ML20072C171
| ML20072C171 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 08/04/1994 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20072C099 | List: |
| References | |
| NUDOCS 9408170110 | |
| Download: ML20072C171 (5) | |
Text
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ADMINISTRATIVE CONTROLS I
CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
1.
Moderator Temperature Coefficient BOL and EOL limits and 300 ppm _
surveillance limit for Specification 3/4.1.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.
Control Bank Insertion Limits for Specification 3/4.1.3.6, 4.
Axial Flux Difference limits, target band *, and APL"
- for Specification 3/4.2.1, 5.
Heat Flux Hot Channel Factor, F"", K(Z), W(Z)**, APL" **. and W(Z),t** for Specification 3/4.2.2, and Nuclear Enthalpy Rise Hot Channel Factor, fig *ification $g, or F ""****, and 6.
Factor Multiplier, MF ****,
limits for Spec
/4.2.3.
3n 7.
Overtemperature and Overpower Delta T setpoint parameter values for Specification 2.2.1.
8.
Boric Acid Storage System and Refueling Water Storage Tank volume and boron concentration limits for Specifications 3/4.1.2.5 and 3/4.1.2.6.
9.
Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3/4.5.1 and 3/4.5.5.
The analytical methods used to determine the cora operating limits shall be those previously reviewed and approved by NRC in:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"
July 1985 (W Proprietary).
N
/I g ;6 m nab Il (Methodology for Specifications 3.1.1.3 - Moderator Temperature 3
Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux USN Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)
Reference 5 is not applicable to target band and APL".
References 4 and 5 are not applicable to W(Z), APL"", and W(Z),t.
Reference 1isnotapplicabletoFIy.
Reference 5 is not applu.able to F[and MF 33 J
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NcGUIRE - UNITS I and 2 6-21 Amendment No. 143 (Unit 1) j 9408170110 940804 Amendment No. 125 (Unit 2)
'PDR ADOCK 05000369 4
P PDR 1
- 10. Reactor Coolant System and refueling canal boron concentration limits for Specification 3/4.9.1.
- 11. Spent fuel pool boron concentration limits for Specification 3/4.9.12.
l I
ADMINISTRATIVE CONTROLS
(
MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the NRC in accordance with 10 CFR 50.4, no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORI 6.9.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle fe; the following:
1.
Moderater Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.
Control Bank Insertion Limits for Specification 3/4.1.3.6, 4.
Axial Flux Difference Limits, target band *, and APL"
- for Specification 3/4.2.1, Heat Flux Hot Channel Factor, F,*, K(Z), W(Z)**, APL" **,F (X,Y,Z) 5.
o and W(Z)a** for Specification 3/4.2.2, and 6.
Nuclear Enthalpy Rise Hot Channel Factor, Fai'***(X,Y) or, F*****,
and Power Factor Multiplier, MFoH****, limits for Specification 3/4.2.3.
7.
Overtemperature and Overpower Delta T setpoint parameter values for Specification 2.2.1.
8.
Boric Acid Storage System and Refueling Water Storage Tank volume and boron concentration limits for Specifications 3/4.1.2.5 and 3/4.1.2.6.
9.
Reactor Water Makeup Pump flowrate limits for Specifications 3/4.3.3.12 and 3/4.9.2.
Abb f%AS lo 4E 11, AWACHEb
\\
Reference 5 is not applicable 1:o target band and APL"".
References 4 and 5 are not applicable to W(Z), and APL", and W(Z ).
a
- Reference 1 is not applicable to FoH'.
' **** Reference 5 is not applicable to F* and MFw.
CATAWBA - UNITS 1 & 2 6-18 Amendment No. 115 (Unit 1)
Amendmet No. 109 (Unit 2)
4
- 10. Reactor Coolant System and refueling canal boron concentration limits for Specification 3/4.9.1.
- 11. Spent fuel pool boron concentration limits for Specification 3/4.9.12.
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1 MCEl-04CD-46 i
Page 14B of 153 Revision 4 McGuire 1 Cycle 9 Core Operating Limits Report 3.10 Refueling Operations - Horon Concentration (Specification 3/4.9.1) 3.10.1 Minimum boron concentrations for the filled portions of the Reactor Coolant System and refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.
Parameter Limi.1 Refueling boron concentration for the filled portions of the 2000 ppm Reactor Coolant System and refueling canal for LCO 3.9.1.b.
3.11 Fuel Storage - Spent Fuel Storage Pool (Specification 3/4.9.12) 3.11.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel is stored in the spent fuel pool.
Parameter Listi Spent fuel pool minimum boron concentration for LCO 2000 ppm 3.9.12.a.
Spent fuel pool minimum boron concentration for 2000 ppm surveillance 4.9.12b.
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