ML20211N612
| ML20211N612 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/30/1986 |
| From: | Charnley J, Casey Smith, Zarbis W GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20211N531 | List: |
| References | |
| 23A4735, 23A4735-R, 23A4735-R00, NUDOCS 8612180264 | |
| Download: ML20211N612 (20) | |
Text
{{#Wiki_filter:r-m _g 23A4735 CLASSI _- JUNE 1986 1 e
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I s 4 SUPPLEMENTAL RELOAD j LICENSING SUBMITTAL FOR 3 LA SALLE COUNTY STATION ]
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l - 23A4735 Revision 0 Class I June 1986 l T i SUPPLEMENTAL RELOAD LICENSING SUBMITTAL FOR LA SALLE COUNTY STATION UNIT 2, RELOAD 1 (CYCLE 2) Prepared: - 46 C. W. Smith Verified: W. A is Approved: J. S C ruley, Manager Fuel ensing , J NUCLEAR ENERGY BUSINESS OPERATIONS
- GENERAL ELEC1RIC COMPANY SAN JOSE. CAllFORNIA 95125 GENER AL $ ELECTRIC ,
1/2 I
23A4735 Rev. O IMPORTAFT NOTICE REGARDING CONTENTS OF THIS REPORT l PLEASE REAL CAREFULLY 1 This report was prepared by General Electric solely for Commonwealth Edison Company (CECO) for CECO's use with the United States Nuclear Regulatory Commission (USNRC) for amending CECO's operating license of the La Salle t County Station, Unit 2. The information contained in this report is believed by General Electric to be an accurate and true representation of the facts known, obtained or provided to General Electric at the time this report was - prepared.
~
The only undertakings of the General Electric Company respecting informa-tion in this document are contained in the contract between Commonwealth Edison Company and General Electric Company for Nuclear fuel and related ser-vices for the nuclear system for La Salle 2 and nothing contained in this doc-ument shall be construed as changing said contract. The use of this informa-tion except as defined by said contract, or for any purpose other than that - for which it is intended, is not authorized; and with respect to any such . unauthorized use, neither General Electric Company nor any of the contributors to this document makes any representation or warranty (express or implied) as to the completenest;, accuracy or usefulness of the information contained in j this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information. 3/4
23A4735 Rav. 0
- 1. PLANT UNIQUE ITEMS (1.0)*
l Transient Analysis Basis: Appendix A Plant Parameters: Appendix B
- 2. RELOAD FUEL BUNDLES (1.0, 2.0, 3.3.1 AND 4.0)
Fuel Type Cycle Loaded Number Number Drilled Irradiated 8CRB176** 1 108 108 8CRB219** 1 432 432 New: BP8CRB299L*** 2 224 224 Total 764 764
- 3. REFERENCE CORE LOADING PATTERN (3.3.1) i Nominal previous cycle core average exposure at end of cycle: 10,216 mwd /ST Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations: 10,016 mwd /ST Assumed reload cycle core average exposure at end of cycle: 14,506 mwd /ST Core loading pattern: Figure 1
*( ) Refers to area of discussion in " General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-7 (dated August 1985). A letter "S" i preceding the number refers to the appropriate country-specific supplement.
** Included in " Final Safety Analysis Report for LaSalle County Station," dated January 1981.
*** Included in Amendment 13 to GESTAR II. See Letter, J.S. Charnley (GE) to C.O. Thomas (NRC), " Proposed Administrative Amendment to GE Licensing Topical Report NEDE-24011-P-A", September 24, 1985.
5 l -- - _ _ _ _ _ _ _ .
l e 23A4735 Rsv. O i
- 4. CALCUIATED CORE EFFECTIVE MULTIPLICATION AND CONTROL SYSTEM WORTH - NO '
VOIDS, 20*C (3.3.2.1.1 AND 3.3.2.1.2) Beginning of Cycle, k,ff Uncontrolled 1.120 Fully Controlled 0.950 Strongest Control Rod Out 0.980 R, Maximum Increase in Cold Core Reactivity 0.006 with Exposure into Cycle, Ak f
- 5. l STANDBY LIQUID CONTROL SYSTEM SHUTDOWN CAPABILITY (3.3.2.1.3)
Shutdown Margin (Ak) g (20*C, Xenon Free) 660 0.039
- 6. RELOAD-UNIQUE TRANSIENT ANALYSIS INPUT (3.3.2.1.5 AND S.2.2)
Values normally reported for this section are REDY inputs. There were no transients analyzed using REDY.
