|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20151T5021998-08-0505 August 1998 Project Implementation Plan, Ngg Yr 2000 Readiness Program, Rev 2 ML20249B9691998-06-11011 June 1998 Rev 1 to VC44.F02, Brunswick Steam Electric Plant,Units 1 & 2,ECCS Suction Strainers Replacement Project,Nrc Bulletin 96-003 Final Rept ML20217E7031998-02-28028 February 1998 Rev 2 to ESR 97-00034, Engineering Evaluation B213R1 Core Shroud Insps ML20203M0141998-02-19019 February 1998 Rev 1 to ESR 9700706, Unit 1 Core Shroud Insp Results ML20199E9601997-12-31031 December 1997 Biological Assessment of Impact to Sea Turtles at CP&L Brunswick Steam Electric Plant ML20202E0441997-11-0606 November 1997 ECCS Suction Strainer Replacement Project,Nrc Bulletin 96-003,Final Rept ML20199A9251997-10-31031 October 1997 Rev 1 to ESR 97-00034, Engineering Evaluation B213R1 Core Shroud Insps ML20249B9751997-09-19019 September 1997 Rev 1 to Summary Rept on Performance of Performance Contracting,Inc'S Sure-Flow Suction Strainer W/Various Mixes of Simulated Post-LOCA Debris ML20198Q8791997-09-19019 September 1997 Rev 1 to Summary Rept on Performance of Performance Contracting,Inc Sure-Flow Suction Strainer W/Various Mixes of Simulated Post-LOCA Debris ML20217H8441997-07-22022 July 1997 Rev 0 to 97-00362, IF-300 Cask Design,Testing & Insp ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML20198P7431997-03-0303 March 1997 Partially Withheld Engineering Service Request,Rev 0 to ESR 97-00087, EQ-Type Jco for Improperly Configured Conduit Seals ML20140E2531997-02-14014 February 1997 Rev 0 to Summary Rept of Performance of Performance Contracting Inc'S Sure-Flow Suction Strainer W/Various Mixes of Simulated Post-LOCA Debris ML20198P5291997-02-12012 February 1997 Rev 1 to ESR 97-00087, EQ-Type Jco for Improperly Configured Conduit Seals. Also Encl,Viewgraphs Re Environ Qualification Issues & EA Request & Enforcement Strategy Forms ML20138F9511997-01-0707 January 1997 Evaluation of Design & Inspection History of Weld Overlay Repairs at Brunswick Nuclear Plant,Units 1 & 2 ML20199J8051996-12-31031 December 1996 Rev 0 to Performance Contracting,Inc ECCS Sure-Flow Strainer Data Rept ML20140E2431996-12-31031 December 1996 Rev 0 to W04536-01, Performance Contracting,Inc ECCS Sure- Flow Strainer Data Rept ML20249B9881996-12-31031 December 1996 Rev 0 to WO4536-01, Performance Contracting,Inc,Eccs Sure- Flow Strainer Data Rept ML20137V8121996-12-18018 December 1996 N-16 Nozzles Upper Shelf Energy Evaluation ML20135E3091996-10-31031 October 1996 Rev 0 to ESR 96-00160, Engineering Evaluation B111R1 Core Shroud Insp ML20108B9101996-02-0808 February 1996 Evaluate Results of U2 Core Shroud B212R1 Insps ML20092G3891995-09-30030 September 1995 Rev 0 to Brunswick Nuclear Plant Units 1 & 2 USI A-46 Relay Evaluation Rept, Final Rept ML20092G3951995-09-30030 September 1995 Rev 0 to Brunswick Nuclear Plant Units 1 & 2 USI A-46 Seismic Evaluation Rept, Final Rept ML20212H6101995-09-13013 September 1995 Site Assessment Rept,Unit 2 Radwaste Effluent Line. Page 2 of 2 in Visual Classification of Sails - Boring ESS3B Section of Incoming Submittal Not Included ML20237A5791995-08-11011 August 1995 Rev 1 to EER 92-0483, E41-V159 Testing Method Change ML20085K9311995-06-21021 June 1995 Unit 1 Core Shroud Evaluation Based on B11OR1 Insp Results ML20083R8081995-02-28028 February 1995 Suppl Reload Licensing Rept for Bsep,Unit 1,Reload 9 Cycle 10 ML20078M0491995-01-31031 January 1995 TS Improvement Analysis for Reactor Protection Sys for Brunswick Steam Electric Plant,Units 1 & 2 ML20072F2501994-08-16016 August 1994 RPV Surveillance Program First Capsule (300) Removal After 8 Fuel Cycles ML20072F2661994-06-30030 June 1994 Neutron Dosimetry Results for Surveillance Capsule Removed at Conclusion of Fuel Cycle 8 ML20072M8461994-06-0404 June 1994 Evaluation of Unit 2 Core Shroud Indications & Operability Assessment ML20079A5911994-06-0101 June 1994 Rev 0 to Engineering Evaluation Rept 94-0182, Unit 2 FW Sparger Evaluation Following Iviv Exams ML20069N8991994-05-31031 May 1994 Suppl Reload Licensing Rept for BSEP