ML20247E577
| ML20247E577 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/03/1989 |
| From: | Clements T CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20247B232 | List: |
| References | |
| NUDOCS 8904030164 | |
| Download: ML20247E577 (11) | |
Text
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CP&L Nuclx r Fu21 SIctica
~Filei.NF-2202;014:
BlC7 Core Operating Limits Report-Page 1, Revision 1.
BRUNSWICK UNIT 1, CYCLE 7 CORE OPERATINC LIMITS REPORT MARCH 1989
' Controlled Copy Prepared By: M. J. DEVOE I6 s////
3 t/tc Approved By:
A Date
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Talmage Clements Principal Engineer Transient Analysis 8904030164 090320 PDR ADOCK 05000324 P
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' Filet ~NF-2202.014'
- 81C7 Core.. Operating Limits Report-
.;Page 2, Revision 1 t-s LIST OF EFFECTIVE PAGES o
Page(s)
Revision L
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CP&L Nuciscr Fu21 S2ction Files NF-2202.014
~B1C7 Core Operating' Limits _ Report Page 3, Revision l1-INTRODUCTION 'AND
SUMMARY
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_ This report provides the values of. the AVERACE PLANAR LINEAR HEAT CENERATION RATE (APLHCR) limits, the Kg core flow adjustment-factor, cand the MINIMUM CRITICAL POWER RATIO (MCPR) limits for Brunswick Unit 1, Cycle 7.as required.by Technical Specification 6.9.3.1.
Per Technical Specifications'6.9.3.2 and 6.9.3.3, these values-have been determined using NRC-approved methodology and are established such that-all applicable limits of the plant safety analysis are met.
i Preparation of this report was performed 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.
natural uranium) of each fuel type as a function of AVERACE PLANAR EXPOSURE is given in Figures 1,2,3, 4, and 5.
These values were determined with the SAFE /REFLOOD LOCA methodology described in CESTAR-II (Reference 2).
Figures 1,2,3, 4, and 5 are used when hand calculations are required as-specified in Technical Specification 3.2.1.
MCPR LIMITS 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-PLUS critical powe. 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 6.
REFERENCE (s)
{
- 1) CP&L Nuclear Fuel Section Quality Assurance File NF 2489.0016,
" Preparation of the Brunswick Unit 1, Cycle 7 Core Operating Limits Report", February 1989 (as supplemented.
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- 2) NEDE-24011-P-A, "Ceneral Electric Standard Application for Reactor Fuel" (latest approved version).
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I CP&L Nuclear Fuel Section File: NF-2202.014
- 81C7 Cora Operating Limits Report Page 4, Revision 1 Figure 1 FUEL TfPE P8DRB284H (P8X8R)
AVERAGE PLANAR LINEAR HEAT VERSUS AVERAGE PL(ANAR EXPOSURE GENERATION RATE APLHGR) LIMIT i
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THIS FIGURE IS REFERRED TO BY
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TECHNICAL SPECIFICATION 3.2.1.
12,0 12,0 12 11
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10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPOSURE (GWD/ST)
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i CP&L' Nuclear Fuel Ssetion B1C7 Core Operating Umits Report.
File: NF-2202.014
. Page 5, Revision 1 -
Figure 2 FUEL TYPE P8DRB299 (P8X8R AVERAGE PLANAR LINEAR HEAT)
VERSUS AVERAGE PL(ANAR EX)POSURE-GENERATION RATE APLHGR LIMIT 13 THIS FICURE IS REFERRED TO BY 12,2 12,3 TECHNICAL SPECIFICATION 3.2.1
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l CP&L Nuclear. Fuel Section File: NF-2202.014 B1C7 Coup : Operating Limits Report Page 6,-. Revision 1 3-Figure 3 FUEL TYPE BP8DRB299 (BP8X8R)
AVERAGE PLANAR LINEAR HEAT VERSUS AVERAGE PL(ANAR EX)"OSURE GENERATION RATE APLHGR UMIT-13 THIS FIGURE IS REFERRED TO BY.
12,2 12.3.
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1 CP&L Nuclear Fuel-Section -
File:' NF-2202.014 B1C7 Cote-Operating Limits Report.
Page 7. Revision 1 Figure 4 d
AVERAGE PLANAR LIN(EAR HEATFUEL TYP VERSUS AVERAGE PL(ANAR EXPOSURE-GENERATION RATE APLHGR) LIMIT 14
~13,10 13
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12,75 THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.1
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12 -- 7 t
1.44 11,29 10,66 0 33 5
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OF ERAfiON 96
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7 6.06 6
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10 15 20 25 30 35 40 45 50 AVERAGE P!ANAR EXPOSURE (GWD/ST) i
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l CP&L' Nuclear Fuel Section File: NF-2202.014 B1C7 Core Operating Limits Report Page 8, Revision.1 l
Figure 5 AVERAGE PLANAR LIN(EAR HEATGE8X8EB FUEL TYPE BD339A VERSUS AVERAGE PL(ANAR EXPOSURE GENERATION RATE APLHGR) LIMIT l
14 12.88 g3-THIS FIGURE IS REFERRED TO BY H
A A ON 3.2.1
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5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWD/ST)
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.CP&L' Nuciccr Fuel S2cticn Fils:.NF-2202.014 B1C7 Core. Operating Limits Report Page 9, Revision 1 TABLE 1 MCPR LIMITS
-Fuel Type (s): P8X8R, BP8X8R, and GE8X8EB Non-Pressurization Transient MCPR = 1.25
-Pressurization Transient MCPR Exposure Range MCPR MCPR Option A' Option B BOC7 to EOC7-2000 MWD /ST 1.32 1.25 EOC7-2000 MWD /ST to EOC7-1.34 1.30 THIS TABLE IS REFERRED TO BY TECHNICAL SPECIFICATIONS 3.2.3.1 AND 3.2.3.2
i CP&L Nuclear Fuel Section File: NF-2202.014 81C7 Core Operating Umits Report Page 10, Revision 1 r
Figure 6 Kr CORE FLOW ADJUSTMENT FACTOR 1.4 l
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THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3.1
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'N AUTOMATIC FLOW CONTROL NNN N
2 1.1 s
3 MANUAL, FLOW CONTROL SCOOP TUBE SETFOINT
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i CAUBRATION POSIllONED SUCH THAT FLOW W = 102.5s
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=1' 2.Os
=1' 7.Os 0.9 30 40 50 60 70 80 90 100 CORE FLOW (s)
..y ENCIDSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT ELIMINATION OF CYCLE-SPECIFIC PARAMETER LIMITS (NRC GENERIC LETTER 88-16)
CORE OPERATING LIMITS REPORT - UNIT 2 I
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