ML20246N753
| ML20246N753 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/31/1989 |
| From: | Clements T, Devoe M CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20246N740 | List: |
| References | |
| NUDOCS 8907200035 | |
| Download: ML20246N753 (10) | |
Text
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' P&L Nuclocr Fu$12S$ction Files NF-2202.014 3:q,. q;.. B1C7 Cora Opareting. Limits Report;
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~u BRUNSWICK UNIT 1, CYCLE 7 CORE OPERATING LIMITS REPORT MARCH 1989 Controlled Copy k Prepared By: M. J. DEV0E I
Approved By "E v d Date
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Talmage Clements Principal Engineer Transient Analysis
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"CP&L Nuciscr Fusi S2ction File NP-2202.014 B1C7 Ccra Op;rcting Limits R2 port Page 2,.R* vision 1 l
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LIST OF EFFECTIVE PACES age (s)
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"CP&L Nuclect Fus1'Saction-File:~ NF-2202.014
.B11Cf Cora Operating' Limits Report Page 3, Revision'1 INTRODUCTION AND
SUMMARY
This report provides the values of the AVERACE PLANAR LINEAR HEAT 7'
CENERATION RATE (APLHCR) limits, the Kg core flow adjustment I
factor, and the MINIMUM CRITICAL POWER RATIO (MCPR) limits for Brunswick Unit 1, Cycle 7 as required by Technical Specification 6.9.3.1.
Per Te dnical 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.
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 APLHGR,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 methohtogy and CEXL-PLUS critical power ratio correlation described ir. CESTAR-II (Reference 2) and are consistent with a Safety Limit MCPi of 1.04.
The Kg core flow adjustment factor for use in Technical Specification 3.2.3.1 is given in Figure 6.
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REFERENCE (s)
- 1) CP&L Nuclear Fuel Section Quality Assurance File NF 2489.0016,
" Preparation of the Brunswick Unit 1, Cycle 7 Core Operating
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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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-tCP&L Nuclear Fuel Section File: NF--2202.014 S1C7. Core Operating Limits ' Report
. Page 4 Revision 1 Figure 1 FUEL TYPE 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 i
TECHNICAL SPECIFICATION 3.2.1 7-n l
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10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPOSURE (GWD/ST) o
' CP&L Nucl:ar. Fu:1 S:cti:n File: NF-2202.014
- B1C7. Core Operating Limits. Report Page ~ 5, Revision - 1
' Figure 2 -
FUEL T(PE P8DRB299 (P8X8R)
AVERAGE PLANAR LINEAR HEAT VERSUS AVERAGE PL(ANAR EXPOSURE
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GENERATION RATE APLHGR) LIMIT 13 1
THIS FIGURE IS REFERRED TO BY 12,2 12,3 TECMICAL SPECIFICATION 3.2.1
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' CP&L Nuclear Fuel Section File: NF-2202.014 B1C7 Core-Operating Limits Report Page 6, Revision.1 -
Figure. 3.
q FUEL. TYPE BP8DRB299 (BP8X8R)
AVERAGE PLANAR LINEAR HEAT VERSUS AdRAGE PL(ANAR EXPOSURE GENERATION RATE APLHGR) LIMIT 13 THIS FIGURE.IS REFERRED TO BY:
12,2 12,3 TECHNICAL SPECIFICATION 3.2.1 g/N 12,1
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CP&L Nucl:ar Fu;l S;ction File: NF-2202.014 81C7 Core Operating Limits Report Page 7, Revicion 1 -
Figure 4 FUEL TYPE BD323B (GE8X8EB)
AVERAGE PLANAR LINEAR HEAT VERSUS AVERAGE PL(ANAR EXPOSURE GENERATION RATE APLHGR) LIMIT 14 13,10 l
13 jq 12.75 THIS FIGURE IS REFERRED TO BY l_
TECHNICAL SPECIFICATION 3.2.1 I
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c CP&L Nuclear Fuel Section File: NF-2202.01 '
B1C7 Core Operating Limits Report Page 8, Revision 1 Figure 5 FUEL TYPE BD339A (GE8X8EB)
AVERAGE PLANAR LINEAR HEAT VERSUS AVERAGE PL(ANAR EX)POSURE GENERATION RATE APLHGR LIMIT 14 l
12,88 MIS FIWRE IS REFERRED TO M 13 -
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1.16 PERMISSIBLE 1 0.36 a
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10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWD/ST)
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'CP&L Nucidir Fust'Sseti'on Filo:
NP-2202.014 BlC) Ctra Op3rcting Limits R:psrt Pcga 9, Revisien 1 i
A TABLE 1 1
MCPR LIMITS i
Fuel Type (s): P8X8R, BP8X8R, and CE8X8EB l
.i Non-Pressurization Transient MCPR = 1.25 Pressurization Tiansient 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 i
THIS TABLE IS REFERRED TO BY l
TECHNICAL SPECIFICATIONS 3.2.3.1 AND 3.2.3.2 1
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J G'4 CP&L Nuclear Fuel Section
. File: NF-2202.014
, 81C7. Core Operating Limits Report Page 10 Revision ' 1, Figure 6 K, CORE FLOW ADJUSTMENT FACTOR 1.4' l
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THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.3.1 1.3
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CALIBRATION POSITIONED SUCH THAT FLOW MAX = 102.5s
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0.9 30 40 50 60 70 80 90 100 CORE FLOW (z)
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