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i t 6
L 23A4735 Rev. 0
- 7. RELOAD UNIQUE GETAB TRANSIENT ANALYSIS INITIAL CONDITION PARAMETERS (S.2.2)
Exposure: B0C 2 to EOC 2 Fuel Peaking Factors Bundle Power Bundle Flow Initial Design Local Radial Azial R-Factor (MWt) (1000 lb/hr) MCPR BP8x8R 1.20 1.48 1.40 1.051 6.322 115.9 1.28 8x8R 1.20 1.50 1.40 1.051 6.414 115.3 1.26 I
- 8. SELECTED MARGIN IMPROVEMENT OPTIONS (S.2.2.2)
Transient Recategorization: No Recirculation Pump Trip: Yes Rod Withdrawal Limiter: No Thermal Power Monitor: Yes Improved Scram Time: No Exposure Dependent Limits: No Exposure Points Analyzed: 1
- 9. OPERATING FLEXIBILITY OPTIONS (S.2.2.3)
Single-Loop Operation: Yes Load Line Limit: No Extended Load Line Limit No Increased Core Flow: No Flow Point Analyzed N/A Feedwater Temperature Reduction: No 7
\ _ _ _ _ _ _ _ _ _ _ _ ._
e 23A4735 Rev. 0
- 10. CORE-WIDE TRANSIENT ANALYSIS RESULTS (S.2.2.1) l Exposure BOC 2 to EOC 2 ACPR Flux Q/A Transient (% NBR) (% NBR) BP8x8R 8x8R Figure Load Rejection Without Bypass 450 121 0.21 0.19 2 Loss of Feedwater Heater 125 125 0.10 0.10
- Feedwater Controller Failure 290 119 0.16 0.14 3
- 11. LOCAL ROD WITHDRAWAL ERROR (WITH LIMITING INSTRUMENT FAILURE) TRANSIENT
SUMMARY
(S.2.2.1) i Limiting Rod Pattern: Figure 5 Includes 2.2% Power Spiking Penalty: No ACPR LHGR (kW/ft) Rod Block Rod Position Reading (feet withdrawn) BP8x8R 8x8R 8x8R/BP8x8R 104 3.5 0.11 0.11 16.01 105 4.0 0.13 0.13 16.39 ! 106 4.5 0.15 0.15 16.46 107 5.0 0.18 0.18 16.46 108 5.5 0.19 0.19 16.46 109 6.0 0.23 0.23 16.46 110 7.5 0.26 0.26 16.46 ; Setpoint Selected: 107
*See Appendix A
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8
23A4735 Rev. 0
- 12. CYCLE MCPR VALUES (S.2.2)
Non-Pressurized Events Exposure Ranger BOC 2 to EOC 2 BP8x8R 8x8R Loss of Feedwater Heater 1.17 1.17 Fuel Loading Error Rod Withdrawal Error 1.25 1.25 Pressure Events Exposure Range: BOC 2 to E0C 2 Option A Option B BP8x8R 8x8R BP8x8R 8x8R Load Rejection Without Bypass 1.34 1.31 1.24 1.22 Feedwater Controller Failure 1.28 1.27 1.25 1.24
- 13. OVERPRESSURIZATION ANALYSIS
SUMMARY
(S.2.3) Psi Py Transient (psig) (psig) Plant Response MSIV Closure 1234 1269 Figure 4 (Flux Scram)
- 14. STABILITY ANALYSIS RESULTS (S.2.4)
Rod Line Analyzed: 105% Decay Ratio: Figure 6 Reactor Core Stability Decay Ratio, x2 /*0: 0.60 Channel Hydrodynamic Performance Decay Ratio, x2 /x0* Channel Type BP8x8R/8x8R 0.47
- Fuel loading error not applicable for C-Lattice plants.
9
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23A4735 Rev. 0
- 15. LOADING ERROR RESULTS (S.2.5.4)
Not applicable for C-Lattice plants.
