ML20082U726
| ML20082U726 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 09/16/1991 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20082U725 | List: |
| References | |
| NUDOCS 9109200318 | |
| Download: ML20082U726 (3) | |
Text
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ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT
-?(
- 6. 9.1. 9 Core operating limits snall be established and documented in the CORE OPERATING LIMITS REPORT before each reloaa cycle or any remaining part
(
of a reload cycle for the following:
)
1.
Mocerator Temperature Coefficient BOL and EOL limits and 300 ppm
(
surveillance lioit for Specification 3/4.1.1.3,
)
2.
Shutcown Bank Insertion Limit for Specification 3/4.1.3.3,
(
3.
Control Bank Insertion Limits for Specification 3/4.1.3.6,
('
4 Axial Flux Difference limits, target band, and APLND*for
)
~
Specification 3/4.2.1,
(
ND "and W(Z)gg RTP
'N 5.
Heat Flux Hot Channel Factor, F
, K(Z), W(Z), APL for Specification 3/4.2.2, and g
gg%
RTP ","* d Power Factor
\\
6.
Nuclear Enthalpy Rise Het Channel Factor,6 F
an Multiplier, MF m., limits for Specificetion 3/4.2.3.
)
3, l
The analytical methods used to determine the core operating limits shall be
)
those previously reviewea ano approved by NRC in:
(
1.
WCAP-9272-P-A, "K STINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (W Proo-ietary).
l (Methodology for Specifications 3.1.1.3 - Moderator Temperature N
Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control T
Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux
/
Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel
(
Factor.)
)
l 2.
WCAP-10216-9-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ
/
SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (W Proprietary).
\\
l (Methocology for Specifications 3,2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z)
(
i surveillance requirements for F Methocology.)
g 3.
WCAP-10266-P-A Rev. 2 "THE 1981 VERSION OF WESTINGHOUSE EVALUATION
(
MODEL USING BASH CODE", Maren 1987, (W Proprietary).
N Lwt M(ioe.L.% 1 Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).
)
/
The core operating limits shall be ceterminco so that all applicaDie limits
(
(e.g., fuel thermal-mecnanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits sucn as shutdown margin, and transient and accident y
analysis limits) of the safety analysis are vt.
N The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or y
supplements thereto, snall be proviced upon issuance, for each reload cycle, N
to the NRC Occument Control Desk with copies to the Regional Administrator and Re icent Inspector.
[
% set wt 2.
SPECIAL REPORTS 6.9.2 Special reports snall be submitted to the Regional Administrator of the NRC Regional Office within the time ceriod specified for eacn report.
McGUIRE - UNITS 1 and 2 6-21
%"r:n %.105 '""" D 9109200318 910916
%n--"
DR ADOCK 05000369 PDR
for Specification 6.9.1.9 :
4.
BAW-10168P, Rev.
1, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants," September, 1989 (B&W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)
5.
DPC-NE-2011P, " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," March, 1990 (DPC Proprietary).
(Methodology for Specification 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
6.
DPC-NE-300lP, " Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," March, 1991 (DPC Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient 3.1.3.5 - Shutdown Rod Insertion Limits, 3.1.3.6 -
Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Mot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
7 DPC-NF-2010P, " Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design,"
April, 1984 (DPC Proprietary).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient.)
8.
DPC-NE-3002,"FSAR Chapter 15 System Transient Analysis Methodology", August 1991.
(Methodology used in the system thermal-hydraulic analyses which determine the core operating limits) 9.
DPC-NE-3000, Rev.
1,
" Thermal-Hydraulic Transient Analysis Methodology", May 1989.
(Modeling used in the system thermal-hydraulic analyses)
for Specification 6.9.1.9 :
Reierence_5.is not applicable to target band and APL*.
l References 4-~and-5-are not applicab APL", and W (Z),6 Ref erence 1 is not applicable to Fy;1e. to W(Z),
Reference 5 is.not applicable to ry' and MFu.
t WN++
3 4
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