ML20151X881
| ML20151X881 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/23/1998 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20151X850 | List: |
| References | |
| PM-1011, PM-1011-R02, PM-1011-R2, NUDOCS 9809170282 | |
| Download: ML20151X881 (48) | |
Text
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ENCLOSURE 4 Core Spray (CS) Pump NPSH Analysis i
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Erh1 bit NE-C-420-1, Rev. 2 1. Calculation No.
I Effective Date:
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CALCULATION COVER SHEET ,
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- 3. Unit (s) D ) !
PECO Nuclear pg . /. .
Doctype 061 35 6. Safety Related Non-Sefety Related D k f 4 ECR/Other No. - O!? .I J 8 - 5. Last Page No.
7.
Description:
- 8. System /ropic No.: N r (C26 Sys et *4 Y ) v='*/ $~' O Structure : lh Component: ;
i Record of Revisions
- 13. Signatures ;
- 9. Rev. 11. Vendor Calc. 12. Assumptions Rev. YES NO Preparer Reviewer Approver (s) / Date >
No. 10. Description of Revision Number lNCsg/c,yT's gy,y;g y ggp 2 (
'l# ' '
Whei (%'4 h% 6p5 46 i A MT h L RA A5 UCX.4Ng0 Ff4A P A -te n h v.\
- 15. Manual g
- 14. Related Calculation No(s). Computer O Provides Info. To: Computer Program 6. Version No. :
Receives Info. From: g g { gg
- 17. Total Pages:
- 16. Provides Info. To: (DS Info. Only)
UFSAR/ Tech. Spec./etc.:
, 50 9 NO CALC. # __7M "/#// REV. f.
l RESP MGR YES l DCD # DATE:
1 CALCULATION REVIEW CHECKLIST 1 l l MANUAL COMPUTER YES or N/A CALC. CALC.
@ X CALCULATION IS THE APPROPRIATE BASIS FOR THE ACTIVITY YEr CALCULATION ASSUMPTIONS, CONSIDERATIONS, AND V43"
@ X METHODOLOGY CONFORM TO APPLICABLE DESIGN REQUIREMENTS
$ X SOURCES OF DATA AND FORMULAS WERE REVIEWED AND VERIFIED TO BE CORRECT AND COMPLETE VEY l l
@ X INPUT DATE IS CORRECT AND USED PROPERLY VA"I l @ THE ANALYTICAL METHOD USED IN THE CALCULATION HAS VE<
BEEN CONSIDERED AND IS PROPER FOR THE INTENDED USE X MATHEMATICAL ACCURACY HAS BEEN CHECKED AND IS CORRECT VilC5' l (INDICATE METHOD USED)
A) COMPLETE CHECK OF EACH COMPUTATION vp r 1 l
l B) SPOT CHECK OF SELECTED COMPUTATIONS hAv l C) PERFORMANCE OF ALTERNATE OR APPROXIMATION ale CALCULATION (ATTECHED) {
X X CALCULATION RESULTS WERE CHECKED AGAINST APPLICABLE v.rs'
! DESIGN CRITERIA AND WERE FOUND TO BE IN COMPLIANCE X X EXISTING CALCULATIONS REQUIRING REVISION AS A RESULT ve c OF THIS CALCULATION HAVE BEEN IDENTIFIED & DOCUMENTED X THE ANALYTICAL METHODS DESCRIBED IN THE COMPUTER udr )
CALCULATION
SUMMARY
IS PROPER FOR THE INTENDED USE X X ALL SYSTEM AND TOPIC NUMBERS ASSOCIATED WITH THE Yrr l CALCULATION ARE LISTED ,
X COMPUTATIONAL ACCURACY HAS BEEN CHECKED AND IS A/f I
l CORRECT (INDICATE METHOD USED)
A) CHECK SAMPLE CALCULATION USING DATA OTHER THAN NIO THAT USED IN THE SAMPLE B) PERFORMANCE OF ALTERNATE OR APPROXIMATION N CALCULATION (ATTACHED)
C) DESCRIBE OTHER METHOD USED: A//t l
X PROGRAM USED IS APPROPRIATE, INPUT IS VALID, AND MA OUTPUT IS REASONABLE CONSIDERING THE INPUT X X BASE CALCULATION HAS BEEN REVIEWED AGAINST CURRENT VE"c" l DRAWING REVISIONS AND POSTED DCDS TO IDENTIFY
[ SIGNIFICANT DIFFERENCES The criteria listed above are the minimum criteria to be considered and are not intended to limit the initiative of the reviewer to consider other criteria.
Attributes applicable to manual and computer calculations are noted by an "X" in the j appropriate column.
List the documents used to support this review. ~2w -/On / Ar.ry . A own w & Fmera2c REVIEWED BY: DATE: M9/9E
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! NUCLEAR GROUP l
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- 1. PURPOSE / OBJECTIVE The purpose of this calculation is:
A. to determine the NPSH margin for the Core Spray pumps and required containment overpressure as a function of time following a DBA LOCA, ( recirc. suction line break) assuming one case with the strainer design basis debris loading and one case with the maximum expected post LOCA debris load, maximum torus water level drawdown, maximum high pressure service water temperature and containment sprays activated at time = 0 seconds.
B. to determine the effect on NPSHA if a LOCA occurs while purging. Some nitrogen and steam will be lost before the purge valves close, which will affect the containment overpressure and l therefore NPSH available to the pumps. This is evaluated with an additional 1 ft. Icss of torus water level and the maximum expected post LOCA strainer debris load.
! C. to generate curves for various pool levels, pool temperatures and overpressure conditions to determine the limits of these parameters for adequate pump NPSH. Four curves will be generated to demonstrate the temperature impact on allowable pump flow rate from various overpressure conditions for 4 torus water levels; 10.5',12.3',14.5' and 20'. All curves assume clean suction strainers.
NOTE: THIS CALCULATION SUPERCEDES THE NPSH AND SUCTION PIPING PRESSURE DROP CALCULATIONS FOR THE UNITS 2 AND 3 CORE SPRAY PUMP SUCTIONS FROM
! THE TORUS IN CALCULATIONS 18247-M-006,18247-M-29; AND ME-363; AND PARTIALLY SUPERCEDES CALCULATION 11187-M-024 AND 18247-M-001, Utilization of this calculation by persons without access to the pertinent factors and without proper regard for its purpose could lead to erroneous conclusions. Should it become desirable to use this calculation to support design or station activities other than those explicitly specified in this section, the responsible engineering branch shall be contacted to ensure that the purposes, assumptions, judgments, and limitations are thoroughly understood.
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l 196 21453 8/96 CALC. NO. : PM-1011 PAGE:
- PECO ENERGY CALCULATION SHEET 3 I N'UCLEAR GROUP l
l 2.
SUMMARY
OF RESULTS l
Part A l
l The limiting NPSH margin for the DBA LOCA (700 cu.ft. of NUKON) is 6.65 ft., which occurs at
! the maximum torus temperature of 205.7 F and a containment pressure of 22.10 psia.
Part B I
- Should a LOCA occur while the containment is being purged, the NPSH margin would be l reduced from 6.65 ft. to 4.59 ft., which is acceptable.
Part C Curves developed by this calculation for the most limiting condition for the core spray pumps are l included in pages 34 through 47.
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CALC. NO. : PM-101i PECO ENERGY CALCULATION SHEET PAGE: 4 NUCLEAR GROUP l 3. DESIGN INPUT / CRITERIA Design inputs for this calculation are as follows:
- 1. The torus temperatures and pressures evaluated in Parts A and C are taken from Calculation PM-1013, Rev.0 ( Ref.15 ) !