- 16. CONTROL ROD DROP ANALYSIS RESULTS (S.2.5.1)
The bounding Control Rod Drop Analysis for Banked Position Withdrawal l Sequence plants was applied.
- 17. LOSS-OF-COOIANT ACCIDENT RESULTS (S.2.5.2) t Fuel Type: BP8CRB299L Exposure MAPLHGR PCT Local Oxidation (GWD/MT) (kW/ft) (*F) (Fraction) 0.22 10.80 1828 0.007 1.1 11.00 1831 0.007 5.5 11.80 1880 0.008 11.0 12.30 1909 0.009 17.0 12.40 1932 0.009 22.0 12.30 1945 0.009 28.0 11.80 1897 0.008 39.0 10.70 1768 0.005 49.0 9.20 1595 0.002
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'j Figure 1. Reference Core Loading Pattern [
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23A4735 R;v. O
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l ~ 23A4735 Rev. 0 l l 150.0 1 NE L['RON FLUt i VESSEL PRES 5 RISEEPSI) 2 AVE 5 ACE HEAT FLUX 0 SAFETY VP.LVE FLOW 3 COEi ! T ' LOW 3 RELIEF VALVE FLOW 130.0 aem I u_ ' ?La 4 BYPASS VALVE FLOW i00.0 ,
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Figure 3. Plant Response to Feedwater Controller Failure 13 i
1 - > 23A4735 R;v. O l 1 i UX 1 VESSEL PRESS RISE (PSI) 2A E HEAT l' LUX 2 RELIEF VALVE FLOW 3C :E Itt ' FLOW 3 SAFETY VALVE FLOW 15 0. 0 308.8 4 BYPASS VALVE FLOW -
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23A4735 Rev. 0 l NOTES:1. NO. INDICATES NUMBER OF NOTCHES WITHDRAWN OUT OF 48. BLANK IS A WITHDRAWN ROD. <
- 2. ERROR ROD IS (13,11).
1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 1 36 36 36 3 6 6 6 6 5 36 32 32 32 36 7 6 2 10 10 2 6 9 36 32 44 40 44 32 36 11 10 6 10 0 0 10 6 10 13 36 32 40 44 40 32 36 15 10 6 2 6 6 2 6 10 17 36 32 40 44 40 32 36 19 10 6 10 0 0 10 6 10 21 36 32 44 40 44 32 36 23 6 2 10 10 2 6 25 36 32 32 32 36 27 6 6 6 6 29 36 36 36 Figure 5. Limiting Rb'E Rod Pattern 15
23A4735 Rev. 0 l ANATURAL CI RCULATION 8 105 PERCENT ROD LINE CU_T. PERFC RMANCE LI MIT 1.00 C C
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- 0. 0 20.0 40.0 60.0 80.0 100.0 120.0 PERCENT POWER Figure 6. Reactor Core Decay Ratio versus Power 16
l . ! 23A4735 Rev. O APPENDIX A TRANSIENT ANALYSIS BASIS The Loss of Feedwater Heating event was analyzed using the BWR Simulator Code (Reference A-1). The use of this code is permitted in GESTAR II (Refer-ence A-2). The Loss of Feedwater Heating Event plot normally reported in Section 10 is not an output of the BWR Simulator Code. Therefore, this plot is not included in this document. REFERENCES A-1. "Three Dimensional BWR Core Simulator," NED0-20953A, January 1977. A-2. " General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A (latest revision). 1 17/18
r~ l 23A4735 Rev. O I l j APPENDIX B l PLANT PARAMETERS These values differ from the values reported in NEDE-240ll-P-A-7-US. Dome Pressure 1030 psig Turbine Pressure 980 psig Dual Mode Safety / Relief Valves 18 Relief Mode Low Setpoint 1087 psig Safety Mode Low Setpoint 1162 psig I 19/20 (FINAL)
ADU1710NAL INFORMATION REGARDING 2 Tk1[PageSUPPLEMDfTAL 1 cf 2) RIIAAD L 1 / CYCLE _ Fog la Salle 2 iLELo&D - Section 3. REFERIACE CORE LCADING PATTIRN 10216 W d/ST Cycle N-1 incremental Exposure 6775 W d/ST Cycle N Ezposure increment Cycle N Full Power Capability (if different 6775 mwd /ST from above) Section 4. CAJfUI.ATED CORI EFFECTIVE MULTIPLICATION AND ColfIROL SYSTEM VORTH (NO VOIDS, 20'C). ( Cycle incremental Exposure Corresponding to 6775 mwd /ST Minimum Shutdown Margin R-Value Section 6. RELO & UNIQUE TRANSIENT ANALYSIS INPUT (RIDY EVENTS) s EOC Void Fraction (Haling) EOC Bypass Flow Fraction ' Delayed Neutron Fraction (50C/EOC) *No RIDY Analyses were performed Void Coefficient,x 103 (BOC/EOC) 1< [ Units are (6k/k)/(61 voids)] , Section 10. CORE-WIDE TRANSIENT ANALYSIS RESULTS 7, pg } Go4+em 9amt Pal % 'h-Power Flow Flur Q/A -4Domeh h v57 Limiting Exposure Transitet,(1 NBR) (1 NBR) (1 NBR) (% NBR) (psig) (psig) _ (psig) [ 119.1 1168 1191 -14% Il#U TINBP 103.9 100.0 367.5 EOC e 100.0 450.2 120.9 1166 1192 103.9 EOC 1ANBP MSIVF 103.9 100.0 646.5 126.1 g34 1269 M , EOC Not Analyzed MSIVD 100.0 126.8 126.8
- 1026 LFWH 103.9 BOC EOC FWCF 103.9 100.0 289.5 119.0 1142 1172 h J
- Numbers not available. PANACEA analysis was used.
kDDITl0NAL INFORMATION _RElhAD _ 1 / CYCLE _ 2 RECARDING [Page 2 of 2) THE S
. 'FOR _ La Salle 2 S2ction 10. CORI-VIDE TRANSIENT ANALYSIS RESULTS (Continued Were resolved OPL-3 values used for safety and Yes _
relief valve characteristics? Assumed MSIV Closure Characteristics: Time (see) _MSIV area (per unitl 0.0 1.0,(fully opened) 0.6 1.0 1.7 0.01 As Used. 3.0 0.0 (fully closed) Section 14. ROD BLOCK LINE EQUATION _ Not applicable RB 1 0.66 W3 + 45 since no LLLA performed. Section 15. 14ADING IRROR RESULTS_ _ Not Analyze _d Bundle Type for Limiting Misorientation i I f
O marnows nsnouwmm 2 1.pnon. c.it 4. ny: Jeff M'N " o.t. //- 2 F- F 4 P.rsons cont.ct.d: Coupemt F.31.39B Garg / W rro k Gaent Elec/r:c /&eli%,auen t
' v subiect: Re p h ; vessel ffCSSafCS llJfek n " Add lfiml Zdergdm Keychy tia. fappfemenbl Asfoad Ocens?Q CubsHal '
vess el pressa res do stof seem cofree t . G<ry clecked, fnnd tLd weers.u kn esde p s;<. fo ps.y Aad been been adveri entlydne by add:3 m is; in sfead ef su bfrach3 IV ps: . c orc ee.+ valaes are (ps ): Pv P< pam e do % Twdr l162 l191 DAN 0/ ///3 //92 Mstvf ig 5g" iuq FWF II Ll l jf f,1, t fo lloW -s^f fr~s m.f a le(fer y, Ges c ,,I E tee +,re w.U
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June 5, 1966 NFS: BPS:86-054 J. L. Anderson
SUBJECT:
LaSalle Unit 2 Cycle 2 Draft Re. load Licensing Submittal
REFERENCE:
Letter from H. E. Bliss to J. L. Anderson, dated June ~1, 1985; concerning the LaSalle Unit 1 Cycle 2 Draft Reload Licensing Submittal. Enclosed for transmittal to General Electric are NFS and Station comments on the Draft Licensing submittal for LaSalle 2 Cycle 2. These connents require resolution before the final submittal is issued. The MAPLHGR values for the new fuel type were included in this Licensing submittal. As requested in the referenced letter, the MAPLHGR valaes should be sent separately from and in advance of the licensing doctanent . The separate transmission will aid in submitting the values to the NRC as preparatory Tech Spec changes to facilitate reload reviews under 10CFR50.59. If you have any questions, please contact Peter Piet of my staff at extension 3852. Hent) . Bliss Nuclear Fuel Services Manager HEB:PLP:mab l ID: 6385N ! cc: M. H. Richter J. A. Silady/K. W. Peterman l L2C2 Licensing NFS-CP
NFS Coasnents 7 L2C2 Draft Reload Licensing Submittal
- 1. As discussed during the LaSalle 1. Cycle 2 licensing, fuel bundle type BP8CRB299L was to have been included in GESTAR by June 1985. This has not yet been done. Provide the necessary bundle information for CECO's submittal to the NRC for the L2C2 Supplemental Reload License Submittal and indicate when this bundle type will be added to GESIAR.
