibm/ft.lu) Shell Skin Temp ('F)

Skin Vise (Ibm/ft hr) Tube Temp In ('F)

Density (ibm/ft') Tube Temp Out ('F)

Cp (BTU/ibm'F) Tav Tube ('F)

K (BTU/hr ft'F) Tube Skin Temp ('F)

Extrapolation Calculation Results Shell Mass Flow (ibm/hr) 8.018E+4 Overall Fouling (hr IP'F/BTU) 0.001049 Tube Mass Flow (ibm/hr) 1.876E+6 Shell-Side ho (BTU/lu"ft"F) 225.6 Tube-Side hi (BTU/hr ft"F) 2,161.2 Heat Transferred (BTU/hr) 1.027 E+6 1/Wall Resis (BTU/hr ft"F) 3,845.3 LMTD 3.2 LMTD Correction Factor 0.3994 Effective Area (ft') 5,065.0 U Overall (BTU/hr A"F) 160.0 Property Shell-Side Tube-Side Velocity (ft/s) 0.113 7.244 Shell Temp In ("F) 118.4 Reynold's Number 1.016E+03 6.238E+04 Shell Temp Out ('F) 130.8 Prandtl Number 3.468 $ 3.26 Tav Shell ('F) 124.6 Bulk Vise (ibm/ft.hr) $ 1.29 $ 1.22 Shell Skin Temp ('F) 129.0 Skin Vise (ibm/ft hr) $ 1.24 $ 1.23 Tube Temp In ('F) 131.1 Density (ibm/ft') $ 61.64 $ 61.54 Tube Temp Out ('F) 130.6 Cp (BTU/ibm'F) $ 1.00 $ 1.00 Tav Tube('F) CP&L Calc ID: SF-00401308 K (BTU/hr ft'F) $ 0.37 $ 0.37 Tube Skin Temp (%tachment: Z

• • Reynolds Number Outside Range of Equation Applicability Rev: 0 Page 40 of 41

!! With Minimum Fouling Thc Test Heat Load Could Not Bc Achie

18:17:16 PROTO-HX 3.02 by Proto-Popover Corporation (SNPPHX-0000) 06/08/98 Carolina Power and Light Calculation Report for Spent Fuel HX - Spent Fuel Pool Heat Exchanger Shell and Tube Heat Exchanger Input Parameters Shell-Side Tube-Side yl' Q~y, TBR gpm 0'P

$ 358.00 Inlet Temperature 105.00 120.00 Outlet Temperature QF 110.62 112.00 Fouling Factor 0.00050 0.00050 Shell Fluid Name Fresh Water Tube Fluid Name Fresh Water Design Heat Transfer (BTU/hr) 15,060,000 Design Heat Trans Coeff (BTU/hr ft2'F) . 418.00 Emprical Factor for Outside h 0.962424000 Performance Factor (% Reduction) 0.00 Heat Exchanger Type TEMA-E Effective Area (A*2) 5,065.00 Area Factor 0.984417230 Area Ratio Number of Shells per Unit 1 Shell Minimum Area 3.187000000 Shell Velocity (A/s) 0.000 Tube Pitch (in) 0.9375 Tube Pitch Type Triangular Number of Tube Passes 2 U-Tubes No Total Number of Tubes 1,324 Number of Active Tubes 1,324 Tube Length (A) 23.75 Tube Inside Diameter (in) 0.569 Tube Outside Diameter (in) 0.625 Tube Wall Conductivity (BTU/hr O') 9.40 Ds, Shell Inside Diameter (in) 39.000 Lbc, Central Baffle Spacing (in) 11.830 Lbi, Inlet Baffle Spacing (in) 0.000 Lbo, Outlet Baffle Spacing (in) 0.000 Dotl, Tube circle diameter (in) 0.000 Bh, Baffle cut height (in) 0.000 Lsb, Diametral difference between Baffle and Shell (in) 0.000 Ltb, Diametral difference between Tube and Baffle (in) 0.000 Nss, Number Sealing Strips 0.000 CPS'alc ID: SF-0040

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