- 2. The torus temperatures and pressures evaluated in Part B are taken from Reference 1. I
- 3. Piping data was derived from Ref. 5 through 9.
- 4. Suction strainer data is taken from Ref. 22.
- 5. Core Spray pump NPSHR data is taken from Ref.15.
- 6. Torus level and pump flow rates followir,g LOCA are taken from Reference 1 for all cases.
- 7. Strainer AP data is as follows: ( Ref. 22, Appendix 111) 1633 ft* Nukon debris load ( strainer design basis )
Temperature Pump flow AP l
(*F) (gpm) ( ft.) ,
205.7 3125 4.34 205.7 4030 5.68 700 ft* NUKON debris load ( debris load in zone of destruction )
Temperature Pump flow AP
(*F) (gpm) ( ft.)
205.7 3125 1.69 Clean Strainer Temperature Pump Flow AP
(*F) (gpm) ( ft.)
205.7 3125 1.35
- 4. Computer Calculations l No computer calculations were used in the development of this calculation. Excel spreadsheets were utilized.- However, these spreadsheets were utilized as an automated calculator only.
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- 5. Assumptions
- 1. The computation of the torus temperature based on calculated vapor pressure, in part B, is not completely interpo!ated in that the pressure conversion factor uses the value of 2.31 rather than a temperature corrected value. The effect on NPSH due to this minor underestimation of temperature is not significant.
1
- 6. References
- 1. GE letter Report EAS 10-0289 on Suppression Pool Drawdown, May 18,1989, transmitted by G-HE-9-114, dated May 18,1989, DC# 027673.
- 2. Piping Specification M-300, Rev.14
- 3. NUREG/CR-2772 " Hydraulic Performance of Pump Suction Inlets for Emergency Core Cooling Systems in Boiling Water Reactors", June 1982.
- 4. Peach Bottom UFSAR Fig. 6.4.2, Condition IV.
- 5. Bechtel Drawing 6280-M-93, Rev.17
- 6. ISO 2-14-1, Rev. 3
- 7. ISO 214-3, Rev.11
- 8. ISO 214-8, Rev. 2
- 9. ISO 2-14-10, Rev. 2
- 10. Crane Technical Paper N. 410 " Flow of Fluids Through Valves, Fittings, and Pipe *,1980 Edition.
- 11. ASME Steam Tables,5* Edition
- 12. Peach Bottom improved Tech. Spec. 3.6.2.2
- 13. NE-265 - Specification for ECCS Suction Strainers, Limerick Generating Station, Units 1 and 2 and Peach Bottom Atomic Power Station Units 2 and 3, Rev. A, dated February 11,1997.
- 14. Calculation PM-1004, Rev 0
- 15. Pump Curve - Core Spray Pump - Dwg. 6280-M-1-U-224-14
- 16. Dwg. 6280-M1-U-99, Rev.15
- 17. Calculation PM-1013, Rev.1
- 18. P&lD M-362 Sheet 2 Rev. 60 Core Spray Cooling System
- 19. Calculation 11187 M-024, Rev.2 MASEEMPORMST,ALCSHT. DOC 6/19/98 1:40 PM
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4 1964114fi3 8/96 CALC. NO. : PM-1011 PECO ENERGY CALCUi.ATION SHEET PAGE: 6 NUCLEAR GROUP
- 20. UFSAR Fig.14.6.10B, Rev.13
- 21. UFSAR Fig.14.6.12A, Rev.13 1
- 22. SDOC # NE-265-17, Rev.1
- 23. Calculaticn ME-
- 24. Calculation ME-
- 25. SDOC#NE-265-16, Rev.0 l
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- 7. Attachments !
1 Attachment #1: Pressure Drops - PBAPS Unit 3 Strainers ( Reference 22, pages 19 and 20 ) i Attachment #2: Core Spray Pump Curves ( Reference 15 )
- 8. Analysis A. NPSH Margins for the Core Spray Pumps Under the Worst Expected Accident Conditions The methodology used to perform this calculation was to review the suct;on piping arrangement for
' the Core Spray pumps at Peach Bottom to detennine the K value for each suction loop. The bounding
- K value was then used along with the strainer head losses from Ref. 22 to calculate the total head losses through the bounding CS suction loop for the temperatures given in Ref.17. This information was combined with containment pressure data from Ref.17 to calculate NPSHA. This data was compared to the NPSHR for the Core Spray pumps to determine NPSH margin at various times following a DBA LOCA.
Calculatino NPSHA NPSHA = Z,,-Z,,+144P ,/p - h,- h,- 144P,,,/p where: Z, = Elevation of torus water surface Zy, = Elevation of pump suction
- Note
- Center line of the Core Spray pump suction is at elevation 94'-6", (i.e.,
l equal to the elevation of the bottom of the torus). Thus, Z,,- Z,,is equal to the torus water level.
P., = Torus pressure P,,, = vapor pressure at torus water temperature t
h,= piping friction losses h, = strainer head loss l'
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PECO ENERGY CALCULATION SHEET PAGE:
REVISION ,
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NUCLEAR GROUP l~
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l p = density of water at forus water temperature I Calculatino h, I The method used to calculate h, for the various flow rates and temperatures is as follows: j l
- 1) Calculate h, at some reference temperature and flow rate.
)
1
- 2) Calculate h, at other temperatures and flows using the following equation: '
hf2= h,,x (O2/ O,)2 x ( v2/Vi )
where: hei = reference piping head loss br2 = calculated piping head loss i Q i = flow rate for reference piping losses I 1
O2= flow rate for calculated piping losses vi = specific volume for water at reference temperature l
v2 = specific volume for water at temperature at which piping losses are being calculated Reference oicino losser From Ref.10, pg. 3-4 h, = 0.00259 KQ'/d' For 16' Core Spray Suction Piping d = 15.25 in. ,
D = 1.27 ft.
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196-214b3 8/96 l
CALC. NO. . PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 8 NUCLEAR GROUP Piping Takeoffs :
Pump A Suction Piping:
Piping Segment Dia. (in.) Length 1 15.25 3'-8*
( 2 15.25 13'-10' 3 15.25 6*-0*
- 4 15.25 6'-0*
5 15.25 3'-9*
6 15.25 2'-7%*
Total 35'-10%* or 35.90 ft.