- 2. Page 6. Item 4: The reported Minimum Shutdown Margin R-value is listed as occuring at EOC. Has an analysis been performed for Shutdown Margin past ROC for possible Coastdown operation? What effect does Coastdown operation have on Shutdown Margin?
- 3. Page 8. Item 10: For LOFVH calculations, what AT was used?
- 4. Page 8 Item 10: In Figure 2 and Figure 3, why are the curves on both of these pages off-scale in various locations?
- 5. Page 10. Item 16: Please provide a more detailed explanation of the bounding Control Rod Drop Analysis as in the LaSalle 1 Cycle 2, Appendix B, Supplemental Reload Licensing Submittal.
- 6. Page 14 Figure 4: In the MSIV closure with Flux scram, why is there relief valve flow? "
~J . Page 17/18. Reference A-2: Specify which revision of GESTAR is applicable for.the L2.C2 ReJoad Licensing Submittal. The.'flatestrevision)' is unacceptable.
ID: 6385N2 I l 1 1
)
l l l
1 GEN ER AL (@ ELECTRIC NUCLEAR ENERGY BUSINESS OPERATIONS GENERAL ELECTRIC COMPANY
- 175 CURTNER AVENUE e SAN JOSE. CAUFORNIA 95125 Mall Code 174 June 27, 1986 cc: H. E. Bliss REP:86-108 P. R. Mattson Mr. J. L. Anderson Fuel Buyer COMMONWEALTH EDISON COMPANY Fuel Department, 234 E P. O. Box 767 Chicago, IL 60690
SUBJECT:
General Electric's Response To Edison's Comments On LaSalle County Unit 2 Cvele 2 Draft Reload Licensine Submittal
REFERENCES:
- 1) Letter, J. L. Anderson to R. E. Parr, "LaSalle County Unit 2 Cycle 2 Draft Reload Licensing Submittal", June 10, 1986.
- 2) Letter, R. E. Parr to J. L. Anderson, " Amendments To General Electric (CE) Licensing Topical Report (LTR) NEDE-24011-P-A (CESTAR Revision 8)", June 23, 1986.
ATTACHh2.NT: General Electric's Response To Edison's Comments
,3 s
... h _
Dear Mr. Anderson:
Enclosed is General Electric's item by item response to the comments provided in reference 1. Please confirm that this response is satisfactory. _ The final document will be issued after resolution of any additional comments. Very truly yours, R. E. Parr Senior Fuel Project Manager Edison Projects M/C 174; (408) 925-6526 Encl. i r. t
GENERAL h ELECTRIC GENERAL ELECTRIC'S RESPONSE TO EDISON'S COMMENTS
- 1. GESTAR Amendments 1 through 13 have been approved by the NRC and Amendments 14 through 16 are being reviewed. The bundle information that you requested is contained in Amendment 13, as provided in Reference 2, Appendix D pages US.DD 217a and US.DD 217b. Revision 8 of GESTAR incorporates Amendments 1 through 13 and is to be issued by June 30, 1986.
- 2. Shutdown margin during coastdown has been analyzed. At a cycle exposure of 7500 mwd /ST (after a coastdown of 725 mwd /ST) shutdown margin has increased by 0.12% relative to the end-of-rated-power exposure point. Shutdown margin will continue to increase for greater coastdown exposures.
- 3. A AT of 145'F was used.
- 4. If the scale of the plots were reduced sufficiently to show the neutron flux peak, then the most important curve, surface heat flux, would be very difficult to read.
- 5. The information that you requested is contained in Amendment 12. as provided in Reference 2.