Unit 2 Reload 10 Cycle 11 ML20058M4451993-12-31031 December 1993 Shroud Repair Hardware Stress Analysis, Rev 1 ML20059K8461993-11-24024 November 1993 Rept of Technical Review Team:Potential Shroud Cracking in 1984 ML20056F6991993-08-18018 August 1993 Operability Assessment of Pinhole Leak in 6 Vital SW Header ML20058P8751993-07-31031 July 1993 Nonproprietary Suppl Reload Licensing Rept for BSEP Unit 1 Reload 8 Cycle 9 ML20094M2611993-04-16016 April 1993 Fatigue Usage to Date for RPV Components BSEP Unit 1 & Unit 2 ML20128G3121993-01-31031 January 1993 EMI Analysis Numac Leak Detection Monitor PM-92-108, Rev 2 to Plant Mod PM 92-108, Cbeaf Improvements1993-01-0808 January 1993 Rev 2 to Plant Mod PM 92-108, Cbeaf Improvements ML20128H8321992-12-19019 December 1992 Rev 1 to Design Basis Document DBD-37, Control Building, Heating,Ventilating & Air Conditioning Sys ML20128H7221992-10-30030 October 1992 Rev 0 to Engineering Evaluation Rept,Eer 92-0352, Cbeaf Single Failure Operability Assessment ML20114D9521992-08-31031 August 1992 Vols 1 & 2 to Brunswick Steam Electric Plant Units 1 & 2 Ipe ML20127N4511992-07-30030 July 1992 General Electric Nuclear Energy Ultrasonic Exam Rept R-1 ML20046A3201992-03-27027 March 1992 Rev 2 to SWS Hydraulic Analysis Rept for Bsep,Units 1 & 2. ML20056D5981991-12-0303 December 1991 Rev 0 to Engineering Evaluation Rept 91-0450, Unit 2 Svc Operability ML20099B9391991-11-30030 November 1991 Corrected GE-NE-523-112-1191, Feedwater Sparger Circumferential Cracking Evaluation for Brunswick Units 1 & 2 ML20086G3181991-07-31031 July 1991 Core Spray Line Crack Analysis Update for Brunswick Steam Electric Plant,Unit 2,Safety Evaluation 1999-05-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied BSEP-99-0005, Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0231, Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0218, Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with BSEP-98-0210, Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired1998-10-30030 October 1998 Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 BSEP-98-0202, Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151Y6211998-09-14014 September 1998 BSEP Rept Describing Changes,Tests & Experiments, for Bsep,Units 1 & 2 ML20151Y6371998-09-14014 September 1998 Changes to QA Program, for Bsep,Units 1 & 2 BSEP-98-0185, Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151T5021998-08-0505 August 1998 Project Implementation Plan, Ngg Yr 2000 Readiness Program, Rev 2 BSEP-98-0164, Monthly Operating Repts for July 1998 for BSEP Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for BSEP Units 1 & 2 ML20236T1961998-07-0101 July 1998 Rev 1 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr ML20236T1921998-07-0101 July 1998 Rev 1 to 1B21-0537, Brunswick Unit 1,Cycle 12 Colr BSEP-98-0142, Monthly Operating Repts for June 1998 for BSEP Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for BSEP Units 1 & 2 ML20236T1971998-06-30030 June 1998 Rev 2 to 24A5412, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13 ML20249B9691998-06-11011 June 1998 Rev 1 to VC44.F02, Brunswick Steam Electric Plant,Units 1 & 2,ECCS Suction Strainers Replacement Project,Nrc Bulletin 96-003 Final Rept BSEP-98-0129, Monthly Operating Repts for May 1998 for Bsep,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Bsep,Units 1 & 2 ML20151S9041998-05-31031 May 1998 Revised Pages to Monthly Operating Rept for May 1998 for Brunswick Steam Electric Plant,Unit 1 BSEP-98-0104, Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 2 ML20151S8991998-04-30030 April 1998 Revised Pages to Monthly Operating Rept for Apr 1998 for Brunswick Steam Electric Plant,Unit 1 ML20247N7501998-04-30030 April 1998 Rev 0 to BSEP Unit 1,Cycle 12 Colr ML20247N7721998-04-30030 April 1998 Rev 0 to J1103244SRLR, Supplemental Reload Licensing Rept for BSEP Unit 1,Reload 11,Cycle 12 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) BSEP-98-0080, Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 2 ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 1999-09-30
[Table view] |
Text
_ -_ _, _. .