K value for *A* Pump Suction Piping: K =i f UD = 35.9fi /1.27 = 28.27 fi Pump B Suction Piping:
Piping Segment Dia. (in.) Length 1 15.25 3'-8*
2 15.25 1 '-3
- 3 15.25 7'-5%"
4 15.25 3'-6*
5 15.25 1 1 '-4
- Total 27'-2%* or 27.23 ft K value for"B" Pump Suction Piping: K = if UD = 27.23fi /1.27 = 21.44 fi Pump C Suction Piping Piping Segment Dia (in.) Length 1 15.25 3'-6*
2 15.25 1' - 0*
3 15.25 5'-8*
4 15.25 1 '-0*
5 15.25 14'-0*
Total 25'-2* or 25.17 ft K value for *C' Pump Suction Piping: K = if UD = 25.17f, /1.27 = 19.82 fi Pump D Suction Piping Piping Segment Dia (in.) Length 1 15.25 1 '-4*
- 2 15.25 0'-6*
l 3 15.25 1 '-6*
4 15.25 11'-7%*
l 5 15.25 2'-6*
6 15.25 6'-10" 7 15.25 3'-9*
Total 28'-0* or 28.0 ft l
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CALC. NO. : PM-1011
- PECO ENERGY CALCULATION SHEET PAGE: 9 NUCLEAR GROUP K value for"D" Pump Suction Piping: K = fi UD = 28.0 f,/1.27 = 22.05 f, Pipe Fitting Takeoff ( See Ref.10 pg A-27 to A-29, for K values)
Pump "A" Suction Piping Fitting Type K No. of Fittings Total K l 90' L.R. Elbow 14 f, 4 56 f, l Tee (flow thru run ) 20 f, 1 20 f, 60' L.R. Elbow 8.5 fi 2 17 f, l Gate Valve 8 f, 1 8 f, Total 101 f, Pump "B" Suction Piping Fitting Type K No. of Fittings Total K 90' L.R. Elbow 14 fi 5 70 f, Tee (flow thru run ) 20 f, 1 20 f, l 60* L.R. Elbow 8.5 f, 1 8.5 f, Gate Valve 8 f, 1 8 f, Total 106.5 f, Pump "C" Suction Piping Fitting Type K No. of Fittings Total K 90' L.R. Elbow 14 f, 5 70 f, Tee (flow thru run) 20 f, 1 20 f, 60* L.R. Elbow 8.5 f, 1 8.5 f, Gate Valve 8 f, 1 8 f, Total 106.5 f, Pump "D" Suction Piping
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Fitting Type K No. of Fittings Total K 90* L.R. Elbow 14 f, 4 56 f, Tee (flow thru run) 20 f, 1 20 f, 60* L.R. Elbow 8.5 f, 1 8.5 f, 45' L.R. Elbow 9.9 f, 1 9.9 f, Gate Valve 8 f, 1 8 f, Total 102.4 f, Total Piping Resistance K Value i
Pump Suction Piping K Fitting K Total K A 28.27 f, 101.0 f, 129.27 f, B 21.44 f, 106.5 f, 127.9 f, C 19.82 f, 106.5 f, 126.3 fi D 22.05 f, 102.4 f, ,124.45 f, i
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' CALC. NO. : PM-1019 PECO ENERGY CALCULATION SHEET PAGE: 90 NUCLEAR GROUP - - -
For a reference point, calculate the piping loss for a flow rate of 3125 gpm at a temperature of 205.7'F.
I For old Core Spray pipe assume c = 0.00085 (ref 10, pg. A-23, value for cast iron ) (c/D = 0.00067)
Calculating Reynold's Number Re = 50.6 Op / d ( Ref.10, pg. 3-2) p = 0.299 ( Ref.10, pg. A-2)
Therefore: for 205.7'F Re = 2.08 E + 06 From Ref.10, pg. A-24 l l
l for 205.7'F f, = 0.018 Finally:
Pump Temp ('F) K hr ( ft.)
A 205.7 2.33 1.09 B 205.7 2.3 1.07 C 205.7 2.27 1.06
, D 205.7 2.24 1.05 1
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'- 196-294$3 8/96 CALC. NO. . PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 11 NUCLEAR GROUP Calculatina h Given the Core Spray strainer configuration for Peach Bottom as shown below, it can be seen that in order to calculate the strainer head-loss, the percentage of the total strainer flow which passes through each module must be known.
4Re3 4Rs2 4Rai
, , 4Rua 4Ru2 4Rui Rp 3 2 1 R ,, R,, R. ,
CS Train Confiauration Rei + Rui + Rn + R i2 + Ri3 + Re = Rroin i
Ri l 2
R4 R3 R2 5 4 3 R7 R. R3 Ro i R. R.
R ii i
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CS Resistance Network i
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196-314h3 8/96
! CALC. NO. : PM-1011 i
l PECO ENERGY CALCULATION SHEET PAGE: 12 NUCLEAR GROUP Strainer Design Basis Debris Load ( 1633 ft* )
From Ref. 22, Appendix ell the percentage of total flow which passes through module 1, the flow rate, temperature and head-loss data is given as follows for a debris load of 1633 ft3 of NUKON.
l - Total Strainer Flow Temperature Module 1 Module 2 Module 3
! (gpm) (*F) % of Total Flow % of Total Flow % of Total Flow
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l 4030 205.7 31.75 31.85 36.59 l 3125 205.7 33.65 33.74 , _ j7.69 l
i Choosing 4030 gpm at 205.7'F as the reference value, an equation was developed to calculate the percentage of total flow as a function of flow and temperature.
t The function for calculating percentage of total flow is as follows:
I
%, = %i ,, x ( Q,/ Q i ,, )an2 x ( pi/pi,,) . a22
%2 = %2 ,, x ( O 2 / 2O r, )" x ( P2/ P2re)" '"
where:
% = Flow percentage at Q and T
%,, = Flow percentage at reference flow rate and temperature Q = New flow (gpm)
Ore = Reference flow (gpm) p= Kinematic viscosity at new temperature T p,,= Kinematic viscosity at reference temperature T,,
Calculating flow percentages for each module for the data given in Ref. 22 ( Appendix II) yields the following results:
Module Flow Temperature Ref. 22 Flow % Calculated Flow % Percent Difference 1 4030 213 31.690 31.690 0 4030 100 32.214 32.214 0 3125 213 32.028 32.028 0 3125 100 32.510 32.557 0.15%
! 2 4030 213 31.789 31.789 0 4030 100 32.282 32.282 0 l 3125 213 32.107 32.107 0 3125 100 32.569 32.605 0.11 %
! 3 4030 213 36.521 36.521 0 4030 100 35.504 35.504 0 3125 213 35.865 35.865 0
- 3125 100 34.921 34.867 -0.16%
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i 196-214B3 8/96 CALC. NO. . PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 13 NUCLEAR GROUP Maximum Expected Post LOCA Debris Load ( 700 ft* )
From Ref. 22, Appendix ill the percer,tage of total flow which passes through module 1, the flow rate, temperature and head-loss data is given as follows for a debris load of 700 ft3 of NUKON.
Total Strainer Flow Temperature Module 1 Module 2 Module 3 ;
(gpm) (*F) % of Total Flow % of Total Flow % of Total Flow '
3125 205.7 29.40 29.64 40.96 Choosing 3125 gpm at 205.7*F as the reference value, an equation was developed to calculate the l
percentage of total flow as a function of flow and temperature.
The function for calculating percentage of total flow is as follows:
%, = %i ,, x ( Qi / Qi r,)4mir2 x ( pi/pire) 22n
%2 = %2 ,, x ( Q/ O 2re )*"'#2 x ( p/92re) ' '
where:
% = Flow percentage at Q and T
%,, = Flow percentage at reference flow rate and temperature Q = New flow (gpm)
Q,,= Reference flow (gpm)
= Kinematic viscosity at new temperature T
,,= Kinematic viscosity at reference temperature T,,
Calculating flow percentages for each module for the data given in Ref. 22 ( Appendix II) yields the following results:
Module Flow Temperature Ref. 22 Flow % Calculated Flow % Percent Difference 1 3125 213 29.398 29.398 0 3125 100 29.983 29.983 0
- 2 3125 213 29.638 29.638 0 3125 100 30.181 30.181 0 3 3125 213 40.965 40.965 0 3125 100 39.836 39.836 0 l Given the flow percentage, the head loss for the strainer can be extrapolated from some reference value
Extrapolatina Strainer Head Loss:
The head loss across a fouled strainer is equal to the sum of the bed and form losses. The bed losses represent the viscous losses across the debris bed, and the form losses represent the friction losses through the strainer assembly.
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196-214$3 8/96 CALC. NO. : PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 14 NUCLEAR GROUP RWISION - 2 Strainer Design Basis Debris Load ( 1633 ft* )
Head loss for the replacement strainers is given in Ref. 22 ( Appendix lil, page lil-7) as:
Flow Rate Temperature Total Loss ( ft.)