- 6. The flow is actually safety valve flow. A code labeling problem caused all S/RV flow to be labeled as relief flow. The label will be corrected in the final version of the reload submittal. -
- 7. Since GESTAR is continuously being updated, the latest revision plus approved amendments is the applicable version of GESTAR for LaSalle Unit 2 Cycle 2. Presently, this is Revision 7, plus Amendments 11, 12, and 13. However, as stated in Item 1 above, this is exactly what will be inc6rporated into Revision 8 of GESTAR.
l i l I l l
1 ATTACIEENT E TECHNICAL SPECIFICATION CHANGE REOUEST LASALLE COUNTY STATION UNIT 2 G.E. Letter REP 84-086 R.E. Parr (G.E.) to L.J. Bridges (CECO), "Kg Curve for LaSalle County Station Units 1 and 2" dated June ~1, 1984. i d 2482K
GENER AL $ ELECThiu . NUCLEAR FUEL ANO sPEcML PeOJECTs oMsO4 GENERAL ELECT *C COMPANY
- 175 CULTNER AVENUE
- SAN Jose. cAuF cc: H. E. Bliss
- June'7, 1984 P. R. Mattson REP:84-086 Ms. L. J. Bridges ,
Principal Fuel Buyer COMMONWEALTH EDISON COMPANY Fuel Department, 234 E P. O. Box 767 Chicago, IL 60690 K Curve for LaSalle County Units 1 and 2
SUBJECT:
7
REFERENCE:
Letter, R. E. Parr to L. J. Bridges, "Kg Curve - LaSalle County Units 1 and 2", April 16, 1984 a
Dear Ms. Bridges:
The following information is provided to supplement that provided . , earlier in the Reference letter. The K f curves for manual and auto flow condition at a power of 3323 MWt and a flow of 108.5 M1b/hr are contained in Table 1. Figure 1 and Figure 2, respectively. Also provided, in Table 2, are the hydraulic constants for the process computer data book. The methodology used in the calculation of the K f curves is described 3 in Appendix B of GESTAR II, and the steady-state computer code used for The reference the calculation is described in Chapter 4.4 of the FSAR. power-flow relatic. used to characterize the runout states corresponds t .
- the 105% power rod line.
corresponds to the LaSalle pump flow runout condition, Please contact me if you have any further questions. j Very truly yours, l R. E. Pa r %r Fuel Project Manager Edison Projects M/C174;(408)925-6526 rem Attach. f
Table 1 K CURVE CONSTANTS f Figures 1 and 2 describe the K, curve for manual and auto flow conditions, respectively, for LaSalle County Units 1 and 2. The curve fit equations for these curves are: KF1 =f 1.0+CP(25,1)*[CP(25,2)-CF] KF2 = 1.0 + CP(26.1) * [CP(26,2) - CF] where the constants are as follows: Manual Automatic
~
CP(25,1) = 0.5158 CP(25,1) = 0.4444 Co(26,1) = 0.08 CP(26,1) = 0.5680 CP(25,2) = 0.838 CP(25,2) = 1.1521
/ CP(26,2) = 1.0 CP(26,2) = 1.0 e
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! J.# pgALal*d 8888Re M DNP L1I3e223 , ,_ sie J. fJ . CORE CHAftACTERl0 TICS . . - .,
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.s al . l . 3 TOTAL POWER (RATCTP3 3323.00 MW-TM I
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.g f.9 . 2. 3 NUMRER OF AMIAL NOOES INFS) 24 O.000 FT
- 3. a.1. 2. 4 AMIAL NOOE LENGTH EDZStel 1.443 FT As.t.2.8 UNHEATED ENO NODE LENGTH (OFEfe) 4
! A&l.2.s TOTAL CORE HEAT TRANSFER AREA (AC) 74072.00 FTest CORE AVERAGE HYDRAULIC OIAMETER (DECORD 0.044e FY 37.1.2.7 n.t039 FT As.l.2.8 AVERAGE SUNOLE FLOW AREA (ASUMAV3 331.8 COOLANT PROPERTIES l- loss.oo PSIA l s s. l . S . I CORE PRESSURE
- 20.300 STU/LB 3Al.3.2 INLET SuecOOLEMe .
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