ML021910190

Tech Spec Pages for Amendments 199 & 192

ML021910190
Person / Time
Site:	Catawba
Issue date:	07/02/2002
From:	NRC/NRR/DLPM
To:
References
TAC MB3728, TAC MB3729
Download: ML021910190 (3)

Text

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1.

Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3.1.3,

2.

Shutdown Bank Insertion Limit for Specification 3.1.5,

3.

Control Bank Insertion Limits for Specification 3.1.6,

4.

Axial Flux Difference limits for Specification 3.2.3,

5.

Heat Flux Hot Channel Factor for Specification 3.2.1,

6.

Nuclear Enthalpy Rise Hot Channel Factor for Specification 3.2.2,

7.

Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1,

8.

Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3.5.1 and 3.5.4,

9.

Reactor Coolant System and refueling canal boron concentration limits for Specification 3.9.1,

10.

Spent fuel pool boron concentration limits for Specification 3.7.15,

11.

SHUTDOWN MARGIN for Specification 3.1.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY" (W Proprietary).

2.

WCAP-10266-P-A, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE" (W Proprietary).

(continued)

Catawba Units 1 and 2 5.6-3 Amendment Nos. 199/192

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

3.

BAW-1 01 68-P-A, "B&W Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants" (B&W Proprietary).

4.

DPC-NE-2011-P-A, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors" (DPC Proprietary).

5.

DPC-NE-3001-P-A, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology" (DPC Proprietary).

6.

DPC-NF-2010-A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design."

7.

DPC-NE-3002-A, "FSAR Chapter 15 System Transient Analysis Methodology."

8.

DPC-NE-3000-P-A, "Thermal-Hydraulic Transient Analysis Methodology" (DPC Proprietary).

9.

DPC-NE-1004-A, "Design Methodology Using CASMO 3/SIMULATE-3P."

10.

DPC-NE-2004-P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01" (DPC Proprietary).

11.

DPC-NE-2005-P-A, "Thermal Hydraulic Statistical Core Design Methodology" (DPC Proprietary).

12.

DPC-NE-2008-P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3" (DPC Proprietary).

13.

WCAP-1 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code" (W Proprietary).

(continued)

Amendment Nos. 199/192 Catawba Units 1 and 2 5.6-4

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

14.

DPC-NE-2009-P-A, "Westinghouse Fuel Transition Report" (DPC Proprietary).

15.

WCAP-12945-P-A, Volume 1 and Volumes 2-5, "Code Qualification Document for Best-Estimate Loss of Coolant Analysis" (W Proprietary).

The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e., report number, title, revision number, report date or NRC SER date, and any supplements).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Ventilation Systems Heater Report When a report is required by LCO 3.6.10, "Annulus Ventilation System (AVS),"

LCO 3.7.10, "Control Room Area Ventilation System (CRAVS)," LCO 3.7.12, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," LCO 3.7.13, "Fuel Handling Ventilation Exhaust System (FHVES)," or LCO 3.9.3, "Containment Penetrations," a report shall be submitted within the following 30 days. The report shall outline the reason for the inoperability and the planned actions to return the systems to OPERABLE status.

5.6.7 PAM Report When a report is required by LCO 3.3.3, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.8 Steam Generator Tube Inspection Report

a.

The number of tubes plugged in each steam generator shall be reported to the NRC within 15 days following completion of the program; (continued)

Amendment Nos. 199/192 Catawba Units 1 and 2 5.6-5