4030 205.7 5.680 3125 l 205.7 4.335 Bed losses:
The bed losses vary as a function of the flow rate and the kinematic viscosity of water at the temperature of the torus water. The bed losses vary as a function of the flow rate and not the flow rate squared because the flow rate across the debris bed is sufficiently low as to be laminar.
The bed losses for the replacement strainers are given in Ref. 22 ( App.111, page lil-7) as follows:
Flow Rate (gpm) Temperature ('F) Bed Loss (ft.)
4030 205.7 4.215 3125 205.7 3.419 Choosing the bed losses at 4030 gpm and 205.7*F as a reference value, the following formula was developed to extrapolate the bed losses to other flows and temperatures:
h, = hn,,x ( %,x i Q / % x Q,)a sta7s x ( ,,/ p.,,,)" " '
where-.
hi = calculated bed loss h,,, = reference bed loss
%, = calculated % of total flow
%,,,= reference % of total flow Q i,= extrapolated total flow Q,,,= reference total flow poi = kinematic viscosity at extrapolated temperature p.,,, = kinematic viscosity at reference temperature i
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196-214$3 8/96 1
CALC. NO. : PM 1011 PECO ENERGY CALCULATION SHEET PAGE: 15 NUCLEAR GROUP REVISION : 2 Calculating the bed losses for the Ref. 22, Appendix Ill data yields the following results:
Total Flow (gpm) Temperature (*F) Bed Loss ( Ref.22) Bed Loss % difference (calculated) 4030 205.7 4.215 4.215 0 3125 205.7 3.419 3.452 1.0%
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Form Losses:
l The form losses vary as a function of the square of the velocity or flow. The form losses for the j replacement strainers are given in Ref. 22, Appendix ill. The form losses for the replacement strainers '
are as follows:
Flow Rate (gpm) Temperature ('F) Form Losses (ft) 4030 205.7 1.465 3125 205.7 0.916 The form losses consist of three components, the drag and turning losses through the strainer mesh, the intemal drag losses in strainer module 1 and the drag losses in the common tee discharge. '
Choosing the form losses at 4030 gpm and 205.7'F as the reference value, the form losses can be extrapolated to other flow and temperature conditions using the following express lon:
h, = h,n. n( %, x Qi / %ns, x One, )*
+ h,,,,n, ((Q, x (%, + % 2))l(Ongr x (Yonsp., + Yoney.2))f
+ h,,, (Q, / One, )
where:
h, = form losses at extrapolated flow and temperature conditions h,n ,n = reference drag and turning losses for module 1 mesh hei.,n , = reference internal strainer drag losses for module 1 h.,
i = reference drag losses for common tee
%, = % of total flow through module 1 at extrapolated flow and temperature conditions
%2= % of total flow through module 2 at extrapolated flow and temperature conditions
%rer.i = % of total flow through module 1 at reference conditions j %,,,.2 = % of total flow through module 2 at reference conditions
(
Q, = extrapolated total flow Q,,,= reference total flow Values for h,n ,n, h,i ,n, and h i , are found in Ref.22 Appendix Ill, page 111-14 as follows:
i M:\SEEM\FORMSTCALCSHT. DOC 6/i9/98 1:40 PM
996 ~114h3 8/96 CALC. NO. : PM.1011 PECO ENERGY CALCULATION SHEE PAGE: 16 NUCLEAR GROUP ON: 2 i h = 0.127 ft.
h , = 0.358 ft.
h, = 0.979 ft.
Calculating the form losses for the Ref. 22, Appendix Ill data yields the following results:
Flow (gpm) Temperature (*F) Form Losses Form Losses % Difference (Ref.22) (Calculated) 4030 205.7 1.465 1.465 0 3125 205.7 0.916 0.887 3.2%
Finally, the form and bed losses as calculated were compared to the Ref. 22, Appendix lil values as follows:
Flow (gpm) Temperature (*F) Strainer Loss (ft) Strainer Loss (ft) % Difference
( Ref.22) (Calculated) 4030 205.7 5.680 5.680 0 3125 205.7 4.335 4.339 0.1%
o l
M:\SEEM\FORMSTALCSHT. DOC 6/19/98 1:40 PM
, .. . .- - - . ~ . ~ - - . - .. - . ~ . . . ~ . -. .- .-
196-314S3 8/96 CALC. NO. : PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 97 REVISION : 2 NUCLEAR GROUP Maximum Expected Post LOCA Debris Load ( 700 ft')
Head loss for the replacement strainers is given in Ref. 22 ( Appendix 111, page 111-7, Licensing Case) as:
Flow Rate Temperature Total Head Loss ( ft.)
3125 205.7 1.694 Bed losses:
The bed losses vary as a function of the flow rate and the kinematic viscosity of water at the temperature of the torus water. The bed losses vary as a function of the flow rate and not the flow rate squared because the flow rate across the debris bed is sufficiently low as to be laminar.
The bed losses for the replacement strainers are given in Ref. 22 ( App.111, page ill-7, Licensing Case) as follows:
Flow Rate (gpm) Temperature (*F) Bed Loss (ft.)
3125 205.7 0.854 Choosing the bed losses at 3125 gpm and 205.7'F as a reference value, the following formula was developed to extrapolate the bed losses to other flows and temperatures:
hi = h,,,x ( %, x Q i / %,,, x Q ,)*" x ( p,i /p.,,,)" "
where:
hi = calculated bed loss h,,, = reference bed loss
%, = calculated % of total flow
%,,,= referance % of total flow
. Oi = extrapolated total flow Q,,,= reference total flow p.3 = kinematic viscosity at extrapolated temperature p.,,, = kinematic viscosity at reference temperature Calculating the bed losses for the Ref. 22, Appendix 111 data yields the following results:
l Total Flow (gpm) Temperature (*F) Bed Loss ( Ref.22) Bed Loss % difference (calculated)
- 3125 205.7 0.854 0.854 0 t
l
! M-\SEEMPORMSV:ALCSHT. DOC
. 6/19/98 1:40 PM
196 214b3 8/96 CALC. NO. : PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 18 NUCLEAR GROUP Form Losses:
The form losses vary as a function of the square of the velocity or flow. The form losses for the replacement strainers are given in Ref. 22, Appendix 111, Page ill-7, Licensing Case. The form losses for the replacement strainers are as follows:
Flow Rate (gpm) Temperature ('F) Form Losses (ft) 3125 205.7 0.840 The form losses consist of three components, the drag and turning losses through the strainer mesh, the internal drag losses in strainer module 1 and the drag losses in the common tee discharge.