r ~!
3, }y ; y
.CP&L.'Nuciscr Fu:1 Sicticn Filot. NF-2202.013
'B2C8., Core Operating;' Limits Report- _Page 1, Revision 0 h,
h.
BRUNSWICK UNIT 2,- CYCLE 8
' CORE OPERATING LIMITS REPORT-FEBRUARY 1989 Controlled Copy n
Prepared By: M. J. DEV0E o
/
~7 />
Approved By: / 2a e > Date (#
f / /
Talmage Clements Principal Engineer Transient Analysis 8903000267 890220 PDR ADOCK 05000324 i P PDR
- _ . - _ _ __ _ _ _ __ . J
- l. .a .; . ,
' g: , -;. i <
- - ~
7 p' t a
- ; 1,t . , . .
~
- CP&L-Nuciocr Fu21~Ssetien
-j Files .NF-2202.013 B2C8[ Core. Operating Limits-Report s
't
'Page 2, Revision 0 i:
4 LIST OF EFFECTIVE:PAGES 4 Page(s)' Revision f
I-9: ~0'
.i s
i i
- r. _ _ _ . ___ _ _ _ _ _ _ _ . _ - -
s '.
CP&L Nuclocr Fual S2cticn Fils: NF-2202.013 B2C8 Core Operating Limits Report Page 3, Revision 0 INTRODUCTION AND
SUMMARY
j This report provides the values of the AVERACE PLANAR LINEAR HEAT GENERATION RATE (APLhCR) limits, the Kg core flow adjustment factor, and the MINIMUM CRITICAL POWER RATIO (MCPR) limits for Brunswick Unit 2, Cycle 8 as required by Technical Specification 6.9.3.1.
l- Per Technical Specifications 6.9.3.2 and 6.9.3.3, these values have been I
determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysia are met. '
Preparation of this report was perforund in accordance with CP&L Nuclear Fuel Section Quality Assurance requirements and is documented in Reference 1.
APLHCR LIMITS The limiting APLHCR value for the most limiting lattice (excluding j natural uranium) of each fuel type as a function of AVERACE PLANAR ;
EXPOSURE is given in Figures 1,2,3, and 4. These values were determined with the SAFE /REFLOOD LOCA methodology described in CESTAR-II (Reference 2). l Figures 1,2,3, and 4 are used when hand calculations are required as specified in Technical Specification 3.2.1.
i l
MCPR LIMITS 1 The ODYN OPTION A, ODYN OPTION B, and non pressurization transient MCPR limits for use in Technical Specifications 3.2.3.1 and 3.2.3.2 for each fuel type as a function of cycle average exposure are given in Table 1. These values were determined with the CEMINI methodology and CEXL critical power-ratio correlation described in CESTAR-II (Reference 2) and are consistent with a Safety Limit MCPR of 1.04.
The Kg core flow adjustment factor for use in Technical Specification 3.2.3.1 is given in Figure 5.
REFERENCE (s)
- 1) CP&L Nuclear Fuel Section Quality Assurance File NF 2489.0014,
" Preparation of the Brunswick Unit 2, Cycle 8 Core Operating Limits Report", February 1989.
- 2) NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel" (latest approved version).
j ..
F 5'.
