ML20082U726

Proposed Tech Spec 6.9.1.9, Core Operating Limits Rept

ML20082U726
Person / Time
Site:	McGuire
Issue date:	09/16/1991
From:	DUKE POWER CO.
To:
Shared Package
ML20082U725	List: ML20082U721 ML20082U726
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, )

RTP ** ** (

5. Heat Flux Hot Channel Factor, F g

, K(Z), W(Z), APL ND "and W(Z)gg for 'N Specification 3/4.2.2, and gg%*

6. Nuclear Enthalpy Rise Het Channel Factor,6 F RTP ","*

an d Power Factor

\

Multiplier, MF3, m. , limits for Specificetion 3/4.2.3. )

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.) (

2.

)

l WCAP-10216-9-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION", June 1983 (W Proprietary).

/

\

l i

(Methocology for Specifications 3,2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for FgMethocology.) (

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

(

analysis limits) of the safety analysis are vt. y 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 DR 910916 %n--" "- " ' ' ' ' "

ADOCK 05000369 PDR

for Specification 6.9.1.9 Attachment 1:

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 Attachment 2:

l

• - Reierence_5.is not applicable to target band and APL*.

_** 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

1

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