Choosing the form losses at 3125 gpm and 205.7'F as the reference value, the form losses can be extrapolated to other flow and temperature conditions using the following expression:
h i = hm.e( %, x Q, / %ner x Ong, )
+ ho,m,((Q xi (% +i % ))l(Oner 2 x (Yonsp., + %aer.2)))*
+ h,,, (Q, / Ong, )
where:
h, = form losses at extrapolated flow and temperature conditions hm..n = reference drag and turning losses for module 1 mesh ha,m, = reference internal strainer drag losses for module 1 h,,, = reference drag losses for common tee
%, = % of total flow through module 1 at extrapolated flow ar9 temperature conditions
%2= % of total flow through module 2 at extrapolated flow and temperature conditions
%w.3 = % of total flow through module 1 at reference conditions
%,.2 = % of total flow through module 2 at reference conditions
%g= % of total flow thrcugh module 1 at reference conditions l O, = extrapolated total flow Q,= reference total flow Values for hm . ha,m, and h,,, are found in Ref.22 Appendix Ill, page 111-14 as follows:
hm.,n = 0.066 ft.
ha,m, = 0.1'85 ft.
h io,, = 0.588 ft.
l MasEEMPORMstALCSHT. DOC 6/19/98 1:40 PM
196-31453 0/96 CALC. NO. : PM-1011 PECO ENERGY CALCULATION SHEET PAGE: 19 NUCLEAR GROUP Calculating the form losses for the Ref. 22, Appendix ill data yields the following results:
Flow (gpm) Temperature (*F) Form Losses Form Losses % Difference (Ref.22) (Calculated) 3125 205.7 0.840 0.840 0 Finally, the form and bed losses as calculated were cornpared to the Ref. 22, Appendix ill values as follows:
Flow (gpm) Temperature (*F) Strainer Loss (ft) Strainer Loss (ft) % Difference
( Ref.22) (Calculated) 3125 205.7 1.694 1.694 0 NPSH Margin Combining the piping and strainer losses described above with the pressure and temperature vs. time data from Ref.17 and the level and flow rate vs. time data from Ref.1, EXCEL spreadsheets was prepared to calculate the NPSH. vs NPSHa,and the required overpressure as a function of time after the accident. The spreadsheet is included as Attachment 3. The results of this analysis are shown graphically below. From these graphs, it can be seen that the minimum NPSH margin occurs at the maximum pool temperature. The minimum NPSH margins for the two cases are as follows:
Minimum NPSH Margin ( at 205.7*F)
Case Torus Debris Load NPSHR NPSHA Margin (ft') (ft) (ft) (ft)
Strainer Design Basis 1633 26 30.01 4.01 DBA LOCA Design Basis 700 26 32.65 6.65 l
2 3
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M:\SEEM\FORMSTCALCSHT. DOC 6/19/98 1:40 PM
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- 14383 20.92 198 11.0580 3.424E-06 0.016624 13.65 3125 16448 21.22 200 11.5260 3 385E-06 0.016637 13.65 3125 _
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'4290 0.32182 0.32256 0.888 3.887 4.776 1.080 34.02 M 5571 0.32166 0.32241 0.888 3.810 4.698 1.081 33.62 I.
6475 0.32158 0.32234 0.888 0.888 3.773 3.700 4.661 4.588 1 082 1.084 33.50 33.01 C 8592 0.32143 0.32220 11143 0.32128 0.32206 0.888 3.630 4.518 1.085 32.41 12505 0.32121 0.32199 0.887 3.597 4.4 84 1.086 32.04 14383 0.32113 0.32192 0.887 3.563 4.451 1.087 31.72 16448 0.32106 0.32185 0 887 3.531 4.418 1.088 31.37 d i 0887 3.499 4.386 1.089 31.00 19302 23787 0.32099 0.32092 0.32178 0.32172 0.887 3.468 4.355 1.090 30.59 O - 31667 0.32085 0.32165 0.887 3.437 4.324 1.090 30.01 Z - 45533 0.32092 0.32172 0.887 3.468 4.355 1.090 30.59 Maxima 36.96 b . Mfnima 30.01 f ITI i iT1
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196 314h3 8/96 CALC. NO. : PM-1011 PA E: 30
- PECO ENERGY CALCULATION SHEET ,,,
, NUCLEAR GROUP B. LOCA While Purging with a concurrent drop in torus water level As previously stated in Part A of this calculation, the available NPSH for the NPSH pumps is expressed by the following equation: NPSHA = Peont + Z -he - P., where Pm = Torus pressure Z = Static Head (Torus water level) l hr = suction line friction losses ( including suction strainer losses) P., = vapor pressure of the pumped fluid From the results in Part A, it can be seen that the NPSH margin at the limiting torus temperature l and pressure conditions is 6.65 ft. l From Ref.17,it can be seen that a LOCA occuning while purging reduces the available j containment pressure at the limiting torus temperature to 21.21 psla. This reduction in torus l pressure (0.890 psi or 2.057 ft) will still provide an NPSH margin of 4.59 ft. Therefore, even with maximum expected accident fouling, the suction strainers can accommodate a DBA LOCA while purging. l l l MAsEEMiFORMsCALCSHT. DOC 6/19/98 2:08 PM
196-21453 8/96 CALC. NO. : PM-1011 PECO ENERGY CALCULATION SHEE PAGE 31 NUCLEAR GROUP C. NPSH LIMIT CURVES AND ECCS SUCTION REQUIREMENTS CURVES FOR THE MOST LIMITING CONDITIONS FOR CORE SPRAY PUMPS The purpose of this section is to determine: 1) the torus temperature limit at which the NPSH requirements will be satisfied for a variety of flow, torus level and pressure conditions. 2) the torus water level at which the NPSH requirements will be satisfied for a variety of flow, torus temperature and pressure conditions. These limits are determined by setting NPSHA equal to NPSHR and solving for the required variable. This equation takes the form: NPSHA = NPSHR = P. + h. - h,- hv., To solve for torus temperature, the values of NPSHR and hewhich correspond to various Core Spray system flows are input into the equation along with varying torus levels and pressures. The equation is then solved for vapor pressure, which is converted to saturation temperature by reference to the steam tables. Similarly, when solving for torus level, torus temperature conditions are converted into vapor pressure and combined with the torus pressure and flow dependent variables, and the equation solved directly for static head, which corresponds to torus level, since the Core Spray pump suction elevation corresr with torus level zero. Torus Temperature Limits The torus temperature limits were calculated for the following conditions:
. Core Spray system flows of 2250,2500,2750,3000,3250,3500,3750,4000 gpm
. Torus water Levels of 10.5',12.3',14.5' and 20'
. Torus overpressures of 0,3,6,10,20,30 and 60 psig A clean suction strainer was assumed in formulating these curves, since these curves will be used to respond to many transients, such as ATWS and Appendix R fires which will not transport insulation debris to the torus.
Suction line friction losses, including strainer losses were calculated using the EXCEL spreadsheet in section A above. These losses were computed as a function of flow only. All losses were calculated at 3125 gpm at 205.7'F. These losses were then corrected for other flows by applying the following formula: hfi = hfr.,( Qi / Q,,, ) hfi = friction losses at new flow hf,,, = friction losses at reference flow ( 3125 gpm) Qi = new flow Q,,,= reference flow ( 3125 gpm) These friction losses are combined in an EXCEL spreadsheet with the flow level and torus pressure conditions given above to calculate the torus temperature limits, using the following equation: hv., = 144 P. / p + h. - h,- NPSHR MASEEM\ FORMS \CALCSHT. DOC 6/10/98 2:14 PM
196 31553 8/96 CALC. NO. : PM 1019 PECO ENERGY CALCULATION SHEET PAGE: 32 REVISION : 2 NUCLEAR GROUP Once hy ,is found, the results are converted into temperature by referring to at ASME Steam Tables (Ref. 3 11) The results are shown in the following spreadsheet. l
)
i l
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M:\SEEMPORMS\CALCSHT. DOC 6/19/98 1:40 PM
196-21453 8/96 CALC. NO. : PM-1011
- PECO ENERGY CALCULATION SHEET PAGE
,,O C' NUCLEAR GROUP Torus Level Limits The torus temperature limits were calculated for the following conditions:
- Core Spray system flows of 2250,2500,2750,3000,3250,3500,3750,4000 gpm
. Torus water temperature of 95* to 300*
- Torus overpressures of 0,3,6,10,20,30 and 60 psig A clean suction strainer was assumed in formulating these curves, since these curves will be used to respond to many transients, such as ATWS and Appendix R fires which will not transport insulation debris to the torus.