CP&L Nuclear Fuel Section File: NF-2202.013 B2C8. Core Operating Limits Report Page 4, . Revision 0 1
Figure 1 FUEL TYPE P8DRB265H (P8X8R)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR) LIMIT VERSUS AVERAGE PL(ANAR > EXPOSURE 13
'i 12.1 12.1
'9 ~
- 12. -
II ' II '9 11.6
/
11.5
\ -
2 N 11
\ 1 0.7 v
b 2
\ .N D.1
$ 10 \
J PERMISS18LE \\ 94 Q REGION QF OPEIMTION
\s 9
O i '
i 0 5 10 15 20 25 30 35 40 AVERAGE PLANAR EXPOSURE (GWD/ST)
. . , _ . = . .,. - .
- - - - - - - - - - ~ - ~ '
'i.;
J.;,
16- _
lq s
pj - .a c t_ i N
'CP&C Nucieor Fuel Section L B2C8--Core Operating Limits Report : File: NF--2202.013 .
. Page 5, Revision. 0.
.h 1
- s ,
E , Fig ure ~ 2 '
J FUEL TYPE BP8DRB299 :(BP8X8R)- ]
AVERAGE PLANAR UNEAR. HEATc
' GENERATION '. RATE APLHGR) LIMIT -' q VERSUS AVERAGE PL(ANAR EXPOSURE !
l l c13 12,2 12,1
% 12,0 12 5
11.C 11
'3. ( PERMISSIBLE
'v 10.9 RE0lON OF g OPl:RATDN 1
J 10.3 m
S 10 y
$ Ns '
N 9 I 9.0 8
0 5 10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPOSURE (GWD/ST) 1
CP&L Nuclear Fuel Section- File: NF-2202.013 82C8 Core Operating Limits Report Page 6, Revision 0 Figure 3 FUEL TYPE BD317A (GE8X8EB)
AVERAGE PLANAR LINEAR HEAT -
GENERATION RATE ' APLHGR LIMIT VERSUS AVERAGE PL(ANAR EX)POSURE 13 1 2.85 12-
,/ 12.65 x
[ 12.07
\
11.20 11 .96 h a
\
11 <23
\
N O jo -
v PERMISSIBl.E REGION OF 1 0.03
\
OF ERATION H
s
\
\
i e 8-37 \
7 '
6 a
5.91 5
0 5 10 1S 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWD/ST)
-l CP&L Nuclear Fuel Section: File: NF-2202.013 82C8 Core Operating Umits Report Page .7, Revision 0 Figure 4 FUEL TYPE BD323A (GE8X8EB)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE APLHGR LIMIT
.VERSUS AVERAGE PL(ANAR EX)POSURE 1 2.62 --
12.40 12.72 12- f
, /11 .33 12,04 1 1.30-4 c. 11
\
\ u PERMISSIBl.E 0.12 v
REGl0H OF 1
OF'ERAfl0N 3 9 \ s
=
N 8 49 b 8 '
7 N l
6 6.02 ,
)
5 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWD/ST) l
___-_a
pL , e, CP&L Nuciccr.Fu21 Ssetion Filot: .NF-2202.013 B2C8. Core Operating Limits, Report Page-8, Revision 0 TABLE 1-MCPR LIMITS Fuel Type (s): P8X8R, BP8X8R, and CE8X8EB Non-Pressurization Transient MCPR = 1'22 .
Pressurization Transient MCPR r
Exposure Range MCPR MCPR Option A Option B BOC8 to EOC8-2000 MWD /ST 1.29 1.22 EOC8-2000 MWD /ST to EOC8 1.30 1.26 i
d l
W.: #,
CP&L 'N'uclear Fuel Section File: NF-2202.013 k;';
- 182C8 Core Operating: Limits Report Page 9,~ Revision 0 r
Figure 5
,. K, CORE FLOW ADJUSTMENT FACTOR l
1.4 1.3 '
, AUTOMATIC FLOW CONTROL
j N N 2
11.
x MANUAL. FLOW Col 4 TROL 1 SCOOP TUBE SETFOINT CALIBRATION POSITIONED SUCH THAT FLOW MAX = 10 1.0
= ,n
-1' 2.5s m
2.Os y
/ x \x s
=1' 7.Os 0.9 30 40 50 60 70 80 90 100 CORE FLOW (z)
- _ _ _ _ _ _ _ _ _ _ _ _ _ .b