Suction line friction losses, including strainer losses were calculated using the EXCEL spreadsheet in section A above. These losses were computed as a function of flow only. All losses were calculated at 3125 gpm at 205.7'F. These losses were then corrected for other flows by applying the following formula: hf i = hfr.,( Qi / Om, )2 hf i = friction losses at new flow hfr., = friction losses at reference flow ( 3125 gpm) Oi = new flow Or., = reference flow ( 3125 gpm) These friction losses are cornbined in an EXCEL spreadsheet with the flow level and torus pressure conditions given above to calculate the torus temperature limits, using the following equation:
- h. = NPSHR + h, + hv.,- 144 P / p The results are shown in the following spreadsheet .
l l l MASEEM'EORMS\CALCSHT. DOC 6/19/98 2:15 PM
19641453 8/96 CALC. NO. : PM-1019 PECO ENERGY CALCULATION SHEET PAGE: 33 NUCLEAR GROUP Torus Level Limits The torus temperature limits were calculated for the following conditions:
. Core Spray system flows of 2350,2800,3125,3500,4030,4200 gpm
. Torus water temperature of 95* to 300*
- Torus overpressures of 0,3,6,10,20,30 and 60 psig A clean suction strainer was assumed in formulating these curves, since these curves will be used to respond to many transients, such as ATWS and Appendix R fires which will not transport insulation debris to the torus.
Suction line friction losses, including strainer losses were calculated using the EXCEL spreadsheet in section A above. These losses were computed as a function of flow only. Alllosses were calculated at 3125 gpm at 205.7*F. These losses were then corrected for other flows by applying the following formula: hfi = hf,,,( Q i / Q,, )2 hf i = friction losses at new flow hf,,, = friction losses at reference flow ( 3125 gpm) Oi = new flow Q,,,= reference flow ( 3125 gpm) These friction losses are combined in an EXCEL spreadsheet with the flow level and torus pressure conditions given above to calculate the torus temperature limits, using the following equation: 1 h, = NPSHR + h, + hy , - 144 P, / p The results are shown in the following spreadsheet . l 6 o M.\SEEM\ FORMS \CALCSHT. DOC 6/19/98 1:40 PM
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m kO Table C-1 Core Spray Pumps with Clean Stramer C,.L. A of Torus Temp vs flow Calculate the Hf at vanous Rows O (GPM) Q^2 rabo Hf ne" 2250 0518 0 985 5O g S g-- Conversson of fnction loss (Hf) for for new stramers 2500 0 640 1.216 :n S W y Clean stramers have .51 ft @100 F & pipmg is 1.09 ft loss. (For 3125 gpm) 2750 0.774 1 471 @Z g Using the equation hvap = hs - NPSHR - hr + PA 3000 0 922 1.751 10 $ Q Friction loss is converted based on the ratio of the flows squared. 3250 1 062 2 055 1 g thus the Hf at 3125= 1.9 feet H2O is coverted fbr various flows 3500 1254 2.383 g a Note: this value is not temperature corrected. This is conservative because 3750 1.440 2 736 strainer head loss values are at 100 F. 4000 1.638 3 113 4 0 Vortex Lermt Orawdown Level Mm Tech Spec Level Q Torus 10 5 Ft Torus Level 12.3 Ft Torus Level 14 5 Ft Torus Level 20 Ft Torus Level Wetwell Pressure PA FLOW NPSHR hf Vapor Pressure TEMP Vapor Pressure TEMP Vapor Pressure TEMP Vapor Pressure TEMP PSIG FT (ABS) GPM FT FT FT PStA dag F FT PSIA deg F FT PSIA deg F FT PStA deo F 0 33 9717 2250 26 0.98 17.4867 7.5667 180 00 19 2867 8.3456 184 00 21 4867 9 2976 189 00 26 9867 11.6775 200 00 33 9717 2500 26 122 17.2557 7 4668 179 00 19 0557 8 2457 184 00 21 2557 9 1976 189 00 26 7557 11 5775 200.00 33 9717 2750 26 1.47 17.0003 7.3563 179 00 18.8003 81352 183 00 21.0003 9 0871 188 00 26.5003 11 4670 199 00 f 33 9717 3000 26.5 1.75 16.2207 7.0189 176.00 18 0207 7.7978 181.00 20.2207 8 7497 186.00 25.7207 11.1297 198.00 33 9717 3250 27 2.06 15 4167 6 6710 174 00 17.2167 7.4499 179 00 19 4167 8 4018 185.00 24 9167 10.78 a 8 196 00 33.9717 33 9717 3500 3750 28 2S 2.38 2.74 14 0883 12 7357 6 0962 55109 170 00 166 00 15.8883 14.5357 6.8751 62898 176 00 18 0883 17200 16 7357 7.8271 72418 181 00 178.00 23 5883 22.2357 102070 9 6217 194 00 191.00 { 33 9717 4000 30 3.11 11.3587 4 9151 161.00 13 1587 5 6940 167 00 15 3587 6 6459 174 00 20 8587 9 0259 188 00 3 40 9047 2250 26 0 98 24.4197 10 5667 195.00 262197 11.3456 199 00 28 4197 122976 203 00 33 9197 14 6775 211.00 40 9047 2500 26 122 24.1887 10 4G68 195.00 25 9887 11.2457 196 00 28 1887 12.1976 202.00 33 6887 14 5775 211.00 40.9047 2750 26 1 47 23 9333 10 3563 194 00 25.7333 11.1352 198 00 27 9333 12.0871 202.00 33 4333 14 4670 211.00 - 40 9047 3000 26 5 1.75 23 1537 10 0189 193.00 24.9537 10 7978 196 00 27.1537 11.7497 200 00 32 6537 14.1297 210 00 40 9047 3250 27 2 06 22.3497 9 6710 191 00 24.1497 10 4499 195 00 26 3497 11 4018 199 00 31 8497 13 7818 208 00 40 9047 40 9047 3500 3750 28 29 2.38 2 74 21.0213 19 6687 90962 8.5109 188 00 185 00 22.8213 21 4687 9 8751 9 2898 192 00 25 0213 189 00 23 6687 10 8271 10.2418 196 00 194 00 30.5213 29 1687 132070 12 6217 206 00 204 00 [ 6 40 9047 47E377 4000 2250 30 26 3 11 0.98 18 2917 31.3527 7 9151 13.5667 182 00 207.00 20 0917 33 1527 8 6940 14.3456 186.00 22 2917 210 00 35.3527 9 6459 152976 191.00 214.00 27.7917 40.8527 12 0259 17.6775 202.00 221.00 47.8377 2500 26 122 31.1217 13 4668 207.00 32.9217 14.2457 210 00 35 1217 151976 213.00 40 6217 17.5775 221.00 47.8377 47.8377 2750 3000 26.5 26 1 47 1.75 30 8663 30.0867 13.3563 13 0169 207.00 205 00 32.6663 31.8867 14.1352 13.7978 210 00 208 00 34 8663 34 0867 15 0871 14 7497 213 00 212.00 40.3663 39.5867 17.4670 17.1297 220 00 219 00 47.8377 3250 27 2.06 29 2827 12 6710 204.00 31.0827 13.4499 20700 33 2827 14 4018 210 00 38.7'L27 16 7818 218 00 47.8377 3500 28 2.38 27.9543 12.0962 202.00 29 7543 12.8751 205 00 31.9543 13 8271 208 00 37.4543 16.2070 216 00 47 8377 3750 29 2.74 26 6017 11.5109 199 00 28 4017 12 2898 203 00 30.6017 13.2418 206 00 36 1017 15 6217 215 00 47.8377 4000 30 3 11 25.2247 10 9151 197 00 27.0247 11 6940 200.00 29 2247 12 6459 204 00 34 7247 15 0259 213 00 to 57.07 2250 26 0.98 40.5850 17.5617 221.00 42.3850 18 3406 223 00 44 5850 192925 226 00 50 0850 21.6725 232.00 57.07 2500 26 1.22 40 3540 17.4617 220.00 42.1540 18.2406 223 00 44.3540 19 1926 225 00 49 8540 21.5725 232 00 y ~0 0 57.07 2750 26 1.47 40 0986 17.3512 220 00 41.8986 18 1301 222.00 44.0986 19 0821 225.00 49 5986 21 4620 231 00 39 3190 17.0138 219 00 41.1190 17.7927 221 00 43.3190 18 7447 224 00 48 8190 21.1246 230 00 { % 57.07 3000 26 5 1.75 - O
- 57.07 3250 27 2.06 38 5150 16 6659 218 00 43 3150 17.4448 220 00 42 5150 18 3968 223.00 48 0150 20 7767 229 00 $ .m ~
57.07 3500 28 2.38 37.1866 16 0911 216 00 38 9866 16 8700 219 00 41.1866 17.8220 221 00 46 6866 20 2019 228 00 57.07 3750 29 2 74 35 8340 15.5058 214 00 37 6340 162847 217 00 39 8340 17.2367 220 00 45.3340 19 6166 226 00 " 57.07 4000 30 3 11 34 4570 14 9100 212.00 36 2570 15 6889 215 00 38 4570 16 6409 218 OC 43 9570 19 0208 225 00 y 5 S h5 3c N O m E
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Clean strainers have .31 ft @100 F & piping is 1.09 ft loss. (For 3125 gpm) (Jsin0 the equation hvap = hs - NPSHR - hr + PA 2750 0.774 1 471 C "b h 3000 0 922 1 751 b Friction loss is converted based on the ratio of the flows squared 3250 1 082 2 055 2
-4 thus the Hf at 3125= 1.9 feet H2O is coverted for vanous flows Note: thes value is not temperature corrected. This is conservative because 3500 1.254 2 383 O 0 strainer head loss values are at 100 F.
3750 1 440 2.736 4 4000 1 638 3.113 8 Vortex Lamit Orawdown Levet Man Tech Spec Level Torus 10 5 Ft Torus Level 12.3 Ft Torus Level 14 5 Ft Torus Level 20 Ft Torus Level Wetwed Pressure PA FLOW NPSHR hf Vapor Pressure TEMP Vapor Pressure TEMP vapor Pressure TEMP Vapor Pressure TEMP PSIG FT (ABS) GPM FT FT FT PSM deg F FT PSIA deg F FT PStA deg F FT PSIA deg F h 20 80 18 80.18 2250 2500 26 26 0 98 1 22 63 6950 63 4640 27 5617 27.4617 245 00 245.00 65 4950 65.2640 28 3406 28 2406 247 00 246 00 67 6950 67.4640 29 2925 29 1926 248 00 248.00 73 1950 72.9640 31 6725 31 5725 253 00 253 00 p 80 18 2750 26 1 47 63 2086 27.3512 245 00 65 0086 28 1301 246 00 67 2086 29 0821 248 00 72.7086 31 4620 253 00 80.18 80.18 3000 3250 26 5 27 1.75 2 06 62 4290 61 6250 27.0138 26 6659 244 00 243 00 64.2290 63 4250 27.7927 27.4448 245 00 245 00 66.4290 65 6250 28.7d47 28 3968 247 00 247 00 71.9290 71.1250 31.1246 30 7767 252 00 251 00 h 80.18 3500 28 2.38 60 2966 26 0911 242 00 62.0966 26 8700 244 00 64.2966 27.8220 246 00 69 7966 30 2019 250 00 80 18 3750 29 80.18 4000 30 2.74 3 11 58 9440 57.5670 25 5058 24 9100 241 00 239 00 60.7440 59 3670 26 2847 25 6889 242 00 241 00 62.9440 61 5670 27.2367 26 6409 244 00 243 00 68 4440 67 0670 29 6166 29 0208 249 00 248 00 ["" 30 10329 2250 26 0 98 86 8050 37.5617 263 00 88 6050 38.3406 264 00 90 8050 39 2925 266 00 96 3050 41 6725 269 00 103 29 2500 26 1.22 86 5740 37.4617 263 00 88 3740 38 2406 264 00 90 5740 39 1926 265 00 96 0740 41 5725 269 00 103 29 2750 26 1 47 86.3186 37.3512 263 00 88.1186 38 1301 264 00 90 3186 39 0821 265 00 95 8186 41 4620 269 00 103 29 3000 26 5 1.75 85 5390 37 0138 262 00 87.3390 37.7927 263 00 89 5390 38 7447 265 00 95 0390 41.1246 268 00 103 29 3250 27 2 06 84.7350 36 6659 262 00 86 5350 37 4448 263 00 88.7350 38.3968 264 00 94.2350 40 7767 268 00 103 29 3500 28 2.38 83 4066 36 0911 261 00 85 2066 36 8700 262 00 87.4066 37.8220 263.00 92 9066 40 2019 267 00 103.29 3750 29 2.74 82.0540 35 5058 260 00 83 8540 36 2847 261 00 86 0540 37.2367 262 00 91 5540 39 6166 266 00 103 93 4000 30 3 11 81 3170 3i 1869 259 00 83 1170 35 9658 260 00 85.3170 36 9178 262.00 90 8170 39 2977 266 00 m W 60 172 59 2250 26 172 59 2500 26 0 96 1.22 156.1050 155 8740 67.5487 67.4487 300 00 300 00 157.9050 157 6740 68.3276 68 2276 301.00 301 00 160.1050 159 8740 69 2795 69 1796 302 00 302 00 165 6050 165 3740 71 6595 71.5595 304 00 304 00 [ 172 59 2750 26 1.47 155 6186 67.3382 300 00 157 4186 68 1171 301 00 159 6186 69 0691 302 00 155.1186 71 4490 304 00 172 59 172.59 300C 3250 26 5 27 1.75 2.06 154 8390 154 0350 67.0008 66 6529 299 00 299 00 156 6390 155 8350 67.7797 67 4318 300 00 300 00 158 8390 158 0350 63 7317 68.3838 301.00 301.00 164 3390 163 5350 71.1116 70.7637 303 00 303 00 172.59 3500 28 2.38 152 7066 66 0782 299 00 154.5066 66 8570 299 00 156.7066 67.8090 300 00 162.2066 70 1889 303 00 172.59 3750 29 2 74 151 3540 65 4929 298 00 153.1540 66.2717 299 00 155 3540 67.2237 300 00 160.6540 69 6036 302.00 172 59 4000 30 3.11 149 9770 64 8970 297 00 151.7770 65 6759 298 00 153 9770 66 6279 299 00 159 4770 69 0078 301 00 23 T O m
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K z-G m C O @g - m Table C-2 Core Spray Pumps with Oean Stramers Detemwiation d ht for fkms ratur2 go p' h o Determne torus levet as a funden d flow fkw 2250 0$184 0985 h' O S-A "U unng the equation hs a NPSHR + tt - PA + hvnp 2$00 0 64 1 216 OITl C I h where hat a state head Onech a torus bewef) 2760 0 7744 1 471 OZ cs 6 tv at 3125 com & 100F Note this value is rut temperature corrected 19 a H2O 3000 3260 0 9216 1 0816 1 751 2 0$$ hg h b This a consaderec to De conservatse because the straner 3500 12$44 2 383 M values are based on 100 F 3750 1 44 2 736 h h 4000 1 6384 3 113 4 0 h 36 126 150 165 180 Torus Temperature (deg F) 190 2uO 220 24u 260 200 30U 110{ wetwen Pressure PA twap 18W1900 2 966; 4 538 e751 12 619 17 657 22 288 2/ 613 41 516 60 e55 87 178 122 313 168 400 (ps*9) (pasa) Flow (gpm) NPSr1R (11) fit (ft) hs (ft) (equates to torus levet) 0 14 7 22$0 26 0 98$ -5233 -4 266 -2 822 1 142 4 840 9 834 14 193 19 381 32 991 $2 011 77 969 112 753 1$8 440 0 14 7 2$00 26 1 216 -5 002 -4 035 -2 591 1 373 $072 10 125 14 424 19 612 33 222 $2 242 18 220 112 984 1$8 671 0 14 7 2750 26 1 471 -4 746 -3 779 2 336 1 628 5327 10 380 14 680 19 867 33 477 52 498 78 475 113 239 1$8 926 0 14 7 3000 26 5 1 751 -3 S67 -3 000 -1 $56 2 408 6 107 11 160 15 459 20 647 34 257 53 277 79 2$$ 114 019 159 706 0 14 7 3260 27 2 O$$ -3 163 -2 196 -0762 3 212 6 911 11 964 18 263 21 451 35 061 $4 081 80 059 114 823 160 S10 0 14 7 3500 28 2 383 -1834 -0867 0 $76 4 $40 8239 13 292 17$92 22 779 36 389 SS 410 81 387 1161$1 161 838 0 14 7 37$0 29 2 736 -0482 0 485 1 929 $893 9592 14 645 18 944 24 132 37 742 $6 762 82 740 117 504 163 191 0 14 7 4000 30 3 113 0 896 1 862 3 306 7 270 to 968 16 022 20 321 25 509 39 119 68 139 84 117 118 881 164 668 3 3 17 7 177 22$0 2500 26 26 0 966 1 216
-12 194 11 963
-11 249
-11 018
-9 831
-9 600
-6918
-5687
-2 2$4
-2 023 2 761 2 992 7 034 7 265 12194 12 42$
23 744 25 975 44 699 44 930 70 606 70 837 105 29$ 105 626 160 900 151 131 f 3 17 7 2750 23 1 471 -11 708 -10 763 -9 34$ -5432 -1 768 3 248 7 S21 12 680 26 230 45 166 71 093 105 781 1$1387 3 177 3000 26 5 1 751 -10 928 -9 983 -8 $65 -4 6$2 -0988 4 027 8 300 13 460 27 010 45 965 71 873 106 661 152 166 3 17 7 32$0 27 2 05$ -to 124 -9179 -7 761 -3 848 -O184 4 831 9 104 14 264 27 814 46769 72 677 107 365 152 970 - 3 17 7 3$00 28 2 383 -8 796 -7 8$1 -6 433 -2 520 1 144 6 160 10 433 15 592 29 142 48 098 74 00$ 108 693 154 299 3 177 3750 29 2 736 -7 443 -6 498 -5080 -1 1 $ 7 2 497 7$12 11 785 16 945 30 495 49 460 75 357 110 G46 155 651 3 10 17 7 24 7 4000 22$0 30 26 3 113 0 98$
-6 066 'S 121
-27 $44
-3 703 0210
-22 392 3 874
-13 881 8 889 13162 18 322
-4 $76 31 872 8 834 50 827 27 638 76 734 33 381 111 423 87 892 157 028 133 308
[ 10 24 7 2$00 26 1 216 -27 313 -22 161 -13 6$0 -4 345 9 065 27 869 $3 612 88 123 133 539 10 24 7 2730 26 1 471 -27 057 -2190$ -13 394 -4 090 9 320 28124 53 867 88 379 133 794 10 24 7 3000 26 5 1 751 -26 278 -21 126 -12 615 -3 310 10 100 28 904 54 647 89 158 134 $74 10 24 7 3260 27 2 0$$ -25 474 -20 322 -11 811 -2 $06 10 904 29 708 55 451 69 962 135 378 10 24 7 3500 28 2 383 -2414$ -18 993 -10 482 -1 178 12 232 31 036 $6 779 91 291 136 706 10 24 7 37$0 29 2 736 -22 793 -17 641 -9 130 0 176 13 586 32 389 $8132 92 643 138 059 10 24 7 4000 30 3 113 -21 4*6 -16 264 -7 753 1 $52 14 962 33 766 $9 $09 94 020 139 436 20 34 7 2260 26 0 96$ -$0822 -45 926 -37 666 -2th $33 -1$ 323 3 264 28 773 63 032 108 1/5 20 34 7 2$00 26 1 216 -60 $90 -45 694 -37 424 -28 302 -1$ 092 3 495 29 004 63 263 108 406 20 34 7 27$0 26 1 471 -50 335 -45 439 -37169 -28 047 -14 836 3 751 29 259 63 $18 108 662 20 34 7 3000 26 5 1 751 -49 $$$ -44 659 -36 389 -27 267 -14 057 4 530 30 039 64 298 109 441 20 34 7 32$0 27 2 OSS -48 751 -43 855 -35 $85 -26 463 -13 2$3 5334 30 843 66 102 110 24$ 7 y g 20 34 7 3500 28 2 383 -47423 -42 527 -34 25/ -2$ 13$ -11 924 6 663 32 171 66 430 til $74 m > 20 34 7 37$0 29 2 736 -46 070 -41 174 -32 904 -23 782 -10 $72s 8 01$ 33 $24 67 783 112 926 ( O 20 34 7 4000 30 3 113 -44 694 -39 797 -31 527 -22 40$ -9195l 9 392 34 901 69 160 114 3G3 5 (T1 O 6"z o z u M A b o o Q a N
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f- uomo the ==y % hs a NPSHR + hf - PA + hvep 2500 0 84 1.216 2N W J where het is ele 8c head (whit 21 is torus level) hr of 3125 gpm & 100F= 1.9 ft H2O 2750 3000 0 7744 0 9216 1471 1 751 h2 V$ cm Qr - Note: this value le not temperature correcenci 3250 1 0818 2 055 y Thss is conewlered to be conservatrwe h = the airesner 3500 1 2544 2 383 m b vehJos are bened on 100 F. 3750 1 44 2 738 ue 4000 16384 3.113 d Torus Temperature (deo F) 95 110 125 150 185 180 190 200 220 240 280 280 300 Weemos Pressure PA hvep 1 861908 2.988 4 538 8.751 12 619 17A57 22.288 27813 41 516 80 865 87.178 122.313 188400 (pene) (pass) Flour (gpm) NPSPR (ft) hi (ft) hs i fu (at- to torus lever) [ 3-0 30 44 7 44 7 2250 2500 26 26 0 985 1.216
-74 099
-73 888
-8G 458
-89.227 41430 4 1.199
-62 490
-62 259
-39 479
-39248
-21 109
-20 878 4 185 4 398 38 171 38 402 83 643 83 274 h
30 44 7 2750 26 1 471 -73 613 48 972 40 fs43 42004 -38 993 -20 823 4 851 38 857 83 529 30 30 44 7 44 7 3000 3250 28 5 27 1 751 2 055
-72 833
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-69 360
-51 224
-60 420
-38 213
-37409
-19 843
-19 039 5 431 6 236 39437 40 241 84 309 85 113 f
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